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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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-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-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-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-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-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-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 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-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-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-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-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 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 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 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) 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-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] |
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P O. BOX 5000 - CLEVELAND. oHlo 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLDG. - 55 PUBLIC SOUARE Serving The Best Location in the Nation MURRAY R. EDELMAN vicE PRESIDENT June 18, 1985 NUCLE A R PY-CEI/01E-0065 L Mr. Martin C. Schumacher, Chief Independent Measurements and Environmental Protection Section U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL. 60137 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Close out of NRC Open Item 50-440/85008-03; 441/85006-03
Dear Mr. Schumacher,
This letter is to acknowledge receipt of Inspection Report 50-440/85008; 50-441/85006 attached to your letter of February 28, 1985. This report identifies areas examined by Dr. M. J. Oestmann during the inspection conducted on February 5, 1985 through February 8, 1985 at the Perry Nuclear Power Plant.
Attached to this letter is information provided to close Open Item 50-440/85008-03; 441/85006-03 on Confirmatory Measure-ments, as requested in the inspection report.
If there are any questions, please feel free to call.
Very truly o es, Murray R. Edel an Vice President Nuclear Group g MRE:nje i l
Attachments ec: J. Grobe Dr. M. J. Oestmann U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 8506270249 850618 JUN 201985 PDR ADOCK 05000440 G PDR
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INSTRUCTIONS FOR ANALYSES OF TEST SAMPLES Radiological and Environmental Sciences Laboratory 550 Second Street Idaho Falls, Idaho 83401
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Count all samples for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or unt.11 20,000 counts have been recorded.
Calculate the resuits and uncertainties in pCi/mL for liquid samples and PC1/ total sample for particulate filters.
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Report of Office theInspection results to the andU.Enforcement, S. Nuclear Regulatgry Commispion, Attn: /f/4Wt/ EIA16Reg @4
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Perform the analyses checked below.
I. Liquid Sample
.j 1. Determine the gamma eritters in /O mL of sample.
- 2. Determine the strontium-89 and strontium-90 content by analyzing
//) mL of sample.
- 3. Determinethetritiumcontentbygistilling '2-O mL and l analyzing a ,/h mL portion -f8 the distillate.
- 4. Correct the results for decay to / // k( .
l II. Liquid Sample f,
- 1. Determine the gross beta activity on mL of the sample.
Report the result as of the date of counting.
III. Particulate Filter
- 1. Quantitatively recover the contents of the bottle containing the filter and determine the strontium-89 and strontium-90 activities in the entire sample.
- 2. Correct the results for decay to .
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FISSILE MATERIALS: No[A'phcable p I Fissile Shipment O Fissile Exempt O qO Fissile Materials U - gms Pu gms Other Fissile Exempt O Class i0 Crass <>O Trans inoe-Class ill O Coni,ois.
(No more than packages may be loaded on any v hicle or storage location)
ACCOUNTABLE NUCLEAR MATERIALS: Not Apphcable Applicable O DOEINRC F 741 No Remarks b
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- GAMMA SPECTRUM ANALYS I S CANBERRA SPECTRAN-F V2.07 SOFTWARE 25-MAY-8507:34105
[ ANALYS I S PARAMETERS MCA UNIT NUMBER: 1 / ADC UNIT NUMBER: 1.0
( DETECTOR NUMBER: 1 / GEOMETRY NUMBER: 10 SPECTRUM SIZE: 4096 CHANNELS ORDER OF SMOOTHING FUNCTION: 5 r NUMBER OF BACKGROUND CHANNELS: 3 ON EACH SIDE OF PEAK PEAK CONFIDENCE FACTOR: 95.0%
IDENTIFICATION ENERGY WINDOW: +- 2.00 KEV ERROR UUOTATION: 2.00 SIGMA UNCERTAINTY MULTIPLET ANALYSIS NOT PERFORMED REGULAR OUTPUT Sf'EC1RAL DATA READ DIRECTLY FROM MULTICHANNEL ANALYZER ANO:
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ANALYZED BY: GAD SAMPLE DESCRIPTION: CONFIRMATORY MEASURE
. GEOMETRY DESCRIPTION: 14.4 ml Liouid Off-Gas Vial SAMPLE SIZE 1.0000E+01 ml / CONVERSION FACTOR: 1.0000E+00 STANDARD SIZE: 1.4400E+01 ml ANALYSIS LIBRARY FILE: ANLOO9 COLLECT STARTED ON 7-MAY-85 AT 17:40:00 COLLECT LIVE TIME: 43200. SECONDS REAL TIME: 43268. SECONDS
( DEAD TIME: 0.16 %
DECAYED TO 116. DAYS, 5.6667 HOURS BEFORE THE START OF COLLECT i
ENERGY CALIBRATION PERFORMED 11-MAR-85 EFFICIENCY CALIBRATION PERFORMED 24-MAY-85
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,, 25-MAY-8507:34805 PEAK ANALYSI S PK CENTROID ENERGY FWHM BACKGND NET AREA ERROR NUCLIDES CHANNEL KEV KEV COUNTS COUNTS %
1 1321.45 661.76 16 75. 654. 9.0 CS-137 2 2344.75 1173.24 2.0 42. 436. 11.0 CO-60,CO-56 3 2663.57 1332.54 2.0 25. 431. 10.6 CD-60 ERROR QUOTATION AT 2.00 SIGMA PEAK CONFIDENCE LEVEL AT 95.0%
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23-MAY-8507:34703 SAMPLE: CONFIRMATORY MEASURE DATA COLLECTED ON 7-MAY-85 AT 17:40:00 DECAYED TO 116. DAYS, 5.6667 HOURS BEFORE THE START OF COLLECT.
