LD-88-046, Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch

Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch

ML20150D989
Person / Time
Site:	05000470
Issue date:	06/30/1988
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Vissing G Office of Nuclear Reactor Regulation
References
LD-88-046, LD-88-46, NUDOCS 8807140271
Download: ML20150D989 (42)

Text

i l

l COMBUSTION ENGINEERING June 30,1988 LD-88-046 Docket No. STN 50-470F (Project No. 675)

Mr. Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Office of Nuclear Regulation Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Response to NRC Request for Additional Information Concerning Chapter 10, Plant Systems Branch

References:

(A) Letter, G. S. Vissing (NRC) to A. E. Scherer (C-E),

dated March 15, 1988.

(B) Letter, LD-87-068, A. E. Scherer (C-E) to F. J. Miraglia (NRC), dated November 30, 1987.

Dear Mr. Vissing:

Reference (A) requested that Combustion Engineering provide additional information concerning CESSAR-DC, Chapter 10. Enclosure (1) to this letter provides our responses, and Enclosure (2) provides the corresponding revisions to our submittal of Reference (B).

Should you have any questions, please feel free to contact me or Dr. M. D. Green of my staff at (203) 285-5204.

Very truly yours, COMBUSTION ENGINEERING, INC.

~

A '

A- E.Wehbe~r Director Nuclear Licensing AES:ss 00h

(

Enclosures:

As Stated cc: Frank Ross (DOE - Germantown) g l

l Power Systems 1000 Prospect Hill Road (203) 688 1911 Combustion Engineering. Inc. Post Ofhce Box 500 Telex: 99297 8807140271 880630 i

PDR ADOCK 05000470 K PDC .

Enclosure (1) to LD-88-046 Page 1 of 18 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTER 10, PLANT SYSTEMS BRANCH l

l s

i l

i 1

Enclosure (1) to LD-88-046 Page 2 of 18 Question 410.1. A Provide a legible large size copy of 1) Figure 10.1-1, Steam and Power Conversion System Flow Diagram, 2) Figure 10.1-3, Main Steam System Piping and Instrumentation Diagram, and 3) Figure 10.4.8-1, Steam Generator Blowdown System Flow Diagram. Also provide large legible copies of flow diagrams and piping and instrumentation diagrams for the main steam supply system (MSSS), main condenser (MC) and main vacuum system (MVS), turbine bypass system (TBS), condensate and feedwater system (CFS), and piping and instrument diagram for steam generator blowdown system (SGBS). The above drawings should include interfaces showing r,afety design classifications, plant-specific scolae information, piping sizes and tabulated process system parameters including flows, pressures and temperatures for the various operational modes.

Response 410.1. A Legible, large copies of Figures 10.1-1,10.1-3, and 10.4.8-1 are provided with this letter. With respect to the other drawings and information requested, some background information on the System 80+# Standard Design should help explain which information we are providing in CESSAR-DC.

The scope of the System 80+ Standard Design includes tha Nuclear Power

• Module (NPM) and Standardized Functional Descriptions (SFDs). The NPM includes the Nuclear Steam Supply System, the Emergency Feedwater System (EFWS), the Nuplex 80+# Control Center, and the Containment System. Our objective is to describe these systems in sufficient detail in CESSAR-DC such that NRC Staff can complete the review of the safety-related aspects of the design. It is recognized that plant safety will impose requirements on other plant systems. These other plant systems will, therefore, be described in SFDs in sufficient detail to enable the NRC Staff to complete the review of the plant design. The SFDs will contain a combination of design detail and, where such detail is not available, commitments to criteria which the NRC Staff will need to complete their review of the design. In this way, either detailed design information or acceptance criteria will be presented in CESSAR-DC for all safety-related components, systems, and maintenance or test procedures. Simply put, for systems covered by the SFDs, CESSAR-DC will be the document containing all the criteria necessary for the issuance of a site-specific license.

Enclosure (1) to LD-88-046 Page 3 of 18 The information presented (or, to be presented) in Chapter 10 of CESSAR-DC was (or, will be) developed in order to:

1. demonstrate compliance with the interface requirements from Chapter 5,

2. demonstrate compliance with the applicable EPRI ALWR Design Requirements ,

3. demonstrate compliance with tne safety analysis assumptions of Chapter 15 (to be provided in Submittal Group F),

4. demonstrate compliance with the assumptions in the Probabilistic Risk Assessment (to be provided in Submittal Group F),

5. provide a functional description of the main steam and power conversion systems, and

6. specify additional criteria which the NRC Staff will need to complete their review.

A future revision to Chapter 10 of CESSAR-DC will include Table 10.1-1 (Steam and Power Conversion System Design and Performance Characteristics), Figure 10.1-2 (Heat Balance for the Steam and Power Conversion System), and Table 10.3-1 (Main Steam Supply System Design Data) . Also, the Emergency Feedwater System, which is within the scope of the NPM, will be described in detail in Section 10.4.9. Combustion Engineering will provide whatever additional Chapter 10 revisions are required to support the review of the plant design and to establish the criteria for future reviews of the design for site-specific licenses.

