Similar Documents at Perry |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That Proprietary Document NEDE-32907P,DRF A22-0084-53, Safety Analysis Rept for Perry NPP 5% Power Uprate, Class III Dtd Sept 1999 Be Withheld.Determined Document Proprietary & Will Be Withheld ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212K9271999-09-30030 September 1999 Refers to 990927 Meeting Conducted at Perry Nuclear Power Plant to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff ML20212J1451999-09-30030 September 1999 Forwards Order,In Response to 990505 Application PY-CEI/NRR- 2394L.Order Approves Conforming License Amend Which Will Be Issued & Made Effective When Transfer Completed ML20217E7111999-09-30030 September 1999 Documents Telcon Conducted on 990929 Between M Underwood of Oh EPA & D Tizzan of Pnpp,Re Request to Operate Pnpp Sws,As Is,Until Resolution Can Be Obtained ML20212G4161999-09-24024 September 1999 Informs of Completion of Licensing Action for Generic Ltr 98-01, Y2K Readiness of Computer Systems at Nuclear Power Plants, for Perry Nuclear Power Plant ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED ML20212A8371999-09-13013 September 1999 Forwards Insp Rept 50-440/99-13 on 990712-30 & Notice of Violation.Insp Included Evaluation of Engineering Support, Design Change & Modification Activities,Internal Assessment Activities & Corrective Actions ML20217A8971999-09-0909 September 1999 Forwards Insp Rept 50-440/99-09 on 990709-0825.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages ML20211Q6911999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Perry Operator License Applicants During Wks of 010108 & 15.Validation of Exam Will Occur at Station During Wk of 001218 IR 05000440/19990011999-08-31031 August 1999 Requests That Page Number 4, P2 Status of EP Facilities, Equipment & Resources, of Insp Rept 50-440/99-01 Be Replaced with Encl Rev PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20210Q8421999-08-13013 August 1999 First Final Response to FOIA Request for Documents.Records Listed in App a Being Released in Entirety & Records Listed in App B Being Withheld in Part (Ref FOIA Exempt 5) ML20210R7861999-08-12012 August 1999 Forwards Insp Rept 50-440/99-12 on 990712-16.No Violations Noted.New Emergency Preparedness Program Staff & Mgt Personnel Were Professional & Proactive ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 ML20210Q7981999-08-10010 August 1999 Informs That Intention to Utilize Sulfuric Acid in Pnpp Circulating Water Sys to Lower Ph Is Anticipated to Be Completed in Nov ML20210Q5831999-08-10010 August 1999 Requests Permission to Chemically Treat CWS for Algae Due to Cooling Water Basin Becoming Infected with Algae of Various Types PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 ML20210K6331999-08-0404 August 1999 Submits Response to Requests for Addl Info to GL 92-01,Rev 1, Reactor Vessel Structural Integrity, for Perry Nuclear Plant,Unit 1 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 ML20210G8411999-07-28028 July 1999 Informs That Based on Determination That Rev 14 Changes to Various Portions of Perry Nuclear Power Plant Emergency Plan Does Not Decrease Effectiveness of Licensee Emergency Plan & Meets Standard of 10CFR50.47(b),no NRC Approval Required ML20210E0661999-07-22022 July 1999 Forwards Insp Rept 50-440/99-08 on 990518-0708.No Violations Noted.Overall Conduct of Activities at Perry Facility, Conservative & Professional with Continuing Focus on Safety PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20209E5951999-07-0909 July 1999 Ltr Contract:Task Order 46, Perry Engineering & Technical Support (E&Ts) Insp, Under Contract NRC-03-98-021 ML20209D5931999-07-0101 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Investigation Rept 3-98-005 Issued on 990510.Corrective Actions Will Be Examined During Future Inspections ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant ML20196H9641999-06-29029 June 1999 Confirms 990615 Telcon Request with J Lieberman for Addl Time to Respond to Enforcement Action 99-012.FirstEnergy Has 60 Days to Respond to EA PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval ML20195G6741999-06-10010 June 1999 Forwards Insp Rept 50-440/99-03 on 990407-0517.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records PY-CEI-NRR-2404, Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology1999-06-0707 June 1999 Submits Rept of Reduction in PCT Greater than 50 F Due to Implementation of Ge,Safr/Gestr LOCA Methodology for Fuel Cycle 8.Methodology Replaces Original LOCA Methodology ML20195E4561999-05-25025 May 1999 Submits Petition Per Other Actions Provision of 10CFR2.206,requesting That Radiation Protection Manager at Perry NPP Be Banned by NRC from Participation in Licensed Activities at & for Any NPP for at Least Five Yrs PY-CEI-NRR-2401, Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars1999-05-20020 May 1999 Forwards Changes to ERDS Data Point Library & Communication Survey for Perry Nuclear Power Plant.Changes Are Identified by Margin Rev Bars PY-CEI-NRR-2402, Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs,1999-05-18018 May 1999 Notifies of Completion of Plant Core Shroud Insp in Accordance with GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, PY-CEI-NRR-2394, Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested1999-05-0505 May 1999 Forwards Application for Order & Conforming License Amend for Transfer of Interest in OL NPF-58 for Pnpp.Authorization of Ceic to Possess Dl 13.74% Undivided Ownership in Pnpp, Requested