ML20212K868
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| ML20212K868 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/18/1986 |
| From: | Diianni D Office of Nuclear Reactor Regulation |
| To: | Musolf D NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20212K873 | List: |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8608250097 | |
| Download: ML20212K868 (2) | |
Similar Documents at Prairie Island | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3371999-10-20020 October 1999
[Table view]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 Category:NRC TO UTILITY MONTHYEARML20217A0031990-11-15015 November 1990
[Table view]Confirms Discision by Bl Burgess & E Watzl to Have Meeting on 901206 in Region III Ofc to Discuss Configuration Mgt, Attention to Detail,Recent Organization Changes & Interpretation of TSs ML20058E7851990-11-0202 November 1990 Forwards Safety Insp Rept 50-306/90-15 on 900904-05,17-19 & 1029.No Violations Noted ML20058F4981990-11-0101 November 1990 Forwards Safety Insp Repts 50-282/90-14 & 50-306/90-14 on 900814-0924.No Violations Noted ML20058D0721990-10-26026 October 1990 Forwards Insp Repts 50-282/90-15 & 50-306/90-16 on 900917-1005.No Violations Noted.Concerns Raised Re Small Break LOCA Analysis.Reanalysis of Results Requested ML20058D1001990-10-23023 October 1990 Advises That Responses to NRC Bulletin 89-002 Re Stress Corrosion Cracking in Stainless Steel Bolting Acceptable ML20059N7181990-10-0505 October 1990 Advises That Util 900925 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2 'Vendor Interface for Safety-Related Components' Acceptable ML20059H1461990-09-10010 September 1990 Requests Procedures & Policies Re Fitness for Duty Program for Insp Scheduled for 901016-19 ML20059E9311990-08-30030 August 1990 Identifies No short-term Safety Concerns Re Util 890525 Response to Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Evaluation of Westinghouse Owners Group Bounding Analysis Encl ML20059D8141990-08-27027 August 1990 Forwards Safety Insp Repts 50-282/90-12 & 50-306/90-12 on 900703-0813 & Notice of Violation ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20055J0451990-07-24024 July 1990 Forwards Safety Insp Repts 50-282/90-13 & 50-306/90-13 on 900709,11 & 12.No Violations Noted ML20055G6671990-07-20020 July 1990 Confirms 900809 Mgt Meeting in Glen Ellyn,Il to Discuss Corporate Reorganization & Other Matters of General Interest ML20055C7331990-06-18018 June 1990 Requests Submittal of Encl Ref Matls within 60 Days Prior to 901029 Scheduled Requalification Program Evaluation ML20059M9431990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248J2821989-09-20020 September 1989 Ack Receipt of Re Rev to Emergency Plan.Plan Consistent w/10CFR50.54(q) & Acceptable ML20246N5781989-08-31031 August 1989 Forwards Safety Insp Repts 50-282/89-22 & 50-306/89-22 on 890814-18.No Violations Noted ML20246N5081989-08-30030 August 1989 Advises That 890614 Response to NRC Bulletin 89-001 Re Westinghouse Steam Generator Mechanical Plugs Fulfills Requirements in Responding to Bulletin ML20247A6981989-08-28028 August 1989 Forwards Safety Insp Repts 50-282/89-20 & 50-306/89-20 on 890702-0812.No Violations Noted ML20246F4151989-08-23023 August 1989 Forwards App to SALP 8 Board Repts 50-282/89-01 & 50-306/89-01 & Errata Sheet W/Corrected Pages for Period Dec 1987 - Apr 1989 ML20245F3101989-08-0404 August 1989 Advises That Util 890724 Response to Generic Ltr 89-08 Re Pipe Wall Thinning Induced by Erosion/Corrosion Acceptable. Records of Program & Results from Implementation of Required Monitoring Program Should Be Maintained for Potential Audit IR 05000282/19890211989-07-26026 July 1989 Forwards Enforcement Conference Repts 50-282/89-21 & 50-306/89-21 on 890713 Re Apparent Violations Noted in Insp Repts 50-282/88-200 & 50-306/88-200 ML20247B1041989-07-17017 July 1989 Forwards Exam Repts 50-282/OL-89-01 & 50-306/OL-89-01 on 890613-15 ML20246N4351989-07-13013 July 1989 Forwards Safety Insp Repts 50-282/89-18 & 50-306/89-18 on 890528-0701 & Notice of Violation ML20246E3871989-07-0606 July 1989 Forwards Enforcement