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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days 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 ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K 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 ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals 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 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc ML20078E2051995-01-20020 January 1995 Proposed Tech Specs Re Snubber Visual Insp Intervals ML20078Q6061994-12-12012 December 1994 Proposed TS Section 3.4/4.4 Re Standby Liquid Control Sys ML20064J3181994-03-11011 March 1994 Proposed Tech Specs Re Snubber Visual Insp Intervals ML20059A7321993-12-20020 December 1993 Proposed Tech Specs 1.1/2.1-1 Increasing MCPR Safety Limit from 1.06 to 1.07 for Units 1 & 2 ML20059A8301993-10-21021 October 1993 Proposed Tech Specs Deleting Requirements for Demonstrating Operability of Redundant Equipment When ECCS Equipment Is Found Inoperable or Made Inoperable for Maint ML20125D6381992-12-0808 December 1992 Proposed Tech Specs 3/4.1 Re Reactor Protection Sys ML20116J7091992-11-0606 November 1992 Corrected Proposed TS 3.2/4.2-8 Re Administrative Changes 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 1999-08-13
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20196K1941999-06-30030 June 1999 Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days 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 ML20196K5861998-11-0505 November 1998 Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20195J9041998-09-24024 September 1998 Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129K3321996-10-18018 October 1996 Cycle 15 Startup Test Results 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 ML20116F3971996-06-30030 June 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20100C0441996-01-24024 January 1996 Secondary Containment Leak Test Summary ML20093K7721995-10-12012 October 1995 Quad-Cities Nuclear Power Station Unit 2 Cycle 14 Startup Test Results Summary ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals 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 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc 1999-08-13
[Table view] |
Text
4 & -_ <---#-u , _
SUMMARY
OF CHANGES PROPOSED TS 5.0
' DESIGN FE ATU R ES" c1oso::0: r.7 910729 POR ADOCK O'I'UOh f,'k" P
i I
E9MAllY QE CHAHOCQ PROPOSED SPECIFICATIori 5.0 DESIGli FEATURES This section contains proposed changes to Quad C4, ties Units 1 and 2 Technical Specification section 5.0. The propcsed change relocates precent figure 4.8-1 to Section 5.0 on Design Features.
Item 1:
EaH2 5.0-1, SpecificatiQD Ed PPR-29 Renumber present paragraph under Section 5.1, " Site," to 5.1.A.
Add new paragraph 5.1.B to reterence new rigure 5.0-1,
" Unrestricted Area Boundary."
Item 2:
Asid Pacte 5. 0-3. figRtc 5.0-1.
2 DEP-12 Renumber present rigure 4.8-1 to 5.0-1 on page 5.0-3.
DESCRIPTION OF CHANGES PROPOSED TS 5.0
' DESIGN FEATURES
4 i
DESCRIPTION QP. PROPOSED hMENDjiENT Br&MER.T PROPOSED SPECIFICATION 5.0 DESIGN FEATURES The changes proposed in this amendment request are made to improve the usability of the present technical cpecifications.
An item by item description of the proposed changes requested is provided below. The Summary of Changes section can be referred to in order to reference back to a given chango and its affected page.
Items 1 and 1 The proposed change to Section 5.0 is administrativo in nature since it involves the relocation, without technical changes, of present Figure 4.8-1 to Section 5.0 on Design Features. The proposed change follows STS guidelines for location of material and provides a consistent presentation of Design Features in one section of the Technical Specifications.
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PROPOSED TECH SPEC TS 5.0
' DESIGN FEATURES' p
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e QUAD CITIES UNITS 1 & 2 I DPR-29 & DPR-30 i 5.0 DESIGN FEATURES 5.1 SITE A. The Quad Cities Station, which consists of a track of land of approximately 404 acres, is located about 3 miles north of Cordova, Illinois, Rock Island County, Illinois. The track is situated in portions of Sections 7, 8, 17, and 18 of Township 20 North, Range 2 East.
B. The UNRESTRICTED AREA boundary shall be as shown in Figure 5.0-1.
5.2 REACTOR A. The core shall consist of not more than 724 fuel assemblies.
B. The reactor core shall contain 177 cruciform-shaped control rods. The control material shall be boron carbide powder (B4 C) co macted to approximately 70%
of theoretical density or hafnium metal.
5.3 REACTOR VESSEL The reactor vessel shall be as described in Table 4.1.1 of the SAR. The applicable design codes shall be as described in Table 4.1.1 of the SAR.
5.4 CONTAINMENT A. The principal design parameters and applicable design codes for the primary containment shall be as given in Table 5.2.1 of the SAR.
B. The secondary containment shall be as described in Section 5.3.2 of the SAR, and the applicable codes shall be as described in Section 12.1.1.3 of the SAR.
C. Penetrations to the primary containment and piping passing-through such penetrations shall be designed in accordance with standards set forth in Section 5.2.2 of the SAR.
5.5 FUEL STORAGE A. The new fuel storage facility shall be such that the 5.0-1
QCAD CITIES UllITS 1& 2 DPR-29 & DPR-30 k,,, dry is less than 0.90 and flooded is less than +
0.95.
B. The k,,, of the spent f uel storage pool shall be less '
than or equal to 0.95.
5.6 SEISMIC DESIGli The reactor building and all contained engineered safeguards are designed for the maximum credible earthquake ground motion with an acceleration of 24% of i gravity. Dynamic analysis was used to determino the earthquake acceleration application to the various elevations in the reactor building.
