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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 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 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 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 ML20209C0621999-06-21021 June 1999 Forwards NPDES Discharge Monitoring Rept,May 1999, for Hcgs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection 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 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 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 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 ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML20207A3451999-05-20020 May 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs ML20195B9931999-05-20020 May 1999 Forwards NPDES Discharge Monitoring Rept,Apr 1999, for Hgcs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection 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 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 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 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 ML20209B6441999-06-21021 June 1999 Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01 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 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-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 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 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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H5391990-09-10010 September 1990 Forwards Data Re Bailey Solid State Logic Modules (Sslm) Reliability Program for Period Ending June 1990.Quarterly Summaries of Sslm Data Will Be Provided to End of June 1991 ML20059E6791990-09-0404 September 1990 Forwards Security Upgrade Project Status Rept,Per Regulatory Effectiveness Review.Rept Withheld (Ref 10CFR73.21) ML20059E6821990-09-0404 September 1990 Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld ML20059E7021990-08-30030 August 1990 Forwards RERR-9, Hope Creek Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Rev 11 to Odcm.Summary of Change to ODCM & Rationale Provided in Part G of RERR-9.W/o Rev 11 to ODCM ML20059D2531990-08-30030 August 1990 Forwards Hope Creek Generating Station Semiannual Radioactive Effluent Release Rept RERR-9 for Jan-June 1990 & Rev 11 to ODCM for Hope Creek Generating Station ML18095A4391990-08-29029 August 1990 Forwards Semiannual Rept Re fitness-for-duty Performance Data for 6-month Period Ending 900630,per 10CFR26.71(d).Rept Includes Testing Results,Random Testing Program Results & Confirmed Positive Tests for Specific Substances ML20059D2191990-08-27027 August 1990 Provides Change to Schedule for Implementing Generic Ltr 88-11.Revised pressure-temp Curves Will Be Submitted Prior to Completion of Second Refueling Outage.Existing pressure- Temp Curves Conservative to 32 EFPY ML20059D2491990-08-24024 August 1990 Requests Regional Waiver of Compliance from Tech Specs 4.0.3 & 4.8.1.1.2.f.2.Waiver Allows Sufficient Time to Perform Surveillance Requirement W/O Requiring Unit Shutdown.Request Involves No Irreversible Environ Consequencies ML20059C3051990-08-24024 August 1990 Notifies of Minor Structural Enhancements to Spent Fuel Racks Issued by Util 891101 Proposed Change to Tech Spec 5.6.3 ML18095A3861990-07-30030 July 1990 Forwards Listing of Station Blackout Major Audit Items Resolution Scope,Per Station Blackout Schedule Commitment ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML18095A3611990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML20055G1571990-07-17017 July 1990 Requests Waiver of Compliance from Tech Spec 6.3.1 Re Requirement That Facility General Manager (Gm) Hold Senior Operator License.Waiver Will Temporarily Allow Individual to Fill Position While Gm Attends off-site Mgt Program ML18095A3591990-07-13013 July 1990 Corrects Typo in 900702 Response to Generic Ltr 90-04 Re Schedule for Completion of Remaining Open Items ML20055G4721990-07-11011 July 1990 Requests Extension Until Sept 1990 to Submit Level 1 Analysis,Per Generic Ltr 88-20 Re Individual Plant Exam Completion