ML18093B225
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| ML18093B225 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/13/1988 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Miltenberger S Public Service Enterprise Group |
| Shared Package | |
| ML18093B226 | List: |
| References | |
| NUDOCS 8810210296 | |
| Download: ML18093B225 (2) | |
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 LR-N990450, 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 Analyses1999-10-18018 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 LR-N990409, Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests1999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 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 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 ML18107A5401999-09-24024 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Sngs,Units 1 & 2 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 NTD-99-302, Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)1999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5371999-09-20020 September 1999 Forwards Insp Repts 50-272/99-06 & 50-311/99-06 on 990719-0806 (Region I-Inoffice) 990809-19 & 0901.NRC Has Determined That Three Violations of NRC Requirements Have Occurred.Violations Being Treated as non-cited 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 LR-N000420, Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 21999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 LR-N990405, Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources1999-09-13013 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 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 LR-N990392, 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 19991999-09-0808 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 LR-N990406, 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 Examinations1999-09-0808 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 LR-N990385, 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 Issues1999-08-26026 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 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 LR-N990396, Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided1999-08-26026 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 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 LR-N990363, 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 99-021999-08-23023 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 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 LR-N990389, 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 Bars1999-08-20020 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 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 LR-N990375, Submits Licensee Comments on NRC Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 11999-08-18018 August 1999 Submits Licensee Comments on NRC Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 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 LR-N990140, Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed1999-08-13013 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 ML18107A4701999-07-30030 July 1999 Discusses Closure of Listed TACs in Response to Requests for Addl Info Re GL 92-01 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 ML18107A4361999-07-16016 July 1999 Accepts Commitment to NRC Re Licensee Providing Clarification Concerning Licensing & Design Basis for 125 Vdc Battery Margins for Hope Creek & Salem Generating Stations for Meeting SBO & Loca/Loop Loading Requirements 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 ML18107A4251999-07-0606 July 1999 Forwards Insp Repts 50-272/99-04 & 50-311/99-04 on 990419-0529.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 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 LR-N990251, Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl 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 LR-N990289, 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 & Discussion with NRC1999-06-25025 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 & Discussion with NRC ML18107A4141999-06-23023 June 1999 Forwards SE Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions, for Plant,Units 1 & 2 ML18107A3891999-06-23023 June 1999 Discusses Evaluation of Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Safety Evaluation Encl 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 LR-N990273, Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed1999-06-21021 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 1999-09-08 Category:NRC TO UTILITY MONTHYEARML18095A6151990-11-20020 November 1990
