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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
[Table view] |
Text
ULATORY INFORMATION DISTR UTION SYSTEM (RIDS)
ACCESSION NHR: 8707210523 DOC. DATE: 87/07/15 NOTARIZED: NQ DOCKET N
~ FACIL: 50-387 Susquehanna Steam Electric Station, Unit 1> Pennsy1va 05000387 50-388 Susquehanna Steam Electric Stationi Unit 2i Pennsylva 05000388 AUTH. NAMr AUTHOR AFF Ii I AT l QN KEISER. H. W. Pennsylvania Power 5 Light Co.
RECIP. NAME RECIPIENT AFFILIATION RUSSELL'. T. Region ii Office of Director
SUBJECT:
Responds to violations noted in Insp Repts 50-387/85-06 0 50-388/85-06. Corrective actions: Deviation Request 3 dtd Sept 1986 submitted to gustify acceptablility of nonrated doors 5 plant drawings re resealing requirements being revised.
DISTRIBUTION CODE:
TITLE: General IE01D COPIES RECEIVED: LTR (50 Dkt)-Insp Rept/Notice of
+ ENCL JResponse Violation SIZE:
NOTES: icy NMSS/FCAF/PM. LPDR 2cys Transcripts. 05000387 1cy NMSS/FCAF/PM. LPDR 2cys Transcripts. 05000388 RECIPIENT COPIES REC IP I ENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-2 PD i. THADANI s M 2 2 INTERNAL: ACR S 2 AEOD 1 1 DEDRO 1 NRR MORISBEAUi D NRR/DOFA D IR 1 NRR/DREP/EPB 1 NRR/DREP/RPB 2 NRR/DRIS DIR 1 1 NRR/PMAB/ILRB '1 0 ERMAN> J OGC/HDS2 1 1 EG FI 1 REB'EPY GI 1 1 RGN1 FILE 01 i EXTERNAL: LPDR NRC P DR 1 1 NSIC NOTES:
TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26
Pennsylvania Power &. Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215/7705151 Harold W. Keiser Vice President-Nuciear Operations 21 5/770-7502
~Rei~l to a Notice of Violation Mr. William T. Russell Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION RESPONSE TO ENFORCEMENT ACTION 85-112 Docket Nos. 50-387/NPF-14 PLA-2887 FILE R41-2/R41-1C/A17-15 and 50-388/NPF-22
Dear Mr. Russell:
Pursuant to 10CFR2.201, Pennsylvania Power & Light Company hereby provides the attached response to Enforcement Action 85-112 (Attachment 2).
In addition to the responses requested in the specific violations, we have taken this opportunity to provide you with an update of our ongoing review of our fire protection program (Attachment 1).
We trust the Commission will find our response acceptable.
Very truly yours, Vice President Nuclear Operations Attachments cc:r'NRC=Document'=Control Desk (original)
NRC Region I Mr. L. R. Plisco, Resident Inspector Mr. M. C. Thadani, Project Manager 8707@gpg 8>0'7>s PDR ADO~CK 0500038'BR 9
ATTACHMENT 1 REVIEW OF FIRE PROTECTION PROGRAM As a result of the Appendix R inspection conducted by the NRC during February 1985, PP&L was requested to respond to a series of NRC concerns. These concerns and the actions to resolve them were itemized and submitted to the NRC on June ll, 1985 (PLA-2482).
Follow-up responses to the NRC transmitted reports, revisions and clarifications to the reports and responses to additional NRC questions related to the deviation requests accompanying these reports (Ref. PLA-2529 dated 9/4/85, 2541 dat'ed 10/3/85, 2566 dated 12/18/85,, 2574 dated 12/18/85, 2592 dated 2/10/86 and 2762 dated 12/ll/86) . Modific'ations described in these letters are on schedule for completion during the Unit 1 third refueling and inspection outage (4th quarter 1987) and the Unit 2 second refueling and inspection outage (2nd quarter 1988). Compensatory actions as provided in PLA-2417 dated 2/22/85 are in effect and will remain so until the committed modifications are installed.
