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MONTHYEARML20244D7891989-06-12012 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 Project stage: Other 1989-06-12
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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:NRC TO UTILITY
MONTHYEARML20217A0031990-11-15015 November 1990 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
[Table view] Category:OUTGOING CORRESPONDENCE
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 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
[Table view] |
Text
__ ..
. 4[ . 'o g UNITED STATES
, ;;[ *}b )g g NUCLEAR REGULATORY COMMISSION
, ;y WASHINGTON, D. C. 20555
"% ...+ /c
- June 12, 1989 Docket Nos. 50-282 and 50-306 Mr. Tom Parker Manager Nuclear Support Services Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401-1927
Dear Mr. Parker:
SUBJECT:
COMMENTS ON THE NORTHERN STATES POWER COMPANY RESPONSE TO GENERIC LETTER 88-17 WITH RESPECT TO EXPEDITIOUS ACTIONS FOR LOSS OF DECAY HEAT REMOVAL FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNITS 1 AND 2 (TAC NOS. 69767 AND 69768)
Generic Letter (GL) 88-17 was issued on October 17,.1988 to address the potential loss of decay heat removal (DHR) during nonpower operation. In the GL, we requested (1) a description of your efforts to implement the eight recommended expeditious actions of the GL and (2) a description of the enhancements, specific plans and a schedule for implementation of the six recommended program enhancements.
The NRC staff has reviewed your response to Generic Letter 88-17 on expeditious actions in the letter of January 6,1989. Your letter also had responses for programmed enhancements. However, these will be reviewed at a later time. We find that your response appears to meet the intent of the GL for expeditious actions but lacks some of the details requested in Enclosure 2 of GL 88-17.
Your response to some items is brief and ".erefore does' not allow us to fully ,
understand your actions taken in response to GL 88-17. You may wish to consider '
several obse'rvations in order to assure yourselves that the actions are adequately addressed. .
- 1. You mention a training packaged developed for operating crews and appro-priate personnel relating to the Diablo Canyon event, specifics of the RHR system, reactor coolant instrumentation and the Westinghouse Owner's Group (WOG) study. It is not specifically stated if maintenance personnel are
- also included in the training. The item was intended to include all >
personnel who can affect reduced inventory operation.
1
- 2. You indicate that procedures and administrative controls are in place to <
reasonably assure that containment closure can be achieved within the l time at which core uncovery could result from a loss of DHR coupled with an inability to initiate alternate cooling or addition of water to the !
RCS inventory. You indicate that refinements and modifications are being !
made to reflect time periods for closure consistent with the GL and WOG '
study. You have not presented the new times for containment closure based on your plant specific analysis. In the meantime, Generic Letter 88-17 states that " containment penetrations including the equipment hatch, may remain open provided closure is reasonably issued within 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of initial loss of DHR." This time will be less if there are vent areas totaling greater than one square inch in the cold leg (see Enclosure 2, Section 2.2.2 of GL 88-17). {
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- 3. In some plants the quick closing of the equipment hatch is achieved by the installation of a reduced number of bolts. If you plan to use less than the full complement of bolts for sealing the equipment hatch then you should first verify that you can make a proper seal of the periphery mating surfaces to r..eet the closure criteria.
- 4. You indicate that two core exit thermocouple will be provided for obtaining continuous temperature indication that is representative of core exit conditions when the RCS is in a mid-loop condition. You have stated that the core exit thermocouple use a common power supply. You indicate that a failure of the power supply will cause temperature indications to increase which is in the conservative direction for operator action.
Although, we do not necessarily agree with your statement " Inaccurate temperature indications cannot cause inappropriate operator actions as would inaccurate RCS level indications," nevertheless, we are not calling for independent power supplies, but two different sensors.
- 5. You indicate that two continuous RCS water level indications are provided to the control room whenever the RCS is in a reduced inventory condition.
In one system, a level transmitter sends signals to a control board level indicator and via a temporary installation, high and low RCS water level alarms are available. Trending of the RCS water level can be performed on the emergency response computer system which also receives the level signal. You have stated that the second RCS water level indication uses a tygon tube which is permanently installed with remote viewing in the control room. You indicate that the level reading is recorded hourly.
You state that if the remote viewing equipment is not operable a designated
" tube watch" operator in contact with the control room will be provided.
As noted in GL 88-17, these observations from other than in the control room should be recorded at intervals no greater than 15 minutes. You have indicated that the common sensing taps for both of the level systems are located off the RCS loop A crossover lege. Since the same commons taps are used for two level systems a common error may occur and extra precautions are needed. You have not stated what the accuracy is of each of the two systems. When two instruments are in place, care should be taken to resolve any discrepancy between the two measurement systems. Also,'the pressure in the reference leg should approximate the pressure of the void in the hot leg or be compensated to obtain the correct level value.
- 6. Walking the tygon tube following installation to verify lack of kinks or loop seals is necessary. Experience shows that periodic walkdowns are needed after installation. We recommend daily walkdowns when the tygon tube is in use, with an additional walkdown immediately prior to its being placed in use.
