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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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i MI Northern States Power Company 1
,, Pralrle Island Nuclear Generating Plant 1717 Wakonado Dr. East Welch. Minnesota $5089 November 13,1997 10 CFR Part 2 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50 282 License Nos. DPR-42 50-306 DPR-60 Reply to Notice of Victation (Inspection Report 97012),
Deficiencies in the Fire Protection Program Your letter of October 14,1997, which transmitted Inspection Report No. 97012, required a response to a Notice of Violation. Our response to the notice is contained in the attachment to this letter.
l in addition, you requested responses to twc Unresolved items. These responses i immediately follow.
URI 97012-01 Hot Shorts with Valve Damage:
1 As indicated in the inspection mport, we willperform additional reviews of the hot short problems following the completion of the safe shutdown analysis currently being revised. After completion of the analysis a revised list of MOVs that are susceptible to hot shorts will be developed and further reviews will be made for <
those MOVs. Information Notice 92-18 will be used for guidance in these additionalreviews. i URI 97012-08 Fire Brigade Drill Requirements:
We are in the process of reviewing all of the commitments made relating to tho l Fire Protection Program. After this review is completed the commitments will be '
assessed against practices allowed by our administrative procedures and any discrepancies between our fire brigade drill commitments and procedures will be t corrected. .
ffU \
9711200012 971113 PDR ADOCK 05000282
,(r O pon g
USNRC NORTHERN STATES POWER COMPANY November 13,1C97.
..* ' Page 2 -
In this letter and attached response we have made new Nuclear Regulatory Commission commitments, these are indicated by italics.
Please contact Jack Levellie (612-388-1121, Ext. 4662) if you have any questions related to this letter.
/
oel P Sorensen Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator - Region lil, NRC Senior Resident inspector, NRC NRR Project Manager, NRC J E Silberg
Attachment:
RESPONSE TO NOTICE OF VIOLATION IR97012. DOC
l.
4
.. RESPONSE TO NOTICE OF VIOLATION l VIOLATION 1 10 CFR 50.71(e) required that revised portions of the Final Safety Analysis Report (FSAR) be submitted to the NRC.
Contrary to the above, on July 1,- 1994, substantial revisions were made to the Fire Hazards Analysis (FHA) (referenced as a portion of the FSAR) that were not submitted to the NRC.
This is a Severity Level IV violation (Supplement 1).
Resoonse to Violation 1
- Reason for the Violation Control & maintenance of the Fire Hazard Analysis (FHA)is outlined in several PINGP site documents. The Prairie Island FHA is currently located in Operations manual section F5 Append!x F. The USAR outlining the Fire Protection Program is located in USAR section 10.3.1. Current practice for control and maintenance of the FHA and-USAR documents are outlined in SAWI 3.13.0," Fire Preventative Practices," 5AWI 3.13.1 " Fire Protection Review of Plant Modifications," and SAWI 4.9,0 " Safety Analysis Reports" as well as other site procedures which use processes to evaluate and make required changes. The documents identified above use the FHA and USAR in separate text and use separate processes for making changes to each.
Prior to this NRC inspection, Prairie Island viewed the FHA as a separate document than the USAR section.
Corrective Actions Taken:
During an unannounced fire protection inspection in March of 1994 the inspector identified a violation relating to timely updates to the facilities FHA. Following the -
issuance of this violation we completed a revision to the FHA that included incorporation of all modifications completed since the previous revision where the FHA was impacted, in addition, the facility developed an Administrative Work Instruction, 5AWI 3.13.1,~ " Fire Piotection Review of Plant Modifications," that implemented .
requirements for reviews of modifications that may impact the Fire Protection Program for the facility. This Administrative Work Instruction has been in effect 'since the inspection of 1994. Changes were made to the FHA as indicated in our response to Violation 282/306/94004-1b dated May 2,1994. In this response we did not indicate that we would or understood we were required to submit the updated FHA to the NRC
' for review. NRC GL 88-10 requires all changes to the approved program be reported
- annually to NRR along with FSAR revisions. A major revision to the FHA could be
Attaennc.
Ngygmber 13,1997 Page 2 considered a program change; however, all that was done was to update the fire
' loading portion of the FHA and to identify the more conservative methodology used to complete this update.
