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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
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ACCELERATED DIST lBUTION DEMONSTRATION SYSTEM
$ h-~'EGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9010010140 DOC.DATE: 90/09/24 NOTARIZED: YES DOCKET g FACIL:50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH. NAME AUTHOR AFFILIATION KEISER,H.W. pennsylvania power a Light co.
RECIP.NAME RECIPIENT AFFILIATION BUTLER,W.R. Project Directorate I-2 R
SUBJECT:
Forwards proposed Amend 87 to License NPF-22,changing TS to I support Cycle 5 reload. Reload summary rept also encl.
D DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:LPDR 1 cy Transcripts. 05000388 RECIPIENT COPIES RECIPIENT COPIES A ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-2 LA '1 1 PD1-2 PD 1 1 D THADANI,M 2 2 D
INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H 1 1 II NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 S NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 QCJWE B 1 0 OGC/HDS2 1 0 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTES 2 2 R
D D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: "LTTR 25 ENCL 23
Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101-1179 ~ 215/7704151 Harold W. Keiser Senior V/ce President.Nuclear 215l770-4194 SEP 2 4 $ 90 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler, Project Director Project Directorate I-2 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT 87 TO LICENSE NO. NPF-22: UNIT 2 CYCLE 5 RELOAD PLA-3445 FILES A7-8C A17-2 R41-2 Docket No. 50-388 Rcfcrcnces: 1. PLA-3407, H.V. Kaiser to V.R. Butler, "Proposed Amerxhaent 132 to Liccnsc No. NPF-14: Unit 1 Cycle 6 Reload", chtcd July 2, 1990.
- 2. PLA-3328, H.M. Kaiser to V.R. Butler, "Suhaittal of Topical Report PL-NF-89-0054, chted January 22, 1990.
- 3. Plh-3420, H.M. Kaiser to M.R. Butler, "Suhaittal of Topical Rcport'L-NF-90-0014, chtcd August 8, 1990.
- 4. Letter, M.R. Butler to H.V. Keiser, "Topical Report PL-NF-87-001 ~ 'Qualification of Steady State Core Physics Nethods for BMR Design and Analysis'TAC Nos. 65171 and 65172)", dated April 28, 1988.
Dear Dr. Butler:
The purpose of this letter is to propose changes to the Susquehanna SES Unit 2 Technical Specifications in support of the ensuing Cycle 5 reload. Changes to the following Technical Specifications and bases are requested:
Index 1.0 Definitions 2.0 Safety Limits and Limiting Safety System Settings B 2.1 Safety Limits 3/4.2.3 Minimum Critical Power Ratio 3/4.4.1 Recirculation System B 3/4.1 Reactivity Control Systems B 3/4.2 Power Distribution 'Limits k B 3/4.4.1 Recirculation System 5.3.1 Fuel Assemblies 5.3.2 Control Rod Assemblies 90i00iOi40 900924 PDR ADOCK 05000383 i Pool P PDC i((
2 FILES A7-8C/A17-2/R41-2 PLA-3445 Dr. W. R. Butler The following attachments to this letter are provided to illustrate and technically support each of the changes:
Marked-up Technical Specification Changes No Significant Hazards Considerations PL-NF-90-005, "Susquehanna SES Unit 2 Cycle 5 Reload Summary Report," September 1990 Susquehanna SES Unit 2 Cycle 5 Proposed Startup Physics Tests Summary Description, September 1990 In addition to the normal analyses and considerations for Unit 2 Cycle 5, the following specific analyses and issues deserve special mention:
This is the first reload cycle where the licensing analyses were performed by PP&L using the safety analysis methods previously approved or currently being reviewed by the NRC (References 2,3 and 4). Advanced Nuclear Fuels (ANF) provided some supporting analyses. This is the second reload cycle for Unit 2 that PP&L designed by using our NRC approved Steady State Physics methods (Reference 4). Additional discussion and results are provided in the attached Unit 2 Cycle 5 Reload Summary Report.
Approximately 50 original equipment control blades will be replaced prior to Unit 2 Cycle 5 with equivalent worth Duralife 160C control blades. A detailed evaluation of the control blade replacements is provided in the attached Unit 2 Cycle 5 Reload Summary Report.
To support single loop operation for Unit 2 Cycle 5 and future operating cycles, ANF performed the recirculation pump seizure accident from single loop operating conditions on a generic basis for the Susquehanna Units.
This generic analysis was part of the Unit 1 Cycle 6 Reload License submittal (Reference 1). This approach should eliminate the need to have the single loop pump seizure accident analyzed for each reload. Further discussion is provided in the attached Unit 2 Cycle 5 Reload Summary Report.
As a result of the issuance of NRC Bulletin No. 90-02, entitled "Loss of Thermal Margin Caused by Channel Box Bow," licensees who use channels, including those who use them for only a single bundle lifetime, have been required to take into account the effects of channel bow in analyses supporting reload applications. ANF has addressed this issue for Unit 2 Cycle 5 through a generic analysis and in a separate letter to the NRC. Additional detail is provided in the attached Unit 2 Cycle 5 Reload Summary Report.
3 FILES A7-8C/A17-2/R41-2 PLA-3445 Dr. W. R. Butler
~ A repaired fuel assembly that failed during U2C2, was repaired during U2C3, and returned to use for U2C4, will be used once again during U2C5. This fuel assembly was repaired by replacing the failed rod with a solid zircaloy-2 rod. A fuel assembly that failed during U2C3 was inspected during U2C4, and is not being reused during U2C5. However, its three symmetric fuel assemblies will be used during U2C5. (Neither the fuel assembly that failed during U2C3 nor the three symmetric assemblies were used during U2C4.) This results in a minor asymmetry in the core loading pattern because no exact match for the three fuel assemblies was available. This asymmetry was evaluated and no significant effects on the core analyses, core operation, or core monitoring are expected. Both of these issues are addressed in more detail in the attached Unit 2 Cycle 5 Reload Summary Report.
Susquehanna SES Unit 2 is currently scheduled to be shutdown for refueling and inspection on March 9, 1991 and to restart as early as May 10, 1991. Based on previous discussions with the NRC staff, it is PP&L's understanding that the NRC believes that the review of References 2 and 3 will be completed in sufficient time to support review and approval of this proposed amendment. PP6L appreciates the NRC staff's efforts to review these documents, and is prepared to meet with the NRC at any time to facilitate the NRC reviews.
We request that your approval of the attached proposed Technical Specifications supporting U2C5 operation be conditioned to become effective upon startup after this outage, and we will keep you informed of any schedule changes. Any questions regarding this proposed amendment should be directed to Mr. R. Sgarro at (215) 770-7916.
Very truly yours, H. W. Keiser Attachments cc: ~NRC-Document ControlDesk (original)>
NRC Region I Mr. M. C. Thadani, NRC Project Manager-Rockville Mr. G. S. Barber, NRC Sr. Resident Inspector-SSES Mr. K. D. Desai, NRC/SRXB Rockville Mr. T. M. Gerusky, Pennsylvania DER
SUSQUEHANNA SES UNIT 2 CYCLE 5 PROPOSED STARTUP PHYSICS TESTS
SUMMARY
DESCRIPTION SEPTEMBER 1990 PENNSYLVANIA POWER 5 LIGHT COMPANY
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SUS UEHANNA SES UNIT 2 CYCLE 5 PROPOSED STARTUP PHYSICS TESTS
SUMMARY
DESCRIPTION Susquehanna SES Unit 2 is planned to be shut down for its fourth refueling and inspection outage on March 9, 1991. During startup and initial Cycle 5 operation, PP&L plans to perform a series of startup activities and tests to assure that the reload core conforms to the design. A list of these proposed activities and tests along with a brief description for each is provided below.
- 1) Core Loadin Verification
Purpose:
To assure the core is correctly loaded per design.
Description:
The core will be visually checked to verify correct loading. An underwater video camera or suitable device will be used to record fuel assembly serial numbers, orientations, core locations, and proper core plate seating. A review of the videotape will be performed and will serve as an independent verification of the core loading. Any discrepancies discovered will be promptly corrected and the affected areas reverified prior to Unit 2 Cycle 5 (U2C5) startup.
- 2) POWERPLEX In ut Deck Validation
Purpose:
To ensure the POWERPLEX Core Monitoring System input deck is updated correctly before the start of the new operating cycle.
Description:
The validation will ensure that POWERPLEX, the 'ANF software system designed to perform in-core monitoring of BWR cores, is correctly updated for monitoring U2C5 operation. Core monitoring calculations within POWERPLEX are performed by XTGBWR, a three-dimensional'eactor simulation code. The POWERPLEX input deck consists of all data needed for the execution of this code and subsequent calculation of the margin to each fuel thermal limit.
This data must be updated to reflect the new core loading prior to the start of a reload operating cycle in order to ensure satisfactory core monitoring. The deck will be updated by PP&L and verified jointly by members of the PP&L Reactor Engineering group located at Susquehanna SES and the Nuclear Fuels Engineering group located at the corporate headquarters.
- 3) Control Rod Functional Insert and Withdrawal Checks
Purpose:
To assure proper control rod function.
Description:
A control rod functional test, which includes mobility and overtravel checks, will be performed on each control cell
loaded in its final configuration. Core subcriticality will be demonstrated and documented as each control rod is functionally tested.
- 4) Subcritical Shutdown Mar in Demonstration
Purpose:
To assure that at least the minimum required Shutdown Margin exists with the analytically determined strongest worth control rod fully withdrawn.
Description:
This test will verify that at least the required amount of Shutdown Margin is maintained without determining the actual amount of Shutdown Margin in the core. The analytically determined strongest worth control rod (or its symmetric counterpart) is fully withdrawn. One or more diagonally adjacent control rods are then slowly notched out (one at a time) and sub-criticality verified at each step, until the analytically determ'ined reactivity worth of the diagonally adjacent control rods at their respective notch position just equals or slightly exceeds the required amount of Shutdown Margin. Verification at this step that the core is still subcritical demonstrates that at least the required amount of Shutdown Margin exists.
- 5) In-Se uence Critical and Shutdown Mar in Determination
Purpose:
a) To determine the actual amount of Shutdown Margin.
b) To compare predicted versus actual critical control rod positions.
Description:
This test will be performed as part of the normal startup.
Control rods are pulled in group order in their normal sequence until criticality is achieved. Taking into account the period and moderator temperature coefficient corrections, the Shutdown Margin is determined by calculation. In addition, to assure that there is no reactivity anomaly, the actual critical control rod position is verified to be within 1% hk/k of the predicted critical control rod position.
- 6) Control Rod Scram Time Testin
Purpose:
To demonstrate that the scram insertion times are within the appropriate Technical Specification requirements following core alterations.
Description:
This test satisfies Susquehanna SES Technical Specifications 3/4.1.3.2, 3/4. 1.3.3 and 3/4. 1.3.4. These specifications place limits on control rod scram performance. The results of the control rod scram time testing will be used to determine the necessary MCPR operating limits described in Technical Specification 3/4.2.3.
C
Purpose:
a) To assure proper operation of the TIP system.
b) To check core symmetry.
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Description:==
A gross asymmetry check will be performed as well as a detailed statistical uncertainty evaluation of the TIP system. A complete set of TIP data will be obtained at a steady-state power level greater than 75% of rated power.
A total average deviation or uncertainty will be determined for all symmetric TIP pairs as well as a maximum absolute deviation. The results will be analyzed to assure proper operation of the TIP system and symmetry of the core loading.
SUS UEHANNA SES UNIT 2 CYCLE 5 PROPOSED ADDITIONAL STARTUP ACTIVITIES
SUMMARY
DESCRIPTION The following is a short summary of additional activities performed during the Startup Testing Program.
Thermal Limits Monitorin The margin to each fuel thermal limit will be checked throughout the startup period through review of the POWERPLEX core monitoring system output.
TIP S stem - OD-1 Performance A full set of TIPs will be run at a low power level to update the core power distribution before the first POWERPLEX core performance calculation is initiated. Subsequent TIP sets will be performed in conjunction with LPRH calibrations. The LPRM currents will be updated and the LPRH GAFS verified to b'e within the acceptable range.
Power Distribution Com arison with Offline Monitorin Actual online core power distribution data from the POWERPLEX Core Monitoring System will be compared to SIMULATE-E core simulation code calculations. The SIMULATE-E code, approved by the NRC (PL-NF-87-001-A) for use in the Susquehanna SES core design and licensing, was used by PP&L Nuclear Fuels Engineering personnel in the'design of the U2C5 core and will be used for operations support applications throughout the cycle.
Core Flow Calibration A core flow calibration will be performed at -100% core flow. Jet pump and recirculation loop flow instrumentation will be adjusted, if necessary, to ensure correct core flow indication and correct calculation of the flow biased Rod Block Monitor, APRH Scram, and APRM Rod Block setpoints.
Recirculation Loo Baseline Data Ac uisition
'ecirculation loop data will be collected throughout the startup program to provide baseline information for plant performance monitoring in two loop and single loop operation.
PP8 L Anal tical Methods Benchmarkin Core physics data obtained from startup testing will be used for the continued benchmarking of PP8L's CPH-2/SIMULATE-E core analysis methodology, as recommended by the NRC in its safety evaluation on PP8L's Topical Report PL-NF-87-001-A ("gualification of Steady State Core Physics Methods for BWR Design and Analysis" ).
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