|
---|
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
REGULATOR INFORMATION DISTRIBUTION S fEM (RIDS)
ACCESSION NBR;8410300213, OOCeDATE: 84/10/25 NOTARIZED: NO FACIL:50 400 Shear on Har r is Nucl ear Power Pl ant-< Uni t 1< Carol ina 05000400 AUTH ~ NAME, AUTHOR AFFILIATION ZIMMERMANgS,R~ Carolina Power,8 Light Co.
NOTES'OCKET
~
RECIP ~ NAME DENTONgH-,RE
SUBJECT:
Forwards addi response DISTRIBUTION CODE: B001D RECIPIENT AFFILIATION Office of Nuclear Reactor Regulationi to info re internally generated missilesgin SER Open Item 2, COPIES RECEIVED:LTR / /'.
ENCL Director.
'SIZE':
TITLE! Licensing Submittal: PSAR/FSAR Amdts 8, Related Correspondence REC IP IENT COPIES RECIPIENT COPIES ID CODE/NAME~ LTTR ENCL ID CODE/NAME LTTR ENCL NRR/DL/ADL 1 0 NRR LB3 BC 1 0 NRR LB3 LA 1 0 BUCKLEYgB Oi 1 1 INTERNAL: ADM/LFMB 1 0 ELD/HDS1 1 0 1 1 IE/DEPER/EPB 36 1 1 IE'ILE'E/DEPER/IRB IE/DQASIP/QAB21 35 1 1 1 1 NRR'OEgM ~ L 1 1 NRR/DE/AEAB 1 0 NRR/DE/CEB il. 1 1 NRR/DE/EHEB 1 1 NRR/DE/EQB 13" 2 2 NRR/DE/GB 28 2 2 NRR/OE/MEB 18 1 1 NRR/OE/MTEB 17 1 1 NRR/DE/SAB 24 1 1 NRR/DE/SGEB 25 1 1-NRR/DHFS/HFEB40 1 NRR/DHFS/LQB 32 1 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 0 NRR/Ds I/AEB 26 1 1 NRR/DSI/ASB 1 1 ~
NRR/DSI'/CPB 10 1 1 NRR/DSI/OSB 09 1 1 NRR/DSI/ICSB 16 1 1 NRR/DSI/METB 12'B 1 1 NRR/OSI/PSB 19 1 1 22 1 1 NRR/DS I/RSB 23 1 04 1 1 RGN2 3 3 RM/DDAMI/MI8 1 0 EXTERNAL: ACRS 41= 6 6 BNL(AMDTS ONLY) 1 OMB/OSS (AMOTS) 1 1 FEMA REP DIV 39 1 1 LPDR 03 1 1 NRC POR 02"'TIS 1 1 ~
NSIC 05 1 1 1
'TOTAL NUMBER'F COPIES REQUIRED! LTTR 53 ENCL 45
,0 l>>
'1' f; 1,1>> my 1tl'j l II I 1>> yI
't f>> Cr <<1<<yl f ~y ~ I ~"
X >> I
~
>>I c<<II'I y 1 c>> ~ '
fIi y,l' III>>, 1' ~ 1 y,tyll, fy l <<y1 1 y ' l1 y rf y 'gryy i' t li f I'fihr,I yr l
,hh yh r>>>y, 44
'I '
I I l I" j 4%
r'i<< I h Ji 4
]Rg>>4 yy f
< I I
yI >>
1 1 1<<
Carolina Power 8 Light Company SERIAL: NLS-84-409 OGT 35 1984, 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. j. DOCKET NO. 50-400 INTERNALLY GENERATED MISSILES
Dear Mr. Denton:
Carolina Power & Light Company (CP&L) hereby submits additional information concerning Internally Generated Missiles at the Shearon Harris Nuclear Power Plant. This information is in response to Safety Evaluation Report Open Item No. 2 from the Auxiliary Systems Branch.
If you have any questions or require additional information on this subject, please contact me.
Yours very truly, S mmerman Manager Nuclear Licensing Section JHE/cfr (592JHE)
Attachments CC'r. B. C. Buckley (NRC) Mr.
Mr.
