Similar Documents at Zion |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20205Q8741999-04-13013 April 1999 Revised Application for Amends to Licenses DPR-39 & DPR-48, Replacing Operational TS with Permanently Defueled TS A98020, Application for Amends to Licenses DPR-39 & DPR-48,to Eliminate License Conditions No Longer Applicable & Replace Existing Operational Custom TS with Permanently Defueled TS1998-10-0202 October 1998 Application for Amends to Licenses DPR-39 & DPR-48,to Eliminate License Conditions No Longer Applicable & Replace Existing Operational Custom TS with Permanently Defueled TS A98016, Application for Amends to Licenses DPR-39 & DPR-40,restoring Plant Custom TS Replaced by Improved TS by Previous Amend & Reinstating License Conditions Deleted by That Previous Amend1998-03-30030 March 1998 Application for Amends to Licenses DPR-39 & DPR-40,restoring Plant Custom TS Replaced by Improved TS by Previous Amend & Reinstating License Conditions Deleted by That Previous Amend A97074, Application for Amends to Licenses DPR-39 & DPR-48,revising TSs Using Guidance Provided in NUREG-1431 to Produce Set of Improved TSs for Zion Station1997-11-28028 November 1997 Application for Amends to Licenses DPR-39 & DPR-48,revising TSs Using Guidance Provided in NUREG-1431 to Produce Set of Improved TSs for Zion Station ML20211A9121997-09-19019 September 1997 Application for Amends to Licenses DPR-39 & DPR-48,coverting Proposed Improved Ts,Per NUREG-1431 ML20148B7251997-05-0808 May 1997 Supplemental Application for Amends to Licenses DPR-39 & DPR-48,revising TS to Add Discussion of Position & Duties of Licensed Operators & Senior Licensed Operators to Section 5.3, Qualification ML20134J2461997-02-0303 February 1997 Application for Amends to Licenses DPR-39 & DPR-48,adding Note to Current TS Governing C-E Process for Sleeving SG Tubes ML20134G0651997-01-27027 January 1997 Application for Amends to Licenses DPR-39 & DPR-48,revising TS Such That Use of Entire Abb/Ce TR,CEN-629-P,would Be Authorized as Governing Document for Installing CE Sleeves in SG tubes.Non-proprietary & Proprietary Repts,Encl ML20133D0821997-01-0202 January 1997 Application for Amends to Licenses DPR-39 & DPR-48,revising TSs Using Guidance in NUREG-1431 to Produce Improved TSs ML20134J3581996-11-0808 November 1996 Application for Amends to Licenses DPR-39 & DPR-48,removing Requirements Governing RCS Pressure & Temp Limits & Relocate Requirements to Util Controlled Pressure/Temp Limits Rept ML20134G5821996-11-0707 November 1996 Application for Amends to Licenses DPR-39 & DPR-48, Requesting Clarification Operability Requirements for RHR Loops During Core Alteration Operations ML20134G4001996-11-0707 November 1996 Application for Amends to Licenses DPR-39 & DPR-48, Requesting Rev to Table 3.7-1 Re Values for Reduced Power Range Neutron Flux High Setpoint Trip ML20134G3201996-11-0707 November 1996 Application for Amends to Licenses DPR-39 & DPR-48, Requesting Rev to Mode 4 TS Surveillance Requirement 4.3.1.A.4.b ML20128H2781996-10-0404 October 1996 Application for Amends to Licenses DPR-39 & DPR-48, Clarifying & Adding Mode of Applicability for Rod Position Indicator Channels ML20128L8231996-10-0404 October 1996 Revised Application for Amends to Licenses DPR-39 & DPR-48, Revising TSs Needed to Implement Option B to 10CFR50,App J ML20059H5761994-01-19019 January 1994 Application for Amends to Licenses DPR-39 & DPR-48,proposing Changes to Ts,Revising Minimun RCS Temperature Required Criticality,In Addition to Editorial Changes in Affected Specifications ML20058C2951993-11-19019 November 1993 Application for Amends to Licenses DPR-39 & DPR-48,revising TS 3.3.2.G & Asociated Bases,Addresses LTOP of Reactor Vessel ML20058A2591993-11-10010 November 1993 Application for Amends to Licenses NPF-37,NPF-66,NPF-72, NPF-77,DPR-39,DPR-48,NPF-11 & NPF-18 Re Limitations on Radioactive Matl Released in Liquid Effluents,New 10CFR21 & Radioactive Matl Released in Gaseous Effluents ML20059H9451993-11-0404 November 1993 Application for Amends to Licenses DPR-39 & DPR-48,proposing Changes to TS 4.7.1.A,SG Safety Valves by Revising Surveillance Frequency & Acceptance Criteria ML20056F7251993-08-23023 August 1993 LAR 93-08 to Licenses DPR-39 & DPR-48,revising TS Sections 1,6 & Bases for Section 3/4.11 & 3/4.12 for Implementation of Latest Rev to 10CFR20 ML20127N0051992-12-22022 December 