ML20055E5181990-07-0303 July 1990 Suppls Request for Noncode Temporary Repair of Svc Water Sys.Ultrasonic Exam of Area Surrounding Patch Will Include Samples,In Accessible Areas,Out to Diameter of 14 Inches ML18095A3301990-07-0202 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues.Table Describing Status of Generic Safety Issue Implementation Encl ML18095A3231990-06-28028 June 1990 Responds to NRC 900518 Ltr Re Violations Noted in Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07.Two Noncited Violations Disputed.Util fitness-for-duty Program Exceeds Part 26 Requirements for Positive Blood Alcohol Limits ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout ML20055D0351990-06-26026 June 1990 Forwards Addl Info Re Svc Water Sys Noncode Temporary Repair,Per 900621 Application.Util Will Perform Ultrasonic Testing of Pipe Wall Adjacent to Fillet Weld Repair & on Patch.Insps Will Be Performed at 90-day Intervals ML20044A6251990-06-21021 June 1990 Requests Approval of Temporary Noncode Repair of ASME Code Class III Piping Flaw.Flaw Located in 30-inch Diameter Moderate Energy Svc Water Line.Svc Water Sys Will Be Evaluated for Other Flaws,Per Generic Ltr 90-05 ML20043F3301990-05-31031 May 1990 Advises That Contrary to 891223 Commitment,Testing Procedures to Demonstrate Full Safety Function Flow for Certain Check Valves Have Not Been Revised.Failure to Comply to Commitment Due to Administrative Error ML20043B3631990-05-22022 May 1990 Forwards Revised Response to Request for Addl Info Re Bailey Solid State Logic Module (Sslm) Reliability for 1988 & 1989. Criteria Used to Monitor & Trend Bailey Model 862 Sslm Failure Rates Described in 900419 Ltr Modified ML20043B7231990-05-21021 May 1990 Forwards Revised Page 8 to Semiannual Radioactive Effluent Release Rept Forwarded on 900228.LER Being Prepared to Provide Details Re Liquid Radioactive Effluent Release Monitor Out of Svc for Greater than 30 Days ML18095A2261990-05-16016 May 1990 Forwards 1989 Annual Financial Repts of Pse&G,Atlantic City Electric Co,Delmarva Power & Light Co & Philadelphia Electric Co ML20043A1221990-05-14014 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Mar 1990 Rept for Hope Creek Generating Station,Unit 1 ML20042G6521990-05-10010 May 1990 Forwards Attachment 1,Plan Figure 4i for Incorporation Into Security Plan,Per 900212 Commitment.Encl Withheld (Ref 10CFR73.21) ML20042F9131990-05-0404 May 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Overfill Protection for Steam Generators in PWRs & Reactor Vessels in Bwrs.Operability of Overfill Protection Sys Assured by Performing Channel Checks Every 12 H ML18094B4451990-04-30030 April 1990 Responds to 900404 Request Re Station Blackout.Licensee Presently Reconstituting Station Blackout Project Team in Order to Fully Assess Third Party Audit Findings & Establish Scope & Schedule for Rework Activities ML20042F1271990-04-30030 April 1990 Advises of Change to Licensing Basis Commitment Re High/Low Pressure Interface Valves,Per 10CFR50.59.Util Intends to Restore Electric Power to Solenoid Operated Pilot Valves Associated W/High/Low Pressure Interfacing Sys ML20042F1311990-04-27027 April 1990 Provides Required Certification for Rev 2 to Updated FSAR for Hope Creek Generating Station.Through Administrative Oversight,Std Affidavit Transmitted in Lieu of Required Certification ML18094B4271990-04-17017 April 1990 Forwards Policy Statement on fitness-for-duty,in Response to Insp Repts 50-272/90-10,30-311/90-10 & 50-354/90-07.Policy Statement Will Be Disseminated to All Site Personnel as Attachment to Paychecks & Included as Part of Bid Spec ML18094B4071990-04-0909 April 1990 Forwards Corrected Pages to Rept Entitled, Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemp'S Ridley & Loggerhead Sea Turtles. Addl Mitigating Measures Will Be Incorporated to Minimize Effects on Turtle Species ML18094B3881990-04-0404 April 1990 Forwards Annual Rept for 1989 & Summary of Owners 1990 Projected Internal Cash Flow Statements ML18094B3641990-03-20020 March 1990 Responds to Generic Ltr 89-19 Re Overfill Protection for Steam Generators in PWRs & Reactors in Bwrs.Overfill Protection Sys Sufficiently Separate from Control