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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML20212H7741999-06-23023 June 1999 Responds to Re Petition Filed by Orange County Board of Commissioners Re Proposed Expansion of Sf Storage Capacity at Shearon Harris Npp.Public Meeting Will Be Held at Later Date.With Certificate of Svc.Served on 990624 ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML20206R2511999-05-19019 May 1999 Responds to Addressed to Chairman Jackson Requesting That NRC Grant Standing to Orange County Board of Commissioners in Shearon Harris Proceeding Currently Before Board.With Certificate of Svc.Served on 990519 ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9601999-05-11011 May 1999 Forwards Resolution Adopted by Carrboro Board of Aldermen at 990504 Meeting.Resolution Expresses Town Concern Re Util Plans to Double high-level Nuclear Waste Storage at Shnpp ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl IR 05000400/19982011999-04-12012 April 1999 Discusses Safeguards Insp Rept 50-400/98-201 (Operational Safeguards Response Evaluation) on 980908-11.No Violations Noted.Licensee Performance During Evaluation Indicated Excellent Overall Contingency Response Capability 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl ML18016A8911999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld ML18016A8891999-04-0101 April 1999 Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings ML18016A8811999-03-31031 March 1999 Responds to NRC 990301 Ltr Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 ML18016A8671999-03-19019 March 1999 Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC ML18016A8631999-03-19019 March 1999 Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl ML18016A8691999-03-18018 March 1999 Forwards Resolution Adopted by Lee County,North Carolina Board of Commissioners Re Proposed Expansion of high-level Radioactive Waste Storage Facilities at Carolina Power & Light Shearon Harris Nuclear Power Plant ML18016A8511999-03-15015 March 1999 Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs 'C' & 'D'. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld ML18016A8601999-03-15015 March 1999 Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0911990-09-12012 September 1990 Confirms That Fee Electronically Transferred to Dept of Treasury for Payment of NRC Review Fees ML18009A6581990-09-11011 September 1990 Submits Addl Info Re Use of Hafnium Control Rods at Facility.All Rods Will Be Removed During Spring 1991 Outage ML20059H4181990-09-0606 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-13.Corrective Action:Changes to EST-717 in Area of Power Normalization Under Study for Past Several Months ML17348B4941990-08-30030 August 1990 Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty ML20059D3511990-08-30030 August 1990 Forwards Decommissioning Financial Assurance Certification Rept Submitted by North Carolina Eastern Municipal Power Agency ML18009A6261990-08-10010 August 1990 Informs That Action Committed to in Response to Generic Ltr 88-14, Instrument Air Supply Sys, Completed ML18009A6241990-08-0303 August 1990 Forwards Addl Info Re Operator Action Times Assumed in Steam Generator Tube Rupture Analyses for Plant,Per 900712 Telcon ML18009A6081990-07-31031 July 1990 Forwards Plan for Shearon Harris Nuclear Power Plant Emergency Exercise - 900919, Per NRC Request.W/O Encl ML20055J4171990-07-30030 July 1990 Forwards Rev 5 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20055F9431990-07-12012 July 1990 Advises That Stated Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900711 for Payment of Operator License Exam Fees for Listed Insp Invoices ML18009A5991990-07-0606 July 1990 Comments on Electrical Distribution Sys Functional Insp Rept 50-400/90-200 on 900212-0316.Seismic Qualification Package Subsequently Upgraded to Include Qualification Info Based on Receipt of Part 21 from Transamerica Delaval ML18009A5851990-06-28028 June 1990 Advises That Emergency Preparedness