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Category:CORRESPONDENCE-LETTERS
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 ML20217G1191999-10-0808 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Brunswick NPP & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next Five Months ML20217C6931999-10-0606 October 1999 Forwards Insp Repts 50-324/99-06 & 50-325/99-06 on 990801- 0911 at Brunswick Reactor Facility.No Violations Were Identified BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl ML20211K9001999-08-27027 August 1999 Forwards Insp Repts 50-324/99-05 & 50-325/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl ML20210S9061999-08-11011 August 1999 Informs That GE Document Entitled, Addl Info Regarding 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant ML20210S9121999-08-11011 August 1999 Informs That Document NEDC-31624P,Suppl 2,Rev 6,entitled, Loss-Of-Coolant Accident Analysis Rept for Brunswick Steam Electric Plant Unit 2,Reload 13,Cycle 14 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) ML20210P8221999-08-11011 August 1999 Advises That Info Contained in Which Submitted Document,Prepared by Siemens Power Corp,EMF-2168(P) Rev 0, Marked Proprietary,Will Be Withheld from Public Disclosure, Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20210P9381999-08-10010 August 1999 Forwards SE Accepting Licensee & Suppls & 0517,which Submitted Assessment of Impact on Operation of Unit 1 with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P8911999-08-10010 August 1999 Forwards SE Authorizing Relief Requests CIP-01,02,06,07,08, 09,10,11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Requests CIP-04 & 05 Would Result in Hardship,Relief CIP-03 Not Required & CIP-11 Denied in Part BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 ML20210Q4581999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section to Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit List of Individuals to Take exam,30 Days Before Exam Date ML20210P2031999-08-0505 August 1999 Discusses Staff Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity for Plant,Units 1 & 2 ML20210N2041999-08-0505 August 1999 Forwards SE Accepting Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46, & Suppl 1 BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld ML20210G2941999-07-28028 July 1999 Discusses Public Meeting Conducted on 990720 to Present Results of Periodic Plant Performance Review for Brunswick Facility for Period of May 1997 to January 1999.List of Attendees Encl BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR ML20210E1181999-07-19019 July 1999 Forwards Insp Repts 50-324/99-04 & 50-325/99-04 on 990509- 0619.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl ML20196H8191999-06-21021 June 1999 Informs That on 980915,Commission Suspended SALP Program for an Interim Period Until NRC Completes Review of Process for Assessing Performance at NPPs ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20196A8111999-06-14014 June 1999 Ack Receipt of 990401 Response to NRC Ltr Issued on 990302 Re OI Investigation to Determine Whether Former BSEP Manager Threatened to Fire Employees Who Brought Safety Concerns to Nrc.Concluded That No Violation Occurred ML20195J1971999-06-14014 June 1999 Advises That GE-NE-523-B13-01920-56,Rev 1,submitted with 990202 Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 1999-09-08
[Table view] Category:EXTERNAL CORRESPONDENCE
MONTHYEARML20204J1261999-02-10010 February 1999 Provides Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel.Matl Will Be Shipped from Southport,Nc & Received at New Hill,Nc ML20204H6431999-01-13013 January 1999 Submits Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel from Southport,Nc to New Hill,Nc ML20198C2951998-12-0202 December 1998 Submits Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Cp&L.Harris Nuclear Plant Scheduled to Receive Radioactive Matl in IF-300 Series Shipping Cask. Info Designated as Safeguards Not Encl ML20154K3271998-08-13013 August 1998 Provides Notification of Shipment of Irradiated Nuclear Reactor Fuel by Cp&L.Shipment Will Consist of Radioactive Material Contained in IF-300 Series Shipping Casks to New Hill,Nc.Attachment Withheld ML20236V9051998-07-16016 July 1998 Provides Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel in IF-300 Series Shipping Casks,Id Number USA/9001/B()F,s/n,IF-303 & S/N IF/304 to New Hill,Nc ML20217C0141998-03-26026 March 1998 Provides Notification of Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Cp&L.Shipments Consists of radio- Active Matl in IF-300 Series Shipping Casks.Shipment from Southport,Nc to New Hill,Nc ML20217N7951998-03-0505 March 1998 Provides Notification of Upcoming Shipment of Irradiated Nuclear Reactor Fuel by Cp&L.Shipment Will Consist of Radioactive Matl in IF-300 Series Shipping Casks ML20217J4001998-02-21021 February 1998 Submits Advance Notification of Upcoming Shipment of Radioactive Matl in IF-300 Series Shipping Cask (S):Cask Id USA/9001/B()F;s/n IF-303,s/n IF/304 to New Hill,Nc ML20203E4451998-02-0505 February 1998 Submits Notification of Upcoming Shipment of Radioactive Matl in IF-300 Series Shipping Cask from Southport,Nc to New Hill,Nc.Info Designated as Safeguards Info & Shall Be Protected IAW Provisions of 10CFR73.21 ML20202G1461998-01-0909 January 1998 Provides Info on Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Cp&L.Shipment Consists of Radioactive Matl in IF-300 Series Shipping Casks,Cask Id No USA/9001/B()F,s/n IF-303,s/n IF/304 to Harris Nuclear Plant ML20202D4981997-12-0202 December 1997 Provides Info Concerning Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Cp&L.Radioactive Matl in IF-300 Series Shipping Cask,Cask Id No USA/9001/B()F;s/n IF-303, S/N IF/304 ML20113F2811996-05-28028 May 1996 Submits Advance Notification of Shipment of Irradiated Nuclear Reactor Fuel,In Accordance w/10CFR73.37 ML20117K8231996-05-0202 May 1996 Submits Notification of Upcoming Shipment of Radioactive Matl in IF-300 Series Shipping Cask from Southport,Nc to New Hill,Nc ML20108E4371996-04-12012 April 1996 Submits Info Re Forthcoming Shipment of Radioactive Matl in IF-300 Series Shipping Casks to New Hill,Nc,Iaw 10CFR73.37 ML20101D0761996-03-12012 March 1996 Notification of Forthcoming Shipment of Irradiated Nuclear Reactor Fuel in IF-300 Series Shipping Casks from Southport, Nc to New Hill,Nc ML20095A3821995-11-17017 November 1995 Provides Info Re Shipment of Irradiated Nuclear Reactor Fuel by Util ML20094D6851995-10-27027 October 1995 Submits Advance Notification of Shipment of Irradiated Nuclear Reactor Fuel,In Accordance w/10CFR73.37 ML20098C3151995-09-25025 September 1995 Informs of Upcoming Shipment of Irradiated Nuclear Reactor Fuel from Brunswick Nuclear Project to Harris Nuclear Project in State of Nc.Nuclear Fuel to Be Shipped in IF-300 Type Cask by Rail BSEP-95-0344, Forwards Corrected Effluent & Waste Disposal Annual Rept for 1993 Suppl Info. Info Will Be Published in NUREG/CR-29071995-07-19019 July 1995 Forwards Corrected Effluent & Waste Disposal Annual Rept for 1993 Suppl Info. Info Will Be Published in NUREG/CR-2907 ML20087K7631995-07-0505 July 1995 Forwards Safeguards Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel,In Accordance w/10CFR73.37. W/O Encl ML20085J2711995-06-0707 June 1995 Submits Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Util in Accordance w/10CFR73.37.Safeguards Info Withheld ML20082N0381995-03-0909 March 1995 Submits Info Re Forthcoming Shipment of Radioactive Matl in IF-300 Series Shipping Cask by Util IAW 10CFR73.37 ML20078S2581995-02-13013 February 1995 Submits Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel to New Hill,Nc by Util,In Accordance w/10CFR73.37 ML20078B8311995-01-20020 January 1995 Informs of Upcoming Shipment of Irradiated Nuclear Fuel from Brunswick Nuclear Project to Harris Nuclear Project in State of Nc.Nuclear Fuel to Be Shipped in IF-303 & IF-304 Type Casks by Rail ML20079A3411994-12-19019 December 1994 Informs of Shipment of Solid Irradiated Nuclear Reactor Fuel in IF-303 & IF-304 Series Shipping Casks,From Brunswick Nuclear Project to Harris Nuclear Project ML20079A4041994-12-0909 December 1994 Provides Info Re Shipment of Irradiated Nuclear Reactor Fuel by Util,To Harris Nuclear Project ML20078N0511994-11-22022 November 1994 Provides Listed Info Concerning Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by License in Accordance w/10CFR73.37 ML20024J5321994-10-11011 October 1994 Submits Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Util ML20072U2041994-09-13013 September 1994 Provides Listed Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Util ML20073C4541994-08-19019 August 1994 Provides Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Util ML20071L1111994-07-22022 July 1994 Provides Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by CP&L ML20071L0871994-06-29029 June 1994 Provides Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by CP&L ML20045A7701992-10-23023 October 1992 Recommends That Util Close This Dangerous Plant & Explore Many Alternate Sources of Energy That Are Both Safe & Cost Efficient ML20094M7291992-03-30030 March 1992 Submits Results of Review of BNL Summary Data Re Radioactive Effluents Released by Facilities for 1990.All Vols Reported Were After Compaction When Solid Waste Shipped to Licensed Waste Processor for Vol Reduction ML20062D4191990-11-0505 November 1990 Advises That Util Decided Not to Request Hearing on Complaint Leading to DOL 901029 Determination in Cited