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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY
' P.O BOX 5000 CLEVELAND, OHIO 44101 . TELEPHONE (216) 622 9800 . ILLUMINATING BLOO. - 55 PUBLICSOUARE Serving The Best Location in the Nation MURRAY R. EDELMAN May 30, 1985 N CLEA PY-CEI/OIE-0052 LQ Mr. C. J. Paperiello, Chief Emergency Preparedness and Radiological Protection Branch U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE: Perry Nuclear Power Plant Docket No. 50-440; 50-441 Emergency Preparedness Appraisal 50-440/85-009 and 50-441/85-007 Dear Mr. Paperiello This letter and its attachments provide the Cleveland Electric Illuminating Company response to the items noted in Appendixes A and B of Inspection Report 50-440/85-009.i 50-441/85-007, dated May 1, 1985. This Report provided the results of the Emergency Preparedness Appraisal conducted February 25, 1985 through March 7, 1985 at the Perry Nuclear Power Plant (PNPP).
Attachment 1 of this letter provides our planned actions for completion of each of the Open Items identified in Appendix A.
Attachment 2 of this letter provides the results of our consider-ation of each of the recommendations for improvement identified in Appendix B.
As was requested, this response has been submitted within 30 days of the date of your letter. If there are any questions, please feel free to call.
Very truly yours, 4W [ W Murra . Edelman Vice President Nuclear Group MRE:sab Attachments i th 8506060244 050500 PDR \
0 ADOCK 05000440 PDR
Mr. C. J. P periollo !
M:y 30, 1985 PY-CEI/OIE-0052 LQ cca J. Grobe, NRC Resident '
U.S. NRC Document Control Desk INPO Records Center James G. Keppler, Region III M. Phillips, Region III H. W. Kohn, Ohio EPA J. W. Harris, State of Ohio R. H. Quillen, Ohio Dept. of Health D. Matthews, OIE, EPB D. Perrotti, NRR W. Weaver, FEMA, Region V
T ATTACHMENT 1 Response to Appendix A Open Items I
r on.a team el (448/85009-51; 441/85007-01)
Revision 5 of the Emergency Plan must clarify the emergency planning responsibilities and authority for maintaining overall emergency preparedness as established by the Pobruary 5, 1985 meno from the Vice President Nuclear Operations Division to Department Managers. The relationships between Technical Department and Project Services Department personnel must be clarified and strengthened. This must be completed prior to fuel load.
Anamar: To consolidate the various emergency planning areas, all emergency planning responsibilities have been reorganized into the Perry Project services Deprtment, Community Relations Section.
The reorganization formally implements the organization outlined in the Pobruary 5, 1985 meno.
The former Emergency Planning Coordinator is now the Emergency Planning Unit Supervisor and reports to the community Relations General Supervising Engineer. The Emergency Planning Unit supervisor in turn directly supervises an "offsite coordinator" and "onsite coordinator",
each of whom is assigned to the Emergency Planning Unit. All public information activities related to the PNPP Emergency Preparedness Program are p rformed by the Perry Media Relations Unit. The Perry Media Relations Unit reports to the community Relations Section General Supervising Eng;,neer, thus ensuring close coordination with the Emergency Planning Unit.
The "onsite coordinator" maintains a direct working relationship with the Perry Plant Technical and operations Departments (PPTD/PPOD).
The "onsite coordinator" interfaces directly with the PPTD and PPOD managers to ensure the effective implementation of the PNPP Emergency Plan and Implementing Instructions.
The PNPP Emergency Plan will be revised prior to fuel load to outline the Emergency Planning Unit suprvisor's responsibilities and authority for maintaining the overall emergency preparedness program. In addition, Revision 5 to the PNPP Emergency Plan will define the reorganization and clarify the interfaces with other PNPP departments.
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onan Iram 42 (448/85009-02; 441/85087-92)
Conduct an augmentation drill of the emergency organization to demonstrate the 30- and 68-minute goals for staffing the emergency response facilities. This must be completed prior to fuel load.
Annwar: Prior to fuel load, one of the monthly periodic tests of the Emergency Pager System will be used to verify the response times for all key emergency response positions. As a part of this test, the paged individuals will provide an estimate of their response time from their present location to the Perry Nuclear Power Plant. An individual for each key emergency response position must be contacted and provide adequate response times for the test to be judged acceptable.
