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MONTHYEARML20096G0101984-08-31031 August 1984 Proposed Tech Specs Implementing Generator Time Overcurrent Protection for Diesel Generators Project stage: Other ML20096G0031984-08-31031 August 1984 Application for Amends to Licenses NPF-9 & NPF-17, Implementing Generator Time Overcurrent Protection for Diesel Generators.Fee Paid Project stage: Request ML20093C9731984-10-0404 October 1984 Proposed Tech Spec,Implementing Generator Time Overcurrent Protection & Instantaneous Overcurrent Protection for Diesel Generators Project stage: Other ML20093C9681984-10-0404 October 1984 Responds to NRC Request for Clarification of 840831 License Amend Request Re Generator Time Overcurrent Protection for Diesel Generators.Amend Seeks to Implement Generator Time & Instantaneous Overcurrent Protection Project stage: Request ML20106J8571984-10-26026 October 1984 Responds to NRC Request for Addl Info Clarifying 840831 Application to Amend Licenses NPF-9 & NPF-17 Re Generator Time Overcurrent Protection.Amend Request Does Not Include Plan to Install Instantaneous Overcurrent Protection Project stage: Request 1984-10-04
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20216E6601999-09-13013 September 1999 Marked-up & Revised TS Pages,Making Permanent One Time Only Changes Incorporated Into TS 3.7.9 Allowing Up to 24 Hours to Restore Control Room Pressure Boundary to Operable Status When Two Cravs Trains Inoperable ML20211G6711999-08-27027 August 1999 Proposed Tech Specs 3.1.4 Re Rod Group Alignment Limits ML20210R0131999-08-10010 August 1999 Revised Tech Specs Bases Pages B 3.4.14-2 & B 3.4.14-6, RCS PIV Leakage ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20195F2941999-06-10010 June 1999 Proposed Tech Specs,Facilitating one-time Addition of Condition G & Administrative Controls Note to TS 3.7.9, Cravs ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206B0761999-04-0606 April 1999 Proposed Tech Specs Expanding Allowable Values for Interlocks P-6 (Intermediate Range Neutron Flux) & P-10 (Power Range Neutron Flux) in TS 3.3.1,Table 3.3.1-1, Function 16 ML20205L2251999-04-0505 April 1999 Proposed Tech Specs,Providing Revised SFP Storage Configuration,Revised SFP Storage Criteria & Revised Fuel Enrichment & Burnup Requirements ML20205B6231999-03-23023 March 1999 Proposed Tech Specs Pages Mark Ups for Unit 1,changing Record for FOL NPF-9 Amend Submittal ML20204F6761999-03-18018 March 1999 Marked-up Tech Spec Pages Re License Bases Record Change to License Amend Submittals ML20207C6921999-02-22022 February 1999 Proposed Tech Specs Bases,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20198B9671998-12-0909 December 1998 Revised TS 3.7.11 LCO Bases to Specify That AB Filtered Ventilation Exhaust Sys Is Considered Operable When Associated Two Fans,Filters,Ductwork,Valves & Dampers Are Operable ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20151Y2461998-09-15015 September 1998 Proposed Improved Tss,Resolving Items Identified by Util During Review ML20151U3521998-09-0808 September 1998 Proposed Tech Specs & Bases Converting to Improved Tech Specs ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5721998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.3 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A0411998-08-0505 August 1998 Suppl 8 to Improved TS Noting Differences Between Two Units. Proposed Changes Require That Specs & Surveillances Apply to Each Unit Individually,Unless Otherwise Noted,Consistent W/Version of Current TS Prior to Amends 166 & 148 ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236G5301998-06-29029 June 1998 Rev to Bases of TS 3/4.6/3,correcting Editorial Errors ML20247E3891998-05-0808 May 1998 Proposed Tech Specs,Revising Power Range Neutron Flux High Trip Setpoints in Event of Inoperable MSSVs & Deleting References to 3-loop Operation in Current TS Section 3.7.1.1(b) & Table 3.7-2 ML20217E6531998-04-20020 April 1998 Proposed Improved Tech Specs Re Section 1.0,2.0,3.0 & 4.0 