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| ~ I Public Service Electric and Gas Company Harold W. Keiser Public Service Electric and Gas Company PO. Box 236, Hancocks Bridge, NJ 08038 609-339-11 oo Chief Nuclear Officer & President . . | | ~ I Public Service Electric and Gas Company Harold W. Keiser Public Service Electric and Gas Company PO. Box 236, Hancocks Bridge, NJ 08038 609-339-11 oo Chief Nuclear Officer & President . . |
| Nuclear Business Unit JUN 171999 LR-N980287 Mr. H. J. Miller Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Rd. | | Nuclear Business Unit JUN 171999 LR-N980287 Mr. H. J. Miller Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Rd. |
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| Mr. H. J. Miller 2 JUN 171998 LR-N980287 As part of this overall SRP, PSE&G established the Management Review Committee. | | Mr. H. J. Miller 2 JUN 171998 LR-N980287 As part of this overall SRP, PSE&G established the Management Review Committee. |
| (MRC). The MRC was established as an oversight committee to review amongst other things the restart action plans (RAPs), and the System Readiness Review Program (SRRP). The RAPs were developed to address the major areas described above and the identified root and contributing causes for their deficiencies. The root and contributing causes identified and addressed by the RAP were the causes, which led to the decline in performance and eventual shutdown of the Salem Units. The SRRP provided PSE&G with reasonable assurance that equipment operability and reliability issues had been identified, and that effective corrective actions had been taken. This* | | (MRC). The MRC was established as an oversight committee to review amongst other things the restart action plans (RAPs), and the System Readiness Review Program (SRRP). The RAPs were developed to address the major areas described above and the identified root and contributing causes for their deficiencies. The root and contributing causes identified and addressed by the RAP were the causes, which led to the decline in performance and eventual shutdown of the Salem Units. The SRRP provided PSE&G with reasonable assurance that equipment operability and reliability issues had been identified, and that effective corrective actions had been taken. This* |
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| JUN 1 7 1998 Mr. H. J. Miller 3 LR-NS80287 In addition, test procedures were improved, test set-ups and sequencing of activities were better controlled, planning was more complete and experienced test engineers applied their knowledge, which resulted in fewer tests and test procedures to test the same functions. This outcome, in itself, was very positive. | | JUN 1 7 1998 Mr. H. J. Miller 3 LR-NS80287 In addition, test procedures were improved, test set-ups and sequencing of activities were better controlled, planning was more complete and experienced test engineers applied their knowledge, which resulted in fewer tests and test procedures to test the same functions. This outcome, in itself, was very positive. |
| Another way to measure the success of the Unit 1 startup is to compar~ the efficient use of time and resources during the two restarts. The following table provides such a comparison: | | Another way to measure the success of the Unit 1 startup is to compar~ the efficient use of time and resources during the two restarts. The following table provides such a comparison: |
Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 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 ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 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 ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 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 IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for 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 ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 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 ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 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 ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 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 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 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 ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments 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 ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE 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 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses 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 ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 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 ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) 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 ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 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 ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 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 ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 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 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML18107A4181999-06-30030 June 1999 Submits Response 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 ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments 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 ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE 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 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal 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 ML18107A1981999-04-12012 April 1999 Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202 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 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 ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) 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 1999-09-08
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~ I Public Service Electric and Gas Company Harold W. Keiser Public Service Electric and Gas Company PO. Box 236, Hancocks Bridge, NJ 08038 609-339-11 oo Chief Nuclear Officer & President . .
Nuclear Business Unit JUN 171999 LR-N980287 Mr. H. J. Miller Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Rd.
King of Prussia, PA 19406
Dear Mr. Miller:
REQUEST TO RELEASE PUBLIC SERVICE ELECTRIC AND GAS FROM THE REQUIREMENTS OF CONFIRMATOR;f ACTION LETTER (CAL-1-95-009) FOR SALEM GENERATING STATION NOs 1and2 FACILITY OPERATING LICENSES DPR-70 and DPR-75 .
