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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) ML17354B2061998-12-0909 December 1998 Informs That Request for Exemption Specified in Section II.B.3 Will Not Be Needed Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg ML17354B1981998-11-25025 November 1998 Forwards Scope & Objective for 1999 Plant Annual Emergency Preparedness Exercise.Objectives Developed in Conjunction with State & Local Govts.Exercise Scheduled for 990210 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17348A5661990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. ML17348A5461990-09-0707 September 1990 Forwards 1990 Inservice Insp Refueling Outage Summary Rept of NDE Activities 900206-0404 First Refueling Outage Second Period Second Insp Interval. ML17348A5501990-09-0707 September 1990 Forwards Jul 1990 Integrated Schedule Regulatory Rept for Facilities ML17348A5521990-09-0606 September 1990 Forwards Matrix of Changes to Emergency Power Sys That Affect Revised Tech Specs Issued on 900828.Matrix Sent for Info & to Assist in NRC Review of No Significant Hazards Rept for Revised Tech Specs ML17348A5431990-08-31031 August 1990 Forwards Objectives for 901108 Emergency Plan Exercise. Exercise Will Involve Participation by Local Emergency Response Agencies & State Emergency Response Personnel & Will Not Be Evaluated by FEMA ML17348A5361990-08-27027 August 1990 Forwards Turkey Point Units 3 & 4 Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17348A5171990-08-24024 August 1990 Forwards Ref Matl in Preparation for Operator License Exams Scheduled for Wk of 901029,per NRC 900628 Request ML17348A5041990-08-17017 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 ML17348A5051990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Turkey Point Units 3 & 4 & Revise Rept for June 1990 for Unit 3 ML20059B0111990-08-14014 August 1990 Requests That Encl Intervenor Motion for Extension of Time to Appeal to Docketing & Svcs Branch Re Tech Spec Replacement Hearing Be Provided.Motion Inadvertently Omitted in Svc of Request on 900813 ML17348A4971990-08-10010 August 1990 Responds to Violations Noted in Insp Repts 50-250/90-18 & 50-251/90-18.Corrective Actions:Unit Stabilized in Mode 3, Operating Surveillance Procedures 3/4-OSP-089 Revised & Event Response Team Formed ML17348A4701990-07-27027 July 1990 Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing L-90-282, Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790)1990-07-25025 July 1990 Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790) ML17348A4281990-07-25025 July 1990 Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b) ML17348A4691990-07-23023 July 1990 Forwards Addl Info on Emergency Power Sys Enhancement Project Re Load Sequencer,Programmable Logic Controllers & Implementation of Sys in Plant,Per NRC 900705 Request ML17348A4191990-07-20020 July 1990 Advises That Comments on NRC Safety Evaluation Re Implementation of Station Blackout Rule Will Be Provided by 900921 ML17348A4201990-07-20020 July 1990 Forwards Revised No Significant Hazards Determination for Proposed Tech Specs 1.17 & 3.0.5 & Bases,Per 890605 Ltr ML17348A4141990-07-20020 July 1990 Responds to Violations Noted in Insp Repts 50-250/90-14 & 50-251/90-14.Corrective Actions:Breakers Closed,Returning Monitoring Sys to Operable Level & Briefings Held to Explain Rvlms Sys Theory to Operations Control Room Personnel ML17348A4171990-07-19019 July 1990 Forwards May 1990 Integrated Schedule Regulatory Rept for Plant ML17348A4121990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML17348A4251990-07-17017 July 1990 Withdraws 900207 & 0424 Proposed Changes to Tech Specs Re Util Nuclear Review Board Composition IR 05000250/19900131990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML20055G8641990-07-16016 July 1990 Informs ASLB That Petitioners Ref to Several Telephone Contacts Between J Butler & M Gutman,Of ATI Career Training Inst Is Inadvertent Misstatement & Should Be Changed to Telephone Contact. W/Certificate of Svc ML17348A4161990-07-16016 July 1990 Responds to Commitment Re Reverse Testing of Containment Isolation Valves Per Insp Repts 50-250/90-13 & 50-251/90-13. Corrective Action Plan Addresses Penetrations 16 & 53 for Unit 3 Only & Penetrations 11,47,54A & 54B for Both Units ML17348A4151990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML17348A4041990-07-12012 July 1990 Forwards Addl Info Re Responses to NRC Questions on