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Category:CORRESPONDENCE-LETTERS
MONTHYEARHNP-99-156, Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools C & D in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration1999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools C & D in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration HNP-99-153, Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon1999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon IR 05000400/19990071999-10-0707 October 1999 Informs That NRC Region 2 Will Conduct Triennial Fire Protection Baseline Insp 50-400/99-07 at Harris Facility on 991101-05.Insp Objection Will Be to Evaluate Fire Protection Program Implementation HNP-99-148, Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld1999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8991999-10-0404 October 1999 Forwards SE Accepting Licensee 990401 Submittal of Rev 99-1 to Harris Nuclear Plant EALs for NRC Review & Approval IAW 10CFR50,App E ML18017A8951999-10-0404 October 1999 Forwards SE Accepting Util 961118,970314,980612 & 990528 Responses to GL 96-05, Periodic Verification of Design- Basis Capability of Safety-Related Motor-Operated Valves ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program HNP-99-142, Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves1999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves HNP-99-145, Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii)1999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A9021999-09-23023 September 1999 Informs That NRC Has Noted That Third Quarter 1999 Performance Indicator Data,Reported in July 1999,showed White PI for Unplanned Scrams Per 7,000 Critical Hours HNP-99-143, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations ML18017A9071999-09-20020 September 1999 Forwards Insp Rept 50-400/99-11 on 990719-23 & 0802-06.No Violations Noted.Insp Found That Engineering Activites Supported Safe & Reliable Operation of Sys HNP-99-140, Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) HNP-99-127, Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety HNP-99-129, Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity1999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS HNP-99-136, Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS1999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML14314A7771999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Slide Presentations & List of Questions Received from Participants Encl HNP-99-130, Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided1999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided ML18017A8481999-08-19019 August 1999 Advises That Info Contained in Encl 3 to Plant Ltr Serial: HNP-99-112, Info Supporting HNP Responses to NRC Rai,Dtd 990616, Will Be Withheld from Public Disclosure HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment HNP-99-128, Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment1999-08-10010 August 1999 Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment HNP-99-163, Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl1999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0541999-08-0505 August 1999 Forwards RAI Re Licensee 981223 Request for Amend to Revise Plant TS 5.6, Fuel Storage, to Increase Sf Storage Capacity by Placing Sf Pools C & D in Service ML18016B0551999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 05000400/LER-1999-006-01, Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS1999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements HNP-99-116, Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed1999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed HNP-99-119, Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 19981999-07-30030 July 1999 Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 HNP-99-113, Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 9909301999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 HNP-99-114, Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP1999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP HNP-99-104, Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl1999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9971999-06-30030 June 1999 Discusses Closure of Review of Response to GL 92-01,rev 1, Suppl 1, Rv Structural Integrity. Info Revised & Being Released as Rvid Version 2.Info Posted on Listed Website. Recommends Info Be Reviewed ML20212H7741999-06-23023 June 1999 Responds to Re Petition Filed by Orange County Board of Commissioners Re Proposed Expansion of Sf Storage Capacity at Shearon Harris Npp.Public Meeting Will Be Held at Later Date.With Certificate of Svc.Served on 990624 ML18016A9921999-06-18018 June 1999 Forwards SER Accepting Util 980127 Relief Request 2RG-008 Related to Snubber Inservice Insp Requirements for Shearon Harris Nuclear Plant Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year Insp Interval ML18016A9881999-06-16016 June 1999 Forwards Request for Addl Info Re Amend Request to Increase Fuel Storage Capacity at Shearon Harris Nuclear Power Plant HNP-99-094, Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration1999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration HNP-99-103, Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated1999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9811999-05-28028 May 1999 Announces Safety Sys Design & Performance Capability Insp Scheduled for 990719-23 & 0802-06,under Insp Rept 50-400/99-11.Forwards Info Requested for HHSI & Lhsi Sys HNP-99-091, Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs1999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re CPL Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9611999-05-26026 May 1999 Discusses Completion of Licensing Action for GL 96-01 for Shearon Harris Nuclear Power Plant.Licensees 960416,970121 & 990504 Responses Provided Both Info Requested & Responses Required by Gl,Therefore TAC M94683 Closed HNP-99-087, Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend1999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML20206R2511999-05-19019 May 1999 Responds to Addressed to Chairman Jackson Requesting That NRC Grant Standing to Orange County Board of Commissioners in Shearon Harris Proceeding Currently Before Board.With Certificate of Svc.Served on 990519 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARHNP-99-156, Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools C & D in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration1999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools C & D in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration HNP-99-153, Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon1999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon HNP-99-148, Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld1999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also HNP-99-142, Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves1999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence HNP-99-145, Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii)1999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) HNP-99-143, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations HNP-99-140, Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) HNP-99-127, Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety HNP-99-129, Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity1999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity HNP-99-136, Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS1999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS HNP-99-130, Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided1999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment HNP-99-128, Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment1999-08-10010 August 1999 Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment HNP-99-163, Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl1999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl 05000400/LER-1999-006-01, Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS1999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements HNP-99-116, Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed1999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed HNP-99-119, Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 19981999-07-30030 July 1999 Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 HNP-99-113, Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 9909301999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 HNP-99-114, Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP1999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP HNP-99-104, Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl1999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration HNP-99-094, Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration1999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration HNP-99-103, Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated1999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 HNP-99-091, Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs1999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re CPL Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation HNP-99-087, Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend1999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend HNP-99-088, Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.461999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 HNP-99-085, Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6)1999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 HNP-99-084, Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) HNP-99-060, Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant1999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant HNP-99-074, Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp1999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-069, Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping1999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld HNP-99-070, Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC1999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC HNP-99-076, Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) HNP-99-072, Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6)1999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) HNP-99-067, Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change1999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change HNP-99-065, Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl1999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl HNP-99-058, Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl1999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A8911999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld HNP-99-059, Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld1999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld HNP-99-024, Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings1999-04-0101 April 1999 Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings 1999-09-08
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ACCELERATED DOCUMENT DISTRIBUTIONSYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9303180079 DOC.DATE: 93/03/12 NOTARIZED: NO ACYL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION VAUGHN,G.E.
Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Suppls 930107 response to violations noted in Insp Rept 50-400/92-27.Correvtive actions:local EDG operator implemented Annunciator Panel Procedire APP-DGP-H-2 Clearance Procedure AP-020 will be revised.
DISTRIBUTION CODE:
IE01D COPIES RECEIVED:LTR 4 ENCL SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:Application for permit renewal filed.
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D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEl CONTACI'HEDOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED(
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Carolina Power & Light Company P.O. Box t65 ~ New Hiil, NC 27562 G.E. VAUGHN Vice President Hania Nuctear Ptant MAR t 2
l995 Letter Number:
HO-930073 Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555 NRC-806 Gentlemen:
SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400 LICENSE NO. NPF-63 SUPPLEMENTARY REPLY TO A NOTICE OF VIOLATION As stated j.n Carolina Power and Light Company's January 7, 1993, reply to, Notice of Violation 400/92-27-02, the attached:supplementary reply is hereby submitted which addresses corrective steps taken to avoid further violations.
It is'considered that the corrective actions taken/planned are satisfactory for resolution of the violation.
Thank you for your consideration in this matter.
G.
E. Vaughn Vice President Harris Nuclear Plant MGW:kls Attachment I
cc:
Mr. S.
D. Ebneter (NRC-RII)
Mr. N. B. Le (NRC-NRR)
Mr. J.
E. Tedrow (NRC-SHNPP)
MEM/HO-930073/1/OS(
P P P q 9
=eti303i80079 9303i2 PDR ADOCK 05000400 Q
PDR
Attachment to 'NRC-806 SUPPLEMENTARY-REPLY TO A NOTICE OF VIOLATION NRC INSPECTION REPORT NO. 50-400/92-27 VIOLATION 400 92-27-02 Re orted Violation:
Technical Specification 6.8.1.a requires that written procedures be established and implemented covering procedures outlined in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Regulatory Guide 1.33, Appendix A, paragraphs l.c and 8, require procedures for the conduct of equipment control and surveillance testing activities.
Administrative procedure AP-020, Clearan'ce Procedure, Step 5.7.1 requires that ground devices installed for wo'rk be removed following maintenance completion.
Surveillance procedure EST-212, Type C Local Leak Rate
- Tests, Attachment 1,
Step 6.1 specifies the steps necessary to return penetration M-7 to service and requires that drain valves be closed prior to opening the isolation valve to refill the system.
Surveillance procedure MST-M0011,'mergency Diesel Generator Crankshaft Web Deflection and Thrust Clearance
- Check, Steps.7.1.3 and 7.2.2 specify that the engine be barred over prior to taking measurements.
Contrary to the above, l.
On November 6,
- 1992, ground devices were not properly removed from the "A" Emergency Diesel Generator following maintenance which resulted in an automatic generator differential trip upon engine startup.
3 On November 12, 1992, while returning penetration M-7 to service, drain valves,lCS-12 and 1CS-13 were not closed prior to opening isolation valve 1CS-16 which spilled approximately 50 gallons of contaminated liquid in the auxiliary building.
On November 8,
- 1992, procedure MST-M0011 was found to be inadequate in that it failed to specify appropriate steps to open and reclose cylinder petcocks following engine barring.
This resulted in a subsequent start of the engine with the cylinder petcocks open.
This is a Severity Level IV violation (Supplement I).
Denial or Admission:
The violation is admitted.
