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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M7571999-10-22022 October 1999 Advises That Attachment 1 to ,Marked as Proprietary,Re Safety Limit MCPR & Fuel Vendor Change Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217H8471999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217K8441999-10-15015 October 1999 Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station ML20217H9771999-10-13013 October 1999 Forwards SRO & RO Initial Exam Rept 50-354/98-302,suppl Rept on 990125-29,mtg Meeting on 990322,990429-30 & 0617-18 in-office Review & 990720 Telcon on Appeal Results.Overall, 11 of 16 Applicants Received NRC Licenses ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML20217C4391999-10-0606 October 1999 Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011 ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML20217A9601999-10-0404 October 1999 Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR ML20217A6861999-10-0101 October 1999 Forwards Insp Rept 50-354/99-05 on 990711-0829.Four Violations Occurred Re Areas of Fire Protection,Operation at Reduced Feedwater Inlet Temp & safety-related Battery Charging Operation & Being Treated as NCVs LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999 Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) 05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl ML20217K7781999-09-16016 September 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station for Month of Aug 1999. Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML20212B4021999-09-13013 September 1999 Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML20211N5421999-09-0808 September 1999 Forwards Amend 121 to License NPF-57 & Safety Evaluation. Amend Revises TSs by Relocating Procedural Details of RETS to Offsite Dose Calculation Manual LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999 Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML20211B5341999-08-20020 August 1999 Forwards RAI Re 2nd 10-yr ISI Interval Relief Requests Re Plant.Info Requested to Be Provided within 60 Days of Receipt of Ltr ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML20210R4911999-08-11011 August 1999 Forwards Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted.Inspectors Reviewed Performance Indicators Submitted as Part of Pilot Program for New Regulatory Oversight Process & Verified Data ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210H9241999-07-26026 July 1999 Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys ML20210F3271999-07-22022 July 1999 Forwards SE Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3 Re First 10-year Interval for ISI Program at Hope Creek ML20210D3971999-07-16016 July 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML20209G2831999-07-14014 July 1999 Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant 05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999 Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999 Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds ML20196J4421999-07-0101 July 1999 Forwards Request for Addl Info Re Increase of Allowable Main Steam Isolation Valve (MSIV) Leak Rate & Deletion of MSIV Sealing Sys for Plant LR-N990316, Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML20209B6441999-06-21021 June 1999 Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01 ML20196F9441999-06-21021 June 1999 Forwards Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Two Violations of NRC Requirements Occurred Re Reactor Bldg Ventilation Setpoints & Control Rod Drop Analyses ML20196E6471999-06-21021 June 1999 Forwards Revised marked-up TS Page for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively. Revised Pages Do Not Alter Conclusions Reached in 10CFR50.92 No Significant Hazards Analysis Previously Submitted ML20209C0621999-06-21021 June 1999 Forwards NPDES Discharge Monitoring Rept,May 1999, for Hcgs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20196E9631999-06-17017 June 1999 Informs That Util Has Made Change to Commitment Stated in NRC Ser,Suppl 5.Commitment That Has Been Changed Is Item Number 1 of First Paragraph on Page 9-3 of Ser,Suppl 5 LR-N990295, Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 9905111999-06-16016 June 1999 Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 990511 05000354/LER-1999-006, Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER1999-06-15015 June 1999 Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER ML20195J1101999-06-0707 June 1999 Informs of Completion of Review of Providing Updated Status on Implementation of Commitments Made in Response to GL 89-13.Confirms Revs Made to Previous Commitments to Resolve Monitoring Pressure Drop