ML17191A306

Updated Final Safety Analysis Report - List of Effective Pages Current Through, Revision 0

ML17191A306
Person / Time
Site:	Dresden
Issue date:	07/10/2017
From:	Commonwealth Edison Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML17191A306 (30)

Text

DRESDEN - UFSAR i

LIST OF EFFECTIVE PAGES I CURRENT THROUGH REVISION 0 This List of Effective Pages identifies those text pages, tables and figures that are currently effective in the FSAR.

Revision Pagefl'able/Figure No. Revision 1-i 0 F 1.2-4 0 1-ii 0 F 1.2-5 0 1-iii 0 F 1.2-6 0 1-iv 0 F 1.2-7 0 F 1.2-8 0 1.1-1 0 F 1.2-9 r 0 1.1-2 0 F 1.2-10 0 1.1-3 0 F 1.2-11 0

('\_ F 1.2-12 0 T 1.1-1 Sheet 1 0 ~ F 1.2-13 0 T 1.1-1 Sheet 2 0 F 1.2-14 0 T 1.1-1 Sheet 3 0 F 1.2-15 I 0 F 1.2-IE/ 0 1.2-1 F 1.2-17 0 1.2-2 F 1. ~18 0 1.2-3  :-.1 F H2-16 0 1.2-4 F .2-17 0 1.2-5 0 1.2-6 0 1.2-7 1.2-8 0 1.2-9 0 1.2-10 0 1.2-11 0 1.2-12 0

\..J 0 1.2-13 0 1.2-14 0 1.2-15 1.2-16 1.2-17 1.2-18 1.2-19 1.2-20 ~

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T 1.2-1 Sheet 1 0 T 1.2-1 Sheet 2 0 1.9-1 0 T 1.2-1 Sheet 3 0 1.9-2 0 T 1.2-1 Sheet 4 0 1.9-3 0 T 1.2-1 Sheet 5 0 1.9-4 0 T 1.2-1 Sheet 6 0 T 1.2-1 Sheet 7 0 2-i 0 2-ii 0 F 1.2-1 0 2-iii 0 F 1.2-2 0 2-iv 0 F 1.2-3 0 I

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Pagefl'able/Figure No. Revision Pagefl'able/Figure No. Revision 3.1-10 0 3.1-63 0 3.1-11 0 3.1-64 0 3.1-12 0 3.1-65 0 3.1-13 0 3.1-66 0 3.1-14 0 3.1-67 0 3.1-15 0 3.1-68 0 3.1-16 0 3.1-69 0 3.1-17 0 3.1-18 0 3.2-1 0 3.1-19 0 3.2-2 0 3.1-20 0 3.2-3 0 3.1-21 0 3.2-4 0 3.1-22 0 3.2-5 0 3.1-23 0 3.2-6 0 3.1-24 0 3.2-7 0 3.1-25 0 3.2-8 0 3.1-26 0 3.2-9 0 3.1-27 0 3.1-28 0 3.3-1 0 3.1-29 0 3.3-2 0 3.1-30 0 3.3-3 0 3.1-31 0 3.3-4 0 3.1-32 0 3.3-5 0 3.1-33 0 3.3-6 0 3.1-34 0 3.3-7 0 3.1-35 0 3.3-8 0 3.1-36 0 3.3-9 0 3.1-37 0 3.3-10 0 3.1-38 0 3.1-39 0 F 3.3-1 0 3.1-40 0 F 3.3-2 0 3.1-41 0 3.1-42 0 3.4-1 0 3.1-43 0 3.4-2 0 3.1-44 0 3.4-3 0 3.1-45 0 3.4-5 0 3.1-46 0 3.4-6 0 3.1-47 0 3.4-7 0 3.1-48 0 3.1-49 0 3.5-1 0 3.1-50 0 3.5-2 0 3.1-51 0 3.5-3 0 3.1-52 0 3.5-4 0 3.1-53 0 3.5-5 0 3.1-54 0 3.5-6 0 3.1-55 0 3.5-7 0 3.1-56 0 3.5-8 0 3.1-57 0 3.5-9 0 3.1-58 0 3.5-10 0 3.1-59 0 3.5-11 0 3.1-60 0 3.5-12 0 3.1-61 0 3.5-13 0 3.1-62 0 3.5-14 0

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Page/Table/Figw;e No .. Revision Page/Table/Figure No. Revision 3.5-15 0 3.7-25 0 3.5-16 0 T 3.7-1 0 T 3.5-1 Sheet 1 0 T 3.7-2 0 T 3.5-1 Sheet 2 0 T 3.7-3 0 T 3.5-2 0 T 3.7-4 0 T 3.5-3 0 T 3.7-5 0 T 3.5-4