Reason for the Violation:
(Example 1)
Ground straps were placed on the output of the 1A-SA Emergency Diesel Generator (EDG), and were added to clearance 0 OP-92-1054 without the knowledge of the MEM/HO-930073/2/OS1
Attachment to NRC-806 SUPPLEMENTARY REPLY TO A NOTICE OF VIOLATION NRC INSPECTION REPORT NO. 50-400/92-27 clearance holder.
This indicates a possible weakness in the interface between AP-020 (Clearance Procedure) and AP-024 (Grounding Device Control)..
The ground straps were properly installed and
- tagged, but were located inside a closed electrical cabinet which is not normally inspected following routine mechanical maintenance.
With work completed, the clearance holder signed off the clearance as having "All work complete with electrical grounds removed".
On subsequent
- startup, the EDG immediately tripped on generator differential.
(Example 2)
Operators inadvertently failed to restore the proper system valve lineup while removing a clearance.
As a result, approximately 50 gallons of Reactor Coolant System (RCS) water was leaked into the Reactor Auxiliary Building (RAB) through an open drain line in, the letdown portion of the Chemical and Volume Control System (CVCS).
The reactor was shutdown for refueling at the time.
(Example.3)
While performing MST-M0011, mechanics weie instructed to open the EDG cylinder petcocks during a barring step.
The barring instruction in MST-M0011 gives no guidance as to the desired position of the cylinder petcocks at the completion of the
- MST, and they were left open.
The condition of the petcocks was not adequately communicated to operations personnel.
OST-1013, 1A-SA Emergency Diesel Generator Operability Test, Monthly Interval Modes 1-2-3-4-5-6, was begun shortly after MST-M0011 was completed.
Since the diesel had been run within the previous four, hours, a barring step in OST-1013 which would-have verified proper position of the petcocks was NA'd.
As a result, the diesel was started with the cylinder petcocks open.
Reasons for this incident were:
- 1) MST-M0011 gives inadequate instruction for the diesel barring step, and 2) there was inadequate communication between maintenance and operations personnel.
Corrective Ste s Taken and Results Achieved:
(Example 1)
The local EDG operator implemented Annunciator Panel Procedure, APP-DGP-H-2 due to the Generator Differential Protection Trip alarm and verified that, all automatic actions required had occurred.
He then placed the diesel in maintenance
- mode, and the diesel was declared inoperable.
Work requests 92-AQWT1 and 92-AQWT2 were written to bridge and meggar the generator and to investigate=
the cause of the trip.
The 87-DG relay was tested satisfactory.
During the investigation, the ground straps were discovered and removed.
MEM/HO-930073/3/OS1
Attachment to NRC-806 SUPPLEMENTARY REPLY TO A'OTICE OF VIOLATION NRC INSPECTION REPORT NO. 50-400/92-27 (Example 2)
Upon notification by Health Physics personnel of a spill in-,the RAB, control room operators promptly isolated, Residual Heat Removal (RHR) letdown and dispatched operators to investigate.
The drain line was isolated and RHR letdown was restored.
The responsible operations personnel were counseled regarding this incident.
(Example 3)
The cylinder petcocks were shut as soon as the condition was discovered.
The control room was notified, and the diesel was shutdown per-OP-155, Diesel Generator Emergency Power System.
After performing appropriate checks per OP-155 Attachment.8, Emergency Diesel Generator Engine Barring Checklist, the diesel was restarted and OST-1013 was satisfactorily completed.
Copies of the Adverse Condition Reports (ACRs) documenting the three examples of the violation described, above have been distributed to the operating shifts for review.
Corrective Ste s Taken to Avoid Further Violations:
(Example 1)
AP-020 (Clearance Procedure) will.be revised to make it clear who the clearance holders are and what their responsibilities are regarding the status of work being performed under the clearance.
The revision will provide for a better interface with AP-024 (Grounding Device Control) by providing a
separate signature blank for removal of grounds.
(Example 1 and 2)
Plant Management will express expectations for adherence to clearance procedures to appropriate plant personnel through site safety meetings.
Expectations regarding clearances willbe expressed to contractors during initial training and retraining.
(Example 3)
Procedure SPP-0025 Rev.
0, Emergency Diesel Generator Barring Proceduie was approved on February 25, 1993 to provide detailed instructions to maintenance personnel for barring of the Emergency Diesel Generator Diesel Engine.
The Manager Maintenance issued a
memorandum to first line supervisors
.instructing personnel that, until procedural guidance was implemented, they would obtain support from the Operations group whenever their procedures called for one of the diesels to be barred.
This interim instruction is no longer required with the implementation of procedure SPP-0025, Rev.
0.
Date When Full Com liance Will Be Achieved The corrective actions as stated above will be completed by June 1,
1993.
MEM/HO-930073/4/Osl