ML17338A465
| ML17338A465 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, Turkey Point  |
| Issue date: | 04/19/1978 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17206A633 | List: |
| References | |
| L-79-18, NAI-76-67, NUDOCS 7901290198 | |
| Download: ML17338A465 (301) | |
Text
{{#Wiki_filter:0'AI DYNODE-P VERSION 2: A NUCLEAR STEAM SUPPLY SYSTEM TRANSIENT SIMULATOR COPY 76-67 No. - g'7 FOR PRESSURIZED WATER REACTORS-
.USER MANUAL mz;~ To >5(TM M~KH tIL5
~ m.gsQ/za i R. C. Kern Lb dftd, HR- 'R Voa.'loins r D. Hodges Reviewed by: D. A. Lampe
-'evision 0 - July 19, 1976 Revision 1 - January 18, 1977 Revision 2 - March 15, 1977 Revision 3 - March 25, 1977 Revision 4 - September 26, 1977 Revision 5 - April 19, 1978 nuclear associates international corporation A SUBSIOIARY OF CONTROL OATA CORPORATIOIV 6003 EXECUTIVE SOULEVARO 'FSOZ 200 >$ 3 ROCKVILLE. MARYLAND20852
NAI 76-67 LEGAL NOTICE This report was prepared by Nuclear Associates International, and neither Nuclear Associates International, nor any person acting on behalf of Nuclear Associates International,
- a. Hakes any warranty or representation express or implied, mth respect to the accuracy, completeness, or usefulness of'the information contained in this report, or that the use of any information, apparatus, method, or process dis-closed in, this report may not infringe privately-owned rights; or
- b. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information apparatus, method, or process disclosed in this report.
e NAI 76-67 Revision 3 March 25, 1977 TABLE:OF'CONTENTS
'~Pa e
- 1. 0 ', INTRODUCTION. 1-1 2.0 MODEL DESCR1PTION . 2-1 2.1 'ystem'Overview..' 2-1
'.2 Reactor Core 2-1
- 2. 2.1 Fuel Rod. 2-3 2.2.2 Coolant Channel 2-6 2.2. 3 'ore Power Transient.. 2-13 2.2.3.1 Power Forced Mode. 2-13 2.2.3.2 Kinetics Model 2-15 2.3 Reactor Coolant System . 2-19 2.3.1 Conservation Equations and Equation of State. 2-19 2.3.2 Control Volume Representations.. 2-21 2.3.3 Pressurizer . 2-24 2.3.4 RCS Flow Rates. . 2-28 2.3.5 Upper Plenum Inactive Region. 2-28a 2.4 Steam Generator. 2-29 2.4 ~ 1 U-Tube Steam Generator. 2-29 2.4.1.1 Geometrv .. 2-29 2.4.1.2 Heat Transfer. 2-29 2.4.1.3 Dynamic Model. 2-31 2.4.2 Once-Through Steam Generator. 2-34 2.4.2. 1 Geometry . 2-34 2.4.2.2 Heat Transfer. 2-34 2.4.2.3 Dynamic Model. . 2-37 2.4.3 'ain Feedwater System . 2-39 2.4.4 Main Steam System Relief and Safety Valves. 2-'40
0 Il
NAI 76-67 Revision 0 July 19, 1976
'TABL'E'OF'CONTENTS '(Continued)
'~Pa e 2.5 Main Steam System....................... . .......... 2-41 2 .5.1 Geometry...................................... 2-41 2.5.2 Main Steam Line Isolation and Check Valves.... 2-41 2.5.3 Steam Dump and Bypass Valves.................. 2-45 2.5.4 Turbine Control and Stop Valves..........,....*2-46 2.5.5 Power Demand................ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
2.5.6 Main Steam System Break........................ 2-47 2.5.7 Dynamic Pressure Model........................ 2-48 2.6 Safety Systems......................................... 2-49'. 2.6.1 High Pressure Safety Injection System......... 2-50 2.6.1.1 Components.......................... 2-50 2.6. 1.2 Activation Signals.................. 2-50 2.6.2 Reactor Protective System..................... 2-51 2.7 Additional Systems.................... ~ ~ ~ ~ ~ ~ . ~ ~ . ~ ~ . ~ ~ ~ . 2-54 2.7.1 Auxiliary Feedwater........................... 2-54 2.7.2 Pressurizer Heaters and Sprays........ ~... ~... 2-56 2.7.3 Charging and Letdown.......................... 2-58 2.7.4 Control Systems.................... ~ ~ ~ ~ ~ ~ ~ ~ " 2-58 2.7.4. 1 Main Feedwater Controller. ~ ~ ~ ~ ~ ~ ~ ~ - ~ 2-58 2.7.4.2 Control Rod Controller.............. 2 61 2 .8 Initialization. ................................ .. 2-62 2.8. 1 C ore.................. ....................... 2 63 2.8.2 Reactor Coolant System....................... 2-63 2.8.3 Main Steam System................ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2-64 111
NAI 76-67 Revision 0 July 19, 1976 TABL'E OF'CONTENTS (Continued)
~Pa e 2.9 Integration...... . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ 2 65 3.0 INPUT DESCRIPTIONe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 3>>1 4.0 OUTPUT DESCRIPTION.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 1
- 4. 1 Vers i on I denti ficati on. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 1 4 2
~ Input...................... ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 1 4.3 Transient Output........................................ 4-1 4.4 Summary Output..........................................
5.0 SAMPLE PROBLEM................................................. 5-1 6 .0 REFERENCES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-1 APPENDICES APPENDIX A - NOMENCLATURE........;.....~............................... A>>l APPENDIX B - CONTROL CARDS AND THEIR USE............................... B-1
NAI 76-67 Revision 4 September 26, 1977
'L'IST'OF'FIGURES
~Pa e
Title'chematic
'1 of'DYNODE-P/2 NSSS Representation 2-2 Radial Fuel Rod Description 2-4 Axial Coolant Channel Description 2-7 Fuel Rod - Coolant Channel Coupling 2-8 5 Power Forced Mode Input 2-14 6 Step or Ramo Reactivity Input 2-17 7 Scram Reactivity Input 2-18 Representation of NSSS With Two Cold Legs Per Steam Generator 2-22 Representation of NSSS With One Cold Leg Per Steam Generator 2-23 9AA Representation of NSSS with Two Cold Legs Per Steam Generator for Dynamic Flow Calculations 2-28bb 9BB Representation of NSSS with One Cold Leg Per Steam Generator for Dynamic Flow Calculations 2-28cc 9CC Homologous Pump Head Relationship 2-28hh 9DD Homologous Hydraulic Torque Relationship 2-28ii 9A Upper Plenum Inactive Region Representation (ICIRCU=O) 2-28b 9B Upper Plenum Inactive Region Representation (ICIRCU/0) 2-28b 10 Schematic of U-Tube Steam Generator 2-30 11 Schematic of Once-Through Steam Generator 2-35 12 Schematic of Main Steam System With One Main Steam Line to Turbine 2-42 13 ~ Schematic of Main Steam System With Two Main Steam Lines to Turbine 2-43 14 Overpower aT Trip 2-53 15 Overtemperature aT Trip 2-55 16 Pressurizer Heater Pressure Control 2-57 17 Pressurizer Spray Pressure Control 2-59 18 Letdown Flow Control 2-60 19 Time Step and Print Interval Input 2-67
~ V E. W
NAI 76-67 Revision 4 September 26, 1977 L'IST 'OF 'TABL'ES
'Title '*~Pa e Homologous Curve Type Identifications 2-28jj RPS Trip Functions 2-52
NAI 76-67 Revision 2 March 15, 1977 Rev. Date Descri tion January 18, 1977 a. Page vii Revision List added
- b. Page 2-45 Steam flow calculation revised
- c. Page 2-45a Page added with temperature control option noted
- d. Page 2-46 Steam flow calculation revised
- e. Page 2-47 Text revision
- f. Page 2-51 Modifications to Overpower and Overtemperature trip functions
- g. Page 2-51a Page added
- h. Page 2-51b Page added
- i. Page 2-51c Page added
- j. Page 2-54 Text deleted
- k. Page 2-62 Revised text
