ML19350E382
| ML19350E382 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/09/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8106220099 | |
| Download: ML19350E382 (45) | |
Text
-
p nea UNITED STATES i'y "j, _
NUCLEAR REGULATORY COMMISSION wasmuorou. o. c.20sss 3
y JilN 3 M1 lJ yp$
i.
Docket No. 50-339 k
1 F
f JUN 1 B198W $
' SW Mr. J. H. Ferguson Executive Vice President - Power Virginia Electric and Power Ccmpany ry T
. Post Office Box 26666 Richmond, Virginia 23261
Dear Mr. Ferguson:
By letter dated February 19, 1981, you provided plant specific data for the North Anna Power Station, Unit No. 2 (NA-2) to be used in the development of a system transient computer code for main steamline and feedwater line break analysis.
Your above letter was in response to Condition 2.C.(14) to Facility Operating License NPF-7 for NA-2.
In our discussions with you regarding this matter which pre-dated your February,1980 response, you committed to provide additional information', should the need arise, in our then continuing develop-ment of the subject computer code.
By letter dated March 6, 1981, we informed you that your submittal was adequate in meeting the requirement set forth in Condition 2.C.(14) to License NPF-7.
Since then, our final development of the computer code has been completed.
The cade, as finally developed, has in excess of 100 nodes and requires a greater input data bank than provided in your submittal. We have reviewed your submitted data and determined your response provides only about 5 percent of the input data required. This data, as required, is provided in the enclosure to this letter.
Because of the magnitude of required input data specified in the enclosure, we have determined to provide you assistance in completing this task by making our consultant from the Idaho National Engineering Laboratory (INEL) available to you for the time required to collect the data.
We request that within seven (7) days of receipt of this letter you c,antact the NRC project manager so that necessary arrangements can be madc for making available our INEL consultant at your choice of place and time.
810 6 2 2 OCAC si P.
=
.o -
2 Our schedule calls for this data to be available by no later than July 31, 1981. Please call us if you'have any questions regarding this matter.
Sincerely, I
i
.Q.-
Robert.A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
PWR Information Request Package cc: See next page 9
F D
o
1 Virginia Electric and Power Company cc:.
Richard M. Foster, Esquire Mr. James Torson Musick, Williamson, Schwartz, 501 Leroy Leavenworth & Cope, P.C.
Socorro, New Mexico 87891 P.: 0. Box 4579
.Bouldgr, Colorado 80306 Mrs. Margaret Dietrich Route 2, Box 568 Michael W. Maupin, Esquire.
Gordonsville, Virginia 22042 Hunton, Williams, Gay and Gibson
- P. O. Box 1535 Mr. James C. Dunstance Richmond, Virginia 23212 State Corporation Commission Commonwealth of Virginia Alderman Libr,ary Blandon Building Richmond, Virginia 23209 Manuscripts Department :
1 University of Vir9 nta Charlottesville, Virginia 22901 Director, Criteria and Standards Division Office of Radiation Prog.ams (ANR-460)
?
Mr. Edward Kube U.S. Environmental Protection Agency Board of Supervisors Washington, D. C.
20460 L39f ro County Courthouse P.~0. Box 27 U.S. Environmental Protection Agency Louisa, Virginia 23093 Region III Office ATTN:
EIS COORDINATOR Ellyn R.-Weiss, Esquire Curtis Building Sheldon, Harman, Roisman and Veiss 6th and Walnut Streets 1725 I Street, N.W. Suite 506 Philadelphia, Pennsylvania 19106 Washington, D. C.
20006 Mr. Paul W. Purdom Mr. W. R. Cartwright, Station Manager Environmental Studies Institute r,. O. Box 402 Drexel University Hineral, Virginia 23117 32nd and Chestnut Streets Philadelphia, Pennsylvania 19104 Mr. Anthony Gambardella Office of the Attorney General Atomic Safety and Licensing 11 South 12th Street - Room 308 Appeal Board Panel Richmond, Virginia 23219 U.S. Nuclear Regulatory Commission i
Washington, D. C.
20555 Mr. Edward Webster Resident Inspector / North Anna
- /o U.S.N.R.C.
~
~~~
Route 2, Box 78A Mineral, Virginia 23117 Mrs. June Allen North Anna Environm' ental Coalition 1105-C Olive Street Greensboro, North Carolina 27401 me' 6
.,,.,,.n.,,..
... ~.,,
an
;.-[
ENCIDS URE PWR INFORMATION REQUEST PACM*GE
~
. Introduction The purpose of this package is.to request specific Pressurized Water Reactor (PWR) information, both pnysical -and operational, tnat will allow the plant to bd modeled using advanced computer codes, sucn as TRAC or RELAP. These plant models will be used in the study of various transients of concern to the nuclear-industry.
For organizational purposes the plant modeling nas been subdivided into 7 main components:-
1.
Reactor Vessel 2.
I-3.
Reactor Coolant Pumps
~
I 4.
Pressurizer -
5.
' Emergency Core Coolant Systems 6.
Primary Coolant Piping 7.
