Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2411999-04-22022 April 1999 Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics ML18107A1841999-04-14014 April 1999 Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl ML18107A1981999-04-12012 April 1999 Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202 ML18107A1691999-04-12012 April 1999 Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept ML18106B1491999-04-0505 April 1999 Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML18107A2201999-03-30030 March 1999 Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML18095A4881990-09-17017 September 1990 Requests Regional Waiver of Compliance from Tech Spec 3.6.2.3, Containment Cooling Sys. Waiver Requested in Order to Allow Replacement of Containment Fan Cooler Unit Motor #22 W/O Requiring Plant Shutdown ML18095A4901990-09-13013 September 1990 Provides Supplemental Info Applicable to Clarification of 10CFR50,App R Exemption Request Re Fire Suppression Sys for Panel 335,per NRC Request ML20059E6821990-09-0404 September 1990 Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld ML18095A4641990-08-31031 August 1990 Forwards Revised Response to NRC Bulletin 88-004 Re Potential pump-to-pump Interaction.Util Pursuing Permanent Solution to Issue & Will Implement Appropriate Permanent Field Change by End of Unit 1 10th Refueling Outage ML18095A4621990-08-31031 August 1990 Provides Revised Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Only HXs Exhibiting Unsatisfactory Test Results Will Be Inspected & Possibly Cleaned ML18095A4431990-08-30030 August 1990 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Rev 6 to Odcm. ML18095A4531990-08-30030 August 1990 Forwards RERR-28, Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revised Odcm.W/O Revised ODCM ML18095A4391990-08-29029 August 1990 Forwards Semiannual Rept Re fitness-for-duty Performance Data for 6-month Period Ending 900630,per 10CFR26.71(d).Rept Includes Testing Results,Random Testing Program Results & Confirmed Positive Tests for Specific Substances ML18095A4421990-08-28028 August 1990 Clarifies 900710 Request for Amends to Licenses DPR-70 & DPR-75,changing Sections I & M.Under Proposed Change,Section I Should Be Changed to Read Section 2.J for License DPR-70 & Section M Changed to Read Section 2.N for License DPR-75 ML20059B6611990-08-22022 August 1990 Confirms That 10 Anchor/Darling Model S350W Swing Check Valves Installed at Plant,Per NRC Bulletin 89-002.All 18 Valves Inspected & Retaining Block Studs Replaced W/Upgraded Matl.No Crack Noted on Any Studs Which Were Replaced ML20059C2861990-08-21021 August 1990 Provides Correction to 900810 Response to Request for Addl Info Re Util Request for Restatement of OL Expiration Dates ML18095A4151990-08-10010 August 1990 Forwards Response to Request for Addl Info Re Reinstatement of OL Expiration Dates Based on Original Issuance of Ols. Advises That Correct Expiration Date for OL Proposed to Be 200418 ML18095A4091990-08-0909 August 1990 Forwards Responses to NRC Comments Re Plant Simulator Certification for 10CFR55.45(b)(2),per 891228 Ltr ML18095A4061990-08-0808 August 1990 Forwards Corrected marked-up Pages for Tech Spec Table 3.3-11 Re Subcooling Margin Monitor & Reactor Vessel Level Instrumentation Sys,Per 900223 Ltr.Administrative Changes Made as Indicated ML18095A3861990-07-30030 July 1990 Forwards Listing of Station Blackout Major Audit Items Resolution Scope,Per Station Blackout Schedule Commitment ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML18095A3751990-07-18018 July 1990 Provides Status of Commitments Made to NRC by Util in 900109 Ltr Re NUREG-0737,Item II.D.1,per 900628 Telcon ML18095A3741990-07-18018 July 1990 Provides Supplemental Info Re Facility sub-cooling Margin Monitor ML18095A3611990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML18095A3621990-07-18018 July 1990 Forwards Corrected Tech Spec Page 3/4 3-5 for License Change Request 89-12 