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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:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML17348A2431990-04-0505 April 1990 Submits Results of Comparisons of Heat Rate Measurements in Reg Guide 3.54 W/Measurements Predicted by ORIGEN-S/SAS2. Cover Pages from Technical Repts Encl ML20138G8311985-10-11011 October 1985 Informs That Bnwl Employee DB Jarrell Will Assist in Support of NRC Maint & Surveillance Program,Phase I ML20136G1941985-06-25025 June 1985 Submits List of Battelle Participants Supporting NRC Maint & Surveillance Program,Phase I ML20069P2701982-10-19019 October 1982 Discusses Summary of ACRS Reactor Operations Subcommittee 820929 Meeting Re Turkey Point Cold Overpressure Incident. Tech Specs Do Not Properly Address Situations in Which Availability of Certain Sys More Vital to Safe Operation ML17341A2051981-06-0808 June 1981 Forwards Containment Leakage Rate Testing, Technical Evaluation Rept ML17340A6411980-12-12012 December 1980 Submits Info in Response to 801126 & 1202 Telcons Re Potential Drop of Steam Generator & Subsequent Release of Radioactive Matl.Release of Radioactivity Would Be Less than 10%.Forwards Article on Deposits in Primary Sys ML19344A8161980-03-27027 March 1980 Forwards Requests for Addl Info to Complete Evaluation of Reactor Bldg Crane to NUREG-0554 Requirements ML17339A5011980-01-22022 January 1980 Forwards Final Inputs for 6-month Period Re Util Fire Protection Review.Recommends Acceptance of Plans for Fire Detection Sys & Proposal for Screen Wash Pump as Backup. Mod Necessary on Water Suppression Sys ML17338A3441978-12-0606 December 1978 Discusses Fire Protection in Operating Nuclear Power Stations,In Particular Providing Analysis of Facilities' Ser.Proposed Fire Protection Mod Increases Level of Protection Against Fire Hazards ML17338A3461978-09-21021 September 1978 Requests Addl Info Re Fire Protec at Subj Facils.Info Concerns Water Supply,Cable Protec,Yard Hydrants,Smoke Venting Equip & Smoke Removal.Documentation Re Info Sought Encl 1990-04-05
[Table view] |
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BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INC.
Upton, New York 11973 Department of Nuclear Energy (516) 345-2144 September 21, 1978 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. R.L. Ferguson Plant Systems Branch
Dear Bob:
~Sub,'ect: Fire Protection in Turke Point Nuclear Power Piant - Units 3 & 4 Re uest for Additional Information At your request, a review has been conducted of Turkey Point Nuclear Power Plant and its respective Draft Safety Evaluation Report, dated August 15, 1978. This analysis examined the relationship of safety-related components, systems and struc-tures with both combustibles and the associated fire detection and suppression systems. Our review has been limited to the aspects of fire protection related to the protection of the public from the standpoint of radiological health and safety.
Me have not considered aspects of fire protection associated with life safety of onsite personnel and with property protection, unless they impact the health and safety of the public due to the release of radioactive material. >le have utilized the fire protection program report as submitted by Florida Power and Light Company for Turkey Point as basis data for this analysis. In addition, Clr. M. Antonetti and Mr. J. Townley, under contract to Brookhaven National Laboratory (BNL), have inspected the plants along with members of your staff.
This letter is being written as a result of a meeting between Mr. M. Antonetti and Mr. I. Asp of Gage-Babcock and Associates, Inc., under contract to BNL, and Mr. E.
MacDougall and myself of BNL. In addition, discussions were held with Mr. J. Townley, consultant to BNL, regarding the manual fire protection analysis of the two plants. eyal-In general, we conclude that there remains four areas within the Turkey Point uation that require further analysis. Me at this time recorrmend that these areas, as discussed in attachment 1 to this letter, be held as open items that require additional information and analysis. Upon receipt of the information and completion of the evaluation, the BNL letter report for Turkey Point Nuclear Power Plant will be issued.
Respectfully yours, obert E. Hall, Group Leader sd Reactor Safety Analysis Attachment lK tz lac [z~
cc: I. Asp M. Antonetti R. Cerbone D. Eisenhut W. Kato E. MacDougall V. Stello J. Tel ford
ATTACHMENT I
- 1. Mater Su 1 - SER Section 4.3. l. 1 The as proposed fire protection water supply consists of two horizontal shaft centrifugal fire pumps, each rated at 2000gpm at 140psig. They take suction from one 500,000 gallon re'ater storage tank with a 700gpm make-up capability.
