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Category:CORRESPONDENCE-LETTERS
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999 Forwards Change J to SSES Security Training & Qualification Plan.Without Encl ML18040B2951999-09-0808 September 1999 Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999 Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl ML18040A9741999-07-0808 July 1999 Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant ML20207G5051999-06-0707 June 1999 Informs That NRC Office of NRR Reorganized Effective 990328.As Part of Reorganization,Divison of Licensing Project Management Created PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999 Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21 ML18040A9731999-05-24024 May 1999 Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant ML20195B2181999-05-20020 May 1999 Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790 ML18040B2901999-04-30030 April 1999 Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999 Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790 ML17164A9891999-03-12012 March 1999 Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl ML18040A9691999-03-12012 March 1999 Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18040A9721999-03-11011 March 1999 Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031 PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999 Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML20203G5821999-02-17017 February 1999 Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Released in Entirety. Documents Listed in App D Being Withheld in Part (Ref FOIA Exemption 5) ML20202F4761999-01-29029 January 1999 First Partial Response to FOIA Request for Documents.Records in App a Encl & Being Released in Entirety.App B Records Being Withheld in Part (Ref FOIA Exemption 7C) ML18040A9671999-01-29029 January 1999 Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125 ML18040A9681999-01-29029 January 1999 Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031 ML18040A9651999-01-12012 January 1999 Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18030A1021998-12-16016 December 1998 Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs ML18030A4331998-11-25025 November 1998 Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50 ML20195J9101998-11-18018 November 1998 Forwards Notice of Withdrawal of Application for Amends to Facility Operating Licenses (Notice).Notice Has Been Filed with Ofc of Fr.Amends Would Have Revised TS to Eliminate HPCI Pump auto-transfer on High Suppression Pool Level ML20155F7201998-11-0303 November 1998 Final Response to FOIA Request for Documents.Documents Listed in App B Being Encl & Being Released in Entirety. Documents Listed in App C Being Withheld in Part (Ref Exemption 7C) ML18026A2941998-10-19019 October 1998 Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage 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 ML18030A4321998-10-12012 October 1998 Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized 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 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 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 ML18030A4071998-01-0606 January 1998 Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998 ML18017A2931998-01-0606 January 1998 Provides Responses to Improved TS Section 3.8 Per 970324 NRC Rai.Schedule 980628 for Improved TS Implementation. Submittal of Revised Specifications Is Planned for Jan 1998 PLA-4828, Expresses Appreciation for Support Received by Former Project Manager C Poslusny1997-12-29029 December 1997 Expresses Appreciation for Support Received by Former Project Manager C Poslusny 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
Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215 l 770-5151 Brdce D. Kenyon Vlcc President-Nuclear Operations XEHQ, ZIZZ COD 215 / 770-4378 SEP 08 1982 Mr. T. T. Martin, Director Division of Engineering and Technical Programs U.S. Nuclear Regulatory Commission Region I 631 Park Ave.
King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION MEETING WITH REGION I ER 100450 FILE 841-4 PLA-1275 Docket No. 50-387
Dear Mr. Martin:
Attached are the handouts provided in our August 25, 1982, meeting with you and your staff. Included with these handouts is PP&L's "Report on the Investigation of Unit One Small Piping System Design, Installation and Inspection-Program Adequacy and Implementation."
Very truly yours, B. D. Kenyon Vice President-Nuclear Operations WEB/mks Attachment cc: G. Rhoads USNRC R. Perch USNRC
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SUS UEHANNA ALLEGATIONS AND FINDINGS QUESTION 1. - Stress Intensification Factor On site simplified calculations did not analyze weldolet/socket
'connections with large pipe. An SIF of 1. 3 was used for fitting/small pipe interface. Fitting/large pipe interface lt was analyzed with large pipe stress analysis.
