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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18017A9241999-10-15015 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 ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 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 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 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 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 ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 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) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 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) ML18017A8651999-09-0808 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 ML18017A8581999-09-0303 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 ML18017A8541999-08-20020 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 ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 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 ML18016B0391999-07-30030 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 ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 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 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 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 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 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 ML18016A9831999-06-10010 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 ML18016A9721999-05-28028 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 ML18016A9631999-05-25025 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 ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9601999-05-11011 May 1999 Forwards Resolution Adopted by Carrboro Board of Aldermen at 990504 Meeting.Resolution Expresses Town Concern Re Util Plans to Double high-level Nuclear Waste Storage at Shnpp 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 ML18016A9451999-05-0404 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) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 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 ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp 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 ML18016A9211999-04-27027 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 ML18016A9221999-04-27027 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) ML18016A9161999-04-22022 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) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 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 IR 05000400/19982011999-04-12012 April 1999 Discusses Safeguards Insp Rept 50-400/98-201 (Operational Safeguards Response Evaluation) on 980908-11.No Violations Noted.Licensee Performance During Evaluation Indicated Excellent Overall Contingency Response Capability 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18017A9241999-10-15015 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 ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 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 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 ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 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) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 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) ML18017A8651999-09-0808 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 ML18017A8581999-09-0303 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 ML18017A8541999-08-20020 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 ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 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 ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0391999-07-30030 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 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 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 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 ML18016A9831999-06-10010 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 ML18016A9721999-05-28028 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 ML18016A9631999-05-25025 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 ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 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 ML18016A9451999-05-0404 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) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 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 ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp 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 ML18016A9221999-04-27027 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) ML18016A9211999-04-27027 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 ML18016A9161999-04-22022 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) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 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 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 ML18016A8891999-04-0101 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 ML18016A8811999-03-31031 March 1999 Responds to NRC 990301 Ltr Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 ML18016A8671999-03-19019 March 1999 Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC ML18016A8631999-03-19019 March 1999 Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl ML18016A8691999-03-18018 March 1999 Forwards Resolution Adopted by Lee County,North Carolina Board of Commissioners Re Proposed Expansion of high-level Radioactive Waste Storage Facilities at Carolina Power & Light Shearon Harris Nuclear Power Plant ML18016A8511999-03-15015 March 1999 Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs 'C' & 'D'. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld ML18016A8601999-03-15015 March 1999 Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0911990-09-12012 September 1990 Confirms That Fee Electronically Transferred to Dept of Treasury for Payment of NRC Review Fees ML18009A6581990-09-11011 September 1990 Submits Addl Info Re Use of Hafnium Control Rods at Facility.All Rods Will Be Removed During Spring 1991 Outage ML20059H4181990-09-0606 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-13.Corrective Action:Changes to EST-717 in Area of Power Normalization Under Study for Past Several Months ML17348B4941990-08-30030 August 1990 Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty ML20059D3511990-08-30030 August 1990 Forwards Decommissioning Financial Assurance Certification Rept Submitted by North Carolina Eastern Municipal Power Agency ML18009A6261990-08-10010 August 1990 Informs That Action Committed to in Response to Generic Ltr 88-14, Instrument Air Supply Sys, Completed ML18009A6241990-08-0303 August 1990 Forwards Addl Info Re Operator Action Times Assumed in Steam Generator Tube Rupture Analyses for Plant,Per 900712 Telcon ML18009A6081990-07-31031 July 1990 Forwards Plan for Shearon Harris Nuclear Power Plant Emergency Exercise - 900919, Per NRC Request.W/O Encl ML20055J4171990-07-30030 July 1990 Forwards Rev 5 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20055F9431990-07-12012 July 1990 Advises That Stated Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900711 for Payment of Operator License Exam Fees for Listed Insp Invoices ML18009A5991990-07-0606 July 1990 Comments on Electrical Distribution Sys Functional Insp Rept 50-400/90-200 on 900212-0316.Seismic Qualification Package Subsequently Upgraded to Include Qualification Info Based on Receipt of Part 21 from Transamerica Delaval ML18009A5851990-06-28028 June 1990 Advises That Emergency Preparedness Exercise Scheduled on 900919.Exercise Will Consist of Simulated Accident at Plant Site & Will Involve Planned Response Actions.Objectives to Be Fulfilled Encl ML18009A5621990-05-30030 May 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Rept 50-400/90-06.Corrective Actions:Procedures OST-1008 & OST-1108 Revised to Delete Stroke Testing of Valve 1ST-359 on Quarterly Basis ML18009A5141990-05-0303 May 1990 Forwards Eddy Current Exam CP&L Shearon Harris Nuclear Power Plant Steam Generators A,B & C, Providing Results of Inservice Insps Performed During Plant Second Refueling Outage in Oct 1989 ML18009A4941990-04-26026 April 1990 Forwards Radiological Environ Operating Rept,1989, Radiological Environ Operating Rept,Vol II,Jan-June 1989, Sample Analyses Data & Radiological Environ Operating Rept,Vol III,Jul-Dec 1989,Sample Analyses Data. ML18009A5031990-04-25025 April 1990 Submits Suppl 2 to Relief Request R2-001 Re Plant 10-yr Inservice Insp Plan,Per 880129 Request ML18009A4911990-04-24024 April 1990 Forwards Addl Info Re Proposed Wakesouth Regional Airport to Be Located Near Facility,Per 900411 Request.Info Previously Provided to NRC During 900320 & 23 Telcons ML18009A4841990-04-24024 April 1990 Forwards Corrected Bases marked-up Page to 900226 Tech Spec Change Request Re Surveillance Intervals ML18009A4251990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule Based on Guidelines Provided in NUMARC 87-00, Guidelines & Technical Bases for NUMARC Initiatives.... No Changes to Previous Calculations Necessary & One Deviation Noted ML18009A4231990-03-29029 March 1990 Suppls Response to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Actions:Surveys Performed to Determined Extent & Level of Contamination & Personnel Involved Decontaminated ML18009A4111990-03-23023 March 1990 Responds to NRC 900227 Ltr Re Violations Noted in Insp Rept 50-400/90-02.Corrective Actions:Personnel Involved W/ Quadrant Power Tilt Ratio Calculations & Operability Determination Counseled ML18009A4121990-03-23023 March 1990 Forwards Rev 17 to PLP-201, Emergency Plan & Fission Product Barrier Analysis.Rev to Emergency Plan Incorporates Comments Received During Recent Licensed Operator Requalification Training in Emergency Plan Procedures ML18009A4151990-03-22022 March 1990 Responds to NRC SALP Rept for Jul 1988 - Nov 1989.Contrary to Statement in Rept Significant Amount of Refresher Training Was Conducted During SALP Assessment Period Including Termination & Splicing & Motor & Bus Relays ML18009A4081990-03-19019 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-400/90-01.Corrective Actions:All Calibr Required by Tech Specs for Power Range Nuclear Instrumentation Satisfactorily Completed ML18022A7891990-03-0909 March 1990 Forwards Vols 1 & 2 of Inservice Insp Summary 1st Interval 1st Period,2nd Refueling Outage Completed 891222. ML18022A7881990-03-0606 March 1990 Confirms Understanding of Status of NRC Activities Re Proposed Wakesouth Regional Airport Located Near Plant Site. Pending Issues Should Be Resolved by 900331 to Enable Util to Complete Negotiations W/Airport Authority ML18022A7851990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-400/89-34.Corrective Actions:Valve SI-332 Closed & Gravity Drain Path Isolated & Shift Foreman Required to Review MMM-012 Re Priority/Emergency Maint Work Control ML18022A7721990-02-26026 February 1990 Forwards Application for Amend to License NPF-63,revising Tech Spec Surveillance 4.0.2 to Permit Surveillances to Be Extended Up to 25% of Specified Interval & Removing 3.25 Limitation from Spec,Per Generic Ltr 89-14 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML18022A7701990-02-14014 February 1990 Notifies of Issuance of Renewal of NPDES Permit for Plant. Permit Encl ML18009A3831990-02-0909 February 1990 Responds to 900112 Ltr Re Violation Noted in Insp Rept 50-400/89-35.Corrective Actions:Valves ICS-775 & ICS-776 Added to Inservice Insp Program for Back Seat & Full Flow Testing & ICS-525 Revised to Satisfy Tech Spec Requirements ML18009A3751990-02-0101 February 1990 Forwards Retyped Tech Spec Pages Re 890630 Application for Amend to License NPF-63 Concerning RCS Pressure Temp Limits ML18009A3701990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 IR 05000400/19890281990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 ML18009A3631990-01-26026 January 1990 Responds to NRC Bulletin 88-008, Thermal Stratification in Piping Connected to Rcs. Design Differences That Either Minimize Potential of Occurrence or Enhance Possibility of Detection Should Scenario Be Created at Plant Determined ML18009A3531990-01-25025 January 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Conducted in Oct 1989.Util Believes That Packing Leaks Discovered Are Isolated Failures & That Repair Should Prevent Recurrence ML18009A3501990-01-22022 January 1990 Forwards Revised Tech Spec Table 3.7-6, Area Temp Monitoring, Per 891218 Tech Spec Amend Request ML18022A7591990-01-17017 January 1990 Submits Results of Aircraft Hazards Study Associated W/ Proposed Wakesouth Regional Airport & Facility ML20005G5731990-01-16016 January 1990 Forwards Response to Insp Rept 50-400/89-32.Encl Withheld (Ref 10CFR73.21) ML18009A3351990-01-0505 January 1990 Forwards Rev 16 to Vol 1,Part 2 of Plant Operating Manual PLP-201, Emergency Plan. Revised NUREG-0654 Comparison W/ Plant Emergency Action Level Flow Path Also Encl for Review ML18009A3171989-12-21021 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-21.Corrective Actions:Incident Reviewed by Both Plant & Nuclear Engineering Dept Personnel to Avoid Future Miscommunication ML18009A3181989-12-15015 December 1989 Forwards Retyped Amend Bar Pages to Tech Spec Table 3.3-3 Re Auxiliary Feedwater Manual Initiation,Per 891026 Application for Amend to License NPF-63 ML18009A3011989-12-15015 December 1989 Forwards Proprietary WCAP-12403 & Nonproprietary WCAP-12404, LOFTTR2 Analysis for Steam Generator Tube Rupture W/Revised Operator Action Times for Shearon Harris Nuclear Power Plant. WCAP-12403 Withheld (Ref 10CFR2.790(b)(4)) ML18022A7371989-12-13013 December 1989 Forwards Change 3 to Rev 2 to State of Nc Emergency Response Plan in Support of Shearon Harris Nuclear Power Plant, Incorporating Administrative Enhancements. W/One Oversize Encl ML18009A2971989-12-0808 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Action:Min of Four Decontamination Personnel Will Be Assigned 24 H Per Day During Fuel/Cask Handling to Maintain Cleanliness in Fuel Handling Bldg ML18009A2841989-11-30030 November 1989 Forwards Rev 0 to Core Operating Limits Rept in Support of Cycle 3 Operations ML18005B1531989-11-27027 November 1989 Forwards Retyped Amend Bar Pages to 890630 Request for Rev to License NPF-63 Re RCS pressure-temp Limits ML18022A7311989-11-27027 November 1989 Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements. ML18005B1511989-11-17017 November 1989 Forwards 15-day Special Rept Identifying Number of Steam Generator Tubes Plugged During Current Inservice Insp Period ML18005B1501989-11-13013 November 1989 Suppls 890403 Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. Addl Nontraceable Molded Case Circuit Breakers (MCCB) & MCCBs Traceable to Refurbishers Noted During Records Review 1990-09-06
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REGUL, INFORMATION DISTRIBUT YSTEM (RIDS)>>ACCESSION NBR 5 8506060496 DOC~DATE t 85/05/31 NOTARIZED!
NO DOCKEiT'FACIL:50 000 Shear on Har ris Nucl ear~Power Pl anti Uni t-ii Car ol ina 05000400 AUTH~NAME>>AUTHOR AFFILIATION
'ZIMMERMANpS,R.
Carolina Power 8 Light Co~RECIP~NAME>>RECIPIENT AFFIL'SATION, DENTON H-,RE Office>>of Nuclear Reactor Regulationr Director n SUBJECT!=Responds to NRC 850325 request for addi, info.re responses to Generic Ltr 83.28'eactor'trip sys components rev{ewed 8 identified as safety related on-component level Q lists DISTRIBUTION CODE!A055D.COPIES RECEIYED:LTR
'NCL'IZE'.TITLE'i OR/Licensing Submittal:
Salem ATHS Events GL-83.28 NOTES!RECIPIENT ID>>CODE/NAME(NRR LB3>>BC 01 INTERNAL: ACRS ELD/HDS1 IE/DQAVT NRR/DE/MEB NRR/DHFS/LQB NRR/DL/GRAB NRR/'L/TAPMG NRR/DSI/ICSB NRR/DS I/RSB RONa>>COPIES LTTR ENCL'3 3 6 6 1 0 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME" ADM/LFMB IE/DI NRR/DE/EQB NRR/DHFS/HFEB NRR/DL DIR NRR/DL/SSPB NRR/DS I/ASB N"/PS B G FIL 00 COPIES LVTR ENCL 0 1 1-1 1=1 1 1 1-EXTERNAL':
24X NRC;PDR, 02 1 1 1 1 LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED'TTR 32'NCL>>30 C~p ()(,, Hsr+61 l l<<I q s)Ff(pffft q I('l I ((1H n~,'i')1<<, l<<s'(l<<~'1~s+'.~1~<<(f~'~<<sPtM'>>2 fft4~P<<($);(1 I~1 1 Pi,1 erg<<,H<<l'H ys<<P s(4s H,-I<<f I'I'ln<<;a4 I 1<<H(kj+<<fl sn se earn w (I<<P Pff I IIP((I)~ff'c.'f tl('fr 451'f.,t]f 1,~rp~g 1 ll'(p pli o<<lr Is HTf 1 P,J H ('"I I ,r7I I<<H g
I CNK Carolina Power 8 Light Company MAY 31$85 SERIAL: NLS-85-186 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.1-DOCKET NO.50-000 GENERIC LETTER 83-28 REQUEST FOR ADDITIONAL INFORMATION RESPONSES
REFERENCE:
March 25, 1985 letter from George W.Knighton (NRC)to Mr.E.E.Utley (CPdcL)
Dear Mr.Denton:
Carolina Power R Light Company (CPttrL)encloses for your review our responses to the request for additional information supplied by the NRC Staff via the referenced letter.Carolina Power R Light Company considers this information sufficient to resolve this issue.If you have any questions, please contact Mr.Gregg A.Sinders at (919)836-8168.Yours very truly, SRZ/GAS/mf (1531GAS)Enclosure S.mmerman Manager Nuclear Licensing Section Cct Mr.B.C.Buckley (NRC)Mr.G.F.Maxwell (NRC-SHNPP)
Dr.3.Nelson Grace (NRC-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP)
Mr.D.Lasher (NRC-RRAB)
Wake County Public Library Mr.Wells Eddleman Mr.3ohn D.Runkle Dr.Richard D.Wilson Mr.G.O.Bright (ASLB)Dr.3.H.Carpenter (ASLB)Mr.3.L.Kelley (ASLB)8506060496 85053i PDR ADDCK 05000400 A PDR+411 Fayettevilte Street 0 P.O.Box 1551 o Raleigh, N.C, 27602
~0 i".'P$E 6 PA<:l"j Question Item 2.1(part 1)-Incomplete Supply a statement confirming that reactor trip system components were reviewed and that they are identified as safety-related on documents, procedures, and information handling systems.Response The reactor trip system components were reviewed and they are identified as safety-related on the component level Q-list.This Q-list is used as input for plant documents, procedures and information handling systems.A copy of the reactor protection system and rod control system portions of the Q-list is provided for your information (Attachment 1).The reactor trip and bypass breakers are included on the rod control system portion of the Q-list and are shown as Q-Class"A", or safety-related.
