|
---|
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
[Table view] |
Text
,x _ , . , , , .e. .
a Y
, - , ~ .
D"s - Northem States Power Company -
j, 3 a
P< , Prairie Island Nuclear Generating Plant _
1717 Wakonade Dr. East-Welch, Minnesota $5089 M
1 1 Septiember 24, 1990 L .,
t h - dr B Clayton, Chief _ '
- Projects- Branch 2. Region III
- - U S. Nuclear Regulatory Commission
? 799: Roosevelt Road
. - Glen Ellyn,f1111nois E 60137 PRAIRIE IS1AND NUCLEAP, GENERATING PIANT Docket Nos. 50 282 License Nos. DPR-42 50-306 DPR 60 Response to Notice of Violation Insoection Reoorts No. 50-282/90012(DRP) and 50-306/90012(DRP) s s
.In response to your letter of August 27, 1990, which transmitted Inspection-Reports'No. 282/90012 and 306/90012, the following information is offered.
_-o Violation #1'
' Technical Specification 3.6.H. Shield Building' Ventilation System allows-only one train to be inoperable with reactor coolant system x average. temperature abovel200* F. With both trains inoperable.
Technical ~ Specification 3.0'.C applies and states in part; when a Limiting Con'dition for operation is not met, and required action is nct specified or cannot be' satisfied, within one h.ur initiate the ..
action necessary to place the affected' unit in-a condition in which, the equipment is not required to be:0PERABLE.
Contrary to the .above, on June 27, 1990, with Unit 1 above 200* F, from approximately 8:20-_a.m, to 10:10 a.m., both the Number 11 and 12 Shield Building Ventilation Systems were rendered inoperable by the improper opening = of the Number 11 exhaust fan breaker. Action was not initisted to place' Unit 1-in a. condition for which the. Shield Building V ntilation System was not required to be operable ~ within one hour (132/90012-02).
This u, a Severity Level IV Violation (Supplement ;I) .
Resoonse O '10 F' Preveritive maintenance was scheduled for the No.12 Shield Building 9010010179 900924 PDR O
ADOCK 05000202 PDC g
- tj o :
,c s
t at_,- .
f
l'
.. i I 1 M- B Clayton- ,
-September 24, 1990- ;
^
-Page,2
' Ventilation System. Exhaust Fan, the' Recirculation Fan, and the filter heater
-contactors. Prior to maintenance.beginning,.the three respective isolation
' breakers were to be turned off. The breakers-for the Recirculation' Fan and '
the- filter ; heater were properly turned off. When maintenance was to begin_at
- 1005,itfwas;discoveredthatNo. 11 Exhaust Fan-breaker had been turned off instead of No. 12~ Exhaust Fan breaker. This made~the No. 11 Exhaust Fan-inope rable '. .Since the No. 12 Exhaust Fan (whose-breaker was left on) is ;
interlocked with No. 12 Recirculation Fan (whose breaker was turned off), the No. 12 Exhaust Fan was also inoperable. 'The exhaust fan can only run when the-recirculation fan is running. The initial evaluation concluded that both trains of the Shield Buildins Ventilation System had been made inoperable, '
since no Shield Building Exhaust Fans were operable. At 1010, the breaker for No. 11 Shield Building Exhaust Fan was turned on.
The violation states that no action was taken within one hour to change the plant condition. Technical Specifications Section 3.0.C states, " Time- ,
limitations specified by the applicable Limiting Condition for Operation L actions are measured from the time of discovery of the failure to meet the Limiting Condition for Operation." Section 3.0.C allows one hour to initiate action to place the affected unit in a condition in which the equipment is not required to be operable. 'No action was taken to place-Unit 1 in a condition for'which the Shield ' Building Ventilation ' System operability was not required, l
.since the No. 11 Shield Building Exhaust Fan breaker was turned on within 5' minutes of discovering it in the off position. ,
f The incorrect breaker had been turned off. the preventive maintenance procedure contained an error in component numbering,- The motor number and component description given in the text of the procedure were correct, but the !,
[
H Motor Control Center number given at the top.of each page of the. preventive
-maintenance procedure was incorrect. The workman turned off the breaker L corresponding to the incorrect Motor Control' Center number.
