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Issue date | Title | Topic | |
---|---|---|---|
ML20217D796 | 12 October 1999 | Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A | Scram Discharge Volume Fuel cladding |
ML20210R828 | 13 August 1999 | Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 | Safe Shutdown Battery sizing |
ML20209J232 | 16 July 1999 | Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs | Hydrostatic Squib Exemption Request |
ML20196K194 | 30 June 1999 | Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual | Offsite Dose Calculation Manual |
ML20209C295 | 29 June 1999 | Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability | |
ML20211C331 | 30 April 1999 | Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood | Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent |
ML20205L263 | 5 April 1999 | Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in | Fuel cladding |
ML20205J991 | 30 March 1999 | Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable | Pressure Boundary Leakage |
ML20205J974 | 30 March 1999 | Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info | Safe Shutdown Safeguards Contingency Plan Fire Protection Program |
ML20205J932 | 30 March 1999 | Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months | |
ML20205A087 | 22 March 1999 | Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets) | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Power change |
ML20199L774 | 21 January 1999 | Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem | Shutdown Margin |
ML20199L692 | 21 January 1999 | Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR | |
ML20199E036 | 12 January 1999 | Proposed Tech Specs Section 3.10, Fuel Handling & Storage, Eliminating Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS | |
ML20196H457 | 30 November 1998 | Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days | Safe Shutdown |
ML20196F645 | 30 November 1998 | Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document | Shutdown Margin Fuel cladding |
ML20196K586 | 5 November 1998 | Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station | Process Control Program |
ML20155D809 | 29 October 1998 | Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 | |
ML20195J904 | 24 September 1998 | Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept | |
ML20151S799 | 31 August 1998 | Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 | Squib |
ML20237A865 | 7 August 1998 | Qualified Unit 1 Supervisor Initial & Continuing Training Program | Job Performance Measure |
ML20236W840 | 31 July 1998 | Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves | Exemption Request |
ML20151S269 | 31 July 1998 | Rev 1.8 to Chapter 12 of Dresden Station Odcm | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Power change |
ML20247D776 | 5 May 1998 | Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 | |
ML20217N933 | 30 April 1998 | Rev 1.7 to Chapter 12 of Dresden Station Odcm | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Power change |
ML20246Q348 | 29 April 1998 | TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C | |
ML20217G148 | 27 March 1998 | Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 | Reactor Vessel Water Level |
ML20216H432 | 31 December 1997 | Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change |
ML20216H855 | 31 December 1997 | Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Power change |
ML20198M249 | 18 December 1997 | Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets) | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Power change |
ML20216H824 | 31 October 1997 | Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent Power change |
ML20216H904 | 31 October 1997 | Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F | |
ML20198P160 | 20 October 1997 | Rev 1.5 to Odcm,Chapter 12 | Grab sample Offsite Dose Calculation Manual |
ML20212A294 | 2 October 1997 | Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld | |
ML20216C638 | 29 August 1997 | Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates | Shutdown Margin Offsite Dose Calculation Manual Anticipated operational occurrence Fuel cladding |
ML20196G878 | 18 July 1997 | Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program | |
ML20148K614 | 5 June 1997 | Proposed Tech Specs,Updating Revised TS to Format Consistent W/Recently Approved TS Upgrade for DNP & Proposed Other Miscellaneous Changes Re Decommissioning Status of Unit 1 | High Radiation Area Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML20141A641 | 31 May 1997 | Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report |
ML20196G027 | 1 May 1997 | Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test | Safe Shutdown Offsite Circuit |
ML20138G332 | 29 April 1997 | Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing | Shutdown Margin |
ML20138B323 | 21 April 1997 | Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 | Shutdown Margin Anticipated operational occurrence Fuel cladding |
ML20216H869 | 31 March 1997 | Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F | |
ML20137G398 | 26 March 1997 | Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment | |
ML20135F732 | 3 March 1997 | Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E | Safe Shutdown |
ML20135D946 | 24 February 1997 | Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c | Ultimate heat sink |
ML17187A799 | 17 February 1997 | Proposed Tech Specs 3/4.7.K & 3/4.8.C Re Issues Resulting from Comeds Efforts to Reconstitute Design Basis of Chrs | |
ML20138L370 | 17 February 1997 | Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements | |
ML20138L401 | 17 February 1997 | Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements | Shutdown Margin Fuel cladding |
ML20137C001 | 31 January 1997 | Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program |
ML20134D219 | 27 January 1997 | Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K |