• Heat balance calcualtions have not yet been completed.

1 7-Enclosure (1) to LD-88-046 Page 4 of 18 Question 410.1.B Provide rated capacity, design conditions including number required, pressure, temperature, flow, codes, and other related data in a tabulated form for safety-related system equipment and major piping for the steam and power conversion systems in the C-E scope including interface requirements for the plant-specific scope of supply.

Response 410.1.B Design parameters for safety-related equipment and major piping are summarized in Tables 10.1-1 and 10.3-1, which will be added to CESSAR-DC in a future revision. Please see the response to Question 410.1. A for an explanation of the basis for determining which information is presented in those tables.

Enclosure (1) .-

to LD-88-046 Page 5 of 18 Question 410.1.C Provide the following information (now shown as "later") in order to permit the staff to perform an integrated review of the steam and power conversion systems:

1) Table 10.1 Steam and Power Conversion System Design Performance Characteristics

2) Figure 10.1 Heat Balance for Steam and Power Conversion System

3) Section 10.2 - Turbine Generator Section 10.4.3 - Turbine Gland Sealing System Section 10.4.5 - Circulating Water System

4) Steam generator mass decrease data from zero percent to 100 percent load based on steady state conditions

5) Steam generator blowdown nozzles (hot leg and economizer) data for thermodynamic conditions Response 410.1.C

1) Table 10.1-1 (Ste:.m and Power Conversion System Design and Performance Characteristics) will be included in a future revision to CESSAR-DC.

2) Figure 10.1-2 (lieat Balance for Steam and Power Conversion System) will be included in CESSAR-DC after completion of the EPRI ALWR Requirements Document, Chapter 8. This figure is expected to be consistent with the EPRI Requirements.

3) CESSAR-DC, Sections 10.2,10.4.3, and 10.4.5, will be provided after completion of the EPRI ALWR Requirements Document, Chapters 8 and 13. These CESSAR-DC sections are expected to be consistent with the EPRI Requirements.

4) CESSAR-DC, Section 10.4.1.2(17), will be revised to indicate a steam generator mass decrease of approximately 103,500 pounds between zero percent and 100% load at steady state conditions.

5) Steam generator blowdown nozzle (hot leg and economizer) data, not yet available, will be provided in a later submittal.

Enclosure (1) to LD-88-046 Page 6 of 18 Question 410.2 Verify that the design of the MSSS includes the capability to operate the atmospheric dump valves locally or remotely following a station blackout so that a safe shutdown can be achieved independent of preferred and onsite emergency ac power in accordance with 10 CFR 50.63. Also, confirm that safety related electrical, instrumentation and control systems are provided for the atmospheric dump valves in order to comply with the BTP RSB 5-1 position regarding the capability to achieve a safe cold shutdown using only safety related equipment.

Response 410.2 Following a station blackout, the plant is maintained at hot standby until AC power (normal or emergency) is restored. Residual heat is removed through the steam generators by utilizing the steam driven emergency feedwater pumps and the main steam, ASME Code Section III, safety valves . Therefore, the atmospheric dump valves (ADVs) are not required during the actual period of station blackout. When AC power is restored, the ADVs are utilized to cool the plant to shutdown cooling system entry conditions.

Two 100% capacity steam driven pumps are provided in the Emergency Feedwater (EFW) System, along with two 100% capacity motor driven pumps. Each of the four pumps is capable of providing the minimum required flow of 500 GPM against a maximum steam generator downcomer nozzle pressure of 1217 PSIA. This head accounts for the steam generator design pressure, safety valve lift uncertainty, and feed nozzle losses from the downcomer nozzle to the steam generator steam space. All controls and valves required to operate in the steam driven EFW subtrains are powered with battery-backed Class 1E emergency power. The EFW System will be discussed in CESSAR-DC, Section 10.4.9.

The ADVs are provided with safety-grade electrical, instrumentation, and control systems in order to comply with BTP RSB 5-1. This is stated in CESSAR-DC, Section 10.3.2.3.3.2, as follows:

"1) Operator interface to the atmospheric dump valve control system is provided in the main control room (MCR) and at the remote shutdown panel (RSP). The following are provided:

l Enclosure (1) to LD-88-046 Page 7 of 18 o The capability to manually close and position the valve, o Valve position indication (both analog position and open/close indication lights).

2) No single failure of the control circuits prevents operation of at least one ADV on each steam generator. The control circuits are designed to the applicable parts of IEEE Std. 279-1971 and IEEE Std. 308-1974.

