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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F3901999-10-14014 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Document Proprietary & Will Be Withheld PY-CEI-NRR-2438, Informs That DBNPS & PNPP Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & PNPP Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217G9201999-10-14014 October 1999 Discusses Utils Request for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 ML18023A0701999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl 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 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 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 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 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 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 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 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 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 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 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 ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE 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-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 PY-CEI-NRR-2377, 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 11999-06-16016 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 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-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 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-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-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-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant 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 PY-CEI-NRR-2377, 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 11999-06-16016 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 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-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 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 PY-CEI-NRR-2378, Submits Withdrawal of Inservice Exam Relief Request PT-0081999-03-24024 March 1999 Submits Withdrawal of Inservice Exam Relief Request PT-008 ML20204G9101999-03-22022 March 1999 Forwards One License Renewal Application Consisting of NRC Form 398 & NRC Form 396 for M Nemcek License Number SOP-30475-2 & Docket Number 55-30267 for NRC Processing,In Accordance with 10CFR55.57.Without Encls 1999-09-09
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to 4 06 Lew W. Myers 440-280-5915 Vse President Fax:440-280-8029 June 29,1999 PY-CEl/NRR-2403L United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Perry Nuclear Power Plant Docket No. 50-440 Response to Request for Additional Information Regarding the Generic Letter 96-05 Program (TAC NO. M97085)
Ladies and Gentlemen:
The response to a Request for Additional Information (RAI), dated March 25,1999, regarding the Generic Letter 96-05 Program at the Perry Nuclear Power Plant (PNPP) is contained in Attachments 1,2 and 3.
There are no regulatory commitments contained in this letter. Any actions discussed in this document represent intended or planned actions, are described for the NRC's information, and are not regulatory commitments if you have questions or require additional information, please contact Mr. Henry L. Hegrat, Manager-Regulatory Affairs, at (440) 280-5606.
Very truly yours,
/
Attachments cc: NRC Project Manager NRC Resident inspector NRC Region 111 State of Ohio A
\\cy 9907060370 990629 PDR ADOCK 05000440 P
PDR
A4achment 1 PY-CEl/NRR-2403L 5
Page 1 of 5 Response to RAI Question 1 in NRC Inspection Report No. 50-440/96-05, the NRC staff closed its review of the motor operated valve (MOV) program implemented at Perry Nuclear Power Plant (Perry) in response to Generic Letter (GL) 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance." in the Inspection report, the NRC staff discussed certain aspects of the licensee's MOV program to be addressed over the long term. For example, the inspectors noted that the licensee (1) agreed to modify valve 1G33-F040 during the next scheduled outage as part of Perry's margin improvement plan; (2) would continue to evaluate applicable information to confirm the valve factors applied to Anchor / Darling flex-wedge gate valves 1E22-F012 and 1E51-F059 and Borg Wamer gate valve Groups 4 and 6; and (3) would monitor stem friction coefficient performance to improve the statistical basis and to confirm the stem friction coefficient assumptions applied to the closing direction thrust calculations. The licensee should describe the actions taken to address the specific long-term aspects of the MOV program at Perry noted in the NRC
!nspection report.
PNPP Response (1) 1G33-F040 modification:
The overall gear ratio for 1G33-F040 was modified during the June 1996 refueling outage.
The gear ratio modification enabled the overall margin of the MOV to be improved from = 7%
to = 62%. Based on this action, there is no further corrective actions necessary regarding GL-96-05 program requirements for this MOV, other than the normally scheduled Periodic Verification testing and Preventative Maintenance tasks to maintain the valve margin.
(2)
Valve Factor (VF) confirmation:
I The PNPP 96-05 Program presently uses in-house test data and intends to use the Joint Owners Group (JOG) data when the data becomes available. The JOG data will be used to confirm design assumptions made relative to Valve Factor values. For the specific caces regarding Groups # 3,4, and 6, Attachment 2 documents the flow test data collected from those valves that are practical to Differential Pressure (DP) test. The intent is to continue this effort until sufficient data has been collected. Flow test intervals are reviewed and adjusted, based on the trend data evaluation process in accordance with FTI-F0019, " Engineering Review of MOV Test Results".
