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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20205Q8801999-04-13013 April 1999 Proposed Tech Specs Page 5-9,replacing Operational TSs with Permanently Defueled TSs ML20154E3441998-10-0202 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-39 & DPR-48,eliminating License Conditions No Longer Applicable & Replacing Existing Operational Custom TS with Permanently Defueled TS ML20217H9451998-03-30030 March 1998 Proposed Tech Specs Restoring Plant Custom TS Replaced W/ Improved TS by Previous Amend & Reinstating License Condition Deleted by That Previous Amend ML20202H3641997-11-28028 November 1997 Proposed Improved TSs Using Guidance Provided in NUREG-1431 ML20199D6251997-11-10010 November 1997 Proposed Improved TS Bases Changes & Supporting Info & Final Proposed TS Bases for Section 3.3,including Revised Table of Contents & List of Effective Pages ML20211B9941997-08-0606 August 1997 Proposed Improved Tech Specs Re Draft SER for Zion Station Conversion,Per NUREG-1431 ML20196G8781997-07-18018 July 1997 Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program ML20140D8071997-06-0606 June 1997 Proposed Tech Specs Using Guidance Provided in NUREG-1431,to Produce Set of Improved TS for Plant ML20148B7371997-05-0808 May 1997 Proposed Tech Specs Re Addition of Discussion of Position & Duties of Licensed Operators & Senior Licensed Operators to Section 5.3, Qualification ML20134J2971997-02-0303 February 1997 Proposed Tech Specs Suppl to 960920 Application for Amend to Licenses DPR-39 & DPR-48,providing Annotated & Clean Copies of ITS Pp Affected by Proposed Amend ML20134G0991997-01-27027 January 1997 Proposed Tech Specs Re 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 ML20133D0901997-01-0202 January 1997 Proposed Tech Specs Using Guidance in NUREG-1431 to Produce Improved TSs ML20132B8331996-12-11011 December 1996 Proposed Tech Specs Completely Revising TS Using Guidance Provided in NUREG-1431, Std Ts,Westinghouse Plants ML20134J3641996-11-0808 November 1996 Proposed Tech Specs Re Rquirements Governing RCS Pressure & Temp Limits ML20134G3401996-11-0707 November 1996 Proposed Tech Specs 4.3.1.A.4.b Re Surveillance Requirement ML20134G4141996-11-0707 November 1996 Proposed Tech Specs Table 3.7-1 Re Reduced Power Range Neutron Flux High Setpoint Trip ML20134G5921996-11-0707 November 1996 Proposed Tech Specs 3.13.1.A Re Limiting Operation for Operation ML20129J7731996-11-0101 November 1996 Proposed Tech Specs Modifying Section 3.15.2.A & Section 4.15.2.A of TS ML20128Q8891996-10-14014 October 1996 Proposed Tech Specs 3.3.2.G Re Limiting Condition for Operation & 4.3.2.G Re Surveillance Requirements ML20128L8371996-10-0404 October 1996 Proposed Tech Specs Re Implementation of Option B to 10CFR50,App J ML20128L7831996-10-0404 October 1996 Proposed Tech Specs Modifying F* Distance Definition ML20128H3011996-10-0404 October 1996 Proposed Tech Specs,Clarifying & Adding Mode of Applicability for Rod Position Indicator Channels to TS ML20059H5811994-01-19019 January 1994 Proposed Tech Specs Revising RCS Temperature Required for Reactor Criticality,In Addition to Editorial Changes in Affected Specifications ML20058C3031993-11-19019 November 1993 Proposed Tech Specs Changing LTOP of Reactor Vessel ML20058A2651993-11-10010 November 1993 Proposed Tech Specs Re Limitations on Radioactive Matl Released in Liquid & Gaseous Effluents & New 10CFR21 ML20059H9541993-11-0404 November 1993 Proposed Tech Specs Revising Surveillance Frequency & Acceptance Criteria ML20056F7291993-08-23023 August 1993 Proposed Tech Specs for Implementation of Latest Rev to 10CFR20, Stds for Protection Against Radiation ML20127N0531992-12-22022 December 1992 Proposed Tech Specs to Relocate Fire Protection TSs to an owner-controlled Document Consistent W/Guidance Provided in Generic Ltrs 86-10 & 88-12 ML20127C6521992-09-0101 September 1992 Proposed TS for License Amend Request 92-03 Re Reactor Vessel Integrity & RCS Heatup & Cooldown Limitation Curves ML20248G1221989-09-29029 September 1989 Proposed Tech Spec Page 210 Re Containment Isolation ML20248B3991989-09-25025 September 1989 Proposed Tech Specs to App a Re Section 3.9 Containment Isolation