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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
[Table view] |
Text
REGULA, RV I ~FOH~ATIO>> DISTRIBUTION SYSTF~ (RIOS)
A CCESSION t hR:8003210<>25 OOC DATE: 80/03/18>>OTARIZEO: >>0 I ACIL:50- 'urkev ~
Point Plant~ Uni t 3i Florida Power and Light C 7
05000250
-251 ur key Point Pl anti Unit 4~ F lorida Power and Liaht C 05000251 Specs'OCYTE AUTP ~ A AU THOR AFF IL I ATION UHRTbgh,ED Floriaa Power 5 Light Co ~
RECIP ~ NA>E RECIPIENT AFF Il.lATl0>>
SCH+EACER~A, Operating Reactors Branch 1 SUOJFCT: Hesponds to 791119 ltr reauestina aadl info on condensate polishing demineralizers 8 steam aenerator repair.
Installation of oemineralizer sys does not reauire mod to Tech DISTRIBUTION COOE: A001S COPIES HE.CE.IVEO:LTR + E~CL Q SIZE:~ 4 ~
TITLE: General Oistribution for after Issuance of Ooeratinn Lic
>>QTFS:
RECIP IE'IT COPIES HEC IP I EN T CUP IES lO COVE/VA.!E LTTR E>>CL IO CODE/NA~E L l'TR ENCL ACTION: 05 8C ORB P / 7 7 INTER>>4l: Of REG f 1 1 02 "lRC POR 1 1~ r 2 c? 15 CURE PERF BR 1 1 1 7 ENGR F3R 1 1 18 REAC SFTY i3H 1 1 19 PLANT SYS BR 1 1 20 EER 1 1 21 EFLT TRT SYS 1 1 EP3-OUR 1 1 OELO 0 STS GROUP LEAOH 1 1 EXTER~~AL; 03 l.POR 1 1 04 i'JS IC 1 1 23 ACRS 16 16 tSR / 4. 1989 TOTAL NU~BEH Of COP IES REOU IREO: L T TH 38 6 'vCL 37
March 18, 1980 L-80-87'ffice of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Operating Reactors Branch 81 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Schwencer:
Re: Turkey Point Units 3 & 4 Docket Nos. 50-250 and 50-251 Steam Generator Re air This letter is in response to your letter dated November 19, 1979 which requested additional information on the condensate polishing demineralizers and our planned steam generator repair. The responses to the questions enclosed with your letter are provided in Attachment 1.
The planned installation of a condensate polishing demineralizer system at Turkey Point Units 3 & 4 has been reviewed by the Turkey Point Plant Nuclear Safety Committee. They have concluded that the planned installation of the condensate polishing demineralizer system does not involve an unreviewed safety question or require a modification to the Facility Technical Specifications. A copy of our evaluation is attached as Attachment 2 in accordance with your request.
Please feel free to call me if you should have any additional questions about this matter.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems & Technology REU/GDW/ah Attachments cc: J. P. O'Rei lly, Region II gaol Harold f. Reis, Esquire 5 mls
A. Provide the following information regarding the full flow condensate 0: polishing demineralizer system (contention 7).
I h 11 and its concentration at point of
<<I I release.
11 ionic species as well as contaminants removed from the demineralizers.
Include I h regenerant ANSWER The condensate polishers planned for installation at PTP 3 and 4 are of the Powdex type. Regenerant chemicals will not be utilized. FPL's current scheme for discharge of the polisher wastes includes a solids-water separation process, with high quality supernatant liquid being discharged into the closed cooling system, and solids held for land type burial.
0 0: I the waste.
h 01 ANSWER: A description of Powdex polisher waste is provided in the attached paper by Dr. Robert Kunin.
0 1 0: I h I I 0 0 ANSWER: Condensate polishers planned for PTP 3 and 4 do not involve a regeneration process.
EE lp 0: <<I discharge.
h f 0 <<I f h ANSWER: Same as 83.
00 0: 0 I I the demineralizer waste.
h<<f I p1 ANSWER: Under the currently proposed scheme of waste disposal, only high quality supernatant liquid would be discharged into the facility's closed cooling water system. It does not appear that dilution of the supernatant liquid prior to discharge will be required.
g 0: ld discharge.
d 1 1 1 h ANSWER: The point of discharge is expected to be on the discharge side of the facility.
