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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211D7501999-08-23023 August 1999 Responds to NRC Re Violations Noted in OI Rept 3-98-043 & EA 99-183.Corrective Actions:Oversight of Training Program & Contractor Policies That Implement Parts of Security Program Have Been Increased by Addl Position ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls ML17230A3661999-03-18018 March 1999 Forwards Listed Nelia Insurance Policy Endorsements for Kewaunee Nuclear Power Plant,Per Requirements of 10CFR140.15 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20155F7951998-11-0303 November 1998 Second Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App C ML20154F1481998-10-0202 October 1998 Forwards Insp Rept 50-305/98-15 on 980831-0904.No Violations Noted.Insp Exam of Activities Conducted Under License Re Physical Security & to Compliance with Commission Rules & Regulations & with Conditions of License ML20237E0881998-08-24024 August 1998 Clarifies Info Provided Re Containment Ventilation Sys & Use of Mixing Factor of 0.5,in Response to NRC Request Made During Telcon ML20237A2301998-08-0707 August 1998 Forwards Original & Three Copies of Rev 11 to Knpp Security Manual.Screening Criteria Form for Each Change W/Description & Criteria of Review Has Been Included as Attachment A. Reissued Security Manual Included in Attachment B.W/O Encls ML20236R9051998-07-21021 July 1998 Informs That Document Entitled, WCAP-14677,Rev 1 F* & Elevated F* Tube Alternate Repair Criteria for Tubes W/Degradation within Tubesheet Region of Kewaunee Sgs, Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20249B7471998-06-23023 June 1998 Forwards RAI Re 980601 Proposed Amend to Revise F* & Ef* Criteria for SG Tubes in Kewaunee Tss.Proposed Amend Would Revise Existing F* & Ef* Distances in TS 4.2.b to Reflect Changes to Primary to Secondary Differential Pressure ML20249A8751998-06-16016 June 1998 Forwards Request for Addl Info Re Proposed Amend to Redefine Parent Tube Pressure Boundary for Westinghouse Mechanical Hybrid Expansion Joint SG Tube Sleeves,Submitted by Util ML20248M2521998-06-0909 June 1998 Forwards Assessment of Kewannee Cycle 22 Alternate Repair Criteria 90 Day Rept,For Info ML20217F3401998-04-23023 April 1998 Forwards Annual Environ Monitoring Rept Jan-Dec 1997, Per TS 6.9.b.1.Results of 1997 Land Use Census,Iaw Plant ODCM, Section 3/4.7.1,included in Rept ML20216B3281998-04-0707 April 1998 Discusses Amend 132 to License DPR-43.Requested Revised Analysis Reflecting Higher Source Term Encl.Results of Analysis Conclude That Potential Thyroid Doses to Public Continue to Be Less than Guideline Values of 10CFR100 ML20217J2131998-04-0202 April 1998 Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided ML20217H4031998-03-27027 March 1998 Informs That NRC Staff Has Initiated Variety of Activities Re Mgt of Licensing Basis Info as Result of Problems Encountered at Millstone & Maine Yankee Facilities ML20217G1461998-03-25025 March 1998 Responds to NRC Re Violations Noted in Insp Rept 50-305/98-03 on 980128-0203.Corrective Actions:Controlling & Properly Securing SGI ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl ML20212H0121997-11-0404 November 1997 Forwards Insp Rept 50-305/97-14 on 970915-19.No Violations Noted.Rept Identifies Areas Examined within Security Program ML20217P3511997-08-26026 August 1997 Ack Receipt of & Check for $50,000 in Payment for Civil Penalty Proposed by NRC in . Corrective Actions Will Be Examined During Future Insp ML20217J9641997-08-11011 August 1997 Responds to NRC Re Violations Noted in Insp Rept 50-305/97-02 on 970106-31.Corrective Actions:Will Revise IST Procedures to Use More Accurate Instrumentation Satisfying Requirements & to Include Acceptance Criteria ML20140E8861997-06-0707 June 1997 Forwards Amend 133 to License DPR-43 & Safety Evaluation. Amend Establishes New Design Basic Flow Rate for AFW Pumps Consistent W/Assumptions Used in Reanalysis of Limiting Design Basis Event for AFW Sys ML20140F2171997-04-30030 April 1997 Final Response to FOIA Requests for Documents.Records in App B Encl & Will Be Available in PDR IA-97-130, Final Response to FOIA Requests for Documents.Records in App B Encl & Will Be Available in PDR1997-04-30030 April 1997 Final Response to FOIA Requests for Documents.Records in App B Encl & Will Be Available in PDR ML20140F2211997-04-0404 April 1997 FOIA Request for Documents Re Recently Issued TIA for Plant Concerning Safety Question on Auxiliary Feedwater Sys ML20137A2111997-03-14014 March 1997 Transmits Info Pertaining to NRC Staff Review of Weld Defects in CE Designed SG