ML20247D0841989-07-18018 July 1989 Proposed Tech Specs,Removing Section 3/4.17.2, Aircraft Fire Detection Sys ML20246D4131989-07-0606 July 1989 Proposed Tech Spec Section 3.15, Auxiliary Electric Power Supply ML20245C6151989-06-13013 June 1989 Proposed Tech Specs Revising Sections 4.0.3 & 4.0.4 Re Applicability of Limiting Conditions for Operations & Surveillance Requirements ML20247M9681989-06-0202 June 1989 Proposed Tech Specs,Revising Tech Spec Section 4.3 to Allow Plant Steam Generator Tubes to Be Repaired Through Installation of Welded Sleeve ML20246N3071989-05-11011 May 1989 Proposed Tech Specs Modifying Section 3.15.2.C to Extend one-time Maint Overhaul to 45 Days to Perform Extensive Overhaul to Diesel Generator O to Conform W/Mfg Recommendation ML20247C2731989-05-10010 May 1989 Revised Proposed Tech Specs Re Reactor Protection Sys ML20245D5981989-04-17017 April 1989 Proposed Tech Specs,Changing Tables 3.1-1 & 4.1-1 to Address Operability & Surveillance Requirements for Reactor Protection Channels ML20248E3751989-03-22022 March 1989 Proposed Tech Specs Re Administrative Controls Section 6.0 ML20235M0411989-02-22022 February 1989 Proposed Tech Specs Changing Section 6.1 Re Administrative Controls ML20155D1451988-09-28028 September 1988 Proposed Tech Spec 4.2.1.F.1 Re Boric Acid Sys ML20195J1571988-06-0909 June 1988 Proposed Tech Specs Section 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 ML20147H5911988-03-0404 March 1988 Revised Proposed Tech Specs Re RCS & Pressure Isolation Valve Leakage ML20149G1981988-02-11011 February 1988 Proposed Tech Spec Page 274 Re 125-volt Battery Testing ML20149F1791987-12-24024 December 1987 Proposed Tech Specs Allowing Use of Westinghouse or C-E Sleeving Methodology to Repair Steam Generator Tubes ML20237B5291987-12-0909 December 1987 Proposed Tech Spec Section 4.15.1.E Re 125-Volt Batteries, Upgrading Plant Program for Verifying Existence of Adequate Battery Capacity ML20236G0681987-10-27027 October 1987 Proposed Tech Specs,Extending Snubber Insp Period ML20236C0421987-10-22022 October 1987 Proposed Tech Specs,Removing Refs to Initial Base Line Inservice Insp & to Specific Version of ASME Section XI Code ML20235E2471987-09-22022 September 1987 Proposed Tech Specs,Allowing one-time Visual Insp of Snubbers to Be Performed During Planned Refueling Outages ML20214T4251987-05-29029 May 1987 Proposed Tech Specs to Allow Simultaneous Charging Pump Operation During Pump Realignment & to Reduce Allowable Time Period for Depressurization Following Failure of PORV 1999-04-13
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216G1351999-09-23023 September 1999 Rev 5 to Chapter 12 of Zion Annex Odcm ML20209F8321999-06-30030 June 1999 Rev 4,Chapter 12 of ODCM for Zion Annex ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205Q8801999-04-13013 April 1999 Proposed Tech Specs Page 5-9,replacing Operational TSs with Permanently Defueled TSs ML20154E3441998-10-0202 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-39 & DPR-48,eliminating License Conditions No Longer Applicable & Replacing Existing Operational Custom TS with Permanently Defueled TS ML18068A7121998-07-31031 July 1998 Rev 3 to Chapter 12 of Zion Station Odcm. ML20217N9661998-03-31031 March 1998 Revs to ODCM for Zion Station,Including Rev 2 to Chapters 10 & 12 ML20217H9451998-03-30030 March 1998 Proposed Tech Specs Restoring Plant Custom TS Replaced W/ Improved TS by Previous Amend & Reinstating License Condition Deleted by That Previous Amend ML20216G8981998-03-16016 March 1998 Certified Fuel Handler Training & Retraining Program ML20202H3641997-11-28028 November 1997 Proposed Improved TSs Using Guidance Provided in NUREG-1431 ML20199D6251997-11-10010 November 1997 Proposed Improved TS Bases Changes & Supporting Info & Final Proposed TS Bases for Section 3.3,including Revised Table of Contents & List of Effective Pages 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 ML20212B4761997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Dept Start- Up Readiness Assessment Guideline ML20212B4601997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Sys Readiness Review ML20212B4421997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Plan ML20212B4471997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Scope