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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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Pubhc Serwce Electric and Gas Company Louis F. Storz Publ<c Service Electric and Gas Company P O. Box 236 Hancocks Brdge, NJ 08038 6090345700
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DEC 011995 '
LR-N95202 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REPLY TO A NOTICE OF VIOLATION OFFICE OF INVESTIGATIONS REPORT 1-94-048 HOPE CREEK GENERATING STATION I FACILITY OPERATING LICENSE NPF-57 )
ROCKET NO. 50-354 l l
Pursuant to the provisions of 10CFR2.201, this letter submits the response of Public Service Electric and Gas Company to the notice of violation issued to the Hope Creek Generating Station in a letter dated September 19, 1995. In addition, the response to Violation B also supersedes letter LR-N95034, which was transmitted on April 3, 1995.
Should you have any questions or comments on this transmittal, do I not hesitate to contact us. l 1
Sincerely, l C 1 f)%0 ,eerd < c l
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Attachment b 7.)[] [j
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h I [ d Pape, 9512070028 951201 PDR ADOCK 05000354 '
-Q PDR ,
DEC 011995 i
. Document Control Desk LR-N95202 C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Jaffe, Licensing Froject Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 14E21 11555 Rockville Pike Rockville, MD 20852 Mr. R. Summers USNRC Senior Resident Inspector (X24)
Mr. K. Tosch, Manager IV N. J. Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 j
a .
d l
l ATTACHMENT i
k i REPLY TO NOTICE OF VIOLATION i OFFICE OF INVESTIGATIONS REPORT 1-94-048
! HOPE CREEK GENERATING STATION
! DOCKET NO. 50-354 LR-N95202 f I. INTRODUCTION j
! The NRC Office of Investigation conducted an investigation l concerning findings set forth in a PSE&G internal investigation report issued on October 11, 1994, and'in a j Licensee Event Report (LER), dated October 14, 1994. As a i result of this investigation, the NRC issued a notice of i violation citing two violations of NRC requirements in a letter dated September 19, 1995.
j In accordance with the provisions of 10CFR2.201, Public
} Service Electric and Gas Company hereby submits a written
- response to the notice of violation which' includes for each a violation
- (1) the reason for the violation; (2) the 2 corrective steps that have been taken and the results i achieved; (3) the corrective steps that will be taken to i avoid further violations; and (4) the date when full
- - compliance will be achieved.
l A. Violation A
- 1. Descriotion of the Notice of Violation
" Technical Specification 6.2.2.b requires that a Senior Reactor Operator (SRO) be in the control room during Operational Conditions 1, 2, or 3.
Contrary to the above, on June 3, 1992, from 1:38 pm until 1:41 pm, while the reactor was in Operational Condition 1, there was no SRO in the control room.
This is a Severity Level IV violation (Supplement 1)."
1 OF 9
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1 . Attachment LR-N95202
- Reply to Notice of Violation
- 2. Rosconse to Notice of Violation PSE&G does not dispute the violation,
- i. Descrintion of Event On June 3, 1992, at 1338 hours0.0155 days <br />0.372 hours <br />0.00221 weeks <br />5.09109e-4 months <br />, the Nuclear Shift Supervisor (NSS) who had assumed the command and
, control role left the control room. The Senior Nuclear Shift Supervisor (SNSS) had previously turned over to :
the NSS to attend a department staff meeting. Some time after the SNSS had left the control room, a problem was brought to the attention of the NSS regarding control room chillers. The NSS decided to go :
to the chillers, and contacted the Shift Technical l Advisor (STA - SRO licensed) to discuss the problem and to be relieved. Following this discussion, the NSS walked into the rear of the control room area to get l his hard hat and safety gear while the STA returned to the work control office. Both individuals believed the 1 other was to remain in the control room; the NSS believed he had turned over command and control while the STA believed the turnover was yet to occur. The two individuals left from different doors that are not ;
visible from each other. The on duty Nuclear Control ;
Operator and a Quality Assurance engineer who were in ;
the control room realized that no SRO was present and l paged the STA. The STA returned to the control room )
within three minutes of the time he exited, i'
- 11. Reason for Violation )
This event was attributed to personnel error on the part of the NSS who left the control room after assuming command and control, i l
iii. Corrective Steos That Have Been Taken and Results l Achieved l l
Command and control turnover process expectations have been reinforced with the SRO's involved in the event as well as with the other SRO's.
A mechanical restraint on the SRO's identification photo badge is being utilized as an additional barrier to prevent inadvertent recurrence.
The individuals involved in this incident have been disciplined.
