ML20153G544
| ML20153G544 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 11/15/1994 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20153G532 | List: |
| References | |
| NUDOCS 9809300107 | |
| Download: ML20153G544 (40) | |
Text
.
j i
t 6
4 PRESENTATION l
TO i
t UNITED STATES NUCLEAR REGULATORY COMMISSION t
AP600 Passive Containment Cooling System (PCS)
Analysis Program i
i f
i Pittsburgh, PA November 15,1994 t
Mm.
9809300107 980928 PDR ADOCK 05200003 r
bd(AdM 6
^
Page1
k Agenda i
Day 1 Woodcock 1 hr.
PCS analysis program summary and status Spencer 4 hrs.
Scaling report methodology overview conclusions Spencer 0.5 hr.
PCS open items relevant to scaling report i
items 1, 3 Kennedy 0.5 hr.
Test analysis and code validation reports schedule and outlines t
NRC 0.5 hr.
Feedback frorn previous presentations uA1545w-l opl:Ib-118494 page 2
Agenda (Cont.)
Day 2 Woodcock 0.5 hr.
Opening remarks f
Kennedy 1.5 hrs.
Framework on usage of LST data
(
matrix of LSTs status of data reduction Kennedy 2 hrs.
Test 212.1 description of tests and data WGOTHIC lumped parameter results Kennedy 1.5 hrs.
Test 222.1 1
description of tests and data WGOTHIC lumped parameter results Kennedy 1 hr.
Subdivided WGOTHIC results Kennedy 0.5 hr.
Blind test description NRC 0.5 hr.
Feedback from previous presentations
\\
^# __;-
- m. m...
l
.7.- -
1 i
Agenda (Cont.)
t Day 3 i
Woodcock 0.5 hr.
Opening remarks l
NRC 1 hr.
AP600 calculation results r
NRC 1 hr.
LST calculation results i
Woodcock 2 hrs.
PCS open items review and status i
i All 1 hr.
Wrap-up and action items i
Orr 1 hr.
Discussion of ADS phase A test results.
I aus4sw-s uptib-::14e4 Page 4
Purposes of Meeting
[
g.
Establish common understanding of:
scaling test data evaluation status WGOTHIC calculations status t
Address open items f
i s
?
I sa.
mus.s....
ii
- em, s
Summary The major results and conclusions of this scaling analysis are:
r All phenomena were identified and ranked in a phenomena identification j
o and ranking table (PIRT)
Control volume equations and closure relationships were developed for o
the significant phenomena and integrated into a scaling model that coupled the inside of containment to the external PCS i
The selected phenomenological models were dimensionless, scalable, l
o and valid for application to both the LSTs and AP600 i
j l
.s u,.#i g,,,
amme.
Summary (Cont.)
~
Comparison of the scaling model predictions to large-scale test (LST) o results validated the completeness of the PIRT and the scaling model equations The LSTs with the steam source in the simulated steam generator o
compartment were representative of a double-end cold leg guillotine (DECLG)
Nonprototypicalities were accommodated in the analytical scaling model:
o JE restricted below-deck circulation into the steam generator compartment overcooled exterior
?
=>
....u.
MINIW M. ID-IlI4M
c i
i l
PCS Post-Wetting Phenomena identification and Ranking Table j
i J P O
ce Phenommon RanMng neemal swer downcomer agedule Two -- a :-.:d - =-; :: " gas H
H L
Vohane Jose Buoyant plumes H*
P, _ ;f H*
H H
Jet-plume moun0 entenment H'
L L
t
/
l Steam soun:o esposheetmg M
Flow told etabshly L
L L
l Riodulo Liqued tilm heat transfer H
H l
Susteos Lepad liim M L
H" Lequed Wim =W L
M Free coswecison heat transfer M
M H
Fosced oorwedson heat transfer L
H H
i Radiation heat transfer L
H H
l
[
Free oorwection eness transfer H
Fasood coswecison mese transfer L
H f
l 80edule Soude 1-0 transeent conduceson heat transfer H
H H
l f
2 or SD condumon L
L L
I 1
inter.asodule Cosweceson H*
M H
Condumon H
H H
Form and incison loseec L
H H
- Intemet p.:-_:-
x dut can be locaBy stiportant,lud were not be induded in die sing $e volume entemel model These phenomena wiu not change the conduesons of this scehn0 analyese, and thus may be consedered of low importance i
i Lsqued liim stabehty is analyzed separately and the reeubs imposed on the model ' ' ~
j
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Page i;
i l1.1 Internal Heat Sinks l
~
The internal heat sinks include steel structures, concrete structures, the i
IRWST, and the containment atmosphere. The intemal heat sinks slow the t
initial containment pressurization rate, and later slow the depressurization rata.
