|
---|
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
. . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _
o e DUKE POWER GOMPANY P.O. HO X 3 3180 CHAMLOTTE, N.C. 28242 HAL H. TUCKER retrenoxz wwa ,mesimust (704) 373-4831
.mu. , November 11, 1983 Mr. Ilarold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief
-Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
On September 30, 1983 representatives from Duke Power Company and the NRC Staff met at the NRC's office in Bethesda, Maryland to discuss two items identified by the Power Systems Branch in the Catawba Safety Evaluation Report.
Open Item 15 - Emergency Lighting Duke agreed to provide a listing of plant locations that had emergency lighting. This information is provided in the attached revision to FSAR Section 9.5.3.
License Condition 18 - Internal Corrosion Protection for Fuel Oil Storage Tanks The following is a summary of ths discussion on this issue.
-System Description The~ diesel-fuel-Gil system at Catarba includes four 45,000 gal, storage tanks per unit or.2 tanks per diesel. Tie tanks are fabricated from 3/8 inch nominal thickness carbon steel which inc1r. des a 1/32 inch corrosion allowance. Each tank is approximately 12 feet in diameter and buried under approximately 5 feet of backfill and'a concrete pad. The Unit 1 fuel oil tanks were coated with motor oil following sand blasting and were filled with fuel oil in March 1980.
A recirculation and purification system takes suction from the flush mounted sample connection on the bottom of the tank and discharges the fuel oil at a rate of 25 gpm through a simplex filter (25 micron particle removal rating).
The supply lines to the day tank are connected by an outlet raised 6 inches
~
above the bottom of the tank.
Statement of Disagreement The Staff's impocition of License Condition 18 apparently derives from NUREG-0800, Section 9.5.4, Acceptance Criteria 4.F. which incorporates the recommendations of ANSI N195. The Staff's reliance on ANSI N195 was discussed in Duke's letter
\
8311220432 831111 y PDR ADOCK 05000413 l E PDR ,
c-L Mr..Har:1d R. Denton, DirGctor November 11, 1983 Page 2-
~
of-June 1, 1983. The ANS Committee that wrote this standard unanimously agreed that an internal corrosion allowance met the requirements of Section 7.5.
Therefore, ANSI N195 is not an appropriate basis for requiring an internal tank coating.
- In Section'9.5.4.2 of the SER the Staff presents a number of arguments in rejecting Duke's. position. Each of these will be addressed.
-Tank Volume The SER consistently misrepresents the tank volume as 90,000 gallons. As
- - previously discussed each diesel has two 45,000 gallon tanks. 'Therefore, comparisons between the FSAR and SER are exaggerated bacause of the'SER's misstatement of tank volume.
- Tank Corrosion The Staff' disagrees _with Duke's position that the fuel oil will act as a deterrent-to internal corrosion and further speculates that the upper portion of the tanks will be exposed to a " harsh environment" and prone to corrosion.
Contrary _to the Staff's conclusions, an inspection of Tank.1B1 on July 8, 1983 revealed;that there had been no general corrosion of the tank, not even in the upper portion, since the tanks were installed in winter 1979/80 and filled in
' March 1980.
Condensation
- Duke and the Staff disagreed on the volume of water that would condense in the e fuel oil storage tanks. It was-agreed'that'the actual quantity of water condensed did not. matter since condensation and impurities would be drained off the bottom of the tanks via'the recirculation and purification system.
' Previous' Experience
' Duke has had extensive experience with buried fuel oil storage tanks as shown
, on the: attached list. Tanks at two locations have been in the ground for over 40 years.
In-the 238 tank-years of operating experience represented by these nine plants, no problems have been experienced.
Coating Reliability
'In taking a position that the Catawba fuel oil storage tanks should be coated, the Staff has: failed'to address the: issue of the reliability of a coating. applied to a tank that has held oil.
p m
CD
J Mr. Harold ~R. Denton, Director November 11,'1983
- Page 3 Coatings vendors contacted by Duke indicated that the tanks could be emptied, cleaned, sand blasted and coated; however, contamination by the previousiv contained fuel oil'could lead to delamination of the coating.
