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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20196E9541999-06-18018 June 1999 Forwards SG Tube Insp Conducted During Unit 1 End of Cycle 11 Refueling Outage.Attachments 1,2,3 & 4 Identify Tubes with Imperfections in SGs A,B,C & D,Respectively ML20195K4571999-06-14014 June 1999 Forwards MORs for May 1999 & Revised MORs for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20195J1691999-06-10010 June 1999 Forwards Written Documentation of Background & Technical Info Supporting Catawba Unit 1,notice of Enforcement Discretion Request Re TS 3.5.2 (ECCS-Operating),TS 3.7.12 (Auxiliary Bldg Filtered Ventilation Exhaust Sys) ML20217G5771999-06-0909 June 1999 Forwards Post Exam Comments & Supporting Reference Matls for Written Exams Administered at Catawba Nuclear Station on 990603 05000414/LER-1999-002, Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 9907081999-06-0303 June 1999 Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708 ML20207F2381999-06-0101 June 1999 Forwards Copy of Catawba Nuclear Station Units 1 & 2 1998 10CFR50.59 Rept, for NRC Files ML20195J1131999-05-26026 May 1999 Requests Approval to Change Cycle Dates for Two Year Requalification Training Program Required by 10CFR55.59,to Improve Scheduling of Requalification Exams to non-outage Periods 05000413/LER-1999-007, Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section1999-05-26026 May 1999 Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section ML20195B4751999-05-24024 May 1999 Forwards Rev 7 to UFSAR Chapter 2 & Chapter 3 from 1998 UFSAR for Catawba Nuclear Station.List of Instructions on Insertion Encl ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers 05000413/LER-1997-009, Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept1999-05-17017 May 1999 Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R1721999-05-13013 May 1999 Forwards Monthly Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 ML20206T0281999-05-12012 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual. Document Constitutes Chapter 16 of UFSAR 05000413/LER-1999-006, Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 9906071999-05-10010 May 1999 Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 990607 ML20206N8201999-05-10010 May 1999 Forwards Revs 15 & 16 to Catawba Unit 1 Cycle 12 COLR, Per TS 5.6.5.Rev 15 Updates Limits for New Catawba 1 Cycle 12 Reload Core & Rev 16 Revises Values Re Min Boron Concentrations for Rwst,Cla & SFP ML20206J4431999-05-0303 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e).Document Constitutes Chapter 16 of UFSAR ML20206D2141999-04-29029 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Catawba Nuclear Station,Units 1 & 2, Per Plant TS 5.6.3. Rept Contains Listed Documents ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5491990-09-14014 September 1990 Forwards Proprietary Response to Question Re Scope of Review of Topical Rept, Safety Analysis Physics Parameter & Multidimensional Reactor Transients Methodology, Per & 900723 Meeting.Response Withheld ML20059L5521990-09-14014 September 1990 Forwards Response to 18 Questions Re Topical Rept DPC-NE-2004,per NRC 900802 Request for Addl Info.Encl Withheld (Ref 10CFR2.790) ML20059K2021990-09-12012 September 1990 Submits Supplemental Response to Generic Ltr 89-14, Svc Water Sys Problems Affecting Safety-Related Equipment. Intake Structure Insp Program Developed.Procedures for Insp Implemented & Intake Structures Sampled & Analyzed ML20064A8041990-09-0505 September 1990 Notifies NRC of Mod to 890301 Response to Violations Noted in Insp Repts 50-413/86-18-01 & 50-414/86-18-01 Re Valves. All Valve Locking Mechanisms Would Be Installed by End of Unit 2 Refueling Outage (Approx Aug 1990) ML20064A5741990-09-0404 September 1990 Discusses Re Info to Support Util Position Relative to Resolving Issue of Main Steam Line Breaks Inside Ice Condenser Containments & Requests That Info Be Withheld (Ref 10CFR2.790) ML20059G3011990-09-0404 September 1990 Forwards Response to NRC 900327 Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20059G8321990-08-30030 August 1990 Withdraws 880726 Proposed Tech Spec Change,Clarifying Tech Spec 3/4.7.6 Re Emergency Power Requirements for Control Room Ventilation Sys ML20059D2011990-08-27027 August 1990 Forwards Piedmont Municipal Power Agency , Authorizing Use of Annual Rept for NRC Docket Requirements ML20059D2441990-08-24024 August 1990 Forwards Special Rept PIR-1-C90-0261 on 900725 Re Cathodic Protection Sys Failure to Pass Acceptance Criteria of 60-day Surveillance.Std Work Request Generated to Check Voltage Potential at Test Station TS-36 on Weekly Basis ML20056B4981990-08-22022 August 1990 Responds to NRC Request for Addl Info Re General