0 0 : 10 h 11 1 1 111 1 immediate area of the discharge.
ANSWER: Under FPL's current plans for handling condensate polisher wastes, only high quality supernatant liquid would be discharged into the facility cooling canal system. The discharge point would be at the facility's discharge basin. The discharge stream is not expected to exceed 150 gpm. Flow rate through the facility discharge basin due to forced pumping is approximately 1.8X106 gpm with all circula-ting water pumps running. Due to the high quality of the discharge, g 0 ANSWER:
0:
discharge.
10 <<
FPL has no minimum requirement for circulating flow during the prior to release.
FPL's current plan
<<h for the handling of ll h 1110'0 condensate 1
polisher waste is as follows:
Spent resins would be backwashed as a resin-water slurry (using condensate quality backwash water), into a backwash receiver tank. Powdex resin and other solids would then be separated from the slurry leaving a high quality supernatant liquid for discharge into the facility cooling canal system. plan to dispose of the solid resins by 0:
We land burial.
1 <<h <<1 0 " hlh 111 1 d.
ANSWER: It is presently estimated that there will be no environmental degradation caused by the effluent release as a result of the operation of the full flow condendate polishing demineralizer system. The water quality of the polishing demineralizer system effluent discharge is expected to be superior to the water quality of the cooling canal system, Biscayne Bay, or Card Sound, FPL has been issued a National Pollutant Discharge Elimination System (NPDES) permit for Turkey Point Plant, NPDES bFL001562
by the United States Environmental Protection Agency (EPA) on June 14, 1978. That permit authorizes discharges to the circulating water cooling canal system without limitations or monitoring requirements provided that there is no surface discharge to Biscayne Bay or Card Sound. The effluent dis-charge from the full flow condensate polishing demineralizer system will be consistent with the terms and conditions of this permit. The permit requires FPL to monitor the water quality of the circulating water cooling canal system.
Grab samples must be taken quarterly at the outlet from Lake Warren and must include the following parameters:
salinity; total suspended solids; and total zinc, iron and copper. Results are submitted in reports annually on January 31 of each year.
In the event of indications of primary to secondary leakage, samples will be collected from the backwash receiver tank and tested for radioactivity prior to disposal of the wastes.
Liquid radioactive releases. are control.led by Appendix A of the Turkey Point operating licenses (Technical Specifications, Section 3.9) as well as by written procedures. Both quantity and concentrations are controlled. The releases are required to and do meet the restrictions imposed by 10 CFR Part 20 and Part 50, Appendix I.
Disposal of any radioactively contaminated polisher wastes will be in accordance with applicable NRC regulations concern-ing the discharge and/or disposal of solid radioactive wastes and 'radioactive effluents.
ETON: i 1<< f i 1ikly b receiving waters near the point of discharge.
ANSWER: Lists of organisms likely to be present in the cooling canal system have been compiled from published and unpublished sources. The lists of organisms are presented in the following tables, Table A-1 and Table A-2.
g 0: 1 <<h inants present i f i h <<i f in the waste stream on the aquatic organisms found near the plant.
ANSWER: FPL's current plans call for discharging only high quality supernatant liquid to the faci,l,ity cooling canal system.
The supernatant will be of higher quality than the water in the cooling canal system. The supernatant will therefore
have no deleterious effect on the organisms living in the cooling canal system.
UESTION 12'escribe the biological monitoring programs that will be conducted to assess the environmental impacts associated with operation of the demineralizer system.
ANSWER: The existing biological monitoring program (Environmental
.Technical Specification (ETS) for FPL Turkey Point Units 3 and 4) which is implemented for the Turkey Point Plant cooling canals will be used. Plankton (ETS Section 4.'. 1.
- 1. 1), fish (ETS Section 4. 1. 1. 1.2), and benthos (ETS Section
- 4. 1. 1. 1.3) monitoring will provide enough information to assess the environmental impacts associated with operation of the demineralizer system.
UESTION 13: Describe the status of all relevant permits required by other state, local and Federal agencies.
ANSWER: FPL has 'applied for and received all required relevant permits for the Turkey Point Plant from state, local or Federal agencies.