DOCKET NOS. 50-272 and 50-311 On June 9, 1995, the Nuclear Regulatory Commission (NRG) issued a Confirmatory Action Letter (CAL) for Salem Units 1 and 2. Since this date, Public Service Electric &
Gas (PSE&G) has taken the required actions and provid_ed information concerning these actions via letters dated June 27, 1997 and March 23, 1998, for Units 2 and 1 respectively. Accordingly, NRG responded by modifying the CAL via letters dated August 6, 1997 (Unit 2 restart) and April 1, 1998 (Unit 1 restart).
With the April 1, 1998 letter, the NRC modified CAL 1-95-009 to permit the restart of Salem Unit 1. NRC also requested PSE&G to provide a summary of our operating and testing experience, and an evaluation of our overall restart plan, including any lessons learned. PSE&G hereby provides the requested information and respectfully requests that it be released from the requirements of CAL 1-95-009 for Salem Units 1 and 2.
Following the May/June 1995 shutdown of both Salem Units and the issuance of the CAL, PSE&G conducted a comprehensive review (self-assessment) of our operational readiness. This review led to the development of the Salem Restart Plan (SRP). The SRP consisted ofa comprehensive and systematic approach for the identification, review, approval, assessment and affirmation of the activities needed to support the restart and reliable operation of the Salem Units. The SRP contained three major sections; (1) Plant, People and Process Improvements, (2) Restart Readiness Review and Affirmation, and (3) Startup and Power Ascension Testing. /l /
/ .) IQ
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9806290129 980617 PDR ADOCK 05000272 p P.DR
Mr. H. J. Miller 2 JUN 171998 LR-N980287 As part of this overall SRP, PSE&G established the Management Review Committee.
(MRC). The MRC was established as an oversight committee to review amongst other things the restart action plans (RAPs), and the System Readiness Review Program (SRRP). The RAPs were developed to address the major areas described above and the identified root and contributing causes for their deficiencies. The root and contributing causes identified and addressed by the RAP were the causes, which led to the decline in performance and eventual shutdown of the Salem Units. The SRRP provided PSE&G with reasonable assurance that equipment operability and reliability issues had been identified, and that effective corrective actions had been taken. This*
was accomplished by a methodical review of selected systems. These systems were selected on the basis of a combination of attributes such as safe shutdown risk, risk significance, and historical power reduction and high incidence of corrective maintenance. The SRP and its associated RAPs and SRRP were considered living documents/programs. As PSE&G moved forward with the restart process, the SRP was revised (e.g., the Operations and Maintenance interventions) to ensure that PSE&G accomplished the goals necessary to allow for a safe and event free restart of .
the Salem Units.
In summary, the successful implementation of the Salem Restart Plan in conjunction with other activities, such as the closure of all NRC restart items, led PSE&G to request the NRC to begin its Readiness Assessment Team Inspections (RATI). These inspections independently concluded that PSE&G was ready to proceed with the restart of the Salem Units and embarked on the last portion of the SRP; the Startup and Power Ascension Testing. Modifying the CAL via letters dated August 6, 1997 (Unit 2 restart) and April 1, 1998 (Unit 1 restart) provided this concurrence.
- At the MRC of June 15, 1998, departmental affirmations were completed establishing the readiness of the Salem management team to support the safe and reliable operation on the Salem Units. In essence, this affirmation signaled the completion of the startup and testing of the Salem Units 1 and 2.
The Startup and Power Ascension Program for the Salem units was originally developed as a part of the PSE&G Restart Plan. The successful restart of both Units demonstrated that the SRP was successful in improving our plant, process and people.
The lessons learned from the Unit 2 startup were captured and used to improve the startup and testing for Unit 1. For example, Unit 2 problem equipment was fixed on Unit 1 and the scheduled was adjusted to do complex tasks first. As a result of better test planning, coordination between departments no major test delays were encountered during the Unit 1 startup.