ML20217B7871998-03-20020 March 1998 Marked-up Proposed Improved TS 3.6 & 5.5.2 ML20217N9311998-03-0303 March 1998 Proposed Tech Specs 5.5 Re Meteorological Tower Location ML20216B9851998-03-0202 March 1998 Proposed Tech Specs Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Encl ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20198H5361997-12-17017 December 1997 Tech Spec Pages for TS 3/4.7.8 for Use in Lieu of ASME Section XI Requirements ML20217H5541997-10-13013 October 1997 Proposed Tech Specs Supporting Replacement of Three Safety Related Narrow Range Refueling Water Storage Tank Level Instruments W/Three Safety Related Wide Range Level Instruments ML20212A2511997-10-0606 October 1997 Proposed Tech Specs Deleting All References to Steam Line Low Pressure Safety Injection Function ML20133M5541997-01-13013 January 1997 Proposed Tech Specs Implementing performance-based Containment Leak Rate Testing Requirements of 10CFR50, App J,Option B ML20133D3991997-01-0606 January 1997 Proposed Tech Specs 3/4.6 Re Containment Systems ML20132F0001996-12-17017 December 1996 Proposed Tech Specs,Supplementing Amend Request to Change Surveillance 4.8.2.1.2.e Which Will Achieve Alignment W/ Improved STS SR 3.8.4.8 ML20135B0381996-11-26026 November 1996 Proposed Tech Specs 3.8.2 Re DC Sources ML20134M1541996-11-0101 November 1996 Proposed Tech Specs 3.8.2 Allowing Use of Low Specific Gravity Cells in Vital 125 Volt Dc Sys When Desired ML20129F7591996-10-22022 October 1996 Proposed Tech Specs 3.6.1.5 Re Containment Systems & Air Temp ML20117K1011996-08-29029 August 1996 Proposed Tech Specs,Replacing 960516 Response to Concerns Re Proposed Changes for Diesel Starting Air Sys Surveillance Testing ML20113C7201996-06-21021 June 1996 Proposed Tech Specs 3.9.6,revising Term Lifting Loads to Lifting Force Used in Manipulator Crane TS 3.9.6b.2 & Redefining Auxiliary Hoist Min Capacities ML20112A7571996-05-16016 May 1996 Proposed Tech Specs 3/4.8 Re Surveillance Requirements ML20101H6101996-03-15015 March 1996 Proposed Tech Specs Re Replacement of SGs ML20101C8281996-03-0808 March 1996 Proposed Tech Specs Reflecting Separate Vols for Unit 1 & Unit 2 ML20100R4601996-03-0404 March 1996 Proposed Tech Specs,Deleting Flow Monitoring Sys from TS 3.4.6.1 & Associated SRs ML20097G3911996-02-13013 February 1996 Proposed Tech Specs Re Listing of Core Operating Limit Methodologies for Editorial Correction ML20095E9571995-12-14014 December 1995 Proposed Tech Specs Action Statements & SRs for Dgs, Incorporating Guidance & Recommendations in NUREG-1366,GL 93-05,GL 94-01 & NUREG-1431 ML20095E8081995-12-12012 December 1995 Proposed Tech Specs,Making McGuire Afd Limit Equations Identical to Previously Approved by NRC for Catawba Nuclear Station ML20095B6221995-12-0505 December 1995 Proposed TS SR 4.8.2.1.2.e Re 60-month Battery Testing ML20093L2861995-10-17017 October 1995 Proposed Tech Specs Listings of Core Operating Limit Methodologies ML20098A4631995-09-18018 September 1995 Proposed Tech Specs,Providing Revised Record Pages for LTOP Protection in TS Amend ML20092K4481995-09-18018 September 1995 Proposed Tech Spec Table 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints ML20092B1571995-09-0101 September 1995 Proposed Tech Specs,Revising TS 3/4.6.5 to Reduce Required Ice Weight in Containment Ice Condenser of Each Unit from 2,099,790 Lbs to 1,516,800 Lbs 1999-09-13
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20217J6401999-10-0606 October 1999 Revised Pages to McGuire Nuclear Station Selected Licensee Commitments Manual ML20216E6601999-09-13013 September 1999 Marked-up & Revised TS Pages,Making Permanent One Time Only Changes Incorporated Into TS 3.7.9 Allowing Up to 24 Hours to Restore Control Room Pressure Boundary to Operable Status When Two Cravs Trains Inoperable ML20211G6711999-08-27027 August 1999 Proposed Tech Specs 3.1.4 Re Rod Group Alignment Limits ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210R0131999-08-10010 August 1999 Revised Tech Specs Bases Pages B 3.4.14-2 & B 3.4.14-6, RCS