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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F9941999-10-15015 October 1999 Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review ML20217J5171999-10-13013 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed 3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999 Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed 3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999 Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made ML20212L0771999-10-0404 October 1999 Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii) ML20217D6551999-10-0101 October 1999 Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025 ML20212J8481999-10-0101 October 1999 Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II 3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999 Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment 3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999 Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331 ML20212F7251999-09-23023 September 1999 Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable ML20212F7331999-09-23023 September 1999 Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition 3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999 Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 ML20212E6741999-09-21021 September 1999 Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals 3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999 Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv) 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999 Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief ML20212F3141999-09-13013 September 1999 Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations ML20211L9081999-09-0303 September 1999 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3 ML20211Q7581999-09-0101 September 1999 Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl 3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999 Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals ML20211G7111999-08-30030 August 1999 Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed ML20211G7031999-08-30030 August 1999 Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval 3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999 Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002 ML20212C1351999-08-27027 August 1999 Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input 3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999 Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71 3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999 Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999 Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999 Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal 3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999 Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2 3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value 05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999 Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented ML20210Q4511999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 ML20210P0741999-08-0505 August 1999 Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3 3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999 Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603 ML20210G8551999-07-27027 July 1999 Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation 3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999 Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments ML20209H5211999-07-16016 July 1999 Forwards Request for Addl Info Re Licensee Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in CR-3 once-through Steam Generators in Order to Complete Review ML20209G3231999-07-15015 July 1999 Forwards Biological Opinion Issued by Natl Marine Fisheries (NMFS) of Dept of Commerce.Nmfs Concluded That Operation of Cw Intake Sys of Crystal River Not Likely to Jeopardize Existence of Species Listed in Biological Opinion ML20209G3481999-07-15015 July 1999 Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon 3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999 Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl 3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999 Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl 3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999 Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl 3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999 Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held 3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21 ML20196L1261999-07-0707 July 1999 Discusses Closeout of TAC MA0538 Re License Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Unit 3 3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999 Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3 ML20196J4991999-07-0101 July 1999 Advises That Info Contained in ,Which Included TR BAW-2346P,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20209C0811999-06-25025 June 1999 Forwards Overdue Controlled Document Transmittals for Listed Documents 3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999 Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl 1999-09-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999 Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed 3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999 Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made 3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999 Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment 3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999 Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331 3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999 Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999 Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv) 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999 Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief 3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999 Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals ML20212C1351999-08-27027 August 1999 Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input 3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999 Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002 3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999 Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71 3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999 Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3 3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999 Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999 Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999 Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2 05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999 Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented 3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value 3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999 Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603 3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999 Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments ML20209G3481999-07-15015 July 1999 Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon 3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999 Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl 3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999 Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl 3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999 Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl 3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999 Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held 3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999 Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3 ML20209C0811999-06-25025 June 1999 Forwards Overdue Controlled Document Transmittals for Listed Documents 3F0699-12, Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested1999-06-23023 June 1999 Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested 3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999 Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl 3F0699-08, Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments1999-06-21021 June 1999 Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments 3F0699-09, Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl1999-06-0404 June 1999 Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl 3F0599-21, Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads1999-05-28028 May 1999 Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads 3F0599-10, Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl1999-05-26026 May 1999 Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl ML20207E4341999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft 3F0599-22, Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs1999-05-21021 May 1999 Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-18, Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM1999-05-14014 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM 3F0599-17, Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments1999-05-14014 May 1999 Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments 3F0599-07, Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 19781999-05-14014 May 1999 Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 1978 3F0599-03, Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR1999-05-12012 May 1999 Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR 3F0599-05, Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl1999-05-12012 May 1999 Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl 3F0599-08, Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments1999-05-0303 May 1999 Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments 3F0599-09, Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 19981999-05-0101 May 1999 Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 1998 3F0499-24, Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent1999-04-30030 April 1999 Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent 3F0499-09, Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 9907301999-04-30030 April 1999 Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 990730 3F0499-23, Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements1999-04-23023 April 1999 Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements 3F0499-18, Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl1999-04-20020 April 1999 Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl 3F0499-05, Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin1999-04-16016 April 1999 Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin 3F0499-08, Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 19981999-04-16016 April 1999 Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 1998 1999-09-27
[Table view] |
Text
'
Florida Power CORPORATION w
June 7, 1993 3F0693-04 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Subject:
10 CFR 50, Appendix R Exemption Request Reactor Coolant Pump Oil Collection System
Dear Sir:
Florida Power Corporation (FPC) has developed a maintenance program for the four Reactor Coolant Pump (RCP) motors at Crystal River Unit 3 (CR-3). A new RCP
- mutor has been purchased from the original manufacturer, General Electric, with design improvements that will enhance motor reliability and simplify maintenance activities on both the motors and the associated lube oil collection systems.