Filling of Tanks The Staff requested additional information on Duke's plans for maintaining
' the' fuel oil tanks nearly' full. In accordance with the Technical Specifications the tanks will be maintained greater than approximately 90% full. Furthermore, it will be a' normal practice to order additional fuel oil whenever there is sufficient capacity in the tanks to accept a full tanker truck load.
It should be pointed out that fuel oil could:not be added to both half-capacity tanks serving the same diesel. As discussed in FSAR Section 9.5.4.3 in response to question 430.66, the contents of a fuel oil tank are allowed to settle for at least.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior.to realigning the tank to its respective diesel. Therefore, all tanks could not be " topped off" at the same time.
Conclusion-It is Duke's position that--
-1) General internal corrosion has not occurred and will be minimised during
-the lifetime of the plant due to a combination of design featutte 2nd operating features including:-
a) Periodic (quarterly) drainage of water accumulation
-b) Use'of:high quality fuel (water and sediment content less than 0.05% volume) c) Keeping the fuel oil tanks nearly full in accordance with Technical-Specifications
-d)
Periodic (10 year) tank cleaning
- 2) . Extensive experience with buried fuel oil tanks has identified no problems with' uncoated tanks.
Based on the information provided at the September 30, 1983 meeting and in this letter, it is requested that the two SER items discussed above be closed out-in a future Supplement to the Catawba SER.
- Very truly yours, -,
C alk <c "
Hal B.. Tucker
-ROS/php
= Attachment t y yr 1- w g p m t-* g- ta y - gr v7yr w Ngy v +v+r q='ee 'y -e+-4 s -"
Mr. Harald R. Dent:n, Dirictor '
November 11, 1983 Page 4 cc: Mr. James P. O'Reilly, Regional Administrator .-
U. S. Nuclear Regulatory Commission Region Il
~101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.
Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412
. Palmetto Alliance 2135 Devine Street Columbia, South Carolina 29205'
- Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 9
i f
s w
d' y.% - p .m.,eg-+ -
.-4 .. --y-.--,-W= , . -*
-9 y,-, -p -- ~w- +,- ,-+
Buried Fuel Oil Tanks on Duke System
- Plant In Service
- Cliffside 1940 Buck 1941 Dan River 1949 Lee 1951 Riverbend 1952 Allen 1957 Marshall 1965 Oconee 1973 McGuire 1981 h
i
-- - .- - -,,1- -,-wL- . , r w.w~ s.- . ~ . . .- , . , , , _,y-. , m,---,__-.w ,,,-.,_...-..---m.-... ,,,--
e CNS 9.5.3 LIGHTING SYSTEMS The plant is provided with adequate illumination through the integrated use of normal and emergency lighting systems. These lighting systems provide illumination for normal and emergency plant operation.
9.5.3.1 Normal Lighting System The Normal Lighting System provides general illumination throughout the plant in accordance with the illumination levels recommended by the Illuminating Engineering Society. Power to the Normal Lighting System is supplied from independent 600VAC motor control centers through individual 600-208Y/120VAC dry-type transformers located in selected areas throughout the plant. All lighting in the Reactor Building is incandescent, while incandescent, floure-scent, and high intensity discharge (HID) lighting is provided for the Auxil-iary and Turbine Buildings. Normal lighting panelboards and their associated transformers and motor control centers are located such that a single failure in the Normal Lighting System will not result in a total loss of illumination in any area.
9.5.3.2 Emergency Lighting Systems 9.5.3.2.1 Design Bases The emergency lighting systems are designed to assure that adequate lighting is provided in all vital areas of the plant including essential access routes to these areas. A single failure analysis of the emergency lighting system is provided in Table 9.5.3-1.
9.5.3.2.2 Emergency 250VDC Lighting System The Emergency 250VDC Lighting System provides general emergency lighting for the control room and selected stairways and corridors throughout the plant.