Case ML20059A2241990-08-15015 August 1990 Forwards Corrected Effluent & Waste Disposal Annual Rept for 1988. Util Understands That Summary Data Will Be Used for Inclusion in BNL Rept of Radioactive Effluents Released from Commercial Nuclear Power Plants During 1988 ML20044A2171990-06-19019 June 1990 Advises That Three Addl Structures of Historical or Architectural Importance Located in General Area of Project. All Three Sites Listed in Natl Register of Historic Places ML20043D9291990-06-0101 June 1990 Informs That BNL Summary Data Re Radioactive Effluents for Third & Fourth Quarters 1988 Reviewed,Per 900405 Request. No Changes Necessary.All Vols Reported Were After Compaction ML19324B8051989-09-28028 September 1989 Forwards NPDES Wastewater Monitoring Repts for Listed Facilities ML20205C9071988-10-17017 October 1988 Verifies Accuracy of Draft Data for Summary of Radioactive Effluents Released During 1987.Corrections Listed ML20150A7271988-03-0909 March 1988 Forwards Corrected Effluent & Waste Disposal Annual Rept for 1986, Per 880205 Request.Corrections Listed ML20238D5771987-09-0909 September 1987 Forwards marked-up BNL Draft Effluent & Waste Disposal Annual Rept for Yr 1985..., Per 870810 Request.Corrections Re Kr-85m Activity for Ground Level Releases Noted ML20197H5211986-05-0606 May 1986 Requests That Cp&L/Power Agency Reach Agreement W/O Delay. Util Prepared to Eliminate Joint Ownership in Roxboro 4, Reduce Ownership Interest in Licenses DPR-62 & DPR-71 & Propose Sliding Scale Adjustments 1999-02-10
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.O CP&L Carolina Power & Light Company P.O. Box 10429 Southport, NC 28461-0429 July 19,1995 SERIAL: BSEP 95-0344 Ms. Joyce L. Tichler Brookhaven National Laboratory Analytical Sciences Division Building 490D P.O. Box 5000 Upton, NY 11973 BRUNSWICK STEAM ELECTRIC PL ANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 REVIEW OF RADIOACTIVE EFFLUEiF ' .. EASES FOR 1993
Dear Ms. Tichler:
As requested by your letter dated April 3,1995, Carolia Power & Light Company has reviewed Brookhaven National Laboratory's (BNL) summary data of radioactive effluents released by the Brunswick Steam Electric Pant, Units 1 and 2 during 1993. Carolina Power & Light Company understands that this data is being used in a summary of radioactive effluents released from commercial nuclear power plants during 1993 and will eventually be published in NUREGICR-2907. Corrections and/or comments to the draft data are indicated by hand-written notes on the enclosed copy (Pages 2 and 28).
Please refer any questions regarding this submittal to Mr. Grant Raker at (910) 457-2664.
Sincerely, kV 6 . D. Hicks Manager-Regulatory Affairs Brunswick Nuclear Plant WRM/wrm Enclosure cc: NRC Document Control Desk Mr. S. D. Ebneter, Regional Administrator, Region 11 Mr. D. C. Trimble, NRR Project Manager - Brunswick Units 1 and 2 Mr. C. A. Patterson, NRC Senior Resident inspector - Brunswick Units 1 and 2 Mr. S. Klementowicz (USNRC)
The Honorable H. Wells, Chairman - North Carolina Utilities Commission t
9507250009 931231 '
PDR ADOCK 05000324 k R PDR
n e ENCLOSURE BPUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 OPERATING LICENSES DPR-71 AND DPR42 REVIEW OF RADIOACTIVE EFFLUENT RELEASES FOR 1993 l
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Printid: 3/6/95 lastelletten: Brunswick Lecetten: 20 Mi S Wilmington, NC Effluent and Waste Disposal Annual Report for 1993 Supplemental Information Unit Number 1 Type BWR Licensee Carolina Power & Light Decket No. 50 325 Licensed Power (MVT) 2.44E+03 Thermal Power (MVH) 0.00E+00 Net Electrical Power (NYH) 0.00E+00 ,
Commercia10peretten 03/18/77 laittel Criticellig 10/08/76 j Coeling Water Source Cape Fear River !
Unit Number 2 Type BWR Licensee Carolina Power & Light Decket No. 50 324 Licensed Power (MYT) 2.44 E+ 03 i Thermal Power (MYH) 1.28 E+ 07 Net Electrical Power (MVH) 3.98E+06 f Commercial Operation 11/03/75 initial Criticallty 03/20/75 l Coeling Water Source Cape Fear River l
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Printed: 10/25/94 lastelletten: Brunswick Location: 20 Mi S Wilmington, NC Unit Member: 1 &2 Effluent and Waste Disposal Annual Report for 1993 Supplemental Information Measurements and Approximations of Total Radioectivity Fission and Activetten Geses Analysis for specific radionuclides in representative grab samples ^^" --"' '- '" 7 spectroscopy by gamma l
i N/A = Not Applicable Page No. 2 N/D = Not Detectable
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Printed: 10/25/94 lastellation: Brunswick Locaties: 20 Mi S Wilmington, NC Unit Number: 1 & 2 Effluent and Waste Disposal Annual Report for 1993 Supplemental Information Heesusesments and Approxisnellens of Tetel Radioactivity !
