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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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:UTILITY TO NRC
MONTHYEARPY-CEI-NRR-1226, Forwards LERs 90-018-00 & 90-019-00 for Plant1990-09-14014 September 1990 Forwards LERs 90-018-00 & 90-019-00 for Plant PY-CEI-NRR-1218, Responds to Generic Ltr 90-07 Re Proposed OL Exam Schedule, Operator Requalification Schedule & Generic Fundamental Exam Schedule for Plant.Licensee Will Continue to Train & Requalify Operators on Annual Basis1990-09-10010 September 1990 Responds to Generic Ltr 90-07 Re Proposed OL Exam Schedule, Operator Requalification Schedule & Generic Fundamental Exam Schedule for Plant.Licensee Will Continue to Train & Requalify Operators on Annual Basis ML20059E8741990-09-0505 September 1990 Forwards Fourteenth Quarterly Rept Cleveland Electric Illuminating Co Seismic Monitoring Network Jan-June 1990. Five Microevents Originating within Network & Three Other Events Originating Outside of Network Recorded PY-CEI-NRR-1216, Forwards Perry Nuclear Power Plant Unit 1 Semiannual Radioactive Effluent Release Rept,1990 Quarters 1 & 2. Response to Recommendations from NRC Re Range of Dilution Flows Will Be Submitted W/Next Effluent Rept1990-08-29029 August 1990 Forwards Perry Nuclear Power Plant Unit 1 Semiannual Radioactive Effluent Release Rept,1990 Quarters 1 & 2. Response to Recommendations from NRC Re Range of Dilution Flows Will Be Submitted W/Next Effluent Rept PY-CEI-NRR-1201, Forwards First Semiannual fitness-for-duty Rept for Plant for 900103-0630,per 10CFR26.71(d) Requirements1990-08-28028 August 1990 Forwards First Semiannual fitness-for-duty Rept for Plant for 900103-0630,per 10CFR26.71(d) Requirements PY-CEI-NRR-1211, Responds to NRC Re Violations Noted in Insp Rept 50-440/89-26.Corrective Actions Noted:Necessary Engineering Design Mods Which Evaluation Found Necessary Contained in DCP 90-00861990-08-23023 August 1990 Responds to NRC Re Violations Noted in Insp Rept 50-440/89-26.Corrective Actions Noted:Necessary Engineering Design Mods Which Evaluation Found Necessary Contained in DCP 90-0086 PY-CEI-NRR-1210, Proposes Date of 901207 to Provide Updated Status & Schedules,Per 900604 Request for Addl Info on Disposition of Bulletin 88-005 Product Forms Other than Pipe Fittings & Flanges Received at Plant1990-08-17017 August 1990 Proposes Date of 901207 to Provide Updated Status & Schedules,Per 900604 Request for Addl Info on Disposition of Bulletin 88-005 Product Forms Other than Pipe Fittings & Flanges Received at Plant PY-CEI-NRR-1208, Responds to NRC 900613 Request for Addl Info Re Inservice Insp Relief Requests.Util Revised Relief Requests PT-001 & PT-003 to Provide More Detailed Info & Has Withdrawn Relief Request IR-017.Revised Relief Requests & Summary Encl1990-08-10010 August 1990 Responds to NRC 900613 Request for Addl Info Re Inservice Insp Relief Requests.Util Revised Relief Requests PT-001 & PT-003 to Provide More Detailed Info & Has Withdrawn Relief Request IR-017.Revised Relief Requests & Summary Encl PY-CEI-NRR-1203, Provides Estimate Duration Schedule Re Installation of post-LOCA Neutron Monitoring Sys.Util Will Evaluate Effect of Resolution on Schedule & Confirm or Revise Installation Date as Needed,When Appeal & Criteria Questions Resolved1990-07-27027 July 1990 Provides Estimate Duration Schedule Re Installation of post-LOCA Neutron Monitoring Sys.Util Will Evaluate Effect of Resolution on Schedule & Confirm or Revise Installation Date as Needed,When Appeal & Criteria Questions Resolved PY-CEI-NRR-1200, Forwards Decommissioning Repts on Financial Assurance for Plant1990-07-25025 July 1990 Forwards Decommissioning Repts on Financial Assurance for Plant PY-CEI-NRR-1196, Forwards Rev 0 to Inservice Exam Program. Program Serves as 10-yr Rev to Inservice Insp Program Plan1990-07-24024 July 1990 Forwards Rev 0 to Inservice Exam Program. Program Serves as 10-yr Rev to Inservice Insp Program Plan PY-CEI-NRR-1205, Forwards LERs 90-014-00 & 90-015-00 for Plant1990-07-20020 July 1990 Forwards LERs 90-014-00 & 90-015-00 for Plant PY-CEI-NRR-1193, Responds to Generic Ltr 90-04 Re Implementation Status of Generic Safety Issues1990-06-29029 June 1990 Responds to Generic Ltr 90-04 Re Implementation Status of Generic Safety Issues ML20043H7371990-06-19019 June 1990 Forwards Individual Plant Exam Project Milestones.Milestones Subj to Change from Project or External Causes & Will Not Be Docketed Again Unless Significant Impact on Final Rept Contents or Submittal Date Exists ML20043H1711990-06-14014 June 1990 Discusses Util Radiological Safety Board of Ohio 900614 Comments on Notice of Opportunity for Hearing Re Rev to Previously Submitted License Amend Application.Licensees Would Welcome Opportunity to Consult W/State of Oh