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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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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 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 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 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-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-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 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 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-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 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 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 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 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 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-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-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-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-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-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 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 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 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-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-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:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML20248D2041989-07-28028 July 1989 Lists Search Commands Used to Satisfy Request for LERs Re Relays or Diesel Generator Control Circuitry Problems Affecting Multiple Diesel Generators Similar to Recent Event at Facility & Calibr Problems W/Relays ML17261A8541989-01-13013 January 1989 Discusses 890110-11 Meetings Re Nozzle Sizing Study.Most Accurate Sizing Obtained by Collecting Data of Edge Diffracted Waves from Geometric Extremities of Flaw ML19324A1111988-05-19019 May 1988 Forwards Memo Describing Results of Testing of Plant Bolting Matls Under FIN A-3866,Task Assignment 12 ML19324B2701988-03-0202 March 1988 Forwards Rept on Metallurgical Evaluation of Five Bolts Obtained from Farley Plant.Bolts Found Acceptable ML20207R7571987-03-10010 March 1987 Forwards Technical Evaluation Rept Input for South Texas Initial Plant Test Program Through FSAR Amend 56,Feb 1987 Sser & & Beaver Valley Unit 2 Initial Plant Test Program Through FSAR Amend 15 & Nov 1986 Sser ML20207S5001987-03-0606 March 1987 Forwards Technical Evaluation Repts for Domestic Mark III Plants (Grand Gulf,Clinton,River Bend & Perry) & Gessar Ii. Inserts to Be Included in Section 6.2.1.8 of Draft Sser 2 for Clinton,River Bend & Perry Plants Also Encl ML20195F8651986-10-31031 October 1986 Forwards Request for Addl Info Re MSIV Operability at Facility,Based on Initial Review of Util Rept Entitled, Final Rept 10CFR50.55(e) MSIV Actuators, Forwarded by Util ML20206H3211986-09-10010 September 1986 Forwards Summary Repts from 860811-14 Visit to Kewaunee Nuclear Station & 851002-03 Visit to Cooper Nuclear Station Re Generic Issue 83 on Control Room Habitability ML20206J6001986-08-0808 August 1986 Advises That NUREG-0956 Support Calculations Using ORNL Trends Code to Evaluate Influence of Containment Chemistry or Retention of Hi Can Also Provide Useful Info for General NUREG-1150 Issue Paper,Per Telcon Discussion ML20206H1131986-06-23023 June 1986 Submits DHEAT2 Parametric Calculations for Plant,Per 860620 Discussions.Calculations Run Assuming Any Steam Spike Would Develop Too Slowly to Contribute to DCH Peak Pressure ML20214E1721986-02-25025 February 1986 Ack Receipt of 860210 & 21 Ltrs Accepting Task Orders 3 & 4 Under FIN A-3552 & Task Order 5,respectively.Orders Include Work at Palisades & LaSalle Stations & Mod Review at Davis-Besse.Modified Task Order 4 Under FIN A-3550 Encl ML20206J2521986-01-24024 January 1986 Forwards Early Draft of Executive Summary from Analysis of Station Blackout Accidents for Bellefonte PWR, Per Request. Initial Draft of Rept Scheduled to Be Completed by 860315 ML20206J3681986-01-15015 January 1986 Discusses Latest Calculations of Molecular Iodine (I2) & Organic Iodide (CH3I) Scrubbing During TC1 Sequence from Draft Plant Rept ML20136F4771985-12-31031 December 1985 Forwards PNL-5718, Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept ML20206J4031985-12-13013 December 1985 Summarizes Preliminary Scoping Calculations for Molecular Iodine (I2) Scrubbing