ML20196J203
From kanterella
| ML20196J203 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/07/1988 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Corbin McNeil Public Service Enterprise Group |
| Shared Package | |
| ML20196J207 | List: |
| References | |
| TAC-66775, NUDOCS 8803140183 | |
| Download: ML20196J203 (2) | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M7571999-10-22022 October 1999
[Table view]Advises That Attachment 1 to ,Marked as Proprietary,Re Safety Limit MCPR & Fuel Vendor Change Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20217M2101999-10-19019 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 ML20217H8471999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217K8441999-10-15015 October 1999 Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station ML20217H9771999-10-13013 October 1999 Forwards SRO & RO Initial Exam Rept 50-354/98-302,suppl Rept on 990125-29,mtg Meeting on 990322,990429-30 & 0617-18 in-office Review & 990720 Telcon on Appeal Results.Overall, 11 of 16 Applicants Received NRC Licenses 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 ML20217C4391999-10-0606 October 1999 Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011 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 ML20217A9601999-10-0404 October 1999 Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR ML20217A6861999-10-0101 October 1999 Forwards Insp Rept 50-354/99-05 on 990711-0829.Four Violations Occurred Re Areas of Fire Protection,Operation at Reduced Feedwater Inlet Temp & safety-related Battery Charging Operation & Being Treated as NCVs LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999 Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) 05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl ML20217K7781999-09-16016 September 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station for Month of 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 ML20212B4021999-09-13013 September 1999 Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes 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 ML20211N5421999-09-0808 September 1999 Forwards Amend 121 to License NPF-57 & Safety Evaluation. Amend Revises TSs by Relocating Procedural Details of RETS to Offsite Dose Calculation Manual LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999 Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also 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 ML20211B5341999-08-20020 August 1999 Forwards RAI Re 2nd 10-yr ISI Interval Relief Requests Re Plant.Info Requested to Be Provided within 60 Days of Receipt of Ltr ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML20210R4911999-08-11011 August 1999 Forwards Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted.Inspectors Reviewed Performance Indicators Submitted as Part of Pilot Program for New Regulatory Oversight Process & Verified Data ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210H9241999-07-26026 July 1999 Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys ML20210F3271999-07-22022 July 1999 Forwards SE Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3 Re First 10-year Interval for ISI Program at Hope Creek ML20210D3971999-07-16016 July 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML20209G2831999-07-14014 July 1999 Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant 05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999 Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999 Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds ML20196J4421999-07-0101 July 1999 Forwards Request for Addl Info Re Increase of Allowable Main Steam Isolation Valve (MSIV) Leak Rate & Deletion of MSIV Sealing Sys for Plant LR-N990316, Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999 Responds 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 ML20209B6441999-06-21021 June 1999 Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01 ML20196F9441999-06-21021 June 1999 Forwards Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Two Violations of NRC Requirements Occurred Re Reactor Bldg Ventilation Setpoints & Control Rod Drop Analyses ML20196E6471999-06-21021 June 1999 Forwards Revised marked-up TS Page for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively. Revised