ML20213E984

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Nonproprietary Amend 2 to RESAR-SP/90 Preliminary Design Approval Module 16, Probabilistic Safety Study
ML20213E984
Person / Time
Site: 05000601
Issue date: 09/30/1986
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19292G234 List:
References
NUDOCS 8611130399
Download: ML20213E984 (19)
v • d • e


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i WESTINGHOUSE CLASS 3 AMENOMEN1 2 TO RESAR-SP/90 PDA MODULE 16 ,

"PROBABILISTIC SAFETY STUDY" j i

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O WAPWR-PSS AMENOMEN1 2 5068e:1d SEPILMBER, 1986 l f 8611130399 861030 t DR W mefw(PDR l

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WESTINGHOUSE CLASS 3 O AMENDMENT 2 TO RESAR-SP/90 PDA MODULE 16 "PROBABILISTIC SAFETY STUDY" i

G INSTRUCTION SHEET l

Insert complete package behind page 720-18 of Amendment 1 in Questions / Answers O section.

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i I WAPWR-PSS j AMENDMEN1 2 SEPTEMBER, 1986 j 5068e:1d i I

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O ENCLOSURE 2 Questions Resulting from Review of RESAR-SP/90, Module 16, Volumes 3 & 4 l

A. Information Needed for STCP Simulation of W-APWR MAAP Analysis 720.26 Pleast provide the heat transfer area, distance peasured f rom the botton of core, mass, heat capacity, thickness, and initial tempr.rature of core support plate and grid plates in the bottom head as snown in Figure 5.3-1.

!tJSPONSE:

The grid plates in the bottom head are known as bottom mounted

instrumentation (BMI) tie plates. Detail and assembly information can be found on drawings 1870E71 through 1870E75 (to be supplied under separate cover). Weights of the various APWR components are listed in Attachment D. The following tie plate information was an input into this listing.

Volume Weight Component (cu. in.) (1bs.)

+(a c)

Upper Tie Plate -

Lower Tie Plate -

Total BMI Assy. _ ,_

]+(,c)

The elevation of the bottom of the fuel above the bottom of the vessel is[ ]ft. (p.5.5-59 of RESAR-SP/90, Module 16, Vol. 3) and the +(a,c) elevationofthetopofthesupportplateis[ [ f t. (p.5.5-73 of +(a c)

RESAR-SP/90, Module 16, Vol. 3). Therefore, the distance between the bottom of the fuel and the top of the support plate is l

[ ] f t. The initial temperature of the core +(a,c) support plate and tie plates is assumed to be the same as the initial primary system coolant temperature which is 591*F.

WAPWR-PSS 720-19 AMEN 0 MENT 2 5068e:1d SEPTEMBER, 1986

i 720.27 Please provide the flow area, equivalent diameter, heat capacity.

O- initial temperatu re, and the fraction of airborne fission product decay heat absorbed in the internal structures listed as No.11,12, 13,14, and 15 in the CIRC input data file.

RESPONSE

Detailed and assembly information for the upper internals is contained on drawings 1870E64, 1870E65, 1870E77, and 1870E78 (to be supplied under separate cover). Much of the information BNL requested should be obtainable f rom these drawings. The initial temperature of the internal structures in the CIRC input data file is 545'F, calculated internally by the MAAP code.

720.28 Please provide the mass of structures falling into the reactor vessel bottom head at core slump.

RESPONSE

O The mass of structures falling into the reactor vessel bottom head at cone slump is not used in the MAAP code and therefore this data is not available. BNL's assumptions during a core slump are not known and therefore W cannot provide the information requested. However, the information for the structures in the core area are contained in drawings 1870E63, 1870E66 through 1870E70, and 1870E76 which will be supplied under separate cover.

720.29 Please provide the mass of structures included in core debris for debris / concrete interaction in the reactor cavity compartment.

! RESPONSE:

The APWR containment design is the responsibility of MHI. More I detailed information as to what exactly is required is needed so that H can request it from MHI, I

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WAPWR-PSS 720-20 AMENDMENT 2 5068e:1d SEPTEMBER, 1986 l

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'O 720.30 Please provide the total mass of zirconium used for in-vessel metal / water reaction.

RESPONSE

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The initial zirconium (zircalloy) mass ] lbm. For each +(a c) accident sequence analyzed, a percent zirconium reaction in vessel is calculated, and this result should be applied to the initial zirconium O (zircalloy) mass.

i 720.31 The initial inventories of 40 species are required by the CORSOR code. MAAP only has six groups of fission products. Please provide the breakdown of the six MAAP groups, indicating the quantity of each radionuclide included in each group.