Tube Sleeves ML20134Q0981997-02-21021 February 1997 Ninth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App P.App Q Documents Partially Withheld (Ref FOIA Exemption 6).Documents Also Available in PDR ML20134Q1251997-02-20020 February 1997 Forwards Original & Three Copies of Rev 10 to Knpp Security Manual.Manual Is Being Changed to Incorporate Use of Vehicle Barrier Sys,Per 10CFR73.55 & 73.1(a).Encl Withheld ML20133E7031997-01-0606 January 1997 Forwards Insp Rept 50-305/96-12 on 961118-27 & Notice of Violation ML20133G2291997-01-0606 January 1997 Ltr Contract:Task Order 115, Kewaunee Safety Sys Operational Performance Insp, Under Contract NRC-03-93-026 ML20129K1131996-11-0505 November 1996 Forwards Copy of Master Bwr/Pwr Gfes Exam W/Answer Key for Info.W/O Encl ML20129J2641996-10-29029 October 1996 Ack Receipt of 960613 & 1024 10CFR50.54(a) Submittals Re Changes to Quality Assurance Program Description.Based on Review,Nrc Concludes That Revision Continues to Meet Requirements of 10CFR50,App B & Acceptable ML18065B0081996-10-14014 October 1996 Informs That Overheads Will Be Presented by Licensee at 961016 Meeting at NRC Headquarters in White Flint.Encl Withheld ML20117P6861996-09-20020 September 1996 Forwards Rev 9 to Security Manual.Encl Withheld ML20117L7171996-09-0505 September 1996 Forwards Proposed Tech Specs Re Amend for Use of Westinghouse Laser Welded Steam Generator Tube Sleeves,Per Discussion W/Nrc ML20100M7451996-02-29029 February 1996 Provides Revised Description of Proposed Vehicle Control Measures.Encl Withheld ML20217H4281996-01-24024 January 1996 Discusses Review of Nuclear Energy Inst Guidance Document, Guideline for Managing NRC Commitments, Rev 2,dtd 951219 ML20094H8491995-11-0606 November 1995 Forwards Rev 8 to Security Manual.Rev Withheld ML20091P4951995-08-28028 August 1995 Forwards Clarification of Rev 7 to Security Manual.Encl Withheld ML20094D9291995-08-10010 August 1995 Forwards Scenario Package for 951011 Emergency Exercise at Plant,Per from Cj Paperiello ML20087K2451995-08-0202 August 1995 Forwards Revised Description of Proposed Vehicle Control Measures.Primary Change in Design Is Use of Jersey Barriers in Lieu of Combination Cable & Rock Design.Encl Withheld ML20084L1091995-05-30030 May 1995 Forwards Rev 7 of Kewaunee NPP Security Manual.Encl Withheld ML20080N0061995-02-28028 February 1995 Forwards Summary Description of Plant Proposed Vehicle Control Measures & Results of Vehicle Bomb Comparison.Encl Withheld ML20078R3291994-12-19019 December 1994 Discusses Results & Conclusions of Osre Conducted During 940815-18.Weakness Noted as Being Unique & Only Possible During Specific Time Periods ML20072J3401994-08-22022 August 1994 Responds to NRC Re Violations Noted in Insp Rept 50-305/94-09 on 940516-0704.Corrective Actions:Memo,Stating That Turbine Driven AFW Pump Should Be Declared Inoperable Whenever AFW-10A or 10B Closed or Inoperable,Issued ML20070P5811994-03-29029 March 1994 Requests Meeting W/Nrc & Appropriate Members of NRC Dept Re Disposal of high-level Radwaste from NPP ML20059E9511994-01-0707 January 1994 Requests Addl Info Re Graded Approach for GL 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20058E6581993-12-0101 December 1993 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 940209.Informs That Facility Must Submit Ltr Identifying Individuals Who Will Take Exam ML20058A1291993-11-16016 November 1993 Forwards Safeguards Info Referenced in Preliminary Draft Guide Re Proposed Rule for Protection Against Manevolent Use of Vehicles at Nuclear Power Plants.Encl Withheld ML20059D2761993-10-26026 October 1993 Forwards Copy of Master Bwr/Pwr Gfes Exam W/Answer Key.W/O Encl 1999-08-23
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20211D7501999-08-23023 August 1999 Responds to NRC Re Violations Noted in OI Rept 3-98-043 & EA 99-183.Corrective Actions:Oversight of Training Program & Contractor Policies That Implement Parts of Security Program Have Been Increased by Addl Position ML17230A3661999-03-18018 March 1999 Forwards Listed Nelia Insurance Policy Endorsements for Kewaunee Nuclear Power Plant,Per Requirements of 10CFR140.15 ML20237E0881998-08-24024 August 1998 Clarifies Info Provided Re Containment Ventilation Sys & Use of Mixing Factor of 0.5,in Response to NRC Request Made During Telcon ML20237A2301998-08-0707 August 1998 Forwards Original & Three Copies of Rev 11 to Knpp Security Manual.Screening Criteria Form for Each Change W/Description & Criteria of Review Has Been Included as Attachment A. Reissued Security Manual Included in Attachment B.W/O Encls ML20217F3401998-04-23023 April 1998 Forwards Annual Environ Monitoring