Submitted on 891227 & 900521 ML18095A3591990-07-13013 July 1990 Corrects Typo in 900702 Response to Generic Ltr 90-04 Re Schedule for Completion of Remaining Open Items ML18095A3471990-07-11011 July 1990 Responds to NRC 900611 Ltr Re Violations Noted in Insp Repts 50-272/90-14 & 50-311/90-14.Corrective Actions:Directive from Radiation Protection Mgt to All Radiation Protection Personnel Issued Re Control of Compliance Agreement Sheets ML18095A3451990-07-10010 July 1990 Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation ML18095A3461990-07-10010 July 1990 Responds to NRC 900608 Ltr Re Violations Noted in Insp Repts 50-272/90-12 & 50-311/90-12.Corrective Actions:Assessment of ECCS & Component Performance Undertaken & ECCS Flow Testing Procedure Upgraded to Address Human Factors ML18095A3491990-07-10010 July 1990 Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002 ML18095A3481990-07-10010 July 1990 Submits Supplemental Rept Identifying Root Cause of Missed Commitment & Corrective Actions to Assure Future Compliance Re Implementation of Mods to Facility PASS ML18095A3441990-07-0909 July 1990 Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification ML18095A3281990-07-0202 July 1990 Responds to NRC 900530 Ltr Re Violations Noted in Insp Repts 50-272/90-09 & 50-311/90-09.Corrective Actions:Util Intends to Use Nuclear Shift Supervisor as Procedure Reader & EOP, Rev 2 Under Development ML18095A3301990-07-0202 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues.Table Describing Status of Generic Safety Issue Implementation Encl ML18095A3391990-06-29029 June 1990 Forwards Correction to 890913 License Change Request 88-09, Consisting of Tech Spec Page 3/4 4-13 ML18095A3221990-06-28028 June 1990 Provides Supplemental Info Re 900223 Proposed Revs to Tech Specs for Reactor Vessel Level Instrumentation Sys.Tables 3.3-11a & 3.3-11b Should Be Combined Into Single Table ML18095A3231990-06-28028 June 1990 Responds to NRC 900518 Ltr Re Violations Noted in Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07.Two Noncited Violations Disputed.Util fitness-for-duty Program Exceeds Part 26 Requirements for Positive Blood Alcohol Limits ML18095A3241990-06-28028 June 1990 Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout ML18095A3161990-06-25025 June 1990 Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613 ML18095A3141990-06-25025 June 1990 Provides Schedule Change for Implementation of Control Room Mods.Schedule Modified to Address Overhead Annunciator Human Engineering Discrepancies During Phase III ML18095A3201990-06-25025 June 1990 Responds to NRC 900524 Ltr Re Violations Noted in Insp Repts 50-272/90-11 & 50-311/90-11.Corrective Actions:All Overdue Operations & Maint Procedure Files Reviewed for Outstanding Rev Requests & Procedure Upgrade Program Initiated ML18095A3001990-06-20020 June 1990 Provides Addl Info Re Application for Amend to Licenses DPR-70 & DPR-75 Concerning Turbine Valve Surveillance Interval,Per 900320 Request.Util Adding Direction to Personnel If Unnacceptable Flaws Found ML20043H6221990-06-20020 June 1990 Provides Supplemental Info Re NRC Bulletin 88-008 for Fifth Refueling Outage.Detailed Test Rept Being Prepared to Document Results of Each Individual Insp Re Insulation, Hangers & High Energy Break Areas ML18095A2991990-06-20020 June 1990 Forwards Westinghouse Affidavit Supporting 900412 Request for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790 ML18095A2721990-06-0808 June 1990 Responds to NRC 900329 Ltr Re Weaknesses Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Corrective Actions:Fire Doors Placed on Blanket Preventive Maint Work Order & Damaged Fire Doors Will Be Repaired Immediately ML18095A2711990-06-0606 June 1990 Submits Info in Support of 900522 Verbal Request for Relief from Requirements of ASME Section XI ML18095A2611990-06-0101 June 1990 Forwards Corrected Operating Data Rept, Page for Apr 1990 Monthly Operating Rept ML18095A2521990-06-0101 June 