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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
[Table view] |
Text
ACCEIZRLTED DI&iIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)
ACCESSION NBR:8804210144 DOC.DATE: 88/04/12 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION LOFLIN,L.'I. Carolina Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Submits addi info to suppl 880111 ltr re plant-specific ATWS mitigating sys acutuation circuitry.
DISTRIBUTXON CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:Application for permit renewal filed. o5ooo4oo S
RECIPIENT COPIES RECXPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 0 PD2-1 PD 5 5 BUCKLEY,B 1 1' A INTERNAL: ACRS 6 ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 1 1 1 1
~RR+1B~~~B 12 1 1 OGC 15-B-18 1 0 1 1 RES/DE/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1
'A TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 24
ggQ1, Carolina Power & Light Company APR 2 2 f988 SERIAL: NLS-88-084 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEHENTAL PLANT-SPECIFIC AHSAC SUBMITTAL
REFERENCE:
CP&L letter to NRC dated January 11, 1988 NLS-87-258 Gentlemen:
Carolina Power & Light hereby submits additional information to supplement the reference letter dealing with the Shearon Harris Nuclear Power Plant (SHNPP) plant-specific AMSAC. This information is required by 10CFR50.62 and delineated in the staff's SER on WCAP 10858. This supplemental information includes: system test frequencies; a simplified logic diagram; and the SER Appendix A information for the output isolation relays. These items are provided in the attachment to this letter.
At that time of the January submittal, the SHNPP AMSAC design was not yet finalized. As a result, some of the testing methodology described in the reference submittal has changed due to subsequent evolutions and refinements of the system design. To aid in your review, CP&L has provided in Section 12 of the attachment a comprehensive, revised discussion of the system's testing capabilities which supercedes Section 12 of the previous submittal.
Carolina Power & Light has proceeded with design and procurement of nonsafety related AHSAC equipment in accordance with Section 19 of the Corporate Quality Assurance Program (Radwaste Q). The activities to date have been primarily performed at the Corporate General Office.
During preparation of the plant modification package that control of quality assurance for site activities related to AMSAC it was determined would be more appropriately implemented via existing site procedures for nonsafety related equipment. Accordingly, CP&L's response regarding nonsafety related equipment in Section 4.0, Quality Assurance, has been revised 'and is included in the attachment. This does not represent a reduction in CP&L's implelnentation of the guidance presented in Generic Letter 85-06, only a change in how CP&L is implementing that guidance.
It remains CP&L's intent to maintain the schedule of installing AHSAC during the first refueling outage (i.e.,July 1988) if final NRC 8804210144 880412 PDR ADOCK 05000400 P DCD 411 Fayettevilte Street > P. 0. Box 1551 o Raleigh. N. C. 27602
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Document Control Desk NLS-88-084 / Page 2 acceptance of the SHNPP AMSAC package is received by June 1,1988.
Approval of the SHNPP AMSAC modification is required by June 1,1988 to provide sufficient time to finalize modification packages to be implemented during the first RFO. If final NRC approval of the SHNPP AMSAC package cannot be provided by June 1,1988 CP&L again requests NRC concurrence with delaying the implementation of AMSAC at SHNPP until the second RFO.
Given the schedule restrictions necessary to ensure that the system can be installed during the first RFO, CP&L requests that the NRC review the SHNPP plant-specific application and provide preliminary feedback by April 29, 1988 to minimize any potential impact upon the implementation schedule.
Please refer any questions regarding this submittal to Mr. Steven Chaplin at (919) 836-6623.