Rept Jan-Dec 1997, Per TS 6.9.b.1.Results of 1997 Land Use Census,Iaw Plant ODCM, Section 3/4.7.1,included in Rept ML20216B3281998-04-0707 April 1998 Discusses Amend 132 to License DPR-43.Requested Revised Analysis Reflecting Higher Source Term Encl.Results of Analysis Conclude That Potential Thyroid Doses to Public Continue to Be Less than Guideline Values of 10CFR100 ML20217G1461998-03-25025 March 1998 Responds to NRC Re Violations Noted in Insp Rept 50-305/98-03 on 980128-0203.Corrective Actions:Controlling & Properly Securing SGI ML20217J9641997-08-11011 August 1997 Responds to NRC Re Violations Noted in Insp Rept 50-305/97-02 on 970106-31.Corrective Actions:Will Revise IST Procedures to Use More Accurate Instrumentation Satisfying Requirements & to Include Acceptance Criteria ML20140F2211997-04-0404 April 1997 FOIA Request for Documents Re Recently Issued TIA for Plant Concerning Safety Question on Auxiliary Feedwater Sys ML20134Q1251997-02-20020 February 1997 Forwards Original & Three Copies of Rev 10 to Knpp Security Manual.Manual Is Being Changed to Incorporate Use of Vehicle Barrier Sys,Per 10CFR73.55 & 73.1(a).Encl Withheld ML18065B0081996-10-14014 October 1996 Informs That Overheads Will Be Presented by Licensee at 961016 Meeting at NRC Headquarters in White Flint.Encl Withheld ML20117P6861996-09-20020 September 1996 Forwards Rev 9 to Security Manual.Encl Withheld ML20117L7171996-09-0505 September 1996 Forwards Proposed Tech Specs Re Amend for Use of Westinghouse Laser Welded Steam Generator Tube Sleeves,Per Discussion W/Nrc ML20100M7451996-02-29029 February 1996 Provides Revised Description of Proposed Vehicle Control Measures.Encl Withheld ML20094H8491995-11-0606 November 1995 Forwards Rev 8 to Security Manual.Rev Withheld ML20091P4951995-08-28028 August 1995 Forwards Clarification of Rev 7 to Security Manual.Encl Withheld ML20094D9291995-08-10010 August 1995 Forwards Scenario Package for 951011 Emergency Exercise at Plant,Per from Cj Paperiello ML20087K2451995-08-0202 August 1995 Forwards Revised Description of Proposed Vehicle Control Measures.Primary Change in Design Is Use of Jersey Barriers in Lieu of Combination Cable & Rock Design.Encl Withheld ML20084L1091995-05-30030 May 1995 Forwards Rev 7 of Kewaunee NPP Security Manual.Encl Withheld ML20080N0061995-02-28028 February 1995 Forwards Summary Description of Plant Proposed Vehicle Control Measures & Results of Vehicle Bomb Comparison.Encl Withheld ML20078R3291994-12-19019 December 1994 Discusses Results & Conclusions of Osre Conducted During 940815-18.Weakness Noted as Being Unique & Only Possible During Specific Time Periods ML20072J3401994-08-22022 August 1994 Responds to NRC Re Violations Noted in Insp Rept 50-305/94-09 on 940516-0704.Corrective Actions:Memo,Stating That Turbine Driven AFW Pump Should Be Declared Inoperable Whenever AFW-10A or 10B Closed or Inoperable,Issued ML20070P5811994-03-29029 March 1994 Requests Meeting W/Nrc & Appropriate Members of NRC Dept Re Disposal of high-level Radwaste from NPP ML20056C5071993-02-19019 February 1993 FOIA Request for Documents Re Meeting Minutes,Summaries, Transcripts or Other Documents Resulting from NRC Meeting Held 930209 at Region III Ofc in Glen Ellyn,Il to Discuss Kewaunee Engineering Activities & Other Items of Interest ML20128H9271993-02-13013 February 1993 Advises That All Actions Necessary to Ensure Compliance W/ 10CFR50,App E,Section VI Re ERDS Completed.Installation of ERDS Hardware in Technical Support Ctr Complete & Temporary Telephone Line Replaced W/Permanent Line ML20128D2721993-02-0202 February 1993 Provides Listed Submittal Describing Actions Currently Being Performed & Schedule for Completion of Actions Associated W/ Resolution of long-term Recommendation GL-4,per ML20126E7221992-12-28028 December 1992 Forwards Response to NRC Re Weaknesses & Followup Items Noted in Insp Rept 50-305/92-21 of Annual Emergency Plan Exercise.Corrective Actions:More Mgt Involvement Will Be Provided & Emergency Plan Will Be Revised ML20095G9561992-04-27027 April 1992 Forwards Rev 5 to Security Manual,Revised to Reflect Requirements of New Access Authorization Rule.Rev Withheld ML20091M5531992-01-27027 January 1992 Forwards Rev 4 to Security Manual,Reflecting Recent Organizational & Title Changes & Adding Vehicle Insp Portal on North Gate.Rev Withheld ML20086E3411991-11-21021 November 1991 Forwards Response to Security Concern RIII-91-A-0056,per NRC .Investigation Determined That No Violation of Burns fitness-for-duty Program Occurred & That Burns Program Meets NRC Guidance for Overtime ML20079L0391991-10-29029 October 1991 Forwards Rev 3 to Security Manual