Mgt Guideline ML20211B4831997-09-0505 September 1997 Restart Action Plan ML20211B9941997-08-0606 August 1997 Proposed Improved Tech Specs Re Draft SER for Zion Station Conversion,Per NUREG-1431 ML20196G8781997-07-18018 July 1997 Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program ML20140D8071997-06-0606 June 1997 Proposed Tech Specs Using Guidance Provided in NUREG-1431,to Produce Set of Improved TS for Plant ML20140C4151997-06-0505 June 1997 Rev 1 to Zion Nuclear Station Recovery Plan ML20148B7371997-05-0808 May 1997 Proposed Tech Specs Re Addition of Discussion of Position & Duties of Licensed Operators & Senior Licensed Operators to Section 5.3, Qualification ML20134J2971997-02-0303 February 1997 Proposed Tech Specs Suppl to 960920 Application for Amend to Licenses DPR-39 & DPR-48,providing Annotated & Clean Copies of ITS Pp Affected by Proposed Amend ML20137B4691997-01-31031 January 1997 Rev 1.9 to Chapter 10, Zion Annex Index & Rev 1.8 to Chapter 12, Radioactive Effluent Technical Stds ML20216E6041997-01-31031 January 1997 Amend 4 to Zion Station Fire Protection Rept ML20134G0991997-01-27027 January 1997 Proposed Tech Specs Re 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 ML20133D0901997-01-0202 January 1997 Proposed Tech Specs Using Guidance in NUREG-1431 to Produce Improved TSs ML20132B8331996-12-11011 December 1996 Proposed Tech Specs Completely Revising TS Using Guidance Provided in NUREG-1431, Std Ts,Westinghouse Plants ML20134J3641996-11-0808 November 1996 Proposed Tech Specs Re Rquirements Governing RCS Pressure & Temp Limits ML20134G3401996-11-0707 November 1996 Proposed Tech Specs 4.3.1.A.4.b Re Surveillance Requirement ML20134G4141996-11-0707 November 1996 Proposed Tech Specs Table 3.7-1 Re Reduced Power Range Neutron Flux High Setpoint Trip ML20134G5921996-11-0707 November 1996 Proposed Tech Specs 3.13.1.A Re Limiting Operation for Operation ML20129J7731996-11-0101 November 1996 Proposed Tech Specs Modifying Section 3.15.2.A & Section 4.15.2.A of TS ML20134H4591996-10-31031 October 1996 Rev 1.8 to Chapter 10 Odcm,Zion Annex Index ML20128Q8891996-10-14014 October 1996 Proposed Tech Specs 3.3.2.G Re Limiting Condition for Operation & 4.3.2.G Re Surveillance Requirements ML20128H3011996-10-0404 October 1996 Proposed Tech Specs,Clarifying & Adding Mode of Applicability for Rod Position Indicator Channels to TS ML20128L7831996-10-0404 October 1996 Proposed Tech Specs Modifying F* Distance Definition ML20128L8371996-10-0404 October 1996 Proposed Tech Specs Re Implementation of Option B to 10CFR50,App J ML20129E5621996-09-30030 September 1996 Rev 1.1 to Chapter 11 to Odcm,Zion Annex Index ML20129J4891995-10-0404 October 1995 On-Site Review for ODCM Revision ML20059H5811994-01-19019 January 1994 Proposed Tech Specs Revising RCS Temperature Required for Reactor Criticality,In Addition to Editorial Changes in Affected Specifications ML20058C3031993-11-19019 November 1993 Proposed Tech Specs Changing LTOP of Reactor Vessel ML20058A2651993-11-10010 November 1993 Proposed Tech Specs Re Limitations on Radioactive Matl Released in Liquid & Gaseous Effluents & New 10CFR21 ML20059H9541993-11-0404 November 1993 Proposed Tech Specs Revising Surveillance Frequency & Acceptance Criteria ML20058E8751993-09-0303 September 1993 Revised AOP-6.3, Loss of RHR Shutdown Cooling ML20056F7291993-08-23023 August 1993 Proposed Tech Specs for Implementation of Latest Rev to 10CFR20, Stds for Protection Against Radiation ML20056H0281993-08-20020 August 1993 Errata to Chapter 12 to ODCM, Including Revised Table 12.2-1,12.2-3 & 12.5-1 ML20056G8131993-06-30030 June 1993 Pump & Valve Inservice Testing Plan for Zion Nuclear Generating Station Units 1 & 2 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 1999-09-23
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ATTACHWNT PROPOSED ZION APPENDIX A TECHNICAL SPECIFICATION CHANTS T0 t- ,
SECTION 5.0 DESIGN FEATURES Pages Modified: 298 w
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4 (Replace corresponding pages'in Attachment 1 of Reference (a))
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1 Th2 rcacter containment strrcture fer Zien Unit Th;ra are thrco secticns cf racks with sach .