Relief Request for Pump Vibration Submitted 900315.Relief Request Changed to Insure Data Taken Over Range That Encompasses All Main Potential Noise Contributors ML20056B5011990-08-22022 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-17 & 50-414/90-17.Corrective Actions:Review Will Be Conducted to Determine Category of Infrequently Run Procedures Needing Addl Verification Controls ML16259A2391990-08-22022 August 1990 Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo ML20056B4971990-08-20020 August 1990 Clarifies Info Submitted in 871207 & s Re Steam Generator Tube Rupture Analysis Demonstration Runs. Demonstration Runs Met plant-specific Requirements in Section D to NRC SER on WCAP-10698 ML20059C1201990-08-20020 August 1990 Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement ML20059B6581990-08-17017 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-15 & 50-414/90-15.Corrective Actions:Present Methods of Testing Operability of CO2 Fire Protection Sys Will Be Evaluated by 910201 to Determine If Addl Testing Necessary ML20059C1591990-08-17017 August 1990 Suppls by Providing Addl Info to Support Util Position Re Anl Confirmatory Analysis of Main Steamline Breaks in Ice Condenser Plants.Encl Withheld ML20063Q0951990-08-15015 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Catawba Nuclear Station Units 1 & 2 & Revised Rept for June 1990 ML20059C1231990-08-15015 August 1990 Advises That Util Submitting Special Rept Re Valid Failure of Diesel Generator 2B Would Be Delayed Until 880229 Had Incorrect Ltr Date.Date of Ltr Should Have Been 880204 Instead of 880104.Corrected Ltr Encl ML20063Q2671990-08-14014 August 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo ML20059C2211990-08-13013 August 1990 Forwards Revised Chapter 16, Selected Licensee Commitments Manual, to Plant Updated Fsar,Per 10CFR50.4 & 50.71.Manual Contains Commitments Which Require Control But Not Appropriate in Tech Specs ML20063Q0261990-08-10010 August 1990 Forwards Rev 0 to Catawba Unit 2 Cycle 4 Core Operating Limits Rept, Per Tech Spec 6.9.1.9 ML20063Q0671990-08-10010 August 1990 Submits Revised Response to Violations Noted in Insp Rept 50-413/90-09.Procedure to Verify Test Inputs Modified to Verify Dummy Input Signal to Channel RTD Circuit ML20058N0181990-08-0808 August 1990 Forwards Response to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20081E1601990-08-0101 August 1990 Advises of Completion of 900330 Commitment Re Standing Work Request for Insp of Air Flow Monitors & Dampers,Per Violations Noted in Insp Rept 50-413/90-03 & 50-414/90-03 ML20058P3261990-08-0101 August 1990 Forwards Public Version of Rev 26 to Station Directive 3.8.4, Onsite Emergency Organization ML20081E0951990-07-27027 July 1990 Forwards Decommissioning Financial Assurance Certification Rept for Duke Power Co,co-owner of Catawba Nuclear Station Units 1 & 2 ML20055H9741990-07-26026 July 1990 Forwards end-of-cycle 3 Steam Generator Insp Rept.Nineteen Tubes Removed from Svc by Plugging W/Rolled Mechanical Plug ML20055H5231990-07-24024 July 1990 Discusses co-licensee Relationship & Obligations Re Decommissioning Financial Assurance for Facilities ML20055H4571990-07-19019 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-11 & 50-414/90-11.Corrective actions:I-beams/ Hoists Rolled to Ends of Ice Condenser & Securely Located on Rails to Prevent Any Movement ML20055H1741990-07-18018 July 1990 Withdraws 880527 & 0725 Amends Clarifying Requirements for Containment Pressure Control Sys ML20055J3441990-07-17017 July 1990 Advises That Commitment Re Procedure IP/O/A/3190/01,per Violation in Insp Repts 50-413/90-06 & 50-414/90-06, Completed on 900619 ML20055H4131990-07-16016 July 1990 Forwards Public Version of Epips,Including RP/0/A/5000/07 & HP/0/B/1009/04 ML20055F8991990-07-13013 July 1990 Forwards Monthly Repts for June 1990 for Catawba Nuclear Station Units 1 & 2 & Operating Status Rept for May 1990 ML20055G2311990-07-13013 July 1990 Withdraws 880311 Proposed Amend to Tech Spec Table 3.3-3, Item 8.f Re Number of Instrumentation Channels Associated W/ Main Feedwater Pumps.Util Determined That Change Unnecessary ML20055F8461990-07-12012 July 1990 Requests 14-day Extension Until 900802 to Submit LER 414/90-010 to Investigate Power Supply Realignment ML20058P1231990-07-0707 July 1990 Advises That Commitment to Revise Maint Mgt Procedure 1.12 to Include Functional Verification Requirements & to Develop Retest Manual to Address Retest Requirements for Any Maint Performed on Components Completed on 900614 ML20055F4131990-07-0505 July 1990 Forwards Inservice Insp Rept Unit 1 Catawba 1990 Refueling Outage 4, Per 10CFR50.55(a)(q) & Tech Spec 4.0.5.Insp Performed Per Section XI of ASME Boiler & Pressure Vessel Code & Applicable