RESPONSE
Methods used to account for stress intensification in small piping design and in branch connections on large piping were explained at a PL/NRC meeting on 8/11. NRC. concurred on the approach with only one remaining,NRC concern which will be resolved If either the requirements I
of footnote 6 of NC-3673.2b are being met or PL demonstrate a safety factor of 2 for the worst case weldolet/sockolet branch connection calculated stress Bechtel is responding to this remaining concern by:
(1) Comparing weld profiles of weldolets/sockolets used in SSES with ASME Section III, 1974 edition requirements of NC-3673.2b-2 and corresponding footnote 6.
(2) Performing analyses to demonstrate safety factor of 2 in branch connection stresses (worst case) .
'TATUS NRC has concurred with the approach used during the meeting on 8/11/82.
Additional response information will be presented to NRC on 8/25/82.
.8209240280,'
QUESTION 2.
Nozzle'oads on equipment were ignored on all SBP analyzed .on site. If the allowable nozzle loads were supplied by the manufacturer, the piping loads were compared to it. If it was not provided it was not compared.
The licensee contends that pipe load on equipment is not critical for nonsensitive equipment because there is enough conservatism built into the analysis and the placement of the first support.
Licensee will supply a list of all equipment that was analyzed for NRC ~
review.
RESPONSE-In 8/11 meeting with NRC, PP&L and Bechtel made a presentation.
concerning the above'.. The NRC indicated they had no further. concerns with this issue and 'consider the item closed .
PP&L did promise to provide by 8/25 a list of equipment f'r which detailed small pipe nozzle loads analysis were performed.
STATUS The above will be prese nted to NRC on 8/25/82.
PP&L considers this item closed.
QUESTION 3.
The licensee routed ie sleeve penetrations after the piping was analyzed for stress. The licensee contends that the penetrations have been inspected and documented by the "as-built" verification program.
RESPONSE-In 8/11 meeting with NRC, PP&L and Bechtel made a presentation concerning the above. The NRC indicated that they had no further concerns on this issue. Item is considered closed.
STATUS-This item is closed .
QUESTION 4.
Small pipe anchors, per Bechtel Detail 600 and SPA-1312, do not provide restraint in three directions (x,y,z). There are three drawings of this hanger (Detail 600, SPA-600, SPA-1312) . Due to fabrication tolerances, the clamp may not have an interference contact to resist axial and .
torsional slippage.
RESPONSE
to insure sufficient. contact to
-'nchors were reworked as necessary resist axial & torsional slippage. Calculations were performed to justify the shimming of the anchors in order to enable them to carry the required load. These calculations showed that all stresses are acceptable.
PP&L has performed a 100% inspection following all required rework and has verified required contact between the pipe and the anchor as well as proper gap between the two halves of the anchor.
STATUS The above will be presented to NRC on 8/25/82.
PP&L considers this item closed.
QUESTION 5.
A generic bolt size, problem exists with all 1" ha@gers (Detail 600, SPA-600, SPA-1312). The bolt shoulder specified extends through both ears of the pipe clamp. This causes the bolt to shoulder out before the W
clamp is adequately torqued.
RESPONSE Bechtel Response:
Bolt length used along with the gap and component thickness could lead up to bottoming out of the nut on the bolt threads without achieving the torque. FCR P-4066 and PL-NCR (82-728) have provisions for adding washers to preclude bottoming out of the nut on the bolt.
PP&L performed 100% inspection of the subject bolts. All required rework has been performed, i.e., washers were added as necessary to bolts not passing acceptance criteria to preclude them from shouldering out.
STATUS PP&L considers this item closed.
QUESTION 6.
Bolts specified on Detail 600 are SA-307 but SPA-600 and SPA-1312 are SA-325. SA-325 bolts are of higher strength.
RESPONSE
Bolt material was not specified on Detail 600, however, standard SA-307 bolts were supplied and installed. A study Calculation was performed which justifies the use of SA-307 bolts for the installed Unit 1 anchors. This was discussed in a telecon between NRC, PP&L and Bechtel on 8/17/82. As the result of this discussion, PP&L agreed to submit to NRC the Justification calculation. This was done on 8/19/82 along with a written response.
