Similar Documents at Perry |
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That Proprietary Document NEDE-32907P,DRF A22-0084-53, Safety Analysis Rept for Perry NPP 5% Power Uprate, Class III Dtd Sept 1999 Be Withheld.Determined Document Proprietary & Will Be Withheld ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212K9271999-09-30030 September 1999 Refers to 990927 Meeting Conducted at Perry Nuclear Power Plant to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff ML20212J1451999-09-30030 September 1999 Forwards Order,In Response to 990505 Application PY-CEI/NRR- 2394L.Order Approves Conforming License Amend Which Will Be Issued & Made Effective When Transfer Completed ML20217E7111999-09-30030 September 1999 Documents Telcon Conducted on 990929 Between M Underwood of Oh EPA & D Tizzan of Pnpp,Re Request to Operate Pnpp Sws,As Is,Until Resolution Can Be Obtained ML20212G4161999-09-24024 September 1999 Informs of Completion of Licensing Action for Generic Ltr 98-01, Y2K Readiness of Computer Systems at Nuclear Power Plants, for Perry Nuclear Power Plant ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED ML20212A8371999-09-13013 September 1999 Forwards Insp Rept 50-440/99-13 on 990712-30 & Notice of Violation.Insp Included Evaluation of Engineering Support, Design Change & Modification Activities,Internal Assessment Activities & Corrective Actions ML20217A8971999-09-0909 September 1999 Forwards Insp Rept 50-440/99-09 on 990709-0825.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages ML20211Q6911999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Perry Operator License Applicants During Wks of 010108 & 15.Validation of Exam Will Occur at Station During Wk of 001218 IR 05000440/19990011999-08-31031 August 1999 Requests That Page Number 4, P2 Status of EP Facilities, Equipment & Resources, of Insp Rept 50-440/99-01 Be Replaced with Encl Rev PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20210Q8421999-08-13013 August 1999 First Final Response to FOIA Request for Documents.Records Listed in App a Being Released in Entirety & Records Listed in App B Being Withheld in Part (Ref FOIA Exempt 5) ML20210R7861999-08-12012 August 1999 Forwards Insp Rept 50-440/99-12 on 990712-16.No Violations Noted.New Emergency Preparedness Program Staff & Mgt Personnel Were Professional & Proactive ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 ML20210Q7981999-08-10010 August 1999 Informs That Intention to Utilize Sulfuric Acid in Pnpp Circulating Water Sys to Lower Ph Is Anticipated to Be Completed in Nov ML20210Q5831999-08-10010 August 1999 Requests Permission to Chemically Treat CWS for Algae Due to Cooling Water Basin Becoming Infected with Algae of Various Types PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 ML20210K6331999-08-0404 August 1999 Submits Response to Requests for Addl Info to GL 92-01,Rev 1, Reactor Vessel Structural Integrity, for Perry Nuclear Plant,Unit 1 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 ML20210G8411999-07-28028 July 1999 Informs That Based on Determination That Rev 14 Changes to Various Portions of Perry Nuclear Power Plant Emergency Plan Does Not Decrease Effectiveness of Licensee Emergency Plan & Meets Standard of 10CFR50.47(b),no NRC Approval Required ML20210E0661999-07-22022 July 1999 Forwards Insp Rept 50-440/99-08 on 990518-0708.No Violations Noted.Overall Conduct of Activities at Perry Facility, Conservative & Professional with Continuing Focus on Safety PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20209E5951999-07-0909 July 1999 Ltr Contract:Task Order 46, Perry Engineering & Technical Support (E&Ts) Insp, Under Contract NRC-03-98-021 ML20209D5931999-07-0101 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Investigation Rept 3-98-005 Issued on 990510.Corrective Actions Will Be Examined During Future Inspections ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant ML20196H9641999-06-29029 June 1999 Confirms 990615 Telcon Request with J Lieberman for Addl Time to Respond to Enforcement Action 99-012.FirstEnergy Has 60 Days to Respond to EA PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval ML20195G6741999-06-10010 June 1999 Forwards Insp Rept 50-440/99-03 on 990407-0517.