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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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
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I CENTERf0R ENERGY PERRY NUCLEAR POWER PLANT Mail Address: Robert A.Stratman PO BOX 97 VICE PRESIDENT NUCLEAR 10 CENTER ROAD PERRY. OHIO 44081 PERRY. OHIO 44081 (216) 259-3737 June 3, 1994 PY-CEI/NRR-1804L U. S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Response to Notice of Violation Gentlemen:
By correspondence dated April 25, 1994 the Nuclear Regulatory Commission (NRC) transmitted Inspection Report 50-440/94004 and an associated Notice of Violation (NOV). The Inspection Report documented the results of'the special team inspection conducted by the resident inspectors and others on January 30 through March 9, 1994. The April 25, 1994 correspondence required a response to the NOV and requested certain information regarding specified weaknesses.
The requested information included actions taken and planned to address the specified weaknesses.
The response to the NOV and the specified weaknesses is provided by the attachment. A change in schedule for the submittal of this response was discussed with the appropriate Region III branch head on May 25, 1994.
If you have questions or require additional information, please contact Mr. J. D. Kloosterman, Manager - Regulatory Affairs, at (216) 280-5833.
Very truly yours, f 1s /
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NRC Resident Inspector !
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PY-CEI/NRR-1804L Attachment 1 of 8 Response to Notice of Violation and Specified Weaknesses Introduction ;
Violation 94004-01 includes four separate examples of which two examples involve deficiencies in the content of instructions and two examples involve failure to adhere to the procedural requirements. Due to the diversity in the circumstances associated with each of the examples described in the Notice of Violation under sections 1.a. 1.b, 1.c and 1.d. a separate response to each example is provided. Although a separate response is provided for each example, the implications of the violation as a whole are clearly recognized. In '
addition to the specific corrective actions delineated in the response to each of the examples, the following activities are planned to improve overall performance in the areas of procedural adherence and procedural deficiencies: '
The Vice-President, Nuclear vill issue a policy statement that clarifies and reinforces the requirement for procedural adherence by July 1, 1994. 1 During employee meetings to be held with the Vice-President, Nuclear and site employees and between department directors and employees, the issue of procedural adherence vill be reviewed and discussed. These discussions vill emphasize management expectations regarding adherence to procedures. These meetings vill be complete by August 31, 1994. :
i A study of the process which governs proccdure development, review, approval and '
revision has been completed. The recommendations from this study include activities which can improve the quality of the process and the resultant ,
procedures. A task force vill be formed to assess and develop an implementation ,
strategy based on the recommendations. This task force vill be formed by August 1, 1994.
Additionally, a procedure review checklist has been developed to improve the quality of procedures and is currently under evaluation. The use of this :
checklist vill be implemented for new and revised procedures by July 15, 1994.
Responses to Violations ;
50-440/94004-01.a Restatement cf the Violation ,
! 10 CFR Part 30, Appendix B, Criterion V, requires, in part, that activities .
affecting quality be prescribed by and accomplished in accordance with, documented instructions, procedures or drawings of a type appropriate to the circumstances. These instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily completed.
1 Contrary to the above, on February 2, 1994, after a water hammer occurred, the !
shift supervisor failed to log the occurrence of the water hammer in the plant l log and failed to inform plant management, as required by Procedure PAP-0201, !
" Conduct of Operations".
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PY-CEI/NRR-1804L Attachment 2 of 8 Reason for the Violation This violation was the result of inappropriate judgment by the shift supervisor in failing to recognize the condition should have been logged in accordance with PAP-0201. Contributing to the violation was a procedural weakness which failed to provide clear instructions regarding the broader category of piping / system thermal transients, in addition to a classical water hammer, which should be ,
identified and appropriately documented.
Corrective Action Taken and Results Achieved The incident has been reviewed with the involved shift supervisor, including a discussion of the sensitivity to be applied to piping / system thermal transients !
and the expected actions regarding logging and initiation of corrective actions '
including condition reports.
A copy of Inspection Report 50-440/94004, including the associated NOV, has been provided to each shift supervisor for review and to share this information with each shift's personnel including discussion of the failures and how improvements can be achieved. This vill be completed by July 1, 1994. ?