Voltage sensing relays automatically energize the normally deenergized emer-gency DC lighting system in the event of a loss of normal lighting. Power to the Emergency 250VDC Lighting System is from the 250VDC Auxiliary Power System as described in Section 8.3.2. Emergency 250VDC Lighting available l for a safe available Lighting shutdowntocondition illuminateissafety shownrelated in Table equipment 9.5.2-2. is Emergency shown in Table 250VDC Q430.57 9.5.3-2.
9.5.3.2.3 Emergency 208Y/120VAC Lighting System The Emergency 208Y/120VAC Lighting System provides general emergency lighting in the control room, stair, exits, corridors, and manned safe shutdown areas Q430.57 as listed in Table 9.5.2-2. Emergency 280Y/120VAC Lighting available to ill-uminate safety related equipment is shown in Table 9.5.3-2.
9.5-7 Rev. 8
CNS The emergency AC lighting is divided into two independent trains (A and B) arranged such that a single failure will not result in a total loss of 11-lumination in any area served. Voltage sensing relays automatically energize the normally deenergized emergency AC lighting in the event of a loss of normal lighting. Power to train A and B of the Emergency 208Y/120VAC Light System is from the A and 8 diesel generators, respectively, through inde-pendent trains of the Essential Auxiliary Power System as described in Section I8.3.1. This of diesel power will be available to the system within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of the start generators.
9.5.3.2.4 Emergency 8 Hour Battery Lighting The Emergency 8 Hour Battery Lighting System is provided specifically for station illumination and access / egress for safe shutdown of the plant and for any other emergency situations that may arise. This safe shutdown and Q430.56 other emergency lighting is provided in the control room, access and egress Q430.57 stairs, exits, and corridors, and manned safe shutdown areas as listed in Emergency 8 Hour Battery Lighting available to illuminate ITable9.5.2-2.
safety related equipment is shown in Table 9.5.3-2.
The 8 Hour Battery Lighting System consists of individual 200 watt, self-contained, sealed lead calcium battery units. The units are normally on con-tinuous charge from the unit normal auxiliary power system. Upon loss of normal voltage these are energized. Means are provided to test each light-ing unit individually.
9.5.4 DIESEL GENERATOR ENGINE FUEL OIL SYSTEM 9.5.4.1 Design Br g The Diesel Generator Engine Fuel Oil Systam is designed to provide for the storage of a seven-day supply of fuel oil for each diesel generator engine and to supply the fuel oil to the engine, as necessary, to drive the emergency generator. The system is designed to meet the single failure criterion, and to withstand the effects of natural phenomena without the loss of operability.
9.5-8 Rev. 8
TABLE 9.5.3-2 (Page 1).
NOTE 1, 2 i LIGHTING SYSTEMS AVAILABLE T0 ILLUMINATE SAFETY RELATED EQUIPMENT OTE 3' NOTE 4 EMERG. LIGHTING AT EQUIP EMERG. LIGHTING FOR ACCESS TO EQUIP SYSTEM EQUIPMENT 8-HR. BATTERY EMERG.AC EMERG.DC 8-HR. BATTERY EMERG.AC EMERG.DC CA MOTOR DRIVEN AUX.