The new motor will be supplied with a seismic RCP lube oil system and re-designed, seismically-qualified upper and lower RCP lube oil collection systems.
FPC plans to install the new RCP motor during Refuel 9 and to upgrade the removed motor to be consistent with the new design for installation during a future outage. This rotation will continue until all four motors are modified and re-installed in the plant.
FPC requests an exemption to the portion of 10 CFR 50, Appendix R, Section III.0, "011 Collection System for Reactor Coolant Pump," that requires the RCP oil collection system to "be capable of collecting lube oil from all potential pressurized and unpressurized leakage sites in the RCP lube oil systems." The modifications to the lube oil collection system will exclude four lube oil system sites from leakage protection, and as such, an exemption to Appendix R . is required. Granting this exemption is justified by 10 CFR 50.12(a)(1) and (a)(2)(ii) in that the exclusion of the four sites listed herein from the oil collection system will not present an undue risk to the public health and safety, and does not prevent meeting the underlying purpose of the rule.
150163 -
CRYSTAL R!VER NUCLEAR PLANT: Powerline Road + P.O. Box 219 + Crysta! River, Florida 34423-o219 + (904) 795 6486 .j l m ma gmu comny l 9306170098 930607 PDR ADDCK 05000302 l p PDR
r:
- t U. S. Nuclear Regulatory Commission 3F0693-04 j Page 2 of 9 j It is requested that this exemption be granted prior to December 31, 1993. This ,
schedule would allow for the first RCP motor replacement to be accomplished l during the upcoming Refuel 9 outage in the Spring of 1994. .
Sincerely, f,
P. M. Beard, Jr.
Senior Vice President Nuclear Operations ,
PMB/REF:ff l Attachment i
xc: Regional Administrator, Region II ,
NRR Project Manager Senior Resident Inspector I
l 1
i i
U. S. Nuclear Regulatory Commission 3F0693-04 Page 3 of 9 l
EXEMPTION RE0 VEST Florida Power Corporation hereby submits a request for an exemption to certain portions of 10 CFR 50, Appendix R, Section 111.0 in accordance with the provisions of 10 CFR 50.12. This exemption will allow for the exclusion of four Reactor Coolant Pump (RCP) motor lube oil system sites from the requirement to provide leakage protection for all potential pressurized and unpressurized leakage sites.
NO UNDVE RISK In accordance with 10 CFR 50.12(a)(1), Florida Power Corporation demonstrates herein that the requested exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. This request does not create conditions adverse to the safe operation of the unit in that the RCP motor lube oil and lube oil collection systems continue to meet the purpose of Appendix R, Section 111.0, as discussed below. .l SPECIAL JUSTIFYING CIRCUMSTANCES 1'
The special circumstances which justify the Commission's approval of this exemption request are consistent with the following requirement of 10 CFR 50.12.
10 CFR 50.12(a)(2)(ii) Application of the regulation in this particular l circumstance does not serve the underlying purpose of i the rule nor is it necessary to achieve the underlying !
purpose of the rule.
The purpose of the rule is to provide assurance that oil leaking from the RCP motor lube oil system does not come in contact with surfaces that are hot enough to ignite the oil. These occurrences could be random or seismically-induced.
