ML20045D382

Forwards SSAR Markup,Replacing Markup in Addressing Draft FSER Open Item 1.2.6-1

ML20045D382
Person / Time
Site:	05200001
Issue date:	06/14/1993
From:	Fox J GENERAL ELECTRIC CO.
To:	Poslusny C Office of Nuclear Reactor Regulation
References
NUDOCS 9306280311
Download: ML20045D382 (9)

Text

.

GENuclear Energy.

~

GeneralDoctricCbmpany.

175 Curtner Avenue, San Jose, CA 95125

-ll 1

June 14,1993

' Docket No. STN 52-001 Chet Poslusny, Senior Project Manager Standardization Project Directorate--

Associate Directorate for Advanced Reactors and License Renewal.

Office of the Nuclear Reactor Regtdation

Subject:

Submittal Supporting Accelerated ABWR Schedule '- DFSER Open Item.

1.2.6-1

Dear Chet:

Enclosed is a SSAR markup which replaces the markup provided in my April 28,1993 letter addressing DFSER Open Item 1.2.6-1.

Please provide a copy of this transmittal to Jerry Wilson.

Sincerely,

• f Jack Fox Advanced Reactor Programs cc: Alan Beard (GE)

Norman Fletcher (DOE)

Bernie Genetti(GE) h.

240057

~

'9306290311 930614 DI PDR. ADOCK 05200001 l.

A-PDR

'Mkb 33A6100AC Standard Plant new c

1.1 INTRODUCTION

1.1.4 Type of License Required 1.1.1 Format and Content This ABWR SSAR is submitted in support of the application for final design approval (FDA)

The Advanced Boiling Water Reactor Standard and design certification (DC) for the ABWR Safety Analysis Report (ABWR SSAR), is written in Standard Plant.

accordance with Regulatory Guide 1.70. For consistency with NUREG-0800, the ABWR SSAR 1.1.5 Number of Plant Units includes Section 15.8 which addresses anticipated transients without scram and Chapter 18 which For the purpose of this document, only a addresses human factors. In addition, response to single standard plant will be considered.

TMI related matters is presented in Appendix 1A.

1.1.6 Description of Location The response to severe accident policy statement is provided in Chapter 19. Chapter 20 is This plant can be constructed at any location included to provide a question and response guide, which meets the pargneters identified in Chapter 2.

1.1.2 ABWR Standard Plant Scope 1.1.7 Type of Nuclear Steam Supply The ABWR Standard Plant includes all buildings which are dedicated exclusively or primarily This plant will have a boiling water reactor to housing systems and the equipment related to the nuclear steam supply system designed and supplied nuclear system or controls access to this equipment by GE and designated as ABWR.

and systems. There are five such buildings within the scope of the ABWR Standard Plant. These are:

1.1.8 Type of Containment (1) Reactor building (including containment);

The ABWR will have a low-leakage containment vessel which comprises the drywell and pressure (2) Service building; suppression chamber._ The containment vesselis a cylindrical steellined reinforced concrete structure (3) Controlbuilding; integrated with the reactor building. The containment nomenclature is specified in Figure (4) Turbine building; and 1.11.

(5) Radwaste building.

1.1.9 Core Thermal Power Levels ne information presented in this ABWR SSAR pertains to one reactor unit with a rated power level of 3926 MWt and a design power level of In addition to these buildings and their 4005MWt. The station utilizes a single cycle, contents, the ABWR Standard Plant provides the forced-circulation, boiling water reactor (BWR).

supporting facilities shown in Figure 1.2-1.

The heat balance for rated power is shown in

> 1 N S E P,T I. t. 2.

Figure 1.12. He station is designed to operate at 1.1.3 Engineering Documentation a gross electrical power output of approximately 1356 MWe and net electrical power output of Engineering documentation for the ABWR approximately 1300 MWe.

Standard Plant is listed on Master Parts List (MPL)

No.18NS07A03*. This MPL is a controlled list, structured by system, that contains the identification of hardware and software documentation that defines the ABWR Standard Plant.

• GE Proprietary 1.1-1 Amendment 9 l

1 Insert 1.1.2 The ABWR evolutionary design provides an essentially complete nuclear power plant except for site-specific elements. The site-specific elements are included as representative conceptual designs with interface requirements sufficient for the final safety analysis and design-specific probabilistic risk assessment in accordance with 10 CFR 52.47 (a) (1) (vii) and (b) (1). Unless other wise noted the following site specific elements are outside the scope of the ABWR standard design:

1)

Ultimate Heat Sink (9.2.5), interfaces with reactor service water (spray pond, conceptual) 2)

Offsite Power (8.2.4), transmission 3)

Makeup Water System (9.2.8), preparation 4)

Potable and Sanitary Water Systems (9.2.4), partial-5)

Reactor Service Water (9.2.15), rejects heat to the Ultimate Heat Sink, partial 6)

Turbine Service Water (9.2.14), rejects heat to the Power Cycle Heat Sink, partial 7)

Lighting and Servicing Power Supply (9.5.3), partial 8)

Communications (9.5.2), partial 9)

Site Security (13.6.2) 10)

Power Cycle Heat Sink (10.4.5.8), provides heat sink for the Circulating Water and Turbine Service Water systems ( cooling tower, conceptual) 11)

Circulating Water System (10.4.5.7), circulates power cycle water and supplies makeup water, partial

I

[

ll-t '

r 1 ; <

\\

h' W# %.qg.

