|
|---|
Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20203G5091999-02-16016 February 1999
Amends 171 & 166 to Licenses DPR-19 & DPR-25,respectively, Revising TS to Reflect Use of Licensee ATRIUM-9B Fuel
ML20237A1111998-08-0707 August 1998
Amend 163 to License DPR-25,revising TS 4.6.E to Allow one-time Extension of 40-month Surveillance Interval Requirement to Set Pressure Test or Replace MSSVs to Max Intenval of 60 Months
ML20203K5081998-02-25025 February 1998
Amends 165 & 160 to Licenses DPR-19 & DPR-25,respectively, Removing 24/48 Vdc Batteries & Associated Charger & Distribution Sys from Unit 2 TS
ML20203H2351998-02-25025 February 1998
Amends 166 & 161 to Licenses DPR-19 & DPR-25,respectively, Correcting Typo Introduced Into TS W/Issuance of Amends 150 & 145 Issued on 960628
ML20202E2611998-01-0505 January 1998
Amends 164,159,179 & 177 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,adding New TS Section 3/4.12.C & Associated Bases to Allow Certain Rc Pressure Tests to Be Preformed in Mode 4
ML20216J8721997-09-10010 September 1997
Amends 162 & 157 to Licenses DPR-19 & DPR-25,respectively,to Revise TS Surveillance Calibr of Reactor Water Level Instrumentation Used to Initiate ECCS
ML20210Q4381997-08-21021 August 1997
Amends 161 & 156 to Licenses DPR-19 & DPR-25,respectively, Revises TS to Increase HPCI Sys Low Pressure Isolation Setpoint from Greater than 80 Psig to Greater than 100 Psig
ML20140G5251997-06-12012 June 1997
Amends 160 & 155 to Licenses DPR-19 & DPR-25,respectively, Incorporating NRC-approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Fuel cycle-specific Thermal Limits
ML20140E9691997-04-30030 April 1997
Amends 157 & 152 to Licenses DPR-19 & DPR-25,respectively, Evaluating Unreviewed Safety Question Associated W/Use of Containment Pressure to Compensate for Deficiency in NPSH for ECCS Pumps Following DBA
ML20138D1651997-04-25025 April 1997
Amends 158 & 153 to Licenses DPR-19 & DPR-25,respectively, Changing TS SR 4.7.P.2.b & 4.7.P.3 Values for Allowed Methyl Iodide Penetration for SBGT Charcoal Adsorbers
ML20137R6301997-04-10010 April 1997
Amends 156 & 151 to Licenses DPR-19 & DPR-25,respectively, Removing 24/48 Vdc Batteries & Associated Chargers & Distribution Sys from Unit 3 Ts,By Adding Footnote to 24/48 Vdc Batteries
ML20135E1901997-03-0404 March 1997
Amends 173 & 169 to Licenses DPR-29 & DPR-30,respectively, Revising TSs by Allowing Single Rc Moved When Plant in Hot Shutdown or Cold Shutdown Condition Providing One Rod Out Interlock Operable & Mode Switch in Refuel Position
ML20135E4301997-02-28028 February 1997
Amends 172 & 168 to Licenses DPR-29 & DPR-30,respectively, Updating pressure-temperature Curves Contained in Licensee TS 22 Effective Full Power Yrs
ML20135E1501997-02-28028 February 1997
Amends 153 & 148 to Licenses DPR-19 & DPR-25,respectively, Updating pressure-temperature Curves Contained in Licensee TS 22 Effective Full Power Yrs
ML20129E0941996-09-26026 September 1996
Amends 151 & 146 to Licenses DPR-19 & DPR-25,respectively, Deferring Implementation Date as Stated Until 970115
ML20096D8331996-01-11011 January 1996
Amends 148 & 142 to Licenses DPR-19 & DPR-25,respectively, Revising TS to Incorporate 10CFR50 App J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors, Option B
ML20096D8531996-01-11011 January 1996
Amends 169 & 165 to Licenses DPR-29 & DPR-30,respectively, Revising TS to Incorporate 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B
ML20099M3541995-12-29029 December 1995
Amends 147 & 141 to Licenses DPR-19 & DPR-25,respectively, Re Partial Implementation of Request & Change Only Implementation Date of Previous TS Upgrade Program Issued for Util
ML20092K3181995-09-20020 September 1995
Amends 139,133,161 & 157 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,responding to 921208 Application,As Supplemented by 930910 & s Re Initiation of TS Upgrade Program for Plants