STATUS Justification calculation and a written response submitted to NRC on 8/19/82.
PP&L considers this item closed .
QUESTION 7.
The upgrade of Detail 600 to the SPA-1312 design caused distortion of the clamp because of welding stresses.
RESPONSE
Four line contact and proper I
bolt torquing result in required clamping forces which preclude the effects of distortion caused by weld stresses.
The justification for four line contact and proper bolt torque is discussed in the responses to questions (4) and (5) respectively STATUS-The above response will be presented to NRC on 8/25/82.
PP&L considers" this item closed.
QUESTION 8.
The "ears" of, large bore pipe hanger clamps were trimmed to prevent interference. This has not been incorporated into the design. Example:
HBC-101-H210 RESPONSE-The GBC-101-H210 clamp trimming was shown conceptually on the as-built detail and .judged to be adequate during the as-built reconciliation.
STATUS The above response will be presented to NRC on 8/25/82.
PP6L considers this item closed.
QUESTEON 9.
SBP Systems on Unit 1 m'ay be too rigid. The hangers required for Unit I were analyzed by the simplified method and resulted in about 700 supports.
The hangers for Unit, 2 were computer analyzed and resulted in about, 270.
RESPONSE
This was discussed in an 8/17 telecon between PPGL, BT and NRC. During meeting on 8/18 between PPGL & NRG; PPaL was informed that this item is closed.
STATUS This item is closed-
QUESTION 10.
Structured steel beam. flange warpage and web damage due to dead load placed on beams at elevation 749'.near outboard MSIV.
RESPONSE
In a meeting between PPGL and NRC on 8/18, PPGL was informed that this item is closed.
STATUS This item is closed.
QUESTION 11.
A design change on December 21, 1981 revised Detail 600 to SPA 600 but the new design was not distributed for work or inspection.
RESPONSE-The installation and inspection of Detail 600 type anchors was done in accordance with Detail-600 Rev. 1 while a drawing superseding it (SPA-600) existed at the site. This occurred because SFHO issued the superseding drawing, SPA-600 on December 21, 1981, without first issuing the cancellation revision to Detail 600. The cancellation for Detail 600 was issued June 2, 1982. Although SFHO issued SPA -600 before the cancellation revision for Detail 600, they did make a note on SPA-600 that it superseded Detail 600. However, due to inadequate document review at the site, this note was overlooked. The cancellation revision should have been issued prior to issuing SPA-600. In addition, a better document review should have been done.
All differences between SPA 600 and Detail 600 have been reconciled with the design requirements, confirming that the existing installations are adequate.
To avoid this problem in Unit 2, SPA's are not being utilized .
Individual pipe support details are being generated like large pipe supports. All drawings for installation and inspection will be issued and controlled by established field procedures, which will include requirements, 'as applicable, to ensure appropriate time constraints and doumentation requirements for field review and implementation of design changes.
STATUS-The above response will be presented to NRC on 8/25/82.
PP&L considers this item closed.
QUESTION 12.
The proposed fix of Detail 600 hangers does not appear to be acceptabl (line contact on pipe, not full length).
RESPONSE-A calculation has been made to justify the acceptability of four line contact. The calculation shows that a two inch contact on each side is acceptable resulting in stresses that are below the allowables'.
STATUS The above response will be presented to NRC on 8/25/82.
PP&L considers this item closed.
QUESTION 13.
One pipe support attached to two seismically independent structures.
Three supports have been identified connected between the reactor building and primary containment.
RESPONSE-PPaL transmitted sets of calculations to NRC on 8/19/82 indicating that the correct response spectra and seismic anchor movement analysis were used.
This was provided along with a written response.
STATUS PPaL considers this item closed.
QUESTION 14.
Snubber, SP-HCC-136-H-.2003 was installed such that the support can be deflected several inches laterally.
