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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
REGULA'lOY INFORMATION DISTRIBUTIOTOTEM (RIDS)
ACCESSION NBR:8509180073 DOC ~ DATE: 85/09/13 NOTARIZED: NO DOCKET" 0 FACIL:50-400 Shearon Harris Nuclear Power Planta Unit ]< Carolina 05000400 AUTH'AME AUTHOR AFFILIATION CUTTERFA,BE Carolina Power 8 Light Co.
RECIP,NAMEt RECIPIENT AFFILIATION BENTON',R, Office. of Nuclear Reactor Regul ationA Director SUBJECT; Forwards- "CRDR Fina) Summary Rept" in response to SSER ]E Open Item ]4<Subpart ].D.]reer rept Suppl 1 to NUREG-0737 8 Reg Guide 1.97.Chronology of util CRDR efforts 8 util*
responses to requirements of SSER ]<Section 18 also encl+
DIS TRI BUT ION CODE: A003D COP IES RECEI VED: L TR ENCl SIZE: l.
TITLE': OR/Licensing Submittal: Suppl 1 to NUREG~0737(Generic Ltr 82"33)
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAMFI LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB3 BC 7 70 INTERNAL: ADM/lFMB 1 IE/DEPER/EPB 3 NRR PAULSONFW 1 NRR/DHFS/HFEB 5 NRR/DHFS/PSRB 2 NRR/DL/ORAB 1 NRR/DL/ORB5 5 NRR/DSI/CPB 1 NRR/DSI/ICSB 1 NRR/DS I/METB 1 AB 1 NRR/DS I/RSB 1 HEG F ]o RGN2 1 EXTERNAL: 24X 1 1o LPDR ]0 NRC PDR ]0 NSIC ]0 i
TOTAL NUMBER OF COPIES REQUIRED: LTTR 36 ENCL Pt
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CKK Carolina Power & LIght Company SEP 1 S f985 SERIAL: NLS-85-325 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT r UNIT NO. 1 DOCKET NO.50-000 RESPONSE TO SER SUPPLEMENT NO. 1, OPEN ITEM NO. 10, SUBPART I.DI CONTROL ROOM DESIGN REVIEW
Dear Mr. Denton:
Carolina Power 4 Light Company (CPRL) hereby submits additional information concerning the Shearon Harris Nuclear Power Plant (SHNPP) Control Room Design Review (CRDR) in response to the SHNPP Safety Evaluation Report (SER),
Supplement No. 1, Open Item No. 10, Subpart I.D.1.
Enclosure I provides a background on CPRL's CRDR ef for ts including a chronology of the licensing correspondence concerning the issue. Enclosure 2 presents each requirement of SER Supplement No. 1, Section 18, with the corresponding CPRL response. Enclosure 3 is the CRDR Final Summary Report, which includes the relevant information on the SHNPP CRDR needed to complete the Staff's review.
With this submittal, CPdcL considers this issue closed. If there are any further questions, please contact Mr. David McCarthy at (919) 362-2010 or (919) 836-7715.
Yours very tru A. B. Cutter - Vice Pre ident Nuclear Engineering ttt: Licensing ABC/DCM/rtj (1908CGL)
Enclosures CC: Mr. B. C. Buckley (NRC) Mr. R. Ramirez (NRC)
Mr. G. F. Maxwell (NRC-SHNPP) Mr. 3ohn D. Runkle Dr. 3. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)
( g0 Mr. Daniel F. Read (CHANGE/ELP) Dr. 3. H. Carpenter (ASLB)
Wake County Public Library Mr. 3. L. Kelley (ASLB)
Mr. Wells Eddleman
[I 0S000400-.
t.. PDR F
ADOCK PDR "'.-'11 Fa yettevilte Street ~ P. O. Box 1551 ~ Raleigh, N. C. 27602
ENCLOSURE 1 to NLS-85-325
~Back round Carolina Power R Light Company (CP&L) conducted a control room human factors design evaluation between April 1980 and 3anuary 1981. By letter dated December 7, 1982, CP&L submitted to the NRC a detailed CRDR Report based on NUREG/CR-1580 criteria. This submittal included evaluations and recommendations concerning the following:
human engineering requirements specifications main control board design annunciator review anthropometrics and workspace systems operation analysis emergency procedures review.
