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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] |
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. INITIAL i-PIPING STRESS ANALYSIS 'li1 CO:GIONWEALTH EDISON CO.
BYRON /ERAIDWOOD UNIT I
' 4391-00/4683-00 ,j
(( ~ i FEEDWATER ij'.
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ACCESSION NO. EMD 019178
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P00R ORIGINAL Page 1 of ,
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C H sC AGo ENGINEERING MECHANICS DIVISION
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- SARGENT & LUNDY E N G1N E E R S CHICAGO Proj. No.: 4391-00/4683-00 Acc. No.: EMD- 019178 Calc. No.: 1FW-04 Rev.: 04 Date: 7-17-80
(
Page 2 of 19 SIGNATURE PAGE
/
PREPARED BY: _
{ .i, ) D / _DATE:
J. Feb "M S'O '
- a [b n A M DATE: '
REVIEWED BY: ~~
R .- Prasad DATE: _ /0 0
- 3. * / 3 . I. 3 > /
APPROVED BY:
B. Tat 6sian
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" ""' """" P00R ORIGINAL 2
- THIS ANALYSIS SUPERSEDES:
h NO.: EMD- 005C21 2
03 DATE: /., .-K -?$ ACC REV.:
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SARGENT & LUNDY E N GIN E E R S C HIC #.C O Proj. No.: 4391-00/4683-00 I Acc. No.: EMD- 019178
( Calc. No.: 1FW-04
- Rev.: 04 Date: 7-17-80 Page 3 of 19 1
e t
~-h- TABLE OF CONTENTS s '
. Part I - To Be Filmed Page I
- 1. Title Page....................................... 1
- 2. Signature Page................................... 2
- 3. Table of Contents................................ 3 3 4 h 4. Subsystem Documentation..........................
- 5. Analyses Performed............................... .
5
- 6. Checklist........................................ 6-11
?' 12-13
- 7. General Notes....................................
. 8. Subsystem Plot................................... 14
- 9. Analytical Drawing............................... 15-18
- 10. Equipment Nozzle Reactions and Allowables........ 19
=
- 11. Miscellaneous.................................... -
- 12. Calculations.....................................
Part II - Do Not Film Check l.
j 1. Combined Reactions
- a. Input........................................ E)
- b. Max. Combined Anchor / Valve-End Reactions..... [3
': c. Max. Rigid Restraint Loads................... E) g
$f d. Thermal Mvt. At The Nodes....................
; e. Spring Hanger Data........................... g
!i: f. Hydraulic Snubber Data....................... g
,,I 2. Miscellaneous
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': Welded Attachment Calculations.....................
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!4 Ii i Part III
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Computer Output Microfiche (COM) -
t Includes " Analyses Performed" as listed in'Part I/Page 5 Number of COM cards 2 .
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r SARGENT & LUNDY E N GIN E E R S CHICAGD Proj. No.s4391-00/4603-00 ~
Acc. No.: EMD- 019178 Calc..No.: 1FW-04
(
- Rev.: 04 Dato: 7-17-80 Page 4 of 19 SUBSYSTEM DOCUMENTATION ,
Feedwater Subsystem: 1FN-04 System:
B Seismic X Yes No Piping Classification Group:
Certified Analysis
,' ' X Initial Formal
\
REFERENCES
- 1. Certified System No.: Rev.: Date:
Design Spec.:
- 2. Anal. Drawing: No.: 1FW-04 Rev.: O/!. Date: ? ~/- ?C)
,,. 3. P&ID Drawings: No.: See analytical 'Rev.: Date:
No.: Rev.: Date:
- 4. Equip. Spec.:
a
- 5. Seismic Information:
Stm. Gen. Feedwater Nozzle-OBE(WO-NS,VR,EW)
Cont. Bldg. El. 399 Stm. Gen. Support (205-OB-NS,EW,204-OB-VS)
Cont. Bldg. El. 394 Outer Wall (201-OB-NS,VW,EW)
- 6. Other :
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1 1
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- SARGENT & LUNDY E N GIN E E R S '
CHICOGO Proj. No.:4391-00/4683-00 }
Acc. No.: EMD- 019178 I
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Calc. No.: 1FW-04 e
Rev.: 04 Date:7-17-80 ,
Page 5 of 19 ig ti
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ANALYSES PERFORMED ,
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Check- j list Sec.