A condition report was generated on March 9, 1994 to document and investigate the specific transient condition. l Actions to Be Taken to Avoid Further Violations ,
PAP-0201 vill be revised to clearly provide instructions regarding the broad category of piping / system thermal transients which require elevated levels of attention. This revision vill be complete by August 15, 1994. ,
Date When Full Compliance Vill Be Achieved Full compliance for this example has been achieved. The initiation of the condition report and subsequent follow-up meets the intent of PAP-0201. An entry to the plant log was made to document the event on May 27, 1994.
.50-440/94004-01.b Restatement of the Violation 10 CFR Part 50, Appendix B, Criterion V, equires, in part, that activities affecting quality be prescribed by and accomplished in accordance with, documented instructions, procedures or drawings of a type appropriate to the i circumstances. These instructions, procedures, or drawings shall include I appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily completed.
Contrary to the above, Surveillance Test Procedures SVI-B21-T9124, T9416, T912.2, and T9415, and Periodic Test Instructions PTI-B21-P001, 2, 3, and 4, used on February 14 and 15, 1994, during leak rate testing of the main steam lines were inappropriate to the circumstances in that they failed to contain a qualitative acceptance criteria for instrument air for the main steam isolation valve actuators.
PY-CEI/NRR-1804L Attachment 3 of 8 Reason for the Violation ,
The preparation and review of the local leak rate test (LLRT) procedures for the main steam isolation valves (MSIV) did not properly consider the need to establish procedural control for the utilization of air in assisting closure of the MSIVs for testing.
Corrective Action Taken and Results Achieved The Surveillance Instructions (SVI) used for testing the MSIVs and the Periodic Test Instructions (PTIs) used to troubleshoot MSIV leakage have been revised to provide appropriate prerequisites to control the availability of the air supply .
to the MSIVs.
Actions to Be Taken to Avoid Further Violations .
The activities identified in the introductory section of this response address corrective actions regarding procedure / instruction adequacy. No further actions specific to this example are deemed necessary. ,
Date Vhen Full Compliance Vill Be Achieved Full compliance relative to this example has been achieved by the revisions to the SVIs and PTIs. _;
$0-440/94004-01.c Restatement of the Violation 10 CFR Part 50, Appendix B, Criterion V, requires, in part, that activities affecting quality be prescribed by and accomplished in accordance with, ,
documented instructions, procedures or drawings of a type appropriate to the circumstances. These instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily completed.
Contrary to the above, on February 25 and 26, 1994, surveillance testing of the safety relief valve (SRV) logic was not accomplished in accordance with procedures appropriate to the circumstances. Surveillance Procedures SVI B21-T0370A, "SRV Pressure Actuation Channel Calibration for B21-N068A and B21-N068E," and SVI-T0370B, "SRV Pressure Actuation Channel Calibration for B21-N068B and B21-N068F" both had an error which unintentionally caused an SRV to open. Also, on February 25, 1994, during the conduct of the SVIs, the Lead
- 1 Test Performer did not stop the test when unexpected plant behavior was experienced, as required by Procedure PAP-1105, " Surveillance Test control".
Reasons for the Violation ,
The cause for the deficiency in the Surveillance Instruction (SVI) was an inadequacy in the preparation and review of the last revision of the affected SVIs, which was not effective in assuring the seal in logic was reset-to preclude the opening of the SRVs. The involved SVIs had been revised since their last performance. During this revision, sequencing of the calibration checks had been changed and. steps to reset the seal in logic had been inadvertently omitted.
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Attachment 4 of 8 The lead test performer did not stop the test when unexpected plant behavior was j
experienced since the lead test performer was unaware the annunciator ("SRV OPEN i SIGNAL RECEIVED") had been received in the control room. Initially, the control room operators incorrectly believed the annunciator was an expected result of the SVI and that it did not indicate an actual SRV opening. The control room operator on the next shift recognized the opening of the SRV and identified it was not an expected result of the SVI. At that time the lead test performer was notified and the SVI was terminated. 7 Additional information regarding this example is contained in LER 94-008-00. ,
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Corrective Action Taken and Results Achieved t Both involved SVIs have been revised to correct the deficiency. On March 3, 1994, the corrected SVI B21-T0379A vas successfully completed.
