ML20199E036
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| ML20199E036 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/12/1999 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20199E026 | List: |
| References | |
| NUDOCS 9901200293 | |
| Download: ML20199E036 (1) | |
Similar Documents at Dresden | |
|---|---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20199E0361999-01-12012 January 1999
[Table view]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 ML20196F6451998-11-30030 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 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G8781997-07-18018 July 1997 Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program ML20148K6141997-06-0505 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 ML17187A7991997-02-17017 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 ML20135B0581996-11-25025 November 1996 Proposed Tech Specs,Submitting Update to Administrative Controls Section of TS Which Reflects Transition of Overall Corporate Responsibility for Storage of Spent Nuclear Fuel ML20129F3231996-10-23023 October 1996 Proposed Tech Specs Replacing All Existing Pages of Unit 1 TS ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20113B6001996-06-20020 June 1996 Proposed Tech Specs,Incorporating New NRC Approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Thermal Limits in Cycle Specific COLR & Change to Fuel Assembly Design Features ML20112E6341996-05-22022 May 1996 Proposed Tech Specs Requesting Emergency Amend to License DPR-25 Temporarily Modifying Description of Certain Corner Room Steel Supports to Match Current Configuration Until Mod During Next Refueling Outage ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20125D6381992-12-0808 December 1992 Proposed Tech Specs 3/4.1 Re Reactor Protection Sys ML20106A6221992-09-15015 September 1992 Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits ML20099D7791992-07-29029 July 1992 Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity ML20096F1161992-04-24024 April 1992 Proposed Ts,Changing OL Section 2.G Re Reporting Requirements ML20058L9381990-07-31031 July 1990 Proposed Tech Specs Reflecting Nonoperating Status of Facility & Clarifying Section 3.10.F ML20137C2401986-01-0707 January 1986 Proposed Tech Specs,Deleting Authority to Operate Unit & Sys Requirements & Surveillances No Longer Applicable ML20052C0761982-04-29029 April 1982 Proposed Changes to Licenses DPR-19,DPR-25,DPR-29 & DPR-30 Re Surveillance Requirements to Test Automatic Pressure Relief Valves Daily When HPCI Subsystem Is Inoperable ML17194A4181982-01-12012 January 1982 Revised Tech Spec Tables 4.2.1 & 3.2.4 Re Restoring Inoperable Indication Prior to Startup ML17194A4061982-01-11011 January 1982 Proposed Tech Specs Re Reload Fuel & Core Design,Transients & Accident Analyses & LOCA Analysis ML18025B6791981-10-19019 October 1981 Proposed Revisions to Tech Spec 4.7.A Re Surveillance Requirements,Primary Containment ML19343D1181981-04-0303 April 1981 Proposed Revision to Tech Spec Table 3.6.1 ML19309H8901980-05-15015 May 1980 Proposed Changes to Tech Specs,Deleting Requirement to Maintain at Least Three Counts Per Second on Each Source Range Monitor When Only Two Fuel Assemblies Are in Quadrant ML17174A1051979-11-0101 November 1979 Proposed Tech Spec Changes 1.1-3.2.3 to Permit Reactor Power Ascension to Proceed Along Modified Power/Flow Line,For Dresden Facility ML17174A1061979-11-0101 November 1979 Proposed Tech Spec Changes 1.1-3.2.3 to Permit Reactor Power Ascension to Proceed Along Modified Power/Flow Line,For Dresden Facility ML17174A1071979-11-0101 November 1979 Proposed Tech Spec Changes 1.1-3.2.3.,for Quad-Cities Facility ML17174A1081979-11-0101 November 1979 Proposed Tech Spec Changes 1.1-3.2.3.,for Quad-Cities Facility ML20084D2751974-01-30030 January 1974 Proposed Tech Spec 15.4.11 Re Hydraulic Shock Suppressors 1999-01-12 Category:TECHNICAL SPECIFICATIONS & TEST REPORTS MONTHYEARML20211C3311999-04-30030 April 1999
