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
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Pubhc Service Electric and Gas Company
' Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. 6cx 236, Hancocks Bridge.NJ 08038 609339-4800 Vice President-Nuclear November 7, 1966 NLn-!,86]SO Mr. James M. Taylor, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Brian K. Grimes, Director Division of Quality Assurance, Vendor, and Technical Training Center Program Gentlemen:
ENVIRONMENTAL QUALIFICATION INSPECTION SALEM CENERATING STATION DOCKET NOS. 50-272 AND 50-311 As a.. result of the recent inspection of the Environmental Quall'fication program at the Salen Generating Station during the week of August 11-15, 1986, five (5) Potential Enforcement / Unresolved Items were identified. Public Service Electric and Gas Company (PSE&G; believes that the equipment referenced in 4 of these items was appropriately qualified in accordance with 10 CFR 50.49 requirements. A sumnary of our position on each of these items is presented in Attachment A.
Attachment B (1-3) presents additional detail.
We ask that you review the attached information and provide un with the results of that review. Your cooperation in this matter is appreciated.
Sincerely,
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Attachrents 8611120210 861107 $N
{DR ADOCK 05000272 PDR di 1
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. -Of fi'ce of Inspection arid 2 11-7-86 I Enforcement 4
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C 'Mr. D..C. Fischer Licensing Project Manager -
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' M r. T. .J. Kenny
. Senior Resident Inspector ,
Mr. Uldis Potapovs
. Vendor Program Banch i
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ROCKBESTOS FIREWALL III EP & COAXIAL CABLE Two potential enforcement items were identified by the NRC related to unacceptable documentation to establish qualification for Rockbestos Firewall III EP cable and Firewall III coax cable. This was based on potential concerns identified in IE Notice No. 84-49.
WE BELIEVE THESE POTENTIAL ENFORCEMENT ITEMS ARE UNWARRANTED FOR THE FOLLOWING REASONS:
Rockbestos Firewall III EP cable was not identified in the IE Notice.
-Retest of Rockbestos Firewall III coax cable completed in March 1986, reinforced the conclusions of the identified test report.
NRC inspection of San Onofre did not question the acceptability of the test reports.
The test performed during the time period in question was not used to qualify the Rockbestos Firewall III EP cable; a subsequent test was utilized.with the results on file.
All retesting has resulted in confirmation of the previous tests.
PSE&G utilized the option provided by the IE Notice to prove qualification, " perform analysis of existing reports".
Attachment A
LIMITOROUE ACTUATOR GREASE RELIEF i
A' potential enforcement item was identified by the NRC related to the absence of gear box grease ~ reliefs on Limitorque actuators located in containment.
WE BELIEVE THIS POTENTIAL ENFORCEMENT ITEM IS UNWARRANTED FOR
-THE FOLLOWING REASONS:
The Limitorque operators are not designed for absolute sealing and need not be considered for qualification.
The test anamoly where grease escaped from the actuator housing was not due to the accident conditions.
The test conditions during the anamoly simulated the less severe out-of-containment conditions, rather than the harsher containment environment.
Test performed by Limitorque indicated that even under extreme super heat conditions, the actuator internals never exceed 315'F.
Mobil grease 28 which is utilized ac Salem, has a dropping point in excess of 500*F. Appreciable expansion of the grease vould not occur until a liquid state is attained.
Attachment A nn, -s. -
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EXO SENSOR HYDROGEN ANALYZER A potential enforcement item was identified by the NRC t
- related'to documentation on file not supporting the Salem-10 year maintenance cycle of the pressure transducer and RTD for the Exo Sensor hydrogen analyzer.--
WE BELIEVE THIS POTENTIAL ' ENFORCEMENT -ITEM IG UNWARRANTED FOR THE FOLLOWING REASONS:
Design life was originally stated as significantly in excess of the levels required, therefore,rthe original ,
aging tests were not required to be extended past 2 years.
