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MONTHYEARML20127P0151993-01-25025 January 1993 Forwards Response to Open Items Contained in NRC SE for Amends 99 & 92 to Licenses DPR-42 & DPR-60,respectively Re single-failure-proof Crane upgrade.TN-40 Special Lifting Devices Will Be Inspected Prior to Each Use Project stage: Other 1993-01-25
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3371999-10-20020 October 1999 Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 October 1999 Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk Sys ML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20217C2351999-10-0606 October 1999 Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel ML20212J8811999-09-28028 September 1999 Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20212D8401999-09-16016 September 1999 Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116 ML20217H2331999-09-10010 September 1999 Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20212A9241999-09-0909 September 1999 Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022 ML20212B0511999-09-0909 September 1999 Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211D3541999-08-24024 August 1999 Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20211B2621999-08-17017 August 1999 Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators ML20211C7371999-08-17017 August 1999 Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective Actions ML20210T5661999-08-12012 August 1999 Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related Barriers ML20210R7021999-08-12012 August 1999 Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy ML20210P5191999-08-11011 August 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901 ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209J0941999-07-15015 July 1999 Forwards SER Finding Rev 7 to Topical Rept NSPNAD-8102, Reload Safety Evaluation Methods for Application to PI Units, Acceptable for Ref in Plant Licensing Actions ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209H8361999-07-0202 July 1999 Forwards Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) for Tests Administered During Week of 990517-21.Two Applicants Passed All Sections of Exam & Issued Reactor Operator Licenses to Operate Pings ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209F0391999-06-30030 June 1999 Forwards Insp Repts 50-282/99-04 & 50-306/99-04 on 990407-0531.Violation Noted.Notice of Violation or Civil Penalty Will Not Be Issued,Based on NRC Listed Decision to Exercise Discretion ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20196D5501999-06-18018 June 1999 Forwards Individual Exam Results for Licensee Applicants Who Took May 1999 Initial License Exam.In Accordance with 10CFR2.790,info Considered, Proprietary. Without Encls ML20196A6741999-06-17017 June 1999 Refers to 990517-20 Meeting with Util in Welch,Minnesota Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20195G4281999-06-0909 June 1999 Notifies That Amsac/Dss Mods Completed & TS 138/129 Has Been Fully Implemented 05000282/LER-1999-005, Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved1999-06-0707 June 1999 Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved ML20207F4301999-06-0101 June 1999 Forwards 1999 Unit 1 SG Insp Results,Per TS 4.12.E.1. Following Insp 84 Tubes Were Plugged for First Time ML20196L2461999-05-21021 May 1999 Forwards Rev 0 to COLR for Pingp,Unit 1 Cycle 20, IAW TS Section 6.7.A.6 ML20195C6861999-05-21021 May 1999 Forwards Rev 17 to USAR for Prairie Island Nuclear Generating Plant.Attachment 1 Contains Descriptions & Summaries of SEs for Changes,Tests & Experiments Made Under Provisions of 10CFR50.59 During Period Since Last Update ML20206U6781999-05-17017 May 1999 Forwards Revised Emergency Response Plan Implementing Procedures,Including Rev 15 to F3-3,rev 15 to F3-16,rev 14 to F3-22 & Table of Contents ML20206U7131999-05-17017 May 1999 Forwards Revised EOF Emergency Plan Implementing Procedures, Including Table of Contents & Rev 2 to F8-10, Record Keeping in Eof. with Updating Instructions ML20206T2461999-05-17017 May 1999 Forwards Off-Site Radiation Dose Assessment for Jan-Dec 1998, Rev 0 to Annual Radiactive Effluent Rept for 980105- 990103 & Effluent & Waste Disposal Annual Rept Solid Waste & Irradiated Fuel Shipments,Jan-Dec 1998 ML20206R0401999-05-13013 May 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Removing Plant Organization Requirement,Imposed in Amend 141/132 That Plant Manager,Who Has Responsibility for Overall Safe Operation of Plant,Report to Corporate Officer ML20206Q0871999-05-13013 May 1999 Forwards Result of Evaluation Re Ultrasonic Exams of SG Number 22 Performed in Accordance