to Address Issues Identified in NRC .Manual Withheld ML20079K8081991-10-28028 October 1991 Forwards Emergency Response Data Sys Implementation Program Plan.Implementation Program Plan Indicates That Sys May Be Operational as Early as Feb 1992 Provided No Obstacles Encountered During Hardware/Software Implementation ML1116610971991-08-30030 August 1991 Forwards Rev 3 to WCAP-11476, Handbook on Flaw Evaluation Kewaunee,Unit 1 Steam Generators Upper Shell to Cone Weld. Proprietary Suppl 1 to Kewaunee Unit 1 Steam Generator Upper Shell to Cone Welds Steam Generator... Withheld ML20091B6991991-07-25025 July 1991 Forwards Exercise Scenario Manual Minus Inject Messages Addressing Ingestion Pathway Objectives on Day 2 & 3 of 910924 Annual Emergency Exercise at Plant,Per NRC Requesting Advance Submittal of Exercise Objective.W/O Encl ML20073C2761991-04-0505 April 1991 Forwards Rev 2 to Security Manual,Reflecting Expanded Protection Area Boundary.Rev Withheld (Ref 10CFR73.21) ML1116610051990-10-0909 October 1990 Forwards Nonproprietary WCAP-12712 & Proprietary WCAP-12711, Reevaluation of U-Bend Tube Fatigue for Kewaunee Plant Steam Generators, Per NRC Bulletin 88-002 ML1116610071990-09-17017 September 1990 Requests Withholding of Proprietary WCAP-12711, Reevaluation of U-Bend Tube Fatique for Kewaunee Plant Steam Generators. ML1116506681990-08-17017 August 1990 Forwards Pages Inadvertently Deleted from 1990 Rev to Updated FSAR Submitted on 900720 ML20055C9811990-06-29029 June 1990 Forwards Response to Violations Noted in Insp Rept 50-305/90-04.Response Withheld (Ref 10CFR73.21) ML1116609691990-04-11011 April 1990 Requests That WCAP-12558 Kewaunee Steam Generator Tubesheet Crevice Indications Return to Power Rept, Be Withheld (Ref 10CFR2.790) ML1116609671990-04-0606 April 1990 Forwards Nonproprietary WCAP-12559 & Proprietary WCAP-12558, Kewaunees Steam Generator Tubesheet Crevice Indications Return to Power Rept, as Followup to 900328 Meeting. Proprietary Version Withheld (Ref 10CFR2.790) ML20012A4031990-03-0101 March 1990 Informs That Revised Listed Drawings Sent to Region III for Filing ML20006E8641990-02-19019 February 1990 Suppl Response to NRC 890725 Ltr Re Safeguards Info Violation Noted in Insp Rept 50-305/89-09.Corrective Action: Section V of General Employee Training Manual Security Removed ML1116609341990-01-15015 January 1990 Forwards Nonproprietary WCAP-12441 & Proprietary WCAP-12440, Presentation to NRC Re Kewaunee (Wps) SECY-83-472 LOCA Analysis Effort. Wiesemann 891204 Request for Withholding Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML20005D9601989-12-27027 December 1989 Forwards Response to Allegation RIII-A-89-A-0137.Encl Withheld (Ref 10CFR73.21) ML20005D8131989-12-22022 December 1989 Forwards Status & Proposed Schedule for Security Mod Completion.Implementation Schedule for Proposed Mods Extended Until Oct 1990 Due to Several Major Project Increases.Encl Withheld (Ref 10CFR73.21) ML20011D9111989-12-20020 December 1989 Forwards Executed Amend 8 to Indemnity Agreement B-53 ML19332E6091989-12-0404 December 1989 Forwards Rev 1 to Security Manual.Rev Withheld (Ref 10CFR73.21) ML1116609361989-12-0404 December 1989 Submits Application for Withholding of Proprietary WCAP-12440, Presentation to NRC Re Kewaunee (Wps) SECY-83-472 LOCA Analysis Effort, Per 10CFR2.790.Affidavit Supporting Request Encl ML20247J7721989-07-19019 July 1989 Forwards Rept for Unannounced off-hours Drills on 881020 for State of WI,site-specific to Zion,Point Beach,Kewaunee & Prairie Island Nuclear Power Stations.No Deficiencies or Areas Requiring Corrective Actions Noted 1999-08-23
[Table view] Category:UTILITY TO NRC
MONTHYEARML1116506681990-08-17017 August 1990 Forwards Pages Inadvertently Deleted from 1990 Rev to Updated FSAR Submitted on 900720 ML20055C9811990-06-29029 June 1990 Forwards Response to Violations Noted in Insp Rept 50-305/90-04.Response Withheld (Ref 10CFR73.21) ML1116609671990-04-0606 April 1990 Forwards Nonproprietary WCAP-12559 & Proprietary WCAP-12558, Kewaunees Steam Generator Tubesheet Crevice Indications Return to Power Rept, as Followup to 900328 Meeting. Proprietary Version Withheld (Ref 10CFR2.790) ML20012A4031990-03-0101 March 1990 Informs That Revised Listed Drawings Sent to Region III for Filing ML20006E8641990-02-19019 February 1990 Suppl Response to NRC 890725 Ltr Re Safeguards Info Violation Noted in Insp Rept 50-305/89-09.Corrective Action: Section V of General Employee Training Manual Security Removed ML1116609341990-01-15015 January 1990 Forwards Nonproprietary WCAP-12441 & Proprietary WCAP-12440, Presentation to NRC Re Kewaunee (Wps) SECY-83-472 LOCA