Q-Class"E" components are non-safety related."For further information on preparation and control of component level classification, refer to the response to Item 2.2.1.(1531GAS/Alf
)
1 5 6 7 8 9 10 ll l2 13 l4 I5 16 17 I8 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 5:l 54 55 56 57 58 59$0 CPL&L CP RUN DATE~05/14/85 RUG T IMF.13.24.52 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO 17C5 HARGETT PLANT 03 UNIT SYSTEM SYSTEM NAME EQUIPh'IENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION 1080 REACTOR PROTECTION SYSTEM+DFG SOLID STATE PROTECTION CABINET A TRAIN A 8 TRAIN 8 I A A SAFEGUARDS TEST CABINET TRAIN A TRAIN 8 AUX ILL IARY RELAY RACKS DFH A 8 DFL AUX RELAY RACKS AUX RELAY RACKS AUX RELAY RACKS TRIP STATUS LIGHT BOX STEAM GENERATORS STEAM GENERATORS
&TURBINE REACTOR COOLANT SYSTEM NIS&CONTAINMENT PRESSURE SWITCH.CONTROL MODULE ELECTROSWITCH TYPE STEAMLINE ISOLATION II STEAMLINE ISOLATION I STEAMLINE ISO.RESET TRAIN A STEAMLINE ISO.RESET TRAIN 8 STEAMLINE S.I.BLOCK RESET A STEAMLINE S.I.BLOCK RESET 8 PRZR PRES.S.I.BLOCK RESET TR-A PRZR PRES.S.I.BLOCK RESET TR-8 S.I.RESET TRAIN A MCB S.I.RESET TRAIN A ACP S.I.RESET TRAIN 8 MCB S.I.RESET TRAIN 8 ACP F.W.ISO.BYPASS VALVES RESET A F.W.ISO.BYPASS VALVES RESET 8 N33A SOURCE RANGE BLOCK RESET N338 SOURCE RANGE BLOCK RESFT N38A INTERMEDIATE RANGE BLOCK N388 INTERMEDIATE RANGE BLOCK N47A POWER RANGE BLOCK N478 POWER RANGE BLOCK SWITCH//1 REACTOR TRIP/CLOSE SWITCH//I S.I.ACTUATION SWITCH//2 REACTOR TRIP SWITCH//2 S.I.ACTUATION REAKER, 120VAC INSTRUMENTATION CIRCUIT SAFEGUARDS TEST CAB.A 2 3 DFM OFN CS-SLIISAB Cs-SLISAB Cs-SLSLRA CS-SLSLRB CS-1008SA Cs-100858.Cs-141SA CS-14158 CS-455.1SA CS-455.2SA CS-455.3SB CS-455.458 CS-810SA CS" 810SB CS-88SA Cs-88SB CS-89.ISA CS-89.158 CS-89.2SA Cs"89.2SB CS-92.1SAB CS-92.2SAB CS-94.1SAB CS-94.2SAB DLX 8 1A-51"3-A A n A A h n A A TAG NUMBFR PAGE 293 REP E888-01 FOAM 0I13 I02/83)1583
CPLSL CO Ri/N DATE 05/i4/85 RUN TIME 13.24.52 h EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO 17CS HARGETT PLANT 03 PAGE 294 REP EB88-01 UNIT SYSTEM SYSTFM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 10 11 12 13 14 15 1G 17 18 19 20 A A h A h A h 1080 REACTOR OLX 1A-51-7 1A-S 1"8 1A-53"7 1A-53-8 18-52-7 16-52-8 18-54-3 1B-S4-7 18-54-8 OMA PROTECTION SYSTEMh BREAKER,120VAC INSTRUMENTATION CIRCUIT RPS CHAIN I TRAIN A RPS CHAIN I TRAIN B RPS CHAIN III TRA1N A RPS CHAIN III TRAIN B RPS CHAIN II TRAIN h RPS CHAIN I I TRAIN B SAFEGUARDS TEST CAR.R RPS CHAIN IV TRAIN A RPS CHAIN IV TRAIN 8 SWITCH, CONTROL MODULE ELECTROSWITCH TYPE 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 38 37 38 39 40 41 47 43 45 4G 47 48 49 50 5>52 53 54 55 50 57 58 59 80 cs-458.isn CS-458.258 FhiZ 10212-16 102 12-18 1E212-21 1E212-23 1E212-25 FKA 18-2 IZP UPP-1-17 RWST S.I.RESET TRAIN A RWST S.I.RESET TRAIN 8 BREAKER,120V POWER PANEL AUX REALY RACK//2 nux RELAY RhcK//i TSLB-4 8 BPLB TSLB-3 TSLB-182 BREAKER, 120V UNINTERRUPT PANEL AUX RELAY RACK//1 120 VAC FUSED SWITCH FUSED SWITCH I Al>th Ilh h'I<Ilhlflhl 1584 J~
CPL&L CO RUN DATE 05/23/85 RUN TIME 17.34.53 A uc 6 cw EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7CS G.SINDERS PLANT 03 iQ PAGE 2 REP EB88-01 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION 1065 , OD C NTROL Y TEM CQY BREAKER, 480V AUX.BUS 1D2-6D MG SET MOTOR 1A 1E2-2A MG SET MOTOR 18 DFV BREAKER, DC DISTRIBUTION PANEL DP-1A-SA-18 GENERATOR OUTPUT 1A DP-1A-1-18 SERVES ROD DRIVE PWR SUPPLY CUB 1 DP-1A-2-18 SERVES ROD DRIVE PWR SUPPL CUB 2 OP-18-58-18