Date Comments ,
( Loadings Item 0 No.
1.0 C ~
DATA 1 7-17-80 2.0 D j THERMAL 1 7-17-80 MAX. OPER. 567 a 3.0 E WEIGHT 1 7-17-80 5.0 F SEISMIC 1 7-17-80 6.0 I TRANSIENT 2 7-17-80 $
8.0 A i}
COMBINED
', STRESSES 7-17-80 ..
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'u 9.0 B q i COMBINED
{'.
REACTIONS 7-17-80 T' I
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Proj. No.: 4391-00/4683 v0 Acc. No.: EMD- 019173 DIVISIONAL g 8;7C'll,Mljj',jM Calc . No .
- 1FW-04 TECIINICAL g Rev.: 04 Date: 7-17-80
' - ;-- ,.;m.,.;32.x PROCEDURE * * ^ " Page 6 of 19 STANDARD EMD CIIECKLIST FOR . -
-PIPING SYSTEM STRESS ANALYSIS X
NOiiEAT SRVA p7pgyg Validat'ed Programs Used:
?
Comments l Checked l Description 1.0 Basic Design Data (Output Section C) 3 1.1 Are all branch lines per Ref.
included where I R/IB <E 7.0?
1.2 Are all m'aterial types coded in agreement with Ref. 2?
{ Are all pipe / fitting thicknesses I, .
1.3 and uniform weights in agreement
(
with Ref. 2?
i / No V.alves 2
j 1.4 Are all motor or pneumatic operated e/'
.e valves modeled using lumped masses (I and cg's?
u Some too short elements Is the system modeled correctly modeled due to fitting j '
1.S (length ratios, etc.) ? configuration.
m o.
1.6 Are all hangers / restraints modeled Sy modeled at 40A in- f, or correctly per Ref. 2? stead of 40B.
1.7 Are there any special modeling Restraints at 73 & 75
~ techniques used in the analyses 50 modeled interchanges.
$ (equipment flexibility, special i
N restraint configurations, etc.)?
j ,
; 1.8 Are all node types coded correctly? /
t' d 1.9 Is the internal pressure (max . op.
pressure from Ref. 2) coded in f
t Psig?
(% - --- . . _ -
Proj. No.: 4391-00/4663-00 l
EMD- 01917o Iscc . No.: 1W-04 DIVISIONAL 0,9]3H[My]]'f Calc. No.:
() TECllNICAL PROCEDURE .
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Description 2.0 Thermal Analysis (Output Section 7.
l 2.1 Are the analyzed thermal modes in 3
agreement with Ref. 2?
2.2 Are the anchor movements in agree-l ment with Ref. 2? . Deflection of order of 2" at some nodes. Check j 2.3 Are all the1.5",deflections reasonable specify)? for interfereace.
(if over Weight Analysis _ (Output Section E)
( 3.0 3.1 Is the overall support system balanced?
Are all pipe deflections within [f
/
I 3.2 0.2 inches?
'l 3.3 For hydro-run, verify that all N/A
! spring hangers were pinned per i
the appropriate standard.
4.0 Eauivalent Static Load Analyses t l g h
! l- i ~(Outpu t Section D) a b c d e f l
The following: analyses are l*i performed using the PIPSYS #
' static analysis routine:
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4.1 Are all design parameters in agreement with Ref. __?
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4.2 Are the forces input correctly
J in the PIPSYS with respect to
,/ magnitude, direction and point of action?
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4.3 Has the ef fect of seismic e$ differential anchor movements been considered (Reference)?
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Proj. No. : 4391-00/4683-00
- acc. No.: EMD- o_9173 DIVI ~IONAL OMU3b{j]'/ Calc. No.: 1FW-04
(* TECIINICAL Rev.: 04 Date: 7-17-80
_; ;c;; ;.u.; J PROCEDURE C " 'C ^C C' Page 8 of 19 Checked Comments Description 5.0 Dynanic Analyses ab c d ef g h (Output Section F) 5.1 The following analyses are performed using response spectra method (Seismic in PIPSYS Output) : /
a-Seismic 1/ .
b-c-
d-il e-
- k. f_
g- SSE spectra not h-used - a more r c nservative
. 5.1.1 Are the latest revisions of estimate used response spectra used for the / instead.
analysis (Raference)?
Are the length ratios accept- /
5.1.2 /
able?
