ML20309A746
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McGuire Nuclear Station UFSAR Appendix 1A. Tables Appendix 1A. Tables
McGuire Nuclear Station UFSAR Table 1-1 (Page 1 of 3)
Table 1-1. Shared Facilities and Equipment
[HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED]
(Note: This table 1-1 is not applicable to 10CFR50 Appendix A General Design Criterion 5, Sharing of Structures, Systems, and Components.)
Quantity System Components Shared Provided Chemical & Volume Control System Chiller Pumps 3 Boric Acid Transfer Pump 4 Resin Fill Tank 1 Boric Acid Tank 2 Boric Acid Batching Tank 1 Batching Tank Agitator 1 Chillers 3 Boron Recycle System Recycle Evap. Feed Demin. 2 Recycle Evap. Feed Filters 2 Recycle Holdup Tanks 2 Recycle Evap. Feed Pumps 2 Recycle Evap. Reagent Tank Unit 1 Package Recycle Evaporator Package 1 Recycle Evap. Cond. Demin. 1 Recycle Evap. Cond. Filter 1 Recycle Evap. Concentrates Filter 1 Ice Condenser Refrigeration Ice Condenser Glycol Mixing & 1 Storage Tank Ice Condenser Glycol Mixing & 1 Storage Pump Ice Cendenser Glycol Pumps 6 Ice Condenser Refrigeration Unit 4 Ice Machine Unit 3 Ice Solution Mixing Tank 2 Ice Solution Pump 2 Ice Bin Condensing Unit 2 Ice Annex Condensing Unit 1 Ice Bin Space Air Handler Unit 1 (22 APR 2017)
McGuire Nuclear Station UFSAR Table 1-1 (Page 2 of 3)
Quantity System Components Shared Provided Ice Bin Wall Air Handler Unit 2 Ice Annex Space Air Handler Unit 2 Ice Condenser Refrigeration Ice Condenser Blower Unit 1 Ice Condenser Air Cooler 1 Ice Condenser Air Chiller Condensing 2 Unit Ice Condenser Air Chiller 3 Ice Condenser Vacuum Receiver 1 Ice Condenser Cyclone Receiver 1 Component Cooling System Component Cooling Drain Tank 1 Component Cooling Drain Tank Pump 1 Liquid Waste Recycle, Liquid Waste Common waste systems are used for Monitor & Disposal, Waste Gas, and the two units. Each Con- tainment Nuclear Solid Waste Disposal Systems structure has its own reactor coolant drain tank and Containment sump serviced by two reactor coolant drain tanks and four sump pumps. All other waste equipment is sized to adequately serve two units and common Auxiliary and Service Building.
Nuclear Service Water System Supply and Return Lines Control, 2 Cable, and Equipment Room Air Conditioning Condenser Auxiliary Building Ventilation System Fuel Handling Area Filter Train 1 Fuel Handling Area Exhaust Fan 2 Fuel Handling Area Supply Air 1 Handling Unit Radiation Area Supply Filter 1 Radiation Area Supply Fan 1 Radiation Area Cooling Coil 1 Groundwater Drainage System Groundwater Sump Pump 6 Conventional L. P. Service Water Conventional Service Water Pump 3 System Control Area Ventilation System Ctrl Rm Outside Air Press. Filter Trn 2 Ctrl Rm Outside Air Press. Filter Trn 2 Pressure Fan (22 APR 2017)
McGuire Nuclear Station UFSAR Table 1-1 (Page 3 of 3)
Quantity System Components Shared Provided Control Room Air Handling Unit 2 Control Room Chillers 2 Equipment & Cable Room Filter Train 2 Equipment & Cable Room Air Handling 2 Unit Fire Protection System Fire Pump 3 Jockey Pump 2 Pump Fire Protection Pressurizer Tank 1 Recirculated Cooling Water System Recirculated Cooling Water Pumps 3 Recirculated Cooling Water HX 4 Recirculated Cooling Water Storage 1 Tank Containment Ventilation Cooling Water Containment Ventilation Cooling Water 3 System Pump Containment Ventilation Cooling Water 1 Strainer Compressed Air System Air Compressors 3 Air Filters 3 Air Aftercoolers 2 Air Receivers 3 Air Dryers 4 Instrument Compressed Air Tanks 2 Radiation Monitoring System Control Room Monitoring Panels 2 For monitors, refer to Tables 11-27 and 11-28 (22 APR 2017)
McGuire Nuclear Station UFSAR Table 1-2 (Page 1 of 4)
Table 1-2. Design Comparison
[HISTORICAL INFORMATION NOT REQUIRED TO BE REVISED]
Chapter Chapter Title FSAR Number System/Component Reference Significant Similarities Significant Differences Chapter 4.0 Reactor Fuel 4.2.1 Trojan & Sequoyah None Reactor Vessel Internals 4.2.2 Trojan & Sequoyah Sequoyah and McGuire Incorporate Upper Head Injection (UHI) Systems. Trojan and McGuire have neutron pads.
Reactivity Control 4.2.3 Trojan & Sequoyah None Nuclear Design 4.3 Trojan & Sequoyah None Thermal-Hydraulic 4.4 Trojan & Sequoyah None Design Chapter 5.0 Reactor Coolant System 5.1, 5.2 Trojan & Sequoyah The following have been added or changed:
Specific stress limits.
Reactor Vessel1 5.4 Trojan & Sequoyah Sequoyah and McGuire vessel heads incorporate UHI penetrations.
Reactor Coolant Pumps1 5.5.1 Trojan & Sequoyah except as Higher flow due to changes to impeller, noted. diffuser, and no motor HP.
Steam Generators1 5.5.2 Millstone 2 Steam drums were not replaced at Millstone.
Piping1 5.5.3 Trojan & Sequoyah Sequoyah and McGuire incorporate UHI piping.
Residual Heat Removal 5.5.7 Trojan & Sequoyah None System Pressurizer1 5.5.10 Trojan & Sequoyah None Chapter 6.0 Engineered Safety Features Containment Systems 6.2 Trojan & Sequoyah Sequoyah and McGuire have Ice Condensers.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-2 (Page 2 of 4)
Chapter Chapter Title FSAR Number System/Component Reference Significant Similarities Significant Differences Emergency Core Cooling 6.3 Trojan & Sequoyah except as Sequoyah and McGuire have Upper Head System noted. Injection Systems.
Chapter 7.0 Instrumentation and Controls Reactor Protection 7.2 System Functions are similar None System to Sequoyah & Trojan.
Engineered Safety 7.3 Systems Functions are similar None Featured Systems to Sequoyah & Trojan.
Systems required for safe 7.4 System functions are similar None shutdown to Sequoyah & Trojan.
Safety Related Display 7.5 System functions are similar Actual physical configuration may differ due Instrumentation to Sequoyah & Trojan. to design philosophy.
Other Safety Systems 7.6 Operational functions are None similar to Trojan &
Sequoyah.
Control Systems 7.7 Operation functions are Load rejection capability is an option.
similar to Trojan & Sequoyah except as noted.
Chapter 8.0 Electric Power Offsite Power System 8.2 Similar to Trojan except as Trojan switchyard has two bus single breaker noted. scheme, whereas McGuire has two bus breaker-and-a-half- scheme. McGuire has a 230 kV switchyard for Unit 1 and a 525 kV switchyard for Unit 2 with an auto-transformer connecting the 230 KV and 525 kV switch- yards.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-2 (Page 3 of 4)
Chapter Chapter Title FSAR Number System/Component Reference Significant Similarities Significant Differences McGuire switchyard feeders to the main step-up trans-formers have two redundant primary relaying circuits with two independent channels per circuit, and two out of four tripping logic.
Onsite Power System 8.3 Similar to Trojan except as Trojan uses startup trans-formers for startup noted. and shutdown power, whereas McGuire uses generator circuit breakers thereby allowing two full size auxiliary transformers (normally operated at half rated capacity) to supply startup and shutdown power.
Chapter 9.0 Auxiliary Systems Chemical and Volume 9.3.4 Trojan & Sequoyah except as Trojan and Sequoyah designs do not include Control System noted. the Boron Thermal Regeneration System whereas McGuire does.
Boron Recycle System 9.3.6 Trojan and Sequoyah except Trojan & Sequoyah CVCS designs include the as noted. BRS where McGuire has a separate system.
Chapter 11.0 Radioactive Waste Management Source Terms 11.1 Joseph M. Farley, Watts Bar. None Liquid Waste 11.2 Joseph M. Farley None Gaseous Waste 11.3 Joseph M. Farley None Processing Process Radiation 11.4 Functionally Similar None Chapter 15.0 Accident Analysis monitoring 15.0 Similar to Trojan & The Accident Analysis section have been Sequoyah except as noted. updated per WCAP 8185.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-2 (Page 4 of 4)
Chapter Chapter Title FSAR Number System/Component Reference Significant Similarities Significant Differences Note:
- 1. All components designed and manufactured to Code edition in effect.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-3 (Page 1 of 7)
Table 1-3. Major Design Changes Since PSAR Item Change in Design FSAR Reference Reason for Change 1 Coarse aggregates for Category 1 structures conform to N. 3.8.1 Local quarries conform to N. C. Highway C. Highway Commission Specification No. 3 and 4 and Commission's Specifi- cations as opposed to fine aggregates conform to ASTM C33, while the PSAR ASTM specifications.
commits concrete aggregates to meet ASTM C33.
2 Fuel assemblies have been changed from a 15 x 15 array Chapter 4.0 This new product line improves the core to a 17 x 17 array. thermal margin.
3 Upper internals have been modified to account for the 4.2.2 Modifications were necessary to change to a 17 x 17 fuel and the addition of UHI. accommodate 17 x 17 fuel and upper head injection.
4 The thermal shield has been replaced by neutron pads. 4.2.2 This change simplies core support design and reduces flow pressure drop and velocity.
5 The refrigeration system for the ice condenser has eight, 6.2.2 This change provides for an increase in rather than six, 25 ton units. thermal loads over those originally assumed in the PSAR design stage.
6 The air handling system for the ice condenser has 30 units 6.2.2 See Item 5.
rather than 19.
7 The glycol system for the ice condenser has six pumps 6.2.2 See Item 5.
rather than four.
8 Ice baskets, ice basket supports and lattice frames for the 6.2.2 Ice condenser components were re-designed ice condenser have been redesigned. to accommodate design loading conditions beyond those committed in the PSAR.
9 The Annulus Ventilation System has been modified to 6.2.3 This change improves the reliability of the provide a separate system with redundant trains for each system and prevents any postulated unfiltered unit. discharge.
10 The Containment hydrogen purge discharges into the 6.2.5 This feature has been added to satisfy the Annulus Ventilation System. requirements of Regulatory Guide 1.7.
11 Deleted (10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-3 (Page 2 of 7)
Item Change in Design FSAR Reference Reason for Change 12 The Air Return Fan System now includes a Hydrogen 6.6 The hydrogen skimmer eliminates postulated Skimmer System. hydrogen pocketing at high points in the lower containment compartment.
13 On-line testing is provided for Engineered Safety 7.3 This change implements a commitment made Features. in the PSAR.
14 Unit 1 employs a 230 kV system rather than a 525 kV 8.2 This change better serves the needs and system. requirements of the transmission network.
15 The tie to the 44 kV system has been eliminated. 8.2 Use of generator PCB's pro- vides two independent circuits tied to the 230 kV Duke trans- mission system; therefore, no tie to the 44 kV system is necessary.
16 Unit 1 has two half-size, three-phase main step-up 8.3 Two independent circuits from the transformers rather than one full-size, three- phase transmission system require the use of two transformer. Unit 2 has two half-size main step-up main transformers in lieu of only one.
transformer systems instead of one main transformer system.
17 Each unit has generator power circuit breakers on the low 8.3 Generator PCB's provide an isolating means voltage side of each half-sized main step-up transformer. to assure independence of the two incoming, off-site power sources.
18 A filter has been added in front of the demineralizer for 9.1.3 This filter protects the demineralizer.
the Spent Fuel Cooling System.
19 Channels 1A and 2A of the Nuclear Service Water System 9.2.2 The system was revised to comply with the are supplied by a header, and Channels 1B and 2B are single failure criteria.
supplied by a different header rather than each unit having its own header.
20 The refueling water transfer pump has been deleted, and 9.2.5 The residual heat removal pumps are used for two recirculation pumps have been added to the piping in the rapid transfer of refueling canal water.
the Auxiliary Building from the refueling water storage Transfer line tempera- ture will be kept above tank. 70°F by recirculation pump operation.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-3 (Page 3 of 7)
Item Change in Design FSAR Reference Reason for Change 21 The reactor makeup water tank and pump have been 9.3.6 These components are not re- quired to be changed from ANS Safety Class 3 to NNS. ANS Safety Class III.
22 The feed demineralizers and filters have been relocated 9.3.6 Demineralizers removed cations and antions from downstream to upstream of the recycle holdup tanks. and filters removed solids prior to liquid storage in the recycle holdup tanks.
23 A halon system, replacing the CO2 and freon systems, has 9.5.1 The CO2 system was redundant to the halon, been added to the Fire Protection System. i.e., freon system.
24 The four fire pumps have been reduced to three. 9.5.1 Three fire pumps satisfy the requirements of the fire protection system.
25 A supply to the auxiliary feedwater pumps from the 10.4.7 Filtered water is preferred due to the Drinking and Filtered Water System has been added. suspended solids in raw water.
26 The 100 percent capacity, turbine-driven auxiliary 10.4.7 The capacity was incorrectly stated in the feedwater pump has been changed to 200 percent PSAR.
capacity, and the 50 percent capacity, motor-driven pumps have been changed to 100 percent capacity.
27 The reactor coolant drain tank heat exchanger has been 11.2 The liquid may now be cooled while pumping moved to the inlet of the boron recycle holdup tank. directly to the boron recycle holdup tank reactor coolant drain tank.