Exercise Scheduled on 900919.Exercise Will Consist of Simulated Accident at Plant Site & Will Involve Planned Response Actions.Objectives to Be Fulfilled Encl ML18009A5621990-05-30030 May 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Rept 50-400/90-06.Corrective Actions:Procedures OST-1008 & OST-1108 Revised to Delete Stroke Testing of Valve 1ST-359 on Quarterly Basis ML18009A5141990-05-0303 May 1990 Forwards Eddy Current Exam CP&L Shearon Harris Nuclear Power Plant Steam Generators A,B & C, Providing Results of Inservice Insps Performed During Plant Second Refueling Outage in Oct 1989 ML18009A4941990-04-26026 April 1990 Forwards Radiological Environ Operating Rept,1989, Radiological Environ Operating Rept,Vol II,Jan-June 1989, Sample Analyses Data & Radiological Environ Operating Rept,Vol III,Jul-Dec 1989,Sample Analyses Data. ML18009A5031990-04-25025 April 1990 Submits Suppl 2 to Relief Request R2-001 Re Plant 10-yr Inservice Insp Plan,Per 880129 Request ML18009A4911990-04-24024 April 1990 Forwards Addl Info Re Proposed Wakesouth Regional Airport to Be Located Near Facility,Per 900411 Request.Info Previously Provided to NRC During 900320 & 23 Telcons ML18009A4841990-04-24024 April 1990 Forwards Corrected Bases marked-up Page to 900226 Tech Spec Change Request Re Surveillance Intervals ML18009A4251990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule Based on Guidelines Provided in NUMARC 87-00, Guidelines & Technical Bases for NUMARC Initiatives.... No Changes to Previous Calculations Necessary & One Deviation Noted ML18009A4231990-03-29029 March 1990 Suppls Response to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Actions:Surveys Performed to Determined Extent & Level of Contamination & Personnel Involved Decontaminated ML18009A4111990-03-23023 March 1990 Responds to NRC 900227 Ltr Re Violations Noted in Insp Rept 50-400/90-02.Corrective Actions:Personnel Involved W/ Quadrant Power Tilt Ratio Calculations & Operability Determination Counseled ML18009A4121990-03-23023 March 1990 Forwards Rev 17 to PLP-201, Emergency Plan & Fission Product Barrier Analysis.Rev to Emergency Plan Incorporates Comments Received During Recent Licensed Operator Requalification Training in Emergency Plan Procedures ML18009A4151990-03-22022 March 1990 Responds to NRC SALP Rept for Jul 1988 - Nov 1989.Contrary to Statement in Rept Significant Amount of Refresher Training Was Conducted During SALP Assessment Period Including Termination & Splicing & Motor & Bus Relays ML18009A4081990-03-19019 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-400/90-01.Corrective Actions:All Calibr Required by Tech Specs for Power Range Nuclear Instrumentation Satisfactorily Completed ML18022A7891990-03-0909 March 1990 Forwards Vols 1 & 2 of Inservice Insp Summary 1st Interval 1st Period,2nd Refueling Outage Completed 891222. ML18022A7881990-03-0606 March 1990 Confirms Understanding of Status of NRC Activities Re Proposed Wakesouth Regional Airport Located Near Plant Site. Pending Issues Should Be Resolved by 900331 to Enable Util to Complete Negotiations W/Airport Authority ML18022A7851990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-400/89-34.Corrective Actions:Valve SI-332 Closed & Gravity Drain Path Isolated & Shift Foreman Required to Review MMM-012 Re Priority/Emergency Maint Work Control ML18022A7721990-02-26026 February 1990 Forwards Application for Amend to License NPF-63,revising Tech Spec Surveillance 4.0.2 to Permit Surveillances to Be Extended Up to 25% of Specified Interval & Removing 3.25 Limitation from Spec,Per Generic Ltr 89-14 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML18022A7701990-02-14014 February 1990 Notifies of Issuance of Renewal of NPDES Permit for Plant. Permit Encl ML18009A3831990-02-0909 February 1990 Responds to 900112 Ltr Re Violation Noted in Insp Rept 50-400/89-35.Corrective Actions:Valves ICS-775 & ICS-776 Added to Inservice Insp Program for Back Seat & Full Flow Testing & ICS-525 Revised to Satisfy Tech Spec