Problem ML20195J1051999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Jw Clifford Will Be Section Chief for Hope Creek Generating Station ML20207F2681999-06-0303 June 1999 Responds to by Forwarding Gfes & NRC Written Exam Grades for List of Hope Creek Operators Submitted by DE Jackson.Absence of Gfes Grade Indicates That Operator Previously Issued RO or SRO License.Without Encl ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML20207D0201999-05-27027 May 1999 Discusses 990512 Meeting to Identify Insp Activities at Hope Creek Facility Over Next Six Months & Informs of Planned Insps in Order for Licensee to Have Opportunity to Prepare & Provide Region I with Feedback on Schedule Conflicts ML20195B9931999-05-20020 May 1999 Forwards NPDES Discharge Monitoring Rept,Apr 1999, for Hgcs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML20207A3451999-05-20020 May 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs ML20206Q6211999-05-14014 May 1999 Informs That on 990119 Licensee Provided NRC with Several Revised TS Bases Pages for Plant.Ts Bases Pages B 3/4 6-1 & B 3/4 6-2 Were Revised 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K8441999-10-15015 October 1999 Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML20217A9601999-10-0404 October 1999 Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999 Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) 05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML20212B4021999-09-13013 September 1999 Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999 Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210H9241999-07-26026 July 1999 Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys 05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999 Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999 Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds LR-N990316, Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML20196E6471999-06-21021 June 1999 Forwards Revised marked-up TS Page for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively. Revised Pages Do Not Alter Conclusions Reached in 10CFR50.92 No Significant Hazards Analysis Previously Submitted ML20209B6441999-06-21021 June 1999 Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01 ML20196E9631999-06-17017 June 1999 Informs That Util Has Made Change to Commitment Stated in NRC Ser,Suppl 5.Commitment That Has Been Changed Is Item Number 1 of First Paragraph on Page 9-3 of Ser,Suppl 5 LR-N990295, Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 9905111999-06-16016 June 1999 Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 990511 05000354/LER-1999-006, Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER1999-06-15015 June 1999 Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML20206P1931999-05-10010 May 1999 Provides Updated Status of Plant Implementation of Commitments to GL 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment, Issued by NRC on 890718.Revised Commitments to Subject Gl,Listed 05000354/LER-1998-008, Forwards LER 98-008-01 Re ESF Actuation/Automatic Reactor Scram Due to Turbine Trip.Caused by High Moisture Separator Level.Commitments Listed in Attachment a1999-05-0404 May 1999 Forwards LER 98-008-01 Re ESF Actuation/Automatic Reactor Scram Due to Turbine Trip.Caused by High Moisture Separator Level.Commitments Listed in Attachment a ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML20206D3301999-04-27027 April 1999 Submits Completion of Requested Actions for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2411999-04-22022 April 1999 Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics ML18107A1841999-04-14014 April 1999 Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl ML18107A1691999-04-12012 April 1999 Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept 05000354/LER-1999-004, Forwards LER 99-004-00 Re Check Valves for Containment Atmosphere Control Sys Vacuum Breaker Isolation Valve Accumulator Did Not Meet Leakage Requirements During Testing.Commitments,Encl1999-04-0808 April 1999 Forwards LER 99-004-00 Re Check Valves for Containment Atmosphere Control Sys Vacuum Breaker Isolation Valve Accumulator Did Not Meet Leakage Requirements During Testing.Commitments,Encl ML18106B1491999-04-0505 April 1999 Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML18107A2201999-03-30030 March 1999 Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek ML18106B1411999-03-30030 March 1999 Forwards Decommissioning Info on Behalf of Conectiv Nuclear Facility License Subsidiaries,Atlantic City Electric Co & Delmarva Power & Light Co,For Listed Nuclear Facilities 05000354/LER-1999-003, Forwards LER 99-003-00,as Found Values for Safety Relief Valve Lift Setpoints Exceed TS