FEEDWATER PUMPS 1A, IB, 2A, 2B X X STEAM TURB. DRIVEN AUX. FEEDWATER PUMP X X X X AUX. FEEDWATER CONTROL PANELS ASP 1A, ASPIB X X X X X X EIA AUX. RELAY RACKS 1ARRI, IARR2 X X X X X PROTECTION SET I, II, I III, IV, Cabinets 1, 2,3,4 X X X X X
[
EME RCP VOLTAGE AND FREQ SYS. PANEL 1RCPM X X l
l E0A MAIN CONTROL BOARDS IMCl-1MC13, 2MCl-2MC13 X X X X X X MC14 1
l CONTROL BOARD INPUT l CABINETS IIC1-1IC18, IIC20, 21Cl-2IC18, X X X 2IC20 ,
X ,
Rev. 8
- New Page
~
TABLE 9.5.3-2 (Page 2)
LIGHTING SYSTEMS AVAILABLE TO ILLUMINATE-SAFETY RELATED EQUIPMENT. E E 1, 2 NOTE 3- NOTE 4
.EMERG. LIGHTING AT EQUIP EMERG. LIGHTING FOR ACCESS TO EQUIP SYSTEM EQUIPMENT- 8-HR. BATTERY EMERG.AC EMERG.DC 8-HR. 8ATTERY EMERG.AC EMERG.DC (E0A) CONTROL BOARD INPUT CABINETS IIC21, IIC22, IIC26-IIC33, 2IC21, 2IC22, 2IC26-2IC33 X X EPB' PT's FEEDING RCP POWER MONITOR X X s l EPC 4160 SWITCHGEAR GROUP 1 ETA, IETB X X X X X X 1
4160 SWITCHGEAR GROUP 2 ETA, 2ETB X X X X X X l EPE 600V LOAD CENTER 1ELXA, 2ELXA X X X X X X 600V LOAD CENTER 1ELXB, 2ELXB X X X X X X 600V LOAD CENTER 1ELXC, 2ELXC X X X. X X X l
600V LOAD CENTER 1ELXD, 2ELXD X X X X X X 600V MCC 1EMXA, 2EMXA X X X X 600V MCC IEMXB, 2EMXB X X X X 600V MCC IEMXC, 2EMXC X X X X X X 600V MCC IEMXD, 2EMXD X X X X 600V MCC IEMXE, 2EMXE X X X X 600V MCC IEMXF, 2EMXF X X X X X X 600V MCC IEMXG, 2EMXG X X X X X 600V MCC 1EMXI, 2EMXI X X
~
X X 600V MCC IEMXJ, 2EMXJ X X X X 600V MCC 1EMXK, ?EMXK X X X X X X Rev. 8
- New Page
]' ; y %,g,.;'[- ,, V
.c . v ~,
. , . :n _
w ,
~
TABLE 9.5.3-2 (Page 3)
NOTE 1, 2 4 . LIGHTING S STEMS AVAILABLE TO ILLUMINATE SAFETY RELATED EQUIPMENT NOTE 3 NOTE 4
_ EMERG. LIGHTING-AT EQUlP EMERG. LIGHTING FOR ACCESS TO' EQUIP S'fSTEM iEQUIPMENT 8-HR. BATTERY EMERG.AC EMERG.DC 8-HR. BATTERY EMERG.AC EMERG.DC (EPE) 600V MCC IEMXL, 2EMXL X X' X X 600V MCC IEMX0, 2EMXO X X 600V MCC IEMXQ, 2EMXQ X X 600V MCC.1EMXR, 2EMXR X X EPG STATIC INVERTER 1EIA, 2EIA X X X X STATIC' INVERTER 1EIB, 2EIB X X
-STATIC INVERTER 1EIC, 2EIC- X X X X STATIC INVERTER 1EID, 2EID X X X X POWER PANEL IERPA, 2ERPA X X X X POWER. PANEL 1ERPB, 2ERPB X X POWER PANEL IERPC, 2ERPC X X POWER PANEL 1ERPD, 2ERPD X X X X EPL BATTERY CHARGER.1ECA, 2ECA X X X X BATTERY CHARGER IECB, 2ECB X X BATTERY CHARGER 1ECC, 2ECC X X BATTERY CHARGER 1 ECD, 2 ECD X X Rev. 8
, New Page
TABLE 9.5.3-2 (Page 4)
NOTE 1, 2 LIGHTING ~ SYSTEMS AVAILABLE TO ILLUMINATE SAFETY RELATED EQUIPMENT NOTE 3 NOTE 4 EMERG. LIGHTING AT EQUIP EMERG. LIGHTING FOR ACCESS TO EQUIP SYSTEM EQUIPMENT 8-HR. BATTERY EMERG.AC EMERG.DC 8-HR.' BATTERY EMERG.AC EMERG.DC (EPL) BATTERY 1EBA, 2EBA X X BATTERY 1 EBB, 2EBP X X BATTERY 1EBC, 2EBC X X BATTERY 1EBD,'2EBD X X DC DISTR. CENTER 1 EDA, 2 EDA- X X DC DISTR. CENTER 1EDB, 2EDB X X DC DISTR. CENTER 1EDC, 2EDC X X DC DISTR. CENTER 1EDD, 2EDD X X DC PANELS 1 EPA-1EPD X X DC PANELS 2 EPA-2EPD X X DC SPARE CHGR. DISTR.
