ML20236E925

From kanterella
Jump to navigation Jump to search
Nonproprietary Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 16, Probabilistic Safety Study
ML20236E925
Person / Time
Site: 05000601
Issue date: 09/30/1987
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19304B645 List:
References
NUDOCS 8710300066
Download: ML20236E925 (35)
v • d • e


Text

_ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _

p i WESTINGHOUSE CLASS.3 AMENDMENT 3 TO RESAR-SP/90 PDA MODULE 16 O PROBABILISTIC SAFETY STUDY l

O 1 O

O O

l[k0 ADohn 0 ji A

O WAPWR-PSS AMENDMENT 3 5960e:1d SEPTEMBER, 1987

AMENDHENT 3 TO RESAR-SP/90 PDA MODULE 16 Instruction Sheet o Insert pages 720-27 through 720-30 after 720-26 of Amendment 2. y o Insert Attachments E through I after Attachment D of Amendment 2. j o Insert Figures 720.46 (A-C) after series of foldouts from Amendment 1.

l O

L-O O

O WAPWR-PSS AMENDHENT 3 E960e:Id SEPTEMBER, 1987

, a REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROBABILISTIC SAFETY STUDY ,"

RESAR SP/90 i l'

720.39 Provide an inventory of elements for 40 species in k (p. 4, STCP User's Guide (MOD 1)) NUREG/CR-4587, July 1986)g [per Table 1 RESPONSE: ,

See Attachment E for fission product inventories.

O 720.40 Provide engineering drawings of: "

i) Reactor cavity and junction flow areas; }-

ii) Reactor building. cross-sections (concrete only) showing wall penetrations; iii) Elevation floor plans; iv) Overall' ventilation system for the reactor building; and v) The 4-V MAAP nodalization illustrating junction flow area, structure heat sink composition, areas and thicknesses, and junctionelevations.

RESPONSE

Later - Reactor Containment design parameters. ~

720.41 Provide the containment failure pressure distribution or mean and standard deviction as used in the PSS. .

RESPONSE

A failure pressure of containment design,+(a,c) was used for the APWR containment. In view of the recent Sandia containment ultimate pressure capacity tests, this is a very ,

conservative assumption. There was no distribution of failure pressures vs. probability of failure used in the probabilistic safety study, and therefore no mean or assceiated standard deviation. This was necessary due to the preliminary state of developunt of the containment design at the time of the performance of the core and containment analysis. ,

O  ;

WAPWR-PSS 720-27 AMENDMENT 3 ',.

5794e:1d SEPTEMBER, 1987  ; ..

1;

  • j l

1

,n 720.42 What;is the PORV capacity per valve at design pressure (Table 5.4-13)?

% j RESPONSE: l The'. relief capacity ofthepressurizerPORV' sat 2385psigis[ ]+(a,c) lb/hr. per valve. This value could change during the FDA design stage.

tq V

720.43 What is the probability of restoration of AC power as a function of i time from accident initiation?

l OG I

RESPONSE

The value for " probability of restoration of AC power as a function of time from accident initiation" used for ,the SP/90 PDA PRA was 50%

recovery within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This was conservatively based on Table 3.2 of l EPRI report NP-2301, " Loss of Offsite Power at Nuclear Power Plants, )

Data and Anal,ysis," 1982, which is included here as Attachment F.

720.44 If the containment fails by overpressure, what is the likely failure mode, failure location (s), and area of the breach?

l O>

% RESPONSE:  !

An overpressure failure of the APWR containment was assumed to consist of a failure of the containment in the upper compartment. The area associated with such a failure was assumed to be +(a c) 720.45 Do sprays survive a hydrogen burn? What is the probability of their successful operation?