Pages Do Not Alter Conclusions Reached in 10CFR50.92 No Significant Hazards Analysis Previously Submitted ML20209C0621999-06-21021 June 1999 Forwards NPDES Discharge Monitoring Rept,May 1999, for Hcgs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20196E9631999-06-17017 June 1999 Informs That Util Has Made Change to Commitment Stated in NRC Ser,Suppl 5.Commitment That Has Been Changed Is Item Number 1 of First Paragraph on Page 9-3 of Ser,Suppl 5 LR-N990295, Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 9905111999-06-16016 June 1999 Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 990511 05000354/LER-1999-006, Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER1999-06-15015 June 1999 Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER ML20195J1101999-06-0707 June 1999 Informs of Completion of Review of Providing Updated Status on Implementation of Commitments Made in Response to GL 89-13.Confirms Revs Made to Previous Commitments to Resolve Monitoring Pressure Drop Problem ML20195J1051999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Jw Clifford Will Be Section Chief for Hope Creek Generating Station ML20207F2681999-06-0303 June 1999 Responds to by Forwarding Gfes & NRC Written Exam Grades for List of Hope Creek Operators Submitted by DE Jackson.Absence of Gfes Grade Indicates That Operator Previously Issued RO or SRO License.Without Encl ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML20207D0201999-05-27027 May 1999 Discusses 990512 Meeting to Identify Insp Activities at Hope Creek Facility Over Next Six Months & Informs of Planned Insps in Order for Licensee to Have Opportunity to Prepare & Provide Region I with Feedback on Schedule Conflicts ML20195B9931999-05-20020 May 1999 Forwards NPDES Discharge Monitoring Rept,Apr 1999, for Hgcs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML20207A3451999-05-20020 May 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs ML20206Q6211999-05-14014 May 1999 Informs That on 990119 Licensee Provided NRC with Several Revised TS Bases Pages for Plant.Ts Bases Pages B 3/4 6-1 & B 3/4 6-2 Were Revised 1999-09-08 Category:NRC TO UTILITY MONTHYEARML20062E7751990-11-15015 November 1990
[Table view]Discusses Util 900910 Submittal of Addl Info Re Reliability of Bailey Solid State Logic Modules ML20197H7051990-11-0808 November 1990 Forwards Exam Rept 50-354/90-17OL Administered During Wks of 900827,0924 & 1001 ML20058H0461990-11-0606 November 1990 Forwards List of Unimplemented Gsis,Per Generic Ltr 90-04 ML20058H0531990-11-0606 November 1990 Informs That Dembek Replaced C Shiraki as Staff Project Manager for Plant ML20062B6611990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20059P0031990-10-0505 October 1990 Grants 900928 Request for Regional Waiver of Compliance Re Safety Auxiliaries Cooling Sys ML20058N8261990-08-13013 August 1990 Advises That Request for Relief from ASME Code Requirements for Svc Water Piping,Granted Until Next Scheduled Outage Per 10CFR50.55a(g)(6)(i) & Guidance of Generic Ltr 90-05 ML20058M4371990-08-0101 August 1990 Forwards Safety Insp Rept 50-354/90-13 on 900618-22.No Violations Noted ML20058L7541990-07-23023 July 1990 Forwards Radiological Controls Insp Rept 50-354/90-15 on 900625-29.No Violations Noted ML20059M9281990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C6241990-05-22022 May 1990 Forwards Exam Rept 50-354/90-06OL Administered During Wk of 900319 ML20248G5531989-09-26026 September 1989 Forwards Exam Rept 50-354/89-08OL Administered During Wk of 890717 IR 05000354/19890141989-09-19019 September 1989 Forwards Safety Insp Rept 50-354/89-14 on 890620-0814.No Violations Noted.Inspectors Noted Addl Attention to Detail Errors by Facility Personnel Similar to Ones Described in Most Recent SALP Rept 50-354/88-99 ML20246E7631989-08-22022 August 1989 Informs of Maint Program Team Insp Scheduled for 891002-13 to Focus on Maint Performance & Whether Components,Sys & Structures Adequately Maintained & Repaired to Perform Intended Safety Function.Encl Ref Matl Requested ML20246J4371989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purpose of Setting Occupational Exposure Limits.Procedures Should Incorporate Applicable Dose Limits of 10CFR20 