Requirements ML18009A3751990-02-0101 February 1990 Forwards Retyped Tech Spec Pages Re 890630 Application for Amend to License NPF-63 Concerning RCS Pressure Temp Limits ML18009A3701990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 IR 05000400/19890281990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 ML18009A3631990-01-26026 January 1990 Responds to NRC Bulletin 88-008, Thermal Stratification in Piping Connected to Rcs. Design Differences That Either Minimize Potential of Occurrence or Enhance Possibility of Detection Should Scenario Be Created at Plant Determined ML18009A3531990-01-25025 January 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Conducted in Oct 1989.Util Believes That Packing Leaks Discovered Are Isolated Failures & That Repair Should Prevent Recurrence ML18009A3501990-01-22022 January 1990 Forwards Revised Tech Spec Table 3.7-6, Area Temp Monitoring, Per 891218 Tech Spec Amend Request ML18022A7591990-01-17017 January 1990 Submits Results of Aircraft Hazards Study Associated W/ Proposed Wakesouth Regional Airport & Facility ML20005G5731990-01-16016 January 1990 Forwards Response to Insp Rept 50-400/89-32.Encl Withheld (Ref 10CFR73.21) ML18009A3351990-01-0505 January 1990 Forwards Rev 16 to Vol 1,Part 2 of Plant Operating Manual PLP-201, Emergency Plan. Revised NUREG-0654 Comparison W/ Plant Emergency Action Level Flow Path Also Encl for Review ML18009A3171989-12-21021 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-21.Corrective Actions:Incident Reviewed by Both Plant & Nuclear Engineering Dept Personnel to Avoid Future Miscommunication ML18009A3181989-12-15015 December 1989 Forwards Retyped Amend Bar Pages to Tech Spec Table 3.3-3 Re Auxiliary Feedwater Manual Initiation,Per 891026 Application for Amend to License NPF-63 ML18009A3011989-12-15015 December 1989 Forwards Proprietary WCAP-12403 & Nonproprietary WCAP-12404, LOFTTR2 Analysis for Steam Generator Tube Rupture W/Revised Operator Action Times for Shearon Harris Nuclear Power Plant. WCAP-12403 Withheld (Ref 10CFR2.790(b)(4)) ML18022A7371989-12-13013 December 1989 Forwards Change 3 to Rev 2 to State of Nc Emergency Response Plan in Support of Shearon Harris Nuclear Power Plant, Incorporating Administrative Enhancements. W/One Oversize Encl ML18009A2971989-12-0808 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Action:Min of Four Decontamination Personnel Will Be Assigned 24 H Per Day During Fuel/Cask Handling to Maintain Cleanliness in Fuel Handling Bldg ML18009A2841989-11-30030 November 1989 Forwards Rev 0 to Core Operating Limits Rept in Support of Cycle 3 Operations ML18005B1531989-11-27027 November 1989 Forwards Retyped Amend Bar Pages to 890630 Request for Rev to License NPF-63 Re RCS pressure-temp Limits ML18022A7311989-11-27027 November 1989 Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements. ML18005B1511989-11-17017 November 1989 Forwards 15-day Special Rept Identifying Number of Steam Generator Tubes Plugged During Current Inservice Insp Period ML18005B1501989-11-13013 November 1989 Suppls 890403 Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. Addl Nontraceable Molded Case Circuit Breakers (MCCB) & MCCBs Traceable to Refurbishers Noted During Records Review 1990-09-06
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REGULATOR NFORMATION DISTRIBUTION S EM (RIDS)ACCESSION, NBR: 8406?10361 DOG, DATE: 84/06/15 NOTARIZED:
NO, DOCKET FACIL:50"400 Shearon Harris Nucl'ear Power Planti Unit ii Carolina 05000400 AUTH.NAME A'UTHOR AFFILIATION
'IMMERM'AN~S
~R~, Carol ina Power L Light Co~RECIP~'NAME i RECIPIENT AFFILIATION, DENTONiH~RE Office of Nuclear Re'actor Regulation~
Director 1
SUBJECT:
Forwards addi info re SER Confi-rmatory Items 27 8 29 8 Ljcensing Condition 4 re filter sludge drawingsipolymer binding sys 8 processing filter sludgerrespectively
~DI'STRIBUTION CODE: 9001S COPIES RECEIVED:LTR
'NCL'SIZEr'ITLE: Licensing Submittal:
PSAR/FSAR Amdts 8 Related Cornespondence NOTES: RECIPIENT ID CODE/NAME~NRR/DL/ADL NRR LB3 LA INTERNAL!ELD/HDS1 IE/DEPER/EPB 36 IE'/DQAS IP/QAB21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/IIFEB40 NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DS I/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DS I/RSB 23 RGN2 EXTERNAL: ACRS 41 DMB/DSS (AMDTS)LPDR 03 NSIC 05 COPIES LTTR ENCL 1 0 1 0 0 3 3 1 1 1 1 2 2 1 1 1, 1 1 1 1 1 1 1 1 1 1 1 3 3 6 1 1 1 1 1 RECIPIENT ID CODE/NAME NRR LB3 BC BUCKLEYpB 01 IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17.NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DI/SSPB NRR/DS I/ASB NRR/DS I/CSB 09 NRR/DSI/METB 12 AB 22 R FILE 04 AMI/MI8 BNL(AMDTS ONLY)FEMA REP DIV'39 NRC PDR 02 NTIS COPIES LTTR ENCL, 1 0 1 1 1 1 1-1 0 1 1 2 2 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 0 1 1 1.1 1 1 1 TOTAL NUMBER, OF COPIES REQUIRED: I TTR.53 ENCL,'46 El l CSEE, Carolina Power&Light Company JUN 16>9S4 SERIAL: NLS-84-255 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.50-400 RESPONSE TO SAFETY EVALUATION REPORT ITEMS
Dear Mr.Denton:
Carolina Power 6 Light Company (CP&L)hereby submits additional information concerning the following Shearon Harris Nuclear Power Plant Safety Evaluation Report (SER)items.2)3)Confirmatory Item 27-WPS Drawings Concerning Filter Sludge Confirmatory Item 29-Description of Polymer Binding System'icensing Condition No.4-Processing of Filter Sludge This information is submitted in response to the items mentioned above from the Meteorology and Effluent Treatment System Branch.If you have further questions or require additional information, please feel free to contact me.Your very ly, S.R.Zimmerman Manager Nuclear Licensing Section ESS/pgp (217NLU)Attachments Mr.Wells Eddleman Mr.John D.Runkle Dr.Richard D.Wilson Mr.G.O.Bright (ASLB)Dr.J.H.Carpenter (ASLB)Mr.J.L.Kelley (ASLB)cc: Mr.B.C.Buckley (NRC)Mr.G.F.Maxwell (NRC-SHNPP)
Mr.Charles Willis (NRC-METB)
Mr.J.P.O'Reilly (NRC-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP)
Chapel Hill Public Library Wake County Public Library 8406210361 840bi5 PDR ADOCK 05000400 E PDR 411 Fayettevilte
'Street o P.O.Box 1551 o Raleigh.N.C.27602 Boo)l e~v'q Shearon Harris Nuclear Power Plant Safety Evaluation Report Confirmator Item No.27 Item The applicant has provided some general information on how the filter sludge will be handled.However, the material did not include drawings showing how the filter sludge from the following filters will be handled: o reactor coolant o seal water injection o seal water return o boric acid BRS recycle evaporator feed o BRS recycle evaporator concentrate o recycle evaporator condensate
~Res onse: The filter backwash system for the filters listed above and the interfaces with other radwaste systems are illustrated in FSAR Figures 11.4.2-5, 11.4.2-6, and 11.4.2-1 and Drawings CAR-2165G-829 and CAR-2165G-847.
A copy of the G-829 drawing is being sent to the reviewer, a copy of the G-847 drawing has been sent to the reviewer previously.
(217NLU/ccc)
, I$1 V I C f m t K' Shearon Harris Nuclear Power Plant Safety Evaluation Report Confirmator Item 29 Item The applicant has committed to provide details, as they become available, on the polymer binding system.~Res esse: As requested in SER Section 11.4.2, the following detailed description of the polymer binder system of the Solid Haste Processing System (SMPS)provides sufficient information for NRC review of system design and acceptability.
Pol mer/Dr Salt Solidification S stem The Polymer/Dry Salt Solidification System (P/DSSS)is designed to solidify the dry salt product generated in the Volume Reduction System (VRS)by application of a vinyl ester polymer product as a solidification agent.The polymer exists in a liquid state, and in combination with the promoter and catalyst, comprises the bulk of the three-element polymer solidification agent.The P/DSSS consists of the following subsystems;(a)Dry Product Storage and Transfer System, (b)Polymer Fill Station and Storage Tank;and (c)Polymer/Dry Salt Drumming Station (Flow Diagram CAR 2165-G-873).
