RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System

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Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
ML16357A526
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Site: Byron, Braidwood  Constellation icon.png
Issue date: 12/15/2016
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Exelon Generation Co
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Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
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RS-16-248
Download: ML16357A526 (156)


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B/B-UFSAR 10.1-1 REVISION 9 - DECEMBER 2002 CHAPTER 10.0 - S TEAM AND POWER C ONVERSION SYSTEM 10.1

SUMMARY

DESCRIPTION

10.1.1 System Layout Equipment arrangement and fluid flows are shown diagrammatically in Figure 10.1-1 along with ma jor line sizes and safety categories. Table 1 0.1-1 summarizes i mportant desig n features and safety aspects.

Figure 10.1-2a and 10.1-2b are the heat balance diagrams for the uprated pow er conditions.

The units are designed to operate under the econom ic generation control system.

10.1.2 Design

After passing through the turbine, the steam exhausts into the shell side of a condenser, where the normal average backpressure is approximately 3.5 in. Hg abs. The condensed steam is pumped via condensate/condensate booster and feedwater pumps through seven stages of feedwater heating and back to the steam generators. In its passage th rough the turbin e, the steam undergoes a moisture separation and reheatin g process; portions of the steam are extra cted from the main tur bine to the feedwater heaters for regenerative heating of the feedwa ter. The steam is condensed in the main condenser by circulating w ater flowing through the condenser tu bes; the heat added to the circulating water is then rejected to a natural draft cool ing tower at Byron Station, and a cooling lake at Braidwood Sta tion, before the water returns to the main condenser.

The steam and power co nversion system is a closed cycle.

Condensate is drawn from the hot well of the cond enser and pumped via the condensate pumps through the steam jet air ejector condensers and gland steam condensers. This condensate is pumped via the condensate boo ster pumps through four stages of low pressure feedwater heaters. This flow is then m ixed with the discharge of the heater drain pu mps and the combined flow passes through a fifth and si xth stage of low pressure feedwater heaters. From this point the wa ter is pumped via the feedwater pumps through one stage of high pressure feedwater heaters through the feedwater re gulating valves to t he steam generator.

In the steam gen erators the feedwate r is converted to steam. The steam exits the steam generators via the main steamlines which are equipped with po wer-operated atmosph eric relief valves, safety valves, and i solation valves. From this point the steam passes via piping inside a tunnel through combination stop and

throttle valves and go vernor valves to t he high pressure turbine. High pressure turbine exhaust is r outed through two stage moisture s eparator reheaters, rehe at stop valves, and interceptor valves to the low pressu re turbine.

B/B-UFSAR 10.1-2 REVISION 7 - DECEMBER 1998 Throughout the portion of the steam cycle downstream of the isolation valves, steam is extra cted at various poin ts to operate auxiliaries and to sup ply heat to the co ndensate and feedwater heaters. Steam used f or these purposes is r eturned to the cycle for reuse.

Steam exhausted from the low pressure turbine at approximately 3.5 in. Hg is condensed to condensate in a sur face type condenser and the condensate drains to the hotwell whe re the cycle begins again. 10.1.3 Governing Desi gn Codes for Steam and Power Conversion System The design of piping , valves, containment penetrations, and equipment on the steam gener ator side of the containment isolation valves, incl uding the isolation valv es, in both the main steam and feedwater lines is Safety Category I, Quality Group B. The design of piping, valves, and equipment in the remainder of the ste am and power convers ion system is Safety Category II, Quality Group D.

10.1.4 Instrumentation Instrumentation systems for the normal opera ting conditions of the steam and condensate systems are designed in accordance with

accepted secondary cycle design for safe and r eliable control, requirements for performance calculations, and periodic heat balances. Instrumenta tion for the secon dary cycle are also provided to meet recommendations by the turbine supplier and ASME Standard No. TWDPS-1 Part 2, 197 3, "Recommended Prac tices for the Prevention of Water Damage to Steam Turbines." Other recommendations by the NSSS supplier for prevention of water hammer in the steam gene rator are also part of t he design bases.