28 A waste drain tank has been added. 11.2 This tank serves to collect liquids with entrained fis- sion product gases for recycle.
29 The recycle monitor tank has been divided into two tanks. 11.2 Two 5,000 gallon tanks are used rather than one 10,000 gallon tank due to space limitations.
30 A waste evaporator condensate return unit has been added. 11.2 This unit serves to return condensate from the evap- orator package to the con- densate system.
31 (Deleted)
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-3 (Page 4 of 7)
Item Change in Design FSAR Reference Reason for Change 32 Non-code pumps have been used for the residual heat 11.2 Pumps for this service designed and removal and Containment spray pump room sumps, manufactured in accordance with Section 3 of whereas the PSAR specified ASME code pumps. ASME Boiler and Pressure Vessel Code are either unavailable or not suitable for this service.
33 A new fuel storage vault has been added. 9.1.1 The vault provides dry storage for new fuel and increases the overall fuel storage capacity.
34 Steam Generator chemistry changed from phosphate to 10.4.10.2 Problems associated with phosphate volatile amine treatment. chemistry.
35 Condensate polishing demineralizers were added and 10.4.10.2 Change to volatile amine chemistry control steam generator blowdown system design modified. necessitate these modifications.
36 Compressed air systems modified so that service air, 9.3.1 Operational experience and problems at instrument air and breathing air each have their own Oconee Nuclear Station.
compressors.
37 Conventional Waste Water Treatment System added. 9.2.9 Increase flexibility to main- tain station water releases within required limits.
38 Spacing on spent fuel storage racks decreased from 21" to 9.1.2 Increase storage capacity of spent fuel pools.
15 1/2".
39 Auxiliary feedwater lines changed to enter steam 10.4.7.2 Preclude the possibility of water hammer in generators directly instead of tapping into main feedwater steam generator preheater.
lines.
40 Provided for semi-automatic switchover to recircula- tion 6.3.2.2.2 7.3.1.1.2 Concerns an adequacy of operator action to mode. accomplish switchover without some automatic action as a backup.
41 Enclosures around containment sump valve removed. 3.9.2.8.3 No practical enclosure could be developed due to conflicting design requirements.
42 Filter bypasses added to auxiliary building and fuel 9.4.2 Increased flexibility in opera- tion and handling building filtered exhaust systems. maintenance of filters.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-3 (Page 5 of 7)
Item Change in Design FSAR Reference Reason for Change 43 Pipe whip restraint/energy absorber added to top of steam Q110.42 Response New restraint design mitigates effects of a generator enclosures. postulated steam line break in enclosure.
44 Groundwater monitoring system added. 2.4.13.14 System alerts operator to a rise in groundwater level in vicinity of reactor and auxiliary buildings.
45 Containment Air Release and Addition System added. 9.5.12 Provide for containment pres- sure control during operation.
46 Additional heat exchanger added to steam generator 10.4.8.2 Provides for additional sub- cooling of steam blowdown system. generator effluent to preclude flashing in blowdown piping.
47 Containment Pressure Control System added. 7.6.16 Prevents underpressurization of containment by air return fans and Containment Spray System.
48 Manually Actuated Sprinkler Systems were added in 9.5.1 These were added to upgrade the defense-in-Cable Rooms. depth concept for fire protection.
49 Automatic Sprinkler Systems were added in the AFW 9.5.1 See Item 48.
Pump Room.
50 Manual Actuated Sprinkler Systems were added to the 9.5.1 See Item 48.
RCP.
51 A missile wall protecting the Reactor Refueling Water 3.2.1 This structure has been added in order to Storage Tank has been added. provide a qualified source of makeup water.
3.2.2 This satisfies the requirements of Regulatory Guide 1.117.
52 Installed automatic switchover of Auxiliary Feedwater 10.4.7 Prevents damage to pumps due to loss of Pump suction to safety grade source of water. normal suction source.
53 Revised Auxiliary Feedwater System pump suction piping 10.4.7 Prevents unacceptable pump runout and and control valve throttle positions. negative suction header pressure conditions which could result in air ingestion.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-3 (Page 6 of 7)
Item Change in Design FSAR Reference Reason for Change 54 A standby Shutdown System was added to supplement 9.5.1 This system was added to provide an alternate normal shutdown system. means of shutdown that upgraded the defense-in-depth concept for fire protection.
55 High Point Vents added to the Reactor Coolant System. 5.2.2 Facilitates venting of combust- ible gas in accident situations NUREG 0737, Item II-B.1.
56 Inadequate Core Cooling Instruments and Control Room For determining margin to satur- ation of the Indications added. Reactor Coolant NUREG 0737, Item II-F.2.
57 Post Accident Sampling System. Deleted from Licensing Basis by Tech Spec Amendment 199/180 dated 9/17/01.
58 Provided Relief and Safety Valve Safety Grade Indication 5.2 For determining inadvertent or or faulty in the Control Room. actuation of Safety/ Relief valves NUREG 0737, Item II-D.3.
59 Deliberate Operator Action is required to reposition 6.2 Necessary to limit radioactivity escape due to Containment Isolation valves following a reset of the inadvertent operator action NUREG 0737, 7.2 Containment Isolation Signal. Item II-E.4.2.
60 Provided Emergency Power for the Pressurized Chapter 8.0 To maintain Reactor Coolant System pressure Equipment. with a loss of Off-Site power NUREG 0737, Item II-G.
61 Provided Following Additional Accident Monitoring/ Chapter 7.0 To enhance diagnostic ability during accident documentation: conditions NUREG 0737, II-F.1.
- 1. Containment High Range Radiation Monitors
- 2. Continuous Containment pressure indication exceeding
- 3. Containment Water level instrumentation
- 4. Containment Hydrogen Monitoring
- 5. Noble Gas Monitors for Unit vents 62 Provided a Technical Support Center. To provide technical support to the operators during accident conditions NUREG 0737, Item III-A.1.2a.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-3 (Page 7 of 7)
Item Change in Design FSAR Reference Reason for Change 63 Provided a Hydrogen Recombine System. Chapter 6.0 To mitigate possibility of Hydrogen explosion during severe accident conditions.
64 Added a new preheater manifold to the Steam Generators. To alleviate tube damage due to vibrations and thermal stresses experienced with the previous design.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 1-4 (Page 1 of 13)
Table 1-4. Regulatory Guides Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.1 - Net Positive Adopted 6.3.2.14, 6.5.2 Suction Head for Emergency Core Cooling and Containment Heat Removal (Rev. 0).
Reg. Guide 1.2 - Thermal Adopted 5.2.4 Shock to Reactor Pressure Vessels (Rev. 0).
Reg. Guide 1.3 - Not Applicable (BWR)
Reg. Guide 1.4 - Modified (on-site data added) 2.3.4.1, 12.1.6.3, Tables 15-Assumptions Used for 21, Evaluating the Potential -33, -34 and -37 Radiological Consequences of a LOCA for Pressurized Water Reactors (Rev. 1).
Reg. Guide 1.5 - Not Applicable (BWR)
Reg. Guide 1.6 - Adopted 8.1.4, 8.3.1.2.3, 8.3.2.2.5, Independence between 8.3.1.1.7, TS B3.8.4 Redundant Standby (On-site) Power Sources and between their Distribution Systems (Rev. 0).
Reg. Guide 1.7 - Control of Adopted With Comment 6.2.1.1.3.1, 6.2.5.1, 6.2.5.3, Combustible Gas 6.2.6.1, 6.2.6.2.3, 12.1.6.3, Concentrations in TS B3.6.8 Containment Following a Loss of Coolant Accident (Rev. 2).
Reg. Guide 1.8 - Personnel Adopted with comment 17.0, TS 5.3.1 election and Training (Rev. 1-R).
Reg. Guide 1.9 - Selection of Adopted with exceptions 8.3.1.1.7, 8.3.1.2.4, 8.1.4, Diesel Generator Set noted in Table 8-17. 8.3.1.1.10.1, TS B3.8.1, SLC Capacity for Standby Power B16.8.3, Table 8-17 Supplies (Rev. 3).
Reg. Guide 1.10 - Adopted 3.8.1.6, 3.8.3.6, 3.8.4.1.6, Mechanical (Cadweld) Table 3-31 Splices in Rein- forcing Bars of Concrete Containments (Rev. 1).
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 2 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.11 - Instrument Adopted 6.2.4.1, 7.1.2, 7.3.1.1.2 Lines Penetrating Primary Reactor Containment (Rev.
0).
Reg. Guide 1.12 - Instrumen- Adopted (Rev 2) 3.7.4.1, SLC B16.7.2 tation for Earthquakes (Rev.
2).
Reg. Guide 1.13 - Fuel Adopted 3.8.4.1.1, 9.1.2, 9.1.3.2 Storage Facility Design Basis (Rev. 1).
Reg. Guide 1.14 - Reactor Exceptions listed in Section 5.2.6, TS 5.5.7, 3.5.2.1 Coolant Pump Flywheel 5.2.6, 3.5.2.1.
Integrity (Rev. 1).
Reg. Guide 1.15 - Testing of Adopted Table 3-31 Reinforcing Bars for Concrete Structures (Rev. 1).
Reg. Guide 1.16 - Reporting No longer used of Operating Information See TS 5.6 (Rev. 4).
Reg. Guide 1.17 - Protection Adopted 13.7 Against Industrial Sabotage (Rev. 0).
Reg. Guide 1.18 - Structural Not Applicable Acceptance Test for Concrete Primary Reactor Containments.
Reg. Guide 1.19 - Exception listed in Section 3.8.2.2 Nondestruc- tive Examination 3.8.2.
of Primary Containment Welds (Rev. 1).
Reg. Guide 1.20 - Vibration Adopted 3.9.1.3.1 Measurements on Reactor Internals (Rev. 1).
Reg. Guide 1.21 - Measuring Adopted with exceptions to 11.4, 12.3.2.4 and Reporting of Effluents frequency and format in SLC 16.1116.12 from Nuclear Power Plants Appendix B.
(Rev. 1).
Reg. Guide 1.22 - Periodic Adopted 7.1.2.1, 7.3.2.2.5, Testing of Protection System 8.3.1.1.10.2 Actuation Functions (Rev. 0).
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 3 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.23 - Onsite Adopted 2.3.3.4, 2.3.6, SLC B16.7.3 Meteorological Programs (Rev. 0).
Reg. Guide 1.24 - Modified (on-site data Assumptions Used for added).
Evaluating the Potential Radiological Conse- quences of a Pressurized Water Reactor Radioactive Gas Storage Tank Failure (Rev.
0).
Reg. Guide 1.25 - Modified (on-site data 15.10.3, Table 15-39 Assumptions Used for added). Exceptions listed in Evaluating the Potential Section 15.7.4.
Radiological Consequences of a Fuel Handling Accident (Rev. 0).
Reg. Guide 1.26 - Quality Modified. Exceptions listed in 3.2.2, 5.2.8.1, 11.2.3.1 and Group Classifications and Section 3.2.2. 17.0 Standards (Rev. 3).
Reg. Guide 1.27 - Ultimate Adopted. Exceptions listed in 9.2.5.3.1 Heat Sink (Rev. 1). Section 9.2.5 Reg. Guide 1.28 - Quality See Quality Assurance 17.0 Assurance Program Program Description Topical Requirements (Rev. 2). Report DUKE-QAPD-001 Reg. Guide 1.29 - Seismic Exceptions listed in Section 3.2.4.2, 5.2.5.7, 9.1.1.1 and Design Classification (Rev. 3.2.4.2. 17.0 3).
Reg. Guide 1.30 - Quality See DUKE-QAPD-001 3.11.2.1.4, 17.0 Assurance Requirements for the Installation, Inspection and Testing of Instrumentation and Electrical Equipment (Rev. 0).
Reg. Guide 1.31 - Control of Exceptions listed in Section 5.2.5.7 Stainless Steel Welding Rev. 5.2.5.7.
3).
Reg. Guide 1.32 - Use of Adopted 8.1.4, 8.2.2.1, 8.3.1.1.4 IEEE STD. 308-1971, 8.3.1.2.5, 8.3.2.2.2, , TS Criteria for Class IE Electric B3.4.11, TS B3.8.4 Systems for Nuclear Power Generating Stations (Rev.
0).
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 4 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.33 - Quality See DUKE-QAPD-001 17.0, 13.5 Assurance Program Requirements (Operation)
(Rev. 2).
Reg. Guide 1.34 - Control of Electroslag welding is not Electroslag Weld Materials used on core support struc-(Rev. 0). tures or Class 1 and Class 2 vessels and components.
Reg. Guide 1.35 - Inservice Not Applicable Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures.
Reg. Guide 1.36 - Adopted 5.2.3.3, 17.0 Nonmetallic Thermal Insulation for Austenitic Stainless Steel (Rev. 0).
Reg. Guide 1.37 - Quality See DUKE-QAPD-001 5.2.5, 17.0 Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants (Rev. 0).
Reg. Guide 1.38 - Quality See DUKE-QAPD-001 5.2.5, 17.0 Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water Cooled Nuclear Power Plants (Rev. 2).
Reg. Guide 1.39 - See DUKE-QAPD-001 17.0 Housekeeping Requirements for Water Cooled Nuclear Power Plants (Rev. 2).
Reg. Guide 1.40 - Adopted 3.11.2.1.4 Qualification Tests of Continuous - Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants (Rev. 0).
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 5 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.41 - Adopted 14.4.8 Preoperational Testing of Redundant On-site Electric Power Systems to Verify Proper Load Group Assignments (Rev. 0).
Reg. Guide 1.42 - Interim N/A Licensing Policy on as low as practicable for Gaseous Radio- iodine Releases from Light Water-Cooled Nuclear Power Reactors (Rev. 1).
Reg. Guide 1.43 - Control of Adopted Stainless Steel Weld Cladding of Low-Alloy Steel Components (Rev. 0).