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open Itam 83 (440/85009-83; 441/85987-93)
The Security Coordinator and Security Personnel (First Aid / Search and Rescue) must complete emergency response train-ing in all required training modules prior to fuel load.
Anawar: The Emergency Plan training modules are being revised to reflect changes which have occurred in the Emergency Plan and Implementing Instructions over the past year. Individuals designated to fill the Security coordinator position will attend the training outlined in Table 8-1 of the PNPP Emergency Plan during the upcoming 1985 training cycle. Security personnel, who are designated First Aid / Search and Rescue responders as part of their job performance requirements, will receive their annual Emergency Plan training during the normal shift training cycle.
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onan Itam 44 (448/85809-04; 441/85007-04)
Complete the TSC by demonstrating operability of the HVAC system, 489V UPS system, ERIS, and TSC radiation monitoring system prior to fuel load.
Anamar The " test description" is being developed for the Technical Supprt Center's HVAC, 488V UPS, and radiation monitoring systems. Testing of these T8C systems will be completed prior to fuel load.
The Safety Parameter Display System (SPDS) functions of the PNPP's Emergency Response Information system will be completed prior to fuel load.
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open Itan 85 (448/85009-05; 441/85007-85)
Complete the installation, test and acceptance of the EOF ventilation system including the HVAC system and the EOF radiation mon:,toring systeep and provide the specified thermoluminescent dosimeters (TLDs) to the EOF prior to fuel load.
AnaMRI: The installation of the Emergency Operations Facility's radiation monitoring and ventilation systems, including the BVAC portion, is complete.
The " test description' outlining the test program of these systems is being developed. Testing of the EOF ventilation and radiation monitoring systems will be completed prior to fuel load.
TLDs for the EOF, as outlined in OM15B: EPI-C2 (Maintenance and Inventory of Emergency Equipment), are ordered to meet emergency planning requirements. The TLDs will be stocked and inventoried at the EOF prior to fuel load.
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open Itan 86 (440/85009-86; 441/85087-06)
Emergency kits and supplies must be stocked and installed at the following locations prior to fuel loads offsite assembly areas (first aid, radiation survey instruments, personnel decontamination supplies, etc.); access control facility (ambulance support kit); decontamination room, and dosimetry kits for offsite organizationa.
Anawart The offsite assembly area equipment specified in GM15B: EPI-C2 (Maintenance and Inventory of Emergency Equipment) have been placed and inventoried in their designated locations at the CEI Ashtabula Service Center and CEI Eastlake Plant. In addition, a first aid kit will be added to the inventory and placed at each of the offaite ass 9mbly areer prior to fuel load.
Two (2) ambulance support kits and one (1) offsite organization dosimetry kit will be placed and inventoried in the Primary Access Control Point prio: to fuel load.
The docontaminstion room, located adjacent to the Operations Support Cent:or uts the 599' level of the Control Complex Buf.1 ding, vill be stocked and inventoried in accordance with OM15B: EPI-C2 prior to fuel load.
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onan Itan 97 (440/85809-07; 441/85087-87)
Complete the stocking and operability of the medical treatment first aid facility prior to the elimination of the construction contractor's first aid facility.
Anavar: The First Aid Room, located adjacent to the Operations support Center on the 599' level of the Control Complex Building, will be fully equipped in accordance with OM15B: EPI-C2 (Maintenance and Inventory of Emergency Equipment) and operable prior to the elimination of the contractor first aid facility.
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onen Item 68 (448/85809-88; 441/85987-98)
-Provide extremity dosimetry for the OSC and hospital kits prior to fuel-load.
Answers Prior to fuel load, extremity dosimetry will be obtained for and placed in the emergency kits maintained in the OSC and at Lake County Memorial Hospital (East).
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onen Item #9 ( (448/85989-99; 441/85987-99)
-Complete the installation of readouts for the Containment High Range Radiation Monitor in the Control Room prior to fuel load.
Answer: The installation of the readouts in the Unit one Control Room for the (D19) Containment High Range Monitors has been scheduled and will be completed prior to fuel load.
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I Open Item #18 (448/85889-18; 441/85987-18) '
. Meterological data.(wind speed, wind direction, stability) must ,
be available in the control Room prior to fuel load.
AnaMSI: . Currently, the data transfer cables'and modems.
are installed from the onsite meteorological tower to the Unit one Control Room. The termination of the cables at the Control Room printers and the set-up of the system modems has been scheduled for completion prior to' fuel load.