RADIONUCLIDE ANALYSIS REPORT NUCLIDE ACTIVITY CONCENTRATION IN uCi/ml DECAY MEASURED ERROR CORRECTED ERROR CO-60 1.15E-05 +-1.27E-06 1.20E-05 +-1.32E-06 CS-137 1.20E-05 +-1.08E-06 1.21E-05 +-1.09E-06 g ___________________ ___________________
TOTAL 2.35E-05 t-1.67E-06 2.41E-05 +-1.71E-06 ESAR = 1.61 MEV/ DISINTEGRATION MAXIMUM PERMISSABLE ACTIVITY = 6.20Ef01 UC/ml TOTAL MEASURED ACTIVITY = 2.41E-05 (+-1.71E-06) UC/ml
% TECH. SPEC. = 0.00 (+-0.00)
ERROR QUOTATION AT 2.00 SIGMA Io e
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.
- CANBERRA SPECTRAN-F V2.07 SOFTWARE 25-MAY-8507:46t42 ANALYS IS PARAMETERS MCA UNIT NUMBER: 2 / ADC UNIT NUMBER: 1.0 DETECTOR HUMBERt 1 / GEOMETRY NUMBER 10 SPECTRUM SIZE! 4096 CHANNELS ORDER OF SMOOTHING FUNCTION! 5 NUMBER OF BACKGROUND CHANNELS! 3 ON EACH SIDE OF PEAK PEAK CONFIDENCE FACTORt 95.0%
IDENTIFICATION ENERGY WINDOW! +- 2.00 KEV LRROR QUO 1ATIONt.2.00 SIGMA UNCERTAINTY MUL11PLET ANALYSIS NOT PERFORMED F.LGULAR UUTPUT SPECIRAL DATA READ DIRECTLY FROM MULTICHANNEL ANALYZER ANil
( ANALYZED BY! OAD SAMPLE DESCRIPTION! CONFIRMATORY MEASURE i - GEOMETRY DESCRIPTION! 14.4 ml Liouid Off-Gas Vial SAMPLE SIZEt 1.0000E+01 ml / CONVERSION FACTOR! 1.0000E+00 STANDARD SIZE! 1.4400E+01 ml ANALYSIS LIBRARY FILE! ANLOO9 COLLECT S1ARTED ON 0-MAY-85 AT 17830 00 COLLECT LIVE TIMEt 43200. SECONDS REAL TIME! 43288. SECONDS DEAD TIMEt 0.20 %
DECAYED TO 117. DAYS, 5.5000 HOURS BEFORE THE START OF COLLECT ENERGY CALIBRATION PERFORMED 11-MAR-85 EFFICIENCY CALIBRATION PERFORMED 24-MAY-85 l
. 25-MAY-8307746842 PEAK ANALYSIS PK CENTROID- ENERGY FWHM BACKGND NET AREA ERROR NUCLIDES CHANNEL KEV KEV COUNTS COUNTS %
1 182.78 92.71 1.4 396. 233. 29.2 2 1321.55 661.74 1.8 83. 825. 7.9 CS-137 3 2346.18 1173.42 2.2 33. 492. 10.0 CO-60,CD-56 4 2664.96 1332.55 2.0 15. 452. 9.9 CD-60 .
ERROR QUOTATION AT 2.00 SIGMA PEAK CONFIDENCE LEVEL AT 95.0%
to t
i
. _ _ , _ _ . _ - _ _ . - - . _ . _- . . _ , - ~ - - - . - , - - - - _ . - _ . .
