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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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
[Table view] |
Text
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O' i
1 ELECTRIC ILLUMlH ATING COMPANY- i f THE CLEVELAND l
P.O DOX 97, o PERRY, OHIO 44o81 m TELEPHONE (216) 259-3737 m ADORESS-10 CENTER ROAD j l
Serving The Best Location in the Nation l Murray R. Edelman PERRY NUCLEAR POWER PLANT l
uy[" October 12, 1987 )
FY-CEI/NRR-0728 L !
l Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Detailed Control Room Design Review Commitments Centlemen:
The purpose of this letter is to address the following outstanding Detailed Control Room Design Review commitments,as > described in Licensing Condition 2.C (7) of the Perry Nuclear Power Plant Operating License - NPF-58.
- 1. HED implementation is complete for 100 flour Warranty Run HEDs - 36, 85, 86, 109, 114, 310, 522, and 600. The closed IIED Report sheets are included as Attachment 1.
- 2. Further review of first refuel HED's has identified revisions to
!!EDs 81,107, 328, and 365. A description and justification for the revisions, as well as the revised HED sheets, are included in Attachment 2.
- 3. A revised HED implementation schedule of remaining changes is provided in Attachment 3.
Please feel f ree to contact me if you have any questions. i Very trul ours, @
~*
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'/
- j. st7 Murray R. Ede an U$
Senior Vice President Nuclear Group p f c,n MRE:nj e o M
At tachment 8710160332 876012 PDR ADOCK 05000440 cc: T. Colburn K. Connaughton P PDR g}
1I USNRC, Region 111 g
i v e i
I l
l ATTACHMENT 1 TO 1
PY-CEI/NRR - 0728 L DETAILED CONTROL ROOM DESIGN REVIEW 100 HOUR WARRANTY RUN HED REPORT SHEETS I
6 l
+*
A" HED REPORT SHEET HED-36 REV. 4 HED DESCRIPTION: Several annunciator panels contain blank tiles which are illuminated.
B3.14 Annunciator vindow missing for "MST Turbine Area Temperature" annunciator. HE0-53 ;
l HUMAN FACTORS REVIEV: Inactive annunciator points vill only illuminate during test.
H.F. GUIDELINES: NUREG 0700, Section 3; Annunciators
(:
IMPLEMENTATION: Fix SAFETY AND OPERABILITY ASSESSMENT: CATEGORY I SAFETY CONSEQUENCE 7 No INCREASE ERROR POTENTIAL? No VERIFICATION: CORRECTS HED? Partial NEV HED? No BLANK VIND0VS ON P870-7A-H1 and P870-5A-E4 ARE ILLUMINATED. THESE VIND0VS VILL BE DEACTIVATED.
CORRECTION SCHEDULE:
~~
PLANNED COMPLETION Fuel Load WORK COMPLETE 8/27/85 PLANNED COMPLETION Prior to the beginning of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> verranty run.
VORK COMPLETE 1/30/87 REFERENCES l 1) Photo: M3 l 7.. 2) ECN 21075-86-393 j t 3) VO 86-16153 l
)
_ _ - - - - _ 4
s ,
f
. m 1
HED REPORT SHEET HED-85 REV. 3 HED DESCRIPTION: There currently exists no positive means for testing or detecting
? i foiled indicating' lights. B5.34 (4.2.4.2) HE0-16 Idsally the M/A indicator lights on the controller on P680-3D stoc:ld Frye a " push-to-test" ~
.y function. HE0-151 -> '
i HUMAN FACTORS REVIEV: Two indicating light bulbs are provided in almost all control .
applications (on-off, open-close). Neither light being lit is an indication of a burned ;
out bulb'or loss of control power. Valve mid-travel is indicated by both lights on.
Throttle valves will be coded with silver glove hand operators and.if an' indicating light ,
chould fail during mid-travel the operator would be aware of the event by the feedback from !
L : the associated flow meter. During surveillance all indicating lights vill be checked for safety systems. During shift change the panel status lights vill be reviewed and failing 4 or failed indicating lights replaced. Normally unlit indicators (i.e., white, blue, amber)
.for which failure cannot be detected vill be checked and replaced if necessary at periodic intervals as recommended by the lamp manufacturer. Lamps vill be tested prior to installation.
H.F. GUIDELINES: NUREG 0700, Section 5; Displays IMPLEMENTATION: Modify SAFETY AND OPERABILITY ASSESSMENT: CATEGORY I SAFETY CONSEQUENCE? No INCREASE ERROR POTENTIAL? No VERIFICATION: CORRECTS HED? Partial NEW HED? No~
. STRENGTHEN ADMINISTRATIVE PROCEDURES TO ENSURE THAT THE OPERATORS TAKE IMMEDIATE CORRECTIVE ACTION TO HAVE DEFECTIVE LIGHT BULBS REPLACED.
CORRECTION SCHEDULE: PLANNED COMPLETION Fuel Load WORK COMPLETE 12/16/85 ;
PLANNED COMPLETION Prior To The Beginning of the 100 Hour Varranty Run.
VORK COMPLETE 8/31/87 1
REFERENCES:
- 1) PAP-0201 Rev. 3 TC-1
- 2) IMI-E2-41
j.
\. *.
L HED REPORT SHEET HED-86 REV. 3 HED DESCRIPTION: There is'no lamp test capability provided for normally unlit indica-
- tors in the Control Room, at the remote shutdown panel, containment isolation status
. indicator panel and a11'other system status indication panels. B5.35 g
i 1
l HUMAN FACTORS REVIEV Two indicating light bulbs are provided in almost all control applications (on-off, open-close). Neither light being lit is.an indication of a burned ,
cut bulb or loss of control power. Valve mid-travel is indicated by both lights on. l
-Throttle valves vill be coded v!! h silvar E inva hand operators and if an indicating light. '
should fail during mid-travel the operator would be aware of the event from the associated flow meter. The'Inop & Bypass status lights are provided with a push-to-test feature. The containment isolation status panels and other status light boxes on P680, P870, and
-C22-P001 & P002 have 4 bulbs, 2 open and 2 close. The P601 SRV solenoid indicating lights have a lamp test pushbutton for both A and B groups. The full core display has status
. light test function. . During surveillance all indicating lights will be checked for safety systems.- During shift change the panel status lights-vill be reviewed and failing or i failed indicating lights replaced. Normally unlit indicators (i.e., white, blue, amber) j for:which failure cannot be detected will be checked and replaced if necessary at periodic l intervals as recommended by the lamp manufacturer. Lamps vill be. tested for proper operation prior to installation.
]
1 H.F. GUIDELINES: NUREG 0700, Section 5; Displays J IMPLEMENTATION: Modify SAFETY AND OPERABILITY ASSESSMENT: CATEGORY I SAFETY CONSEQUENCE 7 No INCREASE ERROR FOTENTIAL? No VERIFICATION: CORRECTS HED? Partial NEW HED? No Strengthen administrative procedures to ensure operators take immediate corrective action to have defective light bulbs replaced, l'
CORRECTION SCHEDULE: PLANNED COMPLET10N Fuel Load VORK COMPLETE 12/16/85 PLANNED COMPLETION Prior to the beginning of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> warranty run.
WORK COMPLETE 8/31/87
REFERENCES:
- 1) PAP-0201 Rev. 3 TC-1 2). IMI-E2-41 l
'J. ,
'i\
HED REPORT SHEET HED-109 REV. 3
.HED DESCRIPTION: Unlabeled white indicating lights are used on Panels 669 and 672 for.
.both LPRM downscale and LPRM bypassed indications. Similarly, red hydrogen purge lights and ember'high/ low. vacuum lights on Panel 845 are not individually labeled. B6.1 (4.1.4.3)
HUMAN FACTORS REVIEV: The closeness and size of the lights on P669 through P672 do not
' allow for individual labeling of LPRM detector status. A large plastic' plaque vill be provided for each panel showing the function of each LPRM detector status light set. This plaque vill be mounted below the rows of lights to enable the operator or technician to identify the meaning cf theLthree lights: downscale, bypass and upscale. The hydrogen '
level and vacuum lights on P845 vill.be individually' identified by new nameplates. )
H.F. GUIDELINES: NUREG 0700, Section 6; Labels and Aids IMPLEMENTATION: Fix SAFETY AND OPERABILITY ASSESSMENT: CATEGORY I SAFETY CONSEQUENCE? N o__ INCREASE ERROR POTENTIAL? No VERIFICATION: CORRECTS HED? Partial NEV HED? No i SPARE LIGHT BULBS-SHOULD BE LABELLED " SPARE". ;
1 CORRECTION SCHEDULE: PLANNED COMPLETION Fuel Load i VORK COMPLETE 11/23/85 PLANNED COMPLETION Prior to the beginning of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> varranty run.
