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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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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~ L E C T R ! C I L L U f/ I N !n l N G -C O M P A !! Y fTHECLE1!ELA..D P.o. BOX 5000 - CLEVELAND, OHIO 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLOG. - $5 PUBLICSQUARE Serving The Best Location in the Nation MURRAY R. EDELMAN VICE PRESIDENT September 19, 1984 NucteAn PY-CEI/NRR-0138 L Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington D.C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Response to NRC Question Nos. 220.32 through 220.36 (480.54)-
Containment Drywell Wall Structural and Bypass Leakage Integrity
Dear Mr. Youngblood:
This letter and its attachments are provided in response to your request for additional information (dated May 30, 1984), regarding containment drywell Structural and Bypass Leakage Integrity for the Perry Nuclear Power Plant (Units 1 and 2).
The inf ormation provided in the attachments will be incorporated into a future FSAR Amendment. If you have any questions, please feel free to contact me.
Very truly yours, M '
N Murray R. Edelman Vice President Nuclear Group MRE:njc Attachments cc: Jay Silberg, Esq.
John Stefano Jack Grobe 8409260274 840919 PDR ADOCK 05000440
[
A PDR If o
Racponza Q 220.32 pg. 1 of-3 h
-Response to NRC Item Q220.32' Q220.32: " Provide detail information on the installation of Hilti expansion concrete bolts in the drywell wall such as
. installing sequences, means for minimizing concrete cracks around the . bolts, maximum size of bolt, procedures for q achieving air tightness around the bolt, bolt patterns,
'c ,
maximum and minimum spacings of bolts, maximum bolt loads and Jeapacity of the bolt."
Response
- 1. Installation Sequence Th'e installation sequence of-Hilti Kwik Bolts through the
'drywell liner plate are specifically delineated iniitem 1:13 of Attachment Specification SP-208-4549-00. Attachment 1 is an excerpt of the pertinent section from SP-208; Sub-items
-1:13.1 and 1:13.2 define bolt installation requirements.
Sub-item'1:13.3 defines concrete and/or liner plate repair-requirements for all unused holes.
- 2. Crack Control Around the Bolts There have been no detectable cracks around Hilti Bolt installations in the drywell wall or any other plant i . structures.. Industry experience with Hilti bolts in comparable installations and loading conditions prove the above installation specifications; special construction methods for drywell installation are not-required. See the response to item Q220.35 for~ additional discussion on the subject of Hilti Bolts potential for initiating or propagating localized cracks.
- 3. Maximum Bolt Size The vast majority of Hilti Kwik Bolts fall in two size categories:
I - 5/8"'8 or 3/4" 9 with embedded depth of approximately 4"
- 3/4" 9 with embedded depth of approximately 7"
+
- 4. -Leak-Tightness Around Each Bolt Each bolt has sealer tape installed in the annular space between the bolt shank and the oversized hole in the 1/4" liner plate, and is individually inspected. Refer to item 1:13.2d of Attachment 1.
- 5. Bolt Patterns and Spacing.
~
Typical base plate details and patterns of installations through the drywell liner are shown on Attachment No. 2.
Pages 1 throtgh 3 of Attachment # 2 show a typical pipe support which uses-one of several standard Hilti base plates.
p: - .---
Responen Q 220.32 pg. 2 of 3 These standard base plates are used by all disciplines.
1 Page 4 of: Attachment #2 shows the typical Hilti support detail used for conduit.
Spacings between individual attachments are governed by the following:
A. Maximum spacing - no limit B. Minimum spacing -
Spacing controlled by Attachment Specification SP-208.
Specifically, the requirements are as follows:
(1) 5/8" 9 or 3/4" 9 with embedded depth of I' approximately 4":
No defined minimum spacing values. Bolts may be as close as individual adjacent attachment y hardware permits. This equates to a minimum bolt-to-bolt spacing between adjacent attachments of approximately 3 inches.
(2) 3/4" 9 with embedded depth of approximately 7" adjacent to the same type bolt or to a bolt from (1) above:
Minimum spacing equals 4 inches.
