Forwards marked-up Listing of Significant Regulatory Actions & Current Status,Per 860430 Request.Addl 60 Days Required to Complete EffortML18092B167 |
Person / Time |
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Site: |
Salem |
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Issue date: |
06/04/1986 |
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From: |
Corbin McNeil, Ncbeukkmc A Public Service Enterprise Group |
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To: |
Fischer D, Fuscgermd C Office of Nuclear Reactor Regulation |
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References |
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RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-OR, TASK-TM GL-82-16, GL-83-43, GL-84-15, NLR-N86085, NUDOCS 8606100149 |
Download: ML18092B167 (11) |
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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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Public Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 399-4800 Vice President -
Nuclear June 4, 1986 NLR-N86085 Off ice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention: Mr. Donald C. Fischer, Senior Project Manager PWR Project Directorate #3 Division of PWR Licensing-A, NRR Gentlemen:
IMPLEMENTATION OF APPROVED REGULATORY REQUIREMENTS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 As requested by your letter of April 30, 1986, Public Service Electric and Gas Company is forwarding the attached marked-up listing of significant regulatory actions and their current status. Due to the time frame in which the initial NRC reviews were completed, information regarding the current status of many of these items is not readily available. Based on the number of man-hours expended to date (approximately 120), it is expected that an additional sixty days will be required to complete this effort.
Should you have any questions regarding this information, please feel free to contact us.
Sincerely, Attachment C Mr. Thomas J. Kenny Senior Resident Inspector
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8606100149 860604 PDR ADOCK 05000272 P PDR
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FACILITY: SALEM 1 PLANT LOCATION: 20 MI S OF WILMINGTON, DEL LICENSED POWER: 3338 MWT PROJECT MANAGER: D. FISCHER DOCKET NUMBER: 050-00272 DESIGN POWER: 1090 MWE BRANCH CHIEF: S. VARGA ARCH/ENGINEER: PUBSERVE NSSS VENDOR1 WEST LIC. ASSISTANT: L. PARRISH IE INSPECTOR: L. NORRHOLM LIC ACT LICENSEE TAC NO, MPA I TITLE COMPLETE STATUS DATE M06659 A-01 10 CFR 50.55 A<G> - ISi 08/12/81C M08154 A-02 APPENDIX I - ALARA 12/05/84C M06981 A-03 SECURITY REVIEWS-MODIFIED AMENDMENT PLANS 02/~3/79C M08825 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 07/28/SOC M10743 A-10 CONTINGENCY PLANNING 09/12/SOC M10738 A-11 GUARD TRAINING PLANS 05/12/81C M10746 A-12 VITAL AREA ANALYSIS 04/12/82C M11224 A-14 10CFR 50.55 A<G> - INSERVICE TESTING 04112183C M47078 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 11/06/81C M51128 A-17 INSTRUMENTATION TO FOLLOW THE COURSE O~ AN ACCIDEN 06/17185C M55736 A-18 TECH SPECS AFFtCTED BY 50.72 AND 50.73 CGL 83-43> 05/13/85C M59136 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS Nl/S I M59978 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE M07905 B-01 DIES~L GENERATOR LOCKOUT 09/29178C M07063 B-02 FIRE PROTECTION 11/20/79C M08398 B-03 PWR MODERATOR DILUTION 04/29182C 0