+.
.'25-MAY-8507:46742 l .
SAMPLE: CONFIRMATORY MEASURE DATA COLLECTED ON B-MAY-85 AT 17:30:00 DECAYED TO 117. DAYSr 5.5000 HOURS BEFORE THE START OF COLLECT.
7 RADIONUCL IDE ANALYSIS REPORT j NUCLIDE ACTIVITY CONCENTRATION IN uCi/ml DECAY MEASURED ERROR CORRECTED ERROR
(
CO-60 1.07E-05 +-1.07E-06 1.12E-05 +-1.11E-06 CS-137 1.25E-05 +-9.84E-07 1.26E-05 +-9.91E-07
( ___________________ ___________________
TOTAL 2.32E-05 +-1.45E-06 2.37E-05 +-1.49E-06 1
EBAR = 1.56 MEV/DISINTEORATION MAXIMUM PERMISSABLE ACTIVITY = 6.40E+01 UC/mi TOTAL MEASURED ACTIVITY = 2.37E-05 (+-1.49E-06) UC/mi
% TECH. SPEC. = 0.00 (+-0.00)
/ ERROR QUOTATION AT 2.00 SIGMA 7
i s
4 o
(
(
(
- CANBERRA SPECTRAN-F V2.07 SOFTWARE 25-MAY-8507:51:39 ANALYSIS PARAHETERS MCA UNIT NUMBER: 4 / ADC UNIT NUMBER: 1.0
( DETECTOR NUMBER: 1 / GEOMETRY NUMBER: 10 SPECTRUM SIZE! 4096 CHANNELS ORDER OF SMOOTHING FUNCTION: 5 NUMBER OF BACKGROUND CHANNELS: 3 ON EACH SIDE OF PEAK PEAK CONFIDENCE FACTOR: 95.0%
IDENTIFICATION ENERGY WINDOW: +- 2.00 KEV ERROR QUOTA 110N:.2.00 SIGMA UNCERTAINTY MULTIPLET ANALYSIS NOT PERFORMED REGULAR OUTPUT SPECTRAL DATA READ DIRECTLY FROM MULTICHANNEL ANALYZER AN3 ANALYZED BY: GAD SAMPLE DESCRIPTION: CONFIRMATORY MEASURE GEOMETRY DESCRIPTION: 14.4 ml Liould Off-Gas Vial SAMPLE SIZE! 1.0000E+01 ml / CONVERSION FACTOR: 1.0000E+00 STANDARD SIZE: 1.4400E+01 ml ANALYSIS LIBRARY FILE! ANLOO9 COLLECT STARTED ON 15-MAY-85 AT 14:14:00 COLLECT LIVE TIME: 43200. SECONDS REAL TIME: 43397. SECONDS DEAD TIME: 0.45 %
DEC AYEli TO 124. DAYS, 2.2333 HOURS BEFORE THE START OF COLLECT ENERGY CALIBRATION PERFORMED 1-APR-85 EFFICIENCY CALIBRATION PERFORMED 24-MAY-85
(
., . 23-MAY-8507851:37
~
l PEAK ANALYSI S PK CENTROID ENERGY FWHM BACKGND NET AREA ERROR NUCLIDES CHANNEL KEV KEV COUNTS COUNTS %
1 471 13 238.39 1.1 335. 224. 29.1 PB-212 2 1318.76 661.39 1.6 77. 661. 9.0 CS-137 3 2343.37 1172.75 1.9 35. 476. 10.2 CO-60 4 2662.46 1332.01 2.2 20. 399. 10.8 CO-60 ERROR QUOTATION AT 2.00 SIGMA
( PEAK CONFIDENCE LEVEL AT 95.0%
f l
l I
i(
l l
l
~
~
~
25-MAY-8507851839 SAMPLE: CONFIRMATORY MEASURE DATA COLLECTED ON 15-MAY-85 AT 14:14:00 '
DECAYED TO 124. DAYS, 2.2333 HOURS BEFORE THE START OF COLLECT.