Reg. Guide 1.44 - Control of Exceptions listed in Section 5.2.5.5 the Use of Sensitized 5.2.5.5 Stainless Steel (Rev. 0).
Reg. Guide 1.45 - Reactor Adopted With Comment 5.2.7.1, Table 5-30, Table 5-Coolant Pressure Boundary 55, 11.4.2.2.4, TS B3.4.13, Leakage Detection Systems TS B3.4.15 (Rev. 0).
Reg. Guide 1.46 - Protection Duke does not fully comply 3.6.1.2, Table 3-20 Against Pipe Whip Inside with Regulatory Guide 1.46.
Containment (Rev. 0). Westinghouse position given in WCAP 8082.
Reg. Guide 1.47 - Bypassed Adopted 7.2.2.3, 7.3.2.2, 7.6.2.2.11, and Inoperable Status 7.6.4.2.11, 7.8.2 Indication for Nuclear Power Plant Safety Systems (Rev.
0).
Reg. Guide 1.48 - Design Adopted With Comment 3.9.2.4 Limits and Loading Combinations for Seismic Category 1 Fluid System Components (Rev. 0).
Reg. Guide 1.49 - Power Adopted Levels of Water-Cooled Nuclear Power Plants (Rev.
1).
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 6 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.50 - Control of Exceptions listed in Section 5.2.3.5 Preheat Temperature for 5.2.3.5.
Welding of Low-Alloy Steel (Rev. 0).
Reg. Guide 1.51 - Inservice N/A Inspection of ASME Code Class 2 of 3 Nuclear Power Plant Components (Rev. 0).
Reg. Guide 1.52 - Design, Adopted With Comment 6.2.3.2, 9.4.2.3, Table 6-110, Testing, and Maintenance 9-37, -38, and -40, TS Criteria for Atmosphere B3.6.10, TS B3.7.9, TS Cleanup System Air Filtration B3.7.11, TS B3.7.12, TS and Absorption Units of Light- B3.9.4, TS 5.5.11 Water Cooled Nuclear Power Plants (Rev. 0). (Rev. 2 adopted for testing purposes only)
Reg. Guide 1.53 - Application Adopted of the Single-Failure Criterion to Nuclear Power Plant Protection System (Rev. 0).
Reg. Guide 1.54 - Quality Adopted for civil work except 3.8.2.4, 17.0 Assurance Requirements for that the provisions of ANSI Protective Coatings Applied N45.2-1971 are not applied.
to Water-Cooled Nuclear Mechanical and electrical Power Plants (Rev. 0). equipment does not comply since material was ordered prior to issuance of the guide.
Reg. Guide 1.55 - Concrete Adopted Placement in Category 1 Structures (Rev. 0).
Reg. Guide 1.56 - Not Applicable (BWR)
Maintenance of Water Purity in Boiling Water Reactors.
Reg. Guide 1.57 - Design Duke does not comply 3.8.2.4 Limits and Loading Combinations for Metal Primary Reactor Contain-ment System Components (Rev. 0).
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 7 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.58 - See DUKE-QAPD-001 17.0 Qualifications of Nuclear Power Plant Inspection, Examination, and Testing Personnel (Rev. 1).
Reg. Guide 1.59 - Design Exceptions listed in Section 3.4 Basis Floods for Nuclear 3.4.
Power Plants (Rev. 2).
Reg. Guide 1.60 - Design Duke does not comply.
Response Spectra for Seismic Design of Nuclear Power Plants (Rev. 1).
Reg. Guide 1.61 - Damping Exceptions listed in Section 3.7.1.3, 5.2.1.10 Values for Seismic Design of 3.7.1.3.
Nuclear Power Plants (Rev.
0).
Reg. Guide 1.62 - Manual Adopted Initia- tion of Protective Actions (Rev. 0).
Reg. Guide 1.63 - Electric Exceptions listed in Section 3.8.2.1, 8.3.1.2.7.7, Penetration Assemblies in 8.3.1.2. 3.11.2.1.4 Containment Structures for Water-Cooled Nuclear Power Plants (Rev. 3).
Reg. Guide 1.64 - Quality See DUKE-QAPD-001 17.0 Assurance Requirements for the Design of Nuclear Power Plants (Rev. 2).
Reg. Guide 1.65 - Materials Exceptions listed in Section 5.4.2.2 and Inspections for Reactor 5.4.2.2.
Vessel Closure Studs (Rev.
1).
Reg. Guide 1.66 - Duke complies with the Nondestruc- tive Examination ASME Code Governing of Tubular Products (Rev. 0). purchase of the materials.
Reg. Guide 1.67 - Installation Exceptions listed in Section 3.9.2.5.1 of Overpressure Protection 3.9.2.5.
Devices (Rev. 0).
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 8 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.68 - Adopted 14.0, TS B3.1.8 Preoperational and Initial Startup Test Programs for Water-Cooled Power Reactors (Rev. 0).
Reg. Guide 1.68.2 - Initial Partial compliance 4/6/79 letter to NRC Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants (Rev. 1)
Reg. Guide 1.68.2 - Initial Partial compliance 4/6/79 letter to NRC Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants (Rev. 1)
Reg. Guide 1.69 - Concrete Adopted Radiation Shields for Nuclear Power Plants (Rev. 0).
Reg. Guide 1.70 - Standard Adopted (Rev 1) 15.0 Format and Content of Safety Partial (Rev 3); Exceptions 5.2.1.5 Analysis Reports of Nuclear listed in Section 5.2.1.5 Power Plants (Rev. 1 and 3).
Reg. Guide 1.71 - Welder Exceptions listed in Section 5.2.3.6 Qualification for Areas of 5.2.3.6 Limited Accessibility (Rev. 0).
Reg. Guide 1.72 - Spray Not Applicable.
Pond Plastic Piping (Rev. 0).
Reg. Guide 1.73 - Adopted With Comment 3.11.2.1.4 Qualification Tests of Electric Valve Operators Installed inside the Containment of Nuclear Power Plants (Rev.
0).
Reg. Guide 1.74 - Quality See DUKE-QAPD-001 17.0 Assurance Terms and Definitions (Rev. 0).
Reg. Guide 1.75 - Physical Not applicable to McGuire. 1.8.27, 8.3.1.2.7.5 Inde- pendence of Electric Safety Evaluation Report for Systems (Rev. 1). CP issued prior to 2/1/74.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 9 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.76 - Design Exceptions listed in Section 3.3.2.1 Basis Tornado for Nuclear 3.3.2.1.
Power Plants (Rev. 0).
Reg. Guide 1.82 - Water Exceptions listed in Section 6.5.2 Sources For Long Term 6.5.2.
Recirculation Cooling Following A Loss-of-Coolant Accident (Rev. 0).
Reg. Guide 1.83 - Inservice Adopted With Comment TS 5.5.9 Inspection of Pressurized Water Reactor Steam Generator Tubes (Rev. 1).
Reg. Guide 1.84 - Design Adopted With Comment 5.2.1.4 and Fabrication Code Case Acceptability - ASME Section III, Division 1 Reg. Guide 1.85 - Materials Adopted With Comment 5.2.1.4 Code Case Acceptability -
ASME Section III, Division 1 Reg. Guide 1.88 - Collection, See DUKE-QAPD-001 17.0 Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records, Rev. 2 (Withdrawn)
Reg. Guide 1.89 - Adopted for replacement 3.11.2.1.4 Environmental Qualification equipment of Certain Electric Equipment Important to Safety for Nuclear Power Plants. (Rev.
1)
Reg. Guide 1.91 - Adopted Evaluations of Explosions Postualted To Occur on Transportation Routes Near Nuclear Power Plants (Rev.
1)
Reg. Guide 1.92 - Combining Partial compliance 3.7.3.4.2 Modal Responses and Spatial Components in Seismic Response Analysis Reg, Guide 1.93 - Availability Adopted TS B3.8.1, TS B3.8.4, TS of Electric Power Sources B3.8.9 (Rev.0 )
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 10 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.94 - Quality See DUKE-QAPD-001 17.0 Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants (Rev. 1)
Reg. Guide 1.97 - Adopted With Comment 1.8.27, 1.11, 7.5.4.2, Instrumentation for Light- 17.1.3.1, TS B3.3.3 Water-Cooled Nuclear Power Plants To Assess Plant and Environs Conditions During and Following an Accident (Rev. 2)
Reg. Guide 1.99 - Radiation Adopted With Comment 5.2.4.3, TS 3.4.3 Embrittlement of Reactor Vessel Materials (Rev. 2)
Reg. Guide 1.101 - Adopted Emergency Plan Emergency Planning and Preparedness for Nuclear Power Reactors (Rev. 3)
Reg. Guide 1.102 - Flood Conforms 8/31/79 letter to NRC Protection for Nuclear Power Plants (Rev. 1)
Reg. Guide 1.108 - Periodic Partial compliance SLC B16.8.3 Testing of Diesel Generators Used as Onsite Electric Power Systems at Nuclear Power Plants, Rev. 1 (Withdrawn)
Reg. Guide 1.109 - Adopted 11.2.9, 11.3.9, 11.6.2, 15.9.4, Calculation of Annual Doses Table 15-17, SLC B16.11 to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I (Rev. 1)
Reg. Guide 1.111 - Cost- Adopted SLC B16.11 Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 11 of 13)
Regulatory Guide Document/Title Disposition Reference Section Power Reactors, Rev. 1 (for Comment)
Reg. Guide 1.112 - Adopted With Comment 11.3.6 Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors (Rev 0-R)
Reg. Guide 1.113 - Adopted With Comment SLC B16.11.3 Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, (Rev. 1)
Reg. Guide 1.114 - Adopted 4/6/79 letter to NRC Guidance to Operators at the Controls and to Senior Operators in the Control Room of a Nuclear Power Unit (Rev. 2)
Reg. Guide 1.115 - Rev 1 Adopted 4/6/79 letter to NRC, 3.5.1.2, Protection Against Low- 3.5.2.7, 10.2.3 Trajectory Turbine Missiles Reg. Guide 1.116 - Quality See DUKE-QAPD-001 17.0 Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems (Rev. 0-R)
Reg. Guide 1.118 - Periodic Adopted 1.8.27 Testing of Electric Power and Protection Systems (Rev. 2)
Reg. Guide 1.121 - Bases for 5.2.1.10 Plugging Degraded PWR Steam Generator Tubes (for Comment)
Reg. Guide 1.122 - Partial use 3/2/81 letter to NRC Development of Floor Design Response Spectra for Seismic Design of Floor -
Supported Equipment or Components (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 12 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.123 - Quality See DUKE-QAPD-001 17.0 Assurance Requirements for Conrol of Procurement of Items and Services for Nuclear Power Plants, Rev. 1 (Withdrawn)
Reg. Guide 1.127 - Adopted With Comment 4/06/79 letter to NRC Inspection of Water-Control Structures Associated with Nuclear Power Plants (Rev.1)
Deleted Per 2005 Update Deleted Per 2005 Update Reg. Guide 1.131 - N/A 3.11.2.1.4 Qualification Tests of Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants (for Comment)
Reg. Guide 1.133 - Loose- Adopted With Comment 7.7.1.12, SLC B16.7.4 Part Detection Program for the Primary System of Light-Water-Cooled Reactors (Rev.
1)
Reg. Guide 1.137 - Fuel-Oil Adopted With Exceptions Table 8-18 Systems for Standby Diesel Noted in Table 8-18 Generators (Rev. 1)
Reg. Guide 1.143 - Design Adopted 17.0 Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants (Rev. 1)
Reg. Guide 1.144 - Auditing See DUKE-QAPD-001 17.0 of Quality Assurance Programs for Nuclear Power Plants, Rev. 1 (Withdrawn)
Reg. Guide 1.146 - See DUKE-QAPD-001 17.0 Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (Rev. 0)
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-4 (Page 13 of 13)
Regulatory Guide Document/Title Disposition Reference Section Reg. Guide 1.147 - Inservice Adopted Inspection Code Case Acceptability - ASME Section XI, Division 1 Reg. Guide 1.149 -Nuclear Adopted 1/4/91 letter to NRC Power Plant Simulation Facilitites for Use in Operator License Examinations (Rev.
1)
Reg. Guide 1.150 - Adopted With Comment ISI Program Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations (Rev. 1)
Reg. Guide 1.152 - Criteria See DUKE-QAPD-001 17.0 for Digital Computers in Safety Systems of Nuclear Power Plants (Rev. 0)
Reg. Guide 1.155 - Station Adopted 4/17/89 letter to NRC Blackout (Rev. 0)
Reg. Guide 1.163 - Adopted With Comment TS 5.5.2, 1/13/97 letter to Performance Based NRC Containment Leak - Test Program Reg. Guide 1.181 - Content Adopted NA of the Updated Final Safety Analysis Report in accordance with 10 CFR 50.71(e) (September 1999)
Reg. Guide 1.183 - Adopted for FHA (except 15.7.4.1.2, 15.7.4.2.2, Alternative Radiological tornado missile accident) 15.7.4.3.2, Tables 15-35, TS Source Terms for Evaluating B3.7.13 and TS B3.9.7 Design Basis Accidents at Nuclear Power Reactors (Rev. 0)
Reg. Guide 1.205 Risk- Adopted 9.5.1 Informed Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants (December 2009)
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-5 (Page 1 of 5)
Table 1-5. Piping and Instrumentation Diagrams Rev.
System Flow Diagram Figure No.
