Similar Documents at Perry |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That Proprietary Document NEDE-32907P,DRF A22-0084-53, Safety Analysis Rept for Perry NPP 5% Power Uprate, Class III Dtd Sept 1999 Be Withheld.Determined Document Proprietary & Will Be Withheld ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212K9271999-09-30030 September 1999 Refers to 990927 Meeting Conducted at Perry Nuclear Power Plant to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff ML20212J1451999-09-30030 September 1999 Forwards Order,In Response to 990505 Application PY-CEI/NRR- 2394L.Order Approves Conforming License Amend Which Will Be Issued & Made Effective When Transfer Completed ML20217E7111999-09-30030 September 1999 Documents Telcon Conducted on 990929 Between M Underwood of Oh EPA & D Tizzan of Pnpp,Re Request to Operate Pnpp Sws,As Is,Until Resolution Can Be Obtained ML20212G4161999-09-24024 September 1999 Informs of Completion of Licensing Action for Generic Ltr 98-01, Y2K Readiness of Computer Systems at Nuclear Power Plants, for Perry Nuclear Power Plant ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED ML20212A8371999-09-13013 September 1999 Forwards Insp Rept 50-440/99-13 on 990712-30 & Notice of Violation.Insp Included Evaluation of Engineering Support, Design Change & Modification Activities,Internal Assessment Activities & Corrective Actions ML20217A8971999-09-0909 September 1999 Forwards Insp Rept 50-440/99-09 on 990709-0825.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages ML20211Q6911999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Perry Operator License Applicants During Wks of 010108 & 15.Validation of Exam Will Occur at Station During Wk of 001218 IR 05000440/19990011999-08-31031 August 1999 Requests That Page Number 4, P2 Status of EP Facilities, Equipment & Resources, of Insp Rept 50-440/99-01 Be Replaced with Encl Rev PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20210Q8421999-08-13013 August 1999 First Final Response to FOIA Request for Documents.Records Listed in App a Being Released in Entirety & Records Listed in App B Being Withheld in Part (Ref FOIA Exempt 5) ML20210R7861999-08-12012 August 1999 Forwards Insp Rept 50-440/99-12 on 990712-16.No Violations Noted.New Emergency Preparedness Program Staff & Mgt Personnel Were Professional & Proactive ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 ML20210Q7981999-08-10010 August 1999 Informs That Intention to Utilize Sulfuric Acid in Pnpp Circulating Water Sys to Lower Ph Is Anticipated to Be Completed in Nov ML20210Q5831999-08-10010 August 1999 Requests Permission to Chemically Treat CWS for Algae Due to Cooling Water Basin Becoming Infected with Algae of Various Types PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 ML20210K6331999-08-0404 August 1999 Submits Response to Requests for Addl Info to GL 92-01,Rev 1, Reactor Vessel Structural Integrity, for Perry Nuclear Plant,Unit 1 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 ML20210G8411999-07-28028 July 1999 Informs That Based on Determination That Rev 14 Changes to Various Portions of Perry Nuclear Power Plant Emergency Plan Does Not Decrease Effectiveness of Licensee Emergency Plan & Meets Standard of 10CFR50.47(b),no NRC Approval Required ML20210E0661999-07-22022 July 1999 Forwards Insp Rept 50-440/99-08 on 990518-0708.No Violations Noted.Overall Conduct of Activities at Perry Facility, Conservative & Professional with Continuing Focus on Safety PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20209E5951999-07-0909 July 1999 Ltr Contract:Task Order 46, Perry Engineering & Technical Support (E&Ts) Insp, Under Contract NRC-03-98-021 ML20209D5931999-07-0101 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Investigation Rept 3-98-005 Issued on 990510.Corrective Actions Will Be Examined During Future Inspections ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant ML20196H9641999-06-29029 June 1999 Confirms 990615 Telcon Request with J Lieberman for Addl Time to Respond to Enforcement Action 99-012.FirstEnergy Has 60 Days to Respond to EA PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval ML20195G6741999-06-10010 June 1999 Forwards Insp Rept 50-440/99-03 on 990407-0517.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records PY-CEI-NRR-2404, Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology1999-06-0707 June 1999 Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology ML20195E4561999-05-25025 May 1999 Submits Petition Per Other Actions Provision of 10CFR2.206,requesting That Radiation Protection Manager at Perry NPP Be Banned by NRC from Participation in Licensed Activities at & for Any NPP for at Least Five Yrs PY-CEI-NRR-2401, Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars1999-05-20020 May 1999 Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars PY-CEI-NRR-2402, Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs,1999-05-18018 May 1999 Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, PY-CEI-NRR-2394, Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested1999-05-0505 May 1999 Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested PY-CEI-NRR-2397, Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.51999-04-30030 April 1999 Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.5 PY-CEI-NRR-2396, Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-en1999-04-28028 April 1999 Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-end Weld 05000440/LER-1999-002, Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available1999-04-26026 April 1999 Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available PY-CEI-NRR-2388, Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits1999-04-22022 April 1999 Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits PY-CEI-NRR-2371, Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted1999-04-21021 April 1999 Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted PY-CEI-NRR-2382, Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl1999-04-21021 April 1999 Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl PY-CEI-NRR-2392, Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette1999-04-19019 April 1999 Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette PY-CEI-NRR-2387, Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 1051999-04-14014 April 1999 Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 105 PY-CEI-NRR-2386, Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing1999-04-0606 April 1999 Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20206N3361999-04-0505 April 1999 Informs NRR of Continued Events Re Transfer of Generation Assets Between Duquesne Light Co & Firstenergy.No Negotiated Settlement Between Firstenergy & Local 270 Pertaining to Generation Asset Swap Has Been Reached PY-CEI-NRR-2384, Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC1999-04-0101 April 1999 Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC PY-CEI-NRR-2383, Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed1999-04-0101 April 1999 Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed L-99-052, Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding1999-03-30030 March 1999 Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding ML20205H6171999-03-29029 March 1999 Forwards Util Consolidated Financial Statements for Twelve Month Period Ending 981231 & Internal Cash Flow Projection, Including Actual 1998 Data & Projections for 1999 PY-CEI-NRR-2377, Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1)1999-03-29029 March 1999 Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1) PY-CEI-NRR-2380, Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure1999-03-25025 March 1999 Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure 1999-09-09
[Table view] Category:LEGAL/LAW FIRM TO NRC
MONTHYEARML20059D6451990-08-31031 August 1990 Requests Dismissal of Ohio Edison Co Application to Suspend Antitrust License Conditions in OL & Follow Recommendation of Doj.Alleged Increase in Nuclear Power Costs Heightens Importance of Continued Imposition of Antitrust Conditions ML20059C9951990-08-27027 August 1990 Responds to Util Re Suspension of Antitrust License Conditions ML20059G1001990-07-24024 July 1990 Requests NRC Expeditious Disposition of Matter Re Ohio Edison 870918 Application to Suspend Antitrust License Conditions.Doj Position in Inconsistent W/Prior Analyses & W/Pertinent NRC Case Law.Jd Pace Affidavit Encl ML20151D8121988-07-15015 July 1988 Forwards Opposition of City of Clyde,Oh to Util Application to Suspend Antitrust Conditions at Facilities,Per 880616 53FR22589 & 53FR22590 ML20150D3541988-07-0505 July 1988 Forwards Response of Ohio Edison Co to Comments on Antitrust License Amend Application.Util Requests Commission Hold Present Proceeding on Application in Abeyance Pending Resolution of Court Action Filed on 880622 ML20197G9591988-06-0808 June 1988 Forwards Technical Rept, Analyses of Northeastern Ohio Seismicity & Tectonics, Which Responds to Ohio Citizens for Responsible Energy 880122 Petition for Immediate Action to Relieve Undue Risk Posed by Inadequate Seismic Design ML20155F2091988-05-27027 May 1988 Requests 30-day Extension Until 880703 to File Response to Cities of Clyde & Cleveland Re Util Antitrust License Amend Application,Due to Length of Comments.Nrc Antitrust Counsel Does Not Object to Granting Extension Based on Discussion ML20155F3831988-05-23023 May 1988 Forwards Tables of Contents & Appendices Inadvertently Omitted from City of Cleveland,Oh 880219 Answer to Util 870918 Application ML20147E8141988-02-29029 February 1988 Forwards American Municipal Power-Ohio,Inc Request for 30 Day Extension for Filing Comments ML20235A5361987-09-18018 September 1987 Forwards Application for Amend to License NPF-58,suspending Antitrust Conditions Insofar as Conditions Apply to Ohio Edison Co.Fee Paid ML20212N1301987-03-11011 March 1987 Forwards Final Draft Plant Operating Agreement Mentioned in Application for License Amend & Approval Re Sale & Leaseback Transactions.Agreement Currently Being Executed ML20212F4651987-03-0303 March 1987 Identifies Potential Equity Investors Wishing to Participate Directly or Through Subsidiary in Sale & Leaseback Transactions,Per Util 870123 Application for Amend to License NPF-58.Annual Repts & Supporting Documentation Encl ML20207Q5861987-01-23023 January 1987 Forwards Application for Amend to License NPF-58 Re Sale & Leaseback Transactions W/Ohio Edison Co.Fee Paid ML20206S2701986-09-17017 September 1986 Notifies of Address Change Effective on 860927.Requests Address on Encl List of Dockets Be Changed ML20214L6681986-09-0404 September 1986 Requests Encl Signature Page Be Substituted for Original Signature Page to MR Edelman 860902 Affidavit Attached to Licensee 860902 Response to Ocre Motion for Continuance.Svc List Encl ML20209B0071986-09-0202 September 1986 Advises That Sunflower Alliance Will Not Suppl or Amplify Notice of Reconsideration Filed on 860808.W Clements Directed to Destroy Notice of Appeal ML20212P0071986-08-28028 August 1986 Requests Scheduled 860905 Meeting Re Discussions/Possible Vote on Full Power OL for Unit 1 Be Stayed Pending Decision from Us Court of Appeals for Sixth Circuit in Ocre Vs NRC ML20214J9641986-08-12012 August 1986 Advises That Licensee Will Await Aslab Decision Before Responding to Ohio Citizens for Responsible Energy 860808 Petition to Reconsider Portions of Aslab 860725 Decision ALAB-841.Svc List Encl.Related Correspondence ML20203Q2991986-05-0505 May 1986 Advises That Per Encl Sec 860429 Order,Cleveland Electric Illuminating Co & Toledo Edison Co Now Subsidiaries of Centerior Energy Corp.Utils Will Continue as Electric Companies & as NRC Licensees & CP Holders ML20210L3931986-04-25025 April 1986 Confirms That Baseline Testing Referred to in Affidavit of Dr Green Completed Prior to Fuel Loading of Unit 1.Svc List Encl.Related Correspondence ML20203D7231986-04-16016 April 1986 Informs That Both Seismic Instrumentation & Hydrogen Control Equipment Will Be Accessible at Time of Aslab Visit,Per 860403 Telcon