1992 Application for Amends to Licenses DPR-39 & DPR-48, Respectively,To Relocate Fire Protection TSs to an owner-controlled Document Consistent W/Guidance Provided in Generic Ltrs 86-10 & 88-12 ML20127C6451992-09-0101 September 1992 License Amend Request 92-03 to Licenses DPR-39 & DPR-48, Changing TS to Achieve Consistency W/Recently Compiled Data Re Reactor Vessel Integrity issues.WCAP-13406,Rev 2 to WCAP-10962 & Rept, Methodology for Calculating... Encl ML20248B3901989-09-25025 September 1989 Application for Amends to Licenses DPR-39 & DPR-48,adding Requirement to Address Containment Purge & Vent Operations While Above Cold Shutdown (Mode 5) ML20247D0791989-07-18018 July 1989 Application for Amends to Licenses DPR-39 & DPR-48,removing Section 3/4.17.2, Aircraft Fire Detection Sys, from Tech Specs Due to Low Probability of Aircraft Crash ML20246D4011989-07-0606 July 1989 Application for Amends to Licenses DPR-39 & DPR-48,modifying Tech Spec Section 3.15, Auxiliary Electric Power Sys to Permit Allowable Out of Svc Period for Diesel Generator to Be Extended to 45 Days for one-time Maint Overhaul ML20245C6111989-06-13013 June 1989 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Specs Sections 3.0 & 4.0 Re Applicability of Limiting Conditions for Operations & Surveillance Requirements ML20247M9641989-06-0202 June 1989 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Spec Section 4.3, RCS, to Allow Plant Steam Generator Tubes to Be Repaired.Proprietary Rev 1 to BKAT-01-P, ... Repair of Defective Steam Generator Tubes..., Withheld ML20246N2991989-05-11011 May 1989 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Spec Section 3.15, Auxiliary Electric Power Sys to Extend Allowable out-of-svc Period for Diesel Generator O from 7 to 45 Days for one-time Maint Overhaul ML20245D5921989-04-17017 April 1989 Application for Amend to Licenses DPR-39 & DPR-48,revising Tech Spec by Adding & Clarifying Tables 3.1-1 & 4.1-1 to Address Operability & Surveillance Requirements for Reactor Protection Channels ML20248E3691989-03-22022 March 1989 Application for Amends to Licenses DPR-39 & DPR-48,changing Administration Control Section 6.0,per Generic Ltr 88-06 ML20235M0191989-02-22022 February 1989 Application for Amends to Licenses DPR-39 & DPR-48,changing Tech Spec 6.1 Re Administrative Controls,Per Generic Ltr 88-06 ML20155D1321988-09-28028 September 1988 Application for Amends to Licenses DPR-39 & DPR-48,modifying Tech Spec Section 4.2.1.F.1, Boric Acid Sys to Clarify Testing Requirements for Heat Trace Which Protects Piping from Boric Acid Tank to Charging Pump Suction Line.Fee Paid ML20195J1371988-06-0909 June 1988 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Specs Sections 3.2,3.4,3.8 & 3.9 to Remove Boron Injection Tank (Bit) & Associated Piping,Valves & Heat Trace for Recirculation Between Bit & Boric Acid Tanks.Fee Paid ML20149F1381987-12-24024 December 1987 Application for Amends to Licenses DPR-39 & DPR-48,allowing Steam Generator Tube Repair Utilizing Westinghouse or C-E Mechanical Sleeving Methodology.Proprietary WCAP-11669 & Nonproprietary WCAP-11670 Encl.Fee Paid ML20237B5231987-12-0909 December 1987 Application for Amends to Licenses DPR-39 & DPR-48,modifying Tech Spec Section 4.15.1.E Re 125-Volt Batteries to Upgrade Plant Program for Verifying Existence of Adequate Battery Capacity.Fee Paid ML20236G0421987-10-27027 October 1987 Supplemental Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Specs to Extend Snubber Insp Period ML20236C0101987-10-22022 October 1987 Application for Amends to Licenses DPR-39 & DPR-48,modifying Tech Specs to Remove Refs to Initial Base Line Inservice Insp & to Specific Version of ASME Section XI Code ML20235E2001987-09-22022 September 1987 Application for Amends to Licenses DPR-39 & DPR-48,for one- Time Visual Insp of Snubbers to Be Performed During Planned Refueling Outages.Fee Paid ML20214T4101987-05-29029 May 1987 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Specs to Allow Simultaneous Charging Pump Operation During Pump Realignment & to Reduce Allowable Time Period for Depressurization Following Failure of Porv.Fee Paid ML20206F0151987-04-0909 April 1987 Application for Amends to Licenses DPR-39 & DPR-48,expanding Containment Isolation Valve Listing,Removing Guidance Involving three-loop Operation & Incorporating Guidance Contained in Rev 4 to NUREG-0452.Fee Paid