Reactor Coolant System MCSF-1553.NC-01 5-1 2 Residual Heat Removal System MCSF-1561.ND-01 5-28 4 Symbols for Flow Diagrams MCFD-1550-01.00 6-1 (1) 9 Symbols for Flow Diagrams MCFD-1550-01.01 6-1 (2) 1 Symbols for Flow Diagrams MCFD-1550-02.00 6-1 (3) 3 Symbols and System Abbreviations for Flow MCFD-1550-03.00 6-2 4 Diagrams Index for Flow Diagrams MCFD-1550-04.00 6-3 19 Cont. Air Return Exchange and Hydrogen MCSF-1557.VX-01 6-107 2 Skimmer Annulus Ventilation System MCSF-1564.VE-01 6-169 1 Safety Injection System MCSF-1562.NI-01 6-176 4 Safety Injection System MCSF-1562.NI-02 6-177 1 Control Area Chilled Water System MCSF-1618.YC-01 6-188 2 Control Area Chilled Water System MCSF-1618.YC-02 6-189 2 Control Area Chilled Water System MCFD-1618-03.00 6-190 9 Control Area Ventilation System MCSF-1578.VC-01 6-191 4 Containment Spray System MCSF-1563.NS-01 6-194 5 Spent Fuel Cooling System MCSF-1570.KF-01 9-13 2 Recirculated Cooling Water System MCFD-1600-01.00 9-25 3 Recirculated Cooling Water System MCFD-1600-01.01 9-26 6 Recirculated Cooling Water System MCFD-1600-02.00 9-27 4 Recirculated Cooling Water System MCFD-1600-02.01 9-28 8 MCFD-2600-02.01 9-28 7 Recirculated Cooling Water System MCFD-1600-02.02 9-29 2 Recirculated Cooling Water System MCFD-1600-03.00 9-30 4 Nuclear Service Water System MCSF-1574.RN-01 9-31 8 Conventional Low Pressure Service Water MCFD-1575-01.00 9-54 28 System Conventional Low Pressure Service Water MCFD-1575-02.00 9-55 3 System (22 APR 2017)
McGuire Nuclear Station UFSAR Table 1-5 (Page 2 of 5)
Rev.
System Flow Diagram Figure No.
Conventional Low Pressure Service Water MCFD-1575-03.00 9-56 16 System Component Cooling System MCSF-1573.KC-01 9-57 2 Refueling Water System MCSF-1571.FW-01 9-65 5 Filtered Water System MCFD-1601-01.00 9-66 9 Filtered Water System MCFD-1601-01.01 9-67 5 Filtered Water System MCFD-1601-01.02 9-68 7 Makeup Demineralized Water System MCFD-1601-02.00 9-69 11 Makeup Demineralized Water System MCFD-1601-02.01 9-70 7 Makeup Demineralized Water System MCFD-1601-02.02 9-71 9 Makeup Demineralized Water System MCFD-1601-02.03 9-72 14 Makeup Demineralized Water System MCFD-1601-02.04 9-73 8 Makeup Demineralized Water System MCFD-1601-02.05 9-74 15 Makeup Demineralized Water System MCFD-1601-02.06 9-75 (1 11 of 2)
Makeup Demineralized Water System MCFD-1601-02-07 9-75 (2 5 of 2)
Drinking Water System MCFD-1601-03.00 9-76 6 Conventional Waste Water Treatment MCSF-1583.WC-01 9-77 8 System Instrument Air System MCSF-1605.VI-01 9-79 10 Station Air System MCSF-1605.VS-01 9-83 0 Nuclear Sampling System MCSF-1572.NM-01 9-90 3 Nuclear Sampling System MCSF-1572.NM-02 9-91 1 Nuclear Sampling System MCSF-1572-NM-03 9-92 2 Chemical and Volume Control System MCSF-1554.NV-02 9-96 1 Chemical and Volume Control System MCSF-1554.NV-01 9-98 8 Boron Thermal Regeneration System MCSF-1555.NR-01 9-107 0 Boron Thermal Regeneration System MCSF-1555.NR.02 9-108 0 Deleted Per 2012 Update Boron Recycle System MCSF-1556.NB-01 9-110 1 Auxiliary Building Ventilation System MCSF-1577.VA-01 9-117 3 Auxiliary Building Ventilation System MCSF-1577.VA-02 9-118 1 (22 APR 2017)
McGuire Nuclear Station UFSAR Table 1-5 (Page 3 of 5)
Rev.
System Flow Diagram Figure No.
Auxiliary Building Ventilation System MCSF-1577.VA-03 9-119 2 (1)
Auxiliary Building Ventilation System MCSF-1577.VA-04 9-119 0 (2)
Turbine Building Ventilation System MC-1614-01.00 9-120 5 Conventional Purge and Ventilation System MCSF-1576.VP-01 9-121 2 Diesel Building Ventilation System MCSF-1579.VD-01 9-123 1 Fire Protection System MCSF-1599.RF-01 9-124 5 Fire Protection System MCSF-1599.RF-02 9-125 0 Diesel Generator Engine 1A Fuel Oil MCSF-1609.FD-01 9-139 1 System Diesel Generator Engine Cooling Water MCSF-1609.KD-01 9-141 1 System Diesel Generator Engine Starting Air System MCSF-1609.VG-01 9-143 4 Diesel Generator Engine Lube Oil System MCSF-1609.LD-01 9-144 1 Groundwater Drainage System MCSF-1581.WZ-01 9-146 1 Diesel Generator Engine Crankcase Vacuum MCSF-1609.ZD-01 9-147 1 System Diesel Generator Room Sump Pump System MCSF-1609.WN-01 9-148 2 Diesel Generator Engine Air Intake & MCSF-1609-VN.01 9-149 1 Exhaust System Containment Air Release and Addition MCSF-1585.VQ-01 9-150 2 System Moisture Separator Reheater Bleed System MCFD-1594-01.00 10-3 18 Moisture Separator Reheater Bleed System MCFD-1594-01.01 10-4 12 Heater Bleed Steam System MCFD-1594-02.00 10-5 9 Heater Bleed Steam System MCFD-1594-02.01 10-6 3 Heater Bleed Steam System MCFD-1594-02.02 10-7 2 Heater Bleed Steam System MCFD-1594-02.03 10-8 3 Heater Bleed Steam System MCFD-1594-02.04 10-9 3 Main Steam System Main Steam Vent to MCSF-1593.SM-01 10-11 4 Atmosphere System Main Steam Supply to Aux. Equip. System MCSF-1593.SA-01 10-13 1 Turbine Exhaust System (22 APR 2017)
McGuire Nuclear Station UFSAR Table 1-5 (Page 4 of 5)
Rev.
System Flow Diagram Figure No.
Steam Supply to FDWP Turbine System MCFD-1593-02.00 10-16 9 Turbine Exhaust System Main Steam Bypass to Condenser System MCFD-1593-02.01 10-17 6 Main Condenser 1A Connections MCFD-1612-01.00 10-18 5 Condensate System Main Condenser 1B Connections MCFD-1612-02.00 10-19 2 Condensate System Main Condenser 1C Connections MCFD-1612-03.00 10-20 4 Condensate System FDW Pump Turbine Condenser 1A & 1B MCFD-1612-04.00 10-21 2 Connections Main Vacuum System MCFD-1598-01.00 10-22 4 Vacuum Priming System MCFD-1598-01.01 10-23 7 Condenser Steam Air Ejector System MCFD-1598-01.02 10-24 7 Condenser Steam Air Ejector System MCFD-1598-01.03 10-25 10 Main Turbine Leakoff and Steam Seal MCFD-1608-01.00 10-26 12 System FDW Pump Turbine Steam Seal System MCFD-1608-02.00 10-27 3 Condenser Circulating Water System MCFD-1604-01.00 10-28 15 Containment Ventilation Cooling Water MCSF-1604.RV-01 10-29 4 System Condensate System MCFD-1590-01.00 10-37 9 Condensate System MCFD-1590-01.01 10-38 6 Condensate System MCFD-1590-01.02 10-39 4 Condensate System MCFD-1590-01.03 10-40 5 Condensate System MCFD-1590-01.04 10-41 6 Condensate System MCFD-1590-01.05 10-42 9 Condensate System MCFD-1590-01.06 10- 4 43(1)
Condensate System MCFD-1590-01.07 10- 0 43(2)
Condensate Storage System MCFD-1590-02.00 10-44 12 Feedwater System MCSF-1591.CF-01 10-45 2 Auxiliary Feedwater System MCSF-1592.CA-01 10-47 9 System Generator Blowdown System MCSF-1580.BB-01 10-51 4 (22 APR 2017)
McGuire Nuclear Station UFSAR Table 1-5 (Page 5 of 5)
Rev.
System Flow Diagram Figure No.
Deleted Per 2002 Update Deleted Per 2002 Update Heater Drain System MCFD-1596-01.00 10-54 5 Heater Drain System MCFD-1596-01-01 10-55 9 Heater Drain System MCFD-1596-02.00 10-56 3 Heater Drain System MCFD-1596-02.01 10-57 7 Moisture Separator Reheater Drain System MCFD-1596-03.00 10-58 5 Moisture Separator Reheater Drain System MCFD-1596-03.01 10-59 5 Moisture Separator Reheater Drain System MCFD-1596-04.00 10-60 7 Moisture Separator Reheater Drain System MCFD-1596-04.01 10-61 3 Moisture Separator Reheater Drain System MCFD-1596-05.00 10-62 6 Moisture Separator Reheater Drain System MCFD-1596-05.01 10-63 3 Liquid Waste Recycle System MCSF-1565.WL-01 11-1 2 Equipment Decontamination System MCFD-1568-01.00 11-11 5 Waste Gas System MCSF-1567.WG-01 11-15 2 Waste Gas System MCSF-1567.WG-02 11-18 1 Nuclear Solid Waste Disposal System MCSF-1566.WS-01 11-22 2 (22 APR 2017)
McGuire Nuclear Station UFSAR Table 1-6 (Page 1 of 42)
Table 1-6. Regulatory Guide 1.97, Rev. 2 Review Format for Comparison Table B-16 Variable: This is the variable as listed in Table 2 of RG 1.97, Rev. 2.
C-15 (The Duke variable name may be shown parenthetically.)
This gives the Table 2 of RG 1.97, Rev. 2 variable type and sequence number. Type A variables are those listed in Section 1.11.5.1.1 of the UFSAR.
Range: This is the Table 2 of RG 1.97, Rev. 2 listed range.
RG1.97 This is the Table 2 of RG 1.97, Rev. 2 listed category.
Recommended Category:
DPC Category: This is the Duke Energy position for the variable's category for McGuire Nuclear Station.
Existing Design: This a description of the present McGuire design for the instrumentation.
Compliance: This a statement concerning compliance to Dukes interpretation of the recommendations of RG 1.97, Rev. 2.
Display: This lists the Control Room indications available to the operator that Duke Power takes credit for in meeting the recommendations of RG 1.97, Rev. 2. Other control room indications may exist for the recommendations of RG 1.97, Rev. 2.
Position: This is a statement regarding the instruments adequacy for the intended monitoring function and lists any necessary changes to the existing design.
A-1, Variable: RCS Pressure B-7, B-11, C-4, C-9 Range: 0 to 3000 psig RG1.97 1 Recommended Category:
DPC Category: 1 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 2 of 42)
Existing Design: McGuire has two redundant, QA Condition 1 channels of Wide Range RCS pressure instrumentation. Each transmitter feeds a different channel of the PCS and is powered by that channel's associated Class 1E buss. QA Condition 1 indication is provided by two qualified redundant displays in the Control Room. The indicated range is 0 to 3000 psig. The two redundant QA1 channels of Wide Range RCS Pressure instrumentation also provide inputs to two additional indicators on the Main Control Board. These two indicators do not meet all of the Design and Qualification Criteria for Category 1 instrumentation. Redundant/Diverse indication is provided by control grade RCS pressure instrumentation provided for the standby shutdown facility, as well as the QA Condition 1 pressurizer pressure instrumentation.
Environmental qualification is described in the McGuire Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification is described in the McGuire FSAR, Section 3.10 and Section 1.11.5.1.3.11.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Two qualified redundant displays in the Control Room (ICCM only).
One channel recorded.
Position: The recorded channel was isolated from the plant computer by NSM MG-12349 and MG-22349. The instrumentation is adequate for the intended monitoring function.
A-2, Variable: Core Exit Temperature B-8, C-1 Range: 32°F to 2300°F RG1.97 1 Recommended Category:
DPC Category: 1 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 3 of 42)
Existing Design: The QA Condition 1 Core-Exit Thermocouple System for accident monitoring consists of two qualified redundant channels of 20 thermocouples each. The primary displays associated with the thermocouples consist of two qualified redundant plasma graphic displays. The backup display is from the plant computer work station. Inputs to the plant computer are through qualified Class 1E isolation devices.
Power for the Class 1E portion of the system is from Class 1E buses, and power for the non-safety portion is from a highly reliable regulated control bus. Redundancy/diversity is provided by the Hot and Cold Leg RCS temperature instrumentation. Environmental qualification for the Class 1E portion is per the McGuire Nuclear Station FSAR, Section 3.11 and the NUREG-0588 submittal. Seismic qualification is described in the McGuire FSAR, Section 3.10 The existing incore thermocouples are environmentally and seismically qualified as allowed by NUREG 0737 II.F.2 Attachment 1.
The plasma displays and the plant computer are installed in a mild environment. The range of the system is 32°F to 2300°F.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Primary displays are the two qualified redundant plasma graphic displays in the Control Room. Backup display is from the plant computer CRTs in the Control Room.
Position: The instrumentation is adequate for the intended monitoring function.
A-3, Variable: RCS Hot Leg Water Temperature B-5 Range: 50°F to 750°F RG1.97 1 Recommended Category:
DPC Category: 1 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 4 of 42)
Existing Design: Each of the four reactor coolant loops employs a QA Condition 1 Hot Leg Water Temperature measurement (Th).
Two of the Th instruments feed into one RVLIS channel and are powered from the associated Class 1E buss. The other two Th instruments feed into a redundant PCS channel and are powered by that channel's Class 1E buss. The control board display devices (recorders) have dedicated output isolation devices. The indicated range is 0°F to 700°F. The environmental qualification of this instrumentation is described in the McGuire Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. The seismic qualification is described in the McGuire FSAR, Section 3.10 and Section 1.11.5.1.3.11 Redundancy/diversity is provided by monitoring Th on all four loops along with monitoring of Tc on all four loops and monitoring of incore thermocouples.