Does cut-of f frequency cover 5.1.3 the peak acceleration value? /
f ([.
S.1.4 Is the square root of the [
double sum method used to '
\..
combine the modal responses?
i 5.1.5 Are all the deflections
/
l l G reasonable (if over 1.0" /
u OBE, specify)?
o m 5.1.6 Ilas the ef fect of seismic differentia) anchor movements
& been considered (Reference)?
a.
w 5.2 The following analyses are per-y formed using the forcing func-tion method ~ (Transient in PIPSYS Output): [g
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= b-C-
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'Proj. No.: 4391-00/4653-00 Acc. No.: EMD 019178 DIVISIONAL Calc. No.: 1ru_04 TECIIMICAL SJ'.03EOTSUJ.~2?/ Fev.: 04 Date: 7-17-80 C' ' PROCCDURE c,g,w n.c m _
C*C^ Page 9 of 19 l Checked l Comments l Description a b c d e f g h see DD-013046 5.2.1 Is the force calculation per-formed per the appropriate I documents (Reference)?
5.2.2 Are all necessary design parameters specified in this analysis (opening / closing times, flow rates, etc.)?
(f 5.2.3 If force calculations are not attached to this analysis, reference.
\'
5.2.4 If a safety / relief valve analysis is performed:
- a. Does the steam stagnation pressure and density re-(
's flect the S/RV set point? s
\
- b. Are the pipe ID and seg- f ment lengths input cor-rectly in the SRVA pro-(-
L- gram?
Is the pipe submerged
( c.
length correctly calcu-lated and input?
- d. Is the correct density G used in the calculation? \
, \
o N y 5.2.5 Are the forces input correct-ly in the PIPSYS with respect , I to magnitude, direction and ,
Sh point of accion? 1 5.2.6 Are.the equipment reactions {
included with the correct s n load set? ~
m Thermal Transient Analysis n' 6.0
* (ASME Class 1 Piping Only) N/A i
[ ,. '
I g 6.1 Are the results of transient analysis attached to this report?
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' (') PROCEDURE
- =;- ~2,q.
C "C ^ Page 10 of 19 Checkhd Comments Description 6.2 Are all transient stresses identi-
- fied and are the NOHEAT RUNS properly documented? / -
i 6.3 Are thermal transient conditions (
and cycles cort.::t per Ref. l?
6.4 Are all discontinui' ties considered?
6.5 Check film coefficients, densities and material thermal conductivity.
tr v.
6.6 Are correct time steps used in performing the transient analysis?
7.0 Hand Calculations 7.1 If hand calculations are not attached to this analysis, reference.
7.2 Are the calculations reviewed in accordance with GO-3.08?
A detailed review of original
() calculation.
( A review by an alternate, simplified or approximate method of calculation.
f -
A review of a representative sample of repetitive calculation w
o m A review of the calculation
- against a similar calculation k E previously performed,
~
Combined Stresses (Output Section A) l r 8.0 f 8.1 Are the stresses within the /
m allowables?
for the 8.2 Are the ' allowable stresses r materials used in the analysis in
(- agreement with the Code?
D l Ci 8.3 Is the design pressure in agreement '
with Ref. 2?
g -
Proj. No.: 4391-00/4683-00 Acc. No.: EMD- 019178
' Calc. No.: Date: lW-04 DIVISIONAL O."C32[[[[1],-j[jf/ Rev.: 04 7-17-80
' TECllNICAL e,y3:.g 3.g 19 PROCEDURE c -ic eo Page 11 of Comments Checked l Description _
S.4 Are all thermal load combinations specified per Ref. l?
8.5 Are all mechanical loads listed, the design specification, as per service 16 vel B, C or D?
N/A 8.6 Are the number of earthquake cycles calculated per the design specifi-cation or per SRP-3.7.3? '
./ N/A 8.7 Are all high-stress / usage' factor (over .1) points run with the detailed output?
Combined Reactions _ (Outp'ut Section B) 9.0 9.1 - Are all applicable forces and moments considered for both upset and emergency conditions?
9.2 -Are all the equipment nozzles identified correctly?
9.3 Are equipment loads and valveHave they f
i accelerations acceptable?
been forwarded to the EMD/CAS?
-(
L 9.4 Are the vendor supplied component supports able to carry the imposed loads?
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9.5 Are all Type 3 restraints reviewedto determine if th l
e by rigid restraints?