- 1. Page 3-17 Revised text
- m. Page 3-24 Option added
- n. Page 3-24a Page added
- o. Page 3-25 Input revised
- p. Page 3-25a Page added March 15, 1977 a. Page 2-15 Text revised; reference to TD deleted
- b. Page 2-47 Revision identi fication corrected
- c. Page 2-65 Text revised; variable ACCURC introduced
- d. Page 2-66 Text revised; separate input specification for print interval and maximum RCS time step; variable NOSTM introduced
- e. Page 3-1 Input revised; ACCURC included
- f. Page 3-2 Input revised; DELMX and NOSTM included
- g. Page 3-2a Page added
i, NAI 76-67 Revision 4 September 26, 1977 Rev;'Ro: Rev tDatet: Descriotion: 3', Harch'25; 1977 . a ~ Page ii; Section'.3.5 added.
- b. Page v; Figures 9A and 9B added to list C. Page 2-22; Figure revised to show inactive region
- d. Page 2-23; Figure revised to show inactive region
- e. Page 2-27; Text revised.
- f. Page 2-27a; Page added.
- g. Page 2-28a; Section 2.3.5 added.
- h. Page 2-28b; Figures 9A and 9B added
- 1. Page 3-2a; NOSTH default value clarified Page 3-7; Inactive region input data added.
Page 3-7a; Page added. Sept. 26, 1977 Page.v; Figs. 9AA through 9DD added to list Page vi; Table 1A added to list
.c ~ Page 1-1; Text revised
- d. Page 2. 28; Text revised
,e, Pages 2-28aa through 2-28kk added
'ff Page"2-64; Text added gf Page 2-64a; Page added
;h. Page 2-66; Text added
.ie Page 2-66a; Page added
,J ~ Pages 3-21; Text revision
.k. Page 3-2la; Page added
'l. Page'3-22; Text added
- m. Pages 3-22a through 3-22e; Added for input description to dynamic flow model
- n. Pages 4-3 and 4-4; Text additions 0 ~ Page 4-4a; Page added P ~ Pages A-1 through A-6; Nomenclature added
- q. Page A-7; Page added
NAI 76-67 Revision 5 April 19, 1978 Rev. No. Revision Date Descri tion April 19, 1978 a. Replace Page 2-6 Revised Text
- b. Replace Page 2-25 Revised Text
- c. Replace Pages 2-50 and 2-51 Revised Text
- d. Replace Page 2-5lb with Revised Text 2-51b and 2-51bb
- e. Replace Page 2-54 Revised Text Replace Page 3-5 Revised Text g ~ Replace Page 3-15 with 3-15 Input Added and 3-15a
- h. Replace Page 3-16 Typographic error corrected
- i. Replace Page 3-20 with 3-20 Input Added and3-20a
- j. Replace Page 3-24 with 3-24 Input Added and 3-24aa
- k. Replace Page 4-2 Text Added
- 1. Replace Page 4-4 Text Added
- m. Add Page 4-6 ., Text Added
- n. Replace Pages'-1 through Sample problem 5-23 with 5-1'hrough 5-28 Revised
- o. Replace Page B-l Revised Control Cards
4 NAI 76-67 Revision < September 26, 1977
1.0 INTRODUCTION
DYNODE-P Version 2 (referenced as DYNODE-P/2) is a Fortran IV computer program which simulates the nuclear steam supply system (NSSS) of a pressurized water reactor (PWR) under transient conditions. DYNODE-P/2 was developed by Nuclear Associates International (NAI) and is an NAI proprietary program. DYNODE-P/2 is an extension of the DYNODE-P code (Reference 1). DYNODE-P/2 includes a simulation of the components of a PWR NSSS which significantly influence the response of the system to transient condi-tions. Geometry options are provided to permit representation of any of the current PWR designs. The major features of DYNODE-P/2 are: 0 Point kinetics model for core power transients with major feedback mechanisms and decay heat represented. 0 Power forced mode option for hot channel analyses. 