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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
I'EQUL+AY INFORNATION DIBTRIBUTI SYSTEN (RIDE)
ACCESSION NBR: 860905'0038 DOC. DATE: 8b/08/29 NOTARIZED: NO DOCKET 0 FACIL: 50 400 Sheav'on Harv is Nuclear Powev'lanti Unit ii Carolina 05000400 AUTH. NAl'>E AUTHOR AFFILIATION ZINNERI'QNi S. R. Cav olina Powev'c Light Co.
RECIP. NANE RECIPIENT AFFILIATION DENTONi H. R. Office of Nuclear Reactov Regul tioni Director (post 851125 h~u s~3 '7 i<I<7
SUBJECT:
Forwards Rev 3 to facility CRBR final ummarg v'ept (FSR)i consisting of revised pages to CRDR FSR 5 addi in fo v e Auxiliary Equipment Panel 1 in vesponse to discussions w/8 gneiss Cc SN Saba on 860819.
DISTRIBUTION CODE: A003D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: OR/Licensing Submittal: Supp l 1 to NUREQ-0737(Qeneric Ltr 82-33)
NOTES: *pp l i cat i on fov p ev mi t renewal fi 1 ed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NANE LTTR ENCL PNR-A ADTS 1 1 PMR-A EB 1.
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0, ggQQ Carolina Power & Light Company SERIAL: NLS-86-328 AUG 2 9 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO.50-000 CONTROL ROOM DESIGN REVIEW FINAL
SUMMARY
REPORT
Dear Mr. Denton:
Carolina Power R Light Company (CPRL) hereby submits Revision 3 to the Shearon Harris Nuclear Power Plant (SHNPP) Control Room Design Review (CRDR) Final Summary Report (FSR). Additional information regarding the Auxiliary Equipment Panel Number One (AEP-1) is also being provided. This material is in response to discussions with Dr. S. Weiss and Dr. S. N. Saba of your staff on August 19, 1986 at the SHNPP site. provides the revised sections of the SHNPP CRDR FSR, which includes the relevant information required to complete the staff's review of the SHNPP CRDR Program. Each revised page is paginated such that it directly replaces the corresponding pages contained in the SHNPP CRDR FSR. Revisions are indicated by the vertical line in the right margin next to the changed areas. provides a revision to the SHNPP AEP-1 Review submitted to you on May 30, 1986. Please note that the AEP-1 Review is additional information and is not part of the CRDR FSR.
The AEP-1 is currently scheduled to be photographed on September 3, 1986. The three different photographs to be taken are:
The entire AEP-l, A closeup of Status Light Box j/12, and A closeup of the reactor vessel and pressurizer vent valve control portion of the AEP-1.
Two color 8" X 10" copies of each of the above will be submitted to you by September 15, 1986.
86090500g8 8608~9 DR QDQQQ 0g0 Fr DR 411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N. C. 27602
0 I
'Ltr. H. R. Denton NLS-86-328 / Page 2 With this submittal, CPRL considers the outstanding NRC concerns regarding the SHNPP CRDR Program to be closed. Should you have any questions concerning this submittal, please contact Mr. Arnold Schmich at (919) 836-8759.
Yours very truly, S.. Zim erman ager Nuclear Licensing Section AWS/mf (0070AWS)
Enclosures cc:~ Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
Dr. S. N. Saba (W/2E)
~ cc Distribution With Enclosures
ENCLOSURE 1 ENCLOSURE 2 AEP-I REVIEW A review of Emergency Operating Procedures was conducted by plant operations personnel to determine which steps require actions on the part of an operator to interface with the Auxiliary Equipment Panel One (AEP-l). Each action was then reviewed to determine the necessity of using the AEP-l (e.g., are other controls or indicators used) and whether there were any consequences of either misuse or nonuse of the AEP-l controls or indicators. In addition, a review of all AEP-l indicators and controls was conducted to determine safety consequences of nonuse or misuse and whether the AEP-l control or indicator was the primary control or indicator for the required actions.
For all AEP-I controls or indicators, excluding the reactor vessel and pressurizer vent valve controls, no safety consequences from misuse or nonuse were discovered. Since the reactor vessel and pressurizer vent valve controls are safety related, they were well labeled and physically separated from the rest of the AEP-l controls. The vent valves have pull-to-lock switches requiring that two separate steps be performed before a vent valve could be opened. In addition, the reactor vessel and pressurizer vent valve control knobs have been painted red, and this section of the AEP-l has been demarcated to further differentiate the valve controls from other AEP-1 controls.
Attached are the results of this AEP-l review.
