ML18094A540
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| ML18094A540 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/16/1989 |
| From: | Bruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-88-003, IEB-88-3, NLR-N89121, NUDOCS 8906300020 | |
| Download: ML18094A540 (3) | |
Similar Documents at Salem | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999
[Table view]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 Category:INCOMING CORRESPONDENCE MONTHYEARML18107A5601999-10-18018 October 1999
[Table view]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 Category:NRC TO UTILITY MONTHYEARML20059M9281990-06-13013 June 1990
[Table view]Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20246J5581989-08-28028 August 1989 Grants 890609 & 16 Requests for Withholding of Rev 0 to TR-ESE-737 from Public Disclosure Per 10CFR2.790 ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20245B2811989-06-19019 June 1989 Ack Receipt of & Payment of Civil Penalty in Amount of $50,000,per NRC .Region I Will Review Info Provided Re Limitorque Gear Case Grease Relief Example of Violation & Provide Separate Response ML18094A5401989-06-16016 June 1989 Fowards Response to NRC Bulletin 88-003 Re Potential Inadequate Latch Engagement in GE Hfa latching-type Relays. Until alternative-type Relays Available,Spare GE Hfa Relays Ordered for Replacement in-kind Applications ML20247A7781989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl ML20151Z2391988-08-25025 August 1988 Forwards Request for Addl Info Re 880227 Request for Exemptions to Allow Util to Take Credit for Respirators Fitted W/Sorbent Cartridges for Protection Against Airborne Radioidine.Response Requested within 30 Days ML20151B2481988-03-31031 March 1988 Forwards Enforcement Conference Rept 50-311/87-29 on 880212 Re Findings in Insp Rept 50-311/87-29 ML20148G5021988-03-22022 March 1988 Forwards Safeguards Insp Repts 50-272/88-06,50-311/88-06 & 50-354/88-04 on 880201-05.No Violations Noted ML20154D4221988-03-21021 March 1988 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-272/83-37. Violations Occurred as Stated in Notice of Violation & Appropriately Classified in Aggregate at Severity Level III ML20237F1231987-12-16016 December 1987 Ack Receipt of Informing NRC of Actions Taken to Correct Violations Noted in Insp Repts 50-272/87-21 & 50-311/87-26 ML20236P4951987-11-12012 November 1987 Forwards Exam Repts 50-272/87-26OL & 50-311/87-26OL for Exams Administered on 870915-17 ML20236G1551987-10-28028 October 1987 Forwards Safety Insp Rept 50-272/87-27 on 870921-25.No Violations Noted ML20238A8771987-08-31031 August 1987 Recommends That Site Specific Info Sheets & Appropriate Training Re Use Be Developed & Provided to Emergency Notification Sys & Health Physics Network Communicators to Facilitate Responses to NRC Requests for Data.Samples Encl ML20237H1641987-08-25025 August 1987 Forwards Requalification Program Evaluation Repts 50-272/87-21OL & 50-311/87-26OL of Exam Administered During Wk of 870615.Requalification Training Program Found Unsatisfactory,Per NUREG-1021 ML20237H5441987-08-12012 August 1987 Forwards Results of Nonradiological Chemistry Stds Insp Activities for All Region I Licensees During 1985-1986. Results of Measurements Made by BNL Also Included ML20236G9631987-07-29029 July 1987 Ack Receipt of Util Transmitting Proposed Amend to Plant Physical Security Plan.Addl Info,Including Commitment to Ensure Prompt Access to Vital Equipment During Emergenies & Revs to Plan,Requested Prior to NRC Approval ML20235H3711987-06-30030 June 1987 Advises That 861202 Miscellaneous Amend Changes to Security, Safeguards Contingency Plan & Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Requests Response to Unacceptable Portions within 30 Days IR 05000272/19830371987-06-15015 June 1987 Discusses Insp Rept 50-272/83-37 on 831205-06 & Forwards Notice of Violation ML20214S8001987-06-0404 June 1987 Forwards NRC Form 398 Re Personal Qualifications Statement for Licensee,Reflecting Changes to 10CFR55,effective 870526. Revised Form Requires New Applicants to Complete Each Category Completely.Form to Be Used Beginning 870526 ML20205G0571987-03-24024 March 1987 Forwards Insp Repts 50-272/87-05 & 50-311/87-07 on 870224-27.No Violations Identified ML20204G7891987-03-20020 March 1987 Advises That 870130 Temporary Change to Salem & Hope Creek Security Plans Re Compensatory Measures to Be