The steel was separated into 5 groups based upon thickness:
o i
the steel with thicknesses less than 0.255 ft. has Biot numbers less than 1, so it can be accurately modeled as lumped masses t
the shell steel was treated as distinct because it has a cooling i
water source on the outside after 11 minutes I
the steel liner on the concrete was modeled with the concrete l
t t
t i
+ w... A. -
u\\l541w upl. Ib-lll394 Page 20
t II.1 Internal Heat Sinks (Cont.)
All concrete is 2 ft. or thicker (2-ft. thick concrete has a time constant of approximately 124 hcurs) i the concrete was modeled with a finite element conduction model i
with heat capacity 94% of the concrete is located below deck e
i l
l u\\l548 w wpl.lb-lll394 I
e l1.1 Intemal Heat Sinks (Cont.)
7{
T-i W
4W i
Distritation of Steel and Concrete inside Containment I
~
t Group 1
2 3
4 5
6 Material Steel Steel Steel Steel Shell Steel Concrete /Uner i
Thickness (ft)
<.015
.015.051.051.255 0.1345
>.255 2/0.042 Area (ft")
44400 68828 38970 54116 1786 52622 s
Volume (ft )
591 2624 4974 7328 765 105243/2193 i
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u\\l54 t w.wpt.lb-li t3h Page 22
I i
l1.1 Containment Gas Volume The containment gas volume mass and energy conservation equations can
~
be combined and put in the following form with the time rate of change of l
pressure as the dependent variable:
6 pp n
i V, dP P,
dV
- *==u,,,,T,,3 + m,_,,c,,,,T,,,,- (
m,.,3 + m,_,)c,,,,T c
o.
(7_g) g (y_g) g (I)
- { h,; A,.,j(T, -T,,)+ h, A,.,(T,,-T,) - h, A,.,(T, -T,y) l 7
it l
Equation 1 was made dimensionless and each term of the resulting dimensionless equation was then divided by the steam source term, rhe,T l
to produce the time constants and pi groups l
u il54Iw.mpt. Ib-Il1394 p
P 5
i l1.2 Shield Building Control Volume l
The time constant of the 3-ft. thick-shield is over 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> a
it was assumed that the convection from the shield to the downcomer o
air is equal to the radiation from the baffle The shield energy equation gives one additional pi group:
1 o
i h,A,_,(T -T
)
l gd*
(rhhg).
{
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ww i
uus4 wwptm. : ses Page 32 l
II.2 Air Flow Path Control Volumes The riser and downcomer make up the PCS air flow path
~
The riser and downcomer energy equations produce no unique pi groups and have already been derived for the extemal film, dry shell, baffle, and shield The integral form of the momentum equation was derived by taking the j
dot product of a differential form of the momentum equation and integrating around a closed path:
M v13-vi, fL,vi vf3-v], _
fL,.vf' vj,-vj,,
gt,vj' 2
d.
2 2
d, ' 2 2
d.
2 (19)
L s
L s
(
- (P P,)gH, - (p.-p )gH, - (p
-p )gH, U+
N a
I i
11.2 Air Flow Path Control Volumes (Cont.)
i i
The left side of Equation 19 is the total system form, acceleration, and friction loss with a value of approximately [3.5 pn n /2,]'# so:
l v
M I
3 5p,v? =(
,)gH, - (p
-p,)gH, - (p
-p )gH, (20 Normalizing the terms on the right side of the equal sign by the left side gives the following three pi groups:
Downcomer buoyancy Riser buoyancy Chimney buoyancy
-l
^
g', (P
-P,)gH
(
H
, P.-P.)E.
(21) g* _ (p
-P )gH 4
(22) a (23) g 3.5 p,v]/2 3.5 p,v]/2 3.5 p,vJ/2 l
i I
u.\\is4 t w wptib-a i1394 Page 34
~
l t
lil. Closure Relationships i
.,7-Calculation of the heat and mass transfer to the individual liquid films is l
possible with the following assumptions:
l The inside of the AP600 containment is well mixed and can be
=
represented by a single volume j
Air and steam are ideal gasses j
t The break supplies steam and water at a saturation pressure equal to the pressure of containment j
The steam is saturated at the liquid film surface temper,ature f
I The heat and mass transfer relationships are the correlations developed for use on AP600 in the EGOTHIC code, except that only free convection is used inside containment l
g, 3s
l Vll. Nonprototypic Test Characteristics There are only 2 significant nonprototypic characteristics in the LST, both of which are understood and are accommodated analytically n
an g
1.