Sys & Not Powered from Same Power Source ML18094B4051990-03-20020 March 1990 Provides List of Sources & Amounts of Financial Protection Carried on Plants,Per 10CFR50.54(w) ML20012D1361990-03-0909 March 1990 Responds to NRC 900207 Ltr Re Violations Noted in Insp Rept 50-354/89-80.Corrective Actions:Periodic Mgt Evaluation of Procedure Writing Effort Will Be Conducted to Ensure That No Recurrence of Backlog Problems Occur ML20012B6391990-03-0808 March 1990 Provides Addl Info in Response to Generic Ltr 88-11 Re Radiation Embrittlement of Reactor Vessel Matls,Including Comparison of Irradiation Embrittlement Predictions of Reg Guide 1.99,Revs 1 & 2 for Plant ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML20006F3831990-02-16016 February 1990 Forwards 1989 Inservice Exam of Selected Class 1 & Class 2 Piping & Components at Hope Creek Generating Station & Sept/Oct 1989 Inservice Exam of Selected Class 1 & Class 2 Components at Hope Creek Generating Station. ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML20006B8721990-01-26026 January 1990 Forwards Progress Rept on Project to Upgrade Nuclear Site Physical Security Features.Encl Withheld (Ref 10CFR73.21) ML19354E7961990-01-19019 January 1990 Responds to NRC Bulletin 89-002 Re Anchor Darling Model S350W Swing Check Valves W/Type 410 Stainless Steel Internal Bolting.No Subj Anchor Darling Valves Installed at Facility. Valves of Similar Design Installed at Facility ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid ML19332F3601989-12-0707 December 1989 Provides Clarification on Status of Rev 9 to Facility Odcm. Rev 10 Superceeds Rev 9 to ODCM Per 890320 Approval 1990-09-04
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Putsic Serece O PS G Company Sectnc and Gas 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulatirn September 12, 1984 i
Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention: Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 EMERGENCY PLAN Public Service' Electric and Gas Company (PSE&G) hereby submits the resolution (Attachment 1) to the Emergency Pre-parednoss concerns discussed on September 5, 1984, as indi-cated in the attachment. Also submitted are fif teen (15) sets of Revision 4 to the Hope Creek Generating Station Emergency Plan (Attachment 2). In accordance with 10 CFR 2.101(a)(4) and 10 CFR 50.30(c)(1), three (3) signed originals of the required af fidavit are enclosed.
If you have any questions on the subject filing, do not hesitate to contact us.
/
Very truly yours, I
Attachment 1 - Resolution of HCGS Emergency Plan Questions Attachment 2 - Fifteen (15) sets of Revision 4 to the HCGS Emergency Plan C D. H. Wagner USNRC Licensing Project Manager (w/ Attach. 1)
W. H. Bateman USNRC Senior Resident Inspector (w/ Attach. 1) f Ok g(
The Energy People %fMhk F
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UNITED STATES OF AMERICA NUCLEAR'~ REGULATORY COMMISSION DOCKET NO. 50-354 e
PUBLIC SERVICE ELECTRIC AND GAS COMPANY EMERGENCY PREPAREDNESS COMMITMENTS AND HOPE CREEK EMERGENCY PLAN REVISIONS Public Service Electric and Gas Company .hereby submits as the resolution ( Attachment 1) to Emergency Preparedness concerns discussed on September 5,1984, as indica ted in the
- attachment. Also submitted are fifteen (15) sets of Revi-
'sion 4 Lto the Hope Creek Generating Station Emergency Plan
-( Attachment 2) - necessary to resolve these items.
Respectfully submitted, Public Service Electric and Gas Company I
By ^% /4/ gw V Thompf J '. Martin VicVPresident -
p Engineering and Construction b
Sworn -to and-' subscribed bef ore me , a Notary Public of New Jersey this /ZZ22' day of . September 1984.
DAYl0~K. BURD
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.NOTARYPUBUC OF NEW JERSEY lly Comm. Empires 10-23 85 i
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ATTACHMENT 1
RESOLUTION OF HOPE CREEK GENERATING STATION EMERGENCY PLAN OUESTIONS This submittal incorporates PSE&G's resolution to areas of concern ' expressed during the September 5, 1984, discussion between Messrs. D. Wagner and D. Perrotti, Nuclear Regulatory Commission and Messrs. P. Moeller, J. MacKinnon, B.
Preston, C. Adams and S. LaBrunna, PSE&G.