in BWR Pressure Suppression Pools. Calculations Made for Most Recent TC1 Sequence in Draft Plant Rept ML20133A3141985-09-27027 September 1985 Forwards Review of Section 4.7 of Technical Evaluation Rept PNL-5600, Review of Resolution of Known Problems in Engine Components for Tdi Emergency Diesel Generators, Reflecting Views Re Crankshafts for 16-cylinder Engines ML20128H7371985-06-27027 June 1985 Forwards Rev 1 to Review of Engine Base & Bearing Caps for Tdi DSRV-12,DSRV-16 & DSRV-20 Diesel Engines, Technical Evaluation Rept ML20141N2981985-05-29029 May 1985 Requests Listed Addl Info Re S&W 1982 Rept, Ultimate Pressure Capacity of Shoreham Primary Containment ML20126E8721985-05-24024 May 1985 Forwards PNL-5200-3, Review of Emergency Diesel Generator Engine & Auxiliary Module Wiring & Terminations, Dtd May 1985 ML20133N7721985-03-27027 March 1985 Forwards Info Telecopied on 850325 Re Locational Distribution of Three Fission Product Species for Surry V Sequence & Time Dependent Release for Fission Product Groups for Peach Bottom ML20214F5101985-03-13013 March 1985 Forwards List of Questions Re Plant Pra,Per 850512 Telcon. Statement of Work, Review of PRA for Seabrook Nuclear Power Plant, Encl ML20107M6231985-02-26026 February 1985 Forwards PNL-5411, Review of Operability & Reliability of Tdi Diesel Generators at Perry Nuclear Power Plant Unit 1, Technical Evaluation Rept ML20133N3461985-02-20020 February 1985 Discusses Review of March Results for Surry & Peach Bottom Sequences,In Order to Quantify Expected Noble Gas Releases. March Model Appropriate for Behavior of Noble Gases ML20134A1011985-02-20020 February 1985 Submits Results of Noble Gas Release Sequences Using March Code for Facilities ML20128P3401984-12-0505 December 1984 Submits Rept for Task 1 Per M Silberberg 841116 Memo Re Concerns Re Lanthanum Releases in BMI-2104.Discusses Discrepancies in Corcon Calculations,Presents Revised Tables 6.14 & 7.16 & Recommends Reanalyses ML20138N6971984-09-18018 September 1984 Forwards Repts Re Irradiation,Decontamination & DBA Testing, Per Request of Y Korobov of Carboline Co ML20134E1591984-08-0202 August 1984 Forwards Brief Summary Rept on Leakage Characteristics of Nuclear Containment Hatches During Severe Accident. Draft of Complete Rept Will Be Mailed Later in Aug ML20127B9221984-07-20020 July 1984 Forwards PNL-5201, Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Grand Gulf Nuclear Station, Unit 1 ML20127B8881984-05-21021 May 1984 Comments on May 1984 Draft Tdi Diesel Generator Owners Group Program Plan.Full Insp of One Engine to Owners Group Spec Recommended ML20093G4821984-05-0202 May 1984 Provides Summary of Battelle Subcontract W/Tdi to Evaluate Special Silicon carbide-impregnated Cylinder Liners & Piston Rings.Task Does Not Involve Dependability Tests of Tdi Engines.No Apparent Conflict Found ML20113A0201984-04-0404 April 1984 Forwards Requests for Addl Info Developed During Review of FSAR Chapter 14 Re Initial Plant Test Program.Review Conducted Through Amend 4.Listing of Items Requiring Resolution Encl ML20117C9421984-04-0303 April 1984 Forwards Proposed Radiological Source Term Input for Facility.Encl Amended to Reflect NRC Suggested Changes ML20093C5281984-03-30030 March 1984 Forwards Audit of Susquehanna Unit 2 Tech Specs, Technical Evaluation Rept ML17320A9711984-03-0606 March 1984 Forwards First Round Questions Following Evaluation of Exxon Rept, Steam Tube Rupture Incident at Prairie Island Unit 1, PTSPWR2 Vs Data,Preliminary Benchmark Analysis. ML17320A9741984-03-0505 March 1984 Forwards First Round Questions on Exxon Methodology Rept for PTSPWR2.Rept Lacks Specific Details Re Biases in Initial Conditions & Boundary Conditions ML20128N6571984-02-22022 February 1984 Comments on Draft Vols IV-VI of BMI-2104,presented at Peer Review 840126 & 27 Meetings.Comments Concern Completed Calculations for Sequoyah Ice Condenser Plant,Recalculated Surry Results & Completed Calculations for Zion Plant ML19306A0151984-02-10010 February 1984 Summarizes 840206-07 Visit to Nevada Test Site Hydrogen Burn Facility to Inspect Condition of Equipment & Cable/Splice Samples After Series of Hydrogen Burn Tests Conducted by Epri.No Indication of External Damage to Equipment Noted ML17320A9731983-11-22022 November 1983 Forwards First Round Questions on Mods to Exxon Draft Repts, PTSPWR2 Mods for St Lucie Unit 1 & Description of Exxon Plant Transient Simulation Model for Pwrs. ML17320A9721983-09-30030 September 1983 