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records PY-CEI-NRR-2404, Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology1999-06-0707 June 1999 Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology ML20195E4561999-05-25025 May 1999 Submits Petition Per Other Actions Provision of 10CFR2.206,requesting That Radiation Protection Manager at Perry NPP Be Banned by NRC from Participation in Licensed Activities at & for Any NPP for at Least Five Yrs PY-CEI-NRR-2401, Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars1999-05-20020 May 1999 Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars PY-CEI-NRR-2402, Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs,1999-05-18018 May 1999 Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, PY-CEI-NRR-2394, Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested1999-05-0505 May 1999 Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested PY-CEI-NRR-2397, Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.51999-04-30030 April 1999 Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.5 PY-CEI-NRR-2396, Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-en1999-04-28028 April 1999 Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-end Weld 05000440/LER-1999-002, Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available1999-04-26026 April 1999 Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available PY-CEI-NRR-2388, Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits1999-04-22022 April 1999 Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits PY-CEI-NRR-2371, Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted1999-04-21021 April 1999 Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted PY-CEI-NRR-2382, Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl1999-04-21021 April 1999 Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl PY-CEI-NRR-2392, Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette1999-04-19019 April 1999 Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette PY-CEI-NRR-2387, Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 1051999-04-14014 April 1999 Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 105 PY-CEI-NRR-2386, Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing1999-04-0606 April 1999 Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20206N3361999-04-0505 April 1999 Informs NRR of Continued Events Re Transfer of Generation Assets Between Duquesne Light Co & Firstenergy.No Negotiated Settlement Between Firstenergy & Local 270 Pertaining to Generation Asset Swap Has Been Reached PY-CEI-NRR-2384, Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC1999-04-0101 April 1999 Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC PY-CEI-NRR-2383, Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed1999-04-0101 April 1999 Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed L-99-052, Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding1999-03-30030 March 1999 Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding ML20205H6171999-03-29029 March 1999 Forwards Util Consolidated Financial Statements for Twelve Month Period Ending 981231 & Internal Cash Flow Projection, Including Actual 1998 Data & Projections for 1999 PY-CEI-NRR-2377, Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1)1999-03-29029 March 1999 Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1) PY-CEI-NRR-2380, Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure1999-03-25025 March 1999 Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure 1999-09-09
[Table view] |
Text
_- -
% e' .
CENTEREOR ENERGY r Power Generation Group Perry Nuclear Power Plant Mail Address: 216-280-5915 Lew W. Myers to Center Road P.O. Box 97 FAX: 216-280-8029 Vice President i Perry, Ohio 44081 Perry. OH 44081 '
July 2,1997 j PY-CEI/NRR-2177L j l
l 1
United States Nuclear Regulatory Commission !
Document Control Desk <
Washington, D.C. 20555 l Perry Nuclear Power Plant l Docket No. 50-440 Response to Request for Additional Information - Inservice Examination Program, Perry Nuclear Power Plant, Unit No.1 (TAC No. M97694)
Ladies and Gentlemen:
Requests for relief from requirements of the American Society of Mechanical Engineers (ASME)
Code,Section XI were submitted to the Nuclear Regulatory Commission (NRC) for the Perry Nuclear Power Piant, Unit 1, inservice Examination Program, in a letter dated January 7,1997 (PY-CEl/NRR-2125L), and supplemented by a letter dated February 12,1997 (PY-CEl/NRR-2136L). In a request for additional information dated May 15,1997, the NRC staff indicated that an initial review of the submittal had been performed, and additional information was needed to complete the review. Specifically, the NRC found the request to knplement Code Cases N-522 and N-546 acceptable provided the conditions stated in the initial review were followed, and ,
requested that infonnation reflecting incorporation of the conditions be submitted. !