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 ML20247J2841989-07-24024 July 1989 Forwards SER & EGG-NTA-8341 Re Generic Ltr 83-28,Item 4.5.3, Reactor Trip Reliability-On-Line Functional Testing of Reactor Trip Sys ML20247N4481989-07-24024 July 1989 Forwards Insp Rept 50-354/89-13 on 890626-30.No Violations Noted ML20246J8671989-07-12012 July 1989 Forwards Safety Insp Rept 50-354/89-11 on 890501-0619.No Violations Noted ML20246F7291989-07-0606 July 1989 Forwards to Ecology Ctr of Southern California Re Petition to Fix or Close Reactors Designed by Ge.Ltr States That Petition Being Treated Under 10CFR2.206 ML20245J8061989-06-27027 June 1989 Grants Util 871211 Relief Requests 3.1.1.1,3.1.1.2 & 3.1.1.3 Re Inservice Insp Plan Category B-A Reactor Vessel Welds,Per 871211 SER ML20247M8211989-05-25025 May 1989 Forwards Director'S Decision,Ltr of Transmittal & Fr Notice Re Denial of Ocre 10CFR2.206 Petition on BWR Stability. Request to Reopen Rulemaking on Anticipated Transients W/O Scram Being Considered as Petition Under 10CFR2.802 ML20246N3441989-05-11011 May 1989 Forwards Safety Insp Rept 50-354/89-09 on 890314-0430.No Violations Noted ML20247A0611989-05-0404 May 1989 Forwards SER Accepting Util Response to Generic Ltr 83-28, Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Technical Evaluation Rept Also Encl ML20247A7781989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl ML20245B6681989-04-10010 April 1989 Forwards Safety Insp Rept 50-354/89-06 on 890227-0303.No Violations Noted ML20244B5961989-04-0707 April 1989 Forwards Exam Rept 50-354/89-04OL Administered During Wk of 890214 ML20248J3851989-04-0404 April 1989 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 890717.Encl Ref Matl Requested by 890515 to Meet Schedule ML20248J1761989-03-31031 March 1989 Forwards Safety Insp Rept 50-354/89-02 on 890124-0313 & Notice of Violation.Concludes That Uncontrolled Installation of Electrical Jumpers in Controls of Drywell Equipment Drain Pumps Represented Violation of NRC Requirements ML20247M9521989-03-27027 March 1989 Forwards Insp Rept 50-354/89-05 on 890227-0303.No Violations Noted.Apparent Violation of Radiation Protection Procedures Identified by NRC Reviewed for Nonissuance of Notice of Violation ML20247E2771989-03-24024 March 1989 Requests Addl Info Re IGSCC Problems in BWR Austenitic Stainless Steel Piping,Per Generic Ltr 88-01.Response Should Be Provided within 60 Days ML20247D3561989-03-23023 March 1989 Confirms Requalification Program Evaluation Scheduled for Wk of 890619,per Telcon.Util Should Furnish Approved Items Listed in Encl 1 ML20247C2371989-03-20020 March 1989 Forwards Eg&G Idaho Evaluation Accepting Rev 10 to ODCM for Plant.Number of Points Remain Open Re Eg&G Suggestions That Could Make ODCM More Useful & Complete ML20236B6061989-03-0606 March 1989 Forwards Safety Insp Rept 50-354/89-03 on 890206-10.No Violations Noted ML20206M2131988-11-23023 November 1988 Informs That Recent Insp of Records Indicated That Util May Have Purchased Class 1E Components from Planned Maint Sys, Inc.Util Should Review Records for Period from Jan 1985 to Present ML20195H6571988-11-22022 November 1988 Accepts Util Response to Part 2 of Item 2.1 to Generic Ltr 83-28 Re Establishing Interface W/Either NSSS or Vendors of Each of Components of Util Reactor Trip Sys.Ser Encl ML20195J1321988-11-22022 November 1988 Advises That 880331 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Satisfactory. Response Confirmed That Westinghouse Ds Series Circuit Breakers Not Used in safety-related Applications IR 05000354/19882001988-11-11011 November 1988 Forwards Emergency Operating Procedures Insp Rept 50-354/88-200 on 880906-16.No Violations Noted.Weaknesses Involving Development & Implementation of Emergency Operating Procedures Identified ML20206C5261988-11-0303 November 1988 Forwards Safety Insp Rept 50-354/88-23 on 880823-1011. Unresolved Area Re Operation at Powers Marginally Above Rated Thermal Power Specified in License Will Be Evaluated for Potential Enforcement Based on Review of Evaluation ML20195E3011988-11-0101 November 1988 Requests Remittance of Fee for 880715 Application for Extension of Time to Submit 90-day Inservice Insp Rept ML20205Q7821988-10-28028 October 1988 Requests Ref Matls Listed in Encl Be