Addenda ML20055D4291990-06-29029 June 1990 Supplemental Response to Violations Noted in Insp Repts 50-413/89-13 & 50-414/89-13,per .Personnel Responsible for Maintaining Crisis Mgt Ctr Drawing Trained. Util Will Continue to Evaluate Changes Made to Program ML20055E2191990-06-29029 June 1990 Submits Revised Commitment Dates Re Implementation of Dept Guidance on post-maint Testing,Per Commitment Made in 891002 Response to Violations in Insp Repts 50-413/89-19 & 50-414/89-19.Completion Date Changed to 900701 ML20044B0621990-06-26026 June 1990 Forwards Public Version of Revised EPIP HP/0/B/1009/05, Personnel/Vehicle Monitoring for Emergency Conditions. W/Dh Grimsley 900716 Release Memo ML20043H6921990-06-18018 June 1990 Advises of Revised Completion Date for VA Ductwork Cleaning to 901231,per Insp Repts 50-413/90-03 & 50-414/90-03. Vendor Personnel Assigned to Task Unavailable to Complete Cleaning Until Late 1990 Due to Outage Support Needs ML20043G1691990-06-15015 June 1990 Forwards Monthly Operating Repts for May 1990 for Catawba Nuclear Station,Units 1 & 2 & Corrected Monthly Operating Repts for Apr 1990 Re Personnel Exposure ML20055C8041990-06-15015 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-10 & 50-414/90-10.Corrective Actions:Instrument Root Valves Unisolated & Analog Channel Operational Tests for Low Temp Overpressure Protection Completed ML20043G4331990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.6.1.8 Re Lab Test of Carbon Samples from Annulus Ventilation Sys ML20043G3771990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.7.7 Which Required That Lab Test of Carbon Samples from Auxiliary Bldg Filtered Exhaust Sys Be Tested for Methyl Iodide Penetration of 0.71% ML20043G2511990-06-12012 June 1990 Withdraws 900419 Suppl to 871221 Application for Amends to Licenses NPF-35 & NPF-32 Re Tech Specs 4.7.6 Re Control Room Area Ventilation Surveillance Requirements ML20043G1741990-06-0707 June 1990 Responds to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire. Correct RCS Operating Pressure Would Be 2,250 Psia as Identified in Table 3-1 ML20043G3451990-06-0707 June 1990 Forwards Proprietary Response to Request for Addl Info Re Topical Rept BAW-10174, Mark-BW Reload Safety Analysis for Catawba & Mcguire. Response Withheld ML20043G0721990-06-0707 June 1990 Responds to NRC 900510 Ltr Re Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09.Corrective Actions:Vc/Yc Train a Returned to Svc W/Supply Power from 2ETA.Terminal Box 1TB0X0346 Inspected & Insured Operable ML20043F6111990-06-0606 June 1990 Advises That Response to Request for Addl Info Re Operator Response Times During Simulated Steam Generator Tube Rupture at Facility,Will Be Delayed Until 900630 1990-09-05
[Table view] |
Text
~
1 11 l e Duke 1%cer Company llu B hse
' PO Bat 31199 nce hesident Charlotte. N C 28242 Nac' rat hvJaaron (iV4)3?.1 till DUKEPOWER September 20, 1988 Document Cc,ntrol Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Catawba Nuclear Station Docket Nos. 50-413 and 50-414 Environmentil Protection Plan NPDES Permit Pursuant to the Catawba Nuclear Station Environmental Protection Plan and NPDES perait, please finds attached the Catawba 316(a) Demonstration. Additionally, please find attached correspondence between Duke Power Company and the South Carolina Department of Health and Environmental Control regarding a modification to the facility NPDES permit.
Very truly yours, fbtl0 W /pl H. B. Tucker Qiru JGT06.Dl/lcs Attachments xct (with attachment)
Dr. J. Nelson Grace Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 W. T. Orders NRC Resident Inspector Catawba Nuclear Station 8809290 POR ADO 880920
4 t
,e DUKE Powen COMPANY t PO BOX 33189 !
WILLI AM A. H ALLEA mean g
,s ' ' \
esmicas
- s. : :
w etagcgic ,
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July IS, 1968 ,
Ms. Nancy Weatherup Gauth Carolina Department of Health and Environmental Control Industrial and Agricultural Wastewate't Division l 2600 Bali Street
- Ce,1umbia, South Carolina 29201 i
SUBJECT:
Catawba Nuclear Station NPDES Permit Modificaticn File: CN-702.13
. Itegarding your letter dated May 31, 1998, we concur with your reconnendation l
to modify Catawba Nuclear Station's existing NPDES Permit to include
- effluent limits for Hydrazine and Ethylene Glycol. We have reviewed the
! draft modifications along with the suppcrting rationale which you provided.
4 f.isted below, please find our concents and suggestions as they pertain to
- the proposed modification. The changes we have suggested are aimed at structvring the permit language to, (1) assure that our discharge is effectively monitored so as not to 1.'gact receiving waters, and (2) provide
!, additional clarification for the requirements in the permit.
