Similar Documents at Salem |
---|
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 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 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 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 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. 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 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 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 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 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 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
[Table view] Category:UTILITY TO NRC
MONTHYEARML18095A4881990-09-17017 September 1990 Requests Regional Waiver of Compliance from Tech Spec 3.6.2.3, Containment Cooling Sys. Waiver Requested in Order to Allow Replacement of Containment Fan Cooler Unit Motor #22 W/O Requiring Plant Shutdown ML18095A4901990-09-13013 September 1990 Provides Supplemental Info Applicable to Clarification of 10CFR50,App R Exemption Request Re Fire Suppression Sys for Panel 335,per NRC Request ML20059E6821990-09-0404 September 1990 Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld ML18095A4641990-08-31031 August 1990 Forwards Revised Response to NRC Bulletin 88-004 Re Potential pump-to-pump Interaction.Util Pursuing Permanent Solution to Issue & Will Implement Appropriate Permanent Field Change by End of Unit 1 10th Refueling Outage ML18095A4621990-08-31031 August 1990 Provides Revised Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Only HXs Exhibiting Unsatisfactory Test Results Will Be Inspected & Possibly Cleaned ML18095A4431990-08-30030 August 1990 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Rev 6 to Odcm. ML18095A4531990-08-30030 August 1990 Forwards RERR-28, Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revised Odcm.W/O Revised ODCM 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 ML18095A4421990-08-28028 August 1990 Clarifies 900710 Request for Amends to Licenses DPR-70 & DPR-75,changing Sections I & M.Under Proposed Change,Section I Should Be Changed to Read Section 2.J for License DPR-70 & Section M Changed to Read Section 2.N for License DPR-75 ML20059B6611990-08-22022 August 1990 Confirms That 10 Anchor/Darling Model S350W Swing Check Valves Installed at Plant,Per NRC Bulletin 89-002.All 18 Valves Inspected & Retaining Block Studs Replaced W/Upgraded Matl.No Crack Noted on Any Studs Which Were Replaced ML20059C2861990-08-21021 August 1990 Provides Correction to 900810 Response to Request for Addl Info Re Util Request for Restatement of OL Expiration Dates ML18095A4151990-08-10010 August 1990 Forwards Response to Request for Addl Info Re Reinstatement of OL Expiration Dates Based on Original Issuance of Ols. Advises That Correct Expiration Date for OL Proposed to Be 200418 ML18095A4091990-08-0909 August 1990 Forwards Responses to NRC Comments Re Plant Simulator Certification for 10CFR55.45(b)(2),per 891228 Ltr ML18095A4061990-08-0808 August 1990 Forwards Corrected marked-up Pages for Tech Spec Table 3.3-11 Re Subcooling Margin Monitor & Reactor Vessel Level Instrumentation Sys,Per 900223 Ltr.Administrative Changes Made as Indicated 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 ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML18095A3751990-07-18018 July 1990 Provides Status of Commitments Made to NRC by Util in 900109 Ltr Re NUREG-0737,Item II.D.1,per 900628 Telcon ML18095A3741990-07-18018 July 1990 Provides Supplemental Info Re Facility sub-cooling Margin Monitor ML18095A3611990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML18095A3621990-07-18018 July 1990 Forwards Corrected Tech Spec Page 3/4 3-5 for License Change Request 89-12 Submitted on 891227 & 900521 ML18095A3591990-07-13013 July 1990 Corrects Typo in 900702 Response to Generic Ltr 90-04 Re Schedule for Completion of Remaining Open Items ML18095A3471990-07-11011 July 1990 Responds to NRC 900611 Ltr Re Violations Noted in Insp Repts 50-272/90-14 & 50-311/90-14.Corrective