As outlined in our September 5, 1984, discussion, the follow-ing commitments and/or changes are provided as listed below.
Areas of concern are highlighted with answers immediately following.
'1. The off-site plans must be - updated with regard to the support and integrated emergency response related to HCGS.
Letters have been sent (enclosure 1) to the Director of the Delaware Department of Public Safety, Division of Emergency Planning and Operations and the Director of the New Jersey State Police, Office of Emergency Management requesting that the state, county and local municipality emergency response plans be revised as necessary to indicate the support to be provided for the Hope Creek Generating Station Emergency Plan. Further, Public Service Electric and Gas will monitor, support and aid the states as necessary in the timely completion of these revisions.
- 2. Clarify all references to the " Emergency Coordinator."
As submitted in Emergency Plan (EP) revisions in Attachment 2, the definition of emergency coordinator in Section 1,Pages 1.3 and 1.4 of the EP, was revised and references to the emergency coordinator in Section 3, Pages 3.3, 3.8, 3.10, and 3.12 and Section 4, Pages 4.2 and 4.3 were clarified as discussed.
- 3. Clarify the interrelationships between PSEEG, Salem County and the Township of Lower Alloways Creek.
The memorandum of understanding for Lower Alloways Creek (LAC) was removed from the Emergency Plan attachments.
This was done with the understanding that LTC will function as outlined in the New Jersey emergency plans.
- 4. Additional information is required on the variance of the 30- and 60-minute augmentation times based on notification and travel times.
Section.3, Page 3.34 of the EP was revised to indicate the staffing goals outlined in Supplement 1 of NUREG-0737.
'5. Provide a description of the steps to be taken to ensure that key functions are performed in the interim time period while augmentation personnel are being notified or in' transit.
On-site ' staffing will provide sufficient numbers of trained-personnel to perform essential functic s during augmentation times.
- 6. Identify the principal PSEEG spokesperson and alter-nates.
'Section.3, Pages 3.9 and 3.29 of the EP, was revised to appropriately identify the individual and alternates assigned the responsibility of . principal media spokesperson.
.7. Update Figure 4-1 ' and Attachment 4-1 with respect to HCGS.
Section 4, Figure 4-1 and: Attachment 4-1 of the EP have been revised.
- 8. Additional information is needed regarding the NRC Region I capabilities, including resources and expected arrival time.
Fede ral response information is supplied in Section 1, Page 1.8 of the EP.
- 9. Update and revise, as discussed previously, Figures 6-4, 6-5 and 6-6.
Revisions to Section 6, Figures 6-4, 6-5 and 6-6 of the EP are provided in Attachment 2.
- 10. Describe the procedures for alerting, notifying and mobilizing PSEEG personnel on site, and notifying site emergency response personnel at home during off-normal
. hours.
Revisions to Section 6, Page 6.1 of the EP have included an' overview of this information.
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11; . Provide additional information regarding the aspect of
. coordinating planning efforts with off-site authorities to ensure - that ' the administrative and physical capa--
bility will exist to make prompt protective action deci-sions for rapidly developing emergency situations especially during off-normal hours.
-Section 17, Page 17.1 of the EP, has been revised to include the -responsibility land commitment to maintain a continued coordination effort between PSE&G- and its support organizations as necessary to maintain the ability to perform decision-making in rapidly developing situations.
- 12. Provide for a communication test with all szates within the ingestion EPZ on a quarterly basis.
Section 15, Page 15.3 and Table 15-1 of the EP, has been revised to include this testing.
- 13. Provide a copy .of all informational material to be disseminated to permanent residents and transients for staff review.
A copy of ' the information disseminated to permanent residents. and transients in the Salem Generating Station Plume Exposure Emergency Planning Zone (same as Hope Creek) is provided as enclosure 2. This information is only a sample.- Appropriate information, to include Boiling Water Reactor information, will be adapted to these brochures and provided to the local population as outlined in Section 8 of the EP.
- 14. The Plan should be updated with regard to the support and resources to be provided by the Salem Generating Station,! including seismic and hydrologic data.
Section. 9 of the EP will be revised to include this
- information in October of 1984.