System Valves -
.v f
The forward and reverse flow energy loss coefftents, required in this package, are used to describe the influence of coolant volume geometry upon coolant flow energy. For exaraple, a 90' elbow will not only cnange thel direction of ccclant flow but will cause the coolant to 1-ese energy as
.well. The coefficient is dimensionless and is a function of the frictio,n factor and the eauivalent L/D of the piping features at the function or in
~
the volume. The basic equation is:
friction factor K = f L/D -
with f
=
L, pipe length
=
pipe diameter D
=
I
/
,.-..---,,e m--
--w.-
w
,ew.----r-
-.ve-
~.,-, - - - - - - -.-
..-ww- - -,.. - - > -
r i.,-*=.e~
- . - +
^
Features with equivalent.l./Os to be considered. include (but are not restricted to) abrupt area changes, plenu:n. volumes, moisture separators, valves and elbows., The terms ' forward' and ' reverse' apply to the normal
' and reversed direction of flow, respectively.
Operational information such as controls, operating conditions and There are alarin setpoints are critical-to the correct modeling of the PWR.
many factors that affect this information. 'Of prime concerr., ;re -the
^
delays in system actuation caused by instrument deadbands, uncertainties and attached electronics. The.se are not specifically written in this package due to the plant specific nature of these factors.
However, this d
information is needed and, is therefore, requeste.
Due to the' generalized nature of this questionaire, some of the information requested may not be applicable for a particular plant.
In these cases the requested parameter should be ignored.
In addition to the requested data in this package, scheme. tic drawings depicting each of the major components should be included.
O h
S 2
1
^
L' 1.0 REACTOR VESSEL 1.
' Inlet nozzles A.
Inside diameter at nozzle inlet ft B.
Inside diameter at nozzle outlet ft
-C.
Distince from nozzle inlet'to ft nozzle outlet D.
Forward flow energy loss coefficient E.
. Reverse flow energy-loss coefficient k/D F.
Inside surface roughness II. Downcomer-A.
Flow area as a function of elevation, 2
relative to inlet nozzle centerline ft
- F E.
Full power inlet temperature psia C.
Full power _ inlet pressure D.
Elevation of top of downcomer relative in~ inlet nozzle centerline ft E.
Forward flow energy loss coefficient F.
Reverse flow energy loss coefficient G.
Surface roughness k/0 H.
Hydraulic diameter as a function of ft elevation, rslative to inlet nozzle centerline III. Lower Plenum (below flow distributor) i 2
A.
Flow area as a function of elevation,"
ft relative to inlet nozzle centerline 3
B.
Total volume including structural ft material C.
Metal-to-water volume ratio 1
9 I
3
. - ~
' c 3.
D.
Forward flow energy 1 css cccfficient-
~ E.
Reverse flow energy loss coefficient k/D F.-
Average roughness G.
Fractional composition.of structural
. components (e.g., 55-306 26.4%, etc)
H.
Hydraulic diameter as a function of ft elevation relative toLinlet nozzle centerline IV.. Lower pienum flow distributor 2
ft A.
Flow area B.
Forward flow energy loss coefficient
- C.
Reverse flow energy loss coefficient D.
Composition E.
Axial elevation at center and at edge-ft F.
Thickness ft V.
Lower plenum between distributor and lower core plate 2-A.
Flow area ft B.
Hydraulic diameter ft C.
Forward flow energy loss coefficient D.
Reverse flow energy loss coefficient E.
Roughness k/D F.
Material composition 3
G.
Total volume ~ including structural material ft H.
Metal-to-water volume ratio
?
e 4
.-l j
. VI.. Reactor core A.
Fuel assemoly 2
~
ft 1.-
. Flow area ft 2.
Hydraulic diameter 3.
Forward flow energy loss coefficient at grid spacer 4
Reverse flow energy loss coefficient
~
at grid spacer k/D S.-
Roughness 6.
Material composition 3-7.
Tdtal volume ft 8.
Metal-to-water volume ratio 9.
Axial elevations of center of grid spacers, ft relative to inlet nozzle centerline B.
Control rod assemoly 2
1.
Flow area ft 2.
Hydraulic diameter ft 3.
Forward flow energy loss coefficient at grid spacer 4.
e ve n a flow energy loss coefficient at grid spacer k/D 5.
Roughness 6.
Material composition 3
7.
Total volume ft 8.
Metal-to-water volume ratio 9.
Axial elevations of center of grid spacers, ft relative to inlet nozzle centerline l
9 I
5
a r
C...
Fuel; assembly.with'. instrument 2'
il.: ' Flow area-ft
- 2.
Hydra,ulic diameter.
ft i
3.
Forward flow energyfloss coefficient 4.
Reverse flow energy' loss coefficient 5.'
Roughness -.
k/0 6.
Material composition 3
'7.. Total volume ft 8.
Metal-to-water volume ratio
. D., -
Core bypass flow' path (s) 2 1.
Flow area ft 2.
.. Hydraulic diameter' ft
'3.. Forward flow energy loss coefficient.
4.
Reverse flow energy loss coefficient 5.
Roughness k/D 3
.6.
Total volume ft
- 7..
Percentage bypass of core full power flow E.
Core power distributions (axial and radial for each of the following conditions)
~
1.
Normal full power 2.
Control rods 50% inserted
~ 3. -
Control rods fully inserted with most significant control rod assembly stuck out F.
Reactor protective system interactions with core G.
Engineered safeguards protective system inter-actions with core H.