Allowable Limits,Per Requirements of 10CFR50.73.Attachment a Contains Commitments Made1999-03-26026 March 1999 Forwards LER 99-003-00,as Found Values for Safety Relief Valve Lift Setpoints Exceed TS Allowable Limits,Per Requirements of 10CFR50.73.Attachment a Contains Commitments Made LR-N990111, Responds to NRC Re Violations Noted in Insp Rept 50-354/98-302.Corrective Actions:Hope Creek Licensed Operator Training Completed Full Audit of 1998 Requalification Training Records1999-03-25025 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-354/98-302.Corrective Actions:Hope Creek Licensed Operator Training Completed Full Audit of 1998 Requalification Training Records LR-N990131, Documents Util Understanding of Info Contained in SER Re Amend 113 for HCGS Re Elimination of Restrictions Imposed by TS 3.0.4 for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities1999-03-22022 March 1999 Documents Util Understanding of Info Contained in SER Re Amend 113 for HCGS Re Elimination of Restrictions Imposed by TS 3.0.4 for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities LR-N990132, Forwards Revised TS Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 in 19971999-03-22022 March 1999 Forwards Revised TS Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 in 1997 LR-N990133, Forwards marked-up TS Bases Page B 3/4 8-1d for LCR H98-11, That Was Submitted on 981216.Original Page Contained Editorial Errors That Had Been Incorporated Into Bases During Implementation of HCGS License Amends 100 & 1011999-03-22022 March 1999 Forwards marked-up TS Bases Page B 3/4 8-1d for LCR H98-11, That Was Submitted on 981216.Original Page Contained Editorial Errors That Had Been Incorporated Into Bases During Implementation of HCGS License Amends 100 & 101 ML18106B1071999-03-22022 March 1999 Forwards Annual Rept on Results of Individual Monitoring for Salem & Hope Creek Generating Stations,Iaw 10CFR20.2206.Info Provided on Encl Floppy Disk.Without Disk ML20206J4021999-03-10010 March 1999 Responds to NRC Oversight of Nuclear Plants Response to Y2K Bug.Consideration of More Aggressive Action to Forestall Any Y2K Problems,Requested LR-N990112, Requests Approval of ASME Code Case N-567,allowing Use of Replacement Valve for Containment Atmosphere Control Sys Valve That Was Constructed to Earlier Version of ASME Code than Existing Valve1999-03-0505 March 1999 Requests Approval of ASME Code Case N-567,allowing Use of Replacement Valve for Containment Atmosphere Control Sys Valve That Was Constructed to Earlier Version of ASME Code than Existing Valve ML18106B0861999-03-0101 March 1999 Forwards Annual Repts for Salem & Hope Creek Generating Stations,Containing Data on Number of Station,Utility & Other Personnel Receiving Exposures Greater than 100 Mrem/ Year & Collective Exposures According to Work & Job 1999-09-08
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l Public Service Electric and Gas Company P.O. Box 236 Hancocks B idge, New Jersey 08038 Nuclear Department MAY 2 81993 NLR-N93081 United States Nuclear Regulatory Commission l Document Control Desk l Washington, DC 20555 Gentlemen: 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON EMERGENCY DIESEL GENERATOR FUEL OIL STORAGE AND DAY TANKS HOPE CREEK GENERATING STATION DOCKET NO. 50-?54 Public Service Electric and Gas received your Request for Additional Information,-dated April 23, 1993, on May 11, 1993.
The following attachment provides our response to the NRC questions raised during the revicw of our amendment request to I
change the UFSAR commitments for the emergency diesel generator fuel oil transfer pump start level and fuel oil storage tank capacity requirements.
If you should have any questions regarding this information please contact us.
'nce y, J. .a an Vice re ident -
Nucl. Operations Attachment (1) 020110 f00l I
9306030227 930528 l PDR ADDCK 05000354 P PDR '
The luver is in gur hands.
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MAY 2 81993 Document Control Desk 2 NLR-N93081 C Mr. T. T. Martin, Administrator - Region I l U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. S. Dembek, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North Rockville, MD 20852 Mr. T. P. Johnson (SOS)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental' Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 i
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i l
ATTACHMENT NLR-N93081 ,
i RESPONSE TO REQUEST FOR ADDITIONAL i INFORMATION ON EMERGENCY DIESEL GENERATOR l FUEL OIL STORAGE AND DAY TANKS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Fuel Oil Transfer Pumo Start Level
- 1. To what extent are the power supplies for the fuel oil transfer pumps independent (i.e. not subject to a common fault)?
