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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) ML17354B2061998-12-0909 December 1998 Informs That Request for Exemption Specified in Section II.B.3 Will Not Be Needed Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg ML17354B1981998-11-25025 November 1998 Forwards Scope & Objective for 1999 Plant Annual Emergency Preparedness Exercise.Objectives Developed in Conjunction with State & Local Govts.Exercise Scheduled for 990210 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17348A5661990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. ML17348A5461990-09-0707 September 1990 Forwards 1990 Inservice Insp Refueling Outage Summary Rept of NDE Activities 900206-0404 First Refueling Outage Second Period Second Insp Interval. ML17348A5501990-09-0707 September 1990 Forwards Jul 1990 Integrated Schedule Regulatory Rept for Facilities ML17348A5521990-09-0606 September 1990 Forwards Matrix of Changes to Emergency Power Sys That Affect Revised Tech Specs Issued on 900828.Matrix Sent for Info & to Assist in NRC Review of No Significant Hazards Rept for Revised Tech Specs ML17348A5431990-08-31031 August 1990 Forwards Objectives for 901108 Emergency Plan Exercise. Exercise Will Involve Participation by Local Emergency Response Agencies & State Emergency Response Personnel & Will Not Be Evaluated by FEMA ML17348A5361990-08-27027 August 1990 Forwards Turkey Point Units 3 & 4 Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17348A5171990-08-24024 August 1990 Forwards Ref Matl in Preparation for Operator License Exams Scheduled for Wk of 901029,per NRC 900628 Request ML17348A5041990-08-17017 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 ML17348A5051990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Turkey Point Units 3 & 4 & Revise Rept for June 1990 for Unit 3 ML20059B0111990-08-14014 August 1990 Requests That Encl Intervenor Motion for Extension of Time to Appeal to Docketing & Svcs Branch Re Tech Spec Replacement Hearing Be Provided.Motion Inadvertently Omitted in Svc of Request on 900813 ML17348A4971990-08-10010 August 1990 Responds to Violations Noted in Insp Repts 50-250/90-18 & 50-251/90-18.Corrective Actions:Unit Stabilized in Mode 3, Operating Surveillance Procedures 3/4-OSP-089 Revised & Event Response Team Formed ML17348A4701990-07-27027 July 1990 Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing L-90-282, Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790)1990-07-25025 July 1990 Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790) ML17348A4281990-07-25025 July 1990 Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b) ML17348A4691990-07-23023 July 1990 Forwards Addl Info on Emergency Power Sys Enhancement Project Re Load Sequencer,Programmable Logic Controllers & Implementation of Sys in Plant,Per NRC 900705 Request ML17348A4191990-07-20020 July 1990 Advises That Comments on NRC Safety Evaluation Re Implementation of Station Blackout Rule Will Be Provided by 900921 ML17348A4201990-07-20020 July 1990 Forwards Revised No Significant Hazards Determination for Proposed Tech Specs 1.17 & 3.0.5 & Bases,Per 890605 Ltr ML17348A4141990-07-20020 July 1990 Responds to Violations Noted in Insp Repts 50-250/90-14 & 50-251/90-14.Corrective Actions:Breakers Closed,Returning Monitoring Sys to Operable Level & Briefings Held to Explain Rvlms Sys Theory to Operations Control Room Personnel ML17348A4171990-07-19019 July 1990 Forwards May 1990 Integrated Schedule Regulatory Rept for Plant ML17348A4121990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML17348A4251990-07-17017 July 1990 Withdraws 900207 & 0424 Proposed Changes to Tech Specs Re Util Nuclear Review Board Composition IR 05000250/19900131990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML20055G8641990-07-16016 July 1990 Informs ASLB That Petitioners Ref to Several Telephone Contacts Between J Butler & M Gutman,Of ATI Career Training Inst Is Inadvertent Misstatement & Should Be Changed to Telephone Contact. W/Certificate of Svc ML17348A4161990-07-16016 July 1990 Responds to Commitment Re Reverse Testing of Containment Isolation Valves Per Insp Repts 50-250/90-13 & 50-251/90-13. Corrective Action Plan Addresses Penetrations 16 & 53 for Unit 3 Only & Penetrations 11,47,54A & 54B for Both Units ML17348A4151990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML17348A4041990-07-12012 July 1990 Forwards Addl Info Re Responses to NRC Questions on Piping Codes Used for Emergency Power Sys Enhancement Project ML17348A3921990-07-12012 July 1990 Summarizes Facility Performance Since Last SALP Evaluation