The spacing from both (1) and (2) above are substantiated by pull-out tests as reported in GAI Report No.:2486, " Perry Nuclear Power Plant Report on Evaluation of Spacing and Edge Distance Violations of Hilti Kwik Bolts and Other Steel Embedments" dated September 19, 1983.
- 6. Maximum Bolt Loads Versus Rated Capacities A. 5/8" 9 or 3/4" 9 bolts with embedded depth of approximately 4".
Maximum allowable loads for drywell vacuum load com-bination:
4 Tension = 250 lbs.
Shear = 250 lbs.
Maximum allowable loads for jet impingement load com-bination:
Tension = 900 lbs.
Shear = 1400 lbs.
.= : ,
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', i
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Responsa Q220.32 pg.3 of 3
. Notes: :1. iThe above' allowable shear'and-tension-
-loads.nay be' applied currently.
. .2. The allowable loads are not governed by Hilti Bolt hardware capacity but rather
~
by the reserve capacity of the embedded stiffener angles which serve as .drywell
. liner. anchors.
- - The fu11' rated bolt capacitites for the above based on a safety factor'of 4 and.5000 psi design strength concrete from the.Hilti design catalog (Abott A. Hanks, Inc. File
.No. H2189-S1, Report No. 8783R) are:
- 5/8" 9 bolt with 4" emb T = 11290/4 =2833>> 900 lbs.
V = 12531/4 =3133)>1400 lbs.
- 3/4".9 bolt with 4" emb.T = 13550/4 =3380>>900 lbs.
V = 17618/4= 4404>>1400 lbs.-
B; 3/4" 9 bolt with embedded depth of approximately 7" The maximum allowable design loads are normally limited to approximately 30 percent of the full rated bolt capacities.
These allowable values were conservatively based on 4000 psi -
concrete at'the time of bolt design and are as follows:
- For vacuum pressurization load combination:
' Tension = 1000 lbs.
Shear = 1980 lbs.
- For jet impingement load combination:
Tension = 1490 lbs.
Shear = 1980 lbs..
- p Notes: 1. Linear shear-tension interaction used with above load allowables.
- 2. The above allowable bolt tension loads are derated as.com e ared to full rated bolt capacity due to pull-out cone overlap with embedded drywell liner stiffener / anchor angles.
The full rated bolt capacity (S.F. of 4 and actual 5000 psi design strength concrete) from the Hilti catalog is:
~
Tension = 22300/4 = 5575>>1490 lbs.
y Shear = 19738/4 = 4934>> 1980 lbs.
In approximately 10% or less of the cases the maximum allowable design loads > of the 3/4" 9 bolts with 7" embedment have been increased via case-by-case evaluation. In these few cases, design loads have generally increased by 50 to 60
' percent with'the full rated bolt capacities (above) being the
' upper bound.
- k. _l.___________.__ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ -_ _ _ _ _
- t. * '.' - Response Q 220.32
. e *. ECN #9092-44-1085, Rev. 8 Attachment I Attacheent #2 Pg. I of 3 Page 1 of 4 s
Add Item 3:02.9.13 to SP-44 as follows in order to modify the provisions O of attachment Specification SP-208-4549-00:
. 13. Add Item 1:13 as follows: -k D 1:13 Instellation Through Dryvell Liner Plate C Hilti Kwik Bolts shall be installed through the Reactor Building drywell liner plate (wall or ceiling) only where specified by the* ENGINEER. Unless approved otherwise by the ENGINEER, installation of Hilti bolts through the liner shall conform to the following re.quirements:
- 1. Hilti Kwik Bolts shall be 5/8" x 6" Ig. Minimum embedded depth shall be as spec fled on the drawings.
- 2. Tha sequence of bolt installation Ehall be' as follows:
- a. A 1" diameter oversize hole shall be drilled completely,through the liner plate using a suitable bit fo.r steel drilling. Embedded stiffener angle .
legs attached to the liner shall not be through drilled. If steel is encountered after drilling to a maximum oversized hole depth of 1/2", drilling shall stop immediately and the bolt location shifted within tolerances as permitted by the ENGINEER. The unused hole shall be repaired per Subitem 3 below.