PIV Leakage ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20195F2941999-06-10010 June 1999 Proposed Tech Specs,Facilitating one-time Addition of Condition G & Administrative Controls Note to TS 3.7.9, Cravs ML20212A2701999-05-28028 May 1999 Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valves Inservice Testing Program ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206Q9311999-05-0404 May 1999 Rev 29 to List of Effective Pages for Chapter 16 & Page 16.11-66 to McGuire Selected Licensee Commitment Manual. with ML20206S9401999-04-30030 April 1999 Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. with List of Effective Pages ML20206K3621999-04-30030 April 1999 Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual ML20206B0761999-04-0606 April 1999 Proposed Tech Specs Expanding Allowable Values for Interlocks P-6 (Intermediate Range Neutron Flux) & P-10 (Power Range Neutron Flux) in TS 3.3.1,Table 3.3.1-1, Function 16 ML20205L2251999-04-0505 April 1999 Proposed Tech Specs,Providing Revised SFP Storage Configuration,Revised SFP Storage Criteria & Revised Fuel Enrichment & Burnup Requirements ML20205L2431999-04-0505 April 1999 SFP Soluble Boron Credit Dilution Analysis (Summary of Applicable Portions) ML20205L2531999-04-0505 April 1999 Boraflex Degradation Analysis ML20205B6231999-03-23023 March 1999 Proposed Tech Specs Pages Mark Ups for Unit 1,changing Record for FOL NPF-9 Amend Submittal ML20204F6761999-03-18018 March 1999 Marked-up Tech Spec Pages Re License Bases Record Change to License Amend Submittals ML20207C6921999-02-22022 February 1999 Proposed Tech Specs Bases,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20198B9671998-12-0909 December 1998 Revised TS 3.7.11 LCO Bases to Specify That AB Filtered Ventilation Exhaust Sys Is Considered Operable When Associated Two Fans,Filters,Ductwork,Valves & Dampers Are Operable ML20198A4691998-12-0909 December 1998 Rev 14 to DPC McGuire Nuclear Station Process Control Program ML20196G6891998-11-23023 November 1998 Rev 26 to Selected Licensee Commitments (SLC) Manual ML20196C9211998-11-14014 November 1998 Rev 26 to Selected Licensee Commitments Manual. with Update Instructions ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y2461998-09-15015 September 1998 Proposed Improved Tss,Resolving Items Identified by Util During Review ML20151U3521998-09-0808 September 1998 Proposed Tech Specs & Bases Converting to Improved Tech Specs ML20151Z7751998-09-0808 September 1998 Rev 25 to McGuire Selected Licensee Commitment Manual, Consisting of Revised Pages 16.7-9 & 16.7-10 ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5721998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.3 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A0411998-08-0505 August 1998 Suppl 8 to Improved TS Noting Differences Between Two Units. Proposed Changes Require That Specs & Surveillances Apply to Each Unit Individually,Unless Otherwise Noted,Consistent W/Version of Current TS Prior to Amends 166 & 148 ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236G5301998-06-29029 June 1998 Rev to Bases of TS 3/4.6/3,correcting Editorial Errors ML20249C2081998-06-0909 June 1998 Rev 24 to Selected License Commitments (SLC) Manual & SLC 16.10.1,dtd June 1998 ML20247E3891998-05-0808 May 1998 Proposed Tech Specs,Revising Power Range Neutron Flux High Trip Setpoints in Event of Inoperable MSSVs & Deleting References to 3-loop Operation in Current TS Section 3.7.1.1(b) & Table 3.7-2 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20217E6531998-04-20020 April 1998 Proposed Improved Tech Specs Re Section 1.0,2.0,3.0 & 4.0 ML20217B7871998-03-20020 March 1998 Marked-up Proposed Improved TS 3.6 & 5.5.2 ML20217N9311998-03-0303 March 1998 Proposed Tech Specs 5.5 Re Meteorological Tower Location ML20216B9851998-03-0202 March 1998 Proposed Tech Specs Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Encl ML20203J9391998-02-19019 February 1998 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20198H5361997-12-17017 December 