ML20043E5771990-06-0808 June 1990 Provides Info Re Implementation of Administrative Controls & Training Related to Use of Tech Spec 3.0.4.Util Intends to Implement Amend 30 Changes by 900618.All Licensed Operators Would Receive Training to Generic Ltr 87-09 ML20043B6981990-05-21021 May 1990 Forwards Info Re Activation Energy Values Utilized for Brand-Rex Co Cable at Facility.Encl Includes Rept, Qualification Tests of Electric Cables for Class 1E Svc in Nuclear Power Plants. ML20043A7041990-05-18018 May 1990 Forwards LERs 90-007-00 & 90-008-00 ML20043A4771990-05-16016 May 1990 Provides Justification Re Events Leading to Declaration of Alert on 900403 Due to Loss of Emergency Svc Water When Manway Flange Gasket Leak Developed at Pump a Discharge Strainer,In Response to Ocre 900406 Petition ML20042F4931990-05-0404 May 1990 Forwards Response to Generic Ltr 89-19 Re Reactor Vessel Overfill Protection ML20042F1961990-04-27027 April 1990 Informs of Adoption of Reorganization Plan Re Plants on 900424.Reorganization Will Make No Changes in Technical or Financial Qualifications for Plants.Application for Amends to Licenses Adding Company as Licensee Will Be Submitted ML20042F8051990-04-19019 April 1990 Forwards 1989 Financial Repts for Centerior Energy Corp, Cleveland Electric Illuminating Co & Toledo Edison Co & Supplemental Sec Form 10-K ML20012F3521990-04-0202 April 1990 Suppls Response to NRC 891215 Ltr Re Deviations Noted in Insp Rept 50-440/89-26.Corrective Actions:Profile of Heat Generation from Stored Fuel Vs Time for First Four Fuel Load Discharges Calculated & Design Changes Implemented ML20012E7811990-03-30030 March 1990 Confirms Basis for 890417 Submittal Re Station Blackout ML20012E9431990-03-26026 March 1990 Forwards Correction Pages to Semiannual Radioactive Effluent Release Rept 1989:Quarters 3 & 4. Changes Affect Liquid Effluent Data Only.Corrections Made Due to High Contribution of Sr-89 to Liquid Effluent Dose ML20012B9851990-03-0909 March 1990 Responds to Generic Ltr 90-01 Re Regulatory Impact Survey ML20012B5931990-03-0808 March 1990 Responds to Open Item Noted in Insp Rept 50-440/89-29. Corrective Actions:Plant Health Physicist & Operations Superintendent Met W/Health Physics & Operations Crews to Discuss Better Methods of Access Control ML20012A1561990-03-0202 March 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Addl Info in Response to NRC 890605 Ltr Re Offsite Dose Calculation Manual ML20012B9801990-03-0202 March 1990 Responds to 890810 Request for Addl Info on Util 890306 Tech Spec Change Request Re MSIV Leakage Limits.Change Does Not Request Increase in MSIV Leakage Beyond Currently Assumed in Updated SAR Chapter 15 ML20006E5131990-02-12012 February 1990 Lists Suggestions on Subj Areas to Be Addressed During Proposed 1990 Licensee Info Conference,In Response to 900117 Ltr ML20006E3211990-02-0909 February 1990 Discusses Implementation of Facility Revised Inservice Testing Program,Per Generic Ltr 89-04.Improvements Listed, Including sign-off Matrix Deletion at End of Instruction & Movement of Comments Section ML20006D0971990-02-0202 February 1990 Provides Update to 880721 Ltr Re Performance of Seismic Margin Evaluation.Util Awaiting Issuance of Individual Plant Exams of External Events Generic Ltr Prior to Proceeding W/ Seismic Margins Study ML20011E1841990-02-0202 February 1990 Forwards LERs 90-001 & 90-002 ML20006D5731990-01-30030 January 1990 Forwards Response to NRC 900112 Request for Addl Info Re 891121 Request for Exemption from Filing Requirements of 10CFR55.45(b)(2)(iii).Qualification Plan for Certification of Existing Simulator Approved in Aug 1987 ML20006B5131990-01-26026 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of Type 410 Stainless Preloaded Bolting in Swing Check Valves.No Bolts Subj to Bulletin in Use at Facility ML20006B5571990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Procedures in Place for Underwater Insp of Intake Structures in Lake as Well as on-shore Pump Houses Annually ML20006A0781990-01-16016 January 1990 Responds to NRC 891215 Ltr Re Deviations Noted in Insp Rept 50-440/89-26.Corrective Actions:Profile of Heat Generation from Stored Fuel Vs Time for First Four Fuel Discharges Calculated & Updated SAR Change Request Will Be Submitted ML20005F9331990-01-0909 January 1990 Provides Inadvertently Omitted Inequality Signs from Util 891213 Response to NRC Bulletin 88-004 Re RCIC Pump Min Flow Limitations from Operating Instructions ML20042D5051990-01-0303 January 1990 Informs That Licensee Implemented fitness-for-duty Program at Plant on 900103,per 10CFR26.More Stringent cut-off Levels Imposed by Util than Required by 10CFR26 ML20005E1391989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance.Each motor- Operated Valve Will Be Stroke Tested to Verify Valve Operability at no-pressure & no-flow Conditions