2 OF 9 i
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. Attachment LR-N95202 Reply to Notice of Violation iv. Corrective Steos that will be Taken to Avoid Further violations All Corrective Actions are stated in LER 354/94-013 and are complete.
- v. Date When Full Comoliance Will Be Achieved Based on the completion of the corrective steps listed above and in LER 354/94-013, full compliance has been ,
achieved.
B. Violation B
- 1. Description of the Notice of Violation "10CFR50.73 (a) (2) (i) (B) requires that the licensee submit a Licensee Event Report (LER) within 30 days after discovery of any event involving any operation or condition prohibited by Technical Specifications.
Technical Specification 6.2.2.b requires that a Senior Reactor Operator be in the control room during Operational Conditions 1, 2, or 3.
I Contrary to the above, on June 3, 1992, from 1:38 pm until 1:41 pm, while the reactor was in Operational Condition 1, there was no SRO in the control room, a condition contrary to the Technical Specifications, which was discovered by the on-duty Senior Nuclear Shift Supervisor on June 3, 1992, and this event was not reported to the NRC in an LER until October 14, 1994.
This is a Severity Level IV violation (Supplement 1)."
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Attachment LR-N95202 Reply to Notice of Violation
- 2. Resoonse to Notice of Violation PSE&G does not dispute the violation.
- i. Descriotion of Event Subsequent to the event discussed in Violation A, the SNSS, NSS, and STA discussed the fact that for a period of approximately three minutes (2 minutes, 56 seconds) no SRO was in the control room and recognized that a noncompliance with the administrative section of Technical Specifications had occurred. The SNSS discussed the matter with a QA Engineer and inappropriately decided not to file an incident report.
The SNSS has explained that when the incident occurred, he did not give it proper consideration. He has also explained that, at the time, he incorrectly minimized the safety significance of the event and allowed that to influence his decision not to report the incident.
As a. result, he failed to fulfill his obligation as the on-duty SNSS to report the event, which then led to PSE&G's failure to file the required LER in a timely manner.
1 ii. Reason for Violation Personnel error on the part of the SNSS, NSS, STA, and QA Engineer resulted in a missed LER. PSE&G has previously investigated the issue of whether the SNSS knew at the time of the event that an incident report was required to be filed. These investigations into the SNSS's knowledge in 1992 yielded inconsistent conclusions. The Company's initial investigation suggested that the SNSS was aware of the reporting requirement. The report of this initial investigation was provided to and discussed with the NRC in October, 1994.
The report's conclusion was later determined by PSE&G l to have an insufficient basis. In the company's April 1 3, 1995 report (letter LR-N95034) to the NRC concerning this matter, PSE&G indicated that due to the absence of conclusive evidence, it had not found that the SNSS was aware at the time of the event that an incident report was required to be prepared.
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b
, Attachment LR-N95202 Reply to Notice of Violation A recent review and assessment of the Company's earlier investigations identified weaknesses in the approach that was utilized to formulate the final conclusion communicated in the April 3, 1995 report. The recent review and assessment also concluded that these weaknesses led to subjective conclusions in the Company's follow-up investigation, which was further hampered by the passage of time since the occurrence.
As a result, this violation response, which contains the Company's final position on the issue, supersedes letter LR-N95034, which was transmitted on April 3, 1995.
PSE&G management realizes that all of the facts relative to the June 3, 1992, Hope Creek Control Room Staffing incident cannot be completely reconstructed because of the elapsed time and the varied investigations. Therefore, due to the fact that the SNSS has not disputed the NRC's conclusion that he was aware an incident report was required, combined with the weaknesses in the approach to the previous investigations, the following represents PSE&G's final position:
1 The SRO's discussed whether an incident report was required and concluded not to file an incident report in violation of station procedures.
Statements in the Report by Winston and Strawn, dated October 11, 1994, that individuals knew, in 1992, that an incident report was required were
-conclusions reached indirectly through the interview process. Nevertheless, such statements are believed to be true.
. While the administrative procedure was not explicit for requiring an incident report for noncompliance with the administrative section of i Technical Specifications, the SRO's and the QA Engineer exhibited poor judgment in determining that this event should not be raised to management's attention. The administrative i procedure has been revised to assure the required j clarity, and site-wide training and communication of management expectations for initiating corrective action documents has been completed.
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4 Attachment LR-N95202 l Reply to Notice of Violation The (Ni Engineer compromised independent QA oversight by failing to assure that the absence of an SRO in the Hope Creek Control Room was reported, and by failing to adequately inform his supervisor of the incident.