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open Item ell (448/85809-11; 441/85087-11) 1 The methodology and responsibility for acquisition of National
. Weather Service forecast information and integration of this information into protective action recommendations and dose assessment must be incorporated into the EPIs. This must be completed prior to fuel load.
Ansvar: OM15B: EPI-B7b (Manual Offsite Dose
-Calculations), section 5.3 has been revised to require the Radiation Protection Assistant, or alternate, to contact the National Weather Service (NWS) using the PNPP Emergency Response Telephone Directory to obtain forecast meteorological data. In addition, the user is now directed to periodically contact the NWS while performing dose assessments to verify potential changes in meteorological conditions.
OM15B: . EPI-B8 (Protective Actions and Guides) does not discuss obtaining meteorological
, information. The user of EPI-B8 is directed to EPI-B7 to obtain meteorological data.
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Open Item #12 (448/85999-12; 441/85987-12)
The dedicated 5-way line in the Control Room, with connection to Ashtabula, Lake and Geauga Counties, the State of Ohio, and plant locations, must be installed and operational prior to fuel load.
Answer: The dedicated 5-way line (State / County Emergency Response Network) is currently in place and operational at the Unit Supervisor's console in the Unit One Control Room. Periodic testing of the dedicated 5-way line began in April 1985 and is conducted monthly on the second Tuesday of each month.
Pg. 12 of 26
O 4 open Item #13 (448/85999-13; 441/85997-13)
Complete testing of the PA paging system to assure audibility in high noise areas and complete testing of intraplant communications system prior to fuel load.
Answer: The testing _of the plant Public Address (PA)
System (R51, Communications - Intraplant) will be completed prior to fuel load. The test procedure for conducting the PA system test has been reviewed and approved. Testing will. include-audibility checks for various locations throughout Unit One. In addition, an operability check of the PA handset modules will be conducted. A tentative testing date is currently being evaluated based on work load and accessability to plant areas.
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Onen Item #14 (448/85989-14; 441/85897-14)
-Where appropriate, reference EPI-Al in the ARIs prior to fuel load.
-Answer: A temporary change is currently being amended to
, OKlB: OAP-8585'(Preparation of Off-Normal Instructions) and OMlB: OAP-8586 (Preparation of Alarm Response Instructions) to require referencing ~of OM15B: EPI-Al in the applicable ONIs and ARI. '
Interfacing with Emergency Plan Implementing Instructions (EPIs) in the ONIs and ARIs shall be accomplished as follows:
- 1. When the event (ONI)/ annunciator (ARI) by itself is indicative of an emergency condition, use the statement, " Declare an (event condition) event and'take the required action per EPI-Al."
- 2. When the event and other conditions are required to meet an emergency condition, use the statement, " Determine if an emergency action level has been exceeded per EPI-Al, Attachment 1 as follows:
, (CATEGORY) (ACTION LEVEL)"
l Existing ONIs and ARIs are currently being revised, where appropriate, using the above guidelines. The applicable. EPI-Al references i
will be completed in the appropriate ARIs and ONIs prior to fuel load.
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- open Item #15 (449/85999-15; 441/85987-15) 1 Modify EPI-Al, page 7, paragraph G under Unusual Event to read, l
" Loss of offsite power or loss of onsite...". l This must be completed prior to fuel load. H Answers- OM15B: EPI-Al (Emergency Action Levels) is currently being revised to correct the i typographical error on Attachment 1, Emergency Classification Flowchart (p. 7). The EPI text on page 38_ currently reflects the proper wording in accordance with NUREG-9654, Appendix 1.
-k pg. 15 of 26
Ooen Item #16.(448/85989-16; 441/85987-16)
Modify EPI-Al prior to fuel load to clearly indicate that an Alert EAL would exist any time primary coolant activity exceeded 399 uCi/cc equivalent I-131.
Answer: OM15B: EPI-Al (Emergency Action Levels) and Section 4.9 of the PNPP Emergency Plan are
. currently being revised to indicate an Alert for a " Severe loss of fuel cladding" condition in accordance with Appendix 1 of NUREG-9654.
As revised, the following indication alone will result in an Alert classification:
QE High reactor water activity as indica-ted by confirmed sample results of 308 uCi/cc or greater dose equivalent I-131."