Test results from valves that can be flow tested will be used to determine the design-calculated assumptions for those valves that are not practical to flow test. The test results will be taken from valves from the same group and size. The PNPP 96-05 program, therefore, addresses long-term actions relative to GL 96-05 required to confirm the Valve Factor applied to Groups # 3,4 and 6 valves.
(3)
Stem Coefficient of Friction (COF) performance confirmation:
Stem COF is monitored whenever thrust and torque loads are available during individual MOV diagnostic testing. Test data to date supports use of the design COF value of 0.15, the value which is typically assumed in the closing direction thrust calculations. Any contradictory information obtained through the JOG program will be resolved utilizing the PNPP Corrective Action Program.
PY-CEl/NRR-2403L t
Page 2 of 5 As part of overalllong-term improvement relative to COF consistency, PNPP has established a program to gradually convert from using Never-Seeze as a stem lubricant to Mobilgrease 28.
This process will be performed in a gradual manner such that it will allow proper monitoring and data trend analysis.
Mobilgrease 28 was first used as a valve stem lubricant at PNPP in February 1996. Overall trend data since then has indicated that MOVs using Mobilgrease 28 as a stem lubricant, some valves being located in harsh environments, have exhibited better overall consistency and improved load sensitive behavior characteristics Question 2 The JOG program specifies that the methodology and discrimination criteria for ranking MOVs according to their safety significan& are the responsibility of each participating licensee. In its letter dated March 17,1997, the licensee stated that MOV risk ranking would be based, in part, on an expert review and Perry's Probabilistic Risk Assessment (PRA). As Perry is a boiling water reactor (BWR) nuclear plant, is the licensee applying the BWROG methocology for ranking MOVs based on their safety significance as described in BWROG Topical Report NEDC-32264 and the NRC safety evaluation dated February 27,1996? If not, the licensee should describe the methodology used for risk ranking MOVs at Perry in more detail, including a description of (1) the process used to develop sample lists of high-risk MOVs from other BWRS; and (2) how expert panels were used to evaluate MOV risk significance.
PNPP Response While the PNPP did not participate in the Boiling Water Reactor Owner's Group (BWROG) development of the BWROG Topical Report NEDC-32264, "Applicatinn of Probabilistic Safety Assessment to Generic Letter 87-10 Implementation," the risk ranking methodology utilized by the Probabilistic Safety Assessment (PSA) Group at PNPP is identical to that as described in the topical report. The motor operated valve risk ranking is based on Fussell-Vesley importance measures utilizing baseline failure data (2.93x10-3/ demand), and sensitivity study failure data defined per NUREG/CR-4550 (9.00x10-3/ demand) and NUREG/CR-5140 (8.70x10-2/dems.0).
The resulting valve ranking was then generated corresponding to the categories as described in the topical report.
Question 3 The licensee's interim static test program allows some valves with medium and high margin to i
be tested on a four or six refueling outage frequency, nspectively. This is consistent with the outage frequency recommended by the JOG interim sta+ic diagnostic test program. However, in the NRC safety evaluation dated October 30,1997, on BWROG Topical Report NEDC-32719 describing the JOG pmgram, the NRC staff stated that MOVs with scheduled test frequencies beyond 5 years will need to be grouped with other MOVs that will be tested on frequencies less than 5 years in order to validate assumptions for the longer test intervals. The i
NRC staff stated that this review must include both valve thrust (or torque) requirements and actuator output capability. The licensee should describe how its MOV static diagnostic-testing pmgram will satisfy this condition of the NRC safety evaluation.
Attachm nt 1 PY-CEl/NRR-2403L Page 3 of 5 PNPP Response PNPP is a participant plant in the JOG Periodic Verification test program. The present PNPP 1
Periodic Verification test frequency matrix in accordance with the Motor Operated Valve (MOV) Program Plan for Generic Letter 89-10 (MPF), Attachment 12, follows the interim JOG program recommendation for static testing on medium and high margin valves, which may result in up to a 10 year frequency. With the exception of Group # 12 (two valves), Periodic Verification testing has been conducted on at least one representative valve from each Group.
Testing on one of the two Group # 12 valves (most likely 1C41-F0018) will be conducted during Cycle 8. A Group by Group breakdown for the valves tested to date as they relate to j
Periodic Verification is included in Attachment 3.
