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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
r REGULATOR NFORMATION DISTRIBUTION . TEM (RIDS)
Zj AOCKSSION 'NBR"f 206010290 DOC DATE,'2/05/26 NOTARI'ZED: NO. DOCKET FAOIL:50- 50'rkey ~
Point Pl anti 'Uni t 3i Fl or ida Power and Light 'C 05000250 AUTH, NAME AUTHOR AFFILIATION UHRIGi 8 E, ~ F1 or ida Power 8 Light Co ~
IR BC I P ~ NAME RECIPIENT AFF ILIAT ION VARGAi A, S ~ Operating Reactors Branch 1
SUBJECT:
For wards addi into r e NUREG-0737i Item II B ~ ii "RCS Ventsi"
~
in response 'to NRC 820229 request Three oversize drawings encl. Aperture cards are available in PDR.
~RACY) i@i4 W DISTRISUTION CODEI AOASS:COPIES RECEIVED:LTR,JENCL Q SIZEi i
(@+3 TITLE: Response to NUREG "0737/NUREG 0660 TMI Action Plan Rgmts (OL's)
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~ SW PiEASVae RECIPIENT ID CODE/NAME To, 4S COPIES Pic.8 LTTR ENCL br'C (i)RECIP IE/T ID CODE/NAME CZ) Sc~~
COPIES LT~TR ENCL ORB 01 BC 01 7 7 INTERNALS ELD/HDSO 1 0 IE/DEP 0IR 33 1 1 IE/DEP EPOS 1 1 IE/DEP/EPLB 3 3 NRR/DE DIR 21 1 1 NRR/DE/ADCSE 22 1 1 NRR/DE/ADMQE 23 1 1 NRR/DHFS D1R 28 1 1 NRR/DHFS/DEPY29 1 NRR/DL D I'R 10 1 1 NRR/DL/ADL 16 1 1 NRR/DL/ADOR 1'5 1 1 NRR/DL/ADSA 17 1 1 NRR/DL/DRAB 18 3 3 NRR/DSI DIR 2A 1 1 NRR/DS I/ADDPS25 1 1 NRR/DS I/ADRP 26 1 1 NRR/DS I/ADRS 27 1 NRR/DS I/AEB 1 1 NRR/DSI/ETSB 1 NRR/DS I/RAB 1 1 NRR/DST D IR 30 1 1 NRR 'GP 31 1 1 NRR/DST/ADT 32 1 G- 00 1 "1 RGN2 1 1 EXTiERNALo ACRS 3u 10 10 FEMA REP DI V 1 1 INPOiJ,STARNES 1 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF lCOPIES REQUIRED0 LTTR 53 ENCL '52
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FLORIDA POWER & LIGHT COMPANY May 26, 1982 L-82-221 f ti Of i ce of Nuc1 ear Reactor Regul a on Attention: Mr. Steven A. Varga, Chief Operating Reactors Branch gl Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Varga:
Re: Turkey Point Units 3 8 4 Docket Nos. 50-250 and 50-251 Post-TMI Requirements NUREG-0737 Item I I.B. 1 Reactor Coolant S stem Vents Attached is the Florida Power and Lighh response to your February 24, 1982 letter which contained a request for additional information concerning the RCGVS at Turkey Point Units 3 and 4. We trust that our response will allow the staff to complete thei r revi ew.
Very truly your s, PuM Robert . Uhrig Vice President Advanced Systems 8 Technology REU/PKG/mbd cc: J.P. O'Reilly, Region II Harold F. Rei s, Esquire S
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ii I
ATTACHMENT Re: Turkey Point Units 3 Docket Nos. 50-250, 50-251 Pos+ TMI Requirements NUREG-0737 Item II.B.1 Reactor Coolant S stem Vents QUESTION l Verify that the reactor coolant gas vent system (RCGVS) flow xestriction oxifices are 'smaller than the size corresponding to the definition of a loss-of-coolant accident (10 CFR Part50, Appendix A) by providing the pertinent design parameters of the reactor coolant makeup systems and a calculation of the maximum rate of loss of reactor coolant through the RCGVS orifices (reference NUREG -0737 Item II.B.l Clarification A.(4)).