CTR IEDS, 2EDS _
X X SPARE CHGR. 600V AC
, POWER PNL 1 EMS, 2 EMS X X AUCTIONEERING D10 DES 1EADA, 2EADA X X X X X X AUCTIONEERING DIODES 1EADB, 2EADB X X X X X X DC DISTR. CENTER 1EDE, 2EDE X X X X X X DC DISTR. CENTER 1EDF, 2EDF X X X X X X EPQ DG BATTERIES DGBIA&B, DGB2A&B X X X X X X BATTERY CHGR DGCIA&B, DGC2A&B X -
X X X X X Rev. 8
, New Page
TABLE 9.5.3-2 (Page 5)
NOTE 1, 2 LIGHTING SYSTEMS AVAILABLE TO ILLUMINATE SAFETY RELATED EQUIPMENT NOTE 3 NOTE 4 EMERG. LIGHTING AT EQUIP EMERG. LIGHTING FOR ACCESS TO EQUIP SYSTEM EQUIPMENT 8-HR. BATTERY .EMERG.AC EMERG.DC 8-HR. BATTERY EMERG.AC EMERG.DC (EPQ) AUCT.D10 DES 1VADA, 2VADA X X X X X X AUCT.010 DES IVADB, 2VADB X X X X X X DISTR.CTR.1DGA&B, 2DGA&B X X X X X X
~
EPY TRANSFORMER 1EKTG X X X X X TRANSFORMER 2EKTH X X X X X TRANSFORMER, IEKTB, X X X X 1EKTI, 2EKTB, 2EKTI X X X X EQA EMERG. DIESEL GENERATOR X X X X X X EQC DIESEL GEN. CONTROL PANELS 1A, IB, 2A, 2B X X X X X X i DIESEL CONTROL PANELS 1A, IB, 2A, 2B X X X X X X DIESEL GEN. EXCITATION VOLTAGE REG. CONTROL PANELS 1A, 18, 2A, 2B X X X X X X ERN DIESEL GEN. GROUND TRANSFORMERS X X X X X X DIESEL GEN. RESISTOR BOXES X X X X X X DIESEL GEN. SURGE PACKS X X X X X X DIESEL GEN. GROUND CT's X X X X X X Rev. 8
, New Page
a ,
TABLE 9.5.3-2 (Page 6)
NOTE'1, 2 LIGHTING SYSTEMS AVAILABLE TO ILLUMINATE SAFETY.RELATED EQUIPMENT NOTE 3 NOTE 4 EMERG. LIGHTING AT EQUIP EMERG. LIGHTING FOR ACCESS TO EQUIP SYSTEM EQUIPMENT' 8-HR. BATTERY EMERG.AC EMERG.DC 8-HR. BATTERY EMERG.AC EMERG.DC (ERN) DIESEL GEN. RELAY-CABINETS 1ETAC14, 15, 2ETAC14,-15 X X X X X X EWA CABLE ROOM CABLE X X SUPPORT SYS EWB BATTERY. ROOM CABLE X X SUPPORT SYS X X EZA ELECTRICAL PENETRATIONS N/A AREA TERMINAL CABINETS X X X 1EATC1-1EATC19 X X X 2EATC1-2EATC19 AREA TERMINAL BOXES X X l 1T BOX 1-27 l FD DIESEL GENERATOR FUEL X X X X X X OIL DAY TANKS DIESEL GENERATOR FUEL X X X X X X l OIL B00 STER PUMPS DIESEL GENERATOR FUEL X X X X X OIL RELIEF VALVES X IPE REACTOR PROT.SYS. SOLID X X X X
' STATE PROT SYS RACKS Rev. 8 New Page
TABLE 9.5.3-2 (Page 7)
TE 1, 2 LIGHTING SYSTEMS AVAILABLE T0 ILLUMINATE SAFETY RELATED EQUIPMENT E3 .EMERG. LIGHTING FOR ACCESS TO EQUIP NOTE 4 EMERG. LIGHTING ~AT EQUIP SYSTEM EQUIPMENT 8-HR. BATTERY EMERG.AC EMERG.DC 8-HR. BATTERY EMERG.AC EMERG.DC (IPE) AUX; SAFEGUARD CABINET AUX. SHUTDOWN PANELS 1A,-1B X X X X X X ISE ESF TEST CABINET' .X X X I(E TURBINE TERMINAL BOX
. A, B D, E X l- -KC -COMPONENT COOLING WTR.