Rather, an 18-month surveillance was specified which would
-visually identify any degradation. !
.Exo Sensor had, subsequent to-the original test, supplied
, documentation extending the aging analysis to 10 years.
i- The Exo Sensor stated maintenance cycle of 120 months for
- q. .the pressure transducer and RTD was backed-up by test data.
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Attachment A 4
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ATTACHMENT nB - 1 Two potential enforcement items were identified by the NRC related to unacceptable documentation to establish qualification for Rockbestos Firewall III EP cable and Firewall III Coax cable. This was based on potential generic problems regarding Rockbestos environmental qualification testing which was promulgated to the industry in IE Information Notice No. 84-44 (Attachment 1).
It is suggested by this IE Information Notice that there may have been inconsistencies in the quality assurance and the documentation practices used in the testing of certain Rockbestos cable. The types of cable were Firewall III (RXLPE, CXLPE insulation), Firewall III coaxial (RXLPE insulation) and Firewall SR (silicon insulation). This Information Notice was generated as a result of an NRC inspection of Rockbestos as described in Attachment 2. The Information Notice suggested three possible courses of action which should be considered by an affected utility. These were 1) to perform a new qualification test, 2) obtain documentation from other tests, and 3) perform analyses of existing reports.
-It was also stated that..."It appears that the validity of some of the Rockbostos qualification reports is in doubt, however the NRC staff has concluded at this time that no immediate safety problem exists in the use of Rockbestos cables. The NRC staff considers that it is the responsibility of the user utilities to review the information provided above and take applicable corrective action to ensure the qualification of Rockbestos cables in their plants."
Note that IE Information Notice 84-44 states that a safety problem does not exist.
! Salem uses two types of Rockbestos cable in safety related l
applications, both inside and outside containment. The type names are Firewall-EP, which was qualified by the test reports in' Salem Equipment Qualification Report No. EO-08, and l
Firewall-III coaxial cable, which was qualified in Salem l Equipment Qualification Report No. EO-32.
Firewall-EP is of particular concern because it is used in safety-related applications inside containment. One of the qualification test reports performed by an outside test organization (Franklin) during the years of concern is F-C3798.
This report was identified by the NRC as possibly being problematic (Attachment 2). This report is not, however, required for the successful qualification of this cable.
Utilization of OR No. 1804A (in EO-08), performed in 1982 establishes the qualified status. Of f urther significance, neither Attachment 2 nor Attachment 6 identifies Firewall-EP as a cable of concern.
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Firewall EP (Ethylene-Propylene Rubber insulation - the most-
- commonly used and' accepted for Class lE cable insulation) has-never been identified as having possibly questionable QA
- practices in testing. It has never been discussed or'even mentioned in-IE Information Notices or NRC inspection reports.
Firewall III - Coaxial is used at Salem, but only outside of containment for both units. This cable was mentioned in IE 84-44,-and.Rockbestos was immediately contacted by PSE&G for discussion (Attachment 6). A complete requalification program for.Firewall III - Coaxial was completed in March 12, 1986.
This test program reinforced the . conclusions of the previous Rockbestos tests of Class IE cable of similar construction. It also reconfirms the similarity between first _ and second generation coax cable previously established in Addendum 1 to Rockbestos technical report TS1981 - YJR-3.
A recent NRC inspection at Rockbestos resulted in several observations and comments as identified on page113 of Inspection Report No. 9900277/85-02 (Attachment 3). Because this cable is used.only outside containment in Salem, most of the NRC comments are not applicable. The applicable and useful observations to Salem are that after the cable was irradiated, a visual examination revealed no degradation, and an aging test
' determined an activation energy of 2.75 eV. .This aging test has not yet been fully reviewed, but an activation energy this large indicates equipment life of substantially greater than 40 years.