ML20085L6861995-06-14014 June 1995
Amends 135,129,156 & 152 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,upgrading TS Section 5.0, Design Features, Per TS Upgrade Program
ML20085H0121995-06-13013 June 1995
Amends 134,128,155 & 151 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,re Proposed Upgrade of Sections 2.0,3/4.11 & 3/4.12 of Dresden & Quad Cities TS
ML20085K3321995-06-0808 June 1995
Amends 133,127,154 & 150 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,integrating Addl Info Such as Equipment Operability Requirements During Shutdown Conditions
ML20078S8211995-02-16016 February 1995
Amends 131,125,152 & 148 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,upgrading Sections 1.0,3.0/4.0 & 3/4.3 of Plants TS Re Definitions,Applicability & Reactivity,Per 920729 Request
ML20071G1301994-07-0606 July 1994
Amends 128,122,148 & 144 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,revising TS 3/4.7.D by Adding Check Valves to Limiting Condition for Operational Statement of TS
ML20065J4471994-04-0505 April 1994
Amends 126 & 120 to Licenses DPR-19 & DPR-25,respectively, Modifying Trip Level Settings for Isolation Condenser & High Pressure Core Injection Sys Steam Lines to More Conservative Values
ML20064H4781994-03-11011 March 1994
Amends 125,119,145 & 141 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,consist of Changes to Facilities TS That Will Update Leakage Test Requirements of Drywell Airlock to Stds of 10CFR50,Appendix J & Section III.D.2
ML20128N5881993-02-11011 February 1993
Amends 122 & 117 to License DPR-19 & DPR-25,respectively, Deleting Table 3.7.1, Primary Containment Isolation, & Modifying Section 3/4.7.D,per Guidance of GL 91-08 in Plant TS
ML20128C2721992-11-23023 November 1992
Amend 121 to License DPR-19,incorporating by Ref,New Siemens Nuclear Power Methodologies,Increasing Resultant SLMCPR in TSs & Removing Specs Referring to SLMCPR for GE Fuel
ML20116L5681992-10-29029 October 1992
Amends 116 & 120 to Licenses DPR-25 & DPR-19,respectively, Restructures Section 3/4.9 (Auxiliary Electrical Sys) as Part of Dresden TS Improvment Program
ML20116A8791992-10-19019 October 1992
Amends 119,115,138 & 134 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,revising Tech Specs Re Auxiliary Electrical Sys
ML20105A7361992-09-11011 September 1992
Amends 118 & 114 to Licenses DPR-19 & DPR-25,respectively, Adding Two New Sections Under Administrative Controls Sections 6.11 & 6.12
ML20114A5631992-07-24024 July 1992
Amends 113,116,131 & 135 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,changing Types of Procedures Requiring Review by Onsite Review & Investigative Function
ML20113H6351992-07-24024 July 1992
Amend 117 to License DPR-19,clarifying Reporting Requirements of Section 2.G of FOL
ML20101L1571992-06-29029 June 1992
Amends 115 & 112 to Licenses DPR-19 & DPR-25,respectively, Revising TS to Reflect Mod to Fast Acting Solenoid Valves Which Initiate Rapid Closure of TCV
ML20079Q1201991-10-24024 October 1991
Corrected Pages B 3/4.6-26a to Amends 114 & 111 to Licenses DPR-19 & DPR-25,respectively
ML20082R1771991-09-0505 September 1991
Amends 114 & 111 to Licenses DPR-19 & DPR-25,respectively, Revising Pressure/Temp Limits for RCS
ML20066K7701991-02-20020 February 1991
License DPR-19 to Operate Facility at steady-state Reactor Core Power Levels Not in Excess of 2527 Mwt
ML20059M8441990-10-0202 October 1990
Amends 113 & 109 to Licenses DPR-19 & DPR-25,respectively, Incorporating ATWS Requirements Into Tech Specs
ML20055H8251990-07-25025 July 1990
Amends 111 & 107 to Licenses DPR-19 & DPR-25 Respectively, Revising Surveillance Interval Requirement for Functional Testing of Reactor Protection Sys Electrical Protection Assemblies
ML20011F5181990-02-0808 February 1990
