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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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-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-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-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-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-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-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 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-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-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-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-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 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 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 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) 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-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
. - -
TliE CLEi!EL AN D ELECTRIC ILL U MIN ATIN G CO M P AN Y l
P O. 00X 5000 e CLEVELAND. OHIO 44101 e TELEPHONE (216) 622-9800 e ILLUMINATING DLDG e 55 PUBLIC SoVARE '
Da:wyniL Davidson ewing e Best Location t'n the Nation VICE PRESwENT SYS TE M ( NGINE E RING AN;.) CONS 1 RUCTION W o>
April 19, 1982 e e N
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e qV I Fr. A. Schwencer Chief, Licensing Branch No. 2 g9 ' @ .
Division of Licensing y 0V fy ;j e3 U. S. Nuclear Regulatory Commission <\
Warnington, D. C. 20555 Cu g \'
Perry Nuclear Power Plant Docket Nos. 50 11440; 50 111 44 Respanse to Draft SER Structural Engineering Bramh
Dear Mr. Schwencer:
This letter and its attachment is subnitted to provide additional information regarding the intake tunnel structure.
It is our intention to incorporate this response in a sur, sequent amendment to our Final Safety Analysis Report.
Verv Truly Yours, 5
t W Dalwyn d. Davidson Vice President System Engineering and Construction DRD: mlb cc: Jay Silberg John Stefano Max Gildner I
Q 00 s
/ I o
$$84558Sk7SSSh8
l Perry Nuclear Power Plant Intake and Discharge Tunnels Responses to Additional Information Requested by the NRC - March 30, 1982
- 1. With respect to the design of the 10 inches concrete tunnel lining provide justification and basis for taking exception on the limitations ;
as imposed on Section 1.4.3 of ACI 322-78 code.
There is no code that has been developed that reflects the design consideration of tunnel supports and linings. The fact that the tunnel i lining is not a simple flexural or compression member makes application of existing codes for reinforced (ACI 318-77) and structural plain ,
concrete (ACI 322-72) inadvisable. The tunnel is not a detenninant structure because of its complex interaction with the surrounding rock '
mass and therefore the ACI code, as developed for beams, columns and slabs for buildings, is not appropriate for describing tunnels. The general failing of most building codes to consider tunnels has prompted the United States Department of Transportation, Urban Mass Transit Administration to fund the development of a more specialized " tunnel code". This research has been carried out by the Department of Civil
, Engineering at the University of Illinois. The results are currently in draft form only, subject to review by some industry representatives and the American Society of Civil Engineers' Tunnel Lining Design Committee, and not available for reference at this time. !
The design of the concrete lining for the Perry tunnels did use the existing ACI codes for guidance, but recognizing the deficiences in the code with respect to tunnel lining design, the codes were not the sole source of justification for the design. In particular, the behavior of an unreinforced concrete-lined tunnel under seismic loads is not considered by ACI 322-72. The limitation of paragraph 1.4.3 is thus not appropriate for tunnels.
1
- A two-fold approach to the design of the tunnel liniag under seismic loads was used in the case of the Perry tunnels. First, seismic ;
loads were applied via computer analyses to the proposed tunnel lining.
- The tensile stresses generated by the seismic loads were then compared to the tensile strength of the concrete, a function of the modulus of I rupture. The'second approach to the consideration of the behavior of a j concrete-lined tunnel under seismic loads was to study the history of other existing tunnels which have been subjected to seismic loads. !
This history was well-documented in STRAAM Engineers, Inc. report,
" Design of Concrete Final Lining," November 1979, with the resulting >
conclusion that all tunnels, whether reinforced concrete-lined, or unreinforced concrete-lined, behave well under seismic loads with ;
damage being very minimal. l
[
- i. :
- 2. With respect to using allowable concrete tensile stress for tunnel lining design, it is believed that under the range of stress computed '
in your response, cracking will probably develop in the plain concrete lining. Please provide an assessment this anticipated cracking on the integrity of tunnel lining and structure. Also provide a consequence analysis of the tunnel structure assuming conservatively the collapse -
of some segment of concrete lining during an SSE and demonstrate that the structural function and integrity of the tunnel is maintained.
