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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: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
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TAHf June 17, 1997 Mr. M. Wadley, Vice President Nuclear Generation Northern States Power Company i
414 Nicollet Mall l Minneapolis, MN 55401 l
SUBJECT:
PRAIRIE ISLAND MANAGEMENT MEETING I
Dear Mr. Wadley:
On May 20,1997, the NRC met with Northern States Power (NSP) management at the Region til Office in Lisle, Illinois.
The purpose of the meeting was to discuss the declining operations performance at Prairie Island Nuclear Generating Plant. Enclosed are copies of the agenda and handout provided by NSP staff at the meeting. ,
in accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosures will be placed in the NRC's Public Document Room.
We appreciate NSP's cooperation in this matter.
Sincerely, Orig, signed by Ronald N. Gardner for )
Geoffrey E. Grant, Director Division of Reactor Projects Docket No. 50 282 Docket No. 50-306
Enclosure:
Agenda and Handouts from May 20,1997, meeting -
Uplumppsu Document: R :\Ltrs 2lic\N S P\Prai\ pra 06107.d r p To receive a copy of this document, indicate in the box "C" = Copy without attach /enci "E" = Copy with attach /enci "N" = No copy OFFICE Rlll O 2
'k11C N NAME JMcB:dp 9p1f b GtWaAY k/Y DATE 06/ly97 N f'17 OFFICIAL RECORD COPY V
9706270293 970617 PDR ADOCK 05000282 P pon
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! Plant Manager,' Prairie Island John W. Ferman, Ph.D.,
Nuclear Engineer. MPCA State Liaison Officer, State
! of Minnesota State Liaison Officer, State .
of Wisconsin Tribal Council l Prairis Island Dakota Community Y lY b
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NSP-NRC MANAGEMENT MEETING May 20,1997 Agenda i
Conduct of Operations issues Dick Lindsey, General Superintendent Safety Assessment Operations Human Performance Imorovement Initiatives Terry Silverberg, General Superintendent Plant Operations Operations Self Assessments Joel Sorensen, Plant Manager ,
i PIl Report Dick Lindsey, General Superintendent Safety Assessment
. _______I
~
i CONDUCT OF OPERATIONS
- ISSUES ESF ACTUATIONS IN 1996 ,
INTENTIONAL ENTRY INTO TECHNICAL SPECIFICATION 3.0.C EXCESSIVE DRAINING OF THE REACTOR COOLANT
- l UNINTENTIONAL DILUTION OR POSITIVE REACTIVITY ADDITIONS
> o NUMBER OF ACTUATIONS
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ESF ACTUATIONS IN 1996 i i
TWO IN THE THIRD QUARTER, ;
ONE IN THE LAST QUARTER ERROR TYPE - ;
SKILL BASED ERRORS - INADEQUATE SELF CHECKING CORRECTIVE ACTION -
SELF CHECKING CULTURE IMPROVEMENT SURVEILLANCE PROCEDURE UPGRADE PROGRAM
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. -l INTENTIONAL ENTRY INTO TECHNICAL SPECIFICATION 3.0.C 1
ERROR TYPE -
RULE BASED ERROR CORRECTIVE ACTION -
SUPERVISOR TRAINING
er EXCESSIVE DRAINING OF THE REACTOR COOLANT ERROR TYPES - :
RULE BASED ERROR - PROCEDURE COMPLIANCE SKILL BASED ERROR - VALVE MISPOSITIONED CORRECTIVE ACTION -
COMPREHENSIVE ASSESSMENT OF PROCEDURE i COMPLIANCE ISSUE & IMPLEMENT RESULTING IMPROVEMENTS PROCEDUREIMPROVEMENT I INDIVIDUAL COACHING AND COUNSELING
~
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UNINTENTIONAL DILUTION OR POSITIVE REACTIVITY ADDITIONS ERROR TYPE -
RULE BASED - PROCEDURE COMPLIANCE !
CORRECTIVE ACTION -
lMPROVE PROCEDURES COMPREHENSIVE ASSESSMENT OF PROCEDURE COMPLIANCE ISSUE & IMPLEMENT RESULTING IMPROVEMENTS i EVALUATE SWl-O-10, OPERATIONS MANUAL USAGE, for ' PROCEDURE IN HAND' REQUIREMENTS !