The resulting fire could produce severe localized environments which could adversely affect the operability of safety-related equipment inside the containment building. The oil collection system was considered necessary to confine any oil discharge due to leakage or failure of the lube oil system and to prevent it from becoming a fire hazard by draining it to a safe location. In support of this, Appendix R required an oil collection system that was designed, engineered and installed such that failure will not lead to a fire during normal' or design basis accident conditions and that has reasonable assurance of withstanding the Safe. Shutdown Earthquake (SSE).
The requested exemption does not prevent achieving the underlying purpose of the rule. The new RCP motor lube oil system has been designed to withstand the SSE.
The accompanying oil collection system is also seismically designed and is capable of channeling and containing the contents of all of the RCP motor lube oil systems with the exception of four sites. These four sites do not present a significant risk of oil leakage and are addressed in the evaluation below.
V . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ -
J U. S. Nuclear Regulatory Commission
,3F0693-04 ,
Page 4 of 9 EVALUATION ,
The existing RCP motor lube oil system includes a high pressure and an induced !
flow system. The high pressure system consists of two independent pumps, one AC ;
pump and one DC pump, and associated piping which supplies oil to the oil lift system at approximately 900 psig during motor startup and shutdown. Its function i is to lift the rotor sufficiently to reduce the breakaway torque to a lower value. These pumps supply oil to the anti-reverse device via a low pressure port when the lift oil system is operating. Either pump is capable of supplying the needed oil flow. The induced flow system is driven by rotation of the RCP motor which provides lubrication at approximately 20 psig during normal operation to the thrust bearings, guide bearings and to the anti-reverse device. The reactor ;
coolant pump motor lube oil system is presently a non-seismic system. The existing reactor coolant pump lube oil collection system is capable of channeling and containing the entire volume of all four reactor coolant pump motor lube oil systems. The oil collection system is seismically-qualified.
The installed RCP motors will be replaced one at a time with a new or refurbished / modified motors having improved design features. Design changes have been made to improve motor reliability and enhance maintenance activities on the motors and the associated lube oil collection systems. The improved design includes a seismic RCP lube oil system and re-designed, seismically-qualified a upper and lower RCP lube oil collection systems.
The new RCP lube oil system eliminates the redundant high pressure RCP motor AC lube oil lift pump and its associated piping, valves and other components. This ,
pump is not necessary for the operation of the RCP motor and its removal will enhance the integrity of the lube oil system by decreasing the number of potential high pressure lube oil leakage sites. Welded connections will be incorporated as much as possible into the re-design of the replacement systems.
The seismic design and system modifications will eliminate the need for complete enclosure of the lube oil system since the system will be designed to withstand the postulated events contained within the Final Safety Analysis Report and 10 CFR 50, Appendix R, Section III.0, without failure. Maintenance on the RCP motors and, in particular, the oil collection systems will be simplified, thereby improving the reliability of these systems, reducing system maintenance time and ,
cost, and lowering the personnel dose associated with RCP motor and oil collection system activities.
During the re-design effort, it was identified that four sites on the RCP motor '
lube oil system could not be readily equipped with leakage protection. The inclusion of these sites would not significantly enhance leakage protection and would create an oil collection system that was extremely difficult to design and
- maintain due to the location and arrangement of the collection devices and associated interferences. Therefore, an exemption to that portion of 10 CFR 50, Appendix R, Section 111.0 that requires the oil collection system to capture all i potential pressurized and unpressurized leakage sites is requested.
U. S. Nuclear Regulatory Commission 3F0693-04 .
Page 5 of 9 i EVALUATION (continued)
The following sites on the lube oil system are proposed to not be equipped with leakage protection. Attachment 1 provides a description of the oil collection system.