Provided for Licensing Exam Scheduled for 890214-17 by 881219.Encls 1 & 3 Describe Requirements for Conducting Exams & Lists Rules & Guidelines in Effect During Administration of Exams,Respectively ML20204B5781988-10-17017 October 1988 Forwards Technical Evaluation Supporting VRS-002, 10CFR61 Waste Form Conformance Program for Solidified Process Waste Chem Corp Vol Reduction & Solidification Sys for Util Use as Ref Document ML20155F5651988-10-0707 October 1988 Forwards Grading & Answer Sheets for 880921 Generic Fundamentals Pilot Exam.W/O Encls ML20154N2221988-09-22022 September 1988 Forwards NRR to Ohio Citizens for Responsible Energy Ack Receipt of Petition Per 10CFR2.206.Request for Immediate Relief Denied Since Allegations Did Not Reveal Any New Operational Safety Issues Posing Safety Concern ML20154M3671988-09-16016 September 1988 Forwards Safety Insp Rept 50-354/88-22 on 880712-0829 & Notice of Violation.Previously Identified Items Re Scaffolding Should Be Promptly & Properly Corrected ML20154N4841988-09-0909 September 1988 Requests Rev to Util Pump Valve Inservice Testing Program, within 90 Days to Reflect Changes Discussed at 880629-30 Meetings & to Address Three Open Items.Questions That Served as Agenda for Meeting & Responses to Questions 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 IR 05000354/19880191988-08-0303 August 1988 Forwards Insp Rept 50-354/88-19 on 880613-17.No Violations Noted ML20151L2061988-07-27027 July 1988 Forwards Revised Notice of Violation Sent on 880714 Re Finding of Discrimination by Util Contractors Against Contractor Employees ML20151J4801988-07-27027 July 1988 Forwards Safety Insp Rept 50-354/88-18 on 880601-0711.No Violations Noted 1990-08-13 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M7571999-10-22022 October 1999
[Table view]Advises That Attachment 1 to ,Marked as Proprietary,Re Safety Limit MCPR & Fuel Vendor Change Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20217M2101999-10-19019 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 ML20217H8471999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217H9771999-10-13013 October 1999 Forwards SRO & RO Initial Exam Rept 50-354/98-302,suppl Rept on 990125-29,mtg Meeting on 990322,990429-30 & 0617-18 in-office Review & 990720 Telcon on Appeal Results.Overall, 11 of 16 Applicants Received NRC Licenses ML20217C4391999-10-0606 October 1999 Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011 ML20217A6861999-10-0101 October 1999 Forwards Insp Rept 50-354/99-05 on 990711-0829.Four Violations Occurred Re Areas of Fire Protection,Operation at Reduced Feedwater Inlet Temp & safety-related Battery Charging Operation & Being Treated as NCVs ML20211N5421999-09-0808 September 1999 Forwards Amend 121 to License NPF-57 & Safety Evaluation. Amend Revises TSs by Relocating Procedural Details of RETS to Offsite Dose Calculation Manual ML20211B5341999-08-20020 August 1999 Forwards RAI Re 2nd 10-yr ISI Interval Relief Requests Re Plant.Info Requested to Be Provided within 60 Days of Receipt of Ltr ML20210R4911999-08-11011 August 1999 Forwards Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted.Inspectors Reviewed Performance Indicators Submitted as Part of Pilot Program for New Regulatory Oversight Process & Verified Data ML20210F3271999-07-22022 July 1999 Forwards SE Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3 Re First 10-year Interval for ISI Program at Hope Creek ML20209G2831999-07-14014 July 1999 Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant ML20196J4421999-07-0101 July 1999 Forwards Request for Addl Info Re Increase of Allowable Main Steam Isolation Valve (MSIV) Leak Rate & Deletion of MSIV Sealing Sys for Plant ML20196F9441999-06-21021 June 1999 Forwards Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Two Violations of NRC Requirements Occurred Re Reactor Bldg Ventilation Setpoints & Control Rod Drop Analyses ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195J1051999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Jw Clifford Will Be Section Chief for Hope Creek Generating Station ML20195J1101999-06-0707 June 1999 Informs of Completion of Review of Providing Updated Status on Implementation of Commitments Made in Response to GL 89-13.Confirms Revs Made