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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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.a Public Servte EMcue md %s
~ Gmtuny Stanley LaBruna Public Servico Electric and Gas Company P O Box 236. Hancocks Bndge, NJ 08038 609-339 1700 m._,.""""
MAR 111994 NLR-N94015 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
NOTIFICATION OF CHANGES TO GENERIC LETTER 89-10 COMMITMENTS GENERIC. LETTER 89-10 IIOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 The purpose of this letter is to provide notification of changes to our Generic. Letter 89-10 commitments for Hope Creek. Our initial response to Generic Letter 89-10 was provided in NLR-N89239 dated' December 27, 1989 and NLR-N90179 dated
' August 31, 1990 and stated that, to date, we had not identified any exceptions to the generic letter recommendations cnr schedule.
Based upon knowledge and experience gained since our' original response, we believe an exception is now' appropriate and can be adequately justified. The specific exception being addressed in this letter involves our intent to discontinue dynamic testing of small globe valves having a. low design basis' differential pressure (less than or equal to two inches and less than or equal to 500 !
paid). We have evaluated the results of EPRI testing of globe valves and completed an evaluation of our utility specific test results. Based on this information, we believe that the above referenced valvo population has demonstrated acceptable performance, and we believe that dynamic testing is not necessary in order to demonstrate,-with a sufficient level of' confidence, the capability of each of these' valves to perform under design basis conditions. Although we intend to discontinue dynamic testing of-the subject valves, we still intend to perform static;
' testing. Details of our justification for the commitment change are provided in the attachment to this letter.
This action is considered a Cost Beneficial Licensing Action, and we have estimated the cost savings of this change in commitment during the upcoming year to be in excess-of $1 million.
l
.l 11100d:
9403180125 940311 obi PDR ADOCK 05000354 .l.
p PDR c
l MAR 11 1gg4 Document Control Desk 2
< NLR-N94015 Should you have any questions or need additional information relative to thic letter, please do not hesitate to contact us.
Sincerely, cfh ,
Attachment (2)
Affidavit e
C Mr. T. T. Martin, Administrator - Region I
- U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike-Rockville, MD 20852 Mr. C. Marschall (SOS)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 4 I
, . . , m , , . . , . - , -, s - - . e - ,
4 REF: NLR-N94015 STATE OF NEW JERSEY )
) SS.
COUNTY OF CALEM )
S. LaBruoa, being duly sworn according to law deposes and says:
I ani Vice President - Nuclear Engineering of Public Service
' blectric and Gas Company, and as such, I find the matters set i
- 1 forth in the above referenced letter, concerning the Hope Creek j i
Generating Station, are true to the best of my knowledge, information and belief.
I r v ks1Y/$w l
l Subscribed and Sworn t before me this / / dd- ,
day of , /0#1 *
, 1994
. 11 < IA t- ]I LOIi!)A -
NotaryPublichof'NewJersey KlMBEfilY JD 000WN NOTARY PU8 tlc OF NEW JERSEY My Commission expires on "I C0033 Ion Endes Agil 21,199g a .. . . ,, , ...
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ATrNJPENT JiffrIFICATIN 101 G2ERIC IEPIH189-10 COMPIMNT OIANGE IUITFICATICE OF OIANZS TO GNEIUC IEPIER 89-10 CDMPINNfS G2ERIC IEPITR 89-10 IDPE OE1X GRERATING STATIM FACILITY OPWATING LIONSE NPF-57 DOCKEP NO. 50-354 NIR-N94015 I. INITOLUCTION 1he purpose of this attachment is to provide justification for eliminating dynamic testing of small globe valves having a low design basis differential pressure (less than or equal to two inches and less than or equal to 500 psid). This population of valves has demonstrated a high level of acceptable performnce, ard PSE&G believes that dynamic testirg is not tw-ry in order to demonstrate, with a sufficient level of confidence, the capability of each valve to perfom under design basis conditions. 'Ihis action is consistent with the goals of the Cost Ihneficial Licensirq Action Initiative.
II. VALVE POWIATION AND ASSOCIATED JUSTIFICATIONS On the basis of globe valve dynamic tests performd to date by PSE&G, EFRI, aid other utilities, PSE&G believes that small, low differential pressure globe valves (less than or equal to two inches ard less than or equal to 500 psid) perfom predictably under dynamic conditions with switch settings established under static conditions in accordance with our mtor operated valve (10V) Programmatic Standard and switch setting methods.