Coolant temperature at core inlet as
- F a function of core power e
6 1
~
~
~... _ _ _., _ _, _.. _, _... - _. _,...
_... _. _,. _. ~...,... -.
4 I. ' Coolant pressure at ccre inlet as a function of core power-psia J.
Coolant temperature at core top as a
'F function of core power - -
X.
' Coolant pressure at core top as a psia function of core power L.
Quantity of gamma ~ heating in core as a kW function of core power and axial elevation 11.
Reactor kinetics--beginning of life 1.
Scram rod reactivity insertion as a function'of time for:
a.
all rods drop b.
all but most reactive rod drops 2.
Reactivity change as a function of moderator density 3.
Density reactivity change as a function of boron concentration 4.
Reactivity change as a-function of fuel temperature (Doppler) 5.
Boron worth as a function of baron concentration and moderator temperature N.
Reactor kinetics - end of life 1.
Scram rod reactivity insertion as a function of time for:
a.
all. rods drop
.b.
all but most reactive rod drops 2.
Reactivity change as a function of moderator density 3.
Density reactivity change as a function of boron concentration 4.
Reactivity cnange as a function of fuel temperature (Doppler)
)
\\
7
,m,-
--p.--,-,, -.,--,, - -,,
,4 g
p-,
i 1
5.
Baron wortn as a' function of boron-concentration and moderator temoerature
.VII. Upper core plenum from top of ' outlet nozzles to bottom of vessel head 2
A.
Flow area ft ft 8.-
Hydraulic diameter C.
Forward flow energy-loss coefficient D.
Reverse flow energy loss coefficient k/D E.
Rougnness F.
Material composition 3
G.
Total volume ft H.
Metal-to-water volume ratio.
I.
Inside diameter.of plenum shroud orifices ft VIII. Upper head 2
ft A.
Flow area B.
Hydraulic diameter ft C.
Forward flow energy-loss coefficient D.
Reverse flow energy loss coefficient E.
Roughness k/D F.
Material composition 3
G.
Total volume ft H.
Metal-to-water volume ratio IX. Outlet nozzles A.
Inside diameter at nozzle inlet ft B.
Inside diameter at nozzle outlet ft C.
Distance from nozzle inlet to nozzle outlet ft D.
Forward flow energy loss coefficient E.
Reverse flow energy loss coefficient F.
Roughness k/D G.
Elevation relative to inlet nozzle ft 8
~
~
2.0 STEAM GENERATOR All elevations -hould be relative to inlet of the steam generator reactor coolant inlet nozzle,,awhose elevation relat.ive to the centerline of tne reactor vessel cold leg inlet snould be included.
If tne_ steam generators differ from each otner the requested information should be provided fcr each generator. All elevations are relative to reactor vessel cold leg inlet nozzle centerline.
~1.
Primary Loop A.
Primary coolant inlet. nozzle 1.
elevation of inlet nozzle centerline at ft the entrance to the inlet plenum 2.
inside diameter at nozzle inlet ft 3.
inside diameter at plenum inlet ft 4._
length of nozzle at nozzle centerline ft 5.
angular orientation of nozzle centerline relative to horizontal
~
6.
forward flow energy loss coefficient 7.
reverse flow energy loss c,oefficent 8.
inside surface roughness 9.
flowrate at nozzle entrance at lbm/sec full load
'F 10.
coolant temperature at nozzle entrance at full load
, 11. coolant pressure at nozzle entrance psi at full load B.
Primary c.oolant inlet plenum 1.
elevation of. tube sheet ft bundle entrance 3
2.
plen'um volume ft
,o
,_m,
-,,w,,
..-p,
-.m--
.,w--
m,,yc 9,
.e
-t'
2-
- ft 3.
area of plenum at entrance to tube bundle.
.4.
forward flow energy loss coefficient 5.
rever.se flow energy loss coefficient. __.
- 6..
-roughness 7.
wall thickness ft 8.
width of. plenum divider (UTSG)*
ft at tube sheet entrance C.
Tube bundle 1.
number'of flow tubes 2.
tube ID ft 3.
tube 00 ft 4.
elevation of tube bundle exit.
once tnrough steam generator (OTSG)D l'
y 5.
lengtn of flow tubes (OTSG) ft Ab V
average length u-tube steam 90 generator (UTSG) 2 6.
Heat transfer area ft l/,
7.
Heat transfer area including curved 2
section (UTSG only) ft 8.
forward flow energy loss coefficient 9.
reverse flow energy loss coefficient ~
10.
internal roughness 3
- 11. total volume in' tubes ft
- 12. maximum / minimum and average tube ft elevation (UTSG) a.
U-tube steam gener ar o.
Once through steam generator 10
--s--
y
---ew-+-a---,w--v-
-sp----,,--,,-w-av
,,-*ye v
r
M
,. 0.
Primary Coolant Outlet Plenum 1.
elevation of tube sneet exit ft 3
.2.
plenum ~ volume ft 2
ft 3.
. area of plenum at tuoe exit 4.
forward flow energy loss coefficient 5.
reverse flow energy loss coefficient 6.
roughness ft 7.
wall thickness E.
Primary Coolant Outlet Nozzle 1.
elevation of inlet nozzle centerline ft at the entrance to the inlet plenum 2.
inside diameter at nozzle putlet ft
(;(.