.GENERATOR OUTPUT 1B LES INDICATOR, SPEED MCB-1C SI-408 INDICATOR, SPEED MCB-1C LEU SWITCH, MOTOR DISCONNECT 102-6D SWITCH, MOTOR DISCONNECT 1E2-2A SWITCH, MOTOR DISCONNECT LEV REGULATOR, VOLTAGE 1A ROD DRIVE VOWER SUPPLY CUB 1B ROD DRIVE POWER SUPPLY CUB 2 LEW SHUNTS, AM&REV.CURR RELAY, 1200A, SMV 1AA SHUNTS, AM&REV.CURR RELAY, 1200A, SMV 1AB SHUNTS, AM&REV.CURR RELAY, 1200A, SMV TAG NUMBER 29 30 31 32 1AC 1BA 188 1BC SHUNTS, AM&REV.CURR RELAY;1200A, 5MV SHUNTS, AM&REV.CURR RELAY, 1200A, SMV SHUNTS, AM.&REV..CURR RELAY, 1200A, SMV SHUNTS, AM&REV.CURR RELAY, 1200A, 5MV 33 34 35 36 37 38 39 40 LEX SWITCH, OVER-TEMP ALARM OTS-1 ROD DRIVE POWER SUPPLY CUB OTS-2 ROD DRIVE POWER SUPPLY CUB 2 LEY SWITCH.REV CURR ALARM 1A ROD DRIVE POWER SUPPLY CUB 1'1B ROD DRIVE POWER SUPPLY CUB 2 LEZ SWITCH.OVER-VOLT ALARM, ROD DRIVE 1A ROD DRIVE POWER SUPPLY CUB 41 42 43 44 E E'B LFA 1A 1B ROD DRIVE POWER SUPPLY CUB 2 SWITCH, MTR BKR TRIP ALARM'OD DRIVE POWER SUPPLY CUB 1 ROD DRIVE POWER SUPPLY CUB 2 45 46 47 48 LFC SWITCH, ROD LIFT DISCONNECT CBA-1 CONTROL BANK A MECH CBA-2 CONTROL BANK A MECH 2 CBA-3 CONTROL BANK A MECH 3 49 50 51 52 53 54 55 se 57 58 59 60 E E E CBA-4 CBA-S CBA"6 CONTROL BANK A MECH 4 CONTROL BANK A MECH 5 CONTROL BANK A MECH 6 FORM 0113<02I83)15
'4~
1 CPL&L CO 2 RUN DATE 05/23/85 3 RUN TIME 17.34.53 4 DELIVER TO EQUIPMENT DATA BASE SYSTEM QUALITY LIST CPB 7C5 G.SINDERS PLANT 03 PAGE 3 REP EB88-01.UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 10 11 12 E E 1065 ROD CONTROL SYSTEM LFC SWITCH, ROD LIFT DISCONNECT CBA-7 CONTROL BANK A MECH 7 CBA.-B CONTROL BANK A MECH 8 13 14 15 16 17 18 19 20 21 22 23 24 25 28 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 CBB-1 CBB-2 CBB-3 CBB-4 CB8-5 CBB-6 CBB"7 C88-8 CBC-1 CBC-2 CBC-3 CBC-4 CBC-5 CBC-6 CBC-7 CBC-B CBD-1 CBD-2 CBD-5 CBD-6 SBA-1 SBA-2 SBA-3 SBA-4 SBA-6 SBA-7 SBA-8 SBA-9 SBB-1 S88-2 SBB-3 588-4 SB8-6 SBB"7 SBB-B SBB-9 SBC-1 SBC-2 SBC-3 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK D CONTROL BANK D CONTROL BANK D CONTROL BANK D SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK C SHUTDOWN BANK C SHUTDOWN BANK C MECH 1 5'IECH 2 MECH 3 MECH 4 MECH 5 MECH 6 MECH 7 MECH 8 MECH MECH 2 MECH 3 I'IECH 4 MECH 5 MECH 6 MECH 7 MECH 8 MECH 1 MECH 2 MECH 5 MECH 6 MECH 1 MECH 2 MECH 3 MECH 4 MECH 6 MECH 7 MECH 8 MECH 9 MECH 1 MECH 2 MECH 3 MECH 4 MECH 6 MECH 7 MECH 8 MECH 9 MECH 1 MECH 2 MECH 3 FOAM 0113 (02I831 7i
~I CPL&L CO RUN DATE 05/23/85 RUN TIME 17.34.53 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7CS G.5 INOERS PLANT 03 PAGE 4 RFP EB88-01 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 5'I'~52 53 54 55 56 57 58 59 60 1065 ROD CONTROL SYSTEM~LFC SWITCH, ROD LIFT DISCONNECT E SBC-4 SHUTDOWN BANK C MECH 4 E SBD-1 SHUTDOWN BANK D MECH 1 E SBO-2 SHUTDOWN BANK D MECH 2 E SBD-3 SHUTDOWN BANK D MECH 3 E SBD-4 SHUTDOWN BANK D MECH 4 LFD FUSE CHASE SHAWMUT AMP-TRAP, FUSE&VOLT E 1 FUSE, CHASE SHAWMUT AMP-TRAP, FUSE&VOLT E 2 FUSE, CHASE SHAWMUT AMP-TRAP, FUSE&VOLT LFH PUSHBUTTON, TRIP TEST E 1D2-6D PUSHBUTTON, TRIP TEST E.1 E2-2A PUSHBUTTON, TRIP TEST LFI