1990 Forwards Application in Support of Request for Renewal of NJPDES Permit NJ0005622,per Requirements of Subsection 3.2 of Plant Environ Protection Plan,Nonradiological ML18095A2591990-06-0101 June 1990 Forwards Corrected Unit Shutdown & Power Reductions, Page for Apr 1990 Monthly Operating Rept ML18095A2411990-05-30030 May 1990 Submits Special Rept 90-4 Addressing Steam Generator Tube Plugged During Fifth Refueling Outage.Plugging Completed on 900516.Cause of Tube Degradation Attributed to Normal Wear Due to Erosion/Corrosion Factors ML18095A2431990-05-30030 May 1990 Informs of Util Plans Re Facility Cycle 6 Reload Core, Expected to Achieve Burnup of 16600 Mwd/Mtu.All Postulated Events within Allowable Limits Based on Review of Basis of Cycle 6 Reload Analysis & Westinghouse SER ML18095A2531990-05-29029 May 1990 Provides Addl Info Re End of Life Moderator Temp Coefficient.Feedback Used in Steam Line Break Has No Relationship to Full Power Moderator Density Coefficient 1990-09-04
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. s O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station May 6, 1982 Mr. J. Allan Acting Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 Dear Mr. Allan LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 83-013/03L Pursuant to the requirements of Salem Generating Station Unit No. 2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 83-013/03L. This report is required within thirty (30) days of the occurrence.
Sincerely yours, 4f U/l
General Manager -
Salem Operations RF:kshd[
CC: Distribution 8305160052 830506 PDR ADOCK 05000311 8 PDR The Energy People p-(fr2!h # Cr '! 1181
O Report Number: 83-013/ 03L 1 Report Date: 05-04-83 Occurrence Date: 04-09-83 Facility: Salem Generating Station Unit 2 4
Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE: r Reactivity Control Systems - No. 22 Charging Pump - Inoperable.
This report was initiated'by Incident Report 83-067.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 6 - RX Power 0 % - Unit Load 0 MWe.
DESCRIPTION OF OCCURRENCE:
At 1618 hours0.0187 days <br />0.449 hours <br />0.00268 weeks <br />6.15649e-4 months <br />, April 9, 1983, du' ring routine shutdown operation, an operator observed increasing lube oil temperatures on No. 22 Charging Pump. At the time of the occurrence. the redundant charging pumps were unavailable due to maintenance activities associated with the shutdown. No. 22 Charging Pump was declared inoperable and Technical Specification Action Statement 3.1.2.3 was entered.
Investigation of the problem indicated that service water flow was 1
being restricted to the charging pump as well as several other safety-related components; the components were all supplied by a common 4 inch branch of the No. 21 Service Water Header. Other components affected included No. 21 Containment Spray Pump Room Cooler, No. 22 Charging Pump Room Cooler, No. 21 Safety Injection Pump Lube Oil Cooler, and No. 21 Residual Heat Removal Pump Room Cooler.
Suspecting the flow may be restricted by shells of American oysters released during maintenance and cleaning of portions of the service water system earlier in the shutdown period, a backflush of the affected components was performed. The backflush path was through the 4 Service Water System auxiliary feedwater pump cross-connect line.
Upon opening the cross-connect line, silt was observed deposited in the end of the line; the silt and approximately 1/2 cubic feet of shells of oysters and other miscellaneous mollusks were removed in the process of flushing the line.
All operations involving core alteration and positive reactivity changes were suspended until the backflushing operation was completed j and No. 22 Charging Pump was restored to an operable status.
Several weeks later, on April 21, 1983, investigation of a high jacket water temperature condition on No. 2C Emergency Diesel Generator revealed loose shells in the diesel jacket water and lube oil coolers.