3.
inside diameter at nozzle inlet ft q}
4.
length of nozzle at nozzle centerline ft i[k 5.
angular orientation of nozzle centerline f.{i relative to horizontal d$.
6.
forward flow energy loss coefficnent L[
7.
reverse flow energy loss coefficnent 8.
inside surface rougnness 9.
flowrate at nozzle entrance at lom/sec full load 10; coolant temperature at nozzle
'F entrance at full load
- 11. coolant pressure at nozzle psi entrance at full load e
11
i II.. Secondary Loop A.-
Feedwater Supply 1.
feed flow-at full load 1bm/sec 2.
feed flow as a. function of lbm/sec a.
load b.-
mixture lev %
3.
feedwater temperature
'F 4.
feedwater pressure.__. _ _ _.
psi S.
auxiliary feed systems a.
initiating setpoints b.
flow rate each type as a function 1bm/sec of pumps running c.
aux feed temperature
'F (each type)
~
d.
number of pumps (each type) e.
aux feel pressure, psi (each ty.1e) ft f.
aux feed inlet elevation 6.
main feed inlet elevation _.
ft B.
Downcomer (Preheat er) Section 1.
downcomer(0/5G) 2 a.
flow area as function of -
ft elevation above top of lower tube plate b.
roughness c.
forward flow energy loss coefficient d..
reverse ficw energy loss coefficient e.
downcomer shroud 10 ft f.
downcomer shroud 00 ft 9
12 1
. - ~..
,,~
g,-
baffle shr:ud ID ft h.
baffle snroud 00 ft ft
=f.
snell 10 ft j.
,snell OD k.
elevation of baffle shroud ft 4
bottom above lower tube plate 1.
elevation of downcomer ft shroud top above lower
~
tube plate _
3 i
~
m.
to'11 volume in section ft 2
n..
heat transfer area ft 2.
pr'eheater(UTSG) j a.
elevation of (1) top of preheater section ft (2) bottom of preheater ft section b.
flow area as function of ft height of section c.
forward flow energy loss coefficient i
d.
reverse flow energy loss coefficient e.
roughness external tubes /
baffles 2
f.
heat transfer surface ft 3
g.
coolant volume of section ft 3
h.
metal volume in section ft 3.
operating conditions a.
outlet temperature
- F b.
outlet pressure psi c.
outlet flow if different lbm/sec from inlat flow 4.
outlet to tube bundle (boiler) 2 a.
flow area ft b.
forward flow energy loss coefficient c.
reverse flow energy le3s coefficient 13
~, -..
v.,
2 T
e.e---"'r ew#
v
^"'v--"-
-~--
- -""W
t
.i C.. Tube Bundle (Boiler)
\\
2
-1.
~ flow' area tnrougn tubes as a ft function of height.
2 2.
total neat.transferf area -
ft
- 3..
forward flow. energy loss coefficient 4.
reverse flow energy. loss coefficient 5._
. roughness (external tubes) 6.
elevations a.
top of baffle assembly ft b.
bottom of upper tube plate ft c.,
top of baffle shroud ft 7.
height of top of nucleate boiling ft region as a fun. tion of load (above lower tube plate) 8.
height of. top of. film boiling ft region as a function of Wa'd-(above. lower tube plate)
~
l I
\\
14
, 9.
flow lesses in bafflo.rsgien 3-
'.10.
metal.' volume in region ft
- 11. operating conditions a.
outlet temperature
- F
~
b.
outlet pressure-p s1' c.
Quality as c function of heignt in region 3
- 12. total free volume in region ft D.
Superneat Steam Downcomer (OTSG)*
1.
steam generator ID ft 2.
ro'ughness 3.
forward flow energy loss coefficient 4.
reverse flow energy loss coefficient 5.
elevations:
a..
bottom of downcomer ft b.
steam outlet centerline ft 2
6.
flow area as a fu'nction ft of height 7.
steam outlet nozzle ID ft 8.
steam conditions at exit a.
outlet temperature
'F b.
outlet pressure psi c.
flow rhte as a function Ibm /sec of load" 2
9.
heat t.ransfer area ft 3
- 10. total free volume in region ft E.
SteamDome(UTSG)h J
a.
Once through steam generator b.
U-tube steam generator 15 g
___,,..-_._s..
m; 2
- 1..
flow ar;a as a function of ;
ft height (top of tunes to swirl vane
. moisture separator (s) (SVMS) 2.
elevations -
a.
top of tube bundle ft g
-b.
bottom of SYMS ft c.
top of SVMS ft d.
bottom of steam dryers ft e.
top of steam dryers ft
.f.
steam outlet -----
ft 3.
SYMS (Steam Separators - CE)a a.
forward flow energy loss coefficient b.'. reverse flow energy loss coefficient c.
roughness 2
d.
flow area through SVMS ft e.
recire. flow as a lbm/sec function of load f.
number of swirl. vanes g.
number of steam separators (CE) 4.
steam dryers a.
forward flow ~ energy loss coefficient b.
reverse flow energy loss coefficient c.
roughness 2
d.
flow area through dryers ft e.
racirc. flow as a function of load 3
5.
total free volume in region ft 3
6.
total metal volcme.
ft 7.
operating conditions a.