Actions:Directive from Radiation Protection Mgt to All Radiation Protection Personnel Issued Re Control of Compliance Agreement Sheets ML18095A3451990-07-10010 July 1990 Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation ML18095A3461990-07-10010 July 1990 Responds to NRC 900608 Ltr Re Violations Noted in Insp Repts 50-272/90-12 & 50-311/90-12.Corrective Actions:Assessment of ECCS & Component Performance Undertaken & ECCS Flow Testing Procedure Upgraded to Address Human Factors ML18095A3491990-07-10010 July 1990 Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002 ML18095A3481990-07-10010 July 1990 Submits Supplemental Rept Identifying Root Cause of Missed Commitment & Corrective Actions to Assure Future Compliance Re Implementation of Mods to Facility PASS ML18095A3441990-07-0909 July 1990 Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification ML18095A3281990-07-0202 July 1990 Responds to NRC 900530 Ltr Re Violations Noted in Insp Repts 50-272/90-09 & 50-311/90-09.Corrective Actions:Util Intends to Use Nuclear Shift Supervisor as Procedure Reader & EOP, Rev 2 Under Development 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 ML18095A3391990-06-29029 June 1990 Forwards Correction to 890913 License Change Request 88-09, Consisting of Tech Spec Page 3/4 4-13 ML18095A3221990-06-28028 June 1990 Provides Supplemental Info Re 900223 Proposed Revs to Tech Specs for Reactor Vessel Level Instrumentation Sys.Tables 3.3-11a & 3.3-11b Should Be Combined Into Single Table 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 ML18095A3241990-06-28028 June 1990 Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout ML18095A3161990-06-25025 June 1990 Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613 ML18095A3141990-06-25025 June 1990 Provides Schedule Change for Implementation of Control Room Mods.Schedule Modified to Address Overhead Annunciator Human Engineering Discrepancies During Phase III ML18095A3201990-06-25025 June 1990 Responds to NRC 900524 Ltr Re Violations Noted in Insp Repts 50-272/90-11 & 50-311/90-11.Corrective Actions:All Overdue Operations & Maint Procedure Files Reviewed for Outstanding Rev Requests & Procedure Upgrade Program Initiated ML18095A3001990-06-20020 June 1990 Provides Addl Info Re Application for Amend to Licenses DPR-70 & DPR-75 Concerning Turbine Valve Surveillance Interval,Per 900320 Request.Util Adding Direction to Personnel If Unnacceptable Flaws Found ML20043H6221990-06-20020 June 1990 Provides Supplemental Info Re NRC Bulletin 88-008 for Fifth Refueling Outage.Detailed Test Rept Being Prepared to Document Results of Each Individual Insp Re Insulation, Hangers & High Energy Break Areas ML18095A2991990-06-20020 June 1990 Forwards Westinghouse Affidavit Supporting 900412 Request for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790 ML18095A2721990-06-0808 June 1990 Responds to NRC 900329 Ltr Re Weaknesses Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Corrective Actions:Fire Doors Placed on Blanket Preventive Maint Work Order & Damaged Fire Doors Will Be Repaired Immediately ML18095A2711990-06-0606 June 1990 Submits Info in Support of 900522 Verbal Request for Relief from Requirements of ASME Section XI ML18095A2611990-06-0101 June 1990 Forwards Corrected Operating Data Rept, Page for Apr 1990 Monthly Operating Rept ML18095A2521990-06-0101 June 1990 Forwards Application in Support of Request for Renewal of NJPDES Permit NJ0005622,per Requirements of Subsection 3.2 of Plant Environ Protection Plan,Nonradiological ML18095A2591990-06-0101 June 1990 Forwards Corrected Unit Shutdown & Power Reductions, Page for Apr 1990 Monthly Operating Rept ML18095A2411990-05-30030 May 1990 Submits Special Rept 90-4 Addressing Steam Generator Tube Plugged During Fifth Refueling Outage.Plugging Completed on 900516.Cause of Tube Degradation Attributed to Normal Wear Due to Erosion/Corrosion Factors ML18095A2431990-05-30030 May 1990 Informs of Util Plans Re Facility Cycle 6 Reload Core, Expected to Achieve Burnup of 16600 Mwd/Mtu.All Postulated Events within Allowable Limits Based on Review of Basis of Cycle 6 Reload Analysis & Westinghouse SER ML18095A2531990-05-29029 May 1990 Provides Addl Info Re End of Life Moderator Temp Coefficient.Feedback Used in Steam Line Break Has No Relationship to Full Power Moderator Density Coefficient 1990-09-04