(3750Aws/pgp)
AEP-1 LIGHT BOXES ALB-023 (Annunciator Light Box) has coordinate axis labels and will be read from directly in front. Operations has no trouble reading it.
DRPI (Digital Rod Position Indication) will be used during rod motion to recover dropped control rods and to verify a reactor trip. In all of the cases, DRPI will be the secondary source of information with the primary source being the ERFIS computer.
SLB-08 (Status Light Box) B Train indication of RAB HVAC damper position. These dampers are slaved to the two RAB normal supply fans which trip on a SI signal.
During normal fan operation, the ERFIS computer will be used to verify the damper positions as the fans are started. The Status Light Box indications will be used as a secondary indication. If the damper position is misread on a fan start, temperature alarms on the ERFIS computer and/or alarms on the RMS computer would indicate the problem. If such an alarm is received, the damper will be locally checked before any action is taken. There is no safety consequence of error from misreading any damper position.
The same actions are taken on a SI signal, except it is for a fan stop and damper closure.
SLB-10 A Train (Same as SLB-08)
SLB-09 B Train indication of chilled water valves, HVAC dampers in the ESW intake structure, and HVAC dampers in the Fuel Handling Building (FHB). The indication will be used to verify proper automatic actions (open dampers or valves) during normal operation. There are no safety consequences from a misreading of the SLB since the indications have ERFIS temperature alarms to alert the operations that the automatic actions did not occur. If the alarms are received, the dampers or valves will be locally checked before any action is taken.
SLB-11 A Train (Same as SLB-09)
SLB-12 indication of HVAC dampers in the RAB. SLB-12 provides indication of inlet and outlet dampers for various fans throughout the plant. These indications would be used to verify automatic actions during normal fan starts. Fourteen, of these status lights are backups to the air flow indication of the AEP-1. The rest of the lights have trouble alarms that annunciate if the proper automatic actions do not occur. In either case, the only consequence of these automatic actions not occurring
'ould be a fan trip. This would also give an alarm in the Control Room. If a fan does trip, it would be monitored upon fan restart. There is no safety consequence of an incorrect reading of these indications. (These indications are not used in the EOPs.)
(3705Aws/vaw)
AEP-I CONTROLS Sample Isolations (Steam Generator, Accum., RCS, PRZ, CNMT atmos, and CNMT sump) - These sample lines have redundant isolation valves so there are no consequences from opening the wrong isolation valve. The sample isolation valves are normally open with the only consequence of an inadvertent closure being a small ~
delay in obtaining a sample. There are no safety consequences from inadvertently operating the control of a sample isolation valve.
The sample isolation valves receive a Phase A CNMT isolation signal. The primary means of verifying the Phase A closure is on the ERFIS computer. The back up means is controlled by plant procedures. An extra operator in the Control Room, after the initial phases of the transient are over, is tasked with verifying items on a check list.
Post Accident Sample System (PASS) - The PASS is only mentioned once in the Emergency Operating Procedures (EOPs). This is in EOP-020 Step 7. This step states "Initiate Evaluation of Plant Status: ~ .. Obtain samples of RCS, SG, and CNMT Sump." The sample of the RCS would be obtained with the PASS.
If the operator does not properly line up the PASS valves from the AEP-l, the result would be that the chemist would not be able to draw his sample without delay. The chemist would then notify the Control Room of his inability to draw the sample.
Upon receiving this information, the operator would correct his valve lineup at the AEP-l, and the chemist would then draw his sample.
The basis for this procedure step (from the Westinghouse Owners'roup) states "Since an evaluation of plant status may require some time to complete . ~ ~ it is initiated early in the recovery..." This sample would be used to help determine the long-term recovery actions. As a result of several plant emergency drills, it was determined that approximately one hour was required to obtain a sample. Should it require two hours (twice the normal time) to obtain this sample, it would still be completed before plant recovery was delayed. There is, therefore, no safety consequence from incorrect operation of this control.
Steam Generator Blowdown Isolation - Same as the sample isolations except these receive a SI signal instead of a Phase A isolation.
Chemical Addition to Steam Generator - These isolation valves must be opened and the ammonia and/or hydrazine metering pump locally started to add chemicals to the steam generators. If a valve is accidentally closed, the only consequence would be a delay in adding chemicals to the steam generator. There are no safety consequences from incorrectly operating the controls to these valves.
These valves receive a feedwater isolation signai and/or a SI signal and are verified closed the same way as the isolation valves.
RCDT - These are redundant isolation valves like the sample isolations and also receive a Phase A isolation which is verified in the same manner.