- steam outlet pressure psi b.
steam outlet temperature
- F c.
steam flow as a function 1bm/sec' f
of load a.
Combustion Engineering l
O 16 l
8.
' steam cutlet n zalo 10 ft F.
-SG Material-Composition
.l.
SG vessel 2.
baffles 3.
downcomer shroud (OTSG) 4.
tube support plates 5.
primary tubes
~
~
6.
SVMS (steam separators) 7.
steam dryers G.
Valves' 1.
valve diameter ft b.
control setpoints c.
distance from SG outlet nozzle I.
vertical ft II. horizontal ft 2.
relief valves a.
valve diameters ft b.
control setpoints c.
distance from SG outlet rozzle I.
vertical ft II. horizontal ft 3.
atmospheric dump valves a.
valve diameters ft b.
control setpoints c.
distance from SG outlet nozzle I.-
vertical ft II. horizontal ft 17
~'
3.0 ' REACTOR COOLANT PUMPS-I.
' GEOMETRY 3
A. -
Pump volume' ft 2
.B.
Effective pump volume flow area ft
[
C.
Effective pump volume hydraulic diameter ft D.
Pump volume flow length ft E.
Pump vo'lume height ft F.
Pump' volume elevation ft G.
Pump inlet (suction)
~
2 1.
flow area ft 2.
hydraulic diameter (ft) ft 4
3.
elevation ft 4.
forward flow energy loss coefficient 5.
reverse flow energy loss coefficient H.
Pumo outlet (disenarge)
~
2 1.
flow area ft 2.
nydraulic diameter (ft) ft 3.
elevation ft 4.
forward flow energy loss coefficient 5.
reverse flo.w energy loss coefficient 18
- m w
-r w
- ~
,,s
~., '
l 2.
-PERFORVANCE-A.
Rated angular velocity rev/ min 3
B.
Rated volumetric flow ft /sec' i
C.
Rated head ft ft-lb D.
Rated pump torque f
-)
E.
Rated pump motor torque _.
ft-lb f F.
Rated density lb,/ft G.
Operating parameters for normal steady state at 100%
rated plant conditions 1.
angular velocity rev/ min 3
2.
volumetric flow ft /sec 3.
head ft
- 4. ' pump toraue ft-lb 7"
f 5.
pump motor torque
~
ft-lbf3 6.
density 1b.n/f t 2
H.
Pump and'pumo motor moment of inertias 1 b._.'/f t 2
1 lb,/ft I.
Pump motor torcue vs. pump motor speed table ft-lb f rev/ min i
l J.
Pump frictional torque coefficients as a function of pump angular velocity I
i l
I l
\\
19
._. i,
K'. Maximum forward and r; versa pump rotational velocities rev/ min rev/ min
'l L.
Single phase nomologous pump data 1.
Require 16 data tables of the independent variable vs. eacn dependent variable with definition of terms in variables given in
-Table 1:
b e
4 e
s, e
0 e
l l
j 20 o
l
~
~
'T~~.
- - -.=
,l t
TABLE 1.
PUMP HOMOLOGOUS CURVE DEFINITIONS
)
Dependent Variable Regime Regime' Mode Independent
- Number 10 Name
._ a y
v/a Variable Head Toroue
.1 HAN Normal
>0
>0
< 1 v/s h/a2 gf,2 2
HVN Pump
>0 7 1 a/v h/v2 afy2 2
af,2
~
3 HAD Energy
>0 4
> -1 v/s -
h/m2 s/v2 4
HVD Dissipation
>0
<0 7 -l' m/v h/v2 3 7, 21
-<0
<0
< 1
-v/a h/m 5
HAT Normal 2'
37,2
~
~
6 HVT Turbine 70
.0 1
m/v n/v 2
gf,2
~0 TO
> -1 v/a h/a 7
HAR Reverre 2
2 8
HVR Pump
[<0
>0 7 a/v h/v
,fy (actual rotational velocity / rated Rotational velocity) ratio.
a =
rotational velocity.
Volumetric flow ratio.
(actual volumetric flow / rated volumetric y =
flow).
Head ratio.
(actual head / rated head).
n =
Toroue ratio.
(actual torate/ rate torque) s =
M.
Four quadrant curves ',recuired only if single phase homologous curves of Item 2-L of above are not available)'.
1.
require data tables (or plots if data are not available) describing the pump characteristics in terms of:
3 alumetric flow ft /sec f
rotational velocity rev/ min head ft and toroue ft-lbf N.
Two phase pump data t
21
.[ *
(1) Reauire fully degraded two phase homologous i
pump data (consisting of 16 data tables in the
. same format as that described in Item 2-L) with,a specific correlation between void fraction and two phase head and toraue relative to single pnase. head and torque (2)' If. the data and correlation of Item 2-N-1 of
.above are not twailable, provide any available
- two phase pump data and'.related correlation (s) with complete explanatory information
.III.THERMALHYDRAijLIC(CONDITIONSFORNORMALSTEADYSTATEAT100% RATED PLANT CONDITIONS A.
Pump volume 2
1.
average pressure ib /in f
absolute 2.-
average temperature - -- -
- F 3.
average cuality --
B.
Pump suction and discharge jynctions 1.
mass flow lo,/sec IV. CONTROL LOGIC A.