I I l :The safeguards function of the Shield Building Ventilation System is to
, collect, mix and filter air leakage from the containment vessel to the-annulus
'- following a postulated accident before it is either recirculated or discharged to.the atmosphere. If the Shield Building Ventilation System had been called
, uoon to actuate while in this condition, only No. 11 Shield Building
! kecirculation Fan and its particulate absolute charcoal filter would have l
operated. However, a test performed on June 13, 1990, shot-d that with both ;
exhaust fans and one recirculation fan disabled, the required drawdown and performance characteristics of the Shield Building Ventilation System detailed
? '
Note that the recirculation fan provides in. Tech Spec 4.4B-1 were still met.
l- both recirculation and exhaust flow. Flow capacity of a recirculation fan is 5000-cfm,-while the flow capacity of an exhaust fan is only 200 cfm.
Therefore, the Shield Building Ventilation System was capable of performin5 L its safeguards function in this degraded eondition.
This event was reported as Unit 1 LER 90-008.
L 1
,e;n , ,
v s .
t
[i; * "
y3
~1B Clayton
- September 24, 1990 Page.3~
t Corrective ~ Action Taken and Results Achieved i At' discovery, the' breaker for No. 11 Shield Building Exhaust-Fan was turned on "
-and an operability test for Train A was done. Motor Control Center preventive
= maintenance procedures for all other safeguards equipment were reviewed for similar errors. One other error was found and corrected.
Corrective Action to Avoid Further Violations Routinely, isolations for Motor Control Center preventive maintenance have .
been performed by the personnel performing the maintenance. Procedures will.
be revised to involve operations personnel in the performance of equipment isolations; this will-have the effect of getting another review of these isolations.
Date When Full Como11ance Will be Achieved Full compliance has been achieved.
Violation 42 Technical Specification 4.1 specifies minimum frequency and types of surveillance to be applied to plant equipment and conditions. l Technical Specification 4.0 states, in part, that the specific time intervals between tests may be adjusted plus or minus 25 percent to accommodate normal test schedules. Technical Specification 4.1.A requires calibration, testing and checking of instrument channels be
+ performed as specified by Table T.S. 4.1-1.
Contrary to the above:
- a. The instrument channels (item 32) for RTD (reactor coolant) i Bypass Flowneter are to be functionally tested monthly by L Surveillance Procedure SP1042, Resistance Temperature Detector L (RTD) Bypass Flowmeter Functional Monthly Test. Surveillance l procedure SP1042 was due to be performed no later than April 16, l
1990, and was not completed until April 24, 1990 (282/90012-03A; L
306/90012-03A),
- b. The instrument channels (item 35b) for radiation monitors (listed in Table T.S. 3.15-2) are to be functionally tested monthly by Surveillance Procedure SP1028, Radiation Monitoring System Test. Surveillance Procedure SP1028 was due to be
- performed no later than April 18, 1990. The test was not performed until April 20, 1990 (282/90012-03B; 306/90012-03B).
This is a Severity Level IV Violation (Supplement I).
a-
v > <
p a
, . 4; 4
]
-* . , 1
-+ ,
BlClayton . 1 September 24, 1990 9 1Page-4l
~
$ y
.Resoonse to' Violation 42a.
SP10421s' a monthly functional test of the reactor coolant system RTD-bypass .
Eloop flow meters.1 The scheduled-due date for completion of SP1042 for the ;
month of April was April 16, 1990. Technical Specification Section 4.0 allows f surveillance test due dates to be adjusted plus or minus 25% to accommedate e normal test schedules.. The last day of the 25% grace period for the April performance of SP1042 was April 23rd. ' +
The I&C supervisors, one assigned to each unit, are responsible for the' I
~
i scheduling and performance of the I&C surveillance procedures. The Unit 1 I&C supervisor was aware that April 23 was the last day of 25% graco period -
for the completion of SP1042 for the month of April. F - .ser, the Unit 1 I&C 4 supervisor. was not'onsite on April 23, and he failed to assign an I&C s -technician to: perform SP1042 prior to his departure.