The diesel is also supplied by No. 21 Service Water Header, which had been completely rafilled following the previous flushing evolution.
LER 83-013/03L DESCRIPTION OF OCCURRENCE: (cont'd)-
i No; problems were evident with Nos. 2A and 2B Diesel Generators.
t however, and surveillance'of the generators has been satisfactorily
' completed to date (No. 2A Diesel Generator is normally supplied byDNo.
22 Service Water Header). Only two' operable generators are required by the Technical Specifications during shutdown' operation, and therefore compliance with the applicable limiting condition for operation was maintained.
APPARENT CAUSE OF OCCURRENGE:
In both cases the reduced service water flow was evidently caused by mollusk shells plugging the tubes of the coolers. Both living i organisms and unattached shells were. observed in the backflushes.
Specimens of shells collected were unusually thin, and appeared to have=been subjected to erosion.
1 Although problems with oysters restricting flow to the containment fan-coil units (CFCUs) have been previously noted (see LERs 82-041/03L, 82-046/03L, 82-049/03L, 82-050/03L, 82-058/03L, and 82-117/03L). the i events were random and .relatively low in frequency. No problems with I other safety related components had been observed during previous operation of-the unit. -
As-noted in previous reports, oyster spat were apparently-drawn into e the Service Water System during operation, and were able to pass through the' system strainers. They cemented themselves to piping i walls in areas of moderate or reduced flow and developed . shells. The 4 -oysters or shells-were evidently released somewhat randomly during i . system operational events (pump shif ts, lineup changes, etc.) and
- . periodic chlorinations. The top shells of dead organisms would also be carried away following decay of the' hinge.
Due to.the previous problems, the No. 21 Service Water Header had been
' drained'and manually cleaned where accessible. The 8' inch ~ header upstream of all components involved except the. diesels'had been hydrolazed prior to the incident. . Shells had been removed from.the
. header, and reverse flow of the hydrolazing' nozzle would likely have deposited a.small volume of the shells in the 4 inch branch line which
! supplied the components. It was not possible to prevent ~a small amount of shells from entering the line, and it was assumed that the l amount involved would have no significant impact on operating-equipment.
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, According to the Environmental Department and biological consultants, i living oysters removed by hydrolazing would likely survive in an unattached state. Draining of major portions of the header may have resulted: in mortality of some oysters; increased mortality would also occur in stagnant portions of the system. Refilling and restoration
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of the system to operation could then result in the release of some I top shells and carrying of unattached live organisms into portions of i
the system which were normally trouble-free. It should be noted that
'the problems are apparently related to shutdown activities and are not likely to occur during operation at power.
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.LLER 83-013/03L APPARENT CAUSE'OF 0CCURRENCE: (cont'd)
Settling of ' silt in low 1 flow portions of the service water system has also1been documented, particularly in the case of plugging of CFCU -
flow' transmitter. sensing lines (see LERs 82-028/01X-1 and 82-038/03L).
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The presence of silt in the normally blanked auxiliary feedwater pump '
supply cross-connect-line is consistent with previously observed problems.
ANALYSIS OF OCCURRENCE:
' Operability of the Service Water System ensures that sufficient cooling. capacity is available for. continued operation of safety related equipment during accident conditions. A boron injection system is required to be operable during Mode 6 operations to insure reactivity control. capability is maintained.
The Auxiliary Feedwater System ensures that the Reactor' Coolant System can.be. cooled to less than~350 F from normal operating conditions, in the event of a total loss of offsite power. The cross-connect to the Auxiliary Feedwater System is required to be available in.30 minutes in the event of a complete loss of A.C. power coincident with tornado missile damage to all redundant-normal auxiliary feedwater supplies (auxiliary feedwater storage tank, demineralized water storage tanks, and fire protection / domestic water storage tanks).