The two relief requests have been revised to incorporate the conditions. A description of the NRC ]
requests and responses to the conditions are provided in Attachment 1, and the revised relief requests are provided in Attachments 2 and 3. In addition, Relief Request PT-005 (Attachment 2) has been revised to reflect the addition of three penetrations to the Identification of Components table. The revised sections are designated by revision bars in the right margin.
If you have questions or require additional information, please contact Mr. Henry L. Hegrat, Manager - Regulatory Affairs, at (216) 280-5606.
Very truly yours, NY y '
i 9707000319 970702*
KMN:sc PDR ADOCK 05000440 C :I P Pm hO Attachments cc: NRC Project Manager NRC Resident inspector NRC Region 111 -
Michael T. Anderson, INEL Research Center
(,'"' SOC 9' Authorized Nuclear Inservice Inspector
' "'~
Ohio Department of Commerce
1 l
l l- . j l , Attachment 1 j l PY-CEl/NRR-2177L :
l PageIof3 l i
1 BACKGROUND l Requests for relief from requirements of the American Society of Mechanical Engineers (ASME)
Code,Section XI were submitted to the Nuclear Regulatory Commission (NRC) for the Perry Nuclear l Power Plant (PNPP), Unit 1, inservice Examination Program (ISEP), in a letter dated January 7,1997 (PY-CEl/NRR-2125L), and supplemented by a letter dated February 12,1997 (PY-CEl/NRR-2136L). l In a request for additional hformation dated May 15,1997, the NRC staffindicated that an initial !
review of the submittal had been performed, and additional information was needed to complete the ,
review. Specifically, the NRC has requested commitments to several specific conditions associated I with Code Cases N-522 and N-546. A description of the NRC requests and responses to the conditions are provided below.
i RELIEF REOUEST PT-005 j NRC Conditions for Relief Reauest PT-005 "In ReliefRequest PT-005, CEIrequested to implement the alternative to Code requirements contained in Code Case N-522, " Pressure Testing ofContainment Penetration Piping." The NRCfinds this alternative to Code regairements acceptable for use with thefollowing conditions (1) the test is conducted at thepeak calculated containmentpressure: and (2) the testprocedure provides criteriafor the detection andlocation ofthrough-wall leakages in CIVs andpipe segments between the CIVs. "
i Resnonse to NRC Conditions (n and (2)
These conditions have been incorporated into Relief Request PT-005, as described below. Appropriate procedures will be revised to incorporate these conditions.
In accordance with 10 CFR 50, Appendix J, Local Leak Rate Tests (LLRTs) of the ,
penetrations identified in Relief Request PT-005 are conducted at a pressure of P., where P, is the peak calculated containment internal pressure.
For LLRT of the penetrations identified in Relief Request PT-005, whenever the testmg ;
results indicate leakage, the test procedure will provide criteria for identification of the l source of the leakage, including provisions for detection and location of through-wall leakage in the containment isolation valves and pipe segments in between.
l l
l f
Attach;nent 1 l PY-CEl/NRR-2177L Page 2 of 3 RELIEF REOUEST PT-006 l NRC Conditions for Relief Request PT-006 I
"In ReliefRequest PT-006, CEIproposed to implement the alternatives to Code l
requirements contained in Code Case N-546, " Alternative Requirementsfor !
Qualification of VT-2 VisualExamination Personnel." The NRC stafffinds this Code case acceptablefor use with thefollowing conditions: \
(1) developproceduralguidelinesfor obtaining consistent, quality VT-2 visual examinations; I
(2) document and maintain records to verW the quahfication ofpersons selected to l
perform VT-2 visual examinations; and l (3) implement independent review and evaluation ofleakage bypersons other than those thatperformedthe VT-2 visualexaminations."
PNPP Resnonse to Conditions (11 (21 and (3)
These conditions have been incorporated into Relief Request PT-006, as described below. Appropriate procedures will be revised to incorporate these conditions.