Based on the overall actions taken and the program already in place, with the exception of Group #12 as stated above, PNPP meets the NRC safety evaluation report requirements on the BWROG Topical Report NEDC-32719, regarding frequency test intervals exceeding a five year span.
Question 4 The JOG program focuses on the potential age-related increase in the thrust or torque required to operate valves under their design-basis conditions. In the NRC safety evaluation dated October 30,1997, on the JOG progism, the NRC staff'specified that licensees are responsible for addawssing the thrust or torque delivered by the MOV motor actuator and its potential degradation. The licensee should describe the plan at Perry for ensuring adequate ac and de MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1.
PNPP Response (1) Long term actuator degradation resulting in torque and thrust load output to the valve:
Long term actuator performance is maintained by means of two programs. These are the PNPP Preventive Maintenance program and the PNPP Periodic Verification test program. Details of the programs follow, a.
Preventive Maintenance Each 96-05 Program MOV is periodically inspected and maintained through the PNPP Preventive Maintenance (PM) program. In general, the program requires maintenance and inspection on the actuator that includes:
intemal gearbox (s) grease sample inspection and inventory level, e
e ' Valve stem cleaning and lubrication.
f imit switch compartment cleaning and inspection.
e Switch contact cleaning / inspection.
Wiring inspection.
General overall bolt and fasteners inspection / tightness.
Motor insulation resistance testing.
The PNPP Preventive Maintenance program ensures that the actuator is maintained properly. The PNPP Corrective Action Program would address degradation.
u PY-CEl/NRR-2403L i
i Page 4 of 6 b.
Periodic Verification Each 96-05 Program MOV is periodically tested at the frequencies established by the GL 96-05 Periodic Verification (PV) test program. Testing is performed and flow data is evaluated. Critical parameters of the test results are then trended. General trending parameters monitored are as follows (as available):
Torque and thrust values (i.e. at unseat, average run, seat contact, control switch trip, maximum, DP test flow cutoff).
Motor Current (i.e. at unseat, average run, control switch trip, maximum).
Spring pack (i.e. at unseat, average run, control switch trip, maximum).
Motor power (i.e. at maximum loads)
Stem friction factor
. Valve Factor
.' Margin.
Based on the overall periodic testing and data trending as specified ahve, any potential dsgradation of the actuator's capability would be dentified. The PNPP Corrective Action Program would address corrective actions.
(2)
Limitorque Technical Update 98-01 and actuator AC / DC motor output capability issues.
a.
AC Motors Limitorque Technical Update 98-01 and Supplement 1 identified concems associated with Limitorque actuator capability using AC motors. The two main issues were AC motor curve performance (i.e., use of Application Factor) and actuator gearbox efficiency (i.e., use of Pullout Efficiency). The two concems are addressed as follows:
Application Factor in accordance with Limitorque Technical Update 98-01 and Supplement 1, it is recommended that an Application Factor of 0.9 be used in all cases when determining output torque, unless an attemate engineering justified method can be used.
Previously, Limitorque endorsed the use of a 1.0 Application Factor under certain i
circumstances.
1 PNPP has opted to use an attemate, industry accepted engineering method, where feasible. The Commonwealth Edison AC motor output calculation methodology was selected and is used at PNPP. The NRC staff has previously reviewed this methodology and determined it to be an acceptable attemative. The Commonwealth Edison method does not require the use of the Limitorque Application Factor or the Limitorque equation methodology.
The Commonwealth Edison testing methodology development process was unable to test every type and size Limitorque AC motor. Therefore, Commonwealth Edison test data is not available for nine PNPP valve AC motors, four motor types. For the nine AC motors not covered by the Commonwealth Edison method, PNPP utilizes the Limitorque Technical Update 98-01 methodology, including the use of a 0.9 Application Factor.
PY-CEl/NRR-2403L Page 5 of 5 l
When the Commonwealth Edison methodology was initially adopted by PNPP in 1996 as part of the GL 89-10 program, there were several valves identified that required minor torque switch re-adjustments in order to meet the new requirements. Since then, the necessary adjustments have been completed. In addition, there was one case ( MOV 1E22-F012) where a torque switch adjustment would have resulted in a margin that was lower then desired. In that case, a gear ratio change modification was implemented to allow for improved overall capability margin.