[Table view]Requests Response to Allegation NRR-90-A-0050 within 90 Days.Encl Withheld (Ref 10CFR9.17) ML18095A5651990-11-0202 November 1990 Forwards List of Unimplemented Generic Safety Issues at Plant,Per 900702 & 13 Responses to Generic Ltr 90-04 ML18095A5741990-11-0101 November 1990 Forwards Safety Insp Repts 50-272/90-22,50-311/90-22 & 50-354/90-16 on 900816-1001 & Notice of Violation.Five Noncited Violations Also Noted.Intradepartmental & Interdepartmental Communications Contributed to Concerns ML18095A5551990-10-19019 October 1990 Forwards Revised Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07 on 900312-15 ML18095A5591990-10-19019 October 1990 Forwards Mgt Meeting Repts 50-272/90-10,50-311/90-10 & 50-354/90-07 on 900719.No Violations Noted ML18095A5371990-10-18018 October 1990 Approves 901009 Request for Addl 30 Days to Respond to NRC 900828 Request for Addl Info Re SG Surveillance ML18095A5391990-10-17017 October 1990 Responds to Util 900831 Request for Addl Info Re Generic Ltr 89-10.Requested Info Contained in Info Notice 90-004 or Transcript of 900418 Public Meeting Re motor-operated Valve Test Results ML18095A5221990-10-0909 October 1990 Forwards SALP Repts 50-272/89-99,50-311/89-99 & 50-354/89-99 for May 1989 - Jul 1990.Mgt Meeting to Discuss SALP Evaluation Scheduled for 901016 ML18095A4651990-09-0404 September 1990 Forwards Safety Insp Repts 50-272/90-19,50-311/90-19 & 50-354/90-14 on 900619-0815.No Violations Noted.Inspectors Noted Weaknesses in Administrative Controls & Guidance for Voluntary Entries Into Tech Spec 3.0.3 for Both Plants ML18095A4321990-08-28028 August 1990 Requests That Listed Addl Info Re Licensee 890913 Proposed Changes to Steam Generator Surveillance Tech Specs Be Submitted within 90 Days of Receipt of Ltr ML18095A4481990-08-25025 August 1990 Forwards Exam Repts 50-272/90-21OL & 50-311/90-21OL on 900813 IR 05000272/19902001990-08-21021 August 1990 Discusses Maint Team Insp Repts 50-272/90-200 & 50-311/90-200 & Forwards Notice of Violation IR 05000272/19900141990-08-20020 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/90-14 & 50-311/90-14 ML18095A4251990-08-16016 August 1990 Forwards Safety Evaluation Accepting Actions Taken by Util to Fully Resolve Issues Identified in Bulletin 88-002 Re Rapid Propagating Fatigue Cracks in Steam Generator Tubes. Util Encouraged to Review Leak Rate Monitoring Procedures ML18095A4291990-08-10010 August 1990 Forwards Details of Allegations Re Activities & Requests Results of Investigation by 900820.Results Should Not Contain Privacy,Safeguards or Proprietary Info.Encl Withheld (Ref 10CFR2.790) ML18095A4051990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Util Encouraged to Initiate Similar Initiative.Cooperative Effort Would Promote Efficiency & Enhance Effectiveness of Nuclear Power Plant Engineering Activities IR 05000272/19900091990-08-0202 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/90-09 & 50-311/90-09 ML18095A3911990-07-31031 July 1990 Forwards Insp Repts 50-272/90-17,50-311/90-17 & 50-354/90-11 on 900611-15.No Violations Noted IR 05000272/19900801990-07-25025 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Actions Will Be Examined During Future Insp ML18095A3511990-07-13013 July 1990 Advises That Response to Generic Ltr 88-14, Instrument Air Supply Sys Problem Affecting Safety-Related Equipment, Complete ML18095A3351990-07-0303 July 1990 Forwards Integrated Performance Assessment Team Insp 50-272/90-81 & 50-311/90-81 on 900514-25.Insp Evaluates Perceived Decline in Performance Identified in Most Recent SALP Rept ML18095A3311990-07-0202 July 1990 Forwards Safety Insp Repts 50-272/90-13,50-311/90-13 & 50-354/90-10 on 900501-0618.Noncited Violations Noted ML18095A3171990-06-18018 June 1990 Submits Invitation to Attend Power Reactor Operator Licensing Seminar on 900801 in King of Prussia,Pa to Discuss Changes to Format for Both Requalification Exams & Initial Exams.Seminar Agenda Encl ML18095A3091990-06-15015 June 1990 Forwards Safety Insp Repts 50-272/90-16 & 50-311/90-16 on 900529-0601.No Violations Noted.Unmonitored Radioactive Liquid Release from Unit 2 on 900521 