- 1. Anti-Reverse Device (ARr>) Vents (2)
- 2. Upper Lines for ARD fr<m Lift Oil Pump
- 3. Lower RCP Motor Leak Catection System Piping
- 4. Lower Guide Bearing and Oil Temperature Thermocouples (2)
The two anti-reverse device vents c.re positioned 'high on the motor and are :
seismically-designed. The vent pipe , would contain only oil mist or foam and are ,
equipped with a demister installed it the end of the vent line. These lines do j not pose a significant oil leak potential and, therefore, will not be provided i with leakage protection with the new oil collection system design.
The upper lines for the ARD which supply low pressure lift oil during pump startups and shutdowns will not be protected from potential oil spray leakage.
Due to the configuration of the RCP motor and the required routing for these :
lines, spray protection would be difficult to provide without aeopardizing maintenance reliability. Extending the spray shield is not feasible. Since the duration of time for operation of this system is limited to a few minutes on '
startup and shutdown of the affected pump, and the cost and maintenance interference i cmoval significant, no spray protection will be provided for these lines. Any mine leakage will be contained by the lip at the radial assembly line of the upper motor.
The lower RCP motor leak detection system piping will not be provided with leak capturing devices. This piping normally does not contain oil and providing ;
leakage protection would interfere with maintenance activities,- existing structures and other components, and would be difficult to design.
The two lower guide bearing and oil temperature thermocouples will not have leak protection associated with them. The installation of leakage protection was , !
determined to not be feasible due to difficulties in designing leak coverage for '
the thermocouple end mechanical connections. Any leakage that could potentially occur would be at the mechanical joint to the lube oil system and would be minor ;
due to the tolerances associated with the threaded connections on the thermocouple well.
The principle risk resulting from not providing leakage protection is the risk of the leaking oil coming in contact with a hot surface and causing a fire. - The likelihood of oil leakage from the above listed sites is remote. The seismic i design for the entire lube oil system precludes failures as a result of the Safe Shutdown Earthquake. The ARD vents and lower RCP motor leak detection piping do not contain oil under routine operating conditions; therefore, leaks would not be postulated from these sites. The upper lines for the ARD from the lift oil system are under pressure for only a very brief time during motor startups and .
shutdowns. Credit is taken for proper maintenance and leak check techniques to assure a leak-tight system. The thermocouple connections can be checked for leaks prior to completion of any maintenance activities on the system and, since these connections are passive in nature, leakage from these sites is considered
U. S. Nuclear Regulatory Commission 3F0693-04 '
' Page 6 of 9 EVALUATION (continued) remote. In addition, CR-3's Fire Hazards Analysis has analyzed a fire in the area of the reactor coolant pumps which resulted from the ignition of the total contents of the lube oil system. The resulting postulated fire did not adversely-affect the plant's ability to safely shut down. Therefore, the consequences of a fire which might result from any spillage or-leakage of RCP lube oil do not i po:e a significant risk to the health and safety of the public. 5 CONCLUSION The granting of this exemption would enhance maintenance activities on the motors and the associated lube oil collection systems, thereby improving system -
performance and reliability. The new motors will be supplied with a seismic RCP !
lube oil system; a re-designed, seismically-qualified upper RCP lube oil collection system; and a modified, seismically-qualified lower lube oil collection system. The system modifications will be designed to withstand-the postulated events contained within the Final Safety Analysis Report and 10 CFR 50, Appendix R, Section III.0, without failure. Leakage from the lube oil ;
system is contained by the oil collection system with the exception of the sites identifisd herein. These sites represent little risk to the initiation of a fire ,
in the containment and, therefore, pose no significant risk to the continued safe operation of the unit.
l 2
b
4 U. S. Nuclear Regulatory Commission
' 3F0693-04 Page 7 of 9 ATTACHMENT I DESCRIPTION OF RCP MOTOR LUBE OIL COLLECTION SYSTEM The following description of the lube oil collection system is to be used with the attached General Electric (GE) Drawings 4005EIO72FT, " Outline Drawing," and 4004D1266CH, "High Pressure Oil Piping". The items identified within these drawings are identified by outline clouds with circled numbers. A description of the items contained within the clouds and the means of oil collection is provided for each numbered circle.
