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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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- O PSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuci0ar Business Unit OCT 2 91998 LR-N98511 LCR H97-10 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen
TRANSMITTAL OF GENERAL ELECTRIC REPORTS NEDC-32511P AND NEDO-32511 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 This !siter provides the Public Service Electric & Gas Company response to a Scptember 29,1998, NRC letter concerning PSE&G License Change Request (LCR)
H97-10, which was transmitted to the NRC on April 28,1998, via letter LR-N97117.
LCR H97-10 requested, in part, a revision to the Safety Relief Valve (SRV) tolerance acceptance limits contained in the Technical Specifications.
In the September 29* letter, the NRC requested that the proprietary information annotations contained in General Electric report NEDC-32511P be re-evaluated, and that a non-proprietary version of the report be provided to the NRC to allow for proper docketing of this information. In response to this request, PSE&G is providing the attached General Electric affidavit for the revised proprietary report, a new proprietary version of report NEDC-32511P, and a non-proprietary version of the same General Electric report (NEDO-32511).
The only changes contained in the attached proprietary General Electric report are associated with the revised proprietary annotations.
I in accordance with 10CFR50.91(b)(1), a copy of this submittal has been sent to the State of New Jersey. J
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-ATTACHMENT 2 OF THIS DOCUMENT CONTAINS PROPRIETARY INFORMATION-
- NOT FOR PUBLIC DISCLOSURE -
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LR-N98511 l l Should you have any questions regarding this request, please contact James Priest at 609-339-5434.
l
! Sincerely, i WY D. R. Powell Director- Licensing / Regulation & Fuels l
Attachments (3) l C Mr. H. Miller, Administrator - Region I i U. S. Nuclear Regulatory Commission l 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis l Licensing Project Manager- Hope Creek l U. S. Nuclear Regulatory Commission l
- One White Flint North Mail Stop 14E21 11555 Rockville Pike Rockville, MD 20852 Mr. S. Pindale (X24)
USNRC Senior Resident inspector- HC l Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 l
-ATTACHMENT 2 OF THIS DOCUMENT CONTAINS PROPRIETARY INFORMATION-
- NOT FOR PUBLIC DISCLOSURE -
I l
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- GENERAL ELECTRIC AFFIDAVIT FOR REPORT NEDC-32511P 1
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General Electric Company ,
AFFIDAVIT I, George B. Stramback, being duly sworn, depose and state as follows:
(1) I am Project Manager, Regulatory Services, General Electric Company ("GE") and have been delegated the function of reviewing the information described ~ in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in the GE proprietary report NEDC-32511P, Safety Review for Hope Creek Generating Station Safety / Relief Valve Tolerance Analyses, Revision 1, Class III (GE Proprietary Information), dated l October 1996. The proprietary information is delineated by bold brackets around the
! specific material.
l (3) In making this application for withholding of proprietary information of which it is the owner, GE relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act,18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), 2.790(a)(4), and 2.790(d)(1) for " trade secrets and commercial or financial information obtained from
! a person and privileged or confidential" (Exemption 4). The material for which exemption from disclosure is here sought is all " confidential commercial information", and some portions also qualify under the narrower definition of" trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Enercy Project v. Nuclear Regulatory Commission. 975F2d871 (DC Cir.1992), and Public Citizen Health Research Groun
- v. FDA,704F2dl280 (DC Cir.1983).
-(4) Some examples of categories of information which fit into the definition of
, proprietary information are:
i l
l a. Information that discloses a process, method, or apparatus, including supporting i
data and analyses, where prevention ofits use by General Electric's competitors without license from General Electric constitutes a competitive economic advantage over other companies; 1
- b. Information which, if used by a competitor, would reduce his expenditure of
- resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; i
GBS-98-6-afhopeereek_srv_ tolerance 2. doc Affidavit Page 1
- c. Information which reveals cost or price information, production capacities, budget levels, or commercial strategies of General Electric, its customers, or its
- suppliers; L
L d. Information which reveals aspects of past, present, or future General Electric customer-funded development plans and programs, of potential commercial value to General Electric; i- e. Information which discloses patentable subject matter for which it may be
! desirable to obtain patent protection.
i The information sought to be withheld is considered to be proprietary for the reasons set forth in both paragraphs (4)a. and (4)b., above.
l l (5) The information sought to be withheld is being submitted to NRC in confidence. ,
l The information is of a sort customarily held in confidence by GE, and is in fact so I held. The information sought to be withheld has, to the best of my knowledge and I belief, consistently been held in confidence by GE, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties 1 including any required transmittals to NRC, have been made, or must be made, )
pursuant to regulatory provisions or proprietary agreements which provide for !
maintenance of the information in confidence. Its initial designation as proprietary -
information, and the subsequent steps taken to prevent its unauthorized disclosure, )
are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of i
the originating component, the person most likely to be acquainted with the value
- and sensitivity of the information in relation to industry knowledge. Access to such l documents within GE is limited on a "need to know" basis.
I (7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and l by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GE are limited to
- regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in l
accordance with appropriate regulatory provisions or proprietary agreements.
l (8) The information identified in paragraph (2), above, is classified as proprietary because it contains detailed results of analytical models, methods and processes, L including computer codes, which GE has developed, obtained NRC approval of, and applied to perform evaluations of the loss-of-coolant accident for the BWR.
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l The development and approval of the BWR loss-of-coolant accident analysis l computer codes used in this analysis was achieved at a significant cost, on the order of several million dollars, to GE.-
The development of the evaluation process along with the interpretation and i application of the analytical results is derived from the extensive experience database that constitutes a major GE asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GE's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GE's comprehensive-BWR safety and technology base, and its ccmmercial value extends beyond the-original development cost. The value of the technology base goes beyond the extensive physical database and analytical m thodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GE.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GE's competitive advantage will be lost ifits competitors are able to use the results of the GE experience to normalize or verify their own process or if they are able to l
claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GE would be lost if the information were disclosed to the public. Making such information available to competitors without their L having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GE of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing these very valuable analytical tools.
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_ Affidavit Page 3 1
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v v,
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STATE OF CALIFORNIA )
) ss: l COUNTY OF SANTA CLARA - ) !
l George B. Stramback, being duly sworn, deposes and says: )
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l That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief.
1 Executed at San Jose, California, this /1 day of r[441 1998.
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441) 0 . '
'" Gedge B. Str'amback '
General Electric Company I
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l Subscribed and sworn before me this dayof hadokr 1998.
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'*A A A A A a a b Qp PAULA F. HUSSEY v &dSa>A lE NotoY SANTA CLARA COUNTY mnio Notary Public, State of Califop E
{ My Comm. Expires DEC 1,1998
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Attachm:nt 3 LR-N98511 l
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l i GENERAL ELECTRIC REPORT NEDO-32511 1
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