[Table view] |
Text
Public Service Electric and Gas Company
- Stanley LaBruna Public Service Electric and Gas Company P.O. Box 2'36, Hancocks Bridge, NJ 08038 609-339-4800 Vice President
-Nuclear Operations SEP 0, 6 1989 NLR-N89176
- United States Nuclear Regulatory Commission Document Control Desk Washington DC 20555 Gentlemen:
RESPONSE TO NOTICE OF VIOLATION NRC COMBINED INSPECTION REPORT NO. 50-272/89-15 AND 50-311/89-14 SALEM GENERATING STATION UNITS NOS. 1 AND 2 DOCKET NOS_. 50-272 AND 50-311 Public Service Electric and Gas Company (PSE&G) has received the subject inspection report dated August 4, 1989, which included a Notice of Violation concerning procedures not properly being implemented and surveillance requirements not being performed within the specified time interval.
Pursuant to the requirements of 10 CFR 2.201, our response to this Notice of Violation is provided in the attachment to this letter. Should you have any questions in regards to this transmittal, do not hesitate to call. Sincerely, Attachment
?ii '\'
- Document Control Desk NLR-N89176 . C Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector 2 Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
- ATTACHMENT Notice of Violation.
Item A Technical Specification 6.8.1 requires that procedures be implemented, including general plant operating procedures, procedures for calibration of safety related equipment and radiation protection procedures.
Contrary to the above, procedures were not properly implemented as follows: 1. On June 3, 1989, control rods were withdrawn with one source range channel inoperable contrary to the requirements of Integrated Operating Procedure 3, "Hot Standby to Minimum Load" and Operating Procedure 8.3.1, "Rod Control System -Normal Operation" which specify that two source range channels are required to be operable prior to energizing the Rod control System and closing the reactor trip breakers.
- 2. On June 3, 1989, two control rod shutdown banks were withdrawn together contrary to the requirements of Maintenance
-I&C procedure IC-8.1.002, "Rod Position Indication Signal Module Calibration" which specifies that one control or shutdown bank be withdrawn at a time. 3. On May 23, 1989, a High Radiation Area (HRA) where radiation levels exceeded 1 R/hr was left uncontrolled for a 10 minute period contrary to the requirements of radiation protection procedure RP-204 which specifies that continuous
- surveillance be provided for unlocked HRAs. RESPONSE PSE&G DOES NOT DISPUTE THE VIOLATION THE ROOT CAUSE FOR EACH ITEM HAS BEEN ATTRIBUTED TO PERSONNEL ERROR. ITEMS 1 AND 2 As discussed in the LERs which reported these events, a portion of the root cause was determined to be inadequate administrative controls in that operators were unfamiliar with a recently issued License Amendment aff ectinq one of these sections of the Technical Specifications.
Licensed Operators are directed and expected to consider Technical Specification applicability prior to conducting operational evolutions.
The failure to follow specific requirements of written procedures for two operable source range channels and for control bank removal are personnel errors. Contributing factors to the personnel errors were the fact that the procedures involved were less than optimum from a human factors standpoint and that the process for Technical
- Specification Amendment implementation did not specifically require notification of each Licensed Operator of changes. CORRECTIVE ACTIONS TAKEN Procedures IC-8.1.002, "Rod Position Indication Signal Module Calibration", and IC-5.2.001, "Rod Drop Time Measurement Hot Full Flow", for both units, have been amended to include a precautionary note immediately before the step specifying rod bank withdrawal.