Analysis Effort. Wiesemann 891204 Request for Withholding Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML20005D9601989-12-27027 December 1989 Forwards Response to Allegation RIII-A-89-A-0137.Encl Withheld (Ref 10CFR73.21) ML20005D8131989-12-22022 December 1989 Forwards Status & Proposed Schedule for Security Mod Completion.Implementation Schedule for Proposed Mods Extended Until Oct 1990 Due to Several Major Project Increases.Encl Withheld (Ref 10CFR73.21) ML20011D9111989-12-20020 December 1989 Forwards Executed Amend 8 to Indemnity Agreement B-53 ML19332E6091989-12-0404 December 1989 Forwards Rev 1 to Security Manual.Rev Withheld (Ref 10CFR73.21) ML20246G3761989-05-11011 May 1989 Forwards Proposed Change to Devitalize Area of Plant (Currently Identified as Vital Area),Per 10CFR50.90.Change Withheld ML20205K3961988-10-28028 October 1988 Forwards Response to NRC Re security-related Violations Noted in Insp Rept 50-305/88-17.Response Withheld ML20151Q4151988-08-0101 August 1988 Advises That Revised Listed P&ID Drawings Being Sent to Region III ML20196L5141988-06-30030 June 1988 Forwards Rev 15 to Industrial Security Manual.Rev Withheld (Ref 10CFR73.21) ML20155A6271988-06-0808 June 1988 Forwards Response to Security Open Item Noted in Insp Rept 50-305/88-04.Encl Withheld (Ref 10CFR73.21) ML20151N3411988-04-22022 April 1988 Forwards Response to NRC Re Violations Noted in Insp Rept 50-305/88-05.Response Withheld (Ref 10CFR73.21) ML20148E2181988-03-22022 March 1988 Forwards Proposed Amend 10a to Industrial Security Manual Re Implementation of 10CFR73.55 Rule Changes.Amend Withheld ML20147G0541988-03-0101 March 1988 Advises That Listed P&Ids Being Sent to Region III Incident Response Ctr Ref Library,Per Jg Keppler 800320 Request ML20236S0671987-11-17017 November 1987 Forwards Rev 14 to Industrial Security Manual & Rev 7 to Security Force Training & Qualifications Manual,Per Provisions of 10CFR50.54(p).Encls Withheld (Ref 10CFR73.21) ML20236A2391987-10-19019 October 1987 Forwards Proprietary Rev 1 to App C of Plant Industrial Security Manual.App C Describes Temporary Security Measures Employed During Const Associated W/Expansion of Security Bldg.Manual Withheld (Ref 10CFR73.21) ML20234E4401987-09-18018 September 1987 Forwards App B,Rev 1 to Industrial Security Manual.App B Describes Temporary Security Measures Employed During Const of Administration & Training Facility.App B Will Be in Effect Until End of Dec 1987.Encl Withheld (Ref 10CFR73.21) ML20214U0381987-06-0505 June 1987 Forwards Table Listing Valves Meeting Revised Definition of Pressure Isolation Valve,Per Generic Ltr 87-06 Request.Table Includes Periodic Leakage,Operational Tests & Frequency of Testing ML20213G7131987-05-12012 May 1987 Forwards App C to Plant Industrial Security Manual, Describing Temporary Security Measures Employed During Const Associated W/Expansion of Existing Security Bldg.App Withheld (Ref 10CFR73.21) ML20215K2851987-05-0606 May 1987 Forwards App B to Plant Industrial Security Manual,Effective Until End of 1987 or Early 1988 When Const Nears Completion. Manual Withheld (Ref 10CFR73.21) ML20210B4381987-05-0101 May 1987 Forwards Response to Violations Noted in Insp Rept 50-305/87-11.Response to One Open Item & One Weakness Also Provided.Encl Withheld (Ref 10CFR73.21) ML20212N7211987-03-0909 March 1987 Responds to Concerns Noted in Insp Rept 50-305/86-09. Operations Dept Initiated multi-faceted Program Aimed at Improving Operator Attentiveness.Control Room Operators Reminded to Walk Boards at Regular Intervals ML20209H0951987-01-30030 January 1987 Forwards Resolution Schedule Re Two Items Identified in Regulatory Effectiveness Review Rept,Per 861218 Telcon. Resolutions Contingent Upon Review & Approval by Util.Encl Withheld (Ref 10CFR73.21) ML20212B8571986-12-26026 December 1986 Forwards Reload Safety Evaluation,Kewaunee Cycle 13. Cycle 13 Design More Conservative than Design Used in Accident Analysis.Refueling Outage Scheduled to Begin 870301.Cycle 13 Startup Testing Scheduled to Begin 870410 ML20212A5131986-12-17017 December 1986 Resubmits Re Proposed Implementation of 10CFR73.55 Rule Changes to Document Control Desk,Per Project Manager Request ML20212B5471986-12-0202 December 1986 Forwards Descriptive Summary of Proposed Changes to Facility Industrial Security Manual Per 10CFR73.55(a),(d)(1),(d)(7), (d)(9) & (e)(1).Encl Withheld (Ref 10CFR73.21) ML20212A5271986-12-0202 December 1986 Forwards Descriptive Summary of Proposed Changes to Security manual,per10CFR73.55 Requirements That Licensees Submit Revs Describing How Paragraphs (a),(d)(1),(d)(7),(d)(9) & (e)(1) Will Be Met.Encl Withheld (Ref 