Amends 110 & 105 to Licenses DPR-19 & DPR-25,respectively, Revising Tech Specs,Per Generic Ltr 88-16,by Replacing cycle-specific Operating Limits W/Refs to Core Operating Limits Rept
ML20245H6521989-08-0909 August 1989
Corrected Amends 106 & 101 to Licenses DPR-19 & DPR-25, Respectively,Consisting of Index Pages to Original Amends
ML20246C8491989-06-30030 June 1989
Amends 106 & 101 to Licenses DPR-19 & DPR-25,respectively, Replacing Existing License Conditions on Fire Protection W/Std Condition Noted in Generic Ltr 86-10
ML20246G9941989-04-26026 April 1989
Amends 117,113,105 & 100 to Licenses DPR-29,DPR-30,DPR-19 & DPR-25,respectively,deleting Organization Charts from Tech Specs
ML20205L1941988-10-26026 October 1988
Amends 101 & 97 to Licenses DPR-19 & DPR-25,respectively, Revising Tech Specs Requirements of Section 3.5.F to Include More Prescriptive Requirements for ECCS Operability During Cold Shutdown & Refueling Operational Modes
ML20150D6091988-06-20020 June 1988
Amend 94 to License DPR-25,changing Tech Specs to Support Cycle 11 Operation W/Advanced Nuclear Fuels Co 9x9 Reload Fuel
ML20235W8271987-10-0909 October 1987
Amends 96 & 91 to Licenses DPR-19 & DPR-25,respectively, Changing Tech Specs to Impose 4 Kv cross-tie Operability Requirement
ML20209B9031986-09-0202 September 1986
Amend 89 to License DPR-25,revising Tech Specs to Provide Surveillance Requirements for Newly Modified Reactor Scram Sys
ML20214K5291986-08-13013 August 1986
Amends 93 & 88 to Licenses DPR-19 & DPR-25,respectively, Revising Tech Specs Re Use of Mobile Vol Reduction Sys
ML20195C7951986-05-27027 May 1986
Amend 86 to License DPR-25,revising High Flow Isolation Setpoint for Isolation Condenser Return Line Due to Replacement of Elbow Taps W/Annubar Flow Element
ML20203N6131986-04-28028 April 1986
Amend 92 to License DPR-19,changing Requirements in Tech Spec Section 3.9.B.2 Increasing Allowable Outage Period for Diesel Generator from Present 7 Days to 14 Days on one-time Only Basis
1999-02-16
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20203G5091999-02-16016 February 1999
Amends 171 & 166 to Licenses DPR-19 & DPR-25,respectively, Revising TS to Reflect Use of Licensee ATRIUM-9B Fuel
ML20237A1111998-08-0707 August 1998
Amend 163 to License DPR-25,revising TS 4.6.E to Allow one-time Extension of 40-month Surveillance Interval Requirement to Set Pressure Test or Replace MSSVs to Max Intenval of 60 Months
ML20203H2351998-02-25025 February 1998
Amends 166 & 161 to Licenses DPR-19 & DPR-25,respectively, Correcting Typo Introduced Into TS W/Issuance of Amends 150 & 145 Issued on 960628
ML20203K5081998-02-25025 February 1998
Amends 165 & 160 to Licenses DPR-19 & DPR-25,respectively, Removing 24/48 Vdc Batteries & Associated Charger & Distribution Sys from Unit 2 TS
ML20202E2611998-01-0505 January 1998
Amends 164,159,179 & 177 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,adding New TS Section 3/4.12.C & Associated Bases to Allow Certain Rc Pressure Tests to Be Preformed in Mode 4
ML20216J8721997-09-10010 September 1997
Amends 162 & 157 to Licenses DPR-19 & DPR-25,respectively,to Revise TS Surveillance Calibr of Reactor Water Level Instrumentation Used to Initiate ECCS
ML20210Q4381997-08-21021 August 1997
Amends 161 & 156 to Licenses DPR-19 & DPR-25,respectively, Revises TS to Increase HPCI Sys Low Pressure Isolation Setpoint from Greater than 80 Psig to Greater than 100 Psig
ML20140G5251997-06-12012 June 1997
Amends 160 & 155 to Licenses DPR-19 & DPR-25,respectively, Incorporating NRC-approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Fuel cycle-specific Thermal Limits
ML20140E9691997-04-30030 April 1997
Amends 157 & 152 to Licenses DPR-19 & DPR-25,respectively, Evaluating Unreviewed Safety Question Associated W/Use of Containment Pressure to Compensate for Deficiency in NPSH for ECCS Pumps Following DBA
ML20138D1651997-04-25025 April 1997