CNMT Fan Coolers - These valves isolate normal service water to the nonsafety CNMT fan coolers. The only consequence for inadvertently closing one of these valves would be the loss of cooling water to the nonsafety fan coolers. This would be (3705AWS/v8H)
detected by a CNMT ambient temperature alarm located on the MCB. These are redundant valves, so there would be no affect from inadvertently opening one of these valves. There is no safety consequence from incorrectly operating a control of the CNMT fan coolers.
These valves receive a Phase A isolation signal and would be verified in the same manner as the sample isolation valves.
Fuel Pool Cooling Pumps - Inadvertent stoppage of a pump would be immediately detected by a low flow annunciator on the AEP-l. There would also be a high temperature annunciation on the AEP-1 before there was any danger of the pool overheating. If a pump was inadvertently started, the only consequence would be an increase in pool cooling flow. There are no safety consequences from incorrectly operating the controls of a fuel pool cooling pump.
Chilled Water Isolation Valves - These normally-open valves isolate a non-essential portion of the chilled water system from the essential portion. The only consequence of inadvertent closure of a valve would be a high temperature alarm on the ERFIS computer. These valves close on a SI signal and will be verified in the same manner as the sample isolation valves. The operator must accidentally open four valves before there is any potential for a problem. There is no safety consequence from incorrectly operating the controls of the chilled water isolation valves.
Essential Chillers and Expansion Tanks - There are two redundant 100-percent capacity chillers and associated expansion tanks. If make-up water is inadvertently stopped or started to either expansion tank, the results will be a hi-hi or lo-lo level alar m on the AEP-1. The affect of inadvertently stopping the running chiller would be the activation of several annunciators on the AEP-1 and eventual initiation of high area temperature alarms on the ERFIS computer. Dependent upon the plant operating mode, either three or four annunciators for each of the two chillers would be activated on the AEP-1. If an idle chiller is inadvertently started, the chiller's automatic control system would shut it off because there would be no service water to cool the chiller. There are no safety consequences from incor rectly operating the controls of a chiller.
Both chillers start on a safety injection signal and would be verified in the same manner as the sample isolation valves.
RAB HVAC - Local Air Handling Units (AHU) - These are two 100-percent capacity automatic cooling trains. There will normally be one train in operation with each AHU cycling on and off based on the ambient temperature in each area. If a fan is inadvertently stopped, the result would be an ERFIS computer high temperature alarm for the respective area or the area fan automatically starting. If a fan is inadvertently started, the result would be the fan automatically stopping or extra cooling in a room in the plant. There are no safety consequences from incorrectly operating the controls of one of the AHUs.
Both trains of the AHUs start on a SI signal and would be verified in the same manner as the sample isolation valves.
RAB HVAC Normal Supply and Exhaust Fans - There are two 100-percent capacity supply fans and four 50-percent capacity exhaust fans. Each fan has flow instrumentation and flow alarms on the AEP-I that will alert the operator if the (3705AWS/va w )
wrong fan is inadvertently stopped. Both supply fans and/or the four exhaust fans must be stopped for a period of time before there is any potential for a problem. If a fan is inadvertently started, the only consequence would be an increase in the air flow through the RAB. There are no safety consequences or potential for radiation release from incorrectly operating the control of a fan.
These fans stop on a SI signal and would be verified in the same manner as the sample isolation valves.
One function of these fans is to ventilate the RAB to minimize the airborne radiation levels. If these fans should trip, it would take from several minutes to several hours before the airborne radiation could pose a significant problem. The time factor is dependent upon plant conditions, work in progress, and the time in core life. Airborne radiation would be detected by the extensive plant radiation monitoring system prior to it becoming a significant problem.
RAB HVAC - Emergency Exhaust Fans - These are two 100-percent capacity exhaust fans used during emergency operation. Both fans must be stopped for a period of time before there is any potential for a problem. If a fan is inadvertently started during normal operation, the only result would be an increase in the air flow through the RAB. There are no safety consequences from incorrectly operating the controls of the emergency exhaust fans.
Both of these fans start on a SI signal and would be verified in the same manner as the sample isolation valves.
One function of these fans is to ventilate the RAB to minimize the airborne radiation levels. If these fans should trip, it would take from several minutes to several hours before the airborne radiation could pose a significant problem. The time factor is dependent upon plant conditions, work in progress, and the time in core life. Airborne radiation would be detected by the extensive plant radiation monitoring system prior to it becoming a significant problem.
RAB HVAC - Room Exhaust Fans - Each room has two 100-percent capacity exhaust fans. Both fans must be stopped for a period of time before there is any potential for a problem. The only consequence of inadvertently starting a fan would be an increase in the air flow through the individual room. There are no safety consequences from incorrectly operating the control of a fan.