Implemented During Training of Security Supervisors for 870202-27 Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20205E9371987-03-20020 March 1987 Forwards Exam Rept 50-311/87-06OL of Exam Administered on 870213.Concern Expressed Re Adequacy of Training Due to Lack of Sufficient Understanding of Unique Requirements of Facility Tech Specs ML20204E7631987-03-19019 March 1987 Informs That 861230 Rev 5 to QA Program Description Acceptable.Omission in Figure 17.2-1 of Original Submittal Clarified ML20207S4981987-03-17017 March 1987 Requests Remittance of Fee for 861231 Application Requiring Review & Approval of Proposed Corporate Reorganization of Atlantic City Electric Co ML20207S4041987-03-12012 March 1987 Forwards Safety Insp Repts 50-272/87-03 & 50-311/87-04 on 870127-0223 & Notice of Violation ML20207S3181987-03-11011 March 1987 Forwards Mgt Meeting Repts 50-272/86-23 & 50-311/86-23 on 870203.Three Potential Enforcement Items Identified ML20207S2901987-03-10010 March 1987 Forwards Insp Rept 50-311/87-05 on 870203-06.No Violations Observed ML20212J2161987-03-0202 March 1987 Forwards Safety Evaluation & Technical Evaluation Rept Re Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys On-Line Functional Testing. Response Acceptable ML20212F1251987-02-27027 February 1987 Forwards Corrected SALP Repts 50-272/85-98 & 50-311/85-98 for Oct 1985 - Sep 1986.Attendees List of 870218 Mgt Meeting W/Util Encl.Believes That Addl Attention Needed to Reduce Number of Challenges to Safety Sys ML20212B9031987-02-25025 February 1987 Forwards Insp Repts 50-272/87-02 & 50-311/87-02 on 870112- 16 & Notice of Violation ML20211F5611987-02-17017 February 1987 Forwards Insp Repts 50-272/87-01 & 50-311/87-01 on 870101- 26.No Violations Observed ML20210V3801987-02-11011 February 1987 Forwards Safety Insp Rept 50-311/87-03 on 870112-23. Enforcement Conference Scheduled for 870227 to Discuss Concerns Re RHR Valve Misalignments Resulting in Inoperability of ECCS on 870112-13 ML20212R2501987-01-21021 January 1987 Forwards Exam Repts 50-272/86-27OL & 50-311/86-27OL of Exam Administered During Wk of 861103 ML20197C9571987-01-20020 January 1987 Forwards SALP Repts 50-272/85-98 & 50-311/85-98 for Oct 1985 - Sept 1986.Meeting Scheduled for 870121 to Discuss Assessment & Plans to Improve Areas Needing Mgt Attention. Requests Written Comments within 30 Days After Meeting ML20212K8501987-01-16016 January 1987 Forwards Safety Insp Rept 50-311/86-35 on 861119-27.No Violations Noted IR 05000272/19860321987-01-16016 January 1987 Forwards Safety Insp Repts 50-272/86-32 & 50-311/86-36 on 861125-1231.Licensee Identified Violations Re Failure to Complete Tech Spec Surveillance Noted.No Notice of Violation Issued,Per 10CFR2,App C ML20207N5281987-01-0909 January 1987 Forwards Safety Evaluation & Eg&G Idaho Input Reviewing Util 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Program - Reactor Trip Sys Components. Response Acceptable ML20207M4391987-01-0606 January 1987 Forwards Exam Repts 50-272/86-26OL & 50-311/86-31OL of Exams Administered on 860912 ML20211Q1821986-12-16016 December 1986 Requests Util Cooperation in Increasing NRC Resident Inspector Onsite Visibility.Inclusion of Resident Inspector Videotape in General Employee Training Requested ML20214L0601986-11-19019 November 1986 Forwards AEOD SALP Input for Facilities Operations (LER Quality) for Oct 1985 - Sept 1986.LERs Sampled of Very High Quality ML20213E9011986-11-0606 November 1986 Requests That Util Investigate Allegation of Use of Controlled Substance by Employee of Util Contractor,As Discussed in 861029 & 1104 Telcons.Response Re Veracity of Allegations & Impact on Safety Requested within 30 Days ML20213E4701986-10-29029 October 1986 Advises That 860930 Temporary Change to Security Plans, Identifying Compensatory Measures to Be Taken During Const Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Consolidated Plans Must Be Separate Amend Submittal to NRR ML20215M7421986-10-24024 October 1986 Forwards Insp Repts 50-272/86-22 & 50-311/86-22 on 860915-17.No Violations Noted.Ability to Implement Emergency Plan Demonstrated ML20211C2001986-10-14014 October 1986 Requests Review of Allegation That Previous Util Employee Identified in 861001 Telcon May Not Possess Valid Educational Credentials.Results of Review & Current Employee Screening Methods Requested within 30 Days ML20210P7451986-09-25025 September 1986 Forwards Insp Rept 