1997 Tech Spec Pages for TS 3/4.7.8 for Use in Lieu of ASME Section XI Requirements ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20203E1911997-12-0101 December 1997 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20217H5541997-10-13013 October 1997 Proposed Tech Specs Supporting Replacement of Three Safety Related Narrow Range Refueling Water Storage Tank Level Instruments W/Three Safety Related Wide Range Level Instruments ML20212A2511997-10-0606 October 1997 Proposed Tech Specs Deleting All References to Steam Line Low Pressure Safety Injection Function ML20216A8691997-09-0101 September 1997 Rev 0 to QAM-2.0, Order Entry ML20210K9281997-08-31031 August 1997 Cycle 12 Startup Rept ML20216B8171997-08-25025 August 1997 Rev 0 to PE-9778-1, Test Rept-Grinnell Hydraulic Snubber Freedom of Motion Test Under Duke Powers McGuire Nuclear Station MSLB Accident Temp Condition 1999-09-13
[Table view] |
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Attichment'1 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 5) Verifying that on an ESF actuation test signal, without loss-of-offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall be at least 4160 volts and 57 Hz within 11 seconds after the auto start signal; the steady-state generator voltage and frequency shall be maintained within 4160 420 volts and 60 i 1.2 Hz during this test;
- 6) Verifying that on a simulated loss of the diesel generator, with offsite power not available, the loads are shed from the emergency busses and that subsequent loading of the diesel generator is in accordance with design requirements;
- 7) Simulating a loss-of-offsite power in conjunction with an ESF actuation test signal, and a) Verifying deenergization of the emergency busses and load shedding from the emergency busses; b) Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 11 seconds, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady-state voltage and frequency of
.the emergency busses shall be maintained at 4160 1 420 volts and 60 1 1.2 Hz during this test; and c) Verifying that all automatic diesel generator and diesel generator breaker trips, except engine overspeed, lube oil pressure, generator differential, and generator time over-current, are automatically bypassed upon loss of voltage on the emergency bus concurrent with a Safety Injection Actuation signal.
- 8) Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Duri'ng the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to greater than or equal to 4400 kW and during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to greater than or equal to 4000 kW. The generator voltage and frequency shall be at least 4160 volts and 57 Hz within 11 seconds after the start signal. The steady-state generator voltage and frequency shall be maintained within 4160 1 420 volts and 60 i 1.2 Hz during this test. Within 5 minutes after completing this 24-hour test, perform Specifi-cation 4.8.1.1.2d.7)b);
8409100311 840831 PDR ADOCK 05000369 P PDR MCGUIRE - UNITS 1 AND 2 3/4 8-5
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_ 7.;
2 m 74 Attachment II g , , .x e .
-JUSTIFICATION AND SAFETY EVALUATION' he -
' Currently. the.following trips are provided to protect the diesel ele :tric generating , units that are not bypassed during starting ss- .of the di~esel generator by an' Engineered Safeguard Signal:-
a)
Low Lube' Oil Pressure b) Engine Overspeed.
c) Generator Differential Protection
- The rationale for. providing these trips is- that operating a diesel, generator even for a short time without prop.er lubrication or under overspeed conditions results in destruction of the diesel generator without fulfilling its safety function. A redundant diesel generator train is provided to takeover the safety loads of the faulted diesel-generator. These trips.are describ4d in the McGuire FSAR section 8.3.lel.7. Duke Power Company plans to install a Generator Time Overcurrent 1
Protection Device to protect'tha generators from destruction due.to' faults :on ' the switchgear buss.