VORK COMPLETE 8/19/87
)
REFERENCES:
i
- 1) Photos: S2, S3, S4, 45, 46
- 2) FDDR KL1-942 l l
L' . I e . .
v. j l' l
[ -($[J HED REPORT SHEET HED-114 REV. 1 I I l
HED DESCRIPTION: The association of pen color to input parameter is generally not I spacified on recorder labels, except for those on Panel 680. 36.6 (4.2.3.8) {
l
. HUMAN FACTORS REVIEV: The recorders vill be provided with nameplates which identify the parameters and pen color. i l
H.F. GUIDELINES: NUREG 0700, Section 6, Labels and Aids IMPLEMENTATION: Fix SAFETY AND OPERABILITY ASSESSMENT: CATEGORY I SAFETY CONSEQUENCE? No INCREASE ERRCR POTENTIAL? No 1 VERIFICATION: CORRECTS HED? Partial NEW HED? _No j B21-R623 PEN LABEL IS MISSING. LABEL VILL BE PROVIDED.
CORRECTION SCHEDULE: PLANNED COMPLETION Fuel Load VORK COMPLETE 12/16/85, PLANNED COMPLETION Prior To Commercial Operation VORK COMPLETE 11/3/86 l
REFERENCES:
- 1) FDDR KL1-942 e
j J
l n HED REr0RT SHEET HED-310 PEV. 2 O l HED DESCRIPTION: SA4.3 Is extraneous information not included (e.g., manufacturer's j tr:dzmark, patent notice, etc.)? Refer to HED Attachment Sheet. HE0-30 j i
?
I l
HUMAN FACTORS REVIEV: Manufacturer's trademarks do exist. Overall this extraneous information is unobtrusive. The vendor labels on P601 chart recorders are prominent and vill be covered.
1 H.F. GUIDELINES: NUREG 0700, Section 6; Labels and Aids IMPLEMENTATION: None and Fix j-SAFETY AND OPERABILITY ASSESSMENT: CATEGORY I SAFETY CONSEQUENCE? No INCREASE ERROR POTENTIAL? No VERIFICATION: CORRECTS HED? Partial NEV HED? No B21-R623B LABEL IS HISSING. EEW LABEL VILL BE PROVIDED.
CORRECTION SCHEDULE: PLANNED COMPLETION Fuel Load VORK COMPLETE 9/13/85 PLANNED COMPLETION Prior To The Beginning of the l 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Varranty Run VORK COMPLETE 8/19/87 1
REFERENCES:
- 1) FDDR KL1-942
( ,
b HED ATTACHMENT SHEET HED-310 REV. 2
~
Observation Panel .j l o' Vendor labels on chart recorders, controllers 601/823 1
p 0- GE label on range selector panel 842/680 )
l
'o Chart recorder - manufacturer label and trademark 800/811 I I
o- Manufacturer's description 807/808
/809
.o' Some' extra info in lower left corner of some labels 845 o All Bailey & GE units have logo 846/865
.o .Rosemont & Bailey 868/869 l
o' All recorders have manufacturers logo & trademark 883 o Manufacturer's logos on equipment 902/906
/907 ho PANALARM tempmatic (not too intrusive) 904 o Peak shock annunciator has manufacturer trademark, partially 969 obscured by nameplate
p '
l HED REPORT SHEET HED-522 REV. 2
- HED DESCRIPTION: Nameplates are missing on P884 and P885.
t
- k. !
.l
-.s c
1 i
. HUMAN FACTORS REVIEV: Nameplates will be provided. I t
'l i H.F. GUIDELINES: NUREG 0700, Section 6, Labels 1
1
'i IMPLEMENTATION: Fix ;
l SAFETY AND OPERABILITY ASSESSMENT: CATEGORY 1 l SAFETY CONSEQUENCE? NO INCREASE ERROR POTENTIAL? No VERIFICATION: CORRECTS HED? Partial N0 NEW HED? YES
' NAMEPLATE IS MISSING FROM RECORDER D19-R400. PERMANENT LABEL VILL BE PROVIDED.