Gear Box Efficiency Limito;que Technical Update 98-01 and Supplement 1, requires the use of Gearbox Pullout Efficiency. PNPP has used Pullout Efficiency in accordance with "Limitorque SEL 7", also known as "The Select Guide", since 1996. However, Technical Update
' 98-01 indicates that in SMB-1 units with 66:1 worm gear ratio, the stated Pullout.
j Efficiency values per the "Limitorque SEL 7" Table may not be conservative. A review
{
at PNPP indicated that the four 96-05 Program valves listed below utilize this actuator.
1E12-F004A 1E12-F004B 1E12-F105 1E21-F001 For the above MOVs (i.e., SMB-1 with 66:1 worm gear ratio), additional information has been requested from Limitorque for the specific efficiency value applicable. In the interim, until vendor information becomes available, PNPP has taken the following actions to account for this concem:
)
- a. Calculations for these four valves have been updated to add an additional
" Adjustment Factor" of 0.9 as a conservative measure.
- b. The valves were reviewed to ensure adequate thrust mardn existed. The review indicated that the safety function is to close under the design basis oifferential pressure of zero (0) psid. As such, these valves currently exhibit thrust margins greater than 100%. This provides assurance that even if a very conservative gearbox efficiency were provided by Limitorque, sufficient margin would exist to envelop it.
Based on the above actions already taken, the Application Factor issue and the Gearbox Efficiency issue, relative to the Limitorque Technical Update 98-01 and Supplement 1, have been addressed at PNPP.
b.
DC Motors i
DC MOV Actuator capability is calculated in accordance with Attachment 1 of "Limitorque Maintenance Update" dated 8/17/88. DC motor capability is calculated by using: (1) pullout efficiency, (2) an application factor of 0.9, (3) a " reduction factor" of 0.9 for motor performance curve correction, and (4) motor winding resistance loses for motor temperature rise.
The BWR Owners Group is working with MPR Associates to develop a methodology for DC MOV torque capability and stroke time determination. PNPP intends on being a participant member in this BWR Owners Group effort. Appropriate action will be taken, if required, when the final results are published and endorsed by Limitorque.
PNPP DC MOVs have adequate capability to perform their design basis function as required by the 96-05 program.
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P:ge 1 cf 1 VERIFICATION FLOW TEST RESULTS Groun # 3 IE22-F012 Original flow test 6/18/94,
-(Open: 0.377, Close: N/A)
'+
Confirmation flow test 5/16/97, VF -(Open: 0.312, Close: N/A) 1E51-F059 Original flow test 4/09/96, VF-(Open: N/A, Close: 0.277)
Confirmation flow test: 07/09/96, VF-(Open: 0.413, Close: 0.424)
Confirmation flow test: 01/24/99, VF -(Open: 0.412, Close: 0.440)
Grouc # 4 1E12-F064A Original flow test 3/31/94, VF-(Open: 0.300, Close: 0.378)
Confirmation flow test 6/25/98, VF-(Open: 0.639, Close: 0.723) 1E12-F064B Original flow test 5/08/94, VF -(Open: 0.266, Close: 0.279)
Confirmation flow test 7/30/98, VF -(Open: 0.508, Close: 0.554) 1E12-F064C Original flow test 5/18/94, VF -(Open: 0.314, Close: 0.382)
Confirmation flow test 2/10/98, VF -(Open: 0.527, Close: 0.588) 1E21-F011 Original flow test 10/28/93, VF -(Open: 0.626, Close: 0.719)
Confirmation flow test 10/03/97, VF-(Open: 0.465, Close: 0.590)
Group # 6 ICll-F083 Original flow test 3/14/96, VF-(Open: 0.693, Close: 0.623)
Confirmation flow test N/A.
1E12-F042B Original flow test 5/15/94, VF-(Open: 0.273, Close: 0.373)
Confirmation flow test N/A.
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PERIODIC VERIFICATION BY VALVE GROUP l
i Group # 1: The group consists of two Anchor Darling 150# Gate valves. One representative valve (IE22-F015) has been tested to meet Periodic Verification validation intent.
i Group # 2: The group consists of one Anchor Darling 655# Gate valve. Valve (IE22-F004) has been l
tested to meet Periodic Verification validation intent.