- b. After drilling through the liner, a S/8" nominal diameter masonry carbide drill bit per Item 1:07.1 shall than be used to complete the hole drilling.
na 5/8" diameter hole shall be drilled in the center of the oversized hole- (i 1/16" tolerance). If steel i
is encountered during drilling at approximately a 3"
. hole depth, an embedded stiffener angle les parallel to the liner is being hit. H is leg of the stiffener I shall be through drilled with a 5/8" diameter bit suitable for steel drilling. After drilling the 1/4" thick stiffener angle, a masonry carbide bit (per Item 1:07.1) shall again be used to complete the bolt hole drilling. Drilling shall stop if steel is encountered deeper than 3-1/2". In this case, the bolt location'shall be shifted within specified tolerances to clear the interference or, if this is not feasible, the
. ENGINEER shall be contacted for direction. Any unused holes shall be repaired per Subitem 3 below.
- c. Without the attachment fixture in place, the Hilti Bolt shall be inserted into the hole by hammering or an gproved alternate method. '
~
, EBRREFEREEE00 O ________A0_ m m* ^
. .' * *. ECN #9092-44-1085, Rsif. O Response Q,220.32
+
Attachm2nt I ac t #2 Pg. 2 of 3 -
. d
~
- d. Sealer tape shall be applied in the oversized hole in the liner around each Hilti Bolt. Sealer tape shall be 3/16" thick x 1/2" wide HVAC METAL AIR DUCT SKATIR TAPE (Type 440) as manufactured by Tresco, Incorporated. De material is classified as Nuclear Safety-Related but need only be supplied from the manufacturer with certificates of Compliance (Cocs) to published physical properties and performance characteristica. The CONTRACTOR is not required to perform a Quality Assurance audit of the manufacturer for the supply of this product.
The sealer tape shall be manually worked into the overs,ized hole to completely fill the hole around the bolt. Excess sealer tape (1/4" maximum thickness) shell be left projecting above the surface of the liner plate. This will be compressed during Hilti Bolt torquing to~ ensure complete sealing of the liner plate around each Hilti Bolt. '
' The CONTRAdIDPS QC shall verify and document that the sealer tape is adequately installed around each Hilti Bolt prior to attachment fixture installation.
- e. If welding to the attachment fixture is specified by the ENGINEER, it shall be performed prior to s attachment fixture installation onto the Hilti Bolts.
- f. The attachment fixture and Hilti Bolt nut and washer shall then be installed on the Hilti Bolt and the Hilti Bolt torqued to specification requirements.
- 3. Unused holes in the concrete and/or drywell liner plate shall be repaired per the following:
I a. Moles in tho' concrete greater than 1/2" depth shall
.; , be dry pack grouted with Masterflow 713 grout per
- Item 1:08 of this specification with the exception
' that the hole shall not be dampened with water prior to placing the grout. The grout shall be allowed to dry for apprawi-ately one day prior to weld repairing of the liner plate per Item "b" below.
FORREFEREEE 0E e
'[ _ ,,
. . . .. . ^;
. ' ' *
- ECN #9092-44-1085, Rdr. B g pg yg
/ Response Q 220.32 Attachment I
[
Attachment $2 3, gh j ,
Pg. 3 of 3
. Page 3 of 4 l
- b. Roles in the liner plate shall be repaired by: ,
- 1) A 1/8" thick x 15/16" diameter round steel slug shall be inserted in the bottom of the oversized hole. Steel slug material shall be per Section 8.2 of AWS D1.1 or a "F" Number material from ASME Section II and shall be supplied with the appropriate Certificates of Compliance.
Unique material traceability to the installed condition is not required. He surface of the slug shall be a minimum of 1/8" below the liner plate surface.
- 2) n e hole shall then be weld repaired to t{ completely seal the opening. H e weld repair 2
0 shall be ground flush with the surrounding liner plate surface. Welders and welding procedures 9 shall conform to either AWS DI.1 or ASME Section e IX requirements. Each weld repair shall have 3 final visual inspection and documentation by the j . CONTRACTOR'S QC.
+
- 3) Weld repairs of the liner plate which will be covered by the attadhment fixture do not require touch-up of the nuclear coating. If the weld repair will not be covered by the attachment f 4 fixture, touch-up of the nuclear coating will be
[- ,
performed by 013ERS.