Amends 158 & 153 to Licenses DPR-19 & DPR-25,respectively, Changing TS SR 4.7.P.2.b & 4.7.P.3 Values for Allowed Methyl Iodide Penetration for SBGT Charcoal Adsorbers
ML20137R6301997-04-10010 April 1997
Amends 156 & 151 to Licenses DPR-19 & DPR-25,respectively, Removing 24/48 Vdc Batteries & Associated Chargers & Distribution Sys from Unit 3 Ts,By Adding Footnote to 24/48 Vdc Batteries
ML20135E1901997-03-0404 March 1997
Amends 173 & 169 to Licenses DPR-29 & DPR-30,respectively, Revising TSs by Allowing Single Rc Moved When Plant in Hot Shutdown or Cold Shutdown Condition Providing One Rod Out Interlock Operable & Mode Switch in Refuel Position
ML20135E4301997-02-28028 February 1997
Amends 172 & 168 to Licenses DPR-29 & DPR-30,respectively, Updating pressure-temperature Curves Contained in Licensee TS 22 Effective Full Power Yrs
ML20135E1501997-02-28028 February 1997
Amends 153 & 148 to Licenses DPR-19 & DPR-25,respectively, Updating pressure-temperature Curves Contained in Licensee TS 22 Effective Full Power Yrs
ML17187A7971997-02-17017 February 1997
Application for Amend to Licenses DPR-19 & DPR-25,App A,Tss, Section 3/4.7.K, Suppression Chamber & Section 3/4.8, Ultimate Heat Sink, to Address Issues Re Efforts to Reconstitute Design Basis of Containment Heat Removal Sys
ML20135B0511996-11-25025 November 1996
Update to 961023 Application for Amend to License DPR-2, Updating Administrative Controls Section of Proposed TS Amend to Reflect Transition of Overall Corporate Responsibility for Storage of Spent Nuclear Fuel
ML20129F3141996-10-23023 October 1996
Application for Amend to License DPR-2,replacing All Existing Pp of Unit 1 TS
ML20129E0941996-09-26026 September 1996
Amends 151 & 146 to Licenses DPR-19 & DPR-25,respectively, Deferring Implementation Date as Stated Until 970115
ML20096D8531996-01-11011 January 1996
Amends 169 & 165 to Licenses DPR-29 & DPR-30,respectively, Revising TS to Incorporate 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B
ML20096D8331996-01-11011 January 1996
Amends 148 & 142 to Licenses DPR-19 & DPR-25,respectively, Revising TS to Incorporate 10CFR50 App J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors, Option B
ML20099M3541995-12-29029 December 1995
Amends 147 & 141 to Licenses DPR-19 & DPR-25,respectively, Re Partial Implementation of Request & Change Only Implementation Date of Previous TS Upgrade Program Issued for Util
ML20092K3181995-09-20020 September 1995
Amends 139,133,161 & 157 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,responding to 921208 Application,As Supplemented by 930910 & s Re Initiation of TS Upgrade Program for Plants
ML20085L6861995-06-14014 June 1995
Amends 135,129,156 & 152 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,upgrading TS Section 5.0, Design Features, Per TS Upgrade Program
ML20085H0121995-06-13013 June 1995
Amends 134,128,155 & 151 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,re Proposed Upgrade of Sections 2.0,3/4.11 & 3/4.12 of Dresden & Quad Cities TS
ML20085K3321995-06-0808 June 1995
Amends 133,127,154 & 150 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,integrating Addl Info Such as Equipment Operability Requirements During Shutdown Conditions
ML20078S8211995-02-16016 February 1995
Amends 131,125,152 & 148 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,upgrading Sections 1.0,3.0/4.0 & 3/4.3 of Plants TS Re Definitions,Applicability & Reactivity,Per 920729 Request
ML20071G1301994-07-0606 July 1994
Amends 128,122,148 & 144 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,revising TS 3/4.7.D by Adding Check Valves to Limiting Condition for Operational Statement of TS
ML20065J4471994-04-0505 April 1994
Amends 126 & 120 to Licenses DPR-19 & DPR-25,respectively, Modifying Trip Level Settings for Isolation Condenser & High Pressure Core Injection Sys Steam Lines to More Conservative Values
ML20064H4781994-03-11011 March 1994