In the 3anuary 1983 Draft SER, the NRC stated that CP&L should submit a report addressing the points of a program plan (in accordance with NUREG-0700 and NUREG-0737, Supplement No. 1) along with a schedule for completing the CRDR and implementing modifications. Furthermore, in a March 25, 1983 meeting, NRC requested CP&L to provide the following:
description of CRDR methods and procedures review staff composition and qualifications resolution of 'Summary Report'ecommendations.
The Company responded to this request by letter dated 3une 1, 1983.
The NRC staff conducted a CRDR audit of the redesigned control room layout and the redesigned main control board on August 15-19, 1983 which resulted in a request for additional documentation (September 9, 1983) to include descriptions of the following:
an analysis performed for developing the control board arrangement (Function/Task Analysis);
an analysis for implementing corrections to Human Engineering Discrepancies (HEDs); and an implementation plan for verifying the Main Control Board design.
CP&L responded to this request by letter dated September 27, 1983. The response also included a description of the development, verification, and validation process for Emergency Operating Procedures.
In the 3anuary 1980 ACRS subcommittee meetings, CP&L discussed the history of the CRDR project, including:
redesign of the control room layout redesign of the main control board emergency operating procedures integration of other NUREG-0737, Supplement No. 1, requirements (1908CGL/r t j)
0 Enclosure 1 NLS-85-325 ERFIS SPDS qualifications of human factors reviewers.
NRC identified areas where the Staff needed additional information to complete its review in its November 1983 SER and 3uly 1980 Supplement No. 1 to the SER.
Furthermore, shortly after issuing SER Supplement No. 1, NRC transmitted requests for additional information (3uly 1983 comments on CPdcL's December 1982 CRDR report, and March 1980 comments on the August 1983 audit). Since these comments were based on much earlier work, CPRL considers the SER Supplement No. 1 requirements as encompassing this transmittal.
CP&L provided preliminary information in response to the SER by letters dated 3anuary I I and April 9, 1985. The April submittal included a Summary Report.
Enclosures 2 and 3 to this submittal complete the response to the SER.
The major documentation concerning the SHNPP CRDR is summarized in the following chronology.
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Cll Enclosure 1 NLS-85-325 CRDR LICENSING CHRONOLOGY 0/80 CP&L begins evaluating CR design.
7/80 NRC issues NUREG/CR-1580.
11/80 NRC issues NUREG-0737 1/28/81 CP&L completes Human Factors Design Evaluation (CRDR) (not formally submitted to NRC until 12/7/82).
9/81 NRC issues NUREG-0700.
12/7/82 CP&L submits "Human Factors Design Evaluation Report for Shearon Harris Vnit 1 Control Room" to NRC based on NUREG/CR-1580 criteria.
t 12/17/82 NRC issues NUREG-0737, Supplement No. l.
1/83 NRC issues DSER - requires CP&L to follow NVREG-0700 criteria for CRDR.
3/25/83 CP&L meets with NRC. NRC requests additional information on CRDR.
0/15/83 CP&L submits letter on Emergency Response Capability, includes discussion on CRDR.
6/1/83 CPRL submits CRDR 'program plan,'esponding to 3/25/83 request from NRC.
8/15-19/83 NRC audits CRDR, comparing CP&:L's efforts against NUREG-0700.
9/6/83 CP&L submits information on compliance with Regulatory Guide 1.97.
9/19/83 NRC submits summary of audit.
9/27/83 CPRL submits additional information as requested at audit.
11/83 NRC issues SHNPP SER; Open Item 10, Subpart I.D.1, addresses CRDR.
I/3-0/80 ACRS meetings discussed CRDR and integration of CRDR activities with SPDS.
7/80 NRC issues Supplement No. 1 to SER; updating Open Item No. 10, Subpart I.D.1, CRDR.
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ik Enclosure 1 NLS-85-325 8/80 NRC requests additional information, forwarding 7/23/83 comments on 12/7/82 submittal and 3/28/80 comments on 8/83 audit.
1/11/85 CPRL submits additional information on CRDR.
0/9/85 CPRL submits preliminary CRDR Summary Report.