0 Hultinode radial fuel rod and multinode axial coolant channel repre-sentations in the core. o Conservation of mass, energy, volume, and boron concentration for the reactor coolant system Conservation of momentum is optional. f n 0 Detailed pressurizer model including spray and heater systems and safety and relief valves. 0 Explicit representation of the shell side of the steam generators including conservation of mass, energy, and volume. 0 Explicit representation of the main steam system with isolation, check, dump, bypass, and turbine valves including conservation of mass, energy, momentum and volume. o Representation of the reactor protective and high pressure safety in-jection systems. 0 Representation of the major control systems. o Provisions for simulating a variety of transients and accidents including a break in the main steam system. 0 Self-initialization. 0 Batch case input. 1-1
NAI 76-67 Revision 0 July 19, 1976 This report contains: < Description of the models incorporated into DYNODE-P/2 (Section 2.0). < Description of the input (Section 3.0). < Description of the output (Section 4.0). o A sample problem (Section 5.0). 1-2
NAI 76-67 Revision 0 July 19, 1976 2.0 MODEL'DESCRIPTION This section describes the theoretical basis for the DYNODE-P/2 computer program. The basic components are:
< The reactor core o The reactor coolant system < The steam generator 0 The main steam system 0 Safety systems < Additional systems 2.1 ~0 The general layout of the PWR-NSSS simulated by DYNODE-P/2 is shown in figure 1. This schematic corresponds to one loop of a particular system design. DYNODE-P/2 provides the capability of full loop simulation for any of the current PWR designs. Models which describe unique features of each design are discussed in the appropriate sections below.
This schematic indicates the major components and systems which are simulated. In addition to the component hardware, controller and actuation system simulation is also provided. 2.2 Reactor Core The reactor core model includes a transient simulation of the neutron power, the fuel and cladding temperatures at the average power, and the energy distribution within the average coolant channel. Each of these features of the DYNODE-P/2 program are discussed below. 2-1
0 Relief Safety Valves Val ves Br ak Relief Valves Safety Valves ~X Spray Turbine Valves Bump Heate Bypass Control Rods Hain Feedwater Co e Charging X s High Pressure Auxiliary Feedwater Safety Injection Letdown C S FIGURE I SCHEMATIC OF DYNODE-P/2 NSSS REPRESENTATION M W~v Vl '4 (Only One Loop Shown) u)O Ch S v Q Qj
'4
&O Ch
NAI 76-67 Revision 0 July 19, 1976 2.2.1 Fuel Rod The fuel rod representation at the average axial power location consists of a discrete radial nodalization with-in the oxide and cladding regions as shown in Figure 2 ~ The oxide region is divided into M equal volume nodes, while the cladding is represented by two nodes. The tem-perature (Tn) is calculated at the average radius (r) within each node (Vn ) and is representative of the average temperature within that node. The fuel-cladding gap is not represented geometrical, but its effect on heat con-ductance is taken into account through the use of a heat transfer coefficient as discussed below. Within the fuel rod, the radial heat conduction equation is: aT(r:t) <~. ~ 1 a f>~aT r,t) The nomenclature is given in Appendix A. The total core power density is Z (see Section 2.2.3). The fraction rf is assumed to be generated in the oxide. No heat genera-tion is assumed in the cladding. The radial heat genera-ti on profi 1 e in the oxide i s f(r) . Thus Q(r,t) = Q o o f(r)r; f 0 <r < RIN (2) 0 r>RIN The heat capacity and conductivi ty of the oxide are temperature dependent and expressed as: cf = ACP + BCP(T) (3a) k~=~*C(T 27) (3b) 2-3