At this time no physical dedication is maintained for fire protection requirements, instead the licensee proposed to administratively set aside 150,000 gal. In add-ition, a 100,000 gallon elevated storage tank, 175 ft. high, floats on the fire protection system as well as others, Again administrative controls are proposed to maintain 30,000 gallons for use during a fire. It should be noted that the licensee has stated that the administrative controls on the total fire water supply of 180,000 gallons will require a water conservation program to be insti-tuted by the two plants.
As a system back up the licensee now proposes to make available a spool piece that will tie the discharge header of the three salt water screen wash. pumps, 1600gpm at 86psig each, into the fire protection water supply.
After careful analysis of existing data we conclude that the water supply system, as proposed, is marginal and thereby may not meet all probable demands of the two nuclear units.
Appendix A to the Branch Technical Position, dated August 23, 1976, page 25 re-quires for operating plants:
- 2. (c) If pumps are required to meet system pressure or flow requirements, a sufficient number of pumps should be provided so that 1005 capa-city will be available with one pump inactive (e.g., three 505 pumps or two 100'A pumps). The connection to the yard fire main loop from each fire pump should be widely separated, preferably located on opposite sides of the plant. Each pump should have its own driver with independent power supplies and control. At least one pump (if not powered from the emergency diesels) should be driven by non-electrical means, preferably diesel engine. Pumps and drivers should be located in rooms separated from the remaining pumps and equipment by a minimum three-hour fire wall. Alarms in-dicating pump running, driver availability, or failure to start should be provided in the control room.
Details of the fire pump installation should as a minimum conform to NFPA 20, "Standard for the Installation of Centrifugal Fire Pumps."
(d) Two separate reliable water supplies should be provided. If tanks are used, two 100Ã (minimum of 300,000 gallons each) system capacity tanks should be installed. They should be so interconnected that pumps can take suction from either or both. However, a leak in one tank or its piping should not cause both tanks to drain. The main plant fire water supply capacity should be capable of refilling either tank in a minimum of eight hours.
Common tanks are permitted for fire and sanitary or service water storage. When this is done, however, minimum fire water storage requirements should be dedicated by means of a vertical standpipe for other water services.
(e) The fire water supply (total capacity and flow rate) should be calculated on the basis of the largest expected flow rate for a period of two hours, but not less than 300,000 gallons. This flow rate should be based (conservatively) on 1,000 gpm for manual hose streams plus the greater of:
(I) all sprinkler heads opened and flowing in the largest designed fire area; or (2) the largest open head deluge system(s) operating.
(f) Lakes or fresh water ponds of sufficient size may qualify as sole source of water for fire protection,,but require at least two in-takes to the pump supply. When a common water supply is permitted for fire protection and the ultimate heat sink, the following conditions should also be satisfied:
(1) The additional fire protection water requirements are designed into the total storage capacity; and (2} Failure of the fire protection system should not degrade the function of the ultimate heat sink.
The proposed water supply does not meet the redundancy or volume as required by the BTP guidelines.
Upon further evaluation discrepancies were found in the maximum, fixed plus hose streams, water demand calculation supplied to the Laboratory by the licensee, Ref. Table 1. This maximum probable demand for the required two hours (BTP) ranges from 2739gpm to 1488gpm assuming 750gpm for manual hose streams. Assuming a total of 180,000 gallons available for fire fighting,,the time period before the depletion of tank water is from 66 to 121 minutes. It should be noted that the 30,000 gallons from the 175'igh head tank may not be able to inject directly into the yard loop at sufficient pressure to supply the demand. Therefore, we have assumed that this water will be available to the system only through the suction side of the fire protection pumps. Because of the minimal nature of the tank water supply for these two plants, a detailed analysis of'the maximum water demand should be required. In addition, we recommend that physical dedica-tion of the minimum needed water supply be enforced. This can be accomplished by either interior suction risers or new, hot tap, suctions for all non fire pumps above the lower limits. This conclusion is based on the lack of an accurate water level versus time history of the tanks and the uncertainties of administrative controls in the form of visual checks of tank level.
When reviewing the proposed use of the salt water screen wash pumps, as a second-ary water supply, we recomnend that if the pressure and flow rate is adequate
to supply the maximum demand for the fire protection system that they be per-manently installed with technical specifications to control their testing and operation during the interfacing from the tank supply. At this point in time the uncertainties in the water demand, Table 1, raises the question of whether the system will require one, two, or three screen wash pumps or, if in fact, they will be at all adequate. We require additional information in the form of pump operating curves to reach a final conclusion in this area.
