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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
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ACCELERATED DISIBUTION DEMONS~ION SYSTEM I'
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9104300273 DOC.DATE: 91/04/24 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit, 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION PLUNKETT,T.F. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document. Control Branch (Document Control Desk)
SUBJECT:
Forwards response to NRC questions during 910307 telcon re 901219 application for amends to Licenses DPR-31 6 DPR-41, revising TS Section 2.2 on limiting safety sys settings 6 D Section 3/4.3.2 on ESFAS instrumentation.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES ID RECIPIENT PD2-2 LA CODE/NAME COPIES LTTR ENCL 1 1
'D RECIPIENT PD2-2 CODE/NAME PD COPIES LTTR ENCL 1 1 D
D AULUCK,R 2 2 INTERNAL: NRR/DET/ECMB 9H 1 1 NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 0 ci L'F R
MB~
ICE 0 1
1 0
1 OGC/HDS3 RES/DSIR/EIB 1
1 0
1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 R
D D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16
P.O. Box 029100, Miami, FL, 33102-9100 APR 24 ~ggt L-91-098 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Reactor Protection S stem Set pints By letter L-90-417, dated December 19, 1990, Florida Power and Light (FPL) submitted a request to amend the Turkey Point Technical Specifications. The proposed license amendment, revises Section 2.2, Limiting Safety System Settings and Section 3/4.3.2, Engineered Safety Features Actuation System Instrumentation.
On February 20, 1991, the methodology and setpoints presented in the proposed license amendment were discussed during a conference call between the NRC, Westinghouse, and FPL. Additional discussions took place during a second conference call on March 7, 1991. Attached please find the NRC questions from the March 7 conference call and FPL's responses to these questions.
Should there be any questions, please contact us.
Very truly yours, T. F. Plunkett Vice President Turkey Point Nuclear TFP/DPS/ds Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant I
QAAA< A S'104300273 910424
'I ppY PDR ADOCK 05000250 P PDR goo/
an FPL Group company l(I
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 ATTACHMENT 1 RESPONSES TO NRC UESTIONS DISCUSSED MARCH 7 1991
Attachment 1 NRC Question Responses Page 1 of 5 FPL's responses to questions raised during the March 7 conference call are as follows:
uestion 1 Pressurizer Water Level High Numerical values and methodology in relation to the NRC position as communicated in the conference call held on 02/20/91 and as stated in NRC Regulatory Guide (RG) 1.105 (basically, upper calibration tolerance band + RD should be less than or equal to the Allowable Value).
If new numbers are proposed, discuss basis for those numbers and the relationship to the 95% criteria/confidence level.
Res onse to uestion 1 The FPL/Westinghouse response stated that the Westinghouse methodology for determining the Allowable Value for a function is consistent with the requirements of RG 1.105 and ISA S67.04-1987.
Two approaches are used to calculate the difference between the Allowable Value and the Nominal Trip Setpoint.
The first approach is the simple arithmetic summation of the process rack uncertainty terms that can be verified during the calibration and analog/digital channel operational tests of protection functions. These uncertainty terms are RCA, RCSA, RMTE and RD, as defined in WCAP-12745, "Westinghouse Setpoint Methodology for Protection Systems Turkey Point Units 3 & 4."
WCAP-12745 was transmitted to the NRC in FPL letter L-90-417, dated December 19, 1990. The definition of the first trigger value is:
Tl = RCA + RMTE + RCSA + RD.
This value meets the requirements explicitly. However, Westinghouse carries the determination of the Allowable Value one step further.
A second trigger value is'alculated based on assuming that the transmitter behaves in a normal, predictable manner and starts the calculation from the Safety Analysis Limit (SAL) . This is an additional factor of conservatism which is not required by RG 1.105 or ISA S67.04-1987. The equation for this second calculation is:
T2 = TA (A + S ) EA.
Attachment 1 NRC Question Responses Page 2 of 5 The smaller of the two values (Tl or T2) is then selected as the difference between the Allowable Value and the Nominal Trip Setpoint. This is a more conservative approach. The difference is never larger than the arithmetic summation of the process rack uncertainties evaluated during the calibration and testing phases. The difference may be smaller depending on the magnitude of the margin present in the determination of the Channel Statistical Allowance (CSA) .
The use of T2 for determination of the Allowable Value does not imply that the process rack drift term is unaccounted for (it is still explicitly allowed for in the CSA calculation), but rather this, second check is necessary to account for the use of the square-root-of-the-sum-of-the-squares (SRSS) technique in the determination of the CSA.
A channel uncertainty calculation is considered acceptable when the CSA is less than or equal to the Total Allowance (the difference between the SAL and the Nominal Trip Setpoint). But this calculation does not take into account the difference in effect between the two calculation techniques (SRSS vs.
arithmetic summation) .
The T2 calculation reflects a conservative determination of the Nominal Trip Setpoint/Allowable Value difference using an SRSS viewpoint. The comparison and utilization of the smaller of the two values accounts for the differences in the two techniques and results in a conservative determination of the Allowable Value.
uestion 2 What other parameters are subject to the same situation as Pressurizer Level High please discuss the same points as (1) abo~e.
Res onse to uestion 2 Any protection function where the trigger value is determined by T2 will result in the difference between the Nominal Trip Setpoint and the Allowable Value being less than the sum of the calibration tolerance and rack drift. As noted in the response above, this is a conservative determination of the Allowable Value.
