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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 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 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) 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 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 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 NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable1998-04-15015 April 1998 Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable 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 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 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 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 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 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 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 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 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 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 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-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 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 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 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 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 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 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. IR 05000387/19900801990-08-0303 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 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 ML20006B4501990-01-25025 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 ML19325F1991989-11-0909 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 ML19325D7411989-10-19019 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 ML19325C3771989-10-11011 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 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 ML18040A9041988-07-19019 July 1988 Forwards Rev 39 to Updated FSAR for Susquehanna Steam Electric Station Units 1 & 2 Per 10CFR50.71 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 1990-09-01
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. NJCLEAR DCPT R LENTCEN GO P.02 ,
@ Pennsylvania Power & Ught Company l Two North Ninth Street
- 215 l 770 5181 Stuce D. Kenyon Wee MeaWent.Nueber OpereWone i miserm.nse JUN 0 81964 - .
Dr. Thomas R. k riey Regional Administrator. Region 1 , y, U.S. Nuclear Regulatory Commission 631 Park Avenue t
Eins of Prussia. FA 19406 8USQUEHANNA $ TEAM ELECTRIC STATION TUnsINE BYPAS$ TRAN51ENT
- IR 100508 FILE $41 FLA-2229 Docket No. 50-388 Dear Dr. k riey
['
As a followup to our meeting with your staff as May 31, 1984, attached is a . '
detailed description and evaluation of the turbina bypass transient which occurred at Susquehanna SE8 Unit 2 on.May 28,1984. Also attached is the NSAG h report on the transiaar. '
Yery truly yours, b' i
e
- 3. D. Eeny Vice President-Nuclear Operations Attachment ces R. W. Staroetecki = NRC Region 1
- 1. W. Jacobe = NRC Resident Inspector R. L. Perch - NRC Bethesda * '
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NJCLEAR EEPT R LENTC4ri to P.03 1
Attachment 1 l FLA-2229 Turbine trusse Transient Following shift turnover on May 27, 1934 Operatione pereoanel began establishing plant conditions to perform the RCIC controller het functional tune-up test (NF-250-010). The INC pressure setpoint wee reduced from an fattial value of appremiastely 950 pSIG to 920 PSIG at the completion of CED seres time testing at 00:10 on May 28. 1984. Control rode were them withdrawa -
to inerasse resetor power to open the #1 turbine bypass valve to approminately 502 to ensure adequate pressure control during the acIc hot fumational test.
Steam dilution flew to the secondary Steen Jet Air Ejector ($ JAI) began to oscillate (+/=130 lb/hr) at approximately 23:50 based on strip chart recorder data. This corresponde to the decrease of the EMC pressure setpoint. At approminately 00:45 the SJAR eteam flow increased from 9400 lb/hr to 9650
- lb/hr se reactor pressure increased. The flow then decreased to 9400 lb/hr as ,
resetor pressure decreased.
At approaimately 01:00 a control rod was selected and withdrawn. This action directly preceded an increastas emplitude oscillation of turbine bypass valve positten as the #1 bypees valve re-poettioned to maintala pressure setpoint.
The assillation induced roaster pressure and bypese steem flow perturbations which apparently induced effgas system eteam dilution flow oseillations.
Variations in the effgas system flow rate would have a negligible effect on reactor pressure and would not be espected to influence EEC operation. The offges system oscillations were further complicated by the fast that two root valves to the offsas main steen pressure reducing centro 11er (PC-20701A) were teolated c.ueing the pressure control valves to be open fully. A review of previous escillations in the SJAE eteen fisw showed two oscillations occurred on May 27, 1934 when reactor pressure was adjusted. Had the pressure '
regulating valves been operable. the oscillations would have been dampened.
Offgas teolated on low steam dilution flow at approximately 01:01:03 due to the oscillatione in the steam flow caused by the increasing magnitude of the '
oscillations in the total bypass valve espaatty. This generated the first indication to the plant control operator (PCO) that an abnormal plant condition existed. Subsequent engineering simulattene of the resulting transient support the suppeetties that the #2 turbine bypass valve opened at 01:01:15 which pressurised the #2 bypese valve diesberge piping and caused marrow range reactor pressure to drop to 894 PSIO. Data in the attached-Figure 1 shove an espected remeter pressure drop of 20 pounds based on mais steen line surge flow when two bypass valves initially opea. This correlates well with the recorded pressure deeresse of 19 pounds and recorded steen flow insrease. As roaster preneure decreased vessel level swelled to approsimately +53" due to increased.veid forestion and a EpCI high level trip signal wee generated. Procese temputer data ladiantes the bypass valves went
- fully elooed to recover reactor pressure. Vessel level dropped to 30" and the feedveter system, in automatic vessel level control using the low lead centre 11er (LIC-2R602), responded to the level perturbatten by increasing feedwater flow. The effect of resocor pressure increasing due to the bypase Valve closure provided a net reactivity incrosse end subsequest small power epike. -
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, ttJCLEAR ECPT R.1.INTOm (c. P.04 i
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! The emaisua AFRM power level recorded in the Shitt Superviser and Startup Test loss during the tramasses was 102 on Ap M 'I'. This ApBN had a seia
- adjustment fester of 1.85 as determined by startup Test (ST) 12.1 which would
' indiaate am setual power level of 5.45 rated power. This to supported by the fact that a red bleek wee received, however ne reseter seres signals were generated. Based oja APat settings for a red block at 112 indiested power and seven faaetion at let indicated power. and applying the current sais adjustaaet fastere for individual AFRN's the minimum power at which a red block would oscur was 4.42 estual' power. The minimum power at which a half serem would eseur yes 3.92 actual power. This would indicate that the actual power level reashed duttas the tranatest to benaded by 4.65 to S.95 rated j power. A separate treasiest power analyste using the actual IEN recorder I i traces, as adjusted by a Mot punctional test which correlated observed IRN readings to the aalibrated APEN readings indicates the initial power level . !