Period Which Ended 890731.Util Pursued Aggressive self- Assessment Program,Including Significant Internal or Outside Assessments in Areas of Operator Performance & EOPs L-90-261, Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld1990-07-11011 July 1990 Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld L-90-259, Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3))1990-07-11011 July 1990 Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3)) ML17348A4321990-07-11011 July 1990 Forwards Rev 8 to Updated FSAR for Turkey Point Units 3 & 4. Rev Includes Activities Completed Between 890123 & 900122. Rept of Changes for Jul 1989 Through June 1990 Will Be Provided by 900901 ML17348A3941990-07-0909 July 1990 Forwards Requested Addl Info Re Emergency Power Sys Enhancement Project.Specific Detailed Changes Will Be Made to Procedures to Address Mods Affecting Equipment Relied Upon for Safe Shutdown ML17348A3881990-07-0505 July 1990 Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs ML17348A4311990-07-0505 July 1990 Documents Written & Verbal Request of Region II Personnel for Temporary Waiver of Compliance of Tech Spec 3.4.2.b.1 Re Allowable Out of Svc Time for One Emergency Containment Cooler from 24 H to 72 Hr W/Addl Reasons ML17348A3851990-07-0303 July 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-250/90-08 & 50-251/90-08.Corrective Actions:Training Dept Increased Emphasis on Radiological Postings in Radiation Worker Training ML17348A3711990-07-0303 July 1990 Responds to NRC 900524 Request for Addl Info on Emergency Power Sys Enhancement Project ML17348A3671990-07-0303 July 1990 Confirms Util Intentions Not to Operate Beyond Refueling Outage That Represents Last Outage Re NRC Bulletin 89-001 ML17348A3841990-06-29029 June 1990 Forwards LER 90-11 on 900609 Re hi-hi Steam Generator Water Level Turbine Trip & Subsequent Reactor Trip Due to Failure of Switch in Feedwater Valve Controller Hand/Auto Station. W/O Encl ML17348A3601990-06-29029 June 1990 Responds to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Test Procedures Developed & Under Mgt Review Reflecting Revised Inservice Testing Program ML17348A3621990-06-28028 June 1990 Notifies That Senior Operator License SOP-20177-2 Will Be Terminated,Effective 900731 ML17348A3651990-06-28028 June 1990 Advises That Completion of safety-related motor-operated Valve Testing & Surveillance Will Be Completed by June 1990, Per Generic Ltr 89-10 Requirements ML17348A3591990-06-27027 June 1990 Responds to Violations Noted in Insp Repts 50-250/90-09 & 50-251/90-09.Corrective Actions:Specialist Counselled on Importance of Stopping Procedure When Steps Conflict W/ Condition of Plant & Procedure Use Guidelines Reviewed ML17348A3641990-06-27027 June 1990 Responds to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions. ML17348A3861990-06-27027 June 1990 Advises That New Date for Submittal of Response to Insp Repts 50-250/90-09 & 50-251/90-09 Is 900702 ML17348A3551990-06-21021 June 1990 Responds to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers. Five Untraceable Circuit Breakers Installed in Unit 3 safety-related Sys.All Five Breakers Replaced W/Traceable Breakers ML20055D9201990-06-20020 June 1990 Advises That Sp Frantz Will Represent Licensee in Argument Scheduled for 900710.Certificate of Svc Encl ML17348A3181990-06-19019 June 1990 Forwards Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects for Turkey Point Nuclear Power Plant, Per NRC Bulletin 88-008 ML17348A2981990-06-12012 June 1990 Forwards Rev 16 to Topical QA Rept. ML17348A2871990-06-0808 June 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Model S350W Swing Check Valves or Valves of Similar Design. Bolt Replacement Performed ML17348A2861990-06-0808 June 1990 Advises That Info Re Operating History of Select Fuel Assemblies Sent to ORNL Between 900419 & 26,per 900510 Request ML17348A2781990-06-0404 June 1990 Forwards Emergency Power Sys Enhancement Project Repts, Reflecting Current Design Info 1990-09-07
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Text
REGULA' INFORMATION DISTRIBUTI YSTEM (RIDS)
ACCESSION NBR t 7905290143 DOC i DATE ~ 79/05/21 NOTARIZED! NO DOCKE FACIL:50 250 TURKEY POINT PLANTg UNIT 3p FLORIDA POWER AND LIGHT C 50 251 TURKEY POINT PLANTi UNIT 4 p FlORIDA POWER AND lIGHT C 05 AUTH~NAME AUTHOR Af FILIATION UHRIGiR ~ Ee FLORIDA POWER 8 LIGHT CO, RECIPeNAh1E RECIPIENT AFFILIATION SCHWENCERiA ~ OPERATING REACTORS BRANCH 1 SUBJECTS FORWARDS SCHEDULE FOR PLANT MODS RE FIRE PROTECTION 8 ADDL INFO RE SAFETY EVALUAT'IONiPER 790321 REQUES'ro DISTRIBUTION CODEe A001S COPIES RECEIYED:LTR ENCL SIZE!