Cracking of the concrete is in itself not necessarily detrimental to the integrity of the tunnel lining. A tunnel lining is a very redundant structure owing to the interaction between the lining and the surrounding rock mass. Cracking, to some degree, is beneficial to the distribution of stress in a tunnel liner. Cracks allow the liner to deform slightly, the crown-invert dimension shortens while the spring-line dimension lengthens. This deformation releases the moments and associated tensile stress developed in the lining and allows the lining to carry the loads in compression for which concrete is more suitable.
The mechanical interlock between the irregular rock surface and the the cast-in-place concrete prevents the accumulation of longitudinal strains and consequently large cracks from developing. Cracks which do occur are generally well distributed.
The unlikely scenario of a segment of concrete lining collapsing into the tunnel will in any case have little effect on the function of the tunnels. The tunnel is self-supporting in a good quality shale.
Thus, the loss of concrete lining in the crown serves only to open up the space to the rockline of the original machine-driven rock tunnel.
The cross-sectional area of the tunnel is not reduced, therefore the flow quantity will be maintained. The roughness of the tunnel is increased due to the segment pieces lying in the invert and due to the lack of coherent lining in the crown. The velocity of flow is technically reduced by the increased roughness but practically the velocity remains nearly unchanged.
- 3. a) Provide information regarding the design basis for use of rein-forced tunnel lining as well as unreinforced tunnel lining which were built in the United States.
b) Provide an *-luation based on available data on the performance of unreinfvg.d tunnel lining under earthquake and other pertinent loads.
_2_
. 1 l
l a) In general, there is no simple basis for deciding to use reinforce-ment in a tunnel liner. The use of reinforcement in a concrete tunnel liner is based on a variety of considerations, the most important being the ground conditions surrounding the tunnel, the size of the tunnel, the shape of the tunnel, and the depth of the tunnel. In good quality rock some tunnels are left unlined.
Reinforcement is often found at tunnel intersections with other tunnels or shafts as in the case of the Perry tunnels. The unusual shape of the opening in these areas causes the stresses to be distributed unequally. Tunnels may show reinforced concrete at the portals. This is usually a result of hillside movements, not a consideration of ground support.
Attached is a list of 46 tunnels and typical statistics which are routinely recorded by the Bureau of Reclamation. Of the 46 tennels on the list, only one shows any significant reinforcement in the lini ng.
b) The performance of tunnels under seismic loads is documented in STRAAM Engineers, Inc., " Design of Concrete Final Lining", November, 1979.
- 4. We reviewed your responses on the seismic analysis of tunnel structures, the following additional clarifications are needed for our final evalua-ti on.
a) Your basis for using 1957 Golden Gate earthquake, instead of R.G.1.60 response spectra anchored to SSE as input motion.
b) Your basis for selecting the shear modulus of water as 31000 psi.
c) Your basis for selecting only six mode in the seismic analysis.
What are the cumulative participation factors for the modes selected?
d) The basis for use of 5% damping for both OBE and SSE.
e) Why the difference in system stiffness and responses of the tunnel structure when different methods of analysis (i.e.,
Time Marching vs. Modal) are used.
a) The time-history analysis was used only to obtain information that would help construct a model for extracting modes for a modal analysis and to provide a check on the modal analysis. It was not used for the final design analysis. In an effort to l reduce the computer costs for the time-history analysis, the Golden Gate record was used since only about 3 seconds of the record was required to match the horizontal criteria spectrum of the safe Shutdown Earthquake between 4 and 20 Hz as required by Regulatory Cuide 1.60.
l l l I
The NRC requirement published in the 1975 Standard Review Plan is that the time-history must provide a spectrum that will match or exceed the criteria spectrum throughout the range of frequen-cies. The liner frequencies of concern are in the 8 to 17 Hz range and the range of 4 to 20 Hz was studied on this basis.
b) The properties of water were based on two assumptions, the bulk modulus of elasticity, K, for ordinary temperature and pressures is 300,000 psi (Streeter, V.L. and Wylie, E.B., Fluid Mechanics, 6th ed., McGraw-Hill Book Company, New York,1975, p.17), and Poisson's ratio, / , is 0.45. The shear modulus, G, falls out of the relationship between these quantities G= 3 (1-2/) K = 31,000 psi 2 (1+ /)
c) The Rayleigh-Ritz approach was used to extract the modal shapes and associated frequencies of the tunnel liner under seismic loads.
In using the Raleigh-Ritz method a set of prescribed force patterns is used as input data. The resulting displacements considered were independent sets and contained the lower mode shapes of the system.