Forwards First Round Questions on Exxon Plant Transient Code,Based on Review of Proprietary Rept, Description of Exxon Nuclear Plant Transient Simulation Model for Pwrs. ML20080B5631983-08-12012 August 1983 Forwards Draft Preliminary Review of Limerick Generating Station Severe Accident Risk Assessment,Vol I:Core Melt Frequency. Rept Satisfies Milestone for Task 1 of Project 3 Under FIN A-3393 ML20211D5971983-04-11011 April 1983 Forwards Summary of Independent Development of Finite Element Models & Determination of Natural Frequencies for Piping Problems in Containment Spray Discharge Line & Accumulator Loop 4 ML20132B4961983-02-11011 February 1983 Forwards Evaluation of Generic Key Indicators for Project Engineering/Design Activities at Facilities ML20072L7101982-12-20020 December 1982 Forwards BNL 821213 Memeo Re Degraded Core Accidents at Facilities,Per Task III.3 Defined in Design Basis for Hydrogen Control Sys in CP & OL Applications. No-cost Extension to Contract Requested ML20079J5641982-12-16016 December 1982 Summarizes Findings of 821207-08 Plant Tour Re Use of PORVs or Depressurization Scheme for Removing Decay Heat.Addl Info Requested Includes General Arrangement & Isometric Drawings of Piping Near San Onofre Pressurizer ML20027D1751982-10-18018 October 1982 Responds to 820806 Request to Evaluate Rapid Depressurization & DHR Sys for C-E Plants W/O Porvs, Discussing Role of Task Action Plan A-45, Shutdown Heat Removal Requirements, in Supporting Evaluation of Facility ML20126F4791982-10-0101 October 1982 Requests Permission to Observe Upcoming Types A,B & C Tests at Listed Facilities,Per FIN B-0489, Containment Leak Rate Testing ML20072L6851982-09-21021 September 1982 Forwards Analysis of Full Core Meltdown Accidents in Grand Gulf Reactor Plant, Draft Informal Rept.Rept Satisfies Preliminary Rept Milestone for Task I Defined in Safety Evaluation of Core Melt Accidents:Cp,Ml & OL Applicants ML20064J3941982-05-0303 May 1982 Submits Record of Telcon Notifying of Union Contract Expiration.Painters,Concrete Workers & Iron Workers on Strike Pending New Contract ML17276B0731982-02-10010 February 1982 Comments on Const of Two Power Reactors by Skagit/Hanford Nuclear Project at Hanford.Purchasing & Finishing Terminated Wppss Plants at Hanford & Satsop Should Be Considered as One Alternative to Proposed Action ML20098C8521976-03-26026 March 1976 Forwards Revised Concept Calculations Requested by Jc Petersen for Facilities & Results of Calculations 1989-07-28
[Table view] |
Text
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May.19, 1988 ,
Mr.' Edward Baker
'U.S. Nuclear Regulatory Commission I&E Vendor Programs. Branch Mail Stop 9D4 ,
Washington, DC 20555 -
Ref: Testing of Perry Bolts, FIN A-3866, Task Assignment 12 Dear Eds' .ri I .
i l . Enclosed is a Brookhaven Nationel Laboratory memorandum describing the + q
- . results of the testing of the Perry bolting materials. This work was per- ,"
formed by Mr. C. Czajkowski and Mr. H. Schuster of BNL. j r -
~If there are any questions, please feel free to cal Mr. Carl Czajkowski at FTS 666-4420. t Very truly yours, W Y ^
.WS af John IL Tcym,'Cr'7uk Leader e Enci .
Plant Systems and Equipment Analysis , ,
i cct' J. Conway, NRC ;. : .
C. Czajkoweki i 'E
-o .- 8. Crenier, NRC dj , '
s R. Hall It' K .(
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c v'oi J. Taylor 6 FROM - C. d. Czajkowski/M. H. Schuster [ e k' */M '
- i Task Order 12 of FIN A-3866
'suancT:
~
A total of twelve SAE Grade 5 bolts (no documentation was received with bnits) were received' from the USNRC. Ten of the bolts were subjected to i hardness / tensile testing and chemically analyzed. Two of the bolts have only been hardness tested to date.due to their short (0.875") length. These bolts will be tested as soon as a cpecial fixture is received at BNL. ,
The. status of the testing program follows:
1.D. Comment .;
- 1. IN35F0538(A) a) Hardnesses satisfactory, awaiting fixture
'2. IN35F0538(B) for further testing.
- 3. IN35F0575( A)- a) Bolt meets specification.
4 IN35F0575(B) a) Hardness exceeds specification maximum.
5 IN35F0575(C) a) Bolt meets specification. P
[ 6 OP21(A). a) Bolt meets specification. .
1 <
l 7. OP21(B) a) Bolt meets specification. T,,
l 8. OP21(C) a) Bolt meets specification.
.i e L- . 9. OP21(D) 6) Bolt meets specification. hhs J,11 a) Bolt meets specification.
l l 10 IN43(A)
.. 9p <
l 11 IN43(B) a) Bolt meets specification. g
- 12. IN43(C) a) Bolt meets specification.