Amends 125,119,145 & 141 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,consist of Changes to Facilities TS That Will Update Leakage Test Requirements of Drywell Airlock to Stds of 10CFR50,Appendix J & Section III.D.2
ML20128N5881993-02-11011 February 1993
Amends 122 & 117 to License DPR-19 & DPR-25,respectively, Deleting Table 3.7.1, Primary Containment Isolation, & Modifying Section 3/4.7.D,per Guidance of GL 91-08 in Plant TS
ML20128C2721992-11-23023 November 1992
Amend 121 to License DPR-19,incorporating by Ref,New Siemens Nuclear Power Methodologies,Increasing Resultant SLMCPR in TSs & Removing Specs Referring to SLMCPR for GE Fuel
ML20116L5681992-10-29029 October 1992
Amends 116 & 120 to Licenses DPR-25 & DPR-19,respectively, Restructures Section 3/4.9 (Auxiliary Electrical Sys) as Part of Dresden TS Improvment Program
ML20116A8791992-10-19019 October 1992
Amends 119,115,138 & 134 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,revising Tech Specs Re Auxiliary Electrical Sys
ML20105A7361992-09-11011 September 1992
Amends 118 & 114 to Licenses DPR-19 & DPR-25,respectively, Adding Two New Sections Under Administrative Controls Sections 6.11 & 6.12
ML20113H6351992-07-24024 July 1992
Amend 117 to License DPR-19,clarifying Reporting Requirements of Section 2.G of FOL
ML20114A5631992-07-24024 July 1992
Amends 113,116,131 & 135 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,changing Types of Procedures Requiring Review by Onsite Review & Investigative Function
ML20101L1571992-06-29029 June 1992
Amends 115 & 112 to Licenses DPR-19 & DPR-25,respectively, Revising TS to Reflect Mod to Fast Acting Solenoid Valves Which Initiate Rapid Closure of TCV
ML20096F1091992-04-24024 April 1992
Application for Amend to License DPR-19,changing Reporting Requirements of OL Section 2.G Re Notification of NRC of Violations
ML20079Q1201991-10-24024 October 1991
Corrected Pages B 3/4.6-26a to Amends 114 & 111 to Licenses DPR-19 & DPR-25,respectively
ML20082R1771991-09-0505 September 1991
Amends 114 & 111 to Licenses DPR-19 & DPR-25,respectively, Revising Pressure/Temp Limits for RCS
ML20066K7701991-02-20020 February 1991
License DPR-19 to Operate Facility at steady-state Reactor Core Power Levels Not in Excess of 2527 Mwt
ML20059M8441990-10-0202 October 1990
Amends 113 & 109 to Licenses DPR-19 & DPR-25,respectively, Incorporating ATWS Requirements Into Tech Specs
ML20058L9351990-07-31031 July 1990
Suppl to 891101 Proposed Amend to License DPR-2,reflecting Nonoperating Status of Facility & Clarifying Section 3.10.F
ML20055H8251990-07-25025 July 1990
Amends 111 & 107 to Licenses DPR-19 & DPR-25 Respectively, Revising Surveillance Interval Requirement for Functional Testing of Reactor Protection Sys Electrical Protection Assemblies
ML20011F5181990-02-0808 February 1990
Amends 110 & 105 to Licenses DPR-19 & DPR-25,respectively, Revising Tech Specs,Per Generic Ltr 88-16,by Replacing cycle-specific Operating Limits W/Refs to Core Operating Limits Rept
ML20245H6521989-08-0909 August 1989
Corrected Amends 106 & 101 to Licenses DPR-19 & DPR-25, Respectively,Consisting of Index Pages to Original Amends
ML20246C8491989-06-30030 June 1989
Amends 106 & 101 to Licenses DPR-19 & DPR-25,respectively, Replacing Existing License Conditions on Fire Protection W/Std Condition Noted in Generic Ltr 86-10
ML20247M4371989-05-16016 May 1989
Application for Amend to License DPR-2,extending Expiration Date of License to 290410
ML20246G9941989-04-26026 April 1989
Amends 117,113,105 & 100 to Licenses DPR-29,DPR-30,DPR-19 & DPR-25,respectively,deleting Organization Charts from Tech Specs
ML20205L1941988-10-26026 October 1988
Amends 101 & 97 to Licenses DPR-19 & DPR-25,respectively, Revising Tech Specs Requirements of Section 3.5.F to Include More Prescriptive Requirements for ECCS Operability During Cold Shutdown & Refueling Operational Modes
1999-02-16
[Table view] |
Text
.