- 15. Describe the provision for transportation of
~
and alternate evacuation routes for on-site personnel.
Section ll, Page 11.2 of the EP, has been revised to include an overview of this information with reference to the specific. emergency plan procedures providing guidance for these' actions.
__ - . _ - ,. . _ - ~ _ _ _ _ _ _ . . _ . - _ _ _ _ - . _ _ -
.16. Incorporate Table 12-2 into the Plan.
Table 12-2 was incorporated into Section 12 of the EP.
- 17. Medical Support A. Provide letters of agreement with local ambulance squads.
This information is included in the emergency plan -
ning statues ' for the State of New Jersey and our letters of agreement with the Salem County Office of Emergency Management.
B. Provide for inventory and inspection of equipment stored at SMH.
Section 13, Page 13.2 of the EP was revised to includa this provision.
C. Include a map showing directions to the hospital in the Plan and implementing procedure (s).
Section 13, Page 13.2 of the EP was revised to i reference this information in Figure 4-1. Procedure I-5, Personnel Emergency, will be developed to include an appropriate map.
D. Submit the Salem Memorial Hospital Radiation Emergency Plan for review.
A copy of the Salem Memorial Hospital Radiation Emergency Plan is provided as enclosure 3.
- 18. Define the mechanism for informing members of the response organizations (including those of PSEEG) that a recovery operation is to be initiated or of' any organizational changes that may occur.
Section 14, Page 14.2 of the EP, has been revised to describe the mechanism for informing company members and key personnel of. support organizations of operational plans to initiate recovery actions.
- 19. Identify in the Plan and submit for staff review, the Recovery Management Plan or equivalent plan and/or procedure that will ensure the necessary coordination and interface with and between site, corporate, local, and state plans and procedures.
1 1
PSE&G's unique organizational structure allows the Nuclear Department to exist as an individual portion of the ' Company. This ability to maintain engineering, design, procurement and all associated support functions at the facility site would preclude the necessity to maintain special corporate plans for continuing this type of support.
~
- 20. Provide a description of the station emergency vehicle, equipment provided for and its use, including the condi-tions under which this vehicle would be used for trans-porting injured / contaminated persons to the hospital.
Equipment located on the vehicle should be included in the quarterly inventory and operability test as is scheduled for other emergency kits.
Reference to use of the emergency vehicle for ambulance support was improperly included in the EP. Section 15, Page 15.3 of the EP, has been revised, removing this reference. Injured / contaminated individuals will only be transported in a station ambulance or local support ambulance. All equipment maintained for emergency support will be inventoried at least quarterly as discussed in Section 9 of the EP.
- 21. Describe the training to be provided for personnel in the protected area who are not badged for unescorted access to the protected area (e.g., visitors, vendors and contractors).
A copy of the emergency information provided to person-nel in the protected area who are not badged for unescorted access is provided as enclosure 4.
- 22. Incorporate Table III-1 into the Plan.
References to Table IIl-1 have been revised as indicated in Paragraph 23, below.
- 23. Provide readable copies of Figures 3-2 and 3-3 in the Plan.
Figures 3-1, 3-2 and 3-3 have beer edited and revised to improve readability and correct references.
- 24. Provide for training. and retraining of Civil Defense /
Emergency personnel, headquarters support personnel and local law enforcement personnel.
Sectica 16, Page 16.4 of the EP, has been revised to discuss the training of off-site state and local emergency respcnse personnel.
- 25. Describe the components of the Emergency Plan Manual as referred to in Section 17.0 of the Plan.
Section 17, Pages 17.1, 17.2 and 17.3 of the EP has been revised to remove and/or clarify the use of the term
" manual."
- 26. Provide emergency classification method which includes emergency action levels (EAL) for all applicable initi-ating condtions included in NUREG-0654, Rev. 1, Appendix 1.
Section 5 of the EP commits to the completion of the Event Classification Guide in December 1984. The Event Classification Guide will provide Emergency Action Levels (EAL) for all initiating conditions, as applicable, included in NUREG-0654, Rev. 1, Appendix 1.
Two sample Draft EAL's are provided as enclosure 5.