3) A safety-grade air pressure supply shall be provided to operate the ADV actuators should the normal air supply fail to be available. This safety-grade backup pressure supply may be a nitrogen supply or a Type A source of air as defined in ANS 59.3/N187 (1984) - Safety Criteria for Control Air Systems."

Enclosure (1) to LD-88-046  !

Page 8 of 18 Question 410.3 l Verify that the design of the secondary systems including MSSS, TBS, CFS, and SGBS are designed in accordance with BTP ASB 3-1 and MEB  ;

3-1 as related to the cracks and breaks in high- and moderate- energy piping outside of containment.

Response 410.3 Design of the secondary piping systems related to cracks and breaks in high- and moderate-energy piping outside containment will be addressed in CESSAR-DC, Chapter 3 (Design of Structures, Components, Equipment, and Systems). The design will be based on the application of leak-before-break, to the extent possible, as described in the EPRI ALWR Requirements Document, Chapter 1, Section 4 and Appendix A.

Enclosure (1) to LD-88-046 Page 9 of 18 Question 410.4 Demonstrate that the main steam isolation valve (MSIV) and main feedwater isolation valve (MFIV) closure times are in accordance with SRP Section 15.0 accident analysis assumptions.

Response 410.4 A closure time of 5 seconds or more for the Main Steam Isolation Valves and Main Feedwater Isolation Valves, as described in CESSAR-DC, Section 10.3.2.3.2.1, will be assumed in the safety analysis.

t Enclosure (1) to LD-88-046 Page 10 of 18 Question 410.5 Confirm that the MSSS design includes the capability to detect and control MSSS system leakage and isolate portions of the system in case of excessive leakage or component malfunctions.

Response 410.5 CESSAR-DC, Section 5.4.5.3. A, states the following:

"The main steam isolation valves are capable of isolating the steam generators within 5.0 seconds after receiving a signal from the Engineered Safety Features Actuation System. In the event of a steam line break, this action prevents continuous uncontrolled steam release from more than one steam generator. This protection is provided for breaks either inside vr outside the containment."

A rupture of a main steam line is detected by the Engineered Safety Feature Actuation System, as discussed in Section 7.3. A Main Steam Isolation Signal (MSIS) automatically shuts the Main Steam Isolation Valves (MSIV), Main Steam Isolation Valve Bypass Valves, and the power operated valves located in any main steam line drain located upstream of the MSIVs.

This prevents continuous uncontrolled steam release from more than one steam generator. This is discussed in Sections 10.3.2.2.8, 10.3.2.3.2.1, and 10.3.2.3.3.1. In the event a rupture occurs upstream of the MSIVs and a single failure of a MSIV on the other steam generator prevents it from closing, blowdown of both steam generators is prevented by isolating all steam paths downstream of the MSIVs on MSIS, or the blowdown through a non-isolated path is shown to be acceptable. This is described in Section 10.3.2.2.12.

A MSIS will be generated by one of the following:

o Low steam generator pressure.

Enclosure (1) to LD-88-046 Page 11 of 18 o Ifigh steam generator water level in either steam generator.

o High containment pressure.

Section 10.3.2.3.2.' describes the MSIVs and the MSIV Bypass Valves.

Section 10.3.2.3.3.1 describes the MSIV controls.

1 1

N

- s ..w-v e -- --- - - , -nem.-- ,, m--, , - ..,-,.e.,ve, --m.-,-, . - _ ,, wm --,-,--r,-,--g,,.y,-~ w _w.,,,,-- _ -nne- ,

m-,, ,3rn-r

Enclosure (1) to LD-88-046 Page 12 of 18 Question 410.6 Verify that measures have been provided to detect radioactive leakage into and out of the main condenser system and to preclude unacceptable releases of radioactive materials to the environment from the system.

Response 410.6 Measures have been provided to detect leakage into and out of the main condenser system and to preclude unacceptable releases of radioactive materials to the environment. These measures include the following:

o Monitoring of the steam jet air ejector discharge (CESSAR-DC, Section 10.4.2.2, will be reviced to describe this) and o Sampling of steam generator blowdown radioactivity

[CESSAR-DC, Section 10.4.8.1 (Steam Generator Blowdown System Design Basis) and Table 9.3.2-1 (Process Sampling Requirements Normal Operation)].

i-i Enclosure (1) .

to LD-88-046 l Page 13 of 18 Question 410.7

. Verify that the design includes protection of safety related equipment from flooding resulting from a complete failure of the main condenser circulating water system.

Response 410.7 Protection of safety related equipment from flooding resulting from a complete failure of the main condenser circulating water system will be addressed in CESSAR-DC after the completion of the EPRI ALWR Requirements Document, Chapter 8. The CESSAR-DC sections which address the above concern are expected to be consistent with the EPRI Requirements.

i 4

...r. , , nn, - - - -. , - - ,, -, -- - - ----. -

Enclosure (1) to LD-88-046.  ;

Page 14 of 18 )

Question 410.8 i

Verify that the main condenser evacuation system '(MCES) design conforms l to the requirements o7 General Design Criteria (GDC) 60 and 64 with regard to control and monitoring of releases of radioactivity to the i environment. .