Procedure OP IV-8.3.1 has been revised to include a check-off-sheet addressing the requirements for energizing the Control Rods. The check-off-sheet provides a check to assure that both* source range channels are operable prior to energizing the control rods. The events were reviewed with the appropriate station personnel stressing the need for full procedural compliance to all parts of the procedures.
An "Information Directive" has been Licensed Operators, identifying all Technical Specification Amendments, Operators are aware of the changes. process will continue to be used to of recent Amendments
- issued to all recently approved to assure that the The Information Directive notify Licensed Operators The Station Operations Review Committee (SORC) will approve all Technical Specification Amendments for implementation after ensuring that all required training and procedural modifications necessitated by the Amendment are properly implemented.
ADDITIONAL CORRECTIVE ACTIONS TO BE TAKEN TO AVOID FURTHER VIOLATIONS Presentations by the General Manager -Salem Operations and training sessions are being conducted to introduce the new "Salem Handbook of Standards".
Each Salem employee will receive their own copy of the handbook at these sessions.
This handbook includes standards for work practices and use of written instruction.
A training video, "Attention to Detail", has also been developed to provide direction to station personnel on proper attention to detail attributes.
station personnel will receive the training by September, 1989. PSE&G is continuing to stress procedural compliance with all station personnel.
The need to read and comply with procedure prerequisites and other requirements has been discussed with Operations' personnel during pre-shift briefings and will continue to be stressed in these discussions throughout the year. . .. . . -. . . . .* . . . : .. *-... -*
- A review of the Technical Specification Amendment implementation process has been initiated to ensure that the appropriate delineation of responsibility, the appropriate direction for procedural changes and the necessary information/training for appropriate station personnel is provided for. The recommended changes and improvements resulting from this review will be incorporated into AP-12, Procedure NA-AP.ZZ-0012(Q) "Technical Specification Surveillance Program" by November, 1989. ITEM 3 Procedures RP-203, "Radiation Protection Key Control" and RP-204 "Posting of Radiation Signs and Barriers" require that unlocked High Radiation Areas (HRAs) have continuous surveillance where the dose rates can exceed 1 R/hr. The contract technician failure to adequately control the HRA was a result of personnel error due to lack of attention to detail. The open door was discovered by the Radiation Protection Manager, who was performing supervisory rounds. These supervisory rounds had been increased prior to this event in an effort to more effectively monitor personnel performance, assure more effective management oversight and ensure personnel attention to detail. CORRECTIVE ACTION TAKEN A guard (cognizant Radiation Protection person) was immediately posted at the entrance to the HRA, to provide the required continuous surveillance
- A "night order" was immediately written to all Radiation Protection Technicians to specify the requirements for entry to the eves Holdup Tank Room. The night order stated that two people are required to enter the eves Holdup Tank Room, one to provide positive access control and the other to perform the necessary surveys. The event has been reviewed by the Radiation Protection Department Management and appropriate corrective disciplinary action has been administered to the contract employee.
The event was reviewed with appropriate Radiation Protection Personnel.
A work request was written requesting the replacement of a lockset on the gate at the entrance to the eves Holdup Tank Room. The previous lockset did not work properly and a padlock and chain were being used to control access. Subsequently, a new lockset was installed.
This lockset provides positive control of the HRA while also allowing egress from the area; thereby, negating the need for the the night order specified above *
- PSE&G IS IN FULL COMPLIANCE Notice of Violation.
Item B B. Technical Specification (TS) 4.0.2 requires in part that surveillance requirements should be performed within the specified time interval.
Contrary to the above, surveillance requirements were not performed within the specified time interval as follows: 1. On February 21, 1989, it was identified that TS surveillance 4.0.5 for inservice inspection and testing of the lA Diesel Generator Service Water Valve and Prelube Oil Pump vibration check were not performed within the previous 92 days as required.
- 2. On May 5, 1989, it was identified that TS surveillance 4.3.3.3.1 for channel check of the Triaxial Time-History Accelographs was not performed within the previous 31 days as required.