PUSHBUTTON, CLOSE TEST E 1D2-6D PUSHBUTTON, CLOSE TEST E 1E2" 2A PUSHBUTTON, CLOSE TEST LFL INDICATOR, TEMPERATURE, MCB E T I-408A INDICATOR, TEMPERATURE, MCB LFM SWITCH, TEMPERATURE, MCB E TS-409 SWITCH.TEMPERATURE, MCB LFN RECORDER, TEMPERATURE, MCB E TR-408 RECORDER, TEMPERATURE, MCB LFO RECORDER, POSITION E ZR-409 RECORDER, POSITION LFP BREAKER W STARTER, 480V MCC E 1E11-6F BREAKER WITH STARTERS 480V MCC LFR PUSHBUTTON E 499-DOWN PUSHBUTTN, DOWN LCL CNTRL ST.499 E 499-UP PUSHBUTTON, UP LCL CNTRL ST.499 LFS SWITCH, CONTROL E 1"LS1 swrTCH, HorsT Upr ER LrMrT E 1-LS2 SWITCH.HOIST LOWER LIMIT E 1-LS3 SWITCH, GRIPPER ASSEMBLY RELEASE SOLENOI LFV MOTOR, ROD DRIVE M-G SET E 1A MOTOR, ROD DRIVE M-G SET E 18 MOTOR, ROD DRIVE M-G SET LFW RELAY E JS/408 ROD CONTROL LFX ROD SPEED CARD E SK-408 ROD CONTROL LFY SIGNAL CONDITIONER E JY-408C ROD CONTROL E JY-408D ROD CONTROL FORM 0113 (02/83)17 I'
1 2 3 4 5 6 7 8 9 10'11 12 13'14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 58 57 58 59 60 CPLSL CO RUN DATE 05/23/8P%UN TIME 17.34.53 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7C5 G.SINDERS PLANT 03 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION 0-CLS SPECIFIC ID SPECIFIC DESCRIPTION 1065 ROD CONTROL SYSTEM LFY SIGNAL CONDITIONER JY-408E ROD CONTROL JY"408J ROD CONTROL TAG NUMBER JY-408K JYr408M JY/408KP1 PY-446 QY-479 SY-4080 TD/4088 TY-4088 TY-408C TY-408F TY-408G TY-408H." TY 408HP1 NI G BYA BYB RTA RTB NIH BYA BYB RTA RTB 025 BYA BYA BYB BYB RTA RTA RTB RTB ROD CONTROL ROD CONTROL ROD CONTROL ROD CONTROL ROD CONTROL ROO CONTROL ROD CONTROL ROD CONTROL iROD CONTROL ROD CONTROL ROD CONTROL ROD CONTROL ROD CONTROL TR IP, SHUNT REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR REACTOR SW GEAR TRIP, UNDERVOLTAGE REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR REACTOR SW GEAR BREAKER, REACTOR TRIP REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR BYPASS REACTOR SW GEAR REACTOR SW GEAR REACTOR SW GEAR REACTOR SW GEAR 027 CABINETS, POWER SCD SHUTDOWN BK C GRP 1&BK D GRP 2 1AC SHUTDOWN BANK A GROUP 180 SHUTDOWN BANK 8 GROUP 2AC SHUTDOWN BANK A GROUP 2 28D SHUTDOWN BANK B GROUP 2 029 MECHANISM, FULL LENGTH ROD CONTROL DRIVE PAGE 5 REP E888-01 FORM 0113 (02I83)18 P
1 CPL&L CO 2 RUN DATE 05/23/85 3 RUN TIME 17.34.53 4 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7C5 G.SINDERS PLANT 03 PAGE 6 REP E888-01 UNIT SYSTEM SYSTEM NAME EQUIPMENT CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION TAG NUMBER 9 10 11 12 1 E E 1065 ROD CONTROL SYSTEM 029 MECHANISM, FULL LENGTH ROD CONTROL DRIVE CBA-1 (F-2)CONTROL BANK A CBA-2 8-10 CONTROL BANK A 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 CBA-3 CBA-4 CBA-5 CBA-6 CBA-7 CBA-B CBB-1 CBB-2 CBB"3 CBB-4 C88-5 CBB-6 C88-7 CBB-B CBC-1 CBC-2 CBC-3 CBC-4 CBC-5 CBC-6 CBC-7 CBC-B CBD-1 CBD-2 CBD-5 CBD-6 SBA-1 SBA-2 SBA-3 SBA-4 SBA-6 SBA-7 SBA-8 SBA-9 SB8-1 588-2 588-3 SB8-4 S88-6 (K-14)(P-6)(K-2)8-6 (F-14)(r-10)(F-4)(D-10)K-12 (M-6)(K-4)(D-e)F-12 (M-10)(D-4)(D-12)M-12 (M-4)(H-e)(F-8)H-10 (K-8)(H-2)(H-14)8-8 (P-8)(6-3)(C-9 d-13 (N-7)(d-3)C-7 G-13 (N-9)(E-5)(E-11)L-11 (L"5)(6-7)CONTROL BANK A CONTROL BANK A CONTROL BANK A CONTROL BANK A CONTROL BANK A CONTROL BANK A CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROl BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK 8 CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK C CONTROL BANK D CONTROL BANK D CONTROL BANK D CONTROL BANK D SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK A SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 SHUTDOWN BANK 8 FORM 0113 102183)