RATIONA.E l
Section 4.B.5. - There is a mistake in the calculation of the l
Daily Average Limit for Ethylene Glycol (outfall 002). The l correct vajue should be 11.9 mg/1.
ouTFALL 002
\
l A. Hydrazine l
We recorrend that the monitoring frequency for hydrazine be reduced to once/ occurrence.
l i
i L
Ms. Nancy Weatherup July 13, 1999 Fage Two B. Ethylene Glycol We recommend that the menitoring f requency for ethylene glycol to reduced to once/ occurrence.
Note: Justification for changing the monitoring f requency of this Outfsli to "once/ occurrence" is because the waste treatrent system is released on a catch oasis and is homogeneous prior to release. Once/ occurrence monitoring will te representative of the entire discharge, ouTTALL 004 A. Hydrazine We recommend that the nonitoring frequency for hydrazine be reduced to once/ occurrence.
B. Ethylene Clycol The presence of Ethylene Glycol in this system is expected to be very infrequent. We therefore recommend that there be no cpecific effluent limitations assigned to ethylene glycol for Outfall 004.
Instead, we suggest that similar language be used here as was use/
for the hydrazine (ies record results and if value is gre "
than 23.8 mg/1, then this permit may be modified to prc limitations on glycol). Furthermore, we suggest that monito frequency for ethylene glycol be reduced to once/ occurrence.
Scts: Justification for changing the monitoring for this Outf all to once/ occurrence is based on the f act tnat the Padwaste system discharge tank is homogeneous prior to discharge.
Once/ occurrence monitoring would be representative of the entAre discharge.
For convenience of understanding, we have attached copics of af fected pages of the NPCES permit incorporating our reco m.endations. Please note, for better clariflestion we have suggested that scee of the language f rem the Rationale be included in Part III (page 24 of 24) of the permit.
Attached also, for your review and approval, are the analytical procedures which we intend to use to comply with effluent Itmitations once they are finalized. The source from which these procedures were cetained, is referenced in Section 5.0 of each procedure.
I t
. l
l
! Ms. Nancy Weatherup 2 July 18, 1988 ,
t Page Three 1
) i i
We appreciat.e the opportunity to coment on this draft of the permit t
! nodification. Please review these corrents at your oorliest convenience. i Gnce you've had an opportunity to perform the review, we would like to meet l with you do diens the specifics of our coments in greater detail. In the k
) rean time, should you have any questions, please contact Mitch Griggs at
- 704-173-7080. Your attention to this matter is greatly apprec 4ted.
l 4
W !
il W. A. Italler, Manager l Nuclear Technical Services t 1
i NOG /28/rhm Attachment .,
4 4 xc; Al Williams, Catawba District I
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be. : T.B. Owen J.C. Lan8cha R.H Charest G.3. Rice S.W. Rogers R.M. Glover R.L. Painter R.R Wyue C.L. Therrien ti . B . Bea ron . J r .
S. Biswas R.E. Baker R.T. Wardoll Staff M.L. Dirch CN-3000.02-01 R.W. Eaker CN-3000.02-02 R.W. cuellette '
9'
M00!flCAi!ON DAIE
. Sureau of Water Pollution Control
_ DRAFI .
f E n
A. ffittillT LIrlifATIOf15 Afl3 MONIIORin RifKilRinitlIS DRA -
During II.c period beginning on the ef fective date asui lasting through the expiration date ti.e gerwittee is aut,horized to discharge from outfall(s) serial nued>cr(s)D02, wastewater treatment system dischar< ped take Wylie (Low volume wastes. chemical metal c1 caning Such discharge shall be limited and monitored by the permittee as specified below: wiste(#005).
Disciurge Limitations ebnitoring Requirements Effluent Characteristics Other Units (Specify)
- Picasurement Sample Daily Avg. Daily mm. Frequency Type O
o flow-m3 / day (ED) - -
1/ week flow Indicator 15 mg/l 20 mg/l 2/ month Grab Oli and Grease 30 mg/l 100 mg/I 2/ month Grab Total Suspended solids
.43 e5/l al/t.ccurrence Grab Ilydrarine -
!!. % /3 23.8m9/l at/occurreisce Grab
{ fthylene Glycol
- Measurement frequency is on.e per occurrence, but need not be more than twice per month.
The radiological cosgenents of this discharge is regulated by the United States llucicar Regulatory Commitsion (NRC 10 CTR 50 Appendix I) and is monitored and reported to the NRC. .
Based on a design flow of 3.4 MCD.
.: =
- '2';
,- , m.
- 7. Z Ihe pH shall not be less than 6.0 statutard units nor greater than 9.0 standard units and shall be g, *"
monitored: cace ger week by grab sample.
a3 i 5' There shall tie no discharge of floating solids or visitale foam in other than trace aocunts. q 3U Samples taken in compliance with the sumitoring requirements specified above shall be talien at the I'"*
gk d following location (s): dischar9e frue the wastewater treatment system prior to mining with any other waste streams.