Calibration SVIs revised since the last refueling outage have been reviewed to identify those SVIs which had not been performed. Similar instrumentation and .
control SVIs revised as a group were examined to ensure at least one of the F group had been successfully performed. Seven SVIs were identified that had not been validated by performance. These seven SVIs vere subsequently ,
validated / verified.
Control room operations crews were initially informed of this event by a daily s instructior.. This event was discussed with the licensed operators to highlight thin event and the operations policy " Control Room Response to Annunciators."
Actions to Be Taken to Avoid Further Violations t The activities identified in the introductory section of this response address corrective actions regarding procedure / instruction adequacy. No further actions specific to this example are deemed necessary.
F Date Vhen Full Compliance Vill Be Achieved Full compliance relative to this example was achieved with the revision of the involved SVIs.
50-440/94004-01.d ,
Restatement of the Violation
- 10 CFR Part 50, Appendix B, Criterion V, requires, in part, that activities affecting quality be prescribed by and accomplished in accordance with, ;
documented instructions, procedures or drawings of a type appropriate to the circumstances. These instructions, procedures, or drawings shall include l appropriate quantitative or qualitative acceptance criteria for determining that ',
important activities have been satisfactorily completed.
Contrary to the above, on March 1, 1994 during vork on Emergency Diesel Generator 1R43C0001A (lA), the measurement of piston ring gap was not accomplished in accordance with the documented instructions in work order (VO)
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PY-CEI/NRR-1804L Attachment 5 of 8 .
f 94-763 in that measurements were not taken as directed by step 5.3.2 and attachment 2 of vork Instruction PMI-0053, " Division 1 and 2 Standby Diesel Generator Connecting Rod and Piston Maintenance".
Reason for the Violation i This event was due to personnel error involving failure to comply with procedural requirements. The craftsmen performing the work took the ring gap measurements with the rings at the top of the cylinder based on verbal instructions from their supervisor. The supervisor, based on previous experience with other diesels, believed that the gap measurements should be taken at the top of the cylinders su that the rings would be in a configuration more representative of their normal operating conditions.
Corrective Action Taken and Results Achieved The gap measurements were re-performed with the rings located 6 inches above the bottom of the cylinder liner as specified by step 5.3.2 and attachment 2 of PHI-0053. .
On April 9, 1994 and April 10, 1994, in response to concerns with the procedure compliance issue, meetings were held with craft supervisory and non-supervisory personnel. These meetings stressed the requirement for procedure compliance.
These meetings also reviewed the consequences (disciplinary and potential legal action) that could result from villful non-compliance. Additionally, on May 6, 1994, a letter was issued from the maintenance manager to maintenance supervisors emphasizing management's expectation for immediate, verbatim, step-by-step procedural compliance.
Actions to Be Taken to Avoid Further Violations I
The activities identified in the introductory section of this response address activities planned regarding the overall' issue of procedural adherence. No further actions specific to this example are deemed necessary.
Date When Full Compliance Vill Be Achieved Full compliance has been achieved for this example based upon the correct performance of the ring gap measurement.
50-440/94004-02 Restatement of the Violation Appendix B of 10 CFR Part 50, Criterion II, requires in part, that activities affecting quality shall be accomplished under suitable controlled conditions.
Controlled conditions include the use of appropriate equipment, suitable environmental conditions for accomplishing the activity, such as adequate cleanliness, and assurance that all prerequisites for the given activity have been satisfied. ,
t Contrary to the above, adequate cleanliness was not maintained for the Division 1 emergency diesel generator during corrective maintenance, as evidenced by a ;
rag observed inside following the corrective maintenance. !
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PY-CEI/NRR-1804L Attachment 6 of 8 Reason for the Violation i The work process did not properly control the work and resulted in a loss of material accountability during the involved maintenance activity. Rags were used during the maintenance to block holes in the cylinder head sub cover so items did not fall into the engine. The work orders for placing the rags into the holes had steps for removal with a second party verification. These steps I were completed, however, the steps did not account for the number of rags used.