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Open Item #17 (448/05389-17; 441/85987-17)
Upon completion of.the appropriate startup tests, and prior to fuel load, verify that the temporary modification to recorders H13-P681, B21-R623-A & B is removed and that these recorders t provide reactor level and pressure indication.
Answer: Instruments IB21-R623 A and B on 1H13-P681 have been reinstalled to provide the appropriate reactor level and reactor pressure indication as per OM15B: EPI-Al (Emergency Action Levels).
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Open Item 418 (449/85809-18; 441/85807-18)
Revise the Emergency Plan to include NRC Headquarters as a responding agency and specify that the NRC Headquarters Operations Center must be notified in the event of any emergency class declaration immediately after notification of offsite officials and not later than one hour. This must be completed prior to fuel load.
Answer: Prior to fuel load, the PNPP Emergency Plan will be revised to indicate the NRC Headquarters as a responding agency. The revision will also delete the NRC, NRR, Emergency Incident Response Center, Bethesda, Maryland and direct the notification of the NRC Headquarters Operation .7 enter immediately upon completion of the notifications to the State of Ohio and local counties but within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the initial declaration or reclassification of an emergency. OM15B: EPI-B1, (Emergency Notification System) has been revised to include this time limitation for the notification of the NRC Headquarters Operation Center.
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l Open Item 819 (449/85999-19f 441/85997-19)
Revise EPI-B1 prior to fuel load to_ provide an adequate means for verification of notification messages.
Answer EPI-B1 (Emergency Notification System) has been revised to list the verification telephone-numbers for the Control Room, TSC and EOF on the initial and follow-up notification forms (Attachments 2 and 3). A PNPP Private Branch Exchange (PBX) extension and a CEI Off-Premise Exchange (OPX) extension are listed for each onsite facility.
Pg. 19 of 26
l onen Item #28 (449/85989-28; 441/85987-29)
Conduct an assembly / accountability drill prior to fuel load to demonstrate the capability to account for all onsite personnel within 38 minutes.
Answer Prior to fuel load, a full scale accountability drill-will be conducted in accordance with OM15B:
EPI-B5 (Personnel Accountability) and OM15B:
EPI-B6-(Evacuation). The drill will encompass all personnel, unless otherwise identified in advance, within the Unit One Protected Area fence and within the Unit Two Construction Area fence.
The drill is tentatively scheduled to be conducted between the hours of 6:99 p.m. to 6:98 a.m. Normal access / exit procedures which would be in-place at fuel load will be used to account for personnel leaving the designated drill areas.
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Open-Item 021 (449/85999-21; 441/85997-21)
Revise the Administrative Procedures prior to fuel load to clarify that the review of the Emergency Plan and EPIs must be conducted annually.
Answer: -OM1A: PAP-8507 (Preparation, Review, Approval, Revision, an'd Cancellation of Instructions) has been revised to require the annual review of the Emergency Plan and Implementing Instructions as part of the periodic review cycle.
An annual review of the Emergency Preparedness Program will also be conducted. See response to Open Item #22. .
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Open Item #22 (448/85989-22; 441/85987-22)
Appendix.E, " Emergency Planning," to the PNPP Quality Assurance Plan must be issued, and it must be compatible with the requirements of 18 CFR 58.54 (t). This must be completed prior to fuel load.
Answer: Appendix E to the PNPP Quality Assurance Plan has been issued, effective March 7, 1985. Appendix E-i does not specify the requirements of the 18 CFR 59.54 (t). 'Instead, the PNPP Emergency Plan will be revised to specify the requirements of the annual-independent audit and to outline the selection of the auditor and the review process.
This will result in the Emergency Plan becoming the controlling document for.the performance of the 18 CFR 59.54(t) audit.
Section 8.2 (Review and Updating of the Emergency Plan and Implementing Instructions) of the Emergency Plan presently identifies the Nuclear Safety Review Committee as solely responsible for i conducting the. annual ~ audit required by 18 CFR 59.54(t). Section 8.2 of the Emergency Plan will i be revised as follows:
1 "8.2 REVIEW AND UPDATING OP THE EMERGENCY PLAN AND IMPLEMENTING INSTRUCTIONS The PNPP Emergency Plan and Implementing Instructions are included in the PNPP Operations Manual. .As such, the Emergency Plan and Implementing Instructions are reviewed and approved by the Plant Operations Review Committee and controlled, distributed, and revised in accordance with PNPP Administrative Procedures. Document holders will l receive revisions to the Emergency Plan and Implementing i Instructions in a controlled manner as they are issued. j In addition,-guidance will be provided to document holders on how-to make comments and recommendations concerning the Emergency Planning Program to CEI.