Re Hearing on Ocre Motion to Reopen Proceeding.Personal Info Requested by 860509.Svc List Encl ML20140A7291986-03-18018 March 1986 Forwards ACRS to Palladino Re ACRS Consideration of State of Oh 860131 Earthquake.Svc List Encl.Related Correspondence ML20141M9561986-02-25025 February 1986 Requests Denial of Ocre 860203 2.206 Petition to Prevent Fuel Loading or OL Issuance Until Assessment of 860131 Earthquake Complete.Encl Affidavits Confirm That Earthquake Did Not Adversely Affect Plant ML20214C8961986-02-19019 February 1986 Forwards Original Signature Page to Be Substituted in Affidavit of Ta Boss,Attachment 1 of Applicant to Commissioners ML20214C9961986-02-18018 February 1986 Responds to Dl Schlemmer 860204 2.206 Petition Requesting Plant Closure Due to Inadequate Seismic Design & Idcvp to Assess Integrity of Site QA Programs.Petition W/O Basis & Should Be Denied in All Respects ML20137U6861986-02-13013 February 1986 Forwards Amend 5 to Form U-1,recently Filed W/Securities & Exchange Commission,Providing Addl Info Re Proposed Affiliation Between Utils.W/Certificate of Svc ML20151U0301986-02-0505 February 1986 Informs of Intent to Respond to Assertions in Ocre Re Summary of 851218 Meeting Between NRC & Hydrogen Control Owners Group.Motion to Reopen Has Not Been Filed by Ocre.Svc List Encl.Related Correspondence ML20137N9701986-01-31031 January 1986 Forwards Amends 3 & 4 to Form U-1,recently Filed W/ Securities & Exchange Commission,To Provide Addl Info Re Proposed Affiliation Between Utils ML20137F1711986-01-14014 January 1986 Forwards 851213 Insp Rept Re 851120 Emergency Preparedness Exercise.Related Correspondence ML20136J0891986-01-0808 January 1986 Forwards Amend 2 to Sec Form U-1,providing Addl Info Re Proposed Affiliation Between Cleveland Electric Illuminating Co & Toledo Edison Co ML20141F5951986-01-0606 January 1986 Forwards Articles Re Turbine Missiles Cited in Memorandum & Order LBP-83-48,per Request.Related Correspondence ML20141F7161986-01-0606 January 1986 Informs of Typo in 851230 Applicant Answer to Ocre Motion to Reopen Record & Submit New Contentions. Steam Binding Should Read Steam Blanketing. W/Svc List ML20151P1341985-12-31031 December 1985 Forwards Original Signature Page to Affidavit of Kw Holtzclaw for Telecopy Attached to Applicant Answer to Ocre Motion to Reopen Record & to Submit New Contentions,Filed on 851230.Svc List Encl ML20138H9201985-12-12012 December 1985 Comments on Applicant Brief in Opposition to Intervenor Appeals from Concluding Partial Initial Decision.Footnote 94 Should Ref Defect W/Crankshaft Oil Hole Plugs as Failure Instead of Simply as Crack.W/Svc List ML20137U2571985-12-0404 December 1985 Forwards Corrected Table of Authorities to Applicant Brief in Opposition to Intervenors Appeals from Concluding Partial Initial Decision ML20205H2241985-11-13013 November 1985 Forwards Amend 1 to Form U-1 Recently Filed W/Securities & Exchange Commission to Provide Addl Info & Exhibits Re Proposed Affiliation Between Utils ML20133H9841985-10-14014 October 1985 Forwards Util to HR Denton Providing Updated Info on Facility Status & Readiness for Fuel Loading & Operation. Unit 1 May Be Ready to Load Fuel as Early as 851108.Svc List Encl.Related Correspondence ML20133J2571985-10-11011 October 1985 Forwards Original Signature Page to Gr Leidich Affidavit Attached to Applicant Response to Ocre Motion for Stay Pendente Lite ML20132C7691985-09-24024 September 1985 Forwards Util Re Unit 1 Status & Operational Readiness.Related Correspondence ML20135B7711985-09-0909 September 1985 Forwards News Release by State of Oh,Dept of Health Announcing State Policy on Distribution of Potassium Iodide.Svc List Encl.Related Correspondence ML20134G0511985-08-21021 August 1985 Forwards Util Updating Progress on Unit 1 During Jul 1985 for ASLB Info.Related Correspondence ML20134D2601985-08-14014 August 1985 Forwards 850805 Application & 850808 Registration Statement Filed W/Securities & Exchange Commission Re Proposed Affiliation Between Cleveland Electric Illuminating Co & Toledo Edison Co.Utils Will Be Subsidiaries of Holding Firm ML20133E5971985-08-0606 August 1985 Forwards Hydrogen Control Owners Group & Hydrogen Control Owners Group Rept on 1/4-Scale Scoping Test Results. Subj Test Program Part of Final Analysis Required by Hydrogen Rule.Related Correspondence ML20128M2761985-07-22022 July 1985 Forwards Util to NRC Re Progress Update for June 1985.Svc List Encl.Related Correspondence ML20129K1411985-07-19019 July 1985 Forwards EC Christiansen & WR Kanda Affidavits Re Placement, Operation & Safety Parameters of Check Valves Used in Lube Oil Generators & 850505 Fire in Reactor Bldg,Respectively ML20128R1171985-07-10010 July 1985 Forwards Recent Press Release Announcing Agreement Between Applicant & Toledo Edison Co to Combine Under Newly Formed Holding Company.Svc List Also Encl.Related Correspondence ML20128A5281985-06-28028 June 1985 Forwards M Edelman to H Denton,Setting Forth Applicant Proposed Schedule for Final Analysis of Plant Hydrogen Control Sys.Completion Expected by End of 1986.Svc List Encl.Related Correspondence ML20127B4821985-06-20020 June 1985 Forwards Addendum to Torsiograph Tests of Emergency Diesel Generators,Divs 1 & 2 at Perry Nuclear Power Plant-Unit 1 on Cylinder Imbalance, Prepared by Failure Analysis Assoc. Related Correspondence ML20127A9931985-06-19019 June 1985 Informs That Unit 1 12 Wks Negative Re 850614 Project Master Plan Fuel Load Date.Related Correspondence ML20126C3921985-06-10010 June 1985 Forwards Failure Analysis Assoc Rept FaAA-85-4-1, Torsiograph Tests of Emergency Diesel Generators,Divs 1 & 2 at Perry Nuclear Power Plant - Unit 1, Discussed During Evidentiary Hearings on Issue 16.Related Correspondence 1990-08-31
[Table view] |
Text
HII W M CORRESPoiyo ~~ gR4 4
SHAW, PITTN1AN, PoTTs & TROWBRIDGE A PARTNERSMiP OF PROFESSIONAL CORPORATIONS 1800 M STRE ET, N. W.
WASHINGTON. D. C. 20036 TELEcOPrER a2021 saa-soes & saa-nee June 10, 1985 TEtEx es-26e3 ISMAWLAW WSMI CABLE SMAWLAW" DOCMC(E0 .
