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Issue date | Title | Topic | |
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ML20217M210 | 19 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 | |
ML20217M663 | 19 October 1999 | Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted | |
ML18107A560 | 18 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 | |
ML20217K924 | 14 October 1999 | Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys | |
ML20217F739 | 14 October 1999 | Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests | Safe Shutdown Exemption Request |
ML20217F684 | 13 October 1999 | Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam | |
ML20217F302 | 12 October 1999 | Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, | Safe Shutdown Fire Barrier |
ML20217E745 | 8 October 1999 | Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 | Hydrostatic VT-2 |
ML18107A553 | 8 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 | |
ML18107A556 | 7 October 1999 | Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests | Coatings Moisture barrier Dissimilar Metal Weld |
ML20217C414 | 6 October 1999 | Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld | Safe Shutdown Safe Shutdown Earthquake Coatings Operating Basis Earthquake Seismically rugged Earthquake Backfit |
ML20217B915 | 6 October 1999 | Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware | |
ML20217B770 | 6 October 1999 | Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions | |
ML20217B405 | 5 October 1999 | Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report | |
ML20217B318 | 5 October 1999 | Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure | |
ML18107A559 | 5 October 1999 | Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 | |
ML18107A550 | 5 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 | |
ML18107A552 | 5 October 1999 | Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys | |
ML20217B889 | 1 October 1999 | Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl | |
05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) | 1 October 1999 | Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) | |
ML20217D521 | 30 September 1999 | Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule | |
ML20212J685 | 29 September 1999 | Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl | |
ML20216J398 | 29 September 1999 | Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity | |
ML20212J575 | 28 September 1999 | Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls | |
IR 05000272/1999007 | 28 September 1999 | Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified | |
ML20216J019 | 27 September 1999 | Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant | |
ML20212H617 | 24 September 1999 | Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier | |
ML20212H543 | 24 September 1999 | Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 | |
ML20216H645 | 24 September 1999 | Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink | |
ML20216H675 | 24 September 1999 | Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 | |
ML20216F881 | 23 September 1999 | Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather | |
ML20212E866 | 22 September 1999 | Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition | |
ML18107A534 | 22 September 1999 | Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) | Generic Fundamentals Examination |
ML18107A542 | 22 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 | NJPDES |
ML20212F548 | 20 September 1999 | Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 | Generic Fundamentals Examination |
ML20212D119 | 17 September 1999 | Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 | |
ML20212B363 | 14 September 1999 | Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld | |
ML18107A532 | 13 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. | |
ML18107A533 | 13 September 1999 | Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 | Hydrostatic |
ML18107A535 | 13 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 | |
ML20212A009 | 9 September 1999 | Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment | |
ML18107A522 | 8 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 | Nondestructive Examination VT-2 |
ML18107A523 | 8 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 | |
ML20211P296 | 7 September 1999 | Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania | |
ML20211K703 | 30 August 1999 | Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 | Minimum Critical Power Ratio |
ML18107A518 | 26 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 | Nondestructive Examination VT-2 Liquid penetrant Pressure Boundary Leakage |
ML20211E694 | 26 August 1999 | Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt | Minimum Critical Power Ratio |
ML18107A506 | 26 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 | Significance Determination Process |
ML18107A498 | 26 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 | |
ML20211Q449 | 25 August 1999 | Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) |