Group # 3: The group consists of two Anchor Darling 900# Gate valves. Both valves (IE22-F012, IE51-F059) have been tested to meet Periodic Verification validation intent.
Group # 4: The group consEts of 25 Borg Warner 300# Gate valves. Ten representative valves (IG61-F030, IE21 F011, IE12-F064 A, IE12-F064B, IE12-F064C, IE12-F028A, IE12-F028B, IE12 F537A, IE12-F537B, IE51-F068) have been tested to meet Periodic Verification validation intent.
)
Group # 5: The group consists of two Borg Warner 900# Gate valves. Both valves (1E12-F003, IE12-F09) have been tested to meet Periodic Verification validation intent.
1 Group # 6: The group consists of I8 Borg Warner 1500# Gate valves. Fifteen representative valves (ICl l-F083, I B21 -F016,1821 -F019, I G33-F053,1 G33-F054, I E51-013, I G33-F001, 1G33-F004, IG33-F039, IG33-F040, I E51-F063, IE51-F064, I E12-F042A, I E12-F042B, 1E12-F042C) have been tested to meet Periodic Verification validation intent.
Group # 7: No valves listed under Group # 7.
Group # 8: All MOVs under Group # 8 no longer apply. E32 system was deleted during RFO-7.
Group # 9: The group consists of three Anchor Darling 900# Globe valves. All three valves (IE22-F010, IE22-F011, IE22-F023) have been tested to meet Periodic Verification validation intent.
Group # 10: The group consists of Anchor Darling 300# Globe valves. All four valves (1E21-F012, 1E12-F021, IE12-F024A,1E12-F024B) have been tested to meet Periodic Verification validation intent.
Group # 10A: The group consists of four Anchor Darling 300# Globe valves (CCI Cage / Plug modification). All four valves (1 E12-F003 A,1 E 12+ F003 B,1 E12-F048A,1 E12-F048B) have been tested to meet Periodic Verification validation intent.
Group # 11: The group consists of two Borg Warner 1500# Globe valves Both valves (IE51-F022, IE51-F045) have been tested to meet Periodic Verification validation intent.
Group # 12: 'Ihe group consists of two Rockwell 150# Globe valves. Neither valve has been Periodic Verification tested to date. Baseline testing was performed on 12-13-95 for IC41-F001 A and 6-15-94 for IC41 F001B.
I Group # 13: The group consists of thirteen Rockwell 1500# Globe valves. Three representative valves (IE51-F076,1E51-F019, IPS2-F646) have been tested to meet Periodic Verification validation intent. Note that two of the thirteen valves listed (1 E32-F006,1E32-F007) no f
longer apply as a result of the E32 system being deleted during RFO-7.
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PY-CEl/NRR-2403L P ga 2 of 2 Group # 14: No valves listed under Group # 14.
Group # 15: The group consists of seven Contromatics 150# (stainless steel disk and body) Butterfly valves. Four representative valves (IG43-F030A, IG43-F030B, IG43-F040A, IG43-F0408) have been tested to meet Periodic Verification validation intent.
Group # 16: The group consists of twenty-seven Contromatics 150# (carbon steel disk and body) Butterfly valves. Twenty three representative valves (IP50-F060, IP50-F140, IP50-F150, IP45-F140, OP42-F150A, OP42-F150B, OP42-F295A, OP42-F295B, OP42-F300A, OP42-F300B, OP42-F325A, OP42-F325B, IP43-F355, IP43-F400, IP43-F410, I G42-F010, I G42-F020, IPl 1-F060, IP43-F055, IP43-F140, IP43-F215, IP45-F130A, IP45-F130B) have been tested to meet Periodic Verification validation intent.
Group # 17: The group consists of four Henry Pratt 150# (seal on disk) Butterfly valves. One representative valve (IM17-F025) has been tested to meet Periodic Verification validation intent.
Group # 18: The group consists of two Henry Pratt 150# (scal on body) Butterfly valves. Both valves (0P41-F420, OP41-F430) have been tested to meet Periodic Verification validation intent.
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