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RESPONSE

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j While the MAAP analysis was performed using only six groups of fission

! products, ORIGEN code runs were made to calculate the initial l inventories of all significant radionuclides. The initial inventories l were used in the consequence analysis in estimating release tc the j atmosphere. A table indicating initial inventories and the associated i MAAP fission product group is attached.

Isotope Inventory Isotope Inventory in the Core at in the Core at MAAP the Time of the MAAP the Time of the Isotope Group _ Accident (curies). Isotope Group Accident (curies) l

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!O WAPWR-PSS 720-21 AMENDMENT 2 l 5068e:1d SEPTEMBER, 1986 i

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Isotope Inventory Isotope Inventory 3
in the Core at in the Core at i MAAP the Time of the MAPP the Time of the
IsotoDe Group Accident (Curies) Isotope GroUD Accident (Curies)

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l MAAP GROUPS

1. Xe, Kr ..
2. Csl
3. Te
4. Sr i
5. Ru
6. Cs0H i

WAPWR-PSS 720-22 AMEN 0 MENT 2 5068e:1d SEPTEMBER, 1986

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B. Justification and Correction of W-APWR MAAP Analysis 720.32 On page 5.5-37 of the' Probabilistic Safety Study, the lower

compartment e 3 +(a,c)
and _

] f tguipment volumeUsing respectively. and surface these values, areathe areequivalent given as+(a,c) []ft thic(ness is computed as ] inches. It appears that the +(a,c) equivalent thickness of the wer compartment equipment is too thin.

Please clarify the volume and surface area given and provide a proper -

value for the equipment equivalent thickness, f

RESPONSE

The lower compartment equipment consists of one-third of items (7),

(8), and (10) as described at the top of page 5.5-37. In the lower i compartment, the following numerical values were used:

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+(a,c) s __

i inches, and reflects the large surface area and small thickness of the item (7) grating and HV duct.

O 720.33 The gap resistance between steel liner and concrete in the upper compartment and annular compartment is given as 0.2 f t' -hr-F/ BTU.

The gap resistance appears too high. Please justify or correct the gap resistance value.

RESPONSE

2 The gap resistance of 0.2 f t -hr 'F/B10 represents a heat transfer 2

coefficient of 5 BTU /f t -hr *F for free convection in air (gap).

j O Per Welty. Wicks, Wilson, " Fundamentals of Momentum, Heat, and Mass Transfer," 1976, John Wiley and Sons, a typical range of values for 2

free convection in air is 1 to 10 BTV/f t -hr *F. As noted above, for use in the MAAP Code for the gap, a value of 5 BTU /f t2 -hr 'F was used.

1 lO l WAPWR-PSS 720-23 AMENDMENT 2 5068e:1d SEPTEMBER, 1986

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'O 720.34 The MAAP analysis shows no zirconium is reacted within the vessel for i the AEF-2 sequence. Why was zirconium reaction not included in the analysis of this sequence.

RESPONSE

Zirconium reaction within the vessel was included in the analysis of I the AEF-2 sequence. The percent Zr reaction in vessel was inadvertently omitted from Table 5.5.3-AEF2-3 (p. 5.5-156). The j correct percent Zr reaction in vessel for the AEF-2 sequence is[ } +(a,c) i i

720.35 There are errors in the release f raction data for the SEFC-2 sequence given on page 5.5-163 (ie, any of the release f ractions exceed 1.0).

Please provide the corrected data.

RESPONSE

The exponents on the release f ractions on page 5.5-163 for the SEFC-2 j sequence have been inadvertently omitted. The corrected data is provided below:

j GrouD  % Release

+(a,c)

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i WAPWR-PSS 720-24 AMEN 0 MENT 2

! 5068e:1d SEPTEMBER, 1986

j A. SP/90 Traomerce Related Desian Data Needs l

720.36 The following data are needed for:

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1. Hot-Leg (between the RV outlet and the pressurizer)
2. Surge Line
3. Pressurizer and relief line Date Needed: gas volume height, flow area, mass times specific heat, l

' wall thickness, settling area, surface area oriented horizontally and vertically.