Categorized as Noncited Violation.Response to Noncited Violation Not Required ML18095A3121990-06-13013 June 1990 Comments on Util 891227 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Operating Switches for Valves Would Be Set on Best Available Data Until Final Data Obtained ML20059M9281990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML18095A3131990-06-12012 June 1990 Requests Addl Data Re Simulator Certification for 10CFR55.45(b)(2),no Later than 900815 ML18095A2881990-06-11011 June 1990 Forwards Insp Repts 50-272/90-14 & 50-311/90-14 on 900501-04 & Notice of Violation ML18095A2731990-06-0808 June 1990 Forwards Maint Team Insp Repts 50-272/90-200 & 50-311/90-200 on 900409-13 & 23-27.Insp Team Concluded That Licensee Implementing Generally Adequate Maint Program IR 05000272/19900121990-06-0808 June 1990 Discusses Safety Insp Repts 50-272/90-12 & 50-311/90-12 on 900411-18 & Forwards Notice of Violation.Nrc Concerned Re Quality of ECCS Flow Surveillance Procedure ML18095A2341990-05-24024 May 1990 Forwards Safety Insp Repts 50-272/90-11,50-311/90-11 & 50-354/90-08 on 900317-0430 & Notice of Violation.Lack of Effective Corrective Actions Noted ML18095A2381990-05-24024 May 1990 Forwards Safety Insp Repts 50-272/90-08 & 50-311/90-08 on 900226-0302.Noncited Violation Re Qualification of Biw Cable Used W/Victoreen Radiation Monitor Observed NUREG/CR-4884, Advises That Assessing Intakes of Radioactive Matl Using Bioassay Data Should Be Based on Best Data Available. Licensee May Use Improved & Generally Accepted Methodology Provided in Icrp Publications & NUREG/CR-48841990-05-22022 May 1990 Advises That Assessing Intakes of Radioactive Matl Using Bioassay Data Should Be Based on Best Data Available. Licensee May Use Improved & Generally Accepted Methodology Provided in Icrp Publications & NUREG/CR-4884 ML18095A2191990-05-18018 May 1990 Forwards Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07 on 900312-15.Non-cited Violations Noted ML18095A2111990-05-16016 May 1990 Discusses Licensee Programmed Enhancements Per Generic Ltr 88-17, Loss of Dhr. Deferral of All hardware-related Mods to RHR Sys Parameters to SPDS & Replacement of Tygon Tubing Until End of Sixth Refueling Outage Acceptable ML18095A2041990-05-15015 May 1990 Advises That Util 900320 Response to Generic Ltr 89-19 Per USI A-47 Acceptable,Based on Implementation of Steam Generator Overfill Protection Sys & Verification of Sys Operability ML18095A1971990-05-0404 May 1990 Proposes Workshop on 900620-21 in King of Prussia,Pa to Promote Better Understanding of NRC Insp Program.Proposed Agenda,W/Keynote Speakers & Outline for Breakout Sessions Encl ML20042F4381990-05-0303 May 1990 Requests Submission of Westinghouse Reassessment of NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML18095A2061990-05-0202 May 1990 Forwards Agenda for NRC Region I Radiation Protection Manager Conference on 900523-24 in King of Prussia,Pa ML18094B4211990-04-17017 April 1990 Forwards Safety Evaluation Concluding That Second 10-yr Inservice Insp Program Plan,W/Addl Info Provided & Relief Requests,Constitutes Basis for Compliance w/10CFR50.55a(g). Eg&G Technical Evaluation Rept Also Encl ML18094B3941990-04-0505 April 1990 Grants Temporary Waiver of Compliance from Requirements in Table 3.3-5 & Section 4.7.1.5. of Facility Tech Specs ML18094B3661990-03-30030 March 1990 Requests Addl Info Re 871103 Application for Amend to Licenses Adding Statement That Requirements Imposed by NRC 830506 Order Terminated.Wording Should Be Revised to State That Terms of Order Satisfied ML18094B3811990-03-30030 March 1990 Grants Temporary Waiver of Compliance to Conduct MSIV Testing at Unit W/Listed Provisions,Per 900329 Request.Util Request to Cycle MSIVs Which Exceeded 8 Stroke Time Criterion Not Approved ML18094B3781990-03-29029 March 1990 Forwards Insp Repts 50-272/90-80 & 50-311/90-80 on 900116- 25.Weaknesses Identified.Confirmation of Commitment to Review,Walkdown,Correct & Implement All Procedures Under Emergency Operating Procedures Family Requested ML18094B3501990-03-20020 March 1990 Advises That 900126 Response to Recommendations I,Iii & IV of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment Acceptable.Insp of Initial Sample of 20% to 30% of Containment Fan Coolers Approved ML20012D0221990-03-20020 March 1990 Advises That Individual Plant Exam Approach,Methodology & Schedule,Provided in in Response to Generic Ltr 88-20,acceptable.Schedule Changes Should Be Reported to NRC ML18094B3531990-03-20020 March 1990 Requests Justification for Exclusion of Statement Contained in Encl Model Tech Specs Re Turbine Valve Testing Surveillance Interval,In Response to 871224 & 900226 Requests to Revise Tech Spec 3/4.3.4 & Associated Bases ML18094B3631990-03-19019 March 1990 Informs of 900523-24 Radiation Protection Manager Conference in King of Prussia,Pa to Exchange Info on Issues of Mutual Interest Re Power Reactor Radiological Controls Programs ML20012D6081990-03-15015 March 1990 Forwards Safety Insp Repts 50-354/90-04,50-272/90-06 & 50-311/90-06 on 900226-0302.No Violations Noted ML18094B3521990-03-14014 March 1990 Forwards List of Unresolved USIs for Facilities,Including USI A-44 Re Station Blackout,Usi A-46 Re Seismic Qualification of Equipment in Operating Plants & USI A-47 Re Safety Implications of Control Sys in LWRs 1990-09-04 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 ML18107A5401999-09-24024 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Sngs,Units 1 & 2 ML18107A5371999-09-20020 September 1999 Forwards Insp Repts 50-272/99-06 & 50-311/99-06 on 990719-0806 (Region I-Inoffice) 990809-19 & 0901.NRC Has Determined That Three Violations of NRC Requirements Have Occurred.Violations Being Treated as non-cited ML18107A4701999-07-30030 July 1999 Discusses Closure of Listed TACs in Response to Requests for Addl Info Re GL 92-01 ML18107A4361999-07-16016 July 1999 Accepts Commitment to NRC Re Licensee Providing Clarification Concerning Licensing & Design Basis for 125 Vdc Battery Margins for Hope Creek & Salem Generating Stations for Meeting SBO & Loca/Loop Loading Requirements ML18107A4251999-07-0606 July 1999 Forwards Insp Repts 50-272/99-04 & 50-311/99-04 on 990419-0529.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 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 ML18107A3891999-06-23023 June 1999 Discusses Evaluation of Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Safety Evaluation Encl ML18107A4141999-06-23023 June 1999 Forwards SE Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions, for Plant,Units 1 & 2 ML18107A4201999-06-0404 June 1999 Informs That NRR Reorganized,Effective 990328.Organization Chart Encl ML18107A2751999-05-0303 May 1999 Forwards Insp Repts 50-272/99-03 & 50-311/99-03 on 990315- 19.No Violations Were Identified ML18107A2701999-04-30030 April 1999 Refers to Investigation Conducted by OI After Chemistry Supervisor at Salem Facility Made Change to Procedure Without Proper Review & Signed Record Indicating That Independent Verifications Had Been Performed ML18107A2161999-04-19019 April 1999 Forwards Ltr from Lg Canton,Regional Director,Fema Region II to Hj Miller,Nrc Region I,Forwarding FEMA Final Exercise Rept for 980303 Plume Exposure Pathway Exercise & 980505-07 Ingestion Pathway Exercise for Salem/Hope Creek Stations ML18107A1761999-04-15015 April 1999 Responds to 981019 & s Requesting Approval of Proposed Changes to QA Program,Per Section 17.2 of Respective UFSAR Per 10CFR50.54(a)(3).Forwards SE Re Changes to QA Program IR 05000311/19980121999-04-0707 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-311/98-12.Review of Effectiveness of Corrective Actions in Rept, as Part of Independent Assessment of RCS & LER Completed IR 05000272/19990011999-04-0101 April 1999 Forwards Insp Repts 50-272/99-01 & 50-311/99-01 on 990117-0307.No Violations Identified.Expresses Concern About Two Human Errors That Caused Plant Events,One Which Challenged Safety Sys ML18106B1091999-03-23023 March 1999 Forwards RAI Re NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML18106B0741999-02-18018 February 1999 Provides Authorization to Administer Written Exams to Listed Applicants on 990226 at Salem Generating Station,Hancocks Bridge,New Jersey.Nrc Region I Operator Licensing Staff Will Administer Operating Tests on 990222-25 & 990301-05 ML18106B0731999-02-11011 February 1999 Discusses Closure of TAC Re Generic Implication of part- Length Control Rod Drive Mechanism Housing Leak ML20206S5951999-02-0303 February 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Their Entirety ML18106B0181999-01-0707 January 1999 Forwards Request for Addl Info Re Proposed Amend That Would Modify TS Section 3/4 7.6, Control Room Emergency Air Conditioning Sys