M06744 B-04 REACTOR V~SSEL OVERPRESSURE PROTECTION 02/21 /80C M07287 B-07 STEAM GENERATOR FEEDWATER FLOW INSTABILITY 11/03/79C M08170 B-08 PWR HPSI-LPSI FLOW RESISTANCE 11/28/BOC M07842 B-09 CHARGING SYSTEMS PIPE VIBRATIONS 11 /09/79C 1,
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F AC I L I T Y I MP L E ME N T A T I 0 N 03/ ~1 / i SALEM 1 CCONTINUATION>
LIC ACT LICENSEE IAC HO, t1fLI TI ILE COMPLETE STATUS DATE MD8658 B-13 FUEL ROD BOW 09126179C M08823 B-14 CEA GUIDE TUBE WEAR 07122180C M12163 B-16 EMERGENCY PLANNING AND REVISIONS 04101181C M11227 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 02102182C M10272 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 01131181C M10336 B-21 LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF ANNUNCIA 02128182C M08822 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 11109179C M10050 B-23 DEGRADED GRID VOLTAGE 01125/82C M08993 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 01131181C M42561 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 05119183C M07491 B-26 INADVERTANT SAFETY INJECTION DURING COOLDOWN 11109179C M08682 B-39 PWR PRESSURE - TEMP.ERATURE LIMIT TECH SPECS 11113180C M11110 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 08/24180C M43739 B-41 FIRE PROTECTION - FINAL TECH SPECS CINCLUDES SER S 06117/83C M11711 B-42 TMI FOLLOW UP - ALL PLANTS 06105181 C M11776 B-43 PWR FEEDWATER LINE CRACKS 09/26/79C
- M43150 B-43 PWR FEEDWATER LINE CRACKS 05125182C M12435 B-44 LESSONS LEARNED IMPLEMENTATION 03/21/81C HASH 1400 EVENT V, "PRIMARY COOLANT SYSTEM PRESSUR 04120/81C
.M12935 M12603 B-45 B-46 ANALYSIS OF TURBINE DISC CRACKS 08121181C M12686 B-47 ECCS; CLAD SWELLING AND RUPTURE 09/12/80C M13009 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 11121/81C M11877 B-52 REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 02/24181C
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LIC ACT LICENSEE TAC NO. tlfA_J TITLE COMPLETE STATUS Mil M42100 1-57 OHR CAPABILITY 03/06/81C M42866 1-59 MASONRY HALL DESIGN 08/18/83C M42467 B-60 ENVIRONMENTAL QUALIFICATION 12/05/84C M42705 1-61 LOSS OF NON CLASS IE I&C POHER 07/28/82C H42776 B-62 ESF RESET CONTROL DESIGN DEFICiENCY 06/04/81C 1143936 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 12109/SfC M47162 B-66 NATURAL CIRCULATION COOLDOHN 08115/UC M46858 1-69 IEI 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 101201a2c H49754 B-72 NUREG 07.57 TECH SPECS CGENERIC LETTER 82-16> 07/31184C H527t0 . B-76 ITEM 1.1 - POST TRIP REVIEH1 PROGRAM DESCRIPTION & 12105/84C Corn P1.-~re:=: D o~ /85 M52795 1-76 ITEM 1.1 - POST TRIP REVIEH1 PROGRAM DESCRIPTION I 09115185C cornPL..G:feD o'B/85 M52376 1-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 09130186 C,offlPLETC:.ti 01 /it../
1152957 1-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 03/17/86C M53031 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 12106/85C com p0e1£D oCf ;ss 1"153093 B-ao ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 03/17/B6C 1153146 1-81 ITEMS 4.2.1 I 4.2.2 -PREVENTATIVE MAINT PRDG FOR R 12106/85C comPLE.Te.D 08/65 1153192 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 06/25/84C COMPLETED 07 /'65 1154564 1-83 TECH SPECIFICATIONS COVERED IY GENERIC LETTERS 83- 04101/86 1153628 B-85 SALEM ATHS 1.2 DATA CAPABILITY 05130/86 P~O.TECTE D 19'0'7 SPDS IIVSTALLfl tJ