50-311/86-26 on 860826-30.Proposed Actions Responding to Unresolved Items Requested within 30 Days of Ltr Receipt ML20214F6671986-09-10010 September 1986 Notifies of 861029-30 Physical Protection Seminar in Cherry Hill,Nj to Discuss Results of 12-yr Implementation of 10CFR73 for Protection Against Radiological Sabotage. Preliminary Agenda Encl ML20207J2191986-07-15015 July 1986 Forwards FEMA 44CFR350 Approval for State of DE & Local Radiological Emergency Plans,Pending Public Alert & Notification Sys Verification ML20244D9251986-05-29029 May 1986 Confirms 860610 Survey of Emergency Data Sys Capabilities for Possible Use as Part of Emergency Response Data Sys. Survey Checklist Encl ML20198S4321986-05-27027 May 1986 Forwards Exam Repts 50-272/86-09 & 50-311/86-09 Administered During Wk of 860407 1990-06-13 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M2101999-10-19019 October 1999
[Table view]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 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 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 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 ML20198H1851998-12-15015 December 1998 Responds to to President Clinton Re Rept by Gao, Issued 970530 on NRC Oversight of Nuclear Power Industry ML20198B7611998-12-0303 December 1998 Informs That on 981007,generic Fundamentals Exam Was Administered to 148 Candidates at 21 Facilities.Summary of Statistical Results of Exam Listed.Contents of Exam Along with Associated Input Data Needed for Updating Catalog Encl ML20155J7191998-11-0505 November 1998 Fourth Final Response to FOIA Request for Documents.Records Listed in App G Being Released in Entirety.Documents Listed in App H Being Withheld in Part (Ref FOIA Exemption 5) IA-98-323, First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3)1998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) ML20154P4011998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) ML20154B3781998-09-25025 September 1998 Informs That Facility Scheduled to Administer NRC Generic Fundamentals Exam on 981007.Sonalysts,Inc Authorized Under Contract to Support NRC in Administration of Activities. Ltr & Encls Provide Instructions & Guidelines ML20151V8401998-09-10010 September 1998 Informs That Util Authorized to Administer Initial Written Exams to Listed Applicants on 980917.NRC Region I Operator Licensing Staff Will Administer Operating Tests on 980914- 16 ML20151W9711998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Have Been Assigned as SRAs in Region I ML20238F1581998-08-31031 August 1998 Informs That as Result of Review of Records,Duplication of Costs Charged for Insp Conducted at Salem Unit 2 Was Found. Amount Overcollected Will Be Transferred to Licensee within 10 Days from Date of Ltr ML20249C7661998-06-26026 June 1998 Second Partial Response to FOIA Request for Documents. Documents Listed in App D,Being Released in Entirety ML20247B4141998-05-0606 May 1998 Final Response to FOIA Request for Documents.Forwards Documents Listed in App a Being Made Available in PDR IA-98-179, Final Response to FOIA Request for Documents.Forwards Documents Listed in App a Being Made Available in PDR1998-05-0606 May 1998 Final Response to FOIA Request for Documents.Forwards Documents Listed in App a Being Made Available in PDR ML20217P4601998-05-0101 May 1998 Forwards ERDS Implementation Documents Including Data Point Library Updates for Robinson (Number 248),Peach Bottom (Number 249),Surry (Number 250),Crystal River (Number 251), McGuire (Numbers 252 & 254) & Salem (Number 253).W/o Encl ML20217N5851998-04-24024 April 1998 Partially Deleted Ltr Ref 10CFR2.790 Re NRC Investigation Repts 1-96-024 & 1-96-031 Conducted at Pse&G Plants Documenting That Crowe as Cas/Sas Operator,Falsified Records of Safeguards Event Log in May 1996 ML20217N8881998-04-24024 April 1998 Partially Deleted Ltr Referring to Investigation Rept 1-96-024 Conducted at Pse&G Plant,Documenting That as Wackenhut Systems Operator Supervisor,Recipient Falsified Records of Safeguards Event Log in May 1996 ML20217N5891998-04-24024 April 1998 Refers to NRC Investigations 1-96-024 & 1-96-031 Conducted by OI Re Allegations of Deliberate Posting of Inaccurate Info in Safeguards Event Logbook & Discrimination by Wackenhut Staff.Decided to Await Issuance of DOL Decision ML20217N5491998-04-24024 April 1998 Refers to NRC Investigations 1-96-024 & 1-96-031 Conducted by OI