Piping Codes Used for Emergency Power Sys Enhancement Project ML17348A3921990-07-12012 July 1990 Summarizes Facility Performance Since Last SALP Evaluation Period Which Ended 890731.Util Pursued Aggressive self- Assessment Program,Including Significant Internal or Outside Assessments in Areas of Operator Performance & EOPs L-90-261, Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld1990-07-11011 July 1990 Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld L-90-259, Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3))1990-07-11011 July 1990 Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3)) ML17348A4321990-07-11011 July 1990 Forwards Rev 8 to Updated FSAR for Turkey Point Units 3 & 4. Rev Includes Activities Completed Between 890123 & 900122. Rept of Changes for Jul 1989 Through June 1990 Will Be Provided by 900901 ML17348A3941990-07-0909 July 1990 Forwards Requested Addl Info Re Emergency Power Sys Enhancement Project.Specific Detailed Changes Will Be Made to Procedures to Address Mods Affecting Equipment Relied Upon for Safe Shutdown ML17348A3881990-07-0505 July 1990 Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs ML17348A4311990-07-0505 July 1990 Documents Written & Verbal Request of Region II Personnel for Temporary Waiver of Compliance of Tech Spec 3.4.2.b.1 Re Allowable Out of Svc Time for One Emergency Containment Cooler from 24 H to 72 Hr W/Addl Reasons ML17348A3851990-07-0303 July 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-250/90-08 & 50-251/90-08.Corrective Actions:Training Dept Increased Emphasis on Radiological Postings in Radiation Worker Training ML17348A3711990-07-0303 July 1990 Responds to NRC 900524 Request for Addl Info on Emergency Power Sys Enhancement Project ML17348A3671990-07-0303 July 1990 Confirms Util Intentions Not to Operate Beyond Refueling Outage That Represents Last Outage Re NRC Bulletin 89-001 ML17348A3841990-06-29029 June 1990 Forwards LER 90-11 on 900609 Re hi-hi Steam Generator Water Level Turbine Trip & Subsequent Reactor Trip Due to Failure of Switch in Feedwater Valve Controller Hand/Auto Station. W/O Encl ML17348A3601990-06-29029 June 1990 Responds to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Test Procedures Developed & Under Mgt Review Reflecting Revised Inservice Testing Program ML17348A3621990-06-28028 June 1990 Notifies That Senior Operator License SOP-20177-2 Will Be Terminated,Effective 900731 ML17348A3651990-06-28028 June 1990 Advises That Completion of safety-related motor-operated Valve Testing & Surveillance Will Be Completed by June 1990, Per Generic Ltr 89-10 Requirements ML17348A3591990-06-27027 June 1990 Responds to Violations Noted in Insp Repts 50-250/90-09 & 50-251/90-09.Corrective Actions:Specialist Counselled on Importance of Stopping Procedure When Steps Conflict W/ Condition of Plant & Procedure Use Guidelines Reviewed ML17348A3641990-06-27027 June 1990 Responds to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions. ML17348A3861990-06-27027 June 1990 Advises That New Date for Submittal of Response to Insp Repts 50-250/90-09 & 50-251/90-09 Is 900702 ML17348A3551990-06-21021 June 1990 Responds to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers. Five Untraceable Circuit Breakers Installed in Unit 3 safety-related Sys.All Five Breakers Replaced W/Traceable Breakers ML20055D9201990-06-20020 June 1990 Advises That Sp Frantz Will Represent Licensee in Argument Scheduled for 900710.Certificate of Svc Encl ML17348A3181990-06-19019 June 1990 Forwards Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects for Turkey Point Nuclear Power Plant, Per NRC Bulletin 88-008 ML17348A2981990-06-12012 June 1990 Forwards Rev 16 to Topical QA Rept. ML17348A2871990-06-0808 June 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Model S350W Swing Check Valves or Valves of Similar Design. Bolt Replacement Performed ML17348A2861990-06-0808 June 1990 Advises That Info Re Operating History of Select Fuel Assemblies Sent to ORNL Between 900419 & 26,per 900510 Request ML17348A2781990-06-0404 June 1990 Forwards Emergency Power Sys Enhancement Project Repts, Reflecting Current Design Info 1990-09-07
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'49yC5 > I'ted@ llY Nay 22, 1981 L-81-220 Mr. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Ga. 30303
Dear Mr. O'Reilly:
Re: RII:
50-250/81-07
.50-251/81-07 Florida Power 6 Light Company has reviewed the subject inspection report and a response is attached.