9.6 Method used to combine the loads:
f Absolute Sum SRSS
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Calc.'No.: IW-05 Rev . : 04 Date :7-14-80 Page 120 f 19 GENERAL NOTES I.
The analysis is based on the following Code and S&L Prograns:
ASME Code, Sec. III - Class 2 of' 1975 issue.
issue.
ANSI B31.1 of issue.
" PIPSYS" -(Prog . No .' 09.5.065-5.0 ) of 6-13-80
- b. issue.
(Prog. No. ) of "SRVi"
) of issue.
- "NOHEAT" (Prog. No. 09.5.075.
i II. Coordinate Systems:
Y b " Mb 4My
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. GLOBAL LOCAL III. Conclusions & Design Requirement.
l
- 1. The pipe stresses'are within Code allowables.
j
- 2. The following support changes were made:
1
' Node 15A & 75 - add Sx skew (horiz. A to pipe)
Node 15A, 40A, 82 - Add Sy Node 45 - add Sx Node'65B - add Sz skew (' axial to pipe)
- 3. The loads on the' Steam Generator nozzle are within
- Westinghouse allowables.
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Rev.: 04 Date :7-14-80 Page 13 of 19 GENERAL NOTES - cont.
- 4. Tee Information:
The instrument taps at nodes, I'i'1, IT2 & IT3 (all 16x16x2-3/4) need no additional reinforcement.
(
- 5. Compressive loads occur on the hangers at the
(.. following node points: 55B & 75.
- 6. Loads from FW Pump Trip Hydraulic Transients were considered in this analysis.
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Acc. No.: E M D - 019178 Calc. Nof 1FW-04
!C- -
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R 2v.: 04 Date: 7-17-80 -
page 17 of 19 4"".p.h
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M M, HELEASE RECOCD PIPtNG AWLVTiCAL & P?tVStcAL DATA f i.:CT imr ' erirA*co J. cmcro J retonA at v c :c"""' -
ron FEED WATER _. ._._ .. svSrce D=#;!?".H.h}
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> Pao,e 18 of 19 P -
VCOE NO.
I EOUtPVENT INFORMATION i , VOCE P40. E Tie w s.t.u.m C A'. b t ;
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Equipr.'.ent No.:/,O #/ N ~ k"'
- 1. ;
- 2. Pipe Line: /#ts 63l'y",- //, Class: 8 . P' Y ,J Allo.wable 2.707.
Pipe Size: g,, - - Thickness: --
- 3. T ickness:,pe/J memo EMD- 020130 Nozzle Size / 4,
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- 7 S. Nczzle Connection:[b) [^[6Pressure:
- 5. Max. Op. Tcm!'. ff7eg //S3'f/'~'f ,.._;. .__ _,. ;. - - -
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j Pro). No.:4 391-0G/-;6 33-00 71 , % OVER ~^
A . . No.: E t,1 D - 01917 8 l Av y pvertical)
( e3u~ sd3.
i 1Fh. 0 4 - (
, West.inqhouse Rcv.: 04 Date: 7-17-80 i Coordinates:* Mf '/)Y' /% !
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5'Me 19 of 19 f./[
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D08 WEP"" l
. SARGENT ANU LONDY ENGINEERS .
. INTEGRATED PIPING ANALYSIS *ROGRAM .
. PIPSYS 09.5.065-5.0 JUN 13 1960 .
............e........
COMBINED REACTIONS 17 JUL 80 4391-00 8/9 1 1FW-04 REV 4 AJP
... CONTENTS OF FILE 13 ON 17 JUL 80 ...
4391-00 8/8-1 1FW-04 REV 4 AJP LOAD DATE RUNID CormENTS iFi UT 1 B ^Jul18 17 JUL 80 itMS 247AJP o8E SEISM 1C AN c SIS-INE u IA WEIGHT ANALYSIS 1
2 TH 1 17 JUL 80 247AJP EXPANSION ANALYSIS AT 567F 3 TR 1 17 JUL 80 684AJP HYDRAULIC TRANSIENT TIME HISTORY ANALYSIS 4 MAXIMUM VJMBER OF ANALYSES THAT CAN BE SAVED FOR THIS SUBSYSTEM IS 20
?