In addition, PP&L decided that it was necessary not only to assure that NRC was satisfied with our Fire Protection Program, but also that we were totally satisfied with the program in light of our improved understanding of Appendix R resulting from the inspection and our own internal reviews. As a result, we included information in PLA-2566 dated 12/18/85 stating that we were embarking on an upgraded Appendix R Safe Shutdown analysis. In addition, PP&L has undertaken a comprehensive fire protection program review intended to establish a well documented, readily auditable and easily understood set of fire protection documentation. This will assure that our commitments with respect to fire protection are incorporated into our standard engineering and operational practices and will simplify the gob of ensuring continuing compliance.
Summa of Fire Protection Pro ram Review PP&L believes'that the basic fire protection design of Susquehanna SES is adequate and safe. The fire protection program review is a comprehensive effort focusing on compliance with the requirements of Sections III G, J, and 0 of Appendix R to 10CFR50. The effort is intended to create easily auditable documentation, confirm compliance and provide a means of more effectively maintaining compliance in the future.
A multi-disciplined team approach is being utilized in the conduct of the review. This approach takes advantage of the individual specialized skills and knowledge of each technical discipline while broadening the base of fire protection knowledge and experience.
The review effort, currently consists of:
SAFE SHUTDOWN ANALYSIS The Safe Shutdown Analysis for Susquehanna Steam Electric Station is being redone using current industry and regulatory interpretations of the requirements of Appendix R. The following activities are being performed:
Cont '. Page 2 of 3 A set of systems sufficient to achieve cold shutdown in accordance with the current interpretation of Appendix R was selected. These systems ensure the ability to accomplish a dual unit shutdown under the Appendix R scenario where the non-fire unit could be subjected to a Loss of Offsite Power (LOOP), simultaneous with a fire and a LOOP in the affected unit.
- 2) Components and cabling which support the operation or which could cause the misoperation of the systems selected in number 1 above are being identified along with their location by fire zone in the plant.
- 3) For each cable and component a review is being conducted to assure that redundant trains are adequately separated by the necessary spatial separation and/or rated barriers and that fire protection
,consistent with the requirements of Section III G of 10CFR50 Appendix R is provided.
COMBUSTIBLE LOADING ANALYSIS A new combustible loading analysis is being performed to confirm the combustible loading for each fire zone. The results of the new analysis will be compared with the current level of fire protection provided in the areas of the plant where safe shutdown equipment is located to assure the level of protection provided bounds that required by the fire hazard.
LONG TERM COMPLIANCE ITEMS The following program improvements are being undertaken to provide a well documented and broadly distributed understanding of our commitments:
- 1) Pre aration of Fire Protection Features Drawin s These drawings are being prepared to show the locations of fire area and fire zone boundaries, to document the required safe shutdown division in each fire zone, and to specify the location of fire doors, fire dampers and fire barriers which must be maintained in order to assure safe shutdown.
- 2) Pre aration of Electric Wra ed Racewa . Drawin s These drawings are being prepared to document the physical location and level of protection required for raceway necessary to support safe shutdown.
- 3) Pre aration of Desi Standards Design standards are being prepared to assure that plant and design personnel have an understanding of the actions that must be performed to preserve our compliance with Appendix R. Design standards to cover the, following are being prepared:
Attachment 1 Cont'd. Page 3 of 3 3.1 A design standard is being prepared to outline the requirements for maintaining compliance with Appendix R Section III G, J & 0 when adding new or modifying existing components and cables in the plant. This design standard references the fire protection features drawings outlined in number 1 above for a determination as to the safe shutdown division required to be protected in a given fire zone.
3.2 A design standard is being prepared to document how to perform a combustible loading analysis and how to maintain our commitments with respect to the combustible loading analysis.
- 4) Pre aration of S ecifications Specifications are being prepared to explain to plant personnel those aspects of the Appendix R analysis which require actions on their part to maintain our commitments. The following specifications are being prepared.
