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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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. . Northem States Power Company 414 N; collet Mall Minneapotes. Minnesota $54011927 Telephone (612) 330 5500 July 29, 1992 U S Nuclear Regulatory Commission Attn: Document Control Desk Vashington, DC 20$55 PRAIR1E IS1AND NUCLEAR GENERATING PiANT Docket Nos. 50 282 1.feense Nos. DPR 42 50 306 DTR 60 Request for URR Temporary Waiver c' Compliance to Technical Specification Surveillance Reauirements_
The purpose of this letter is to confirm the results of discussions batveen Northern States Pouer Company and the NRC Staff on July 27, 1992, in which Northern States Power requested a NRR Valver of Compliance from the 4160V safectards bus surveillance test requirements of Prairie Island Technical Spe nfication Section 4.6.A.3.b.1. An NRR Waiver of Compliance was verbally issued by the NRC Staff at 2025 on July 27, 1992.
As a result of not completing all of the individual surveillance test requirements specified in Section 4.6.A.3.b.1, and the associated bases for Section 4.6, Unit 14160V safeguards bus 16 was declared inoperable at 1600 on July 27, 1992. Unit 2 4160V bus 26 will exceed its 18 month surveillance interval plus 25% on August 5, 1992. Northern States Power requests a M ay in the completion of the surveillance test requirements and operability verification for 4160V safeguards buses a* specified in Spccification 4.6. A.3.b.1 and the basis for Section 4.6 untti an Emergency License A mendment can be submitted and approved. That License Amendment will request authorization to delay the performance of the incomplete portion of the surveillance testinr on buses 46 and 26 until completion of the electrical system upgrade modh ications of the station blackout project during the two unit outage scheduled to begin in October 1992.
Requirements for Vhich Relief in Recuested Section .6..A.3.b.1 of the Prairie Island Technical Specifications requires verification that the simulation of a loss of offsite power in conjunction with a safety injection signal will result in the de energization of the emergency buses and load shedding from the emergency buses. The bases for Section 4,6 state that this test will detronstrate that the emergency power system and the control systems for the engineered safeguards equipment will function automatically in the event of loss of all other sources of a-c power, and that the diesel generators will start automatically in the event of a loss-of-cooltnt accident. The bases further state that this test will !
demonstrate proper tripping of motor fen Nr breakers, main s'aply and tie i
- breakers on the affected bus, and seg .1 starting of enr o tial equipment,
! as well as the operability of the diens generatore. A
^^ ^
9200060135 920*/29 PDR ADOCK 05000202 PDR l P
E
'USNilC July 29, 1992 Northern States Power Company Page 2 Circumstances Leadinr to Reauest and Need for Prompt Action As a result of a detailed exatnination of the Emergency Power System Technical Specifications conducted during the Operating Experience Assessments of Kewaunee Licensee Event Report 92 n11 and NRC Information Notice 92 40,
" Inadequate Testing of Ernergency Bus Undervoltage Logic circuitry", it was identified on July 27, 1992 that a portion of the surveillarice testing described in the bases for Section 4.6.A.3.b.1 had not been completed within the required tirne fratne. Since a portion of the required surveillance testing for Unit 1 4160V bus 16 was not completed within the required survellL tce interval plus 25%, Unit 1 4160V safsguards bus 16 was declared inoperable at 1600 on July 27, 1992. boit 2 4160V bus 26 will exceed its 18 month surveillance interval plus 25% on August 5, 1992.
During each refueling outaga. the integrated safety injection test has been used to fulfill the requirements of Technical Specification 4.6. A.3.b.1. The integrated Si test simulates a loss of off site power by directing an operator to manually open the supply breaker to the safeguards bus. This method of tripping the source breakers from the safeguairds buses was used in the pre-operational test of the diesel generators and during each subJequent integrated SI test, llowever, the integrated SI test does not demonstrate the full capability of the undervoltage trip feature to automatically de attergize the safeguarus buses upon a loss of powet. The testing perfortned during the integrated SI test does not demonstrate proper tripping of the main supply and tie breakers on the affected 4160V safeguards bus. All other requirements of 4.6.A.3.b.1 are fulfilled by the integrated SI tent.