A_
- E08 M"2 4391-00 8/8-1 IFW-04 REV 4 AJP LOADINGS FOR COM INED REACTIONS 17 JUL 80 WEIGHT LOADING 1 TNERMAL LOADING (S) 1 SEISMIC (08E) LOADING 1 SEISMIC (08E) LO@ING 2.00*(08E LOM1W )
HYORALLIC TRANSIENT LOADING UPSET COMITION 1 EMERGENCY CflNDITION 1 ANCHOR /DISPLACENDIT LOA 0(S) (NOT APPLICA8LE)
MECHANICAL LOADS (NOT APPLICABLE) i 1
V -
_ _ A
- ^
~ .
F08 .
M2'1' 4391 00 8/8 1 1FW.04 REV 4 AJP MAXIMUM OF COMBINfD ANCHOR REACTIONS 17 JUL 80 i
IN LOCAL COORDINATES
! (RESULTS A4E IN FT.LB UNITS) l LOCATION WEIGHT THERMAL ANC/ NYORAULIC TRANS SEISMIC MECHANICAL 1 MECHANICAL 2 COPSINED r DISP UPSET ENERNCY UPSET EMERNCY UPSET EMERNCY UPSET EMEAMCY UPSET EMEANCY 5 FA -6. 4682. O. 4176. 4176. 620. 1240. O. O. O. O, 9471. 10091.
l F8 2311. 657. O. - 86' 866. 434. 868. C. c. O. O. 3611. 4045.
l FC -13. 903. O. 12570. 12570. 971. 1943. O. O. O. O. 14458. 15429.
l MA 1906. 15964. O. 1449. 1449. 3187. 6374. O. C. . O. O. 22506. 25692.
MB 513. -20702. O. 67590. 67590. 5140. 10281. O. C. O. O. '92920. 98060. ,
! MC 8148. 4138. C. 3782. 3782. 2299. 4599. O. O. O. O. 14230. 16529.
l j 115 FA 13. 1027. O. 5384. 5384. 3307. 6414. 0. O. O. O. 9731. 13034..
! FB -2213. 1275. O. 12260. 122(0 2413. 4826. 0. O. C. C. 16887. 19299 FC 7. 4673. O. 7792. 7792. 2846. 5692. O. O. C. O. '15304. 18150. .
i 28'28. 26128. 20064. 40128. O. 65591. 45655.
KA 3993. -21391. 0. . C. O. O.
PS -328, 38177. C. 16344. 16344. 10571. 21143. O. O. O. 0. 64764. 75336.
, MC 2173. 7154. O. 17640. 17640. 10506. 21013. O. 0. O. C. 37473. 47980.
I l
h
- l G08 EP"1' 4391-00 8/8 1 1FW-04 REV 4 AJP MAXIMUM 0F ColWDCD ANCHOR REACTIONS 17 JLA. 40 (REstA.TS AAC IN FT-L8 UNITS)
LOCATION WEIGHT TERMAL ANC/ NYDRALA.IC TRANS' SEISMIC MECHANICAL 1 MECHANICAL 2 COPSINED DISP wsET EMEaNCY WSET EMERNCY WSET EMUNICY WSET EMEANCY UPSET EMEANCY L
5 FX 7. 3335. O. 11085. 11085. 836. 1672. O._ , O. O. O. 15 63. 16099. ELS84L FY 2311. 657. O. 466. 466. 434. 868. c.,. o. c. O. 3611. 4045.
FZ 12. 3404. O. 4154. 8154. 793. 1584. c. O. O. O. 12342.~~13135.
MX -3744. 12253. O. 3369. 3369. 2552. 5105. O. O. O. O. 12427.1 14979.
MY 513. 20702. O. 67590. 67590. 5140. 10281. O. O. O. O. 92920. 94060.
MZ 6082. 11037. C. 2250. 2250. 2984. 5976. O. O. O. O. 22358." 25346.
115 FX 7. -3316. O. 4498. 4694. 1680. 3360. O. O. O. O. 9701. 11300. GLOBAL F1 2213. -1275. O. 12260. 12260. 2413. 4426. O. O. O. O. 16887. 19299.
FZ 12. 3449. O. 9034. 9038. 4026. 8052. O. C. O. O. 16501. 20527.
MX -2271. 21979. O. 18741. 18741. 21869. 43737. O. O. O. O. 60317.- 82186.
MY 328. 38177. c. 16344. 16344. 10571. 21143. O. O. O. O. 64764. 75336.