4.1 Specifications referencing the fire protection features drawings and the electrical wrapped raceway drawings are being prepared to identify the specific surveillance items required by our new Appendix R analysis in the following areas: fire doors, fire dampers, fire rated barriers and wrapped raceway.
4.2 A specification providing an acceptable calculational method for the control of transient combustibles is being prepared.
4.3 Existing cable routing specifications are being revised to reference the electrical wrapped raceway drawings for a determination of the required level of protection for raceway which are required to be protected.
The work described above is scheduled for completion by December 31, 1987.
Potential conflicts with existing plant design identified by the review will be thoroughly evaluated. If the evaluation identifies any safety significant deviations from the requirements of Appendix R, Sections III. G, J or 0, appropriate compensatory actions as required by our NCR process and technical specifications will be implemented until permanent modifications are completed.
At the completion of the review, the Fire Protection Review Report will be revised. The revision will summarize the analytical work and will reflect any changes which result. The revised report is scheduled to be issued during the second quarter of 1988.
ATTACHMENT 2 RESPONSE TO NOTICE OF VIOLATION I. Violation
=
The Susquehanna Unit 1 Operating License NPF-14, Paragraph 2.C(6),
requires the licensee to maintain the fire protection program set forth in Appendix R to 10 CFR Part 50. The Susquehanna Unit 2 Operating License NPF-22, Paragraph 2.C(3), requires the licensee to maintain in effect and fully implement all provisions of the approved fire protection program. In a letter dated March 26, 1981 to NRC, the licensee stated that the Susquehanna Fire Protection Program would be implemented in accordance with Appendix R, particularly Sections III.G, J, and 0. The fire protection program was approved by the staff in the Safety Evaluation Report and associated Supplements 1 - 3.
10 CFR Part 50, Appendix R, Section III.G.1 requires that fire protection features shall be provided for structures, systems, and components important to safe shutdown. These features shall be capable of limiting fire damage so that one train of systems necessary to achieve and maintain hot shutdown conditions from either the control room or emergency control station(s) is free of fire damage.
Sections III.G.2 and III.G.3 specify four alternatives that may be implemented outside of primary containment to assure that one redundant train of equipment cabling and associated circuits necessary to achieve and maintain hot shutdown remain free of fire damage. The 'alternatives are:
Separation of redundant trains of- equipment, cabling and associated circuits by a three-hour rated fire barrier.
Separation of redundant trains of equipment, cabling and associated circuits by a horizontal distance of 20 feet with no intervening combustibles and fire detection and automatic fire suppression systems installed in the area.
Enclosure of redundant trains of equipment, cabling and associated circuits by a one-hour rated fire barrier with fire detection and automatic fire suppression systems installed in the area.
Installation of alternative or dedicated shutdown capability independent of the equipment, cabling and associated circuits under consideration, and installation of fire detection and fixed fire suppression systems in the. area under consideration.
Contrary to the above, as of February 15, 1986, fire protection features were not provided for certain redundant tiains of equipment and/or cabling located outside the primary containment and necessary to achieve and maintain hot shutdown conditions from either the control room or emergency control stations such that one train would remain free of fire damage and none of the alternatives provided by Section III.G.2 and III.G.3 were implemented. Specifically:
Attachment 2 Cont'd. Page 2 of 6 I.A. Violation (387/85-06-02
~ ~ and 388/85-06-02)
Redundant trains of residual heat removal (RHR) pumps located in the RHR pump rooms of Units 1 and 2 (Fire Zones l-lE, 1-1F, 2-1E, 2-1F) were separated by more than 20 feet with no intervening combustibles and provided with fire detection capability. However, the suppression system provided was not automatic. No alternative or dedicated shutdown capability was provided.
Res onse to Violation I.A.