Conference Insp Repts 50-282/89-19 & 50-306/89-19 on 890608.Violations Discussed ML20245L2071989-06-29029 June 1989 Forwards SALP 8 Board Repts 50-282/89-01 & 50-306/89-01 for Dec 1987 - Apr 1989.Improvements Needed in Areas of Security,Surveillance & Engineering/Technical Support ML20245K9231989-06-27027 June 1989 Confirms Arrangements for 890727 Meeting at Plant Site to Discuss SALP 8 Rept ML20245G8321989-06-21021 June 1989 Forwards Safety Insp Repts 50-282/89-04 & 50-306/89-04 on 890606.No Violations Noted ML20245F1181989-06-20020 June 1989 Forwards Insp Repts 50-282/89-17 & 50-306/89-17 on 890416- 0526 & Notice of Violation ML20245A0931989-06-13013 June 1989 Advises That 890526 Rev 21 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20244D7891989-06-12012 June 1989 Comments on Util 890106 Response to Generic Ltr 88-17 Re Expeditious Actions for Loss of DHR for Plant.Expeditious Actions Re Reduction in Risk Associated W/Reduced Inventory Operation Will Be Replaced by Programmed Enhancements ML20244C2141989-06-0606 June 1989 Forwards Safety Insp Repts 50-282/89-10 & 50-306/89-11 on 890411-13.No Violations Noted IR 05000282/19890151989-05-30030 May 1989 Forwards Safety Insp Repts 50-282/89-15 & 50-306/89-16 on 890508-18.No Violations Noted ML20247K3631989-05-26026 May 1989 Requests Encl Listed Ref Matls 60 Days Prior to Requalification Program Evaluation Visit Scheduled for Week of 891023 ML20247C2521989-05-18018 May 1989 Forwards EGG-PHY-8073, Technical Evaluation Rept for Evaluation of ODCM Updated Through Rev 9,Prairie Island Nuclear Generating Plant Units 1 & 2. Rev 9 Acceptable, Except for Listed Discrepancies Noted in Rept.Rev Requested IR 05000282/19882011989-05-15015 May 1989 Advises That NRC Plans to Forward Vendor Interface & Procurement Program Insp Repts 50-282/88-201 & 50-306/88-201 to Other Utils in Region Iii.Ltr Transmitting Rept Sent to Other Utils Encl for Info ML20246P7231989-05-11011 May 1989 Informs That NRC Initiated Series of Insps at Nuclear Generating Plants in Area of Vendor Interface & Procurement Programs for Procurement of Items for Use in safety-related Applications ML20246J8511989-05-10010 May 1989 Confirms 890512 Enforcement Conference in Region III Ofc to Discuss RCIC Turbine Steam Line Flooding Event ML20246K3741989-05-0606 May 1989 Forwards Insp Repts 50-282/89-14 & 50-306/89-15 on 890417-21 & 27 & Notice of Violation ML20247L3851989-05-0404 May 1989 Forwards Safety Insp Repts 50-282/89-08 & 50-306/89-08 on 890305-0415 & Notice of Violation ML20246E2871989-05-0404 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification Agreed Upon at 890411 Meeting W/Westinghouse Owners Group.Analyses Should Be Available by End of May ML20246D9021989-05-0303 May 1989 Ack Receipt of .E Tomlinson Planning to Attend 890523-24 Meetings of Fairbanks Nuclear Emergency Generator Owners Group.Tomlinson Prof Qualifications Listed ML20246C8421989-05-0202 May 1989 Forwards Safety Insp Rept 50-306/89-10 on 890403-06 & 24. No Violations Noted ML20245L1721989-04-28028 April 1989 Forwards Safety Insp Repts 50-282/89-09 & 50-306/89-09 on 890403-17.No Violations Noted ML20244A8131989-04-0404 April 1989 Ack Receipt of 890316 Description of Scope & Objectives for 1989 Exercise Scheduled for 890606.No Concerns Identified ML20248G0511989-03-30030 March 1989 Forwards Safety Insp Repts 50-282/89-07 & 50-306/89-07 on 890306-10.No Violations Noted ML20248F9031989-03-28028 March 1989 Forwards Safety Insp Repts 50-282/89-03 & 50-306/89-03 on 890129-0309.No Violations Noted ML20236B4131989-03-10010 March 1989 Forwards Insp Repts 50-282/88-201 & 50-306/88-201 on 881025-1104 & Potential Enforcement Findings.Weaknesses Exist in Procurement & Dedication of commercial-grade Items & Util/Vendor Interfaces IR 05000282/19880191989-01-10010 January 1989 Ack Receipt of Re Corrective Actions.Third Violation Contained in NRC Being Withdrawn as Erroneous,Since Duplicate Violation Issued in Insp Repts 50-282/88-19 & 50-306/88-19 ML20196C8931988-12-0202 December 1988 Requests That Util Address Generic Ltr 88-17 Re Loss of DHR During Nonpower Operation.Industry Response to Generic Ltr 87-12 Deficient in Areas of Prevention of Accident Initiation & Mitigation of Accidents ML20196A9281988-11-30030 November 1988 Forwards Insp Repts 50-282/88-18 & 50-306/88-18 on 880919-22.No Violations Noted 1990-09-10 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M3371999-10-20020 October 1999