Compliance: The existing design does not fully comply with the recommendation of RG 1.97, Rev. 2 because the range does not conform to RG 1.97, Rev. 2 range of 50°F to 750°F.
Display: Two Control Room Indicators (ICCM)
Four loops recorded Position: The range of the installed instrumentation is adequate for the intended monitoring function. No range change is required as the installed range is adequate for a Westinghouse NSSS System. Also note, the present range meets the recommendation of RG 1.97, Rev. 3. The recorders for this variable were isolated from the plant computer by NSM MG-12349 and MG-22349.
A-4, Variable: RCS Cold Leg Water Temperature B-4, B-6 Range: 50°F to 750°F RG1.97 1 Recommended Category:
DPC Category: 1 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 5 of 42)
Existing Design: Each of the four reactor coolant loops employs a QA Condition 1 Cold Leg Water Temperature measurement (Tc).
All four Tc's feed into the same qualified channel of the PCS and are powered by that channel's Class 1E buss. The indicated range is 0°F to 700°F. Environmental qualification is described in the McGuire Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification is described in the McGuire FSAR, Section 3.10 and Section 1.11.5.1.3.11. Additional redundancy/diversity is provided by the Hot Leg Water Temperature (Th) instruments, the incore thermocouples, and steam pressure indication.
Compliance: The existing design is not in full compliance with RG 1.97, Rev. 2 in the following areas: 1) the instrumentation is not totally redundant, and 2) the range does not conform to RG 1.97, Rev. 2 recommendations.
Display: Four loops recorded on two recorders Position: Redundancy/diversity is provided by the Hot Leg RTDs, the incore thermocouples and steam pressure instrumentation.
No range change is required as the installed range is adequate for Westinghouse NSSS Systems. Also note, the present range meets the recommendation of RG 1.97, Rev.
3.
A-5, Variable: Pressurizer Level D-11 Range: Bottom to Top RG1.97 1 Recommended Category:
DPC Category: 1 Existing Design: This station has three redundant, QA Condition 1 channels of pressurizer level instrumentation. Each transmitter feeds a different channel of the PCS and is powered by that channel's associated Class 1E buss. Each indicator channel and associated input to the recorder have PCS output isolation devices. The indicated range is 0% to 100% corresponding to an approximate volume of 5% to 95%. Environmental qualification is described in the McGuire Nuclear Station FSAR, Section 3.11 and in the NUREG 0588 submittal.
Seismic qualification is described in the McGuire FSAR, Section 3.10 and Section 1.11.5.1.3.11.
Compliance: The range of the instrumentation is slightly less than the recommendation of RG 1.97, Rev. 2.
Display: Three Control Room indicators (one per channel)
One channel recorded (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 6 of 42)
Position: The installed range of the instrumentation is consistent with Westinghouse NSSS requirements and Duke considers this instrumentation range to be adequate for the intended monitoring function.
A-6, Variable: Degrees of Subcooling B-10 Range: 200°F Subcooling to 35°F Superheat RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: This variable is a computer (ICCM and plant computer) calculated value using various inputs from the Primary System. A graphic display over the required range gives the operator a representation of primary system conditions compared to various curves of importance (saturation, NDT, etc.). The ICCM is a fully qualified, redundant, Class 1E display. The plant computer is powered by highly reliable battery backed control power. The computer processing and display are located in a mild environment. Primary inputs to this graphic display are provided from QA Condition 1 instruments which have been isolated for input to the plant computer. Additional inputs of lesser qualification are used, when available and within valid ranges, to provide additional accuracy. A procedure to manually calculate sub-cooling margin, using these instruments for information, exists as a backup to the graphic displays.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Inadequate Core Cooling Monitor (ICCM)
Control Room - Computer graphic on demand Position: The installed instrumentation is adequate for the intended monitoring function.
A-7 Variable: Steam Generator Narrow Range Level Range: 0-100%
RG1.97 1 Recommended Category:
DPC Category: 1 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 7 of 42)
Existing Design: The station has four redundant, QA Condition 1 channels of Steam Generator Narrow Range Level per Steam Generator.
Instrumentation is powered by Class 1E busses. Each indicator channel and associated input to the recorder have PCS output isolation devices. The indicated range is 0 to 100% corresponding to 427 " above the tube-sheet to the separators (or, approximately 70 to 100% of the wide range scale). Environmental qualification is described in the McGuire Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification is described in the McGuire FSAR, Section 3.10 and Section 1.11.5.1.3.11.
Compliance: The instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev.2 as clarified in McGuire FSAR Section 1.11.5.
Display: All channels are indicated in the Control Room (16 indicators)
Four channels recorded (one per Steam Generator).
Position: The recorder and unisolated indicator channels were isolated from the plant computer by NSM MG-12349 and MG-22349.
A-8, Variable: Steam Line Pressure D-17 Range: Atmospheric pressure to 20% above lowest safety valve setting.
RG.197 1 Recommended Category:
DPC Category: 1 Existing Design: Each steam generator has two redundant, QA Condition 1 channels of steam generator pressure instrumentation. Each transmitter feeds a different channel of the PCS and is powered by that channel's Class 1E buss. The indicated range is 0 to 1300 psig corresponding to 11% above the lowest safety valve setting and 6% above the highest safety valve setting. The instrumentation is located in a mild environment. Seismic qualification is described in the McGuire FSAR, Section 3.10 and Section 1.11.5.1.3.11.
Compliance: The range is not in compliance with the recommendation of RG 1.97 Rev. 2.
Display: Per Steam Generator:
Two Control Room indicators One channel recorded Position: Maximum system pressure during the worst postulated loss of heat sink accident is 1304 psig. Thus the range of the installed instrumentation is adequate for the McGuire design.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 8 of 42)
A-9, Variable: Refueling Water Storage Tank Level D-8 Range: Top to Bottom RG 1.97 1 Recommended Category:
DPC Category: 1 Existing Design: The instrumentation for this variable provides continuous display of refueling water storage tank level. Three separate, QA Condition 1 channels provide redundant indication of tank level from 0 to 500 inches. Each channel is powered by a separate Class 1E bus. These instruments are located in a mild environment. The QA1 instruments are seismically qualified in accordance with the criteria of the McGuire FSAR Section 3.10 Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: QA1:
Three Control Room indicators One channel recorded 2/3 Control Room Annunciator alarm Position: The installed instrumentation is adequate for the intended monitoring function.
A-10 Variable: Containment Spray HX RN Flow Range: 0 to 5000 GPM RG 1.97 1 Recommended Category:
DPC Category: 1 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 9 of 42)
Existing Design: QA Condition 1 instrumentation is provided in each of two redundant trains of Nuclear Service Water to indicate cooling water flow through the respective train's Containment Spray Heat Exchanger. The receiver gauge's indicated range is 0 to 5000 gpm. Required minimum flows are listed in Table 9-8.
Each train of instrumentation is powered by a separate Class 1E buss. Each train of instrumentation also provides flow signal inputs to the plant computer through qualified Class 1E isolation devices. The computer performs a periodic logging function. The plant computer is powered by highly reliable battery backed control power. The instrumentation is located in a mild environment with the exception of a pipe rupture.
However, the instrumentation is not required to mitigate the consequences of the pipe rupture. Seismic qualification is described in the McGuire UFSAR, Section 3.10 and Section 1.11.5.1.3.1.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire UFSAR Section 1.11.5.
Display: Two Control Room indicators Two channels periodically logged on computer Position: The installed instrumentation is adequate for the intended monitoring function.
A-11 Variable: Diesel Generator Cooling Water HX RN Flow Range: 0 to 1500 GPM RG 1.97 1 Recommended Category:
DPC Category: 1 Existing Design: QA Condition 1 instrumentation is provided in each of two redundant trains of Nuclear Service Water to indicate cooling water flow through the respective train's Diesel Generator Cooling Water Heat Exchanger. The receiver gauge's indicated range is 0 to 1500 gpm. Required minimum flows are listed in Table 9-8. Each train of instrumentation is powered by a separate Class 1E buss. Each train of instrumentation also provides flow signal inputs to the plant computer through qualified Class 1E isolation devices. The computer performs a periodic logging function. The plant computer is powered by highly reliable battery backed control power. The instrumentation is located in a mild environment.
Seismic qualification is described in the McGuire UFSAR, Section 3.10 and Section 1.11.5.1.3.1.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 10 of 42)
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire UFSAR Section 1.11.5.
Display: Two Control Room indicators Two channels periodically logged on computer Position: The installed instrumentation is adequate for the intended monitoring function.
B-1 Variable: Neutron Flux Range: 10-8 to 200% Full Power RG 1.97 1 Recommended Category:
DPC Category: 1 Existing Design: There are two complete channels of full range neutron flux instrumentation that are QA Condition 1 Class 1E and fully qualified environmentally and seismically for post-accident monitoring. Each loop consists of a detector, signal processor, control room receiver gauge and a computer point.
One channel also includes a control room recorder. Inputs to the plant computer are provided with qualified Class 1E isolation. The instrumentation is powered by Class 1E buses.
The receiver gauges, the recorders and the plant computer are installed in a mild environment. The range of the system is 10-8% to 200% power.
Compliance: The instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. as clarified in McGuire FSAR Section 1.11.5.
Display: Two Control Room meters One channel recorded Position: The instrumentation is adequate for the intended monitoring function.
B-2 Variable: Control Rod Position Range: Full in or not full in RG 1.97 3 Recommended Category:
DPC Category: 3 Existing Design: Each control rod's position is indicated on a digital display.
The indicated range is Full In to Full Out in 42 increments.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 11 of 42)
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: A Control Room digital display indicating all control rods Position: The installed instrumentation is adequate for the intended monitoring function.
B-3 Variable: RCS Soluble Boron Concentration Range: 0 to 6000 ppm RG 1.97 3 Recommended Category:
DPC Category: 3 Existing Design This variable is monitored by sampling and laboratory analysis. Sampling frequency is determined by plant conditions and operating procedures.
Compliance The existing design is in compliance with Dukes interpretation of Regulatory Guide 1.97, Revision 2 as clarified by letter Duke Power to NRC, November 18, 1993.
Display Not Applicable Position: Evaluation of available equipment and the use of sampling and laboratory analysis has been determined to be adequate for the intended function as clarified by letter Duke Energy to NRC, November 18, 1993.
B-9 Variable: Coolant Level in Reactor Range: Core bottom to vessel top RG1.97 1 Recommended Category:
DPC Category: 1 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 12 of 42)
Existing Design: This system consists of two redundant QA Condition 1 channels powered from Class 1E busses. Each channel contains the necessary equipment to calculate vessel level or relative void content of the primary coolant. Instrument taps will be located at the head vent, hot legs and the seal table for narrow and wide range level transmitters. RTDs on the impulse lines for these transmitters are used to compensate for temperature variations between these impulse lines in containment. This instrumentation will be used to detect the presence of a gas bubble or void in the reactor vessel, detect the approach to inadequate core cooling (ICC) and indicate void formation in the RCS during forced flow conditions.
Environmental qualification is described in the McGuire Nuclear Station NUREG 0588 submittal. The instrumentation is seismically qualified in accordance with the the criteria of the McGuire FSAR Section 3.10 Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: One Control Board Indicator (ICCM) per channel:
- 1. Upper head level (64 to 120%)
- 2. Narrow range level (0 to 70%)
- 3. Wide range level (0 to 120%)
One channel recorded Position: The installed instrumentation is adequate for the intended monitoring function.
B-12, Variable: Containment Sump Water Level Narrow Range C-6 (Containment Floor and Equipment Sumps)
Range: Narrow Range Level RG 1.97 2 Recommended Category:
DPC Category: 3 Existing Design: Two instruments monitor the containment sump water level from 5 to 23 inches depth in the sump. The instrumentation is powered from an auxiliary buss. Qualified backup indication is provided by the Wide Range Sump Level Instrumentation.
Compliance: This instrumentation is not in compliance with the RG 1.97, Rev. 2 recommendations for environmental qualification.
Display: Two indicators in the Control Room (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 13 of 42)
Position: Instrumentation is adequate for the intended monitoring function. The wide range sump level instruments provide primary indication of post accident containment sump level.
The level of environmental qualification provided for the narrow range sump level instrumentation is consistent with performance expectations and meets the recommendations of Category 3 in Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
B-12, Variable: Containment Sump Water Level C-6 Range: Wide Range (bottom of containment to 600,000 gal. level)
RG1.97 1 Recommended Category:
DPC Category: 1 Existing Design: Two redundant, QA Condition 1 level transmitters measure containment sump water level from the bottom of containment to approximately the 1,000,000 gal. level. The indicated range is 0 to 20 feet. Also, two redundant, QA Condition 1 level switches are provided for both ECCS and containment spray swap to sump. Redundancy/diversity is provided by the Refueling Water Storage Tank Level instrumentation and the narrow range sump level instrumentation. The instruments are powered by Class 1E busses. Environmental qualification is described in the McGuire Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. The instrumentation is seismically qualified in accordance with the criteria of the McGuire FSAR Section 3.10 Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Two Control Room indicators for wide range level indication, plus two Control Room annunciators for both ECCS and NS swap to sump.
One channel recorded for wide range level.
Position: The installed instrumentation is adequate for the intended monitoring function.
B-13, Variable: Containment Pressure B-15, C-5, C-11 Range: -5 to 60 psig RG1.97 1 Recommended Category:
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 14 of 42)
DPC Category: 1 Existing Design: This station has two redundant QA Condition 1 wide range channels and two intermediate range channels of instrumentation for monitoring containment pressure. This instrumentation is powered by Class 1E busses. The wide range indication is -5 to 60 psig, the intermediate range -5 to 20 psig. Environmental qualification is described in the NUREG0588 submittal. The instrumentation is seismically qualified in accordance with the criteria of the McGuire UFSAR Section 3.10.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Two wide range Control Room indicators, two intermediate range indicators.