RAB HVAC - Smoke Purge Fans There are two smoke purge fans which are used after a fire is extinguished to assist in the recovery effort. Upon detection of a fire, all HVAC for the area is automatically secured by fire dampers and/or operators in the Control Room. After the fire is extinguished, the fire brigade leader will inform the Control Room to begin the smoke purge. The fire brigade leader will remain on the scene until the smoke has been cleared. During fan use, only fire brigade personnel will be in the affected area. The result of accidentally stopping a smoke purge fan would be an increase in the time needed to remove the smoke. If a fan is inadvertently started, the only result would be an increase in air flow through the RAB. There are no safety consequences from incorrectly operating the control of a smoke purge fan.
Fuel Handling Building HVAC There are two parallel trains of normal HVAC for the FHB. If a fan is inadvertently stopped, there is a high temperature annunciator on the AEP-1 for the spent fuel pool (SFP) area and ERFIS alarms for the SFP pump (3705Aws/vaw)
room temperatures. Accidental starting will only result in an increased air flow.
There are no safety consequences of incorrectly operating the controls of the fans.
ESW Intake Structure HVAC - There is one train of HVAC for each train of ESW. These fans are used when the associated ESW pump is running or the room temperature is above 90'F. No single failure can disable both trains of HVAC. If one train is inadvertently stopped, it would be detected by an auxiliary operator on his normal rounds or by a high temperature alarm on the ERFIS computer. The operators normally go on rounds twice per 12-hour shift or approximately every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Continuous operation of these fans is not required so it is acceptable for these fans to be stopped until the operator makes his next set of rounds. If a fan is started, the only consequence would be an increased air flow through the building. There are no safety consequences from incorrectly operating the control of one fan.
These fans start on a Sl signal and would be checked in the same manner as the sample isolation valves.
Diesel Fuel Oil Pump Exhaust Fan - There are two exhaust fans in each train. Both fans in one train must be stopped before there is any potential for a problem. If one fan is inadvertently stopped, it would be detected by an auxiliary operator on his normal rounds or by a high temperature alarm on the ERFIS computer.. The operators normally go on rounds twice per 12-hour shift or approximately every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Continuous operation of these fans is not required so it is acceptable for these fans to be stopped until the operator makes his next set of rounds. There is no safety consequence from incorrectly operating the control of one of these exhaust fans.
These fans start on a SI signal and would be checked in the same manner as the sample isolation valves.
Pressurizer and Reactor Head Vent Valves During normal operation, if these valves were incorrectly opened (two series valves must be open for an RCS release path),
the Control Room would receive an alarm. This alarm would either be immediate or within approximately 30 minutes depending on which valves were opened. In either case, an alarm on the MCB would be received before any action would need to be taken to correct the situation.
The vent valves can be aligned to discharge to two different locations. The preferred location is to the Pressurizer Relief Tank (PRT). When there is vent flow to the PRT, there will be a "REACTOR VESSEL VENT FLOW" alarm o.-the main control board. This alarm will be used to verify flow and, therefore, a proper valve lineup. The second location, which should only be used if the PRT cannot be lined up, is to discharge to the CNMT atmosphere.
EOP use of the head vent valves occurs in two different ways. The first use is as an RCS bleed path, that is to deliberately create a controlled release in the RCS. The EOPs tell the operator to open all pressurizer PORVs and vent valves. If the vents are not properly lined up to the PRT and there is no flow, the flow alarm will not be received. If the vents are supposed to be discharging to the CNMT atmosphere (secondary source), but are not, the error would be comparatively insignificant because the PORVs should have about 25 times the flow as the vents.
The second use of the vents is to release a gas bubble from the RCS (increase the water level in the vessel). Implementation of this procedure would be a very slow and deliberate process in which the water level in the vessel will be constantly monitored. If the valves are not properly lined up, the operator monitoring the (3705AWS/vow)
vessel level will notice it is not increasing and stop the venting process to check the valve lineup for the vents.
Since the reactor vessel and pressurizer vent valve controls are safety related, they were well labeled and placed on the AEP-l such that they were physically separated from the remainder of the panel. In addition, the vent valves have pull-to-lock switches which require that two separate steps be performed before a vent valve could be opened. In order for these switches to be turned, they must first be pushed in to unlock them. These are the only pull-to-lock switches on the AEP-l and are normally locked closed. As a result of the Control Room Design Review, the reactor vessel and pressurizer vent valve control knobs have been painted red, and this section of the AEP-I has been further demarcated to differentiate the vent valve controls from other AEP-l controls.
(3705Aws/vow )