[Table view]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 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 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 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 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island 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 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 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 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 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 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 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 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 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 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 ML20207B5841999-05-26026 May 1999 Forwards SER Concluding That Licensee 990412 Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Reactor Vessel Head Penetrations for part-length CRDMs Will Provide Acceptable Quality & Safety ML20207D0641999-05-26026 May 1999 Informs of Plans to Conduct Meeting on 990614 in Red Wing,Mn,To Present Planned Changes to NRC Regulatory Processes & Pilot Plant Program for Prairie Island Nuclear Generating Station ML20207B7941999-05-25025 May 1999 Forwards Insp Repts 50-282/99-05 & 50-306/99-05 on 990426- 30.No Violations Noted.Overall Plant Radiological Controls Effective in Maintaining Reasonable Collective Dose for Work Being Conducted During Unit 1 Refueling Outage ML20207B3281999-05-24024 May 1999 Informs That in May 1999,Region III Received Rev 20 to Portions of Prairie Island Nuclear Generating Center Emergency Plan.Rev Submitted Under Provisions of 10CFR50.54(q) ML20207A1491999-05-20020 May 1999 Forwards Request for Addl Info Re Areas of Seismic,Fire,High Winds,Floods & Other External Events for IPEEE Submittals for PINGP Dtd Dec 1996,March 1998 & Dec 1998 ML20206S0891999-05-13013 May 1999 Informs That on 990505 NRC Staff Held Planning Meeting for Plant to Identify Insp Activities at Facility Over Next 6 to 12 Months ML20206N4581999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created. Reorganization Chart Encl ML20206J2101999-05-0404 May 1999 Forwards Insp Repts 50-282/99-02 & 50-306/99-02 on 990226-0406.No Violations Noted.During Insp Period,Sf Casks 08 & 09 Successfully Loaded & Cask 08 Transported & Placed in ISFSI ML20206E1801999-04-29029 April 1999 Forwards Insp Rept 72-0010/99-01 on 990308-0413.No Violations Noted.Purpose of Insp Was to Observe Various Portions of Dry Fuel Cask Loading Program ML20205R4841999-04-16016 April 1999 Forwards Security Insp Repts 50-282/99-03 & 50-306/99-03 on 990322-26.No Violations Noted.Objective of Insp Effort Was to Determine Whether Activities Authorized by License Were Conducted Safely & IAW NRC Requirements ML20205R1791999-03-30030 March 1999 Responds to Issue Re Generic Implication of part-length Control Rod Drive Mechanism Housing Leak at Praire Island, Unit 2 & Beaver Valley Power Station,Units 1 & 2 IR 05000282/19980161999-03-30030 March 1999 Discusses Fpfi Repts 50-282/98-16 & 50-306/98-16 on 980810-28.Determined That Violations Occurred Involving MOVs Being Unable to Satisfy post-fire Safe Shutdown Function & Spurious Actuation of Sys Due to Fire Damage ML20205B5781999-03-26026 March 1999 Advises That NSPNAD-8102-P,rev 7, Prairie Island NPP Reload Safety Evaluation Methods for Application to PI Units Submitted in 990129 Application Will Be Withheld from Public Disclosure ML20205G9321999-03-26026 March 1999 Informs of Planned Insp Effort Resulting from Prairie Island Plant Performance Review for Period 980328-990131.