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F 3.8-24 0 3.9-30 0 F 3.8-25 0 3.9-31 0 F 3.8-26 0 3.9-32 0 F 3.8-27 0 3.9-33 0 F 3.8-28 0 3.9-34 0 F 3.8-29 0 3.9-35 0 F 3.8-30 0 3.9-36 0 F 3.8-31 0 3.9-37 0 DRSLEP.NEN/1293 5

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T 4.4-2 0 F 4.6-12 0 F 4.6-13 0 F 4.4-1 0 F 4.6-14 0 F 4.4-2 0 F 4.4-3 0 5i 0 F 4.4-4 0 5ii 0 F 4.4-5 0 5iii 0 5iv 0 4.5-1 0 5v 0 4.5-2 0 5vi 0 4.5-3 0 5vii 0 4.6-1 0 5.1-1 0 4.6-2 0 5.1-2 0 4.6-3 0 4.6-4 0 T 5.1-1 Sheet 1 0 4.6-5 0 T 5.1-1 Sheet 2 0 4.6-6 0 T 5.1-1 Sheet 3 0 4.6-7 0 T 5.1-2 0 4.6-8 0 4.6-9 0 F 5.1-1 0 4.6-10 0 4.6-11 0 5.2-1 0 4.6-12 0 5.2-2 0 4.6-13 0 5.2-3 0 4.6-14 0 5.2-4 0 4.6-15 0 5.2-5 0 4.6-16 0 5.2-6 0 4.6-17 0 5.2-7 0 4.6-18 0 5.2-8 0 4.6-19 0 5.2-9 0 4.6-20 0 5.2-10 0 4.6-21 0 5.2-11 0 4.6-22 0 5.2-12 0 4.6-23 0 5.2-13 0 4.6-24 0 5.2-14 0 4.6-25 0 5.2-15 0 4.6-26 0 5.2-16 0 4.6-27 0 5.2-17 0 5.2-18 0 T 4.6-1 0 5.2-19 0 5.2-20 0 F 4.6-1 0 5.2-21 0 F 4.6-2 0 5.2-22 0 F 4.6-3 0 5.2-23 0 F 4.6-4 0 5.2-24 0 F 4.6-5 0 5.2-25 0 F 4.6-6 0 5.2-26 0 F 4.6-7 0 5.2-27 0 F 4.6-8 0 F 4.6-9 0 T 5.2-1 0 F 4.6-10 0 T 5.2-2 0 DRSLEP.NEN/1293 8

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DRESDEN - UFSAR Table 1.1-1 (Continued)

• POL ACRONYMS AND INITIALISMS provisional operating license ppm parts per million psi pounds per square inch ps1a pounds per square inch, absolute psid pounds per square inch, differential ps1g pounds per square inch, gauge PWR pressurized water reactor RBCCW reactor building closed cooling water RCPB reactor coolant pressure boundary RETS Radiological Effiuent Technical Specifications RHRS residual heat removal system RPS reactor protection system RPV reactor pressure vessel RWCU reactor water cleanup

• SAR SBGTS SEP SER safety analysis report standby gas treatment system systematic evaluation program safety evaluation report SLC standby liquid control SNP Siemens Nuclear Power (formerly ANF)

SRP Standard Review Plan SRV safety relief valve sws service water system TBCCW turbine building closed cooling water TIP traversing incore probe TLD thermoluminescent dosimeter TMI Three Mile Island TSC technical support center UHS ultimate heat sink USI unresolved safety issue

• (Sheet 3 of 3)

DRESDEN - UFSAR The steam dryer and separator assemblies are transferred to a special storage pit.

Water is added to the storage pit to provide shielding - usually a few inches of water in the bottom is sufficient, since it covers the parts of the separator which have been adjacent to the top of the core and which have been the most heavily irradiated.

Spent fuel discharged from the reactor is transferred under water into racks provided in the storage pool. The storage pool is designed to accommodate the channel stripping operation and the many other fuel maintenance operations that are required. Storage space is also provided in the pool for irradiated fuel assembly channels and control rods and for small internal components of the reactor.

New fuel is brought in through the equipment entrance of the reactor building and hoisted to the upper floor utilizing the reactor building crane. The new fuel for both Units 2 and 3 is stored in the new fuel vault located adjacent to the Unit 2 refueling pool area within the reactor building.

1.2.2.9 Turbine System The saturated steam leaving the reactor vessel flows through four carbon steel steam lines to the turbine located in the turbine building. After passing through the turbine, the low pressure steam is condensed, the noncondensible gases are removed, and the condensate is demineralized before being returned to the reactor through. the feed water heaters .