The primary and alternate fuel oil transfer pumps, for each diesel, are fed from separate class 1E 480 VAC Motor Control Centers (MCC). These MCC's are eventually tied back to the same 4.16 KV bus via their individual transformers. A fault at the 4.16 KV bus level could affect both fuel oil transfer pumps for a particular diesel, but will have no impact on the fuel oil transfer pumps of the other three diesels.
- 2. To what extent is the logic for starting one pump vs. the alternate pump independent (i.e. not subject to common fault)?
The logic circuits for the primary and alternate fuel oil transfer pumps are not completely independent. They maintain separate power sources up to their individual MCC's and have separate control switches. However, a number of control relays are common to the logic of both pumps (UFSAR Figure 9.5-21a). Since the only faults that disable the start of the transfer pumps are a loss of the 4.16KV bus feeding the MCC's or loss of a relay in the logic itself, these faults would have no impact on the fuel oil transfer pumps of the other three diesels.
- 3. How will operators be alerted to a problem concerning the fuel oil transfer pump operation? How would a blown fuse or .
erroneous fuel oil storage tank low level condition be identified?
Operators are alerted to problems related to fuel oil transfer operations via control room annunciator summary alarm window E4-A3 " Diesel Eng Pnl A/B/C/D C423". Operators respond to this window by procedures HC.OP-AR.KJ-0001 (A EDG), -0003 (B EDG),-0005 (C EDG) and -0007 (D EDG). While a blown fuse or erroneous fuel oil storage tank low level condition are not alarmed directly, some of the alarm inputs (as described in procedure HC.OP-AR.ZZ-0017) are as follows: fuel oil day tank level low, loss of AC control power, fuel oil day tank level 1 of 5
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I high, fuel oil transfer puay no. 1 malfunction,-fuel oil transfer pump no. 2 malfunction, fuel oil storage tank no. 1 level low low, fuel oil storage tank no. 1 level low, fuel oil '
storage tank no. 2 level low-low, fuel oil storage-tank no. 2 i level low and fuel oil transfer system not in automatic.
- 4. Verify that-the flow paths from each fuel oil transfer pump to :
the fuel oil day tank are completely independent (UFSAR Figure 9.5-22 shows that the' lines are-independent; however, UFSAR !
Table 9.5-5 states that a pipe failure in one.line will cause a complete loss of fuel supply to the EDG). ;
Upon examination of Figure 9.5-2211t can be shown that the lines are completely independent. And upon-initial ;
examination of Table 9.5-5, it does look as if there is a discrepancy between theJFigure and_the Table. .However, the Table represents a' conservative approach to the evaluation of' the effects of a single failure. If the line between the i transfer pump and the day tank _were to sever, only the !
contents'of that particular1 fuel' oil storage tank-would be_ i unavailable for that EDG. _However, it would be difficult to +
quantify how much fuel oil would ovemflow from the day tank into that.particular. storage tank line and it would be l difficult to quantify how much fueltoil would go into that particular storage tank as wastage from the fuel oil racks on-that particular'EDG.- Therefore, the-UFSAR takes the ~
conservative approach and evaluates that particular failure as if that EDG were unavailable. -
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- 5. What specific administrative' controls are being implemented to address this situation?-
Operators daily log HC.OP-DL.ZZ-0006(Q) was revised to' require the EDG fuel oil day tanks to be maintainedLat 440 gallons or greater. If the volume falls below this-level the operators are instructed to fill the day tank.
- 6. How frequently.will each fuel oil transfer pump. cycle on and off if the setpoint were changed to comply with the Standard Review Plan guidance?' Is this frequency of operation outside of the pump and motor design rating?