Response-The orifice used in the RCGV'S (7/32" x l") is the standard size orifice used throughout the C-E NSSS to limit mass loss from instrument line breaks to less than the makeup capacity of a single charging pump.
Initial conditions upstream of the orifice were consideredwith pxessures ranging from 1800 to 2250 psia at corresponding saturation temperatures to calculate the mass flow rate through the orifice. Under these con-ditions, the orifice will limit the mass loss to approximately 4 ibm/sec (29 gpm), which is w'ell within the capacity of a single charging pump (77 gpm).
J> 1
UESTION 2 The following items apply to the portions of the RCGVS that form a part of the reactor coolant pressure boundary, up to and including the second normally closed valve (reference NUREG-0737 Item II.B.l Clarification A.(7)).
Verify that the materials of. construction will be fabricated and tested in accordance with SRP Section 5.2.3, "Reactor Coolant Pressure Boundary Materials."
- b. Demonstrate that internal missiles and the dynamic effects associated with the postulated rupture of piping will not prevent the essential operation of the RCGVS (i.e., at least one vent path remains functional) (reference Appendix A'o 10 CFR part 50, General Design Criterion 4).
RESPONSE
The RCGVS is a modification to the existing reactor vent, thus the change was performed in accordance with ASME Section XI. Therefore, the system was installed in accordance with the applicable PSAR committments in regard to the requirements of SRP Section 5.2.3. The components for the system were procured in accordance with SRP Section 5.2.3.
- b. There are no postulated piping failures which would preclude the essential operation of the RCGVS. In the vicinity of the RCGVS there are no potential internal missiles or dynamic effects (pipe whip, jet impingement, etc.) that= would preclude the essential operation of the RCGVS. The high energy lines inside containment are not in close proximity to the RCGVS.
i+I UESTION 3 Since your submittal of July 16, 3.981 was based on the Combustion Engineering, generic RCGVS design., verify that your final piping configurations have been "reviewed or analyzed to assure their capability in maintaining the integrity of the piping system" (reference p.23 of your submittal).
RESPONSE
Attached. for your information is the stress report certificate for the piping stress analysis of Turkey Point Units 3 6 4 Reactor Head Vent System. Mhen the "final as-built" configurations of the, system are complete, the information will be transmitted to Combustion Engineering for final verification of the stress analysis. However, no maj or modifications of the system during installation is anticipated.
Ql 4 ~
Stress Report Certificate This is to certify that, in accordance with'SIDE Boiler and Pressure Vessel
.Code; Section III, Paragraph NA-3260, the following Stress Report has been reviewed and is based on the Design and Service Loadings stated in the De-
.sign Specification identified below.
Stress Report: Vendor: Nuclear Structures Inc.
Report: '002-08 Revision: 00 Date: 11-17-81 Design Specification f: 96480-PE-141 Revision: 02 Date: 10-21-81 Plant Owner: Flordia Power & Light (Turkey Point Units 3 5 4}
Designee: Combustion Engineering, Inc.
Power Systems Group Nuclear Power Systems .
Mindsor, Connecticut Certified by:
Approved by:
Name Title Date
i' UESTION 4 Verify that the following RCGVS failures have been analyzed. and found not,to prevent the essential operation of safety-related systems required for safe reactor shutdown or mitigation of the consequences of a design basis accident:
a0 Seismic failure of RCGVS components that are .not designed to withstand the safe shutdown earthquake.
- b. Postulated missiles generated by failure of RCGVS components.
C~ Fluid sprays from RCGVS component failures. Sprays from normally unpressurized portions of the RCGVS that are Seismic Category 1 and Safety Class 1, 2, or 3 and have instrumentation for detection of leakage from upstream isolation valves need not be considered.
RESPONSE
- a. The entire reactor coolant head vent system at Turkey Point Units 3 6, 4 will be seismically supported, thus this question is not applicable.