RESPONSE-We have inspected the support after the question was raised. The support frame is flexible in the north-south direction, i.e.,'n the axial direction of the pipe. It maintains rigidity in the east-west direction. Since the design requirement of the axis of restraint is east-west only, the support is considered to meet its intended purpose.
Therefore, the as-built support is technically sound.
STATUS The above will be presented to NRC on 8/25/82.
PP6L considers this item closed.
QUESTION 15.
Lack of clearance between snubber end and clamp ear.
RESPONSE
There may be a lack of sufficient clearance on the size 35 snubbers.
Therefore a 100K inspection for clearance will be done on all size 35 snubbers. In conjunction, a 10X inspection for clearances will be done on the balance of snubbers in Unit /31.
STATUS-The above response will be presented to NRC on 8/25/82.
PP&L is currently pursuing this course of action. - A corrective action will be taken prior to heat up exceeding 200 F.
QUESTION 16.
Site fabricated rear brackets of snubbers did not provide adequate clearance for lateral movement of the snubber.
RESPONSE
There are no site fabricated rear brackets for snubbers at SSES Unit 81.
STATUS The above response will be presented to the NRC on 8/25/82.
PP&L finds the above response satisfactory and considers this item closed.
QUESTION 17.
Falsification of records: QC inspection on acceptance of SPA-1312 bolting.
RESPONSE
The small pipe hanger detail drawing for hangers utilizing the SPA-1312 clamp does not identify material type for the bolts in question, therefore, it was not required to be verified. The specific activity on the Quality Control Inspection Record was signed because it deals with other attributes in addition to material type such as material size of rods, clamps, saddles, clevises, etc.
QC. inspection of inaccessible items takes into account the sequence of installation to allow inaccessible items to be inspected.
Where items which are required to be inspected per design drawings/
Quality Control inspection Records are found inaccessible, they are identified on Nonconformance Reports or P-20 exception forms for pipe supports as quality indeterminate.
STATUS
-'he above response wf.ll be presented to NRC on 8/25/82.
PP&L considers this item closed.
QUESTION 18.
Division of responsibility between Field Engineering and Resident Engineering.
RESPONSE-There have always existed distinct organizations and division of responsibilities between the field engineering and resident engineering.
The Resident Engineering has a dual reporting relationship within engineering as they report to the Project Resident Engineer and to the Project Engineering Group Supervisor primarily for technical guidance.
There have been instances where resident engineers were loaned to field engineers to work in the field engineering organization and perform field engineering duties and functions.
Around February 1982, a Hanger Design Coordination Team was formed to promote better communication, and to improve efficiency and productivity of the installation interference resolution process. Normally, crafts present an interference problem to Field Engineering and Field Engineering in turn passes on the problem to,Resident Engineering after they make an evaluation to decide that Resident Engineering's involvement is needed.
The Resident Engineering branch of the team worked as a separate entity in the manner they do when they work from Resident Engineering's work location. The team was physically situated in one trailer to expedite the documentation process and also to get prompt involvement of the Resident Engineering by bringing them to the close pr'oximity of the Field Engineering organization. Resident Engineering members during these operations reported to the Resident Engineering Group Supervisor and received technical as well as administrative guidelines from him.
Thus, there is no instance where the organizational and division of responsibilities charter was violated during the Unit 1 hanger program.
STATUS The above response will be presented to NRC on 8/25/82.
PP&L considers this item closed.
QUESTION 19.
Field engineering's initialing of check/approve entries'on field drawings .
RESPONSE
Field Piping Engineer's (LFPE) initials were often I'he Lead entered by others in the "APPROVED BY" block on hanger drawings, without the identity of the actual approver being indicated. This specific discrepancy was previously addressed and corrected via Bechtel Q.A. Audit PFA-24-4-10, QAF /k4.