- 7. For expeditious action regarding provision of at least two available or operable means of adding inventory to the RCS that are in addition to pumps that are a part of the normal DfiR systems, you state that present procedures require the charging system to be operable and give guidance
d !
on injection rates. You have.not' stated the ' injection point for this system. You further. state that additions to. the procedures will be made g requiring that a safety. injection pump be made available which is' aligned-for upper plenum injection. 'As alluded to in Enclosure 2,.Section 2.'2.2-j q
of GL 88-17, if openings totaling greater than 1 square. inch exists in~ . i the cold legs, reactor coolant pumps.and' crossover. piping of-the RCS, the I core can uncover quickly when pressurized under loss of RHR conditions. l If this situation should arise, it=is generally more effective toc inject' D makeup water.into the hot leg. rather than the cold leg. j 8.
~
You have not, stated the use of any specific vent _ openings on the~ hot-side:
of the RCS to relieve RCS~ pressurization. The removal of a. pressurizer manway or steam generator manway, for example, is a means to provideLRCS.
venting. Calculat. ions ~need to' be performed to . verify the effectiveness of RCS openings, however, because even for'relatively~1arge hot side l openings in the RCS, pressurization to several psi can still result ~. For-example, with removal of a pressurizer manway large_ steam flows in combination with~ flow restrictions in the' surge line and. lower pressurizer-hardware may still iead to pressurization.
There.is'no need to respond to the above observations.-
As you are awar,e,'the expeditious' actions you'have briefly described are an interim measure to achieve an immediate' reduction in risk associated withz reduced inventory operation, and these will be supplemented ~and in some cases replaced by programmed enhancements.. ' We' intend to audit.both your response to ~
the expeditious actions and your programmed enhancement. program. The areas where_we do not fully understand your responses as indicated above may be covered in the audit of expeditious actions.
This completes the staff review of your responses to the expeditious actions -
listed in the GL. The area of programmed enhancements'will be addressed in a separate letter. ,.
Sincerely,
~ .
W .
, x %: ,
l Dominic C. Dilanni, Project Manager Project. Directorate III Division of Reactor Projects:- III,~IV, V
&'Special, Projects Office of Nuclear. Reactor Regulation 1
_ - _ _ _ _ _ _ - - - _ - _ - _ _ _ _ - _ _ _ - _ - - - _ --_E-__._ -_ ____
Hr. T. M. Parker Prairie Island Nuclear Generating i
Northern States Power Company Plant cc:
Gerald Charnoff, Esq.
Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Dr. J. W. Ferman Minnesota Pollutice. Control Agency 520 Lafayette Road St. Paul, MN 55155
' Mr. E. L. Watzl, Plant Manager Prairie Island Nuclear Generating Plant Northern States Power Company Route 2 Welch, Minnesota 55089 Joseph G. Maternowski Assistant Attorney General Environmental Protection Division Suite 200 520 Lafayette Road St. Paul, Minnesota 55155 U.S. Nuclear Regulatory Comission Resident Inspector's Office 1719 Wakonade Drive East Welch,iiinnesota 55089 l
I Regional Administrator, Region III U.S. Nuclear Regulatory Comission Office of Executive Director fu e Operations 799 Roosevelt Road Glen Ellyn, Illinois 60137 l Mr. William Miller, Auditor Lodhue County Courthouse Red Wing, Minnesota 55066 .
I l
4
.. n. .
d-1 on injection rates. .You'have not stated the injection point:for this system. ,You further state that additions:to the procedures will be made requiring that a safety' injection pump be made available.which'is aligned for upper plenum injection. ;Ascalluded to in Enclosure 2,'Section:2.2.2 of. GL 88-17, if openings totaling greater. than 1l square inch exists in the cold legs, reactor coolant pumps'and crossover piping ofLthe RCS,tthe
- core can uncover q'uickly when pressurized under loss of RHR conditions.
If this situation should arise, it is generally more effective to^ inject makeupf water into the hottleg rather than the cold. leg.
8.- You have not stated the use.of any specific' vent openings on'the' hot 1sidel of the'RCS to relieve RCS pressurization. The' removal'of a pressurizer .
manway or steam. generator.manway, for example,fis a.means to provide'RCS; venting. . Calculations'need~to be performed to. verify the effectiveness of RCS openings, however,Lbecause even for relatively large hot l side ,
openings in the RCS,. pressurization.to several psi can;still ' result. -For.
example, with removal of a pressurizer manway'large. steam flows in combination with flow restrictions in the surge line and lower pressurizer-hardware-may still lead to pressurization. 1 There is no need to respond to the above observations.
As you are' aware, the expeditious. actions you have briefly described are an-interim measure to achieve an immediate~ reduction 'in' risk: associated with reduced inventory operation ~, and these-will be supplemented'and-in'some cases replaced by programmed enhancements. 'We intend-to audit both your response _to the expeditious actions and your programmed enhancement program. The areasi where we do not fully understand your responses.as indicated above may be covered in the audit of expeditious actions.
2 This completes the staff review of your responses;to the expeditious actions l listed in the GL. The area of programmed enhancements will be addressed in.a-separate letter. 1 1
i Sincerely, I l
I
,, _Vm _ -
T ,
minic C. Dilanni, Project Manager 1
- Project Directorate III .
Division of Reactor. Projects?-LIII,.IV; V"
&'Special Projects
~
L Office;of. Nuclear Reactor Regulation-PM/PD31:DRSP -
(A)D/PD3 PSPs
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