Continuous sampling syst em instrumentation and grab sample points are provided for maintaining acc eptable limits of water chemistry in the secondary cycle as required by the NSSS and turbine suppliers. Condense r conductivity sam pling is provided for tube/sheet leakage detec tion to meet r equirements to identify and promptly isolate leaka ge in the condenser.

Safety-related instrumen tation systems f or steam generator level and main steamline press ure are designed and s upplied by the NSSS supplier and identified in Chapter 7.0.

B/B-UFSAR 10.1-3 TABLE 10.1-1 STEAM AND POWER CONVERSION SYSTEM DESIGN FEATURES ITEM SAFETY-RELATED COMMENTS Main Steam Piping Yes Pipi ng is Safety Category I from steam generators to and

including main steam

isolation valves. The

remainder of the piping is

Safety Category II.

Main Steam Relief and Safety Valves Yes Safe ty Category I Steam Generator Blowdown System Yes System is Safety Category I from the steam generators to

the outermost containment

isolation valve. The

remainder of the system is Safety Category II.

Main Turbine No Switch c ontacts are provided as interface with Reactor Protection System in event

of turbine trip.

Generator No Turbine Protection System No

Reheat Steam System No Condenser No Turbine Steam Dump System No Turbine Gland Sealing System No Main Condenser Evacuation

System No Circulating Water System No

Condensate System No B/B-UFSAR 10.1-4 TABLE 10.1-1 (Cont'd)

ITEM SAFETY-RELATED COMMENTS Feedwater System Yes Feedwa ter lines are Safety Category I between the FW

bypass isolati on valves and the steam generators.

B/B-UFSAR REVISION 5 - DECEMBER 1994

Attachments 10.A and 10.B have been deleted intentionally.

B/B-UFSAR

ATTACHMENT 10.C

AN EVALUATION OF THE A UXILIARY FEEDWATER SYSTEM SECTION 10.4.9 OF THE STANDARD REVIE W PLANS AND BRANCH TECHNICAL POSITION ASB 10-1

B/B-UFSAR 10.C-i TABLE OF CONTENTS SECTION SUBJECT 10.C.1 Evaluation to the Stan dard Review Plan Section 10.4.9 10.C.2 Evaluation to the Bran ch Technical P osition ASB 10-1

B/B-UFSAR 10.C-1 REVISION 13 - DECEMBER 2010 10.C.1 An Evaluation of the Auxiliary Feedw ater System to Section 10.4.9 of the Standard Review Plans (for ESF Pump Trains Only)

The evaluation of th e auxiliary feedwater system to the guidance of Section 10.4.9 of the Standard Rev iew Plans is provided in the subsections that follow. Each subsection identifies a separate recommenda tion and provides a response that shows compliance with that recommendation.

10.C.1.1 Recommendation System components and pi ping have sufficient physical separation or s hielding to protect the

essential portions of the system from the effects of internally and extern ally generated missiles.

Response Byron/Braidwood system components and piping satisfy physical separation and shielding requirements relating to internally and externally generated missiles.

See Subsections:

3.5.1.1 Internally Gen erated Missiles (Outside Containment), 3.5.1.4 Missiles Generated by Natural Phenomena, 3.5.1.5 Missiles Generated by Events Near the Site, 3.5.1.6 Aircraft Hazards, 3.5.2 Systems to be Protected, and 3.5.3 Barrier Desi gn Procedure.

10.C.1.2 Recommendation The system satisfies the recommendations of Branch Technical Position ASB 3

-1 with resp ect to the effects of pipe whip and jet impingement that may result from high or moderate energy piping breaks or cracks (in this regard the AFS is considered to be a high energy system).

Response The auxiliary feedwater system is not used for normal startup and shutdown at Byron and Braidwood and is, therefore, considered to be a moderate e nergy system and satisfies BTP ASB 3-

1. See Section 3.6 and Subsection 10.4.9.2.

B/B-UFSAR 10.C-2 10.C.1.3 Recommendation The system and components satisfy design code requirements as appr opriate for the as signed quality group and seismic classifications.

Response Byron/Braidwood Stat ion system and c omponents satisfy design code requirements for assigned quality group and seismic classifications.