PY-CEI-NRR-2397, Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.51999-04-30030 April 1999 Forwards Revised COLR Cycle 8, & Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7,Cycle 8, IAW TS Section 5.6.5 PY-CEI-NRR-2396, Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-en1999-04-28028 April 1999 Provides post-examination Results of Weld Overlay Repair for FW Nozzle to safe-end Weld at Pnpp.Info Supplements Licensee 990325 & 0401 Ltrs Submitted to NRC That Requested Approval of Repair Plan for 1B13-N1C-KB FW Nozzle to safe-end Weld 05000440/LER-1999-002, Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available1999-04-26026 April 1999 Forwards LER 99-002-00, LCO 3.0.3 Entered Due to TS Bases Statement Interpretation. Action Occurred After RHR Pump Failed to Start.Plant at No Time Was in Condition Where Required Decay Heat Removal System Were Not Available PY-CEI-NRR-2388, Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits1999-04-22022 April 1999 Forwards Annual Environ & Effluent Release Rept for Pnnp Unit 1 for 1998. Pnpp Had No Liquid Effluent Discharges in 1998 & All Other Release Points Were Well Below Applicable Limits PY-CEI-NRR-2371, Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted1999-04-21021 April 1999 Provides Suppl Response to Violations Noted in Insp Rept 50-440/98-18.Corrective Actions:Two Condition Rept Investigations Were Performed to Evaluate Issues Re Fire Protection Program & Addl Training Was Conducted PY-CEI-NRR-2382, Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl1999-04-21021 April 1999 Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl PY-CEI-NRR-2392, Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette1999-04-19019 April 1999 Forwards Diskette Containing Pnpp Thermoluminescent Dosimeter Doses in Format Requested by Reg Guide 8.7.Without Diskette PY-CEI-NRR-2387, Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 1051999-04-14014 April 1999 Documents Telcon Held Between NRC Staff & Members of Perry Nuclear Power Plant Staff on 990406,re Safety Evaluation for License Amend 105 PY-CEI-NRR-2386, Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing1999-04-0606 April 1999 Forwards Copy of Application Submitted to FERC Proposing Transfer of Jurisdictional Transmission Facilities of Firstenergy Corp Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20206N3361999-04-0505 April 1999 Informs NRR of Continued Events Re Transfer of Generation Assets Between Duquesne Light Co & Firstenergy.No Negotiated Settlement Between Firstenergy & Local 270 Pertaining to Generation Asset Swap Has Been Reached PY-CEI-NRR-2384, Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC1999-04-0101 April 1999 Provides Supplemental Info Re 990325 Request for Approval of Repair Plan for Feedwater Nozzle to safe-end Weld. Clarification Provided on Listed Three Items,Per 990329 Telcon with NRC PY-CEI-NRR-2383, Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed1999-04-0101 April 1999 Withdraws Inservice Exam Relief Requests IR-036 & IR-041, Submitted in Licensee to Nrc.Relief Request IR-041 Is Being Clarified with Respect to Alternative Proposed L-99-052, Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding1999-03-30030 March 1999 Forwards Info Concerning Dls Decommissioning Planning for Bvps,Units 1 & 2 & Pnpp Unit 1.DL Is Continuing to Utilize External Sinking Funds to Provide Financial Assurance for Nuclear Decommissioning Funding ML20205H6171999-03-29029 March 1999 Forwards Util Consolidated Financial Statements for Twelve Month Period Ending 981231 & Internal Cash Flow Projection, Including Actual 1998 Data & Projections for 1999 PY-CEI-NRR-2377, Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1)1999-03-29029 March 1999 Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1) PY-CEI-NRR-2380, Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure1999-03-25025 March 1999 Requests Approval of Attached Repair Plan for Feedwater Nozzle to safe-end Weld N4C-KB.Proposed Weld Overlay Design & Installation Plan Details Included in Attachment 1. Attachment 2 Provides Applicable Preliminary Weld Procedure 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARPY-CEI-NRR-1226, Forwards LERs 90-018-00 & 90-019-00 for Plant1990-09-14014 September 1990 Forwards LERs 90-018-00 & 90-019-00 for Plant PY-CEI-NRR-1218, Responds to Generic Ltr 90-07 Re Proposed OL Exam Schedule, Operator Requalification Schedule & Generic Fundamental Exam Schedule for Plant.Licensee Will Continue to Train & Requalify Operators on Annual Basis1990-09-10010 September 1990 Responds to Generic Ltr 90-07 Re Proposed OL Exam Schedule, Operator Requalification Schedule & Generic Fundamental Exam Schedule for Plant.Licensee Will Continue to Train & Requalify Operators on Annual Basis ML20059E8741990-09-0505 September 1990 Forwards Fourteenth Quarterly Rept Cleveland Electric Illuminating Co Seismic Monitoring Network Jan-June 1990. Five Microevents Originating within Network & Three Other Events Originating Outside of Network Recorded PY-CEI-NRR-1216, Forwards Perry Nuclear Power Plant Unit 1 Semiannual Radioactive Effluent Release Rept,1990 Quarters 1 & 2. Response to Recommendations from NRC Re Range of Dilution Flows Will Be Submitted W/Next Effluent Rept1990-08-29029 August 1990 Forwards Perry Nuclear Power Plant Unit 1 Semiannual Radioactive Effluent Release Rept,1990 Quarters 1 & 2. Response to Recommendations from NRC Re Range of Dilution Flows Will Be Submitted W/Next Effluent Rept PY-CEI-NRR-1201, Forwards First Semiannual fitness-for-duty