With the exception of IN35F0538(A) and (B) testing, this completes Task Order 12
.If da. e are any quest' ions, please contact Carl Czajkowski at x4420. -
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.... BOLT IDENTIF.ICATION: .IN35F0538(A)* ' BOLT SPECIFI, CATION: ;SAE Gr.ade 5' . . ,
2;
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f1 . /', 'f(, s/'[ "k ). ( . . . . ..* A', E$' #4 - +
j y' *" ' ' ;t; , "y'*[,.
?["3:
- D0LT SIZE: , 5/I6"T' 18 UNC x 7/8"' ' ' ]. W.j: M, .N,,'f.
.;7 .: ;
T ,.
. , e, . . o . 7:ce . . >.
9g, i TENSILE STRENGTH: Actual Required by Specification 4 :;
+ <
n s
- ? 9 I g&l Faifure Location
- q' Required by Specification HARDNESS: Actual 29.375 R e average 25 Re min.-34 Rc max.
~
CHEMICAL ANALYSIS:-
Actual w/b Required'by Specification w/o Carbon 4
Manganese-Phosphorus ;[
li Sulfur L Silicon. .a u
L ', . Chromium Ni ckel ' . .
i
- u. ..+ ._
Molybdenum l
i Venadien:
1 N ',
Boron ikg% :
.s L
Copper @
a[.
i i < = less than &;
. 20 q CO M NTS: (A)* is BNL identifier. Due to bolt size testing could not be $y j completed at this time. Mechanical testing and enemica'. unalysis will be completed upon receipt of Special test fixtures Sv. _
- 3
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. . : a i' t > . ' ' ' '80LT. IDENTIFICATION:' IN35f0538(B)* . BOLT SPECIFICATION: .SAE GradeT55,' Y N,
- 'i;" , > ' W q v n p s . . . , , , :y
.ana;,, T,yj;;g3' n;x%;gtyg.grG%
p BOLT, SIZE: ' , S/16" . i18 UNC x,7/8"E""',
y . ', - <
tr C' r%
, . o . , q v;,; y . : ,,
(< .r.. <a 'w
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, TENSILE STRENGTH: Actual ' Required by Specificaticn j<
wy :
i f,'
1::yy n, . . y3 y..g j g;}- - - .
g ,a f- m.
- - g.
. . Failure Locaticn , . ,
usr ,
- a,,
' i HARDNESS: Actual Required by Specification !
i 29.375 Re average 25 Rc min.-34 Re max, [r CHEMICAL ANALYSIS: -
a_
i gy:
Actaal w/o ' Required.by Specification w/o .
Carbon .
Manganese Phosphorus L j- Sulfur Silicon Ch romium ,
4r[
Nickel _.
F,01ybdenum - ,
_.---...3- ,
jQ 0 M Vanadium < < pv yg 1
L Boron
<a less than fg' COMENTS: (B)* is BNL identifier. Due to bolt size testing could not be fQ
^ Sirl completed at this time. Hechanical testing and chemical at.alysis will be n.,.
completed upon receipt of special test fixtures by BNL.
l[I .b i [g, I hi; @{. h5 3 $]'l[}j:! ! . ;{ ];
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y ,; y,. m y n g y , : Y, g g BOLT SPECIFICATION: 1: SAE Grade 5s i
- 60LT. IDENTIFICATION:~.IN3SF0575(A)*
80LT SIZE: .$/8h e c -
+
DNh sn N hI
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q;.. x.: ~, ,3 x%,4;g jy
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Required by' Specification ' -; . ,
1 ENSILE STRENGTH:' . Actual . . .
.....gf
, t ie ,.g9,,
4 , w' .
}
127.8 ksi ,120 ksi? min ,.c W :lo:, -l v'M
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+ * , . ,~~'
' Failure Loca. ion Threads .
- i. f HARDNESS: Actual Required by Specification l 29.25 Rc average 25 Rc min.-34 Re max.
v CHEMICAL ANALYSIS:
t' Actual w/o Required by Specification w/o r
Carbon 0.32 0.28 min. - 0.55 max.
Manganese 0.70 --
Phosphorus 0.016 0.048 max. ,
Sulfur 0.012 0.058 max.
Silicon 0.26 --
1 Chromium 0.03 --
Nickel 0.06 --
Molybdenum --
~J
.tVanadium + >
-- J
>t
. :y
=_ . . , ,4 Boron < 0003 --
.4 Copper --
f;
< = less than ,, ( -
COMMENTS: (A)* is BNL identifier, b
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'80LTLIDENTIFICAT10N:. IN35F0575(B)* C lBOLT' SPECIFICATION . $AELGrade_. .
- e. ey g -
p ; jp ,
- p. ;;3 ,; : .
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; q. : e ,,..y' d;y*mag gp n gow :n, .q _,>.q:a.g sy%gyx;w9 s ,
- s. .