RESPONSE _:

Sprays will survive a hydrogen burn. The successful operation of the containment sprays is unaffected by a hydrogen burn because the spray water is capable of absorbing a large amount of the heat generated during a hydrogen burn.

o Y

WAPWR-PSS 720-28 AMENDMENT 3 5794e:1d SEPTEMBER, 1987

,; w

'l I

y 720.46 Provide the following detailed output from the MAAP calculations: l i)'The transient output in table form and plots for TE, SE, and )

SEFC; j ii) The molar gas concentrations in the four compartments; )

iii) The temperature of the gas and of the surrounding structure in l q the tour compartments; iv) The containment leak rate; Qi- .

v) The gas release rate from corium/ concrete interactions and the j

total. release; 4 vi) The aerosol generation rate in corium/ concrete interactions- 1 vii) The fraction of I, Cs, and Te released in-vessel prior to vessel e failure, retained. in-vessel after vessel failure, and the

(~

ex-vessel release to containment after vessel failure; also revaporization from vessel after vessel failure as a function of time; and viii) The temperature of corium as a function of time. l

RESPONSE

Detailed output from the MAAP Code is not available in al1 of the specific forms and/or for the specific quantities requested. Output is available and is provided for : molar gas concentrations (item ii)

- Attachments G, H & I; temperature of gas (item iii) - Figures O

y 720.46 iii A, B & C; temperature of corium (item viii) -

Figures 720.46 viii A, B & C.  ;

720.47 What is the penetration size and failure mode due to over-temperature?

?

RESPONSE

No specific failure mode was identified for over-temperature failure of the APWR containment. For over-temperature failure (temperature in upper compartment greater than 400'F) a failure ~

j

+(a,c) 720.48 For severe accidents where the reactor vessel fails while the primary coolant system is still at high pressure, direct containment heating has been identified as a potential means for early containment

failure. There are large uncertainties in the methods used to make

\ current predictions of the likelihood and consequences of direct heating. However, if the vessel can be depressurized before failure occurs, direct heating is precluded. Some recent studies by the NRC and its contractors and by the industry have indicated that there are a number of potential schemes for ensuring such depressurization.

O Have these " accident management" schemes been considered for the SP/90 WAPWR-PSS 720-29 AMENDMENT 3

'5794e:1d SEPTEMBER, 1987

-pp design, and if so, please describe them along with any conclusions

.ig that have been reached regarding their viability?

RESPONSE:  :

Such " accident management" schemes have not been considered in the APWR Probabilistic Safety Study. Potential strategies for ensuring primary system depressurization for APWR could be implemented through-the use'of specific' safety procedures during severe accidents.

O i

l O

O 1

)

O l

l l o

V l

WAPWR-PSS 720-30 AMENDMENT 3 5794e:1d SEPTEMBER, 1987

O ATTACHMENT E APWR Fission Product Inventory - for 40 species in CORSOR Code CORSOR Code APWR Inventory Group Species Kg

. +(a,c)

O s

l l

l I

l O

O O

O WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987 l

' i

, . J l

-ATTACHMENT F l C 3.2 RECOVERY TIME FROM LOSS OF OFFSITE POWER q The object of this section is to use the data to estimate the probability that j

( recovery of offsite power after a LOSP exceeds a certain length of time. The empirical distribution of recovery time is shown in Table 3-2. l Table 3-2 i

( RECOVERY TIME DISTRIBUTION RECOVERY TIME NO. OF PCT. OF -

IN HOURS EVENTS EVENTS )

+(a,c) l l

l' NOTE: Recovery time not obtainable for 3 events in data 1

A rough estimate of the recovery time distribution would indicate that, as a i

/ whole, plants recover offsite power within one half hour about 48 percent of the time and within four he'urs about 77 percent of the time. The four hour threshold is important in LOSP events at nuclear plants since plant battery <

systems can drain of all power in about four hours. Recovery of offsite power, then, is crucial if the LOSP event is coupled with unavailabilities of the plant diesel generators or other backup power sources (assuming these sources cannot be made available within four hours).