Rept for Plant for 900103-0630,per 10CFR26.71(d) Requirements1990-08-28028 August 1990 Forwards First Semiannual fitness-for-duty Rept for Plant for 900103-0630,per 10CFR26.71(d) Requirements PY-CEI-NRR-1211, Responds to NRC Re Violations Noted in Insp Rept 50-440/89-26.Corrective Actions Noted:Necessary Engineering Design Mods Which Evaluation Found Necessary Contained in DCP 90-00861990-08-23023 August 1990 Responds to NRC Re Violations Noted in Insp Rept 50-440/89-26.Corrective Actions Noted:Necessary Engineering Design Mods Which Evaluation Found Necessary Contained in DCP 90-0086 PY-CEI-NRR-1210, Proposes Date of 901207 to Provide Updated Status & Schedules,Per 900604 Request for Addl Info on Disposition of Bulletin 88-005 Product Forms Other than Pipe Fittings & Flanges Received at Plant1990-08-17017 August 1990 Proposes Date of 901207 to Provide Updated Status & Schedules,Per 900604 Request for Addl Info on Disposition of Bulletin 88-005 Product Forms Other than Pipe Fittings & Flanges Received at Plant PY-CEI-NRR-1208, Responds to NRC 900613 Request for Addl Info Re Inservice Insp Relief Requests.Util Revised Relief Requests PT-001 & PT-003 to Provide More Detailed Info & Has Withdrawn Relief Request IR-017.Revised Relief Requests & Summary Encl1990-08-10010 August 1990 Responds to NRC 900613 Request for Addl Info Re Inservice Insp Relief Requests.Util Revised Relief Requests PT-001 & PT-003 to Provide More Detailed Info & Has Withdrawn Relief Request IR-017.Revised Relief Requests & Summary Encl PY-CEI-NRR-1203, Provides Estimate Duration Schedule Re Installation of post-LOCA Neutron Monitoring Sys.Util Will Evaluate Effect of Resolution on Schedule & Confirm or Revise Installation Date as Needed,When Appeal & Criteria Questions Resolved1990-07-27027 July 1990 Provides Estimate Duration Schedule Re Installation of post-LOCA Neutron Monitoring Sys.Util Will Evaluate Effect of Resolution on Schedule & Confirm or Revise Installation Date as Needed,When Appeal & Criteria Questions Resolved PY-CEI-NRR-1200, Forwards Decommissioning Repts on Financial Assurance for Plant1990-07-25025 July 1990 Forwards Decommissioning Repts on Financial Assurance for Plant PY-CEI-NRR-1196, Forwards Rev 0 to Inservice Exam Program. Program Serves as 10-yr Rev to Inservice Insp Program Plan1990-07-24024 July 1990 Forwards Rev 0 to Inservice Exam Program. Program Serves as 10-yr Rev to Inservice Insp Program Plan PY-CEI-NRR-1205, Forwards LERs 90-014-00 & 90-015-00 for Plant1990-07-20020 July 1990 Forwards LERs 90-014-00 & 90-015-00 for Plant PY-CEI-NRR-1193, Responds to Generic Ltr 90-04 Re Implementation Status of Generic Safety Issues1990-06-29029 June 1990 Responds to Generic Ltr 90-04 Re Implementation Status of Generic Safety Issues ML20043H7371990-06-19019 June 1990 Forwards Individual Plant Exam Project Milestones.Milestones Subj to Change from Project or External Causes & Will Not Be Docketed Again Unless Significant Impact on Final Rept Contents or Submittal Date Exists ML20043H1711990-06-14014 June 1990 Discusses Util Radiological Safety Board of Ohio 900614 Comments on Notice of Opportunity for Hearing Re Rev to Previously Submitted License Amend Application.Licensees Would Welcome Opportunity to Consult W/State of Oh ML20043E5771990-06-0808 June 1990 Provides Info Re Implementation of Administrative Controls & Training Related to Use of Tech Spec 3.0.4.Util Intends to Implement Amend 30 Changes by 900618.All Licensed Operators Would Receive Training to Generic Ltr 87-09 ML20043B6981990-05-21021 May 1990 Forwards Info Re Activation Energy Values Utilized for Brand-Rex Co Cable at Facility.Encl Includes Rept, Qualification Tests of Electric Cables for Class 1E Svc in Nuclear Power Plants. ML20043A7041990-05-18018 May 1990 Forwards LERs 90-007-00 & 90-008-00 ML20043A4771990-05-16016 May 1990 Provides Justification Re Events Leading to Declaration of Alert on 900403 Due to Loss of Emergency Svc Water When Manway Flange Gasket Leak Developed at Pump a Discharge Strainer,In Response to Ocre 900406 Petition ML20042F4931990-05-0404 May 1990 Forwards Response to Generic Ltr 89-19 Re Reactor Vessel Overfill Protection ML20042F1961990-04-27027 April 1990 Informs of Adoption of Reorganization Plan Re Plants on 900424.Reorganization Will Make No Changes in Technical or Financial Qualifications for Plants.Application for Amends to Licenses Adding Company as Licensee Will Be Submitted ML20042F8051990-04-19019 April 1990 Forwards 1989 Financial Repts for Centerior Energy Corp, Cleveland Electric Illuminating Co & Toledo Edison Co & Supplemental Sec Form 10-K ML20012F3521990-04-0202 April 1990 Suppls Response to NRC 891215 Ltr Re Deviations Noted in Insp Rept 50-440/89-26.Corrective Actions:Profile of Heat Generation from Stored Fuel Vs Time for First Four Fuel Load Discharges Calculated & Design Changes Implemented ML20012E7811990-03-30030 March 1990 Confirms Basis for 890417 Submittal Re Station Blackout ML20012E9431990-03-26026 March 1990 Forwards Correction Pages to Semiannual Radioactive Effluent Release Rept 1989:Quarters 3 & 4. Changes Affect Liquid Effluent Data Only.Corrections Made Due to High Contribution of Sr-89 to Liquid Effluent Dose ML20012B9851990-03-0909 March 1990 Responds to Generic Ltr 90-01 Re Regulatory Impact Survey ML20012B5931990-03-0808 March 1990 Responds to Open Item Noted in Insp Rept 50-440/89-29. Corrective Actions:Plant Health Physicist & Operations Superintendent Met W/Health Physics & Operations Crews to Discuss Better Methods of Access Control