See Subsections:

10.4.9.1 AFW System D esign Basis and 10.4.9.2 AFW System Description.

10.C.1.4 Recommendation The failure of nonessential equipment or components does not affect essential functions of t he system.

Response Nonessential systems int erfacing with the auxiliary feedwater system are:

1. The condensate storage tank: Failure of the condensate storage tank or suction lines is accommodated by essential service water backup supply to each auxiliary feedwater pump suction.
2. Station air system: F ailure of the air system is accommodated by failing air operated flow control valves open on loss of air. Therefore, failure of nonessential equipment does not affect the essential fun ctions of th e auxiliary feedwater system.

10.C.1.5 Recommendation The system is capable of withstanding a single active failure.

Response The auxiliary feedwa ter system is capable of withstanding a singl e active failure.

B/B-UFSAR 10.C-3 See Subsections:

7.2.2.2.3b Single Failure Criteria (Electrical),10.4.9.2 AFW System Des cription (Mechanical), and Table 10.4-4 Failure Modes and Effects Analysis.

10.C.1.6 Recommendation The system possesses diversity in mo tive power sources such that system performance requirements may be met with either of the assigned power sources, e.g., a

system with an a-c s ubsystem and a r edundant steam/d-c subsystem.

Response The auxiliary feedwa ter system possess es diversity in motive power sources and the capability for feeding two or more unfaulted steam ge nerators at the required rate concurrent with a single active f ailure. In the event of loss of both onsite and offsite a-c power, the diesel-engine driven pump will deliver feedwater

to the steam generators.

See Subsections:

10.4.9.1 AFW System Design Basis, 10.4.9.2 AFW System Description, and 7.3.1.1.6 AFW System Operation.

10.C.1.7 Recommendation The system precludes the occurrence of fluid flow instabilities, e.g., water hammer, in system inlet piping during no rmal plant operation or during upset or accident conditions (see SRP Section 10.4.7).

Response Byron/Braidwood auxiliary fe edwater system includes water hammer prevent ion capabilities.

See Subsections:

10.4.7.3 Water Hammer P revention Features and 10.4.9.3.1 Auxiliary Feed water System General Safety Evaluation.

B/B-UFSAR 10.C-4 10.C.1.8 Recommendation Functional capability is assured by suitable protection during abnorm ally high water levels (adequate flood protection considering t he probable maximum flood).

Response The functional capabilities of systems a re assured as stated in Section 3.4.

10.C.1.9 Recommendation The capability exist s to detect, collect, and control system leakage and to isolate portions of the system in case of excessive leakage or component

malfunctions.

Response Pump seal leakage is directed to the auxiliary building equipment drain system. Visual periodic inspections will provide indication of system leakage. The piping and valving in the auxiliary feedwater system is suff iciently diverse to allow component isolation for malfunction and repair while still maintain ing the essentia l functions of the auxiliary fe edwater system.

10.C.1.10 Recommendation Provisions are made for operational testing.

Response Provisions are made for operational testing of Byron/Braidwood Stations aux iliary feedwater as outlined in Subsection 10.4.9.4.

10.C.1.11 Recommendation Instrumentation and control fe atures are provided to verify the system is ope rating in a correct mode.

Response Technical Specifications require verification by flow demonstration or va lve position verification for proper operating ali gnment. Instrumentation is available to verify syst em alignment by either means from the contr ol room. See Su bsection 10.4.9.5.

B/B-UFSAR 10.C-5 10.C.1.12 Recommendation The system is capable of automatically initiating auxiliary feedwater flow upo n receipt of a system actuation signal.

Response The auxiliary feedwater system is capable of automatic initiation.

See Subsections; 10.4.9.3.1 AFW System Gener al Safety Evaluation, 7.3 Engineered Safety Features Actuation System, 7.2.1.1.2.e Low-low Steam Generator Water Level Trip. 10.C.1.13 Recommendation The system satisfies the recommendations of Regulatory Guide 1.62 with respect to the system capability to ma nually initiate prot ective action by the auxiliary fee dwater system.

Response The commitment to comp ly with the intent of Regulatory Guide 1.62 is fou nd in Appendix A, page A-1.62-1.