! PUMPS- X X X X l COMPONENT COOLING HEAT X X X ,X l EXCH.
COMPONENT COOLING SURGE-X X l TK KD DIESEL GEN. COOLING.WTR.
HEAT EXCH X X X DIESEL GEN JACKET WTR.
X X X PUMPS DIESEL GEN JACKET WTR.
STANDPIPE X X X KF SPENT FUEL COOLING PUMPS X X SPENT FUEL COOLING X X HEAT EXCH SPENT FUEL COOLING PUMP SUCTION STRAINERS X X Rev. 8 New Page
~
TABLE 9.5.3-2 (Page 8)
NOTE 1, 2~
LIGHTING SYSTEMS AVAILABLE TO ILLUMINATE SAFETY RELATED EQUIPMENT NOTE 3 NOTE 4 EMERG. LIGHTING AT EQUIP EMERG. LIGHTING FOR ACCESS TO EQUIP SYSTEM EQUIPMENT 8-HR. BATTERY EMERG.AC EMERG.DC 8-HR. BATTERY EMERG.AC EMERG.DC LD DIESEL GENERATOR LUBE OIL FILTERS X X X X DIESEL GENERATOR LUBE OIL COOLERS X X X X DIESEL GENERATOR LUBE OIL RELIEF VLVs X X X X
' DIESEL GENERATOR LUBE OIL HEAT EXCH X X X X DIESEL GENERATOR LUBE OIL SUMP TK X X X X NB BORON RECYCLE EVAP FEED PUMPS X X BORON RECYCLE HOLDUP TANK X X BORON RECYCLE EVAP FEED FILTERS X X BORON RECYCLE GAS STRIPPER PKG X X ND RESIDUAL HEAT REMOV. PUMPS X X X X RESIDUAL HEAT REMOV. HEAT EXCH X X X X NI SAFETY INJECTION PUMPS X X BORON INJ.RECIRC. PUMPS X X SAFETY INJ. ACCUMULATORS X X X X BORON INJ. TANK X X UHI WATER ACCUMULATORS X X X UHI NITROGEN ACCUMULATORS X X X UHI SURGE TANK
TABLE 9.5.3-2 (Page 9)
LIGHTING SYSTEMS AVAILABLE TO ILLUMINATE SAFETY RELATED EQUIPMENT _ NOTE 1, 2 NOTE 3 NOTE &
EMERG. LIGHTING AT EQUIP EMERG. LIGHTING FOR M CESS TO EQUIP SYSTEM EQUIPMENT 8-HR. BATTERY EMERG.AC' EMERG.DC 8-HR. BATTERY EMERG.A; EMERG.DC NM NUCLEAR SAMPLING DELAY ~
COIL X NUCLEAR SAMPLING VLV.
OPER. PNL X NR BORON THERMAL REG. M0D.