ML20012A1561990-03-0202 March 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Addl Info in Response to NRC 890605 Ltr Re Offsite Dose Calculation Manual ML20012B9801990-03-0202 March 1990 Responds to 890810 Request for Addl Info on Util 890306 Tech Spec Change Request Re MSIV Leakage Limits.Change Does Not Request Increase in MSIV Leakage Beyond Currently Assumed in Updated SAR Chapter 15 ML20006E5131990-02-12012 February 1990 Lists Suggestions on Subj Areas to Be Addressed During Proposed 1990 Licensee Info Conference,In Response to 900117 Ltr ML20006E3211990-02-0909 February 1990 Discusses Implementation of Facility Revised Inservice Testing Program,Per Generic Ltr 89-04.Improvements Listed, Including sign-off Matrix Deletion at End of Instruction & Movement of Comments Section ML20006D0971990-02-0202 February 1990 Provides Update to 880721 Ltr Re Performance of Seismic Margin Evaluation.Util Awaiting Issuance of Individual Plant Exams of External Events Generic Ltr Prior to Proceeding W/ Seismic Margins Study ML20011E1841990-02-0202 February 1990 Forwards LERs 90-001 & 90-002 ML20006D5731990-01-30030 January 1990 Forwards Response to NRC 900112 Request for Addl Info Re 891121 Request for Exemption from Filing Requirements of 10CFR55.45(b)(2)(iii).Qualification Plan for Certification of Existing Simulator Approved in Aug 1987 ML20006B5131990-01-26026 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of Type 410 Stainless Preloaded Bolting in Swing Check Valves.No Bolts Subj to Bulletin in Use at Facility ML20006B5571990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Procedures in Place for Underwater Insp of Intake Structures in Lake as Well as on-shore Pump Houses Annually ML20006A0781990-01-16016 January 1990 Responds to NRC 891215 Ltr Re Deviations Noted in Insp Rept 50-440/89-26.Corrective Actions:Profile of Heat Generation from Stored Fuel Vs Time for First Four Fuel Discharges Calculated & Updated SAR Change Request Will Be Submitted ML20005F9331990-01-0909 January 1990 Provides Inadvertently Omitted Inequality Signs from Util 891213 Response to NRC Bulletin 88-004 Re RCIC Pump Min Flow Limitations from Operating Instructions ML20042D5051990-01-0303 January 1990 Informs That Licensee Implemented fitness-for-duty Program at Plant on 900103,per 10CFR26.More Stringent cut-off Levels Imposed by Util than Required by 10CFR26 ML20005E1391989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance.Each motor- Operated Valve Will Be Stroke Tested to Verify Valve Operability at no-pressure & no-flow Conditions ML19332F7941989-12-13013 December 1989 Responds to NRC 890531 Request for Addl Info Re NRC Bulletin 88-004, Safety-Related Pump Loss. Info Covers pump-to-pump Interaction That Could Result in Deadheading & Adequacy of Min Flow Bypass Lines Against Pump Damage ML19332E6921989-12-0707 December 1989 Responds to Violations Noted in Insp Rept 50-440/89-12 on 890627 & 1023.Corrective Actions:Flange Leakage of Relief Valve Repaired During First Refueling Outage & Design Mods to Enhance Testability of Gasketed Flanges Being Developed ML19332F3851989-12-0606 December 1989 Forwards Twelfth Quarterly Rept Cleveland Electric Illuminating Seismic Monitoring Network,Jul-Sept 1989. Rept Describes Area in Vicinity of Two Waste Injection Wells Located 3 Miles South of Plant Site ML19332E7971989-12-0101 December 1989 Responds to Generic Ltr 89-21 Re Implementation Status of USIs ML19332E3611989-11-28028 November 1989 Submits Supplemental Info Re Tech Spec Change Request Proposing Addition of Requirement to Verify Trip Setpoint of Intermediate Range Monitor Control Rod Block Instrumentation During Performance of Weekly Channel Functional Testing ML19332D5771989-11-27027 November 1989 Submits Supplementary Info to 880520 Tech Spec Change Request,Changing Setpoints for Turbine First Stage Pressure to Reflect Values Actually Measured During Startup Test Program at 40% of Rated Reactor Power.Table Encl ML19332C7341989-11-22022 November 1989 Forwards Executed Amend 3 to Indemnity Agreement B-98 ML19332C4041989-11-22022 November 1989 Responds to NRC 891025 Ltr Re Violations Noted in Insp Rept 50-440/89-23.Corrective Actions:Work Stopped on Div III & Restoration Began to Return to Operation & All Actions Required by Tech Spec 3.0.3 Completed ML19332C8321989-11-21021 November 1989 Forwards Inservice Insp Summary Rept NP0059-0001, Results for Outage 1 (1989),First Period,First Interval, Vols I & Ii,Covering Insp Period 871118-890805 ML19332C4531989-11-21021 November 1989 Requests Exemption from Requirements of 10CFR45.(b)(2)(iii), to Allow for Submittal of NRC Form 474, Simulation Facility Certification, After 910326 Deadline 1990-09-05
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< THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P.O. BOX 97 e PERRY. OHIO 44081 e TELEPHONE (216) 259-3737 e ADDR E S S - 10 CENTER ROAO Serving The Best L.ocation in the Nation PERRY NUCLEAR POWER PLANT Al Kaplan
(((($, April 29, 1983 PY-CEI/NRR-0845 L U.S. Nuclear Regulatory Cocmrission Document Control De sk Washington, D. C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Response to Notice of Violation 50-440/87025-03
Dear Gentlemen:
This letter acknowledges receipt of the Notice of Violation contained within Inspection Report 50-440/87025 dated March 31, 1988. The report identified areas examined by Mr. W. Kropp and others during their inspection conducted f rom January 11, 1988 through February 9,1988 of activities at the Perry Nuclea r Power Plant, Unit 1.