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M53711 a-a6 SALEM ATHS 2.2 S-R COMPONENTS . 01/01187 1153794 1-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 03/17/86C CofY\PLET6.0 01 j'Bt.J M53877 B-aa SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 12106/85C c.,,omPLE.TEb 0°1/'i!.5 1153933 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 1 f/30/86 11 i
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LIC ACT LICENSEE AC NO, MPA I ______T.....I......_,~-------------- COMPLETE STATUS DATE M55374 B-90 SALEM ATWS 4.3 WAND B&W T.S. 04/30/86 M54104 B-92 SALEM ATWS 4.5~1 DIVERSE TRIP FEATURES 03/17/86C Co<<lflG. l~D M54D21 B-93 SALEM ATWS 4.5.2 & 4.5.3 TEST ALTERNATIVES 04/31/~7 PRo.:r e,clEt:>
M07642 C-01 PWR SECONDARY WATER CHEMISTRY MONITORING REQUIREME 04/24/80C M07245 C-06 PUMP SUPPORT-LAMELLAR TEARING 01/21/81C M08826 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 11/2~/79C M08081 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL CPHASE 06/22/84C M43661 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICATION 08/24/82C ~
M52266 C-15 CONTROL OF HEAVY LOADS - PHASE II CFOLLOWUP OF MPA 06128/85C M58084 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 02/12/86C MD7874 D-02 ECCS ZIRC CLAD MODEL ERROR-COMPLIANCE WITH 10 CFR- 06/06/79C MD7856 D-03 PRESSURIZER HEATUP RATE ERROR 07/27/79C M08824 D-10 ASYMMETRIC LOCA LOADS 06/30/Bl M08998 D-11 FISSION GAS RELEASE 02/22/80C M12276 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 01/31/84C M43010 D-17 DEFINITION OF OPERABLE 11/28/80C M55898 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS CGL 84-15> 09/12/85C M07158 E-01 SPENT FUEL POOL EXPANSIONS 01/15/79C M07579 E-01 SPENT FUEL POOL EXPANSIONS 01/15/78C M11124 E-01 SPENT FUEL POOL EXPANSIONS 06/01/79C M44055 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/11/82C M44126 F-02 l.A.1.3 SHIFT MANNING 06/30/83C M44197 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 01/27/82C COfh PL.E.TE D 11 I
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LIC ACT LICENSEE TAC ND. MPA ! TITLE COMPLETE STATUS DATE M44268 F-04 I.C.1.213.A EMERGENCY OPERATING PROCEDURES GENERIC 06t07184C M44:S:S8 F-05 I.C.1.213.B PROCEDURES GENERATION PACKAGES CNUREG 12130188 M47251 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 11t15181C M4732:S F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 11115181C M51198 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 06101186 M51278 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 07/15186 PRO.'.fC:C..T~D M44405 F-10 11.B.1 RCS HIGH POINT VENTS 09127/83C M47974 F-11 11.B.2 PLANT SHIELDING 01/31/8:SC Com fl.ET I:/)
M44476 F-12 II.B.:S POST ACCIDENT SAMPLING 11/0418:SC M44547 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 01/27/82C Coff'i PLE. T~ D M44618 F-14 11.D.1 RV AND SV TRAINING 05130186 Co1Y1PLETE t>
M44650 F-15 II.E.1.1 AFW SYSTEM EVAL.UATION 09120182C M44690 F-16 II.E.1.2.1 AFW SYSTEM INITIATION 06116181C CoMfte:.le.D 1q8/
M44729 F-17 ll.E.1.2.2 AFW SYSTEM FLOW INDICATION 06116181C com PUE. re D I CJ 8 I M44815 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 06116/81C ~omPLr=.reD /"181 M44886 F-19 11.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 04111182C Coft\Pl.,~TIG f) j 98 (
M44957 F-20 II.F.1 .1 NOBLE GAS MONITOR 10101181C C,, ofl'\ PLE T 0 J9 9J-M45028 F-21 Il.F.1.2 IODINE/PARTICULATE SAMPLING 10101181C e-omPLer eD I q i?d-M45099 F-22 II.F.1.3 .CONTAINMENT HIGH RANGE MONITOR 02/11182C
'M476:S5 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 09/28/82C Corri P LG TE b 198 ;J..