TITLE'ENERAL DISTRIBUTION FOR AFTER- ISSUANCE- OF OPERATING LIC C' ~
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RECIPIENT COPIES RECIPIENT COPIES IO CODE/NAME ID CODE/NAME LTTR ENCL ACTION: 05 BC 4g lS ~/ "7 CTTR ENCL
'7 INTERNALe 01 1 1 02 NRC PDR 1 1 12 ILK 2 2 14 TA/EDO 1. 1 15 CORE PERF BR 1 1 16 AD -SYS/PROJ 1 1 17 ENGR BR 1 1 18 REAC SFTY BR 1 1 19 PLANT 'SYS BR 1 20 EEB 1 1 21 EFLT TRT SY8 1 1 22 BR INKMAN 1 EXTERNAL: 03 LPDR 1 04 NSIC 1 1 23 ACRS 16 16
/AD: g&k(L. St/s 8g
, k/8<8hcp W. &ugeW~gz dEL,B TOTAL NUMBER OF COPIES REQUIRED: LTTR 38 ENCL '8
P.O. BOX 529100, MIAMI, FL 33152 FLORIOA POWER & LIGHT COMPANY May 21, 1979 L-79-128 Office of Nuclear Reactor Regulation Attention: Mr. A'. Schwencer, Chief Operating Reactors Branch gl Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Schwencer:
Re: Turkey Point Units 3 6 4 Docket.Nos. 50-250 6 50-251 Fire Protection In accordance with your letter of March 21, 1979 (Amendments 45 and 37 to Facility Operating Licenses DPR-31 and DPR-41, respectively), a schedule for the completion of plant modifi-cations related to fire protection is attached.
Additional information regarding incomplete items listed in Section 3.2 of the Safety Evaluation (enclosed with your March 21 letter) is also attached.
Very truly yours, obert E. Uhrig Vice President Advanced Systems G Technology REU/MAS/ms Attachment cc: Mr. James P. O'Reilly, Region II Robert Lowenstein, Esquire VODKA90l(/$
PEOPLE... SERVING PEOPLE
ATTACHMENT Re: Turkey Point Units 3 s 4 Docket, Nos. 50-250 6 50-25l Pire Protection X. Plant Modification Schedule XX. Water Supply (NRC Safety Evaluation Section 3.2.3)
,~ ~
t P3KLIMINABY MODXFICATXON SCHEDULE t
TURKEY POXNT UNXTS 3 6 4 PIRE PPL's PROTECTION'ngineeering NRC NRC Proposed Design Submittal Approval Implementatic Com letion Date Date I 3.1.1 Pire Detection
~Ss t.