NAI 76-67 Revision 0 July 19, 1976 oxide I / ROUE
\
I I I I I I I I I I ) I T I I M+1 I I TM+2 I I I I I I I I M nodes FIGURE 2 RADIAL FUEL ROD DESCRIPTION 2-4
NAI 76-67 Revision 0 July 19, 1976 where ACP, BCP, A, 8, and C are user specified con-stants and T is the oxide temperature in C. The cladding conductivity and heat capacity and the oxide and cladding densities are assumed constant and uniform. The boundary conditions for the oxide region are: BT = 0 ar (4a) r=0 I~aT 1 (4b) The heat transfer area between the oxide and cladding A is 2nRIN. The heat flux can be expressed in terms of the tempera-ture difference between the last oxide and first cladding node as M M+1 (5a) gap gap where the effective heat transfer coefficient is 1 (5b) g'p (RIN - - RIN) rM) 1 (rM+1 HG is the gap heat transfer coefficient which depends on the average fuel temperature through the relationship
<5T <6T >:2 HG = HG + AHG + BHG (5c)
<T f0 f where < Tf> is the average fuel temperature in K.
2-5
4~ NAI 76-67 Revision 5 Apr il 19, 1978 The boundary conditions for the cladding are: 2" kc r r A P (6a)
= RIN
.and
-2m k c
r aT ar
= A s Ps (6b)
= ROUT The surface heat transfer area A is 2m ROUT and the surface heat flux is given by
~
s s M+2 W (7a) where the effective heat transfer coefficient is
= 1 U
ROUT -.@M+2 (7b) 1 HF is the surface heat transfer coefficient which is assumed to be proportional to the core flow rate raised to the 0.8 power with a minimum value of 5.0 Btu/hrft F. The core average bulk coolant sinktemperature, TW, is computed from the core average coolant enthaloy and RCS pressure. 2.2.2 Coolant Channel The axial coolant channel representation is shown schem-atically in Figure 3. The coupling between the fuel and coolant channel is shown in Figure 4. The nodal spacing is divided equally along the full length of the channel. 2-6
NAI 76-67 Revision 0 July 19, 1976 TOP OF CORE NS nodes w Wg BOTTOM OF CORE WT, h ~ l t FIGURE 3 AXIAL COOLANT CHANNEL DESCRIPTION 2-7
NAI 76-67 Revision 0 July 19, 1976 oxide 1 adding y A
~sAs AXFK WT, inlet FIGURE 4 FUEL ROD - COOLANT CHANNEL COUPLING 2-8
0 NAI 76-67 Revision 0 July 19, 1976 The core average heat flux at the cladding surface is given by Equation (7a). The axial heat flux profile (AXFK) is assumed to be constant, however the magnitude (P s ) will vary during the transient because of tempera-ture variations.'he axial profile is input into OYNODE-P/2 which is normalized internally in the program to an average of 1.0. The heat balance equation in the coolant channel at an arbitrary point z is 8 >,A,f(z) s s Bh 1 ~d+ r Zf(z)
+ (8) w at ) Afl Aflo8z J dt w
~mRIH) flow f(z) is the normalized axial heat flux profile. rw =
(1 - rf) is the fraction of the core power generated directly in the coolant. The coolant mass flow rate (W) is assumed to always be in the positive (upward) direc-tion and is given by the sum of the loop flows (see Section 2.3.4). The boundary condition at the core inlet is
= h. (9) inlet The coolant properties, which are based on the enthalpy and pressure, are evaluated from polynominal fits to the ASME 1967 Steam Tables below the critical pressure (Reference 2). The pressure used in these evaluations is obtained from the pressurizer model described in Section 2.3.3.