[Table view]Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205A0871999-03-22022 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) ML20199E0361999-01-12012 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 ML20196F6451998-11-30030 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 ML20237A8651998-08-0707 August 1998 Qualified Unit 1 Supervisor Initial & Continuing Training Program ML20151S2691998-07-31031 July 1998 Rev 1.8 to Chapter 12 of Dresden Station Odcm ML20217N9331998-04-30030 April 1998 Rev 1.7 to Chapter 12 of Dresden Station Odcm ML20216H4321997-12-31031 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 ML20216H8551997-12-31031 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 ML20198M2491997-12-18018 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) ML20216H8241997-10-31031 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 ML20216H9041997-10-31031 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 ML20198P1601997-10-20020 October 1997 Rev 1.5 to Odcm,Chapter 12 ML20212A2941997-10-0202 October 1997 Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G8781997-07-18018 July 1997 Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program ML20148K6141997-06-0505 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 ML20141A6411997-05-31031 May 1997 Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM ML20216H8691997-03-31031 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 ML17187A7991997-02-17017 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 ML20137C0011997-01-31031 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 ML20135B0581996-11-25025 November 1996 Proposed Tech Specs,Submitting Update to Administrative Controls Section of TS Which Reflects Transition of Overall Corporate Responsibility for Storage of Spent Nuclear Fuel ML20129F3231996-10-23023 October 1996 Proposed Tech Specs Replacing All Existing Pages of Unit 1 TS ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20216H8841996-06-30030 June 1996 Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F ML20113B6001996-06-20020 June 1996 Proposed Tech Specs,Incorporating New NRC Approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Thermal Limits in Cycle Specific COLR & Change to Fuel Assembly Design Features ML20112E6341996-05-22022 May 1996 Proposed Tech Specs Requesting Emergency Amend to License DPR-25 Temporarily Modifying Description of Certain Corner Room Steel Supports to Match Current Configuration Until Mod During Next Refueling Outage ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20092C8091995-05-12012 May 1995 Rev 2, Shroud Repairs Program for Dresden Units 2 & 3, Back-up Calculations for RPV Stress Rept Number 25A5691, May 1995 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20085M6171994-07-31031 July 1994 Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM ML20063F9011994-01-31031 January 1994 Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Dresden Station Units 2 & 3 ML17179B0931993-09-10010 September 1993 Rev 2 to Dresden Station 3rd Interval IST Plan, Sections 2,13 & 14,pages 2-1,13-1 to 13-4 & 14-40,respectively ML20058E8751993-09-0303 September 1993 Revised AOP-6.3, Loss of RHR Shutdown Cooling ML20058E8351993-06-10010 June 1993 Revised AOP-7.4, Control Room Inaccessibility ML20127D0691992-12-30030 December 1992 Corporate Emergency Response Organization Required Reading Package 92-11 ML20125D6381992-12-0808 December 1992 Proposed Tech Specs 3/4.1 Re Reactor Protection Sys ML20058E8681992-09-29029 September 1992 Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1 ML20106A6221992-09-15015 September 1992 Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits ML20081M1251992-08-31031 August 1992 Rev 17 to Procedure Dgp 03-04 Control Rod Movements ML20099D7791992-07-29029 July 1992 Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity ML20096F1161992-04-24024 April 1992 Proposed Ts,Changing OL Section 2.G Re Reporting Requirements ML20081M1851992-01-31031 January 1992 Rev 17 to Procedure DAP 07-02, Conduct of Shift Operations ML20081M1611991-11-20020 November 1991 Rev 0 to Procedure DAP 14-4, Control Rod Sequences ML20058E8761991-11-18018 November 1991 Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1 ML20081M0311991-11-15015 November 1991 Rev 2 to Procedure Doa 0300-12, Mispositioned Control Rod (W-2,W-3) ML20081M1721991-08-31031 August 1991 Rev 15 to Procedure DAP 07-01, Operations Dept Organization ML20081M1401991-05-17017 May 1991 Rev 6 to Procedure DOP 0400-02, Control Rod Minimizer ML20081M1971990-08-30030 August 1990 Rev 9 to Procedure DAP 07-05, Operating Logs & Records 1999-04-30 |
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Pool Water Level 3/4.10.A BASER FUEL HANDLING AND STORAGE 3/4.10.A Fuel Storace Pool Water Level And Quality To assure there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established. The minimum water level of 18 feet is established because it would be a significant change from the normal level, well above a level to assure adequate cooling (just above active fuel).
l To prevent the growth of micro-organisms a'id concern about corrosion of metallic pool structures, quality limits for fuel pool chemistry have been established.
i DRESDEN - UNIT 1 B 3/4.10-1 Revision 1
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