The normally closed isolation valves on the system which are the only components of the system which could generate a missile have been provided with backseats to,preclude a missile. In accordance with the Turkey Point Units 3 & 4 FSAR, Page 5E-5, valves provided with backseats do not have to be considered to generate internal missiles. Hence, the ability to achieve and .maintain a safe reactor shutdown is assured.
Ce The normally unpressurized portions of the reactor coolant head vent system are entirely Seismic Category I and Safety Class 1, 2 or 3'up to the second isolation valve, and have leak detection capabilities from upstream isolation valves.
Fluid spray from the normally pressurized portion of the RCS head was not considered in accordance with SRP 3.6.2, since the, pipe diameter is one inch or less.
Qi I
uestion 5 Describe the design features or administrative procedures, such as key locked closed val'ves or removal of power during operation, that will be employed to prevent inadvertent actuation of the RCGVS (reference iXUREG-0737 Item II.B.l Clarification A. (7)).
~RBS OllSL The RCGVS at Turkey Point utilizes key.:locked closed valves during operation, to prevent inadvertant actuation.
4~
UESTION 6 Demonstrate, using engineering drawings (including isometrics) and design descriptions as appropriate, that the RCGVS paths to the containment atmosphere (both direct and via the quanch tank rupture disc) discharge into areas:
- a. That provide good mixing with containment air to prevent the accumulation or pocketing of high 'concentrations of, hydrogen, and
- b. 'n whichshutdown any nearby structures, of the reactor systems, and components essential or mitigation of a design basis to safe accident are capable of ~ithstanding, the effects of the anticipated mixtures of steam, liquid, and noncondensible gas discharging from the RCGVS (reference NUREG-073'7 Item II.B.l Clarification A.(9)).
RESPONSE
The flow path to be used during post accident operation is the vent to the containment atmosphere. The flow path to the pressurizer relief tank is provided as an aid during the filling and venting of the reactor. Therefore, our response is limit'ed to the direct flow path to the containment.
The discharge point from the RCS vent is located at elevation 80'-0" (see Nuclear Structures, Inc. Drawing No. 2002-08-2, Rev. 0, Coordinates C-6). As can be seen on drawing 5610-M-60 and 5610-M-154 this discharge point is in an open area of the containment that is well suited'or mixing. There is no equipment or structure above the discharge point that could form pockets of high concentrations of hydrogen.
- b. As can be seen on the same drawings referenced above, there is no safety related equipment in the area that would be affected by the discharge from the 'RCS vent.
Ol I
uestion 7
- 1. Submit operating guidelines for use of the RCGVS including the following:
- a. Guidelines to determine when the operator should and should not manually initiate venting, and information and instrumentation required for this determination (reference NUREG-0737 Item II.B.1 Clarification A.(2)). The guidelines to determine whether or not to vent should cover a variety of reactor coolant system conditions (e.g., pressures and temperatures). The effect of the containment hydrogen concentration on the decision to vent or to continue venting should also be addressed considering the balance between the need for increased core cooling and decreased containment integrity due to elevated hydrogen levels.
- b. Methods for determining the size and location of a noncondensible gas bubble (reference Position (2) and Clarification A.(2)).
- c. Guidelines for operator use of the vents, including information and instrumentation available to the operator for initiating or terminating vent usage (reference Position (2)).
- d. Required operator actions in the event of inadvertent opening, or failure to close after opening, of the vents including a description of the provisions and instrumentation necessary to detect and correct these fault- conditions (reference Position (2) and Clarification A (2)).
- e. Methods which in lieu of venting will assure that sufficient liquid or steam will flow through the steam generator U-tube region so that decay heat can be effectively removed from the reactor coolant system (reference Clarification C.(2)).
~Res ense The Turkey Point nuclear Safety Committee has appr oved a new procedure (0P 1008.10, Response to .Voids in the Reactor Vessel) for the off-normal use of
. the reactor vessel head vent.
- a. The procedure directs the operator to initiate venting when needed and to terminate when not needed or wnen adverse RCS conditions exist. The procedure allows use of the head vent system under a variety of RCS conditions. Hydrogen concentration in containment is addressed in the procedure and is one of the parameter prerequisites governing RCS venting.
t
- b. The procedure is primarily concerned with void formation in the reactor vessel and does not attempt to distinguish as to size and location of the non-condensible gas bubble.