One wide range channel recorded, one intermediate range recorded.
Position: The installed instrumentation is adequate for the intended monitoring function.
B-14 Variable: Containment Isolation Valve Position Range: Closed - Not Closed RG1.97 1 Recommended Category:
DPC Category: 1 Existing Design: All remote operated, active containment isolation valves provided with control switches on the main control boards have actual valve position provided by QA Condition 1 limit switches on the valves which operate both Closed-Not Closed, and Open-Not Open control switch indicating lights.
These valves and their control switch indicating lights are powered by Class 1E busses. Redundancy is not necessary on a per valve basis since redundant barriers are provided for all fluid penetrations as discussed in the McGuire FSAR, Section 6.2.4. Environmental qualification of the limit and reed switches is described in the FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification of the limit and reed switches is described in the McGuire FSAR, Section 3.10 Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as described in McGuire FSAR Section 1.11.5.
Position: The installed instrumentation is adequate for the intended monitoring function (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 15 of 42)
Display: Control Room control switch indicating lights Computer points C-2 Variable: Radiation Level in Primary Coolant Range: 1/2 Tech Spec limit to 100 times Tech Spec limit.
RG1.97 1 Recommended Category:
DPC Category: Not Applicable Existing Design: McGuire has one channel of primary coolant radiation level instrumentation. This channel is powered from a highly reliable battery backed buss. The indicated range is 101 to 107 counts per minute corresponding to 10-2 to 103 µCi/ml Ba-133.
Compliance: This monitor was not installed as a Category 1 (QA Condition
- 1) instrument. RG 1.97, Rev. 2 range is not met.
Display: One Control Room indicator One channel recorded Position: This monitor was not installed to quantify accident conditions and cannot be assured flow following an accident.
Information for this variable is obtained by sampling and analysis which is considered adequate for the intended monitoring function.
C-3, Variable: Analysis of Primary Coolant E-18, Accident Sampling Capability, Primary Coolant and Sump, E-19 Containment Air Range: 10 µCi/gm to 10 Ci/gm or TID 14844 source term in coolant volume Grab Sample RG 1.97 3 Recommended Category:
DPC Category: 3 Existing Design: The existing design of the sampling system for the primary coolant, the containment sump (sample taken from RHR pump discharge) and containment air allows samples to be taken for laboratory analysis. Capabilities for making the recommended measurements are provided. Information concerning the laboratory equipment available for radiological analysis is contained in the McGuire FSAR, Section 12.3.2.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 16 of 42)
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Not Applicable.
Position: Available equipment is adequate for the intended analyses.
C-7, Variable: Containment Area Radiation - High Range E-1 Range: 1 to 108 R/hr RG 1.97 1 Recommended Category:
DPC Category: 1 Existing Design: McGuire has two redundant QA Condition 1 channels of containment high range radiation instrumentation. Each channel is powered by a Class 1E Bus. The indicated range is 1 to 108 R/hr. Diversity is provided by portable instrumentation or sampling and analysis. Environmental qualification is described in the McGuire Nuclear Station UFSAR, Section 3.11 and in the NUREG 0588 Submittal.
The instrumentation is seismically qualified in accordance with the criteria of the McGuire UFSAR Section 3.10 Compliance: Duke procured and installed seismically and environmentally qualified radiation monitors. Duke considers all aspects of this instrumentation to be in compliance with the recommendations of RG 1.97 Rev. 2 as clarified in McGuire UFSAR Section 1.11.5.
Display: Two Control Room indicators (one per channel)
One channel recorded Position: The qualification aspect of this installed monitoring system has been thoroughly evaluated and has been found to be in full compliance with the requirements of RG1.97 Rev. 2.
The bullets below are for system clarification and completed evaluation of IN 97-45, Thermally Induced Current (TIC),
effects.
- System Clarification: Radiation instrumentation indication level consists of the instruments keep alive source and actual containment radiation level measured.
- IN 97-45: TIC effects on the radiation instrumentations were evaluated to have minimal impact at the lower reading for a limited amount of time, and do not affect the instrumentations ability to perform RG 1.97 Rev. 2 functions.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 17 of 42)
C-8, Variable: Condenser Air Ejector Effluent Radioactivity E-6, Containment Effluent Radioactivity C-12, C-14, Effluent Radioactivity (from buildings in contact with the E-3, containment)
E-4, Containment Purge Effluent Radioactivity E-5, E-9 Annulus Effluent Radioactivity Auxiliary Building Effluent Radioactivity Other Identified Release Point Effluent Radioactivity Range: Various - from 10-6 to 10-2 µCi/cc to 10-6 to 105 µCi/cc RG 1.97 2 Recommended Category:
DPC Category: Not Applicable Existing Design: Airborne process radiation monitors exist for monitoring ventilation exhausts and the condenser air ejector exhaust (see the McGuire FSAR, Section 11.4 and Table 11-28).
However, in accordance with RG 1.97. Rev. 2 these monitors are not required for accident monitoring due to the fact that ventilation systems and the condenser air ejector exhaust to the common unit vent (see variable sheet E-7 on the unit vent radiation monitor).
Compliance: Not Applicable.
Display: Not Applicable.
Position: Individual radiation monitors are not needed for compliance to the recommendations of RG 1.97, Rev. 2 due to effluents exhausting to the common unit vent.
C-10 Variable: Containment Hydrogen Concentration Range: 0 to 30% Hydrogen RG 1.97 1 Recommended Category:
DPC Category: 3 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 18 of 42)
Existing Design: Two redundant channels of QA Condition 1 instrumentation monitor containment hydrogen concentration. The indicated range is from 0 to 30% concentration. Both channels are powered by Class 1E busses. These instruments are installed in a mild environment. The instrumentation is seismically qualified in accordance with the criteria of McGuire FSAR Section 3.10 Diversity and backup is provided by manual sampling and analysis. The instrumentation is no longer required to be safety-related.
Compliance: The revised 10 CFR 50.44 no longer defines a design-basis LOCA hydrogen release. Hydrogen monitors are no longer required to support mitigation of design-basis accidents, and therefore, no longer meet the definition of Category 1 in RG 1.97. NRC concluded that Category 3, as defined in RG 1.97, is an appropriate categorization for the hydrogen monitors since they are required to diagnose the course of beyond design-basis accidents.
Display: Two Control Room indicators One channel recorded Position: The installed instrumentation is adequate for the intended monitoring function.
C- Variable: Area Radiation 13, E-2 Range: 10-1 mR/hr to 104 mR/hr RG1.97 2 Recommended Category:
DPC Category: 3 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 19 of 42)
Existing Design: McGuire has an extensive Area Radiation Monitoring System installed for personnel protection. Channel detector locations were selected based on areas normally having free access and low radiation dose rates with the potential of becoming high radiation areas. Range selections were based on normal background radiation levels to allow reasonable monitoring and alarm settings for keeping personnel exposures ALARA. All of these channels, with the exception of the monitors adjacent to the Reactor Coolant filters, have an indicated range of 10-1 to 104 mR/hr. The indicated range of the Reactor Coolant filter area monitors is 10-1 to 104 R/hr.
Redundant indication is provided by portable instrumentation.
The channels are powered by a highly reliable regulated control bus. The instrumentation is rated to withstand the temperatures and radiation doses for normal and accident conditions, except for those monitors in areas where access is permitted only during normal plant shutdown (e.g., the containment refueling bridge monitor was installed for personnel protection during refueling operations and is not required to be operational during a DBA). See the McGuire FSAR, Section 12.1 for additional information concerning the Area Radiation Monitoring System.
Compliance: The range of most of the instrumentation, and the absence of recording is not in compliance with the recommendations of RG 1.97, Rev. 2.
Display: One Control Room indicator per channel.
Position: The installed range of the instrumentation is acceptable for the intended function of personnel protection. The functions of detection of releases, release assessment and surveillance are performed through Health Physics Procedures with supplemental information provided by the effluent process Radiation Monitoring System. The qualification is within the guidance provided for Category 3 instrumentation which Duke considers adequate for the intended monitoring function. Also note, this is in compliance with the recommendations of R.G.
1.97 Rev 3. Recording is not required for the intended monitoring function.
D-1, Variable: Flow in Low Pressure Injection System (RHR System Flow)
D-7 Range: 0 to 110% Design Flow RG1.97 2 Recommended Category:
DPC Category: 2 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 20 of 42)
Existing Design: The existing design provides a separate display for each of the two RHR trains. The power is provided by highly reliable battery backed busses. Indicated range is 0 to 5000 GPM with a design flow of 3000 GPM. This instrumentation is installed in a mild environment.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Two Control Room indicators Position: The installed instrumentation is adequate for the intended monitoring function.
D-2 Variable: RHR Heat Exchanger Outlet Temperature Range: 32°F to 350°F RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: Each train of the McGuire Residual Heat Removal System contains instrumentation to monitor RHR return temperature.
The range for this instrumentation is 50°F to 400°F and the power supply is a highly reliable battery backed control buss.
The RHR instrumentation is located in a mild temperature environment but is subject to post accident radiation.
Environmental qualification is described in the McGuire FSAR Section 3.11 and the NUREG-0588 submittal. The instrumentation is seismically qualified in accordance with the criteria of the McGuire FSAR Section 3.10 Compliance: The Duke range is 50°F - 400°F, whereas the recommended range is 32°F - 350°F.
Display: Two channels recorded in the Control Room Position: The Duke range for this instrumentation is suited to the operating and accident temperature expected in the Residual Heat Removal System and is therefore considered acceptable.
D-3 Variable: Accumulator Tank Pressure (Cold Leg Accumulator)
Range: 0 to 750 psig RG1.97 2 Recommended Category:
DPC Category: 3 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 21 of 42)
Existing Design: McGuire has two channels of accumulator tank pressure instrumentation on each of four accumulator tanks. Power for these channels is provided by two different highly reliable battery backed busses. The indicated range is 0 to 700 psig.
The rating of the instrument is not adequate to prove survivability for the in containment accident environment or post accident radiation exposure.
Compliance: The range of this instrumentation is not in total compliance with the recommendations of RG 1.97, Rev. 2. The equipment is not rated to assure survivability for the in containment accident environment or post accident radiation exposure, however, this instrumentation does not perform a safety function during or in a post-accident environment and operator actions to mitigate the effects of an accident do not depend on the information provided by this instrumentation.
Per NRC letter dated April 3, 1992, Category 3 qualification of this instrumentation is acceptable.
Display: Eight Control Room indicators (2 indicators per accumulator tank)
Position: A design and qualification Category of 3 is adequate for this function. The installed system meets the Duke interpretation of Category 3 recommendations as clarified in McGuire UFSAR Section 1.11.5. Duke considers the rating and environmental and radiation withstand capability adequate to meet the intended monitoring function.
D-3 Variable: Accumulator Tank Level (Cold Leg Accumulator)
Range: 10% to 90% volume RG 1.97 2 Recommended Category:
DPC Category: 3 Existing Design: McGuire has two channels of accumulator tank level instrumentation on each of the four accumulator tanks.
Power for these channels is provided by two different highly reliable battery backed busses. The indicated range is 0% to 100% which corresponds to approximately 68% to 83% of the accumulator tank volume which is appropriate to perform Technical Specification Monitoring. The rating of the instrument is not adequate to prove survivability for the in containment accident environment or post accident radiation exposure.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 22 of 42)
Compliance: The range of this instrumentation is not in compliance with the recommendations of RG 1.97, Rev. 2. The equipment is not rated to assure survivability for the in containment accident environment or post accident radiation exposure, however, this instrumentation does not perform a safety function during or in a post-accident environment and operator actions to mitigate the effects of an accident do not depend on the information provided by this instrumentation.
Per NRC letter dated April 13, 1992, Category 3 qualification of this instrumentation is acceptable.
Display: Eight Control Room indicators (2 indicators per accumulator tank)
Position: A design and qualification Category of 3 is adequate for this function. The installed system meets the Duke interpretation of Category 3 recommendations as clarified in McGuire UFSAR Section 1.11.5. Duke considers the range and environmental and radiation withstand capability adequate to meet the intended monitoring function.
D-3 Variable: Accumulator Level (UHI Accumulator)
This variable does not apply to McGuire Nuclear Station design. Function was deleted per NSM MG-11768 and NSM MG-20598.
D-3 Variable: Accumulator Pressure (UHI Accumulator)
This variable does not apply to McGuire Nuclear Station design. Function was deleted per NSM MG-11768 and NSM MG-20598.
D-4 Variable: Cold Leg Accumulator Isolation Valve Position Range: Closed or Open RG 1.97 2 Recommended Category:
DPC Category: 2 Existing Design: The cold leg accumulator isolation valves are provided with control switches on the main control boards. Actual valve position is provided by QA Condition 1 limit switches on the valves to operate both Closed-Not Closed, and Open-Not Open control switch indicating lights. These valves and their control switch indicating lights are powered by Class 1E busses. Additional indications are provided by monitor lights and by the computer. Environmental qualification of the limit switches is described in the McGuire Nuclear Station UFSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification of the limit switches is described in the McGuire UFSAR, Section 3.10 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 23 of 42)
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire UFSAR Section 1.11.5.
Display: Control Room control switch indicating lights Monitor lights.
Position: The installed instrumentation is adequate for the intended monitoring function.
D-4 Variable: UHI Accumulator Isolation Valve Position This variable does not apply to McGuire Nuclear Station design. Function was deleted per NSM MG-11768 and NSM MG-20598.