2 essentially identical in design and section made up of two rows. The two parallel .
construction to that of Unit 1 except that it rows in each section have a nominal center to is reoriented. Numerous mechanical and center spacing of 21 inches and each section is electrical systems penetrate the containment separated by a distance of 44" to assure a K wall through welded steel penetrations.(2) effective of less than 0.95 even for a condition of optimum moderation if unborated 5.4.3 Containment Penetrations Sideways water was to fill the vault, for fuel having a maximum loading of 46.4 gas. U-235 per axial All containment penetrations (both electrical centimeter of fuel assembly length (about 3.7 and piping) are double barrier assemblies weight percent U-235). The new fuel storage consisting of a closed sleeve, in most cases, vault is protected from flooding by its free or a double gasketed closure for special flood drain, penetrations such as the fuel transfer tube.
The space between the double barriers will be New fuel may also be temporarily stored in the continuously pressurized, by the Penetration spent fuel pool in preparation for refueling.
Pressurization System, to a pressure in excess The fuel assemblies are stored in racks in of the containment design pressure. (*) parallel rows, having a nominal center to center distance of 10.35 inches in both References directions. This spacing is sufficient to maintain a K effective of less than .95 when (1) FSAR Section 5.1.1 flooded with unborated water, for fuel having a (2) FSAR Section 5.1.2 maximum loading of 46.4 gms. U-235 per axial (3) FSAR Section 5.1.4 centimeter of fuel assembly length (about 3.7 weight percent U-235).
5.5 Fuel Storage 5.5.2 Spent Fuel Storage 5.5.1 New Fuel Storage Irradiated fuel assemblies will be stored prior New fuel assemblies are stored in a to offsite shipmer.t in the stainless steel separate storage vault which is designed lined fuel pool which is located in the fuel to hold 132 new assemblies. The new fuel hanaling building. Borated water is used to storage racks accommodate 2/3 of a core. fill the spent fuel storage pit at a concentration to match that used in the reactor cavity and refueling canal during refueling operations. The fuel is stored in a vertical array with a nominal center to center spacing of 10.35" between assemblies to assure a K effective of less than 0.95 even if unborated
. water is used to fill the pit, for fuel having l a laaximum loading of 46.4 gas. U-235 per axial 09510/09520 298
3 5.5.2 Seent Fuel Storace fContinued) 5.6 Seismic Destin ].
l centimeter of fuel assembly length (about 3.7 The structuras, mechanical components and weight percent U-235). Engineered Safeguards Systems vital to safe shutdown and containment isolation, or whose peterence failure might cause or increase the severity of a loss of coolant accident, are designed per Criticality Analysts of Zion Units 1 and 2. Fresh and the seismic criteria of Design Basis Earthquake Spent Fuel Racks, dated October 25, 1984. (98E). Design Basis Earthquake is based on i ordinary allowable stresses as set forth in i
applicable codes, plus the additional requirement that a safe shutdown be made during a horizontal ground acceleration of 0.17g and a
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i vertical acceleration of 0.11g occurring 4 simultaneously. These systems and equipment are i defined as Seismic Class 1.
t other systems and mechanical components in a j support or auxiliary function are designed per the seismic criteria of Operational Basis l Earthquake (08E), or per applicable codes.
These systems and equipment are defined as j either Classes 2 or 3 depending on their function.
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