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Enclosure 2 NLS-85-325 ENCLOSURE 2 to NLS-85-325 Res onse to SHNPP SER Su lement No. 1, 0 n Item No. 10. Sub art I.D.I:
Control Room Desi n Review
- l. Action Re ired b SER Su lement No. 1, Section 18.6(1):
"Provide a detailed descri ption of the Shearon Harris system function and task-analysis." (SFTA)
Furthermore, Section 18.0.1 states:
"The staff finds that the applicant must provide a more complete rationale and justification of the method for conducting task analysis for the staff to determine whether the requirements of Supplement No. 1 to NUREG-0737 have been satisfied."
~kli CPRL described the SHNPP SFTA in its December 7, 1982, April 15, 1983, 3une 1, 1983, September 27, 1983, and April 9, 1985 submittals.
The Company's April 15 and 3une I, 1983 submittals indicated that CPRL used H. B.
Robinson Unit 2 (also a Westinghouse PWR Emergency Operating Procedures (EOPs) adapted to the SHNPP design to perform the task analysis. The 3une submittal indicated that these EOPs were used at the simulator to videotape operator activities in abnormal operating and emergency situations. In turn, the videotapes were reviewed by senior human factors specialists to analyze task flows for human factors concerns. This letter also stated that operational information was obtained from H. B. Robinson operators cross-trained to SHNPP and through document reviews (such as FSAR and system descriptions).
In the September 1983 letter, CPRL described involvement in the development and use of the Westinghouse Owners'roup (WOG) Emergency Response Guidelines (ERGs), Revision l. CPRL committed to the following:
identifying SHNPP EOPs deviations from the generic EOPs task analyzing those deviations generating plant-specific lists of instruments and controls needed to perform the EOPs in the SHNPP control room comparing the lists to control room design to identify missing or additionally needed components reviewing the Generic Task Analysis along with the ERGs deviations analysis to ensure review of each EOP step and resolving any discrepancies The letter further stated that the functional analysis that CPRL would perform in redesigning the Main Control Board (MCB) would preclude major human engineering discrepancies.
Sections 6.1.3.3 and 6.0 of the Final Summary Report (Enclosure 3) describe the SFTA in detail including how CPRL used Revision 1 of the WOG ERGs, and the WOG High Pressure (HP) Basic System Review and Task Analysis (SRTA) to develop the plant-speci fic SFTA.
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Enclosure 2 NLS-85-325 The methodology of the SFTA is outlined below:
I. Plant-specific ERGs were prepared based on the WOG ERGs.
- 2. A EOP/ERG Transition Document was prepared which (a) lists differences between the ERG High Pressure (HP) reference plant and SHNPP, (b) explains differences between a WOG and SHNPP step (using step deviation forms), and (c) describes deviations for SHNPP EOP parameters.
- 3. Using the SHNPP ERGs, the Transition Document, and other pertinent data, the WOG HP Basic SRTA was converted into a plant-specific SFTA. For each plant-specific ERG, CPkL prepared a plant-specific Task/System Sequence Matrix and Element Table (similar to the WOG tables). The Matrices provided inventories of tasks and sub-tasks; the Element Tables described tasks and include related knowledge, task decision, action, instrumentation, and control requirements.
- 0. A list consisting of plant-specific action and information requirements for each task, was generated using ACTION-INFORMATIONREQUIREMENTS DETAIL Forms. This form breaks down each task into behavioral elements.
- 5. After computerizing the system, data were selected and sorted by task to summarize information and action requirements.
The final SFTA product identifies the action and information requirements and performance criteria for tasks that a SHNPP operator would have to complete under emergency conditions.
In conclusion, the information provided in the April and 3une l983 and April 1985 submittals and Final Summary Report adequately describes the SHNPP SFTA.
Furthermore, recent discussions with the NRC staff indicated that completion of the process described in the April 9, 1985 submittal would adequately satisfy the NUREG-0737, Supplement No. I, requirements. Therefore, CPRL considers the SER Supplement No. I, Sections I8.0. l and l8.6(I) open items resolved.
- 2. Action Re ired b SER Su lement No. I, Section I8.6(2):
"Describe the process used to compare display and control requirements as determined by the function and task analysis, with the control room inventory."