CORRECTION SCHEDULE: PLANNED COMPLETION - Fuel Load WORK COMPLETE 12/16/85 PLANNED COMPLETION Prior to the beginning of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Warranty Run.
VORK COMPLETE 8/19/87' i
REFERENCES:
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h HED REPORT SHEET HED-600 REV. 2~
HED DESCRIPTION - :F1.11 When.the operator is talking on the radio channel of the Control Room Communication Module, any Channel 5 PA page occurring at the same time vill be transmitted over-the top of the radio conversation.
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.. , I HUMAN FACTORS REVIEU Modify the communication' module's circuitry to prevent PA messages from being transmitted over the top of Radio Conversations.
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'H.F. GUIDELINES:- NUREG 0700, Section 2; Communications !
IMPLEMENTATION: -Fix.
SAFETY AND OPERABILITY ASSESSMENT: CATEGORY 2 SAFETY CONSEQUENCE? No INCREASE ERROR POTENTIAL? Yes VERIFICATION: CORRECTS HED7 NO NEV HED?
' CORRECTION SCHEDULE: PLANNED COMPLETION Prior to the beginning of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> varrant run VORK COMPLETE 8/31/87
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REFERENCES:
- 1. DCP 860969 1
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1 ATTACHMENT 2 -j i
TO PY-CEI/NRR - 0728 L .i 1
f DETAILED CONTROL ROOM DESIGN REVIEW ]
i HED REVISIONS {
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I HED # REV. CHANGE / JUSTIFICATION 81 2. Corrected typos, added new meters, deleted meters that are correct for Priority 2 changes.
Panel Change P680-3B Added N11-R311 P680-15B Added N31-R011 P877-1B Added R42-R020A, R021 &
R43-R012A P877-2B Added R42-R030B,R031 &
R43-R022B P601-17B Deleted E12-K100s, Corrected in HED-364 P601-20B Deleted E12-R100A, Corrected in HED-364 P601-21B Deleted E51-R604, Corrected In HED-70 P601-22B Corrected type, C11-R100A/B P622 Added MPS #'s B21-659A-D, 660A-D P623 Added B21-661A-D, 662A-D P904 Corrected MPLs P50-R170-172 to P47-R290-R292 1
107 1 Change implementation to a "NONE". The four (4) leak detection indicators on P632 will remain as-is since the pointers do not totally obscure the scale markings and the operator can read the scale.
328 1 Mimic change that was made at fuel load was adequate to correct the deficiency. The first i refuel fix to move the light is not necessary. j 365 1 Changed implementation to "FIX and NONE". The first refuel fix to rearrange P53-F030, 35, 40
- and 45 by alphanumeric designation. These L valves isolate "OPEN" instead of " CLOSED".
These indications have been separated from the l other "CLOSE" valves to prevent confusion during the isolation.
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..a IF HED REPORT SHEET HED-81 REV. 2 HED DESCRIPTION: Number scale divisions that were not in decimal multiples of 1, 2, or 5 vare observed on the following panels:
001 680 870 601 800 904 622 821 970 669/672 823-842 B5.29 (4.2.2.15)
- 11UMAN FACTORS REVIEV: Scales vill be modified to meet the above criteria for the instruments identified in the attached sheet. A two stage implementation, plan vill take place. 1) All scales associated with RG 1.97 instrumentation or those found during the task analysis of the PEI's and 10I-11 vill be fixed prior to fuel load. 2) The remaining instruments vill be modified prior to startup following first refuel.