Recuire all trip setpoints, logic, and interlocks associated with the tripping off of each ump B.
Recuire all reactor system information needed to interpret the requested information of Item 4-A I
22 e..r-,
,-.e c,,
~,
9--,
g 4.0 PRESSURIZER JD
~
I.
Tank.
f A
A.-
OD ft B..
ID ft C.
Height ft i
3 D.
Total internal volume including ft structural materials -
2 E.
Flow area as a function of heignt ft ft F.
Composition II. Surge line A.
OD pipe ft B.
ID pfpe ft C.
Rougnness k/D O.
Forward flow energy loss coefficient E.
Forward flow energy loss coefficient F.
Pipe length ft G.
Number of elbows H.
Elevations 1.
Hot leg connection ft 2.
Pressurizer connection ft
. III. Surge line nozzle A.
Elevation of nozzle inlet centerline at entrance t6 pressurizer B.
ID nozzle inlet C.
ID pressurizer inlet D.
Length of nozzle at nozzle centerline E.
Forward flow energy loss coefficient at pressurizer inlet
/
23
+
m
, _ + _
-. 7. ;. :-.
F.. Reverse flow energy _1 css coefficient at pressurizer inlet G.
Inside surface roughness O
a
- IV.- Safety nozzles 2
.A.
Flow area ft -
- 8.
Flow resistance C.
Maximum nozzle. capacity lbm/sec 0.e Osc.ational setpoint psia Y
V.
Relief nozzle 2
ft M
A.
Flow ar,ea
/ 8.
Flow resistance
+
//
C.
MaH m m nozzle capacity lom/sec O.
Operational setpoint psia
,VI.
Pressurizer Neaters'~~
A.
Number of rods B.
Outer diamcter of rod ft 2
'C.
Total heat transfer surface area ft D..
Power input kW
~
E.
Composition F.
Heater setpoints 1.
fiermal operation 2.
Transient operation
,e
'.VII. Operational 3
A.
Water volume as a function of load
~ft B.
Operating conditions as a function of load 1.
Pressure psia
'a p.
2.
Temperature
- F 3.*
Quality 4.
Baron concentration ppm i
24
r
.~
' e'.
- C.. Spray line'-volume flow 'as a function of #
' O.
Spray.'ine setpoints 1.
Norn;41 operation...
psi 2.
transient operation
- psi 9
e 9
4 e
O O
i 4
e e
e 9
. 4 O
9 4
i -
F t
L
[
i.
I l..,.
25 L
i-i
- - -. - - ~ _._. _.. _,_,,_,_, _,, _ _.,,, _
y..'
5.0 EMERGENCY CORE COOLANT SYSTEMS I.
Accumulator A.
Tanks 1.
Number of tanks ft 2.
00.
3.
ID ft
~
3 4.
Total volume ------
-~
ft ft 5.
Height 2
6.
Flow area as a function of height ft /f t 7.
Composition B.
Surge line 2
1.
Junction flow area ft 2.
Pipe 00 ft 3.
Pipe 10 ft 4.
Yotal length ft 5.
Forward flow energy loss coefficient 6.
Reverse flow energy loss coefficient 7.
Roughness kR J
8.
Elevations a.
Tank connection ft b.
Cold leg connection.
ft C.
Operational (Botn nominal and upper and lower limits) 1.
Liquid level ft 3
2.
Liquid volume ft G
26
-e
,*-mn--
o m-
-,+ - - --+ ~
4
. 3.
Operating conditions a.
Pressure psi b.
Temperature
'F B,oron concentration
. ppm c.
4.
F111 gas a.
Composition t
b.
Volume II. HPIS 1.
' Injection liquid conditions a.
Pressure psia b.'. Temperature
- F l
c.
Baron concer,i# tion-ppm 2.
Flow rate as a function of primary lbm/sec system pressure and.# pumps 3.
Number of. pumps _.-.
4.
Operational setpoints psia III. LPIS 1.
Injection liquid condition's --
a.
Pressure psia n.
Temperature
'F c.
boron concentration ppm 2.
Flow rate as.a function of. primary.. -.
Ibm /sec system pressure and i pumps 3.
Number of pumps 4.
Operational setpoints psia.
a.
actuation time delays s
G 9
27
. o
__________.-..,_-..m.._
- i t
IV. Charging systea 1.
Injection liquid conditions a.
Pressure.
psia
'F b.
Temperature c.
Enthalpy BTU /lbm 2.
Flow rate as a function of primary lbm/sec sy' stem pressure and f pumps 3.
Number of pumps 4..
Operational setpoints psia e
t S
en
- en mamme * *em -
eemme --
e 9.,
O e
0 e"
- ee N.-p ee O
9
$Y B
O l
~
gg l
- - - n
=
6.0 PRIMARY'C00LANT PIPING SYSTEM The primary coolant system consists of tne piping leading from the reactor vessel-to -the-steam. generators,. from.the. steam. generators _.toutne _
reactor coolant pumps, and from the coolant pumps to tne reactor vessel inlet nozzles. To adequately model the piping, information concerning flow direction enanges, the, presence of valves, elbows, tees and changes in flow l
areas must be adecuately described.
