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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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v 0- .
' s PubGc Service ,
Electric and Gas Cornpany E. C. Simpson Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Ser@ Vce President Nuclear Engineenng Mt l
l United States Nuclear Regulatory Commission ,
l Document Control Desk l Washington, DC 20555 Gentlemen:
RZPLY TO NOTICE OF VIOLATION INSPECTION REPORT NO. 50-354/96-09 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Pursuant to the provisions of 10CFR2.201, Public Service Electric and Gas Company (PSE&G) hereby submits a reply to notice of violation (NOV) issued to the Hope Creek Generating Station in a letter dated December 5, 1996. Per discussion between D. Smith of PSE&G and S. Barber of NRC Region I, a submittal date of January 10, 1997 was agreed upon based on late receipt of the violation by PSE&G. The i details of th'e reply are contained in the attachments to this letter.
This letter completes our response to the two Notices of Violation in the December 5, 1996 letter. Our other I response was dated December 26, 1996 and discusses Offsite Safety Review department concerns.
Should you have any questions or commente on this transmittal, do not hesitate to contact us.
Sincerely, fl l j,5 t
4 Attachments (2) 9701210144 970109 PDR ADOCK 05000354 G PDR
@ Printedon Recycled Paper
Document Control Desk JAN 0 91997 LR-N96436 C Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Jaffe, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. R. Summers USNRC Senior Resident Inspector (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 i Trenton, NJ 08625 l
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. . l l
T I J
l ATTACHMENT 1
- EMERGENCY DIESEL GENERATOR / FIRE SUPPRESSION SYSTEM INTERACTION l
INSPECTION REPORT NO. 50-354/96-09 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 LR-N96436 l I. DESCRIPTION OF VIOLATION the description of the violation contained in the notice of
- violation received in the December 5, 1996 letter is as follows
A. Violation B "10 CFR 50.59 requires, in part, that licensees maintain records of changes to the facility as described in the final safety analysis report (FSAR). These records must include a written safety evaluation which provides the bases for the determination that the changes do not involve an unreviewed safety question.
Contrary to the above, on October 29, 1996, the NRC determined that PSE&G had conducted a de facto change of the facility as described in the FSAR without a written safety evaluation which provided the bases that the change did not constitute an unreviewed safety question. This is evidenced by the following two examples where the facility design does not meet the FSAR description:
- 1. Section 8.1.4.14.1.3 of the FSAR states that "Non-Class .
1E circuits or equipment may be connected to Class 1E !
equipment or circuits by the use of approved qualified isolation devices to assure that, in the event of failure of the non-Class 1E equipment, the Class 1E 4 equipment will continue to perform its function."
i In the design of the Class 1E emergency diesel generator room ventilation system, PSE&G incorrectly used qualified isolation devices in non-Class 1E circuits and failed to assure that, in the event of a failure of these circuits, the Class 1E ventilation system could continue to perform its function.
- 2. Sections 1.8.1.53 and 8.1.4.10 of the FSAR requires compliance with IEEE 379-1972 and Sections 5.2 through 5.5 of IEEE 379-1977, respectively. IEEE 379 requires, in part, that single failure analyses of Class IE systems be preconditioned by the failures that non-Page 1 of 6
Att chm:nt 1 LR-N96436 Response to EDG/FSS Interaction Violation Class 1E systems--which are coupled in some manner to l the Class 1E systems--may cause.
l In their single failure analysis of the Class 1E emergency diesel generator room ventilation system,
- PSE&G failed to precondition it by the potential l failures of the non-Class 1E fire suppression system l with which it is coupled electrically and mechanically, i l thereby failing to recognize that the ventilation l system did not meet the single failure criterion.
l This is a Severity Level IV violation (Supplement I) . "
l l II. REPLY TO VIOLATION B l
l Pursuant to the provisions of 10CFR2.201, PSE&G hereby submits a written reply to the above notice of violation which includes the reason for the violation, the corrective steps that have been taken and the results achieved, the corrective steps that will be taken to avoid further violations, and the date when full compliance will be achieved. This information is provided as follows:
A. PSE&G Position PSE&G agrees with the violation.
B. Description of Event Inspection Report 354/96-03 identified a concern relative to l
the interaction between Hope Creek's Emergency Diesel Generators (EDGs) and the Fire Suppression Systems (FSS).
i Of specific concern is the effects of a postulated failure of the non-safety related fire suppression system on the i ability of the EDGs to perform their function. PSE&G responded to the concern in letter LR-N96296 dated October 4, 1996, stating that "the design of the EDG fire suppression system is adequate and no modifications to the system are necessary." The NRC has reviewed PSE&G's position and issued the above violation describing certain sections of the Hope Creek UFSAR which appear to be inconsistent with Hope Creek's as built configuration.
l C. Reason for the Violation a
Hope Creek's EDG/ Fire Suppression System Interaction Design The EDG Fire Suppression System is non-safety related and powered by non-Class 1E, UPS electrical power. The system is seismically installed. The EDG room ventilation system Page 2 of 6
. ~ . -_ . .- - - - . . -
, - - =. .- - - _ _ - -.
