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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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Attachment IC McGuire Nuclear Station EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 BCRON INJECTION SYSTEM BORON INJECTION TANK LIMITING CONDITION FOR OPERATION 3.5.4.1 The boron injection tank shall be OPERABLE with:
- a. A minimum contained borated water volume s: 900 gallons, and
- b. Between 2,000 and 4,000 ppm of boron.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With the boron injection tank inoperable, restore the tank to OPERABLE status within I hour or be in HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to 1% Ak/k at 2000F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the tank to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.4.1 The boron injection tank shall be demonstrated OPERABLE by:
- a. Verifying the contained berated water volume at least once per 7 days, and
- b. Verifying the boron concentration of the water in the tank at least once per 7 days.
McGUIRE - UNIT 1 3/4 5-11 8203090232 820302 PDR ADOCK 05000369 P PDR
Attachment 2A McGuire Nuclear Station Technical Specification 3/4.5.4 - Baron Injection System Proposed Change Change 3.5.4.2 as follows:
Delete entire specification (3.5.4.2) on heat tracing for boron injection tank.
Change 4.5.4.2 as follows:
Delete entire surveillance requirement (4.5.4.2) on heat tracing for boron injection tank.
Justification and Safety Analysis The current requirement for heat tracing is due to high boron concentration required in the BIT tank and associated piping. Reduction of this require-ment to less than 4,000 ppm eliminates the need for heat tracing, resulting in cumulative maintenance savings on the heat tracing equipment associated with the BIT. Heat tracing is only required for boron concentration above 4 weight percent, corresponding to approximately 7,000 ppm.
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Q E~E 3ENCY .'CRE COOL:';G SYSTEZS _
HEAT TRACI.*:G LL. TING CONDITION FOR OPERATION
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3.5.4.2 At least two independent channels of heat traci shall be OPEPABLE for the ron injection tank and for the heat traced por ions of the associate flow paths.
APDLICABILI : MODES 1, 2 and 3.
ACT!ON:
With only one cha el of heat tracing on either 6he boron injection tank or on the heat traced po ion of an associated flow th OPERABLE, operation may centinue for up to e days provided the tank nd flow path temperatures are verified to be greate than or ecual to 145* at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; otherwise, be in at le t HOT STANDBY withi 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 h urs.
SURVEILLANCE REOUIREPENTS
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4.5.4.2 Each heat tracing ch nnel for t boren injection tank and associated flow path shall be demonstra ed OPERABLE:
- a. At least once pe 31 days by energiz ng each heat tracing channel, and
- b. At least onc per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying th tank and flow path tempera ture to be greater than or ecual to 45'F. The tank tempera tur shall be determined by measurement The flow path temoera tur shall be determined by either measur . nt or recir-culation . low until establishment of ecuilibrium t peratures within the tan T_:;,E f. NIT ! 3/a E-12
Attachment 2B (cont.)
EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 3000F provides assurance that a
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mass addition pressure transient can be relieved by the operation of a single PORV.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) Prevent total pump flow from exceeding runout con-ditions when the system is in its minimum resistance configuration,-(2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
3/4.5.4 BORON INJECTION SYSTEM The OPERABILITY of the boron injection system as part of the ECCS ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rupture.
The limits on injection tank udnimum contained volume and boron concentration ensure that the assumptions used in the steam line break analysis are met.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
! 3/4.5.5 REFUELING WATER STORAGE TANK i
! The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient l supply of borated water is available for injection by the ECCS in the event of l a LOCA. The limits on RWST minimum volume and boron concentration ensure that l 1) sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor will remain suberitical in the cold condition following mixing of the RWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses.
I McGUIRE UNIT 1 B 3/4 5-2
Attachment 3A McGuire Nuclear Station Technical Specification 3/4.6.1 - Primary Containment Proposed Change Change 3.6.1.5a to read:
"a. between 75 F* and 100 F in the containment upper compartment, and" Justification and Safety Analysis The low temperature limit is set because of the density of air at the pre-scribed temperature. In an accident condition, the volume increase which would result in heating up dense air could significantly increase the pressure in containment. A review of the various containment integrity analyses (including Westinghouse and FSAR analyses) performed as a result of a recent difficulty in maintaining this limit revealed that the minimum temperature assumed in these analyses was 75 0F. Thus, the current Technical Specification limit of 85 F is overly conservative, and may result in unnecessarily detrimental effects on plant availability. Most plants have a 750F minimum temperature. The inadvertent 85 F limit was probably the result of a typo-graphical error.
The foregoing assessment demonstrates that the proposed Technical Specifica-tion change reducing the minimum average air temperature in the primary con-tainment upper compartment from 85 F to 75 F does not have any adverse effect on safety of plant operation or the health and safety of the public.
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- Attachment 3B McGuire Nuclear Station CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING _ CONDITION FOR OPERATION 3.6.1.5 Primary containment average afr temperature shall be maintained:
- a. between 750F* and 1000F in the containment upper compartment, and
- b. between 1000F* and 1200F in the containment lower compartment.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With the containment average air temperature not conforming to the above limits, restore the air temperature to within the limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 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 />.
d SURVEILLANCE REQUIREMENTS
- 4. 6.1. 5.1 The primary containment upper compartment average air temperature shall be the weighted average ** of all ambient air temperature monitoring stations located in the upper compartment. As a minimum, temperature readings will be obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />'from the following locations:
Location l a. Elev. 826' at the inlet of upper containment ventilation Unit 1A.
- b. Elev. 826' at the inlet of upper containment ventilation Unit 1B.
- c. Elev. 826' at the inlet of upper containment ventilation Unit IC.
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- d. Elev. 826' at the inlet of upper containment ventilation Unit 1D.
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- Lower limit may be reduced to 60 0F in MODE 2, 3 and 4.
l **The weighted average is the sum of each temperature multiplied by its j respective containment volume fraction. In the event of inoperable tempera-ture sensor (s), the weighted average shall be taken as the reduced total divided by one minus the volume fraction represented by the sensor (s) out of i service.
! McGUIRE UNIT 1 3/4 6-11
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