Twenty-four force patterns were used on the Perry tunnel liner analysis. The computations were terminated when six lower fre-quencies and mode shapes were obtained. Frequencies and mode shapes were limited to the lower range (< 20 Hz) of the criteria spectrum.
The maximum frequency suggested by the Reg. Guide 1.60 criteria spectrum is 35 Hz. The stress contribution above 20 Hz frequency was neglected since the magnitude was small.
Of the six modes analyzed, the responses were combined when frequencies of the modes were within 10".. As directed by Reg.
Guide 1.92 the absolute sum of the closely spaced modes were combined and the square root of these sums taken.
d) Damping used in the seismic computer analysis is taken as a function of the mass and stiffness matrices in the form:
[c] =
C4 [M] + B [K]
where x and B are related to the critical damping ratio by
An = + B 2 Wn 2 i
l l
l l
Since the predominant frequencies of earthquake acceleration records normally occur between 1 and 8 cps, values of oc and B were selected for the first trial so that 2n varied from 4 to 8 percent and averaged 5 percent.
e) The time-marching solution was not used as a basis for design.
The time-marching solution provided information on the response of the tunnel lining to a specific earthquake record, the Golden Gate S80E component. This general information was used to develop the model for the modal analysis only. The details of the time-marching solution were not refined as was the modal solution and the criteria spectrum was not used as input. These basic inconsistencies and the fact that the programs themselves were developed on the basis of different assumptions would of course result in different responses of the tunnel structure. The magnitude of that difference was not considered inconsistent.
- 5. We need additional information and reference materials pertaining to your longitudinal tunnel analysis procedures. Also assess and discuss your analysis approach with respect to the applicable requirement of SRP Section 3.7.3.
The longitudinal analyses of the tunnel lining is discussed in " Stress Analysis of Perry Nuclear Power Plant,10-ft Diameter Cooling and Emergency Service Water Tunnel System, Vol. II." by Agbabian Associates, July 1975. The appropriate sections are reproduced herein.
l l
l l
1 I
i 1
It is again noted that the dead load D, the grout load G, and the ground load H' are not included in these cases for tne shaf t analyses. l 1
For this reason, Case 1 is not a real !cading condition. Also, it will be noted ;
that the shaf t stresses are ecual to cr lower than the tunnel s tresses for
- all' cases.
5 STRESSES PARALLEL TO THE LON3;TUDINAL AXES OF TUNNELS AND SHAFTS lt is pointed out in Section 4 of Volume I that stresses produced by both the static and dynamic loads are of greatest significance in pianes normal to the longitudinal axes of the tunnels. For this reason, detailed analyses have been provided in Volume I of typical transverse sections of the tunnels and extrapolated to the shafts in the previous section. Plane strain finite element models, which restrain deformations parallel to the longitudinal axes (z-direction) of the tunnels were used for these analyses. The re fo re ,
except for one seismic load condition, the stress (c,) parallel to the longi-
.. tudinal axes is given directly in the computer printout of stresses for the grout load G, the ground load H', and the temperature stresses T g and T'. The c stresses derived from these analyses are shown in Figures 10
- 4. z through 16. The longitudinal stresses resulting from the dead load are small 9-and have been neglected. Also, for the external and internal fluid pressures, J .
I the longitudinal stresses of the tunnel are low and approximately uniform l circumferentially. Stresses of +20 psi tensien result from an internal water pressure of 50 psi and, -60 psi compressive stresses result from an external water pressure of the sar.e magni tude. Plots of stresses are not
!, shown for the fluid pressure loads.
Stresses developed parallel to the longitudinal axes of the tunnels from seismic loads can be divice6 :nto two categories for presentation. First, the plane strain models used for the transverse modal analysis (see Figs. 41 and 42 of Volume 1) indicate longitudinal stresses c, which are provided in Figures 17 and 18 for the OBE and DSE, respectively. These stresses are of
. . low intensity. 30 psi or less, and can be characterized as being stresses I
13 t
.- - _ ., .. .- , = - . . . . - . ,
1 E
STRESSCS AT CONCRETE 121 SURFACCS HAVE BEEtt EXTRAPOLATED Lit!EARLY FROM ELEMEllT STRESSES
-16 !