FP-P-11 Paras. 4.3.6 (small pipe isometrics), 5.3.1.2.c (large pipe hanger details), and 6. 2. 7. 2.c (small pipe hanger details) all require approval of the LFPE or his designee; but do not clearly specify the method of initialing (i.e., whose initials are entered) .
Early in the project, various individuals are designated to sign/approve these drawings for the LFPE. The designees were generally supervisors involved in the dr'afting effort, but other piping supervisors were also delegated this authority.
NOTE: "Approval" of Field piping drawings although not actually defined in any of the procedures, actually signifies concurrence that required design reviews/checks have been performed (i.e., checker's initials on the drawing) and formal authorization to issue the drawing.
The requirements of FP-P-11 were understood by some of the designees involved in field hanger "design"* to mean that the signature (or initials) of the LFPE himself must appear on the drawings. Consequently, several of the designees/approvers entered only the initials of the LFPE to document their approval of the drawing. ')his method of documenting approval, although contrary to standard ~ualit verification conventions was not considered by the individuals involved to reflect improper ~draftXn conventions.
- Although referred to as Field hanger "design", in actuality the Field performed varying degrees of configuration revision and drafting but in all. cases Project Engineering was considered the final approval authority.
In some cases the person reviewing/checking hanger drawings was the originator of the drawing, who entered fictitious initials
("E.D.") in the "BY" block and ("D.E.H.") in the "CHECKED" block.
FP-P-11 omits specific checking requirements for Field revisions to small pipe hanger details. (Although independent checking was the established practice.) Paras. 4.3.5 (small pipe isos) and 5.3.1.2b (large pipe hangers) imply separate and independent checks, but are not really specific. Nonetheless, the revision block. entries on
QUESTION 19 PAGE 2 OF 3 the drawings do imply that a separate individual must check the drawing. Entry of the originator's initials in both the "BY" block and the "CHECKED" block, as well as entry of fictitious initials can only reflect ignorance on the part of the person involved, and-attempts by that party to take a shortcut..
In some cases the checkers entered the Small Pipe Hanger supervisor's initials ("A.G." or "T.G.") in the "CHECKED" block.-
The entry of the SPH supervisor's initials in the "CHECKED" block involved an independent checker who was qualified but who was not formally designated as a checker, so he entered his supervisor's initials again without any ill intent or attempt at deceit.
When Field Engineering performs field inspection of hangers, they inspect the installation against the detail drawing to verify agreement. This, in effect is a review/check of the hanger detail. Upon verifying agreement (or correcting the drawing) the drawing is presented to Quality Control who inspects the installation for compliance with the drawing and vice-versa. Any discrepancies identified during this additional "check" are identified and the drawing is corrected accordingly (either by red-line or by revision) and the correction is rechecked/verified by Quality Control prior to'heir acceptance of the installation.
Therefore, even if an independent drafting check was never
~etfotmed (ooz investigation indicates that this happened only in isolated cases) subsequent Field Engineering and Quality Control checks d9d occur after the drafting and checking of the drawings, and any resultant design discrepancies would have been resolved during as-built verification. (The adequacy of the as-built verification was substantiated under separate audit programs involving PPGL QA, Bechtel Quality Control and a sp'ecial audit team within Field Engineering.) Thus, the procedural discrepancies would have no effect on the validity of the as-built drawing actually reflecting the as-built conditions and as used by engineering to perform the as-built reconciliation.
Additionally all hanger drawings have received, after final as-built, a final LFPE/designee approval documented on the drawing per Para. 8. 1. 2 of FP-P-11. Any discrepancies in previous LFPE approvals documented on the hanger drawings are. therefore irrelevant because the final LFPE/designee. approval covers the final QC-verified as-built drawing.
Also, Pro]ect Engineering has reconciled the field as-built hanger details w'ith the design and signed 'the drawings per Para. 8. 1.2 .of FP-P-11. This involves final verification that the as-built drawing represents an adequate structure based on the stress analysis.