The reason for this globe valve predictability can be understood by examining the manner in which these globe valves react to applied dynamic loads. The primary dynamic loads that may affect the ability of an 10V to achieve its safety position urder design basis conditions as cmpared to static conditions involve disc forces, stem friction forces, and cperator sprirg pack behavior. In accountirg for these forces, the chief difference between gate and globe valves is the manner in which the differential pressure forces acrcss the disc for each valve type is determined. In accounting for globe valve differential pressure forces across the disc, little to no friction is involved because the flow across the seat tends to center the disc. For a gate valve, additional friction may be present as the disc slides across the seat. Thus, globe valves may be considered more predictable because disc friction and disc contact surface cordition minimally affect the motor operator output requirements.
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Attachment NLR-N94015 Changes to GL 89-10 Commitments l
PSE&G has tested appmximately 20% (29/118) of the total Generic letter 89-10 globe valve population at Salem and Hope Creek uMer differential pressure corriitions. In all cases, the target thnist value established by our WN Pmgramatic StaMard and the resultant static actuator switch settings were sufficient to bourd the differential pressure test closing thrust requirements, including extrapolated values to design basis l coniitions. l The majc-ity of the valves tested am two inch or smaller with only two havirq a (gh design basis differential pressure. In achieving greater I than 90% the design basis differential pressure in the tests for the tw high Lfferential pressure valves, the reverse determination for the v w ert alve factor yielded values of nearly unity (1.0). This is t wtmc with actuator sizing methodology considerirg the uncertainties I s3nized to exist with thrust meastatuait equipment. The other small valves were tested at substantially lower differential pressures in acx:ordance with their design bases. Psverse determinations of apparent valve factors for these valves yielded a range of values with all but two below the 1.1 value assumed in our calculations. For the two valves with higher valve factors, the calculated values were 1.50 and 1.56. In our judgement, the higher valve factors can be attributed to the following set of circumstances and phenomena. The thrust sensors employed react to the turbulence caused prior to valve seating such that the thrust traces l contain noise or vibrational energy dissipated in the yoke. For the low differential pressure tests, this noise has the potential to mask actual stem thrust at flow cut off causing an artificially high apparent valve factor. It must be remembercd that all of these valves did, in fact, perform satisfactorily with no anamolous behavior and with sufficient margin of capability during dynamic testing.
Three cases in the subject population having cmparable design features and perfonnance requirements were arbitrarily examined by cmparing static to dynamic thrust measurements at torque switch trip. Each case exhibitcd essentially identical results for thrust at this point. This irdicates that static test results thmugh our switch setting methods can be relied upon for the subject MOVs to satisfy design basis requirecients.
EPRI also performed scue limited testhq of globe valves as part of tN MCf/ Performance Prediction P1:Wauu. A total of six valves of various sizes ard pressure classes from four different manufacturers were involved. All testiry corducted at low differential pressure conditions demonstrated good agreement with predictive metixds.
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Attachment NLR-N94015 Changes to GL 89-10 Commitments ihtust margins have been conservatively calculated and are provided in the table attached to this letter. The predictability of the subject valves coupled with their large calculated thrust capability margins provide a high level of confidence that they will satisfy all performance requirements under design basis conditions. Our testiry has validated that the method used to determine required thrust and switch settings for globe valves is both reasonable and canservative. As iniicated above, our test experienos has demonstrated that established target thrust values and the resultant static switch settings were more than adoquate to bound the differential pressure test closing thrust requirments, incitriing extrapolated values to design basis conditions.
Based on the discussion provided above, we believe that continued testing of small, low differential pressure globe valves provides limited ack11tional assurance of valve capability and, therefore, negligible benefit to safety. In adiition, testing of the subject valves 1xnld unr-mrily require considerable time and resources to ccuplete and would, therefore, create a distraction and divert resources that could be more effectively applied in other areas.
As a result of the above infoantion, we will consider the baselina and dynamic performancx3 testing recmmendations of the generic letter satisfactorily addressed for the subject MJVs upon corpletion of switch settin] verification tests errler static conditions. In the future, their performance will be monitortd as part of the tracking and trending program.
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TABT VAIVE IDIUIATIG NOTIFICATIm OF GANES 'IO GENHlIC IEI'ITR 89-10 CCMEDENIS GFNHtIC IEI'ITR 89-10 10PE GEEK GDERATDC STATION FN'TTJ'IY OPERATDC LIOKE NPF-57 DOO TT NO. 50-354 NIR-N94015 A description of each of the subject valves along with its calculated thrust manJin is provided belcw. Thrust margins provided are based on limit switch .
operation since the torque switches for the subject valves are bymW when l the valves are perfonnirg their safety function. As a result, the valves have ;
access to the full capability of the motor cperator to achieve their safety l position. This capability conservatively considers degradcd voltage Itotor I output and a stem friction value of 0.15. The valves which have already been dynamically tested are identified with an asterisk.