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. +1 1 73 PLOT OF CIRCUMFERENTIAL NORMAL STRESSES:
. RADIAL VARIATl0tl SHOWN ON LEFT OllE-HALF
- 0F SECTiott AVERAGE STRESS ACROSS SECTION SHOWN ON RIGHT ONE-tiALF OF SECT 10tl ALL STRESSES ARE lti PSI:
+ = tells 10N
! - = COMPRESS 10tl l
FIGURE 10. LONGITUDINAL STRESSES P,ESULTING IN PERMANENT LINING FROM GROUT LOAD G
- 14
E 121 STRESSES AT CONCRETE SURFACES HAVE BEEN EXTRAPOLATED Lit 1EARLY FROM ELEMEllT STRESSES ,
-49 I
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7.5 s +5 4 l \ '
-2 p
+1 3 73 PLOT OF CIRCUMFERE!1TIAL 110RMAL STRESSES:
. RADIAL VARIAT10t1 SHOWN ON LEFT ONE-HALF OF SECTION AVERAGE STRESS ACROSS SECTION SHOWN 0:1 RIGHT ONE-HALF 0F SECTION ALL STRESSES ARE IN PSI:
+ = TEtiSIOtt
- = COMPP.ESSION FIGURE 11. LONGITUDINAL STRESSES RESULTING IN PERMANENT LINING FROM GROUND LOAD H' 15 1
s
l E
121 STRESSES AT C0!1 CRETE SURFACES HAVE BEEN EXTRAPOLATED LINEARLY FROM ELEMENT STRESSES ,
-587 '
i ELEMENT NO. (;; f ,,,
- -695 ,,- u.-u 75, ,w o M
-584 45 -
4
-641 C~Yg 106, u .g go f
-e90 ,4
-637 3
. 103 r 45
, f gD O 5". g 6-I s'c
- t, ,7 :
e- L 'i > -635 f./
t
- \- -687 7.,
-583 45 88 -587 .
', s
. , t 90 i ;,
-645 A
. 37.5 75 o
y,
. /4
.a . -687 ,
.. I. -699
-486 i /I
-5911 73 PLOT OF CIRCUMFERENTIAL NORMAL STRESSES:
. RADIAL VARIATION SHOWN ON LEFT ONE-HALF 0F SECTION 75 AVERAGE STRESS ACROSS SECT 1011 SHOWN ON l RIGHT ONE-HALF 0F SECTION ALL STRESSES ARE IN PSI:
+ = TENS 1014
- = COMPRESSION FIGURE 12. LONGITUDINAL STRESSES RESULTING IN PERMAt1ENT LINING FROM SEASONAL TEMPERATURE RISE T' (To = +570) o 16
I l E
STRESSES AT CONCRETE 121 SUP. FACES HAVE BEEN EXTRAPOLATED Lit 1EARLY FROM ELEr.ENT STRESSES
+ 220 ',
, y _
.- ~ n\ t f . ,. ,
ELEMEt1T l10. ,yd j
+255 %
118 ,
~
+222 , o 7.5 g
- +248 45 +237 106 ,
.. s" o
/
+235 103 .(
\b s
o, 9 W
., +253 f _ __ .p ..__ _
+219i j 85 S +236 .!
d 45 88 +226 7
~
I \ 90 ,
+262
+250
+ '30
.o. 7.5 -
- s. .I s, +266 -s.
+190 ' :4 j g f 1 1
+234 , i 73 PLOT OF CIRCUMFERENTIAL NORMAL SikE55L5:
RADI AL VARI AT10tl SHOWN Ott LEFT ONE-flAll OF SECTION 7
AVERAGE STRESS ACROSS SECTION SHOWri ou RIGilT ONE-HALF 0F SECTION ALL STRESSES ARE lH PSI:
+ = TENSION
- = COMPRESS 10rl FIGURE 13 LONGITUDINAL' STRESSES RESULTING IN PERMANENT LINING FROM SEASONAL TEMPERATURE DROP T g (T = -230)
'(WITH PARTIAL ROCK RESTRAINT) 17
l C_
STRESSES AT CONCRETE 121 *
.. SURFACES HAVE BEEN !
EXTRAPOLATED LINEARLY !
I FROM ELEliENT STRESSES
+192:
ELEMENT NO.
e -724 l
+190 7.5 45 -266 p 106 , sOh
, f -722 / l 103 ! -266 45 ,
, go' J
~
" I 05 i 3
+189 ;
-270
~
g 70 ' .,
-729 45 oo
\
\ N
-259 No k-274
/ / . )u -
I l ' S~, ~~t\
- j. -706
+188 __.