In the attached-tables-the-locations-where flow conditions-enange in-a The piping section are requested using a cylindrical coordinate system.
origin of the coordinate system is at the intersection of tne reactor vessel axial centerline with a-utility-designated reactor vessel inlet nozzle norizontal centerline. Angular references are counterclockwise.and will.be with respect to the referenced inlet nozzle. The relationship of the cylindrical coordinate system to the rea'ctor vessel is shown senematically in Figure 1.
An example of how piping component locations would be specified is as follows. A section of primary piping connecting a reactor coolant pump to a reactor inlet nozzle is' snown senematically in Figure ~2.
Fdr simp 1'icity, 4
assume the piping does not have any flow area reductions, changes in inner e
l 29
4 Z
,a-Pd-s q
q/
1
/
reference inlet nozzle I
-r m
IQ e\\h
.L J'
r/
=
L h.)
'R d'
Figure 1.
Piping system cylindrical coordinate system.
30
,_ i
m.4
-4 1
I 1
I I
i i
I 10.0 ft 9
- ---12.5 ft I
I r s_-
3 L
L, 15.0 ft t
L
(
d"~
7. 5 f t.--
(.
/
Figure 2.
Piping to reactor vessel inlet nozzle.
l I
1 l
31 l
surface roughness, valv;s, or piping pehetraticns. The angular oricntation of tne inlet nozzle witn respect to the reference inlet ncazle is 270*.
The various coordinate locations should be systematically specified, j
preferably starting where-the-coolant enters._tnis section _of. pip _ing.and ending at the inlet to the reactor vessel inlet nozzle.
The convention of starting at the_ normal coolant flow inlet and ending at the riormal coolant flow exit should be followed througnout the reactor coolant system piping description.
The first coordinate location to be specified is at the coolant pump disenarge nozzle exit. This location is also at 270* orientation, and is 30.0 ft from tne, reactor vessel axial centerline and.15.0 ft below the inlet nozzle centerline.
Its coordinate location is therefore 270*,-
30.0 ft -15.0 ft.
Tne next coordinate location of interest is the 90* elbow where the coolant flow direction changes from horizontal to vertical. As shown in the figure, tne only coordinate that nas changed is the distance, r, from tne reactor vessel centerline. The location of this 90* elbow is therefore 270*, 22.5 ft, -15.0 ft.
The coordinate location of the next elbow is 270*, 22.5 ft, 0.0 ft.
This is assuming all. inlet nozzles on the reactor vessel are at the same elevation. Note that the only coordinate value to change was the elevation
(-15.0 ft to 0.0 ft).
The final coordinate' location is the inlet to the reactor vessel inlet nozzle, which is at 270*, 12.5 ft, 0.0 ft.
For enanges in coolant flow directi'on of greater tnan 90*, the section of piping should be divided into two or more sections, such.tnat no one section represents more tnan a 90* change in directiori.
l
[
32 9
---w--
. l.:
in. addition to information concerning the physical layout.of the primary. piping, several other items of data are needed to accurately model' the. system at the specified points of interest.
These are:
1.
Flow area 2.
. Pipe inside rougnness 3.
Hydraulic diameter 4.
Forward flow energy loss coefficient (s) 5.
Reverse. flow energy loss coefficient (s) 6.
If an. area change, abrupt or smooth 7.
Normal condition coolant pressure 8.
Normal condition coolant temperature 9.
Normal condition coolant fluid component flow rate
- 10. Normal condition coolant vapor component flow rate 11.' Piping material,' e.g. SS-306, inconel X750, etc
- 12. Piping thickness
- 13. Reason for description, e.g. motor valve, pipe penetration, piping tee, etc Table 2 is provided to simplify the presentation of the data. The
~
first column is for a user-supplied reference number in the event there is a need for further information. For example, if there is a primary 1000 I
33
+-
-w
+-
,,,w
,w
-,---w-w-w--
- ~ - - - - - - - -,
r--~,-=*-
a e
- l AE 2,, Pirisu(SCdif filkt Coordinate locat ten Cruelant Caeleet Iype field T aper.
~
Angeler free flow.
Blydraulic forward Beverse of Coelaat Caelaat f low F lem Plples Ulstance stee Urgentation Core 4 Elevatten Are)
Revgwess Olameter Flow less flow Loss Area Pressure legwatere - Rate Rate Flplag -
thittne
! runner (peereesL _ (ft)
(ft), y (t/r{
(fil Coef f icient(s) Cof f icient(si Chang 8,p t l).
(*f )
(lbm/teC[ (Ibe/leCl Mettrial ]Q e
h 4
4 e
b e
i C3 CD "Xl3 Q
I a,
2E 2:= I c-I
?
i i
-em
.ij i
i.
isolation valv2, additional informatien w:uld be recuired. The location of tne valve would be'specified using the user-supplied item number.
It is
' recuested tnat tne item numbers be uniously specified to eliminate possible - ---.
misintrepretations.o,f. data.._..
O f
O
+
4 9
6 4-S I
e O
0 O
O s
l l
35
gf 7.0 SYSTEM VALVES A separate section is provided for-description of the various valves-in the primary. and secondary systens.__ This _has_been done so.that the additional information required for describing the various valves does not cause unnecessary clutter.
a Tne easic information' required for all valves is as follows:
1.
Location of valve in system.
a.
component name, or b.
iten, number, if located in primary-piping (refer to section on primary piping) 2.