J AY E. SIL BERG. P.C. I 2 e 2 oe3 James P. Gleason, Chairman l Atomic Safety and Licensing Board '85 JUN 13 A10:50 1 513 Gilmoure Drive Silver Spring, Maryland 20910 CFFICE OF SECRE 7' 00CKETING A SERWl Dr. Jerry R. Kline SRANCH Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. Glenn O. Bright Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: The Cleveland Electric Illuminating Company (Perry Nuclear Power Plant, Units 1 and 2)
Docket Nos. 50-440 and 50-441% L Gentlemen:
During the course of the evidentiary hearings on Issue 16 (TDI Diesel Generators), there was considerable discussion on the torsiograph tests of the Division 1 and 2 emergency diesel generators. Enclosed for your information is Failure Analysis Associates Report FaAA-85-4-1, "Torsiograph Tests of Emergency Diesel Generators, Divisions 1 and 2, at Perry Nuclear Power Plant - Unit 1" (May 1985). The cylinder imbalance test, also discussed during the evidentiary hearings, will be included in a supplement to the torsiograph test report.
y truly q urs, 85061gO gO d G l. 3ilberg Ce nel for Applican d JES:L j Enclosure cc: Service List i
i FaAA-85-4-1
. QRCEI TORSIOGRAPH TESTS OF EERGENCY DIESEL GENERATORS, .
DIVISIONS 1 AND 2 AT PERRY NUCLEAR POE R PLANT--UNIT 1 Prepared by Failure Analysis Associates Prepared for TDI Diesel Generator Owners' Group May 1985
/
4
\
TABLE OF CONTENTS Page
1.0 INTRODUCTION
........................................................... 1 2.0 INSTRUMENTATION........................................................ 1 3.0 PR0CEDURE.............................................................. 1 3.1 Cal i brati on and Inst rumentat i on Run-i n. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.2 Va ri abl e Speed , 0% Load Tes t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.3 Variable Load 0perating Speed Tests.............................. 3 3.4 S t a rt up / Coa s t down Te s t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.5 Post Test Data Veri fication and Calibrati on. . . . . . . . . . . . . . . . . . . . . . . 3 4.0 RESULTS................................................................
4.1 Calibration Data..................................................
4 4
4.2 Variable Speed Results............................................ 6 4.3 Va ri abl e lo a d R es u l t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4.4 St a rt up / Coa s t down R e s u l t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
5.0 CONCLUSION
S............................................................ 9 REFERENCES.................................................................. 9
1.0 INTRODUCTION
The purpose of the torsiograph test of the emergency diesel generator was to measure the angular displacements of the forward end of the crank-shaft. These displacements were then used in conjunction with a dynamic torsional analysis of the crankshaft to assess the maximum stresses in the crankshaft. Torsiograph tests were performed on diesel generators Unit 1 Division 1 (U101) and Unit 1 Division 2 (U102) at Perry Nuclear Power Plant.
Data were obtained during both steady-state and transient (startup and coast-down operation) conditions.
2.0 INSTRUMENTATION The- instrumentation generally consisted of an HBM Torsiograph, Signal Conditioner, Data Tape Recorder, Frequency Analyzer, Oscilloscope, Multimeter, and assorted interconnecting cables. The specific instrumentation used is shown in Table 2.1.
3.0 PROCEDURE The torsiograph, which was attached to the front end of the crankshaft through an adapter plate supplied by the Perry plant, was used to measure angular displacements of the crankshaft relative to its mean rotational speed. The angular displacement signal from the signal conditioner was recor-ded on magnetic tape for further analysis to determine angular displacement components for each order. Tests were conducted at several speeds under no-load conditions, and at several loads at operating speed. In addition, fast starts were performed with predetermined crankshaft positions. The torsio-graph data was recorded continuously from startup through coastdown. The spectrum analyzer was used to verify data integrity by datermining harmonic components for each test condition.
The test was carried out for each diesel engine in the following five stages:
1
- 1. Calibration and instrumentation run-in.
- 2. Variable speed tests at 0% load.
- 3. Variable load tests at rated speed.
4 Startup and coastdown tests.
- 5. Post test calibration.
3.1 Calibration and Instrumentation Run-in The torsiograph was mounted on the front end of the crankshaft using a rigid adapter plate. The torsiograph was connected to the signal conditioner and the signal conditioner to the instrumentation recorder with the designated caoles. The signal conditioner was also connected to the spectrum analyzer and oscilloscope to monitor the torsiograph signals.
The following steps were completed to calibrate the instrumentation before and after testing:
- 1. The recording equipment and cabling was calibrated 'ay introducing a known signal into the signal conditioner connection and recording the signal.
- 2. The calibration signal was verified by playing back the calibration recording.
- 3. A field calibration of the torsiograph was completed following the manufacturer's instructions [1]. The field calibration signal was recorded.
4 The field calibration signal was played back for verification.
After the calibration procedure was completed, the diesel engine was operated at no load for approximately two to ten minutes while data was recor-ded. The engine was then shut down while the recorded data was examined to verify the instrumentation and recording system operation.
The test documentation information in Table 3.1 was logged.
2
3.2 Variable Speed. 05 Load Tests The engine was operated for two to five minutes at rated speed and no load. The speed was then adjusted using the mechanical governor to operate at speeds between 400 and 470 rpm. The engine was operated at each speed for two to ten minutes while the torsiograph output was recorded. The output speeds and tape footage were recorded (Table 3.2).
3.3 Variable Load, Operating Speed Tests i
The engine was brought to operating speed. The load was adjusted !
successively to operate at the following load conditions for five to ten minutes: 25%, 50%, 75%, 100%. The load, current, speed, and tape footage were recorded (Table 3.3).
3.4 Startup and Coastdown Tests Transient data was recorded for each engine at four different startup
. positions and the four coastdowns from 450 rpm. The startup and coastdown conditions monitored are the normal procedural fast starts and coastdowns in use at Perry.
The fast starts were performed with predetermined initial crankshaft positions at 180 degree intervals of crankshaft rotation to cover the full 720 degree firing cycle. The positions are described in Table 3-4 Once at the ;
operating speed of 450 rpm the engine was allowed to coastdown. No load was i applied to the engine du-ing this test. The tape footage and run I.D.'s were recorded (Table 3.5).