We are currently revising the Safe Shutdown Analysis which will require changes to the FHA. The revised FHA will be submitted during the first USAR update submittal of 1998.
Action to Be Taken to Prevent Recurrerice A procedure change request was submitted for SAWI 4.1.0, Plant Operations and Site Engineering Manuals to require that any changes made to the Fire Hazards Analysis be submitted to the site Licensing Department for inclusion with the next USAR submittal
, to the NRC.
. Date When Full Comoliance Will Be Achieved The Praide Island Fire Hazards Analysis will be submitted with the first USAR submittal of 1998.
d IR97012. DOC
Attachment November 13.1997 Page 3 VIOLATION 2.a Prairie Island Technical Specification 6.5.A.7 required that detailed written implementing procedures be prepared and followed for the fire protection program.
- a. Administrative Work Instruction 5AW13.13.0, " Fire Preventive Practices,"
Paragraph 6.9.6, stated: " Individual Fire Brigade members SHALL actively participate in at least one drill per year."
Contrary to the above, during 1996, SAW13.13.0 was not followed in that 7 members of the fire brigade did not actively participate in fire brigade drills.
This is a Severity Level IV violation (Supplement 1).
Resoonse to Violation 2.a Reason for the Violation !
The reason for the violation was that we interpreted " active participation" to include participation from the control room functions during a fire scenario. We are unaware of the existence of clear NRC guidance on the meaning of " active participation."
i Corrective Actions Taken l i-ollowing the identification of this issue by the inspector we removed from Fire Brigade l duty those individuals that had not participated as a member of the fire brigade at the l
scene of a drillin the past 12 months. In the following days, additional fire drills were conducted and the individuals who had not previously participated in a fire drill at the drill scene did participate as brigade members at the drill scene. Following this participation these individuals were returned to active Fire Bngade status, it should be noted that these individuals had all participated in hands-on fire brigade training, during l the preceding 12 months, which includes full suit-up and full participation in fire fighting I scenarios. l Corrective Actions to Prevent Recurrence j 1
We will change our administrative requirements to identify that A.CTIVE participation in 1 a Fire Drill willrequire fire brigade members to respond to the location of the simulated fire in fullprotective equipment and willinvolve participation in fire brigade activities to extinguish er'd prevent the spread of fires simulated for the drill. We will develop a
\ program to track this ddllparticipation and fire brigade qualifications willrequire this active participation in drills. The program will be in place by March 1,1998.
Date When Full Comoliance Will Be Achieved Full compliance has been achieved. '
l 1R97012. DOC
.- . . - . ~ ~ - _ - - _ - .- = -
I Attachment l November 13.1997 ;
Page 4 l VIOLATION 2.b-Prairie Island Technical Specification 6.5.A.7 required that detailed written implementing procedures be prepared and followed for the fire protection program.
- b. Prairie Island Administrative Work Instruction SAWI 3.4.0, *QA Records Control,"
Revision 4, stated in paragraph 6.2.3: " Records that meet one or more of the following criteria SHALL be classified as lifetime records: a. Would be of significant value in demonstrating capability for safe operation of a safety related or fire protection related item."
Contrary to the above, the December 12,1996, detector surveillance data documented during fire protection surveillance SP 1189," Safety Related Fire Detector Check," was not available for inspector review because it had been discarded.
This is a Severity Leve! IV violation (Supplement 1).
Resoonse to Violation 2.b Reason for the Violation The inspection repost states:
The inspector identified that detector surveillance data documented during SP 1189, " Safety Related Fire Detector Check," Revision 16, was not available for inspector review because it had been discarded. Only the cover sheets of surveillances were saved. The licensee stated this was allowed by the licensee's Administrativo Work Instruction, 5AWI 1.5.0, Revision 2, in Paragraph q.3.d.
It is true that we stated that the discarding of pages from the completed surveillance procedure was allowed by Administrative Work Instruction SAWii.5.0, which states that pages of standing procedures may be discarded if several requirements are met, including:
The discarded pages SHALL contain only routine, initialed steps and no data, dates or signatures.