O,*
u, E
N)DirICATION DME:
Bureau of W ter Pollution Control b
2 DRAF1-c.~
l~'. s, A. EfftDfHI tittlIATI0ftS Alto I:DillI0 RING Rti)tilRitifMIS During tiee peritw1 tscolonin9 on the effective date amt f asting thrteiil the capiration date ll.e pensittee is authorized to discharge from outfall(s) serial send.cr(s))D4: Rachsaste System Discharge Such discharge shall be limited and monitored by the permittee as siccified below:
Discharge Limitations Monitoring Requirements, Effluent Characteristics O other Units (Specify]
- Itasurement Sample Monthly Aves. Daily Max. Irequency lype U
I 15 mg/l 20 swj/1 t/ year Crab Oli and Grease Total Suspended Solids 30 mg/l 100 mg/l ./ year Grab
- 1/ quarter 30 Day Composite Boron
- **1/ occurrence laydrazine Grab
' *
- a*1/occurrence y Ethylene Glycol 4 _ _ .
E 1his disciurge is regulated by the United $tates MucIcar Regulatory Commission (NRC 10 CFR 50 Appendix I)
- - and is monitored and reported to the NRC. Ifowever, in the event that chmical metals cicaning wastes as defined a in 40 CfR Part 423 are discharged through this serial ammber, treatment shall be,provided to assure -
7 ttat discharges are in compilance with requirements of Part 423.13.
v
' Based on a Design of .140 MGD.
-- Q Samples taken in compilance with the monitoring requirements specified above shall be taken }7U at the following location (s): Wastewater treatment system prior to mixing with any other waste 'g#
$g
" stream. Boron shall be sangled from the radiological sample location. ~
" "'
- Measurement frequency is onc.- per occurrence. t>ut need not be more than twice per month.
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P47 ::'
. Page 24 of 24 Pemit No. SC000:273 y
JRAt U. A menitoring pregram will be imolemented to determine downstrean concentratiens of boren. A downstrean sarole shall be collected at the radiolcgical samole location and analyzed f or boren 'once per quarter. If there is no significant impact on water quality af ter 5 years of dsta collection, the menitorina requirement will be eliminated. ..
V. Monitoring of the rad waste discharge for oil and grease and total suspended solids will be implemented for one year. If shown that the above parameters are not in significant amounts in the rad wastewster tne monitoring requirement will be eliminated.
Duke will perfom a 316(a) study to assess any measurable therm.al effects on the biota of Lake Wylie. ine first year pre-operational W.
data was collected by a censultant, Industrial Biotest, Inc. Duke implemented the second yeaa of pre-ocerational data Collection in The operational impact. .
May, 1933 and will continue through May, 1984 assessment phase of the study will be similar to the secend year pre-operational phase with only minor changes made if the results indicate modificatiens are necessary. The plan and any significant change must be approved by CeDartrent of Health and Environmental Control. The o;erational phase will co rence when Unit I reaches Another second year of 50% power and will continue for one year.
data collection will be initiated when Unit 2 reaches 50% power.
A report will be subcitted to DHEC upon Co Dietion of each one-year operaticnal phase study.
X. The rad waste discharge vill be required to be monitored and1resultsPage 7 reported of the discharge concentration for Hydrazine (Part of 24). If values are greater than 15 mg/1, this permit may be modified to provide Hydrazine ilmitations and/or biological monitoring.
to Section 402 of the Clean Vater Reporting requirements, pursuantSection 102 of CERC1.A (Regulation 40 CTR Act (Regulation 40 CTR 117), for an 302), end Section 302 of SARA Title !!! (Regulation 40 CTR 355),
exceedence of the applicable reportable quantity for Hydrazine, will be initiated if the discharge concentration of Hydrazine exceeds 15.0 mg/1, and the reportable quantity has been exceeded.
Y. The radwaste discharge vill be required to be monitored and results!
reported of the discharge concentration for Ethylene Clycol (Part Page 7 of 24). If values are greater than 23.3 mg/1, this permit may be nodified to provide Ethylene Clycol limitations.
I
CP/0/3/0500/09 Revision 1 OLTI PobtR CCMPANY CATAh1A NYC!.ZAR STATION CXEM!STRY PROCEDull TOR TXE DETEMINAT!CN OF m RA2!NI IN VASTI WATER 1.0 DISCUSSION 1.1 Scope ,
This procedure desertbes the colorimetric method for the deterwination of hydratine in vaste water.
1.2 Principle Para dimethylasinobenzaldehyde produces a specif tc yellow reaction with hydrastaa se cheval 0
CH3 / ,
)
~
c.j +
O s,
+ ">"- >
FAS 2
G3 I
f3
\- OC '
= - =c O- +
3 C33 para dimethylaminobenzaldehyde azine (yellow)
Thr' intensity of the yellow color is proportional to the amount of hydrazine in the sample within the specified concentration range.