A Main Steam System Valves i l
VALVE NUMBER 111FUST MAIGIN VALVE DESCRIPTION 1AlllV-F071 192% Main Steam Line Downstream Header !
Isolation Valve (2" Globe) !
Although our calculations for this valve conservatively assume a differential pressure of 1035 psid, the realistic value is approximately 25 psid.
B. Feedwater System Valve VALVE tGIBER 711FUSP MARGUI VALVE DESCRIPTION 1ADN-4144 97% Feedwater Supply Headers Cross Connect Valve (2" Globe)
C. RHR Systma_V31ves VALVE NUMBER 311 RUST MAIGIN VALVE DESGIPTION 1 DON-5055A 213% RHR Icop A to H2 Recmbiner Isolation Valve (2" Globe) 1EO N-5055B 207% RHR Loop B to H2 Recmbiner Isolation Valve (2" Globe)
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I Table NLR-N94015 l Changes to GL 89-10 Commitments !
D. RCIC System Valve VALVE NUMBER 'nWST MATGIN VALVE DESCRIPTION 1BCEN-F046 188% RCIC Cooling Water Valve (2" Glche)
Although our calculations for this valve conservatively assume a differential pressure of 1507 psid, the realistic value is approximately 100 psid.
E. Control Rod Drivg ifvdraulic System Valves VALVE NUMBER TINST MARGDI VALVE DESCRIPTION 1BFIN-3800A 285% CRD to A Recirculation Ptmp Seal' Isolation Valve (2" Glcbe)
IBFIN-3800B 285% CRD to B Recirculation Punp Seal Isolation Valve (2" Globe)
Although our calculations for this valve conservatively assume differential pressures of 1534 and 1530 psid, the realistic values am approximately 500 psid.
F. HFCI System Valves VALVE NUMBER 'IHRUST MARGIN VALVE DESCRIPTION 1BRN-4803 48% Suppmssion Pool Invel LP Instrument Tap Isolation Valve (2" Globe)
IBRN-4804 48% Suppression Pool level HP Instrument Tap Isolation Valve (2" Globe) 1 BEN-4865 103% Suppression Pool Invel LP Instrument Tap Isolation Valve (2" Glcbe) 1 BEN-4866 lolt Surpression Ibol level HP Instrument Tap Isolation Valve (2" Globe) 1BRN-1059 487% HPCI Cooling Water Valve (2" Globe)
The IBRN-4803 and 1BRN-4804 valves have lower thrust margins than many of the other valves within the sccpe of this letter; however, when viewed frcn a valve capability perspective, these valves are capable of acccmxlating a valve factor of approximately 5.3.
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Table NLR-N94015
. Changes to GL 89-10 Commitments G. Miel Pool Cbolim and Cleanun System Valves VALVE } UMBER UUUST MARGIN VALVE DESCRIPTIGi LEON-4647 169% Service Water Icop A to Fuel Fool Makeup Valve (2'? Globe) 1EQ W-4648 176% Service Water Iccp B to Fuel Ibol Makeup Valve (2" Globe)
H. SACS System Valves VALVE ? UMBER UlRUST MARGIN VALVE DESCRIPTION 1EGN-2320A 97% SACS loop A Return from A Primary (bntainment Instrument Gas Compressor Cooler Isolation Valve (2" Globe) 1EGN-2320B 92% SACS Icop B Return fran B Primary Containment Instrument Gas Ccatpressor Cooler Isolation Valve (2" Globe) 1EGN-2321A 159% Prirary Containment Instrument Gas Compressor Cooler A Cutlet Cross Connect Valve (2" Globe) 1EGN-2321B 154% Primary Containment Instrument Gas Compressor Cooler B Outlet Cross Connect Valve (2" Globe) 1EGIV-2446 76% Service Water Makeup to SACS Icop A Isolation Valve (2" Globe) 1B2N-2447 71% Service Water Makeup to SAG Iccp B Isolation Valve (2" Globe) 1EGN-2452A 97% SAG Icop A Supply to A Primary 1 Containment Instnment Gas Ctatpressor Cooler Isc;1ation Valve (2" Globo) 1EGN-24520 92% SACS Icop B Supply to B Primary l Containment Instrument Gas j Cctrpressor Ccoler Isolation Valve (2" Globe) l 1EGN-2453A 159% Primary Containnent Instrument Gas Ctx: pressor Cooler A Inlet Cross Connect Valve (2" Globe) l l
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i Table N LR-N94015 >
Changes to GL 89-10 Commitments 4 II. SACS System Valygsj0ontinued) ,
1 VALVE NUMBER 'IHEUST MARGIN VALVE DESCRIPTION I 1H2N-2453B 149% Primary Containment Instrument Gas Ompressor Cooler B Inlet i Cross Connect Valve (2" Globe) J I
'Ihe lIX2N-2446 and 1EGN-2447 valves have lower thrust margins than many ]
of the other valves within the scope of this letter; however, when viewrd from a valve capability perspective, these valves are capable of ;
axcznodating a valve factor of approximately 3.7. l I. RCIC 'Ibrbine Steam System Valve VALVE NUMBER 'IHRUST MARGIN VALVE DESCRIPTION 1FO N-F060 255% RCIC Vacuum Pump Discharge Isolation Valve (2" Globe) j l
J. HICI Turbine Steam System Valve j VALVE NUMBER 'HIRUST MARGIN VALVE DESCRIPTION i 1FDIV-4922 261% HPCI Vacuum Pump Discharge .