Our response to Notice of Violation 50-440/87025-03 is attached. Please call should you have any additional questions.
Very tru y yours, n H1, uubv w l Al Kaplan Vice President ;
Nuclear Group j AK: cab l
At tac hme nt ec: T. Colburn K. Connaughton H. Miller - USNRC, Region 111 f
g9 8805030419 880429 PDR ADOCK 05000440 0 PDR
Attachment PY-CEI/NRR-0845 L Page 1 of 9 50-440/87025-03 Restatement of Violation 10 CFR 50, Appendix B, Criterion V, as implamented by PNPP, Operational Quality Assurance Plan, Section 5.0, requires that activities affecting quality be prescribed by instructions or procedures and accomplished in accordance with those instructions or procedures. Section 5.0 further requires procedures to include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
Contrary to the above:
A. Procedure PAP-0906, "Control of Maintenance Section Preventive Maintenance," Revision 1, did not include criteria to make technical evaluations for rescheduling preventive maintenance activities. As a result, repetitive tasks (preventive maintenance) already several months past due, vere rescheduled for nine motor-operated valves in the residual heat removal and liquid radvaste systems without evaluations of the effects the delays could have on plant safety, operability, or reliability. (440/87025-03B)
B. The licensee failed to fully accomplish Preventive Maintenance Instruction, PHI-0030, "Maintenance of Limitorque Valve Operators,"
Revision 1, as follows:
o The inspector observed that valve stems for several residual heat removal system and liquid radvaste system valves vere lubricated with Neolube although PMI-0030 specified Nebula EPO.
o There vas no objective evidence that two residual heat removal system valves had been electrically and manually cycled as specified in the post maintenance requirements of PM1'-0030. (440/87025-03C)
C. The licensee failed to properly implement Administrative Procedure PAP-0905, "Vork Order Process," Revision 7, which outlined the requirements for processing vork orders (V0) from initiation to closure as follows:
o V0 87-9677 - Summary description did not accurately reflect the activity performed; o V0 87-5727, 87-10390, 88-0080 - Incomplete or incorrect corrective action indicated on VO Closing and Summary Sheet; o VO 87-6175, 87-7385, 87-8746, 87-9361, 87-9498, 87-9677, 87-10213 -
Incorrect or inadequate immediate failure cause identified on the VO Closing and Summary Sheet;
- A Attachmtnt PY-CEI/NRR-0845 L Page 2 of 9 o VO 87-2249, 87-8746, 87-9361, 87-9677, 87-10390 - Incorrect or incomplete V0 closing codes; o VO 87 4925, 87-8298, 87-8597, 87-9677 - Incorrect or incomplete Master-Part List (HPL) npmbers; and o VO 87-9361 - Inadequate closing summary on the V0 Closing and Summary Sheet. (440/87025-03A)
D. The licensee failed to fully accomplish Nuclear Quality Assurance Department procedure, NOAD 1840, Revision 2, "Audit Performance," Section 6.2, which required that deficiencies noted during audits be documented on Action Requests. Deficiencies identified during Audit 87-12, "Effectiveness of Corrective Action" vere listed as observations; therefore, the established corrective system was bypassed. One-observation pertained to continued untimely and ineffective corrective action, which prior to Audit 87-12, had also been identified as a concern by the licensee's OA organization and the NRC. (440/87025-03D)
This is a Severity Level IV violation (Supplement I).
Corrective Action Taken and Results Achieved A. Failure to document technical evaluations for rescheduling preventive maintenance activities.
CEI agrees that PAP-0906 did not specifically include criteria to make the technical evaluations nor require documentation of the evaluations.
However, system engineers involved in rescheduling repetitive tasks have used engineering judgment, verbal instructions from unit leads, and/or informal desk-guide type instructions when performing this activity. The issue is not whether technical evaluations vere performed for rescheduled repetitive tasks, but whether this evaluation was documented. In order to allow for documentation of the technical evaluation, a Preventive Haintenance Deferral Evaluation / Justification Sheet has been developed and is being incorporated into the appropriate repetitive task procedures.
This form provides for a documented "Justification for Reschedule" and ,
"Effect on Component / Consequences of Non-performance" for safety-related j repetitive tasks. Also, informal desk-guide instructions are being !
developed which vill provide the system engineer with a list of appropriate questions to ask when considering approval or denial for rescheduling of a task. The form and the desk-guide instructions vill provide consistent documented technical justification of approval or denial for rescheduling of safety-related repetitive tasks.
Attachm:nt PY-CEI/NRR-0845 L Page 3 of 9 B. Several examples were identified of failure to fully accomplish Preventive Maintenance in accordance with PMI-0030.
- 1. The inspectors observed incunsistencies in valve stem lubrication.