Any new application or amendments required as a result of changes or additions to current operating practices will be made at the appropriate time.
UESTION B: Provide the design details and exact location of the storage building (referred to in contentions 6* and lid). Include the structural design details to the extent necessary for the staff to determine the adequacy of the building to withstand hurricanes and floods. Also include the weight and dimensions of the steam generator lower assemblies to be stored in the building.
Provide the details of the method of sealing the steam generator lower assemblies; weld design, weld material, cap material and dimensions, corrosion protection, and any related information that will be needed to evaluate the possibility of radioactive material leaking out of the stored assemblies.
- Contentions referred to in this request are to be taken as given in the Atomic Safety and Licensing Board's "Order Relative to Contentions and Discovery" dated September 25, 1979.
ANSWER:=- The conceptual design and nominal dimensions of the storage compound are shown on the attached figure'. The final design might change depending on the outcome of ongoing engineering studies and evaluations. Each steam generator lower assembly with steel support saddles will rest on reinforced concrete
bearing pads. The compound will be designed and constructed in accordance with the South Florida Building Code, ACI 318, AMS Dl. 1 and AISC t1anual of Steel Construction; The approximate location of the storage compound in the laydown area is also shown on the attached figure. The current elevation of the laydown area ranges from +6 to +9 feet HLW. The approxi-mate subsurface profile in the vicinity of the storage compound consists of 4 feet of limerock fill fill over 6 feet of muck under and muck will be lain by Miami limestone. The existing excavated to a minimum distance of 15 feet beyond the edge of the storage compound. The entire compound and lay down area will be backfilled or filled as required with compacted limerock fill to + 17'" MLM with perimeter slopes of 1-vertical on 3-horizontal. Heavy equipment transport, laydown storage, and heavy lift crane implacements in support of repair and storage operations will require a minimum of 65 feet around the storage compound.
The limerock fill willfootbe which compacted to a minimum dry density of laboratory tests yields 110 pounds per cubic based on allowable bearing capacity of approximately 15 kips per square
'oot, strength of cohesion of approximately 3 kips per square foot, and an internal angle of friction of approximately 39.
A steam generator lower assembly is approximately 39 feet long and 127 inches in diameter except for the last 6 feet 4 inches where the diameter expands linearly from 127 inches to 166 inches.
The volume is approximately 3620 cubic feet and the dry weight is approximately 205 tons which yields a total vessel density of about 113 pounds per cubic foot.
The top of the assembly (approximately 13'0" diameter) and the two channel head nozzles (approximately 31" diameter) will be provided with 3" steel shield plates. The two blowdown nozzles (approximately 2" diameter), one shell drain (1" diameter), and one instrument nozzle (3/4" diameter) will be provided with 1" steel shield plates. The shield plate materials will be ASTN A36 or equivalent and will be welded to the lower assembly openings. Only carbon steel weld materials will be used and the weld throat will be 1" minimum. Since the storage compound will have a water tight roof the lower assemblies will be protected from industrial corrodent and salt spray deposition, hence special corrosion protection will not be required.
FPL is presently evaluating the effects of a postulated design basis hurricane upon the steam generator storage facility and its foundation. The results of this evaluation will be made available upon completion.
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0 0: 10 h 1 1 (referred to in contentions 1 h 7 and 11 lie).
0 h d ANSWER: The estimated costs for installing a condensate polishing demineralizer system for Turkey Point Units 3 and 4 is $ 9. 1 million.
0 0: dd h <<1" to in contention 11e).
1 1 0 d ANSWER: The cost involved in retubing the Turkey Point Units 3 and 4 condensers was approximately $ 1 million per water box; or a-total of $8 million.
0: 1 <<1 to the present time (discussed in contention llf).
>>11 ANSWER: The repair of the Turkey Point Units 3 and 4 steam generators is estimated to be $ 119.3 million (1979 dollars).
