Proposed,Revised Tech Spec Table 4.2-1 Re Instrument Functional Test & Calibr Requirements for Analog Trip UnitsML20077G351 |
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Quad Cities |
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06/13/1991 |
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COMMONWEALTH EDISON CO. |
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Shared Package |
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ML20077G346 |
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References |
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NUDOCS 9106270112 |
Download: ML20077G351 (6) |
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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] |
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Attachment 3 Revised Technical Specification Pagos OP&29 Pago 3.2/4.2 28 3.2/4.2 29 DPlh30 Page 3.2/4.217 l
l l
l 9106270112 910613 PIIR ADOCK 05000254 P PDR l ZNLD/863/18
. . . . , . . . . - . - - . _ - . . . _ - . - . _ . . - _ . . . ~ . - - . - . - - - . - - - . , - .
. QUAD-CITIES OPR-29 TABLE 4.2-1 (Cont'd)
Instrument Instrument functional Instrument Channel Test [2] Calibration I23 Check [2]
RCIC Isolation
- 1. Steamline high flow Once/3 months [9] Once/3 months [9] None
- 2. Turbine area high temperature Refueling outage Refueling outage None
- 3. Low reactor pressure Once/o .aonths Once/3 months None HPCI Isolatio'n 7'
- 1. Steamline high flow (1) [9 [Nl03) Once73 monthe None
- 2. Stean.line area high Refueling ou age Refueling outage None temperature-Low reactor pressure gh
- 3. [1] Oiw irenths None Reactor Building Ventilation System Isolation and Standby Gas Treatment System Initiation
- 1. Refueling floor radiation (1) Once/3 months Once/ day monitors Steam Jet Air Ejector Off-Gas Isolation
- 1. Off gas radiation monitors [1] [4] Refueling outage Once/ day .
Control Room Ventilation System Isolation
- 1. Reactor low water level J1] Once/3 months Once/ day .
- 2. Drywell high pressure ;1) Once/3 months None
- 3. Main steamline high flow [1] Once/3 months Once/ day ,
- 4. Toxic gas analyzers Once/ month Once/18 months Once/ day (chlorine, ammonia, sulphur dioxide)
Notes
[1] Initiallyongepermonthuntilexposurehours(MasdefinedonFigure4.1-1) l are 2.0 X 10 ; thereafter, according to Figure 4.1-1 with an interval not
. less than 1 month nor more than 3 months. The compilation of instrument f ailure rate data may include data obtained from other boiling water reactors for which the same design instrument operates in an environment similar to that of Quad Cities Units 1 and 2.
[2] Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or tripped.
3,2/4.2-28 AmendmentNo.fi[
QUAD-CfTIES OPR-29 M
TABLE 4.2-1 (Cont'd)
(3) This instrumentation is excepted from the functional test definition. The function test shall consist of injecting a simulated electric signal into the measurement channel.
[4] This instrument channel is excepted from the functional test definitions and shall be calibrated using sta1ulated electrical signals once every 3 months.
[5] Functional tests shalt be performed before each startup with a required frequency not to exceed once per week. Calibrations shall be performed during each startup or during controlled shutdowns with a required frequency not to exceed once per week.
(6) The positioning mechanism shall be calibrated every refueling outage.
[7] Logic system functional tests are performed as specified in the applicable section for these systems.
(8) Functional tests shall include verification of operation of the degraded voltage 5 minute timer and 7 second inherent timer.
(9) Verification of the time delay setting of 31 t i 9 seconds shall be -
performed during each refueling outage.
(10) Trip units are functionally tested monthly. A calibration l
of the trip unit is to be performed concurrent with functional testing. Transmitters are calibrated once per operating cycle.
3.2/4.2-29 Anendnent No.