I CPLSL CO 2 RUN DATE 05/23/85 3 RUN TIME 17.34.53 4 EQUIPMENT DATA BASE SYSTEM QUALITY LIST DELIVER TO CPB 7C5 G.5INDERS PLANT 03 PAGE 7 REP EB88-01 9 10 11 12 UNIT SYSTEM SYSTEM NAME EQUIPMENT.CODE EQUIPMENT DESCRIPTION Q-CLS SPECIFIC ID SPECIFIC DESCRIPTION 1 1065 ROD CONTROL SYSTEM 029 MECHANISM, FULL LENGTH ROD CONTROL DRIVE E SBB-7 (G-9)SHUTDOWN BANK B E SBB-8 8-9 SHUTDOWN BANK B TAG NUMBER 13 14 15 16\7 I8 19 20 SBB"9 (U-7)SBC"1 (E-3)SBC-2 (C-11)SBC-3 L-13 SBC-4 (N-5 SBD-1 (F-6)SBD-2 (F-10)SBD-3 K-10)SHUTDOWN BANK 8 SHUTDOWN BANK C SHUTDOWN BANK C SHUTDOWN BANK C SHUTDOWN BANK C SHUTDOWN BANK 0 SHUTDOWN BANK 0 SHUTDOWN BANK D 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43.44 45 46 47 48 49 50 51 52 53 54 55 56 E SBO-4 K-6 SHUTDOWN BANK 0 032 SETS, ROD DRIVE M.G.E 1A MOTOR GENERATOR SET 1A (SOUTH)E 1B MOTOR GENERATOR SET 1B (NORTH)57 58 59 60 END OF REPORT EB88-01 FORM 0113 (02I83)20 h t Question Item 2.l (part 2)-Incomplete Submit detailed information describing your vendor interface program for reactor trip system components.
Information supplies should state how the program assures that vendor technical information is kept complete, current and controlled throughout the life of the plant and should also indicate how the program will be implemented at Shearon Harris, Unit l.Rce~onse The Shearon Harris Nuclear Power Plant (SHNPP)reactor trip system is supplied by Westinghouse (NSSS vendor).CPRL has verified that Westinghouse Technical Bulletins applicable to Generic Letter 83-28 have been received.The recommendation of the Westinghouse Technical Bulletins on reactor trip breakers have been reviewed by CPdcL and acted upon.Westinghouse has incorporated return receipt letters into their Technical Bulletins.
These return receipt letters are followed up by Westinghouse if the receipt is not returned within a reasonable time.Westinghouse is also providing an updated list of Technical Bulletins which CPRL will use as an additional tool in ensuring that applicable Technical Bulletins have been received.Westinghouse has issued a complete list of past recommendations on NSSS equipment.
The index of recommendations is also updated periodically to ensure the plant is aware of issued recommendations.
Once the Technical Bulletins are received, the vendor recommendations are processed in accordance with our procedures dealing with Operational Experience Feedback.Vendor recommendations concerning plant equipment are tracked by the Onsite Nuclear Safety Unit in accordance with the above Operating Experience Feedback Program procedures..
This program ensures that the information is provided to Operations or Maintenance or other appropriate organizations for their use.The recommendations are tracked until final disposition occurs.SHNPP has implemented procedures for initial review and revisions to the Technical Manual.Once the Technical Manual has been accepted for use by the Technical Support Unit, Document Control distributes the vendor manuals per Document Control Instruction.