VT-2 examination personnel qualified in accordance with Code Case N-546 will perform examinations using procedures that provide for consistent, quality VT-2 examinations.
Training and qualification of VT-2 personnel will be documented and the records will be maintained for the life of the plant.
Procedures for the performance of VT-2 visual examinations will require that an independent review and evaluation of the VT-2 visual examination results be performed and documented on the examination records.
l l .
I ', Attachment 1 PY-CEI/NRR-2177L Page 3 of 3 i .
t COMMITMENTS The following table identifies those actions which are considered to be regulatory commitments.
Any other actions discussed in this document represent intended or planned actions, are l described for the NRC's information, and are not regulatory commitments. Please notify the l Manager - Regulatory Affairs at the Perry Nuclear Power Plant of any questions regarding this i document or any associated regulatory commitments.
Commitments I These conditions have been incorporated into Relief Request PT-005, as described below.
Appropriate procedures will be revised to incorporate these conditions.
In accordance with 10 CFR 50, Appendix J, Local Leak Rate Tests (LLRTs) of the penetrations identified in Relief Request PT-005 are conducted at a pressure of Pa, where Pa is the peak calculated containment internal pressure.
For LLRT of the penetrations identified in Relief Request PT-005, whenever the testing ;
results indicate leakage, the test procedure will provide criteria for identification of the i source of the leakage, including provisions for detection and location of through-wall i leakage in the containment isolation valves and pipe segments in between. ;
These conditions have been incorporated into Relief Request PT-006, as described below.
Appropriate procedures will be revised to incorporate these conditions.
VT-2 examination personnel qualified in accordance with Code Case N-546 will perform examinations using procedures that provide for consistent, quality VT-2 examinations.
Training and qualification of VT-2 personnel will be documented and the records will be maintained for the life of the plant.
Procedures for the performance of VT-2 visual examinations will require that an independent review and evaluation of the VT-2 visual examination results be performed and documented on the examination records.
l
, Attachment 2 PY-CEI/NRR-2177L Page1of3 Perry Nuclear Power Plant Unit 1 RELIEF REQUEST No. PT-005 l
t Code Case N-522
- 1. Identification of Comoonents Penetration No. Drawing No. Associated ISI Pressure Test Instruction P204 D-302-871 ISI-C11-T1201-2 P201 D-806-004 1SI-D17-Tl 100-2 l
P317 D-806-007 ISI-D17-T1101-2 P109 D-302-811 ISI-E61-Tl 100-2 Pl19 D-302-811 ISI-E61-Tl 101-2 P120 D-302-811 ISI-E61-Tl 102-2 ,
P317 D-302-811 ISI-E61-Tl 103-2 P319 D-302-811 ISI-E61-T1104-2 P424 D-302-672 ISI-G33-Tl 100-2 P420 D-302-737 ISI-G50-Tl 100-2 P417 D-302-739 1SI-G61-T1100-2 P418 D-302-740 ISI-G61-T1101-2 V313 D-912-604 ISI-M14-T1100-2 V314 D-912-604 ISI-M 14-Tl 101-2 P114 D-912-606 ISI-M 17-Tl 100-2 !
P208 D-912-606 ISl-M 17-Tl 101-2 P428 D-912-606 ISI-M17-Tl102 2 P436 D-912-606 ISI-M 17-Tl 103-2 P108 D-302-102 ISI-P11-Tl100-2 Pl11 D-302-102 ISI-P11-Tl101-2 P309 D-302-713 ISI-P22-Tl100-2 P310/P311 D-302-613 ISI-P43-T1200-2 _
P404/P405 D-913 008 ISI-P50-T1200-2 _
P308 D-302-242 1SI P51-T1200-2 P305/P306 D-302-244 ISI-P52-T1200-2 P312 D-302-243 ISI-P52-T1200-2 P406 D-914-003 ISI-P54-Tl100-2 P210 D-914-005 ISI-P54-T1101-2 l
P117 D-302-950 ISI-P86-Tl100-2 P413 D-302-431 ISI-P87-Tl 100-2
- 11. ASME Boiler & Pressure Vessel Code Section XI Reauirements The following requirements of the 1983 Edition through Summer 1983 Addenda of 1
Section XI apply:
1 i
Attachment 2 '
PY-CEl/NRR-2177L l Page 2 of 3 l
- l. IWA-5211, states "The pressure retaining components within each system boundary shall be subject to system pressure tests under which conditions visual examination VT-2 is performed in accordance with IWA-5240 to detect leakages."