0 QUESTION 19 PACZ 3 OF 3 Finally, we believe that piping drawings prepared by the field do accurately reflect .the installation. In addition, we believe that Quality Assurance programmatic requirements were adequately controlled by the engineering and field programs.
Based on the above described checking and approvals accomplished after final issuance of the hanger detail drawings by the field hanger groups, no further remedial corrective action should be necessary to address completed Unit 1 hangers.
With respect to other drawings used for piping as-building and design verification, review with applicable personnel indicates that the LFPE initials were not entered on FCI's (large pipe as-built. drawings) and small pipe fabrication isometrics (used for small pipe, as-building); that it was standard practice for the checkers and approvers to enter their own initials.
1 Action to Preclude Recurrence
'he basic cause of the problems identified is lack of clear direction concerning defini~ the'eview/checking and approval functions involved with'ield drafting, and identifying concisely the requirements for documenting these functions. All Field Procedures involving Field Design (all disciplines) will be reviewed for similar lack of direction; and appropriate revisions to the Procedures will be processed . In addition, all persons responsible for drafting, review, and approval functions will 'be instructed as to the importance of adhering to these requirements to ensure similar didcrepancies do not occur in the future.
Corrective action will be completed by September 30, 1982.
STATUS-The above response will be presented to NRC 8/25/82.
With implementation of the above corrective action, PP&L considers this item closed.
l I
Question 20 PP&L was requested to determine whether PP&L and Bechtel Q.A. Programs covered the areas of concern identified during the PP&L Investigation of Small Pipe Design/Installation.
Response
Generally, the audits performed by Bechtel were of enough detail and depth to indicate that there was sufficient review of the particular aspect of the system being audited. Bechtel MCAR's (Management Corrective Action Report) and QAR's (Quality Action Report) are written for any particular discrepancy (outside an audit scope) that requires corrective action and follow-up. The following are examples of audit findings and QAR's that indicated problem areas related to those found during the PP&L investigation:
- 1. Audit 8'24-4-10, February, 1982, contained a finding that neted a noncompliance with the procedure for "voiding" drawings.
(Another finding in this audit, although not related to the Investigation Report, reported .that supervisor's signature (initials) being misused .)
- 2. Audit //'s 30-3-4, 30-3-5, 30-3-6, and 30-9-2, dated March, 1981; August, 1981; April 1982; and May, 1982; respectively, discovered various instances of lack of controls for procedural implementation and engineering interfaces.
- 3. Audit 824-4-9, June', 1981', 'contained findings that indicated various areas in which the'as-built" configurat'ion of the
~
piping did not agree with the drawings.
- 4. QAR 8859, July 30, 1982, dealt with Field Engineering not reviewing SPA Drawings in a timely manner.
- 5. QAR //856, July 22, 1982, deals with the deficiency identified in the design of "SPA 600" hanger. 4 B.. PP&1 <P.A.
During the period under review, there were seven (7) formal and seven (7) unannounced audits relating to the small pipe program.
'.'... '-"..'.-':.';: These. audits covered such areas as document control, Q.C.
.Inspection, and design control (related to interface control and the use of the latest information for design verification) . Numerous findings were identified during these audits and several of these still remain open. Some ohe audits in which the findings were similar to those of the PP&L Investigation are:
8
- 1. Audit f/C-82-14 (joint audit with Bechtel), April, 1982, in which some procedural control were lacking in the Resident Engineering Group.
Ques%ion 20 Cont'd Page 2 of 2
- 2. Audit PC-81-06, January, 1982, identified problem, areas in the Field Engineering locating hanger deficiencies in this walkd own.
3 ~ Unannounced Audit f/1 1 1, September, 1981, discovered various areas of procedural and implementation problems in the design portion of the small pipe program.
- 4. N-5 Package Review Audit f/'s CL-48, Hay, 1982; CL-34, May, 1982; and CL-34, June 1982; indicated areasin which there were drafting errors.