Response 410.8 The Main Condenser Evacuation System design will conform to General

- Design Criteria 60 and 64 with regard to the control and monitoring of releases of radioactivity to the environment. To address the monitoring of '

primary to secondary leakage, the cteam jet air ejector discharge w!11 be continuously monitored for radiation. CESSAR-DC, Section 10.4.2.2, will t'e revised to reflect this.

g; m ,

Enclosure (1) to LD-88-046 Page 15 of 18 Question 410.9 Verify that the steam bypass capacity of the TBS is consistent with

, reactor transient analysis in accordance with the criteria of SRP Section 4.4.

Response 410.9 The steam bypass capacity of the Turbine Bypass System (TBS) is consistent with reactor transient analyris. The capacity (55%) in terms of percent of full power steam flow is tised as input to these analyses. [The TBS capacity for the System 80+D is the same as that for the System 80 R design, as described in CESSAR-F. ]

Enclosure (1) to LD-88-046 Page 16 'of 18 Question 410.10 Verify that the CFS'is designed in accordance with the guidance contained in BTP ASB 10-2 to eliminate or reduce possible fluid flow instabilities (e.g. , water hamme' =) .

Response 410.10 The Condensate and Feedwater System (CFS) is designed in accordance with the guidance contained in BTP ASB 10-2 to eliminate or reduce possible flow instabilities (e.g. , water-hammers). In addition, the System 80+ U CFS meets the intent of the EPRI ALWR Requirements Document.

Fluid flow instabilities such as water-hammer are minimized as a result of the following design features:

o The feedwater distribution ring inside the steam generator (see Figure 5.4.2-1) is located:

1) below the normal water level, reducing (a) the probability that the distribution ring will be uncovered and (b) the time the distribution ring is uncovered, and

2) below the downcomer feedwater nozzle, minimizing the potential for the feed ring to drain and become filled with steam.

l o The feedwater distribution ring flow holes are located in the l top of the distribution ring, which is located in the steam f generator downcomer region, to minimize draining.

L o A 90-degree elbow, facing downward, inside the steam generator, is attached to each feedwater nozzle to minimize the horizontal run of feedwater piping.

o The cavitating venturis restrict the emergency flow rate to each steem generator (Section 10. 4. 9.1. 2. G ) .

l . - - , . .. __ .~ _ _ _ _ _ . _. . _ . . _ _ , _ . , _ , , _ _ _

Enclosure (1) to LD-88-046 Page 17 of 18 o The Emergency Feedwater (EFW) System piping in the vicinity of the steam generators is arranged to minimize the potential for destructive water-hammer during system startup (Section 10. 4. 9.1. 2. M) . The EFW pipe continuously rises 'as it penetrates the containment to connect with the downcomer feedwater pipe which enters the steam generator.

After the two lines connect, the downcomer feedwater pipe continues to rise to prevent draining into the steam generator with the feedwater flow shutoff. It then connects to a 90-degree elbow facing downward, which is attached to the downcomer nozzle.

m Enclosure '(1) to LD-88-046 Page 18 of 18 Question 410.11 Identify these features of the CFS which are provided to improve its reliability and thereby reduce tite number of challenges to safety. related

- systems.

Response 4,10.11 Features of the Condensate and Feedwater System that are provided to improve reliability include:

1. Standby Condensate, Condensate Booster, and Feedwater Pumps (Section 10.4.7.2),

2. Ability to ride through loss of feedwater pump transient using reactor power cutback (Section 7.7),

3. Deaerating Feedwater Tank, (Figure 10.1.1), and

4. Full range automatic feedwater control (Section 7.7).

7_

Enclosure (2) to LD-88-046 Page 1 of 19 r

PROPOSED REVISIONS TO THE COMBUSTION ENGINEERING STANDARD SAFETY ANALYSIS REPORT l

l

Enclosure (2)

CESSARinaemo, kafi*$ #

qg wea TABLES 10.1-1 Steam and Power Conversion System Desian

[

andPerformancecharacteristics{wE 10.3.5-1 Operating Chemistry Limits for Secondary A Steam Generator Water 10.3.5-2 Operating Chemistry Limits for Feedwater and condensate l

Amendment A 11 September 11, 1987

. _ _ . - _ . . - _ _ _ . - _ - . _ _ .. . - ,_ . . _ - . . _ . . . . - . - _ . . . . - - . - = - . _ - . - - . ..-.

Enclosure (2) to LD-88-046 d"

CESSAR !!nhuon P"o G R Wo.1 _

Two turbine and two electric driven emergency feedwater punps are provided to assure that adequate feedwater will be supplied to the steam generators in the event of loss of the main and startup feedwater pumps. The Emergency Feedwater System is discussed in Subsection 10.4.9.