At present, the fuel oil transfer pump for a storage tank starts on a level in the day tank of 248 gallons and stops when the level in the day tank reaches 489 gallons. Using a consumption rate of 5.8' gal / min with 100% load on the EDG and a transfer pump flowrate of 37 gal / min (UFSAR Table.9.5-4),
with the way the fuel oil transfer pump system is designed, each transfer pump will run-for approximately 7.72 minutes and be idle for approximately 93.1. minutes. If the setpoint for-transfer pump start was set at a point to comply with the Standard Review' Plan guidance (458 gallons), a particular 2 of 5
transfer pump will run for approximately 1 minute and be idle for approximately 11.68 minutes. l l
The increased operating frequency was discussed with the Vendor. The Vendor has stated that the pump is capable of up to a maximum of 6 starts per hour. Since operation of the transfer pump at a start level consistent with the Standard Review Plan would result in the transfer pump being operated between 5-6 times an hour, the pump and motor would be within their design ratings. Even though the pump and motors would be within their design ratings, increasing the cycling of the pump and motor would increase the component degradation (i.e.,
increased maintenance, early component replacement) beyond the benefit gained from raising the transfer pump start level.
Fuel Oil Storace Tank Capacity
- 1. What are the maximum run times if all four diesels are operating after the design basis accident?
Using UFSAR Table 8.3-2 for loadings of the EDG's after a design basis accident and assuming that fuel oil can be transferred between all four EDG's, the EDG's will run for approximately 223 hours0.00258 days <br />0.0619 hours <br />3.687169e-4 weeks <br />8.48515e-5 months <br />. Looking at each EDG independently, the maximum run times for each EDG based only on the fuel oil contained in the storage tanks are 163 hours0.00189 days <br />0.0453 hours <br />2.695106e-4 weeks <br />6.20215e-5 months <br /> for A EDG, 353 hours0.00409 days <br />0.0981 hours <br />5.83664e-4 weeks <br />1.343165e-4 months <br /> for B EDG, 195 hours0.00226 days <br />0.0542 hours <br />3.224206e-4 weeks <br />7.41975e-5 months <br /> for C EDG and 238 hours0.00275 days <br />0.0661 hours <br />3.935185e-4 weeks <br />9.0559e-5 months <br /> for D EDG.
- 2. What is the basis for the 6 days 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> run time? Is this based on the " worst case" diesel' consumption, or is this based on the total consumption of all operating EDG's and then averaged? If this is based on the worst case diesel consumption, what is the maximum run time for the two other EDG's? What will the run times be if the fuel oil from the idle EDG is used?
The 6 days 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> run time is based on the highest total KW loading of 3 EDG's utilizing the numbers for KW loading located in the UFSAR Tables 8.3-2 through 8.3-6. The assumption in the run time number is that fuel oil can be transferred between the 3 operating EDG's since their fuel oil transfer pumps'will have power available for such an operation. If the idle EDG fuel oil storage tanks were l available for use and assuming that fuel oil can be l transferred between the remaining EDG's as needed, the same 3 EDG's will run for approximately 58.5 additional hours. This additional time due to the use of the extra tanks does not take into account the 10% margin required by the Standard Review Plan.
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- 3. What fuel oil rating is credited for determining the diesel engine consumption rate? What assurance is there that a lesser quality fuel oil will not be used?'
The specification for the fuel oil used in the manufacturer's tests was that the fuel oil would have a LHV of 18190 BTU /lb and a HHV of 19350 BTU /lb. Using Mark's Standard Handbook for Mechanical Engineers, this corresponds to a Deg API at 60*F of approximately 28. The actual HV's used during the manufacturer's consumption rate test were 19266 for A, 19272 for B, and 19273 for C and D. By Technical Specification requirements (TS 4.8.1.1.2.f.1.c), the lowest specific gravity fuel oil that is acceptable is 28 Deg API at 60*F.
- 4. How do you intend to transfer the fuel oil from the idle EDG's storage tanks to the active EDGs' storage tanks (i.e., what are the applicable details such as pumps required, power supplies, temporary hoses used, etc.)? The reliability of this contingency must be understood by the staff.