Re Activities Performed by Wackenhut Staff Working as Contract Security Force Personnel at Salem & Hope Creek. Decided to Await Issuance of DOL Decision Re Discrimination ML20217B6341998-03-20020 March 1998 Discusses NRC OI Rept 1-96-031 & DOL Case 97-ERA-52 on 971001.Contract Security Officer Employed by Wackenhut at Salem/Hope Creek Discrimiated Against for Raising Safety Concerns ML20203F2311998-02-20020 February 1998 Ltr Contract:Task Order 136 Entitled, Salem Restart Readiness Review, Under Contract NRC-03-93-026.Statement of Work Encl IA-97-325, Seventh Final Response to FOIA Request for Documents. Documents Listed in App I Being Released in Entirety. Documents Listed in App J Being Withheld in Entirety (Ref FOIA Exemption 4,6 & 7C)1997-12-10010 December 1997 Seventh Final Response to FOIA Request for Documents. Documents Listed in App I Being Released in Entirety. Documents Listed in App J Being Withheld in Entirety (Ref FOIA Exemption 4,6 & 7C) ML20203G5611997-12-10010 December 1997 Seventh Final Response to FOIA Request for Documents. Documents Listed in App I Being Released in Entirety. Documents Listed in App J Being Withheld in Entirety (Ref FOIA Exemption 4,6 & 7C) ML20202J3211997-12-0808 December 1997 Sixth Partial Response to FOIA Request for Documents.Record Subj to Request Encl & Identified in App H ML20202B0251997-11-26026 November 1997 Fourth Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App D ML20199J1611997-11-24024 November 1997 Third Partial Response to FOIA Request for Documents. Documents Listed in App C Being Released in Entirety & Encl ML20199J1161997-11-21021 November 1997 Second Partial Response to FOIA Request for Documents. Records in App B Encl & Withheld in Part (Ref FOIA Exemption 7) ML20202D0541997-11-19019 November 1997 First Partial Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in App a ML20202B6531997-06-0606 June 1997 Discusses Investigation Conducted by NRC OI to Review Whether Pse&G Intentionally Operated Outside Design Basis & Failed to Make Timely Notification of Unanalyzed Condition Re Pops.Concluded That Pse&G Made Changes to Facility ML20140E1091997-06-0505 June 1997 Ltr Contract:Task Order 112, Salem Restart Readiness Review, Under Contract NRC-03-93-026 ML20148K0551997-06-0404 June 1997 Forwards Amends 194 & 177 to Licenses DPR-70 & DPR-75, Respectively.Amends Change TSs 3.4.3 & 3.4.5, Relief Valves, to Ensure Automatic Capability of PORVs to Relieve Pressure Is Maintained When Valves Are Isolated ML20148C3561997-05-12012 May 1997 Thirty-fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App Rrr Being Made Available in Pdr.App SSS Records Being Withheld in Part (Ref FOIA Exemption 6) ML20148C2281997-05-0808 May 1997 Ltr Contract:Task Order 126, Evaluation of Salem Restart Test Program, Under Contract NRC-03-93-026,awarded to Parameter,Inc ML20137X4881997-04-11011 April 1997 Final Response to FOIA Request for Documents.Forwards App Ee Records Being Withheld in Part (Ref Exemptions 5 & 6) ML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML20147F8381997-03-25025 March 1997 Responds to to Chairman Jackson Expressing Concerns Re NRC Confirmatory Order Suspending Authority for & Limiting Power Operation & Containment Pressure & Demand for Info, ML20137H4051997-03-24024 March 1997 Twelveth Partial Response to FOIA Request for Documents. App DD Records Being Withheld in Part (Ref Exemptions 5 & 6) ML20137A6311997-03-14014 March 1997 Third Final Response to FOIA Request for Documents.Records in App E Encl & Will Be Available in Pdr.App F Records Withheld in Part (Ref FOIA Exemption 3) ML20137A8601997-03-11011 March 1997 Second Partial Response to FOIA Request.Records Listed in App D Encl & Will Be Available in Pdr.App C Records Withheld in Entirety (Ref FOIA Exemption 5) ML20147F8591997-02-27027 February 1997 Responds to to Hj Miller Re Millstone,Salem & Myap Npps.Provides Answers to Questions Raised in to HR Meyer ML20135C0211997-02-26026 February 1997 First Partial Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in Pdr.App B Records Withheld in Entirety (Ref FOIA Exemption 5) ML20135B7551997-02-26026 February 1997 Eleventh Partial Response to FOIA Request for Documents. App AA Document Forwarded.App Bb Documents Partially Withheld (Ref FOIA Exemption 5).App CC Documents Withheld (Ref FOIA Exemption 5) ML20134P2801997-02-22022 February 1997 Ack Receipt of & Electronic Transfer of $100,000 