There is no propietary information in the report.
Very truly yours, Robert E. Uhrig
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Vice President Advanced System and Technology REU/JEM/ras Attachment cc: Harold F. Reis, Esquire
I 0 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250, 50-251 P"
FINDING A Technical Specification 6.8.1 requires written procedures and administrative policies be established, implemented, and maintained that meet the requirements and recommendations of Section 5.1 and 5.3 of ANSI 18.7 1972 and Appendix "A" of Regulatory Guide 1.33. Operating Procedure 5120, Waste Disposal System Laundry and Hot Shower System Normal Operation, did not specify waste water transfer to CVCS Monitor Tank A.
Contrary to the above, on March 10, 1981, Operating Procedure 5120 was not followed in that laundry waste water was inadvertently transferred to CVCS Monitor Tank A which subsequently overflowed.
RESPONSE A (A-1) FPL concurs with this finding.'A-2)
The reason for the finding is that Operating Procedure 5120 inadvertently neglected this operating evolution.
(A-3) As corrective action, Operating Procedure 5120 was revised to include provisions for the transfer of fluid to the CVCS Monitor Tank A from the laundry tank. These revisions were implemented on March 24, 1981.
(A-4) As corrective action to avoid further problems, Operating Procedure 5120, will be followed for transfers of liquid from the laundry tank to other tanks.
(A-5) Full compliance was achieved on March 24, 1981.
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 APR 3 0198)
Florida Power and Light Company ATTN: R. E. Uhrig, Vice President Advanced Systems and Technology P. O. Box 529100 Miami, FL 33152.
Gentlemen:
Subject:
Report Nos. 50-250/81-07 and 50-251/81-07 This refers to the routine inspection conducted by A. J. Ignatonis of this office on February 26 March 25, 1981, of activities authorized by NRC Operating License Nos. DPR-31 and DPR"41 for the Turkey Point facility. Our preliminary findings were discussed with J. K. Hays at the conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspectors. ~
During the inspection, it was found that certain activities under your license appear to violate NRC requirements. ~ This item and references to pertinent requirements are listed in the Notice of Violation enclosed herewith as Appendix A. Elements to be included in your response are delineated in Appendix A.
We have examined actions you have taken with .regard to previously identified enforcement matters. These are discussed in the enclosed inspection report.
In accordance with Section 2.790 of the NRC "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will. be placed in the NRC Public Document Room. If this report contains any information that you believe to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public disclosure. Any such application must include the basis for claiming that the information is proprietary and the proprietary information should be contained in a separate part of the document. If we do not hear from you in this regard within the specified period,'he report will be placed in the Public Document Room.
APR 8 Olgg~
Florida Power and Light Company Should you have any questions concerning this letter, we will be gl.ad to discuss them with you.
Sincerely,
.C
- C. , ctsng Oirector Oivision of Resident and Reactor Project Inspection
Enclosures:
- l. Appendix A, Notice of Violation
- 2. Inspection Report Nos. 50-250/81-07 and 50-251/81-07 cc w/encl:
H. E; Yaeger, Plant Manager
APPENOIX A NOTICE OF VIOLATION Fl ori da Power and Light Oocket Nos. 50-250 & 50-251 Turkey Point 3 and 4 License Nos. OPR-31 & OPR-41 As a result of the inspection conducted on February 26 March 25, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980),
the following violation was identified.
Technical Specification 6.8. 1 requires written. procedures and administrative policies be established, implemented, and maintained that meet the require-ments and recommendations of Section 5. 1 and 5.3 of ANSI 18.7-1972 and Appendix "A" of Regulatory Guide 1.33, Operating Procedure 5120, Waste Disposal System Laundry and Hot Shower System - Normal Operation did not specify waste water tranfer to CVCS Monitor Tank A.