., i
-r i 5 7 '
73 PLOT OF CIRCUMFEREllTIAL NORMAL SlRESSC.,:
RADIAL VARIATION SHOWil ON LEFT OllL-ilALF OF SECTION
! AVERACF STRESS ACROSS SECTION 5110'.r: 0N RIGHT ONE-HALF 0F SECTION ALL STi(CSSES ARE IN PSI:
t = TENSION
- = CONPRESSION FIGURE 14. LONGITUDl!1AL STRESSES RESULTING IN PERMANENT LINING FROM RAPID TEMPERATURE RISE T' (T' = +570) i 18 i .-
l STRESSES AT CONCRETE 121 SURFACES HAVE BEEN EXTRAPOLATED LINEARLY FROM ELEMEllT STRESSES
-71 l ELEMENT I40.
+385 w 118
-70
[7 +384 45
- 7.5
+157
/
5, 9 103 +157 45 I g \b
'O,
, +387 -
lD 1 1
85 r- +158 _
70 g
- _ _73 -
n, 45 83 , +153 g
\ 90 i
+378 l .g3 I
30
.' 7.5 L- ,
/ N +392 [
-72 L
f\ ,
-70 t 73 PLOT OF CIRCultFERENTI AL NORMAL STRESSES:
RADIAL VARIAI1011 SHouri ON LEFT ONE-ilALF OF SECTl0!1 b
AVERACE S TRESS ACROSS SECTI0li Sil0WN On ki GMT Otil-ilAI.F 0F SECT 10N
+ = TENSIOlJ
- = CottPRESb l0H FIGURE 15 LONGITUDINAL STRESSES Rr5ULTlHG lti PERftANENT LitiltJG FROM RAPID TEMPERATURE DROP T' (T' = -230) (WITH FULL ROCK RESTRAltlT) 19 l
t ..
\
5 STRESSES AT C0!! CRETE 171 SURFACES HAVE SEEtt EXTRAPOLATED LitJEARLY FROM ELEMEliT STRESSES
-68 I
, A 22
\,
-58.[! W +253 45"/ if il 106
/ / +97 \
f f j ! \b L l TC, 9 '
,/ !
45 ce, I
kN co .i
+100 N +108 30
/ 7.5L-s +271 -
' e
^
-4__ ;
\
-54
~- '
W
-54 1 73 PLOT OF CIRCUMFEREt1TIAL tl0kliAL STRES$ts:
RADI AL VARI ATI0tt SliOWri Ott i Er f OllE-itALF Ol' SECT 10:1 AVERAGE STRESS ACROSS SECTI0tt Sil0Wil Oil RIGHT Or;E-IIALF OF SECT 10ft ALL STRESSES ARE I l'S ! :
+ = tells l ut.1
- = COMI'RESSIOli FIGURE 16. L0t1GITUDif1AL STRESSES RESULT!!1G lti PERMAtJEtiT LitiltiG FROM RAPID TEMPERATURE DROP T' ]T' = 320)
(WITH PARTIAL ROCr) RESTRAltlT) 20 __
l ..
l
E 121 STRESSES AT CONCRETE SURFACES HAVE BEEF 4 EXTRAPOLATED LINEARLY FROM ELEMEllT STr. ESSES
'7 l 12L
- <J l ELEMEt4T NO. ;
- g
+11 N
+13 _7}-45 +12 45
- \
106, , go"
/
105 45 o \,
103 9 \b- 1 . . . .:-i
\0 112 $ +15-M b
e 45 88
\
+11 '^
/
45*~ .W 45
^
\ s
+5 / ,_ l hD, 79 l M I +7 73 I PLOT OF L0tlGITUDir:AL STRESSES l 76 ALL STRES3ES Ac.E !!! PSI STRESSES CAli GE E Tota tells 1011 0R CC ' PRESS I0 FIGURE 17 LONGITUDillAL STRESSES IN PET.MAfE:;T Lit:ll:0 FOR OPET.AT'!;G SASIS EARTHQUAKE RESULTil1G FROM TRA!!SVERSE t'CDAL A!!ALYSIS 21
E STRESSES AT C0tlCRETE I2I SURFACES HAVE BEEll .
EXTRAPOLATED LINEARLY FROM ELEMEllT STRESSES
+13l 124
,~ le l
/
l
+22
+26 45 - Q45 +23 106 ,
, go" 109 \
/
45 103 0
\' *
, {+30 _
+23
{ .