- c. The procedure offers adequate guidelines for operator use of the vents including. i nformation on instrumentation available to the operator for initiating and terminating vent usage.
- d. The procedure does not address operator actions in the event of inadvertent openi ng or failure to close after opening. Uue to the fact that the RCGYS is equipped with key locks and because it utilizes double valve protection, ther e exi sts .more than adequate protection against inadvertent opening. The administrative procedural controls used in the procedure to prevent failure to close after opening are deemed adequate by the Turkey Point Plant Nuclear Safety Committee.
- e. The procedure requi res the operator to attempt to repressurize the RCS prior to venting in an attempt to collapse any existing voids.
If this attempt and the head vent attempt fail,, the RCS parameters should exceed the limits stipulated in the procedure.. If this was the case, the operator is instructed to reinitiate safety injection to assure adequate core cooling.
A copy of procedure OP- 1008. 10 is enclosed for your information. The procedure was written utilizing, for the most part, the guidelines provided by the Westinghouse Owners Group.
Ql QUESTION 8 Verify that all displays (including alarms) and control's, added to the control room, as a result of the THI Action Plan requirement for reactor coolant system vents, have been or will be considered in the human factors analysis required by NUREG-0737 Item X.D. I, "Control-Room Design Reviews."
RESPONSE
All displays and controls, added to the Control Room as a result of the TMI Action Plan requirement for reactor coolant system vents are being considered in the human factors analysis .required by NUREG-0787, Item I.D-l, "Control Room Design Reviews."
I '
~
RIDA POWER AND LIGHT CQHPA.'IY TURKEY POINT UiHTS 3 P~iD 4 OFF-NOR"1AL OPERATING PROCiDL~v 1008 10 APRIL 29, 1982
1.0 Title
RESPONSE TO VOID IN REACTOR VESSEL 2.0 Approval and List of Effective Pages:
2.1 ~Ao revel:
Reviewed by Plant Nuclear Safety Committee: 82-42 Approved by Plant ~iwnager-Nuclear. 4/29!82
- 2. 2 Lis t o f Ef fective Pages:
~Pa e Date ~Pa e Date Page 1 4/29/82 3 4/29/82 5' 4/29/82 2 4/29/82 4 4/29/82 "
4/29/82 7 4/29/82 3.0 Purnose and Discussion:
- 3. 1 cirrose 3 This procedure provides instructions when a void is detected in the reactor vessel and when the operator determines that it should be removed.
3.2 Discussion; 3.2.1 Any number of transients can result in a void, whenever saturation conditions exist in the vessel head, or gas 's infected into or generated in th RCS.
3.2.2 Removal of a void in the reactor vessel should not be at tempted until a stable, subcooled RCS exists.
3.2.3 This procedure describes steps to remove the void. An initial attempt is made to condense the void. Th's attempt will ultimately succeed if the void is steam. I the void is gaseous, a head vent operation must be performed to remove the void.
- 4. 0 ~gross:
4.1 Variations from the normal pressurizer pressure and level response due to no. al charging and sparying op rations my be observed the RCS.
if a void exists in The pressurizer level may decrease during charging due to void contraction and level may rise rapidly during a spraying operation due to a void expansion.
4.2 Gases in the reactor coolant system ay result from several types of plant event"-. An accumulator d'scharge or a core uncovery may result in non-condensible gases being trapped in the RCS.
4.3 A rapid RCS cooldown may resul t in the'essel h ad temperature being greater than the primary saturation temperature and result in a steam bubble being developed.
NOTS: The of the operator should suspect tha above events occar.
p= eence oi gases ln the RCS li any
4/29/02 OFF-lClIHAL OMUTING PBDQ3XIRE IOOS. IO, PAtZ 2 RESIYNSE 'IO tJom TH RIMCIOR VL'SSEL me ACTIN/Iniycrm RESmm RFSIOIKE MÃ OKATNH) 5.0 Instruct hms:
5.1 Xaucdfate kutanatf c Acting None 5.2 Tnaedfate rator P~: thne 5.3 Sh Actfona:
C h U T I 0 N: EO IXX stop a~ running RCP's or start any stopped RCP's until carpletion of tld.s pmcedure 5.3.f Rcaad RCS Praaure: ~dg 5.3.2 Rx9Xy SZ 9ystea SIC TM OPBKfflH IF ST systan is in oImration, 'HRB go to Step 5.3.9.