with ASME Boiler & Pressure Vessel Code Section Xi.Procedure Used for Evaluation Contained in WCAP-14166,submitted for Review ML20206F9381999-05-0303 May 1999 Forwards Response to NRC 990304 RAI Re GL 96-05 Program at Pingp.Licensee Commitments Are Identified in Encl as Statements in Italics ML20206J3851999-05-0303 May 1999 Forwards 1998 Annual Radiological Environmental Monitoring Rept 05000282/LER-1999-004, Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics1999-05-0303 May 1999 Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics ML20206E1761999-04-28028 April 1999 Forwards Revised TS Pages for Amends 144 & 135 to Licenses DPR-42 & DPR-60,respectively,to Update Controlled Manual or File ML20205S3221999-04-20020 April 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements of TS 5.1 ML20205P9891999-04-12012 April 1999 Requests Approval for Proposed Alternatives to Liquid Penetrant Requirements of N-518.4 of 1968 ASME Boiler & Pressure Vessel Code.Results of Analysis & Summary of Tests Performed & Tests Results Are Encl ML20205Q0191999-04-12012 April 1999 Forwards Application for Amend to License DPR-42 & DPR-60, Relocating Shutdown Margin Requirements from TS to COLR 05000282/LER-1998-010, Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER1999-04-0808 April 1999 Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER ML20205P9221999-04-0101 April 1999 Submits Relief Request 8,rev 0 Which Addresses Limited Exams Associated with Unit 2 Third ten-year Interval Inservice Insp Program.Util Requests Relief Per 10CFR50.55a(q)(5)(iii) Due to Impracticality of Obtaining 100% Exam Coverage ML20205E8371999-03-31031 March 1999 Submits Four Copies of Rev 38 to Prairie Island Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Security Plan.Encl Withheld,Per 10CFR73.21 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205Q5051999-03-30030 March 1999 Forwards Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327- 981229. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarized Results ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20204H3371999-03-19019 March 1999 Forwards Application for Amend to Licenses DPR-42 & DPR-60, Removing Dates of Two NRC SERs & Correcting Date of One SER Listed in Section 2.C.4, Fire Protection 1999-09-07
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Northern States Power Company 414 Neollet Man -
Minneapons. Minnesota 55401
, Telephone (612) 330 5500 January 25, 1993 U S Nuclear Regulatory Commission Attn: Document Control Deck Washington, DC 20555 PRAIRIE ISLAND NUCLEAR CENERATING PLANT Docket Nos. 50 282 License Nos. DPR-42 50 306 DPR 60 Response to Single-Failure-Proof Crane Upgrade License Amendment Safety Evaluation Open Items TAC N)s. M81883 and M81884 The attached information is provided in response to open items contained in the NRC Safety Evaluation for Prairie Island License Amendments 99 and 92 issued July 9,1992. Amendments 99 and 92 revised the Prairie Island Technical Specifications to eliminate cask handling restrictions and replace them with requirements for the use of a single-failure-proof handling system in the handling of heavy loads.
Attachment 1 describes the test plan for the special lifting device to be-utilized in handling the TN-40 spent fuel storage casks at Prairie Island.
Attachment 2 provides the justification. for the dynamic load factor. utilized ;
in the structural analysis of the TN-40 spe.cial lifting device. '
Our October 4,1991 License Amendment Reques,t, which proposed the Technical Specification changes issued by Amendment 99 and 92, stated that the special-lifting device to be utilized in handling the TN-40 spent storage casks would be-designed to meet the requirements of the 1978-revision of ANSI N14.6. -The: ;
October 4, 1991 License Amendment Request was in error. As stated in Section 2.1 of Transnuclear Specification- E-12261, Revision 0, " Design Criteria for j]
Lifting System for TN-40 Dry Cask Storage Cask at Prairie Island"', which was-transmitted to the NRC by our letter dated February 3,1992, the special lifting device-to be utilized in handling the-TN-40 spent storage. casks is-being designed in accordance with the requirements of ANSI N14.61986.
~
'We.
apologize for any-inconvenience this error may'have caused. ?
Our October 4, 1991, License Amendment Request stated that we Mould be unabic l
to comply with the special lift device load test-requirements of ANSI N14.6 and that any load testing performed per ANSI N14.6-would be performed at the 125% level. .That exception to ANSI N14.6 is no longer valid, the special lifting device for the TN-40 cask will be load tested in accordance with the requirements of ANSI N14,6,1986.