In addition, Section IS.0.2 states:
"During the in-progress audit, the applicant stated that the Ebasco panel component list had been substituted for a control room inventory [to check existence of controls and displays on the MCB drawings and confirm content vs. need]....Because of the list used and the fact that the WOG generic function and task analysis does not provide a detailed list of control and display requirements, an accurate comparison of control and display requirements with the inventory is not possible."
j (1908CGL/r t )
Enclosure 2 NLS-85-325
~CPR R CPRL described the process used to compare display and control requirements with the control room inventory in its April 9, 1985 submittal. In addition, Sections 6.1.3.0 and 6.5 of the Final Summary Report describe the control room inventory, and Section 6.6 describes how this inventory was used to verify the availability and suitability of control room (CR) components, as identified in the task analysis. Appendix A-26 of the Final Summary Report contains the HEDs generated by this task (as well as their dispositions).
The methodology of the comparison process is outlined below:
- l. The CR and relevant information were reviewed to prepare the inventory, which is a database containing information on each CR component including:
type of component location description or nomenclature application/function identification number labels characteristics (scale ranges, etc.).
- 2. The inventory was compared to the operator action and information requirements identified in the SFTA for each component to verify the presence of required instruments and controls for each task sequence analyzed.
- 3. The inventory was also compared to the range, accuracy trend, nomenclature, and control function requirements in the SFTA database to verify the suitability of CR components.
- 0. Deviations found in Steps 2 and 3 were documented as HEDs (See Appendix'A of the Final Summary Report for HED disposition).
In conclusion, the information provided in the April 1985 submittal and in the Final Summary Report adequately describes the process used to compare display and control requirements with the CR inventory. Furthermore, recent discussions with the NRC staff indicated that completion of the process described in the April 1985 submittal would adequately satisfy NUREG-0737, Supplement No. 1, requirements.
Therefore, CPRL considers the SER Supplement No. I, Sections 18.0.2 and 18.6(2) open items resolved.
- 3. Action Re ired b SER Su lement No. 1, Section 18.6(3):
"Describe the process used to verify that the corrective actions achieved the desired improvement without introducing new HEDs into the control room."
CPRL Res onse:
As a result of the CRDR (conducted from April 1980 through 3anuary 1981), CPRL redesigned the main control board and modified associated CR components using human factors engineering principles. This complete redesign effort produced an optimum human factors design (This effort is described in CPRL's December 7, 1982, 3une I, 1983, and April 9, 1985 submittals to the NRC).
(1908CGL/rtj )
~ I Enclosure 2 NLS-85-325 Furthermore, to provide consistent application of human factors principles throughout CR construction, Human Engineering Requirements Specifications (HERS) were developed and applied in designing features that could not be evaluated at the time of the review (such as CR noise levels, unpurchased equipment, etc.).
These HERS included the following areas:
P annunciator systems color codes for strip chart recorders, pens, and pointers computer systems demarcation and mimic lines labeling rotary selector switches status/monitor light boxes vertical indicators ambient illumination control room furnishings control room temperature, humidity, and ventilation emergency operating procedures noise procedures protective equipment temporary labels voice communications, unaided and telephone.
The HEDs identified through this application of human factors guidelines are listed in Appendices A and B of the Final Summary Report. The methods CPRL used to resolve HEDs are described in the responses to Nos. 0 and 6 of this enclosure. These methods followed human factors guidelines.
Section 7.3.0 of the Final Summary Report indicates that corrections were verified to be in compliance with NVREG-0700 human engineering guidelines by using mockups, computer-aided design systems and simulator and H. B. Robinson EOPs (where possible).
In conclusion, the information provided in the December 1982, 3une 1983 and April 1985 submittals, and the Final Summary Report adequately describes the process used to verify that the corrective actions achieved the desired improvement without introducing new HEDs into the control room. Therefore, CPRL considers the SER Supplement No. 1, Section 18.6(3) open item resolved.
- 0. Action Re ired b SER Su lement No. 1, Section 18.6(0) I'first art]:
"For each of the HEDs listed in Part A of the in-progress audit report, the applicant.
should give the Staf f the status and proposed resolutions, as ivell as a schedule for implementing cor rective action."