RESPONSE PSE&G DOES NOT DISPUTE THIS VIOLATION The root cause of Item 1 has been attributed to lack of adequate administrative controls and the root cause of Item 2 has been attributed to personnel error as discussed in the respective LERs reporting these items. In addition to the violation cited above, the inspection report delineates a concern that corrective actions for a previous similar violation (in 1988) did not prevent these recurrences.
Corrective actions implemented as a result of the previous violation included assignment of a Technical Specification Administrator, establishment of a MMIS surveillance data base and generation of surveillance status reports. Those corrective actions have reduced the occurrence of missed/overdue surveillances since that violation.
As a.result of the above violations and feedback from the program administrators, PSE&G has instituted additional corrective actions as described herein, to strengthen the program and provide backup review. ITEM 1 CORRECTIVE ACTIONS TAKEN The February 21, 1989 event was, in fact, attributable to the lack of adequate administrative controls of the program established .following the 1988 violation.
- As a result, the following actions were implemented to enhance the effectiveness of the program. -. * *' * '
., '* *** '* * **-.-*" °! * *
- The frequency of the MMIS Technical Specification surveillance overdue report was increased, and is now printed daily at the line printer located in each department.
This report provides a 14 day "look ahead" listing of surveillances, with a greater than seven (7) day frequency, that will become overdue with the next fourteen (14) days and have not yet been completed.
The report is sorted by Unit, Department, Mode in which the surveillance can be performed, and overdue date. Each Department appointed a surveillance coordinator who is responsible to review the Technical Specification Overdue report daily, contact the line supervision if a surveillance is nearing (within 3-4 days) the overdue date, and to provide a single point of contact for the Technical Specification Administrator.
ITEM 2 The Mays, *1989 event was the result of personnel error (failure to follow the established program) in that the Technical Specification Overdue Report was not reviewed by the appropriate personnel as required.
PSE&G believes that this does not represent a programmatic deficiency of the corrective actions implemented following the 1988 violation.
CORRECTIVE ACTIONS TAKEN All appropriate Station Personnel were counseled to review and use the Technical Specification Surveillance Overdue report for tracking and completion of all Technical Specification surveillance requirements.
As a backup, the Technical Specification Administrator was also assigned the responsibility of reviewing the Technical Specification Surveillance Overdue report daily and contacting the department coordinators when any surveillance is not completed within 3-4 days of the overdue date. The Technical Specification Overdue report was revised, to provide the Modes of operation the equipment was required to be operable in, and to list all surveillances in order by overdue date. These changes were made for human factors reasons; i.e., to provide ease of review. In summary, PSE&G believes that Salem currently has an effective Technical Specification Administrative program. The additional actions stated above will further assure that TS surveillances are properly performed.
Corrective actions taken will prevent recurrence of the problems associated with this violation.
' "': * * *' :: *.L * * **: -.. *-. --. . . .. -. .. . , -. . -... '
- ADDITIONAL CORRECTIVE ACTIONS TO BE TAKEN TO AVOID FURTHER VIOLATIONS Increased management attention has been and will continue to be focused on this area. Programmatic changes will be made as necessary to enhance and solidify the Technical Specification Administrative Program as feedback is received from users or potential problem areas are identified.
PSE&G IS IN FULL COMPLIANCE SUPPLEMENTAL INFORMATION The following represents information relative to a missed surveillance occurring after issuance of Inspection Report 272/89-15
& 311/89-14, and is being provided pursuant with discussions held with Salem Resident Inspector, s. Pindale. Additionally, as required by the letter transmitting the subject Inspection Report, a discussion is being provided relative to corrective actions being taken to prevent recurrence of missed surveillances
The missed surveillance was identified by a Technical Department engineer when reviewing an Amendment change in response to an Action Tracking System (ATS) open item. The root cause of the event was determined to be inadequate administrative control of Technical Specification Amendment processing and implementation, which allowed the Amendment to be implemented with insufficient review. A recent Technical Specification Amendment (No. 94) had been implemented which had added the requirement to vent ECCS pump casings and accessible discharge piping high points to the Unit 1 surveillance Requirements (Unit 2 already had this requirement).