- 4. Hilti Bolt spacing requirements for adjacent attachments to the drywell liner plate shall be as fo11ces:
- a. 5/8" or 3/4" diameter bolt with 4-1/4" minimum specified embedment depth (or less) adjacent to the same type bolt (s) -
h ere are no minimum bolt spae.ing requirements. De attachments may be as close as the physical hardware and specified locational tolerances for,the attachments permit.
~
- b. 3/4" diameter bolt with specified embedmont depth greater than 4-1/4" adjacent to a bolt from 4.a above -
Minisme, spacing (center line to center line) = 4" l C
- c. 3/4" diameter bolt with specified embedmont depth greater than 4-1/4" adjacent to the same type bolt -
Minimum spacing (center line to center line) = 4" C IaREfDGCE50 , . ..
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Rieponsa Q220.33 pg. 1 of 1 Response to NRC Iten Q220.33 Q220.33: Perry FSAR committed that drywell liner and the anchorage system were designed in accordance with the ASME Section III, Division 2 CC-3000 to utilize the liner's inherent leak tightness and achieve
-leak tight details at penetrations. In view-of the 6000-8000
' concrete expansion anchor bolts installed through the drywell liner into 'the concrete well, provide a discussion to demonstrate that the applicable provisions of the code covering liner integrity and leak tightness are fully met. If the provisions are not fully met, list the deviations and the bases thereof.
Response: The drywell liner was designed in accordance with ASME Section III Division 2, however it was not fabricated and constructed to all the requirements of CC-4000, " Fabrication and Construction" nor all the-requirements of CC-5000, " Construction Testing and Examination." The drywell liner was provided as a form for the concrete. The design itself meets the stress and strain allowable of CC-3000 " Design" and materials, fabrication, and construction were all in accordance with the nuclear safety related quality procedures and program.
The ability of the liner and its anchor system to meet the stress, strain and displacement limits of Article CC-3000 is essentially unaffected by the use of concrete expansion anchors, because the anchor or bolt loads are transferred directly to the concrete. To provide structural integrity under vacuum and seismic loads, and to meet the anchor displacement limits of Article CC-3000 the allowable loads on the bolts are limited as described in our response to Q220.32. The allowables are based on the worst
- possible bolt location - which is directly over the liner anchorage.
In conclusion, although the drywell liner may enhance the leakage integrity of the drywell structure, it is not required to meet the bypass leakage requirements of the FSAR. The use of Hiltis is consistent.with the drywell liner's function as a form for the drywell concrete.
6 e
Raspanse Q220.34 pg. 1 of 2 Response to NRC Item-Q220.34 Q220.34: With respect to the as-built drywell cancrete wall, are there through wall concrete cracks? If yes, what are_the extent of those cracks and their estimated crack dimensions? What is the potential for those cracks to form an interconnected crack network to the extent of affecting the functioning of the drywell as a pressure barrier under LOCA and SSE conditions?
If your assessment indicates that there should be no through cracks in the drywell wall, please provide the technical basis for the assessment, s
Response: There are no through wall concrete cracks in the as-built drywell concrete wall. The as-built wall, even after the SIT at the design pressure of 30 psi, is not expected to have through wall cracks based on calculations performed. These calculations were performed using conservative assumptions and are discussed in response to Q220.35. In additior, NED0-10977 "Drywell Integrity Study: Investigation of Potential Cracking for BWR/6 Mark III Containment [Drywell] " demonstrated that during normal operation only minor surface cracking exists due to drying shrinkage of the concrete.- A LOCA (DBA or SBA) plus SSE does not result in significant propagation of normal operational cracking nor does it result in through wall cracks.