ML18106A9921998-12-18018 December 1998 Responds to Re Fire Protection Matl Used at Salem Nuclear Generating Station.In 1993,NRC Identified Deficiencies in Electrical Raceway Fire Barrier Sys at Which Time Compensatory Measures Were Put in Place ML20198H1851998-12-15015 December 1998 Responds to to President Clinton Re Rept by Gao, Issued 970530 on NRC Oversight of Nuclear Power Industry ML18106A9911998-12-0808 December 1998 Forwards Synopsis of Investigation Rept 1-98-013 Re Fire Protection Operator Falsified Six Daily Fire Insp Logs During Feb & March 1998.Concludes That Operator Deliberately Violated Fire Protection Program Procedures 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 IR 05000272/19980081998-11-24024 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/98-08 & 50-311/98-08 ML18106A9751998-11-10010 November 1998 Forwards Exam Forms with Answers,Results Summary for Plant & Individual Answer Sheets of GFE Section of Written Operator Licensing Exam,Administered on 981007.Without 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) ML18106A9341998-10-22022 October 1998 Forwards SE Related to USI A-46 Program Implementation.Nrc Has Determined That Util Actions Completed & Proposed Resolution of Outlier Items Will Result in Safety Enhancements.Usi A-46 Program Complete 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) ML18106A8981998-10-0505 October 1998 Forwards SRO Initial Exam Repts 50-272/98-302 & 50-311/98-302 for Exams Conducted on 980914-24.All Three SRO Applicants Passed All Portions of Exams 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 ML18106A8841998-09-24024 September 1998 Provides Individual Exam Results for Applicants on Initial Written Exam & Operating Tests Conducted at Salem Facility on 980914-17.W/o Encls ML18106A8701998-09-15015 September 1998 Forwards SE Accepting 960518 Request for Approval to Incorporate W WRB-2 Correlation Into Licensing Basis for Plant,Units 1 & 2 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 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 ML18106A8571998-09-0202 September 1998 Informs That Licensee 980310 Response to GL 97-05, Steam Generator Tube Insp Technique, Includes Info Requested. Staff Did Not Identify Any Concerns W/Techniques Employed at Plant Re Conformance W/Current Licensing Basis for Facility 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 IR 05000272/19980051998-08-27027 August 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/98-05, 50-311/98-05 & 50-354/98-06 ML18106A8311998-08-21021 August 1998 Forwards Insp Repts 50-272/98-06 & 50-311/98-06 on 980622-0801.One Apparent Violation of Maint Procedure Requirements That Led to Failure to Meet TS Operability Requirements for AFW Sys,Identified.Nov Not Encl ML18106A8061998-08-0707 August 1998 Responds to Request for Statistics on Allegations Received by NRC Re Salem & Hope Creek.Encl Tables Provide Comparison to Allegations Received at Other Operating Sites for CY93-97 & First Seven Months of 1998 ML18106A7991998-08-0606 August 1998 Discusses Improved Std TS Guidance for Plants,Per Licensee ML18106A7941998-07-24024 July 1998 Summarizes Discussions Re Salem Units 1 & 2.Based on Discussions NRC Concluded That Plant Units 1 & 2 Have Sustained Improvement to Be Removed from NRC Watch List IR 05000272/19980031998-07-14014 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/98-03 & 50-311/98-03 ML18106A7031998-07-10010 July 1998 Forwards Insp Repts 50-272/98-05 & 50-311/98-05 on 980504-0621 & Nov.Violations Include Failure of Staff to Adhere to Established Procedures,Including Procedures Requiring 10CFR50.59 Reviews & Test Equipment Calibration IR 05000272/19982021998-07-0909 July 1998 Forwards Insp Repts 50-272/98-202,50-311/98-202 & 50-354/98-202 on 980420-23.No Violations Noted.Enclosure Contains Safeguards Info & Being Withheld Ref 10CFR73.21 ML18106A6991998-07-0808 July 1998 Forwards Senior Reactor Operator Retake Exam Repts 50-272/98-301(OL) & 50-311/98-301(OL) on 980626.Staff Administered Exam to One SRO Candidate Who Failed Initial Written Exam in Jan 1998.Candidate Passed & Issued License ML18106A6891998-07-0202 July 1998 Provides Individual Exam Result for Applicant on Initial Retake Written Exam Conducted at Salem Facility on 980626. Info Considered Proprietary in Accordance w/10CFR2.790.W/o Encls 1999-09-24 |
See also: IR 05000272/1988017
Text
I
_ .,
- .