The Amendment was implemented without assuring that a thorough review had been performed to ensure that all necessary procedures had been implemented.
Personnel error contributed to the event, as the individual responsible for reviewing the ATS open item (which required reviewing the Technical Specification Amendment for procedural modifications) had not performed a thorough review of the Amendment prior to implementation
- . -. :*** .. ' _,... * ......... : .. -**: . .*** .. -, ..... **:--........ .
- I_ Weaknesses in the Technical Specification Amendment implementation program had been identified by the Technical Specification Surveillance Group (originated to eliminate missed/overdue Technical Specification Surveillances at Salem) in conjunction with other station personnelo Corrective actions were instituted as a result of these identified weaknesses.
These actions changed the program to require all new Amendments to be approved for implementation by SORC. This ensures that all departments are prepared to implement the programmatic or procedural changes necessitated by the Amendment.
In addition, ths program was revised to require computerized tracking (using ATS) to identify personnel responsibilities for the implementation of Technical Specification Amendments.
These processes were put in place at the direction of the General Manager -Salem Operations.
The draft revision of AP-12, Procedure NA-AP.ZZ-0012, "Technical Specification Surveillance Program", which will specify these changes, is now in the review process. At the time that Amendment 94 was received the corrective actions, mentioned above, were not in place. Had the corrective actions (SORC review and a designated individual for tracking ATS open items associated with Amendments) been in place when Amendment 94 was received, this event would have been prevented.
There is no safety impact associated with missing this surveillance.
There was no previous requirement to vent the pumps and the pumps have been proven operable repeatedly, by surveillance and use, over that duration.
The Technical Specification change is really an enhancement to provide further assurance that the pumps will perform as required when called upon. Fifty five (55) minutes after Technical Specification Action Statement 3.0.3 was entered for the missed surveillance, the surveillance was successfully completed.
In addition to the corrective actions that had been previously instituted, the individual involved was counseled stressing the need to ensure attention to detailo The Operations Surveillance Procedure SP(O) 4o5.2b was revised to include the pump casing and piping venting requirements.
PSE&G management is committed to ensuring that the Salem Generating Stations Surveillance Program provides the necessary controls and monitoring to assure that Technical Specifications are performed as requiredQ The current program is significantly improved and PSE&G is confident that the program is now effective in controlling the surveillances.
Increased management attention to insuring surveillance requirements are met as well as the continued management emphasis for attention to detail should lead to continued improvements in the program. PSE&G management will continue to dedicate resources to ensuring surveillance compliance and encourages all employees to improve the process. PSE&G's actions to reduce personnel errors and improve attention
- to detail will be continued.
The "Attention to Detail" video and the "Salem Handbook of .standards" are presently being provided to every station employee, along with a General Manager -Salem Operations presentation and specific training to further stress attention to detail and high work standards.
Management will continue to focus on these areas to assure that deficiencies in these areas are identified and and to insure continued improvement in these areas. In addition to responding to the Notice of Violation, PSE&G was requested to "address the adequacy of its' corrective action program in general, relative to preventing recurrence of previously identified problems including what improvements in this area are needed". PSE&G believes that it has an aggressive and responsive incident investigation and corrective action program. The main elements of the program are described in AP-06, Procedure NA-AP.ZZ-0006(Q), "Incident Report and Reportable Event Program".
This program delineates the responsibilities and the flow path for investigation, root cause determination, and corrective action determination for events of appropriate cause or significance.
The extent of evaluation and follow-up is relative to cause/significance, but can always be increased at individual discretion.
Each incident report is now reviewed by station management at the daily.morning meeting. If follow-up investigation is required, internal and external operational experience is reviewed for similar events. A Department Manager/Engineer is assigned responsibility for the investigation and a copy of the Incident Report (IR) is sent to the HPES (Human Performance Evaluation system) Engineer if human performance problems are involved (presently all IRs are sent to the HPES Engineer).