M47706 F-24 Il.F.1.5 CONTAINMENT WATER LEVEL INSTRUMENT 09128182C c__om PL~ Te.0 1ct cao M47777 F-25 Il.F.1.6 CONTAINMENT HYDROGEN MONITOR 09/28/82C Con1PlE T£D 19 Bd-M45169 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 10124184C PRo::n;txe D /Cf 'd'1
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LIC ACT LICENSEE TAC NO. MfA._! TITLE COMPLETE STATUS DATE M46903 F-30 11.K.2~13 THERMAL-MECHANICAL REPORT 06/18/84C C.om PLE T~ D olo/ 6'-1 M47817 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 01/30/84C ComPlE~D 01/~'-l M45247 F-36 11.K.3.1 AUTO PORV ISOLATION 10/06/83C c.omPLeTE D 19 ~3 M45293 F-37 11.K.3.2 REPORT O~ PORV FAILURES 10/06/83C com PL..ETED M45379 F-38 11.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 02/21/82C M45410 F-39 11.K.3.5 AUTO TRIP OF RCPS 02/22/83C M45459 F-40 11.K.3.9 PIO CONTROLLER 08/24/81C M45489 F-41 II.K.3.10 .ANTICIPATORY TRIP MODIFICATIONS 08/24/81 c Com pu:;Tt:; D /980 M45519 F-42 II.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP 08/26/81 c c.,o m Pl..(; re; D /'1 Bo M45.665 F-47 II.K.3.17 ECCS OUTAGES 09/27/83C ComP <.A;TeD I q 81 M48431 F-53 II.K.3.25 POWER ON PUMP SEALS 06/28/82C M45862 F-57 II.K.3.30 SB L~CA METHODS 06/17/85C M48201 F-58 II.K.3.31. COMPLIANCE WITH 10 CFR 50.46 01 /15/87 M45981 F-63 111.A.1.2 TECHNICAL SUPPORT CENTER 12/30/87 PAo.:rGCTBO /997 M46052 F-64 111.A.1.2 OPERATIONAL SUPPORT CENTER 12/30/87 M46124 F-65 111.A.1.2 EMERGENCY OPERATIONS FACILITY 12/30/87 M46196 F-66 111.A.1.2 NUCLEAR DATA LINK 07/30/82C M46268 F-67 111.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 08/08/83C M46340 F-68 111.A.2.2 METEOROLOGICAL DATA UPGRADE 06/30/87
'M46411 F-69 111.D.3.3 IMPLANT RADIATION MONITORING 02/01/82C M46480 F-70 111.D.3.4 CONTROL ROOM HABITABILITY 01/31/84C M56160 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEW CFOLLOWUP TO M49669 G-01 REACTOR COOLANT PUMP TRIP CD660 - 11.K.3.5> 04/01/86
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.l-12087 31-001 R EGUL AT 0 RY I N F 0 R MA T I 0 N T R AC KI NG S YS T EM PAGE NQ.* : 4.3, F AC I L I T Y I MP L E ME N T A T I 0 N 03131181 FACILITY: SALEM 2 PLANT LOCATION: 20 MI ~ OF WILMINGTON, DEL LICENSED POWER: 3411 MWT PROJECT MANAGER: D. FISCHER DOCKET NUMBER: 050-00311 DESIGN POWER: 1115 MWE BRANCH CHIEF: S. VARGA ARCH/ENGINEER: PUBSERVE NSSS VENDOR: WEST LIC. ASSISTANT: L. PARRISH IE INSPECTOR:
LIC ACT LICENSEE TAC NO. MEL! TITLE COMPLETE STATUS DATE M48327 A-02 APPENDIX I - ALARA 12/05/84C M46814 A-14 10CFR 50.55 ACG> - INSERVICE TESTlNG 09/03182C M51129 A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 06/17/85C M55731 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 CGL 83-43) 05/13/85C M59137 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS N//S /