RESPONSE

O Much of the requested information can be found on MHI's drawing L-290C091 Rev.1 Attachment-1 to MAPP-W-1356 and M-710D001 Rev. 0 (to be provided under separate cover). In addition, the surge line is a 16-inch schedule 160 sst pipe, and the pressurizer relief line consists of 6-inch schedule 160 sst pipe connected to a 14-inch schedule 40 sst pipe header. A preliminary calculation of the surge l line volume is also attached for BNL's information. The broken hot 2

leg settling area is [ ] m (p.5.5-94 of RESAR-SP/90, Module 16, +(a,c)

Vol. 3).

720.37 The following additional data are needed for: .

j 1. Core plate (upper)

2. Tubes and columns in upper plenum l 3. Support casting in upper plenum
4. Core barrel Date needed: mass times specific heat, flow hydraulic diameter for the above structures, flow area in the proximity of the structure, length (along the flow path), wall thickness, surf ace area, settling area.

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! The information requested is contained in Attachment D and on drawings

1870E64, 1870E65, 1870E77 and 1870E78 (to be provided under separate cover). The hydraulic diameter of the upper plenum structures is l

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! WAPWR-PSS 720-25 AMENDMENT 2 5068e:1d SEPTEMBER, 1986 i

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_..,,.w., , , , _ - _y_ _ - - - _ -___,.,,.,___.-_m...

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[ ]m (p.5.5-94 of RESAR-SP/90, Module 16, Vol. 3), and the gas flow +(a,c) j area in the upper plenum is[ ]m (p. 5.5-94 of RESAR-SP/90,*(a,c) )

Module 16. Vol. 3). )

B. C-Matrix 7?O.38 If available, provide copies of containment event trets or the C-matrix used by Westinghouse in its assessment of the SP/90 O containment for severe accident loadings.

RESPONSE

The containment event trees and containment event tree structures are given in Subsection 5.6 and Appendix 5A, respectively, of RESAR-SP/90 PDA Module 16 Volume 4. The C-eatrix is given in Table 5.6.4-9 of Volume 4.

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O WAPWR-PSS 720-26 AMENDMEN1 2 5068e:1d SEPTEMBER, 1986

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! ATTACHMENT 0 (Sheet 1 of 5)

I l APWR WFIGHTS AND CENTERS OF GRAVITY i

, O WEIGHT TOTALS CG FIRST MOMENT

! COMPONENT 00AN i

(LB) (LB) (IN) (IN-LB)

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i AMENDMEN1 2 ,

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J-i ATTACHMENT D (Sheet 2 of 5) l APWR WEIGHTS AND CENTERS OF GRAVITY I

COMPONENT GUAN WEIGHT TOTALS CG FIRST MOMENT (LB) ( LP.) (IN) (IN-LB) i

+ (a , c)

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WAPWR-PSS AMENDMENT 2 I 5068e:1d SEPTEMBER, 1986 '

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, ATTACHMENT D (Sheet 3 of 5) l APWR WEIGHTS AND CENTERS OF GRAVITY l l

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j COMPONENT 00AN WEIGHT TOTALS CG FIRST MOMENT

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! 5068e:1d SEPTEMBER, 1986  !

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! ATTACHMENT D (Sheet 4 of 5) l 4  !

APWR WEIGHTS AND CENTERS OF GRAVITY l,

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l i WAPWR-PSS AMENDMENT 2 1 5068e:1d SEPTEMBER, 1986

ATTACHMENT D (Sheet 5 of 5)

APWR WEIGHTS AND CENTERS OF GRAVITY j l

O v GENERAL NOTES 3

The density of carbon and stainless steel is .285 lb/in ,

The density of Inconel is .307 lb/in3 ,

l The density of H O is 40.8 lb/ft3 (hot) and 42.6 lb/ft3 (cold).

2

) Centers of gravity are from the vessel mating surface, i All weights listed are dry weight.

l I NOTES

1. T hot.

! 2. T cold.

3. Without barrel radial supports.

l 4. With head adapters and penetrations.

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WAPWR-PSS AMEN 0 MENT 2 i 1 5068e
1d SEPTEMBER, 1986 l

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i AMEN 0 MEN 1 2 WAPWR-PSS SEPTEMBER, 1986 '

'O SURGE LINE VOLUME - Based on sketch attached to MAPP-W-1356,1/13/84, "Most Optimized Surge Line Route."

-+(a,c)

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AMEN 0 MENT 2 WAPWR-PSS SEPTEMBER, 1986

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  • A-PWR PlPING ROOTE CONCFPT-AMEN 0 MENT 2 WAPWR-PSS SEPTEMBER, 1986 ,

fop ppcqqjpjjpg L-290C091 2' O _

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