5.3.3 (bede Stab1e P,CS Gmditioos:
- a. Presamizer Level STABLE HEMPEN 4'nd 6CC a. Krually adjust letdown ~d cImrgfrg.
- b. RCS Presaxre h&URZ b. Operate liters ard @ray
- c. RCS Ibt Leg Teaperature SfAEfZ C. Ad)ust GtCQGL dOlp.
5.3.4 Try to Collapse Void in Reactor Vessel 2'.
- a. Turn on pressurizer heaters to increase pressure by 50 psf o
- b. Hdntain Manced cIerging md letdown flow.
- c. Ihfntafn pressurizer level G~ 'HIAN TF level less tlen Step 5.3.3.
20X, %Kl turn off pressurizer heaters P2Q return to
II 4/29/82 OFF~V OiHKfigl BSCGNRE 1008.10, PhCH 3 RLSfQSE 'IO IOm IH REACfA? VIA%i Sm -uyralhXPEClm RES>em BESIM% NZ OBTAINED 5.3.5 Vm1fy VMd fblIapm in Reactor Vessel:
- a. Pressurizer level clunges in the direction and at a rate a. IF level clmnges indicate that the void hao not oollapoed, go to corre~fng to RCS l43ter inventory balanceo Step 5.3.6.
(1) Men cl~rgfng plus oeal in)ectfon exceeds letdown plus oeM leakoff, presmrizer level deuld in"reaoe at a rate equivalent to the inventory df fference.
(2) Men chargfng plus oml injection are less than letdown plus oeal leakoff, presairfzer level dmuld deem".oe at a rate equivalent to th invaCory difference. ~
(3) pressurizer spr y operation slxuld not affect presmrf zer level.
- b. Return to procedures in effect.
5.3$ Isolate Iotckan 5.3.7 Qmk Pressurizer Gondftions
- a. Presmrf zer Level GKQ1?R 'JH"f HE a. Increase clmrgfng floe. IF level ca+mt be maintained above antisun chargfng, llR4 m~~ly ini.tiate SI ad go to EW; lm'ith Step 5.1.
- b. Presasrfzer Level REDKBl 2CX and 9QX b. Aliquot cl urging flo~.
- c. RCS Presmre GKGHt 11%1 OR RQM. '10 HlESRM~ c. Energfze liters. IF p'resmre decreasing in an unawtrolled BKXRM) IN Sf' 3.1 muuw.r, 'HRN annually inftiate SI ard go to EW, Step 5.1.
N 0 T E: Venting of the RPV may result in RCS presmre decreasfng belm SI initiation setlmfnt.
4(29/82 OI'F~V OKRATPG KOCEIXmE 1008.10, PAlZ 4 RESmm ID VOID IW I enOI VESSEI.
SIIP ACfIC+B{I'ECKDRESIDlSE Rale N0r aITAmm 5.3.8 (heck Iov Pressure@ Measure & Sigil Status:
- a. Pressurizer Pressure SI SIgnal EUXXED a. KraLslly block.
5.3.9 Q~ RCS Rdxualirg=
- a. RCS Subcooling QIEKIIR MINI 80 P a. IP less elan 80 'F, Vlf'ncrease steam hxnp. IP 80 'F subcoolirg camme be obtained, 'HIBl jo eo E-O, Step 5.1.