l lodines Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy i
N/A = Not Applicable rege me. 3 N/D = Not Detectable h
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Printed: 10/25/94 lastelletten: Brunswick Lacetten: 20 Mi S Wilmington, NC Unit Number: 1 & 2 Effluent and Waste Disposal Annual Report for 1993 Supplemental Information Heesurennents and Approximettens of Total Radioactivity Particulates Analysis for specific radionuclides collected on filter papers by gamma spectroscopy -'
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N/A = Not Applicable p ,, no, 4 N/D = Not Detectable 1
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Printed: 10/25/94 lastelletten: Brunswick Location: 20 Mi S Wilmington, NC Unit Nasaber: 182-Effluent and Waste Disposal Annual Report for 1993 Supplemental Information ,
Measurements and Approximations of Total Radioactivity ;
Liquid Effluents Analysis for specific radionuclides by individual releases and composite sample by gamma spectroscopy a
N/A = Not Applicable Page No. 5 N/D = Not Detectable >
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Printed: 10/25/94 lastellation: Brunswick Location: 20 Mi S Wilmington, NC Unit Number: 1 &2 Effluent and Waste Disposal Annual Report for 1993 Supplemental information First Six Second Six Batch Releases Months Months A. Liquid
- 1. Number of Betch Releases - 229 227
- 2. Total Time Perled for Betch Releases (min) - 2.40 E+ 04 2.29 E+04
- 3. Maximum Time Period for a Betch Release (min) . 1.77 E+ 02 1.6 5 E+02
- 4. Average Time Period for Betch Releases (min) - 1.05E+02 1.01 E +02
- 5. Minimum Time Perled for e Batch release (min) - 8.00E+00 1.40 E+01
- 6. Average Stream Flev During Periods of Release of Effluent inte a rioving Stream (Its/ min) . 2.06 E + 06 2.27E+06 N/A = Not Applicable Page No. 6 N/D = Not Detectable i
', I Printed: 10/25/94 lastelletten: Brunswick Location: 20 Mi S Wilmington, NC -
unit nomeer: 1&2 Effluent and Waste Disposal Annual Report for 1993 Gaseous Effluents - Summation of All Releases Est Total Quarter Quarter Error 5 A. Fission and Activation Geses
- 1. Total Release cl N/D 9.70 E+ 01 4.50 E+01
- 2. Average Release Rate for Period act/sec N/D 1.23 E+ 01
- 3. Percent of Techalcol Specificetten Limit 3 0.00E+00 1.96E 02 B. ledines !
- 1. Tetel lodine - 131 et N/D 8.27E-05 3.50E+01
- 2. Average Release Rete for Period act/sec N/D 1.05E 05
- 3. Percent of Techalcel Specification Limit g I C. Particulates
- 1. Particulates with Half-Lives > 8 Dogs Cg 4.36E-04 1.68E-03 3.50E+01 2.. Average Release Rete for Period acl/sec 5.61E-05 2.14E 04
- 3. Percent of Technical Specification Limit 5
- 4. Cross Alphe Radioectivity ci 1.02E 05 7.67E 06 ,
D. Tritium
- 1. Total Release c 1.08E 01 1.65E+00 3.00 E+01
- 2. Average Release Rate for Period uct/sec 1.3 9 E-02 2.10 E-01
- 3. Percent of Technical Specification Limit 5 N/A = Not Applicable p.,, g , y N/D = Not Detectable
~__ . _ . - --- - -. -
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Printed: 12/7/94 lastellation: Brunswick Lecetten: 20 Mi S Wilmington, NC Unit Number: 1&2 Effluent and Weste Disposal Annual Report for 1993 Gaseous Effluents - Summation of All Releases Est Total Quarter Quarter Error %
A. Fission and Activation Geses
- 1. Total Release cl 1.38E+02 1.06E+02 4.50E+ 01
- 2. Average Release Rete for Period uct/sec 1.74 E+ 01 1.3 3 E+01
- 3. Percent of Technical Specificellen Limit X 3.62E-02 2.16E-02 l B. ledines l
- 1. Total ledine - 131 C1 1.37E-04 1.08 E-04 3.50E+01 1
- 2. Average Release Rete for Period uct/sec 1.72 E-05 1.3 6 E-05 l
- 3. Percent of Techalcel Specificellen Limit g '
C. Particulates 'l
- 1. Particulates with Half-Lives > 8 Dogs Ci 7.24 E-04 4.73 E-03 3.50E+01
- 2. Average Release Rate for Period sci /sec 9.52E-05 5.99 E-04
- 3. Percent of Technical Specificetten Limit E
- 4. Gross Alphe Radleectivity C1 1.17E-05 7.46 E-06 D. Tritium
- 1. Total Release cg 4.80E+00 1.34 E +01 3.00E+01
- 2. Average Release Rate for Period uct/sec 6.03 E-01 1.69E+00
- 3. Percent of Technical Specification Limit E Note: Since LA-140 has a half-life < 8 days it was not included in this sumation.