The safety related portions of the Steam and Power Conversion System are as follows:

a. Emergency Feedwater System, including main feedwater isolation valves and piping to steam generators,

b. Main steam isolation valves, including piping from steam generators,

c. Atmospheric dump valves.

d. Safety relief valves.

e. Steam supply to Emergency Feedwater System.

f. Feedwater main isolation valves including piping from steam generators.

Means are provided to monitor and prevent the discharge of A radioactive material to the environment to insure that technical specifications are met under normal operating conditions or in the event of anticipated system malfunctions or fault conditions.

Figures 10.1-1 , 10.1-2 and 10.1-3 provide an overall system flow diagram and heat balance. See the site specific SAR for additional detailed information.

--- .e , _ , -> , , - -

- _,_. _, m_ mz_,, m, c . -

a -- : 71 More detailed information will be provided on system connections and instrumentation when Chapters 7, 8 and 18 are submitted.

Amendment A 10.1-2 September 11, 1987

I Enclosure (2) en851; '

@R Wo. /

TABLE 10.1 1 STEAM AND FCWER CCNVERSION SYSTEM.0tstan "hD ?ERFGRMANCE CHARACTERi575c5

~

1\e

~

[/1S&

-hdole on Gbs es.

(L. i-R) 12 kene. men No. 12 Septem:er 11, 1;a7

, . . _ . _ _ . _ . , _ , . . - . . _ - - _ _ - _ . , , _ . . _ , . - _ _ , _ ,,-_ .,m._., __- _.x.- .._ , . , , - . . . , ~ .

1 Enclosure (2) to LD-88-046 Pege 5 of 19 Q/R 410.1 T ABLE 10.1-1 (Sheet 1 of 4)

STEAM AND POWER CONVERSION SYSTEM DESIGN AND PERFORMANCE CHARACTERISTICS Desistn and Performance Characteristics Value Main steam system design pressure / 1200/570 temperature, psia /'F Main steam system nominal operating 1000/544.6 pressure / temperature, psia / F (at steam generator) 6 Main steam nominal flow,10 lb/hr 17.12 Main feedwater temperature, *F 450 (+0 -10) 6 Main feedwater nominal flow 6 10 lb/hr 17.29 Downcomer nominal flow,10 lb/hr 1.71 Economizer nominal flow,10 lb/hr 15.58 Steam generator blowdown system, .2%/1%/10% of nominal flowrate, normal / abnormal /high maximum steam rate System / Component Performance Characteristics Main Steam System (Section 10.3)

Main steam piping From each steam generator up to and including the main steam isolation valves: ASME III, Code Class 2.

(design pressure 1200 psia, design temperature 570 F, Seismic Category I)

Balance of the main steam piping:

ANSI B31.1.0 w - -.--me- - - - - .u-e. - g --. e--e- , - - .~ .e- - -y--q-ey--w 3,

---gr

Enclosure (2) to LD-88-046 PCge 6 of 19 Q/R 410.1 TABLE 10.1-1 (Cont'd)

(Sheet 2 of 4)

STEAM AND POWER CONVERSION SYSTEM DESIGN AND PERFORMANCE CHARACTERISTICS System / Component Performance Characteristics Main steam isolation valves Maximum closing time 5 seconds after (1 per steam line) receipt of signal. ASME III, Code Class 2 valves. (design pressure 1200 psia, design temperature 570 F, Seismic Category I)

Main steam safety valves Total sgam safety valve flow rate is 19 x 10 lb/hr; set pressure in accordance with Article NC-7000 of ASME Section III. ASME III, Code Class 2 valves. (maximum accumulation pressure 1320 psia, design temperature 570 F, Seismic Category I)

Atmospheric dump valves Saturated steam flow not less than (1 per steam line) 950,000 g/hr but not more than 1.9 X 10 lb/hr. ASME III, Code Class 2 velves. (design pressure 1200 psia, design temperature 570'F, Seismic Category I)

Turbine Bypass System (Section 10.4.4)

Bypass valves downstream of Flow capacity equal to 55% of design main steam isolation valves steam flow: Piping ANSI B31.1.0 l (design pressure 1200 psia, design temperature 570 F, non-Seismic Category I).