RADIONUCLIDE ANALYSIS REPORT NUCLIDE ACTIVITY CONCENTRATION IN uCi/ml I
DECAY MEASURED ERROR CORRECTED ERROR
! CO-60 1.18E-05 +-1.20E-06 1.24E-05 +-1.26E-06 CS-137 1 15E-05 +-1.03E-06 1.16E-05 +-1.04E-06
( ___________________ ___________________
l TOTAL 2.34E-05 +-1.59E-06 2.40E-05 +-1.63E-06 4
EBAR = 1 65 MEV/ DISINTEGRATION MAXIMUM PERMISSABLE ACTIVITY = 6.07E+01 UC/ml i TOTAL MEASURED ACTIVITY = 2.40E-05 (+-1.63E-06) UC/ml i
% TECH. SPEC. = 0.00 (+-0.00) j ERROI. QUOTATION AT 2.00 SIGNA 1
s I
e I
- I l
l l
OM12A : CHI-45 Page : 15 Rev. : 0 Attachment 2 Fo rm: OM12A: CHI-45-la Sheets a-c Sr-89, 90 Data Sheet Sample id en t if ica t ion b d., a 6 h,4t re 3
Sample date, time N/Jw/ D C Q iloc2 t 0
Sample volune used_for analysis (normally 200ml) lO ml A Sr-89,90 standard carrier per 2m1, 93.4 mg B (standardized value)
Sr-89,90 separation date, time Olmteles at iits t 3
Wha tma n 54 2 f 11 t e r pa pe r w igh t , (used for Sr) 40 1 mg C Sr-89,90 ppt we igh t '14.1 mg D Final Sr-89,90 ppt w igh t = D-C 39. t mg E Sr-89,90CYF=f I.16 F cpm /
Sr-89 efficiency using E, see FIGURE 2 h5 dpm C cpm /
Efficiency factor G x 0.01 0,9 s apm a cpm /
Sr-90 ef ficiency using E, see FIGllRE 3 79.'l dpm I cpm /
Ef ficiency factor I x ODI O.295 dpm J Sr-89,90 count date, time krAV)BsGriew t 2
Sr-89,90 gross counts 4 T 2. 67 counts K Sr-89.90 duration of count 60 minutes L Sr-89,90 gross cpm = {K SS 4. s epm M Background at Sr count time 2l cpm N Sr-89,90 net cpm = M-N 633.'I cpm 0
/ 21 ( 2. d g -l
, _g Sr-89 decay constant +.-M B--se-lO 4-hou r St-89
OMllA : CHI-45 Page
- 16 Rev. : U Attachment 2 (Cont.)
Fo rm: OM12A : CH I-4 5-l b Sr-89, 90 Data Sheet (Cont.)
Y '> u s t..ndard carr ter per 2m1 2b 3 mg P
(.,tandardized value)
Y-W deparat idir da te. time 2 #lAf[8 Q OQS1 t 3
Wha tt.a n $4 2 f ilte r 'pa pe r w igh t (used for yttrium) 39. T mg Q Y-90 ppt weight f/, L mg R
//, 7 mg S Final Y-90 pp{ wight = R-Q Y-90CYF=h 2.26 T Y-90 efficiency using S, see FIGURE 4 49 '
U Ef ficiency f actor U x 0.01 0.%% v Y-90 count date, time J 'ifAW[95Cdi l 57 t 4
Y-90 gross counts (e b % o counts W Y-90 duration of count (30 minutes x
' cpm Y Y-90grosscpm=f 11 0 "1 '
Background at Y count time 21 cpm Z Y-90 net cpm = Y-7 ,,
98.7 A A
Y-90 decay constant
/,80 f v a:~~
2 "ue-l Y-90
( ,
Decay time Sr-90 (t4 -t3) in minutes JNO mins B B
Decay correction for Sr-90 =' , Y-90(Bg) I.049 C C
2t%1 mins D Decay time Sr-90 (t3 -t g) in minutes D Decay correction for Sr-90 = g,,- Y-90(DD } E Decay time Sr-89 (t 2 ~t " ' F 0
Decay c.orrection for Sr-89 = Sr-89(FF) L4 , et V G e G
(
Conversion from dpm to uci '
2.22 x'10 H H
=
OM12A: CHI-45 Page . 17 Rev. . O Attachment 2 (Cont.)
Fo rm: OM12A: CHI-45-Ic Sr-89, 90 Data Sheet (Cont.)
Calculations:
Sr-90 uci/mi 0 t 0 "
^A C VxE E ^
= [ BB.T ]x[ t.uw ]x[ t LC ]xl 1.14, j
[ o.% lx[ o.in ]xl l* lxl2 2 tit ]
= 2.W L -5 =1 1
5 Sr-89 uci/mi 0 t 0 = 0 x F -1 fi x
M f x c
G AxHxg [1 H g
=
( Sh <)x( l.lb ) _ _
( 2.7 st 5) x ( 0.2s 't) x (9 94 )
( to )x(e ws )x(z.tsac) ( o.ws ) _
= 3. 2 T E -M Sr-90, Y- 1/mi 0 t 0= I*
= )x2
=
'A . ,.