10CFR73.55) ML20211K0131986-11-11011 November 1986 Forwards Response to IE Bulletin 86-003, Potential Failure of Multiple ECCS Pumps Due to Single Failure of Air-Operated Valve in Min Flow Recirculation Line. ECCS at Plant Not Vulnerable to Single Failure in Pump Lines ML20215N4251986-10-27027 October 1986 Forwards Rev 9 to Industrial Security Manual & Rev 6 to Security Force Training & Qualifications Manual,Per 10CFR50.54(p).Revs Withheld (Ref 10CFR73.21) ML20210C3531986-09-0808 September 1986 Updates 860514 Response to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Full Flow Max Differential Pressure Tests for Valves Will Be Performed ML20210B5951986-09-0505 September 1986 Forwards Addl Info to 850411 Response to NRC Re Results of Regulatory Effectiveness Review on 840611-15. Protection of Vital Equipment Addressed in Encl.W/O Encl ML20206R4661986-07-30030 July 1986 Forwards List of Exercise Objectives & Abstract of Scenario for 861014 Emergency Exercise.State of Wi & Kewaunee & Manitowoc Counties Will Support Exercise,Answering Notification Messages W/O Personnel Response.W/O Encl ML20212H5691986-07-28028 July 1986 Responds to IE Bulletin 86-002 Re Static O-Ring Differential Pressure Switches.Review Indicated That Sor,Inc Series 102 or 103 Differential Pressure Switches Not Installed in Electrical Equipment Applications 05000305/LER-1986-009, Forwards LER 86-009-00.Delay in Submitting Rept 2 Days Beyond 10CFR50.73 Requirement Necessary to Include Results of Special Test Procedure Performed as Final Corrective Action for Event.Delay Concurred W/By NRC Project Manager1986-06-16016 June 1986 Forwards LER 86-009-00.Delay in Submitting Rept 2 Days Beyond 10CFR50.73 Requirement Necessary to Include Results of Special Test Procedure Performed as Final Corrective Action for Event.Delay Concurred W/By NRC Project Manager ML20211G0361986-06-13013 June 1986 Forwards Rev 8 to Industrial Security Manual,Addressing NRC Concern in Insp Rept 50-305/85-18 & Updating Titles of Plant Staff W/Security Responsibilities.Rev Withheld (Ref 10CFR73.21) ML20155J3081986-05-14014 May 1986 Responds to IE Bulletin 85-003, Motor-Operated Valve Common Failures During Plant Transients Due to Improper Switch Setting. Westinghouse Owners Group Developed Methodology for Determining Which motor-operated Valves Included ML20204A5161986-05-0606 May 1986 Requests Reconsideration of 860430 Denial of Schrock 860418 Application for Senior Reactor Operator Exam.Rationale Supporting Request Submitted ML20203F0391986-04-0202 April 1986 Discusses AEOD Assessment of Util Lers.Quality of Future LERs Will Be Improved by Using Outline Format During Text Preparation & Guidelines from Suppl 2 to NUREG-1022 ML20154L6131986-03-0707 March 1986 Forwards Proposed Rev to Industrial Security Manual,In Effort to Resolve Violation Cited in Insp Rept 50-305/85-18. Rev Withheld (Ref 10CFR73.21).Fee Paid ML20154J5471986-02-28028 February 1986 Forwards Annual Operating Rept,1985 ML20154B2831986-02-25025 February 1986 Forwards Procedure for Prevention & Correction of Steam Binding of Auxiliary Feedwater Pumps in Response to IE Bulletin 85-001 ML20137Y0241986-02-18018 February 1986 Expresses Concern Re FEMA Guidance Memo PR-1, Policy on NUREG-0654/FEMA-REP-1 & 44CFR350 Periodic Requirements. Apparent Conflicts Noted Between PR-1 & 10CFR50,App E, Section E.3(3) & 44CFR350.9(c)(4).PR-1 Should Be Reviewed ML20199F0711986-01-28028 January 1986 FOIA Request for Draft NUREG/CR-4178 ML20137X0421985-11-27027 November 1985 Requests Extension for Completing NUREG-0737,Suppl 1 Requirements,Per 840614 Order Confirming Util Commitments. Description of NUREG-0737,Suppl 1 Items Under 840614 Order & Reasons for Relief Provided ML20132D6121985-09-13013 September 1985 Responds to NRC Re Violations Noted in Insp Rept 50-305/85-09.Corrective Actions:Engineering Control Directive 14.1 Revised to Ensure Adequacy of Emergency Preparedess Program Interfaces W/State & Local Govts ML20134D4231985-08-0101 August 1985 Updates 850201 Response to Weaknesses 2 & 3 Identified in Insp Rept 50-305/84-14 Re Dose Projection Program Flow Rates.Results of Auxiliary Bldg & Reactor Bldg Ventilation Sys Evaluation & Recommended Corrective Actions Provided 1990-08-17
[Table view] |
Text
REGULATORYSFORMATION DISTRIBUTION S4EM (RIDS)
ACCESSION NBR:7910250287 DOC,DATE: 79/10/19 NOTARIZED2,YES DOCKET #
FACIL;50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic 05000305 AUTH.NAME . AUTHOR AFFILIATION MATHEWSE.R. Wisconsin Public Service Corp.
RECIPNAME RECIPIENT AFFILIATION SCHWENCERA, Operating Reactors Branch I
SUBJECT:
Forwards proposed Tech Spec Amend 40 re fire protection.