H.F. GUIDELINES: NUREG 0700, Section 5; Displays IMPLEMENTATION: Fix SAFETY AND OPERABILITY ASSESSMENT: CATEGORY I SAFETY CONSEQUENCE? No INCREASE ERROR POTT:.NTIAL? No VERIFICATION: CORRECTS HED? Yes e NO NEW HED? Yes CORRECTION SCHEDULE: PLANNED COMPLETION Fuel Load - Priority 1 VORK COMPLETE ,,9/6/85 PLANNED CCMPLETION Prior to start-up following first refuel
- Priority 2 VORK COMPLETE
REFERENCES:
1
- 1) Photos: 27, 28
- 2) ECN 28465-86-2240 k
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f, .jg f.; @ HED ATTACHMENT SHEET HED-81-1 REV. 2 c
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Priority 1 - Fuel Load MPL Panel E12-R100C P601-17B B21-R623B P601-17B
- RG 1.97 instrumentation i C41-R600A P601-19B
- j E51-R601 P601-21B L E31-R100 P601-21B j C61-R012 C61-P001
, E32-R601 P601-16B D23-R170A P883
- Priority 2 - Prior to Startup After First Refuel '
_,MQ Panel
~G33-R600 P680-1B l N21-R181A P680-2B
(. N21-R181B P680-2B N21-R181C P680-2B N11-R243A P680-3B N11-R243B P680-3B N11-R311 P680-3B l N21-R051 P680-3B N21-R111 P680-3B N37-R146A P680-3B N27-R146B P680-3B N27-R191 P680-3B B33-R605A P680-4B B33-R605B P680-4B l- B33-R603A P680-4B B33-R603B P680-4B B33-R602A P680-4B l B33-R602B P680-4B N41-R016 P680-9B N41-R018 P680-9B N41-R019 P680-9B
,. N31-R011 P680-15B l N31-R012 P680-15B 7431-R013 P680-15B N31-R014 P680-15B N31-F.015 P680-15B N31-RU16 P680-15B N31-R017 P680-15A ,
.'.? N31-R018 P680-15B N31-R019 P680-15B l N31-R020 P680-15B !
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HED ATTACHMENT SHEET HED-81-2 REV. 2' i
N31-R021- P680-15B 1- 'N31-R022- P680-15B
-N34-R135 P680-15D L R22-R010 P870-1B i R22-R011' P870-1B l
~R11-R010 P870-1B R11-R011 P870-1B R11-R012 P870-1B R11-R013 P870-1B 1;1
.R11-R014 P870-1B L .R11-R015 P870-1B'
'R11-R016- P870-1B
'L -R11-R017 P870-1B R11-R018. P870-1B R42-R012 P870-1B
.R42-R013 P870-1B -i R42-R010. F870-1B R42-R011 P870-1B .;
1 R51-R112- P870-2B-P52-R010 P870-2B PS2-R102- P870-2B G41-R098 P870-2B
-(.' N36-R341A 'P870-4B N36-R341B P870-4B N36-R341C P870-4B N36-R481 P870-5B
-N11-R191A1 P870-6B N11-R191B P870-6B i N11-R141A P870-5B
-N11-R141B P870-6B-N11-R146A P870-6B N11-R146B P870-6B N11-R196A P870-6B N11-R196B P870-6B ,
N21-R183 P870-7B N42-R036~ P870-9B l N42-R041 P870-9B
-R42-R020A P877-1B
'R42-R021 P877-1B R43-R012A P877-1B R42-R030B P877-2B R42-R031. P877-2B R43-R022B P877-2B P43-R026A P970 P43-R026B P970 P43-R026C P970 P43-R221 P970 G41-R032 P970 j (i.orP43-R350 P970 _.
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( ". HED ATTACHMENT SHEET HED-81-3 REV. 2 P43-R351 P970 P43-R352 P970 C41-R077 P970 G41-R101A P970 G41-R101B P970 P45-R178 P601-16B R42-R040C P601-1f3 R42-R041C P601-16B E22-R011C P601-16B P42-R096B P60.'-17B P45-R011 P601-17B l
P45-R102B P601-17B N11-R011A P601-19B N11-R011B P601-19B N11-R011C P601-19B N11-R011D P601-19B P42-R096A P601-20B P45-R010 P601-20B P45-R102A P601-20B E51-R602 P601-21B C11-R100A,B P601-22B P43-R602 P800
( B21-R659A-D P622 B21-R660A-D P622 B21-R661A-D P623 B21-R662A-D P623 P47-R290 P904 P47-R291 P904 P47-R292 P904 N31-R005 P823 N27-R401 P823 C61-R011 C61-P001 C61-R010 C61-P001 P42-R045A C61-P001 ;
P45-R055A C61-P001 P45-R033A C61-P001 D23-R230 C61-P001
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HED REPORT SHEET- HED-107 REV. 1 HED DESCRIPTION: Pointers partially obscure scale markings or numerals on round indica-tors located on Panel 680 and four indicators on Panel 632. B5.57 (4.2.2.7)
HUMAN FACTORS REVIEV The four leak detection flow switch indicators (E31-R613A, B, C, D) pointers do not totally obscure the scale markings and the operator can read the scale.