- TENSILE STRENGTH: Actual >-
- Required by Specification '"*.
~'
n .. .
s.
. .-. : ;n
' 135.1 ksi W; ~"; . Sti w , '!
L. - -
,s s
.v..w".,:n x.* ?..;.:120
. min.-
ksi p y
^
Fa11urc location. ' Th' read s HARDNESS: Actual Required by Specification 34.125 Re average 25 Re min.-34 Re max.
+
(Note 1)
CHEMICAL ANALYSIS:
Actual w/o itequired by Specification w/o Carbon 0.37 0.28 min. - 0.55 max. 4 Manganese 0.72 --
Phosphorus 0.018 0.048 max.
Sulfur 0.015 0.058 max. .
Silicon 0.27 --
Ch romium . 0.04 --
Nickel 0.02 --
Molybdenum --
I; ~CVanadtun; -- ' ~? -
d.'
Boron < 0003 --
5.i.'.
Copper -- --
. .7 o
< = less than g:
C0peENTS: (B)* is BNL identifier.
- h Note 1: Hardness exceeds specification maximum. ,, _
~
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l' l
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, a ,,4.y y , % q n g!:p; g &: Q.W ; a , ' *;, ::4; 4&;p ::pq 4^ ^ 1 y m ngw" 'e 'q q, ,
BOLTIDENTIFICATION:'iOP21(A)*, ', 80LT SPECIFICATION I SAE. Grade 5. Ji?.T .
..,?'m MWRMy @fM
(
l(.p,$
(
,+N0LT u.
' ; .~ . w.
9 SIZE i 3 /16"e Jy 7 .
4 4 , %%[12.UNC d:' J.q:' t' ' A z yp%.M,Mg r.
- .i. N W
. . , m:: , ,
^
>; , 1. !
1 . ,;g. g't., a q-, 7f hn.
t;' m.
q
'e a a',ma '
.y 4i g ' /Ay c
,e # .
-e* -ee t s
s j?
U . .f#:
.m i
^ TENSILE STRENGTH: ...l.
Actua
.+
. ' Required by Specification
? r.;
t.
, ' 'i , ^.. f (I .d " 5
*'h
@h z , , ,,
, "x ,
't;"
~,162 ksi " '
3'
. . .E - '120 ksi n
. y failure Location ' Reduced tens 11'e section - v ,
w
, HARDNESS: Actual Required by Specification ,
3? 375 Re average 25 Re min -34 Rc max. .
CHEMICAL ANALYSIS: .
Actual w/o '
Required by Specification w/o Carbon 0.38 0.28 min. - 0.55 max, Manganese 0.82 --
I Phosphorus 0.008 0.048 max.
j Sulfur- 0.026 0.058 nax.
Silicon 0.25 --
Ch romium 0.12 -- 'i Nickel 0.06 --
Molybdenum- -- --
IVanacium
-- -- t Boron < 0003 --
.T_:.,
- J . , .n!
Copper -- --
- .y L
i$
< = less than .~,.
COMENTS: (A)* is BNL identifier. i ,
;w
, 'Yk,.
, e
- I i.
I A
y
...I ^
h 0 *
- . t a * . d 4 ,
y ,
4 v m, y; u. j;,,,, g , mq3m! & - p p < w ux.u. p ;.<>, a.+:s, x,+ .g g m n w 4.,u y;a;.x y .
. r , y 4 r.?,pg p g'zy,4.,f. g 7 g4 4;pg.y.9ggg.yq. 7.fl7g > ;.p.
g,
- y . , 9; d S r" W T9 4 m i e t. +y,,,t:W.g$A$9k
,. g .. ,_
-E.,.0 , ' > " : .
1 ,. ,. / :80LTIDENTIFICATION:)[0P21(B)*11 BOL'(SPECIFICATION:lSAEGrade5~ $
y .
. , m.s . . x g ~.)
m e g m.m.m. g" ' s
, .w m m. . 3...m. . . . . , .y ..
,hs .3:w 90LTeg, 4 ,", . .
- w. e,. SI,Y f, t ,w p,3w..g.c.i,,.g4 . y ,6c a J m., i7 . 9.g /.4,, ,,'T ,.. -..d,,g..f.).?
o ,?g*.*w:' . q.7M, .Js t
a m,,..9/16"J-c120NChyo -
; ,. y .m c cy. m .
7 v, , ,c ; .,3 ,
, , ;gg '
; ev,: .s , , q.< .
j v p, ,o y , , , u., . ,
.t TENSILE STRENGT.H: . Actual
' Required by Specification f; e
*e, ,
',,?