We also request that the staff consider three additional concerns regarding the use of salt water in the system.
- 1. Has the licensee considered the effect of salt water on the proposed foam system? All foam supplies do not respond favorably to brackish water.
- 2. Is there a positive means to assure that no salt water back flows into the raw water supply for the plant? If this does occur, what will be the impact on the plants and its personnel?
- 3. Have detailed operational specifications been developed to utilize the 500gpm portable fir e pump effectively with the minimum staffing of the fire brigade of five men? Is this pump tested on line discharging into the yard loop or is the gasoline engine simply test started?
In addition to reviewing Turkey Point 1 8 2 for the adequacy of its water supply, we reviewed the historical requirements of the staff on the following sixteen plants.
Arkansas 2 Haddam Heck Point Beach 182 Brunswick 182 Maine Yankee Rancho Seco Dresden 1,283 Oconee Three Mile Island 1 Duane Arnold Oyster Creek Trojan H.B. Robinson 2 Palisades Vermont Yankee Pilgrim Based on this review, we again conclude that the proposed water supply could represent. a minimal fire protection system and therefore at this time recoranend augmenting the tank/screen wash pump system as described above. Upon receipt of the needed additional documentation this conclusion will be reevaluated.
- 2. Cable Protection -" SER Section 5.8 There presently exists a main access hallway in the auxiliary building in which essential safety cabling, serving both units 3 and 4, are run - Area 58. In-cluded in this area are the following cables:
Charging pump's, 3A, 3B and 3C Component cooling water pump 4C Boric acid transfer pumps 3A, 3B, 4A and 4B Auxiliary feedwater pump steam supply valves {MOV-3-1405, MOV-4-1405)
Boric acid injection stop valves (MOV-3-350, MOV-4-350)
Volume control tank isolation valve (MOV-3--115C, MOV-4-115C)
Auxiliary/Radwaste building exhaust and supply fans 3A, 3B, 3A-V30, 3B-Vll RHR pumps 3A, 3B, 4A and 43 Accumulator stop valves (MOV-3-865C, MOV-4-865A)
Cold leg safety injection valves (NOY-3-843A, MOY-3-8438, NOV-4-843A}
Feedwater isolation valves (NOV-3-1408, MOV-4-1408)
Residual heat exhanger cooling water isolation valves (NOV-3-749A, MOV-3-749B, MOV-4-749A)
Refueling water stop valve (NOV-3-862A)
RHR to RCS isolation valves (MOV-3-744A, NOV-4-744A)
RCS to RHR isolation valves (MOV-3-751, NOV-4-751)
Component cooling water flow 3A, 3B, 4A and 4B Steam generator level 4A and 4B 480 V motor control center feeder breakers 3C, 4C, D and D (alt)
Boric acid storage tank heaters A, B and C Boric acid heat tracing transformers A and B Unit 3 and 4 emergency lighting panels Due to the large volume of safety related cables for the two plants in this area, and the constant exposure of these cables to transient flammable liquid and com-bustible oils we, at this time, recommend a fixed automatic sprinkler system or protection. >le do not recorrmend the licensee proposed solution of administratively controling the transients in the area since there is a necessity of bringing chemicals of this type into the auxiliary building through the area.
it If is desired to reevaluate the presently needed conservatism in this con-conclusion in light of plant alternate shutdown capabilities, we recommend the following:
Postulating a flammable liquid fire in this area, which would most probably affect normal shutdown capabilities of both units, evaluate the procedures, locations of controls and number of individuals that are required to shut the two units down through alternate means. Does this scenario allow the five trained members of the recommended fire brigade to fight the'fire on all shifts of the plants without being reduced in number?
Based on the answer to the above question, refinements can be made on our present recommendation of a fixed sprinkler system to mitigate a transient exposure fire, if necessary. It should be noted that due to the types of transients being con-sidered detection systems, electrical or fire watch, could prove too slow in responding to prevent major cable exposure.-
- 3. Yard H drants - SER Section 3. 1.3 chargee There should be a 2-1/2" gate valve provided for each hydrant 2-1/2" outlet as recommended in staff position P.F.-23 submitted to F.P.L. under the date of July 14, 1978. The utility has stated that only one of the two outlets on each hydrant will be fitted with throttling gate valves. This will require both hose lines to be throttled by the hydrant in the event that the ungated portion must be throttled. Based on experience, concern exists that, due to the unusually high fire main pressure, the throttling of the hydrant valve could cause a dis-out of the drain valve which in turn could undermine the hydrant. The utilities contention that this blow down will not occur past one turn of the hydrant should be documented so that an evaluation of the data can be made.