As mentioned, the . occurrences were apparently. the result of shutdown maintenance activities, and would.not have likely occurred during operation in; elevated moder. Based on the initial results of an evaluation by the system Sponsor. Engineer, - the silt present in the auxiliary'feedwater supply cross-connect would not have interfered.
with the availibility of the supply or the proper function of the Auxiliary Feedwater System.
Action. Statement'3.1.2.3 applies in-Mode 6 and' requires:
With no charging pump operable, suspend all operations involving core alterations or positive reactivity changes until at least one charging pump is restored to' operable status.
As-noted no core alterations or reactivity changes were conducted. . in compliance with the action statement. Due to this and the general confinement of the problems to shutdown modes. no risk to the health or safety of the ' public was involved. Because of operation in a degraded mode permitted by a limiting condition for operation, the occurrence is reportable in accordance with Technical Specification 6.9.1.9b.
.- CORRECTIVE ACTION:
~As stated, core alterations and reactivity changes were suspended
.during inoperability of the charging pump. Remedial action was taken to clean or flush out the shells-from the portions of the Service Water System involved. At 1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br />, April 10, 1983, No. 22 Charging Pump was restored'to operation and was satisfactorily tested. The pump was declared operable and Action Statement 3.1.2.3 was w.-..- - - - - - , - - , - . ,an-,.- _ . . . -e.-,,---.-e. %m--.-%,-.,ww.w ..-----.--,*--wc,%,,-e, -=----,---,,,,=e%,-,mo---w--,---wm 9w e,- c, 3,-w e t , , v ,, .-y
- LE'R 83-013/03L CORRECTIVE ACTION: (cont'd) terminated. The other safety related components involved were also satisfactorily tested and demonstrated to be operable.
Development of a chlorination program to fully eliminate the oysters from the Service Water System and to prevent reinfestation is in progress. Design Change Request 2EC-1327 has been submitted to provide continuous chlorine monitoring at the Circulating Water System discharge. The modification will allow increased levels and durations of chlorination.
Due to concern over the overall problem of oysters in the Service Water System, a formal Safety Evaluation will be performed prior to the unit startup. Initial results of engineering investigation indicate that operation may safely proceed with only minor modification of the existing chlorination program. A one-time, increased chlorination will be performed to kill soft-bodied organisms, followed by a flush and inspection of the system. Any plugged components will be cleaned as necessary. A commitment to submit a Supplemental Report upon resolution of the oyster problem in general was made in LER 82-041/03L.
With respect to the accumulation of silt in the Auxiliary Feedwater System supply cross-connect, a Design Change Request will be issued to relocate the cross-connect isolation valve to eliminate future deposition of silt in the line.
FAILURE DATA:
Not Applicable Prepared By R. Frahm I 4N! # /
/ ' G6neral Manager -
F Salem Operations SORC Meeting No.83-060 l
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05000311/LER-1983-001, Forwards LER 83-001/03L-0.Detailed Event Analysis Encl | Forwards LER 83-001/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-002, Forwards LER 83-002/03L-0.Detailed Event Analysis Encl | Forwards LER 83-002/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl | Forwards LER 83-003/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-003, Forwards LER 83-003/04L-0.Detailed Event Analysis Encl | Forwards LER 83-003/04L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-004, Forwards LER 83-004/04L-0.Detailed Event Analysis Encl | Forwards LER 83-004/04L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-004, Forwards LER 83-004/03L-0.Detailed Event Analysis Encl | Forwards LER 83-004/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-005, Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-006, Forwards LER 83-006/03L-0.Detailed Event Analysis Encl | Forwards LER 83-006/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-007, Forwards