D-5 Variable: Boric Acid Charging Flow Range: 0 to 110% Design Flow RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: The existing instrumentation provides continuous monitoring of centrifugal charging pump flow through the NI System directly into the reactor coolant cold legs. The loop range is 0
- 1000 gallons per minute with a design flow of approximately 750 GPM. This instrument loop is powered by a highly reliable battery backed control buss and is installed in a mild environment.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire UFSAR Section 1.11.5.
Display: One Control Room indicator.
Position: The installed instrumentation is adequate for the intended monitoring function.
D-6 Variable: Flow in HPI System (Safety Injection System Flow)
Range: 0 to 110% of Design Flow RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: One set of instrumentation per train measures the flow from 0
- 800 GPM with a design flow of 650 GPM. Power is provided by highly reliable battery backed busses. This instrumentation is installed in a harsh environment due to radiation as defined by Duke.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 24 of 42)
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire UFSAR Section 1.11.5.
Display: Two Control Room indicators (one per train)
Position: Non QA condition 1 category 2 instrumentation must have reasonable assurance that it will be operable for accident monitoring. The installed instrumentation is subject to a total radiation dose that is slightly larger than the threshold for a harsh environment definition as defined by Duke (1.0E3 Rads). The installed transmitters have not been formally environmentally qualified. However, the limiting subcomponents due to radiation within the insalled transmitters are bipolar devies. The installed transmitters are similar in construction to other transmitters that are fully qualified for harsh environment radiation exposure levels.
NUREG/CR-9156 documented results of tests that have been performed to show that typical bipolar devices remain functional when subjected to radiation doses which exceed that experienced by these installed transmitters.
Therefore, the installed instrumentation is adaquate for the intended monitoring function.
D-9 Variable: Reactor Coolant Pump Status Range: Motor Current RG 1.97 3 Recommended Category:
DPC Category: 3 Existing Design: The indicated range for RCP motor current is from 0 to 800 amps. The instrumentation derives power from the monitored source.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Four Control Room ammeters Position: The installed instrumentation is adequate for the intended monitoring function.
D-10 Variable: Primary System Safety Relief Valve Positions (Power Operated Relief Valves)
Range: Closed - Not Closed RG1.97 2 Recommended Category:
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 25 of 42)
DPC Category: 2 Existing Design: The Power Operated Relief Valves are provided with control switches on the main control boards. Actual valve position is provided by QA Condition 1 limit switches on the valves which operate both Closed-Not Closed, and Open-Not Open control switch indicating lights. These valves and their control switch indicating lights are powered by Class 1E busses.
Additional indications are provided by the computer.
Environmental qualification of the limit switches is described in the McGuire NUREG 0588 submittal. The limit switches are seismically qualified in accordance with the criteria of the McGuire FSAR Section 3.10 Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Control Room control switch indicating lights Position: The installed instrumentation is adequate for the intended monitoring function.
D-10 Variable: Primary System Safety Relief Valve Positions (Code Valves)
Range: Closed - Not Closed RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: A QA Condition 1 Acoustic Leak Detection System is provided to monitor the position of these valves. Indicator lights indicate valve (closed - not closed) position. The McGuire Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal contain information on the environmental qualification of the Acoustic Leak Detection System. The instrumentation is seismically qualified in accordance with the criteria of the McGuire FSAR Section 3.10 The instrumentation is powered by a Class 1E buss.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Control Room indicating lights Position: The installed instrumentation is adequate for the intended monitoring function.
D-12 Variable: Pressurizer Heater Status Range: Electric Current (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 26 of 42)
RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: Each of the four pressurizer heater groups have instrumentation for monitoring current. The range is 0 to 600 amps. Power for the transducers is derived from the sources they monitor. The computer readout is powered by highly reliable battery backed busses. This instrumentation is installed in a mild environment.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: On demand display by the plant computer. Control Room monitor lights to indicate heater operation.
Position: The installed instrumentation is adequate for the intended monitoring function.
D-13 Variable: Quench Tank (Pressurizer Relief Tank) Level Range: Top to Bottom RG1.97 3 Recommended Category:
DPC Category: 3 Existing Design: The indicated range of Pressurizer Relief Tank Level is from 0 to 100% corresponding to tank volume of approximately 3%
to 97%.
Compliance: The range is not in complete compliance with RG 1.97 recommendations.
Display: One Control Room indicator Position: The range of the installed instrumentation is adequate for the intended monitoring function.
D-14 Variable: Quench Tank (Pressurizer Relief Tank) Temperature Range: 50°F to 750°F RG1.97 3 Recommended Category:
DPC Category: 3 Existing Design: The indicated range of Pressurizer Relief Tank temperature is from 50°F to 350°F.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 27 of 42)
Compliance: The range is not in compliance with the RG 1.97, Rev. 2 recommendation.
Display: One Control Room indicator Position: The instrument range is 50°F to 350°F, to cover the range of saturation temperatures up to the tank rupture disc pressure of 100 psig. This range is adequate for the intended monitoring function.
D-15 Variable: Quench Tank (Pressurizer Relief Tank) Pressure Range: 0 to design pressure RG1.97 3 Recommended Category:
DPC Category: 3 Existing Design: The indicated range of the Pressurizer Relief Tank pressure is from 0 to 100 psig. The tank rupture disc pressure is 100 psig.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: One Control Room indicator Position: The installed instrumentation is adequate for the intended monitoring function.
D-16 Variable: Wide Range Steam Generator Level Range: From tube-sheet to separators RG1.97 1 Recommended:
Category:
DPC Category: 3 Existing Design: McGuire has four (one per steam generator) channels of wide range steam generator level instrumentation. Each transmitter feeds the PCS and is powered by a battery backed Class 1E buss (moved to PCS Protection Cabinets by EC 78241 and EC 78243). The indicated range is 0 to 100%
corresponding to 6.6 " above the tube-sheet, to the separators. Upgraded Level Transmitters were installed environmentally and seismically qualified per NRC correspondence to H.B. Tucker dated 03/17/1988.
Compliance: The range of the instrumentation does not meet the recommendations of RG 1.97, Rev. 2.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 28 of 42)
Display: Four channels recorded. Control room display via seismically mounted indicating recorders. The recorders are made by the same manufacturer as those used in safety-related applications.
Position: Primary indication of S/G level is provided by the Narrow Range S/G Level indicator (see variable A-7). The level of environmental qualification provided is consistent with the performance expectations of the instrumentation and exceeds the recommendations of Category 3 in Duke's interpretation of RG 1.97 Rev. 2 as clarified in McGuire FSAR Section 1.11.5. The installed range is adequate for measuring wide range steam generator level and Duke considers the installed instrumentation adequate for the intended monitoring function.
D-18 Variable: Main Steam Flow (or, Safety Relief Valve Position)
Range: No range listed in RG 1.97, Rev. 2 RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: This station has two channels of main steam flow instrumentation on each of four steam generators. Each (of two per steam generator) transmitter feeds a different channel of the PCS and is powered by that channel's associated battery backed buss. The indicated range is 0 to 117% with 100% flow corresponding to normal 100% power maximum flow. The instrumentation is environmentally rated for the installed location. Environmental qualification of this instrumentation is described in the McGuire Environmental Qualification Maintenance Manual (EQMM) and Environmental Qualification Master List (EQML).
Compliance: The instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as declared in McGuire FSAR Section 1.11.5.
Display: Eight Control Room indicators Four channels recorded (one of two per steam line)
Position: The installed instrumentation is adequate for the intended monitoring function.
D-19 Variable: Main Feedwater Flow Range: 0 - 110% Design Flow RG1.97 3 Recommended Category:
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 29 of 42)
DPC Category: 3 Existing Design: McGuire has twelve main feedwater flow channels, of which eight (two channels per steam generator feedline) are used in post-accident monitoring. The indicated range for this variable is 0 to 120%. This corresponds to 4.65x106 lbs/hr which is 120% of design flow.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Eight Control Room indicators Four channels recorded (one per feedline)
Position: The installed instrumentation is adequate for the intended monitoring function.
D-20 Variable: Auxiliary Feedwater Flow Range: 0 - 110% Design Flow RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: McGuire has four QA Condition 1 and four non-QA condition auxiliary feedwater flow transmitters, one each steam generator, monitoring flow from all auxiliary feedwater pumps to each steam generator. The indicated range is 0-600 GPM for a system design flow of 350 GPM. The QA condition 1 instrumentation is powered by Class 1E busses.
Environmental qualification is described in the McGuire NUREG 0588 submittal. This instrumentation is seismically qualified in accordance with the criteria of the McGuire FSAR Section 3.10. The Non-QA instrumentation is powered by a highly reliable battery backed buss. This instrumentation is seismically mounted. Pressure boundary intergrity has been documented in a calculation. Additional indication is provided on the operator aided computer.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: QA Condition 1 - four Control Room Indicators. Non-QA condition - four indicators, two on each Motor Driven Auxiliary Feedwater Pump Panel.
Position: The installed instrumentation is adequate for the intended monitoring function.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 30 of 42)
D-21 Variable: Auxiliary Feedwater Condensate Storage Tank Level, Auxiliary Feedwater Storage Tank Level, Or Auxiliary Feedwater Assured Source Range: Plant Specific RG1.97 1 Recommended Category:
DPC Category: 1 Existing Design: McGuire's Auxiliary Feedwater System (CA) draws Condensate grade suction from the following source:
- 1. CA Storage Tank The safety related source for CA System suction is the Nuclear Service Water (RN) System. This system is QA Condition 1 and is the assured source of secondary side inventory. It is automatically aligned to the suction of the CA pumps by QA Condition 1 pressure switches which monitor suction pressure. When the pressure switches detect low suction pressure, the affected CA pump will align to the Nuclear Service Water System. Operator confirmation of the supply or availability of RN as the assured safety source of water to the CA pumps is provided by:
- 1. QA Condition 1 indication of RN pump operational status.
This instrumentation is seismically qualified and located in a mild environment.
- 2. QA Condition 1 indication of the RN & CA suction supply source isolation valves. Valve operators, limit switches, indicating lights are seismically and environmentally qualified.
- 3. QA Condition 1 indication of CA pumps flow to the steam generators. (See variable D-20).
Additional Category 3 indication is available for further confirmation of transfer of the CA pump suction to the assured source. This indication includes:
- 1. RN pump header discharge flow.
- 2. CA pumps suction pressure.
- 3. CA pumps discharge pressure.
These monitoring instruments are located in a mild environment.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 31 of 42)
Display: 1. RN Pump Status:
Two operational status indicating lights per pump
- 2. RN & CA Suction Supply Valves' Positions:
Two valve position indicating lights per valve.
- 3. CA Pumps Flow to the Steam Generators: (see variable D-20):
Four Control Room indicators (1 per S/G).
- 4. RN Pump header discharge flow (Category 3):
Two Control Room indicators (1 per pump)
- 5. CA Pumps Suction Pressure (Category 3):
Three Control Room indicators (1 per pump)
- 6. CA Pumps Discharge Pressure (Category 3):
Three Control Room indicators (1 per pump)
Position: The installed instrumentation is adequate for the intended monitoring function.
D-22 Variable: Containment Spray Flow Range: 0 to 110% Design Flow RG1.97 2 Recommended Category DPC Category: 2 Existing Design: The containment spray instrumentation provides an indicated range of 0 to 4000 gpm for containment spray flow. Design flow is approximately 3400 gpm, and the power supply is a highly reliable battery backed control buss. One channel is provided for each of two containment spray pumps. The containment spray flow instrumentation is installed in a mild temperature environment. Environmental qualification of this instrumentation is described in the McGuire Environmental Qualification Maintenance Manual (EQMM) and Environmental Qualification Master List (EQML).
Compliance: The transmitters for this variable are rated to withstand the anticipated maximum design basis accident radiation dose for the installed location.
Display: Two Control Room indicators (one per pump)
Position: The installed instrumentation is adequate for the intended monitoring function.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 32 of 42)
D-23 Variable: Heat Removal by the Containment Fan Heat Removal System This variable does not apply to McGuire Nuclear Station design.
D-24 Variable: Containment Atmosphere Temperature Range: 40°F to 400°F RG 1.97 2 Recommended Category:
DPC: 2 Existing Design: Four RTD's are provided to monitor upper containment temperature and four RTD's are provided to monitor lower containment temperature. The range of the lower containment instrumentation is 32 to 400°F and the upper containment instrumentation is 32 to 212°F. Environmental Qualification of the RTD's is described in the McGuire FSAR, Section 3.11 and the NUREG-0588 submittal. Seismic qualification is described in the McGuire FSAR, Section 3.10 The instrumentation loops are powered by a highly reliable battery backed buss.
Compliance: The range of the upper containment instrumentation is not in compliance with the recommendations of R.G. 1.97 Rev. 2.
Display: Eight analog computer points (four upper and four lower containment).
Position: The installed installation is adequate for the intended monitoring function. The worst case upper containment post accident temperature is 190°F and is within the range of installed instrumentation.
D-25 Variable: Containment Sump Water Temperature For the McGuire design, this variable is not utilized in the management of a design basis accident and therefore is not provided.
D-26 Variable: CVCS Makeup Flow Range: 0 to 110% Design Flow RG1.97 2 Recommended Category:
DPC Category: 3 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 33 of 42)
Existing Design: The existing instrumentation for this variable provides continuous monitoring of reactor coolant charging flow. The loop range is 0 to 200 gallons per minute. Design flow is 120 GPM. This instrument loop is powered from a highly reliable battery-backed buss. The instrumentation is located in a mild temperature environment.
Compliance: The transmitter for this variable is not rated to withstand the anticipated maximum design basis accident radiation dose for the installed location.