1 i The PNPP Emergency Plan, including appended letters of-l agreement and Emergency Action Levels will be reviewed and agreed upon by State and local officials, and will be reviewed at least annually thereaft'er. The results of the review with offsite agencies are reported to the Vice-l President, Nuclear Group, and the NSRC by the Emergency Planning Unit Supervisor.
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An. annual review of the Emergency Preparedness Program in accordance with 18 CFR 55.54(t) will be conducted ~by an independent group selected by the Emergency Planning Unit Supervisor. The review will be conducted by a group that has no direct responsibility for implementation of the Emergency Preparedness Program for PNPP. The review-will ;
include an evaluation of the. Emergency Plan and Emergency Plan Implementing Instructions, drills and exercises,
, response capabilities, and the adequacy of interfaces with State and County officials. This review will verify compliance with CEI Corporate. Policy, CEI Quality Assurance Program, Federal Regulations and operating license provisions. At the completion of the review, the
- group will prepare a written report including
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recommendations for improvements and will provide this report to the Nuclear Safety Review Committee (NSRC) and the Emergency Planning Supervisor. Those portions of the report involving the interface with State and local governments will be made available to the appropriate State and local governments. The Emergency Planning Unit Supervisor is responsible for resolution of all recommendations, and will then report to the NSRC on the i
disposition of the recommendations.
The NSRC will, on an annual basis, review the results of the independent review, any regulatory agency Emergency Preparedness Inepection Reports, any Quality Assurance i Audits of Emergency Preparedness, and any other reviews of the Emergency Preparedness Program and report to the Vice-President, Nuclear Group, on the overall adequacy of the PNPP Emergency Preparedness ~ Program.
I Documentation of the above reviews and resolutions will be retained for at least five (5) years'.
pg. 23 of 26
Open Item #23 (448/85899-23; 441/85987-23)
Update letters-of-agreement so that none are more than two years old at fuel load. .
Answer: Currently, the PNPP is actively seeking to update the letters-of-agreement contained in the PNPP Emergency Plan. Prior to fuel load, the PNPP Emergency Plan will be revised such that the Appendix B, " Letters-of-Agreement", will have been updated to ensure that no agreement is older than two years, i
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Open Item #24 (449/85999-24; 441/85007-24)
Complete the distribution of public emergency information hand-books and other informational material prior to fuel load.
Answer: The distribution of the public emergency-information handbooks is scheduled-for June 1985.
The handbooks are being printed and will be available to meet.this schedule.
Public emergency information advertisements for the telephone directories encompassing the 19 mile EPZ have been placed. The ads will-appear in the upcoming annual revision of the telephone directories. .
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Ooen Item #25 (449/85999-25; 441/85997-25)
The operability of the entire siren system must be demonstrated prior to fuel load.
Anawar A full scale test of the siren system within the 18 mile EPz is scheduled for June 12, 1985.
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- . J ATTACHMENT 2 Response to Appendix B Improvement Items
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l rmprovament Item fl The plan should be revised as follows: describe in Section 8.9 the managerial overview responsibility of the Technical Superintendent; describe in Section 8.8 that the EPC has, in addition to the responsibilities delineated in Section 8.1.1 (1) to (8), the responsibility for overall coordination with offsite support groups and agencies.
Answer: As outlined in response to Open Item #1 (448/85989-81; 441/85997-91), the PNPP emergency preparedness program has been reorganized; therefore, the Technical Superintendent will no longer function in the manner previously stated. The PNPP Emergency Plan will be revised to reflect the overview responsibilities being assumed by the Community Relations General Supervising Engineer.
Revision 5 to the PNPP Emergency Plan will also outline-the Emergency Planning Unit Supervisor's responsibility for the overall coordination of the PNPP with offsite agencies and support groups.
pg. 1 of 23
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1 Improvament Item 42 All individuals with. assigned responsibilities in the emergency. planning effort should be delegated commensurate authority to implement these functions.
Answers- See response to Improvement Item 86 Improvement Item 95 Specific selection and qualification criteria should be developed and implemented for individuals performing emergency preparedness development activities.