Isolation Valve (2" Glche)
K. Ccntainment Atmosphere Co_Gtml System Globe Valves VALVE NUMBER 'DIRUST MARGIN VALVE DESCRIPTION 1GSIN-4955A 1122% Containment Atmosphern A H202 Analyzer Uger Drywell Suction Inboard Isolation Valve (2" Globo) 1GSIN-4955B 1112% Containment Atmosphere B H202 Analyzer Upper Drywell Suction Inboard Isolation Valve (2" Globo) 1GSIN-4959A 669% Oontainment Atmosphere A H202 Analyzer Suppression Pool Suction Inboard Isolation Valve (2" Globe) 1GSkN-4959B 646% Containment Atuosphere B H202 Analyzer Suppression Pool Suction Inboatti Isolation Valve (2" Globo)
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Tablo NLR-N94015 Changes to GL 89-10 Commitments K. Containrognt Atnocrtere Control System Globe Valves (Cbntinued)
VALVE NUMBER 'IURUST MATGIN VALVE DESCRIPTION 1CSIN-496SA 925% Containment Atmosphere A !!202 Analyzer Suppression Ibol Suction Outboard Isolation Valve (2" ,
Globe) !
1 1GSIN-496SB 885% Containmnt Atacophore B H202 l Analyzer Suppression Pool suction l Outboard Isolation Valve (2" Globe) 1GSIN-4966A 661% Containment Atmosphere A H202 Analyzer Suppression Pool Return Inboard Isolation Valve (2" l Globe) 1GSIN-4966B 669% Containment Atmosphere B 11202 Analyzer Suppression Pool Return Inboard Isolation Valve (2" Glcbe) 1GSIN-4974 171% Containment Nitrogen Makeup outboard Isolation Valve (2" Globe) !
l 1GSIN-4983A 887% Containment Atmo6There A H202 Analyzer Upper Drywell Suction outboard Isolation Valve (2" Globo) 1CSIN-4983B 850% Containment Atmosphere B H202 Analyzer Upper Drywell Suctilon outboard Isolation Valve (2" Globe)
- 1CSIN-4984A 646% Containment Atmosphere A 11202 Analyzer lower Drywell Suction Outboard Isolation Valve (2" Globe) 1GSIN-49848 638% Containment Atmo6There B H202 Analyzer Irwer Drywell Suction Outhoard Isolation Valve (2" GloLA) 1GSIN-5019A 624% Containmnt Atmosphere A H202 Analyzer Iower Drywell Suction Inboard Isolation Valve (2" Globo)
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Table NLR-N94015 Changes to.GL 89-10 Commitments K. Containment AtamThere Control System Globe Valves (Continued)
't VALVE NUMBER 'nHUST MARGIN VALVE DESCRIPTION 1GSIN-5019B 624% . Containment Atmosphere B H202 i Analyzar Iower Drywell Suction i Inboard Isolation Valve (2" l
Globe) 1GSIN-5022A 692% Contairnent Atmosphere A H202 4- Analyzer suppression Pool Return Outboard Isolation Valve (2" Glcbe) 1GSIN-5022B 685% Containment Atmosphere B H202 Analyzer Suppression Pool, Return Outboard Isolation Valve (2" Globe) 1GSHV-5057A 216% Cbntainment H2 Recmbiner A RHR Outboard Isolation Valve (2"
- Globe) 1GSIN-5057B 223% Containment H2 Recmbirer B RHR Outboard Isolation Valve (2" i
Globe)
L. Containment Instnntent Gas System Valves
, VALVE NUMBER 'nHUST MARGIN VALVE DESCRIPI' ION I
1KUN-5124A 791% Primary Containment Instrument Gas Supply Header A Shutoff Valve (2" Globe) 1KUN-5124B 770% Primary Containment Instnment Cas Supply Header B Shutoff Valve (2" Globe) 1KuiV-5126A 97% Primary Containment Instrument Gas Sugply Header A' Outboard Isolation Valve (2" Globe) 1KUN-5126B 92% Primary Containment Instrument '
Gas Supply Header B Outboard Isolation Valve (2" Globe).