- 2. IWC-5210(a) states, "The pressure retaining components within each system boundary shall be subjected to a system pressure test conducted during a system functional test, system inservice test, or a hydrostatic test, and visually examined by the method specified in bble IWC-2500-1, Examination Category C-H."
- 3. Table IWC-2500-1, Examination Category C-H, specifies a VT-2 examination once per inspection period for inservice or functional testing and once per inspection interval for hydrostatic testing.
III. ReliefRequested Code Case N-522 accepts the test requirements of 10 CFR 50, Appendix J as an alternative to the testing requirements of ASME Section XI, Table IWC-2500-1, Category C-H, for pressure testing piping that penetrates a containment vessel when the piping and isolation valves that are part of the containment system are Class 2 but the ,
balance of the piping system is outside the scope of Section XI. !
IV. Basis for Relief Pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative provides an acceptable level of quality and safety. l The proposed alternative reduces the amount of redundant testing required on the same systems by the imposition of both ASME Section XI and 10 CFR 50, Appendix J.
Cunently, imposition of the IWC-2500-1 test requirements results in additional testing as follows:
- 1. Water systems are flooded and pressurized through the associated penetration test tap and a VT-2 visual examination performed during the pressurization period.
- 2. Air and gas systems are tested in an identical manner to the 10 CFR 50, Appendix J method and a VT-2 visual examination is performed during the pressurization period.
For the penetrations listed in Section I above,10 CFR 50, Appendix J testing is performed by draining the test volume and pressurizing the test volume with air to a pressure of P , where P, is the peak calculated containment internal pressure. The rate of makeup flow is determined and compared to acceptance criteria based on allowable containment leak rates.
Thus, by being able to take credit for the ASME Section XI testing by using the 10 CFR 50, Appendix J testing, elimination of the redundant testing reduces the number of tests required on the same system.
. u-. - ~ s . a axs . ~ . .
s - . ._ ..x. > . - - . .,
l l Attachment 2 4 PY-CEI/NRR-2177L l l Page 3 of 3 Leakage from water systems would be indicated during the 10 CFR 50, Appendix J test more readily than the IWC-2500-1 test due to the lower density of the air test medium.
Based on this fact, use of the Appendix J test program for water systems is conservative ,
when compared to the ASME Section XI program. 1 1
Leakage from air and other gas systems would be indicced by 10 CFR 50, Appendix J testing in a similar manner to an IWC-2500-1 test. Based on this fact, the two programs are essentially equivalent. j i
The frequency of testing will be in accordance with 10 CFR 50, Appendix J. The l 10 CFR 50, Appendix J testing is performed by a staffof Perry employees supplemented )
by contract personnel. All personnel involved in local leak rate testing (LLRT) at Perry ;
are qualified in accordance with the current Perry-specific LLRT training program. ;
Therefore, Appendix J testing is performed by personnel trained to recognize i l
unacceptable leakage from a pressure boundary.
V. Alternate Examination In lieu of the requirements specified in IWA 5211 and IWC-5210, Perry will follow the ,
guidance of Code Case N-522 for pressure testing of safety class 2 containment i penetrations associated with non-safety class systems.
Testing required by 10 CFR 50, Appendix J may be used as an alternative to the rules in Table IWC-2500-1, Category C-H, for pressure testing piping that penetrates a containment vessel, when the piping and isolation valves that are part of the containment system are Class 2 but the balance of the piping system is outside the scope of ;
Section XI. !