in Payment for Civil Penalty Proposed by NRC in ML20135B9511997-02-20020 February 1997 Responds to 970113 & 30 Ltrs Requesting That Full Commission Vote to Determine Whether Plant Should Be Permitted to Resume Operations ML20134K1311997-02-11011 February 1997 Tenth Partial Response to FOIA Request for Documents. Forwards App X & Y Documents.Documents Available in Pdr.App X Documents Withheld in Part (Ref FOIA Exemptions 3 & 5).App Z Documents Withheld in Entirety (Ref FOIA Exemption 5) IR 05000272/19970011997-02-11011 February 1997 Forwards Initial Exam Repts 50-272/97-01OL & 50-311/97-01OL Administered on 970106-10 ML20134J8571997-02-0707 February 1997 Nineth Partial Response to FOIA Request for Documents. Records in App U Encl & Being Made Available in Pdr.App V Records Being Withheld in Part (Ref Exemptions 6) & App W Records Being Withheld in Entirety (Ref Exemption 5) ML20134H2521997-02-0606 February 1997 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR 1999-09-28 Category:UTILITY TO NRC MONTHYEARML18095A4881990-09-17017 September 1990
[Table view]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 |
Text
Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P..o. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations June 16, 1989 NLR-N89121 United States Nuclear Regulatory Commission Document Control Desk Washington, DC
- 20555 Gentlemen:
RESPONSE TO NRC BULLETIN 88-03 SALEM GENERATING STATION UNIT NO. 1 DOCKET NO. 50-272 Public Service Electric and Gas Company (PSE&G) has received the subject NRC Bulletin regarding potential inadequate latch engagement in GE HFA_latching-type relays. The information requested by .this Bulletin as it relates to Salem Unit 1 is provided in the enclosure to this letter.
Should you have any questions with regard to this transmittal, please do not hesitate to contact us.
Sincerely, C Mr. J. c. Stone Licensing Proj.ect Manager Ms. K. Halvey Gibson ,
Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Mr. K. Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality_
Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
! \
8906300020 890616 PDR ADOCK 05000272 Q PNU
REF: RESPONSE TO NRC BULLETIN.
88-03 NLR-89121 STATE OF NEW JERSEY )
) SS.
COUNTY OF SALEM )
Stanley LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated June 16, 1989 , concerning the Salem Generating Station, Unit No. 1, are true to the best of my knowledge, information and belief.
Subscribed and Sworn to before me
- / _.
- ..;_. /)
this .~. ~* day of '*./ t~-*'"-- , 1989
- /
Notary Publ.ic of New Jersey LARAINE Y. BEARD
_Notary Public of New Jersey
. My Commission Expires May 1, 1991 My Commission expires on
ENCLOSURE RESPONSE TO BULLETIN 88-03 SALEM GENERATING STATION UNIT NO. 1 DOCKET NO. 50-272 The purpose of this bulletin was to request licensees to perform inspections to ensure that all GE latching-type HFA relays installed in safety-related applications have adequate latch engagement and that those relays which fail to meet acceptance criteria be repaired or replaced.
The bulletin requested a letter of confirmation that the inspection had been completed and a summary of the number of relays inspected and any corrective actions taken. This information is presented below as it relates to_ Salem Unit 1.
RESPONSE
The NRC Bulletin 88-03 GE HFA latching-type relay inspection for Salem Unit 1 was performed in May 1989 during the Eighth _
Refueling Outage. Documentation reviews and field examination revealed twent:y-one (21) HFA latching-type relays, seven in each of the three emergency diesel generator control cabinets. The relays all have the Model No. 12HFA54H187H.
All of these relays were checked in accordance with a special test procedure (T-246) written to address those criteria noted in the Actions Requested portion of the NRC Bulletin 88-03. The results of the examinations of all the relays were found to be satisfactory. The Procedure T-246 data sheets are available onsite for inspection, if requested.
Until alternatively designed relays are made available which remedy the problem noted in NRC Bulletin 88-03, spare GE HFA latching-type relays of the model noted above have been ordered for replacement-in-kind applications, if replacement should be necessary in the future. These spare relays will be inspected in accordance with the criteria of NRC Bulletin 88-03 upon receipt.
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