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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M7571999-10-22022 October 1999 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
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E7751990-11-15015 November 1990 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
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M7571999-10-22022 October 1999 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
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N4% DISTJf1TdTION:
p et No. 50-354 NRC PDR Docket No. 50-354 Local PDR PRC System BWD-3 r/f Mr. Corbin A. McNeill, Jr., Vice President - lluclear EAdensam Public Service Electric & Gas Company EHylton Nuclear Administration Building DWagner P.O. Box 236 RBernero Hancocks Bridge, New Jersey 08038 Attorney, OELD JPartlow BGrimes
Dear Mr. McNeill:
EJordan ACRS (10)
Subject:
Hope Creek Draft Low Power License As you are aware, the,. staff'is preparing a low power license (NPF-50) for the Hope Creek Generating Station facility. At the request of Mr. Dave Distel of your staff, enclosed is a draft copy of this license, without the attachments and appendices. It is prov.ided for your information, review and comment to ensure that it accurately reflects the commitments required of you as described in tne FSAR, SER and other documents. The enclosed draft license supersedes the one sent to you by our letter dated March 17, 1986. We request that you review this draft low power license and provide any comments in writing.
If you have any questions regarding this draft low power license, contact the Hope Creek Project Manager, Dave Wagner at (301) 492-9418.
Sincerely,
% S!rned by Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensing
Enclosure:
As stated cc: See next page 4
" BWD-3: DBL LA:@ ': DBL W 3: DBL DWagner/hmc Iton E sam 4/ L//86 4/ /86 4/ /86 B6041404gG DR 860404 '
ADOCK 05000354 .
PDR ,
Mr. C. A. McNeill Public Service Electric & Gas Co. Hope Creek Generating Station cc:
Gregory Minor Susan C. Remis Richard Hubbard Division of Public Interest Advocacy Dale Bridenbaugh New Jersey State Department of MHB Technical Associates the Public Advocate 1723 Hamilton Avenue, Suite K Richard J. Hughes Justice Comples San Jose, California 95125 CN-850 Trenton, New Jersey 08625 Troy B. Conner, Jr. Esquire Office of Legal Counsel Conner & Wetterhahn Department of Natural Resources 1747 Pennsylvania Avenue N.W. and Environmental Control Washington, D.C. 20006 89 Kings Highway P.O. Box 1401 Dover, Delaware 19903 Richard Fryling, Jr., Esquire Mr. K. W. Burrowes, Project Engineer Associate General Solicitor Bechtel Power Corporation Public Service Electric & Gas Company 50 Beale Street P. O. Box 570 T5E P. O. Box 3965 Newark, New Jersey 07101 San Francisco, California 94119 Manager - Licensing and Regulation Resident Inspector c/o Public Service Electric & Gas U.S.N.R.C. Bethesda Office Center, Suite 550 P. O. Box 241 4520 East-West Highway Hancocks Bridge, New Jersey 08038 Bethesda, Maryland 20814 Ms. Rebecca Green Richard F. Engel New Jersey Bureau of Radiation Deputy Attorney General Protection Division of Law 380 Scotch Road Environmental Protection Section Trenton, New Jersey 08628 Richard J. Hughes Justice Complex l CN-112P Trenton, New Jersey 08625 Mr. Robert J. Touhey, Mr. Anthony J. Pietrofitta Acting Director General Manager DNREC - Division of Power Production Engineering Environmental Control Atlantic Electric 89 Kings Highway 1199 Black Horse Pike P. O. Box 1401 Pleasantville, New Jersey 08232 Dover, Delaware 19903 Regional Administrator, Region I ;
Mr. R. S. Salvesen U. S. Nuclear Regulatory Commission General Manager-Hope Creek Operation l 631 Park Avenue Public Service Electric & Gas Co. King of Prussia, Pennsylvania 19406 P.O. Box A Hancocks Bridge, New Jersey 08038
Public Service Electric & Gas Co. Hope Creek Generating Station cc:
Mr. R. A. Preston Public Service Electric & Gas Co.
Hope Creek Site MC12Y Licensing Trailer 12LI Foot of Buttonwood Road Hancocks Bridge, New Jersey 08038 1
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- UNITED STATES
,j NUCLEAR REGULATORY COMMISSION .
- h. :, WASHINGTON, D. C. 20555 .
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PUBLIC SERVICE ELECTRIC & GAS COMPANY AND ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE License No. NPF-50
- 1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A. The application for a license filed by the Public Service Electric &
Gas Company, acting on behalf of itself and Atlantic City Electric Company (the licensees), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis-sion's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B. Construction of the Hope Creek Generating Station (the facility) has been substantially completed.in conformity with Construction Permit No. CPPR-120 and the application, as amended, the provisions of the Act and the regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.0. below);
D. There is reasonable assurance: (1) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.0.
below);
E. Public Service Electric & Gas Company
- is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F. The licensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public;
- Public Service Electric & Gas Company is authorized to act as agent for Atlantic Electric Company and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
m . . .