Entrainment into break compartment 2
Externai subcooling l
- dP.
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f f
l u us4 = wps.ib-i e sas4 Page 54
i t
I B
W P l
Vll.1 Entrainment into Break Compartment gl l
AP600 has large openings between compartments The LST simulated steam generator compartment was not open to the other below-deck compartments The result in the LST was a significant increase in the below-deck air concentration, with a modest increase in the above-deck steam concentration 1
l The available LST data span a sufficient range of steam and noncondensible concentrations to validate the mass transfer models for i
use on AP600 t
1p gr f
i
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I u \\1541m W. lb-lll384 Page 55
t 4 m t
Vll.2 External Subcooling The LST external water flow rate and its supply temperature produced approximately 4 times the scaled subcooled heat transfer of AP600 (approximately 20% of the LST heat is lost by subcooled water, versus 5%
in AP600)
Part of this mismatch is due to the safety-related assumption that the a
AP600 source is 120 F; an AP600 water source at 60 F would reduce the mismatch to a factor of 2 l
The subcooled heat capacity of the external film is easily modeled analytically and the WGOTHIC model is undergoing validation with LST results l
r i
l u M544 w wpt. lb-ll1494 Page Sti
Summary The major results and conclusions of this scaling analysis are:
All phenomena were identified and ranked in a phenomena identification and ranking table (PIRT) i Control volume equations and closure relationships were developed for j
the significant phenomena and integrated into a scaling model that coupled the inside of containment to the external PCS i
Comparison of the scaling model predictions to LST results validated the completeness of the PIRT and the scaling model equations i
i l
ww.
l i
u us4tw wptab-sitae4 Page 57 f
t h
Summary (Cont.)
l a
The selected phenomenological models were dimensionless, scalable, o
and valid for application to both the LSTs and AP600 l
The LSTs with the steam source in the simulated steam generator o
compartment were representative of a DECLG break Nonprototypicalities are accommodated in the analytical scaling model:
l o
1 P en a
j restricted below-deck circulation into the steam generator compartment overcooled exterior l
i dh i
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I u us4i..,s im.iii3e4 Page 58
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4 Test Facility Description t
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Large-Scale PCS Instrumentation Elevations h
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1JIV.
l Obsentations Internal velocity meters along the wall indicated the following:
at locations DO-165 and DO-345, velocities are 2-3 ft/s l
r at location A-90, the velocity is 1 ftis in the downward direction Exterior water coverage for the first and second steady-state periods was 100% wet. For the third steady-state period, the water coverage was 95%.
v mu m a,u &iii
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Westinghouse Energy Systems Ba 355 Pinstergh Pennsylvania 15230-0355 Electric Corporation DCP/NRCl415 NSD-NRC-98-5759 Docket No.: 52-003 1
August 17,1998
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Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 2055 ATTENTIC 2: T. R. Quay
SUBJECT:
RESPONSE TO NRC LETTERS CONCERNING REQUEST FOR WITilllOLDING INFORMATION
Reference:
- 1. Letter, Donohew to Liparuto, " Request for withholding information from public disclosure for Westinghouse AP600 design letters of November 21,1994," dated August 1,1995.
- 2. Letter, McIntyre to Quay, " Status review of AP600 proprietary submittals," dated September 18,1995.
- 3. Letter, Jackson to Liparulo, " Request for withholding information from public disclosure for Westinghouse AP600 design letters of June 20,19954," dated November 16,1995.
4.
Letter, McIntyre to Quay, "WCAP-14845, ' Scaling analysis for AP600 containment pressure during design basis accidents', Rev 3 errata," DCP/NRCl379, dated June 9,1998.
- 5. Letter, McIntyre to Quay, " Errata to WCAP-14407, Rev 3, '_WGOTHIC application to AP600'," DCP/NRCl395, date.1 July 14,1998.
- 6. Letter, McIntyre to Quay, " Response to NRC letter of August 23,1995, ' Request for withholding information in the design certification application for the AP600',"
DCP/NRCl400, dated July 22,1998.