0 i l
' i
.i 9 Page : 15
<t Rev. : 0 1
Attachment 2 -
' Forn: OM12A: CHI-45-la
[ Sheets a-c 4
Sr-89, 90 Data Sheet Sample identification bor < m o de ,- s ccq . a j '
12 cp t Sample date, time !I. TAN 9s' 0 Sample volume used for analysis' 10 el A j (norma:ly' 200::)
Sr-89,90 s tanda rd ca rrier per 2-/1, c/ 9 q mg B j
(standardized value) -
Sr-89,90 separation date, time < S mJv S3- ,, f r t g
Wa tman 54 2 f ilte r pa pe r we igh t , (usedfoYsr) ,
, 3 <7 t, mg C
(
') f , 79.9 mg D Sr-89,90_ ppt weight ,
., , +'J.. sa' Final Sr-89,90 ppt we igh t = D-C 3 9. 1 mg E j- Sr-89,90CYF=f _
/. 2 (,.
cpe/
F Sr-89 efficiency using E, see FIGURE 2 4,/ g- dpm G cpm /
Ef ficiency - f actor G x 0.01 . .W- 'dpm H 4
.I cpm /
I Sr-90 ef ficiency using E, see FIGURE 3 'A 9. 3 dpm I cpm /
Ef ficiency factor I x 0.01 ,
,293 dpm J
} s Sr-89,90 count date, time cl m A Y s r 12 t'I t 2
Sr-89,90 gross counts -
T2729 counts K
,e Sr-89,90 duration of count , l. gr .< minutes L r ;
~
K 5'/6 ^ cpm M Sr-89,90 gross cpm = p ,
t.
fl/
'lij'l pm N
-Background at Sr count time
.i. f 5'16 cpm 0 Sr-89,90 net, cpm = M-N A i ,
,, g ,'5.710 x-10 4 hour-1 Sr-89 Sr-89decap'tonstant- '
l, 3^1 F 2 dn.j~ '
Q 2
OMilA: CHI-45 Page . 16 Rev. : O Attachment 2 (Cont. )
Form: OM12A : CHI-45-lb Sr-89, 90 Data Sheet (Cont.)
Y-90 s tanda rd carrier per 2ml 263 mg P
(. standardized value) 2 7 m,9 P ts s' 09 >~ 7 1 3
.Y-90 . separation date, time 39 f ec Q yna te.an 54 2 f l ite r pa per we igh t (used for yttrium) 4/F,9 mg R Y-90 ppt weight
- 9. 4 mg S Final Y-90 ppt we igh t = R-Q Y-90 CYF = E 2. 9 T S
4/ C/ U Y-90 ef ficiency using S, see FIGURE 4 c/ t/ v Efficiency factor U x 0.01 t
Y-90 count date, time 23m/7 rF r 11 c i 4 5 yj g counts W Y-90 gross counts-6o minutes X Y-90. duration of count W 7 (. cpm Y I ~Y-90 gross eps = 7 17 cpm 2 Background at Y count time Y-90 net cpm = Y-Z 79 A 680E-Z~*' ' -l g 4 1-.002 a 10 ' Luut Y-90 Y-90 decay constant 2 '-/ O mins B Decay time Sr-90 (t -t 3) in minutes B
. Decay correction for Sr-90 = , Y-90(B B C 2/7.39 mins D Decay time Sr-90 (t3 -t ) in minutes
- Y-90(DD} b Decay correction for.Sr-90 = E F
Decay. time Sr-89 (t - t 0 n m a es // 7 F Decay correction for Sr-89 = Sr-89(Fy) 4 97 Gg 6 H 2.22 x 10 H Conversion from dpm to uci m.- c..- .._._ - ,,n-.__. - . . , _ .
1 OMi lA : CHI-45 Page . 17 Rev. : 0 Attachment 2 (Cont.)
Form: OM12A : CHI-45-Ic Sr-89, 90 Data Sheet (Cont.)
Calculations:
Sr-90 uci/ml O t 0 = AA xC CxTxF VxE Ex AxH
= l 79 lxl I.o# lx{ 2 c ] x [ f. 2 0 }
[ w9 ]x{ Cie jx[ (0 J x [ 2.2 2('}
=
= .? O 3 E - C 1 II C Sr-89 uci/ml O t 0 = 0 x F -
I x I '/
+
x G AxHxH H [ H d ,
= (526 )x( / ; c ) (.f e!c-O x ( . 2 9 3 )
i x ( 4 'i ? )
( wr )
( /> )x( .~s' )x(;.;2q 3 = 232F 'I Sr:90, Y-90 uc1/ml Q t 0= *
=
( )x2
!y .