Furthermore, Section 18.5.1 states:
"For those instances in which an HED with safety significance cannot be designed out of the system, and a decision is made by the applicant not to correct the HED or to only partially correct it, the applicant must provide
'ustification for the action taken."
(1908CGL/r t j)
Enclosure 2 NLS-85-325 n
~R CPRL P rovides t he dispositions of the HEDs listed in Part A of the in-progress audit report (Enclosure 2 of NRC's August 1980 transmittal) in Appendix B of the Final Summary Report. In addition, CPRL-identified HEDs and their dispositions are listed in Appendix A.
Corrective actions for currently identified HEDs have either been completed (as indicated in Appendices A and B of the Final Summary Report) or are currently in the process of being completed. CPRL expects to complete these prior to fuel load, with the exception of installation of carpeting (HED No. 3100-0107; A17-5), which is expected to be completed prior to commercial operation.
CPRL described the methods used to prioritize and resolve HEDs in Sections 7.2 and 7.3 of the Final Summary Report. This methodology is outlined below:
- 1. HEDs were assessed for potential for error based on component design factors, task factors, and human factors.
- 2. Consequences of the error were estimated. The systems and/or functions that would be affected were used to determine impact.
- 3. Four categories of 'severity'ere assigned to the HEDs. The highest category was given to HEDs having errors related to safety-related systems and/or functions and those related to Technical Specifications.
- 0. HEDs that could be corrected by enhancements, training, and/or procedural revisions were identified.
- 5. HEDs initially identified for correction by enhancement were reassessed for their effect on operator performance.
- 6. For the remaining HEDs, design improvement alternatives were chosen after considering:
relevant task analysis data potential constraints costs and benefits (where applicable) impact of operator training, plant maintenance, and documentation reduction in probability of operator error.
verification that the improvements provide the necessary correction without creating new HEDs Section 7.3.5 describes the method used for scheduling HED solutions. The schedule was chosen after considering:
safety consequences of operator errors that could be caused by the HED integration with other NUREG-0737, Supplement No. 1, programs plant construction, turnover, and operational constraints operator training/retraining requirements.
In conclusion, the information provided in the Final Summary Report adequately describes the resolutions for implementing corrections for the HEDs identified in NRC's in-progress audit report. Furthermore, the methodology described above (1908CGL/r tj )
Enclosure 2 NLS-85-325 assured that proper resolutions and implementation schedules were chosen for HEDs with safety significance. Recent discussions with the NRC staff indicated that these methods represented a satisfactory process for evaluating the significance of HEDs and developing corrections. Therefore, CPRL considers the SER Supplement No. I, Sections 18.5.1 and 18.6(0) [first part] open items resolved.
Action Re ired b SER Su lement No. I, Section I8.6(0) [second art]:
"..provide the results of the evaluation of the following items so the staff can determine whether the requirements of Supplement No. 1 to NUREG-0737 have been satisfied."
- l. workspace
- 2. communications
- 3. remote shutdown panel Q, recorder panel 51 CRTs
- 6. process computer and periphirals
- 7. annunciator systems.
CPdcL described these evaluations in its December 7, 1983, 3une 1, 1983, and April 9, 1985 submittals. In addition, the Final Summary Report addresses the evaluation processes and results for each of the items in the sections listed below:
Section of Final NRC Item Summar Re ort Addressin
- l. workspace 3 2) 6 I 3 2~ 6 2 2 0~ 6 3 1
- 2. communications 3.2, 6.1.3.2, 6.2.2.0, 6.3.1 30 remote shutdown panel 5.0 recorder panels
- 5. CRTs 6.1.3.2, 6.3.3.10
- 6. process computer and periphirals 6.1.3.2, 6.3.3.10 7, annunciator systems 6.1.3.2, 6.2.2.0, 6.3.1, 6.3.3.6 Appendix A of the Final Summary Report contains the HEDs generated as a result of these evaluations and their dispositions. The communications survey has not yet been completed; however, it will be completed prior to fuel load and any related corrections will be dispositioned.
In conclusion, the information provided in previous submittals and in the Final Summary Report adequately addresses the seven items listed above. Therefore, CPkL considers SER Supplement No. 1, Section 18.6(0) [second part] open item resolved.