Wells Eddleman John D. Runkle Mr. G. F. Maxwell (NRC-SHNPP)
Mr. J. P. O'Reilly (NRC-RII) Dr. Richard D. Wilson Mr. Norm Wagner (NRC-ASB) Mr. G. 0. Bright (ASLB)
Mr. Travis Payne (KUDZU) Dr. J. H. Carpenter (ASLB)
Mr. Daniel F. Read (CHANGE/ELP) Mr. J. L. Kelley (ASLB)
Chapel Hill Public Library Wake County Public Library p84i03002i3 DR ADOCK 84i025
'05000400 PDR 411 Fayettevilte Street o P. O. Box 1551 ~ Raleigh, N, C. 27602
glI m i)
I d
Shearon Harris Nuclear Power Plant SER Open Item No. 2(a)
Internally Generated Missiles Essential Services Chilled Water S stem
~Oen Item:
The SER noted t".at neither the ESCWS or the WPBCWS appears on the list of structures, systems, and'omponents requiring protection against internally generated missiles (outside containment). In response, the applicant stated that the following had been considered as potential sources of missiles that could damage the ESCWS: high pressure systems, rotating machinery, gravitational missiles, and secondary missiles (resulting from the impact of primary missiles). However, the applicant concluded that these missiles were either not credible or would not affect safety-related equipment in the ESCWS area.
The staff finds this conclusion to be unacceptable. Missiles from these potential sources are considered credible unless some deliberate element in the design or extra precaution is provided to prevent their generation.
Design of equipment to appropriate codes is not a satisfactory means for preventing missile generation. Therefore, to justify the conclusion that such missiles are not credible, the applicant must show, in detail, that the design specifically considered the problem of missile generation from these potential sources, or the applicant must show that the ESCWS is protected against such missiles. Either of these approaches will satisfy the staff's concern regarding protection of the ESCWS against internally generated missiles outside containment.
As for the WPBCWS, the applicant noted that no adverse safety or radiological impact results from failure of the nonnuclear WPBCWS and, therefore, -the WPBCWS need not be protected against missiles. The staff finds this acceptable.
~Res ense:
FSAR Table 3.5.1-1 will be revised in a future amendment to include the Essential Services Chilled Water System as a system required for safe shutdown or whose damage by internally or externally generated missiles could result in significant release of radioactivity.
A missile study was performed to evaluate the effects of internally generated missiles on the ESCWS outside containment. This study identifies the potential sources of missiles that could damage the ESCWS. Justification for the determination of non-credible missiles or recommendations to protect the ESCWS from credible missiles has been provided. The following highlights of the study are summarized below:
- a. High Pressure Systems FSAR Section 3.5.1.1 indicates that the only credible potential missiles generated from high energy systems outside of containment would be instrument wells. These potential missiles have been evaluated and the results are documented in FSAR Table 3.5.1-17.
(592JHE/cfr)
Rotating Machinery A pump generated missile study which considered the possibility of rotating machinery as potential missile sources has been performed. This missile study has concluded that the ESCWS is protected from the possible effects of internally generated pump missiles.
Gravitational Missiles SHNPP is designed to ensure that failure of non-safety related, non-seismically designed equipment and/or structures will not adversely affect the operation of safety-related equipment. The ESCWS has been reviewed in its entirety in order to ensure its continued availability. Equipment, systems, components and/or structures in the vicinity of the ESCWS are either seismically designed to ensure, their continued structural integrity post-SSE or the postulated failure of non-seismically designed components has been assumed and it was determined that both trains of ESCWS would not be rendered inoperable.
Secondary Missiles The effects of secondary missiles on safety-related systems including ESCWS, structures, and components is based on fragments generated from primary missiles ~ Our review has identified the existence of potential secondary missiles generated by primary missiles from high pressure systems and rotating machinery. Zn the event that secondary missiles are generated, we have determined that one of the following interactions would occur-'.
- 1. safety-related equipment would not be within the strike zone of the secondary missiles generated; or
- 2. the impact energy from secondary missiles on safety-related equipment is negligible and would not cause any significant damage; or
- 3. barriers and compartmentalization of safety-related equipment would confine secondary missiles to a finite area so that a single missile will be incapable of negating redundant safety trains.
Based on the above analysis, the generation of secondary missiles cannot disable the necessary functioning of the redundant trains of the ESCWS.
(592 JHE/cf r)
Shearon Harris Nuclear Power Plant SER Open Item No. 2(b)
Internall Generated Missiles Missiles From Pum s
~Oen Item:
During the staff review, a concern arose regarding the possibility of internally generated missiles resulting from pump failure. The applicant was made aware of this concexn, and, in response, the applicant noted that missiles from pumps within the nuclear steam supply system (NSSS) scope that are outside of containment have been designed so that their maximum no-load speed is equivalent to their operating speed. Thus, a sudden loss of load (resulting, for example, from a line break) will not result in the generation of missiles. Further, the FSAR states that the balance-of-plant (BOP) is designed so that missiles from internal sources will not damage engineered safety features in a way that would jeopardize the minimum required safety functions.
The staff finds this unacceptable. Although the pumps in the NSSS scope are prevented from overspeeding, the staff concern relates to the possibility of missile generation from.well-designed pumps operating normally (see Item 3, above). In addition, the applicant must provide detailed information to explain how safety-related structuresR systems, and components are protected against internally generated missiles generated from pumps within the BOP scope.
~Ree once:
General Design Criteria 4, "Environmental and Missile Design Bases of Appendix A, "General Design Criteria for Nuclear Power Plants", to 10CFR Part 50, Licensing of Production and Utilization Facilities", requires, in part, that structures, systems, and components important to safety be appropriately protected against the effects of missiles that might result from pump failures. A missile study was performed to evaluate the effects of internally generated pump missiles at SHNPP. Our assessment of internally generated pump missiles was conducted for high speed, reciprocating pumps.
Small capacity support pumps associated with vendor packages were not evaluated in this study because of their small mass, low inertia, and integral incorporation within skid mounted packages.
The objective of this response is to provide assurance that redundant portions of safety-related structures, systems, and components are adequately protected from the effects of internally generated missiles from pumps.
In many cases, protection against pump generated missiles has been provided by the use of missile barriers. In other cases, protection of essential systems or structures against direct strikes by pump missiles was also provided by appropriate placement and orientation of the pump. The'ingle failure criterion is used in the analysis. Therefore, if a safety related pump fails, the single failure criterion is met. If a non-safety related pump fails, an additional single failure is postulated.
Pumps were evaluated in accordance with the following criteria to ensure that missile damage is not credible:
(592JHE/cfr)
- 1. Safety-related pumps which, because of their location, cannot affect multiple power or component trains by generating missiles shall not be considered as a potential danger to the safety of the plant.
- 2. Safety-related pumps which are isolated in cubicles and cannot damage other essential equipment by generating missiles shall not be considered a potential danger to the safety of the plant.
3~ Non-safety related pumps which are located in non-safety related areas or which are isolated in cubicles and cannot damage essential equipment by generating missiles shall not be considered a potential danger to the safety of the plant.
- 4. Pumps for which vendor calculations or certifications are available stating that the pumps cannot generate missiles that penetrate the pump
~
casing shall not be considered a potential danger to the safety of the plant.
- 5. Any pumps which are intended for use only during cold shutdown, shall not be considered a potential danger to the safety of the plant.
In order to assess the effects of pump generated missiles, the pumps listed in Table 1 were located and reviewed in terms of the evaluation criteria listed above. Evaluation Criteria 1, 2, and 3 eliminated most of the pumps (safety and non-safety related) from further analysis because of their location and the location of other essential components in the area of the pump.
Pumps which did not fall into categories 1, 2, or 3 were reviewed in terms of Evaluation Criteria 84. The pump vendor was contacted to determine whether the pump could actually generate a missile that could penetrate the pump casing. The vendor'was requested to submit a letter of certification or a calculation showing that the pump could not generate a missile that would penetrate the pump casing. If such information was not available, the vendor was requested to supply pump data necessary to allow appropriate calculations to be performed.
Pumps which did not fall into any aformentioned categories were reviewed'in terms of their mode of operation. If a pump was intended to operate only during cold shutdown conditions, evaluation criteria /I5 was utilized.