j e%4d
~
PAGE: 1 USER: 1 ID:H-3 BKGD PRESET TIME: 10.00 WED 08 MAY 1985 17:37 l SAMPLE REPEAT: 2 CYCLE REPEAT: 1 SCR:N RS232:N Hr: 2 AOC:N OCF:N RCM:N 2 PHASE MONITOR:N CHANNEL I-LL: 0 UL: 1000 2 SIGMA: 2.00 DVG SUB: 0.00 BKG 2SIG: 0.00 LSR: 0 DATA CALC: CPM, UNKNOWN REPLICATES: 1 NORM FACIOR:0 1.00000 I HALF LIFE (DAYS):N SAM POS CH CPM 2SIG% TIME EL TIME AVG Hs ERR 1 **- 1 1 36.20 10.51 10.00 11.05 117.0 Hs: 116, if8 1 --- 1 1 30.90 11.38 10.00 21.97 !16.0 He: 117, 115 SAM AVG CPM (RilG) 1: 33.55< 7.90)
PAGE: !
USER: 5 ID:H-3 CONF MEA PRESET TIME: 60.00 WED 08 MAY 1985 18:07 SAMPLE REPEAT: 2 CYCLE REPEAT: 1 SCR:N RS232: N Hs: 2 AOC:N OCF:N RCM:N 2 PHASE MONITOR:H 0.00 LSR:
CHANNEL 1-LL: 0 UL:1000 2 SIGMA: 2.00 PKG SUD: 33.55 BKG 2SIG:
O SINGLE LABEL DPM, SET UP DN THU 28 OCT 1982 09:04 UNKNOWN ID:H-3 OUENCH CURVE UNKNOWN REPLICATES: 1 UNKNOWN NORM FACTOR:0 1.00000 UNKNOWN UNITS:DPM OUENCH MODE:H CALCULATE COEFF:N HALF LIFE (DAYS): 4503.530 1 C:-0.0000068 D:-0.0000000333 OUENCH COEFF.A: 4.140551 B:-0.0037587 l
STANDARD ID:SCN-231 0UENCH LIMITS LOW:7.000 HIGH:264.0 l TIME EL TIME AVG Hs ERR l SAM POS CH CPM 2SIG%
1 *-- 1 1 203646.45 1.98 0.05 0.50 61.5 He: 61. 62
%EFF: 48.23 IS01 DPH :422262.9 1 --- 1 1 201286.45 1.41 0.10 0.96 62.0 He: 63, 61
%EFF:48.11 IS01 DPM :418412.5
%RNG: 0.5 SAM AVG IS01 DPM :420337.7 2 --- 2 1 50.53 4.69 60.00 63.47 97.5 Hs: 99, 96
%EFF: 39.59 IS0! DPM :127.6434 2 --- 2 1 49.07 4.78 60.00 125.66 97.5 Hs: 98.- 97
%EFF: 39.59 IS01 DPM :123.9400 l' XRNG: 1.5 SAM AVG IS01 DPM :125.7917 3 ---~3 1 47.98 4.86 60.00 188.11 99.0 Hs: 97. 101
%EFr: 19.23 ISO' DPM :122.3104 3 --- 3 1 49.13 4.78 60.00 250.24 99.0 Hs: 99, 99
%EFF: 39.23 IS01 DPM :125.2424
%RNG:- 1.2 SAM AVG IS01 DPM :123.7764 4 **- 4 1 43.80 5.18 60.00 312.60 98.5 He: 98, 99
%EFF: 39.35 IS01 DPM :111.3098 ;
4 **- 4 1 44.72 5.11 60.00 374.66 98.0 H s: 98, 98
%EFF:39.47 IS01 DPM :113.2961
%RNG: 0.9 SAM AVG IS01 DPM :112.3030 5 --- 5 1 46.05 5.00 60.00 437.01 97.0 Hs: 97, 97
%EFF:39.71 IS01 DPM :115.9736 5 ~~- 5 1 46.80 4.95 60.00 499.07 97.5 Hs: 97, 98
%EFF:39.59 IS01 DPM :118.2189
%RNG: 1.0 SAM AVG IS01 DPM :117.0963
l l
I -- '
.,,.,..o;
-n-.--- . -n = w- m .tr>v ". : : n -
s , ,; , s;** . *
- -f' r.?. j ' '
.z e.
~
s f%m.C2 92. M ~ Q '.l ' .>; *
- c:&M __9. : r.