Answers - See response to Improvement Item 96 Tenrovament Item 46 A professional training program for emergency planners should be established and implemented. This program should be described in Section 8.8 of the Plan.
Anawar: As a part of reorganization of emergency preparedness personnel and the formation of an Emergency Planning Unit, the following areas are currently being evaluated:
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- 1 An Emergency Planning Specialist position i
which would include seseral levels of advancement. This approach would allow personnel to be assigned according to experience level ar.d would also allow the development of a specific job improvement
- program.
- 2. Personnel developnent and training require-ments based on internal job performance and professional training courses available in the emergency preparedness field.
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- 3. Assignment of job hierarchy based on assigned responsibilities. The assignment of authority will be based on the Emergency Planning Unit structure being developed and the responsibilities delineated in the PNPP Emergency Plan.
This will not be reflected in the Emergency Plan.
pg. 2 of 23 e ~ a-- --.--ne- e,-w a,,,e - n o. --,---s,e- _m,.e r-r wm,en-ww, as , e,. , - , - ,,,w-,en , , ., _ . . - -,-,.eno w e-wwwe-,-e,-ene-~e -.-,ee nr ,.,m,w-.
Tmprovement Item 63 i Explicit authority should be given to the EPC for the over-all emergency preparedness coordinating effort.
- Anaver
- The Emergency Planning Unit Supervisor is responsible for coordinating the overall emergency preparedness effort. Section 8.1 (Organizational Preparedness) of the PNPP.
Emergency Plan will be revised to delineate this responsibility.
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- . ranrov== ant item to The EPC should report to the plant manager or equivalent.
4 Answer The Emergency Planning Unit Supervisor reports
. directly to the Community Relations General Supervising Engineer; however, the Emergency
- Planning Unit Supervisor has the autonomy to go
. directly to the Perry Plant Managers or the Vice President, Nuclear Operations Division if conditions warrant.
Interfacing with and obtaining approval from senior PNPP management personnel has not been.
- demonstrated as a problem in the past.
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, improvement Item 67 The Information Liaison should be added to the TSC position.
of Figure 5.3 of the. Emergency Plan since this position must be filled during an Alert.
- Anaver: Section 5.2.2.3 ~(Technical Support Center) of J- the PNPP. Emergency Plan will be revised to 1 discuss the Information Liaison's function in the TSC prior to the activation of the Emergency Operations Facility. This will also be indicated on Figure 5-3 of the Emergency Plan.
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1 Imnrovement Item 88 l
All references in the General Emergency (sic) Training (GET) ;
module to " Site Emergency" should be-changed to " Site Area Emergency".
Answer: See response to Improvement Item 49 Tanrovement Item 69 The GET module referencing a fire lasting 15 minutes as an Unusual Event should be changed to specify a fire lasting for 19 minutes as identified in the EALs.
I Answer: The General Employee Training (GET) module i covering emergency planning is currently scheduled for review in 1985. The noted
, discrepancies will be corrected in the next GET
- revision. In the interim, these two items are being addressed by the GET instructors at each session.
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w Improvement Item #19 Toavoid'hpoordoseprojection,andthereforeanincorrect I
protectivocaction recommendation, the MIDAH-boftware should be revised.to allow time share computation'of diverse dose projection" problems-originating from any of the Emergency Response Facilities. .
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AnzugIt Dose-assessment pers'onnel will be trained l during ths upcoming.annu'al emergency plan training cycle on the limitations of the current MIDAS. software package and precautions
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to bs use4'when accessing MIDAS'from multiple s
terminals.
The option to modify the MIDAS software package i to allow ind'ependent dose projections from I
multiplo, terminals is currently being l evaluated. A decision will be made at a later date based on user-worths' ^"~ software and hardware limitations, and cost. t 1
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1 Imnrovement' Item $11 Procedures for obtaining and using backup meteorological data should be clarified and simplified.
Answers EPI-B7b (Manual Offsite Dose Calculations) has been revised to address Open Item #11 (449/85809-11; 441/85987-11) concerning the acquisition and use of National Weather Service data. EPI-B7b will be reviewed during the next annual review cycle in an attempt to further simplify and clarify the acquisition and use of backup meteorological data.
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- . l Improvement Item 412 l
Procedures should be established to ensure PNPP will be }
included in the notification of severe weather through the !
utility's Systems Operation Center. j 1
1 AnaMars A notification of severe weather is received !
from the CEI Systems Operation Center (SOC) as ;
a matter of practicer no formal procedure needs !
to exist. l P9 9 of 23
Tmnrovament Item #13 PAP-9581 and PAP-9191 should be revised to conform to the present plant organization.
Answer: OM1A: PAP-9191 (Perry Plant Department Organization) was revised effective 3/22/85 to reflect the present Perry Plant Technical and Operations Department organization. PAP-9191 is being revised to reflect the formation of tne Emergency Planning Unit in the Perry Project Services Department.
OM1A: PAP-9581'(PNPP Operations Manual) is currently being revised to reflect the present
. plant organization.
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Taprovament Item #14 A method'of resolving errors introduced during the procedure printing cycle should be developed.
Answer: An Administrative Unit Instructiori (OM2: AUI) is currently being developed that will require procedures to be.page and quality checked prior to distribution.
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Improvement Item #15
. During the augmentation of emergency personnel, key persons paged might not have enough information to determine how many persons. represent an adequate number; therefore, minimum manning should be'specified for positions such as communicators, log keepers, etc.-
Answer: . Currently, OM15B: EPI-A6 (Technical Support Center Activation) and OM15B: EPI-A8 (Emergency Operations Facility Activation)
.specify a recommended minimum staffing of .
communicators and support staff personnel. The responsibility for the support staff and communicator positions is assigned directly to the TSC Administrative-Assistant and the EOF Manager. In addition, during an emergency the shift I &-C technician is designated as the 4
Control Room Communicator to assist the Shift Supervisor in conducting the required notifications.
The augmentation of health physics and
~c hemistry personnel, and maintenance, 1
electrical and I & C supervision are also outlined in EPI-A6 and OM15B:
EPI-A7 (Operations Support Center Activation) for g specific emergency classifications.
Key personnel will be trained in facility manning requirements and recommendations during i the upcoming annual emergency plan training
. cycle.
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Improvement Item #H EPI-B1, Attachment 1 should be revised to " direct" emergency personnel to report to their stations.
Answer: OM15B: EPI-B1, Attachment 1 (Pager Message Format) currently directs the activation of specific emergency response facilities. Key personnel who are trained to respond for their facility are currently the only personnel utilizing the emergency pager system.
H2 Problems in personnel response have been demonstrated during the previous evaluated and practice exercises with the wording currently used in Attachment 1.
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Innrovement Item 417
- Two operators and at least one HP and one chem tech'should be added to the recall list to augment the shift personnel available to the Shift. Supervisor during an emergency.
Answers Currently, OM15B: EPI-A6 (Technical Support Center Activation) directs the augmentation of health physics personnel upon activation of the TSC, and additional health physics and chemistry'aupport upon activation of the EOF.
No additional operator support is specified in the Implementing Instructions; however, the Shift Supervisors have been trained to contact additional personnel if required, or to activate and utilize the Operations Support Center.- )
i It should be noted that normal and abnormal unscheduled evolutions and operations, not listed as classifiable emergencies, occur throughout a plant's operating life. The plant's operating staff is therefore proficient in personnel augmentation.
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i Taprovament Item #18 The emergency plan and procedures should be revised to indicate that the Emergency Coordinator has the authority to initiate a Site Area Evacuation prior.to the declaration of a site Area Emergency.
Anawart Section 6.4.1 (Onsite Protective Actions) of the PNPP Emergency Plan will be revised to direct site personnel to begin personnel accountability in the event of a site Area or General Emergency, or at the discretion of the Emergency Coordinator based on an assessment of plant conditions.
OM15B: EPI-B5 (Personnel Accountability) and OM15B: EPI-B6-(Evacuation) will be revised during their next annual review to specifically allow the Emergency Coordinator to initiate a Site Area Evacuation at his/her discretion prior to the declaration of a Site Area Emergency.
pg. 15 of 23
Improvement Item #19 Procedures EPI-A6,. EPI-A7 and EPI-A9 should be reviewed for consistency and continuity relative to the functions and responsibilities of the Maintenance Coordinator, the OSC Coordinator,.the Reentry Team Coordinator and the Operations Manager.