1 2.3 Nov. 1979 Dec. 1980 4,5 Sept. 1979 Sept. 1979 Nov. 1979 Dec. 1980 Nov. 1979 Dec. 1980 7,8 Nov. 1979 Nov. 1979 Dec. 1980 9,10 Nov. 1979 Dec. 1980 ll Peb. 1979 3.1.2 Pire Mater
~Su ~1 Sept. 1979 Sept. 1979 Nov. 1979 Dec. 1980 1.2 Nov. 1979 3.1.4 Pirehouse Nov. 1979 3.1.5 Xnterior Hose Stat>on Nov. 1979 Dec. 1980 Nov. 1979 Nov. 1979 Dec. 1980 Nov. 1979 Dec. 1980
- 3. 1. 6 Naser
~Sstem Sept. 1979 Sept. 1979 Nov. 1979 Dec. 1980 3.1.7 Poam Su ression Nov. 19'79 Sept,. 1979 Sept. 1979 Nov. 1979 Dec. 1980
PPL' Engineering 'RC NRC Proposed Design Submittal Approval Xmplementatio I'tom Com leti'on Date 'ate 'S'ee (*)
3.1.8 Portable L'xtruguishers Nov. 1979 3.1.9 Pire Doors Nov. 1979 Nov. 1979 Dec. 1980 ci 2,3,4 ' Nov. 1979 Dec. 1980 k$
V Nov. 1979 Nov. 1979 Dec. 1980 Nov, 1979 Dec. 1980 1 ,Nov. 1979 Dec. 1980 2 -
Nov. 1979 Nov. 1979 Dec. 1980 3 Nov. 1979 Dec. 1980
- 3. l. 11 Penetrations 1/2 Nov, 1979 Dec. 1980 3.1.12 Barriers 1 Nov. 1979 Dec. 1980
.3 . 1. '13 Curbs 1,2,3,4 Nov, 1979 Dec. 1980 3.1.14 Pire Retardant Cable Coatin s Jan. 1979 2 Jan. 1980 3,4,5 Jan. 1979 3.1.15 Control of Combustibles Sept. 1979 Sep't. 1979 Nov. 1979 Dec. 1980 2 Nov. 1979 Dec. 1979 3 Nov. 1979 Jan. 1980 Nov. 1979 Dec. 1980 Jan. 1980 6,7 Nov. 1979 Dec. 1980
FPL' Engineering NRC NEC Proposed Design Submittal Approval Implementatio Item Com letion Date Date 3.1.16 Fire Fighting Access Jan. 1980 3.1.17 Smoke-Ventin EcCE~i> .
Dec. 1979
- 3. l. 18 Air Breathing EqEui Dec. 1979 Light:in Nov. 1979 Dec. 1980 Nov. 1979
tern 3.2 ' Smoke Detection No Modification Identified
~ss To Date
- 3. 2. 2 Reactor Coolant No Modification Identified
~Pum To Date See Enclosure II 3.2.4 Auxiliary Building See PP6L letter dated April 5, Corridor 1979 L-79-77
- 3. 2. 5 Cable S readin Room See FPGL letter dated April 5, 1979 L-79-77
3.0
SUMMARY
OF MODIFICATIONS AND INCOf1PLETE ITEtlS 3.1 tlodifications The licensee plans to make certain plant modifications to improve the fire protection program as a result of both his and the staff's evaluations.
These proposed modifications are summarized below. The sections of this report which discuss the modificatio'ns are noted in parentheses following each item. Further detail is contained in the licensee submittals. The licensee will provide a schedule for all modifications within 60-days of the issuance date of this Safety Evaluation. All modifications will be completed by December 1980.
Certain items listed below are marked with an asterisk to indicate that the NRC staff will require additional information in the form of design details to assure that the design 'is acceptable prior to actual implemen-tation of these modifications. Me request that this information be sub-mitted within six months of the issuance date of this Safety Evaluation.
The balance of the other modifications has been described in an acceptable level of detail.
3.1.1 Fire Detection S stems Early warning automatic fire detection systems will be provided in the following areas:
(1) In the makeup air supply to the control room (5.1).
(2) In the kitchen area of the control room (5. 1).
(3) In the rod control equipment rooms (5.5).
(4) In the switchgear rooms (5.6).
(5) In the diesel generator rooms (5.7).
(6) In the charging pump rooms (5.8).
(7) In the chemistry laboratories (ho't and cold labs) (5.8).
(8) In the new laundry facility (5.8).
in" The licensee is reevaluating this commitment as part of the issues identified Section 3. 2.4 and 3.2.5. Me will require that this, or an equivalent improvement be made.
3-1
Hoditications will be made f'r if required to insure an unimpeded flow path smoke for the vertical control boards and freestanding panels to the smoke detectors located in the false ceiling of'he control room (5.