wee 3.22 and that actual power reached during the tranatest was between 4.7X 1 and 5.02 rated power. - '
t '
4 Roseter pressure aestiaued to ineresse te a monimum value of 923 PSIG at '
l 01:01:44 et which peine turbine bypass valvee #1 and #2 re-opened t'a 343 of i total bypass valve espasity. Rosator pressure decreased to til PSIC and both ,
l bypase valves realesed at 01:01:33 to regulate pressure based on the pressure :
setpoint. The #1 bypsea valve re-opened at 01:02:03 and oest11sted three times while attempting to stabilies reacter pressure. When pressure again oneseded the pressure seapoint at 01:02:5g the #2 bypese valve re-opened and a !
i
{ assimum of 235 total bypese valve espasity was recorded by the process i I
semputer. Manimum reactor pressure reached prter to the second bypese valve <
operation was 924 PSIC. Figure 2 graphically depicts the total bypese valve 1
opea positten and marrow range reacter pressure reopense during the transient. ,
At 01:03:09 the #1 bypese valve reelooed and the #1 bypase velve etabilised .
reseter pressure at approainstely 918 PgIO. Minor resator vessel level swinge
- and a power transiest less severe than the tattial power spikes slee escurred ,
durtag these embeequest bypass valve operations. '
1 To mitigate the transient. Operatione personnel began to insert control rode and placed'the feedwater low lead controllar in asaval to minimise further I vessel level oseillations. plaat aseditions stabilised at approminately 01:04 and the effgas system hydrogen resembiner was returned to service. Shift oupervistem, believing the effgas system had tuitiated the traseisat. then 1
! directed the pCO to meaually feelate the offsee system to proelude further f transient operaties. At 01:05:19 the asia steen supply (NT-20701A/3) to !
i effgas wee iselsted. At 01:15 the Unit #2 recombiner wee shutdown and the :
I asehemical vaevue pump wee placed is seretse. 27-2$0-010 and ST 14.2 (RCIC Quick Start to the Yeeeel) were satisfestertly esopleted at 04:34. ,
y i
j Subsequent plant staff 14C and General Electria inveettgaties of the WIC i .
pressure esserel and bypese valve sentrol legia indicated that all centrol fumettens were operating sermally. Plant staff Meehanteel Naistenesse investigaties of the #1 bypese valve revealed that a shipping haemer was found wedged between the bypees valve seat and the valve dise preventing the #1 bypese valve free fully closing. sinee the valve indicated fully closed en i
two oesseiens during the transient. At een be reaseeably soeused that the hemmer became ledged is the valve either duttag the final stages of the l
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.- transient or when plaat tenditions had stabilised following the tranatent.
N presease of the hessier is the vicialty of the #1 bypees valve may have impeded the steen flew rate through the valve possibly producing the pressure ineresse which preeipitated the initial observed bypese valve sea 111ation.
N ahipping her that was retrieved was the type typically used during welding precedures. The head of the hammer wee 6" wide and tapered to a point with a chisel design at the oppeetta and. Apparently the bypass vel */e. upon sleeing, severed the spring portion free the handle and the spetag wee leet la the main eendesser. Apprestaately 4" of the handle remained 1staat. The upper porties of the headle was flattened on both sidee due to operation of the bypass valve. Neehesteal interferesse of the bypass valve operation saused by either the hammer er the spring destee attached to the handle saa only be taferred but not samalusively deseestrated. Disaseeably of the #1 bypass valve ekswed small dents on the dise and the seat of the valve. All the deste em the dies appeared to be concentrated in an area approminately 1 square inch. The deste en the seat serresponded to the pene relative positten as on the dise. The seat see maahimed to remove the dente and the disc wee replaced due to the difficultiae in removing the old dise.
An evaluaties of the e*ent by PP&L's Engineerlag Analysie Group has determined that the event is less limiting them the main turbine trip without bypass transient from e30% power which is dieauseed in Section 13.2.3 of the FSAR.
N turbine trip event resulta in a greater reduction la steam flew and is
~ fattiated free a higher power level. The higher tattial power level resulte in a larger void ee11apee in the sore caustag a higher power spike. Secties 13.2.3.3.3.3 of the FSAR states that the turbine trip without bypsea event results in a high vessel pressure seren. Therefere. the peak power remaine below the flew biased simulated thermal power upeesle trip seapoint and the MCPR remains well above the GETAE safety limit. Sinee the lattial power wee lower the steem flew reducties and subsequent pressuriaation was less. The e
pressurisatten ineresse was attigated by bypese valve operaties, and therefore the event that securred on May 28. 1984 was lose severe than a turbine trip withe.ut bypese event free low power. -
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