to Previous Commitments to Resolve Monitoring Pressure Drop Problem ML20207F2681999-06-0303 June 1999 Responds to by Forwarding Gfes & NRC Written Exam Grades for List of Hope Creek Operators Submitted by DE Jackson.Absence of Gfes Grade Indicates That Operator Previously Issued RO or SRO License.Without Encl ML20207D0201999-05-27027 May 1999 Discusses 990512 Meeting to Identify Insp Activities at Hope Creek Facility Over Next Six Months & Informs of Planned Insps in Order for Licensee to Have Opportunity to Prepare & Provide Region I with Feedback on Schedule Conflicts ML20207A3451999-05-20020 May 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs ML20206Q6211999-05-14014 May 1999 Informs That on 990119 Licensee Provided NRC with Several Revised TS Bases Pages for Plant.Ts Bases Pages B 3/4 6-1 & B 3/4 6-2 Were Revised ML20206Q4461999-05-14014 May 1999 Forwards SE Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206U8451999-05-14014 May 1999 Forwards Insp Rept 50-354/99-02 on 990308-0418.Violations Re Fuel Handling Errors & Missed Temp Monitoring During Reactor Vessel Head Tensioning Occurred & Being Treated as non-cited Violation ML20206R2691999-05-12012 May 1999 Informs That During 990504 Telcon Between J Caruso & H Hanson,Arrangements Were Made for Administration of Licensing Written Retake Exam at Hope Creek Nuclear Generating Station During Week of 990927 ML20206C8431999-04-22022 April 1999 Forwards SER Authorizing Util 980728 Submitted Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B ML20205S7911999-04-19019 April 1999 Forwards Insp Rept 50-354/99-01 on 990124-0307.Violations Noted.Some Human Performance Errors Occurred During Numerous Outage Activities,Util Appropriately Reacted to Each of Errors & Initiated Corrective Actions ML20205R0461999-04-14014 April 1999 Forwards Associated Page with Correction Marked in Margin of PPR of Salem Issued 990409.During Final Review of Hard Copy, Error Was Noted.Without Encl ML20205R0861999-04-14014 April 1999 Informs That Final Review of Hard Copy of PPR Re Hope Creek, Issued 990409 Had Error.Electronic Version e-mailed Was Not Effected.Forwards Pp with Correction in Margin.Without Encl ML20205N2111999-04-0909 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-302 Issued on 990226.Response Indicates That Licensee Corrected Violation & Initiated Measures to Prevent Recurrence ML20205N2481999-04-0909 April 1999 Discusses Hope Creek Generating Station Plant Performance Review Conducted for Period April 1998 Through Jan 1999 & Informs of NRC Planned Insp Effort Resulting from Ppr. Historial Listing & Insp Plans for Next Few Months Encl ML20205G5961999-03-19019 March 1999 Forwards Safety Evaluation of Relief Request Re ASME Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components Section Xi,Div 1. Request Acceptable ML20205F8771999-03-18018 March 1999 Forwards SE Authorizing Licensee 971222 Relief Requests Re Second 10-year Interval for Pumps & Valves IST Program for Hope Creek Generating Station ML20207D5741999-03-0101 March 1999 Discusses Pse&G 980604 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verification at Hope Creek Generating Station. Forwards RAI Re GL 96-05 Program at Hope Creek ML20198H6211998-12-24024 December 1998 Forwards Notice of Withdrawal of 970826,as Suppl 980424 & 0924 Amend Request for FOL NPF-57.Proposed Change Would Have Modified Facility TSs Pertaining to Filtration,Recirculation & Ventilation Sys Surveillance Testing Requirements ML20198L3571998-12-22022 December 1998 Forwards Insp Rept 50-354/98-11 on 981101-1212.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Effective Engineering & Maint Practices & Careful Radiological Work Controls ML20198H6661998-12-17017 December 1998 Informs That Attachment 1 to Ltr LR-N98404,dtd 980825 Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20196K1371998-12-0909 December 1998 Advises of Planned Insp Effort Resulting from Hope Creek Insp Review Planning Meeting Conducted on 981110.Details of Insp Plan for Next 6 Months Encl ML20197H3841998-12-0707 December 1998 Informs That Licensee Authorized to Administer Initial Written Exams to Listed Applicants on 981222.NRC Region I Operator Licensing Staff Will Administer Operating Tests ML20196H0301998-12-0101 December 