Yours very truly, Leonard I'oflin Manager Nuclear Licensing Section LIL/SDC Enclosure cc: Mr. B. C. Buckley W/A Dr. J. Nelson Grace W/A Mr. G. F. Maxwell W/A
Attachment to NLS-88-080
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SHNPP RESPONSE TO PLANT-SPECIFIC REQUIREMENTS OF ATWS/AMSAC SAFETY EVALUATIONREPORT ADDENDUM (540 l SDC/ess )
t t Attachment to NLS-88-080 Page 1 of 12 SUPPLEMENTAL RESPONSE TO PLANT-SPECIFIC REQUIREMENTS OF ATWS SAFETY EVALUATIONREPORT GENERAL The CPRL AMSAC system utilizes the capabilities of a pair of redundant microprocessors in a moderately sophisticated scheme in order to enhance system operability and reliability. As a result, the system does not lend itself to the type of simplified logic diagrams typically depicted in the AMSAC WCAPs. However, in order to facilitate the staff's review, a simplified Functional Diagram (Figure 1) has been attached to provide an overall view of the AMSAC system from its interface with the existing plant input signal to its interface with the output actuation circuitry. To maintain the simplicity of the diagram, the more relevant functions of the microprocessors have been depicted as subprograms, the outputs of which feed the overall program logic. The detailed operations of these subprograms have been provided on separate figures (Figures 2 and 3). Although all of the functions and capabilities of the system are not depicted by the diagram, CPRL believes that the attached figures provide the level of detail required for the NRC to perform its review. The information concerning testing capabilities (Section 12) provides a discussion of the system capabilities which will help explain the Functional Diagram.
PLANT-SPECIFIC INFORMATIONSPECIFIED BY SER 0.0 QUALITYASSURANCE The plant-specific submittal should provide information regarding compliance with Generic Letter 85-06, "Quality. Assurance Guidance for ATWS Equipment that is not Safety Related."
RESPONSE
A. Nonsafet Related QA guidance for nonsafety-related AMSAC equipment has been provided by the NRC through Generic Letter 85-06. Carolina Power R Light Company has reviewed the Generic Letter and has determined that the requirements for radioactive waste management systems provided in Section 19 of the CPRL Corporate Quality Assurance Program (CQAP) meet or exceed the guidance provided in Generic Letter 85-06 with the exception of Sections IX and XVIII. Therefore, CPRL's corporate design and procurement activities for nonsafety-related AMSAC equipment will be controlled in accordance with Section 19 of the CQAP.
Carolina Power R Light Company's plant site activities will be controlled by plant procedural requirements for nonsafety-related equipment. These site procedures meet or exceed the guidance for quality assurance pr ovided in Generic Letter 85-06 with the exception of Section XVIII.
In order to ensure that the guidance concerning Audits (Section XVIII)is met, plant modifications that involve AMSAC will be included in the population of modifications from which QA audit samples are selected. This measure will be taken in addition to the normal reviews by line management provided for in procedures for engineering plant modifications.
(5401SOC/I ah )
Attachment to NLS-33-030 Page 2 of 12 Existing engineering and plant modification control procedures provide for controls over Special Processes (Section IX).
Record keeping for design control and modification of existing plant systems will comply with the requirements of 10CFR50.59.
9.0 ELECTRICAL INDEPENDENCE FROM EXISTING REACTOR PROTECTION SYSTEM The plant-specific submittal should show that electrical independence is achieved.
This is r'equired from the sensor output to the final actuation device at which point nonsafety-related circuits must be isolated from safety-related circuits by qualified Class 1E isolators. Use of existing isolators is acceptable. However, each plant-specific submittal should provide an analysis and tests which demonstrate that the existing isolator will function under the maximum worst-case fault conditions. The required method for qualifying either the existing or diverse isolators is presented in Appendix A.
RESPONSE
Isolation relays will be used for the nonsafety to safety-related interface on AMSAC outputs. Nonsafety AMSAC outputs will energize the coils of the isolation relays with the relay contacts initiating ATWS mitigation in safety-related circuits. Safety and nonsafety relay panel wiring will be physically separated.
Carolina Power dc Light will use the Struthers and Dunn Model 219XBX230 relay for output isolation. These relays are existing spares which are seismically and environmentally qualified Class IE devices installed in Class 1E isolation cabinets at SHNPP. It is CPRL's understanding that this relay module had been accepted by the NRC for this application at other facilities and that selection of this module would resolve the NRC concerns that a qualified isolation device would be used. It is not used in the reactor protection system, thereby ensuring the required diversity for protection against common mode failures in both AMSAC and RPS. To the extent applicable, the Appendix A information for this unit is provided below to show'that this unit is used in a configuration enveloped by its testing.
Specific responses to the Appendix A information requests are provided below for the signal output isolation devices. The Appendix A information requests are restated followed by the response pertaining to these output isolation devices.
RESPONSE TO APPENDIX A: OUTPUT ISOLATION DEVICES Information Re uest A For the type of device used to accomplish electrical isolation, describe the specific testing performed to demonstrate that the device is acceptable for its application(s). This description should include elementary diagrams when necessary to indicate the test configuration and how the maximum credible faults were applied to the devices.