Electrical preventive maintenance is perfo,w d on one of the two 4160 V safeguards buses during each refueling outage, while the refueling cavity is flooded. Prior to restoring the bus, a separete. surveillance procedure is performed to ft.nettonally check the voltage testoration scheine. During this test, the ti typing of the source breakers (main supply and tio breakers) is verified during a bus undervoltage. This surveillance test was performed as part of post maintenance testing prior to bus rectoration and was not intended to meet Technical Specification requirements (as interpreted at the time),
llowever, it provices sufficient overlap vith the integrated safety injection test to meet the Technical Specification requirements in Section 4.6.A.3.b.1 and its bases. This test is ;- dormed every other refueling outage, rather than the each r fueling outage (or 18 month) frequency in TS 4.6.A.3.h.1.
Testing on Unit 1 4160 V bus 16 was last performed on February 20, 1990.
Testing on Unit 2 4160 V bus 26 was last performed on September 20, 1990.
The requested Temporary Waiver of Cotopliance is necessary to avoid the initiation of a shutdown of Unit 1 at 2400 on July 27, 1992 and a shutdown of 3 Unit 2'on August 5, 1992.
Due to the natura of this event, it was not possible to foresce its occurrence and take ineasures to avoid it. Therefore, it was not possible to avoid the 4 submittal of this request for a Temporary Waiver of Compliance.
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'USNRC July 29, 1992 Northern States Power Company Page 3 Evaluation of Safety Sirnificance and Potential Connavery Portions of the load reject / voltage restoration scheme are tested frequently.
The undervoltage and degraded voltage relay setpoint calibration la verified on a monthly basis. Also on a monthly basis, under a separate surveillance, the emergency diesel generators are started, synchronized to the safeguards bus and the load sequencing portion of the scheme is tested. This normal monthly surveillance testing verifies operability of the majority of the load reject / voltage restoration scheme components.
Further, no probletas affecting operability have been identified with the-voltage restoration logic during the perfortaance of the preventative maintenance described above. This preventative snaintenance program has been in place since 1977.
This testing and maintenance demonstrates the reliability of the voltage restoration logic and provides a high degree of assurance-that it will remain operabic until the two unit outage scheduled to begin in October 1992.
Even though Unit 14160V bus 16 was declared inoperable at 1600 on July- 27, k 1992, the bus is energized and its related controls remain available and capable of responding to any plant transient. Based on the results of past testing a high degree of confidence extsta that all electrical functions are
. fully operable.
- It is overly conservative to assume that systems or components are inoperable when a surveillance requirement has not been perfortoed at its required frequency. The opposite is in fact the case; t!.e vast. majority of surveillances demonstrate that systems or componento in fact are operable.
When a surveillance har not been completed, it is primarily a question of operability that has not been verified by the perforna.nce of the required surveillance.
Assuming that the incomplete surveillance testing results in inoperable voltage restoration logic, only 4160V buses 16 and 26 would be affected.
4160V buses 15 and 25 are still within the required surveillance test interval and remain operable. Therefore, consistent with the plant accident analysis, at least one train of safeguards components would remain
Therefore, safety significance and potential consequences of this event are
, minimal.
Discussion o ' Compensatory Actions
' Even though Unit 14160V bus 16 was declared inoperable at 1600 on July 27, 1992, the bus is etiergized and-its related controls remein available and capable of responding to any plant transient. Based on the-results of past testing a high degree of confidence exists that all electrical functions are fully opecable.
. . . . . ___.____o
USNRC July 29, 1992 Northem States Power Company Page 4 Even though there is a high degree of confidence that the voltage restoration logic for buses 16 and 26 will function as designed, the following compensatory actions are being put in place:
- 1. The monthly safeguards bus undervoltage testing and emergency diesel generator surveillance will continue.
- 2. The relays associated with the 4160V safeguards bus undervoltage restoration scheme will be visually inspected monthly.
- 3. Should unforeseen degradation, not the result of pre planned testing or maintenance, occur on the onsite electrical supply system (including the switchyard), discussion will be initiated with the NRC Staff for the verbal re confirmation of the acceptability of. the Temporary Waiver of Compliance.
- 4. All control room operators will review the emergency operating and abnormal operating procedores related to safeguards bus voltage restoration.
- 5. A procedure to complete the delinquent portions of the Specification 4.6.A.3.b.1 testing requirements, at a mode other than cold shutdown, will be evaluated.
- 6. Following a unit trip or the placing of either unit in hot sh.tdown, discussion will be initiated with the NRC Staff for the verbal re-confirmation of the acceptability of the Temporary Waiver of Compliance. .