DISTRIBUTION CODE; A001S COPIES RECEI'VEDtLTR , ENCL SIZE: _1 TITLE: General Distribution for after Issuance of Operating Lic NOTE7S; REC I PI EN I COPIES RECIPIENT .COPIES
.10 CODE/NAME: LTTR ENCL ID CODE/NAME: LTTR ENCL ACTION: 05 BC 6 i %*/ 7 7 INTERNAL (R EZGF 1 1 02 NRC PDR 1 1 2 2 14 TA/EDO 1 1 15 CORE PERF BR 1 1 17 ENGR BR ! 1 18 REAC SFTY BR 1 1 19 PLANT SYS BR 1 1 20 EEB 1 1 21 EFLT TRT SYS 1 1 22 BRINKMAN 1 1 OELD 1 0 EXTERNAL: 03 LPDR 1 1 04 NSIC 1 1 23 ACRS 16 16 I I OCT 26 1979 TOTAL NUMBER OF COPIES REQUIRED: LTTR -W ENCL 37'
WISCONSIN PUBLIC SERVICE CORPORATION P.O. Box 1200, Green Bay, Wisconsin 54305 October 19, 1979 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention Mr. A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Gentlemen:
Docket 50-305 Operating License DPR-43 Proposed Technical Specification Amendment No. 40 Fire Protection Enclosed please find forty (40) copies of proposed Amendment No. 40 to the Kewaunee Nuclear Power Plant Technical Specifications. The purpose of this amendment is to add those fire protection systems previously committed to in Amendment No. 23, to delete the modifications required as a condition to our license, to add a requirement of a five man fire response team, and to correct several wording inconsistencies of the previous specification.
We have to date completed all the modifications and satisfied all commitments made with respect to fire protection with the exception of the screenhouse corridor sprinkler system. This last modification will be completed by January 1, 1980. As of that date the condition to our license enacted by Amendment No. 23 would have been satisfied and should be deleted from the license.
Response to Item 3 in our February 15, 1979, letter provided a commitment to prepare a formal procedure for the actions to be taken in the event of a relay room fire. The basic steps of that procedure were submitted for review.
Specific comments from the NRC staff were received with respect to the timing of implementing certain steps, e.g. starting the SI pumps. Those comments were reviewed and will be incorporated in the procedure by January 1, 1980.
7910250
U. S. Nuclear Regulatory Commission October 19, 1979 Page 2 This proposed amendment is exempt from an application fee because this application does not constitute a new or additional review by the NRC staff.
The Technical Specification changes submitted herein constitute previously reviewed material which was initiated prior to the March 23, 1978, implementation of 10 CFR 70.
Very truly yours, E. R. Mathews, Vice President Power Supply & Engineering snf Enc.
Subscribed and Sworn to Before is 19th Da of cfober 79 Notary Public, State of Wisconsin My ommis ion E pires
- 0 Section C of the Kewaunee Plant Operating License should be changed as follows:
C. This license shall be deemed to contain and is subject to the condi tions specified in the following Commission regulations in 10 CFR, Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensees are authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 30, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications."
(3) Deleted 40 (4) The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan documents, withheld from public disclosure pursuant to 10 CFR 2.790(d), are collectively titled "Industrial Security Manual" dated May 25, 1977, January 9, 1978, December 18, 1978, January 30, 1979, March 7, 1979 and March 27, 1979."
7910250 4
Specification 6.9.2 within the next 30 days.
- 4. With no fire water systems operable:
A. Establish a backup fire water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. Submit a report in accordance with Specification 6.9.2; a) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and b) In writing no later than the first working day following the event, and c) In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
- c. Spray And/Or Sprinkler Systems Whenever equipment in spray and/or sprinkler protection areas is required the following spray and/or sprinkler systems shall be OPERABLE:
- 1. Special Ventilation Room AX-23
- 2. Cable Tray Sprinkler System (AX-32) 140
- 3. Screenhoue. Sprinkler System With one or more of the above required spray and/or sprinkler systems inoperable, establish backup fire suppression equipment for the un protected area(s) within one hour; restore the system to OPERABLE status within 14 days or submit a report to the Commission pursuant to Specification 6.9.2 within the next 30 days..
- d. Low Pressure CO2 Systems Whenever equipment in the low pressure CO 2 protected areas is required to be OPERABLE, the following low pressure CO systems shall be OPERABLE with a minimum of 60% indicated level and a minimum pressure of 295 psig in the associated storage tank(s).
- 1. Diesel Generator lA, TU-90 and day tank room, TU-91
- 2. Diesel Generator lB, TU-92 and day tank room, TU-93 TS 3.15-2 Proposed Amendment No. 40 10/19/79
TABLE TS 3.15-1 FIRE DETECTION INSTRUMENTATION Minimum #
Fire Area Detectors Required Required Actions 140 AX-21 4160 Switchgear Room 3 2 Establish an hourly fire watch inspection AX-23 Special Vent 9 9 If filter housing is in operation with charcoal 40 Filter Housings filters in service establish an hourly fire watch inspection. If not in service establish a 4-hour inspection frequency.