(540ISDC/lych )
Attachment to NLS-88-084 Page 3 of 12
~Res onse New and thermally aged,Struthers-Dunn test relays were subjected to a hypot test between the coil and contacts of 0000 VRMS for one minute. A hypot test between coil and frame of 0000 VRMS for one minute was also conducted. The results of this testing concluded the relays performed their required isolation function and withstood the specification for the 0000 VRMS isolation test.
Information Re uest B Data to verify that the maximum credible faults applied during the test were the maximum voltage/current to which the device could be exposed, and define how the maximum voltage/current was determined.
~Res onse The power supplies used for the Struthers-Dunn isolation relays will be nominal 120 VAC. In view of the 0000 VRMS isolation design (0000 VRMS Test), the isolation relays are adequate for this application.
Information Re uest C Data to verify that the maximum credible fault was applied to the output of the device in the transverse mode (between signal and return) and other faults were considered (i.e., open and short circuits).
~Res onse While this request seems to be for an electronic signal isolator, a 0000 VRMS isolation test between relay coil, contacts, and frame should satisfy any transverse concerns for a relay.
Information Re uest D Define the pass/fail acceptance criteria for each type of device.
~Res onse Isolation relays type tested for SHNPP must withstand 0000 VRMS hypot testing for one minute without a loss of electrical isolation.
Information Re uest E Provide a commitment that the isolation devices comply with the environmental qualifications (IOCFR50.09) and with the seismic qualifications which were the basis for plant licensing.
~Res onse The Struthers-Dunn isolation relays will be installed in a mild environment. The relays were thermally aged and seismically tested to meet the environmental and seismic qualification for the plant licensing basis at SHNPP.
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Attachment to NLS-88-080 Page 0 of 12 Information Re uest F Provide a description of the measures taken to protect the safety systems from electrical interference (Le., Electrostatic Coupling, EMI, Common Mode, and Cross Talk) that may be generated by the ATWS circuits.
~Res onse The subject Class lE isolation cabinets at SHNPP are dedicated for control circuits and are, therefore, segregated from signal circuitry which may be susceptible to electrical interference.
Information Re uest G Provide information to verify that the Class 1E isolator is powered from a Class 1E source.
~Res onse ATWS output isolation relays will be powered from a battery-backed nonsafety power source supplied in the existing relay isolation cabinets. Loss of power to the output isolation relay would disable the AMSAC output; however, it would not have any effect on isolation of AMSAC from existing safety-related circuitry. The output relays do not require power classification beyond the level of nonsafety battery back-up on the nonsafety side of the isolation equipment.
12.0 TESTABILITYAT POWER Measures are to be established to test, as appropriate, nonsafety-related ATWS equipment prior to installation and periodically. Testing of AMSAC may be performed with AMSAC in bypass. Testing of AMSAC outputs through the final actuation devices will be performed with the plant shut down. The plant-specific submittals should present the test program and state that the output signal is indicated in the Control Room in a manner consistent with plant practices including human factors.
~Res onse Some of the testing methodology described in the 3anuary 11, 1988 submittal have changed as a result of subsequent evolutions and refinements of the system design. To avoid any confusion as to the capabilities of the existing design, the following is a comprehensive, revised discussion of the system's testing capabilities which supersedes the description provided in the previous submittal. The attached AMSAC Functional Diagram will be used to help demonstrate which portions of the system are being tested by each manual test described below.
AMSAC will undergo testing/calibration on a refueling outage basis. It is anticipated that testing/calibration will be performed in three overlapping segments: sensor input loops, the AMSAC processors and output isolation relay, and the final actuation circuitry/device. Regardless of the number of segments, the testing of AMSAC will be conducted pursuant to plant procedures in a manner that provides effective end-to-end testing of the AMSAC capability.
(540lsDc/mss)
~ 'ttachment NLS-88-080 to Page 5 of 12 o INPUT INSTRUMENT LOOP VERIFICATIONAND CALIBRATION The existing steam generator level and turbine pressure input instrumentation loops are presently calibrated once a refueling outage as a part of the existing reactor protection system. The plant procedures governing those calibrations will be modified to test the additional isolator and current-to-voltage conversion in each loop that feeds the AMSAC system.