The lack of the second gate valve introduces a second concern. In the event of a need to add hoses or replace damaged hoses to the line fed by .the ungated section, both lines could have to be turned off. The licensees suggestion of utilizing a hose clamp to circumvent this scenario should be reviewed closely by the staff. Hose clamps are designed for emergency shutoff and as such do not assure a positive method to control water flow on a routine basis. Additionally there is no assurance that the clamps wi')1 be available at the required location when needed.
- 4. Smoke Ventin E ui ment - SER Section 3. 1.17 Smoke venting equipment should be provided as recommended in staff position P.F.-24 submitted to F.P.L., Duly 14, 197S. F.P.L.'s response that they can see no mea-surable benefit by providing a third smoke ejector is in error. Two (2) 5,000 CFM or greater smoke ejectors will not be adequate to remove smoke and heat from areas of the plant, for example: 4160V SWITCHGEAR ROOMS, ELECTRICAL PENETRATION ROOMS, AUXILIARY BUILDING CORRIDOR and adjacent FIRE AREAS 21 and 22. It is recommended to the NRC staff that they require a minimum of three approved portable smoke ejectors for these two plants. The third ejector'allows the total system the added versatili.ty to remove isolated pockets of dense smoke by the direction of circulating air currents from three independent sources. In addition, the three unit concept can, if required, control the by product exhaust location by having one ejector discharging into the suction of a second and thereby removed to remote locations. Concurrently, the third unit feeds fresh air into the involved area.
The three unit system also affords more portability than two ejectors since each unit can be lighter and smaller in volume and still meet the required air move-ment needs of the fire brigade. If in a two ejector system one unit malfunctions, smoke ventilation can be defeated. This is not the case with three ejectors since at least minimal air movement can be maintained by the two units that remain. This generic concept, utilized by professional fire fighting organizations, has pre-viously been expressed to the NRC in other plant reviews and in a letter to R. Ferguson from R. Hall dated November 14, 1977.
Smoke Removal The optimum means of smoke removal is a properly designed fixed ventilation system. This would be a fixed system with smoke removal as one of its prime design parameters. 'ield experience has shown that it is not always obtain-able without extensive plant modification, and therefore portable smoke ejectors are recommended.
A minimum of three portable smoke ejectors with at least 17,500 CFM capacity...
An examination of specific locations at Turkey Point showed that there were areas where the BNL consultant determined that three fans were required due to the large size of these areas. An example of this is the 4160 volt switchgear rooms which contain approximately 14,000cu. feet each, and the long hall in the auxiliary building which contains approximately 21,000cu. feet. These areas and other large areas may require one fan blowing fresh air in and two fans exausting smoke.
A typical large room pre-fire plan is attached showing the recommended fan arrangement, Rer. Figure l.
TABLE 1 9/18/78 TURKEY POINT FIRE PROTECTION HATER DEMANDS Supply Time Highhead Tank Required of 180,000 gal Head Loss Screen Hash pump Fixed System Hose Stream Pump Discharge Dedication of at Five Protection Discharge Capabilities Hater Demand Watev Demand Total Pressure Water into Fire Protection GPM GPM GPM si min Headers'i 100ft** ard loo ***
1989 Taken from Fire Hazards Screen Hash pumps Analysis Report 100 may not handle by F.P.L. 750 2739 estimated by BNL 66 29 water demand 738 Submitted to BNL at Licensee, 92 NRC meeting 750 1488 supplied 'by Lic. 121 Two pumps required 874 Discussed with BNL on Telecon with 62 icensee E NRC 750 1624 supplied by Lic. One pump required cJuly 14 letter) 1190 Calculated by BNL based on Licensee sub- 100 mitted data.* 750 1940 estimated by BNL 93 15 Three pumps required
- Calculation based on maximum fixed demand of 3,597 ft. at .3 density plus a 10K calculation factor.
"*Calculation based on "C" factor of 110 and 76psig discharge pressure of high head tank (175ft}.
FIA quick Reference flow tables were utilized assuming no orifice ov elbows.
- The conclusions drawn regarding the capability of the screen wash pumps to maintain fire protection system pressure is based on three pumps at 1600GPM and 86psig each, ref. FSAR, It should be noted that these conclusions are judgmental in basis since the exact pump operational curves were not available to the Laboratory and the details of installation of fire protection connection was not submitted.
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