ML20206E6601987-04-0808 April 1987 Application for Proposed Amend to Licenses DPR-39 & DPR-48, Revising Tech Specs Re Matls Irradation Surveillance Specimen Insp Re Specimen Withdrawal Schedule Which Incorporates Removal of Two Addl Capsules.Fee Paid ML20211C0181987-02-10010 February 1987 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Specs to Allow one-time Change & Extend Allowable Outage Time on Diesel Generator O from 7 to 21 Days.Fee Paid ML20207H9511986-12-16016 December 1986 Application for Amend to Licenses DPR-39 & DPR-48,correcting Minor Errors,Consisting of Clarifications & Typos,In Recently Approved Radiological Effluent Tech Specs.Fee Paid ML20211N9431986-12-0505 December 1986 Application for Amends to Licenses DPR-39 & DPR-48,providing Revised Set of Heatup & Cooldown Limitation Curves & Extending Current Limitations from Expiration Exposure of 8 EFPY to 15 EFPY.WCAP-11247 Encl ML20211P4791986-12-0404 December 1986 Application for Amends to Licenses DPR-39 & DPR-48.Amends Clarify Tech Spec Sections 3.5 & 4.5 Following Recent Mod to Reactor Containment Fan Coolers & Convert Entire Section Into STS Format.Fee Paid ML20197B0421986-10-17017 October 1986 Application for Amends to Licenses DPR-39 & DPR-48,modifying Tech Specs to Remove Refs to Initial Base Line Inservice Insp & Specific Version of ASME Section XI Code.Fee Paid ML20197B1131986-10-16016 October 1986 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Specs to Disable Rod Control Sys During Time Periods When Reactor in Mode 3 W/Less than Four Reactor Coolant Pumps Operating.Fee Paid ML20215M1901986-10-15015 October 1986 Application for Amends to Licenses DPR-39 & DPR-48,changing Tech Spec Sections 3.3.6 & 6 Re Specific Activity & Administrative Controls,Respectively.Fee Paid ML20215L9131986-10-10010 October 1986 Application for Amend to Licenses DPR-39 & DPR-48,correcting Error in Existing Tech Spec for Figure 3.2-9, Hot Channel Factor Normalized Operating Envelope. Fee Paid ML20215B3441986-09-23023 September 1986 Application for Amends to Licenses DPR-39 & DPR-48,extending Duration of OL for 40 Yrs.Fee Paid 1999-04-13
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20205Q8741999-04-13013 April 1999 Revised Application for Amends to Licenses DPR-39 & DPR-48, Replacing Operational TS with Permanently Defueled TS A98020, Application for Amends to Licenses DPR-39 & DPR-48,to Eliminate License Conditions No Longer Applicable & Replace Existing Operational Custom TS with Permanently Defueled TS1998-10-0202 October 1998 Application for Amends to Licenses DPR-39 & DPR-48,to Eliminate License Conditions No Longer Applicable & Replace Existing Operational Custom TS with Permanently Defueled TS ML20236U6251998-07-24024 July 1998 Amends 179 & 166 to Licenses DPR-39 & DPR-48,respectively, Restoring Custom TS & Associated License Conditions Replaced by Improved TS & Changing Mgt Titles & Responsibilities to Reflect Shut Down Condition of Plant A98016, Application for Amends to Licenses DPR-39 & DPR-40,restoring Plant Custom TS Replaced by Improved TS by Previous Amend & Reinstating License Conditions Deleted by That Previous Amend1998-03-30030 March 1998 Application for Amends to Licenses DPR-39 & DPR-40,restoring Plant Custom TS Replaced by Improved TS by Previous Amend & Reinstating License Conditions Deleted by That Previous Amend A97074, Application for Amends to Licenses DPR-39 & DPR-48,revising TSs Using Guidance Provided in NUREG-1431 to Produce Set of Improved TSs for Zion Station1997-11-28028 November 1997 Application for Amends to Licenses DPR-39 & DPR-48,revising TSs Using Guidance Provided in NUREG-1431 to Produce Set of Improved TSs for Zion Station ML20211A9121997-09-19019 September 1997 Application for Amends to Licenses DPR-39 & DPR-48,coverting Proposed Improved Ts,Per NUREG-1431 ML20148B7251997-05-0808 May 1997 Supplemental Application for Amends to Licenses DPR-39 & DPR-48,revising TS to Add Discussion of Position & Duties of Licensed Operators & Senior Licensed Operators to Section 5.3, Qualification ML20134J2461997-02-0303 February 1997 Application for Amends to Licenses DPR-39 & DPR-48,adding Note to Current TS Governing C-E Process for Sleeving SG Tubes ML20134G0651997-01-27027 January 1997 Application for Amends to Licenses DPR-39 & DPR-48,revising TS Such That Use of Entire Abb/Ce TR,CEN-629-P,would Be Authorized as Governing Document for