AX-23 Auxiliary Building 4 2 Establish an hourly fire watch inspection 40 AX-24 Fuel Handling Area 3 3 Establish an hourly fire watch inspection AX-30 Relay Room 19 6 Establish an hourly fire watch inspection cv AX-32 Cable run area 11 8 Establish an hourly fire watch inspection (D
crA AX-35 Control Room 13 0 Control room is continuously manned I-. AX-37 CRD Room 7 4 Establish an hourly fire watch inspection SB-65 Shield Building 2 Establish a four hour fire watch inspection SC-70 Screenhouse 2 Establish an hourly fire watch inspection TU-90/91 D/G 1A and day tank room 5 Establish an hourly fire watch inspection TU-92/93 D/G lB and day tank room 5 Establish an hourly fire watch inspection TU 94 Cardox Room 1 Establish an hourly fire watch inspection 40 TU 95 Air Compressor & Pump Room 4 Establish an hourly fire watch inspection TU 97 Battery Room 1A 1 Establish an hourly fire watch inspection TU 98 Battery Room lB S1 Establish an hourly fire watch inspection
4.15 FIRE PROTECTION SYSTEM Applicability Applies to the testing and surveillance requirements for the fire protection equipment addressed in Specification 3.15.
Objective Verify performance capability of the fire protection system.
Specification
- a. Fire Detection Instrumentation
- 1. At least the minimum required number of fire detection instruments in Table TS 3.15-1 shall be demonstrated OPERABLE semi-annually by performance of a CHANNEL FUNCTIONAL TEST. Those detectors that are of the fusible link type shall be verified operable by visual inspection.
- 2. Deleted 40
- b. Fire Water System The fire water system shall be demonstrated OPERABLE:
- 1. Each pump shall be tested monthly in accordance with Table TS 4.1-3.
- 2. At least once per 12 months by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position, and by cycling each testable valve in the flow path through at least one complete cycle of full travel.
- 3. At least once per 12 months by performance of a system flush.
- 4. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence, and:
a) Verifying that each pump develops at least 1800 gpm 'at a system head of 310 feet, b) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and TS 4.15-1 Proposed Amendment No. 40 10/19/79
c) Verifying that each high pressure pump auto-start setpoint is 25
>100 psig.
5- Deleted 40
- c. Spray/Sprinkler Systems Each of the spray and/or sprinkler systems in Specification 3.15.c shall be demonstrated OPERABLE:
- 1. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.
- 2. At least once per 18 months:
a) By performing a system functional test which includes simulated automatic actuation of the system, and:
- 1. Verifying that the automatic valves in the flow path actuate to their correct positions, and
- 2. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.
b) By visual inspection of the spray headers to verify their integrity, and c) By visual inspection of each nozzle to verify no blockage.
- 3. At least once per three years by performing an air flow test through each open head spray/sprinkler header and verifying each open head spray/sprinkler nozzle is unobstructed.
- d. Low Pressure CO2 Systems Each of the low pressure CO2 systems in Specification 3.15.d shall be demonstrated OPERABLE:
- 1. At least once per 7 days by verifying CO2 storage tank level and pressure, and
- 2. At least once per 18 months by verifying:
a) The system valves and associated ventilation dampers actuate manually and automatically, upon receipt of a simulated actuation signal, and TS 4.15-2 Proposed Amendment No. 40 10/19/79
b) Flow from each nozzle during a "Puff Test."
- e. Fire Hose Stations Each of the fire hose stations shown in Table TS 3.15-2 shall be demonstrated OPERABLE:
- 1. Monthly:
a) Visual inspection of the station to assure all required equipment is at the station, and
- 2. At least once per 18 months by:
a) Removing the hose for inspection and reracking, and b) Replacement of all degraded gaskets in couplings.
- 3. At least once per three years by:
a) Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.
b) Conducting a hose hydrostatic test at a pressure of at least 160 psig.
- f. Penetration Fire Barriers Each of the required penetration fire barriers shall be verified to be intact by a visual inspection:
- 1. At least once per 18 months, and
- 2. Prior to declaring a penetration fire barrier functional following repairs or maintenance.
BASES Fire Detection Instrumentation Failure of a fire detection instrument results in an alarm to the control room Control Panel and local panels and, thus, an annual functional test is adequate to detect otherwise failed detector.
40 Fire Water System Both pumps in the system shall be individually tested monthly4 The fire water system consists of a 12" 0 40 TS 4.15-3 Proposed Amendment No.
10/19/79
I 9
- c. At least one licensed operator shall be in the control room when fuel is in the reactor.
- d. At least two licensed operators shall be present in the control room during reactor startup, turbine generator synchronization to the grid, and during recovery from reactor trips.
- e. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. This individual may be one of the shift operators.
- f. Refueling operations shall be directed by a licensed Senior Reactor Operator assigned to the refueling operation who has no other concurrent responsibilities during the refueling operation.
g- A five man fire response team, consisting of 3 Fire Brigade members and 2 Assistant Fire Brigade personnel, shall be maintained. If a member of the fire response team becomes incapacitated due to ill- 40 ness or injury this requirement is deemed satisfied if a replace ment arrives within two hours in all but the severest weather.
6.3 PLANT STAFF QUALIFICATIONS 6.3.1 Qualifications of each member of the Plant Staff shall meet or exceed the minimum acceptable levels of ANSI-N18.1-1971 for comparable positions.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the Plant Staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI-N18.1-1971 and Appendix A of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Fire Marshall and shall meet or exceed the re- 20 quirements of Section 27 of the NFPA Code-1975 , except that training sessions shall be held quarterly.
TS 6-2 Proposed Amendment No. 40 10/19/79