ML19332F7941989-12-13013 December 1989 Responds to NRC 890531 Request for Addl Info Re NRC Bulletin 88-004, Safety-Related Pump Loss. Info Covers pump-to-pump Interaction That Could Result in Deadheading & Adequacy of Min Flow Bypass Lines Against Pump Damage ML19332E6921989-12-0707 December 1989 Responds to Violations Noted in Insp Rept 50-440/89-12 on 890627 & 1023.Corrective Actions:Flange Leakage of Relief Valve Repaired During First Refueling Outage & Design Mods to Enhance Testability of Gasketed Flanges Being Developed ML19332F3851989-12-0606 December 1989 Forwards Twelfth Quarterly Rept Cleveland Electric Illuminating Seismic Monitoring Network,Jul-Sept 1989. Rept Describes Area in Vicinity of Two Waste Injection Wells Located 3 Miles South of Plant Site ML19332E7971989-12-0101 December 1989 Responds to Generic Ltr 89-21 Re Implementation Status of USIs ML19332E3611989-11-28028 November 1989 Submits Supplemental Info Re Tech Spec Change Request Proposing Addition of Requirement to Verify Trip Setpoint of Intermediate Range Monitor Control Rod Block Instrumentation During Performance of Weekly Channel Functional Testing ML19332D5771989-11-27027 November 1989 Submits Supplementary Info to 880520 Tech Spec Change Request,Changing Setpoints for Turbine First Stage Pressure to Reflect Values Actually Measured During Startup Test Program at 40% of Rated Reactor Power.Table Encl ML19332C7341989-11-22022 November 1989 Forwards Executed Amend 3 to Indemnity Agreement B-98 ML19332C4041989-11-22022 November 1989 Responds to NRC 891025 Ltr Re Violations Noted in Insp Rept 50-440/89-23.Corrective Actions:Work Stopped on Div III & Restoration Began to Return to Operation & All Actions Required by Tech Spec 3.0.3 Completed ML19332C8321989-11-21021 November 1989 Forwards Inservice Insp Summary Rept NP0059-0001, Results for Outage 1 (1989),First Period,First Interval, Vols I & Ii,Covering Insp Period 871118-890805 ML19332C4531989-11-21021 November 1989 Requests Exemption from Requirements of 10CFR45.(b)(2)(iii), to Allow for Submittal of NRC Form 474, Simulation Facility Certification, After 910326 Deadline 1990-09-05
[Table view] |
Text
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P O. Box 5000 - CLEVELAND. OHIO 44101 - TELEPHONE (216) 622-9800 - lLLUMINATING BLDo - S$ PUBLICSQUARE Semng The Best Location in the Nation MURRAY R. EDELMAN VICE PRESIDENT NUCLEAR September 13, 1985 PY-CEI/NRR-0336 L Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Comraission Washington, D. C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Pool Dynamic Loads SER Open Item (9)
Dear Mr. Youngblood:
The purpose of this letter is to provide further clarification to our May 16, 1985 letter and to resolve staf f concerns regarding the PNPP design f or LOCA-Related Hydrodynamic Loads.
Attachment 1 to this letter provides a copy of the Draf t Acceptance Criteria used to modify the GESSAR 11 methodology in the PNPP design for LOCA-related pool dynamic loads. It is Appendix C to the Draft Technical Evaluation Report on Mark III LOCA-Related Hydrodynamic Load Definition provided by letter dated October 8,1982 f rom Mr. T. Speis (NRC) to Mr. H. Pfef ferlen (GE). CEL committed to meet this version of the draf t acceptance criteria in a letter dated January 31, 1983. This commitment was reflected in Appendix 3B in Amendment 11 to the FSAR dated February 15, 1983.
Attachment 2 to this letter is a supplemental clarification of our response to Item 4 of the May 16, 1985 letter, regarding submerged drag loads due to chugging (3B.8.1.6). This response further supports the conclusion that, based on our design methodology, the drag loads associated with the chugging phase of a LOCA are bounded by the conservative LOCA loads used in our design.
Attachment 3 consists of the proposed revisions to FSAR Appendix 3B pages to clarify our design methodology.
8509190422 850913 PDR ADOCK 05000440 E PDR e
la ls
i Mr. B. J. Youngblood September 13, 1985
. PY-CEI/NRR-0336 L j~
Finally, Attachment 4 provides the methodology of our evaluation of the impact
- loads on short structures and' structures close to the pool surface, using the revised NRC impact criteria.
i We believe that this information resolves all outstanding NRC staff concerns regarding the LOCA-related hydrodynamic load definition utilized at PNPP and should enable Outstanding Issue (9) to be resolved in the next supplement to the SER.
Very truly yours
@k Murray R. Edelman Vice President Nuclear Group j MRE:njc Attachments l cc: Jay Silberg, Esq. ,
John Stefano (2)
, J. Grobe
+
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o ATTACHMENT l uf .
h, UNITED STATES o
3 NUCLEAR REGULATORY COMMISSION f wAsmNcToN. o. c. 20ses N *...*) 00T 8 1982 Mr. Hank Pfefferlen, Manager BWR Licensing Programs General Electric Company M/C 682 175 Curtner Ave.