Of interest is the fact that San Onofre recently underwent an NRC EO inspection. NRC Inspection Report No. 50-312/85-14 (Attachment 4), mentioned the Rockbestos cable on page 13. It
-is stressed that the ability of Firewall III and Firewall SR to
' survive-a LOCA is not-questioned. The only concern was that San Onofre had not adequately established similarity between the cable in their plant and the specimens tested in their Qualification Reports.
Although Salem does not utilize Firewall III SR cable, it is interesting to note that the NRC's concern is not the establishment of ' qualification per the test report but of similarity to the plant cable, thereby stating that once simiarlity is established qualification would also'be established. This is contrary to what is indicated as a potential enforcement item for Salem.
It is concluded that Salem did not have a safety concern with Rockbestos cable. The existing in-house documentation (EO-32;
- EO-08; and Attachments 1-6) sufficiently demonstrated qualification, and the test which is currently in progress at Rockbestos will serve only to supplement the existing reports currenty found in EO-32.
It should also be noted that, to date, all retesting has resulted in ' confirmation of the previous results questioned by IE'Information Notice 84-44.
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{ G LICENstNG 5 INSaSd Nn REGULATIO 935 IN 84-44
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. NUCLEAR REGULATORY COMMISSION -
T d%@ ji I0FFICE OF INSPECTION AND ENFORCEMEN r 1
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1:Ci > . I I June 8, 1984 -
7 v-NOTICl; NO 84-44:
WQ ENVIRONMENTAL QUALIFICAl 1Un IESTINC AC IErINFO
- ROCK 8ESTOS CABLES a.my n e Addressees: pm w. ne All holders of a nuclear power reactor operating license (OL) or construction permit (CP). . ,
Purpose:
This information notice is provided to inform licensees and construction permit holders of potential aeneric oroblems reaardina Rockbestas enviennmental '
qualification (EQ) testing of Class 1E electrical cables. Addressees are expected to review the information for applicability to their facilities.
No specific action or response is required.
Description of Circumstances:
The NRC has performed a number of inspections of the QA programs established at several environmental testing facilities. This effort was started in late August 1982 to assess the facilities' establishment and implementation of a QA program based on the requirements of 10 CFR Part 50, Appendix B.
Several such inspections were recently conducted at the Rockbestos Company in New Haven, Connecticut. The NRC inspection team reviewed qualification .
related documents such as EQ reports, associated supporting items including test plans, test procedures, test instruments, test log books, related raw data and QA documents. The inspections revealed several QA nonconformancos and related testing / documentation problems. Details of these nonconformances and inspection findings are documented in the following NRC Inspection Reports:
99900277/83-01, 99900277/83-02, and 99900277/83-04. Listed below are some of the QA nonconformances and related testing / documentation problems which may affect the qualification of Rockbestos cables that are installed at licensees' facilities:
- 1. The Rockbestos Comnanv did not impose cuality assurance / test control re-ouirements on an outside test oraanization which performed testing (LOCA/
HELB) during ti.e period of 1969-1979.
- 2. The Rockbestos Company did not establish and implement a QA program.in accordance with 10 CFR Part 50, Appendix B requirements to control Rock-bestos EQ testing; i.e., the EQ program was controlled by a Rockbestos engineering organization which was not under a QA program until 1983.
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IN 84-44 June 8, 1984 Page 2 of 3
- 3. As a result of inadequate QA controls, testing and the required documen-
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tation were not properly controlled. Several discrepancies oetween final qualification reports and supporting test data were found.
- 4. Rockbestos' QA and engineering organizations did not imoose OA and techni-cal reouirements/ acceptance criteria on organizations that performed qualification testing for Rockbestos between 1969 and 1979. Furthermore, no supporting test data for these tests were available for audit at Rock-bestos or subtier test organizations. ,
- 5. Test equipment and instrumentation were observed to have inadequate reso-lution to record LOCA test parameters and functioning of test specimen during testing.
- 6. Test equipment was not properly calibrated or under the control of the calibration system. An internal Rockbestos audit dated May 10, 1983, documented these generic deficiencies in their calibration s:ystem.