CEI agrees that inconsistencies existed among the as-found conditions as well as the procedures and instructions which control the lubrication of these valve stems. As a result of these inconsistencies, procedures have been revised and training has been performed for maintenance personnel involved in this activity. These inconsistencies vere also evaluated as described below. An engineering evaluation was performed to determine the significance of valve stems lubricated with Neolube instead of Nebula EPO. The conclusion was that all of the valve stems identified vere adequately lubricated in accordance with vendor recommendations. However, improvements in lubrication practices should be made. The vendor of these valves recommends Neolube as an acceptable valve stem lubricant.
Neolube is a graphite type lubricant that dries upon application to the stem, leaving a fine dry graphite film coating. In cases where only Neolube exists on the valve stems, it should be recognized that PMI-0030 did not require stem lubrication if the existing lubrication was determined to be sufficient. Additionally, for MOVATS testing cf these valves per General Engineering Instruction (GEI)-0056, Neolube was utilized as the valve stem lubricant. In cases where both Neolube and Nebula EPO exist on the valve stem, i t is possible that lubrication with Nebula EPO was deemed necessary during a performance of PHI-0030. This PHI did not require cleaning of the stem before applying lubrication, thus potentially resulting in both Neolube and Nebula EP0 being present. An engineering evaluation of the compatibility of the two lubricants determined that mixing of the two lubricants vill have no' deleterious effect on the valve or its operability. For the case where PMI-0030 did not require lubrication of the MOV upper bearing, a review of the vendor recommendations determined that the upper bearing should be lubricated periodically, resulting in a change to PMI-0030 on January 29, 1988.
The following procedure changes and training have been completed.
PMI-0030 as revised January 29, 1988 and GEI-0056 vas revised January 28, 1988 to be consistent in future lubrication activities. For future Rockwell Hermaseal valve stem lubrication, Nebula EPO vill be used. For future stem lubrication of rising stem gate and globe valves, Never-Seez vill be used. Never-Seez is a lubricant that leaves a vet film coating which does not dry upon application.
Mobilgrease 28 vill be used in limit switch gear boxes, and Nebula EPO vill be used on operator main housings and upper bearing grease fittings. Also, the instructions now require that when a valve stem needs to be relubricated, it shall first be thoroughly cleaned and inspected prior to relubrication. Appropriate maintenance workers have been trained to these changes.
-.___.._.____.______--___---_. vee --
=-9 .-T-eiT--F W "'
k Attachment PY-CEI/NRR-0845.L Page 4 of 9 4
- 2. The inspectors found ne objective evidence of valve cycling af ter performance of PHI-0030. Research into the work history of the subject RHR . valves determined that the valves have been cycled since the performance of the PHI. This was performed on January 9, 1988 in accordance with the periodic-Technical Specification surveillance to verify opetability, and no problems were experienced. PHI-0030'has been revised (effective April 29, 1988) to specifylthat the, Control Room Unit Supervisor shall establish retest requirements. A further revision to PHI-0030 vill provide for documentation _of. retest completion.
f C. .Several examples were identified of inadequate and/or incomplete documentation during the review of' completed V0s.
- 1. V0 87-9677: Summary description did not accurately reflect the activity performed.
This VO was performed to troubleshoot and repair a Residual Heat Removal (RHR) pump.not initiating on high heat exchanger level as expected. The cause of this problem was determined to be a level transmitter lE12-N008A being out of calibration. The corrective actions taken with the VO vere recalibration of the transmitter and a circuit loop check. The closing' summary as stated on the VO Closing and Summary Sheet was, "Recalibrated transmitter and loop checked Sat." PAP-0905 in section 6.7, Vork Order Package Closeout, requires the planner or vork supervisor to "...vrite a short, concise summary statement of the work actually performed..." Ve believe the requirement of PAP-0905 was met and the summary descript did accurately reflect the activity performed. The only enhancement that could be made to the summary would be to include the transmitter HPL number. Fovever, this HPL number was adequately reflected on the same Closing and Summary Sheet vithin the corrective action summary description.
i
- 2. VO 87-5727, 87-10390, 88-0080: Incomplete or incorrect corrective action indicated on VO Closing and Summary Sheet..
- a. VO 87-5727 is still in the planning stages; no work has been performed on this V0; and thus, no Closing and Summary Sheet has been nor should have been complete for this V0. Ve believe that the VO number should have been 87-5722 in your inspection report.
The V0 Closing and Summary Sheet for this VO initially stated in the corrective action summary, "All work completed per the job traveler; change out and H0 VATS per NR PPDS-2554". This'was deemed insufficient and was revised to "Replaced Limitorque operator with rebuilt spare, performed H0 VATS on actuator per
- GEI-0056, adjusted torque svitch per SCR 1-87-1576, and installed new limiter plate". This change has been incorporated into the PPHIS history file for this V0.
4
Attachment PY-CEI/NRR-0845 L Page 5 of 9
- b. VO 87-10390 vas performed to troubleshoot intermittent relay problems in the Feedvater Control circuitry and to change three relays as directed by Design Change Package (DCP)87-807. The VO Closing and Summary Sheet initially stated in ti corrective action summary, "Implemented DCP 87-0807". This was deemed insufficient and was revised to, "Replaced existing time delay relays with Potter-Brumfield relays per DCP 87-807. Calibrated relays and obtained voltage readings for operating point of PDU output switch. Cleaned contacts and calibrated associated relays in control panel". This change has been incorporated into the PPMIS history file for this V0.
- c. VO 88-0080 was performed to replace the charge for the Standby Liquid Control squib valve per Surveillarice Instruction (SVI)-C41-T2002. During the performance of this VO power indication problema were observed. Troubleshooting of the circuitry identified two blown fuses which were promptly replaced.