The follow-up investigation analyzes the event and determines root cause(s), identifies the corrective actions, and assesses the safety consequences and implications of the incidente The IR Form is used to document the investigation.
The responsible Department Manager approves the investigation findings and corrective actionse The LER Coordinator also reviews the IR for completeness.
If the incident is reportable the root cause and corrective actions are specified in the report and SORC reviews and approves them. The General Manager -Salem Operations must review and approve these reports prior to issuanceQ For significant or reportable events Quality Assurance (QA) and/or Onsite Safety Review (SRG) will often be present at the associated SORC and special station meetings at which the root cause and corrective actions are reviewed.
This provides each with the opportunity to discuss and provide feedback into the process prior to final determination.
Formal review of certain reportable events and all events involving Reactor Trips or ECCS actuations are performed by SRG. These reports are utilized by management.
to assess root cause and corrective action ,, *-.. --... , *-.
.. *'
QA also reviews various events and reports, and provides essential feedback to the management team. Further feedback is provided on selected (significant) events as a result of the HPES evaluations.
Management often requests QA, LSRG, and OSR (Offsite Safety Review) to perform special investigations and requests to provide analysis, root cause evaluation and recommend corrective actions for items relative to events sensitive to operational performance concerns, programmatic concerns, human factor concerns, and other type events for which they may have additional concerns.
PSE&G has frequently utilized the system engineering group, to perform the root cause analysis and help determine corrective actions, for events involving equipment failure, system performance and design concerns.
This has resulted in increased technical investigation and often better resolution of the problem. Even though the corrective action program was viewed as aggressive and thorough, management believed that the program was not as consistent with regard to the varying levels of investigation and that the program did not provide a consistent systematic approach.
Furthermore, industry information revealed that analyzing "near miss" events could be more significant for preventing future events than the actual events; therefore, it was felt that the program should be directed to place more emphasis on this. PSE&G determined that utilizing the INPO HPES methodology could improve root cause analysis, provide more complete corrective actions and better detect human performance deficiencies.
In implementing the HPES program, the need for formal training of key personnel in root cause analysis was identified and a training program was developed.
Select individuals have been trained and this training is ongoing. PSE&G is continuing to evaluate its root cause analysis program and is implementing various actions to this end. These actions will be provided to the NRC, as part of PSE&G's integrated strategic plan for improving operational performance at Salem, during the late October, 1989 meeting with Region 1, as discussed in the SALP responsee PSE&G does not believe that the Violations cited in this report occurred directly as a result of the program established as a corrective action being inadequate, but that they were more a result of other problems i.e. lack of attention to detail (personnel error) and inadequate administrative controls for administering the program. PSE&G is aware of and has been addressing these problem. However, the corrective actions in these areas had not been fully implemented at the time of the event and are still being implemented.
These corrective actions are included in the corrective actions provided in the Notice of Violation response.
- Further improvements are also being implemented to improve the root cause and corrective action programs.
A formal training program to provide root cause analysis training to key personnel (those who will be involved in root cause analysis) is presently being developed.
A Significant Event Response Team (SERT) has been developed to perform thorough investigation/reports of significant events. This investigation process will provide a more systematic approach to the investigation of future events. Implementation of these actions will be discussed during the October, 1989, Region 1, meetingo PSE&G management will continue to monitor the progress of its corrective actions for assuring surveillance requirements are met, increased attention to detail, reduced personnel errors and ensuring administrative controls and management oversight are effective in ensuring these goals. As such, PSE&G is determined to meet the highest operating standards and will ensure that all necessary actions will be taken to attain those standards
- ** -*-** *-*-..:: *-. *.*** * < * -** ** ,_ ' -.. *-***-.*;.""*
- -=* *;; :**:* * * * * ****-* *-** * **-:.***:
* * *-
--*,** _,. * * ** * ":--:** r ** * * *' *' ** *** ** * . . --. *-.* '