Valve type a.'
check valve b.
inertial check valve (flapper) c.
motor valve
~
d.
servo valve 3.
Valve flow area in full open position 4.
Forward flow energy loss coefficient (s),
5.
Reverse flow energy loss coefficient (s) l l
6.
Presence of any flow area enange 7.
Subcooled discharge coafficient 36
- =
4 4
- 8.. Tw:-pnase discharg] c efficiant 9.
Normal conditions fluid flow rate
- 10. Normal conditions vapor flow rate Specific information related to a particular type of valve is given below.
1.
presence or absence of hysteresis a.
b.
no'rmal valve position--open -or. closed c.
closing backpressure
.d.
leak ratio--fraction of valve area when valvc is normally closed 2.
Inertial check valves (see Figure 3) a.
repeatability of operation b.
initial valve position ~-open or closed c.
closing backpressure (P) d.
leak ratio--fraction of valve area wnen valve is normally closed e.
initial flapper angle (e )
g f.
minimum flapper angle (emin) g.
maximum flapper angle (e,x) g h.
moment of iner.tia of flapper i.
initial angular velocity (m) j.
moment arm length of flapper (L) k.
radius of flapper disk 1.
mass of flapper (W) 37
~
9 g
j e.e I
(
e '
s 4
a a
9 6
e e
6 4
en.
G G
g a,=
9 M
. f
_e st M
O I
y Q.
.3d a
uG
.c
~
3 M
o.
4 4
M 1.
G
==l N3 5
l O
G d
b N
=
=,e.
s
==.
= =.
= -
o' e
O e
e e
e O
4 i
38
- * * *N 'we=
e4
= e we m.,,
.N
--.,. ~, _. _.. -,, _,,
-m q
3.
Motor valve
- a.. conditions initiating motion b.-
conditions terminating motion c.
valve enange rate--eitner (1) rate of change.of the normalized valve area as the j
3 valve opens and closes, or (2) rate of chan,ge of the normalized valve steam position o
w d.
initial position of the valve
~
If 3.c.2 is given--normalized valve area as a function of e.
normalized stem position 4.
S'ervo 'alve--use one of the following
"~
~
normalized valve area as a function of the controlling a.
parameter (s) b.
normalized stem position as a function of the controlling parameter (s) 5.
Motor and Servo valves--for smooth area changes only forward flow energy loss coefficient (s) as a fun'ction of a.
normalized stem position reverse flow energy loss coefficient (s) as a function of o.
nonmalized stem position l
2 I
39 j
(
'8.0 FUEL R00 DESIGN 1.
Fuel Pellet Data.
A.
Composition
% U-235 B.
Enrichment (s)
+
C.
Cold state temperature for fuel
- F dimensions 3
D.
Density lbm/ft E.
Fuel pellet height ft F.
Diameter ft G.
Pellet dish spherical radius ft H.
Pellet dish depth ft I.
Pellet dish diameter ft J.
Burnup at end of each cycle mwd /MTU K.
Fuel sihteridg temireEiifure
~~
'F L.
0/M ratio M.
Fuel surface roughness um N.
Radial power distribution across pellet such that N
pn ("n+1 - "n) =.1 E
n=1 "f2 i
where j,
radius to outside of fuel pellet r
=
f th inner radial coordinate of n mesh spacing r
=
n th r +1 outer radial coordinate of n mesh spacing
=
n th power pr file ctor for n mesh spacing P
=
n number of mesh spacings in fuel N
=
i l
T
~
II. Fuel Rod Data A.
Fuel stack height ft B.
Fuel stack insulating pellets 1.
composition 2.
length a.
top pellet ft a
b.
bottom pellet ft 3
C.
Upper plenum volume including spring -
ft D.
Plenum spring :
1.
c,omposition 2.
number of coils 3.
uncompressed height ft 4.
uncompressed outer diameter ft 5.
spring wire diameter ~
ft E.
Fill gas composition-F.
Fill gas pressure at cold state psia G.
F.ill gas temperature at cold state
'F H.
Fuel rod cladding 1.
composition 2.
inside diameter ft 3.
outside diameter ft 4.
fuel rod length ft 5.
arithmetic mean roughness um I.
Axially sveraged a'nd time averaged fast neutrons /m -sec neutron flux cladding exposed to during lifetime. Fast neutron lower threshold is 1 MeV.
J.
Axially averaged and time averaged neutrons /m -sec
. thermal neutron flux cladding exposed to during lifetime X.
Time span of cladding' neutron exposure days
~
L.
Fuel rod piten ft
.l 4
III. Fuel Rod / Assembly Therma 1 hydraulic Data
}.
A.
Hydraulic diameter, nominal channel ft G.
Rod' average linear heat rate kW/ft C.
Peak to average heat flux factors as a
. function of axial elevation-D.
Hot channel and hot spot parameters 2
1.
maximum heat flux BTU /hr-ft 2.
maximum linear heat rate kW/ft 3.
fuel maximum temperature
'F
'F 4.
cladding maximum temperature 5.
hot channel outlet _ temperature
'F 6.
hot channel outlet enthalpy BTU /lbm 7.
DNB ratio (W-3 correlation),
steady state 9
9 9
e G
- 1
-l t
e 9
9 g
W:t* = - _T. m. me m ee ean,,
-