The discarded pages of SP-1189 contained only routine, initialed steps and did not contain dates or signatures. We have questioned whether these routine, initialed steps constitute " data" or provide " significant value in demonstrating capabi!ity for safe operation of a safety related or fire protection related item." We have discovered that we have an internal disagreement regarding this question in general. However, in the case of SP-1189, the procedure itself refers to the information in the table (the initials) as test results. Test results must be maintained as quality records. Therefore, we IR91012. DOC
- Attachment November 13,1997 Page5 acknowledge the violation but have not determined that it extends beyond this particular
' procedure.
Corrective Actions Taken 6 The discarded surveillance pages have not caused us to doubt the operability of the fire detectors. The cover sheet, which is maintained:
e documents completion of the test by the signature of the performer (along with the date and time),
e acceptability of the test results, documented by the signature of the fire protection administrator, e documents, by signature, the system engineer review of the test for completeness e documents necessary corrective maintenance by referring to work orders generated in addition,-any pages with deviations are maintained with the coversheet. Because revisions of surveillance procedures are maintained, it is possible to recover the specifics that were addressed by past surveillances of the fire detectors.
The information is available from the preserved documentation to make appropriate safety, operability, or reportability determinations. We, therefore, believe that no repeated surveillance is deemed necessary.
Corrective Actions Regarding Fire Protection Data Retention We will revise SP-1189 to require the retention of allpages that contain any documentation ofperformance (priorto the next performance of the test). As discussed in the reason for the violation, the violation resulted from the procedure calling out the information in the table as test results;" we are not considering this to be a global concern and are not currently changing our retention practice for other than fire detector surveillance procedures. Further action is dependent on the conclusion to be determined as discussed in the following section. We may elect to subsequently re-revise the retention practice for SP-1189 as a result of that determination.
Corrective Actions to Preclude Recurrence We will determine the acceptable definition of data (in particular, as it relates to test
' results) and revise the administrative workinstruction(s) as necessary. If a revised concept of data is incorporated into the administrative work instruction (s), we will perform an appropriate review of other surveillance procedures for conformance.
Date When Full Comoliance Will Be Achieved Full compliance has been achieved, we are currently maintaining ~ completed fire detector surveillance procedures in their entirety.
IR97013.COC
. Attachment November 13,1997 Page 6
- VIOLATION 2, c Prairie Island Technical Specification 6.5.A.7 required that detailed written implementing procedures be prepared and followed for the fire protection program.
- c. Surveillance Procedure (SP) 1192, " Safeguards Electrical and Mechanical Penetrations Surveillance Inspection," Revision 7, requires the verification of penetration seal operability through visual inspection.
Contrary to the above, on April 4,1997, SP 1192 was not followed in that 8 penetrations were not verified to be operable.
This is a Severity Level IV violation (supplement 1).
Resoonse to Violation 2.c Reason for the Violation There are approximately 100 sketches attached to surveillance procedure SP-1192.
The surveillance procedure outlines several steps for completing the work. lt directs the inspector to plact checkmarks by the individual penetrations on the sketches; this is to keep track of thein because there are several on each drawing. The procedure also directs the inspector to initial and date each sketch when it has been completed. A field or working copy of the inspection procedure is used while performing the penetration inspections. The field information is then transferred to an office copy which is used as the master work order. The craft inspector assured us the penetrations had been inspected although he had not properly transferred the checkmarks onto the master copy of the work order, causing the violation.
Note that the engineering review after all the work has been done verifies by each page signoff that all the penetrations were checked, not by looking for individual checkmarks on each sketch.
Corrective Actions Taken When the question arose whether or not the inspections had been performed for the subject penetrations, a roving fire watch was established for the penetrations noted as being possibly inoperable and a. work order issued to inspect those penetrations that were not indicated as being inspected on the sketches. These penetrations were inspected and found to be intact and acceptable.
Actionig Preclude Recurrence Ths surveillance procedure has been submitted to the Enor Reduction Task Force (ERTF) for a Human Factors review and will be modified following this review based on IR970kJ. DOC-
, Attachment November 13,1997 Page 7 the tecorninendatiuhs 6f thd ERTF, Through improvementa in the human perfo_rmance
, ,- aspects of the surveillance and its logging of completion of inspections the ability to
_ properly determine if all penetrations were inspected will be enh6nced.
Date When Full Comoliance Will Be Achieved Full compliance has been ach!eved.
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4 IR97012. DOC
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