Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2411999-04-22022 April 1999 Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics ML18107A1841999-04-14014 April 1999 Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl ML18107A1981999-04-12012 April 1999 Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202 ML18107A1691999-04-12012 April 1999 Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept ML18106B1491999-04-0505 April 1999 Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML18107A2201999-03-30030 March 1999 Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek 1999-09-08
[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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LER-2082-100, Forwards LER 82-100/01T-0.Detailed Event Analysis Encl |
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> I 4n] ,O PSEG Public Service Electric and Gas Corrpany P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station September 22, 1982 Mr. R. C. Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Haynes:
LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-100/0lT Pursuant to the requirements of Salem Generating Station Unit No. 2, Technical Specifications, Section 6.9.1.8.c, we are submitting Licensee Event Report for Reportable Occurrence 82-100/0lT. This report is required within fourteen (14) days of the occurrence.
Sincerely yours, l , %( <b v'V H. J. Midura General Manager -
Salem Operations RF:ksf,D[
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Report Number: 82-100/0lT Report Date: 09-22-82 i Occurrence Date: 09-15-82 Facility: Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Containment Service Water Leak - No. 22 Containment Fan Coil Unit.
This report was initiated by Incident Report 82-278.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 - Rx Power 81% - Unit Load 900 MWe.
DESCRIPTION OF OCCURRENCE:
At 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br />, September 15, 1982, following planned maintenance on No. 22 Containment Fan Coil Unit (CFCU), a small service water leak of approximately 0.3 GPM was discovered emanating from a secondary coil. The leak was isolated and the NRC was immediately notified by telephone. No. 22 CFCU had been taken out of service at 1117 hours0.0129 days <br />0.31 hours <br />0.00185 weeks <br />4.250185e-4 months <br />, September 15, 1982, for repair of a previous leak which had been temporarily isolated with a blank in the service water piping. Technical Specification Action Statement 3.6.2.3.a had been entered at that time, and remained in effect. A service water leak was subsequently discovered on No. 21 CFCU at 0033 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, September 16, 1982, and Action Statement 3.6.2.3.b was entered (see LER 82-101/0lT). Both containment spray systems were operable throughout the occurrence providing containment cooling capability.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Investigation of the problem revealed that the leakage was due 1 to erosion of the cooling coils The coils are fabricated of l copper nickel alloy, which is se ceptible to erosion by silt laden service water. Similar failures of other CFCU's have {
been noted, with most leaks occurring at bends where erosion is 1
.more significant. I l
ANALYSIS OF OCCURRENCE:
Primary containment is a design feature which ensures that the release of radioactive materials in the event of accident con-ditions will be restricted such that site boundary radiation doses will be within the limite of 10CFR100.
I
LER 82-100/0lT .
ANALYSIS OF OCCURRENCE: (continued)
NRC IE Bulletin 80-24 requires that any service water leak inside the containment be considered as a degradation of the containment boundary. If containment pressure increased to the design pressure of 47 psig during an accident, there is a possibility of the release of radioactivity through the
)
service water discharge. The occurrence, therefore, consti-tuted an abnormal degradation of the primary containment and is reportable in accordance with Technical Specification 6.9.1.8.c.
The CFCU's operate in conjunction with the containment spray systems to remove heat and radioactive contamination from the containment atmosphere in the event of a design basis accident.
Operability of either all fan coil groups or of both containment spray systems is necessary to ensure offsite radiation doso is maintained within the limits of 10CFR100.
Action Statement 3.6.2.3a requires:
With one group of CFCU's inoperable and both contain-ment spray systems operable, restore the inoperable group of cooling fans to operable status within 7 days, or be in at least hot standby within the next I 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l Action Statement 3.6.2.3b requires:
With two groups of containment cooling fans inoperable, restore at least one group of cooling fans to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Because the leakage was immediately isolated, containment integrity was maintained. Containment cooling capability was provided by the containment spray systems. The occurrence, therefore, involved no risk to the health or safety of the public. Due to the loss of redundancy in design and engineered safety features, the event constituted operation in a degraded mode permitted by the limiting
( conditions for operation.
CORRECTIVE ACTION:
As noted, the leakage was immediately isolated and prompt noti-fication of the NRC was performed in accordance with Technical Specification 6.9.1.8. The leaking coil was repaired with Belzona metal filler, and No. 22 CFCU was satisfactorily tested.