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- 1 PRE-JOB BRIEFS
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1994 INSTITUTED AS A SPECIAL PROCEDURE INCORPORATED INTO STANDING PROCEDURES l STRESSED IN TRAINING SUPERVISION BELIEVE IN IT
- DEMAND IT BECOME OUR CULTURE
~
~
COMMUNICATIONS 1995 OLD STANDARD CONFUSING 4
- NOT ENFORCED DEVELOPED NEW STANDARD
- COMMUNICATION TRIANGLE i
1 TRAINED AND PROMOTION
- FILM SUPERVISION BUY-IN
-SUPERVISION DEMAND IT BECOME PART OF OUR CULTURE
~
SELF-CHECKING 1996 HUMAN PERFORMANCE DECLINE l -SKILL BASED ERRORS STRESS OF MANAGEMENT l EXPECTATIONS DROP IN SKILL BASED LER'S '
MORE TO DO--Pil
- RECOMMENDATIONS BECOMING CULTURE l
.i E
PROCEDURAL COMPLIANCE 1997 ,
ERTF CREW SOLUTION MUST BE i
- PRACTICAL
- EASILY UNDERSTOOD
- BELIEVED IN MUST BECOME PART OF OUR CULTURE!
_ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _______________.I
. i
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OPERATIONS TACTICS CREW SIMULATOR LISTS
-STARTING POINT FOR MANY INITIATIVES REDUCE OPERATOR STRESS
- GSPO VISION MEETINGS
- OUTAGE WORKING HOURS PROMOTING E&A VISITS :
- t i
i OPERATIONS TACTICS :
DEPARTMENT STAFFING
-YEAR ROUND WORK CONTROL CENTER
- SRO'S TO TRAINING ,
UTILIZATION OF CREWS FOR PERFORMANCE ISSUES ISSUES RESPONSE COORDINATOR l
Operations Self Assessments
" Assessment of Operations Outage Implementation and Related Human Errors"
- Requested by GSPO
- Organizational and Programma:ic Study
- Completed 4th Quarter of 1995 by NSP ERTF
- Looked at O oerator Inappropriate Actions from 1989 to mid 1995
- CCA, survey, and interviews
_m.
o Percentage of Inappropriate Actions by Human Error Type from 1989 to mid 1995 by NSP .
80%_
70%.
60%- o <-T e
l 50'/o -
{ m Skill Based 40%_ j ------~
m Rule Based 30%_ ( y E Knowledge Based 20% _ g O Normal 10%- ?
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t 0%- h k b <
Skill Based Rule Based Knowledge Based l
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" Assessment of Operations Outage
~
j Implementation and Related 1 Human Errors" Corrective Actions Taken
- Outage Shift Manager (Shift Outage
. Coordinator)
! - SRO on floor for critical outage evolutions
! - Management expectation for supervisors' responsibility for causes of operator inattention to detail (alertness, reduce time pressures, distractions, etc.)
-Individual S':atus Report (ISR) used to prioritize SM/ Crew work commitments l
~l NSP Nuclear Generation Excellence in Human Performance Survey Completed in August,1996 4
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! Survey of employee work place
- attitudes and perceptions First attempt at leading indicators
! Surveyed all departments including Ops Surveyed areas of
- Individual Behaviors i
- - Leadership Behaviors l
- Organizational Behaviors
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~l Excellence in Human Performance Survey Areas for Improvement i
Individual Behaviors
- Methods to check co-workers Leadership Behaviors l - Address personality conflict to minimize impact Organizational Behaviors
- Eliminate jury rigs l
~
- l Why did PI need outside opinion ?
Study done by NSP in 1995 showed excessive rule based errors
-Yet events in 1996 showing excessive skill basec
- Were inappropriate actions being ,
categorized correctly ?
- SAC recommended outside look similar to Monticello Validate Human Performance Survey l
4 t
y FPl/Pil Common Cause Analysis of Operations Human Performance Concerns Requested by GSPO, GSSA, PM Organizational and Programmatic Study '
Look:ed at Operator Inappropriate Actioris in 1995 and 1996 CCA, survey, and interviews
' .l
.l
-l Percentage of inappropriate Actions by Human Error Type from 1995 &1996 data by Pil 80b1 70%_ --
60%. - !
50'/o -
M n g
B Skill Based a
40%-
F m
E Rule Based '
30%. g s a Knowledge Based '
20%. - c4 O Normal 10%- h h h i 5 g 0%_ ~ _, _ P, Pc 1- i Skill Based Rule Based Knowledge Based i
i
Pil Common Cause Analysis of Operations Human Performance Concerns General Conclusions
-Ina apropriate actions were being categorizec correc:ly
- But, industry " norms" were incorrect in our 1995 study
- Further comparison of leading indicator surveys needed ,
-i Percentage of inappropriate F Actions by Human Error Type 1st Quarter 1997 by NSP i
80% a l
70%- i t
60%- ql 50'/* -
i cr 40%-
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E Skill Based E Rule Based e :
30%- f E Knowledge Based ;
j O Normal 20%- .
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- 10%- i
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Skill Based Rule Based Knowledge !