I i

l t

Enclosure (2) to LD-88-046 Page 7 of 19 Q/R 410.1 ,

TABLE 10.1-1 (Cont'd)

(Sheet 3 of 4)

STEAM AND POWER CONVERSION SYSTEM DESIGN AND PERFORMANCE CHARACTERISTICS System / Component Performance Characteristics Condensate and Main

. Feedwater System (Section 10.4.7)

Feedwater pumps 3-50% turbine driven; 1 in standby Feedwater booster pumps 3-50% motor driven; 1 in standby Condensate pumps 3-50% motor driven; -

. 1 in standby Low pressure feedwater heaters 4 stages of low pressure feedwater heating. 1/3 total feedwater flow per string Deserator 100% of total feed flow High pressure heaters 2 stages,1/2 total feed flow per string Condensate and Main Feedwater Piping in main steam support structure System piping to downstream feedwater isolation valves

- ASME III, Code Class 2; Feedwater isolation valves and piping from feedwater isolation valves to steam generators - ASME III, Code Class 2 (Seismic Category I).

Balance of the condensate and main feedwatei piping: ANSI B31.1.

F

Enclosure (2) to LD-88-046 Page 8 of 19 Q/R 410.1 TABLE 10.1-1 (Cont'd)

(Sheet 4 of 4)

STEAM AND POWER CONVERSION SYSTEM DESIGN AND PERFORMANCE CHARACTERISTICS System / Component Performance Characteristics Emergency Feedwater System Two Seismic Category I motor-driven (Section 10.4.9) emergency feedwater pumps and two steam turbine-driven emergency feedwater pumps, each 500 gal / min design capacity. Two emergency fe=dwater storage tanks storing 350,000 gallons feedwater.

All piping from the emergency fecdwater storage tank to the Seismic Category I emergency feedwater pumps and containment isolation valves is ASME III, Code Class 3; piping from and including the isolation valves to the steam generators is ASME III, Code Class 2, Seismic Category I.

Secondary Chemistry Control Full flow condensate demineralization.

System (Section 10.4.6) Continuous hydrazine additions for oxygen scavenging and continuous ammonia additions for pH control.

Continuous monitoring of significant chemical parameters. Continuous steam generator blowdown at a rate up to 1%

of the maximum steaming rate.

OVERSIZE DOCUMENT PAGE PULLED -

~

SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS .

APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-8989 l

.i A

l I

i

~

m" * ,

li JN"

\ i

\

\ l 1

\ / / s\

1

/j e- .

ec 9 ,e e .

be e ee eC ee ee d55a 3 nU' /! i lp V

gP I i

!P

'j=

x a' I [ s t

~ 0 y-m-

I = -

/ L s;

~ T.

ii  !

.A

[ . . b1dlY/

} p >< >< I me -

1 $'

ki

_8

=

i

>? ><

VM -

i  ;

I n i 1g s qgm

,e 4

f i

=

hp

>g>e

!g5r8

_ . 4

• I n 1b U

a_91 r [

m )Q

!i fh yCe -

I LgC6 e

I f

Qr [g yi -

a ii 9t,  !

{

1e5tt- i i e*

2n2g a i b

ao a5_

o= anir

. e;-

" " *"y" Enclosure (

to LD-88-OL/6 r..._ Page 9 or 19 7

- ~-.. _

a p t.>.' . . . y e s ;__ _ _ _

.3_

m ,

T '

8 8: 1- g.g_ _

l T

w-

@ t')y 3 ll---__.. _ _ _ _ _

+  !

g . p_ : : ,____.,_______,g.. ,

w

'N v y ,

_ .Tr . .. ~ i

. . _ . - - an . < - - -

Jr. .. _

. . T l

. s

- . - m,ue g ess l l

) [ dan,: o f

,___.___________,e-

f. ,

- , - & w --.

2c%

~m,

,,, l, l III l _.] , ,? iT., l

, i

,--_&_. l l j f]=%.

__ w l l  !

J I. Q  !

k, ,, O- litrIi i

s 1

\ \/ l  :

ll en m.- l ,

, , j

._, x x _. , i

. L. 4: ~ s l

l l a l .

! 6~ ,

l D-< s s y s s l 1  ! I L _1_ _._. _ j i l f *-}

[

r

,\lT,tll'OllIS

-' "{  ; N, ,

1 1 Im a: RD s e D-s n .

n n

-~

'- ~

i j

{r . :q.

-e-~

~{ -

f x

l Also Available On

- > - - ~_.

l; l l Aperture Card

,. o- 1: ,

-. ,% g.f, i .

i_. _. ________;

t#M m Figure STEAM AND POWER CONVERSION SYSTEM JMfg /*/ FLOW DI AGR AM 10.1 1 OPoo/s e a7/- ov~'

Enclosure (2) to LD-88-046 Page 11 of 19 Q/R 410.1 TABLE 10.3-1 (Sheet 1 of 2)

MAIN STEAM SUPPLY SYSTEM DESIGN DATA Component Parameter _

Main Steam Piping:

6 Nominal steam flow,10 lb/hr 17.12 Number of main steam lines 4 Pipe size, O.D. inches 28 Design pressure, psig 1200 Design temperature. *F 570 Pipe material carbon steel Main Steam Isolation Valves:

Number per main steam line 1 Total nuruber required 4 Atmospheric Dump Valves Number per main steam line 1 Total number required 4 Design relieving capacity per valve 6

(minimum / maximum),100% open,10 lb/hr (at 1,000 psia) 0.95/1.9 Minimum controllable capacity per valve, Ib/hr (at 1,100 psia) 63,000

Enclosure (2) to LD-88-046 P:go 12 of 19 Q/R 410.1 TABLE 10.3-1 (Cont'd)

(Sheet 2 of 2)

MAIN STEAM SUPPLY SYSTEM DESIGN DATA Component Parameter Main Steam Safety Valves: i Minimum total relieving capacity, 6

10 lb/hr 19 Maximum relieving capacity per valve (at 1,000 psia),106 lb/hr 1.9 i

, - . . , , - . , - - . - _ _ _ . , , _ _ , , - . - - - - - - , . . - - - , , . , , , . , , , , , , - - , . . . - - , . _ , , . , - .--,-n-,---. - ,,- , - , _

Enclosure (2)

CESSAR !!!Memon jaleM*7fs

$N WN

10) The condenser and circulating water system are designed to permit isolation of a portion of the tubes (segmented ,

condenser) to permit repair of leaks and cleaning of water boxes while operating at reduced power.

11) The condenser is capable of being filled with water for a hydrotest. Provisions are made to allow draining and cleaning of the hotwell.

12) A stainless steel expansion joint and a water seal trough between the condenser and the turbine are provided.

13) An automatic condenser cleaning system is provided.

14) Heater shells and piping installed in the condenser neck are located outside of the turbine exhaust steam high velocity regions and within the limits specified by tho turbine supplier. Internal piping is as short and straight as possible and all steam extraction piping slopes downward toward the heater shells.

15) Sections of heater shells and piping that are located inside the condenser and normally operated with a full load inside temperature of about 90'C (194 ' F) or more shall be lagged.

The lagging is made of stainless steel at least 1/16" thick and is designed consistent with proven practice.

16) The condenser neck fluid design is based on air tests, ,

modelling the steam flow path from the LP turbine exhaust hoods to the condenser tube bundles. The test model accounts for the condenser neck heaters and associated piping and for the neck major structural elements, lines and baffles. The tests cover all major operating modes including operation with steam bypass dump and operation with one tube bundle out of service.

17) The change in liquid inventory in the steam generators, as plant load changes, is considered in designing the Condensate System and sizing the condenser hotwell. On a M steady state basis, the steam generator mass decreases by I ggf8 t 'T R} pounds between o percent and 100' percent load.

10.4.1.3 Safety Evaluation The main condenser is normally used to remove residual heat from the Reactor Coolant System during the initial cooling period after plant shutdown when the main steam is bypassed to the condenser by the Turbine Bypass System. The condenser is also

! used to condense the main steam bypassed to the condenser in the event of sudden load rejection by the turbine generator or a turbine trip.

Amendment A 10.4-3 September 11, 1987

Enclosure (2)

CESSAR 8necmo,. lag'ed*71s q g 40 6 ed 410. 8

b. Maintain adequate condenser vacuum for proper turbine oparation during startup and normal operation.

10.4.2.2 gystem Descriotion The Main vacuum System consists primarily of vacuum pumps and steam jet air ejectors (SJAE) which are used to pull a vacuum on the main condenser. See the site-specific SAR for detailed information and an overall system flow diagram.

There is no direct connection between the Main Vacuum System and the Reactor Coolant System; therefore, normal function of one wilj not directly affect the other.

10.4.2.3 Safety Evaluation 2nurf01 A

The system is not assigned a safety class as it serves no plant safety function. It is not required for safe shutdown of the plant.

10.4.2.4 Tests and Insoections The system is fully tested and inspected before initial plant operation and is subject to periodic inspections after startup.

System performance will indicate proper function of the system and any system malfunction will be corrected by appropriato means. See the site-specific SAR for additional test and inspection applications.

10.4.2.5 Instrument Acolication The Main vacuum System includes sufficient instrumentation to assure proper operation. All of the instrumentation for this system is operating instrumentation and nonc is required for safe shut-down of the reactor. See the site specific SAR for i additional instrumentation applicationc.

10.4.3 TURBINE GLAND SEALING SYSTEM (Later - pending completion of EPRI Chapter 13) A 10.4.4 TURBINE BY! ASS SYSTEM

{ 10.4.4.1 Des _ tan Bases

! The turbine bypass system has no safety functions. The turbine bypass system, operating in conjunction with the reactor power cutback system (Section 7.7.1.1.6), is designed to accomplish the following functions:

Amendment A i

- - vu=s ,

I Enclosure (2) '

to LD-88-046 -

Page 15 of 13  ;

Qf 4{O'b i Nl0'S INSERT 1 The steam jet air ejector air dir. charge is continuously monitored for radiation. 3 F

b f

D e

4 i

1 .