No. 22 CFCU was declared operable at 1852 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.04686e-4 months <br />, September 16, 1982, and Action Statement 3.6.2.3b was terminated. Since No. 21 CFCU was still inoperable, Action Statement 3.6.2.3a remained in effect.
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LER 82-103/0lT ' CORRECTIVE ACTION: (continued)
Design Change Request 2EC-0505 has been issued to replace the CFCU cooling coils with coils manufactured of AL-6X steel, for
. improved erosion and corrosion resistance in the service water j environment. This change is scheduled for implementation during the next. refueling outage. A commitment to submit a Supplemental Report-upon completion was made in LER 82-070/0lT.
FAILURE DATA:
A number of containment service water leaks due to similar failures of CFCU cooling coils have occurred since January 1, 1982.
Westinghouse Electric Corporation Containment Fan Coil Unit
' U-Tube Cooling Coil Prepared By R. Frahm /
Generai Manager -
Salem Operations SORC Meeting No. 82-85 l
.,w. ..
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05000311/LER-1982-001, Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed | Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed | | 05000272/LER-1982-002, Supplemental LER 82-002/01X-2:on 820119,during Surveillance, Indications of Tube Thinning Detected by Eddy Current Exam. Tubes Above 30% Degradation Plugged.Tube R44C62 Sent to Westinghouse for Chemical & Metallurgical Testing | Supplemental LER 82-002/01X-2:on 820119,during Surveillance, Indications of Tube Thinning Detected by Eddy Current Exam. Tubes Above 30% Degradation Plugged.Tube R44C62 Sent to Westinghouse for Chemical & Metallurgical Testing | | 05000311/LER-1982-002, Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Vo | Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Voltage | | 05000272/LER-1982-003 | LER 82-03L/031-0:on 820502,while Testing Valve 11SW122, Safeguards Equipment Control Cabinet Actuation Occurred. Caused by Locked Out Supply Breaker to Safety Injection Pump 11,due to Spurious Nature of Actuation | | 05000311/LER-1982-004, Forwards LER 82-004/03X-1.Detailed Event Analysis Encl | Forwards LER 82-004/03X-1.Detailed Event Analysis Encl | | 05000272/LER-1982-004, Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration | Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration | | 05000272/LER-1982-005, Forwards LER 82-005/01X-1.Detailed Event Analysis Encl | Forwards LER 82-005/01X-1.Detailed Event Analysis Encl | | 05000272/LER-1982-007, Forwards LER 82-007/01X-2 | Forwards LER 82-007/01X-2 | | 05000272/LER-1982-008, Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added | Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added | | 05000272/LER-1982-009, Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage | Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage | | 05000272/LER-1982-011, Forwards LER 82-011/03X-1.Detailed Event Analysis Encl | Forwards LER 82-011/03X-1.Detailed Event Analysis Encl | | 05000311/LER-1982-012, Forwards LER 82-012/03X-1.Detailed Event Analysis Encl | Forwards LER 82-012/03X-1.Detailed Event Analysis Encl | | 05000272/LER-1982-014 | LER 82-014/03L-0:on 820306,wind Speed Indications for 150 & 300-ft Elevations Failed.Local Indications Also Failed. Caused by iced-up Anemometers.Anemometers Thawed & Declared Operable | | 05000311/LER-1982-015, Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor Trip | Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor Trip | | 05000272/LER-1982-015, Forwards LER 82-015/03L-0.Detailed Event Analysis Encl | Forwards LER 82-015/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-016, Forwards LER 82-016/03L-0.Detailed Event Analysis Encl | Forwards LER 82-016/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-017, Supplemental LER 82-017/03X-1:on 820228,svc Water Flow Indicated Zero Upon Starting Containment Fan Coil Unit 22 (Cfcu).On 820301,svc Water Flow to Cfcu 23 Less than Required 2,500 Gpm.Caused by Stuck Valve | Supplemental LER 82-017/03X-1:on 820228,svc Water Flow Indicated Zero Upon Starting Containment Fan Coil Unit 22 (Cfcu).On 820301,svc Water Flow to Cfcu 23 Less than Required 2,500 Gpm.Caused by Stuck Valve | | 05000272/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-018 | LER 82-018/03L-0:on 820304,steam Generator 24 Feedwater Channel 2 Flow Indicator Failed.Caused by Failure of Force Motor in Flow Transmitter.Transmitter Properly Repaired, Calibr & Returned to Svc | | 05000272/LER-1982-018, Forwards LER 82-018/01T-0.Detailed Event Analysis Encl | Forwards LER 82-018/01T-0.Detailed Event Analysis Encl | | 05000311/LER-1982-019 | LER 82-019/03L-0:on 820307,undervoltage Condition in Safeguards