- 45 l
94
\
r-45 88
+27 45
' o 45 /
\
+10 l 4 , 7g I 1 I+13 73 PLOT OF L0tlGITUDitlAL
, STRESSES 76 ALL STP. ESSES ARE It! PSI STRESSES CAN BE EITHER tells 10tl l OR COMPRESS 10!!
FIGURE 18. LO!1GITUD!!!AL STRESSES Irl PERMAllEffr LittitlG FOR SAFE SHUTDOWil EARTHQUAKE RESULTillG FR0ft TRAllSVERSE MODAL AtlALYS I S 22 1
- that result f rom the Poisson ef fect of seismic loads resisted by the tunnel in the transverse direction due to circumferential loading of the tunnel. Addi-tional stress, or a second category of longitudinal seismic stress, results f rom the fact that the tunnel section is translated laterally and deformed longitudinally as the earthquake stress waves engulf the tunnels and pass i through the shale surrounding the tunnels. Additional discussion of the phenomenology associated with this second category of stress is required and follows in the next paragraphs.
Stresses resulting parallel to the longitudinal axes of the tunnels f rom translation and deformation of the tunnel axes were calculated by the approach given by Keusel (Ref. 1). In this method the strain in the longi-tudinal direction of the tunnel induced by an earthquake stress wave having a wave length L, and a single wave ampli tude A, is given by:
c = c, + cb" L s n $ cos $ + 2 L
.. Here, c = Axial strain
- s cg = Bending strain 4 = Depth or width of structure
$ = Angle between the direction of wave propagation and longitudinal axis This equation shows that when 0 = 45 , c reaches a maximum value and wLen v = 0 , the bending strain c b is a maximum. In addition, i t 'indi cates that for a structure having a width W much smaller than the wave length L, the axial strain is predominant.
23 k.
t W y+e
i To solve this equation, the relationship of the length L and the amplitude A of an earthquake wave traveling in the medium in which the tunnel is located must be determined. Relationships between A and L for an earthquake wave traveling in sand and clay media are given by Kuesel and are shown in Figure 19 For Chagrin shale, the relationship between wave amplitude and wave length has been estimated based on the A versus L curves for clay and sand, and from the moduli of the three materials (Chagrin shale, clay, and sand). The A versus L and A/L'versus L curves estimated for Chagrin shale are given in Figure 20.
Having determined the A and L relationship of earthquakes in the Chagrin shale, the seismic stress in the longitudinal direction was computed in the following manner:
From Figure 20,
-6 (A/L) max
=
19 x 10 at L =
9000 ft u_
I" Since the, wave length, L, is much g'reater than the tunnel width, W, which L is only 10 ft, only the fi rst term in the equation is important and the r- equation may be reduced to
=
2nA .
c i c3 sin
From this equation, it is evident that the strain c reaches a maximum s
when * = 45 and is equal to the following:
(c,) ,,x =
[^ sin 45 cos 45 =-f-Substi tuting the (A/L) , value
-6 -6
( c,) ,, = 19 x 10 x 3 1416 - 59 7 x 10 24 ,
4 e
28 3
I i CURVE l A = CL" A f, L IN FT l M A 24 2
L. r 0@
0 6 .,d d CURVE 8 l
@ s .'
\@ p) n '. 1 -
I a 5 G 2 3 E E
"U ;;
--- 12 ot*55 pt;c
_ l g o t i.,
s g
g- 8 l
4 3
0 0 4 8 12 16 20 24 28 32 36 *Q -
' WAVE LEMOTH "L" (N 1,000 FT.
FIGURE 19 TRANSVERSE GROUl10 DISPLACEME!1T SPECTRUM (FROM REF. 1) e 4
25
+ . . .
o . . . . . . . . , -, , .
6 . J o
II I I i i i i I I I I I I I I I I 2%
i I 22 11 -
20 10 18 3 -
8 -
g8 -
16 f ~ l%
/ e
~
I2 6 -
hs
< /g e m _ 10 -
4 .-
8
~
6 3 (UPNO _-----_
Ciggg f
5B h g 4
2 -
p
/ /
2 1
p
' ' ' '- l J- ' ' - L- - - 3 L I ' I 8 I '
C i 2 3 4 5 6 7 8 9 to 17 i3 a5 16 17 18 19
~
L (1000 IIi g593g FIGURE 20. TRAllSVERSE GR00t10 DISPLACEMEt!T SI'ECTl:Ull FOR CllAGI,Ill SilALE
The maximum strain can be either tensile or compressive, and the equiva-c, lent stress in the tunnel lining is given by:
9
= = +215 ps!