Item number one (1) is the Anti-Reverse Device (ARD) vents for the RCP motor l A vent is provided for each side of the ARD. These vents are seismically-designed and have a demister installed at the end of each of the vent lines. Per i discussions with General Electric, the equipment manufacturer, these lines would contain oil mist or foam only; therefore, oil leakage from the lines and the i demisters is not expected to occur.
Reference:
GE Drawing 4005E1072FT.
Item number two (2) contains the Upper Bearing Lube Oil Level Instrument, Oil '
Level Instrument Isolation Valve, Oil Level Instrument Drain Valve, Oil Fill, :
Remote Fill Connection, Drexelbrook Probe, Oil Level Gage, Thrust Bearing Thermocouples, Guide Bearing Thermocouple and Oil Temperature Thermocouple. ,
These items are part of the Upper Bearing Lube Oil System which are supplied by the RCP motor induced flow lube oil -system, and are seismically-designed.
Therefore, spray protection for the mechanical joints for these items will not ,
be provided. Oil leakage which may occur from the mechanical joints for these ;
items will be collected by the lip installed at the upper radial assembly'line i of the RCP motor. Oil collected within this area will drain to the drip pan located below the Upper Lube Oil System Heat Exchanger. This drip pan will be ;
attached to the existing RCP Lube Oil Collection System by an existing flex hose connected at the bottom of the drip pan.
Reference:
GE Drawing 4005EIO72FT.
Item number three (3) contains the Upper Lube Oil flanged supply and return lines for the Upper tube Oil System Heat Exchanger. These items are seismically-designed and supplied by the RCP motor induced flow lube oil system. Therefore, spray protection for these lines will not be provided. Oil leakage which may occur from the flanges will be collected either by the lip at the upper radial assembly line for the flanges located near the RCP motor housing or the drip pan 1 located below the heat exchanger for the flanges located near the heat exchanger.
Item three 'A' (3A) identifies the Upper Lube Oil System reservoir drain valve /line and the heater exchanger drain valve /line (located below the heat exchanger - not shown on drawing). These drain lines are seismically-designed and part of the RCP induced flow lube oil system. Therefore, spray protection-is not provided. Leakage from these drain lines will be collected by the drip pan located below the heat exchanger for the Upper Lube Oil System.
Reference:
GE Drawing 4005E1072FT.
J
?
U. S. Nuclear Regulatory Commission '
3F0693-04
'Page 8 of 9 Item number four (4) is the fiberglass spray guard for the High Pressure l' . -
Lube Oil System. The spray guard is seismically designed and is a one nece l cover protecting the High Pressure Lube Oil Lift Pump, associated high pressure i oil piping, tubing and other piping / tubing components, high pressure relief valve which relieves to the reservoir, high pressure switches and high pressure oil hoses and tubing. The RCP High Pressure Lube Oil System is also seismically-designed. Oil leakage and oil spray from the mechanical joints in this area will be contained within the spray guard and lip at the radial assembly line area. ,
Leakage or spray collected will drain to the drip pan located below.the Upper Lube Oil System Heat Exchanger and into the existing RCP Lu' a Oil Collection ,
System via the flex hose connection at the bottom of the heat e.. changer drip pan. '
Reference:
GE Drawing 4005E1072FT and 4004D1266CM.
i Item four 'A' (4A) identifies the lines from the low pressure side of the Upper Lube Oil System Lift Pump which provides lubrication to the ARD during initial '
startup and shutdown of the RCP Motor. These lines are seismically designed.
Spray protection for the mechanical joints is not being provided for these lines i as a result of the design interferences and maintenance problems created. Oil ;
leakage from the mechanical joints for these lines will be collected by the lip r located at the radial assembly line area and directed- to the drip pan located i below the heat exchanger for the Upper Lube Oil System or the drip pan located at the lower end of the motor.