Installing CE Sleeves in SG tubes.Non-proprietary & Proprietary Repts,Encl ML20133D0821997-01-0202 January 1997 Application for Amends to Licenses DPR-39 & DPR-48,revising TSs Using Guidance in NUREG-1431 to Produce Improved TSs ML20132F5061996-12-20020 December 1996 Amends 177 & 164 to Licenses DPR-39 & DPR-48,respectively, Allowing Comed to Control Reactor Coolant Sys Pressure & Temp Limits for Heatup,Cooldown,Low Temp Operation & Hydrostatic Testing ML20134P7831996-11-25025 November 1996 Amends 176 & 163 to Licenses DPR-39 & DPR-48,respectively, Adding Mode of Applicability to TS 3.2.3.D ML20134H6691996-11-12012 November 1996 Amends 295 & 162 to Licenses DPR-39 & DPR-48,respectively, Amends Change TS to Implement 10CFR50,App J,Option B,By Referring to Reg Guide 1.163 W/Exception as Detailed in Licensee Application ML20134J3581996-11-0808 November 1996 Application for Amends to Licenses DPR-39 & DPR-48,removing Requirements Governing RCS Pressure & Temp Limits & Relocate Requirements to Util Controlled Pressure/Temp Limits Rept ML20134G3201996-11-0707 November 1996 Application for Amends to Licenses DPR-39 & DPR-48, Requesting Rev to Mode 4 TS Surveillance Requirement 4.3.1.A.4.b ML20134G4001996-11-0707 November 1996 Application for Amends to Licenses DPR-39 & DPR-48, Requesting Rev to Table 3.7-1 Re Values for Reduced Power Range Neutron Flux High Setpoint Trip ML20134G5821996-11-0707 November 1996 Application for Amends to Licenses DPR-39 & DPR-48, Requesting Clarification Operability Requirements for RHR Loops During Core Alteration Operations ML20134F9771996-11-0606 November 1996 Amends 174 & 161 to Licenses DPR-39 & DPR-48,respectively, Revising Definition of F* Distance by Removing Uncertainty Term from Specified Distance & Removing Footnote Which Specifies Time Frame Applicable ML20129H2761996-10-29029 October 1996 Amends 173 & 160 to Licenses DPR-39 & DPR-48,respectively, Incorporating Revised Installation Procedures for SG Tube Sleeves Designed by Abb/Ce ML20128L8231996-10-0404 October 1996 Revised Application for Amends to Licenses DPR-39 & DPR-48, Revising TSs Needed to Implement Option B to 10CFR50,App J ML20128H2781996-10-0404 October 1996 Application for Amends to Licenses DPR-39 & DPR-48, Clarifying & Adding Mode of Applicability for Rod Position Indicator Channels ML20059H5761994-01-19019 January 1994 Application for Amends to Licenses DPR-39 & DPR-48,proposing Changes to Ts,Revising Minimun RCS Temperature Required Criticality,In Addition to Editorial Changes in Affected Specifications ML20059E2681993-12-30030 December 1993 Amends 57,57,45,45,93,77,152 & 140 to Licenses NPF-37, NPF-66,NPF-72,NPF-77,NPF-11,NPF-18,DPR-39 & DPR-48, Respectively.Amends Change Instantaneous Limits for Radioactive Liquid & Gaseous Effluent Release Rates ML20058K2791993-12-0303 December 1993 Corrected Tech Spec Pages to Amend 150 to License DPR-39 & Amend 138 to License DPR-48 ML20058G2661993-11-29029 November 1993 Amends 139 & 151 to Licenses DPR-48 & DPR-39,respectively, Revising TS to Address Concerns of GL 90-06 Re PORV & Ltop. Operated Relief Valves & Low Temp Overpressure Protection ML20058C2951993-11-19019 November 1993 Application for Amends to Licenses DPR-39 & DPR-48,revising TS 3.3.2.G & Asociated Bases,Addresses LTOP of Reactor Vessel ML20059M7801993-11-15015 November 1993 Amends 150 & 138 to Licenses DPR-39 & DPR-48,respectively, Revising Reactor Protection & Engineered Safeguards TSs & Limiting Safety Sys Setting ML20058A2591993-11-10010 November 1993 Application for Amends to Licenses NPF-37,NPF-66,NPF-72, NPF-77,DPR-39,DPR-48,NPF-11 & NPF-18 Re Limitations on Radioactive Matl Released in Liquid Effluents,New 10CFR21 & Radioactive Matl Released in Gaseous Effluents ML20059H9451993-11-0404 November 1993 Application for Amends to Licenses DPR-39 & DPR-48,proposing Changes to TS 4.7.1.A,SG Safety Valves by Revising Surveillance Frequency & Acceptance Criteria ML20059C5401993-10-21021 October 1993 Corrected Amends 148 & 136 to Licenses DPR-39 & DPR-48, Respectively,Correcting License Page 6 to Add SER Date of 930831 Under License Condition 5 Re Fire Protection Program ML20059A7131993-10-14014 October 1993 Amends 149 & 137 to Licenses DPR-39 & DPR-48,respectively, Revising TS to Account for Completion of Eagle 21 Process Protection Sys Upgrade ML20057F8331993-10-13013 October 1993 Amends 148 & 136 to Licenses DPR-39 & DPR-48,respectively, Relocating Fire Protection TS to Fire Protection Program, Per GLs 86-10 & 88-12 ML20056F7251993-08-23023 August 1993 LAR 93-08 to Licenses DPR-39 & DPR-48,revising TS Sections 1,6 & Bases for Section 3/4.11 & 3/4.12 for Implementation of Latest Rev to 10CFR20 ML20127N0051992-12-22022 December 1992 Application for Amends to Licenses DPR-39 & DPR-48, Respectively,To Relocate Fire Protection TSs to an owner-controlled Document Consistent W/Guidance Provided in Generic Ltrs 86-10 & 88-12 ML20127C6451992-09-0101 September 1992 License Amend Request 92-03 to Licenses DPR-39 & DPR-48, Changing TS to Achieve Consistency W/Recently Compiled Data Re Reactor Vessel Integrity issues.WCAP-13406,Rev 2 to WCAP-10962 & Rept, Methodology for Calculating... Encl ML20056C0491992-06-0909 June 1992 Amends 138 & 127 to Licenses DPR-39 & DPR-48,respectively, Revising TS Definitions Section ML20058D8031990-10-31031 October 1990 Amends 120 & 109 to Licenses DPR-39 & DPR-48,respectively, Revising Tech Specs to Remove Ref to Initial Baseline Inservice Insp to Specific Version of ASME Section XI Code ML20248B3901989-09-25025 September 1989 Application for Amends to Licenses DPR-39 & DPR-48,adding Requirement to Address Containment Purge & Vent Operations While Above Cold Shutdown (Mode 5) ML20247E7271989-09-0808 September 1989 Amends 118 & 107 to Licenses DPR-39 & DPR-48,respectively, Authorizing one-time Change to Tech Specs to Allow Performance of Extensive Preventive Maint ML20245F1601989-08-0101 August 1989 Amends 117 & 106 to Licenses DPR-39 & DPR-48,respectively, Modifying Tech Spec Sections 4.0.3 & 4.0.4, General Surveillance Requirements & Section 3.3.1.F, Relief Valves to Include Exception to Limiting Condition 3.0.4 ML20247D0791989-07-18018 July 1989 Application for Amends to Licenses DPR-39 & DPR-48,removing Section 3/4.17.2, Aircraft Fire Detection Sys, from Tech Specs Due to Low Probability of Aircraft Crash ML20246D4011989-07-0606 July 1989 Application for Amends to Licenses DPR-39 & DPR-48,modifying Tech Spec Section 3.15, Auxiliary Electric Power Sys to Permit Allowable Out of Svc Period for Diesel Generator to Be Extended to 45 Days for one-time Maint Overhaul ML20245C6111989-06-13013 June 1989 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Specs Sections 3.0 & 4.0 Re Applicability of Limiting Conditions for Operations & Surveillance Requirements ML20247M9641989-06-0202 June 1989 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Spec Section 4.3, RCS, to Allow Plant Steam Generator Tubes to Be Repaired.Proprietary Rev 1 to BKAT-01-P, ... Repair of Defective Steam Generator Tubes..., Withheld ML20246N2991989-05-11011 May 1989 Application for Amends to Licenses DPR-39 & DPR-48,revising Tech Spec Section 3.15, Auxiliary Electric Power Sys to Extend Allowable out-of-svc Period for Diesel Generator O from 7 to 45 Days for one-time Maint Overhaul ML20245H7991989-04-27027 April 1989 Amends 115 & 104 to Licenses DPR-39 & DPR-48,respectively. Amend Revises Administrative Controls Section of Tech Specs to Reflect Guidance Provided by Generic Ltr 88-06 & Recent Corporate & Station Reorganizations ML20245D5921989-04-17017 April 1989 Application for Amend to Licenses DPR-39 & DPR-48,revising Tech Spec by Adding & Clarifying Tables 3.1-1 & 4.1-1 to Address Operability & Surveillance Requirements for Reactor Protection Channels ML20248E3691989-03-22022 March 1989 Application for Amends to Licenses DPR-39 & DPR-48,changing Administration Control Section 6.0,per Generic Ltr 88-06 ML20235M0191989-02-22022 February 1989 Application for Amends to Licenses DPR-39 & DPR-48,changing Tech Spec 6.1 Re Administrative Controls,Per Generic Ltr 88-06 ML20207K9951988-10-11011 October 1988 Amends 113 & 102 to Licenses DPR-39 & DPR-48,respectively, Modifying Paragraph 2.C(6) of License to Require Compliance W/Amended Physical Security Plan 1999-04-13
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- ' Y Commonwo-Ith Edison O ) One First National Plaza. Chicago. litenois C '/ Address Reply to: Post Othee Box 767
.q Chicago, I!!inois 60690 November 18, 1985 Mr. Harold-R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Zion Nuclear Power Station Units 1 and 2 Proposed Amendment to Facility Operating License Nos. DPR-39 and DPR 2/29/80 Confirmatory Order NRC-Docket Nos.-50-295 and 50-304 l References (a): . February 29, 1980 letter from H. R.