(1) Reason for the Violation:
The barriers separating fire zones 1-1E and 1-1F in Uni't 1 and fire zones 2-lE and 2-1F in Unit 2 were not three-hour rated fire barriers. The plant configuration existing at the time of the inspection and the justification thereof were clearly provided in the Susquehanna SES Fire Protection Review Report revision 2 dated November 1982 (Unit 1, pages 4.3-8 through 4.3-12; Unit 2, pages 4.4-8 through 4.4-12). Until the inspection it was PP&L's position that although this fire zone barrier could not be termed a three-hour rated fire barrier, the construction was adequate to mitigate the spread of fire from one redundant train to the other considering the actual fire hazard. Therefore, an automatic suppression syst: em or alternative shutdown capability were not thought to be necessary.
(2) Corrective steps that have been taken and the results achieved:
Upon identification of the concern, interim compensatory measures as stated in PP&L letter PLA-2417 dated February 22, 1985 were implemented. These measures are being maintained.
The construction of these fire zone boundaries was reviewed to determine the changes which were necessary in order to upgrade these fire barriers to three-hour rated status. The following actions were taken:
o Deviation Request Number 3 dated September, 1986, has been submitted to justify the acceptability of non-rated doors.
o A design change package for upgrading all penetrations and the seismic gap between the subject barriers and the primary containment to a three-hour rating has been prepared.
Installation is scheduled for the next refueling and inspection outage on each unit.
Attachment 2 Cont'd. Page 3 of 6 (3) Corrective steps taken to avoid further violations:
Plant design drawings detailing'he sealing requirements for penetrations through plant fire barriers are being revised to require a three-hour rating in all cases.
(4) Date of full compliance PP&L will complete the modifications identified in (2) above by the end of the third refueling and inspection outage for Unit 1 (4th Quarter 1987) and the second refueling and inspection outages for Unit 2 (2nd Quarter 1988). PP&L is revising Deviation Request Number 3 to clearly extrapolate the Factory Mutual results to cover water tight doors in these barriers. The revised Deviation Request will be submitted prior to the end of the third refueling and inspection outage for Unit 1 (4th Quarter 1987). Additional actions related to Deviation Request Number 3 are contingent upon NRC review.
I.B. Violation (388/85-06-03)
Electrical power and control raceways (Nos. E1K715, E2PJ19, E2KJ19, F2K123) located in the Containment Access Area of Unit 2 (Fire Zone 2-4A) were provided with fire detection and automatic suppression capabilities, but were not enclosed by a one-hour fire barrier, or separated by a horizontal distance of 20 feet. No alternative or dedicated shutdown capability was provided.
Res onse to Violation I.B.
(1) Reason for the Violation:
PP&L's new safe shutdown analysis has made the following determinations.
o Raceway F2K123 is not contained in fire zone 2-4A and, therefore, is not in violation. There is a raceway F2K132 in fire zone 2-4A, but this raceway contains no safe shutdown cables and, therefore, is not in violation.
o Raceway E2PJ19 is an end section of cable tray which contains no cables and, therefore, is not in violation.
o Raceway E1K715 is located. in fire zone 2-4A-W. As outlined in Deviation Request Number 4, revised September, 1986, fire zone 2-4A-W is a wraparound fire zone. The intent of the wraparound area is to provide a minimum 50 feet spatial separation between redundant shutdown paths. This 50 foot distance is comprised of 25 feet North and 25 feet South of Column 33 in fire zone 2-4A-W.
Raceway E1K715 is 29 feet South of Column 33, which is outside of the portion of the wraparound zone where protection is required and, therefore, is not'a violation.
E Attachment 2 Cont'd. Page 4 of 6 o Raceway E2KJ19 is located in fire zones 2-4A-W and does contain safe shutdown cables related to train A of the Emergency Switchgear Room HVAC System and three inboard containment isolation valves required to prevent loss of vessel inventory.
Since the FPRR Revision 2 indicates a loss of these functions was acceptable, PP&L believed we were in compliance.
(2) Corrective steps that have been taken and the results achieved:
PP&L's current safe shutdown analysis identified raceway E2KJ19 as requiring wrapping.
(3) Corrective steps to be taken to avoid further violation:
A long-term compliance program as described in Attachment 1 is under development.