10.C.1.14 Recommendation The system design poss esses the capability to automatically termin ate auxiliary feedwater flow to a depressurized steam generator and to automatically provide feedwater to t he intact steam generator.

Response The flow orifices in the aux iliary feedwater lines automatically limit flow to a depressurized steam generator and ensure flow to unaffected steam generators. See Sub section 10.4.9.3.1.

10.C.1.15 Recommendation The system possesses suf ficient auxiliary feedwater flow capacity so that a cold shutdown can be achieved.

B/B-UFSAR 10.C-6 REVISION 10 - DECEMBER 2004 Response Subsection 10.4.9.1 states a minimum of approximately 212,000 gallons is necessary to cool down to residual heat removal system in itiation. Technical Specification 3.7.6 states the limiting condition for operation for the condensate storage tank. This limit is based on a sufficient volume of water in the condensate storage tank to meet the design basis requirements for cooldow n, and includes the time needed for completio n of placing residual heat removal (RHR) into service.

In addition, su fficient water volume is available from the essential s ervice water system to achieve cold shutdown.

10.C.1.16 Recommendation The Applicant's proposed techn ical specifications are such as to assure the continued reliab ility of the AFW during plant operati on, i.e., the limiting conditions for opera tion and the surveillance testing requirements are specified and are con sistent with those for other similar plants.

Response Byron/Braidwood Technical Specifications have been developed from the Sta ndard Specifications for Westinghouse plants.

B/B-UFSAR 10.C-7 10.C.2 An Evaluation of the Auxiliary Feedw ater System to Branch Technical Position ASB 10-1 (for ESF Pump Trains Only)

The evaluation of the auxiliary feedwater sy stem to the guidance of Branch Technical Position ASB 10-1 is provided in the subsections that follows. E ach subsection identifies a separate recommendation and prov ides a response that shows compliance with the recommendation.

10.C.2.1 Recommendation The auxiliary feedwa ter system shoul d consist of at least two full-capacity, ind ependent systems that include diverse power sources.

Response Byron/Braidwood auxiliary fe edwater system consists of one 100% capacity emer gency a-c powered motor-driven pump and one 100% cap acity diesel driven pump (capable of supplying water independent of a-c power availability).

See Subsections:

10.4.9.1 AFW System Design Basis, 10.4.9.2 AFW System Description, and 10.4.9.3 AFW System S afety Evaluation.

10.C.2.2 Recommendation Other powered components of the auxiliary feedwater system should also u se the concept of separate and multiple sources of motive e nergy. An example of the required diversi ty would be two se parate auxiliary feedwater trains, each c apable of removing the afterheat load of the re actor system, having one separate train power ed from either of two a-c sources and the othe r train wholly p owered by steam and d-c electric power.

Response Motor-operated valve s in each auxiliary feedwater train employ div ersity in power supplies. All motor- and air-o perated valves e mploy the same diversity of supplies. This diversity is discussed in Subsection 10.4.9

.3 In addition, Chapter 8.0 specifically add resses electrical power from all aspects applicable to train separation and diversity of power. All motor-o perated and air-operated

B/B-UFSAR 10.C-8 REVISION 9 - DECEMBER 2002 valves are normally open, with the exc eption of essential service water suction and recirculation valves which are normally closed.

10.C.2.3 Recommendation The piping arrangeme nt, both intake and discharge, for each train should be des igned to permit the pumps to supply feedwater to any combination of steam generators. This arrangemen t should take into account pipe failure, active com ponent failure, power supply failure, or control system f ailure that could prevent system function.

One arrangement that would be acceptable is crosso ver piping contain ing valves that can be operated by remote manual control from the control room, using the power diversity principle for the valve operators and actuation systems.

Response A common header in the s uction to the AFW pumps

exists where the supply lines from the condensate storage tank combine. The line then splits to supply suction to the indiv idual AFW pumps.

A common header exists where the auxiliary f eedwater ent ers the steam generator. This is downstre am of the flow control valves on the discha rge of the pumps (see Drawing M-37). Any of the A FW pumps can be aligned to supply any of the steam gen erators by operating motor-operated valves fr om the control room.