Denton to D. L. Peoples.
(b): September 8, 1981 letter from L. O.
DelGeorge to H. R. Denton.
(c): December 15, 1982 letter from F. G.
Lentine to H. R. Denton.
(d): August 17, 1983 letter from F. G.
Lentine to H. R. Denton.
(e): January 27, 1984 letter from Cordell Reed to H. R. Denton.
(f): January 30, 1984 letter from F. G.
Lentine to H. R. Denton.
(g): October 19, 1984 letter from R. N.
Cascarano to H. R. Denton.
(h): February 28, 1985' letter from R. N.
Cascarano to H. R. Denton.
(1): June 25, 1985 letter from P. C. LeBlond to.H. R. Denton.
(j): August 26, 1985 letter from S. A. Varga to D. L. Farrar.
Dear Mr. Denton:
The purpose of this'l'etter is to transmit a proposed license amendment to delete the Zion Confirmatory Order, dated February 29, 1980.
Reference (a) imposed the Zion Confirmatory Order in response to the perception that Zion Station represented a disproportionate share of the total societal risk. Commonwealth. Edison Company has never shared this view.
Thus, this issue has been the subject of much correspondence. References (b) through (i) all represent requests to modify segments or rescind all of the Confirmatory Order. Attachment 1 provides a brief ription of this correspondence. g 0g )
00g B511220288 851118 0 PDR ADOCK 05000295
__--__2______ . _ -__ kn .. % 4
i
.H. R. Denton November 18, 1985 Attachment 2 contains a description of a proposed amendment to Facility Operating License Nos. DPR-39 and DPR-48. This amendment request involves the deletion of the Zion Confirmatory Order, dated February 29, 1980.
- Attachment 3 provides Commonwealth Edison Company's analysis of the issue of no significant hazards consideration as required by 10 CFR 50.91.
This amendment request has received on-site and off-site review and approval.
This amendment request supercedes the requests contained in References (b) through (h). These submittals can be considered closed.
Reference (1) contains a request to delete Items A.1 and A.2. It is anticipated that this request will be approved shortly. Thus, reference (1)
-should remain open until NRC approval has been issued.
.A $150.00 fee remittance is enclosed in accordance with 10 CFR 170. As provided by 10 CFR 50.91, the State of Illinois is being notified of this amendment request by transmittal of a copy of this letter and the attachments.
. If there are any further questions regarding this matter, please
-contact Comonwealth Edison's Nuclear Licensing Department.
Three signed originals and thirty-seven (37) copies of this letter
-and its attachments are hereby provided for your review.
Very truly yours, Cordell Reed Vice-President 1m Attachments
- cc
- NRC Resident Inspector - Zion l J. A. Norris - NRC l M. C. Parker - State of Ill.
I SUBSCRIGED AND*S to beforp me_th}s day of .4/gbit/u4 , 985 i i ? Odh Notary,Publ'ic g 0838K
V ATTACHE NT 1 DESCRIPTION OF ZION CONFIRMATORY ORDER CORRESPONDENCE The Zion Confirmatory Order was transmitted to Commonwealth Edison by Reference (a). This order was prompted by the perception that the Zion Site represented a disproportionately high contribution to the total societal risk from reactor accidents. This belief stemmed from the fact that the population density surrounding the Zion Site is relatively high as compared to other nuclear power plant sites. The Order was comprised of a number of extraordinary interim measures that were intended to significantly increase the level of safety at Zion Station.