/
Contrary to the above, on March 10, 1981 operating procedure 5120 was not followed in that laundry waste water was inadvertently transferred to CVCS Monitor Tank A which subsequently overflowed.
This is a Severity Level V Violation (Supplement I.E.).
Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit.to this office within twenty-five days of the date of this Notice, a written state-ment or explanation in reply, including: (1) admission or denial of the alleged violation; (2) the reasons for the violation if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
APR 3 0198)
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~4 0 UNITED STATES ep e Cl NUCLEAR REGULATORY COMMISSION v
REGION II 101 MARIETTAST., N.W., SUITE 3100 V/ ATLANTA,GEORGIA 30303
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Docket Nos. 50-250/81-07 and 50-251/81-07 Licensee: Florida Power and Light Company 9250 West Flagler Street.
FL 33101 'iami, Facility Name: Turkey Point Docket Nos. 50-250 and 50-251 ton'ate License Nos. DPR-31 and OPR-41 Inspection at Turkey Point site near Homestead, Florida Inspectors:
A. J. Ig Signed W. C. Marsh Date Signed Approved by: C H. Dance, ection Chief, RRPI Branch 0 te Signed
SUMMARY
Inspection on February 26, - March 25, 1981 Areas Inspected This routine inspection. involved 223 resident inspector-hours on site in the areas of (1) followup of previous inspection findings; (2) followup on licensee event reports; (3) surveillance test observations; (4) followup on implementation of post-TMI requirements; (5) containment instrument relocation per IEB 79-01B; (6) plant operations; and (7) plant tours.
Results Of the seven areas inspected, no violations or deviations were identified in six areas; one apparent violation was found in .,one area (Yiolation-failure to follow the Waste Disposal-System Laundry and Hot Shower Drain System procedure - para-graph 9.).
J' DETAILS
- 1. Persons Contacted Licensee Employees
- H. E. Yaeger, Site Manager "J. K. Hays, Plant Manager Nuclear-J. E. Moore, Operations Superintendent Nuclear D. W. Haase, Technical Department Supervisor J. P. Mendieta, Maintenance Superintendent W.. R. Williams, Assistant Superintendent Electrical Maintenance D. C. Bradford, Outage Management Plant Supervisor W. A. Klein, Licensing Engineer "D. W. Jones, QC Supervisor C. J. Baker, Construction Coordinator B. A. Abrishami, Systems Test Engineer Other licensee employees contacted included construction craftsmen, technicians, operators, security force members and office personnel.
0, Attended exit. interview Exit Interview The inspection scope and findings were summarized on March 27, 1981 with those persons indicated in Paragraph 1 above. The site and plant managers acknowledged the stated violation.
- 3. Licensee Action on Previous Inspection Findings (Cl osed) Fai 1 ure to Fo1 1 ow Emergency Di ese1 Gener ator Normal Standby Condition Operating Procedure 4303. 1 (50-250, 251/80-05-03). The inspector verified both diesel air start systems properly aligned in accordance with OP 4303. 1 and a. revised 'diagram in agreement with the procedure posted in both generator rooms. The inspector had no further questions.
- 4. Unresolved Items Unresolved items were not identified during this inspection.
- 5. Licensee Event Report ( LER) Fo 1 1 owup During this inspection the following Licensee Event Reports were reviewed to
.assure the accurary and completeness of the report, that regulatory requirements had been met, and that appropriate corrective actions were being taken. The LER's listed below were reviewed with comments as appro-priate.
2 250/80-29 "3A" Boric Acid Transfer Pump Leak Repair The "3A" Boric Acid Transfer (BAT) pump was removed from service due to a water leak. It was repaired and then returned to service; Outages for the same type of. pump on Unit 4 have been previously recorded. These pumps are the Series G chem pumps manufactured by Crane,, and are of a canned pump and motor design. Due to previous history of motor problems and the unavai 1" ability of replacement motors, the licensee will replace all of the BAT pumps with Goulds pumps scheduled for installation during the summer of 1981. The Goulds pump casing wi 11 be separated from the motor.