. . , i, *.'r *
..'YA 'j '
./ ~ ' 163.5 ksi: ," , , ,G-
~120 ksi-' '
.c Failurethcation Reduced tensile section HARDNESS: Actual Required by Specification i 1
32.70 Rc average 25 Re min.-34 Re max.
CHEMICAL ANJd.YSIS:
Actual w/o Required by Specification w/o Carbon 0.39 0.28 min. - 0.55 max.
Manganese 0.83 -
Phosphorus 0.007 0.048 max, i Sulfur 0.028 0.059 max.
Silicon 0.26 -- I
- l.
Chromium 0.13 --
Nickel 0.06 -- .
I Molybdenum -- --
. m adix; ; -.. --
. s i nc Doron <.0003 --
t, Copper --
.s. ;
< = less than ViF i
COMENTS: (B)* is BNL identifier.
.n .
'..,,...*..'I
., b i
- s. -
i
,y.2r #.;v -
. q , ,, , . g -
, agq.c h: _k.y:'J g [u.z.qfi1 . , y. ,V ; Ql r f f q q f k yr C_,, -]hW %gfppy.c.cuq e.g.pp&. a;y;;;kyg;yt.y.jQ* f,f W.3;g lMil,. '
aanmw .wm : . wW;wg.:
m:r% m;i:;pf.9:qG 19;pf;Q m hy h. y gw g q :y q: < b } v; &w:.D. a t z. " - <e;'n p + ,;L* n.-
; v
. :w ;. ;g
' p g g: . ; p; m , n. n e z e g ; ; , y r y ~ yp3 : , r
,;y
- P 's: 190LT IDENT!FICATION: OP21(C)* BOLY SPECIFICATION: SAE kade'5 "V D Q Q N y k ..,;c:c; & j p & q" ' 7 (, c , .;c . ',, .
. m;,
; :., ;. z 4,, s m
.,~
. ' ' ;,3g y ev xc4 30LT 512E: 19/16 1 .N 12 UNC "1 .
.s ,
9 ..
.f s4 1 . . , , ;n;;w. v Requiredby'Specificaf. ion
.n TENSILE STRCNGTH: Actual i.'
j r I !
g 1
163.4 ksi 120 ksi" Q _gg ;
Failuie Location Reduced tentile section Q HARDNESS: Actual Required by Specification
, 32.5 R c average 25 Re min.-34 Rc max. .,
CHEMICAL ANALYSIS:
Actuel w/o Required by Specification w/o '
Carbon 0.s9 0.28 min. - 0.55 max. 1 Manganese 0.83 --
Phosphorus 0.008 0.048 max.
Sulfur 0.027 0.058 me.x.
V Silicon 0.26 --
l Chromium 0.13 -- +
Nickel 0.06 -- r e'. '
Molybderum -- --
. Vanadium >
l
- ~
.gf r,
Boron <.0003 -- -
5 '
Copper -- --
< = less than CO M NTS: (C)* is BNL identifier. a .,
.g S.
4-
.a t
' . '4
< /
a a s ,.h r e,mu
- w. <gg.; .<.v..
~
d,;e#v ,. eq., y ., ;xj--g. 4.mcag gaz,. ...g a
,m : Wk y.y.s;g p< n > .. ,
~,3 eq: .g-.f ' fqg y e,d ..y;.4 b.g.
g ,-
.;y'i.t
..g
, 1-y.
; - w y . ' ~m e , a , >
J w <;pA.g)
JBOLT! IDENTIFICATION: OP21(D)* ' . BOLT SPECIFICATION: .SAE Grade 5 I'$
i' :g A %yj;? t,ggy#17. . e4,4f( ,1 t . 4 .
1:1' g .bu,;;;J
..f y ; P 'l. 1 M;1.y. p g;r, i p' y w' J.O1.. C, p lr^ BOLT, m SIZE: ' 9/16"f .12'UNC E ,' ,
C < ,
;s. .
04: .u .
& qq.v?,a r ,
, ;!' (- ,. ,, m. 3 g t ( , < ,- 4
.3
, ..:l.ofi i e TVNSILE STRENGTH: Mtual' ,
Required by Specification . .S. .'
., . w ,
% 4n 166.3 ksi 120 ksi W '
0.
;d i h :
. Failure Location Reduced tensile section % '
_t. .a HARDNESS: Actual Required by SLecification i
.i$
S2.375 Re averaga 25 Rc min.-34 Re, max. 'l CHEMICAL ANALYSIS: T
. Y.:.
s -
Actual w/o Required by Specification w/o ft Carbon 0.39 0.28 min. - 0.55 max. _4. . -
Manganese 0.81 --
Phosphorus C.007 0.048 max.