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 6 Months Encl ML20205C0671999-03-26026 March 1999 Informs That Exhibit E (CEN-629-P,Rev 03-P, Repair of W Series 44 & 51 Steam Generator Tubes Using Leak Tight Sleeves Will Be Withheld from Public Disclosure,Per Util 990205 Application & C-E Affidavit,Per 10CFR2.7990 ML20205B5161999-03-26026 March 1999 Discusses Util Re Rept of Corrections to Licensee ECCS Evaluation Models.Attachments 1 & 2 from Were Withheld from Public Disclosure Due to Proprietary Markings from W.Attachments 1 & 2 Will Now Be Placed in PDR ML20204E4651999-03-18018 March 1999 Forwards Insp Repts 50-282/99-01 & 50-306/99-01 on 990115-0225.No Violations Noted ML20207E0401999-03-0404 March 1999 Forwards Request for Addl Info Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, Program at Prairie Island Nuclear Generating Plant ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20206U1831999-02-0909 February 1999 Responds to Encl Ltrs, & 1223 Re Generic Implication of part-length CRDM Housing Leak.Review Under TAC Numbers MA1380 & MA1381 Considered Closed ML20202G2101999-01-29029 January 1999 Forwards Insp Repts 50-282/98-23 & 50-306/98-23 on 981204- 990114.No Violations Noted.Insp Characterized by Several Unexpected Operational Events,Caused by Equipment Failure, Personnel Errors & Procedure Problems ML20199L4421999-01-25025 January 1999 Informs That by Encl Ltrs & 981223,NRC Has Responded to WOG Positions Re C/As to Address Generic Aspects of part-length CRD Mechanism Housing Issue That Originated as Result of 980123 Leak at Pings ML20202J1421999-01-22022 January 1999 Informs of Completion of Review of NSP Which Proposed Alternative to Surface Exam Requirements of Paragraph N-518.4 of 1968 ASME BPV Code for CRD Mechanism Canopy Seal Welds.Forwards SE Supporting Alternative ML20199F8471999-01-14014 January 1999 Forwards FEMA Evaluation Rept for 980721-22 Emergency Preparedness Exercise at Prairie Island Nuclear Generating Station ML20206U2101998-12-23023 December 1998 Provides Staff Response to Re WCAP-15126, Technical Assessment of Part Length CRDM Housing Motor Tube Cracking in WOG Plants.Nrc Agrees That Incremental Core Damage Frequency for Range of Defects Might Be 10.6 Per Ry 1999-09-09 |
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'o,, UNITED STATES P[ ,
4, n NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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r"318 CG Docket No. 50-282 Mr. D. M. Musolf, Manager Nuclear Support Services Northern States Power Company 414 Nicollet Mall Midland Square, 4th Floor Minneapolis, Minnesota 55401
Dear Mr. Musolf:
SUBJECT:
PROJECTED VALUES OF MATERIAL PROPERTIES FOR FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS-PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 1 On June 23, 1986, the Commission issued a Safety Evaluation (SE) on
" Projected Values of Material Properties for Fracture Toughness Requirements For Protection Against Pressurized Thermal Shock Events" for Prairie Island
- Nuclear Generating Plant Unit No. 1. Errors have been found on pages 2 and 3 of the SE.
Corrections are listed below and a reissue of the SE is enclosed.
- 1. Top of page 2 - The number for " Utility Submittal" for "M (Margin, F) was left out. The number should be "59."
- 2. Page 2 " Evaluation of the Calculated RT " - The material properties ofthecontrollingmaterialandtheass$Natedmarginandchemistry factor were incorrect for copper and nickel. The correct factor is 0.14 for copper (Cu) and 0.17 for nickel (Ni). This error causes the equation to change.
- 3. Page 33 line 2 and line 4 from top of page "189.4 F" should be "154.1 F" for the limiting circumferential weld material.
860easco97 DR ADocg a60818 p 99999282 PDR
_2_
0 4.
Pageg,)line3-thelargemarginbecomes"(145.9F)"insteadof 110.6 F .
Please accept our apologies for any inconvenience these errors may have caused you.
Sincerely, s/
Dominic C. Dilanni, Project Manager 3
Project Directorate #1 Division of PWR Licensing-A 3-
Enclosure:
'As Stated
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8 ll '
Surname: PShuttlew .
DDilanni/lp Glear Date: 08//.F/86 08/ /f/86 08/lf/86
,
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