M59979 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE M12164 B-16 EMERGENCY PLANNING AND REVISIONS 05/20/81C M46782 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 02/02182C M46781 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 05/19/83C M46712 B-41 FIRE PROTECTION - FINAL TECH SPECS <INCLUDES SER S 06/17183C M11712 B-42 TMI FOLLOW UP - ALL PLANTS 07/31/81C M48330 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 05/02/82C M46813 B-59 MASONRY WALL DESIGN 08/18/83C M42533 B-60 ENVIRONMENTAL QUALIFICATION 01/14/85C M43949 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 12/09/81C
- '147163 B-66 NATURAL CIRCULATION COOLDOWN 08/15/83C 1
M46859 B-69 IEB 80-4 MAINSTEAM LINE BREAK WITH CONTINUED FEEDW 10/20/82C M49755 B-72. NUREG 0737 TECH SPECS <GENERIC LETTER 82-16) 07/31184C M52796 B-76 ITEM 1.1 - POST TRIP REVIEW; PROGRAM DESCRIPTION & 09/15/85C M52877 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 09130186
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SALEM 2 CCONTINUA TI ON)
LIC ACT LICENSEE JAC NO, MELI TITLE COMPLETE STATUS DATE M52958 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 12/06/85C torn PL£ ri= D o'1/%4 M53039 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 12/06/85C comp 1...12,re D oqf&S M53094 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO M53147 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 12/06/85C ComPLt:r~D M53193 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 06/25/84C Com PLE rc:;Q M54565 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 04/01/86 M53629 B-85 SALEM ATWS 1.2 DATA CAPABILITY 05/30/86 Pf~o:rec,T~D M53712 B-86 SALEM ATWS 2.2 S-R COMPONENTS 01 /01/87 M53795 B-87 SALEM ATWS 3.2.1 & 3.2.2 S-R COMPONENTS 03/17/86C Cof{lfl,,~TeD 01 /'64 M53878 B-88 SALEM ATWS 3.2.3 T.S. S-R COMPONENTS 12/06/85C com p LE r ~ b O 9 / <g 5 M53934 B-89 SALEM ATWS 4.2.3 & 4.2.4 LIFE COMPONENTS 11/30/86 H55375 B-90 SALEM ATWS 4.3 WAND B&W T.S. 04/30/86 M54105 B-92 SALEM ATWS 4.5.1 DIVERSE TRIP FEATURES 03/17/86C C..,OmfLE.TE.D 01 /85 M54022 B-93 SALEM ATWS 4.5.2 & 4.5.3 TEST ALTERNATIVES 04/31/87 ?~ 0-:J 12c..TE f) J 9 'i3 '7 M46815 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL <PHASE 06/22/84C M43674 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICATION 08/24/82C M52267 C-15 CONTROL OF HEAVY LOADS - PHASE II CFOLLOWUP OF MPA 06/28/85C M58085 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 02/12/86C DIESEL GENERATOR RELIABILITY TECH SPECS CGL 84-15) 09/06/85C
.M55899 M44056 D-19 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/11/82C M44127 F-02 I.A.1.3 SHIFT MANNING 06/30/83C M44198 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 01/31/81 c Com PLI~ n~ D M44269 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/25/84C
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LIC ACT LICENSEE ;