(

0'

, ISource: EPRI Report NP-2301, " Loss of Offsite Power at Nuclear Power Plants Data and Analysis, 1982]

WAPWR-PSS AMENDMENT 3 E794e:1d SEPTEMBER, 1987

ATTACHMENT G (Sheet 1of4)

MOLAR GAS CONCENTRATIONS-SE BASE Time Mole Frac. Upper Comp Lower Ccmp Reactor Cavity Annular

+(a,s, O

O O

O O WAPWR-PSS AMENDMENT 3 E794e:1d SEPTEMBER, 1987

n b ATTACHMENT G (Sheet 2of4)

MOLAR GAS CONCENTRATIONS <

SE BASE Time Mole Frac. Upper Comp Lower Comp Reactor Cavity Annular

+( a , c ) -

l O

t.

O O

O WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

1

-g ATTACHMENT G (Sheet 3of4)

MOLAR GAS CONCENTRATIONS j SE BASE Time Mole Frac. Upper Comp Lower Comp Reactor Cavity Annular

+(a,c) !

i i

O l 1

l l

O i i

5 i

i r

(_)\

O l

I O

1 F

I WAPWR-PSS AMENDMENT 3 l E794e:1d SEPTEMBER, 1987  ;

I l

.. r ATTACHMENT G (Sheet 4 of 4)

MOLAR GAS CONCENTRATIONS SE BASE Time Mole Frac. Upper Comp Lower Comp Reactor Cavity Annular

~

+(a,c)

O I

l O 1 O

O l

O WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

i

.,, s I

ATTACHMENT H (Sheet 1 of 3)

MOLAR GAS CONCENTRATIONS SEFC BASE (24 hr run) l Time Mole Frac. Upper Comp Lower Comp Reactor Cavity Annular O- -

+(a.c)' )

l l

O '

l

)

O O

O

~

O WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

4 b.

L ATTACHMENT H (Sheet 2 of 3)

MOLAR GAS CONCENTRATIONS SEFCBASE(24hrrun)

! Time Mole Frac. Upper Comp Lower Comp Reactor Cavity Annular .

g f

+(a,c) 1 O 1 l

1 i

j l

O i O

O

O  :

WAPWR-?SS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

.1 .

ATTACHMENT H (Sheet 3of3)

MOLAR GAS CONCENTRATIONS SEFC BASE (24 hr run)

Time Mole Frac. Upper Comp Lower Comp Reactor Cavity Annular O, -

+(a,c) i

{

\

O

'd l

O e

O O

I O  !

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

- - _ ___ ______________ _ ._ \

.r 7, > ['/ '.m a

l ATTACHMENT I- (Sheet 1of5)'

.? MOLAR GAS CONCENTRATIONS TE BASE Time' Mole Frac. Upper Comp- Lower Comp Reactor Cavity Annular

~

+(a,c)

O l

O .

O l

l 1

O l 1

O WAPWR-PSS. AMENDMENT 3 E794e:1d SEPTEMBER, 1987 L1 ___ _-- -_. - - _ - _

ATTACHMENT I (Sheet 2 of 5)

/^ MOLAR GAS CONCENTRATIONS TE BASE Time Mole Frac. -Upper Comp Lower Comp Reactor Cavity Annular

~ -

+(a.c)

O O

1 O

.O l

rO WAPWR-PSS 5794e:1d AMENDMENT 3 SEPTEMBER, 1987 1

C________________._...__ _

j

ATTACHMENT I (Sheet 3of5)

O MOLAR GAS CONCENTRATIONS TE BASE Time' Mole Frac. Upper Como Lower Comp Reactor Cavity Annular

~

+(a,c)

O O

I

\

1 l

l l

i l

l O I j

L I l

- l L

O WAPWR-PSS AMENDMENT 3 l

5794e:1d SEPTEMBER, 1987 l

ATTACHMENT I (Sheet 4 of 5) l I MOLAR GAS CONCENTRATIONS

'TE BASE l

' Time Mole Frac. Upper Comp Lower Comp Reactor Cavity Annular l

O- '+(a,c)