.r

.i.

i.

D 9

4 Y-a 1

k I'

i >

l .

+

L i,

o I

j.  !

f-l

1 Enclosure (2) i to LD-88-046 i

• • 6 # 9 CESSAR :necmo,.

Q R Hl0 l _

2. Steam generator pressure as a function of power is given in Figure 10.4.7-2.

3. Feedwater temperature at 100% power is 450' +0

• F/~10

• F.

4. Feedwater temperature is equal to or greater than 200'F prior to initiation of feedwater flow to the economizer nozzles during plant startup. The 200*F feedwater temperature is achieved prior to reaching 15% power. All feedwater at a temperature lower than 200'F is directed to the downcomer feedwater nozzle. This does not include post turbine trip conditions.

5. The feedwater flow split between the economizer nozzles and the downcomer nozzle throughout ascent in power is shown on Figure 10.4.7-3.

6. The Main Feedwater System provides the proper flow to the steam generators under the operating and design conditions contained in Section 7.7.1.1.4, Feedwater Level Control System.

7. The chemistry requirements of Section 10,3.5 apply during all phases of plant operation including startup, hot standby and cooldown. g g, ( g g

8. The change in liquid inventory in the steamkenerators, as plant load changes, amounts to a decrease of @IJ pounds between 0 percent and 100 percent load. In designing tha condensate System and sizing the condenser hotwell, this difference is considered.

A

9. Plant operation can continue at reduced power with loss of one operating feedwater pump.

10. Plant operation can continue at 100% power with loss of one operating condensate or feedwater booster pump.

11. The feedwater and condensate system is designed to avoid erosion damage. The design and layout of piping systems considers the effect on the piping material from fluid velocity, bend location and the location of flash points.

The following velocity limits are recommended: P a) Pipe velocity 5 20 ft/ sect b) Feedwater heater inlet flow velocity 5 12 ft/sec; and, c) Condensate pump suction line velocity 5 5 ft/sec.

Amendment A 10.4-14 September 11, 1987

Enclosure (2) to LD-88-046

"*** ' # *9 CESSAR !!ninemon Q R 4f0 'I _

See the site-specific SAR for additional test and inspection requirements.

10.4.7.5 Instrumentation Acclications A Feedwater flow control instrumentation measures the feedwater flow rate from the condensate and feedwater system. This flow measurement, transmitted to the feedwater control system, regulates the feedwater flow to the steam generators to meet system demands. Refer to Section 7.7.1.1.4 for a description of the feedwater control system.

10.4.8 STEAM GENERATOR BLOWDOWN SYSTEM 10.4.8.1 Desian Basis The design bases for the Steam Generator Blowdown System are:

a. Maintain proper steam generator shell side water chemistry as outlined in Section 10.3.5 by removing non-volatile materials due to condenser tube leaks, primary to secondary tube leaks, and corrosion that would otherwise become more concentrated in the shell side of the steam generators,

b. Process steam generator blowdown for reuse as condensate.

c. Enable blowdown concurrent with steam generator tube leak (s) or radioactivity present on the secondary side without release of radioactivity to the environment.

d. Process a continuous steam generator blowdown rate of 0.2% or 1% of the full power main steam flow. A

e. Continuously sample the radioactivity of the steam generator blowdown.

f. Isolate the blowdown lines leaving the Containment upon a Containment Isolation Signal, Main Steam Isolation Signal, or Emergency Feedwater Actuation Signal.

10.4.8.2 System Description A continuous high flow blowdown controls the concentration of impurities in the steam generator secondary side water. A general schematic of ( m u32 blowdown system is shown in Figure 10.4.8-1.

\&

Amendment A 10.4-20 September 11, 1987

Enclosure (2)

LD 0 44 Page 18 of 19 I

e, ,s 0

f g' :t>

"Y" W

~

0-il 0-i:

m

_ 1

.i..,

[

4%

4,y

_ .i .

0-i; 0-i:

=

^v^

y+....

l M*:n l

This figure indicates minary design concept and cont etails that may j

change duri fina esign process, l

1 m ws

L -

M., T

== x .::.u .

(H:

j m...

l i ,

I i l ' - - - - - -<H: l'i,4 i

I l

..,--a.

l l ="- . , .

Il ..,,...,

g g 7 i

,1s1 a'- i i ~\PEUTURE V V l

CARD l

y ,usi Available On y me Apertiire Caril

. . . . .(,) ,,

m Figure STEAM GENER ATOR BLOWDOWN SYSTEM Jg / FLOW DIAGRAM 10.4,8 1 3F09/3 0 9 7/- 03 -

. Enclosure (2)

- to LD-88-046 Page 19 of 19 QlR 410.2, 410.10 Section 10.4.9 - Emergency Feedwater System (To Be Submitted as Part of Submittal Group CJ