4.u.:z -%i-OM12A: CHI-47
( )
Page : 5 - LAST Rev. : 0
' Attachment 1 Form: OM12A: CHI-47-1 Tritium Data Sheet Sample Identification bd *<aM hio Au 44Uws?. h -p s Sample date and time n-Iw-e.vo % cc t y
Gaseous sampling initial flow rate tJ A cc/ min A Gaseous sampling final flow rate cc/ min B Gaseous sampling stop date and time t 2
Total gaseous sampling period (t 2 -t --
C AveragegaseoussampleflowrateA+b) cc/ min D 2
Gaseous sample volume (C X D) cc.E Gaseous sample rig efficiency (later) F Total gaseous sample volume (E X F) v cc G Tritium standard source count date & time 6 -m M- e s s i s v'i Tritium standard source dpm 4 to 3 51.7 dpm Tritium standard source Hi 61 Sample count date and time b-N -M G ie:io t Sample dpm t .15. 8 dpm I 3 Sample H# 97. 6
() _
Tritium decay coef ficient 1.539E - 4 days d CALCULATIONS I -
Liquid Sample, H-3 uci/mi = (1ml)(2.22E 6 dpm/uci). _ - (e $(t 3 t 1-) )
(12re )
= (1ml)(2.22E 6) (ek"*)(N (1.ons , - ))
- f. Ti f - S uci/ml H-3 I (250 ml) (t 3 -t))
Gaseous Sample, H-3 uci = (iml)(G)(2.22E 6 dpm/uci) (e 1
, ~ ,..-.:. -
. ig . - .
. t ;; .
1g ( ,; } ( 6) u
. . _ NA
.q ue m
- wg-3 .: . , ;: :4,'> , .
.'.3 r q~ . - ,
Jy
' Q g ~!.;; f{ ? :s~.l. L l %:yf.y
^ '
'3 . ,
, lgT *+ ^y .> ~.r'.
-(_ -
.s
.c. .-' ,
, ;.y , :*
'\ ,,
. d h,*[ [*"*
,- . ' *h p . "I f.'d f 1 jf 3p .
.d.k ~ t j .' g? .,
(.* .
3M9MQMWsegnME9t!N
. .m - . . . . . , . , - - -- .
g- , - .j .. ,3.; ..
,.r..- ,
., 4
- s.
~
i' ?$r9y:N:f,0bkk.w$-! i l:5 '
- x.j..
f.
.a
-=- .
. w ,. v< .
- OM12A
- CHI-47
[ Page : 5 - IAST Rev. : 0
/ Attachment 1
- Form: OM12A: ' CHI-47-1 Tritium Data Sheet Sample Identification ( _, C .', a . . N u.,-e. L b.Q.u.#.
Sample date and time n-g .cc q 4 i>co t 3
Gaseous sampling initial flow rate t) A cc/ min A Caseous sampling final flow rate ! cc/ min B Gaseous sampling stop date and time t 2
Total gaseous sampling period (t 2 -t C AveragegaseoussampleflowrateA+$) cc/ min D 2
Gaseous sample volume (C X D) cc E Gaseous sample rig ef ficiency (later) F Total gaseous sample volume (E X F) v cc G Tritium standard source count date & time 8 - M W- M CL .P -M" rF 4 Tritium standard source dpm % 2. o m .1 dpm Tritium standard source Hf 61 Sample count date and time 6-fw-es @ ae: co t Sample dpm i a v, . e dpm I 3
(, ) Sample Hf 99 Tritium decay coefficient 1.539E - 4 days" K CALCULATIONS I
Liquid Sample, H-3 uc5m1 = (Iml)(2.22E 6 dpm/uci) (e A(t 3 -
t)) 1 W.6 )
~
= (1ml)(2.22E 6) (e ( ..ce )( - ))
- 5. 6 8 E - 5' uci/ml H-3
.. . m; -
I (250 ml)
(t 4 --.. -Gaseous Sample, H-3 uci/
1ml)(G)(2.22E 6 dpm/uci) (e 3 t))-
1 3 f. . j, )( )( . .
.i!?M'O h'3j.7l6hW' '
q'. < .; f3n a.:;C;g[df%' ' -w".6- . WP.7 f.p Gid'
'l - - . .: . MJ@'.[,/
.=c Ab #, - :uc 21 E-3. . . u .Q;ad. f ~
R .?;'... 2 ; L* n.--;d ), N ~j -l- \ ,
. . _ > . t l. _o,*.. lt_* l .M MTQ'? % ~ '
h j'Ty'y&t. n.
. . l.
_.g'
- ,
- .,s %.. -
' Y ho l b ..h
-a ~ -- s: >
.~ . c.w - *
~
._3. ; - s - - < -
I !~+' ;.
y* -. I M .'; 3
- 1. , ,; ,
s ,
- .1. +,7..6, ; ,m *rg
.4.. L q-*
..t a... +.).m';.'..
s', . '.