These procedures will test and calibrate the AMSAC input signals from the sensors through the isolators to the test terminal strips in the AMSAC cabinet.
o PROCESSOR TEST AND CALIBRATION The AMSAC cabinet is equipped with a special test/terminal strip which enables the technician to break the connection from any input signal to either processor by simply opening a knife blade type contact across the input and output lugs of the terminal strip. A simulated input signal can then be injected into either processor by plugging a 0-5 VDC signal generator into the signal injection port on the output lug of the terminal strip. The terminal strip is accessible from the front of the AMSAC cabinet so that the technician can readily view the information displayed on the local panel.
Using this capability to simulate inputs and the various information displayed on the AMSAC panel, a functional test and calibration of the AMSAC processor can be performed. The processor's comparators which identify the "tripped" condition'and perform the "spread checks" for each of the AMSAC signal inputs can be calibrated. The setpoints can be verified or adjusted by observing the input value which activates the corresponding lamps on the cabinet display. By injecting various combinations of signals into each "processor, the program logic can be verified and the capability of each processor to independently trip the final output isolation relay can be verified. During the course of this testing and calibration, proper functioning of the AMSAC panel and Control Room displays can be verified. At the conclusion of the tests, the continuity across the closed knife contacts on the terminal strip will be verified for each input to the processor under test/calibration.
The processor test and calibration will cover the AMSAC circuitry from the input test/terminal strip to its output interface with the existing turbine trip and Auxiliary Feedwater (AFW) actuation circuits, i.e., the output isolation relay. This testing will verify that AMSAC, at the output interface, is capable of initiating the required actuation functions.
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Attachment to NLS-88-080 Page 6 of 12 o FINAL ACTUATIONCIRCUIT TEST The turbine trip and AFW actuation circuits are tested independently of AMSAC by the existing test program on at least a once per refueling basis.
The plant procedures governing these tests will be amended as appropriate to include the additional circuit from AMSAC. The combination of the input instrument loop calibration, the processor testing, and the final actuation circuit testing will provide effective end-to-end testing of the AMSAC capability.
In addition to the manual periodic test/calibration described above, the following sections describe the automatic checks performed by each processor.
CONTINUOUS SELF-DIAGNOSTICS (AUTOMATIC)
Each programmable controller will perform self-diagnostics to ensure proper operation. Immediately upon power-up, it will perform a cyclic redundancy check on the read only memory (EPROM) containing the microprogram which directs the programmable controller operation. The self-diagnostics will test the random access memory (RAM) to ensure it can be written to, and read from, and verify proper operation of the arithmetic and logic functions.
A parity check on the program memory is performed each time an instruction is executed. This involves encoding a specific "parity bit" tracer at predetermined locations in the program data in memory. The controller verifies the authenticity of the command by verifying the existence and location of the parity bit. A watchdog timer will check that each scan is executed normally. These checks will ensure that the hardware functions properly and the software is not corrupted. Processor failures identified will be indicated by activation of the "Trouble Lamp" in the control room and on the local AMSAC panel.
o SENSOR INPUT QUALITYCHECKS (AUTOMATIC)
The AMSAC controller program will perform a "spread check" on AMSAC input signals every scan cycle and light the "AMSAC Trouble" lamp in the Control Room and on the local AMSAC panel if a large difference exists among the signal inputs from the steam generators or the turbine. The plant personnel will then use the AMSAC panels diagnostic features to investigate the nature of the problem. The spread checks test each signal for most failure modes, however, slight instrument drift cannot be detected. Figure 0 shows the controls and displays currently planned for this local AMSAC panel.
The final design is subject to minor changes.
Status lights for the steam generator level and power level inputs to each controller unit will indicate which of the inputs was exhibiting the excessive "spread" which initiated the "AMSAC Trouble" lamp in the Control Room.
Diagnostic capabilities at the AMSAC panel, in conjunction with existing control room instrumentation, will enable plant personnel to establish the probable source of the problem that actuated the trouble light.
(5401SDC/ms s )
Attachment to NLS-88-080 Page 7 of l2 These status lamps will also indicate any inputs which are in a "tripped" status for having exceeded their setpoint values. A separate "variable
.tripped" lamp indication will allow plant personnel to distinguish indication of an input exceeding its setpoint from that of the input exhibiting an excessive spread from the other corresponding inputs.
o PROCESSOR VOTING RELAY TEST (AUTOMATIC)
To enhance reliability and testability, each AMSAC controller unit will drive three relays wired in a configuration shown in the attached Figure 5.