3.5 Post Test Data Verification and Calibration Selected data records were played back to verify proper measurement and recording. The calibration procedure outlined above was repeated and the signals recorded.
3
4.0 RESULTS 4.1 Calibration Data The pre and post test static calibration data are shown in Tables 4.1 and 4.2. The torsiograph sensitivity was :alculated as follows:
Teac
) Amp. Range mV/V)
Torsiograph Sensitivity, =
degree (Input, degrees) ( Tape Deck )
Gain, V /V in The multiplication factors used in data reduction were calculated as follows:
Vibration mV/V (TapeDeck*)[
Output, Vpk Amp. Range TN)
Setting, Amplitude =
(degrees-pk) Torsiograph ,yfy Tape Deck (Sensitivity, degree) (Gain, V out IYin) where Amp. Range Setting = 20 y Tape Deck Range Setting = 0.1 Vout / Vin Ch. 1 0.2 V out / Vin Ch. 2
- Unit 1 - Division 1 From Table 4.1 for Channel 1, Torsiograph Sensitivity = *
= 4.747 t 0114%
(.1) (6) degree For out put in VRMS (as in spectral plots) multiply by /2.
4
and for Channel 2, Torsiograph Sensitivity = II* = 4.753 1 0.14%
d e The sensitivities for the post test calibration were found to be 4.750 and mV/V 4.730 for channels 1 and 2 respectively.
Multiplication factors for time domain response:
Ch 1.
Input, degrees-pk = (Output, Vpk) (4.213 9***'P)
Vpk Ch 2.
Input, degrees-pk = (Output, Vpk) (2.10edegr es-pk) and for frequency domain response:
Ch 1.
Input, degrees-pk = (Output, V<g3) (5.958 degrees-pk)
RMS Ch 2.
Input, degrees-pk = (Output, VRMS) (2.975 9"*S-@)
y RMS Unit 1 - Division 2 From Table 4.1 for Channel 1, TorsiographSensitivity=II[40 = 4.750 de ee ! 0.2%
and for Channel 2, 5
Torsiograph Sensitivity = II* = 4.730 d g ee t 0.2%
The - sensitivities for the post test calibration were found to be 4.747 and 4.727 d ree for channels 1 and 2 respectively.
Multiplication factors for time domain response:
Ch 1. '
Input, degrees-pk = (Output, Vpk) (4.211 degres-pk)
Ch 2.
Input, degrees-pk = (Output, Vpk) (2.114 degres-pk) and for frequency domain response:
Ch 1.
Input, degrees-pk = (Output, VRMS) (5.955 y M*N RMS Ch 2.
Input, degrees-pk = (Output, VRMS) (2.990 degrees-pk)
RMS 4.2 Variable Speed Results The variable speed test was performed to determine the frequency of the first mode of the crankshaft torsional system. The results of this test are shown in Table 4.3. Figures 4.1 and 4.2 show that the 4th order critical speed is reached at about 436 rpm for each crankshaft. Thus, the first natural frequency is 29.1 Hz. This is in good agreement with the Holzer calculation of 29.2 Hz made by Delaval [2].
6
The amplitude of nominal shear stress may be estimated from the ampli-tude of free-end vibration by assuming that the shaft is vibrating in its first mode. Under these conditions, the nominal shear stress in the number 8 crankpin journal and the number 9 main journal is 8596 psi per degree of free-end vibration (2]. Thus, the maximum amplitude of nominal shear stress during the variable speed test was 2923 psi for each crankshaft.
4.3 Variable Load Results The variable load test at rated speed was performed to determine the amplitude of vibration and estimate the nominal shear stress as a function of load. The results of this test are shown in Table 4.4. Figures 4.3 and 4.4 show that the amplitude of vibration increases with load to a maximum of 0.54 degrees at 7000 kW. The figures also show the response of the other major orders.
, The amplitude of nominal shear stress may be estimated from the ampli-tude of free-end vibration by assuming that the shaft is vibrating in its first mode. Under these conditions, the nominal shear stress in the number 8 crankpin journal and the number 9 main journal is 8596 psi per degree of free-end vibration (2]. Thus, the amplitude of nominal shear stress at full load is as follows:
Diesel Generator Nominal Torsional Stress at Full Load (7000 kW)
Single Order Combined Order Unit 1 - Division 1 1891 psi 4659 psi Unit 1 - Division 2 2020 psi 4642 psi DEMA (3] allowable 5000 psi 7000 psi 7
4.4 Startup/Coastdown Results Coastdown For the coastdowns monitored, the response of the crankshaft was found to be repeatable in both shape and magnitude. The maximum peak-to-peak ampli-tude recorded was found to be 0.96 degrees and occurs at the 8th order critical speed of approximately 218 rpm. The approximate length for a coastdown is 80 seconds.
An analytical model to predict the stress as a function of time during coastdown at each shaft section as well as the free-end rotational vibration was performed for the crankshaft at Perry. The analysis was performed using a cold compression curve with a peak pressure of 450 psi. It was found that with a damping of 1.5 percent of critical modal damping in each mode, the maximum peak to peak response was 0.93 degrees which is in good agreement with that measured in the torsiograph test.
The maximum amplitude of nominal stress was found to be 3970 psi and occurred between cylinders No. 7 and No. 8 based on the analysis. A comparison of the predicted and measured free-end amplitude time histories is shown in Figure 4-5. The good comparison of dynamic features is readily apparent in these plots. The time occurrence of some features are shifted due to the assumed linear change of angular velocity with time in the analysis.
Startuo The maximum peak-to-peak response for each of the four conditions tested in each engine is shown in Table 4.5 The mean maximum peak-to-peak response is 1.89 degrees for Unit 1 Division 1 and 1.84 degrees for Unit 1 Division 2. For each engine the maximum peak-to-peak response for each condition tested varied within 9% of the mean maximum peak-to-peak response (except for the one start that had a poor quality signal). The duration of a fast start was found to be 6 seconds.