The detectors measure gross leakage and normally indicate no flow. The round indicators on P680 for RFPT control valve position, RFPT RPM, GEN FREQUENCY, GEN VATTS, GEN VARS, POVER FACTOR and SYNCHR0 SCOPE have the pointer obscuring the numerals. The scales are vell marked with major and intermediate markings. The pointer partially obscuring the numerals on these non critical plant parameters introduces only very slight risk.
H.F. GUIDT. LINES: NUREG 0700, Section 5; Displays IMPLEMENTATION: None SAFETY AND OPERABILITY ASSESSMENT: CATEGORY I SAFETY CONSEQUENCE 7 No INCREASE ERROR POTENTEAL7 No VERIFICATION: CORRECTS HED? N0 NEW HED? !
CORRECTION SCHEDULE: PLANNED COMPLETION VORK COMPLETE 9/3/87 i
REFERENCES:
- 1) Photos: C1, C2
VN dil HED REPORT SHEET HED-328 REV. 1 HED DESCRIPTION: PEI-1 (3.1.4) Generator breaker mimic is incorrect.
P680-9C S-610-PY-TIE P680-9C S-611-PY-TIE HE0-61 HUMAN FACTORS REVIEV: The generator breaker mimic vill be corrected. Permanent mimic is cd2quate as designed. Voltage potential light vill not have to be moved.
H.F. GUIDELINES: NUREG 0700, Section 6.6; Labels and Aids IMPLEMENTATION: Fix SAFETY AND OPERABILITY ASSESSMENT: CATEGORY I SAFETY CONSEQUENCE? No INCREASE ERROR POTENTIAL? No VERIFICATION: CORRECTS HED? Yes NEV HED7 No CORRECTION SCHEDULE: PLANNED COMPLETION Fuel Load - Provide permanent mimic VORK COMPLETE 11/23/85
REFERENCES:
- 1) FDDR KL1-6100 i
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J' HED REPORT SHEET HED-365 REV. 2 HED DESCRIPTION: PEI-4 (CS3.0.2) Indication of BOP isolation is not very salient.
Tha positions of chilled water valve status lights in matrix differ from Panels 601-18B cnd P601-19B. Indicators P50-F150 and P50-F060 in P601-19B matrix are in reverse numerical order.
P601-18B P50-F140 P601-19B P50-F060 PEI-7.(3.0.1)' Isolation matrices on P601 are not arranged to best identify isolation groups.
P601-19B Containment Isolation matrix P601-18B HE0-109, HE0-119 HUMAN FACTORS REVIEV: The isolation matrices on P601 vill be improved by rearranging valve position indication to identify isolation groups. Vithin each isolation group, velves vill be organized by MPL alphanumeric designation with the exception of P53-F030, F035, F040, F045 which isolate open instead of closed. Theso indications have been ssparated from the other "CLOSE" valves to prevent confusion during the isolation
( NUREG 0700, Section 5; Displays H.F. GUIDELINES:
IMPLEMENTATION: Fix and None SAFETY AND OPERABILITY ASSESSMENT: CATEGORY 1 SAFETY CONSEQUENCE? No INCREASE ERROR POTENTIAL? No VERIFICATION: CORRECTS HED? Yes NC NEV HED? Yes CORRECTION SCHEDULE: PLANNED COMPLETION Fuel Load VORK COMPLETE 9/19/85
REFERENCES:
- 1) ECN 24002-86-654, 655 t
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ATTACHMENT 3 TO l
PY-CEI/NP.R - 0728 L DETAILED CON 1ROL ROOM DESIGN REVIEW HED IMPLEMENTATION SCHEDULE
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1 l L I LThe following is the status of the remaining open HED's and '
1 their' proposed-implementation schedules.
'1'. HED's to be corrected prior to startup following the first refueling outage:
1 29,_33,172, 74, 76,.77, 80, 81, 84, 94, 96, 100, 102, 105, 110,-158, 182, 195,'313, 314, 320, 354, 360, 363, 364, 366, 370,'408, 501, 506, 508, 509, 511, 512, 513, i 514, 515, 521, 525, 526, 527, 528, 529, 601, 602,f603, 604, 606, 607, 608, 609, 610, 611, 612, 1012, 1019, 1036. -
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