Neither the work order instructions nor the flousekeeping/ Cleanliness Control i Program (PAP-0204) provided appropriate controls / instructions for material exclusion. The procedural controls in PAP-0204 for internal cleanliness requirements were written specifically to address piping and valve openings and ,
were vague for components such as diesel engine crank case and pump internals.
Corrective Action Taken and Results Achieved An action plan was developed and implemented for the Division I diesel engine to .
remove the rag and address the potential that other foreign material may have !
been inadvertently introduced into the engine. The completion of this action plan did not find any other instance of significant foreign material intrusion.
Vork order packages for the diesel engines were reviewed and appropriate controls implemented to preclude further instances of foreign material intrusion into the engine. Plastic zip lock type bags with numbers and lanyards were filled with five rags each and secured closed with duct tape. These bags were used to cover openings during subsequent maintenance on the Division II diesel generator with the work package documentation identifying the location by bag number, date of installation and date of removal. The numbered zip lock bags were not used during the subsequent Division III diesel generator maintenance due to the smaller size of the Division III diesel engine and configuration differences. Material and personnel accountability logs were maintained during the subsequent maintenance on both the Division II and Division III diesel generators during activities which had the potential for introduction of foreign material into open systems or areas of the engines.
Actions to Be Taken to Avoid Further Violations PAP-0204 vill be revised to strengthen material exclusion controls when opening equipment or systems which have areas which will not be accessible to direct visual inspection. This revision vill be complete by September 8, 1994.
Date When Full Compliance Vill Be Achieved Full compliance relative to this example was achieved upon completion of the specified diesel generator action plan and the subsequent successful engine testing.
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Attachment 7 of 8 Additional Actions Taken or Planned Regarding Specified Veaknesses In addition to the response to the NOV, additional information was requested regarding actions taken or planned for weaknesses in cleanliness and material accountability during earlier maintenance activities on the diesel engine and for weaknesses in the ownership in the diesel generator.
Actions which have been taken regarding the veaknesses in housekeeping and material accountability during earlier maintenance activities on the diesel engine include the following:
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- This incident was communicated to appropriate work groups to ensure system cleanliness requirements and material accountability are maintained during performance of maintenance activities.
- The action plan for the diesel generator specified in the above response to violation 94004-02 vas implemented. This action plan included the following activities:
- Removal of the rag
- Removal of the engine sump oil
- Inspection of affected lube oil sump and strainer ,
- Removal of cam shaft galley doors and inspection of the cam shaft galley area
- Inspection of the engine's internals
- Cleaning (vacuuming) oil from bottom of engine and inspection
- Inspection of keep varm lube oil filter
- Flushing jacket water through the strainer and evaluation of results
- Removal of the injectors and inspection of the piston area ,
The completion of this action plan did not identify additional instances ,
of significant foreign material in the diesel engine. r In addition to these actions, the revision to PAP-0204, specified in the above
- response to the violation, vill strengthen material exclusion controls when opening equipment or systems which have areas which are not accessible to direct visual inspection.
Regarding the weakness in ownership of the diesel generator, the issue is considered to include the ownership and accountability for identification and resolution of diesel generator related problems. Similar issues along with objectives and associated action plans have been previously identified in the ;
Perry Course of Action (PCA). The PCA provides the framework for improving the organizational culture at Perry Nuclear Power Plant and for effecting the changes necessary to achieve the appropriate attitudes and actions by personnel.
One specific action of the PCA, Site Policy H&C - 7, Management Meetings, was developed to ensure that senior and middle managers meet with employees on a regular basis to discuss expectations and review both successes and failures of the organization. During the first cycle of employee meetings to be held between the Vice President, Nuclear and site employees and between department directors and employees, the issues of ovnership, accountability and management i
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Attachment 8 of 8 I expeciationsvillbereviewedanddiscussed. The above incident involving the diesel generator vill be used as an example of a failure to meet ..snagement i expectations. These meetings vill be completed by August 31, 19D. This action, i as well as other activities described in the PCA is expected-to improve performance relative to the ownership issue. .
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