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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 |
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 | |
ML20205J991 | 30 March 1999 | Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable | Stress corrosion cracking Pressure Boundary Leakage Unidentified leakage |
ML20199L692 | 21 January 1999 | Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR | |
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 |
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 |
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 |
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 | |
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 |
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 Water rod |
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 Overspeed trip |
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 |
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 |
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 Subsequent actuation |
ML20138L370 | 17 February 1997 | Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements | |
ML20134D219 | 27 January 1997 | Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K | |
ML20129K332 | 18 October 1996 | Cycle 15 Startup Test Results | Shutdown Margin |
ML20129C239 | 16 October 1996 | Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage | Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML20129D398 | 20 September 1996 | Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases | Shutdown Margin Hydrostatic Power change Operational leakage |
ML20216H884 | 30 June 1996 | Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program |
ML20116F397 | 30 June 1996 | Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change |
ML20113C357 | 25 June 1996 | Proposed Tech Specs Re Upgrade Program | Offsite Circuit |
ML20113A786 | 10 June 1996 | Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp | Shutdown Margin Packing leak Offsite Dose Calculation Manual Anticipated operational occurrence Nondestructive Examination FLEX Abnormal operational transient Scram Discharge Volume Intergranular Stress Corrosion Cracking Process Control Program Earthquake Fuel cladding Pressure Boundary Leakage Power change Unidentified leakage Subsequent actuation Water rod |
ML20117D712 | 6 May 1996 | Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt | High Radiation Area Offsite Dose Calculation Manual Process Control Program |
ML20107A188 | 4 April 1996 | Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys | |
ML20101H138 | 25 March 1996 | Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project | Safe Shutdown Shutdown Margin Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Packing leak High Radiation Area Ultimate heat sink Grab sample Offsite Dose Calculation Manual Anticipated operational occurrence Hydrostatic Nondestructive Examination Squib Abnormal operational transient Annual Radioactive Effluent Release Report Scram Discharge Volume Annual Radiological Environmental Operating Report Intergranular Stress Corrosion Cracking Process Control Program Stress corrosion cracking Excess Flow Check Valve Battery sizing Overtravel Exemption Request Fuel cladding Pressure Boundary Leakage Offsite Circuit Fire Protection Program Grace period Power change Unidentified leakage Failure to Scram Overspeed trip Subsequent actuation Water rod Operational leakage Loss of condenser vacuum Water hammer |
ML20097D923 | 8 February 1996 | Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs | |
ML20100C044 | 24 January 1996 | Secondary Containment Leak Test Summary | |
ML20093K772 | 12 October 1995 | Quad-Cities Nuclear Power Station Unit 2 Cycle 14 Startup Test Results Summary | Shutdown Margin |
ML20098A382 | 20 September 1995 | Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals | Safe Shutdown Shutdown Margin High Radiation Area Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Safeguards Contingency Plan Fire Protection Program |
ML20086D474 | 30 June 1995 | Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 | Grab sample Hydrostatic Pressure Boundary Leakage Unidentified leakage Overspeed trip Operational leakage |
ML20087H865 | 2 May 1995 | Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 | Shutdown Margin Reactor Vessel Water Level |
ML20082H748 | 10 April 1995 | Proposed Tech Specs,Revising SR for HPCI & RCIC Sys | |
ML20080K817 | 23 February 1995 | Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc |