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MONTHYEARML20117K1121985-05-0707 May 1985 Proposed Tech Spec,Requiring Ice Condenser Doors to Remain Closed & Be Capable of Opening Automatically Project stage: Other ML20117K0771985-05-0707 May 1985 Application for Amend to Licenses NPF-35,NPF-9 & NPF-17, Changing Tech Specs Re Operability of Ice Condenser Doors. Fee Paid Project stage: Request ML20129D9171985-07-12012 July 1985 Proposed Tech Specs,Extending Surveillance Interval for Ice Condenser Doors to Once Every 18 Months.Fee Paid Project stage: Other ML20129D9081985-07-12012 July 1985 Application for Amend to Licenses NPF-9 & NPF-17,revising Tech Specs to Extend Surveillance Interval for Ice Condenser Doors to Once Every 18 Months.Fee Paid Project stage: Request 1985-05-07
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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
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f ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION REVISION CONTAINMENT ICE CONDENSER DOORS 8507160605 850712 PDR ADOCK 05000369 p PDR
) CONTAINMENT SYSTEMS ICE CONDENSER 000RS LIMITING CONDITION FOR OPERATION 3.6.5.3 The ice condenser inlet doors, intermediate deck doors, and top deck doors'shall be closed and OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one or more ice condenser doors open or otherwise inoperable, POWER OPERATION may continue for up to 14 days provided the ice bed temperature is monitored at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the maximum ice bed temperature is maintained less than or equal to 27 F; otherwise, restore the doors to their closed positions or OPERABLE status (as applicable) within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE0VIREMENTS 77 l 1 v
4.6.5.3.1 Inlet Doors - Ice condenser inlet doors shall be:
- a. Continuously monitored and determined closed by the inlet door position monitoring system, and
- b. Demonstrated OPERABLE during shutdown at least once per months by:
- 1) Verifying that the torque required to initially open each door is less than or equal to 675 inch pound::;
- 2) Verifying that opening of each door is not impaired by ice, frost or debris;
- 3) Testing a sample of at least 50% of the doors and verifying that the torque required to open each door is less than 195 inch pounds when the door is 40 degrees open. This torque is defined as the " door opening torque" and is equal to the nominal door torque plus a frictional torque component. The doors selected for determination of the " door opening torque" shall be selected to ensure that all doors are tested at least once during two test intervals;
\_)
Amendment No. (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 6-37 Amendment No. (Unit 1)
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' ATTACHMENT II JUSTIFICATION AND SAFETY ANALYSIS I
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JUSTIFICATION AND SAFETY ANALYSIS The current Technical Specification 4.6.5.3.1 requires that the ice condenser inlet doors be demonstrated operabic during shutdown at least once every 9 months. The testing and surveillance required to demonstrate operability is time consuming as well as requiring a power plant shutdown. In the past the ice condenser door testing was scheduled concurrently with the ice weighing operations in the containment. The ice weighing surveillance for the containment is also required once every 9 months. Weighing of the ice baskets of the ice condenser has been carried out with the reactor "0N-LINE".
Therefore, an extension of the duration between two ice condenser door inspections to 18 months would avoid a plant shutdown to carry out the ice condenser door surveillance.
The proposed Technical Specification changes would require that the sur-veillance on the ice condenser doors be performed at least once every 18 months rather than every 9 months as currently required. The extension of the surveillance interval to 18 months would not be a safety concern due to high reliability and forgiving design features of the ice condenser doors as discussed below:
liigh Reliability of the Icc rendenser Doors Due Power has reviewed the surveillance records of the ice condenser door to evaluate the door reliability. Unit 1 and Unit 2 doors have been inspected periodically since 1981 and 1983 respectively. There have been 416 individual inspections of the doors at Unit 1 and 216 door inspections at Unit 2. There has not been any failure to meet the acceptance criteria for door testing in all the inspections / tests carried on to date. One reason for the excellent surveillance history of the ice condenser doors is a design change made to the McGuire door seals to prevent the doors from freezing closed. The efficacy of this modification has been commended in the NRC Safety Evaluation Report (Amendment 36, License NPF-9, 1984) concerning the door surveillance requirements (Ref. 1).