8
-- , - - , - - - , , --m-------.----, ----- - - - , - - . - - - - --
The analytical model was used to determine the stresses in the crank-shaft during startup for each of the four conditions tested. The analysis was performed using pressure-time data recorded during a fast start at another plant (Ref. (4)], and using damping of 2.5 percent of critical modal damping in each mode. The analysis confirms that the effect of initial crankshaft position on the maximum peak-to-peak response is small. l The analysis indicates that the maximum amplitude of nominal stress for a typical fast start is 7650 psi and occurs between cylinders No. 7 and No. -
- 8. A comparison of the predicted and measured free-end amplitude time histories for a typical fast-start is shown in Figure 4-6.
5.0 CONCLUSION
S The following conclusions are made:
e the first natural frequency of the torsional system for each engine was found to be approximately 29.1 Hz, and is in good agreement with Delaval Holzer calculations [2]. Thus the 4th order critical speed is 436 rpm.
e for both Unit I diesel generators, the stresses in the crank-shaft are below DEMA's [3] allowables for both single order and combined order response at full load (7000 kW) for steady-state operation.
e The coastdown transient response is repeatable and has a maximum peak-to-peak amplitude of approximately 0.96 degrees, which produces a maximum amplitude of nominal stress of 3970 psi.
e A typical startup transient response produces a maximum peak-to-peak response of 1.86 degrees. Such a startup has a maximum amplitude of nominal stress of 7650 psi. This stress amplitude exists for only a few cycles on each startup.
e The results of the torstograph test indicate that the crankshafts are adequate for their intended service at perry nuclear Power Plant.
References
- 1. HBM Operating Manual for Rotary Vibration Transducer, 160.03-1.0-1.0e.
9
- 2. Yang, Roland, " Torsional and Lateral Critical Speed, Engine Numbers 75051/54 Delaval-Enterprise Engine Model DSRV-16-4, 7000 kW/9734 BHP at 450 RPM for Cleveland Electric Illuminating Co.," Delaval Engine &
Compressor Division, Oakland, California. !
- 3. Standard Practices for Low and Medium Speed Stationary Diesel and Gas Engines, Diesel Engine Manufacturers Association, 6th ed.,1972.
4 " Evaluation of Transient Conditions on Emergency Diesel Generator Crankshafts at San Onofre Nuclear Generating Station Unit 1," FaAA 84-12-14, Revision 1.0, April 1985.
l l
10 l
.~
Table 2.1: EQUIPMENT LIST Equipment Equipment Model Serial FaAA Manufacturer Descriptio.1, No. No. ID No.
HBM Rotary Vibration BD 5 701 n/a Transducer HSM SKHz Carrier KWS 7073 72984 n/a Frequency Amp.
Teac Cassette Data MR-30 116404 00138 Recorder B&K Precision Sweep / Function 3020 89-11576 00119 Generator B&K Precision Dual Trace 40MHz 1540P 11400731 00118 Oscilloscope Hewlett Packard Dual Channel 3582A LO39823 FFT Analyzer HBM cable (connect n/a n/a n/a transducer to amplifier) n/a cable (connect n/a n/a n/a amplifier to tape deck) n/a cable (connect n/a n/a n/a tape deck monitor to Spectrum analyzer or oscilloscope)
Fluke Digital Multimeter 8060A 8396137 00128 Hewlett Packard Dual Channel 5423A 2040A00345 00124 FFT Analyzer Hewlett Packard Plotter 7225B 1206A01534 00122 I
, 11
Table 3.1: TORSIOGRAPH TEST DOCUMENTATION Job Name: Perry Torsiograph Test Date:
Job Number: QRCEI Div. 1: 3/27/85 Location: Perry Nuclear Power Plant Div. 2: 3/28/85 Cleveland Electric Illuminating Co.
Engine
Description:
Unit 1, Div. 1 Unit 1, Div. 2 Transamerica Delaval Inc. Transamerica Delaval Inc.
DSRV-16-4 DSRV-16-4 Serial No. 75051 Serial No. 75052 Notes:
Test Personnel:
Steve Riess FaAA Paul Johnston FaAA Tony Pusateri CEI Mark Hickman CEI l
l j
12
Table 3.2: TORSIOGRAPH VARIABLE SPEED TEST Test Personnel: Steve Riess, FaAA Date:
Paul Johnston, FaAA Div. 1: 3/27/85 Tony Pusateri, CEI Div. 2: 3/28/85 Mark Hickman, CEI Unit 1 - Division 1 Tape I.D. Tape Footage Test Speed (RPM) 136-144 400 148-161 410 165-175 420 179-190 430 QRCEl-1 193-204 435 TORSIOGRAPH 207-216 440 TEST 222-230 450 242-250 460 262-271 470 278-289 425 Unit 1 - Division 2 Tape I.D. Tape Footage Tape Speed (RPM)
ORCEI-2 177-186 400 TORSIOGRAPH 192-200 410 TEST 204-210 420 215-233 425 226-232
)
430 236-242 435 ;
245-253 440 255-265 445
~268-275 450 278-287 460 304-312 470 13 l
Table 3.3: TORSIOGRAPH VARIABLE LOAD TEST Test Personnel: Steve Riess, FaAA Date:
Paul Johnston, FaAA Div. 1: 3/27/85 Tony Pusateri, CEI Div. 2: 3/28/85 Mark Hickman, CEI Test Speed: 450 rpm Unit 1 - Division 1 Tape I.D. Tape Footage load (kW)