N/A = Not Applicable p ,, No. 8 N/D - Not Detectable ;
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Printed: 10/25/94 lastelletten: Brunswick Lacetten: 20 Mi S Wilmington, NC Unit Number: 1&2 Effluent and Waste Disposal Annual Report for 1993 Gaseous Effluents - Elevated Release Fission Geses Unit Continuous Mode Batch Mode Nuclide Released Cl Quarter Quarter Quarter Quarter 1 2 1 2 KR-85M 4.64 E+00 KR-87 1.46E+01 KR-88 1.09E+01 XE 133 2.81 E 01 XE 135M 7.93 E+00 XE 135 2.14 E+01 XE 138 4.71 E + 00 l
N/A = Not Applicable pi,,, n , o N/D = Not Detectable l
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Printed: 10/25/94 lastellation: Brunswick Lecetten: 20 Mi S Wilmington, NC unit Non.ber: 1&2 Ef fluent and Waste Disposal Annual Report for 1993 Gaseous Effluents - Elevated Release ledines Unit Continuous Nede Batch Nede l Nuclide Released ci Quarter Quarter Quarter Quarter 1 2 1 2 1131 8.27 E-05 1133 5.08 E-04 ;
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l N/A = Not Applicable Page No.10 N/D = Not Detectable
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O Printed: 10/25/94 laste11etten: Brunswick - Lacetten: 20 Mi S Wilmington, NC ,
unit Number: 1&2 Effluent and Waste Disposal Annual Report for 1993 Gaseous Effluents - Elevated Release Porticulates Unit Continuous Mode Betch Mode Nucilde Released Ci Quarter Quarter Quarter Quarter 1 2 1 2 CO-60 3.33 E-06 2.04 E-06 SR-89 2.24 E-05 SR-90 2.43E-07 CS 137 1.54 E-06 BA-140 1.83 E-06 H3 6.14 E-02 1.22E+00 N/A = Not Apphcable page no.11 N/D = Not Detectable l
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Printed: 10/25/94 T
lastelletten: Brunswick Location: 20 Mi S Wilmington, NC unit Nesnber: 1&2 :
Effluent and Waste Disposal Annual Report for 1993 Gaseous Effluents - Elevated Release fission Geses Unit Continuous Mode Batch Mode Nuclide Released Ci Quarter Quarter Quarter Quarter 3 4 3 4 KR 85M 5.09E+00 6.04E+00 KR 87 2.02E+ 01 1.55E+01 i KR 88 1.74 E+01 1.62 E+01 XE 133 6.87 E-01 XE 135 2.51 E+01 2.26E+01 XE 135M 1.11 E+01 6.64 E+00 XE-138 3.10E+01 1.72E+01 N/A = Not Applicable Page No.12 N/D = Not Detectable l
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e Printed: 10/25/94 lastellation: Brunswick Location: 20 Lii S Wilmington, NC +
unit Member: 1&2 Effluent and Weste Disposal Annual Report for 1993 Gaseous Effluents - Elevated Release !
ledines Unit Continuous Mode Betch Mode ;
Nuclide Released Ci Quarter Quarter Quarter Quarter 3 4 3 4 j I131 't .3 5 E-04 1,08 E-04 t.133 E.93E-04 6.37E 04 l
N/A = Not Applicable pg.n,13 i
N/D = Not Detectable l
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Printed: 12/7/94 Installation: Brunswick Location: 20 Mi S Wilmington, NC Unit Number: 1&2 Effluent and Weste Disposal Annual Report for 1993 Gaseous Effluents - Elevated Release Particulates Unit Continuous Nede Batch Mode Nuclide Released ct Quarter Quarter Quarter Quarter 3 4 3 4 CO-60 5.20E-06 1.93E-04 SR 89 2.20E-05 4.81 E-05 SR 90 3.85E-07 1.39E-06 CS-13 7 6.50E-06 6.60E-04 BA-140 3.69E-05 5.96E-05 LA-140 3.33E-05 2.6 5E-05 H-3 4.08E+00 1.14E+01 N/A = Not Applicable pa,, no.14 tuD - Not Detectable l
. s, et Printed: 10/25/94 lastellation: Brunswick Location: 20 Mi S Wilmington, NC Unit Number: 1&2 Effluent and Waste Disposal Annual Report for 1993 Gaseous Effluents - Ground Release Fission Gases tinit Continuous Mode Batch Mode Nuclide Released Ci Quarter Quarter Quarter Quarter 1 2 1 2 XE 133 4.04 E +00 XE 135M 3.64 E+00 X E-135 2.50E+01 N/A = Not Applicable pag, No.15 N/D = Not Detectable
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O Printed: 10/25/94 lastellation: Brunswick Location: 20 Mi S Wilmington, NC Unit pomber: 1 & 2 Effluent and Weste Disposal Annual Report for 1993 Gaseous Effluents - Ground Release ledimos Unit Continuous Mode Betch Mode Nuclide Released CI Quarter Quarter Quarter Quarter 1 2 1 2 r
1-131 8.52 E-08 1133 9.08E-07 N/A = Not Applicable Page me.1 s N/D = Not Detectable l
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Printed: 10/25/94 Installation: Brunswick Location: 20 Mi S Wilmington, NC unit Nosaber: 1 &2 Effluent und Waste Disposal Annual Report for 1993 Gaseous Effluents - Ground Release Particulates Unit Continuous Mode Batch Mode Nec11de Released Ci Quarter Quarter Quarter Quarter ,
1 2 1 2 MN 54 4.38 E-05 1.60E-04 CO-60 3.55 E-04 1.49 E-03 SR-89 1.07 E-06 SR-90 4.28E-07 2.24 E-07 CS 137 2.48E-05 2.67E-07 AM 241 8.56E-06 H3 5.69 E-02 4.24 E-01 l
N/A = Not Applicable p.g, n.,17 .