, H. After weighing the environmental, eco.1omic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-50, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.
- 2. Based on the foregoing findings regarding this facility, Facility Operating License No. NPF-50 is hereby issued to the Public Service Electric & Gas Company and Atlantic City Electric Company (the licensees) to read as follows:
A. This license applies to the Hope Creek Generating Station, a boiling water nuclear reactor, and associated equipment (the facility) owned by Public Service Electric & Gas Company and Atlantic City Electric Company. The facility is located on the licensee.s' site on the east bank of the Delaware River in Lower Alloways Creek Township, Salem County, New Jersey. The facility is located approximately eight miles southwest of Salem, New Jersey and is described in the Public Service Electric & Gas Company's " Final Safety Analysis Report," as supplemented and amended, and in the its Environmental Report as supplemented and amended.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Public Service Electric & Gas Company (PSE&G), pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the above designated location in . Salem County, New Jersey, in accordance with the procedures and limitations set forth in this license; (2) Atlantic City Electric Company, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess the facility at the designated location in Salem County, New Jersey, in accordance with the procedures and limitations set forth in this license; (3) PSE&G, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;
(4) PSE&G, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, I possess, and use at any time any byproduct, source and special I nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitor-ing equipment calibration, and as fission detectors in amounts as required; 1
(5) PSE&G, pursuant to the.Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) PSE&G, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the condi-tions specified in the Commission's regulations set forth in 10 CFR 1 Chapter I and is subject to all applicable provisions of the Act and l to the rules, regulations and orders of the Commission now or here- 1 after in effect; and is subject to the additional conditions specified i or incorporated below: l (1) Maximum Power Level l l
PSE&G is authorized to operate the facility at reactor core power levels not in excess of 3293 megawatts thermal (100 percent rated j power) in accordance with the conditions specified herein and in <
Attachment I to this license. The preoperational tests, startup tests, and other items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorpor-ated into this license. Pending Commission approval, this license is restricted to power levels not to exceed five percent of rated power (164.65 megawatts thermal).
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the En- l vironmental Protection Plan contained in Appendix B, both of which ,
are attached hereto, are hereby incorporated into this license. !
PSE&G shall operate the facility in accordance with the Technical l Specifications and the Environmental Protection Plan.
(3) Turbine System Maintenance Program (Section 3.5.1.3.3, SER; Section 3.5.1.3.3, SSER No. 5)*
PSE8G shall submit a turbine system maintenance program based on the manufacturer's calculations of missile-generated proba-bilities by no later than 3 years from the date of this license.
(4) Inservice Testing of Pumps and Valves (Section 3.9.6, SSER No. 4)
Pursuant to 10 CFR 50.55a and for the reasons set forth in Section 3.9.6 of SSER No. 4, the relief identified in the PSE&G submittal dated July 12, 1985, requestin5 relief from certain pump and valve testing requirements of 10 CFR 50.55a(g) is granted, for a period of no longer than two years from the date of issuance of this license or until a detailed review of the inservice testing program for pumps and valves, has been completed, which-ever comes first.
(5) Environmental Qualification (Section 3.11.5, SSER No. 5)
- a. Prior to startup following the first refueling outage, the qualified life of the electrical equipment under purchase order M-48 shall be recalculated on the basis of the actual temperatures monitored at the equipment locations during the first cycle of operation, with adequate consideration of margin,
- b. Prior to achieving initial criticality, all Tobar Model 32, Series 2 transmitters shall be replaced with qualified Rosemount Model 1153 transmitters.
(6) Inservice Inspection (Section 6.6, SER; Sections 5.2.4.3 and 6.6.3, 55ER No. 5)
- a. PSE&G shall submit an inservice inspection program in accordance with 10 CFR 50.55a(g)(4) for staff review within six months of the issuance of this license.
- b. Pursuant to 10 CFR 50.55a(a)(3) and for the reasons set forth in Sections 5.2.4.3 and 6.6.3 of SSER No. 5, the relief identified in the PSE&G submittal dated November 18, 1985, as revised by submittal dated January 20, 1986, requestin 50.55a(g)g forrelief from certain the preservice requirements inspection of 10 program, CFR is granted.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
(7) Fuel Storage and Handling (Section 9.1, SSER No. 5)
- a. No more than a total of three (3) fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks or the reactor at any one time,
- b. The above three (3) fuel assemblies as a group shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and the storage rack array.
- c. Fresh fuel assemblies, when stored in their shipping con-tainers, shall be stacked no more than three (3) containers high.
(8) Fire Protection (Section 9.5.1.8, SSER No. 5)
PSE&G shall implement and maintain in effect all provis' ions of the '
approved fire protection program as described in the Final Safety l Analysis Report for the facility through Amendment No. 14 and as '
described in submittals dated August 12 and 27, November 21 and 29, December 3 and 16, 1985, and January 3, 1986, and as approved I in the SER dated October 1984 (and Supplements 1 through 5) l subject to the following provision below.
