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 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] |
See also: IR 05000272/1989015
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
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
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. -. * *' * '
., '* *** '* * **-.-*" °! * * * I * *
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 * * **: -.. *-. --. . . .. -. .. . , -. . -... '
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
- After the subject inspection
report was issued, PSE&G identified
a missed surveillance
on August 11, 1989, pertaining
to venting of ECCS pumps and associated
piping per Technical
Specification
3.5.2 (Surveillance
Requirement
4.5.2.b.2}.
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
- . -. :*** .. ' _,... * ......... : .. -**: . .*** .. -, ..... **:--........ .
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.
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 ** * * *' *' ** *** ** * . . --. *-.* '