- 7. Test plans, acceptance criteria, and test procedures for certain quali- ,
fication tests were not made available during the NRC audits.
- 8. A number of test deficiencies, deviations, and other anomalies were not documented and evaluated in the test reports.
The results of the NRC inspections show that several deficiencies were present in the Rockbestos Company qualification programs in effect at time of the audit.
Individually, some deficiencies could be adequately reconciled, but taken col-lectively, the nature and number of deficiencies identified would not adequately demonstrate that acceptable qualification had been established. It appears that the validity of some of the Rockbestos qualification reports is i doubt. how-ever. the NRC staff has concluded at this time that no immediate safety problem exists in the use of Rockbestos cables. The NRC staf f considers that it is the retnantibility of the user utilities to review the information provided above and take aDolicable corrective action to ensure the qualification of Rockbestos cables installed in their plants. The following possible courses of corrective action should be considered:
a) Perform a valid qualification test of the installed Rockbestos cables.
b) Obtain documentation from other available qualification tests alreacy performed and determine its applicability to the install-ed cables.
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.i IN 84-44 June 8, 1984 Page 3 of 3 c) Perform analyses of existing qualification reports applicable to tne installed caotes to ensure tnat tne oocumentation relied upon to demonstrate environmental qualification supports such a conclusion.
The NRC staff considers this review to be part of the on going activities that_ V ~
the licensees are currently undertaking to resolve other environmental quali- % ,
fication deficiencies to meet the deadline and requirements set forth in the EQ final rule, 10 CFR 50.49.
Questions regarding details of, and resolutions to the NRC inspection findings described above should be directed either to the equipment manufacturer, or the cognizant design / test agency. If you have questions regarding this information notice, contact the Regional Administrator of the appropriate NRC Regional Office, or this office. , ,
di Jordan, Director dward -
Divisi of Emergency Preparedness and gineering Response Office of Inspection and Enforcement Technical Contacts: R. G. LaGrange, NRR (301) 492-8208 N. B. Le, IE (301) 492-9673
Attachment:
List of Recently Issued IE Information Notices i
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l TO: E. A. Liden Manager - Nucit.ar Licensing and Regulation FROM: 7. T. S tacJ ey
.sta.,ager - N :c J e: 2.r Systems Engineecing l
SUBJECT:
EQUIPMENT QUALIFICATION TEE'.rNG OF ROCKBESTOS CABLE i S-C-A910-EEE- 0 0 8 7-k0 i DATE: August 12, 1935 l The attached Engine .t ing F. valuation, Equip:nent Qual ifir . tion Testing of Rockbestos Cabje., Ic perwarded for yoer information. IE Notice No. E4-44 cescri'aec a possible
- inadequacy in the quality t ce.acco o r t.:.'. i c e n o f th . .ock:>esto .
Company. Engineering in ir. t.c r ; ? r r ier, o . ~. to s t 1.p.. f ts. shic!.
demonstrate the ability of the 'teceLut<cos LO.~.: in safety-related syste.ns s t SC.cm to n .eet all specifications and a letter from Rockbestos addressing each item in TE Notice 84-44 individually.
l Should any further informatior, bc requiree please contact the
_ Systems Analysis Group.
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BGH: jab Attachment C 1 General Manager - Nuclear Quality Assurance 1 General Manager - Nuclear Services 1 General Manager - Salem Operations l 1 Assistant General Manager.- iiuclear Engineering 1 Manager - Nuclear Systems Engi.neering 1 Manager - Nuclear Plant F.ngineering 1 Manager - Nuclear Engineering Design 3 Manager - Nuclear Engineering Co.itrol 1 Manager - Nuclear Safety & Assurance 1 On-Site Safety 1 Site Engineering 1 Station OA Engineer - Salem 1 Salem Operations Response Coordinatcz 1 M. Levine 1 B. G. Horst 1 SAG File 1 TDR GH-BGH/l
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