Subsequent to the application of Evaluation Criteria 1-5, four types of pumps could not be eliminated from further consideration. For three of these types, the Charging Pumps, the CVCS Chiller Pumps, and the RHR Pumps, the potential for missile generation has been evaluated,.on the basis of the projected missile strike zones. Missiles from these pumps will not result in the impact of redundant essential component trains. The remaining pump type, the Boron Injection Recirculation Pump, is a close-coupled pump whose missile expulsion potential is not considered a potential danger to the safety of the plant.
(592JHE/cfr)
The results of the evaluation are summarized in Table 1 Pump Generated Missile Study. This evaluation supports the conclusion that systems, structures and components whose failure could prevent safe shutdown of the plant or result in significant uncontrolled release of radioactivity have been protected from the possible effects of internally generated missiles.
(592 JHE/c fr)
TABLE I - PNP GENERATEO MISSILES STUOY Eliminated er criteria:
T e of Pu Location 2 3 4 Remarks Charging Pump RAB EL, 236' The potential for mlssl le generation 016 (J 6~ 7p 8) has been Identified. Subsequent evaluation of the proJected missile strike zone has resulted in the conclusion that missile generation from this pump can not result in t Impact of redundant essential component trains.
SW Booster Pump RAB EL, 236'-016 (K-11) (K-16)
Boric Acid Transfer RAB EL, 236)
G-016 (J" 16)
CVCS Chl lier Pump RAB EL, The potential for missile generation (M-'lb) has been identified, Subsequent 236'-016 evaluation of the proJected missile strike zone has resulted In the conclusion that mlsslle generation fran this pump can not result In the impact of redundant essential component trains.
Reactor Makeup Water Pump Tank Area EL. 236~
G-033 (H"8)
(592JHE/cfr)
EI iml nated er cr I ter I a:
T eof Pum Location 2 3 4 Remarks Condensate Transfer Pump Tank Area EL, 236'433 (H-8)
Sec. Waste Sample Tank Pump Tank Area EL. 236~
G"033 (H-7)
Tank Area Drain Pump Tank Area EL 236'-033 (1-4)
Reactor Coolant Orain Tank Pump Cont. Bldg. EL, 221~
G-011 (J-4)
Reactor Coolant Pump Cont. Bldg, EL, 236~
G-Oil (F-13)
Fuel Pool Cooling Pump FHB EL, 236'-023 (H-8)
Containment Spray Pump RAB EL, 190~
G-015 (1-12, 19)
RHR Pump RAB EL, The potential for missile generation (l-13, Identl f led, Subsequent 190'-015
- 18) has been evaluation of the projected missile strike zone has resulted In the conclusion that missile generation fram this pump can not result in the impact of redundant essential component trains.
El Imlnated er criteria:
T e of Pum Location Remarks Floor Drain Transfer Pump RAB EL, (J-I) 190'&15 Boron InJection Reclr, Pump RAB EL, 216~ Analysis of the potential for G-015 (J-8) miss l le generation has ldentl f led a penetration constraint due to pump design. A potential missile would be required to Impinge upon and penetrate either the casing flange or a portion of the pump driver.
This pump, therefore, is not considered to be a potential danger to the safety of the plant, HVAC Condensate Transfer Pump RAB EL. 216~
G-015 (K-5)
SSE Fire Protection Booster Pump RAB EL.