1.3 !.isits Sample concentration should be between 0.005 and 0.25 pre hydrazine. Higher concentrations suit be proportionally diluted prior to analysts. The lover liatt of detectable hydrazine is 0.005 ppe.
CP/0/3/4500/cg
, Page 2 of 5 Revision 1 1.4 Precision and Accuracy 1.4.1 The precision and accuracy of this method will be determined by Q Sua data.
1.4.2 A new calibration curve should be generated at least once a year.
1.5 Interferences 1.5.1 Hydraatne content say be dtaintshed by oxidizing agents.
1.5.2 Turbadity say cause high results. Ifturbidityisaprobles, filter the sample through a .45pe sembrane filter prior to analyzing.
1.5.3 Coloration in a sample say interfere with the quantitative determination of hydrazine.
1.6 Precautions 1.6.1 Labcoat, eye and hand protection shall be worn when .
worktes with para disethylaminobenzaldehyde or hydrochloric acid (HCL).
1.6.2 Hydrazine is a skin irritant and a potential skin sensitizer; therefore, precautions must be taken to avoid skin contact. Lab coat, hand and eye protection will be worn when working with hydrazine dihydrochloride and hydrazine containing solutions and samples. If skin contact occurs, wash the af fected area immediately with
. soap and water.
1.6.3 The light path surf aces of cuvettes should be buf fed with a lint free tissue such as "Xiavipes" prtor to being placed into the spectrophotometer.
1.6.4 If matched cuvettes are not available, correct the sample absorbance by subtracting the absorbance caused by the cuvette.
2.0 AFPARATUS. .
2.1 Spectrophotometer, with wavelength set at 458 na. Allow spectrophoto-seter to warm up for 30 minutes before use.
2.2 Erler.meyer flanks 2.3 Oraduated cylinder 2.4 Eppendorf pipets with required tips 2.5 Pipet dispenser 2.6 Balance 2.7 Two matched 1.0 ca cuvettes
CP/0/8/8500/09
. Page 3 of 5 Revision 1 3.0 RIACENTS 3.1 Hydrazine Stock Solution (100 pre) !
Dissolve 0.3280 2 0.0005 grass of hydrazine dihydrochloride (N H 2HC1) in a 1000 al volumetric flask with desineralized waker, . Add to 10.5 si of concentrated MC1, then dilute this solutton to volume with destneralized water and six. Shelf life is 6 sooths.
3.2 Hydrazine Reagent (PAB) i J Otssolve 16.0 1 0.1 grams para dimethylantacbenzaldehyde in 800 t to al of methyl alcohol and 80 1 0.5 el of concentrated MC1.
Store in an amber bottle. This solution is stable indefinitely.
3.3 Hydrochloric Acid Solution (1% V/V)
, In a volumetric flask, dilute 1010.5 al concentrated hcl to 1 liter u th desineralized water. This solution is stable indefinitely.
4 4.0 PROCEDt.'RE .
4.1 Generation of Calibration Curve 1 NOTE: Generation of a new calibration curve ts not required if I this procedure is in current use; however, a new l calibration curve should be generated at least once a year, ,
1 Two (2) .050 ppa Q sua standards should be run datly when !
ustog this procedure.
4.1.1 Prepare a series of hydrazine standards by diluting suitable volumes of hydrazine stock solution (Section 3.1) with 1% V/V hcl (Section 3.3) in 100 al volumetric flasks ;
! to produce solutions of the desired concentrations as !
! follows:
I i
j pl of 100 pro stock solution diluted to 100 s1 a pre N,H.
\ \
10 pl 0.010 pre l 25 pl 0.025 ppe l 50 pl 0.050 ppe r 100 pl 0.100 ppe l 250 pl 0.250 ppe
}
4.1.2 Transfer 50 al of each standard and a desineralized water .
blank into separate Erler.neyer flasks.
4.1.3 Ad!. 5.010.5 al of para disethylaminobenzaldehyde solution (
(Section 3.2) to each flash. MLa by swirling the flasks. f I.Jt the sixture stand 10 minutes, but not more than 100 minutes.
4.1.4 Adjust the spectrophotometer to the 458 na wavelength. l 4.1.5 Place the reagent blank in the spectrophotometer in a clean 1.0 ca cuvette. ,
CP/0/3/8500/09 Page 4 of 5
.- Revistoa 1 4.1.6 Set zero absorbance, s
4.1.7 Transfer the standards into the 1.0 ce cuvette la appropriate order and read the absorbance on the spectrophotometer checking the zero with the reagent blank before each seasurement. Standard concentration sessurements are to be made in order of increasing concentration. Rinse the cuvette with the subsequent sasple before each seasurement.
4.1.8 Prepare a calibration curve by plotting the absorbance vs -
concentration on a piece of graph p,qper. Indicate on the graph the date generated, analysts name, procedure number and spectrophotometer instrument number. This graph to particular to the instrument it was generated on.