Additional factors supporting the conservative nature of these conclusions and the applicablility of the GE study to the Perry Nuclear Power Plant are as follows:
4 1. Comparison of physical parameters:
- a. Reinforcement ratios, Perry to that used in NED0-10977 CYLINLER PNPP/NEDO-10977 VERTICAL REINFORCEMENT Below EL 606'-6" 1.72' Above EL 606'-6" 1.45 h
HORIZONTAL 1.75 DIAGONAL 1.07 TOP SLAB RADIAL 1.57 CIRCUMFERENTIAL 2.56 L
Rasponta Q220.34 pg. 2 of 2
- b. CONCRETE COMPRESSIVE STRENGTH NEDO 10977 based on f' =4500 psi PNPP-based on f' =5000 psi
.c. REINFORCEMENT STRENGTH NEDO 10977 'uased on f =40 Ksi PNPP based on.f =60Ksl y
- 2. PNPP adapted details around all penetrations to minimize local cracking. Around through-wall or structural penetrations where reinforcement is terminated, the reinforcement area is replaced each side and above and below.
the openings to satisfy the strength requirements. In addition, although not required for strength, additional reintareement was added diagonally around the penetrations in two directions on each face to control local cracking and strains.
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Responsa Q220.35 pg. I of 1 Kesponse to NRC Item Q220.35 Q220.35: Assuming that initially there are no through thickness cracks in the wall, would the presence of 6000 to 8000 expansion anchor bolts enhance the probability of initiating and propagating localized cracks into through wall cracks, thus affecting the drywell pressure barrier function under LOCA plus SSE7 Response: The'Hiltis do not contribute to the initiation and propagation of localized cracks any more than the minor surface cracking which may already exist do to drying shrinkage of the concrete. The presence of expansion anchor bolts will
.therefore not affect the drywell pressure barrier function due to crack initiation or propagation. The majority of the Hiltis will only be installed 4 to 7" inches deep. The clear cover to the inside face vertical reinforcement is 5 1/2 inches. The majority of the drilled anchors will not go beyond the first layer of reinforcement. Given the
' installation requirements as described in Q220.32, permissible loads in the Hiltis are so small as to be considered negligible, and thus do not contribute to cracking.
Both the normal operating (135 F inside drywell and 90 F outside), as well as the accident (250 F - 350 F inside drywell and 185 F outside) temperature gradients through the drywell tend to keep the inside of the drywell in compression; in compression there is no potential for crack initiation or propagation.
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> R sponsa Q220.36, Q480.54
' - pg. 1 of 2 l
Response to NRC Item Q220.36, Q480.54
-Q220.36: If no credit is claimed with respect to the liner elements and 4
Q480.54: the drywell concrete is to be depended upon to maintain a leak tight barrier, provide a specific. concrete crack analysis to
!' demonstrate'that the maximum effective allowable leakage area of 1.68 square feet is'not exceeded (Perry SER Section
- 6.2.1.7),~and also that the bypass leakage measured during the leak tightness tests will be maintained within the allowable
, - leak rate (SRP Section 6.2.1.1 C-II.4.C). .The effects of
~ potential construction defects such as voids, construction joints, rock pockets, and local effects such as, stress concentration must be considered in the above concrete crack analysis.
r 1
-Response: The drywell liner is not required to maintain a leak tight barrier and the following discussion of plant-specific and generic concrete crack analyses demonstrates that the maximum allowable bypass leakage will be maint.1ned. As discussed in the FSAk Section 6.2.1.1.5, the allowable bypass leakage capacity expressed in germs of A/(ii for a small primary system break is 1.68'ft . General Electric (GC) in the PNPP Containment and NSSS Interface Document.(Doc. No. 22A3759AL)
I U
- concludedthatforalargebreak(DBA)theallowaglebypasg).
leakage flow path would be nearly an A/ 6 of 5 ft- (720 in As' discussed.in our response.to Question 220.34, the drywell. .
will have'no through cracking.due to a rupture in a small primary system-(SBA plus SSE). .This conclusion was reached by NEDO-10977 and has'been confirmed by our own calculations
-(Attachment 1).
LNEDO-10977.also. concluded that there was no through cracking
{
- due to a -large break DBA in a main steam or. recirculation line
[ : plus SSE. Again, our calculations support this conclusign.