QRCEI-1 410-418 1750 (25%)
Torsiograph Test 427-435 3500 (50%)
442-448 5250 (75%)
460-510 7000 (100%)
Unit 1 - Division 2 Tape I.D. Tape Footage Load (kW)
QRCEl-2 361-369 1750 (25%)
Torsiograph ,
Test 379-387 3500 (50%)
397-405 5250 (75%) j 423-432 7000 (100%)
l l
14 1
Table 3-4: PREDETERMINED INITIAL CRANKSHAFT POSITIONS FOR STARTUP TESTS Crankshaft Rotation Run I.D. w.r.t.1 LB TDC Firing (degrees) 1 LB TOC firing O' 7 LB TDC firing 180*
8 LB TDC firing 360' 2 LB TOC firing 540' 15
Table 3.5: STARTUP AND COASTDOW TESTS Test Personnel: Steve Riess, FaAA Date:
Paul Johnston, FaAA Div. 1: 3/27/85 Tony Pusateri, CEI Div. 2: 3/28/85 Mark Hickman, CEI Unit 1 - Division 1 Tape ID Tape Footage Startup/Coastdown ID 555-566 Cylinder ILB TDC Firing QRCEI-1 566-581 Cylinder 7'_8 TDC Firing Torsiograph Test 581-595 Cylinder 8LB TDC Firing 595-611 Cylinder 2LB TDC Firing Unit 1 - Division 2 Tape ID Tape Footage Startup/Coastdown ID ORCEl-2 469-485 Cylinder ILB TDC Firing Torsiograph Test 485-500 Cylinder 2LB TDC Firing 500-517 Cylinder 7LB TDC Firing 517-534 Cylinder 8LB TDC Firing 16
Table 4.1: PRE TEST STATIC CALIBRATION Unit 1 - Division 1 Static Voltage Output Teac Range Setting HBM Signal Cond. Setting Input (Vdc) (V/V) (mV/V) Ug (degrees) Ch. 1* Ch. 2* Ch. 1 Ch. 2 1RT'7 (V )
0 .005 .009 .1 .1 20 5
+3 .719 .726 .1 .1 20 5 0 .005 .010 .1 .1 20 5
-3 .705 .700 .1 *
.1 20 5 0 .003 .008 .1 .1 20 5
+3 .719 .726 .1 .1 20 5 0 .004 .010 .1 .1 20 5
-3 .705 .700 .1 .1 20 5 0 .002 .008 .1 .1 20 5 Unit 1 - Division 2 Static Voltage Output Teac Range Setting HBM Signal Cond. Setting Input (Vdc) (V/V) (mV/V) UB (degrees) Ch. 1* Ch. 2* Ch. 1 Ch. 2 TU 7- (V )
0 .004 .008 .1 .1 20 5
+3 .722 .721 .1 .1 20 5 0 .009 .013 .1 .1 20 5
-3 .703 .698 .1 .1 20 5 0 .006 .009 .1 .1 20 5
+3 .722 .721 .1 .1 20 5 0 .009 .010 .1 .1 20 5
-3 .704 .697 .1 .1 20 5 0 .006 .009 .1 .1 20 5
t Table 4.2: POST TEST STATIC CALIBRATION Unit 1 - Division 1 Static Voltage Output Teac Range Setting HBM Signal Cond. Setting Input (Vdc) (V/V) (mV/V) Ug (degrees) Ch. 1* Ch. 2* Ch. 1 Ch. 2 WT (V )
0 .011 .018 .1 .1 20 5
+3 .727 .730 .1 .1 20 5 0 .012 .020 .1 .1 20 5
-3 .698 .689 .1 .1 20 5 0 .011 .019 .1 .1 20 5 l
+3 .727 .730 .1 .1 20 5 l 0 .015 .021 .1 .1 20 5
-3 .697 .689 .1 .1 20 5 0 .012 .019 .1 .1 20 5 Unit 1 - Division 2 Static Voltage Output Teac Range Setting HBM Signal Cond. Setting Input (Vdc) (V/V) (mV/V) Ug (degrees) Ch. 1* Ch. 2* Ch. 1 Ch. 2 10 V (V )
0 .014 .022 .1 .1 20 5
+3 .729 .733 .1 .1 20 5 l 0 .015 .022 .1 .1 20 5
-3 .695 .685 .1 .1 20 5 l 0 .014 .021 .1 .1 20 5 1
+3 .730 .734 .1 .1 20 5 l
0 .016 .024 .1 .1 20 5
-3 .695 .686 .1 .1 20 5 0 .013 .020 .1 .1 20 5 i
f t .002 Vdc 18
7 Table 4.3: VARIABLE SPEED RESPONSE Unit 1 - Division 1 Asolitude of free-end' vibration (millidegrees) for given speed (rpm)
Order 4)3 412 423 428 434 438 443 454 463 474 0.5 6 11 9 6 10 13 11 11 9 12 1.0 2 2 2 2 1 0 1 1 1 1 1.5 39 40 40 40 40 40 40 41 41 41 2.0 6 7 8 8 9 11 12 13 14 16 2.5 55 56 57 58 58 59 60 62 64 65 3.0 2 2 2 3 2 2 1 2 2 3 3.S 39 42 46 49 52 56 61 74 93 130 4.0 37 55 99 153 240 211 140 80 57 43 4.5 68 43 31 27 23 20 19 15 13 10 l 5.0 2 2 2 2 22 2 2 2 2 2 5.5 ' 9 8 7 6 6 5 5 4 4 5 6.0 4 5 6 7 8 7 5 3 3 3 Total 170 170 210 260 340 290 240 230 230 240 i Unit 1 - Division 2 Amplitude of free-end vibration (millidegrees) for given speed (rpm)
Order 400 410 420 425 431 435 439 445 451 460 470 0.5 5 6 4 4 5 5 5 7 6 6 5 1.0 1 1 1 1 2 2 2 2 2 3 3 1.5 38 39 39 38 38 38 39 39 39 39 40 2.0 6 6 7 8 8 9 11 12 12 14 15 2.5 57 59 60 60 60 61 62 64 64 66 68 3.0 3 3 4 4 4 3 3 4 4 5 5 3.5 36 40 43 45 48 51 56 61 66 81 107 4.0 26 40 66 96 151 25' 186 122 89 48 43 4.5 91 50 34 29 25 L 20 18 16 13 10 5.0 2 1 1 1 1 2 2 2 2 2 2 5.5 10 8 7 7 7 6 5 5 4 4 4 6.0 5 5 5 6 7 8 6 4 4 3 3 Total 185 165 160 200 255 340 270 235 215 205 230 19
Table 4.4: VARIABLE LOAD RESPONSE Unit 1-Division 1 Amplitude of free-end vibration (millidegrees) for given load (kw)
Order 0 1750 3500 525) 7000 0.5 22 55 95 72
~
93 1.0 2 4 5 5 5 1.5 43 67 103 137 181 2.0 12 9 6 4 1 2.5 64 89 130 173 220 3.0 2 2 2 5 8 3.5 72 94 133 173 201 4.0 94 85 95 92 130 4.5 16 18 27 38 26 5.0 2 3 3 4 5 5.5 5 6 9 12 14 6.0 3 5 7 9 10 Total 225 273 368 417 542 Unit 1 - Division 2 Amplitude of free-end vibration (mil 11 degrees) for given load (kw)
Order 0 1750 3500 5250 7000 0.5 7 6 13 34 55 1.0 3 3 3 3 1 1.5 41 64 98 138 184 2.0 11 8 5 5 7 2.5 68 96 138 185 235 3.0 4 7 8 7 4 3.5 69 93 129 172 205 4.0 88 69 80 133 141 4.5 15 19 29 41 52 5.0 1 1 1 2 1 5.5 5 6 10 12 14 6.0 4 6 8 11 12 .