N/D = Not Detectable !
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e Printed: 10/25/94 lastelletten: Brunswick Location: 20 Mi S Wilmington, NC Unit phunber: 1&2 Effluent and Weste Disposal Annual Report for 1993 Gaseous Effluents - Ground Release Fission Geses Unit Continuous Nede Batch Mode I
NucIlde Released Ci Quarter Quarter Quarter Quarter .
3 4 3 4 KR-85M 3.23 E-01 6.45E 01 XE 135 2.43E+01 1.58 E+01 XE 135M 3.56E+00 4.52 E+00 N/A = Not Applicable Page No.18 N/D = Not Detectable i
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Printed: 10/25/94 lastellation: Brunswick Location: 20 Mi S Wilmington, NC Unit Number: 1 &2 Effluent and Waste Disposal Annual Report for 1993 i Gaseous Effluents - Ground Release lodines Unit Continuous Mode Batch Mode Nac11de Released ct Quarter Quarter Quarter Quarter 3 4 3 4 1-131 2.12 E-06 9.36E-08 ,
I l133 6.07E-05 2.21 E-05 1
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N/A = Not Applicable p.,, no 1 g l
N/D = Not Detectable i
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e Printed: 10/25/94 i
instelletten: Brunswick Locettom: 20 Mi S Wilmington, NC Unit Number: 1 & 2 ;
Effluent and Waste Disposal Annual Report f or 1993 Gaseous Effluents - Ground Release Porticalatee Unit Continsees Mode Betch Mode Nw11de Released ct Quarter Quarter Quarter Quarter 3 4 3 4 CR 51 1.62 E-04 8.14 E-04 MN 54 2.31 E-05 2.51 E-05 !
CO-58 1.47 E-05 4.65E-05 ,
0 0-60 4.44E 04 2.88 E-03 SR-89 2.63E-06 2.44 E-06 ,
CS-137 2.80E-06 2.00 E-06 AM-241 2.84 E-06 H-3 7.18E-01 1.95E+00 N/A = Not Applicable p.,, No. 2 0 N/D = Not Detectable
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Printed: 10/25/94 laste11stion: Brunswick Location: 20 Mi S Wilmington, NC ,
Unit Number:1&2 Effluent and Weste Disposal Annual Report for 1993 Liquid Effluents - Summation of All Releases Est Total Overter Quarter ErrerE 1 2 l A. Tission and Activetten Products Unit
- 1. Total Release (Not including Tritium, Geses, Alphe) Ci 9.90E 03 1.91 E-02 4.00E+01 j
- 2. Average Diluted Concentration During Period act/mi 5.00E 10 6.45E 10
- 3. Percent of Applicable Limit 3 2.58E 02 4.78E 02 B. Tritium ,
- 1. Total Release cg 3.43 E +00 5.80E+00 4.50 E + 01
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- 2. Averege Diluted Concentration During Period sci /ml 1.73 E-07 1.96E 07
- 3. Percent of Appilceble Limit 3 1.73E-02 1.96 E-02 ;
C. Dissolved and Entrained Geses
- 1. ' fetal Release Cg N/D 1.50E-03 4.00E+01
- 2. Avereipe Diluted Concentration During Period act/ml N/D 5.07E 11
- 3. Percent of Applicable Limit 3 0.00 E +00 2.54E 05 D. Gross Alphe Rediesetivity
- 1. Total Release et N/D N/D 4.00 E + 01 E. Veleme of Weste Released (Prior to Dilution) liters 5.92E+06 8.53E+06 1.50 E + 01 F. Volume of Dilution Water Used During Period liters 1.98 E+ 10 2.96 E + 10 1.30 E + 01 N/A = Not Applicable Page No. 21 N/D = Not Detectable
Printed: 10/25/94 laste11etion: Brunswick Location: 20 Mi S Wilmington, NC Unit Number:1&2 Effluent and Waste Disposal Annual Report for 1993 Liquid Effluents - Summation of All Releases Est Total Quarter Quarter ErrorX 8 4 A. Fission and Activation Products Unit
- 1. Total Release (Not including Tritium, Geses, Alpha) ci 2.59E 02 4.94E 02 4.00 E+ 01
- 2. Average Diluted Concentratten During Period act/mi 1.10 E-09 1.74 E-09