Continuity is required across these contacts in order to supply power to the isolation relays which initiate mitigating actions. One of the relays from each controller unit (labeled A3 and B3) we be normally closed during operation and opened only when the associated controller unit is isolated in a test mode. The other two relays from each unit are redundant modules which are normally open and close only upon an AMSAC actuation signal from the associated controller. This configuration of redundant output relays from independent controller units contributes significantly to the reliability of the system. These relays are automatically tested every IO days by the Output Relay Test Subprogram. Auxiliary circuits enable each processor to open or close its associated relays individually while maintaining a non-tripped configuration. The processor is then capable of testing relay operation by generating a test signal which is passed through the relay contracts. Proper contact position is verified by receipt of the signal at the contact output.
The test signal connections and relay sequencing logic are configured to ensure that each output relay (e.g., Al to A3 and Bl to B3) is unambiguously tested to open and close on the appropriate command.
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Attachment to NLS-88-084 Page 8 of 12 SHNPP AMSAC FUNCTIONAL DIAGRAM LEGEND AMSAC jCABINET 7 I )ER AN) GATE INPUTS SUBPROGRAMS OUTPUT CR OAVE SIGNAL PROCESS I M IA)IICNAT I C/CO)IT I IA)KS)
PROCESSOR A TEST Io SPREAD FAluRE INI')PUT I~
CIECK TERMINAL O ALL PINER I ~S BYPASSED STRIP Q ALL LEVEL BYPASSED I LOCAL Q REFERENCE SIGNAL FAILLE SIGNAL lEST/CALI BRATI Ctl CABINET MAIN CONTROL ISOLATOR SIGNAL ItkECTICN L J DISPLAYS BOARD INPUTS RACKS PO PRCCtKSCA SELF-CtECW S IAUTCMATIC/CONTltA)CUS)
SIGNAL LEVEL I SOLATCR Ll I Q SELF~ FA IUD Ll BYPASS L J SWITCH ITYP ICAL)g LI BYPASS TD PROCESSOR 8" OUTPUT RELAY TEST IAUTONATIC/INTERMITTENT)
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Dl SARM DELAY S/8 C" SIGNAL T I)ER LEVEL LT ISOLA TCR ARMED" LEEE +2 TING It% SIGNAL Pl PRESSum PT ISOLATOR Pl PROCESSCR A TtSml ~ PT SIGNAL I BYPASS ACTUATE CELAY I
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Attachment to NLS-88-084 Page 9 of 12 PROCESSOR UIOER TEST Pi LOI POIER I POIER I BTPASSEO OUTPUT TO P2 LOI Disarm POIER 2 Delay Timer POIER 2 STPASSEO LEGERO:
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>RVERTOR COLIPARATPR AMSAC FUNCTIONAL LOGIC DIAGRAMS AMSAC ARMED LOGIC FIGURE 2
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Attachment to NLS-88-084 Page 11 of 12 LEVEL 1 ~ AMSAC TRIPPED LEVEL 2 Q K (RED) 0 TROUBLE SYSTEM POWER 1 (ORANGE)
RESET POWER 2 SYSTEM BYPASSED TEST 'PP TEST (ORANGE)
DIGITAL TEST DIGITAL READOUT READOUT TIMER TRIGGERED Q Q VARIABLETRIPPED VARIABLE VARIABLE SELECT SELECT AMSAC LOCAL PANEL FIGURE 4
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L Pm)ea Td ZdeWcszE'cruArlou/lsocArIMI RzC AYD Notes: l) All contacts open when de-energized.
- 2) Contacts labeled A are driven by Processor A; those labeled B are driven by Processor B. Either processor is capable of independently generating the AMSAC initiating signal.
- 3) Contacts A3 and B3 are held closed when the AMSAC is running. A3 opens when Processor A is under test; Contact B3 opens when B is under test.
- 0) Contacts numbered l and 2 are from redundant output modules on each controller. Both close upon a signal from the controller to initiate AMSAC mitigating action.
ARRANGEMENT OF SIGNAL OUTPUT RELAYS FIGURE 5