p *S*co p
'4 UNITED STATES s
j NUCf. EAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30e06-0001
\\...../
COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 f.pf1ESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 165 License No. DPR 19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
Thw application for amendment by the Commonwealth Edison Company (the licensee) osted November 7,1997, complies witn the standards and requirements of the Atomic F.nergy Act of 1954, as amended (ths Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment 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 ragulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; :.nd E.
The issumce of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment sod paragraph 2.C.(2) of Facility Operating License No. DF'R 19 is hereby amended to read as follows:
i 9803050t15 900225 PDR ADOCK 05000237 P
PDR
2-(2)
Technical Specifications The Technical Specifications cantained in Appendix A, as revised through Amer:dment No. 165, are hemby incorporated in the licenst The licensee shall operate the facility in accordance with the Technical Specificat ens.
3.
Tbk eense amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION W}O
- d. y J in F. Stang, Senior Project Manager Project Directorate ill-2 Division of Reactor Proju,in - til/IV office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 25, 1998 l
p uro, i
5 UNITED STATES y
}
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, n.C. SeteH001 Ts...../
COMMONWEAL.TH EDISON COMDAtf(
POCKET NO. 50-249 j.
DRESDff[ NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
l Amendment No.160 l
License No. DPR 25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated November 7,1997, complies with the standards and requirements of to Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the 4
Act and the rules and regulations of the Commission; J
C.
There is reasonable assurance (i) that the activities authorized by this amendment 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;
+
D The issuance of this amendment will not be inim: cal to the common defsnse and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications, ss indicated in the attachment to this license amendment und paragraph 3.B. of Facility Operating Licenn No. DPR-25 is hereby amended to read as follows:
i
+-
y.
.*~..-g.
e.
i 2
B.
Tecnnical Specifications The Technical Specifications contained in Appendix A, as revised through Amoredmont No. 160, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the data of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION b
Mk hn F. Stang, S or Project Manager Project Directorate 1112 Division of Reactor Projects. lil/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: February 25, 1998 4
4
ATTACHMENT TO LICENSE AMENDMENT NOS.165 AND 160 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR 25 DOCKET NOS. 50-237 AND 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages The revised pages are identified by the captioned amendment number and contain marginallines indicating the aretdf change.
REMOVE INSERT 3/4.9-12 3/4.9-12 3/4.9-16 3/4.9 16 3/4.9 18 3/4.9-18 I
2/4.9-20 3/4.9-20 J
ELECTRICAL POWER SYSTEMS D.C. Sources - Oporating 3/4.9.C 3.9 LIMITING CONDITIONS FOR OPERATION 4.9 SURVEILLANCE REQUIREMENTS C.
D.C. Sources - Operating C.
D.C. Sources Operating As a minimum, the following D.C. electrical Each of the required 125 volt and 250 volt l
power sources shall be OPERABLE with the batteries and chargers shall be identified parameters within the limits demonstrated OPERABLE":
specified in Table 4.9.C 'i:
1.
At least once per 7 days by verifying 1.
Two station 250 volt batteries, that:
each with a full capacity charger, a.
The parameters in Table 4.9.C-1 2.
Two station 125 volt batteries, meet Category A limits, and each with a full capacity charger.
b.