TABLE A-1 ORGANISMS OCCURRING IN THE TURKEY POINT COOLING CANAL SYSTEM (ANNUAL REPORTS, ABI 1974-1980)
ANNELIDA MOLLUSCA Polychaeta Gastropoda (continued)
Amphi ctei s gunneri floridu Prunum apici num Autolytus brevicirrata Retusa eburnea Capi tella capi tata Cauli eri ella killariensis Ci rri formia filigera MOLLUSCA Dorvi llea soci abilis Pelecypoda Fabricia sp. Astarte nana Glycera ambri cana Haploscoloplos foliosus Chione cancellata Laonone salmi ci dis Chione gl US Lumbrineris Sp. Diplodonta nuclei formis Maldane sarsi Gouldia cerina Marphysa sanguinea X,ucina mul tilineata Nereis succinea Lyonsia floridana Odontosyllis enopla modul us carchedoni us Paraoni des lyra Pitar albida Pista cristata Pseudocyrene floridana Platynereis dumel il1ii Tellina Sp.
Tellina al tezata Podarke obscura Polydora li gni ARTHROP0DA
'olyophthalmus pictus Pri onospi o heterobranchia texana Pycnogonida Sebi stomeringos rudolphi Scyphoproctus Sp. Anoplodactylus lentus syllzs sp.
'erebellides stroemi ARTHROPODA Crustacea Tri chobranchus glaciali s Typosylli s Sp. Cylindroleberi s mari ae MOLLUSCA Sarsi ella ameri cana Gastropoda Harpacticoida Oxyurostyli s smithi Batillaria minima Leptocheli a savi gnyi Bulla striata Aegathoa oculata Bulla occi dentale Cymodoce fa'xoni Crepidula forni cata Eri chsonella filiformi s Crepi dula maculosa Idotea metalli ca Cyclostremiscus trilix Sphaeroma quadri denta turn Cyli chna cerina l Elasmopus evi s Hami noea el egans li Eri ch thoni us brasi ensi s Grandi di erel la bonni eroi des Hydrobi a minuta
~
Hemiaegina minuta
TABLE A-1 (continued)
ORGANISMS OCCURRING IN THE TURKEY POINT COOLING CANAL SYSTEM (ANNUAL REPORTS, ABI 1974-1980)
ARTHROPODA FISHES (continued)
Crustacea (continued)
Centropomus undeci mali s rysianopsis alba Fundulus grandis Microdeutopus SP. Haemulon sci urus Mysi s st enol epi s Arius felis Taphromysi s bowmani Strongylura notata Alpheus armillatus Meni dia beryllina Hippolyte pleuracantha Diapterus plumieri Palaemonetes pugio Lagodon rhomoboi des Thor floridanus Caranx hippos Pinnixia sayana Haemulon parrai, Atherinomorus sti pes ECHINODERNATA Ophiuroidea l
Mugi cephalus Elops saurus Chaetodi pterus faber Amphi pholi s squamata Syngnathus Sp.
Gobi onellus SP.
MISCELLANEOUS Selene vomer Strongylura marina Echiuroi d cworms Hippocampus erectus Priapulid cworms Echenei s naucrates Sea squirts Caranx crysos Trachinotus falcatus SHELLFISHES Menticirrhus li ttoralis Archosargus probatocephalus Callinectes sapidus Dormitator maculatus Penaeus SPP. Mi crogobi us mi crolepi s Meni ppe mercenaria Sphoeroides testudineus Panuli rus argus Megalops atl anti ca Zi mulus polyphemus. Carcharhi nus leucas FISHES Floridichthys carpio Cypri nodon vari egatus Poeci lia lati pinna Lophogobi us cyprinoi des Gerres cinereus Euci nostomus gula Belonesox beli zanus Euci nostomus argenteus Lucania parva Albula vulp s Sphyraena barracuda Opsanus beta Fundulus confluentus L,gtjanus griseus L,utj anus apodus
TABLE A-2 ORGANISMS OCCURRING IN THE TURKEY POINT COOLING CANAL SYSTEM (FPL, 1975)
Blue Green Algae Lyngbya sp.
Chroococcus planctonica OsciZZatoria sp.
Chroococcus gigantea Schizothrix calcico1a Arthrospira sp.
Spirul~ sp.
Oscillatoria minor Merismopedia g1auca Johannesbaptisia sp.
Gomphospharia sp.
Merismopedia punctata Anabaena sp.
Eu glen ophyceae Astasia sp.
Eutreptia sp.
Uolvocidae Pyramkdcuonas grossi a
Cryptophysida Silicoflagellida Dictyocha ~ula Baci13 m9.ophyceae Navt.u1a sp.