Based
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WHAT WERE Pil's CONCLUSIONS? 1 HUMAN PERFORMANCE IN THE OPERATIONS GROUP IS DECLINING i
THE DECLINE IS NOT ISOLATED TO OPERATIONS SEVERAL FACTORS EXTERNAL TO THE OPERATIONS GROUP HAVE COMBINED TO INCREASE THE BASE ERROR
. RATE, WHILE AN EFFECTIVE MANAGEMENT CONTROL LOOP (CONTINUOUS IMPROVEMENT LOOP) IS NOT IN PLACE j THE EXTERNAL FACTORS CAN BE COLLECTIVELY CONSIDERED AS " WORK STRESS" i
" Changes in the industry due to utility deregulation have led to NSP initiatives to reduce cost. The department experiences some of these in the form of; staff reduction via attrition and hiring freezes, changes in work hour.s to reduce overtime, increased work load due to the same (or fewer) Operators performing more work, increasingly unpopular bargaining unit contract proposals, etc."
i "The Nuclear Industry continuously focuses more attention on human performance, with less tolerance for errors, increasing the " fear of failure"."
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"Several management changes have occurred. The new management is perceived by the staff as being q very technically competent, though less humanistic than previous management teams. This induces work stress, while limiting the ability of the staff to deal with the existing stress."
" Prairie Island has a long history of recognition as a top performer by the NRC and INPO. This adds further to the " fear of failure" factor in work stress, as no operator wants to be the one whose error leads to ending this recognition."
"The first symptom of long-term work stress is a high rate of " inattention-to-detail" human errors." We had this symptom.
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Pil conclusions, cont.
....... the following conclusions can be made Prevention Human error prevention / avoidance skills of workers and supervisors are not l comprehensive in nature.
i Weaknesses exist in implementing the accountability program for human error reduction. !
Detection !
Trending and Monitoring capabilities for the department's human performance are weak. !
Only " Lagging" indicators for human performance are used. " Leading" and :
"Real-Time" indicators are not utilized.
Correction i
Root cause analyses do not always address the organizational and programmatic contributors to the events."
i Note the similarity to the Continuous improvement model- of Plan, Do, Check, Adjust '
t
. 1 Pil's RECOMMENDATIONS 1
ENHANCE SELF-ASSESSMENT, ROOT CAUSE ANALYSIS AND PERFORMANCE MONITORING & TRENDING.
t PROVIDE INTEGRATED HUMAN ERROR PREVENTION t TRAINING
?MPROVE SHIFT SUPERVISION ACCOUNTABILITY FOR CREW ERROR PREVENTION / REDUCTION VERTICAL COMMUNICATION SHARE THE RESULTS OF THE REPORT WITH OPERATORS i
PLANS FOR IMPLEMENTING HUMAN PERFORMANCE IMPROVEMENT BASED ON Pil ANALYSIS !
PROMPT ACTION IMPROVE WORKER ERROR PREVENTION SKILLS Pil 1 day course Optional PI Instructor certification IMPROVE SUPERVISOR ERROR REDUCTION SKILLS Pil 2 day course Optional PI Instructor certification IMPROVE MANAGEMENT ERROR REDUCTION SKILLS :
Pil 1 day course Pil has been asked to submit a new proposal that includes Monticello and Prairie Island j ASSESS ADMINISTRATIVE LOAD ON LPERO, SS, SM and OTHERS l f
=
INTERMEDIATE TERM ACTIONS UTILIZE LEADING INDICATORS AS A PREDICTOR OF PERFORMANCE t
Option A - Have Pil do their Culture Assessment on a yearly basis t
Option B - Develop our own Leading Indicator based on the Human Performance initiative survey - to be done on a yearly basis Compare and contrast the HPI survey with the one given by Pil i i
Compare and contrast the HPI survey results with Pil results See if an integrated (HPI, new INPO fundamentals course & Pil) !
approach to corrective actions is feasible !
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i REFINE OUR LAGGING AND REAL-TIME PERFORMANCE INDICATOR PROCESSES l Refine Employee Observation Report (EOR) system to provide the needed information !
Increase the use of the EOR process for problem reporting - '
Ops, Maint, I&C, RP, etc.
IMPLEMENT SUPERVISORY TRAINING PLANS i
THESE PLANS WERE DERIVED FROM THE HPI SURVEY CONCLUSIONS !
6 k
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LONG TERM ACTIONS CONTINUING (REFRESHER) TRAINING OF THE ITEMS IN THE ' PROMPT ACTION' SECTION DEVELOP AND USE CONTINUOUS IMPROVEMENT MODELS FOR PLANT WORK GROUPS TRAIN PLANT PERSONNEL IN HUMAN PERFORMANCE FUNDAMENTALS This is a new INPO course. Monticello and Prairie Island are sending two people each to ' Train the Trainer' courses this year
- Monti in May and PI in August CONTINUE SUPERVISORY TRAINING PLANS I