A copy of this drawing has been provided to the reviewer.A.Dr Product Stora e and Transfer S stem The Dry Product Storage and Transfer System includes a small Isolation Hopper interfacing with the VRS, a large Product Storage Hopper and Gas/Solid separator, and a Fluidizing Turbine Air Blower Skid.1)The Isolation Hopper (IH)functions as a surge hopper to the VRS, a dry product staging point to allow for partial temperature decay and a redundantly controlled feeder/eductor that provides air pressure and moisture isolation between the VRS and the dry product storage hopper.Physical isolation and residence time at the bottom of the IH provides for additional temperature decay.Isolation between the VRS and P/DSSS is accomplished thru a combination of the IH that provides 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> reserve capacity for the VRS and a group of specifically designed valves that isolate system pressures.
The VRS will operate at about 7.5 to 12 psi while the P/DSSS operates at negative 100 inches of H20~is controlled by reciprocation of a metering piston that accepts material from the IH and transfers it thru a flow barrier and deposits it in a cooling chamber below the IH where it is cooled by fluidization.
Residence time of the material in the IH is approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, while residence time in the cooling chamber is approximately 8 minutes.At the end of this time, material is educted to the Storage Hopper.(217NLU/ccc)
~~P The IH will accept dry product from the VRS at an operating temperature of 900'F (maximum)as a flow rate of 10 to 20 lb/hr of fines and bed material.Six heaters are installed in the IH to maintain a processing temperature of 180'P (minimum).
Temperature is controlled automatically by a combination of a thermocouple and temperature indicator switch.When the IH reaches 180'P the heaters will shutdown and the hopper is ready to receive dry product from the VRS.Most of the heat carried by the dry product is transferred into the air surrounding the surge hopper by radiation and, convection.
The hot air is vented to the HVAC exhaust system (equipped with charcoal and HEPA Filters)to maintain temperature in the area at 104'P.The IH has three (3)level sensors.The Operating Level (OL)sensor works in conjunction with the OL switch to start transfer of dry product from the IH to the fluidizing chamber.The Intermediate Level (IL)sensor works in conjunction with the IL switch to cause an increase in flow rate of dry product from IH to fluidizing chamber.The High Level (HL)sensor works in conjunction with the switch to indicate that the dry product has backed up the IH to a point where it is almost at holding capacity and a shutdown of VRS system is imminent.Major components of the Product Storage Hopper (SH)are the product hopper, Packflushable filter cell and feeder/eductor system.The SH receives dry product from the IH at a temperature less than 180'P.Residence time in the SH is more than sufficient for the temperature to decay below the limits set by the pretested solidification formula.The feeder/eductor is computer controlled to provide uniform and predictable flow from the SH to the Gas/Solid Separator directly above the downcomer of the polymer drumming station.The feed of the product is controlled at the SH slot discharge by five independently driven pneumatic vibrators.
The redundant feed system assures that the SH can be completely emptied when service is required.Peed from the SH discharge falls into an air acceleration chamber beneath the feeders, which is piped to the Gas/Solid Separator above the drum process enclosure.
All air used during transfer of dry product and any residual particulate is returned to the SH via the backflushable filter mounted above it.The SH is the optimum location for air filtration because powder located anywhere in the pneumatic system including drumming station downcomer can be returned to storage at any time.The turbine air blower is the primary component of the dry product storage and transfer system.It provides transfer air for moving the dry product from the IH to the Gas/Solid Separator and SH, and from the storage hopper to the drumming station by virtue of the Gas/Solid Separator at the drumming station.The blower is also a component that provides return air from the Gas/Solid Separator to the filter above the SH, returning filtered air to the air stream supply (217NLU/ccc)
A heat exchanger is used to cool the air stream leaving the discharge of the turbine blower.Room air is drawn up thru the heat exchanger radiator to provide necessary cooling of the blower outlet air.The heat exchanger is mechanically connected to the plant HVAC System by ducting.The turbine blower load limit control valve IV-901 on the blower discharge side is used to prevent motor overload condition and is monitored by the blower load limit control.The system make-up air pressure regulator (PCV-510)will maintain system pressure at or above negative 100 inches of H20.When the system pressure drops below negative 100 inches of H20, the pressure regulator will open to allow instrument air pressure to enter the system,'and raise t'e pressure above the negative 100 inches of H20~The transfer system operates below atmospheric pressure and down to pressure approaching negative 3 1/2 psig, thus minimizing radioactive release from the system under both normal and upset conditions.