San Jose, CA 95125
Dear Mr. Pfefferlen:
Enclosed is a copy of the staff's draft technical evaluation report on the Mark III LOCA-related hydrodynamic load definition for sur review and comment. Our evaluation was based on the information contained in Appendix 3B of GESSAR-II and the reports refenrced therein. In your review, please focus on whether we correctly interpreted the informa-tion you furnished and identify those treas where we are quoting infor-mation you consider to be proprietary.
We plan to issue the final version of this report by January 1983 and will need any comments the General Electric Company may have on the ma-h terial contained in the report by early December 1982. If you believe that 6 meeting to discuss your comments on our report would be useful, please contact Mr. M. Fields at 492-9417 to arrange for such a retting.
Sincerely.
Themis P. Spets. Assistant Director for Reactor Safety Division of Systems Integration
Enclosure:
As stated I
m
+ pq> Pj
I 4 l Appendix C NRC Acceptance Criteria for LOCA-Related Mark III Containment Pool Dynamic Loads The following acceptance criteria were developed from the staff's review of Appendix 3B of GESSAR-II 238 Nuclear Island (GESSAR) and the supporting analytical and experimental programs as referenced therein. The staff has determined that the procedures described in the GESSAR are accsptable for evaluation of the Mark III conta16 ment response to LOCA-related pool dynamic loads with the following exceptions, modifications, qualifications and/or clarifications:
- 1. 0 Pool Swell Loads 1.1 pool Swell Velocity
/
The water slu; velocity V tc be u:ed fer me cetereinaticn of slug drag loacs, )
as well as slug impact Icads as prescribed in 1.2,1.3 and 1.5 below, shall be determined frcm the relation:
V = 5 H (2.6 - 0.506 JH); H < 10 ft, and
- Y = 50 ft/sec H > 10 ft .
In these relations, V is the slug velocity in feet per second (fps), H denotes the height (in feet) above the initial pool surface.
- 1. 2 Pool Swell toads _on Structures Attached to the Containment Walls The GESSAR-II specification for these loads is given in Section 38.6.1.5. It is based on steady drag at a flow velocity of 40 ft/sec. The specification needs to be modified to make it acceptable.
8 (1) If the local pool swell velocity', as specified in Section 1.1 above, is greater .then 40 f t/sec, the drag pressures obtained by the GESSAR
r eG. um ureen eu s s e ve ce co 11: 4< e.
,, g g specification shall be multiplied (V/40)2, where V is the local pool velocity in ft/sec.
(2) If the frontal area of the structure is not immersed prior to pool swell, it will experience an impact force. This must be included in the specification.
For half wedge protrusions the force history during impact shall be determined from Figure C-1. The local velocity of impact (needed in '
Figure C-1) shall be taken from the specification in Section 1.1, corre-sponcing to the height where the wedge is first fully submerged. If the lower portion of the wedge is initially submerged, the same impact history is applied except the abscissa is replaced by Vt/h, where h is the "unsubmerged height of the wedge.
If the wedge angle is other than 45', the following ratios can be used after obtaining the force history for a 45* wedge from Figure C-1.
tO F
= (50? p) e t p, and (C-1)
= cot S
where $ is the wedge angle.
1 .
For horizontal ledges the impact force shall be determined in the following manner:
(a) The force history will have a triangular shape as shown in Figure C-2.
(b) Determine the hydrodynamic mass of impact (per unit area) for flat targets from Figure 6-8 of NEDE-13426). Use b (and not b/2) for target width.
O .
C-2
D 0
. b
. . . 4 gP ,
. t a time, sec. ,
3 p = density, slugs ft F = impact force,1bf .
W >
. U i
b s/2 . .,
( -
Drag .
. \
. g .
. \
0- - -
1'. o .
i.s . i.o 2Vt/b Figure C-1 Impact Force (per unit length) on Wedge-$ha' ped Protrusions from the Containment Well ..
C-3
. -- . . . _ __ . _ . . - _ _ . __ __ ._ ~ _ . . _ _ __ ___ _ __ _ _ . _ _ _
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,a b
-*- 2 +l- .
1 V
i V .
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j Figure C-2 Impact Pressure on Nortrontal Ledges Attached 4e Containment Wall i
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(c) Calculate the impulse using the equation b 1
~ IP*T Y " (32.2)(144) (C-2) where:
Ip = impulse per unit area, psi-sec p a hydrodynamic mass per unit area, ibm /ft, from,(b) above.
V
= impact velocity, ft/sec, determined according to Section 1.1.
(d) Calculate the pulse duration from the equation t=0.02h(h) (C-3) where:
C 1 = pulse duration, sec H = height above tr.c pec1, feet b/2 = width'of the ledge, feet V
= impact velocity, ft/sec, determined according to Section 1.1 (e) The value of P, will be obtained using the following equation:
P, = 2 Ip /t ,
(C-4) where: ,
t P, = the peak pressure amplitude, psi.
1.3 Bulk Impact loads on Small structures "Small structures", in the present context, are defined as beams and pipes O ita 1 t r i ai a taa ao i rs r sa a 2o $aca - rar ta. tructur ta-bulk impact specification, as described in Section 38.10.11 of CESSAR-II, is C-5
-,-------m - -,- -
p w , ,- -- ,-v w , -- -
.- 1 1
acceptable with the specific limitations discussed in Section 380.3.2.33 of Attachment 0 (Question / Response 38.33).
o (1) Targets must have combinations of widths and natural frequencies such that Figures 38.33-1, 2, 3 and*4 indicate them to be in the "GESSAR conservative" region with respect to the V = 50 ft/see pool velocity curve.