Reference:
GE Drawing 4004D1266CM.
Item number five (5) identifies the Upper Bearing Bracket Vents for the RCP motor. These vents are seismically-designed, and will be provided with oil collection pans which will drain to the drip pan located below the heat exchanger for the Upper Lube Oil System.
Reference:
GE Drawing 4005E1072FT.
Item number six (6) identifies the lower RCP Motor (Air Box) Leak Detection :
System. This system is seismically designed. Oil leakage collection from the mechanical joints for this system will not be provided since these lines do not ;
contain oil during normal operations.
Reference:
GE Drawing 4005E1072FT.
Item numbers seven (7) and eleven (11) identify four covers which are used to gage gap the lower RCP Motor Bearing. Oil leakage from these sealed covers will i be captured by the existing lower end motor drain pan.
Reference:
GE Drawing 4005E1072FT. See item number eleven for the description of the vents identified ,
in item eleven.
Item number eight (C) contains the lower Lube Oil System level Instrument, Oil. )
Level Instrument Isolation Valve, Oil Level Instrument Drain Valve, Oil Fill, i Remote fill Connection, Drexelbrook Probe and Oil Level Gage. These items are l seismically-designed and are part of the RCP induced flow lube oil system. !
Therefore, oil spray protection will not be provided for these items. Leakage l from the mechanical joints for these items will be collected by a drip pan which l will be connected to the existing Plant Lube Oil Collection System using an !
existing flex hose connected to the bottom of the drip pan for these items. l
Reference:
GE Drawing 4005E1072FT.
l
T 4
U. S. Nuclear Regulatory Commission :
3 F0*693-04 l Page 9 of 9 i
Item number nine (9) identifies the lower Lube Oil System reservoir drain !
valve /line and shaft seal for the RCP motor. This drain line'is seismically- l' designed. Leakage from the drain line or shaft seal will be collected by a drain pan located at the bottom of the motor. This drain pan is currently installed on the existing RCP motor and will be removed and re-installed on the new ;
replacement RCP motor in its existing configuration. Drainage from the drain pan is transported to the RCP Lube Oil Collection System using a flex hose connection at the bottom of the drain pan.
Reference:
GE Drawing 4005E1072FT.
^
Item number ten (10) identifies the lower bearing vents for the RCP motor. These vents are piped from within the lower end of the RCP motor and protrude through -
the lower end cover. Leakage from these vents will be collected by the drain pan i for the lower end of the motor as described within item nine.
Reference:
GE Drawing 4005E1072FT. .
Item number eleven (11) identifies the lower motor vents. Oil leakage from these -
vents will be captured by the lower end motor drain pan.
Reference:
GE Drawing 4005E1072FT.
Item number twelve (12) identifies the_ threaded connections at the lower bearing oil reservoir for the lower Lube Oil System Level Instrument, Oil Fill, Oil Level Gage, Lower Guide Bearing Thermocouple and Lower Oil Temperature Thermocouple.
These lines are seismically-designed. Leakage from the mechanical joints for ;
these items will be collected by the drain pan for the lower RCP motor. .
Reference:
GE Drawing 4005E1072FT.
Item number thirteen (13) identifies the Lower Guide Bearing Thermocouple and the Lower Oil Temperature Thermocouple. These items are seismically-designed. Oil leakage at the outer end mechanical connections for these thermocouples will not be provided since design of capture devices would be extremely difficult and maintenance and inspection assures a leak-free connection for these passive -
components.
Reference:
GE Drawing 4005E1072FT.
The drain lines for the Upper and Lower Lube Oil System reservoirs, Upper Lube ;
Oil System Heat Exchanger; and the drain valves for the upper and lower level instruments will be in the closed position during normal operation and. the outlets plugged. ,
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