Abnormal operating procedure HC.OP-AB.ZZ-0135(Q) has been.
revised to require the control room to contact the TSC, in the event that an emergency diesel generator (EDG) can not be started in an emergency, to have engineering develop a plan to transfer the fuel from the inoperable EDG storage tanks to the operable EDG storage tanks. Due to the number of equipment failures that can be postulated to cause the EDG failure, PSE&G believes that developing specific procedures to address this concern is not prudent. PSE&G believes that the amount' of time provided by the remaining EDG's (6 days 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> worst case) would be sufficient to develop and implement a plan to transfer fuel from the inoperable EDG storage tanks to the operable EDG storage tanks.
- 5. Provide the following details on the EDG load / fuel consumption determinations:
- a. Day tank total capacity and usable volume, including the consideration for vortex effects.
- b. The fuel oil storage tank total capacity and usable volume,
- c. The worst-case fuel consumption rate over time, based on the load calculations. How is the fuel oil consumption rate adjusted for different diesel loads?
The day tank is a 550 gallon tank. At the current transfer pump stop setpoint level, there nre 489 gallons in the tank.
The amount of fuel oil that is unavailable due to vortex effects is approximately 47.3 gallons. This makes the total ;
useable volume of the tank 441.7 gallons. At the current low !
level setpoint in one fuel oil storage tank (there are two 4 of 5
c .
4 fuel oil storage tanks per EDG), there are approximately l
24436.4 useable gallons in the tank. This number takes into account the amount.of fuel oil that is unavailable due to i vortex effects. The unusable volume in the tank is '
approximately 1192.4 gallons. .The total capacity of the storage tanks is 26500 gallons. The worst case fuel oil l consumption-over time was determined by examining the UFSAR Tables 8.3-2 through 8.3-6.. The worst case fuel oil consumption rate over time is for the case of the highest l total KW loading for 3 EDG's with the D EDG unavailable. Using l these UFSAR tables, it was determined to base the fuel oil l consumption rate on the loading of the EDG's that occur at the 60 minutes & beyond point, after a design basis accident, since the loads for the less than 60 minutes time period have no significant impact on fuel oil consumption over 6+ days.
- 6. What administrative controls will be implemented to ensure that fuel oil is available on site in time to ensure continued diesel operation during an' event?
I In response to NRC FSAR Question 430.88, pSE&G evaluated the l ability to refuel the EDG fuel oil storage tanks within the seven day time period under severe weather conditions. This evaluation states that while extremely adverse wind, weather and tidal conditions at the Hope Creek Site could interfere with diesel fuel oil delivery for approximately 24-36 hours, it would be a very improbable situation that would preclude delivery by truck or barge for as long as 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.
l In accordance with procedure HC.OP-AB.ZZ-0139(Q), " Acts of Nature," if severe flooding is forecast and the Delaware River level is steadily increasing, the operators are instructed to make arrangements to obtain diesel fuel.in advance of and during the anticipated flooding. If high winds, tornadoes, or hurricane warnings are forecast, the operators are instructed 4 to order a diesel fuel oil shipment to top off all the storage i tanks.
During daily operator rounds (procedure HC.OP-DL-ZZ-0006(Q))
the EDG fuel oil storage tank levels are recorded. If the fuel oil storage tank level is below 24400 gallons (Technical l
Specification minimum level is 48800 gallons for each EDG and there are two storage tanks per diesel), the operator will notify the SNSS/NSS. The SNSS/NSS will order fuel oil'for the EDGs IAW Operations Department Directive HC.OP-DD.ZZ-0015(Z).
Typically EDG fuel oil is ordered before the fuel oil storage i
l tanks reach their Technical Specification minimum volume.
During normal operation, actual fuel oil delivery from time of order to transfer to the EDG storage tanks has been accomplished in less than one day.
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