(J-1) 216'-015 Recycle Monitor Tank Pump RAB EL, 261>
G-017 (L-12, 16)
HVAC Chilled Water Pump RAB EL, 26ls G-017 (L-8)
Steam Generator Wet RAB EL, 261>
Lay&p Reclrc. Pump G-017 (J-5)
(592JHE/cfr)
EI Imi nated er cr I ter la:
T eof Pum Location 2 3 4 Remarks Condenser Water Pump RAB EL, (L-I) (L-8) 261'-017 Component Cooling Water Pump RAB EL, 236~
G-016 (M-3, 9)
Motor Driven Steam Gen. RAB EL, 236'"016 Aux. Fee@rater Pump (M-6)
Turbine Driven Steam Gen, RAB EL, 236>
Aux. Feebrater Pump G-016 (M-9)
Decontamination Wash Pump FHB EL 261 )
G-022 (8-21)
Decontamination Rinse Pump FHB EL, 261>
G-022 (8-21)
Decontamination Transfer Pump FHB EL, 236~
G-023 ( I -18)
HVAC Cond. Receiver Transfer Pump FHB EL, 216'-023 (E-3)
Fuel Pool Skinner Pump FHB EL, 236'-023 (G-13)
(592JHE/cfr)
EI lml nated er cr I ter I a:
T eof Pum Location 2 3 4 Remarks CCW Transfer Pump FIB EL, 216'-023 (D-18)
Spent Fuel Pool Refueling FfS EL, 216<
Water Purl f lcatlon Pump G-023 (C-6)
Equipment Drain Transfer Pump RAB EL, 190~
G-015 (J-16)
Hydrotest Pump RAB EL (I-3) 236'-016 Aux. Bul ldlng Fl lter RAB EL X 236'-016 Backwash Transfer Pump (G-I3)
Recycle Evaporator Feed Pumps RAB EL, X 236'-016 (G-10)
FHB Filter Backwash Transfer Pump FIS EL, 216~
G-023 (C-4)
Diesel Oil Transfer Pump OOSTA G-214 (D-9, 13)
Cooling Tower Makeup Pump ES)f Intake G-202 (E-5, 7)
(592JHE/cfr)
Eliminated er criteria:
T e of Pum Location Remarks Normal Service Water Pump NSW I ntake G-201 (H-10)
Circulating Water Pump CT Intake G-203 (C-12)
WPB Cooling Water Pump WPB CL 261'-912 (1-13)
Waste Monitor Tank Pump Tank Area G-033 (L-4)
Chlorine Booster Pump NSW Intake G-201 (I-12)
Caustic Metering Pump CT Intake G-203 (0-9)
Acid NeterIng Pump CT intake G-203 <E-8)
Fire Service Screen Wash Pump ESW Intake G-209 (F-5, 11)
Fconomizer Reclrc. Pump Aux. Boiler Bldg, G-243(Sl) (G-10)
(592JHE/cfr)
Eliminated er criteria:
T e of Pum Location 2 3 Remarks Rinse Recycle Pumps Turb, El'40
&404 (0-5)
Condensate Pumps Turb, Bldg.
G-004 (J-10)
Steam Generator Feed Pumps Turb." B I dg, G-005 (C" 13)
Heater Orain Pumps Turb. Bldg.
G-004 (E-14)
Condenser Vacuum Pumps Turb. Bldg.
G"005 (G-9)
Aux. Bol ler Fuel Ol I Yards Unloading Pump G-210(SO I ) (E-14)
Screen Wash Pump ESW Intake G-205 (G-4, 6)
Aux. Steam Condensate Pump WPB G-910 (G-11) (J-11)
Main Reservoir Make-Up Pump Deleted (Unit 2 Cancellation)
(592JHE/cfr)
EI lmlnated er criteria:
T eof Pum Location Remarks Fire Water Pump ESW Intake Screen G-209 (E-14)(F-4)
Jockey Pump ESW Intake Screen G-209 (G-14)
Condensate Booster Pump Turb.
G-005 (C-B)
Emergency Service Water Pump ESW Intake G-202 (C-13, 18)
Floor Oraln Tank Pump WPB EL, 2IIs G-910 (K-3)
Floor Drain Tank Mixing Pump WPB EL, (L-3) 211'-910 FO Polyelectrolyte Feed Tank Pump WPB EL, 2l l~
G-910 (L-4)
Waste Evaporator Feed Pump WPB EL 211'"910 (L-7)
Waste Evaporator Conc, Tank Pump WPB EL, X (L-8) 211'-910 (592JHE/cfr)
EI iml nated er cr I ter I a:
T eof Pum Location 2 3 4 Remarks Gas Decay Tank Drain Pump WPB EL, 2iii G-910 (N"7)
,t WPB Flit. Part, Cond. Tank Pump WPB EL.
211'-910 (N-7)
WPB Filter Backwash Storage WPB El.