4.2 Deterstaation of tlminown Concentrations cal TION: If the analysis is of a sample with turbidity and/or coloratton that might interfere with the analysis (RI., VC, and etc.), analyze a second portton of the saeple with no PAR added. Subtract ;he absorbance valve obtained from this sample with no PAR from the absorbance valve obtat'ned free the sample with PAB added.
4.2.1 Prepare two (2) .050 ppe standards for Q Sus by diluting 50 pl of the 100 pra hydrazine standard (Section 3.1) to 100 al with 1% hcl (Section 3.3) in a volumetric flask.
Measure 50 al of the .050 pps hydrazine standard into two (2) separate Erlenmeyer flasks. (To be done once per day when procedure is tn use.)
4.2.2 Transfer 50 si of each unknown sample and a desineralized water blant into separate Erlenmeyer flasks.
a.2.3 Add 5.0 g 0.5 al of para disethylasinobenzaldehyde solution (Section 3.2) to each flask. Mix by swirling the i
' flasks. 14t the etsture stand for 10 minutes, but not more than 100 minutes.
4.2.4 Adjust the spectrophotoneter to 458 nm. vavelength.
4.2*5 Place the reagent blank in the spectrophotometer in a 1.0 ca cuvette.
l 4.2.6 Set zero absorbance.
4.2.7 Transfer the unknown sample or standard into a 1.0 es cuvette. Read the absorbance.
4.2.8 Deterzine the hydrazine concentration of the sasple by comparing the sample absorbance to the calibration curve, l
1
) '
CP/0/8/4500/09 Page 5 of 5 l 4
Reviates 1 i l !
5.0 A8FIRDC88 l
I 5.1 American Society for Testing and Materials,1987 Annual look of j ASTM Standards, D 1385 86. Page 514 517.
i l 6.0 ENC LO$t.'RIS None l
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'v CHIMISTRY PROCEDURE TOR THE DETERMINATION OF ETHYLENE GLYCOL CP/0/B/8500/29 1.0 DI S CL'S S ICN 1.1 Scope This procedure descrtbes the colorimetric determination of Ethylene Glycol in small concentrations. **
1.2 Principle Ethylene Glycol is reacted with Sodium meta Periedate to yield fo rmaldehyde :
H0CH 2 CH 0H + NaI0s
- 2CH 0 + Na!0 3+H 0 The formaldehyde is than determined colorimetrically.
1.3 Limits
/x This method is applicable to samples having a concentration of 1 to
('- j 7500 ppe. Samples containing hister concentrations must be diluted accordingly.
1.4 Precision and Accuracy Precision and Accuracy will be determined by Q-Sua data.
1.5 Interferences 1.5.1 Some waters purified by too exchange techniques cannot be used because of the presence of minute particles of resin that might react to form f ormaldehyde. Demineralized water has not been found to cause this problem and should be used for this analysis.
1.5.2 Turbid saeples will interfere. All samples shall be
.- filtered before analysis.
1.6 Precautions 1.6.1 Eye protection, gloves and labcoat should be worn when performing analysis.
1.6.2 Concentrated Sulfuric Acid is very corrosive. Extreme care should be exercised when working wtth this chemical.
Tollow precautions given in CP/0/B/8300/09.
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. CP/0/3/8500/29 Page 2 of 5 2.0 6[l&R.AR
\ 2.1 Spectrophotometer 2.2 1.0 ce cuvettes 2.3 Ippendorfs - 200, 400, 600, 800 and 1000 pt 2.4 Pipets - 10 al disposable 2.5 Automatic dispensers - 2a1 .
2.6 Glass stoppered graduated cylinders 50 and 100 al 2.7 Volumetric flasks 50, 200 and 1000 31 2.8 Clamp or holder for Nitrogen cylinder 2.9 Bubbling Apparatus 2.10 ...trogen Regulator 2.11 Analytical Balance 3.0 REAGENTS O 3.1 Sodius Chronotropate (Sodium 1. 8 dihydrory - napthalene disulfonate) CgeH 70 S
3, 6 -
3,2 Concentrated Sulfuric Acid (N:$0e) 3.3 Sodium sulfite (Na 50 3) 5.5%
Dissolve 11.0 1 .5 grams of Sodius Sulfite (Na:Sos ) into a 200 al volumetric flask, dilute to volume with dominera11:ed water and mix. Shelf life is one week.
3.4 Sodium meta Periodate (Na!0.) 0.1:t Dissolve 21.0 2.5 grams of sodium meta-Periodate (Na!0.) into a 1000 al volursetric flask, dilute to volume with desineralized water and six. Shelf life is six sonths.
3.5 Ethylene Glycol (HOC 1:rCH 0li) Stock Solution (100 pra)
Dissolve $00 2 .005 g of Ethylene Glycol into a 50 al volumetric flask, dilute to volume with desineralized water and six. Pipet 10 als of this solution and transfer it to a 1000 mi volumetric flask, dilute to volume with desineralized water and six. This solution should be made daily.