MZ 3938. 5066. O. 25079. 25079. 5892. 11784. O. c. O. O. 34910. 40802.
l 1
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_L__________ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 4
! H08 -
gig S f 4391-00 B/8-1 1FW-04 REV 4 AJP EQUIPMENT N0ZZLE REACTION SUPMARY (LOCAL) 17 JUL 80 LOCATION : 5 PENETRATION P.87 i LOAD FORCES IN LOS HOMENTS IN FT-LOS CASE FA FB FC MA MS MC j ................................................................................................
I WEIGHT -6. 2311. 13. 1906, 513. 8148.
! THERMAL EXPANSION 4682. -657. -903. 15964. 20702. -4138.
4 ANCHOR / DISPLACEMENT 0. O. O. O. O. O.
HYDRALA.IC TRANSIENT UPSET 4176. 866. 12570. 1449. 67590. 3782.
EMERGENCY 4176. 866. 12570 1449. 67590. 3782.
SEISMIC UPSET 620, 434 971 3187. 5140. 2299 EMERGENCY 1240. 868. 194 . 6374 10281. 4599.
MECHANICAL 1 UPSET 0. O. O. O. O. O.
EMERGENCY 0. O. O. O. O. O.
MECHANICAL 2 UPSET 0. O. O. O. O. O.
EMERGENCY 0. O. O. O. O. O.
MAXIMUM CONDITION UPSET 9471. 3611 14458, 22506. 92920. 14230 EMERGENCY 10091. 404$.. 15429. 25692. 98060. 16529.
MAXIMUM CONDITION UPSET FA = 17657 MR = % 660.
EMERGENCY 18875. 102709.
4
s I08 ME1 5 4391 00 8/8 1 1FW-04 REV 4 AJP ESUIPMENT N0ZZLE REACTION SUPW1ARY (LOCAL) 17 JUL 80 LOCATI006 : 115 STEAM GENERATOR . FW Ilt.ET (1C-1RC018C)
LOAD FORCES IN L85 MOMENTS IN FT-LBS
- CASE FA F8 FC MA MB MC WEIGHT 13. -2213. 7. 3993. 328. 2173.
TManAL EXPANSION 1027. 1275. 4673.. -21391. 34177. 7154.
ANCHOR /DISPLACEPDIT
- 0. O. 0. O. O. O.
HYDRAULIC TRANSIENT UPSET 5384. 12260. 7792. 28128. 16344. 17640.
EMERGOICY 5384. 12260 7792. 20128, 16344. 17640.
E Y 64 4.
- h. *
. h$4k' h
! MECHANICAL 1 UPSET 0. O. O. O. O. O.
- DERGOICY -
- 0. O. O. O. O. O.
! MECHANICAL 2 UPSET 0. O. O. O. O. O.
DE.1GOGCY 0 O. O. O. O. O.
, MAXIMUM C00GITION UPSET 9731. 16887 15304. 65591. 64764. 37473.
- EMERGDICY 1D38. 19299. 18150. 85655. 75336. 47990.
MAXIMUM C0fSITION UPSET FR = 24780. PWI = 9*503.
DERGOICY 29528. 123751.
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J08 .
g S 4391 00 8/8 1 1FW.04 REV 4 AJP EOUIPMENT N0ZZLE REACTION SUPMARY (GLOOAL) 17 JUL 80 LOCATION : 5 PENETRATION P.87 LOA 0 FORCE.1 IN L85 M0MENTS IN FT.L85 CASE FX FY FZ MX MY MZ WEIGHT 7. 2311. -12. 5748, 513. 6082.
TERML EXPANSION 3335. 657. 3408. 12253. 20702. 11037.
ANCHOR / DISPLACEMENT 0. O. O. C. O. O.
HYDRAULIC TRANSIENT UPSET .11085. 8f%. 8154. ' 3369. 67590. 2250.
uiun.UsCY 11085. 866. 8154. 3369. 67590. 2250.
SGSMIC UPSET 836. 434. 793. 2552. 5140. 2948.
EMEAGOICr 1672. 868. 1586. 5103. 10281. 5976.
. ECMNrC= 1 UPSET 0. O. O. O. O. C.
EMERGOeCY 0. O. O. O. ,
O. O.
"cc""2c" 2 MIENCr 8: 8: 8: 8: 8: 8:
MAXIMLM C00eITION UPSET 15263. 3611. 12342. 12427. 92920. 22358.