10.C.2.4 Recommendation The auxiliary feedwa ter system shoul d be designed with suitable redundancy to offset the consequences of any single active component failu re; however, each train need not c ontain redundant act ive components.

Response See response to Item 10.C.1.5.

10.C.2.5 Recommendation When considering a high ener gy line break, the system should be so arranged as to assure the capability to supply necessary emergency f eedwater to the steam generators, despite the postul ated break of any high energy section of the sy stem, assuming a concurrent single activ e failure.

B/B-UFSAR 10.C-9 REVISION 7 - DECEMBER 1998 Response See response to Item 1 0.C.1.2 of the previous

section.

7 1998 24[0 a4-1.D.361.0.REVISION DECEMBER GLAND SEAL STEAM SUPPa-Y BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT STOP VALVES STOP THROTTLE VALVESFROMMSRI-l1E&1W EXTRACTION FROM H.F?TURBINE EXTRACTION TO L.P.HEATERS 5A,58 EXTRACTION TO H.P.HEATERS 714..78 TO MOISTURE SEPARATOR REHEATER IE FEED MTER PUMPS FLASH TANt<.!-fEArER DRAIN TANK PUMPS\.EXTRACTION FROM LP.TURBINE'J(lO&FROM L.P.Hm'JA&DR.AlN COOtER 18 5.'lOW PRESSURE TURBINE"8-TURBINE

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STC4,M Ol.!Mp TO CONDENSER 30'FROM MSRH IE-.: c.."'ONDENSATE PUMPS C1RCUlAT1NG WATE TO CONDENSER D A c FIGURE 10.1-1 STEAM, CONDENSATE, AND FEEDWATER PIPING-UNIT 8 7 1998 24[0 a4-1.D.361.0.REVISION DECEMBER GLAND SEAL STEAM SUPPa-Y BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT STOP VALVES STOP THROTTLE VALVESFROMMSRI-l1E&1W EXTRACTION FROM H.F?TURBINE EXTRACTION TO L.P.HEATERS 5A,58 EXTRACTION TO H.P.HEATERS 714..78 TO MOISTURE SEPARATOR REHEATER IE FEED MTER PUMPS FLASH TANt<.!-fEArER DRAIN TANK PUMPS\.EXTRACTION FROM LP.TURBINE'J(lO&FROM L.P.Hm'JA&DR.AlN COOtER 18 5.'lOW PRESSURE TURBINE"8-TURBINE

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REVISION 9 -DECEMBER 2002 B/B-UFSAR Figures 10.2-4 through 10.2-7 have been deleted intentionally.

REVISION 12 -DECEMBER 2008 B/B-UFSAR REVISION 9 - DECEMBER 2002 Figure 10.3-1 has been deleted intentionally.

B/B-UFSAR REVISION 9 - DECEMBER 2002 Figures 10.4-1 through 10.4-2 have been deleted intentionally.

140000 120000 REVISION 9 DECEMBER 2002 80000 60000 40000 20000 sa'LOW-LOW LEVEL REACHED AT 47 SECONDSAUX FEED COMMENCES AT 102 SECONDS I V TURNAROUND

-2048 SECONDSo 10 1 10 2 10 TIME (SECONDS)3 10 4 10 BYRON/BRAIDWOOD STATIONS Updated Final Safety Analysis Report FIGURE 10.4-3 STEAM GENERATOR MASS VS.TIME LOSS OF MAIN FEEDWATER REVISION 9 DECEMBER 2002 Intact Faulted 140000-.--------------------------------,-------nMEOFBREAK J , ,\\\TURNAROUND

-3956 SECONDS I v---SG LOW-LOW LEVEL\REACHED AT 32 SECONDS->\

20000 120000 (/)(/)100000 c(:2 II: 0..80000 c(-II: E WlJ Z;.W 60000 CJ:2 c(W..40000 (/)\o 10 I 10 2 10 TIME (SECONDS)3 10 4 10 BYRON/BRAIDWOOD STATIONS Updated FInal Safety Analysis Report FIGURE 10.4-4 STEAM GENERATOR MASS VS.TIME FEEDLINE BREAK WITH OFFSITE POWER AVAILABLE