(4) Date of full compliance:
Raceway E2KJ19 will be wrapped by the end of the Unit 2 second refueling and inspection outage (2nd Quarter 1988).
I.C. Violation (388/85-06-04)
Redundant trains of saf e shutdown equipment located in the Equipment Removal Room of Unit 2 (Fire Zone 2-3B) were not separated by three-hour fire barriers and were provided with automatic suppression capability in only a portion of the area. No alternative or dedicated shutdown capability was provided.
Res onse'o Violation I.C.
(1) Reason for Violation:
The approved revision of the Susquehanna SES Fire Protection Review Report (FPRR), revision 2 indicated in figures 5.10 and 5.12 and Table 6-1 that the equipment removal area of fire zone 2>>3B and the equipment shaft area of fire zone 2-5A were provided with automatic suppression. These drawings incorrectly indicated automat'ic suppression capabilities for all elevations in the shaft. As described in PLA-2592 dated 2/10/86, only the lower elevation of the equipment shaft is required to contain automatic suppression capabilities. Additionally, it was never PP&L's intent to provide full automatic suppression in the equipment removal area (2-3B).
Also, the first sheet in Section 5.0 of Revision 2 to the FPRR indicates that the figures in that section are representative of the plant fire protection features and are not as-built or controlled drawings.
Cont'd. Page 5 of 6 (2) Corrective steps that have been taken and results achieved:
During 1983, and subsequent to the issuance of Revision 2 to the FPRR, plant fire protection design drawings, were generated to document and control the plant fire protection features. On these plant drawings the'artial fire suppression in fire zones 2<<3B and 2-5A has been properly depicted. (Ref. Drawings E-184302 Sh. 3 Revision 4 & Sh 5 Revision 3). Additionally, a review of raceway requiring protection in these areas has shown that no raceways have been improperly protected (i.e. one-hour rated wrapping.vs.
three-hour rated wrapping) in the portions of Fire Zone 2-3B that were improperly indicated as having automatic suppression or in the shaft area of 2>>5A.
(3) Corrective steps to be taken to avoid further violations:
The revised Fire Protection Review Report will properly depict the plant configuration for the area in question.
(4) Date of full compliance:
A revised Fire Protection Review Report is scheduled to be issued during the second quarter of 1988.
Violation (388/85-06-07)
The Susquehanna Unit 1 Operating License NPF-14, Paragraph 2.C(6),
requires the licensee to maintain the fire protection program set forth in Appendix R to 10 CFR Part 50. The Susquehanna Unit 2 Operating License NPF-22 Paragraph 2.C(3), requires the licensee to maintain in effect and fully implement all provisions of the approved fire protection program. In a letter dated March 26, 1981 to the NRC, the licensee stated that the Susquehanna Fire Protection Program would be implemented in accordance with Appendix R, particularly Sections III.G, J, and O. The fire protection program was approved by the staff in the Safety Evaluation Report and associated Supplements 1 3.
10 CFR Part 50, Appendix R, Section III.J, requires that emergency lighting units with at least an 8-hour battery power supply be provided in all areas needed for operation of safe shutdown equipment and in access and egress routes thereto.
Contrary to the above, as of February 15, 1985, the battery power supply for, the emergency lighting unit provided in the stairwell to the Remote Shutdown Panel at elevation 670 feet of the Unit 2 Reactor Building was only rated for 3.75 'hours.
Attachment 2 Cont'd. Page 6 of 6
~Res ense:
(1) Reason for Violation:
The improperly rated battery power supply was incorrectly installed during the construction phase of the plant. The 3.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> rated battery power supply are those used throughout the plant where a higher rated power supply is not required.
(2) Corrective steps that have been taken and the results achieved:
The incorrect power supply unit was replaced with a power supply of the proper rating.
(3) Corrective steps to be taken to avoid further violations:
No additional actions are required.
(4) Date of full compliance:
Base on the actions taken above, PP&L is in full compliance.
Additionally, the Resident Inspectors closed this violation in Detail 1.2 of Inspection Report 50-388/86-04.
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