QUAD CITit5 DPR-30 TABLE 4.2-1 (Cont'd)
Instrument Instrument Instr nt functggal CAlRI Ality 2) g1gg (bJnnel InL HPCI ! solation
- 1. Steamline high flow (1) (9) (10) (9) (10) Nord l
- 2. Steamline ares high temperature refueling outage Refueling outage Nane
- 3. tow reactor pressure (1) (10) (10) None l Reactor Butiding ventilation System Isolation and Standby Treatment System Initiation
- 1. Refueling floor radiation (1) Once/3 months Once/ day monttors Steam Jet Air Ejector Of f-Gas isolation
- 1. Off-gas radiation monitors (1) (4) Refueling outage Once/ day Control Room ventilation System Isolation
- 1. Reactor low water level (l) Once/3 nonths Once/ day
- 2. Drywell high pressure (1) Once/3 months None
- 3. Main steamline high flow (1) Once/3 months Once/ day
- 4. Tonic gas analyzers (chlorine. Once/ Month Once/18 months Once/ Gay ammonia, sulphur dioxide)
EQ1t1
- 1. Initially onge per month until exposure hours (H as defined on Figure 4.1-1) ,
are 2.0 X 10 ; thereafter, according to Figure 4.1-1 with an interval not itss than 1 month nor more than 3 months. The Compilation of instrument f atlure rate data uay include data obtained f rom other boiling water reactors f or which the same design instrument operates in an environment
$1mtlar to that of Quad Ctttes Units I and 2.
- 2. Functional tests, calibrations, and instrument checks are not reautred when these instruments are not required to ba operable or tripped.
- 3. This instrumentation is excepted from the functional test definition. The function test shall constst of injecting a simulated electric signal into the measurement channel.
- 4. This instrument channel is excepted f rom the functional test definitions and shall be calibrated using simulated electrical signals once every 3 months.
- 5. Functional tests shall be performed before each startup with a required frequency not to exceed once per week. Calibrations shall be performed during each startup or during controlled shutdowns with a reQutred f requency not to exceed once per week.
- 6. The positioning mechanism shall be Calibrated every refueling outage.
- 7. Logic system functional tests are perf ormed as specified in the applicable section for these systems.
- 8. Functional tests shall include verification of operetton of the degraded voltage, 5 minute timer and 7 secona innerent timer.
- 9. Verification of the time delay setting of 3 1 t i 10 seconds shall be perf ormed during each refueling outage.
(1
- 10. Trip units are functionally tested monthly. A calibration of the trip unit is to be perf ormed concurrent with the f unctional testing. Transmitters are calibrated once per operating cycle.
0515J 3.2/4.2-17 Amendment ho.
9 Attachment 4 Evaluation of No Significant flazards Consideration I
As described in the Safety Evaluation for the Amendment Request, the proposed amendnient returns the information which was previously approved and inadvertently omiPed in subsequent amendments to Table 4.2-1.
C. i . Mnwealth Edison hLs revie*ved the proposeo amondment in accordance with the criteria delineated in 10 C"-R 50.02 and has conemded that the proposed amendment does not present a Sigallicen: Hazards Consideration The bacis for this determination is as follows:
- 1. The proposed change does not irtvolve a signVicant i.v:roase in the probability or consequeix:es of an accident.
I i
The proposed amendment to Table 4.21,
- Minimum Test and Calibration ;
Frequency for Core and Containment Cooling Systems instrumcatation, Rod .
Blocks and Isolations", has been previously evaluated by Commonwealth Edison l and the Commission and it was determined that this change does not involve a significant increase in the probability or consequence of an accident. This proposed amendment corrects Table 4.2-1 to inclr le that Information which was previously approved, however, was inadvertently removed in a subsequent revision to the Table. As a result, this proposed amendment is an administrative change and does not involve any accic ent initiators.
I
- 2. The proposed change does not create the possibility of a new or detterent kind of accedent from any accident previously evaluated.
i The pro 30 sed amendment to Table 4.2-1 has been areviously evaluated by
- Commonwea th Edison and the Commission, and it was cletermined that this change does not create the possibility of a new or different kind of accident from any accident areviously evaluatecl. This proposed amendment corrects Table 4.2-1 to include that nformation which was previously approved, however, was inadvertently removed in a subsequent revision to the Table. As a result, this proposed amendment is an administrative change and does not involve any new operation of the plant.
L ZNLD/863/19
Attachment 4 (Continued)
- 3. The proposed chango does not involvo a significant reduction in the margin of safety.
The proaosed amendment to Table 4.2-1 has been previously determined by Commonwea th Edison and the Commission not to involve a significant reduction in the margin of safety. The aroposed amendment corrects the information on Table 4.2-1 to include information wh ch was previously approved, however, inadvertently omitted in subsequent amendments to Table 4.2-1. The proposed amendment is administrative in nature and does not affect the margin of safety.
.ZNLD/863/20
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