There is correct breaker alignment l
to the battery chargers and total battery terminal voltage is 2125.9 or h260.4 volts, as l
APPLICABILITY:
applicable, on float charge.
OPERATIONAL MODE (s) 1,2, and 3.
2.
At least once per 92 days and within 7 days after a battery discharge with a battery terminal voltage below 105 or l
_ ACTION:
210 volts, as applicable, or battery overcharge with battery terminal l
1.
With one of the above required 250 voltage above 150,r 300 volts, as l
volt station batteries and/or chargers applicable, by verifying that:
inoperable, restore the inoperable equipment to OPERABLE status within a.
The parameters in Table 4.9.C-1 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />".
meet the Category B limits, b.
There is no visible corrosion et either terminals or connectors, or the connection resistance of those items is $150 x10s ohms or s20% above baseline connection resistance, whichever is higher, and a
An aitemate 125 volt battery shall adhere to these same Surveillance Requirements to be considered OPERABLE.
except the Unit 2 total battery terminal voltage on float charge shall be verified weekly as 2130.2 volts, b
Each 250 voit battery may be inoperable for a maximum of seven days por operating cycle for rnaintenance or testing, if it is determined that a 250 voit battery need bo replaced as a result of maintenance 1 testing, a specific battery may be inoperable for an additional seven days per operating cycle.
DRESDEN - UNITS 2 & 3 3/4.9-12 Amendment Nos.165,160
I ELECTRICAL POWER SYSTEMS D.C. Sourca Shutdown 3/4.9.D 3.9 LIMITING CONDITIONS FOR OPERATION 4.9 - SURVEILLANCE REQUIREMENTS D.
D.C. Sources - Shutdown D.
D.C. Sources Shutdown As a minimum, the following D.C. electrical The required batteiles and chargers shall be power sources shall be OPERABLE:
demonstrated OPERABLE
surveillance requirements in Specification 1.
One station 250 volt battery with a 4.9.C.
full capacity charger.
2.
One station 125 volt battery with a full capacity charger.
l' APPLICABILITY:
OPERATIONAL MODE (s) 4 and 5, and when handling irradiated fuelin the secondary containment.
ACTION:
With any of the above required station batteries and/or associated charger (s) inoperable, suspend CORE ALTERATIONS, suspend handling of irradiated fuel in the secondary containment, and suspend operations with a potential for draining the reactor vessel.
i An alternate 125 volt battery shall adhere to these same Surveilla. ce Requirements to be considered OPERABLE. !
a except the Unit 2 total battery termir el voltage on float charge shall be verified weekly as h130.2 volts.
DRESDEN - UNITS 2 & 3 3/4.9-16 Amendment Nos.165,160 t
ELECTRICAL POWER SYSTEMS Distributi:n - Operating 3/4.9.E 3.9 LIMiilNG CONDITIONS FOR OPERATION 4.9 - SURVElLLANCE REQUIREMENTS 4.
For Unit 3,125 volt D.C. power distribution, consisting of:
a.
TB Main Bus Nos. 2A 1,3A and 3A 1, b.
TB Res. Bus Nos. 38 and 3B 1, and c.
RB Distribution Panel No. 5.
l APPLICABlyIYi OPERATIONAL. MODE (s) 1, 2, and 3.
ACTIONS:
1.
With one of the above required A.C.
distribution systems not energized, re-energize the system within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 I,ours.
2, With ore of the above required D.C.
distribution systems not energized, re-energize the system within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I DRESDEN - UNITS 2 & 3 3/4.9-18 Amendment Nos.165,160
. - ~....
ELECTR;0AL POWER SYSTEMS Distributi:n Shutdswn 3/4.9.F 3.9 LIMITING CONDITIONS FOR OPERATION 4.9 SURVEILLANCE REQUIREMENTS -
l APPLICABILITY:
OPERATIONAL MODE (s) 4,5, and when -
handling irradiated fuel in the secondary _-
containment.
ACTIONS:-
.With less than the above required A.C. or D.C. distribution systems energized, suspend CORE ALTERATIONS, suspend handling of irradiated fuel in the secondary containment, and suspend operations with a potential for_ draining the reactor vessel.
I t-I:
DRESDEN - UNITS 2 & 3.
--3/4.9 20 Amendment Nos. 160, 160-
,.. -