. g q5'?
g s*=.-
..i J.(. c
.3...
1
.e. . , , , ,.. .
. . . , w , , .f . ' . ,
- 2. .
,e~ L
. c . , .f . 9
.....~;r-gr,
--4 - . - ,-
g i a
[' . '- . ,s a
.. . g .. xWsx.. ? "i'?' " P W M 'A% # 3 " ' " -W ^ &. : WW
%iQW'
1
- .'+-o. ,4 . . . . . _ . . . = .3 ,
t (.:.:t'M,7 gi$. - "-
~; .
- ,;.QD : ..: , . s.'i t,G jd. k ' ' '
- 'c -- ~.
x .n. ,..' =.e p . ;
- v. s . -
. , op : - a j
( i OM12A: CHI-47 Page : 5 - IAST Rev. : 0
/ Attachment 1 Form: 'OM12A: CHI-47-1
, J .t . -
)
1 Tritium Data Sheet l Sample Identification C.d .', . A . , Af , . w., d,'dC,2 sa-ge \
Sample date and time t, - n.3-M G o co t g
Gaseous sampling initial flow rate nA cc/ min A Gaseous sampling final flow rate cc/ min B Gaseous sampling stop date and time t 2
Total gaseous sampling period (t -t C
Average gaseous sample flow rate 2 A + E) cc/ min D 2
Gaseous sample volume (C X D) cc E Gaseous sample rig efficiency (later) F Total gaseous sample volume (E Y. F) v cc G Tritium standard source count date & time R..M Y-e.5 G>is o, Tritium standard source dpm 916 3 w 1.7 dpm
. Tritium standsrd source HP 62.
.' Sample count date and time 8 - r.i Aw - M cc .w nn t Sample dpm ii 2. 3 dpm I 3 Sample H#
() 9f.T Tritium decay coefficient 1.539E - 4 days- K CALCUIATIONS I
A(t 3 -t))
Liquid Sample, H-3 uci/ml - (Iml)(2.22E 6 dpm/uci) .(e 1
( #s2.3 ) )( - )
3
=
(Iml)(2.22E 6)
(e ( (l.ose) )
= 5. / 6 E - 5 uci/ml B-3 4
~ ' -
I (250 ml) (t
= (1ml)(G)(2.22E 6 dpm/uci) (e Gaseous Sample, H-3 uci 3 -t)) 1
~ )Q.f ' n ' }u%n~, ., . , x. . .wf ;.p y,,;;,
.?, _ , , . . ..
( ._, _
,.e . Qg;;;;,.
.g . Es g
?YW:g 4 W 9 af ; F, % j,g,.y t
.1 - g(Iml) ( ,:) .(259 mg);.,
e, m e j Q
=g.
,gJE)(,
' m.).. _
. 3 :-n n , 2E 6) JF(' 7.o' ' . -;g.
' ~4,.);:?
s~. " i.E V. i' "~
$M7 vln fhi-l'?
s , W, * ,
- ' ' !XJU .' # -dT+! 9- * ' )--AA--
t~J+l m B-3'. .*l;:N2.<dRe, ,
m.
- w. vi N:. e' $, J. >O. rk.r,a ' ', w- l/f -- - - -
- o .. .
- m. y c e . ;. t . . . .
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Page : 5 - IAST Rev. : 0 Attachment 1
Tritium Data Sheet Sample Identification C d.k L., M a 3 vee d U \ n.. 2s.-p.1 '
Sample date and time // -Iro- G r 9.9 a oc, t Gaseous sampling initial flow rate /2A cc/ min A Gaseous sampling final flow rate cc/ min B Gaseous sampling stop date and time t 2
Total gaseous sampling period (t 2 -t C AveragegaseoussampleflowrateA+d) cc/ min D 2
Gaseous sample volume (C X D) cc E Gaseous sample rig ef ficiency (later) F Total gaseous sample volume (E X F) cc G v
Tritium standard source count date & time Tritium standard source dpm w 1 o % ', i. 1 dpm Tritium standard source Hf f,1 Sample count date and time 9 - m t. Y- B r @ o .2 c o t Sample dpm // 7. / dpm 7 3
( i Sample Hf 4 7. r Tritium decay coef ficient 1.539E - 4 days %
CALCUL.ATIONS I
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=
(1ml)(2.22E 6) (e(i. cn-( 1.org t.a h-)) (in J s-
= f. 3 ') E -5 uci/ml H-3 I (250 ml)
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