Ni$

$Bga E

5o 4

l K

M T

L l

j ti l

l E

E N

R S

)

N K

3 0

Nc U

(

An K

O 1

To N

K' R l

l i

E P

I l

E EB A

CI M

N.

G l T OA

.U l

f A

G' A

AE I

W2P M

t

)

NGGW N

F I

EG Y

I NND GGI O

GA RN( N AI I E NN D K

T HR~

O O

T b NI Y

TDD I I L I

S CO N1 AT l

EDD U R I

Nl K OuU 4EEBE E i T I

ECTC l

T S

t MUU K

W TE E E

Ci CBB E

A L

ABB TOS SI NT T

l t L E EESB N LO EO G O A

A f lOO OT F

MR R R IRSINCA EE ALK PP O P BVWSD ME CI I

I CCT AANIN RRDUN RS AUETE EEOAUEAOO OE TQIRSRI I

RRCMTSRHC NDSEF F

O o1 2345 6

1 1 1 1 1 1

N 23456789t 1

g 6

g NA o2 L

1 P

E T

1 I

1 8

S 3

4 1

Yhg 1

-2 1

E i

4 R

c, U

o, 5

G t

I 3

F O

3 1

b g

s i

7 E*

I1!~ U

' 23A6100AJ Standard Plant am A i0.4.5 CirculatingWaterSystem each pump is fitted with a butterfly vtive. This arrangement permits isolation and maint' nance of e

The circulating water system (CWS) provides any one pump while the others remain in operation.

cooling water for removal of the power cycle waste heat from the main condensers and transfers this The circulating water system and condenser is heat to th timato cat sink.

designed to permit isolation of each set of the three Power cycle series connected tube bundles to permit repair of 10.4.5.1 Design Bases leaks and cleaning of water boxes while operating at reduced power.

10.43.1.1 Safety Design Bases The circulating water systtm includes water box j

The CWS does not serve or support any safety vents to help fill the condenser water boxes during function and has no safety design basis.

startup and removes accumulated air and othes gases from the water boxes during normal operation.

10.4.5.1.2 Power Generation Design Bases A chemical additive subsystem is also provided to Power Generation Desien Basis One - The CWS prevent the accumulation of biological growth and supplies cooling water at a sufficient flow rate to chemical deposits within the wetted surfaces of the condense the steam in the condenser, as required for system.

optimum heat cycle efficiency.

10.4.5.2.2 Component Description Power Generation Desim Basis Two. The CWS is automatically isolated in the event of gross leakage Codes and standards applicable to the CWS are into the condenser pit to prevent flooding of the listed in Section 3.2. The system is designed and l turbine building.

constructed in accordance with quality group D spec-ifications Table 10.4-3 provides design parameters 10 0.5.2 Description for the major components of the circulating water system.

10.4.5.2.1 General Description 10.43.2.3 System Operation The circulating water system is illustrated in Figure 10.4-3. The circulating water system consists The CWS operates continuously during power of the following components: screen house and generation including startup and shutdown. Pumps intake screens; pumps; condenser water boxes and and condenser isolation valve actuation is controlled piping and valves; tube side of the main condenser; by locally mounted hand switches or by remote water box fill and drain subsystem; and related manual switches located in the main control room.

support facilities such as for system water treatment and general maintenance.

The circulating water pumps are tripped and the gewer eve /g pump and condenser valves are closed in the event of The 4gtneat sink is designed to maintain a system isolation signal from the condenser pit the temperature of the water entering the circulation high-high level switches. A condenser pit high level water system within the range of 32 F to 100 F. The alarm is provided in the control room. The pit water circulating water system is designed to deliver water level trip is set high enough to prevent inadvertent to the main condenser within a temperature range of plant trips from unrelated failures, such as a sump 40 F to 100 F. The 40"F minimum temperature is

overflow, maintained, when needed, by warm water recircula-tion.

Draining of any set of series connected con-denser water boxes is initiated by closing the The cooling water is circulated by three fixed associated condenser isolation valves and opening speed motor driven pumps.

the drain connection and water box vent valve.

When the suction standpipe of the condenser drain The pumps are arranged in parallel and dis-pump is filled, the pump is manually started. A low charge into a common header. The discharge of level switch is provided in the standpipe, on the Amendment 21 104 9

33A6100AJ Standard Plant bA suction side of the drain pump. This switch will tion valves are interlocked with the circulating water automatically stop the pump in the event of low pumps so that when a pump is started,its discharge water levelin the standpipe to protect the pump valve will be opening while the pump is coming up to from excessive cavitation.

speed, thus assuring there is water flow through the pump. When the pump is stopped, the discharge 10.433 Evaluation valve closes automatically to prevent or minimize backward rotation of the pump and motor.