IV. CONCLUSIONS A.. PP&L and Bechtel audits covered the programmatic/procedural aspects of the small pipe design/installation program, but did not include a technical review of these aspects.
B. The Investigation Team had the benefit of technical support. The majority of the concerns identified during the Investigation were a result of the technical review. As a consequence of PP&L and Bechtel audits not having technical support, it cannot be expected
,that they would'aise the same concerns that the Investigation Teams did.
C. The reviewing of PP&L and Bechtel audits reveal that their frequency did not increase in proportion to work being accomplished during the "final hectic period" (April-June 1982). But both Bechtel and PP&L QA coverage of small pipe program existed in the forms of Bechtel QA surveillance of hanger as-built installation (from Oct. 1981) and PP&L N-5 Package Review, which occurred from September, 1981, through July, 1982. These activities increased in proportion to. the work being accomplished during the "final hectic period ." These activities and any discrepancies were formally documented.
STATUS PP&L considers this item closed .
~ ~
gust 23, 1982 FILE MEMO SUSQUEHANNA STEAM ELECTRIC STATION INVESTIGATION OF SMALL PIPING SYSTEMS PROBLEMS A meeting was held on August 18, 1982 between the Nuclear Regulatory Commission and PP&L concerning the small piping program. Cer ain questions were raised concerning the program and PP&L committed to investigate these. The NRC questions and PP&L responses follow:
Question: l. Nhy had Bechtel QC accepted (signed-off) certain attributes of hangers which were inaccessible and thus not inspectable?
Response: The NRC made reference to the "detail 600" clamps which were modified per SPA 1312. The modifications were of such a nature that the clamp bolt heads were concealed after the modification and thus it is not possible to verify that the markings on the bolt head indicate the correct material (A-325) ..
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The'Bechtel QC inspector sign-off in Section 3.0 of the Inspection Report.'IR) does not, indicate that the attribute of bolt material was inspect:ed, only that the "detail 600" clamp is at that location. This is consistent with the inspection program in that the bolting material is not identified on the unique hanger detail drawings and, therefore, was not a required QC verification. The bolts are inspected by the Bechtel QC Receiving Group upon receipt at Susquehanna for material type. =
If the bolting material had been an attribute to be inspected, the fact that it was uninspectable would have been noted on a non-conformance report for.
resolution. The PP&L Investigation Teams noted this type of Bechtel QC action during +he Investigation since non-conformances were generated for areas where plate thick-ness could not be measured due to grouting completion or:-where structural tubing thickness could not be measured due to construction close-up. These types of items were resolved'by UT measurements or by dr'ling a hole to permit thickness measurement.
In summary:
- a. All attributes of modified friction clamps (SPA-1312) required to be inspected were accessible.
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- b. The inaccessibility noted by the NRC involved an attribute (bolting material) which was not required by Project Engineering to be inspected by OC.
Question: 2. Are the Bechtel Field Engineering and Resident Engineering personnel working together and reporting to the same Group Supervisor?
Response: The Field Engineers and Resident Engineers were located in the sam facility for the purpose of exoediting changes required during the installation of the small bore piping systems and hangers. The Investigation Team reviewed the reporting functions, organizational chart and names of personnel involved in those organizations. The con-clusion of the Investigation Team was that for Unit 1 Field Engineers and Resident Engineers worked closely together for efficiency sake but had different reporting supervision.
The area of Resident Engineering personnel being "lent" to Field Engineering and returning sometime later to the Resident Engineering group was investigated. This organizational system applies only to Unit 2. There are no Bechtel program requirements preventing its im-plementation. The concern that the same individual may perform the initial design as a Field Engineer and subsequently perform the verification calculations as a Resident Engineer was investigated. The Resident
-.,Engineering calculation procedure xequires that a checker and Supervisor review and sign the calculation after the originator performs'the initial calculation.
This series of reviews and signatures provides assurance that the calculation is performed accurately and correctly.
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