- 3. Percent of Applicable Limit g 5.89E-02 6.42E 02
- 5. Tritium
- 1. Total Release ~
cg 1,09 E + 01 2.71 E+01 4.50E+01
- 2. Averege Diluted Concentration During Period sci /m1 4.61E-07 9.56E-07
- 3. Percent of Applicable Limit g 4.61 E-02 9.56E 02 C. Dissolved and Entrained Geses
- 1. Total , Release c1 2.21 E-03 3.30 E-03 4.00 E + 01
- 2. Average D11sted Concentration During Period sci /mi 9.36E 11 1.16 E-10
- 3. Percent of Applicable Limit 5 4.68E-05 5.80E-05 D. Gross Alphe Red'oectivity
- 1. Tet=1 Release et N/D N/D 4.00E+01 E. Veleme of Weste Released (Prior to Dilution) liters 6.40E+06 7.13 E +06 1.50 E + 01 F. Yelume of Dilution Water Used During Period liters 2.36 E+ 10 2.83 E + 10 1.30 E+ 01 N/A = Not Applicable Page No. 2 2 N/D = Not Detectable j i
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o Prin;ed: 10/25/94 I
lastelletten: Brunswick Locaties: 20 Mi S Wilmington, NC 1 Unit Number:1&2 Effluent and Waste Disposal Annual Report for 1993 Liquid Effluents Unit Continuous Mode Batch Mode Nuclide Released ct Quarter Quarter Quarter Quarter 1 2 1 2 MN-54 6.60E-04 3.68 E-04 1.14 E-03 ;
FE-55 7.83E-03 1.81 E-02 CO-60 NB 95 4.73 E-06 1.76 E-06 ;
CS 134 1.11 E-04 CS 137 2.69E-04 5.40E-04 XE 133 2.03 E-04 XE-135 1.30 E-03 N/A = Not Applicable Pagefla.23 N/D = Not Detectable ,
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4 Printed: 10/25/94 lastelletten: Brunswick Location: 20 Mi S Wilmington, NC Unit Number: 1&2 Effluent and Waste Disposal Annual Report for 1993 Liquid Effluents Unit Continuous Mode ~ Batch Mode Nuclide Reisesed Cl Quarter Quarter Quarter Quarter 3 4 3 4 NA-24 5.80E 06 CR-51 4.05E-04 1.97 E-02 MN 54 2.29E-04 8.54 E-04 FE-55 2.51 E-03 MN-56 7.99 E-04 CO-58 1.32 E-03 CO-60 2.19 E-02 2.44 E-02 AS 76 4.47E-05 1.22 E-04 SR 92 6.22 E-06 TC-99M 6.97E-04 AG 110M 2.83 E-05 S0-125 1.77 E-04 1131 1,18 E-06 l133 3.54E-07 CS-134 1.53 E-04 2.92E-05 N/A = Not Applicable Page fle. 2 4 N/D = Not Detectable i
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Printed: 10/25/94 lastellation: Brunswick Location: 20 Mi S Wilmington, NC Dalt Number:1&2 Effluent and Weste Disposal Annual Report for 1993 Liquid Effluents Unit continuous Nede Batch Nede r Nuclide Released Ci Quarter Quarter - Quarter Quarter 3 4 3 4 CS-137 6.42 E-04 2.65 E-04 5 BA 140 4.28 E-06 CE 144 2.20E-05 W 187 1.06 E-03 KR-85M 4.23 E-06 XE 133 3.80E-04 6.80E 04 !
XE-135M 1.36 E-05 XE 135 1.83E-03 2.61 E-03 i
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i N/A = Not Applicable p.,, No. 2 5 N/D = Not Detectable
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Printed: 10/25/94 lastellation: Brunswick Location: 20 Mi S Wilmington, NC -
Unit Number: 1&2 Effluent and Waste Disposal Annual Report for 1993 Solid Waste and Irradiated Fuel Shipments i
Solid Weste Shipped Offsite for Buriel er Disposal (not irradiated feel)
Type of Weste Unit Est T*tal First Six Monthe Description Error 15 A. Spent Resins, Filter Sledges, m3 5.89E+00 Evaporator Bottoms, etc. m3 C1 2.53 E +00 1.00E+01 B. Dry Compressible Weste, m3 1.31 E + 02 Centaminated Egelpment, etc. m3 C1 1.14 E + 01 1.00E+01 C. Irred!sted Compnents, Centrol m3 Reds, etc. m3 C1 D. Other (describe) m3 m3 Ci Fill in a brief description for each waste volume (Ex. conpacted, non-conpacted, burial volume, incineration).