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ENCLOSURE 1 1
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1PSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bndge New Jersey 08038 Nuclear Depadment September 10, 1984 EP-84-066 Major Harold E. Spedding Office of Emergency Management P.O. Box 7068 West Trenton, NJ 08625
Dear Harold:
PSE&G is currently well into the emergency preparedness planning process for the Hope Creek Generating Station which is expected to begin commercial operation in January 1986. We have submitted an initial station plan to the Nuclear Regulatory Commission for review and evaluation.
To support the Hope Creek licensing schedule, a revision to the New Jersey state plan, to incorporate Hope Creek, will be needed. We request a review and revision of your state, county and municipal plans to ensure a consistent basis of operations. My staff has made a detailed review of the state plan and discussions of the modifications have been held with your staff. Support for plan revisions will be provided by my staff.
If you have any questions concerning this matter, please feel free to contact me. As always, your cooperation is appreciated.
Sincerely, P. A. Moeller Manager -
Nuclear Site Protection The Energy Peopk-v,v e man
4PSEG Pubhc Serwce Electric and Gas Company P O. Box 236 Hancocks Bndge, New Jersey 08038 Nuclear Depa"" ent September 10, 1984 EP-84-067 Mr. Clarke V. Jester, Director Division of Emergency Planning & Operations P.O. Box C Delaware City, DE 19706
Dear Clarke:
PSE&G is currently well into the emergency preparedness planning process for the Hope Creek Generating Station which is expected to begin commercial operation in January 1986. We have submitted an initial station plan to the Nuclear Regulatory Commission for review and evaluation.
To support the Hope Creek licensing schedule, a revision to the Delaware state plan, to incorporate Hope Creek, will be needed. We request a review and revision of your state and county plans to ensure
. consistent basis of operations.
Discussions staff. of the modifications have been held with your staff. Support for plan revisions will be provided by my If you have any questions concerning this matter, please feel free to contact me. As always, your cooperation is appreciated.
Sincerely, P. A. Moeller Manager -
Nuclear Site Protection The Energy Pegm 9'3 2 t fJ4 4 2*/A f, c4 5*
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ENCLOSURE 2 1
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- Additional Information Request
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sgT AeoeEss if you would like additional information, have TELEPHONE NUMBER questions or have identified on area of public concern that has not been addressed, please fill out and mail in Area of interest the ottoched card. We will provide to you the infor-motion you request. Your request will also help us update this brochure.
If you have specific needs, fill out and mail this card.
Farmer's Information Request vEs NO I am hard of hearing O O l l farm in the region around the Salem Station. Please i om viselly impaired o o forward the special booklet outlining protective ' * 'h*'*' * d i ' *d actions that I might have to take if a major emergency develops at the plant. i ouio neeo t,ansportation a a I would like to recewe an advisor radio O O Other special needs (explain)
NAME ADDRESS NAME ADORESS TELEPHONE NUMBER TELEPHONE NUMBER
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- Farmer's Informat. ion -----.--
Director ------- --------
- P. O. Box 570 ,,. - - - - ,
Division of Emergency Planning - -
--===== Newark' NJ 07101
& Operations -------- -
P. O. Box C ------- Attn: Emergency Preparedness --------
Delaware C.ty, i DE 19706 - Nuclear Department -
- MC-150 _-
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g)gg{ _% Additional information Request NAMe ADDRESS _
If you would like additional information, have ,,,,,,,,,yy,,,
questions or have identified on area of public concern that has not been addressed, please fill out and mail in Area of interest the attached card. We will provide to you the infor-motion you request. Your request will also help us update this brochure.
If you have specific needs, fill out and mail this card.
Farmer's information Request ytS NO I am hard of hearing O O I farm in the region around the Salem Station. Please i om visually impaired O O forward the special booklet outlining protective 1 om otherwise disabled actions that I might have to take if a major emergency develops at the plant. I would need transportation O O 1 would like to receive an advisor radio O O other specia, needs (explain) _
NAME NAME ADDRESS TELEPHONE NUVBER TELEPHONE NUMBER
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09'96900-o3 DCd ~DY
l ENCLOSURE 3 L ----