The VO Closing and Summary Sheet corrective action summary initially only described the squib valve charge replacement. This was deemed insufficient and was revised to include the circuitry troubleshooting and replacement of identified blown fuses. Thir change has been incorporated into the PPHIS history file for chis V0.
- 3. VO 87-6175, 87-7385, 87-8745, 87-9361, 87-9498, 87-9677, 87-10213:
Incorrect or inadequate immediate failure cause identified on the V0 Closing and Summary Sheet.
- a. VO 87-6175 was performed to modify the stem and manufacture a new stem nut for valve lE12-F0024A in accordance with DCP 87-463. The V0 Closing and Summary Sheet initially stated in the immediate failure cause summary, "Modification of valve stem". This was deemed incorrect and was evised to "N/A" since the VO vas only implementing a design change. This change has been incorporated into the PPHIS history file for this V0.
- b. VO 87-7385 facilitated the mechanical portion of vork required to implement DCP 87-162A, which replaced the 1E22-C0004A diesel engine with an electric motor. The V0 Closing and Summary Sheet initially stated in the immediate failure cause summary, "Replace diesel engine (Petter diesel) due to diesel failure". This was deemed incorrect and was revised to "N/A" since the VO vas only implementing a design change. This change has been incorporated into the PPMIS history file for this V0.
- c. V0 87-8746 vas performed to troubleshoot and repair the Division II Diesel Generator due to the field not flashing. The VO Closing and Summary Sheet initially stated in the immediate failute cause summary, "Diesel vould not field flash". This was deemed incorrect and was revised to "Unable to identify /unknovn" since the troubleshooting failed to identify any problems. This change has been incorporated into the PPHIS history file for this V0.
Attachment PY-CEI/NRR-0845 L Page 6 of 9
- d. VO 87-9361 was performed to troubleshoot and repair a leak from a snubber located above an RHR pressure transmitter 1E12-N0050B.
The VO Closing and Summary Sheet initially stated in the immediate failure cause summary, "steam leak at snubber". This was deemed insufficient and was revised to "Instrumentation tubing connection leaking. Loose connection" since the problem was identified as a loose tubing connection. This change has been incorporated into the PPMIS history file for this V0.
- e. VO 87-9498 was performed to troubleshoot a Division II Diesel Generator failure to start during the performance of SVI-R43-T1318. The VO Closing and Summary sheet initially stated in the immediate failure cause summary, "Diesel Div. II did not see pneumatic start". This was deemed insufficient and was revised to "Not identified - Suspect solenoid start valves 1R43-F0037B and F0030B" since the troubleshooting failed to pinpoint the cause. This change has been incorporated into the PPMIS history file for this V0.
- f. V0 87-9677 vas performed to troubleshoot and repair incorrect level indication for a RHR heat exchanger. The V0 Closing and Summary Sheet initially stated in the immediate failure cause summary, "RHR HX A level indication is low". This was deemed insufficient and was revised to "Level transmitter 1E12-N0008A out of calibration" since the calibration problem is the cause which vould be utilized in Failure Analysis trending. This change has been incorporated into the PPMIS history file for this V0.
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- g. V0 87-10213 vas performed to repair bad connectors for two LPRMs reading downscale. The VO Closing and Summary Sheet states in the immediate failure cause summary, "Bad connectors". This vas deemed adequate since the problem was dovnscale LPRMs ael Une immediate cause was bad connectors. Identification (: 0. emisa of bad connectors vould be part of the root cause evaluation as part of the Failure Analysis program and is thus outside the scope or requirements of PAP-0905. I
- 4. V0 87-2249, 87-8746, 87-9361, 87-9677, 87-10390: Incorrect or j incomplete V0 closing codes. '
i The ineffectiveness of VO closing codes was identified by CEl during the INPO Maintenance Self Assessment which was completed in November l of 1987. These codes were initially designed to aid in failure '
analysis. However, due to recommendations provided from the Failure Analysis committee and the ongoing developnent of the Reliability )
Information Tracking System (RITS), the decision was made to eliminate I many of these PPMIS closing codes from the PAP-0905 vork order process. The failure analysis program needs vill be better supplied through a centralized evaluation of the existing VO closing summaries.
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Attachm:nt PY-CEI/NRR-0845 L Page 7 of 9
- 5. VO 87-4825, 87-8298, 87-8597, 87-9677: Incorrect or incomplete Master Part List (HPL) numbers.
The concern over HPL numbers chosen during VO initiation was identified by CEI during a QA audit report PIO 87-12, "Effectiveness of Corrective Action", issued July 29, 1987. PAP-0905 states that Vos should, when practical, address only one HPL number, and that single HPL numbers need not be addressed on Vos written to fill and vent instrumentation, for troubleshooting, or on standing V0s.
- a. VO 87-4825 was written to determine the cause of a Reuter-Stokes i indexer failure. The MPL number utilized to open this VO was !
"N/A" since the indexer was not installed in the plant and thus had no HPL number. This indexer was removed from the field and replaced with a new indexer on Harch 26, 1987 in accordance with VO 87-2620. The MPL number used for V0 87-2620 was 1C51-J0002C l and the failure cause vas identified es "unknown, VO 87-4825 vritten to troubleshoot failed indexer". VO 87-4825 could not have had a HPL number assigned to a salvaged component no longer installed in the field. However, to ensure identification of this V0 during future trending or failure analysis, the work summary specified the MPL number of the component when it was installed in !
the field and also referenced VO 87-2620 as the VO vhich )
originally removed the component from the field. Therefore, we i believe that this VO vas written properly and is not an example of a violation.