7 At SHNPP, no distinction is made for on-site processing of vendor information for the reactor trip system components and other safety-related equipment.
The current established controls provide for processing of vendor information with the same methodology established for Technical Manuals and Bulletins received.In summary, CPRL believes the current vendor interface program for the reactor trip system components in conjunction with established plant procedures for maintenance, surveillance testing, equipment repair and replacement, and quality assurance program provide a comprehensive equipment reliability program throughout the life of the plant.(1531GAS/Nf
)
OO Question Item 2.2.1-Incomplete Submit information on how equipment will be classified as safety-related and will be designated as such on plant documentation as requested in sub-items 2.2.l.l to 2.2.1.6.Reeonse An established procedure exists at SHNPP for the preparation and control of a component level classification.
By procedure, the quality classification of components for quality purposes is obtained by applying the quality designation inherent in existing controlled design documents such as flow diagrams, controlled wiring diagrams, etc.Safety-related components are classified as Q-Class"A" with non-safety/seismic, radwaste, fire protection, and non-safety classified as"B","C","D", and"E", respectively.
A component may meet more than one quality classification criteria;but in all cases, the highest quality class is the resultant quality classif ication.(1531GAS/mf
)
0 l y~4 Question Item 2.2.2-Incomplete Submit detailed information describing your vendor interface program for all safety-related components.
Information supplied should state how the program assures that vendor technical information is kept complete, current, and controlled throughout the life of the plant and should also indicate how the program will be implemented at Shearon Harris, Unit I.If the recommendations of NUTAC are to be implemented at Shearon Harris, Unit l, you need to supplement your response to address to concern about establishing and maintaining an interface with all vendors of safety-related equipment since the staff found NUTAC lacking in this respect.Reeonse A unique aspect about SHNPP construction is the program of using permanent plant staff to order the initial loading of spare parts instead of depending on parts received only with initial equipment purchase.To support this program, a parallel effort is in process to systematically review all vendor technical manuals, starting with safety related vendors first.In this process, each vendor is contacted to verify the information is current, and maintenance personnel perform a review for adequacy of content.Once these technical reviews are completed, the manuals are accepted by Technical Support and sent to Document Control for distribution.
As a result of these programs, SHNPP will be assured of having the latest technical manuals for safety-related equipment at time of fuel load.With regard to continued maintenance of technical manuals, SHNPP intends to retain the function of technical manual upgrade in concert with our Operational Experience Feedback program, consistent with the NUTAC recommendations.
CP&L has reviewed the NUTAC Vendor Equipment Technical Information Program (YETIP)and believes that the NUTAC effort provides effective guidelines in establishing a vendor interface program.The VETIP as defined in the March 1980 NUTAC document is considered a valid response to Section 2.2.2 of the NRC Generic Letter 83-28.CPRL is in the process of implementing a program to meet the intent and guidelines of the NUTAC/VETIP.
(1531GAS/mf
)
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Question Item 3.1.3-Incomplete Results of review of test and maintenance programs shall identify any post-maintenance testing that may degrade rather than enhance safety and shall describe actions to be taken including submitting needed Technical Specification changes.Item 3.2.3-Incomplete Same at Item 3.1.3.Response CPdcL submitted the"pen and ink" version of the SHNPP Technical Specifications to the NRC on April 23, 1985.These Technical Specifications will undergo a detailed review by CPRL to assess the implementation of the required surveillances.
This review will determine if the surveillances proposed by the SHNFP Technical Specifications (which are based upon NUREG-0052, Rev.5, Westinghouse Standard Technical Specifications) can be implemented.
Implicit in this assessment is that: (1)the surveillance does not damage the component, and (2)the applicable surveillance test(s)is/are required prior to declaring a component OPERABLE following maintenance which removes the component from service.The results of this review will be provided to the NRC as changes to the Technical Specifications during the review process for the SHNPP Technical Specifications.
However, a specific submittal on the 3.1.3 and 3.2.3 items will not be made.The Westinghouse Maintenance Manual for DS-016 reactor trip breakers has been received and reviewed.The appropriate maintenance procedures that implement the recommended maintenance action have been drafted.(1531GAS/mf
)
~0 P Question Item 0.5.2-Incomplete Provide a description of the design provisions that will permit on-line testing of the reactor trip system.Response Refer to FSAR Section 7.2.2.2.3.10 (Revision 17)for a description of the design provisions that will permit on-line testing.(1551GAS/mf) 0 4~t*r%
Question Item 0.5.3-Incomplete Provide results of review of existing or proposed intervals for on-line testing considering the concerns of 0.5.3.1 to 0.5.3.5 in the generic letter.Proposed Technical Specification changes resulting from this review shall be submitted for review.Response CPRL's November 7, 1983 submittal on Generic Letter 83-28 responded to this item.CPRL referenced WCAP-10271"Evaluation of Surveillance Frequencies and Out of Service Times for Reactor Protection Instrumentation Systems" for reduced surveillance intervals for on-line testing of Reactor Protection System Channels.This WCAP was approved by the NRC on February 21, 1985.CPRL's April 23, 1985 Technical Specification submittal incorporates the reduced surveillance intervals within the limitations of the NRC's SER.(1531GAS/mf
)
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