95-4933
JUN 1 7 1998 Mr. H. J. Miller 3 LR-NS80287 In addition, test procedures were improved, test set-ups and sequencing of activities were better controlled, planning was more complete and experienced test engineers applied their knowledge, which resulted in fewer tests and test procedures to test the same functions. This outcome, in itself, was very positive.
Another way to measure the success of the Unit 1 startup is to compar~ the efficient use of time and resources during the two restarts. The following table provides such a comparison:
UNIT2 Unit 1 UNIT 1 vs.
STARTUP STARTUP Unit2 Day of Activity . Day of Activity Startup Days Event Startup Davs Days 1 Entered Mode 6 1 5 Fuel Load Complete 4 11 Entered Mode 5 11 175 Entered Mode 4 60 194 45 Entered Mode 3 87 21 -24 239 8 Entered Mode 2 108 5 -3 247 5 Entered Mode 1 113 3 -2 252 3 Reactor Power at 116 4 1 25%
255 9 Reactor Power at 120 4 -5 47%
264 8 ADFCS 10% Load 124 6 -2 Swing Performed 272 3 Reactor Power at 13.0 3 0 90%
275 - Reactor Power at 133 - -
100%
81 Total Mode 3 to 1 46 -35 However, since the Unit 2 startup was delayed by several unscheduled activities (e.g.,
installation of the containment fan coil unit (CFCU) modification), the comparison can best be measured by evaluating the timeframe from Mode 3 to 100 percent power (i.e.,
below the heavy black line). As the table shows for this period, the Unit 2 startup took 81 days, while the Unit 1 startup took only 46 days. This difference represents a 43%
reduction in the startup time for Unit 1, an accomplishment even more significant since it also included testing of the new steam generators.
95-4933
- if JUN 171998 Mr. H. J. Mil.ler 4 LR-N~80287 Again, this comparison demonstrates how better teamwork has resulted in greater schedule adherence and more efficient use of organizational resources.
In summary, the Unit 1 startup demonstrated that the Nuclear Business Unit (NBU) has successfully integrated plant, people and process to assure safe, and reliable operation of our nuclear plants.
Attachment 1 to this letter contains a detailed comparison of the two unit startups.
As we move into the future, PSE&G acknowledges that there are a number of areas requiring further management attention. Reducing the Maintenance and Engineering Backlogs, and fully implementing the Workweek Management process are areas where additional management focus is needed. Currently, plans are in place to .
implement the same model to reduce the maintenance backlog that was used for Hope Creek. The engineering backlog will be reduced utilizing both internal and external resources. The plans to reduce the backlogs are either in place or being developed and will be initiated during the remainder of 1998. PSE&G expects that several
- operating cycles will be needed to achieve their full effect.
In conclusion, PSE&G is committed to operating its nuclear plants safely and reliably.
Our goal is to become a top quartile performer. A strong foundation has.been established to achieve this goal; however, we must continue to improve our .
performance to maintain pace with today's increasing industry standards and competitive challenges. In particular, we need to continue to improve our quality of work and ensure that our operational decisions are conservative. We recognize that the nuclear environment requires people to work to increasingly higher standards.
PSE&G leadership strives not only to meet these standards but exceed them in our daily work practices.
Based on the discussion above and the information contained in Attachment 1, PSE&G firmly believes that it has demonstrated its ability to safely and reliably operate all of its nuclear units. Therefore, PSE&G respectfully requests that it be released from the requirements of CAL 1-95-009 for Salem Units 1 and 2.
If you have any concerns regarding this submittal, please contact us.
Sincerely,
~~/~fo 95.4933
e
' i JUN 1 7 1998 Mr. H. J. Miller 5 LR-N9Bo2a1 C U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Mr. P. Milano, Licensing Project Manager- Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. S. Morris (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4933