Total 215 240 330 445 540 20
r _ __ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ .
Table 4.5: STARTUP RESPONSE l
l Maximum Peak-to-Peak Free-End Vibration Fast Start ID (degrees)
Unit 1 Unit 1 Division 1 Division 2 1 LB TDC Firing 2.39* 1.90 7 LB TDC Firing 1.80 1.68 8 LB TDC Firing 1.61 1.76 2 LB TDC Firing 1.75 2.00
\
l Torsiograph data for this test was determined from a noisy signal, t
21
0.6 , , , , , , ,
^
- c. O Total response e 4th order response
$ O.5 - _
. A 3-1/2 order response 8 Natural frequency: 29.1 Hz E
I 0.4 - -
e Q
Z "m 0.3 - -
m E
to E
C ; O O O.2 - -
m -
t::
0.1 - -
^ -
_7 .
0 400 410 420 430 440 460 460 470 480 y ENGINE 8 PEED (rpm) a T Figure 4-1. Variable speed response of Unit 1. Division 1.
t
- Amplitude of nominal shear stress is 85% psi / degree of free-end vibration, assuming the shaft is vibrating in its first mode.
0.8 , , , , , , ,
G Total response 3, a 4th order response 3 '
A a-1/2 order response g Natural frequency: 29.0 Hz 9
P-g 0.4 - -
a c
2
" 0.3 - -
m m
E ts.
O 0.2 "
m _
O . -
t:
a
$ 0.1
=
i r 0 ' ' ' ' ' ' '
400 410 420 430 440 450 480 470 480
, , ENGINE SPEED (rpm)
S Y
h Figure 4-2. Variable speed response of Unit 1, Division 2.
t
- Amplitude of nominal shear stress is 85% psi / degree of free-end vibration, assuming the shaft is vibrating in its first mode.
o o
I i i i i o, e
o
. o e o
e d T.
oe QJ V 6
o *O *
- O .wa 9 -
- o. .-. o @
u
>= C0-oow e u m Cn m
-GG
>V O
o -e-e s "
o = .m-e n .-. a m 3
.= .a-mu #5
=
ll
=
os o(
o 5*2 w--
m .o god o,>
Gmm E **
e o o""
o i.
o "*%
o< e o u .c
- s. m m Aw m2e ll z = m .c w o a o e eee
- o . - -
o 185
>c e o .& .
ne c.- o o .
oc o , ,,
'4 ,
o m 2 .a i ua
-3 d *"2 e e-o on e an u -
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- of s," _ o '
e o.
ea4
' 4: b o
@*P) .NOl1VWWA ON3-33Wd 40 BOf1D'WMV FeAA-85-4-1
- e 0.6 , , , , , , , ,
? ., _
. ro..i ,e.po..e _
3 a 4th order response g A 31/2 order response 9
g 0.4 - -
=
- O 2
- W 0.3 - -
i =
j IRA
- E i As.
i-f o 0.2 -
nel D
i 3 C g -
0.1, 4: d i 0 O 1,000 2,000 3,000 4,000 5,000 6.000 7,000 8,000 0,000
, GENERATOR LOAD (kw)
S T
h figure 4-4. Variable load response of Unit 1, Division 2.
?
- Amplitude of nominal shear stress is 85% psi / degree of free-end
- vibration, assuming the shaft is vibrating in its first mode.
i .
1
. . _ . _ ._..._..__m.. m -,_ _ .-.. _ . - - - _ . . . -_ - _ . _ - _ .-- . . . ~_ u_... _ ..m. - . .. ___-mu .__ .
w s
. I 1 0
4 0 ea 0 1 g g g j g t t I
, e e e e e te et el j , .
i , ,
e i I 8
- , , . . e i
$55Y ==
1
- e i
, e i
- . . i l i 0 I g i - . .
i .
c s ,
j - - ,,
l I tnf (5 E C O N D SD 1
l _ _ _ _ . . . . _ . _ . . _ . . _ _ _ . _ _ . _
! Figure 4-5. Comparison of predicted and measured free-end amplitudes during a typical coastdown.
3 a
I 1
4 1
0
<1 e I e 4
as i( l .
- a
} I I a
.5 1
D I I I I I I 1 I I I I I i _ i I i FREE-END AMPL1TUDE lglj jl (DEGREES)
, [jMQ I 8
-[,h kd d ll ,j, f 2 LB DC FlR NG 'F lT' '! i
.i _
l i I I I I I I I
-2 .
l l l l l 1 I I I 2 _
I l l I l l 1 -
1 I I (DEGREES)
ANALfitCAL NODEL
, k hn (i hk j 2 LB TDC FIRING l- pg l ll 1 i
-l
- g ,
-i - l l l l I I
-2 -
I I l l I i l l f f l 2 3 4 5 TIME. (S E C 0 N D S)
Figure 4-6. Comparison of predicted and measured free-end amplitudes.
FaAA-46-4-1