- b. V0 87-8298 vas written to troubleshoot a contact failure to open on relay lE12-K42. The HPL number utilized to open this VO vas the system HPL lE12. The Plant Equipment Master-file System (PEMS) which ties into PPHIS to provide equipment data based on the HPL number input, does not contain HPL numbers for relays.
Therefore, the identification number for this relay could not have been used as the V0 initiating HPL number. However, to ensure identification of this VO during future trending or failure analysis, the work summary specified the problem as a relay lE12-K42 failure to open. Therefore, ve believe that this VO was written properly and is not an example of a violation,
- c. V0 87-8597 vas written to troubleshoot a lov temperature indication for the Division I Diesel Generator lube oil. Since the problem had not yet been identified, the HPL number utilized to open this VO vas the DG lube oil system HPL 1R47. If a specific component vere to be identified as the problem, the only way to change the MPL number would be to void the V0 and then open a nev V0 vith that HPL number. Nonetheless, troubleshooting failed to identify any problems. For future trending or failure analysis the suspected trouble components are vell documented throughout this V0. Therefore, we believe that this VO vas written properly and is not an example of a violation.
t Attachssnt PY-CEI/NRR-0845 L Page 8 of 9 f
- d. VO 87-9677'vas written to troubleshoot and. repair incorrect level I indication for a RHR heat exchanger. Since the problem was suspected to be the controller 1E12-R0604A, this HPL number was utilized to open this V0. Troubleshooting identified the level transmitter 1E12-N0008A as~being out of calibration. Again, the only way to change a V0 initiation HPL number is to void the VO and then open a new V0 vith the new HPL number. Since this is not required and extremely inefficient, this vill not be done.
However, to ensure identification of the V0 during future trending or failure analysis, the corrective action identified in the Closing and Summary Sheet specifies the required recalibration of level transmitter 1E12-N0008A. Therefore, we believe that this VO vas written properly and is not an example of a violation.
- 6. V0 87-9361: Inadequate closing summary on the VO Closing and Summary Sheet.
This VO vas performed to trmibleshoot and repair'a leak from a snubber located above an RHR pressure transtaitter 1E12-N0050B. The VO Closing and Summary Sheet initially stated in the cl< ming summary, "No leakage anymore". This was deemed insufficient and was revised to "Revorked ,
tubing fitting with reactor seal #5" since this was the actual work' ,
required to correct the problem. This change has been incorporated into the PPHIS history file for this V0.
l D. The concerns identified in Audit PIO 87-12 vere listed as observations because they were subjective and related to ef fectiveness of implementation of the corrective action programs as opposed to compliance with the procedures. The Quality Assurance procedure, NOADI-1840,-
requires that each deficiency be documented on an Action Request (AR).
As indicated in your report, our audit progcam has become more "performance related". The audit found compliance with the program to be adequate but the deficiency noted was "performance related". The line which separates deficiencies from improved performance is not vell defined and is open to interpretation resulting in this deficiency being.
documented as a recommendation rather than an IR. As for your identifiec example, the audit organization has re-evaluated the effectiveness'of the Condition Report program and noted an improvement in both number open and mean time for closure of Condition Reporta. This improvement was partially due to actions taken as a result of the-recommendations in Audit PIO 87-12.
Corrective Action To Avoid Further Violations A. The Preventive Maintenance Deferral Evaluation / Justification Sheet as discussed previously will be formally incorporated into IAP-0501 and PAP-0906, for Instrumentation and Control Section and Maintenance Section respectively, by June 30, 1988. The guidelines for performing a proper technical evaluation for rescheduling repetitive tasks vill be provided to the appropriate engineers by May 30, 1988.
4 Attachment PY-CEI/NRR-0845 L Page 9 of_9 B. 1. As discussed _previously, procedure changes relative to the valve. ,
lubrications vere completed January 29, 1988. Training for i appropriate maintenance personnel to these procedure changes has also been completed.
- 2. The previously discussed revision to PMI-.0030 to provide for documentation of retest completion vill'be complete by Hay _ 20, 1988.
C. To ensure that the intent of the requirements of PAP-0905 is adequately met, the following corrective actions _have been or vill be. implemented. -
- 1. Training is being provided to work supervisors and planners emphasizing their VO review responsibilities and the importance of providing adequate summaries on the V0 Closing and Summary. Sheet.
This effort vill be complete by May 31, 1988.
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- 2. A Reliability Information Tracking System (RITS) is being implemented !
manually and vill be fully computerized by April 30, 1989. The objective of this program is to analyze component failures, and. based on the results, recommend corrective actions to prevent recurrence.
As a result of this program, changes are being made to PAP-0905, Vork Order Process.
- a. A Program Change Request (PCR) has been initiated to provide a }
section on.the VO Closing and Summary Sheet for MPL numbers of all i affected equipment. This vill ensure a greater capture percentage when trending for failure analysis or planning a VO on a i particular mmponent. This PCR vill be complete by l November 30, 1988. I
- b. PAP-0905 was revised (effective March 1, 1988)~to eliminate the need for the work groups to determine "Failure Category" and "Cause of Failure" closing codes. The RITS program vill utilize the summaries within the VO package to consistently determine VO closing codes for trending purposes when deemed necessary.
D. To ensure that the interpretation between deficiency and improved performance is made conservatively, OA guidelines have been revised to-clarify the threshold for issuing ARs to include not only-programmatic I
deficiencies or noncompliance, but also significant deficiencies which affect the effective implementation of processes. Appropriate QA personnel vere trained to this change April 29, 1988.
Date of Full Compliance Full compliance vill be achieved upon full implementation of RITS by j April 30, 1989.
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