Display: One Control Room indicator Position: The installed instrumentation is adequate for the intended monitoring function. For accidents in which harsh environments are a result, the system containing this instrumentation (letdown and charging portion of the CVCS) is not required in the mitigation of these accidents and is automatically isolated upon an ESF Actuation. The level of environmental qualification provided for the instrumentation in this system is consistent with the performance expectations of the system and meets the recommendations of Category 3 in Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
D-27 Variable: CVCS Letdown Flow Range: 0 to 110% Design Flow RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: The existing instrumentation for this variable provides continuous monitoring of reactor coolant letdown flow. The loop range is 0 to 200 gallons per minute with a design flow of approximately 120 GPM. This instrument loop is powered from a highly reliable battery-backed buss. The instrumentation is located in a mild environment.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: One Control Room indicator Position: The installed instrumentation is adequate for the intended monitoring function.
D-28 Variable: Volume Control Tank Level Range: Top to Bottom (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 34 of 42)
RG.1.97 2 Recommended Category:
DPC Category: 3 Existing Design: The existing instrumentation for this variable provides continuous monitoring of volume control tank level. The loop range is 0 to 100% of tank level which covers the linear portion of the tank (approximately 18 to 82% of tank volume).
This instrument loop is powered from a highly reliable battery backed buss. This instrumentation is located in a mild temperature environment.
Compliance: The range and radiation withstand capability of the instrumentation are not in compliance with the RG 1.97, Rev.
2 recommendations.
Display: One Control Room indicator Position: The installed instrumentation is adequate for the intended monitoring function. Minimum and maximum tank levels are maintained within the range of the instrument. Extending the range into the domed portions of this tank would result in nonlinear readings at each extreme of the scale. For accidents in which harsh environments are a result, the system containing this instrumentation (letdown and charging portion of the CVCS) is not required in the mitigation of these accidents and is automatically isolated upon an ESF Actuation. The level of environmental qualification provided for the instrumentation in this system is consistent with the performance expectations of the system and meets the recommendations of Category 3 in Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
D-29 Variable: Component Cooling Water Temperature to ESF System Range: 32°F to 200°F RG 1.97 2 Recommended Category:
DPC: 2 Existing Design: The water temperature to the ESF Systems is monitored at the outlet of each train of the Component Cooling Water Heat Exchangers. The power for this instrumentation is a highly reliable battery backed buss. Range for the read-out is 50 ºF to 150 ºF. This instrumentation is installed in a mild environment.
Compliance: This instrumentation is not in full compliance with RG 1.97, Rev. 2 because the range of the instrumentation is slightly less than the recommendation of RG 1.97, Rev 2.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 35 of 42)
Display: Two computer points (one per Component Cooling train)
Position: The installed instrumentation is adequate for the intended monitoring function. The monitored range is 50 ºF to 150 ºF, which is adequate for the design ratings of the component cooling system piping. This range is suitable for normal KC operating conditions as well as post accident monitoring.
D-30 Variable: Component Cooling Water Flow to ESF Systems Range: 0 to 110% Design Flow RG 1.97 2 Recommended Category:
DPC Category: 2 Existing Design: The installed instrumentation indicates flow in each of two redundant Component Cooling headers. Indicated range is 0 to 10,000 GPM for a system design flow of 8700 GPM. The instrumentation is powered by a highly reliable auxiliary buss and is located in a mild environment.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Two Control Room indicators.
Position: The installed instrumentation is adequate for the intended monitoring function.
D-31 Variable: High Level Radioactive Liquid Tank Level Range: Top to Bottom RG 1.97 3 Recommended Category:
DPC Category: 3 Existing Design: The indicated range for this variable is 0 to 100% for each of three tanks. There are two Recycle Holdup Tanks which are shared by Units 1 & 2. The indication corresponds to the tank volume of approximately 2 to 91%. There is one Waste Drain Tank shared by Units 1 & 2. The indication corresponds to the tank volume of approximately 9 to 91%
Compliance: The range is not in complete compliance with the recommendation of R.G. 1.97, Rev. 2.
Display: 1 Computer point per tank.
Position: The tap to tap range of the installed instruments is adequate to provide tank level information.
D-32 Variable: Radioactive Gas Holdup Tank Pressure (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 36 of 42)
Range: 0 to 150% Design Pressure RG 1.97 3 Recommended Category:
DPC Category: 3 Existing Design: McGuire utilizes six tanks for radioactive waste gas storage.
The maximum operating pressure for these tanks is approximately 100 psig (per the McGuire FSAR, Section 11.3). The indicated range is 0 to 150 psig for each tank.
Compliance: This instrumentation is in compliance with Duke's interpretation of R.G. 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Six computer points (one per tank).
Position: The installed instrumentation is adequate for the intended monitoring function.
D-33 Variable: Emergency Ventilation Damper Position Range: Open-Closed Status RG 1.97 2 Recommended Category:
DPC Category: 2 Existing Design: All active emergency ventilation dampers which are actuated under design-basis accident conditions and whose failure could result in a radioactive release to atmosphere have position indication or indication that the required emergency system alignment has been achieved in the Control Room. At least one channel per damper is provided, and this instrumentation is powered from Class 1E busses.
Environmental qualification of the position indication limit switches is described in the McGuire FSAR, Section 3.11 and the NUREG-0588 submittal. Seismic qualification is described in the McGuire FSAR, Section 3.10 Compliance: Some emergency ventilation dampers do not meet the range recommendations of RG 1.97, Rev 2. Those dampers not in compliance have positive indication that the required emergency system alignment has been achieved but no individual Open-Closed status. Positive indication may be provided by system flows, pressures, etc.
Display: Control Room control switch indicating lights Analog indicators (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 37 of 42)
Position: The installed instrumentation is adequate for the intended monitoring function since the operator is always provided with positive indication that emergency dampers have achieved their safety mode alignment during and after an accident.
D-34 Variable: Status of Standby Power and Other Energy Sources Important to Safety Range: Voltages, currents, pressures RG 1.97 2 Recommended Category:
DPC Category: 2 Existing Design: All QA Condition 1 (Class 1E) or battery backed control busses have undervoltage alarms in the Control Room with local diagnostic capabilities to enable an expedient assessment of abnormal situations. In addition, the 125 VDC distribution centers have analog indicators of voltage level in the Control Room. All of the Control Room alarms are on highly reliable battery backed busses. All of the sensing relays and alarm electronics are located in a mild temperature and radiation environment.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Control Room annunciators Control Room analog indicators.
Computer digital points Position: The installed instrumentation is adequate for the intended monitoring function.
D-35 Variable RN Strainer Differential Pressure Range 0 - 10 psid RG 1.97 2 Recommended Category:
DPC Category: 2 Existing Design: The instrument provides local and OAC indication for strainer D/P. This instrument loop also supplies a control room annuniciator. The instrument loop will automatically backwash the strainer on high D/P. This loop is supplied by a QA condition 1 power source. All impulse tubing associated with this loop is QA condition 1. All loop components are QA condition 1. This instrument is located in a mild environment.
This instrument is seismically qualified in accordance with the criteria of the McGuire FSAR section 3.10.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 38 of 42)
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Control Room annunciators, Computer analog points, local indication.
Position: The installed instrumentation is adequate for the intended monitoring function.
E-7 Variable: Common Plant Vent Radioactive Discharge Range: 10-6 µCi/cc to 104 µCi/cc 0 to 110% vent design flow (where design flow is the maximum flow anticipated in normal operation)
RG1.97 2 Recommended Category:
DPC Category: 2 Existing Design: McGuire has a high range, mid-range and low range channel of unit vent radioactivity instrumentation. These channels are powered from a highly reliable battery backed buss. The indicated range is 1 to 108 R/hr gross gamma for the high range and 10 to 107 cpm and 10 to 106 cpm corresponding to 10-6 to 5 x 103 µCi/ml Kr-85 for the low and mid-range monitors. The instrumentation is installed in a mild temperature environment. The instrumentation is rated to withstand the environmental conditions that would exist during accidents in which it is intended to operate.
Detection, release assessment and long-term surveillance is assisted with unit vent flow instrumentation whose range is enveloped by at least 0 to 110% vent design flow at McGuire.
The instrumentation displays this flow in the control room and plant computer. The instrumentation is installed in a mild temperature environment.
Compliance: Duke considers all aspects of this instrumentation to be in compliance with the recommendations of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Three control room indicators and three channels recorded for the unit vent radioactivity. One channel to control room indicator and the plant computer for the unit vent flow.
Position: The instruments are adequate for their intended monitoring function.
E-8 Variable: Radiation Monitoring for the main steam lines.
Range: 10-1 µCi/cc to 103 µCi/cc Mass of Steam Released (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 39 of 42)
RG 1.97 2 Recommended Category:
DPC Category: 2 Existing Design: Area radiation monitors are located in the doghouses adjacent to the main steam lines and upstream of the main steam isolation valves. These monitors are capable of monitoring radiation in the steam supply to the SG PORVs, SG safety relief valves, and airborne activity in the doghouses. Correlation curves will allow conversion of the monitor readings in mR/hr to µCi/cc. The indicated range is 0.1 to 104 mR/hr. Steam releases are calculated on the plant computer with the information being printed on the alarm typer. This instrumentation is powered from a highly reliable battery backed bus. This instrumentation is rated to withstand the environmental conditions that would exist during accidents in which it is intended to operate. A steam line break in the vicinity of this instrumentation may cause the environment to exceed the rated temperature, however, the instrument is not required to remain functional for this event.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Display: Four Control Room indicators Four channels monitored by OAC.
Position: The installed instrumentation is adequate for the intended monitoring function.
E-10 Variable: Plant Airborne and Area Radiation (sampling with onsite E-12 analysis, portable instrumentation)
E-13 E-14 Range: Various ranges as listed in RG 1.97, Rev. 2 RG 1.97 3 Recommended Category:
DPC Category: 3 Existing Design: Equipment and facilities exist at McGuire for making the measurements and analyses recommended by RG 1.97, Rev. 2. Information concerning these capabilities is in the McGuire FSAR, Section 12.3.
Compliance: Some instrumentation may have ranges which differ from the recommendations of RG 1.97, Rev. 2.
Display: Not Applicable.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 40 of 42)
Position: The instrumentation has been selected using the considerations shown in the McGuire FSAR, Section 12.3.
Evaluation of the equipment has determined it to be adequate for the intended functions.
E-11 Variable: Radiation Exposure Meters This variable is not required based on information given in Supplement 1 to NUREG 0737 Section 6.1-b and the Errata sheet to RG 1.97, Rev. 2 dated May, 1981.
E-15 Variable: Wind Direction Range: 0° to 360° RG 1.97 3 Recommended Category:
DPC Category: 3 Existing Design: McGuire has two channels of wind direction instrumentation at two elevations. The indicated range is 0° to 540°.
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev 2 as clarified in McGuire FSAR Section 1.11.5. Accuracy is not in compliance with RG 1.97 Rev. 2 recommendation.
Display: Two channels on the computer Two channels recorded.
Position: The instruments are adequate for the intended monitoring function as follows:
RG 1.97 Rev. 2 recommended range is 0-360º and McGuire meets this recommendation with a 0-540º range.
The recommended accuracy is +/-5º (with a deflection of 15º)
and McGuire meets this recommendation with a direction sensor having a +/-2.7º accuracy. However, when the total loop uncertainty considers all components connected to the wind direction sensor, a resulting accuracy of +/-7º is calculated. For conservatism, this will be denoted as not in compliance with the RG 1.97 Rev. 2 recommendation.
The recommended starting speed is 1.0 mph and McGuire meets this recommendation with a threshold velocity of 0.7 mph.
Finally, the recommendation is for a damping ratio between 0.4 and 0.6, distance constant less than or equal to 2 meters.
McGuire meets this recommendation with a damping ratio of 0.4 and a distance constant of 1.1 meters.
E-16 Variable: Wind Speed (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 41 of 42)
Range: 0 - 67 mph RG 1.97 3 Recommended Category:
DPC Category:
Existing Design: McGuire has two channels of wind speed instrumentation.
The indicated range is 0 - 90 mph.
Compliance: Accuracy is not in compliance with RG 1.97, Rev. 2 recommendations.
This instrumentation is in compliance with Dukes interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR, Section 1.11.5 Display: Two channels on the computer Two channels recorded Position: The instruments are adequate for the intended monitoring function as follows.
RG 1.97 Rev. 2 recommended range is 0-67 mph and McGuire meets this recommendation with a 0-90 mph range.
The recommended accuracy is +/-0.5 mph (for winds speeds less than 25 mph) and McGuire meets this recommendation with a +/-0.25 mph speed sensor. However, when the total loop uncertainty considers all components connected to the wind speed sensor, a resulting accuracy of +/- 1.12 mph (for wind speeds less than or equal to 25 mph) is calculated. For conversatism, this will be denoted as not in compliance with the RG 1.97 Rev. 2 recommendation.
The recommended starting threshold is less than 1.0 mph and McGuire meets this recommendation with a 1.0 mph starting threshold speed sensor.
E-17 Variable: Atmospheric Stability Range: -5° to 10°C RG 1.97 3 Recommended Category:
DPC Category: 3 Existing Design: The indicated range for atmospheric stability is -4° to 8°C for a 50 meter interval.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-6 (Page 42 of 42)
Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in McGuire FSAR Section 1.11.5.
Range and accuracy are not in compliance with RG 1.97, Rev. 2 recommendations.
Display: One computer point One channel recorded Position: The instruments are adequate for the intended monitoring function as follows.
RG 1.97 Rev. 2 recommended range is -5ºC to 10ºC.
McGuire does not meet this recommendation and has a -4ºC to 8ºC range.
The recommended accuracy is +/- 0.15ºC per 50 meter intervals. The McGuire atmospheric stability interval is 50 meters and this recommendation is met with a temperature sensor accuracy of 0.05ºC. However, when the total loop uncertainty considers all components connected to both atmospheric stability sensors, a resulting accuracy of +/-
0.19ºC is calculated. For conservatism, this will be denoted as not in compliance with the RG 1.97 Rev. 2 recommendation.
(13 OCT 2018)
McGuire Nuclear Station UFSAR Table 1-7 (Page 1 of 1)
Table 1-7. Deleted Per 2002 Update (27 MAR 2002)