HEAT EXCH 'X X BORON THERMAL REG.
LETDOWN CHILLER X X BORON THERMAL REG.
LETDOWN REHEAT X X THERMAL REG.
DEMINERALIZER X X NS CONTAINMENT SPRAY PUMPS X X CONTAINMENT SPRAY HEAT EXCH X X 4
NV CHEMICAL AND VOLUME CONTROL CHARGING PUMPS X X CHEMICAL AND VOLUME CONTROL BORIC ACID TRANSFER PUMPS CHEMICAL-AND VOLUME CONTROL LETDOWN HEAT EXCH X X X X CHEMICAL Afl0 VOLUME TANK X X CHEMICAL AND VOLUME CONTROL BORIC ACID - -
TANK. X X Rev. 8 New Page
TABLE 9.5.3-2 (Page 10)
OTE 1, 2 LIGHTING SYSTEMS AVAILABLE TO ILLUMINATE SAFETY RELATED EQUIPMENT NOTE 3 NOTE 4 EMERG. LIGHTING AT EQUIP EMERG. LIGHTING FOR ACCESS'TO EQUIP SYSTEM EQUIPMENT- 8-HR. BATTERY :EMERG.AC EMERG.DC 8-HR. BATTERY EMERG.AC EMERG.DC RF FIRE PROT DIESEL ROOM CONTROL PANEL X X X X SM MAIN STEAM ISOLATION o VLVS. X X SV MAIN STEAM SAFETY VLVS.
RELIEF VLVS. X X ,
VA AUX. BLDG. VENT SYS.
FILTERS X X VC CONTROL BLDG. VENT SYS FAN X X 4
CONTROL BLDG. VENT SYS FILTERS X X CONTROL BLDG. VENT SYS A/C UNITS X X
, CONTROL BLDG. VENT SYS HVAC AUX. RELAY
, CAB. A&B X X VD DIESEL BLDG. VENT FANS X X X DIESEL BLDG. VENT FILTERS X X X DIESEL BLDG. VENT DAMPERS X X X VP CONTAINMENT PURGE VENT SYS ISOLATION VALVES X X WG WASTE GAS COMPRESSOR PKG. X X <
WASTE GAS TANKS * -
X X Rev. 8
. New Page i
TABLE 9.5.3-2 (Page 11)
LIGHTING SYSTEMS AVAILABLE.T0 ILLUMINATE SAFETY RELATED EQUIPMENT NOTE 1,'2L NOTE 3 NOTE 4-EMERG. LIGHTING AT EQUIP EMERG. LIGHTIMG FOR ACCESS'TO EQUIP
- SYSTEM EQUIPMENT 8-HR. BATTERY EMERG.AC EMERG.DC 8-HR. BATTERY EMERG.AC EMERG.DC (WG) WASTE GAS HYDROGEN RECOMBINERS X X
. WL LIQUID WASTE SYS.
j DRAIN TK RHR & CS ROOM SUMP X X X
~
'WN DIESEL GEN ROOM
, SUMPS X X X DIESEL GEN ROOM SUMPS PUMP. PANELS X- X X WS SPENT RESIN STORAGE TK
! YC CONTROL AREA CHILLER i COMPRESSOR CRA-C-1, 2 PANELS X X X
! NOTES: 1 EQUIPMENT LISTING TAKEN FROM " NUCLEAR SAFETY RELATED i STRUCTURES,' SYSTEMS,-AND COMPONENTS" 2 LISTING DOES NOT CONTAIN EQUIPMENT LOCATED IN REACTOR BLDGS.
3 LISTED LIGHTING IS LOCATED IN CLOSE PR0XIMITY TO EQUIPMENT 1 LISTED 4 LISTED LIGHTING IS LOCATED IN CORRIDORS / AREAS OUTSIDE ROOMS,
~
1 ALC0VES, ETC. THAT EQUIPMENT IS C0CATED IN.
a 4
Rev. 8
] New Page i
i- , ,_ ,_