250/81-02 Boric Acid Flowpath Blockage In review of this event, the- inspector noted that another similar event occurred on Unit. 4 subsequent to this report. In both cases the apparent cause of obstruction in the, lines resulted from failed and faulty heat tracing circuits. The licensee restored the flow by repairing the heat.
tracing circuit. These heat tracing circuits are of the Chromalox design, however, fn the long-term the .licensee has committed to replace all of the circuits with the Chemelex type which are more easily maintained and appear to be more reliable. Since an LER on Unit 4 boric acid flowpath blockage is forthcoming, LER 250-81-02 will remain open. The inspector expects to e, complete this evaluation in the subsequent inspection report.
Surveillance veillancee Test Observations On March 18, 1981 the inspector witnessed testing of the 3A Intake Cooling Water System. Pump following maintenance and portions of the monthly sur-test on the. Unit 4 pumps. The tests were performed in accordance with Operating Procedure 3404.2, Intake Cooling Water System - Periodic Test of Pumps. The following ins'pection items were verified: Testing is scheduled in accordance with technical specification requirements, procedures were being followed, testing was by qualified personnel, LCOs, were being'et, and system restoration was correctly accomplished following testing.
No violations or deviations were identified for the areas inspected above.
- 7. Followup on Implementation of Post-TMI'equirements
'I (Open). Item II.F. 1, Accident Monitoring In the monthly inspection report of October, 1980 (50-250/80-33; 50-251/80-32) pertaining to the inspector followup on the implementation of post-TMI Lessons Learned Category "A" requirements, it wag stated that the wide range noble gas monitors and the high range containment radiation
monitors were scheduled to be installed in Unit 3 and 4 containments during the March-April, 1981 outage and the November, 1980 - January, 1981 outage, respectively. The status of these requirements is as follows:
For. Unit 3 containment the installation of the radiation monitors will be completed dut ing thi s current March-April, 1981 outage. One detector has been installed at the 58 foot level, on the steam generator 3A shield wall.'nstallation of the other detector is in progress which will be located on the 14 foot level next to the personnel access penetration. The associated recorders and meters that wi 11 be located in the main control room will be installed at a later date.. Due to late delivery of the high range radiation monitors the installation of these detectors for Unit 4 containment will slip to the July, 1981 outage..
The wide range noble gas monitors have not been installed for either unit. One noble gas monitor unit has been recently delivered to the site. This unit has been designated to monito~ the Unit 3 spent fuel pool vent stack. The others are planned to monitor effluents released from the air ejectors, the stack vent which is common to both unit containments, and main steam. The licensee is awaiting delivery for the remaining wide range noble gas monitor units. The inspector verified the installation and receipt of the hardware described above, and will continue to carry this as a followup item.
(Closed) Item II'.F.2..la., Instrumentation for Core Cooling Also, during the current Unit 3 outage the licensee installed redundant resistance temperature detectors (RTD's) on each of the primary loop hot legs. The output of these RTD's will be fed to the sub-cooled margin meter. Originally, the sub-cooled margin monitor sensed signals from RTD's having an arrangement of one RTD located in each hot leg loop., and one RTD in each cold leg loop. This was found to be unacceptable by NRR, and as a'esult the configuration was modified to have two RTD's in each hot leg loop and one RTD in each cold leg loop.
The. sub-cooled margin meter will provide readings from the highest hot leg RTD output. The redundant hot leg RTDs and their associated wiring have already been installed for unit 4 during the November 1980 January, 1981 outage.