(2) There are no structures smaller than 4 feet long.
(3) There are no structures closer than 6 feet above the pool.
For those structures that do no meet limitations 2 and/or 3, the pulse width and amplitude of the bulk impact specification described in Section 38.10.11 of GESSAR-II should be modified as follows:
() (1)
For structures smaller than four feet long, reduce the GE specified pulse width (7 esec for radial criented structuros; 2 msee for circumferential oriented structures) by f, where x is the actual length of the structure in question.
(2) .
For structures closer than six feet above the pool, reduce the GE specified pulse width by {, where y is the actuale 'levation of structure in question.
For structures less than 10 feet above the pcol, the amplitude may be reduced by .
=
3 h = i g (2.6 - 1.6 h )8 max max
- where A is the amplitude at a structure H feet above the pool surface and A ,,
T is the GE-specified amplitude for bulk impact on small structures above the
'Q_,) Voole O
9 C-6 -
/ 1. 4 Froth Impact Leads The froth impact specification is applicable between an elevation of 19 feet above the pool and the HCU floor.
Over open areas of the HCU floor this specification extends to an elevation of 26 feet for flat structures and 28.5 feet for pipes. . Between these elevations and 30 feet the froth drag specificatico in GESSAR-II, Section*38.12 is app 1 feeble.
The forcing function for froth impact shall be an Isosceles triangle with a maximum amplitude given in Figure C-3.
The pulse duration shall be chosen such as to give a maximum OLF with a triangular pulse.
For elongated structures that span the annulus of the wetwell, pulse durations shorter than 50 esec need not be considered.
1.5 Drac_ Loads The GE5SAR-II specification for drag loads on small structures, as describ h in Section 38.10.2, is acceptable with the following limitation.
If the local pool velocity, as specified in section 1.1 abeve, is grcater than ao ft/sec ,
the dra; forces cbtained by the GESSAR-!! specification shall be ymultiplied a (V/40)2 where V is the local velocity in ft/sec.
If Figure 38-75 in GESSAR-II is used for drag loads on plates and if the -
shorter side (b) is attached to a well, the abscissa of the graph becomes 2a instead of a/b.
2.0 loads on Submerced Structures The procedures for the codpu'tation of loads on su6 merged structures as in sections 3.8.8 to 3.8.8.1.1 and Attachment L of GESSAR are acceptablej subject to the limitations and/or modifications of Section Attachment 0. 3.8.0.3.2.31 of In particular, the computation of acceleration loads on non-cylindrical structures and the evaluation of standard drag for C0 loads must be based on the Mark I Acceptance Criteria (NOREG 0661) as described in the
' responses to questions 3.8.31(b. f t), (c. ii) and (c.111) in Attachment 0.
C-1 ~
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_ Nac' ACCEPTANCE CRITERI A A ,
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Figure C 3 NRC Acceptance Criteria for Froth Impact: * ,
Peak Amplitude of Pressure Pulse
. C.g '
- 3.0 Impact loads on Structures Above the Weir Annulus (4
- -;TW The staff finds ^th4 GESSAR-!! impact specification on structures above the weir wall, with the exception of radial structures within one foot of the top
,; of weir wall.
The stresses in these structures must be increased by a multiplier. ,
This multiplier is 1.0 when the natural fregancy of the structure is less than 200 Hz, 1.8 when the natural frequency is greater than 500 Hz with a linear ramp between these values.
Forstructureslocatedbetweenzeroand0.25feetabovethe[a wall, flat pool impact should be considered (e.g., the acceptance criteria in Section 2.7 of Appendix A, NUREG 0661 is appropriate for flat pool impact). The velocity at impact for these structures shall be taken at 4 ft/sec.
e C
4 9
C9
ATTACHMENT 2 RESPONSE TO 35.8 1 6 Chugging Loads For piping and other items in the pool, the conservative PNPP design definition used for SRV and LOCA submerged drag loads, envelopes the GESSAR 11 chugging drag load when combined with the GESSAR 11 Nethod of Images technique for calculating SRV drag loads.
For piping, the LOCA submerged drag load was calculated based on bubble pressure attenuation (10psid applied statically with a minimum DLF of 1 2).
The chugging DLF times the method of images pressure calculated as shown in CESSAR 11 section 3BL2.9 is significantly less than the LOCA load used.
Therefore, the conservative LOCA submerged drag load definition bounds the SRV + Chug load definition for piping. '
For the columns, chugging was included in the design using the appropriate DLF.
For the strainers, a DLF was calculated and when multiplied times the chugging pressure is less than 0 5 psi. This load, when combined with SRV, is bounded by the submerged drag load of SRV 1 valve 2nd pop. Therefore, the SRV + chug load combination is bounded by the SRV second pop used for design of the strainers.
i 1
0 1
i
ATTACHMENT 3 6
6 APPENDIX 3B CONTAINMENT LOADS e
a
_a- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ . _ . . . . . _ _ _ _ . . _ . - . _ . _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ . _ _ . .
D-PREFACE h is section has been revised to delete the GESSAR Appendix 3B which had been reproduced as Appendix 3B of the PNFP PSAR. The following section follows the format of GESSAR II - Rev. 2 Appendix 3B and provides a step-by-step Perry
. specific comparision. GESSAR II, as modified by Draft Acceptance Criteria a (Reference 1: Appe:ndix C to the Draf t Technical Evaluation Report on Mark III l LOCA-Related Hydrodynamic Load Definition provided by memo dated 10/8/82 from Mr. Thesis P. Speis (NRC) to Mr. Hank Pfefferlen (GE))is the basis for the PNPP design.
G 5
35-1
m ,m.(-W--+.g
APPENDIX 35 CONTATNMENT IDADS
38.1 INTRODUCTION
i
. No deviations.
3B.1.1 CONFIRMATORY TESTINC i
No deviations.
38.1.2 DEFINITION OF LOCA No deviations.
35.1.3 DESICN MARCINS No deviations.
l 38.2 REVIEW OF PHENOMENA No deviations.
38.2.1 DESIGN BASIS ACCIDENT (DBA)
CESSAR FiBures 3B-2 through 38-6 are not applicable to Perry. See FSAR Figures 3B-1 through 38-5.
38.2.2 INTERMEDIATE BREAX ACCIDENT (IBA)
No deviations.
38.2.3 SMALL BREAK ACCIDENT (SBA)
The Perry drywell pressure resulting from an SBA is increased from 3.0 psid, as required by CESSAR, to 3.3 psid.
3B.2.4 SAFETY RELIEF VALVE ACTUATION No deviations. i 9
38-1 -
9
~e o oww - e s.',we_. m , . me ma ,e +en
,. ~,~.y. . -.-g..,, _y,..- . . , . ----sr --. -._--.m, - w ,---w,
3B.2.5 OTHER CONSIDERATIONS
\
No deviations.
3B.3 DYNAMIC LOAD TABLE No deviations.
3B.4 DRYWELL STRUCTURE No deviations.
3B4.1 DRYWELL LOADS DURING A LARCE BREAK ACCIDENT No deviations.
3B.4.1.1 Sonic Wave No deviations.
3B.4.1.2 Drywell Pressure CESSAR Figure 3B-10 is not applicable to Perry. FSAR Figure 6.2.11 shows the Perry dryvell pressure response to a main steam line break (DBA).
38.4.1.3 Hvdrostatic Pressure No deviations.
3B.4.1.4 Loads on the Drywell Wall During Pool Swell No deviations.
35.4.1.5 condensation Oscillation Loads CESSAR Figure 3B-17 is not applicable to Perry. See FSAR Figure 3B-6 for the distribution of condensation oscillation loads on the drywell.
3B.4.1.6 Fallback Loads No deviations.
38.4.1.7 Negative Load During ECCS Flooding No deviations.
3B.4.1.B Chugging No deviations.
38.4.1.9 Loads Due to Chugging
, No deviations.
I 3B-2
l
~
38.4.1.9.1 Chugging Loads Applied to Top Vent No deviations.
38.4.1.9.2 Pool Boundary Chugging Loads .
CESSAR Figures 3B-28 through 3B-31, and 3B-34 and 3B-35 are not applicable to Perry. See FSAR Figures 38-7 through 3B-12.
38.4.2 DRYWELL LOADS DURINC INTERMEDIATE BREAK ACCIDENT No deviations.
38.4.3 DRYWELL DURING SMALL BREAK ACCIDENT No deviations.
38.4.3.1 Drywell Temperature No deviations.
38.4.3.2 Dryvell Pressure No deviations. ,,
38.4.3.3 Churting
(
No deviations.
3B.4.4 SAFETY / RELIEF VALVE ACTUATION No deviations.
35.4.5 LRYWELL ENVIRONMENTAL ENVELOP No deviations.
3B.4.6 TOP VENT TEMPERATURE (CYCLINC) PROFILE DURING CHUCCING No deviations.
3B.4.7 DRYWELL MULTICELL EFFECTS No deviations.
38.5 WEIR WALL No deviations.
38.5.1 WEIR WALL LOADS DURING DESICN BASIS ACCIDENT No deviations.
(
38-3 /
se =e. ,..w -+~ - tm. -
,,y .
~3B
...5 1 1 Sonic Wave No deviations.
3B.5.1.2 Outward Load During Vent Clearina No deviations.
~
35.5.1.3 Outward Load Due to Vent Flow No deviations.
38.5.1.4 Chugging Loads No deviations.
Invard Load Due to neRative Drywell Pressure
. 38.5.1.5 Deviations from GESSAR as required by the NRC Draft Acceptance Criteria l
. 3B.5.1.6 Suppression Pool Fallback Loads No deviations.
3B.5.1.7 Hydrostatic Pressure No deviations.
I ~
38.5.1.8 Safety / Relief Valve Actuation No deviations.
35.5.1.9 Condaasation 1
No deviations.
35.5.2 WEIR WALL LOADS DURINC AN INTERMEDIATE BREAK ACCIDENT No deviations.
38.5.3 WEIR WALL LOADS DURINC A SMALL BREAK ACCIDENT No deviations.
38.5.4 WEIR WALL ENVIRONMENTAL ENVELOPE No deviations.
38.5.5 WEIR ANNULUS MULTICELL EFFECTS No deviations.
i, (
38-4 9
- ,ee-,,w_g -e ,w o- - ~- . ,,--.,.,.# , %,g m v- g- r , - , - g , -p--- , - - -
e- 7-,- -,-,r- -
38.6 CONTAINMENT I
No deviations.