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- Pago- 2 January 25, 1993 - Northem States Power Comparri The specific NRC commitments contained in this transmittal are listed in Attachment 1 . Please contact Gene Eckholt (612-388-1121, ext. 4663) if.you have any questions related to-the information provided.
lW
. Thomas M Parker
' Director Nuclear Licensing c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg Attachments:
- 1. Testing of TN-40 Cask Special Lifting Device.
- 2. Justification of TN-40 Cask Special Lifting Device Dynamic Load Factor.
- 3. NRC Commitments Contained in This Transmittal
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., -.c PRAIRIE ISLAND NUCLEAR CENERATING PLANT' >
ATTACHMENT 1-Testint Plan for the TN-40 Cask Special Lifting Device As stated in our October 4', 1991 License Amendment Request, the'special lifting device to be utilized in handling the TN-40 spent fuel a;orage casks at Prairie Island will meet the requirements of ANSI N14.6, " Standard for-
- Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds:or More for Nuclear . Materials", as outlined in guideline (1)(a) of Section 5.1.6 of -
NUREG-0612. 1Run testing plan for the TN-40 special lifting device is ~ outlined below. Except as noted below, testins of the TN-40 special lifting device will conform with the requirements of ANSI N14.6, 1986. j ACCEPTANCE TESTINC Initial acceptance testing of the special lif ting device for the TN-40 cask will be conducted in accordance with the requirements Sections 6.2, 7.1 and 7.3 of ANSI N14.6, 1986.
Load Testing Section 7.1 of ANSI N14.6 defines the requirements for special lifting devices for critical loads. Section 7.1(1) of ANSI N14.6 allows the use of special-lifting devices, like the TN 40 special lifting device, that utilize load bearing members with increased stress factors-for handling the critical load-rather than dual load paths. Section 7.3 of ANSI N14.6 states that if.c special-lifting device is' designed with increased. stress design factors instead of dual load _ paths, acceptance testing shall be_ conducted in.
accordance with 6.2.1, except that the test load shall be three. times the weight that the device is to support rather than: the 150% requirement of-Section 6.2.1. -The acceptance _ testing of the special lifting device for the-Prairia Island TN-40 casks will be performed at three times the weight the device is to support.
Section 6.2 of Transnuclear Specification-E-12261, Revision 0, " Design Criteria-for Lifting System for TN-40 Dry Storage Cask at Prairie Island",
which was transmitted to the NRC by our letter dated February 3,1992, states that the TN 40 special' lift device.will be load tested to 150%_of the design 4
load prior to shipping. That statement was in error. As stated above, :ne-TN.40 cask special lifting device will be acceptance tested at three ,mes the .l weight that~the-device is to support.
- ' Functional Testine _
Non-load bearing functioning parts of the TN-40 special lif ting device will be :
tested, as. prescribed by Section 6.2.3 of ANSI N14.6, 1986, prior to initial use of the device.
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- Page 2 of 3 TESTING TO VERIFY- CONTINUING COMPLI ANCE Testing of the special-lifting device for the.TN-40' cask to verify continuing compliance with the requirements of ANSI N14.6_will be conducted as described below. The plan for periodic testing and inspection the TN 40fspecial lifting device is based, with some exceptions, on the requirements of Sections 6.3 and 7.3 of ANSI N14.6, 1986.
Annual Testine Section 7.3 of ANSI N14.6, 1986 states that annual testing shall be' conducted in accordance with Section 6.3.1 of ANSI N14.6 except that the device shall be subjected to'three times the weight that the device is_to support. Section-6,3.1(2) of ANSI N14.6, 1986 allows, in cases where surface cleanliness and-conditions permit, the annual load testing requirements to be replaced with:
dimensional testing, visual inspection, and nondestructive testing of' major.
load carrying welds and; critical areas in accordance with-Section 6.5 of ANSI- ,
N14.6, 1986. The annual testing of the special lifting device for-the Prairie Island TN-40 casks will be performed in accordance with Section 6.3.1(2),
therefore, no annual load testing will be performed.