- 8. Instrument Relocation in Containment per IE Bulletin 79-01B 1n order to prevent certain safety-related electrical components from becoming submerged after a postulated event inside the containment, the licensee originally proposed to relocated and/or replace 12 components in the Unit 3 containment. These items were addressed in the component evalu-
ation section c.1 of the licensee's response to IE Bulletin 79-01B, They are as follows:
(1) PT-3-403 Reactor coolant system (RCS) Narrow Range Pressure Transmitter (2) PT-3-404 RCS Pressure Transmitter (3) PT-3-405 RCS Pressure Transmitter (4) PT-3-406 RCS Pressure Transmitter (5) FT-3-932 Safety Injection Flow Transmitter (6) F1=3-933 Safety Injection Flow Transmitter (7) TB 3143 Terminal Box containing wiring associated with solenoid valve for CV-3-310A, Charging Pump discharge line (8) TB 3371.Terminal Box associated with Pressurizer Level Transmitter (9) TB 3379 Terminal Box associated with Steam Generator "C" Narrow Range Level Transmitter (10) LS-3-1570 North Containment Sump Level Switch (11) LS-3-1517 South Containment Sump Level Switch (12) SV-3-310B Solenoid Valve for CV-3-310B, Charging Line Loop "C" On March 19, 1981 the inspector performed a walkdown in the Unit 3 contain-ment and verified the relocation of eight instruments listed above. These were items (1) through (7) and item (12) of. above. Per discussions with the licensee, PT-3-403 was not replaced as committed by the licensee. The reason is that a qualified replacement part,was not available at this time; once obtained, it will be installed.
Items (8), (9), (10), and (11) of the above list were not relocated nor replaced. The list of instruments subject to potential submergence were based on Unit 4 walkdown. A similar walkdown of Unit 3 showed that items (8) and (9) do not have to be relocated since they were already above maximum flood level. Items (10) and (11) containment level switches are not planned to be relocated because they will be able to be compensated by future installation of'wide range containment water level monitors required by the post-TMI lessons learned task implementation.
- 9. Plant Operations The inspector kept informed on a daily basis of the overall plant status and any significant safety matters related to plant operations. Oiscussions were
'held with plant management and various members of the operations staff on a regular basis. Selected portions of daily operating logs and operating data sheets were reviewed on at least a weekly basis during the report period.
The inspector conducted various plant tours and made frequent visits to the control room; Observations included witnessing work activities in progress, status of operating and standby safety systems, confirming valve positions, instrument readings and recordings, annunicator alarms, housekeeping, radiation area controls, and vital area controls.
Informal discussions were held with operators and other personnel on work activities in progress and status of safety-related equipment or systems.
The inspector observed Unit 3 fuel handling operations and verified that containment integrity was maintained as required by the Technical Specifi-cations. No violations were identified within the areas inspected.
Ouring this reporting period the inspector'ollowup on two occurrences described below.
On March 10, 1981 at approximately, 11:20 a.m. the contents of the laundry tanks being transfered to the Chemical Volume Control System (CVCS) tank caused the tankto overflow. The over flow rate was such that 'A'onitor the gravity drain system which transfers the overflow from the CVCS Monitor tanks to the Waste Hold-up Tank backed up and out of the floor drains in the Safety Injection Pump Room and the Unit 3 Component Cooling Pump and Heat Exchanger area. The overflow in the Safety Injection Pump Room was contained by the room structure. The overflow in the Component Cooling Pump and Heat Exchanger. area which is outside the Auxiliary Building was collected by the storm drains also located in the area. The activity of the water spilled into the storm drains (which empty into the intake canal) was three to nine times less than the level authorized for release by Technical Specifications. The inspector reviewed the administrative procedure for controlling the evaluation. It was determined that the procedure had not been correctly followed in that it precludes transfer of laundry tank content to CVCS monitor Tank A. This failure to follow procedure number 5120 "Waste Oisposal System - Laundry and Hot Shower Grain System - Normal Operation" constitutes a violation of technical specification 6.8 (50-250, 251/81-07"01).
On March 22, 1981, at approximately 11:30 a.m. Unit 4 tripped from 100K power on "A" steam generator low level coincident with feed flow steam flows mismatch.
The trip occurred when "A" Main Feed Regulating Valve failed shut when a protective system solenoid coil failed open, effectively pi oducing a feed-water isolation signal for "A" Main Feed Regulatory Valve. All safety systems operated .normally. The defective solenoid coil was replaced; however, the unit's return to power was delayed beyond the end of this report period due to a nonrelated problem with 4A Reactor Coolant Pump motor.
Plant Tours The inspector surveyed the Radiation Controlled Area excluding the interior of Units 3 and 4 containments and the spent fuel pool with the digital zetex exposure rate meter. No violations or deviations were identified within the areas inspected.