The Unit .1 I&C supervisor noticed on his return to work on April 24, 1990 that
-SP1042 had not been performed on April 23 as required. The Unit.1 I&C
- supervisor immediately assigned an I&C technician to perform SP1042 and it was satisfactorily completed on April 24, 1990.
l This : event was reported as Unit 1 LER 90-004.
Corrective Action Taken and Results Achieved l N
- SP1042 was satisfactorily performed immediately upon discovery that it had not f been completed within the required time period.
^
L M Corrective Action to Avoid Further Violations As;a result of this event, the two I&C supervisors (one for each unit) will <
perform daily reviews of each other's surveillance schedules. This will provide increased assura .ce that surveillance procedures will be performed i within the required time periods.
L
-Date When Full Comoliance Will be Achieved h .
. Full compliance has been achieved.
p.
I
)
v e '
7
_ .Y? +\ r
" i s, s:
n;; -- ,
- J i( '
c- 1 F -B Clayton L September 24, 1990 V Page S:
t Resoonse t'o Violation d2b h .
i SP1028 is a' monthly functional test of the Radiation Monitoring Sysrem. .The scheduled;due date for completion of SP1028 for the month of April was April. $
' 4, 1990. Technical Specification Section 4.0 allows surveillance test due 1
- dates to be adjusted plus or minus 25% to accommodate normal test schedules.
The'last day of the 25% grace period for the April. performance of SP1028 was '
April 11, 1990, but the test was not done until April 20, 1990.
Plant surveillance testing is done in accordance with a master surveillance 4 < schedule. .The Radiation Protection group uses the master schedule to generate '
their own surveillance schedule which is then incorporated into an
.all-inclusiJ work schedule for the group.
On March 15, 1992 *he plant Quality Assurance group pointed out, for a few surveillance proceu. '- hat there were discrepancies between the due dates ,
shown on the master - " _ilance schedule and the Radiation Protection group' schedule. =Between h. con 15 and March 21, 1990, the Radiation Protection Supervisor and the plant Surveillance Coordinator conferred to resolve the discrepancies. As a-result, both the. master schedule and the Radiation Protection group's schedule were changed. SP1028 was rescheduled from April 4-to April' 25, 1990. The Surveillance Coordinator pointed out the need for an L. - additional test,.since the-new due date had been advanced three weeks. Later discussions batween the Radiation Protection Supervisor and his supervisor
- resulted in the mistaken belief that the additional test was not' required and ;
- . was not performed. ,
Radiation Protection personnel misunderstood the necessity for performing an l' additional test. Contributing to the cause was the lack of a written policy l on rescheduling surveillance tests.
l This event was reported as Unit 1 LER 90 010.
' Corrective Action Taken and Results Achieved.
I 1 Plant administrative control documents governing surveillance schedules have been modified to prevent the need for similar rescheduling.
]
Corrective Action to Avoid Further Violations
- Procedures governing surveillance schedule changes will be in place by October
. 31, 1990.
l Date When Full Como11ance Will be Achieved Full compliance has been achieved.
pg --
m- '
7 F g-;m _i . .
- S ipjA s > ,
$y0ll 4 -T,
- ,7 .. c 3 m , ,
.;i;., . . -l; @ ,' t- -j
. , ip ' e
' ~i t '
-r+/ t f
,'B'Clayton-J ti, ' q, September, 24,.1990 ;
si? .7 Page;6 2 ao j
E . - . . ,
,. Please contacc: us if. you have' any questions related to our response to th,e
+l o . ,. : subj ect inspection- reports , .
, tar, b
't'
, j
- N
. P .
n.. ' nLeon- R~ Eliason - i Vice President' -j p ,
Nuclear Generation- l tj c: Regional Administrator III, NRC
'1 Senior Resident: Inspector, NRC
, NRR Project Manager, NkC .i G Charnoff- '
.NRC Document Control' Desk ,
- l i
c' m c t 4
.i.' . ;?
I
/ 6 w
Y
-5
}
4 t
y <
1
,1, ':
i t
')
~j.
.