The CWS is not a safey-related system; however, a flooding analysis of the turbine building is Level switches monitor water levelin the con-performed on the CWS postulating a complete denser discharge water boxes and provide a permis-rupture of a single expansion joint. The analysis sive for starting the circulating water pumps. These assumes that the flow into the condenser pit comes level switches ensure that the supply piping and the from both the upstream and downstream side of the condenser are full of water prior to circulating water break and, for conservatism,it assumes that one pump startup thus preventing water pressure surges system isolation valve does not fully close.

from damaging the supply piping or the condenser.

Based on the above conservative assumptions, To satisfy the bearing lubricating water and shaft the CWS and related facilities are designed such that scaling water interlocks during startup, the circulating the selected combination of plant physical arrange-water pump bearing lubricating and shaft seal flow ment and system protective features ensures that all switches, located in the lubricating seal water supply credible potential circulating water spills inside the lines, must sense a minimum flow to provide pump turbine building remain confined inside the con-start permissive.

denser pit. Further, plant safety is ensured in case of multiple CWS failures or other negligible probability Monitoring the performance of the circulating CWS related events by the plant safety related gen-water system is accomplished by differential pressure eral floodmg protection provisions that are discussed transducers across each half of the condenser with in Section 3.4.

remote differential pressure indicators located in the main control room. Thermal element signals from 10.4.5.4 Tests and Inspections the supply and discharge sides of the condenser are transmitted to the plant computer for recording, The CWS and related systems and facilities are

. display and condenser performance calculations tested and checked for leakage integrity prior to p

,r c 9 c je, initial plant startup and, as may be appropriate, To prevent icing'and free p wnen the ambiem following major maintenance and inspection.

temperature of the _ tima e eat sink falls below 32 F, warm water from the discharge side of the All active and selected passive components of condenser is recirculated back to the screen house the circulating water system are accessible for intake. Thermat elements, located ia cach condenser inspection and maintenance / testing during normal supply line and monitored in the main control room, power station operation.

are utilized in throttling the warm water recirculation valve, which maintains the minimum inlet tempera-10.433 Instrumentation Applications ture of approximately 40 F.

Temperature monitors are provided upstream 10AJ4 Flood Protection and downstream of each condenser shell section.

A circulating water system pipe, waterbox, or Indication is provided in the control room to expansion joint failure,if not detected and isolated, identify open and closed positions of motor-operated would cause internal turbine building floodmg up to butterfly valves in the CWS piping.

slightly over grade level, with excess flood waurs potentially spilling over on site. If a failure occurred All major circulating water system valves which within the condensate system (condenser shell side),

control the flow path can be operated by local the resulting flood level would be less than grade level controls or by remote manual switches located on due to the relatively small hotwell water inventory the main control board. The pump discharge isola-relative to the condenser pit capacity. In either event the floodmg of the turbine building would not affect Amendment 26 10.4-10

i 33A6t00AJ Standard Plant

,,,3 P

safety related equipment since no such equipment is located inside the turbine building and all plant safety related facilities are protected against site surface water intrusion, tus E e r s 1,4. S. 7 Ano 10 f f ed 10.4.6 Condensate Cleanup System The condensate cleanup system (CCS) purifies and treats the condensate as required to maintain reactor feedwater purity, using filtration to remove suspended solids including corrosion products, ion exchange to remove dissolved solids from condenser leakage and other impurities, and water treatment additions to minimize corrosion / erosion product releases in the power cycle.

e I

l

(

1

(

I l

l t

)

10.4 10.1 Amendment 26

lN3f9T 10.4.5.7 Portions of the CWS Outside Scope of ABWR Standard Plant.

The portion outside the ABWR Standard Plant includes:

~

screen house and intake screens; pumps and pump discharge valves; and related support facilities such as nnkesp water system water treatment and general maintenance.

10.4.5.7.1 Safety Design Basis ( Interface Requirements) j None.

10.4.5.7.1 Power Generation Design Basis (Interface Requirements)

The COL applicant shall provide the following system design features and additional information which are site dependent:

sA

1) Conceptual design as described infection 10.4.5.2.

2) Evaluation perg b 3 ection 10.4.5.3 sob

3) Tests and Inspections per3section 10.4.5.4.

4) Instrument /pplications per%b3section 10.4.5.5.

sA

5) Flood [otection per3section 10.4.5.6.-

' l i

i s

-,w,__

JNSER 10.4.5.6 Power Cycle Heat Sink ( Conceptual Design ).

j I

I

'Ihe Power Cycle Heat Sink is outside the ABWR Standard Tlant Scope.

10.4.5,8.1 Safety Design Basis ( Interface Requirements)

{

None.

i

{

10.4.5.0.2.

t Power Generation Design Basis (Interface Requirements)

{

The COL applicant shall provide the following system

}

design features and additional information which are site dependent:

Sub

1) Conceptual design as described in,section 10.4.5.2.

2) Evaluation per,Lbsection 10.4.5.3 Sub

3) Tests and Inspections per section 10.4.5.4.

/

44

4) Instrument Applications per section 10.4.5.5.

54

5) Flood Protection per section 10.4.5.6.

s

/

i

,