N/A = Not Applicable Page No. 2 6 N/D = Not Detectable
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Printed: 10/25/94 t
lastellation: Brunswick Location: 20 Mi S Wilmington. NC Unit Number: 182 ,
Effluent and Waste Disposal Annual Report for 1993 Solid Waste and irradiated Fuel Shipments Solid Weste Shipped Offsite for Burlel er Disposal (not irradiated fuel)
Type of Weste U st Est Total Second Six Months Description Error 15 A. Spent Resias, Filter Sludges, m3 1.08E+02 ~
Evaporator Bottoms, etc. m3 C1 1.05 E +03 1.00 E+ 01 B. Dry Compressible Weste, m3 1.16E + 02 Contaminated Equipment, etc. m3 C1 4.32E+00 1.00E+01 C. Irrediated Components, Centrol m3 3.11 E + 01 ,
Reds, etc. m3 l Cl 1.03E+03 1.00 E + 01 l D. Other (describe) m3 m3 Ci "
Fill in a brief description for each waste volume (Ex. cor:pacted, non-corppacted, burial volume, incineration).
N/A = Not Applicable Page No. 2 7 i N/D = Not Detectable j l
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Printed: 10/25/94 lastellation: Brunswick Location: 20 Mi S Wilmington, NC Unit Musaber:1&2 Effluent and Waste Disposal Annual Report for 1993 Solid Weste and irradiated Fuel Shipments First Six Months Estisnete of Mejor Nec11de Compositten gg Neclide Estimate, E CR-51 2.46E+00 MN-54 6.72E+00 FE-55 .LaaE.ee. M,(,0 El CO-58 1.11E+00 CO-60 3.73E+01 N163 1,19E+00 CS-137 2.49E+00 N/A = Not Applicable Pge No. 2 8 N/D = Not Detectable .,
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Printed: 10/25/94
' lastelletten: Brunswick Locetten: 20 Mi S Wilmington, NC i Unit Numiser: 1&2 Effluent and Weste Disposal Annual Report for 1993 Solid Weste and irradiated Fuel Shipments First Six Months Estimate of HeJer Nuclide Compositten Nacilde Estimate, 5 bd MN 54 6.12E+00 .
FE-55 6.57E+01 CO 58 3.17E+00 CO-60 2.19E+01 NI-63 1.69E+00 1
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N/A = Not Applicable Page No. 2 9 N/D = Not Detectable l
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Printed: 10/25/94 l Instellation: Brunswick Location: 20 Mi S Wilmington, NC Unit Number:1&2 -)
Effluent and Waste Disposal Annual Report for 1993 ;
Solid Waste and Irradiated Fuel Shipments First Six Months j Solid Wette Dispositten Number of Shipments Mode of Transportetten Destination =
44 Sole use CNS!, Barnwell, SC 1
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Irrediated fuel Shipments (Disposition)
Number of Shipments Nede of Transportetten Destinetten 2 Ralicar CP&USHNPP l
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N/A = Not Applicable Page No. 3 0 N/D = Not Detectable I
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Printed: 10/25/94 lastelletlen: Brunswick Location: 20 Mi S Wilmington, NC timit Number: 1&2 Effluent and Waste Disposal Annual Report for 1993 Solid Weste and Irradiated Fuel Shipments Second Six Months Estimate of Major Nuclide Compositten gg Nuclide Estimete, 5 FE-55 6.46E+01 CO-60 2.37E+01 NI63 1.08E+00 CS-137 1.15E+00 N/A = Not Applicable Page No. 31 N/D = Not Detectable i
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- . , l Printed: 10/25/94 5 l
laste11etten: Brunswick Lecellen: 20 Mi S Wilmington, NC l Unit Number: 1&2 j
Effluent and Waste Disposal Annual Report for 1993 l
Solid Weste and Irradiated Fuel Shipments Second Six Months '
Estimate of Mejor Nuclide Compositten gg Nacilde Estimate, X FE-55 4.91 E+01 CO-60 4.36 E+ 01 NI-63 2.25E+00 1
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N/A = Not Applicable Page No. 3 2 N/D = Not Detectable i
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i Printed: 10/25/94 lastellation: Brunswick Location: 20 Mi S Wilmington, NC Unit Number: 1&2 Effluent and Waste Disposal Annual Report for 1993 Solid Weste and Irradiated Fuel Shipments Second Six Months
. Estimate of Mejor Nuclide Compostilon ;
y,g NucIlde Estimate,15 FE-55 3.15E+01 CO-60 6.57E+01 >
NI63 2.83E+00 e
r N/A = Not Applicable Page No. 3 3 N/D = Not Detectable i
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e Printed: 10/25/94 lastellation: Brunswick Location: 20 Mi S Wilmington, NC Unit Number:1&2 )
Effluent and Weste Disposal Annual Report for 1993 3
Solid Weste and Irradiated Fuel Shipments ;
i Second Six Months '
Solid Weste Dispositten Number of Shipments Mode of Transportetten Destination 60 Sole use CNSI, Bamwell. SC i
Irradiated I' vel Shipments (Disposition) >
Number of Shipments Mode of Transportetten Destination 8 Ralicar CP&USHNPP l
N/A = Not Applicable pg,g,,34 i N/D = Not Detectable e
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