The licensee may make changes to the approved fire I protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(9) Solid Waste' Process Control Program (Section 11.4.2, SER; Section 11.4, SSER No. 4)
PSE&G shall obtain NRC approval of the Class B and C solid waste process control program prior to processing Class B and C solid wastes.
(10) Emeraency Planning (Section 13.3, SSER No. 5) i In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
(11) Initial Startup Test Program (Section 14, SSER No. 5)
Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
RAFT
(12) Partial Feedwater Heating (Section 15.1, SER; Section 15.1, SSER No. 5)
PSE&G shall not operate the facility (other than for normal ,
start-up or shutdown) with the feedwater inlet temperature less l than 424.5 F.
(13) Detailed Control Room Design Review (Section 18.1, SSER No.5) 1
- a. PSE&G shall submit for staff review Detailed Control Room Design Review Summary Reports II and III on a schedule consistent with, and with contents as specified in, their letter of January 9, 1986.
b, Prior to exceeding five percent power, PSE&G shall provide temporary zone markings on safety-related instruments in the control room.
(14) Safety Parameter Display System (Section 18.2, SSER No. 5)
Prior to resthet following the first refueling outage,'the licensee shall, per its commitment made in a letter dated March 7, 1986, add the following parameters to the SPDS and have them operational.
1
- a. Primary containment radiation
- b. Primary containment isolation status
- c. Conbustible gas concentration in primary containment
- d. Source range neutron flux D. The facility requires exemptions from certain requirements of 10 CFR l Part 50 and 10 CFR Part 70. An exemption from the criticality alarm I requirements of 10 CFR 70.24 was granted in Special Nuclear Material License No. 1953, dated August 21, 1985. This exemption is described in Section 9.1 of Supplement No. 5 to the SER. This previously granted exemption is continued in this operating license. Exemptions from certain requirements of Appendix A to 10 CFR Part 50, are described in Supplement No. 5 to the SER. These include (a) a schedular exemption to the requirements of General Design Criterion l 17, permitting delaying completion of preoperational testing of Diesel Generator "D" until prior to initial criticality (Appendix R of SSER 5); (b) a schedular exemption to the requirements of General Design Criterion 13, permitting delaying completion of preoperational testing of the Traversing Incore Probe System until prior to initial criticality l (Appendix R of SSER 5); (c) a schedular exemption to the requirements of General Design Criterion 60, permitting delaying completion of preoperational testing of the Offgas System until prior to fully tensioning the reactor pressure vessel head closure bolts (Appendix R of SSER 5); (d) a schedular exemption to the requirements of General
Design Criterion 64, permitting delaying functionality of the Turbine Building Circulating Water System-Radiation Monitoring System until 5 percent power for local indication, and until 120 days after fuel ,
load for control room indication. Exemptions from certain requirements i of Appendix J to 10 CFR Part 50, are described in Supplement No. 5 to the SER. These include (a) an exemption from the requirement of Paragraph III.D.2(b)(ii) of Ap;endix J, exempting overall containment air lock leakage testing unless mainteo nce has been performed on the air lock (Section 6.2.6 of SSER 5); (b; an exemption from the require-ment of Paragraph III.C.2(b) of Appendix J, exempting main steam isolation valve leak-rate testing at 1.10 Pa (Section 6.2.6 of SSER 5);
(c) an exemption from Paragraph III.D.3 of Appendix J, exempting Type C
of testing)on SSER 5 ; (d)transverse incore an exemption probe from systemIII.D.2(a)
Paragraph shear valves (Section of Appendix J, 6.2.6 exempting Type C testing for instrument lines and lines containing excess flow check valves (Section 6.2.6 of SSER 5); and (e) an exemption from Paragraph III.C.2(a) of Appendix J, exempting Type C testing of thermal relief valves. These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The special circum-stances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto.
These exemptions are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E. PSE8G shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification, and safeguards contingency plans previously approved by the Commission and all amend-ments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). These plans, which contain safeguards information protected under 10 CFR 73.21(m), are entitled: " Hope Creek Generating Station Security Plan," with revisions submitted through March 20, 1986, " Hope Creek Generating Station Security Training and Qualification Plan," with revisions submitted through July 18, 1984, and " Hope Creek Generating Station Security Contingency Plan," with revisions submitted through July 23, 1985.
F. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, PSE&G shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hurs to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures de:cribed in 10 CFR 50.73(b), (c), and (e).
DRAR i p- - -
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G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accord-ance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
H. This license is effective as of the date of issuance and shall expire at midnight on FOR THE NUCLEAR REGULATORY COMMISSION
- r. -
+
Harold R. Denton, Director 3
Office of Nuclear Reactor Regulation
Enclosures:
- 1. Attachment 1
- 2. Appendix A - Technical Specifications (NUREG-1186)
- 3. Appendix B - Environmental Protection Plan Date of Issuance:
I d
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