(
e Attachment 1 LR-N96436 Response to EDGIFSS Interaction Violation is safety related and powered by Class 1E electrical power.
The systems interact through the qualified 3ZZ relay which is a Class 1E isolation device powered by non-Class 1E, non UPS electrical power. The EDG room recirculation system is designed to recirculate the air in the EDG room. The EDG room recirculation system is interlocked to start with the respective EDG. The EDG Fire Suppression System and the EDG room ventilation system interaction is illustrated in Attachment 2.
Upon initiation of the Fire Suppression System, the non-Class 1E Fire Suppression System ES-1 contact closes, energizing the Class 1E 3ZZ relay. This 3ZZ contact in the EDG room ventilation recirculation fan circuitry trips the safety related EDG room recirculation fan. A signal from the non-Class 1E Fire Suppression System circuitry also provides power to electrothermal links which allow the EDG room ventilation mechanical fire dampers to close. This design assures proper concentration of carbon dioxide remains in the EDG room to suppress the fire. This interface is an approved exception to Standard Review Plan criteria which is described in UFSAR section 9.5.1.6.30.
Our letter dated October 4, 1996 describes the details of this exception.
In the event of a loss of voltage condition, when the EDGs are required to perform their function, the system is designed such that the non-Class 1E, non UPS backed 3ZZ relay could not energize and the fans would start to support EDG operation. A valid or invalid trip signal to the fans from the non-Class 1E fire suppression system would drop out ;
due to the 3ZZ relay losing power. As a result, the safety related recirculation fan is assured to operate and the Class 1E circuits are assured to continue to perform their function, j l
Hope Creek UFSAR section 8.1.4.14.1.3 states that non-Class )
1E circuits may be connected to Class 1E circuits by use of approved qualified isolation devices to assure that in the event of failure of non-Class 1E equipment, the Class 1E equipment will continue to perform its function. UFSAR Sections 1.8.1.53 and 8.1.4.10 discuss compliance with IEEE 379-1972 and Sections 5.2 through 5.5 of IEEE 379-1977, respectively. IEEE 379 discusses, in part, that single
, failure analyses of Class 1E systems be preconditioned by
! the failures that non-Class 1E systems--which are coupled in' some manner to the Class 1E systems-- may cause.
l l
Page 3 of 6
Attachment 1 LR-N96436 Response to EDG/FSS Interaction Violation As a result of the investigation of this design initiated by 1
this Notice of Violation, PSE&G has identified a design flaw. In the event of sustained degraded voltage from the non-Class 1E offsite power sources, the EDG is required to
- start and load to support plant safe shutdown. It can be postulated that if a fault develops in the non-Class 1E Fire
- Suppression System, the non-Class 1E degraded power can remain available to energize the 3ZZ relay. If not detected, this condition could prevent the fan from starting i
and thus impact continuous operation of the associated EDG
- per UFSAR section 9.4. 6.2. This situation was reported to the NRC in accordance with 10CFR50.72 (b) (1) (ii) (B) on January 3, 1997. A Licensee Event Report, in accordance
- with 10CFR50.73 will follow within 30 days.
For non-LOP (Loss of Power) conditions (i.e., Loss of Coolant Accident, manual initiation of Core Spray logic, I l manual initiation of the EDG), the EDGs receive a start signal. As discussed in UFSAR section 15.6.5.2.1.1, the
- EDGs remain idling unloaded in anticipation of a LOP. If a j LOP occurs, the same situations as above may occur. If no
. LOP occurs, the EDGs will operate potentially without-
- ventilation but no accident mitigation response is required.
i
- Response to Example 1 Section 8.1.4.14.1.3 of the FSAR states that "Non-Class 1E j circuits or equipment may be connected to Class 1E equipment or circuits by the use of approved qualified isolation devices to assure that, in the event of failure of the non-Class 1E equipment, the Class 1E equipment will continue to perform its function."