The functional testing of the TN-40 special lifting device, prescribed in-Section 6.2.3 of ANSI "14.6, 1986 for acceptance testing, will be repeated on an annual basis per Section 6.3.4 of ANSI N14.6, 1986. -
Sections 6.3.1 and 6.3.4 of ANSI N14.6, 1986 specify'that the period for annual testing of special lifting devices not. exceed 14 months. Section 4.0 of the Prairie Island Technical Specifications sllows the time interval between surveillance tests to-be adjusted plus r r minus(25% to- accommodate normal test schedules. Surveillance testing performed at Prairie Island, including testing nco specifically required by Technical Specifications, is-scheduled using this allowance. For consistency, the TN-40 special lifting device annual testing will be scheduled as part of the plant surveillance-program using the plus or minus 25% allowance ~. The surveillance will be scheduled to be competed every.12 months, but the interval could-be extended to a maximum interval -of 15 months if scheduling or other conflicts. arise.
The ar.nual testing required by Sections 6.3.1(2) and 6.3.4 of ANSI N14.6,-1986 will not be performed on an annual basis if the TN-40 lifting device is_not to be used~for a period exceeding one year. In that case, the testing required by. Sections 6.3.1(2) and 6.3.4 will be performed before returning the device to service.
Section 6.3.8 of ANSI N14.6, 1986 prescribes that each special lifting device be tagged or the record system updated after annual testing, indicating the expiration date of the validity of that test. Ar'noted above, surveillance-testing of the_TN-40 special lifting device wilt be scheduled and controlled by tho' plant' surveillance program. This program will cnsure that the annual.
testing will be performed per the required schedule and that the results of the annual testing will be properly documented.
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' Additional lead Testine .
The TN 40 special-lifting device will be load tested as prescribed in_Section-6.2.1;of ANSI 14.6, 1986 after any of the following:
- 1. Major' maintenance or alterations, as defined in Section 6.3.2 of ANSI _
N14.6, 1986,
- 2. An incident in which any of the load-bearing components of.the TN-40 special lif ting device may have been subjected to stresses substantially in -
excess of those for which it was previously quali.fied or
- 3. An incident that may have caused permanent distortion of its load bearing ,
4 parts.
Additional Functional Testing
'Per Section 6.3.5 of ANSI N14.6, 1986, the functional testing prescribed in Section 6.2.3 of AhSI-N14.6, 1986 for acceptance-testing, will be repeated following any incident in which repairs or alterations have been required.on non-load-bearing functioning components or in which the TN-40_special lifting device has suffered detectable distortion. H Visual-Insoection i Section 6.3.6 of ANSI N14.6, 1986 presccibes that special lifting devices _bE visually inspected by operating personnel for indications of. damage or deformation prior to each use. 'Section 6.3.7 of ANSI N14.6,E1986 prescribes that special lifting devices be visually inspected by maintenance or other non-operating personnel at intervals not .to exceed three months for indications.of: damage or deformation.
The visual inspections _ prescribed by Sections 6.3.6 and 6.3.7 appear to be-designed to address concerns with a special' lifting device which'is'used on a- !
continuing basis and, as 'such, could experience _ significant degradation 'over time from usage. The visualiinspection by' operating personnel would; identify any degradation which may occur between mort thorough quarterly inspections.
Because the.TN-40 special lifting-device is only expected toLbe used onTthe average of twice per year, the quarterly visual inspection re'quirements prescribed by Section 6.3.7 are inappropriate. _Therefore, the requirements.of:
Sections 6.3.6 and 6.3.7 will be combined; and the TN-40 special. lifting device;will be visually inspected by maintenance or non-operating personnel prior to each use of the lifting device.
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT-ATTACHMENT 2 Justification of TN-40 Cask Special Liftine Device Dynamic load Factor A dynamic load factor of 0.05 was used in th6 structural anelysis of the-special lifting device to be utilized in handling the TN 40 spent fuel storage casks at Prairie Island. The dynamic load factor was obtained by mu?tiplying the maximum hoisting speed for the upgraded Prairie Island auxiliary building crane (5 ft/ min) by 0,005 (0.5%). This it recommended in the Crane Manufacturers Association of America (CMAA) Specification #70, 1988 revision, to calculate the Hoist. Load Factor for a crane. The result, 0.025, was doubled to provide an additional safety margin. -}
Crane Manufacturers Association of America Specification #70, 1988 revision, also recommends that the Holst Load Factor not be less than 0.15 for the crane -
design. However, the Crane Manufacturers Association of-America minimum Holst I Load Factor value is not applicable for the Prairie Island TN-40 special lifting device design because the Crane Manufacturers Association of America minimum Hoist Load Factor pcrtains to the crane structure which is-designed.
with a stress factor of 5 to ultimate; while the Prairie Island TN-40 special lifting device is designed with stress factors of 6 to yield and 10 to ultimate.