Commonwealth Edison Company subsequently performed the Zion Probabilistic Safety Study (ZPSS) which demonstrated that the risk associated with Zion was less than either previous NRC Staff estimates or the estimate for the WASH-1400 PWR, The ZPPS was completed in August,1981 and was transmitted to the NRC by reference (b).
Reference (b) also contained a request to rescind the Order, while agreeing to continue the testing of the residual heat removal system check valves. This requirement was orginally contained in Item A.5 of reference (a).
References (c) and (d) transmitted proposed changes to the Technical Specifications regarding the Auxiliary Feedwater System and the Emergency Diesel Generators, respectively. Since these issues were also discussed in reference (a), references (c) and (d) also contained requests to rescind Items E.1.C and B.6 to preclude any conflict between the Order and the Technical Specifications. The proposed Technical Specification changes concerning the Auxiliary Feedwater System contained in reference (c) have been approved.
Reference (e) provided the status of each order item and reiterated the original request of reference (b) to rescind the entire order. Reference (f) discussed the detrimental effects of the diesel generator testing program imposed by Item B.6 and requested the deletion of the restrictions on allowable outage time.
Reference (g) requested the renoval of Items A.1 and A.2 in conjunc-tion with the approval of a recently submitted LOCA reanalysis. Items A.1 and A.2 imposed restrictions on the calculated peak clad temperature during a LOCA and on the performance of load follow manuevers.
Reference (h) discussed the conflict between Zion's efforts to improve diesel generator reliability and the continued enforcement of Item B.6. A proposed modification to Item B.6 was also transmitted.
. ~.. . . . . .-. -- . __ - - - . .
Reference (i) transmitted a request for a license amendment to delete Items _A.1 and A.2. This request has been public noticed on September 11,-1985 and NRC approval is anticipated.
Reference (j) requested Commonwealth Edison's comments on the NRC Staff's report on the ZPSS. It also contained a number of recommendations for changes in Zion's design and operation. These changes were intended to increase the level of safety at Zion.
In summary, the Technical Specification change transmitted with reference (c) is the only request that has been approved. All other requests
~ discussed above remain open.
0838K L.__
e ATTACHMENT 2 l
PROPOSED CHANTS TO ZION OPERATING LICENSE NOS.
OPR-39 and DPR-48 CONFIRMATORY ORDER DATED FEBRUARY 29, 1980 DESCRIPTION OF CHANCE An amendment to Facility Operating License Nos. DPR-39 and DPR-48 is proposed to celete the Zion Confirmatory Order, dated February 29, 1980.
PAGES DELETED Zion Confirmatory Order, dated Fe'ruary o 29, 1980 Order - Pages 1, 2, 3, 4 Appendix A - Pages 1,2,3,4,5,6,7,8 Annex 1 - Page 1 Table 1 - Pages 1, 2 Annex 2 - Pages 1, 2, 3, 4, 5, 6 0838K
ATTACHMENT 3 Evalulation of Significant Hazards Consideration Proposed Changes to Zion Operating License Nos. DPR-39 and DPR-48 Confirmatory Order dated February 29, 1980 DESCRIPTION OF AMENDHENT ,
An amendment to Facility Operating License Nos. DPR-39 and DPR-48 is proposed to delete the Ziun Confirmatory Order, dated February 29, 1980.
BACKGROUND 10 CFR 50.92 states that a proposed amendment will involve a no significant hazards consideration if the proposed amendment does not:
(1) Involve a significant increase in the probability of consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a signflicant reduction in a margin of safety.
In addition, the Commission has provided guidance in the practical j
application of these criteria by publishing eight examples in 48 FR 14870.
The discussion below addresses each of these three criteria and demonstrates that the proposed amenoment involves a no significant hazards consideration.
BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Does the proposed amendment (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or dif ferent kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety?
DISCUSSION - ITEM 1 The Confirmatory Order addressed a large number of varied issues.
Each individual item placed some additional restriction on a given activity. The sum total of these restrictions was believed, in 1980, to result in a signficantly lower level of risk. This belief now appears to be unsupportable. The details of how this reassessment was arrived at apply more directly to Item 3 and thus they will be discussed under that heading.
However, the conclusion reached applies to Item 1 also. That is, that the presence or absence of the Order's restrictions has no significant effect on the level of risk at Zion Station. Thus, the probability or consequences of any previously evaluated accident is similarly unaffected.
DISCUSSION - ITEM 2 As discussed above, the Confirmatory Order has been shown to have a very slight effect on the overall level of risk at Zion Station. In addition, the individual order items are generally directed at accidents that were previously evaluated. For example, Item A.7 required licensed operators to be retrained in the pre-existing Emergency Procedures, which cover only previously evaluated accidents. Also, Item E.1 addressed the status of pre-existing procedures and safety-related systems. This logic is repeated tnroughout tne Order.