~toms unid.
Cymatopleura solea Amphora oval.s Synedra ulna Nitzschia sigmoidea Synedra crysta1lina Nitzschia acicularis Su~e1la sp.
Pleurosi~ sp.
Synedra superba Nitzschia longa
Attachment 2 Condensate Polishin Oemineralizer S stem The new condensate polishing demineralizer system is planned for installation in the condensate/feedwater system at the discharge of the condensate pumps between the pumps and the No. 1 low pressure feedwater heater. The system's function is to purify the condensate by filtration and demineralization to assure high quality feedwater to the steam generators.
The condensate polishing demineralizer system control is independent from the existing condensate/feedwater system. When in use, the system treats full condensate flow from the condensate pumps. A full flow bypass system has been provided to assure continuous uninterrupted condensate/feedwater system operation.
Loss of normal feedwater flow due to pipe break, pump failures, valve malfunctions or loss of outside AC power, is discussed in Section 14. 1. 11 of FSAR, Chapter 14.
Technical specification 3.8 discusses the steam and power conversion system.
The condensate/feedwater system is not a safety related system.
10 CFR 50.59 (a) (2) defines an unreviewed safety question as follows:
"A proposed change, test, or experiment shall be deemed to involve an unreviewed safety question (1) if the probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in the safety analysis report may be increased; or (2) if a possibility for an accident or malfunction of a differe'nt type than any evaluated previously in the safety analysis report may be created; or (3) if the margin of safety as defined in %he basis for any technical specification is reduced."
A summary of the review of the planned addition of the demineralizer system against the foregoing definition of an "unreviewed safety question" follows.
With respect to the probability of occurrence of an accident previously evaluated in the FSAR: As discussed previously, a full flow bypass line is provided for the condensate polishing demineralizer system. The probability of a loss of feedwater (LOFW) accident due to a failure in the condensate polishing demineralizer system and a concurrent failure of the bypass control valve to open is extremely small. This probability is not significant when considered in light of the frequency of feedwater transients (2 to 3 per year) as documented in Section 3. 1 of NUREG-0560 "Staff Report on the Generic Assessment of Feedwater Transients in PWR's designed by Babcock and Wilcox," 51ay 9, 1979. Therefore, the probability of occurrence of this accident is not increased by the addition of this system.
With respect to the consequences of an accident previously evaluated in the FSAR:
The addition 'of the condensate polishing demineralizer system has no effect on
the severity of any of the accidents discussed in Chapter 14 of the FSAR. The LOFW accident, which is the most severe accident for the feedwater system, has already been evaluated in the FSAR.
With respect to the probability of malfunction of equipment important to safety previously evaluated in the FSAR: The only system affected is the condensate/
feedwater system, which is not required to mitigate the consequences of a LOFW accident. The addition of the condensate polishing demineralizer system will have no effect on the auxiliary feedwater system since the systems are totally independent of each other.
With respect to the consequences of the malfunction of the equipment important to safety previously evaluated in the FSAR: For the reason stated above, the addition of the condensate polishing demineralizer system will have no effect on the consequences of malfunction of equipment important to safety.
With respect to the probability of an accident of a different type than analyzed in the FSAR: As discussed earlier, the most severe accident for the condensate/
feedwater system is the LOFW. This accident has already been evaluated in the FSAR. The addition of the condensate polishing demineralizer system does not create the possibility for a different type of accident.
With respect to the possibility of malfunction of a different type than any analyzed in the FSAR: For the reason discussed in 2.a above, the addition of condensate polishing demineralizer system would not create the possibility of a malfunction of a different type than considered in Chapter 14 of the FSAR.
With respect to the margin of safety as defined in the basis for any Technical Specification: The addition of the condensate polishing demineralizer system would not decrease any margin of safety discussed in the Facility Technical Specifications.
Conclusion For the reasons discussed above, addition of the condensate polishing demineralizer system does not involve an "unreviewed safety question" as defined in 10 CFR 50.59 (a) (2). The planned addition of the condensate polishing demineralizer system has also been reviewed against the Facility Technical Specifications. The addition of the condensate polishing demineralizer system does not require a change to Facility Technical Specifications.