TAC NO. MU...! TI E COMPLETE STATUS DATF, M44339 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES CNUREG 12/30/88 M47252 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 11/15/81C M47324 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/15/81C M51199 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 06/01/86 M51279 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 07/15/86 PROJ6CTE D J q 6'7 M44406 F-10 11.B.1 RCS HIGH POINT VENTS 09/27/83C M47975 F-11 11.B.2 PLANT SHIELDING 01/31/83C C.oM (> L~re D 1qe1 M44477 F-12 11.B.3 POST ACCIDENT SAMPLING 11 /04/83C M44548 F-13 11.B.4 TRAINING FOR MITIGATING CORE DAMAGE 05/19/81C Cofl'I P L-i= r-e*D tcr 9 D M44619 F-14 11.D.1 RV AND SV TRAINING 05/30/86 c.om PL-8T6D o8 / '?:5 M44651 F-15 11.E.1.1 AFW SYSTEM EVALUATION 09/20/82C M44691 F-16 Il.E.1.2.1 AFW SYSTEM INITIATION 06/12/81C C Orfl P l..6' re; IJ 1'1Bd-M447 30 F-17 II.E.1.2.2 AFW SYSTEM FLOW INDICATION 06/12/81C C., 0 tr. P ~E T i:::: D IC) Bd--
M44816 F-18 11.E.4.1 DEDICATED HYDROGEN PENETRATION 08/24/81C C.ofYlPC...~ ~D 1960 M44887 F-19 11.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 04/19/82C C o fY\ PL-t::: r<=:: D I q 'BI M44958 F-20 II.F.1.1 NOBLE GAS MONITOR 10/01/81C M45029 F-21 11.F.1.2 IODINE/PARTICULATE SAMPLING 10/01/81C M45100 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 01/31/81 c M47636 F-23 11.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 09/28/82C c...o m Pc.., 12 n; D 0
M47707 F-24 11.F.1.5 CONTAINMENT WATER LEVEL INSTRUMENT 09/28/82C C-om PLt::Tt::; D M47778 F-25 11.F.1.6 CONTAINMENT HYDROGEN MONITOR 09/28/82C Cofrt Pl..~ n:; D M45170 F-26 11.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 10/24/84C 'PRDJ"8CT 8 i:)
M46904 F-30 ll.K.2.13 THERMAL-MECHANICAL REPORT 06/18/84C eomPLETelJ II*
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~ALEM 2 CCONTINUATION)
LIC ACT LICENSEE TAC NO. .MfA.._I TITLE COMPLETE STATUS DATE M47818 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 01/30/84C I co M f t...e. re D of BL.f M45248 F-36 11.K.3.1 AUTO PORV ISOLATION 10/06/83C eomPL..c=:r e: D 1°I93 M45294 F-37 11.K.3.2 REPORT ON PORV FAILURES 10/06/83C c.,omPLe.rt~D /'183 M45380 F-38 11.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 02/26/82C comPu~reD I 9Bd-M45411 F-39 11.K.3.5 AUTO TRIP OF RCPS 02/22/83C M45460 F-40 11.K.3.9 PID CONTROLLER 08/24/81 c M45490 F-41 ll.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 08/24/81C Com Pl-ereD M45520 F-42 II.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP 08/24/81 c co,mPL.rc re"i)
M45666 F-47 Il.K.3.17 ECCS OUTAGES 09/27/83C M48432 F-53 II.K.3.25 POWER ON PUMP SEALS 06/28/82C /98d-M45863 F-57 ll.K.3.30 SB LOCA METHODS 06/17/82C M48202 F-58 II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 01/15/87 M45982 F-63 111.A.1.2 TECHNICAL SUPPORT CENTER 12/30187 /98'7 M46053 F-64 111.A.1.2 OPERATIONAL SUPPORT CENTER 12/30187 M46125 F-65 111.A.1.2 EMERGENCY OPERATIONS FACILITY 06130187 M46197 F-66 III.A.1.2 NUCLEAR DATA LINK 07130182C M46269 F-67 111.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 08108/83C M46341 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 06/30/87 M46412 F-69 Ill.D.3.3 IMPLANT RADIATION MONITORING 01102182C 01/31/81 c 0
M46481 F-70 111.D.3.4 CONTROL ROOM HABITABILITY M56161 F-71 l.D.1.2 DETAILED CONTROL ROOM REVIEW CFOLLOWUP TO M49670 G-01 REACTOR COOLANT PUMP TRIP CD660 ~ II.K.3.5> 04/01/86 II*