1998 Informs That NEDC-32511P,rev 1,dtd Oct 1998 Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20196F7991998-11-30030 November 1998 Forwards Rept Representing Results of 981026-29 Audit of Year 2000 Pragram at Hope Creek Generating Station.Audit Conducted as Followup to NRC GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Issued 980511 ML20196D0711998-11-23023 November 1998 Forwards Insp Rept 50-354/98-10 on 980920-1031 & Notice of Violation Re Preforming Single Cell Charge on safety-related Battery Cell in Configuration Prohibited by Station Procedures ML20154Q7071998-10-16016 October 1998 Forwards Exam Rept 50-354/98-03OL Conducted by NRC During Periods of 980304-12,0519-21,22-28 & 0629.All Five Reactor Operator Applicants & Four of Five Senior Reactor Applicants Passed Exams 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) ML20154J8501998-10-0909 October 1998 Forwards Insp Rept 50-354/98-08 on 980809-0919 & Notice of Violation Re Inadequate Corrective Actions to Resolve Steam Leaks from Piping Located in Torus Room 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) ML20154F1121998-10-0202 October 1998 Forwards Insp Rept 50-354/98-09 on 980817-26 & 0908.No Violations Identified.Major Areas Inspected:Maint, Engineering & Mgt Meeting ML20154B3341998-09-29029 September 1998 Requests That Encl Info on GE Rept NEDC-32511P Be Reviewed & Revised Proprietary Version of Subj Rept Be Submitted.Some Info in Rept Should Not Be Exempt from Public Disclosure & Should Be Released & Placed in PDR 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 ML20151Z1111998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-06 Issued on 980721 ML20151Z5941998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-02 on 980423.Response Indicated Violations Corrected & Measures Initiated to Prevent Recurrence 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 1999-09-08 |
Contents
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. ,
Docket No. 50-354 Mr. Corbin A. McNeill, Jr.
Senior Vice President - Nuclear Public Service Electric and Gas ;
Company Post Office Box 236 Hancocks Bridge, New Jersey 08038
Dear Mr. McNeill:
SUBJECT:
ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT (TAC NO. 66775)
RE: Hope Creek Generating Station ,
In response to your letter dated December 14, 1987, the Commission is considering issuance of an amendment for Hope Creek Generating Station. The ;
! proposed amendment would change the Hope Creek Technical Specifications regarding Minimum Critical Power Ratio, Maximum Average Planar Linear Heat Generation, Control Rod Block Instrumentation, and the Recirculation System.
We have enclosed a copy of the Environmental Assessment and Finding of No Significant Impact for this proposed amendment which is being forwarded to the Office of the Federal Register for publication.
Sincerely, ,
/s/ .
Walter R. Butler, Director Pro,iect Directorate I-2
, Division of Reactor Projects I/II j Office of Nuclear Reactor Regulation l
Enclosure:
Environmental Assessment and Finding of i
No Significant Impact
) cc: w/ enclosure:
1 See next page DISTRIBUTION ,
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% **"* } March 7, 1988 Docket No. 50-354 Mr. Corbin A. McNeill, Jr.
Senior Vice President - Nuclear Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038
Dear Mr. McNeill:
SUBJECT:
ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT (TAC NO. 66775)
RE: Hope Creek Generating Station In response to yeu- letter dated December 14, 1987, the Comission is considering 'ssuance
. of an amendment for Hope Creek Generating Station. The proposed 1:aendment would change the Hope Creek Technical Specifications regarding Minimum Critical Power Ratio, Maximum Averace Planar linear Heat Generatie,, Control Rod Block Instrumentation, and the Recirculation System.
We have enclosed a copy of the Environmental Assessment and Finding of No
, Significant Impact for this proposed amendment which is being forwarded to the
- Office of the Federal Register for publication.
Sincerely, Md WTiter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Environmental Assessment and Finding of No Significant Impact cc: w/ enclosure:
- See next page 4
4
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