LER 83-007/03L-0.Detailed Event Analysis Encl | Forwards LER 83-007/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-007, Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days | Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days | | 05000311/LER-1983-008, Forwards LER 83-008/99X-0.Detailed Event Anaysis Encl | Forwards LER 83-008/99X-0.Detailed Event Anaysis Encl | | 05000272/LER-1983-008, Supplemental LER 83-008/03X-1:on 830311,pressurizer Code Safety Valves 1PR3,1PR4 & 1PR5 Exceeded Lift Set Pressure Range & Had Heavy Seat Leakage.Partly Caused by Difference in Test Vs Actual Operating Conditions | Supplemental LER 83-008/03X-1:on 830311,pressurizer Code Safety Valves 1PR3,1PR4 & 1PR5 Exceeded Lift Set Pressure Range & Had Heavy Seat Leakage.Partly Caused by Difference in Test Vs Actual Operating Conditions | | 05000311/LER-1983-009, Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-009, Forwards LER 83-009/99X-0.Detailed Event Analysis Encl | Forwards LER 83-009/99X-0.Detailed Event Analysis Encl | | 05000311/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-011, Forwards LER 83-011/01T-0.Detailed Event Analysis Encl | Forwards LER 83-011/01T-0.Detailed Event Analysis Encl | | 05000311/LER-1983-011, Forwards LER 83-011/03L-0.Detailed Event Analysis Encl | Forwards LER 83-011/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-012, Telecopy Message of LER 83-012/01P-0:on 830222,both Reactor Trip Breakers Failed to Open.Cause Not Yet Determined. Investigation Underway | Telecopy Message of LER 83-012/01P-0:on 830222,both Reactor Trip Breakers Failed to Open.Cause Not Yet Determined. Investigation Underway | | 05000311/LER-1983-012, Forwards LER 83-012/03L-0.Detailed Event Analysis Encl | Forwards LER 83-012/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-013, Forwards LER 83-013/99T-0.Detailed Event Analysis Encl | Forwards LER 83-013/99T-0.Detailed Event Analysis Encl | | 05000272/LER-1983-014, Forwards LER 83-014/03L-0.Detailed Event Analysis Encl | Forwards LER 83-014/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-015, Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-015, Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-016, Forwards LER 83-016/03L-0.Detailed Event Analysis Encl | Forwards LER 83-016/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-017, Supplemental LER 83-017/03X-1:on 810515,during Startup & Cycle 1 Operations,Leakage Past Pressurizer PORVs & Pressurizer Overpressure Protection Sys Values Observed. Cause Not Stated.Porvs Modified | Supplemental LER 83-017/03X-1:on 810515,during Startup & Cycle 1 Operations,Leakage Past Pressurizer PORVs & Pressurizer Overpressure Protection Sys Values Observed. Cause Not Stated.Porvs Modified | | 05000272/LER-1983-017, Forwards LER 83-017/03L-0.Detailed Event Analysis Encl | Forwards LER 83-017/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-018, Forwards LER 83-018/03L-0.Detailed Event Analysis Encl | Forwards LER 83-018/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-023, Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired | Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired | | 05000272/LER-1983-023, Supplemental LER 83-023/01X-1:on 830602,notification Received from Westinghouse of Potential Unreviewed Safety Question Re Operation at Full Power Following Extended Reduced Power Operation.Procedures Implemented | Supplemental LER 83-023/01X-1:on 830602,notification Received from Westinghouse of Potential Unreviewed Safety Question Re Operation at Full Power Following Extended Reduced Power Operation.Procedures Implemented | | 05000272/LER-1983-062, Supplemental LER 83-062/99X-1:on 831122,during Testing on Seismic Instrumentation,Triaxial Time History Accelograph Did Not Respond as Required.Caused by Detector Failure. Accelerometer Replaced | Supplemental LER 83-062/99X-1:on 831122,during Testing on Seismic Instrumentation,Triaxial Time History Accelograph Did Not Respond as Required.Caused by Detector Failure. Accelerometer Replaced | | 05000311/LER-1983-083, Forwards Supplemental LER 83-083/03X-1.Detailed Event Analysis Encl | Forwards Supplemental LER 83-083/03X-1.Detailed Event Analysis Encl | |
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