• 1.2.2. ro Electrical System The electrical output of the units is fed into a 345-kV switchyard and from the yard to CECo's networkgrid system via six 345-kV transmission lines and six 138-kV transmission lines. The 138-kV transmission lines receive power from the Dresden units through 345-kV to 138-kV transformers via a 138-kV switchyard. Auxiliary power is supplied from the respective units themselves, from the 345-kV switchyard (for Unit 3), or from the 138-kV switchyard (for Unit 2). A diesel-generator (DG) system provides emergency power.

Batteries are used for all controls which are vital to unit and station safety, for emergency lighting, and as a power supply for certain functions required for unit shutdown, such as closing of isolation* valves, driving motors, and opening valves for ECCS. A separate battery supplies the neutron monitoring equipment to monitor the core during shutdown.

1.2.2.11 Shielding, Access Control, and Radiation Protection Procedures Control of radiation exposure of plant personnel and people external to the plant is accomplished by a combination of radiation shielding, control of access into certain

• areas, plant ventilation systems, and administrative procedures. The requirements of 10 CFR 20 are used for establishing the basic criteria and objectives.

1.2-14

DRESDEN - UFSAR 1.2.3 Summary of Technical Data Design features and data appropriate to achieve a reactor thermal output of 2527 MW are summarized in Table 1.2-1. Since some of the parameters in Table 1.2-1 are cycle-specific (depending on fuel type and core configuration), typical values have been provided.

1.2.4 Interaction of Units 1. 2, and 3 The objective followed in designing Units 2 and 3 is that each unit would operate independently of the other. A malfunction of equipment or operator error in either of the two units would not affect the continued operation of the remaining unit. A high degree of station reliability is accrued from the standpoint of continuity of power for the operation of standby equipment through the operation of a multi unit generating station.

1.2.4.1 Gaseous Waste Effiuents The 300-foot chimney for Unit 1 is used to discharge Unit 1 ventilation air, from those systems still in operation .. The 310-foot chimney is used to discharge Units 2 and 3 off-gas, radwaste building ventilation air, turbine building ventilation air, and the effiuent from the standby gas treatment system. A stack on top of the reactor building is used to discharge the Units 2 and 3 reactor building ventilation air, except when the standby gas treatment system is used. Fixed release limits are not imposed on the individual chimneys or stack; rather, the aggregate release from both chimneys and the reactor building vent stack is limited.

Continuous monitoring of steam jet air ejector (SJAE) off-gas is provided for both units. Each unit's monitoring system has *indication, recording capability, and annunciation in the control room upon receipt of a high-radiation signal. A high-high radiation signal closes* off-gas system chimney isolation valve.*

Both chimneys and the reactor building vent stack have release level indication, recording, and high-level annunciation in the control room. The monitors provide high-range monitoring (i.e., are designed to measure the release level in a design basis accident) for particulates, iodine, and noble gases. In addition to conventional recorders, the computerized monitors *also have a sliding 21-day memory and can be programmed to sum the releases from the various points or present the data in various ways.

1.2.4.2 Liquid Waste Effiuents Units 2 and 3 share an intake structure and canal for river water to their respective turbine condensers. However, Units 2 and 3 each have their own circulating water systems. Both the Unit 1 and Unit 2/3 intake canals obtain their water from the Kankakee River.

1.2-17

DRESDEN - UFSAR Since Unit 1 has excess compressor capacity, the crosstie provides a backup air

• supply for both Units 2 and 3. The crossties also proviQ.e operating flexibility between the three units with regard to maintenance of the service air compressors on any of the units.

The only reactor system equipment operated by this air system are valves, which

• are fail-safe. Loss of instrument _and service air causes safe plant shutdown.

1.2.4.4.3 Service Water System The service water system is a Unit 2 and 3 combined facility that is provided with*

a common 50% capacity backup.

1.2.4.4.4 Reactor Building Ciosed Cooling Water System The reactor building closed cooling water systems for Units 2 and 3 are intertied.

The operating flexibility of both cooling systems is enhanced by the use of the interties.

1.2.4.4.5 Turbine Building

• The Unit 2 and 3 turbines are housed in a single turbine building. The turbine building supply and exhaust ventilation systems are operated as a combined system.

1.2.4.4.6 Reactor Containment Units 2 and 3 have separate primary containments and pressure suppression systems but share a common secondary containment (reactor building). Units 2 and 3 also share the same SBGTS and ventilation systems, each having sufficient capacity to accommodate the combined secondary containment volume.

1.2.4.4. 7 Demineralized Water Makeup System Makeup water is obtained from the 200,000-gallon well water tank,demineralized, and discharged either to two 200,000-gallon tanks on Unit 1 or to two*

250,000-gallon tanks which serve both Units 2 and 3.

1.2.4.4.8 Control Rooms

• The control rooms for Units 1, 2, and 3 are adjacent and open to each other. Since Unit 1 is no longer in service only those instruments and controls of 1.2-19