Dear Mr. Quay:
l' Reference 1 provided the NRC assessment of the Westinghouse claim that proprietary information was provided in a letter dated November 21,1994, that :ontained presentation materials from the l
November 15 through 17,1994, meeting where the AP600 passive containment cooling system was discussed. The NRC assessment was that some, but not all, of the material was sufficiently specific to 3792a wpf
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DCP/NRCl415 NSD-NRC-98-5759 August 17,1998 the AP600 and the AP600 passive containment cooling testing to reveal distinguishing aspects of the 3
passive containment cooling system and improve a competitors advantage. Our 1995 request, Reference 2, indicated that the material provided in the Westinghouse letter of November 21,1994, was presentation material that was intended for clarification only, not part of the formal review material and requested that the material be returned to Westinghouse. At the time this subject was being discussed with the NRC technical statT, the information was considered to be proprietary by Westinghouse since it wntained information that had commercial value to Westinghouse. If this presentation material was indeed used by the staff in development of the AP600 final safety evaluation report, then at this time, almost four years later, this information will no longer considered to be proprietary by Westinghouse.
l Reference 3 provided the NRC assessment of the Westinghouse claim that proprietary information was i,
provided in a letter dated June 20,1995, which provided a copy of WCAP-14382, ",_ GOTHIC Code W
l Description and Validation." He NRC assessment was that all of the material identified as l
proprietary, with the exception of Figure 8-19, "Large scale PCS Instrumentation Elevations" would be accepted as proprietary by the NRC. He Reference 3 pointed out that this same figure was nonproprietary on page 3-12 of WCAP-14382. Figure 8-19, therefore, will no longer considered to be l
proprietary by Westinghouse.
Westinghouse has been verbally informed by the NRC that the Westinghouse letter of June 9,1998, l
(reference 4), appeared to contain proprietary information that was not clearly identified other than being marked " Westinghouse Proprietary Class 2" on the page and also that there was no affidavit included with the letter. He June 9,1998, letter contained errata for WCAP-14845, Revision 3, j
which is a proprietary report and for WCAP-14846, Revision 3, which is the nonproprietary version of l
WCAP-14845. In accordance with Westinghouse company policy, each page of a proprietary report has " Westinghouse Proprietary Class 2" on the page header. Specific information that is proprietary is then indicated with brackets. It is possible that there will be no information on a page that is marked as being proprietary. In the case of the June 9,1998, letter, none of the errata pages for WCAP-14845 contained Westinghouse proprietary information, thus no affidavit was necessary and the letter can be placed in the NRC public document room.
Westinghouse has been verbally informed by the NRC that the Westinghouse letter of July 14, 1998, (reference 5), appeared to contain proprietary information that was not clearly identified ott,r than being marked " Westinghouse Proprietary Class 2" on the page and also that there was no affidavit included with the letter. He July 14, 1998, letter contained errata for WCAP-14407, Revision 3, which is a proprietary report. In accordance with Westinghouse company policy, each page of a l
proprietary report has " Westinghouse Proprietary Class 2" on the page header. Specific information that is proprietary is then indicated with brackets. It is possible that there will be no information on a page that is marked as being proprietary. In the case of the July 14,1998, letter, none of the errata j
pages for WCAP-14407 contained Westinghouse proprietary information, thus no affidavit was necessary and the letter can be placed in the NRC public document room.
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DCP/NRCl415 NSD-NRC-98-5759 August 17,1998 On August 14,1998, Westinghouse was verbally informed by the NRC that the information contained in Chapter 18 of Revision 0 of the AP600 Standard Safety Analysis Report (SSAR) that was submitted to the NRC on June 26,1992, and was requested to be withdrawn by Reference 6, forms the basis of the Chapter 18 of the AP600 Final Safety Evaluation report that will soon be issued by the NRC and therefore cannot be withdrawn without seriously affecting the FSER issuance date. To maintain this information as proprietary, Westinghouse would have to provide a marked proprietary version and a corresponding nonproprietary version of this material. Reference 6 pointed out that Chapter 18 has been entirely reformatted since the SSAR was submitted originally as a result of Westinghouse significantly changing the approach being taken to human factors as a part of design certification. As i
a result, the information in Revision 0 through 8 of the SSAR is essentially no longer applicable to the AP600 design certification process, except for the information contained in Subsection 18.9.8.1 -
1 Development of emergency operating procedures and Tables 18.9.8-1 through 18.9.8 Emergency response guidelines, which was declared to be nonproprietary in Reference 6. Given the desire to complete the AP600 FSER and Final Design Approval in a timely manner, Westinghouse will no longer consider the material in Chapter 18 of Revisions 0 through 8 of the SSAR to be proprietary.
i This response addresses the proprietary issues delineated in the references.
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Brian A. Mc'.ntyre, Manager Advanced Pla.,t Safety and Licensing jml cc:
J. W. Roe - NRC/NRR/DRPM J. M. Sebrosky - NRC/NRR/DRPM W. C. Huffman - NRC/NRR/DRPM H. A. Sepp - Westinghouse I
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