Additionally, as outlined below, the upgraded Prairie Island auxiliary building crane is designed for very smooth operation which will minimize dynamic loads on the lift beam due to accelerations or decelerations.
Tha crane is equipped with a DC hoist control with a stepless drive which provides for smooth acceleration and deceleration. It also requires less maximum motor torque than AC type drives.
The impact forces imparted on the lif t beam are further minimized by the following: 1 e The maximum hoist speed that will be used when handling a TN-40 storage:
cask is-very slow (5~ft/ min).
- The hoist is equipped with an energy absorbing torque limiter, which-limits the torque to 130% of the design value, e The hoist is equipped with a load cell which automatically stops the crane if a load of 125% of the rated static load'is dctected.
- Strict administrative controls are exercised over all' crane operations Only qualified and trained operators nill operate the crane.
- The crane wire cable will also provide damping effects which will reduce the dynamic load amplification factor.
- Two separate magnetic brakes are provided on the crtue as well as regenerative braking. .Each magnetic brake providra a braking force of' 150% of rated load and are timed (s(quenced) to act in series. .Thus, the sequenced magnetic brakes and the regenerative motor brake assures that smooth lowering and hoisting' speeds can be maintained regardless of the load on the hook. ,
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- ,, 1-f*i -PRAIRIE: ISLAND NbCLEAR CENERATING PLANT c'
' ATTACHMENT 3 ,J NRC Commitments Contained in This Transmittal l
- 1. Initial ~ acceptance testing of the specialnlifting: device forfthe TN.40tcask: -
will be conducted in accordance_with the requirements Sections 6.2, 7,1 and; 7.3 of ANSI N14.6,;1986. The acceptance testing-of the-special lifting '
device for the ' Prairie Island TN-40 casks willL be. performed-at!three timesL " ' .
the weight the device is to support.-
e
- 2. Non-load-bearing functioning parts of the TN 40 special lifting devic lwill- -
be tested, as prescribed by Section 6.2.3~of ANSI N14.6, 1986, prior-to1 initial use of the device.
- 3. The annual testing of the special lifting device for the Prairie Island TNk 40 casks will be performed in accordance wich'Section 6.3.1(2) of ANSI N14.6, 1986, no annual load testing will be performed.
- 4. The functional testing of the TN 40_ special lifting device, prescribed irt ,
Section 6.2.3 of ANSI N14.6, 1986 for acceptance testing,~will be_ repeated on an annual basis per Section 6.3.4 of ANSI N14.6, 1986.
- 5. The TN 40 special lifting _ device annual testing will be scheduled _as part--
cf the plant surveillance program using the Technical Specification plus or minus 25% allowance. The survnill.ance will be scheduled-en be competed:
every 12 months, but the interval could be extended to a maximum interval:
of 15 months if scheduling or other conflicts arise.
- 6. The annual testing required by Sections 6.3.1(2) and 6.3.4 of ANSI-N14.6, 1986 will not be performed on an annual basis. if the TN-40 lifting device :
0 is not to be used for a p'eriod exceeding one_ pear. In-that case, the. .
testing required by Sections 6,3.1(2)- and 6.3.4 -will be performed before -
returning the device to service.
7.TheTNe40specialliftingdevicewillbeloadtestedas-prescribed [in- 14 Section 6.2.1 of ANSI 14.6, 1986 after any of;the following:
- a. Major maintenance or alterations, as defined _ in! Section 6.3.2; of, ANSI.
N14.6, 1986,
- b. An incident in which any of the -load-bearing components of the TN special lifting devi.ce may have-been subjected'to stresses substantially.
in excess of those for wh2ch it was previously qualified, or c..An incident that may have caused permanent distortion of its load--
bearing parts.
- 8. Per Section 6.3.5 of ANSI N14.6, 1986, the functional, testing prescribedlin Section 6'.2.3 of ANSI N14.6,' 1966 for acceptance testing,- willlbe repeated.
following any incident in which repairs or alterations have been. required on non-load-bearing-functioning components.or in which the TN 40'special:
p .liftirg device has suffered detectable distortion.
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~9 . i*he'TN-40 special lifting uevice will-be visuelly' inspected.by maintenance. -
or. non' operating -personnel prior to each use of the liftiv.g Jevi.ce.
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