- . :.* .. '*** .. ___ .: ........... ; _
1 B OCT 1988
Docket Nos.
50-272
50-311
Public Service Electric and Gas Company
ATTN:
Mr. Steven E. Miltenberger
Vice President and Chief Nuclear Officer
P. 0. Box 236
Hancocks Bridge, New Jersey 08038
Gentlemen:
Subject:
Combined Inspection 50-272/88-17 and 50-311/88-17
This refers to the routine resident safety inspection by Mr. R. Borchardt
and Mrs. K. Halvey Gibson, of this office, on August 23, 1988 to September
26, 1988, at the Salem Nuclear Generating Station, Hancocks Bridge, New
Jersey.
The inspection consisted of document reviews, interviews, and
observation of activities.
The findings were discussed with Mr. L. K.
Miller of your staff.
This letter also acknowledges your response dated September 2, 1988 to the
violations cited in NRC combined inspection report 50-272/88-14 and
50-311/88-14.
Your response and corrective actions for the failure to
enter the safeguard equipment control system action statement when required
were reviewed and found to be acceptable.
In reference to your corrective
actions for the violation relating to the scheduling of surveillance and
periodic tests and the issue concerning administrative control of control.
room documents, we request the following clarifications:
a.
Your response regarding surveillance scheduling provides a
general description of corrective actions you plan to implement
(i.e. establishment of a program based on an INPO Good Practice,
revision of an administrative procedure, etc.) to enhance the
work control process which you indicate will prevent further
occurrence of missed surveillances.
Please provide a more
detailed description of specific program changes and actions
planned in this regard.
b.
Your response regarding the administrative control of control
room documents addresses corrective actions which you plan to
implement with regard to surveillance files in the control room.
Please provide clarification on corrective actions that you plan
to take to ensure administrative control of control room
documents other than surveillance files (i.e. procedures, logs,
etc.). Another example of inadequate administrative control of
documentation used in the control room was identified during this
report period and further indicates the need for licensee
corrective actions in this area.
OFFICIAL RECORD COPY
CIR SALEM 88-17 - 0001.0.0
10/13/88
8810210296 881013
ADOCK 05000272
Q
~fo1
Public Service Electric and
Gas Company
2
18 OCT 19SS
Please provide the requested clarifications in writing to this office
within 30 days of receipt of this letter.
Your cooperation with us in this matter is appreciated.
Sincerely,
ORIGINAL SIGNED BV
EDWARD C. WENZINGER
Edward C. Wenzinger, Chief
Projects Branch No. 2
Division of Reactor Projects
Enclosure:
NRC Combined Report 50-272/88-17 and 50-311/88-17
cc w/encls:
S. LaBruna, Vice President - Nuclear Operations
L. K. Miller, General Manager - Salem Operations
Jack Urban, General Manager, Fuels Department, Delmarva Power & Light Co.
B. A. Preston, Manager, Licensing and Regulation
Scott B. Lingerer, Manager, Joint Generation Projects Department, Atlantic
Electric
M. J. Wetterhahn, Esquire, Conner & Wetterhahn
R. Fryling, Jr., Esquire
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center
NRC Resident.Inspector
State of New Jersey
bee w/encls:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
DRP Section Chief
J. Stone, NRR Licensing Project Manager
Robert J. Bores, DRSS
G. W. Meyer, Senior Resident Inspector, Hope Creek
L. W. Rossbach, Senior Resident Inspector, Indian Point 2
R. J. Kiessel, Generic Communications Branch, NRR
Lrhl
10/(/ /88
~'2
101f88
OFFICIAL RECORD COPY
CIR SALEM 88-17 - 0001.1.0
10/13/88
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