Operation of a diesel generator with a multiphase; fault on the switch :
gear busswould quickly result in destruction of'the associated generator.
without= fulfilling its safety function. The Generator Time Overcurrent-Protection trips the diesel generator associated with the faulted buss' to prevent its destruction. Three separat's measurements of the over-Lcurrent are provided'by this device and a specific coincident (2 out'of ;
- 3) logic is required to initiate a trip of the diesel generator. This:
trip is not bypassed by.the Engineered Safeguard Signal. The-tripping ~ ,
of-the diesel generator associated with the faulted busadoes not compromise safety as the redundant diesel' generator is available to take 'over the safety loads.
The proposed installation of the Generator Time ~Overcurrent Protection Device would not violate the single failure criterion (GDC 17) for ~
class 1E' diesel' generators.' The postulated single failure can disable only'one diesel generator or one buss. The redundant diesel generator would not be exposed to the same fault 'and is presumed to' be available.
Duke Power Company also plans to install a Generator Instantaneous Overcurrent 7
-Protection to protect the diesel generators during testing periods.
'This' trip along with six other' trips for testing. periods are bypassed in '
the event of'an accident condition. The design includes the capability to test the status and operability,.of the bypass circuits and the '
' capability to alarm abnormal. values of bypassed parameters in the control room.
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o JUSTIFICATION AND SAFETY EVALUATION (Continued)
. The proposed Technical Specification amendment covers the Surveillance
- requirements-for the Generator Time Overcurrent Protection device.
Based on the above analysis, the proposed installation of the Generator Time Overcurrent Protection and the Generator Instantaneous Overcurrent Protection does not have any. adverse impact on safety.
4
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e ATTACHMENT III
. .;- r .
Analysis of Significant Hazards Consideration This' analysis is;provided as required by 10CFR50.91 and is performed according to the standards of 10CFR50.92. The proposed implementation Eof the Time:Overcurrent Protection trip is discussed with reference
'to its potential for causing any significant hazards.
The= consequences of a previously evaluated' accident will not increase due to this modificacion. There are three situations which may occur.
- First, the protective. device will' operate properly. If a fault of two or more of the three phases occurs on the vital buss the device will-trip, disabling the associated D/G 'until the fault is cleared, the re-lays reset and the D/G is restarted. Any, buss fault for which the pro-tactive device would trip would be too large for the'D/G to maintain voltage.on the-buss; by the time the device trips, the D/G is no longer effective in supplying power. If the, protective device were not in the circuit (current configuration) the.D/G would be destroyed and dis-abled indefinitely.
If.the~. protective device operates spuriously, the protection device.
would disable the associated D/G train temporarily (until problem
. diagnosis and device reset) . GDC 17 requires that Class 1E onsite electric power supplies be available assuming a single failure.- Addition of this protective device will not violate the' single failure criteria.
Spurious operation of the protective device is not considered likely
, .- since it is necessary.for two of the three relays (one relay for each phase) to trip on overcurrent before the breaker is tripped.
Finally, if the protective device fails to trip when legitimately
. required to do so, the D/G.will probably be destroyed. The current configuration.(bypassed time overcurrent protection device on a safety' siEnal) will produce the same result. In each of the above cases, the accident mitigation response of the D/G trains is at least as good with the proposed modification as without it so that the consequences of previously evaluated FSAR accidents will not be increased due to this modification.
Initiation of a new accident.due to the proposed modification is not considered credible.' The probability of failure of each of the D/G trains is' increased slightly by the' addition of a new component with
- s failure / spurious operation probability' greater than zero. Coincident 2.out of'3 logic within the overcurrent trip device is necessary to
- initiate a: trip of the associated breaker so that the failure probability increase is insignificant. Also, the possibility of failure / spurious
- operation of the time overcurrent protection device which will disable its related D/G train is created. Although the probability of' failure of each of the D/G trains is increased slightly, the consequences of failure of each of the D/G trains remains the same.
w
- s ; >
l .':
f .-
Analysis.of?Significant Hazards'Considerstion (Continued)
This-in$tillationoftheOvercurrentProtectiontripwillnot:
I
- 1) Involve a significant' increase in the probability
-or 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 significant reduction in a margin of
. safety.
Based upon this analysis, Duke Power Company has determined that the l proposed amendment does not involve a ,significant hazards consideration.
F' .
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