1).'l0)
.Remote alarm lamps will be provided for the smoke detectors located above the false ceiling in the control room (5. 1).
A fire watch patrol will be established to inspect the lower level of the turbine area at a frequency of once per hour (5. 12).
Fire Mater Su 1 adequately'ized spool piece connection will be provided w'ith gated .
valves on the fire water loop and the discharge header of the screen wash This connection will not be permanently installed (3.2.3 and pumps.
4.3.1.1). ':
3.1. 3
'n ~Yd A
at d d 2b-inch gate valve one of'he two will be provided at the hose. house for installation outlet ports at the yard hydrants (4.3.1.3).
The equipment in the yard hydrant hose cabinets will be augmented by the addition of one portable hand light, a hose clamp, one 2<-inch fog nozzle-with shutoff valve, and two 1~>-inch spanner wrenches (4. 3. 1. 3).
'3.1.4 Firehouse E ui ment The complement of equipment in the firehouse will be augmented by the addition of eight portable hand lights, a forceable entry tool, two 2<-inch by 24-inch double female adaptors, and protective clothing to outfit eight men. Storage facilities will be provided in the firehouse for two smoke six air breathing units, spare fire hose, gaskets, and nozzles 'jectors, (5.13.
6).'.1.5 Interior Hose Stations Booster hose stations with low flow capacity shutoff nozzles will be provided with sufficient hose reach for all of the. following areas:
(1) Control room (5. 1).
(2) Cable spreading'oom (5.2).
(3) Switchgear rooms (5.6).
The licensee is reevaluating this commitment,.as part of issues identified i' Section 3.2.4 and 3.2.5. Me will require that this, or an equivalent improvemen ,
be made.
3" 2
3.1.6 9/ater Su ression S stems (l) Fixed automatic water spray protection will be provided for the door and ventilation openings of the switchgear rooms which face main and.auxiliary transformers (5.6).
~
3.1.7 Foam Su ression (1) Portable foam suppression equipment will be provided (4.3. 1.6).
(2) A means will be provided for introducing foam from a portable foam system into the diesel generator rooms and diesel fuel oil day tank raoms (5. 7).
3.1.8 Portable Extin uishers Two portable 2, gallon pressurized water extinguishers will be provided ir..
the control room (5. 1).
3.1. 9 Fire Doors in the following areas will be replaced with rated fire doors as I'oors noted:
(1) Access doors from cable spreading area to turbine building - 1',-hour rating (5. 2).
(2) Access doors from switchgear room to transformer area - three-hour .
rating (5. 6).
1<-hour-(3) Access doors from switchgear room to east turbine area rating with fuse link dampers, normally closed (5.6).
(4) Access doors'o diesel day tank rooms (5.7).
(5) Corridor access doors in the auxiliary building leading to the chem-istry laboratories (hot and cold labs) and new laundry facility-three-hour rating (5.8).
(6) Access doors to containment electrical penetration rooms 14-hour rating (5.9).
The .licensee is reevaluating this commitment as part of issues identified in made.'-3 Sections 3.2.4 and 3.2.5. Me will require that this, or an equivalent improvement.,
be
~RD (l) Three-hour rated fire dampers will be provided in the ventilation openings of the switchgear room which faces the transformer areas. These dampers will be normally closed (5.6).
The chemistry laboratories (hot and cold labs) and the new laundry facility will be isolated from the auxiliary building corridor by the use of 3-hour fire dampers in ventilation openings (5.8).
(3) The side wall,vent openings in the containment electrical penetration rooms will be protected by l~-hour fire dampers
- 3. 1.
(5.9).'enetrations, 11 (1) The openings between the floor and south wall of the upper level of the
'witchgear rooms will be sealed (5.6).
(2) Penetrations in the. wall separating. the diesel generator units and between the diesel generator units and day tank rooms will be sealed to provide a three-hour rated fire barrier (5.7).
3.1.12 Barriers A barrier will be constructed to impede heat and smoke from entering the diesel generator rooms via the louvered openings facing the outdoor fuel oil storage tank (5.7).
- 3.'1.13 Curbs (j) Curbs will be provided for the doors on the lower level of the switchgear rooms (5.6).
(2) A curb will be provided at the doorway in the west wall of the south
'iesel generator room (5.7).
(3) A curb will be provided at the doorway in the north wall of the Unit 3 charging pump room (5.8).
(4) Curbing will be provided around each auxiliary teedwater pump (5. 12).
- 3. 1. 14 . Fire Retardant Cable Coatin s Cables in trays with safe shutdown related cables in the following areas.
will be covered with a flame retardant coating:
'he licensee is reevaluating this commitment as part of'he issues identified in Sections 3.2.4 and 3.2.5. >le will require that this, or an equivalent improvement, be made.
3-4
(1) Inverter room (5.3).
(2) Containment (5. 10).
(3) Lower level of turbine area (5. 12).
(4) Auxiliary feed pump area (5. 12).
(5) In the vicinity of the condensate storage tank and transfer pumps (5.13).
- 3. l. 15 Control of Combustibles The use of the hydrogen supply lines in the auxiliary building corridor will be discontinued and new lines will be provided for use outside of this area (5.8).
(2) barrels in the auxiliary building used to collect radiation
'lastic protective clothing will be replaced with barrels made of a fire retardant material (5.8).
The hydraulic coupling oil cooler lines on the charging pumps will be replaced with lines made of a noncombustible material (5.8).
The control point guard house at the entrance of the auxiliary building will be replaced by a structure of noncombustible construction (5.12).
(5) The oil dispensing station at the south end of the turbine area will be relocated to an area which will not expose safety-related systems (5. 12).
The flammable chemical storage located on the ground floor of the turbine area will be relocated (5. 12).
(7) Isolation valves will be provided within the diked area of the outdoor diesel fuel storage tank for the feed lines to the transfer pumps. Manual bypass valves will be provided for the fail-closed isolation valves (5. 13).
- 3. 1. 16 Fire Fi htin Access (l) Unused portions of cable trays in the containment electrical penetration rooms will be removed to'mprove fire fighting access. Fixed ladder-access wil'1 be provided for all levels of the penetration .rooms (5.9).
The licensee is reevaluating this commitment as part of the issues identified in Sectio'ns 3.2.4 and 9.2.5. >Ie will require that this, or an equivalent improvem nt, be made; 3-5
- 3. 1. 17 Smoke Ventin E ui ment Two fire service portable smoke ejectors of the explosion proof type with a capacity of 5,000 cfm or, greater will- be provided for fire brigade use (4.4. 1).
- 3. 1. 18 Air Breathin E ui ment Air breathing equipment will be augmented to provide a total of 15 self-containe air breathing apparatus and 30 spare air cylinders. At least 15 of the spare cylinders will be fully charged. Six air cylinders will be stored a readily accessible location neai the control room. A 6-bottle cascade
't system capable of'efilling 23 air bottles will be provided (4.4.2).
- 3. l. 19 Emer enc Lit htin Fixed seal beam self-contained battery-operated lighting units will be provided in the control room, auxiliary building corridor, cable spreading room, and switchgear rooms (4.6).
(2) Portable seal beam battery"operated lights will be provided for fire brigade and emergency operations personnel use (4. 6).
3.2 Incom lete Items In addition to the licensee s'roposed modifications, a few incomplete items remain, as discussed below. The sections of this report which discuss these incomplete items are noted in parentheses. 9/e will address the resolution of incomplete items in a supplement to this report. Your submittal should include a schedule for any additional modifications, such as may'be required as a result of the resolution of the incomplete items.
- 3. 2.1 Smoke Detection S stems Bench tests will be conducted on a minimum of 50K of the installed smoke detectors in each zone to verify that the detectors will provide prompt response and have adequate sensitivity to the products of combustion for the combustibles in the areas where they are installed. If detection systems are f'ound to be inadequate,'ppropriate modifications will be made to provide adequate detection system performance.
(2) With regard to the adequacy of'he smoke detection systems, we have requested in situ testing be conducted w>th a suitable smoke generation device 'hat to verify that the location and placement of smoke detectors is adequate to give prompt response and. that the ventilation air flow patterns in the area do not significantly reduce or prevent detection system response.
The licensee has not found a suitable means to conduct such tests in a manner which does not introduce further safety considerations. Further action is being taken in the developm nt of a suitable test method.