38.6.1 CONTAINMENT LOADS DURING A LARCE STEAMLINE BREAK (DBA)
CESSAR Figures 35-2 through 35-6 are not applicable to Perry. See FSAR Figures 3B-1 through 38-5.
a 35.6.1.1 Compressive Wave Loadina No deviations.
35.6.1.2 Water Jet Loads No deviations.
38.6.1.3 Initial Bubble Pressure No deviations.
38.6.1.4 Hydrostatic Pressure No deviations.
3b.6.1.5 Local Containment Loads Resulting from the Structures at or Near the Pool Surface Deviation from CESSAR as required by the NRC Draft Acceptance Criteria.
35.6.1.6 Containment Load Due to Pool Swell at the HCU Floor (Wetwell Pressurization)
Th( Perry H7U finar is approxim1tely 27 feet ah>ve the suppressien po<il surface and has been designed for 10 paid across the total area of the platform (structural steel plus grating). This was reduced from the CESSAR specification due to the Perry HCU floor being 7 feet higher than the CESSAR standard. In addition, a plant unique analysis showed a peak calculated pressure differential equal to approximately 5.4 psid based upon a design open area ratio of 30 percent of the total HCU floor area, (Refs. 2, 3 & 4).
GESSAR Figure 35-58 is not applicable to Ferry.
38.6.1.7 Fallback Loads No deviations.
38.6.1.8 Post Pool-Swell Waves No deviations.
35.6.1.9 condensation Oscillation Loads CESSAR Figure 38-17 is not applicable to Perry. See FSAR Figure 38-6 for condensation oscillation loads on containment.
38.6.1.10 Churrina No deviations.
38-5 e
38.6.1.11 Long-Term Transient No deviations.
38.6.1.12 containment Environmental Envelope No deviations.
g 35.6.2 CONTAINMENT LOADS DURING AN INTERMEDIATE BREAK ACCIDENT No deviations.
38.6.3 CONTAINMENT LOADS DURING A SMALL BREAK ACCIDENT No deviations.
38.6.4 SAFETY / RELIEF VALVE LOADS No deviations.
38.6.5 SUPPRESSION POOL THERMAL STRATIFICATION No deviations.
38.6.6 CONTAINMENT WALL MULTICELL EFFECTS No deviations.
38.7 SUPPRESSION POOL BASEMAT LOADS No deviations.
33.8 LOADS ON ETRUCTURES IN THE SUPPRET.SION POOL No deviations.
38.8.1 DESIGN BASIS ACCIDENT No deviations.
38.8.1.1 Vent Clearing Jet Load No deviations.
38.8.1.2 Drywell Bubble Pressure and Dram Loads Due to Pool Swell The PNPP design basis for drywell bubble pressure and drag loads conservatively uses the LOCA bubble pressure. A comparison of the PNPP load methodology and the CESSAR II methodology is given in Section 3BL.2.3 of the FSAR.
32.8.1.3 Fallbsek Loads I
No deviations.
38-6
. _ . ~ . _ _ _ _ . ... ._.
38.8.1.4 Condensation Loads LOCA condensation-oscillation drag loads are bounded by the PNPP LOCA bubble pressure drag load methodology. (Reference 4) l 0
35.8 1.5 Chugging Chugging drag loads are bounded by the PNPP LOCA bubble pressure drag load metholology. (Reference 4 & 5) l 358.1.6 Compressive Wave Loading No deviations.
38.8.1.7 Safety / Relief valve Actuation The PNPP design basis for safety / relief valve quencher air bubble drag loads is conservatively based on the maximum quencher bubble pressure. A comparison of the PNPP load methodology and the GESSAR II load methodology is given in Section 3BL.3.2. of the FSAR.
31.9 LOADS ON STRUCTURES AT THE POOL SURFACE Ae required by the NRC Draf t Acceptance Criteria, the Perry analysis used a velocity ranging from sero fps at the pool surface to a maximum of 50 fps as a function of height; instead of the constant 40 fps velocity specified in GESSAR Table 38-2, to calculate pool swell drag loads.
38.10 LOADS ON STRUCTURE BETWEEN THE P00L SUkFACL AND TnE llCU )LOORS No Deviations.
35.10.1 IMPACT LOADS lapact loads are calculated in accordance with CESSAR as modified by the requirements of the NRC Draf t Acceptance Criteria.
The design basis for bulk pool swell impact loads on small structures less than 4 ft. long and/or 6 ft. above the pool have been evaluated using an alternative method. (Reference 5) 35 10 2 DRAG LOADS Drag loads are calculated in accordance with CESSAR as modified by the requirements of the NRC Draft Acceptance Criteria.
33-7
35.10 3 FALLBACK LOADS No deviations.
35.11 LOADS ON EXPANSIVE STRUCTURES AT THE HCU FLOOR ELEVATION.
Yhe only expansive structure in Perry in the pool swell region is the steam tunnel, which is designed in accordance with the NRC Draf t Acceptance Criteria.
(References 1, 3 & 4) 35 12 LOADS ON SMALL STRUCTURES AT THE ABOVE AND THE HCU FLOOR ELEVATION Deviation f rom CESSAR as required by the NRC Draf t Acceptance Criteria.