Sulfur 0.028 0.058 max.-
=1 Silicon 0.26 L
1 Chromium 0.13 -- y; '
2 Nickel 0.06 -- ;
Molybdenum -- --
, W4 1 Vanadium -- . .
Q Q;;iJ ', t Boron < 0003 --
{ '$ i L Copper -- --
./'
l m, h s-a j
< = less than - '
CO M NTS: (D)* is BNL identifier._
.N ,
.s,[,$d) '
l' 1..
i L o y u 8 i
1
] L *;;.@;dy,,pg.y.4.yy 1
.hf h kkh b
, lw%;.e; L 95mga::n.
h b h '
i
. ;,g b y. s...y w.p ey; 3 .. ,, v
~
, , , - ,y..
4 m
.. . ;i.
a, .u, ,
t u
,.y ; a3g a . ;, g,e g.g e- :;s.:"';;g qm gH
,c gwwmyfg, m+c3gcp
; .;; .q. . ;y , t.P y,1;7".g4 W,
. <, . .p" x .n ,. .
n ..
vat e 9; / # P' ;BOLTIDENTIFICATION:..IN35F0575(C)* BOLTSPECIFICATION:'SAE,: Grade'5ljyd.
Vl, .fs e. g;( 3 .;;g3/8" ;16-UNC3[.; {gg,,e ; yQ ,ne ,
.g,jQ.g f ', f S0LT SIZE: g ~ n .cy -r */./1 y y ,tc,: m r3)yyp.j;gM.;MWw c
f MW ..mg . ,
m y.g qe .[ ' 7,;c;( w n. w:> 5
?
, ~ . , y ,..
.a. n - <L'- .
, , , ., ..v .. a ., ..
p TENSILE STREKGTH: Actual _ Required by Specifice':, ion > q
. i t.... .
, >. ,.,w? , .,
a 'n < W Aq
.'146.7-ksi 120lksi m. i, n., 4 . &.
Failure Location Threads d
, '
- HARDNESS: Actual Required by Specification o
33.5 R e average 25 Re min.-34 Re max, CHEMICAL ANALYSIS:
'ctual w/o-
. Required by Specification w/o Carbon 0.35 0.28 miri. - 0.55 max.
Manganese 0.71 --
Phusphorus 0.018 0.048 max.
Sulfur 0.014- 0.058 max.-
'\
Silicon 0.28 --
Chromium 0.04 --
Nickel 0.01 --
Molybdenum. -- --
i:' panadium -- ,
h.: >
Boron <.0003 --
g
,p ,
Copper -- --
74 5
, Ji y '.
e
< = less than COMMENTS: (C)* is BNL identifier, ,
n ,
e h
1 e
?.y
, r -
/ '
a, s, y./ . y; ,(.s. q , m, ,
- . w . n.a , .
m(c3 ,, .1,,,.n.u,,.zyl a.a~ m..y V, 73 m, M .py, a. n .: #. , . we, e .re w ig.,m. z,. e:
g e
- e. .t .s ,,.r a . .
/ , ;, s..,a: x...~,,,,.
], . Y4 ; /? e s;W9 i [ x j !lX 2y ' ;:.
y ;-;'[,;r., pMF{-., g. - .Q
+-
; ; y ,! yg;p(14 '
c .
;v 3 ,Q.,; y gf %.g,.y,
. . n ,- .f~+9 . ,QC g.,.
. j,f
'. 4 y .7 v t .h ;;; -
A ) v , BOLT.SPECIFICATI0E SAE;. Grade:Sy. . a 4 s.9 ar m .: 80LTIDENTIFICATION:
.g,y 7 SIN 43(g)*L,.' , yyy ;;f
' '80LT . SIZE:' L3/4f U 3l10.UNC qi, fij,""g.g*g3. ;
".T;M g~.m$g g;g g y.M
; I ,
g/ g:0'., "",4
.s u. u m' n ,p , v: . c ty . : a ,-
, , vp .: .
,7 1. a .%. .
's '- ..s ; Z v.t ?@ ' > si',
~
1 TENSILE, STRENGTH: L : Actual. ,
. ._ Required by Specific.: tion 4 r. r.
J, > '
Q .o ,
140.8 ksi l 120'khi ,' D; m
.$:k . .
t g Failure location Threads V
HARDNESS: Actual _ Required by Specification .)
29.525 Rc average 25 Re min.-34 Rc max. . ,;
2.:
CHEMICAL ANALYSIS: Q; -
x t
T>
Actual w/o Required by Specification w/o
.m Carbon 0.32 0.28 min. - 0.55 max. -',
Manganese 0.75 --
Phosphorus 0.015 0.048 max.
Sulfur 0.020 0.058 max.