I Justification of Duration of the Recuegg This request for a Temporary Waiver of Compliance requests a delay in the completion of a portion of the surveillance' test requirements and operability verification for 4160V safeguards buses as specified in Specification 4.6.A 3.b.1 and the basis for Section 4.6 until an Emergency License Amendment can be submitted and approved. That License Amendment will request authorization to delay performance of the incomplete portion of the surveillance testiny .. buses 16 and 26 until completion of the electrical system upgrade modifications of the station blackout project during the two
, . unit outage scheduled to begin in October 1992.
As discussed above, even though Unit 1 4160V bus 16 was declared inoperable at 1600 on July 27, 1992, the bus is energized and its related controls remain available and capable of responding to any plant transient. Based on the results of past testing a high degreo of confidence exists that all electrical functions are fully operable.
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4 USt@C July 29, 1992 Northern States Power Company Page 5 l
i jinnificant llazards Consideration Evaluation I
This request for Temporary Waiver of compliance has been evaluated to
- determine whether it constitutes a significant hazards consideration. This analysis is provided below
1
- 1. The requested Temporary Vaiser of Compliance will not involve a significant i
) increase in the probability or consequences of an accident previously !
j evaluated. )
l j Assumin6 that incomplete surveillance testing results in inoperable voltage i restoration logic, only 4160V buses'16 and 26 would be a"fected. 4160V buses 15 and 25 are still within the required surveillance test interval l
j and remain operable. Therefore, consistent with the plart accident analysis, at least one train of safeguards components would remain operable
} on each unit.
Even though Unit 14160V bus 16 was declared inoperable at 1600 on July 27 i 1992, the bus is energized and its related controls remain available and capable of responding to any olant transient. Based on the results of past
{. testing a high degree of confidence exists that all electrical functions l are fully operable.
)
l Therefore, the requested Temporary Waiver of Compliance vill not i significantly affect the probability or consequences of an accident l previously evaluated.
I '
- 2. The requested Temporary Waiver of Compliance will not create the
! possibility of a new or different kind of accident from any accident ;
I previous 1v analyzed.
2 There are no new failure modes or mechanisms associated with the requested
- Temporary Waiver of Compliance. The requested Temporary Waiver of ;
j Compliance does not involve any modification of plant-equipment or changes in operational limits, it only requests the delay of a portion of the -
surveillance testing of the voltage restoration logic.;
Therefore, the requested Temporary Whiver of Compliance does not create the possibility of a new or different kind of accident from any previously evaluated, and the accident analyses. presented in the Updaced Safety -t Analysis Report will remain bounding.
- 3. The requested Temporary Vaiver of Compliance will not involve a significant: >
reduction in the marrin of safety, i
-Assuming that incomplete surveillance testing results in inoperable voltage restoration logic, only 4160V buses 16 and 26 would be affected. 4160V buses 15 and 25 are still within-the required aurveillance test inte rval and remain operable. Therefore, consistent with the plant accident analysis, at:1 east-one. train of safeguards components would remain operable.
on each unit, p
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4 USJ1RC July 29, 1992 Nodhorn States Power Company Page 6 Even though Unit 14160V bus 16 was declared inoperable at 1600 on July 27, 1992, the bus is energized and its related controls remain available and capable of responding to any plant transient. Based on the results of past testing a high degree of confidence exists that all electrical functions are fully operable, Thorofore, the requested Temporary Waiver of Compliance will not result in any reduction in the plant's margin of safety.
Based on the evaluation described above, Northern States Power Company has determined that operation of the Prairie Island Nuclear Generating Plant in accordance with the requested Temporary Valver of Compliance does not involve any significant hazards considerations ao defined by NRC regulations.
Environmental Assessment The requested Temporary Waiver of Compliance does not change effluent types or total offluent amounts nor does it involve an increase it; power level.
Therefore, this change will not result in any significant environmental impact.
Operations Comt.ttee Review end Approval The Plant Operations Committee has reviewed and approved this request for a Temporaty Veiier of Compliance.
Please contact us if you have any questions related to this request for a Temporary Waiver of Compliance.
hasThomasMParker Manager Nuclear Support Services c: Regional Administrator Region III, NRC Senior Resident Inspector, NRC NRR Project Manager NRC J E Silberg 4
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