Equipment Control Cabinet Caused Mod 1 2A Sec Actuation.Caused by Failure of Card File Assembly.Card File Assembly Replaced & Loads Secured.Sys Returned to Svc | | 05000311/LER-1982-020, Forwards LER 82-020/03L-0.Detailed Event Analysis Encl | Forwards LER 82-020/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-021, Forwards LER 82-021/03L-0.Detailed Event Analysis Encl | Forwards LER 82-021/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-022, Forwards LER 82-022/03L-0.Detailed Event Analysis Encl | Forwards LER 82-022/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-024, Supplemental LER 82-024/03X-1:on 820410,svc Water Flow to Containment Fan Coil Unit 12 Discovered to Be Less than Required 700 Gpm.Caused by Valve 12SW223 Being Stuck in Closed Position.Valve Exercised | Supplemental LER 82-024/03X-1:on 820410,svc Water Flow to Containment Fan Coil Unit 12 Discovered to Be Less than Required 700 Gpm.Caused by Valve 12SW223 Being Stuck in Closed Position.Valve Exercised | | 05000311/LER-1982-024, Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added | Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added | | 05000311/LER-1982-025, Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-025, Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-027, Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State | Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State | | 05000272/LER-1982-028, Corrected LER 82-028/03L-0:on 820425,both Channels of Refueling Water Storage Tank (RWST) Level Indication Showed Less than Min Vol.Caused by Refilling Spent Fuel Pool. Makeup to RWST Initiated | Corrected LER 82-028/03L-0:on 820425,both Channels of Refueling Water Storage Tank (RWST) Level Indication Showed Less than Min Vol.Caused by Refilling Spent Fuel Pool. Makeup to RWST Initiated | | 05000311/LER-1982-028, Forwards LER 82-028/01X-1.Detailed Event Analysis Encl | Forwards LER 82-028/01X-1.Detailed Event Analysis Encl | | 05000272/LER-1982-029, Supplemental LER 82-029/03X-1:on 820501,during Surveillance Testing,Svc Water Flow to Containment Fan Coil Unit 12 Discovered Less than Required 2,500 Gallons Per Minute for Low Speed.Caused by Stuck Flow Control Valve | Supplemental LER 82-029/03X-1:on 820501,during Surveillance Testing,Svc Water Flow to Containment Fan Coil Unit 12 Discovered Less than Required 2,500 Gallons Per Minute for Low Speed.Caused by Stuck Flow Control Valve | | 05000311/LER-1982-029, Forwards LER 82-029/03L-0.Detailed Event Analysis Encl | Forwards LER 82-029/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-030, Forwards LER 82-030/03L-0.Detailed Event Analysis Encl | Forwards LER 82-030/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-031, Forwards LER 82-031/03L-0.Detailed Event Analysis Encl | Forwards LER 82-031/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-031, Forwards LER 82-031/03L-0.Detailed Event Analysis Encl | Forwards LER 82-031/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-032, Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-032, Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-033, Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-033, Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-034, Forwards LER 82-034/03L-0.Detailed Event Analysis Encl | Forwards LER 82-034/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-035, Forwards LER 82-035/03L-0.Detailed Event Analysis Encl | Forwards LER 82-035/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-035, Supplemental LER 82-035/99X-1:on 820526,fire Pump 2 Failed to Start.Caused by Damaged Fire Pump Electrical Sys Voltage Regulator/Alternator,Due to Faulty Wiring Harness.Damaged Components Replaced | Supplemental LER 82-035/99X-1:on 820526,fire Pump 2 Failed to Start.Caused by Damaged Fire Pump Electrical Sys Voltage Regulator/Alternator,Due to Faulty Wiring Harness.Damaged Components Replaced | | 05000272/LER-1982-036, Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-036, Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-037, Forwards LER 82-037/03L-0.Detailed Event Analysis Encl | Forwards LER 82-037/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-037, Forwards LER 82-037/03L-0.Detailed Event Analysis Encl | Forwards LER 82-037/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-038, Forwards LER 82-038/03L-0.Detailed Event Analysis Encl | Forwards LER 82-038/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-038, Forwards LER 82-038/03L-0.Detailed Event Analysis Encl | Forwards LER 82-038/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-039, Forwards LER 82-039/01T-0.Detailed Event Analysis Encl | Forwards LER 82-039/01T-0.Detailed Event Analysis Encl | |
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