In view of the fact that the ice condenser doors have a history of very high reliability, extension of the surveillance interval to 18 months is not a safety concern.
Forgiving Design Features of the Ice Condenser Doors The acceptance criteria for the ice condenser door passing the inspection is that the door should open with relatively low torque of 675 inch pounds. This translates into a force of 17 pounds at the door handle. A very small change in the differential pressure across the door exerts a large force on the door.
During a LOCA or a high energy line break within the containment, the internal pressure of the containment will rise to between 0 to 15 psig. A rise of
, internal pressure of about 0.1 psia will open all ice condenser doors by
! exerting a force of at least 160 lbs.
A rise of pressure of 1 or 2 psig following an accident would open the ice condenser doors even if these were obstructed by debris or were restrained shut by a h" thick iron bar (Ref. 2). The ice condenser doors are made of 0.5 inch thick Fiber Reinforced Polyester (FRP) reinforced by 6 steel ribs.
The doors are expected to rupture during accident if the doors fail to open, thus venting steam to the ice condenser (Ref. 3). The ice condenser doors are designed so that it is virtually impossible to keep the doors shut during any small increase of containment pressure. Surveillance or testing of the doors does not make the doors more or less reliable as far as accident mitigation is concerned.
The doors perform two distinct functions. While the doors are shut, the doors insulate the lower containment from the ice condenser to prevent the degradation of the ice condenser by sublimation, etc. This function is monitored continuously by the inlet door position monitoring system. The second function for the doors is to open during a LOCA or high energy line break. Our analysis has demonstrated that the doors are virtually impossible to keep shut in event of a minor rise of containment pressure. The extension of the ice condenser door surveillance interval to 18 months would not have any adverse impact on the proper functioning of the ice condenser doors.
Conclusion The ice condenser doors at McGuire have a history of very reliabic operation for several years. The doors are designed to make a door-failure virtually impossibic during a LOCA or a large high energy line break; the proper functioning of the door during an accident is a passive design feature and it does not depend upon performance of periodic surveillance and testing of the doors. The current Technical Specifications for the ice condenser doors are excessive as well as disruptive. The functional readiness of the ice condenser doors as deemed necessary in the Bases 3/4.6.5.3 (pg. B 3/4 6-5) is adequately addressed by operability of the Door Position Monitoring System and door surveillance once every 18 months.
The extension of the door surveillance interval to 18 months would not have any significant adverse safety consequences.
REFERENCESr
- 1. NRC Safety Evaluation Report related to Amendment No. 36 to Facility Operating License NPF-9 and Amendment No. 17 to Facility Operating License to Facility Operating License NPF-17.
- 2. Letter from H. B. Tucker to Dr. J. Nelson Grace (NRC, Region II) dated Feb. 8, 1985.
Subject:
LER 413/85 Concerning the Blockage of Ice Condenser Lower Inlet Doors (Catawba Nucicar Station).
- 3. McGuire FSAR Section 6.2.2.8.
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ATTACHMENT III SIGNIFICANT HAZARDS EVALUATION I
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.o ANALYSIS OF SIGNIFICANT IIAZARDS CONSIDERATION The proposed changes to the Technical Specification 4.6.5.3.1 have been reviewed pursuant to the requirements of 10CFR50.91. The following analysis provides a determination that the proposed amendment of the Technical Specifications does not involve any significant hazards consideration, as defined by 10CFR50.92.
The proposed amendment seeks to relax an excessive surveillance requirement.
The Duke Power review of the ice condenser door surveillance records concludes that higher frequency of door testing does not contribute to improving the reliability of the doors. Similarly reduction of routine surveillance of the ice condenser doors does not reduce their reliability in fulfilling their protective function during an accident. The protective function of the doors is semi-passive and the doors do not require much maintenance or testing.
Therefore, the extension of the surveillance interval to 18 months is not a safety concern.
The proposed amendments would not:
- 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 the preceding analysis, Duke Power Company concludes that the
.roposed
) amendments do not involve a significant hazards consideration.
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