Due to the number of investigations performed to date, with varied results, no further discipline has been initiated for the four individuals involved in the manning incident. However, each individual will receive formal feedback regarding the Company's final position on the event.
.iii. Corrective Steos That Have Been Taken and Results-Achieved An LER was promptly issued to the NRC when management became aware of the issue.
Additional training has been provided to appropriate personnel on the reporting requirements of 10CFR50.73 and NUREG-1022.
As stated in the letter transmitted on April 3, 1995, the individuals involved in this incident have been disciplined and remediated and have completed the following Remediation Plan:
They each submitted a written response to the investigation report that focused on their role in-the incident. Preparing these responses helped the individuals to gain a better understanding of the issues surrounding this incident.
They met with the Station Operations Review Committee, the Licensing Manager, the General Manager - Hope Creek Operations, the Hope Creek Operations Manager, the Manager - Station Quality Assurance - Hope Creek, and the Nuclear Safety Review Manager. The purpose of these meetings was for the individuals to gain a broader perspective and deeper level of understanding of their actions and the impact they had. The individuals documented the key lessons learned in a )
Remediation Plan document. l l
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- j. Attachment . .
LR-N95202 j j Reply to Notice of Violation j
. Corrective action recommendations that generally i focused on the command and control process, l training enhancements, and the root causes of this '
- incident were included as part of the Remediation Plan.
1
- The individuals interviewed with senior management.
to ensure that they were ready to return to work.
The remediation was determined to be successful.
i i- The individuals have complied with the Remediation Plan and were returned to their normal duties.
- Management's expectations for initiating incident reports were clarified and communicated both to the
' personnel involved in this incident and other
- applicable Nuclear Business Unit (NBU) personnel.
- i j The NBU has developed and implemented a new Corrective Action Program (CAP) to ensure timely problem identification and resolution. As part of the
- development of the CAP, the NBU benchmarked several other utility's programs that have been successfully
- consolidated.
2 i The CAP has consolidated and improved previously existing programs within the NBU. The program includes
. a low threshold for reporting problems, provides for
- aggressive problem assessment and root cause determination, and establishes management controls on completion schedules for specified corrective actions.
The CAP includes a graded approach to root cause
, determination based on significance level. The CAP
- j. also requires timely completion of cause determination.
, Accountability for CAP implementation rests with station line management. As such, station managers are responsible to ensure cause determinations are appropriately thorough, including the designation of corrective actions to address root and contributing causes. The Director - Quality Assurance / Nuclear Safety Review has oversight responsibility for the CAP and has established dedicated resources under the Manager - Corrective Action and Quality Services, to fulfill that responsibility. Measures have also been established to monitor the performance of the corrective action process. These include performance indicators and monthly reports to senior management.
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F .
2 Attachment LR-N95202
' Reply to Notice of Violation The Company has undertaken a review of its investigation process and has made changes that have improved its quality and effectiveness, including the formation of an Employee Concerns Group that has been given the responsibility to conduct this type of investigation. Significant investigations that are conducted by the Employee Concerns Group require a charter that is approved by a member of Senior Management. The charter includes an identification of the issue to be resolved, a proposed approach, and a timetable. Interviews are conducted in a structured manner, and include a way of recording the interview.
For these significant investigations, the interviewees review the record of the interview and are given an opportunity to provide corrections and additional information. This record is used to formulate the conclusions of the investigation. This structured approach minimizes the possibility of introducing uncertainty regarding "what was said" following the completion of the investigation.
iv . Corrective Steos that will be Taken to Avoid Further Violations As stated in part (iii) above, the Company implemented an aggressive corrective action and Remediation Plan, including appropriate discipline of the SNSS, NSS, STA, and QA Engineer. These actions have been successfully completed and are considered to be sufficient to' avoid !
further violations.
The recently completed assessment of the Company's ,
earlier investigations has been reviewed to determine l additional corrective actions. Corrective actions i include counseling or discipline for the individuals !
involved in the conduct of the Company's follow-up l investigation; feedback to the individuals involved in l the original manning incident regarding the Company's l final position on the event; and a review of lessons learned to identify any additional improvements in the investigation process.
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a
. Attachment LR-N95202
. Reply to Notice of Violation
- v. Date When Full Comoliance Will Be Achieved
- . All actions that are required to achieve full
. compliance are stated in LER 354/94-013 and are '
complete. Based on the completion of the Remediation Plans and the return of the individuals to their normal duties, full compliance has been achieved.
The actions identified as a result.of the recently completed assessment of the Company's earlier investigations, identified in part (iv) above.are in-the process of being completed.
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