The function of the eight (two per EDG) independent safety related recirculation fans is to recirculate the air in the EDG rooms. The electrical interaction between the EDG room ventilation system and the Fire Suppression System does not meet the requirements of UFSAR Section 8.1.4.14.1.3 under degraded grid voltage conditions in that a fault in the non-Class 1E Fire Suppression System circuitry could prevent the function of the Class 1E EDG room ventilation recirculation fan.
1 Response to Example 2 Sections 1.8.1.53 and 8.1.4.10 of the UFSAR requires compliance with IEEE 379-1972 and revised Sections 5.2 through 5.5 of IEEE 379-1977, respectively. IEEE 379 requires, in part, "that single failure analyses of Class 1E systems be electrically preconditioned by the failures that i
l i
Page 4 of 6 ,
i
Attachment 1 LR-N96436 Response to EDG/FSS Interaction Violation non-Class 1E systems -- which are coupled in some manner to the Class 1E systems -- may cause."
At nope Creek, under loss of voltage conditions, the single failure of the Class 1E EDG room ventilation circuitry can be preconditioned by the failures that the non-Class 1E Fire Suppression System circuitry may cause. As discussed previously, a valid or invalid trip signal from the Fire Suppression System would trip the Class 1E EDG room ventilation fan through the approved qualified isolation device (3ZZ relay). However, upon a loss of voltage, the recirculation fan trip circuitry drops out and the Class 1E LOP sequencer starts the recirculation fan to support operability of the EDGs. Therefore, under loss of voltage conditions, the EDG room ventilation circuitry single failure can be preconditioned by the failures of the non-Class 1E fire suppression system circuitry and meets the single failure criterion.
I Under degraded grid voltage conditions, the single failure l of the Class 1E EDG room ventilation circuitry is not ,
preconditioned in that a failure of the non-Class 1E circuitry may cause the EDG room ventilation fans to de-energize. Under specific degraded grid conditions, the EDG would be required to start and load and it is postulated that the recirculation fan could be inhibited from starting.
Apparent Cause A 10CFR21 notification was issued on November 6, 1984 by the fire damper manufacturer (Ruskin), documenting the potential for fire dampers to inadequately close against normal ventilation system flow. The resolution of this generic ,
issue is discussed in UFSAR section 9.5.1.1.15.1, item 1. l The resolution of the Part 21 was a. design change implemented in October 1985 (prior to receipt of operating license) to install the 3ZZ relay to trip the EDG room recirculation fan upon Fire Suppression System initiation.
This fan trip assures closure of the fire dampers.
Although the design change appropriately considered loss of voltage, sustained undervoltage consistent with EDG design basis requirements was not appropriately considered. The non-Class 1E, non UPS power source supplied to the 3ZZ relay is de-energized upon detection of less than or equal to 90%
grid voltage by the non-Class 1E under voltage relays.
However, the Technical Specifications require the EDGs to start and load at less than 92% grid voltage. Additional information will be provided in the Licensee Event Report.
Page 5 of 6
l Attachment 1 LR-N96436 4 Response to EDG/FSS Interaction Violation l
D. Corrective Steps That Have Been Taken and Results Achieved ,
A temporary modification was implemented to disconnect the 3ZZ relay from the non-Class 1E Fire Suppression System circuit.
l l Fire watches were posted in accordance with the Hope Creek Fire Protection Program to compensate for the degraded fire protection system.
l E. Corrective Steps That Will Be Taken to Avoid Further Violations :
I Specific commitments to avoid further violations will be '
described in the Licensee Event Report to be issued by February 3, 1997.
F. Date When Full Compliance Will Be Achieved Partial compliance with Hope Creek's Design and Licensing l Bases was achieved when the 3ZZ relay was disconnected from the non-Class 1E Fire Suppression System circuit using a !
l temporary modification. Full compliance will be achieved l upon permanent resolution of the circuit interface concern.
Various options are under consideration. The options selected, including the implementation dates, will be described in the Licensee Event Report.
l l
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Page 6 of 6
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I ,
Attechment 2 LR-N96436 i Response to EDG/FSS Interaction Violation i
i
! EDG Room Ventilation System Class 1E/ Fire Suppression System i
non-Class lE Circuit Interaction 1 l l
1 rul-Class 16, LLPS j
- E S-1]r Fire Suppression i l I_ ._ .
ajs4ern C,ircuit l i
, rco-Class 1E con-tLPs 12cvAc Poteer CbSS 16 %uajded l
j s -- J i j 3E j Csolcdien dcv(ce f
I__ _
j i
.+.4 .,
i i
1 i.
EDG TCcrn 3E3 9ecirculoMcn Ventilokion ,
I Fan 1 1 CirouIh fan WTP circuit (Glass JE)
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