> For a DBA, a bypass leakage' flow path (A/ (K) of 0.35 ft is prgdicted. .This predicted flow path is much less ghan the 5
~
+ ft allowable as defined by GE. Even the 0.35 ft is very -
conservative because:-(1) it is based on peak drywell pressure of 30 psi-(maximum calculated is only 21.4 psi which only lasts for a few-seconds), (2) it is based'on peak SSE h . earthquake forces estimated to last for only 10 seconds as ,
4 referenced in FSAR Section 3.7.1.1.c, (3) it is based on a
- load combination including a safety' relief valve actuation ,
- (P g recky) witn peak pressures (P ) from a main steam orreulation line break which is
- Othu conservations in the Perry analysis are discussed in.
u; Attachment-1. Our calculations have shown that as the D
pressure :is reduced fna the design pressure of 30 psi to O psi, the crack width is reduced by approximately 50%. Without
. earthquake,' crack widths are reduced to one-third of the
- maximum crack width at 30 psi and further reduced to no crack width at the maximum calculated pressure (21.4 psi).
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Response Q220.36,Q480.54
.pg. 2 of 2 4
The conservatisms in the GE crack study (NEDO-10977) as supplemented by our own calculations, our reinforcement ratios and our penetration reinforcement practices- provide a conservative bound on estimated crack widths and drywell
-bypass leakage flow paths. Under an SBA, no bypass leakage flow paths are predicted through the drywell concrete. Under a'DBA, even with the extremely conservative assumption of concurrent peak drywell pressures, maximum SSE earthquake
- forces, concurrent-SRV actuations, and precracks at all-construction joints,2the maximum predicted bypass leakage2 f1 "
fpath is'only 0.35 ft as compared to an allowable of-5 ft .
'With respect to potential construction defects, several voids
.were found and. reported to the USNRC under 10CFR50.55 (e).
These voids.were found as a result of our Hilti installation
- program. An evalution of these voids was made including
. cutting windows in the liner for examination where it was felt reinforcement. congestion was heaviest. Voids found as a result of these investigati ns were limited to the steam tunnel slab area of the drywell wall. These limited areas are being_ repaired. Other than these very localized voids, there
.has been no evidence af rock pockets or other construction
~ defects in the drywell structure.
- . e ~In addition to analytical predictions based on design conservatisms which predict drywell leakage integrity, a commitment has been made for a-structural-integrity test (SlT)-
1 at drywell design _ pressure, and periodic, low pressure leak. ,
-rate tests in FSAR Sections 3.8.3.7 and Section 6.2.6.5. The al{owabledrywellleakage_rateforthesetests,L,is0.168-
~
f t , which-is 10_ percent of .the allowable bypass dIeakage for
, ~
he. limiting case of a small break accident with containment
- spray.
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Rasponse Q220.36, Q480.54 Attachment 1 pg. 1 of 1
SUMMARY
OF CALCLATIONS ON BYPASS LEAKAGE FLOW PATHS ASSUMPTIONS AND CONSERVATISMS:
- 1. A precrack exists at all drywell wall construction joints even though these joints'are very rough and have a key which is 1 1/2 inches deep and 1/3 the wall thickness.-
- 2. The concrete tensile strength at construction joints is zero.
3.. Liner induced tensile forces are included in all calculations for crack widths.
- 4. jNo credit has been taken for liner tensile strength whsn the section (is under complete tension for the DBA case at construction joints.
z 5.- Diagonal reinforcement which was added to limit concrete strains and cracking was neglected in calculating crack widths. It is estimated
._that crack widths would be' reduced by approximately 30 percent if diagonal' reinforcement'were included.
' 6. Five different references (cited below) were used to' calculate crack widths.
- a. ACI 318-84,' Section 10.6
- b. ACI 424, Section 4
-c._ _'ACI 313, Section 4.5.5.5.2 .
E d. " Comparison of Maximum Flexural and Tensile Crack Widths" by L.
A. Lutz.
e.. " Reinforced Concrete Structures" by Park &. Paulay, John _Wiley &
-Sons, 1975, Section 10.4..
"ACI/313 provided the-largest crack widths, and these were used to estimate crack areas at the construction joints.
. . ' CONCLUSIONS:
t 1.~ ;No throughLwall cracking and, therefore, no bypass leakage flow-paths
~
=through the drywell: wall for_the small break accident case (including assumed ' construction joint -precracks).
2
- 2. - A bypass leakage flow path A/(K of 0.35 ft for the DBA (based on the assumption _of a complete precrack at construction joints).
-3.. No through' cracks and, therefore, no bypass leakage flow paths through the drywell wall at locations other than construction joints 4-
>- for the-DBA.
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