EMERGENCY 16099. 4045. 13135. 14179. 98060. 25346.
MKIMUM C00eITION UPSET FR = 19958. M= 96376.
EMERGENCY 21168. 102385.
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/;
4391 00 8/8-1 1FW.04 REV 4 AJP s EOUIPMENT N0ZZLE REACTION S M Y (GLOSAL) 17 JUL 80
) LOCATION : 115 STEAM GEERATOR - FW IILET (1C-1RC01SC) i LOAD FORCES IN L85 MOMENTS IN FT-LO$
i CASE FX FY FZ MX NY MZ q
WEIGHT , -7. 2213. 12. -2271. 328. 393C.
TW" MAL EXPANSION -3316. -1275. -3449. 21979. -38177. -5064.
l
) ANCHOR /DISPLACEMDIT 0. O. O. C. O. O.
! NYDIIAULIC TRANSIENT UPSET 4698. 12260. 9034. '18741. 16344. 25079.
EERGDICY 4698. 12260. 9038. 18741. 15344. 25079.
; SEISMIC UPSET 1640. 2413. 4026. 21869, 10571 5892. '
i r.numUsCY 3360. 4826. 8032. 43737. 21143 . 11784.
4 MECR4NICAL 1 0. O. O. O. O. C.
GDICY 0. O. O. O. O. O.
MECMANICAL 2 UPSET 0 C. c. O. O. O.
EERGDICY 0. O. O. C. O. O.
MAXIMUM ColeITION UPSET- 9701. 16887. 16501. 60317 64764. 34910.
l EMERGDICY 11380. 19299. 20527. 82166. 75336. 40442.
MAXIMUM C0feITION UPSET FR = 25525. PWI = 95138.
EMERGDICY 30387. 118721.
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4391 00 B/8 1 IFW.04 REV 4 AJP MAX RI RJ , Og5 IN L85 17 JUL 80 N00E WEIpfT THERMAL ANC/ NYORAULIC TRANS SEISMIC MECHANICAL 1 MECHANICAL 2 CorSINED DIRECTION DISP UPSET EMERNCY UPSET EMERNLY UPSET EMERNCY UPSET thatNCY UPSET EMEANCY 15 4543. 2946. O. 1439. 1439. 1459. 2917. O. O. O. O. 10347. 11845. Y 0 1H5. 186.
658 6566. O. O. 8275. 8275. 2558. 5117. C. O. O. O. 17399. 19957.. Y
, -1008. 5275. 7834.
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! SECTION 8 '
PAGE 6 I 4391 00 8/8 1 1FW.04 REV 4 AJP HYDRAULIC SNUBBER DATA 17 JUL 80 (RESTRAINT TYPE 3)
RANGE OF THERMAL DYNAMIC LOADS LOS)
MOVEMENTS (INCHES) FNC/ HYORAULIC TRANS MECHANICAL 1 SE SMIC MECHANICAL 2 COMBINED DIRECTION N00E X Y Z DISP UPSET EMERNCY. UPSET EMERNCY UPSET EMERNCY UPSET EMERNCY UPSE7 EMERNCY
- ..............................................................................................................................
20A .911 000 000 0. 17888. 17888. 0. O. 2592. 5184 C. O. 20480. 23072. Z SKEV .
! .000 .004 .332 40A 1.2% .000 .000 0. 2122. 2122. O. O. 1861. 3721. O. C. 3982. 5843. Y
- .000 . 654 -1.029 400 1.383 .000 .000 C. 20148. 20148. O. O. 2686. 5372. O. O. 22634 25520.
- .000 .661 -1.018 1
4 45A 1.361 .000 .000 0. 4752. 4752. O. O. 2548. 5096. O. O. 7300. 9847.. Z
- .000 . 605 .595 l 508 .977 .000 .000 0. 3094. 3094. O. O. 1633. 3266. O. O. 4727. 6360. X t .000 . 589 . 475 .
60 .592 .000 000 C. 8173. 8173. O. O. 4325. 8649 O. O. 12497. 16822. Z .
.000 .230 .753
, 75 .830 .315 .000 0. 15200. 15200. O. O. 3763. 7526. O. O. 18M3. 22726. X l .000 .000 .382
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n o Appx. A, L'M.D-02697.
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