5.3.10 ~are QmtaIramt for Reactor easel Venting:
- a. Source (heck R-ll or R-12 and Verify Contaiamnt Ventilation Isolation:
(1) CV~-2819 Cont. Instnaent Air Bleed mSED (2) CV~2826 Cont. Instnma>t Air Bleed QQSH)
(3) NN~-2600 Cont. urge Air Ripply Isol. QlÃED (4) HN~2601 Cont. leery. Air Supply Isol. QUASH)
(5) K@~2602 Cont. urge Atr Shet Isol. (XQK)
(6) ~-2603 (bne. erg Air EdLsust Isol. QIANA)
(7) 1'AN ~V 9 Cont. Vent Supply IRII'iM (8) FAN *-V20 Cone. Vent EdunLst XIII'ILD
- b. Start Contaiarant Afr (Xrculation Fquiprent:
(I) Start all operable ?brmal Contaiamnt (bolers (2) Start all operable HrerI~cy Contaiarmt Coolers (3) Start all operable Bnergency Containment Filters
Ql II,
4/29/82 QV~~SI. 0)IIIATBG HSQQXRIE 1008.10, PAlZ 5 RESMM T0 VOID IH RFACKR VESSEI.
RESIGN NOf QlTATRB 5.3.11 Ihtendne Ihxtaaza All~bio Venting Ihtiod:
- a. Contairmant lgdmgul Concentration - IEiS 'IIIAN 3Z
- b. Calculate Ihximm Venting Rriod:
(See Graph cn Page 7 )
C A,U T I0 H & ANY vent tennlnation criterion jn Step 5 3 12 is reacIRB or exceeded Qlile ventingy IBHSNAIHYB'top venting 5.3.12 Ihvtaz RPV Vent 'lhnuination Criteria:
- a. Contafnaent ligdmgen ConcentratiuHRKKIIR '1IRM 3X IIY MIIHE
- b. RCS Kbcooling IXSS 'IINI Xl F
- c. Pr~~rizer leal IZSS 'IIIAM 3X
- d. HCS Pressure MRP~S IIY 200 PSI
- e. 'enting Period QKZQR llNlImHO CAURIA'IH) IH SIEP 5.3.11 5.3.13 Ant actor Vial
- a. ~ Vent Valves to Containrant: a. ~n Vent Valves to M'.
(I) ~x 6318A or 63188 (I) Jan 6318A or 63188 (2) Cpen 6320B (2) q 63m
'l
~ ~
4/29/02 OFF-1m'. OmlAVaC WXmau. 1OOS.10, Pml 6 tuxmSZ m urn IN RF me mob Sly'Cl'HN/HPcCKO RESIGNS RISI&gLr lCI'E1'AINH) 5.3.13 (cont 'd)
- b. Clom Vent Valves Nun:
(1) Presmrizer 1evel reqxxds in a nornal manner as described in Step 5.3.5.b OR (2) Any tenafnatica criterion of Step 5.3.12 is reached.
c.
5.3.12, ~
IF venting stopped becaua. of PXC criterion in Step return to Step 5.3.7.
5.3.14 Osedc Presaadzer Level SEARS Ad+at ingecticn aal letcka;n, as taquired.
5.3.15 Return to Procedure In Effect 6.0
References:
6.1 Meath')aua. Punctionnl hnvery Qxidelira (%7~) Basic dated S~tudjer 1, 190l.
6.2 ~xy Prccakce 2NXO (EW), ~~ Acticna ard ~~ca 7.0 iiunls mrts md Notifications; 7.1 leg Entries 7.2 Voids in tbe reactor Msa'1 may be reportable oca~s or algnlficant evens, or cay require initiatigg tlat Rheg~xy Plan. '?la Qxxctlons %pe~isa' >bchar, Opcratiom SUperinbxrknt kbdcar or Phyla Huv~ 143aar, @auld be rotlfied as +em aa poedble.
~i ONOP 1008.10
,~
~ ~
.Page j 4/29/82 A ~ Containment,Volume (at STP),
6 2250= (1.55 x 10 Ft ) x 4 92 R Cont. emp. F + CO 8 Haximum H Volume to be Vented 2
(3.0 - Present Cont H Concntration)x A 100~~
2000 o 1750 1500-1250 1000 r',
C I 1 2
~O V
4I~
C4 750 n
500 200 500 750 1000 1250 1500 1750 20 0 C ~ HYDROGEN F2 GW RATE (SCFM)