Dynamic seals, packing and rotating or translating penetrations are~totall absent from the radioactive portion of the system eliminating need for routine maintenance and/or replacement.
Since all penetrations are statically sealed, only catastrophic failure and a particulate release to the off gas systems need be considered.
The system supports two transfer modes: a)transfer from the IH to the SH and b)transfer from the SH to the Gas/Solid Separator above the drumming station.Only one transfer mode is used at a time.Both the IH and the SH are adequately instrumented to provide pressure, high level, low level, and temperature information to the process control computer.B.Pol mer Fill Station and Stora e Tank The Polymer Filling System performs a number of related functions:
inspection of drum and caps for structural integrity and proper thread line, long-term storage of large quantities of polymer chemicals under controlled conditions, insertion of the in-drum mixing device, application of specifically proportioned quantities of polymer to the drum, recording of drum tare weight and filled weight, drum sealing and assigning a number.The Polymer Fill Station (PFS)includes all the equipment necessary to actually transfer the waste solidification chemicals in specified proportions from the polymer storage tank into drums.The principal items of equipment include a 5100 gallon polymer storage tank, circulating pump and flow measurement, 6 gallon promoter tank and metering pump, heat exchanger with chiller, drum weighing scale and necessary sensors and valving for process control.Circulation of polymer must'ake place at regular intervals to maximize its storage life and prevent possible polymerization within the piping and monitoring equipment.
Recommended intervals of recirculation are: (a)for 10 minutes every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> the binder in the piping is recirculated, and (b)for 400 minutes every 2 weeks the entire contents of the storage tank is recirculated and sparged with air.The sparge air control system, (217NLU/ccc) activated by the programmable controller, is used to inject 60 scfh of 65 psi air into the binder during tank recirculation.
The air is introduced thru a 40 micrometer eductor element located in the binder return line.Recirculation is controlled automatically by timers in the programmable controller as long as the PFS remains powered in the standby mode.The circulating pump is also used to add polymer to the drum in the drum filling operational mode.The circulating pump is driven by a two-speed motor with high speed (875 rpm)employed during recirculation and low speed (430 rpm)for drum filling.A heat exchanger with chiller is installed in the return line to cool the recirculated polymer prior to its return to the storage tank.This prevents the temperature increase which is a normal result of the recirculating process and maintains the temperature of the binder in the storage tank within the 50 to 75'F range to maximize its storage life.The heat exchanger is a tube type unit sized for binder flow at a range of 1.5 to 3.0 gpm.Cooling is provided by chilled 42'F water at a flow rate of 1.5-3 gpm.The heat exchanger includes a temperature actuated control valve in the influent chilled water line, which opens the water supply on demand by the programmable controller.