'i t 5.0-2
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EXISTING TECH SPEC TS 5.0
' DESIGN FEATU RES' 1
QUAD ClllES 9PR-29
- 5. 0 DESIGN FEATURIS 5.1 SITE,m. .
A.
The Quade&'ities Station, which consists of a tract of land of approximai.ely 404 acres, Illinois.is located about 3 miles north of Cordova, Illinois, Rock Island County, The tract is situated in portions of Sections 7, 8,17, and 18 of Township 20 North, Range 2 East.
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- 5. 2 , REACTOR -
A.
The core shall consist of not more than 724 fuel assemblies.
B.
The reactor core shall contain 177 cruciform-shaped control rods. The control material shall be boron carbide power (8 C) compacted to approximately70%oftheoreticaldensityorhafniummetal.
5.3 REACTOR VESSEL,u, The reactor vessel shall be as described in Table 4.1.1 of the SAR. The applicable design codes shall be as described in Table 4.1.1 of the SAR.
- 5. 4 CONTAINMENT,u-A.
The principal design parameters and applicable design codes for the primary containment shall be as given in Table 5.2.1 of the SAR.
B.
The secondary containment shall be as described in Section 5.3.2 of the SAR, and the applicable codes shall be as described in Section 12.1.1.3 of the SAR, C.
Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in Section 5.2.2 of the SAR.
5.5 FUEL STORAGEs u-A.
The new fuel storage facility shall be such that the K,ff dry is less than 0.90 and flooded is less than 0.95.
B. The K 0.95 ,ff of the spent fuel storage pool shall be less than or equal to 5.0-1 Amendment No. 114
- 5. 6 SEISHlc OESIGN p The reactor building and all contained engineered safeguards are designed for the gravity. credible maximum earthquake ground motion with an acceleration of 24% of Dynamic analysis was used to determin3 the earthquake acceleration application to the various elevations in the reactor building, h
5.0-2 Amendment No. 114
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SIGNIFICANT HAZARDS CONSIDERATIONS AND ENVIRONMENTAL ASSESSMENT EVALU ATION PROPOSED TS 5.0 '
DESIGN FEATURES"
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I EVALUATION EQB S19EIFICANT HAZABDA QQFJJDERATION PROPOSED SPECIFICATION 5.0 DESIGN FEATURES The proposed changes provided in this amendment request are made in order to provide a more user friendly document. These changes have been reviewed by Commonwealth Edison and we believe that they do not present a Significant Hazards consideration. The basis for our determination is documented as follows:
RhSl3 EQ.B HQ SIGNIFICANT lihZARDS CpNSIDERATION Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards consideration.
In accordance with the critoria of 10 CFR 50.92(c) a proposed amendment to an operating-license involves no sLgnificant hazards consideration if operation of the facility, in accordance with the proposed amendment, would nott J
- 1) Involve a significant-increase in the probability or consequences of an accident previously evaluated, because:
The proposed changes are administrative in nature and do not represent changes to the technical content of the present Technical Specifications. The relocation of present Figure 4.8-1, " Unrestricted Area Boundary," places this material in the Design Features Section of the Technical Specifications for consistency in location and presentation of material. Due to the nature of the proposed changes, they do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2) Create the possibility of a new or different kind of accident from any previously evaluated because:
Due to the administrative nature of the proposed changes, they cannot create the possibility of a new or different kind of accident from any previously evaluated.
- 3) Involve a significant reduction in the margin of safety because:
The proposed changes maintain current Technical Specification requirements and the relocation of present Figure 4.8-1 to Section 5.0, is an administrative change. Therefore, the proposed changes do not involve a significant reduction in the margin of safety.
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ENVIRONMENTAL hgER88 MENT EVALUATION !
PROPOSED SPECIFICATION SECTION 5.0 1 i
DESIGN TEATURES Commonwealth Edison has evaluated the proposed amendment in accordance with the requirerents of 10 CFR 51.21 and has determined that the amendment meets the requirements for categorical exclusion as specified by 10 CFR 51.22(c)(9).
Commonwealth Edison has deter'.nined that the amendment involves no significant hazards consideration, there are no significant change in the types or significant increase in the amounts of any effluent that may be released offsite, and there is no significant increase in individual or cunulative occupational radiation exposure.
The proposed amendment does not modify the existing facility and does not involve any new operation of the plant.
As such, the proposed amendment does not involve any change in the type or significant increases in effluents, or increase individual or cumulative occupational radiation exposure. The proposed amendment to Section 5.0, " Design Features" contains only one change. In the existing Technical Specifications, the figure r; reficct the unrestricted area boundary is currently contained in Section 3.8/4.B. The proposed amendment removes the figure from Section 3.8/4.8 and relocates the figure to Section 5.0. As such, the proposed change is administrative in nature.
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4 QC-1 / QC-2 DIFFERENCES TS 5.0
' DESIGN FEATU RES'
4 COMPARISON OF UNIT 1 AND UNIT 2 TECHNICAL DPECIFICATIONS FOR THE IDENTIFICATION OF TECHNICAL DIFFERENCES SECTION 5.0 DESIGN TEATURES Commonwealth Edison has conducted a comparison review of the Unit 1 and Unit 2 Techr.ical Specifications to identify any technical differences in support of combining the Technical Specifications into one document. The intent of the review was not to identify any differences in presentation style (e.g. table formats, use of capital letters, etc.), punctuation or spelling errors, but rather to identify areas which the Technical Specifications are technically or administratively different.
The review of Section-5.0, " Dosign Pontures" revealed the no technical or administrativo di"forences.
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