(s) max E(cs) max -
which is uniformly distributed throughout the entire section. In the above calculation the short term modulus of concrete was used. This value of stress is assumed to apply to the SSE condition. One-half of this value, +110 psi is assumed for the OBE.
( The maximum bending strain, c, b
f the tunnel can be demonstrated to be insignificant in the following manner:
For p=0 9 2 3
2n'AW cos o , 2r AW
.. b) max g2 g 2
i Substituting in this equation the A/L, and L values found above gives the i
following for V = 10 ft, e-(c b max = 0.42 x 10' 1
This is the maximum value of bending stress that could develop for the same I
A/L, but it does not develop simultaneously with the maximum value of c s
. as a different value of $ has been used in the two equations. Since this value is only +2 psi, it can be neglected, it should be noted that an absolute maximum for c b ccurs for a different value of A/L than considered above (i .e. , A/L 2
should be a maximum). However, in all cases c b is an rder of magnitude lower than e smax and can be neglected.
27 I
. ~ . -_ - . _ _ - . . .. . . - .- - ., .- _ -
0
- Comparison of the longitudinal stresses given in Figures 10 and 11 for the grout load G and the ground load H' with the stresses resulting f rom the fluid pressures indicates that the longitudinal static load stresses are quite low and vary from tensile stresses of less than +50 psi to compres- ,
sive stresses of about -100 psi. This statement neglects temperature stress effects. The temperature and seismic stresses, however, are suf ficient to cause transverse cracking. The designer i s , therefore, faced with four j _. alternatives. Recognizing that transverse temperature cracks will result i in a sllsht 1::-! increase in stress in the transverse section, but will not impai r the load-carrying capacity of the tunnel, three of the alternatives involve relieving the longitudinal temperature stresses through the use of transverse Joints or cracks. These alternatives are (1) provide' transverse constructicn join *s at regular intervals along the longitudinal axes of the tunnels; (2) provide control joints rather than construction joints; and (3) provide no joints but let transverse cracks develop at random. The fourth alternative is to control the temperature cracks by the use of longi.udinal temperature reinforcing steel. These alternatives are preroga-
)r-I tives of the designer, if the longitudinal stresses are to be carried by i
!. reinforcing steel, the stresses that must be considered are given in
, . Figures 21 through 27 for the seven loading conditions considered in this analysis.
Since the dead load, grout load, and ground loads do not act as transverse loads.on the shafts, stresses in the longitudinal direction of the shaf ts f rom static loads are less than estimated for the tunnels. It is conservative, and recommended that the same stress conditions be assumed in design of the shafts as computed for the tunnels.
1 s
d 28 i
.k
- - , y m - , , - . . g ..-g- . umvw,m .,--e-
E STRESSES AT CCNCRETE 121 SURFACES HAVE BEEN EXTRAPOLATED LINEARLY FRCM dLEMENT STRESSES
-864 l 1
ELEMENT NO. [ l {,
II0 ' -920 h N
-848(.,' -892 , s go" 106, ,'j (.
/'
f -976 / \'.
103
-912 ,
U' 45 Ua 0, g\b .- ; a
.l '
\
I d -889 l \ -944 .
833 j ,.
I 45 88 _gjg j'.'
i 90 j
/
o
-868 30 o ,'.
-925 7.5 - ,,
- ^~ ./ 917 _.. -3 ,, \
w 1 ll i LL '
-713 i fI
-818' 73 PLOT OF LO!!GITUDitlAL STRESSES:
RADIAL VARIATI0tt SHO'.Jil ON LEFT OrlE-HALF 0F SECT 10tl 75 AVERAGE STRESS ACROS3 5ECilott SliG'.JN ort RICiti J;.E-r!ALF 0F iECT . L'.
SAFE SHUTDOWN EARTHQUAKE CONDITION: ALL SinESSES ARE tu MI-U = 1.000 + 1.00H' + 1.00T + 1.00E' + - trnston
< s .' . ,
. c.y s FIGURE 27 L0tlGITUDINAL STRESSES RESULTitlG FROM CASE 7 LOADS I 35
..