.7 Silicon 0.26 --
Chromium 0.1) -- -
Niekel- 0.02 --
,v n Molybdenum' --
a
, Yanadiv. --
, 4 .
. .g pA '
. g Boron <.0003 --
.s S3':
Copper -- --
c$ 4 ocA Mk}g
< = less than Sh.hIj m COMMENTS:
(A)* is BNL identifier. M.
re - !
l
'} -
\
~
x.w a h5 1- g e
i i: 4 4
'L 'r . _ ._
h .f kn fk$Apyvcg,hf$ [fd hdh.f ig hNkh: 4 hkh N y;M,3jn:c,@;n;;mp.
4(::;1 u A3 o w+ wq n_e y:S.; % .wp e q;., qq.yqgg
,; y p s 4 Q p;2: 3,yy p :
a BOLT SPECIFICATION:: y x yep: p gay y* g
* >., y;LT BO IDENTIFICATION:), IN43(B)* .a, z P
.,w SAE Grade'l
- w. u .: g;j ,
f 4
.. , , n ;, , ,,. . .
+
jn -
MT"SIZEI3 E '/kl-[10 NCYM%.,'.f,f?. ;$g.$$m $$,dif 3O; yh.o y c;y@y; ahM.c gf'N, ,d U 1
5 ,i.
(
a, s : j- w"O '
I. <
.a 4,
,,4- ,x m_ : ;
S ,o J,l 3 , ..,;. .jg A v".;M" yg' . < < t g.e c
.c 31 , .,,o ,. @ !
* > S? .o .
..... b' .
.,a ,
. i Actual Required by Specific'ation_ f ' ,92 ,
j' o TENSILE STRENGTH:
f, ,m, ,,u .m
,s , . ,_
,141.4/ksi; /E '
N s.120 ksi. min.pl' y ,:. !
9
. . . t ..- 5
- p S ,t 'g
. Failure Location Threads' HARDNESS: Actual Recuired by Specification' N 1
28.125 Re average 25 Re min.-34 Re max. .t .
x
..e CKENICAL ANALYSIS:
Actuel w/o Required by Specification w/c Carbon 0.35 0.28 min. - 0.55 max.
t Manganese 0.75 --
Phosphorus 0.019 0.048 max.
Sulfur 0.017 0.058 max. ,
1 Silicon 0.22 --
Chromium 0.10 --
Nickel 0.02 --
r Molybdenum --
7 . ,
-- -- *s:
Vanad.ium _
.o Boron <.0003 --
' Y.x r Copper -- . t, sut!r. .;
.. 1
< = less than .gf. .
u
- , C000ENTS
- (B)* is BNL identifier. //fh :.
i e, L. ,
s-l f'
9 l
l 4
j s
9 .e-M 4 pggeg
' i,&l:b, , - w' .qfpM;p:f,pfy;My.7,;fqp@RQ;payygn f&pfQ, M Gfpyp.:W.
..e pc gqq@up@ga@Wll93 t
p m yg;
.. .a w ,
p .
, o,
' m y?9 Ji'A , yg,9 f .n g ,s. , . ,
.s e i O
's
<% , ,, gn.5 e 4p,4;c ,; 3. , .N
,:y" )o , ie
, , t; : ; 6f e.pt-;8t x '
'n .,
i,
}' ,. > ,
< gj *
> ~ :
y ,1; F ' BOLT IDEhTIFICATION: IN43(C)* BOLT SPECIFICATION:- SAE Grade'5 ~r !{
, '. a , .- % ,- . . s . .
, ,,, 9
' ' ~
BOLT.SIZEt' !3/4" - 10 UNC"w
{# ,
'j:p- i
.;i l TENSILL STREh6TH: Actual Required by Specification Je '
s i 152.2 ksi 120 ksi o { - -
9
. Failure Location Threads l HARDNESS: Actual Required by Specification
' i. f,3 27.375 Rc average. 25 Rc min.-34 Rc max. @s '
vg.
D CHEMICAL ANALYSIS:
F r.
Actual w/o Required by Specification w/o M J A 0.28 nin. - 0.55 max.
Carbon 0.32 -
Manganese 0.72 --
-l
- s. >
Phosphorus 0.018 0.048 max.
Sulfur 0.021 0.058 max.
Silicon 0.24 -.
Chromium 0.10 --
I
. x r; .
Nickel 0.02
$Ly Molybdenum -- -- ?., .
kh t Vanadium ;
Boron <.0003 --
.' t
- 9 Copper --
.a !
3:
< = less than %
CO M NTS: (*)* is BNL identifier. .;,;
3 5
;.4
,U l
'!gn
- U. :
. . R'3hJ g-. . .,}}