The magnitude of T2 is sensitive to the magnitude of the margin present in the uncertainty calculation, (i.e., the larger the positive difference between the Total Allowance and the CSA, the larger the magnitude of T2) . With the Westinghouse methodology, the smaller of the two trigger values is used for the
Attachment 1 NRC Question Responses Page 3 of 5 determination of the Allowable Value. This is conservative when the trigger value is T2 since a plant investigation of the operability of the channel is required before the'esign values for calibration and rack drift are exceeded. Use of T2 as the trigger value requires the performance of better "as left" calibrations than that assumed in the uncertainty calculation in order to allow more room for rack drift.
The protection functions which have Allowable Values determined by T2 are: Overtemperature delta-T, Overpower delta-T, Pressurizer Water Level High, Loss of Flow, Steam Flow/Feed Flow Mismatch, Differential Pressure Between Steam Header & Steam Lines High, High Steam Flow, and Tavg Low-Low. However, it should be noted that the Allowable Values noted in WCAP-12745 are acceptable based on past operational experience.
uestion 3 Steam Plow High and Steam/Feed Flow Mismatch Is the proposed trip setpoint the same as in the current Technical Specifications what is the current Technical Specification value, in terms of 0 flow. If the proposed trip setpoint is less conservative than the existing trip setpoint provide additional basis including effect whether direct or indirect on accident analysis and assumptions submi;ttal mentions sufficient margin; based on judgement, please provide basis for margin.
if TA is Res onse to uestion 3 The current trip setpoint for Steam Flow High is: a differential pressure (delta-p) corresponding to 20% Steam Flow (0.64 x 10'bs/hr) at 0% load, increasing linearly to a delta-p corresponding to 120% Steam Flow (3.84 x 10'bs/hr) at 100%
load. The revised setpoint documented in WCAP-12745 is: a delta-p corresponding to 40% Steam Flow from 0 to 20% load, increasing linearly to a delta-p corresponding to 120% Steam Flow at 100%
load. Thus there is a significant difference between the two setpoints at 05'oad (20% Steam Flow) with the revised setpoint higher than the current setpoint. However, at 20% load and above, the revised setpoint is conservative, i.e., actuation will occur at a steam flow lower than the current setpoint. In the event of a large steamline break at 0% Rated Thermal Power (RTP),
steam flow increases considerably above the trip setpoint noted in WCAP-12745.
Attachment 1 NRC Question Responses Page 4 of 5 The current setpoint for Steam Flow/Feed Flow Mismatch High is a mismatch of 20% Steam Flow (0.64 x 10'bs/hr) . The setpoint noted in WCAP-12745 is a mismatch of 20% Steam Flow. There is no difference between the current Technical Specifications (noted by Amendment Nos. 137 & 132, dated August 28, 1990) and WCAP-12745.
uestion 4 Reactor trip system interlocks P-6, P-7, P-S, P-10 Provide basis for the Allowable Values.
Res onse to uestion 4 The difference between the Allowable Value and Nominal Trip Setpoint for a permissive is the same as for the protection function providing the input to the permissive bistable. For example, P-10 is based on input from the NIS Power Range channel.
Thus the same trigger value (T1 or T2) is used to determine the Allowable Value for P-10. Since permissives are not required to be operable in adverse environmental conditions, only steady state errors are used to determine the trigger values. A list of protection channels vs permissive, for evaluation of trigger values is as follows:
p-6 Historical value (4 x 10-11 amps)
P-7, P-8, P-10 NIS Power Range High Reactor Trip uestion 5 Evaluation of Differential Pressure Between Steam Header & Steam Lines High and Pressurizer Water Level High Res onse to uestion 5 The NRC Staff was unable to reproduce the exact values noted in the various tables of WCAP-12745 for some of the functions. The values provided in WCAP-12745 are based on a first decimal place precision level. The computer programs used to perform the calculations provide results for two decimal places. However, indication of values to that degree implies a level of precision which is not representative of the input. Therefore, rounded values were provided for the tables which represent the level of precision noted (one decimal place) . A review of all calculation input values and results has been performed by Westinghouse. The results of the calculations and this review are noted in WCAP-12745.
Attachment 1 NRC Question Responses Page 5 of 5 uestion 6 High Differential Pressure Values proposed for S and Z already challenge the TA equation, please clarify.
Res onse to uestion 6 Several functions have large values of S or Z when compared to the magnitude of TA. This would indicate that if Equation 2.2-1 (page 1 of Appendix A of WCAP-12745) was solved, there would be no margin for an "as measured" rack drift term of any significant magnitude. This does not indicate that there is no margin for rack drift, but rather, it points out the significant differences due to two different treatments of the instrument uncertainties.
When this situation arises (e.g., the two protection functions noted above) the Allowable Value is determined by T2. This
,calculation is predicated on the normal, random behavior of the transmitter.
Equation 2.2-1 is very conservatively based on the assumption that the transmitter has drifted to the maximum assumed in the uncertainty calculation and that the drift is in the non-conservative direction. These assumptions are made when the value of S is selected from Table 2.2-1 or Table 3.3-3 of Appendix A of WCAP-12745. However, the option of performing a measurement for determining the magnitude and direction of the transmitter drift through the utilization of "as found/as left" data is available as noted in the Technical Specifications (ie. S can be a measured value.) . If the current drift status of the transmitter is not investigated, the values for S and Z for certain functions would result in Equation 2.2-1 not being satisfied for any non-conservative rack drift. In this event, the protection channel would be determined to be inoperable and the corresponding action requirements must be satisfied.
The satisfaction of Equation 2.2-1 is not required unless the Allowable Value is exceeded. This is considered acceptable based on the assumption that the transmitter and racks are exhibiting normal, random behavior. This is considered a valid assumption until a history is generated for a device (transmitter or process rack loop) which notes otherwise.
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