Answer:' The position of Reentry Team Coordinator (RETC) is the General Supervisor (GS) or General Supervising Engineer (GSE) who, in the judgement of.the Operations Manager, is responsible for the area being re-entered. The arrangement thus allows the normal emergency organization to be utilized for re-entry. The Perry Plant GS(s) and GSE(s) are normally assigned key TSC positions, and the OSC is available to supply re-entry team personnel.
The GS or GSE is given the title of Reentry Team Coordinator'to specify his responsibilities. The RETC shal'1 utilize the Maintenance Coordinator and the OSC Coordinator in their stated-roles to accomplish the re-entry objectives.
OM15B: EPI-A9 (Re-entry) will be reviewed and revised as part of the annual review cycle in
, an attempt to clarify between re-entry and
, emergency operations.
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4 Improvement Item 420 Additional. references to the EPIO Manual should be incorporated into the Emergency Plan.
Answer: The PNPP Emergency Plan will be revised to include references to the Emergency Public Information Organization-Implementing Instructions Manual in Section 5.8 (Organizational Control of Emergencies) and Appendix E (List of Supporting Plans).
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IMPROVEMENT ITEM #21 19CFR 59.54 (t) should be referenced in the QA plan, Appendix E, aus the regulatory basis for conducting the annual audit. ]
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t ANSWER: The PNPP Emergency Plan will be revised to serve as the controlling document for the performance of the 19 CFR 59.54 (t) audit.
Refer to Open Item #22 (448/85999-22; i 441/85997-22) for a detailed description of the .l proposed emergency plan revision.
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Improvament Item #22 Section 8.2 of the Emergency Plan should be revised to ensure it adequately describes the scope of the annual audit.
Answer: Section 8.2 (Review and Updating of the Emergency Plan and Implementing Instructions) of the PNPP Emergency Plan will be revised to clarify the scope and content of the annual review. See response to Open Item #22.
pg. 19 of 23
- - m Taprov== nt Item 423 The hospital procedure for handling contaminated patients should be integrated or appended to the EPIs.
Answer: The hospital procedures as written do not control the actions of the plant's health physics personnel; these procedures provide guidance to hospital personnel on the handling,_
movement and treatment of a contaminated-injured individual. OM15B:
EPI-B4 (First Aid and Medical Care) provides the health physics actions onsite and requires the collection of PNPP dosimetry and the monitoring for contamination at the hospital.
Health Physics personnel are trained annually 1
in general hospital procedures and interfacing with hospital personnel.
Since the hospital procedures are written to outline hospital actions only, these procedures will_not be included in the PNPP Implementing Instructions at this time; however, PNPP health
- physics personnel will continue to be trained annually
- in the aspects of interfacing with hospital personnel.
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4 Tanrovament Item 424 The Lake County Memorial Hospital - East should be provided with a copy of the applicant's Emergency Plan and appropriate EPIs dealing with contaminated-injured. personnel.
Anawar A controlled copy of the PNPP Emergency Plan has been provided to the Lake County Memorial Hospital Administrator.
An additional controlled copy of the Emergency Plan and OM15B: EPI-B4 (First Aid and Medical Care) will be provided to Lake County Memorial Hospital-East for use as a reference in the Emergency Room, Radiation Emergency Area (REA).
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l Imnrovement Item 425 A procedure for maintenance and testing of the siren system should be established and implemented.
Answer: See response to Improvement Item #26 Imnrovement Item #26 A test frequency for the siren system which conforms to the frequencies and methods recommended in NUREG-9654, Appendix 3 should be implemented. A description of the tests and frequencies should be included in the Emergency Plan.
Answer: Instruction, NDASI-9951: Prompt Alert System, is being developed to outline the test frequencies and methods to be used for the maintenance and testing of the siren system.
NDASI-9951 meets the test frequencies specified in NUREG-9654, Appendix 3 (Section C.3.h).
Section 7.2.5 (Prompt Alerting and Notification System) of the PNPP Emergency Plan will be revised to include a description of siren tests and frequencies.
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Taprovement Item 527 The fine print on the EPI-Al flow chart shocid be enlarged.
Answers -The two pages of the EPI-Al flowchart were each purposely reproduced on 8.1/2" x 11" sheets of
< paper to allow simultaneous viewing of both sheets by the user. This format was preferred by the instruction users during the previous i training period and emergency preparedness practice exercises. PNPP does not therefore plan to enlarge the flowchart; however, the improvement item will be re-evaluated during the next annual review.
pg. 23 of 23