Action Re uired b SER Su lement No. I, Section 18.5.2:
"Applicant must submit for staff evaluation information concerning any HEDs identified during the verification process, their resolution, and an acceptable time schedule for implementing corrective actions."
(1908CGL/r t )
j
Enclosure 2 NLS-85-325
~PR R CPRL describes the verification process in Section 6.6 of the Final Summary Report. (The response to No. 0 of this enclosure summarizes the methods used to resolve and schedule HEDs.) This report indicates that HEDs were prepared for any action or information requirement where an appropriate display, control, or other device was missing or where components deviated from selected NUREG-0700 criteria.
Appendix A-26 of the Final Summary Report provides a summary description and disposition for HEDs identified in the verification process. Corrective actions for currently identified HEDs have either been completed (as indicated in Appendices A and 8 of the Final Summary Report) or are currently in the process of being completed. CPdcL expects to complete these prior to fuel load, with the exception of installation of carpeting (HED No. 3100-0107; A17-5), which is expected to be completed prior to commercial operation.
In conclusion, the Final Summary Report provides adequate information on the HEDs identified during the verification process, including their resolution and implementation schedule. Therefore, CPRL considers the SER Supplement No. I, Section 18.5.2 open item resolved.
Action Re ired b SER Su lement No. 1, Section 18.5.3 "The applicant did not provide information on coordinating the CRDR activity with the SPDS, Regulatory Guide 1.97, and the emergency response facilities."
C~PR R Safet Parameter Dis la S stem (SPDS)
CPRL described the coordination of CRDR activities with the SPDS in its April 15, 1983 and April 9, 1985 submittals, as well as in the 3anuary 3, 1980 Advisory Committee on Reactor Safeguards (ACRS) Subcommittee meeting.
In the April 1983 submittal, CPRL stated that it would perform the control room design improvement verification and validation activities after the SPDS was installed and functional; in the ACRS meeting, CPRL explained that as a result of the CRDR, the SPDS would be added as two board-mounted CRTs nearest the dedicated ESF controls.
Sections 1.3, 6.1.3.2, 6.1.3.7, 6.0.3.10, and 6.3.3.10 of the Final Summary Report (Enclosure 3) also discuss the coordination of CRDR activities with SPDS.
Section 1.3 states that the placement of the primary and redundant SPDS CRTs ensure maximum readability of the displays.
Re ulator Guide 1.97 CPRL described the coordination of CRDR activities with Regulatory Guide 1.97 requirements in its September 6, 1983 and April 15, 1983 submittals and in the 3anuary 1980 ACRS Subcommittee meeting.
In its April 1983 submittal, CPRL indicated that it was developing final Regulatory Guide 1.97 compliance plans following the ERC NUTAC Draft Guidelines for (1908CGL/rtj )
Enclosure 2 NLS-85-325 I
Integrated Implementation Plan, and that it would perform the design improvement verification and validation activities after the Regulatory Guide 1.97 instrumentation is installed and functional.
In the January 1980 ACRS meeting, CPRL described the integration of the ERFIS computer system with Regulatory Guide 1.97 requirements.
Section 1.3 of the Final Summary Report (Enclosure 3) states that CPRL incorporated the Regulatory Guide 1.97 instrumentation into the MCB layout using the same human factors guidelines used in the MCB re-design effort.
The Final Summary Report also states that the verification and validation activities have assured that these modifications did not introduce HEDs.
Emer enc Res onse Facilities (ERFs)
In the January 1980 ACRS meeting, the April 9, 1985 submittal, and Section 1.3 of the Final Summary Report, CPRL states that the same integrated plant computer system (ERFIS) drives the CRTs in the MCB and ERFs. The Final Summary Report further states that the communications systems between the control room and ERFs conform to 10CFR50, Appendix E, requirements. These documents adequately describe coordinating the CRDR activities with the ERFs.
Conclusion:
The information provided in previous submittals and in the Final Summary Report adequately describes the coordinating of the CRDR activities with the SPDS, Regulatory Guide 1.97, and the emergency response facilities. Therefore, CPdcL considers the SER Supplement No. 1, Section 18.5.3 open item resolved.
(1908CGL/rtj )