211'-910 Tank Pump (M-B, 9)
Chemical Drain Tank Pump WPB EL, 211'-910 (J-5)
Waste Evaporator CNDS Pump WPB EL, 21 I>
G-910 (J"7)
RO Feed Pump WPB EL, 21I>
G"910 (H-6)
Spent Resin Transfer Pump WPB EL, 211'-910 (H-10)
Sluice Pumps Turb. EL, 240~
G-004 (E-8)
Lube Ol I Transfer Pump Turb.
G-005 (J-16)
(592JHE/cfr)
Eliminated er criteria:
T e of Pum Location 2 3 4 Remarks Spent Resin Sluice Pump WPB EL, (1-10) 211'-910 Aux. Steam Cond, Tank Pump WPB EL, (J" 11) 211'-910 (G-11)
Sec. Waste Evap.'ond. Tank Pump WPB EL. 2II~
G-910 (G" 13) (1-13)
Sec. Waste Evap. Conc, Pump WPB EL.
211'-910 (H-14)
Sec, Waste Evap. Reclrc. Pump WPB EL, 2II~
G-910 (G-14)
SW Filter Backrash Transfer WPB EL, 211'-910 Tank Pump (H-15)
High Conductlvlty Hold Tank WPB EL 211>
Mixing Pump G-910 (J-14)
High Conductlvlty Hold Tank Pump WPB EL, 211~
G-910 (J-14)
Low Conductivity Hold Tank Pump WFB EL, 2II~ X G"910 (L-13)
(592JHE/cfr)
Eliminated er criteria:
T e of Pum Location Remarks Chiller Pumps WPB EL, 291'-914 (G-10)
Sol ldi f i cation System Pretreat. WPB EL, 291'ank Pump G-914 (L-4)
WPB Feed Pumps WPB Ef, 291~
G-914 (J-9)
RO Conc. Evap. Cond, Pump WPB EL, (M-3) 236'G-911 RO Conc, Evap. Reclrc. Pump WPB EL, 236>
G-911 (K, L-3)
RO Conc. Evap. Distill Pump WPB EL, (L-3) 236'-91'I RO Conc, Evap, Conc. Pump WPS EL, (J-3) 236'-911 LNS Tank Pump WPB EL, 236)
G-911 (H-3)
LQ6 Tank Mixing Pump WPB EL, 236'-911 (H-3)
(592JHE/cfr)
El lmlnated er criteria:
T e of Pum Location 2 3 5 Remarks LATHS Polyelectrolyte Feed Pump WPB EL. 236~
G-9ll (H-3)
Treated Laundry 4 Hot WPB EL, 236>
Shower Tank Pump G-9ll (E-3)
Demineralized Water Storage Pump 'ard G-210 (SO) (L-5)
Skimned Ol I Trans Pump Yard G-210 (S03) (H-5)
Burner Fuel Ol I Pump Yard G-210 (SO I) (E-14)
Effluent Water Transfer Pump Yard G-210 (S03)(H-3)
Neutralization Basin Reclrc. Pump Yard G-201 (S03)(E, H-12)
Flash Mixer Feed Pump Yard G-2'IO (S03) (E, I-16)
(592PIE/c fr)
Eliminated er crlterla:
T e of Pum Location 2 3 Remarks Secondary Waste Evap. WPB EL, Distillate Pump 236'everse Osmosis Concentrate WPB EL 236<
Evaporator Feed Pump
~ I Laundry and Hot Showers Reverse WPB Osmosis Feed Pump EL'36'ettling Tank Drain Transfer Pump Turb. Bldg, EL, 240'mmonia Recycle Pump Turb, Bldg. EL.
240'ube Oil Conditioner Circulation Turb, Bldg, EL, 26i~
Pumps Emergency and Bearing Oll Turb. Bldg. EL, Pumps ln Oil Reservoir 286'mnonla Transfer Pumps Yard Diesel Ol I Unloading Pumps Yard Evaporator Concentrates Pump RAB EL ~ 236<
G-0l6 (592JHE/cfr)
Eliminated er criteria:
T eof Pum Location Remarks Distillate Pump RAB, EL, 236'-016 ESCWS Lubricating System Oil Pump RAB ~ EL. 26I~
G-017 (592JHE/cfr)