1KUN-5147 183% Primary Containment Instrument -
Gas Ctmpressor A Suction Outboard Isolation Valve (2" Globe)-
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--.m... ...,m ,, , , , - - - - , 9.-.. - -
1 Table NLR-N94015 J Changes to GL 89-10 Commitments L. Contairumnt Instrument Gas System Valves (Coatinued)
VALVE NUMBER 71IRUST MARGIN VALVE DESCRIPTION i l
1KUN-5148 171% Primary Containnent Instrument i Gas Otxtanon Ocstpressor Suction '
Inboard Isolation Valve (2" Globe) 1KUN-5152A 149% Primary Containment Instrument Gas Sumly Header A Inboard Isolation Valve (2" Globe) ,
1KUN-5152B 154% Primary Containment Instrument l; Gas Supply Header B Inboard Isolation Valve (2" Globe! l 1KUN-5160A 125% Primary Containment Instrumnt Gas Ctatpressor A IOCA Suction Isolation Valve (2" Globe) 1KUN-5160B 119% Primary Containment Instrument Gas Otxtpressor B IDCA Suction Isolation Valve (2" Glche) l IKUIV-5162 177% Primary Containment Instrument Gas Ctatpressor B Suction Outboarti Isolation Valve (2" Globe) 1KUN-5172A 123% Primary Containment Instrument l Gas to Vacuum Bruaker Amm11ator A Suction Isolation Valve (2" Globe) 1KUN-5172B 128% Primary Containment Instrument Ces to Vacuum Breaker Ammilator B Suction Isolation Valve (2" Globo) 11 MSIV Steam Sealim System Valves VALVE NUMBER 711FUST MARGUI VALVE DESCRIPTION 1}G4N-5829A 506% Inboard Seal Gas Supply Header Shutoff Valve (2" Globe) 1KHN-5829B 506% Outboard Seal Gas Supply Hoader Shutoff Valve (2" Globe) 1KRN-5834A 593% Steam Line A Seal Gas Supply Inboard Isolation Valve (2" Glcbe)
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Table NLR-N94015 Changes to GL 89-10 Commitments l
l M. 331V Steam Scalim System Valves (Continued) i VALVE NUMBER 'I100ST MATODI VALVE DESGIPfION 1 m lV-5834B 593% Steam Lim A Seal Gas Supply outboard Isolation Valve (2" Globe) 1 E N-5835A 593% Steam Lim B Seal Gas Supply Inboard Isolation Valve (2" Globe) 1 m lV-5835B 593% Steam Line B Seal Gas Su@ly .
l Outboard Isolation Valve (2" Globe)
I m !V-5836A 581% Steam Line C Seal Gas Supply j Inboard Isolation Valve (2" l Globe) l l
1 m N-5836B 593% Steam Line C Seal Gas Supply l Outboard Isolation Valve (2" l Globe) 1 1 m lV-5837A 605% Steam Line D Seal Gas Supply Inboard Isolation Valve (2" Globe)
I mlV-5837B 593% Steam Line D Seal Gas Supply Outboard Isolation Valve (2" Globe)
N. Plant Lea}LDetection System Valves )
q 1SMIV-4953 118% Irak Detection Gas Sample Outboard Isolation Valve (2" j Glom) j 1
ISMN-4957 843% Isak Detection Gas Sanple Return Inboard Isolation Valve (2" Globe) 1SMIV-4981 910% Irak Detection Gas Sanple
]
Return Outboard Isolation Valve l (2" Globe)
ISMN-5018 97% Icak D3tection Gas Sample "
Inboard Isolation Valve (2" Globe)
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