However, if a practical solution to this type of testing cannot be estab-lished within six months of the date of this Safety Evalua-tion, an evaluation by an independent registered fire protection engineer (as defined in our guidance dated February 23, 1978 attachment 1 page 3. }
knowledgeable in fire detection will be performed within nine months of the date of this Safety Evaluation to certify the adequacy of smoke detec-tion systems in lieu of in situ testing. No additional information is requested from the licensee (4.2).
Reactor Coolant P~um s Me have requested that an oil collection system be provided for each of the reactor coolant pumps. The licensee has deferred action on this recommendation pending the final resolution of an EPRI study, "Evaluation and Test of Improved Fire Resistant Fluid Lubricants for Mater Reactor Coolant Pump Motors." If a suitable lubricant is not found, the licensee provide a system to suppress potential fires or provide for the 'ill removal ot potential oil leakage to a saf'e location by December 1980. No additional information is required from the licensee (5. 10):
Mater Su ly Me have requested that an adequate supply of water for fire protection be physically dedicated (e.g. by a vertical standpipe). Me have requested that the licensee confirm his calculations on the adequacy of the screen
'ash pumps, as an alter nate source of water for fire fighting, to meet the maximum area of demand for fixed systems. Me will request, should the screen wash pumps prove to be an adequate alternate water source, that the spool piece, which the'icensee proposed, be permanently connected to the-screen wash system to provide a completely redundant water supply. Mhen the above information on the water demand is available. we will evaluate and report our findings in a supplement to this report.
it This information will be provided within 60 days from the date of this'afety Evaluation (e.3.1).
Auxi 1 i ar Bui 1 din Corridor Me have requested the installation of sprinklers to provide protection for safety-related cables from exposure fires in the auxiliary building corridor.
Me have also requested additional information in our letter dated March 2, 1979 regarding the shutdown of both units following a fire in this area..
After our review of the additional information we will report on the adequacy of the fire protection for the Auxiliary Building corridor (5.8).
Cable S readin Area It is our position that a capability independent of the cable spreading room should be provided to safely shutdown both units. Me have re'quested additional information from the licensee in our letter dated triarch 2, 1979 3" 7
to demonstrate that both units can be shut down independent of a fire in the cabling and equipment located in the cable spreading room. After we have reviewed the additional information we will report on the adequacy of the fire protection plans for the cable spreading room (5. P).
Technical S ecif'ications for Existin E ui ment On November 8, 1978 amendments 42 and 34 were issued with limiting condi-tions for operation and surveillance requirements for existing fire protec-tion systems and administrative controls. Certain exception taken by the licensee were identified as being subject to further staff review. The staff position in regard to those items is unchanged. No additional information is required from the licensee.
3-8
WATER SUPPLY Florida Power 6 Light Company (FPL) has evaluated the hydraulic sprinkler demand calculations for the Turkey Point Unit 4 Wet Pipe Sprinkler System. Due to the zonal nature of the sprinkler system, FPL has determined that the largest area is located under the Unit 4 turbine operating floor between columns 30.1 and 32.1 North/South and between columns E and A East/West, including the condensate pump pit,, for a total area of 3945 square feet:.
However, by precluding an unmitigated oil fire from flow-ing into the condensate pump pit, this area of concern can be effectively reduced to 2685 square feet. Based on the smaller area, FPL has confirmed the adequacy of the fire pumps and the screen'ash pumps as follows:
- l. Assuming one fire pump is supplying the wet. pipe system under the North end of the turbine deck on Unit 4, and the wet pipe system is operating in its entirety, the total flow would by 2090 gpm at 145 psig. 750 gpm would be utilized for fire hose streams, leaving 1340 gpm for the wet pipe system.
This provides about 0.50 gpm/ft to the area of concern.
- 2. Assuming one screen wash pump (connected to the fire main) is supplying the wet pipe system under the North end of the turbine deck on Unit 4, and the wet pipe system is operating in its entirety, the total flow would be 1600 gpm at 63 psig. 750 gpm would be utilized for hose streams, leaving 850 gpm for the wet pipe system. This provides about 0.32 gpm/ft to the area of concern.
We propose to install curbing to preclude an unmitigated oil fire from flowing into the condensate pump pit.