The promoter metering pump assembly is used to apply promoter to the polymer in the polymer mixing mainfold at a ratio of 1 part promoter to 1000 parts of polymer.The pump is a positive displacement unit driven by rotary gear from the adjacent motor assembly.A magnetic pick-up is used to monitor pump rpm for the variable speed control.The speed control also receives a 4-20 ma signal from the binder flow indicator and based on these data, continuously adjusts motor rpm to deliver promoter at a fluctuating rate that remains in proportion to actual polymer flow.The ventilation equipment has the required 10 cfm at negative one inch of H 0 (minimum)service from the fill station areas non-radioactive 2.ventilation system to remove potentially dangerous styrene vapors from the polymer filling station.The equipment consists of an activated charcoal filter assembly and butterfly valve.A differential pressure switch is installed around the filter to indicate when it is in need of service.Although the primary device controlling the amount of polymer applied to each drum is the binder flow totalizer, a scale assembly has been included beneath the polymer filling station conveyor rollers to serve as a weight-activated back-up to end the drum fill cycle in case of the totalizer failure.(217NLU/ccc)
K a C.Pol mer/Dr Salt Drummin Station The solidifcation process is initiated at the PFS by filling a 55 gallon drum with a controlled amount of vinyl ester polymer.A controlled ratio of polymer and promoter are mixed at the time they are metered into the 55 gallon drum.At this time, the polymer feed is stopped, the in-drum mixer is precharged with stabilized catalyst and inserted into the top of the drum, the weight of the drum is recorded, the dxum is capped and a control number is applied to the drum head.All drum preparation and solidification agents filling operations are performed on the safe side of the shielded wall.The drum is prefilled with solidification agents and sealed.The drum is then conveyed by a conveyer to the drum pick-up point for removal by fixed bridge crane.The crane transfers the drum to the Polymer/Dry Salt Drumming Station.This completes the non-radiation-side chemistry process for the drumming operation.
The drum is positioned inside the drumming station to engage the mixer drive and to align the fill port.The drum is provided with a seal system at the fill hole as part of the in-drum mixer such that a dust seal is obtained when the drum is positioned against the fill nozzle.The drumming station enclosure and fill nozzle are pressure controlled in such a way as to produce a differential pressure across the drum/nozzle boundary to the extent that the seal system can be continually monitored during the filling process and the leakage of air, if any, will always be from the exterior toward the interior of the drum, thus preventing contamination of the drum exterior.At the drumming station, once the prefilled drum has been placed in the drum processing enclosure and the hatch closed, all subsequent operations, such as uncapping, filling/mixing, and recapping are performed automatically.
The drum position for capping is assured by a mechanical device which guides the cap flange into the proper position.When in position, the capper inserts the capper collet into the cap, expands the collet with sufficient force for the cap removal, reverses direction, and turns the cap out of the drum on the same helix as the threads in the cap.Dry salt/ash from the SH is fed at a controlled rate directly to the 55 gallon drum via the in-drum mixer which mixes the dry salt waste and the polymer until either the drum is determined to be full or the quantity of polymer is exhausted; the flow of dry salt waste materials is then automatically stopped.Process parameters including maximum mixing time is controlled by a micro processor.
Maximum mixing time is based on solidification formulas.Stabilization of the catalyst permits it to be in intimate proximity to the polymer for an indefinite time without catalysis.
The catalyst is dispersed into the binder/promoter mixture during the verification phase that takes place within the drum processing enclosure during the drumming process.The three-component binder works as a solidification agent by surrounding the waste stream and physically entrapping it after (217NLU/ccc) r~I polymerization.
Generally, there is no chemical reaction between the waste and the solidification agent as there is with cement and liquid waste.Once addition of the waste stream is complete, reaction of the solidification agent components proceeds by first gelling and finally becomming a solid block.The polymer waste solidification process is a cross-linking reaction, which is exothermic.
The exothermic reaction is not noticeable until the polymer waste mixture has gelled and begun to harden.Solidification is assured thru temperature monitoring.
The automatic drum capper is part of the drumming station and utilized for the capping and uncapping operations at the drumming station.Upon completion of the drumming process the drum is weighed, radiation levels are recorded prior to drum removal and the drum is then transferred remotely to the drum storage area, During the drum filling process, sufficient surge capacity is available in the XH for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of feed from the VRS.Polymer drumming time on the other hand, takes from 20 to 45 minutes.(217NLU/ccc)
P Shearon Harris Nuclear Power Plant Safety Evaluation Report License Condition No.4 Item Approval of the VRS is contingent on the applicant's agreeing not to process filter sludge in it.~Res esse: Filter sludges will not be processed through the volume reduction system (VRS).Instead, the processing path will be that the filter sludges are sent to the waste processing decanting tanks where the excess carrying water is.decanted and drained to the floor drain treatment system.The concentrated filter sludges will be transferred to the waste processing cement drumming stations where they will be solidified with cement in accordance with solidification procedures.
This has been previously discussed with the NRC staff reviewer and agreed upon.This item should be removed as a license condition.
(217NLU/ccc) tf f