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- CP/0/3/8500/29 Page 3 of 5 3.5 Desineralized Water 3.7 Nitrogen 4.0 Procedure 4.1 Generation of Standard Curve Generation of a standard curve is not requireal if method is currently in use; however, a new standard curve should be generated at least once a yeat. Two (2) 1.0 ppa Q Sua standards should be run daily . (
when procedure is in use. -
l 4.1.1 Prepare a series of standards by diluting suitable volumes of Ethylene Clycol solu'. ton to 20 als with desineralized water in a 100 ml glass stoppered graduated cylinder.
Include a graduated cylinder with 20 als of desineralized water to be used as a blank, Mis of Ethylene Glycol Solution Concentration
.2 1.0 ppe 1
.4 2.0 ppe
.8 4.0 ppe 1.2 6.0 ppa O 1.6 2.0 8.0 ppa 10.0 ppa 4.1.2 Dispense 2.0 1 .1 al of Sodium meta Periodate solution into each 100 al glass stoppered graduate, stopper and six.
Allow to react for 15 minutes at room temperature. l 4.1.3 Dispense 2.0 t .1 al of Sodium Sulfite solution to each graduate, dilute to volume, stopper and mix.
, 4.1.4 Pipet 10.0 mis of each of the above dilutions into 50 31
, glass stoppered graduates.
6 4.1.5 Add approximately 0.06 aus of Sodium Chronotropate to each graduate and dissolve.
4.1.6 CAtTTIONt Extreme care should be taken when handling acids.
Add 10 als of concentrated Sulfuric Acid by riesas of a pipet and allow the normal heat rise to occur.
4.1.7 By means of the bubbling apparatus immersed in the solution, bubble vigorously with Nitrogen for 10 minutes. Allow the contents of each graduate to cool to room temperature.
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- CP/0/B/8500/39 Pa8e 4 of 5 1.8 Adjust the spectrophotometer to a wavelength of 570 na.
. 4.1.9 Place the blank in the spectrophotometer in a cleas 1.0 ce cuvette.
I 4.1.10 Set the "zero" absorbance.
i 4.1.11 Read the absorbance of the standards, in order of increasing concentration. Rinse the cuvette with each
. subsequent standard before each measurement. Recheck "zero" absorbance with the blank before each standard.
4.1.12 Prepare a standard curve by plotting absorbance vj ppa Ethylene Glycol.
4.2 Detertnination of Unknown Concentrations 4.2.1 Prepare two (2) 1.0 ppe standards for Q-Sua by diluting
.2 mis of Ethylene Glycol solution to 20 mis with deminer-alized water in a 100 ml glass stoppered graduated cylinder.
(To be done once per day when procedure is in use).
4.2.2 Into a glass stoppered graduated cylinder introduce the amount of sample indicated in the table below, diluting to 20 mis with desineralized water, if necessary.
Concentration, ppm Sample Size, mis 1-35 20.0 35-75 10.0 75-150 5.0 150-750 1.0 750-7500 0.1 Fc,r f.orcentrations of Ethylene Glycol greater than 7500 ppa
(.757) use a ruitable dilution of the sample in demineralized water. Include one graduated cylinder containing 20 ml of demineralized water for a blank.
4.2.3 Dispense 2.0 t 1 al of 0.1 M Sodium meta-Periodate solution 1 each graduate, stopper and mix, allow to react
... for 15 a.u ttes room temperature.
4.2.4 Dispense 2.0 t .1 mis of Sodium Sulfite solution to each graduate, dilute to the 100 ml mark with demineralized
! water, stopper and mix.
l 4.2.5 Pipet 10 mis of each unknown sample or standard into a 50 31 glass stoppered graduated cylinder.
l 4.2.6 Add approximately .06 gas of Sodium Chromotropate to each i graduate and dissolve.
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4.2.7 CaJTION
Extreme care should be taken when handling acid. l C',] Add 10 mis of concentrated Sulfuric Acid by means of a pipet and allow the normal heat rise to occur.
4.2.8 By means of the bubbling apparatus immersed in the solution, bubble vigorously with Nitrogen for 10 minutes. Allow the contents of each graduata to cool to room temperature.
4.2.9 Adjust spectrophotometer to a wavelength of $70 nm.
4.2.10 Placetheblankinaclean1.0cmcuveIte.
4.2.11 Set the "zero" absorbance.
4.2.12 Read the absorbance of the standards, in order of increasing concentration. Rinse the cuvette with each subsequent sample before each measurement . Recheck "zero" absorbance with the blank before each sample, 4.2.13 Determine the Ethylene Glycol concentration by comparing '
the sample absorbance to the standard curve. -
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5.0 REFERENCES
g- 5.1 Union Carbide, Technical S wice Bulletin - Ethylene Glycol, Colorimetric Determination cf Low '.oncentrations by the Sodium Periodate Procedure.
6.0 ENCLOSURES 1 .
6.1 Bubbling Apparatus 4
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