O l 1

O  !

l I

O O

O_ AMENDHENT 3 WAPWR-PSS 5794e:1d SEPTEMBER, 1987

ATTACHMENT I (Sheet.5 of 5)

MOLAR GAS CONCENTRATIONS TE BASE Time Mole Frac. Upper Comp Lower Comp Reactor Cavity Annular

+(a,c)

O O

i l

lO  ;

O i

i f O '

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987 <

k. [

~. ,s: ,

s O '

+(a,c) (

i 1

j i

O O

O o ,

FIGURE 720.46 iii) A l-SE BASE (Sheet 1 of 4)

{-

WAPWR-PSS AMENDMENT 3 5794e:Id SEPTEMBER, 1987

O +(a,c) ]

l l

O i

LO q

l O  ;

i 1

I O

l l .  !

FIGURE 720.46 iii) A i t O SE BASE (Sheet 2 of 4)

WAPWR-PSS AMERCHENT 3 5794e:Id SEPTEMBER, 1987

,. l l

+

.(a.c) e V

O l

I

~

\ l l I l

l FIGURE 720.46 iii) A

) SE BASE (Sheet 3 of 4) 1 WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

.v 7891 ,REBMETPES d1:e4975 3 TNEMDNEMA SSP-RWPAW

)4 fo 4 teehS( ESAB ES A )iii 64 027 ERUGIF l

\ J* O 1

l

' l l

1

.,a- ,

l

+(a,c)

- 1

[

l O l V l i

l 1

O O i e

9 O-G l

l FIGURE 720.46 iii) B SEFC BASE (Sheet 1 of 4) l WAPWR-PSS AMENDMEN1 3 5794e:1d SEPTEMBER, 1987

]ac)

O I j i

I I I t

i I 1

o -

l I

l FIGURE 720.46iii) B SEFC BASE (Sheet 2 of 4)

WAPWR-PSS AMENDHENT 3 5794e:1d SEPTEMBER, 1987

j ~ , [i(k O i

- +(ac){

q o

O I

O O

l I

I O _

l i

FIGURE 720.46iii) B  ;

SEFC BASE (Sheet 3 of 4)

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

. , h :' , j

+(a,c) e  !

l l

i O

f

^

l a

O V,- - )

i FIGURE 720.46 iii) B SEFCBASE(Sheet 4of4)

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

O _ _

+(a,c)

-D

-v O

I I

l l FIGURE 720.46 iii) C

( TE BASE (Sheet 1 of 4)  !

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

., 0 _,

+(a,c) e l

l I I I I L --

l FIGURE 720.46 iii) C TE BASE (Sheet 2 of 4)

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

+(a,c) 0-O l

I l

i 9

O O

i FIGURE 720.46 iii) C TE BASE (Sheet 3 of 4)

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987 i

o _ --- i

y. Wi

+(a c)

G l

1 I

l l

(, I 4'

(r -

1 FIGURE 720.46iii) C TE BASE (Sheet 4 of 4)

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987 t _ - _ . _ . . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ __

, 4 $

+(a,c)

G G

G I

l

.)

l

\

l

$ }

l

- ~

j FIGURE 720.46viii) A SE BASE (Sheet 1 of 1) l WAPWR-PSS AMENDHENT 3 1

f E794e:1d SEPTEMBER, 1987

, *' s p _

+(a,c)

L-O 9

9 e

~

O~

FIGURE 720.46 viii) B SEFC BASE (Sheet 1 of 1)

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

.,: A f.

+(a,c).

v 1

O l

e I

l 8

l

)

9- -

FIGURE 720.46viii) C O- TE BASE (Sheet 1 of 1)

WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987

- - _ - - _ - _ _ _ _ _

Retrieved from "https://kanterella.com/w/index.php?title=ML20236E925&oldid=3179674"