Thus, the Order not only has a minor effect on overall safety, but it is directed primarily at previously evaluated accidents. Therefore, its removal does not create the possibility of any new or different type of accident.
DISCUSSION - ITEM 3 The Zion Confirmatory Order was enacted because the Zion Site was believed to be a risk outlier. Specifically, reference (a) stated in part; Due to the relatively high population density surrounding the Zion site as compared to other nuclear power plant sites, the Zion site is believed to present a disproportionately high contribution to the total societal risk from reactor accidents. ...the Staff has identified a number of extraordinary interim measures that should be accomplished both by the licensees and the Staff. These measures will significantly increase the level of safety at tb ' Zion Station and thereby further reduce the probability of a severe reactor accident.
Both the belief that the Zion site may be responsible for the hi;her societal risks and that the Order significantly reduces those risks have ber.n dispelled. The NRC conducted hearings which specifically addressed the effect of an analogous order on the risks at Indian Point.
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The decision in that case (CLI-85-06, dated May 8,1985) found that the Indian Point Order did not significantly affect the level of safety.
Specifically, the Board Concluded; The staff was unable to quantify the extent to which compliance with the Director's Order reduced risks but estimated the reduction as less than a factor of 3. ...On the basis of uncontroverted testimony of I the licensees and staff, the Board found that the measures required or referenced by the D114ctor's Order of February,1980 had a small, positive effect on risa reduction, and that the effect is not amenable to quantification, but is probably considerably less than an order of magnitude. 18 NRC at 908.
l The Commission then decided to rescind Indian Point's Order by !
stating; On the basis of the record, the Commission finds,it difficult to conclude that all of the measures imposed by the Director in 1980 provide substantial, additional protection which is required to protect the public health and safety. ...Second, the special proceeding record contradicts .the Director's previous conclusion that "these measures will signficantly increase the level of safety at the Indian Point Station."
00-80-5,11 NRC 351 (1980). Therefore, we have decided to rescino all of the requirements of the Order unless they are required to meet other license requirements for he Indian Point units or are required to fulfill generic requirements applicable to similar types of power reactors.
The NRC Staff has reached similar conclusions regarding Zion's overall safety and the need for the continued enforcement of Zion's Confirmatory Order. Specifically, the Staff concluded in Section 1.3 of Reference (j);
The staff concludes that Zion poses no undue risk to public health and safety. This conclusion does not depend upon the continued enforcement of the Directors Order of February 1980. Those few clauses of the Directors Order that significantly affect our risk evalation are complete or covered by other requirements.
In addition, the Staff concludes that Zion's design has attributes S
that directly counter-balance the relatively high population density surrounding the Zion site. That is; The staff review of the Zion plant systems indicates that the Zion units have strengths in the area of the response of plant systems to transients and small-break loss-of-coolant accidents (LOCA). The staff has also determined that large, dry containments (such as Zion contain-ment) are likely to contain most core melts, should they occur,
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resulting in a significant reduction in the magnitude of off-site !
- . consequences. For Zion, the site characteristic obviously most >
important is the population density around the plant, which is at the i high end of the population spectrum for plants licensed by the NRC. s Thus, Commonwealth Edison Company has concluded that the Zion site ;
m - poses no undue risk and that the removal of the Zion Confirmatory Order does j not significantly reduce the margin of safety.
USE OF COMMISSION EXAWLE IV TO DEMONSTRATE NO SIGNIFICANT HAZARDS l CONSIDERATION Reference (a) stated that the Confirmatory Order was imposed because; The Zion site is believed to present a disproportionately high .I contribution to the total societal risk from reactor accidents. I
...These measures will significantly increase the level of safety at the Zion Station and thereby further reduce the probability of a severe reactor accident.
However, the conclusion of reference (j) states; l The staff concludes that Zion poses no undue risk to public health and safety. This conclusion does not depend upon the continued enforcement of the Directors Order of February 1980.
While an acceptable level of risk had not been demonstrated to the NRC Staff in February 1980, this task had been completed by August of 1985.
Thus, example iv is applicable in this instance. The fourth Commission example of No Significant Hazards Consideration reads as follows; (iv) A relief granted upon demonstration of acceptable operation from ;
an operating restriction that was imposed because acceptable operation was not yet demonstrated. This assumes that the operating restriction and the criteria to be applied to a request for relief have been established in a prior review and that it is !
justified in a satisfactory way that the criteria have been met.
Based on the above discussion, the proposed changes satisfy the criteria of 10 CFR 50.92 and are similar to the Commission's examples. ,
Therefore, Coninonwealth Edison Company has made a determination that no significant hazards consideration is involved.
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