35.13 REFERENCES
- 1. Draf t NRC Accepanee Criteria for. LOCA Related Mark III Containment Pool Dynamic Loads Appendix C of Attachment to NRC letter from T.P. SPeis NRC, to H. Pfefferlen, CE, dated October 8,1982.
- 2. CEI letter, PY-CEI/NRR-0010L from M. R. Edelman, CEI, to 5. J. Youngblood, NRC, dated January 31, 1983.
- 3. CEI letter, PY-CEI/NRR-0055L from M. R. Edelman, CEI to B. J. Youngblood, NRC, dated June 20, 1983.
- 4. CEI letter, PY-CEI/NRR-0123L f rom M. R. Edelman, CEI to B. J. Youngblood, NRC, dated July 11, 1984.
- 5. CET letter, PY-CEI/NRR-0235L f rom M. R. Edelman, CET to E. J. Youngblood, Nac, dated May 16. 1985.
- 6. CEI letter, PY-CEI/NRR-0336L f rom M. R. Edelman, CEI to B.J. Youngblood, NRC dated September 13, 1985.
35-8
ATTACHMENT 4 PERP.Y NUCLEAR POWER PLAlfr EVALUATION OF IMPACT LOADS ON SHORT STRUCTURES AND STRUCTURES CLOSE TO THE POOL The design basis for bulk pool swell impact loads on structures less than 4 feet long and/oc closer than 6 feet to the initial pool surface is based on the impact method given in Gessar II (Reference 1) as modified by the NRC Draf t Acceptance Criteria (Appendix C to the Draf t Technical Evaluation Report on Mark III LOCA-Related Hydrodynamic Load Definition provided by meno dated 10/8/82 from Mr. Thomas P. Speis (NRC) to Mr. Hank Pfef ferlen (CE)). This report presents the methodology used for evaluating structures which are outside the range for which the NRC Acceptance Criteria (NUREG-0978) Reference 2 finds GESSAR II acceptable.
All structures (beams, piping, pipe supports, & miscellaneous structural steel) have been identified.
Summary All beams, piping, pipe supports, and miscellaneous structural steel which are outside the range for which the NRC Acceptance Criteria (NUREG-0978) Reference 2 finds GESSAR II acceptable are being evaluated. We will demonstrate that
! sufficient design margin exists between the original design basis pressure and the impact pressure calculated using the methodology listed below.
Method The impact loading for each component was determined using the following:
. (a) Pulse Duration The impact pulse duration was calculated using the suggested Haisc criteria (Reference 3) or the Mark 11 criteria (NUREG-0487) Reference 4, whichever was greater.
7"(sec) ,
(b) Impact Pressure The impact pressure is calculated using the hydrodynamic mass of the target which is a function of the target shape (flat or cylindrical) and orientation above the pool (radial or circumferential). The hydrodynaste mass is determined from NEDE-13426P (Reference 5), Figures 6-8 and 6-9 for radial and circumferential orientation, respectively.
The impact velocity as a function of height above the pool is determined using equation C-1 of the Mark III Acceptance Criteria (NUREG-0978).
V=5H(2.6-0.506/H) H f 10 ft.
V = 50 ft/sec H 7 10 ft.
p
The total impulse is calculated using equation C-4 of Reference 2.
I p= (M H ( * *I where:
f 1, = lePulse per unit area, psi-see M /A = hydrodynamic mass per unit area, Ibe/f t2 H
V = impact velocity, it/sec Using the pulse duration (7) the impact pressure is determined assuming an isosceles triangle loading.
P = 2* Ip /7 (Psi)
The above impact load and pulse duration was used to evaluate each component.
Methods used to evaluate the revised load are given below.
- 1. The dynamic load f actor was evaluated based on the natural f requency of the component. In most cases the DLF used in the original design was the theoretical maximum.
The original design load (Psax x DLF) was compared to the revised impact load (revised Psax x DLF revised) and found acceptable if for the Radial Orientation, Porig/p ) 1.25 and if for the Circumferentiai Orientation, Porig/p ) 2 00.
- 2. For components other than structural beams originally qualified using a f orce tiu history evaluat ion, either mothud 1 'm use ! f or remnaluation or the force time history was redone using the teviacd load using radini M /A.
H
- 3. Components that were originally designed to a lower load were re-evaluated and qualified based on sufficient margin in the original design.
- 4. For structural beams originally qualified using a force time history evaluation, the force time history was recalculated using the Maise criteria.
i l
l
References 1.
General Electric Co., General Electric Standard Safety Analy i s s Report for
~ 238 Nuclear Island Design (CESSAR II), Volume 6/Arpendix 3B
~][~ 2. .
1 U.S. Nuclear Regulatory Commission,valuation NUREG-0978. 1983.
Appendix D),
- 3. C. Maise:
III Structures Close to the Pool," Department gy, ofr Nucle Brookhaven National Laboratory, Upton, N.Y. 11973 4.
February 15, 1984.
Program Load Evaluation and Acceptance 1978.
ant Criteria
, October 1~
5.
Scale Pool Swell Impact Testt:. General Electric August 1975.
. Co., " Mark ;
One-Third Test Series 5805," C.E. Report NEDE-13426P.
4 O
D