The testing will be conducted at a pressure of P., where P is the peak calculated containment internal pressure. Whenever the testing results indicate leakage, the test procedure will provide criteria for identification of the source of the leakage, including provisions for detection and location of through-wall leakage in the containment isolation valves and pipe segments in between.
i i
I
^ Attachment 3 PY-CEl/F RR-2177L Page 1 of 2
\
l Perry Nuclear Power Plant Unit 1
' RELIEF REQUEST No. PT-006 Code Case N-546 l I. Identification of Components i
Class 1,2, and 3 systems subject to pressure testing.
II. ASME Boiler & Pressure Vessel Code Section XI Requirements l
Tables IWB-2500-1,IWC-2500-1 and IWD-2500-1 of the 1983 Edition through Summer I 1983 Addenda of Section XI require the VT-2 examination method for pressure testing. l IWA-2300(c) requires that personnel performing the VT-2 visual examinations be l qualified by the Owner or the Owner's agent in accordance with the comparable levels l
of competency as defined in ANSI N45.2.6-1973. Perry further utilizes Code Case l N-448, " Qualification of VT-2 and VT-3 Visual Examination Personnel,Section XI, Division 1," which reflects later editions oflWA-2300 that require personnel perfonning visual examination to be qualified and certified to comparable levels of qualification as defined in SNT-TC-1 A and the Employers written practice. j Ill. ReHef Reauested Pursuant to 10 CFR 50.55a(a)(3)(i), reliefis requested from requiring that the personnel performing the VT-2 examinations be aualified and certified to comparable levels of j qualification as defined in SNT-TC-1 A. l I
IV. Basis for Relief The use of Code Case N-546 will eliminate the need to treat VT-2 examination j personnel as NDE personnel. The Abstract of SNT-TC-1 A states, "This standard applies to personnel whose specific tasks orjobs require appropriate knowledge of the technical principals underlying nondestructive testing (NDT) methods for which they have responsibilities within the scope of VT-1 and VT-3 examination methods." VT-2 requires no special knowledge of technical principals underlying its performance. It is simply the straight forward examination for leakage. No special skills or technical training are required in order to observe water dripping from a component or bubbles i forming on ajoint wetted with leak detection solution. As such, qualification in accordance with the provisions of the Code Case does not present any reduction in quality or safety. Ir fact, it will facilitate the qualification of those personnel most familiar with the walkdown of plant systems.
Additionally, there is a cost benefit of approximately $12,000 per operating cycle realized by eliminating the formal certification of Perry and contracted VT-2 examination personnel.
. Attachment 3 PY-CEI/NRR-2177L Page 2 0f 2 4
In summary, approval of this request would be in accordance with 10 CFR 50.55a(a)(3)(i), as compliance with Code Case N-546 will provide an essentially equivalent alternative to the IWA-2300 requirements. It would also provide relief from l
~
the administrative and financial burdens of certification, which do not provide any compensating increase in the level of quality or safety.
V. Alternate Examination CEI proposes to perform VT-2 examinations utilizing personnel qualified in accordance {
with the provisions of Code Case N-546 in lieu of personnel who are qualified and
, certified to comparable levels of qualification as defined in SNT-TC-1 A. The qualification provisions specified in Code Case N-546 are as follows: '
(1) Personnel must have at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of plant walkdown experience, such as that gained by licensed and nonlicensed operators, local leak rate personnel, system engineers, and inspection and nondestructive examination personnel.
(2) Personnel must receive at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of training on Section XI requirements and i plant specific procedures for VT-2 examination.
i (3) Personnel must meet the vision test requirements ofIWA-2321,1995 Edition.
Training and qualification of VT-2 personnel will be documented and the records will be maintained.
Additionally, to provide for consistent, quality VT-2 visual examinations, the examinations will be performed using standard procedures. An independent review and evaluation of the VT-2 visual examination results will be performed and documented on the examination records.
.