2-9
NAI 76-67 Revision 0 July 19, 1976 Equation 8 is integrated over a typical nodal volume. The resulting equation yields a coupled set of differ-ential equations which are integrated simultaneously over each time step. Based on the new enthalpies and the pressure at the beginning of the time step, the specific volumes for each node are calculated from the above water properties. These specific volumes are used with the fixed nodal volumes to compute the new nodal masses. The differences between the new masses and those at the beginning of the time step form one component in the calculation of the mass transported between the RCS and pressurizer ('surge line flow) over that time step (see.Section 2.3.3). The nodal quality is given by XK (hg h f)/(h (Ioa) For saturated conditions, the local void fraction (ak) is calculated with one of the following models de-pending on the user's option: Variable Slip Model ak = CC1 + CC2(Xk) + CC3(Xk) + CC4(Xk) (Iob) Constant Slip Model ek = 1/(1 +((1-Xk Xk 'f . SLIP/v g
) (Ioc) where the constants CC1, CC2, CC3, CC4, and SLIP are input parameters.
DYNODE-P/2 considers departure from nucleate boiling (DNB) along the coolant channel. The W-3 correlation is the basis for this analysis. Non-uniform axial heat 2-10
NAI 76-67 Revision 0 July 19, 1976 flux effects are taken into'account explicitly. The user has the option of considering cold wall effects on DNB. This correlation is given by. DNB x 10 ~ QDNB1
- gDNB2/FF (lla) gDNB1 is the basic W-3 correlation given by ODNB1 = ((2.022 - 0.0004302 p) (lib)
+'(0.1722 - 0.0000984 p)
- exp f(18.177 - 0.004129 p) x3} *
( (0.1484 - 1.596 x + 0.1729 x ]x])
- G
+ 1.037} *
( 1 157 " 0 869 x} * {0.2664 + 0.8357 exp)-3.151 O j} * ( 0. 8258 + 0. 000794 (h f- hi nl t) } gDNB2 is the optional cold wall factor (included only if the input value of OEH > 0) given by gDNB2 = I.1.36 + 0.12 exp (9x)] * (1 1 c) tl.2 - 1.6 exp (-1.92 D )]
- I:1.33 - 0.237 exp (5.66 x)]
DEH is the heated equivalent hydraulic diameter and is used to evaluate both gDNBl and gONB2 when an unheated surface is present in the channel (D =DEH>0). DE is the hydraulic diameter and is used in Eq (lib) (D =DE) when DEH < 0. The FF factor accounts for non-uniform axial effects and is given by 2-11
NAI 76-67 Revision 0 July 19, 1976 FF(z) = CC
>(z') e
-CChz - z'3
-CZ DNB,EUj dzo'
'z'
.~a (1 1 d)
L-1
)
1.0 . ~a az where 1 B L(] )4 31((G< )0+475] ft 1 (1 1 e) The distance ZONB t EU in (lid) is the equivalent uniform heat flux DNB length defined by DUB,EU hk hi 1 (eA AZF dz (llf) In the above expressions, the local quality is eval-uated from Equation (10a) and G =~ MT flow x10 -6 (llg) If the heat flux at any location along the fuel rod equals or exceeds the ONB heat flux at that location divided by CHFFRC (a DNB margin factor as input by the user); i.e., gk > pDNB/CHFFRC, the heat flux at that location is set to zero. Rewetting (pre-DNB) is per-mitted if the calculated heat flux becomes less than ONB'/CHFFRC. The analysis of the core boron concentration is performed in the same manner as for the remainder of the reactor coolant system; i .e., only the average concentrati on i s calculated (see Section 2.3.1). 2-12
NAI 76-67 Revision 0 July 19, 1976 2.2.3 Core Power'Transient In DYNODE-P/2, the core power can either be calculated directly from the point kinetics model or be input. These models are described below. The initial power density, PO, and the radial pin power peaking factor, PRAD, are input into the program. The radial peaking factor is used to increase the input value of the power'ensity, so that the initial power density used in the analysis is given by PO
- PRAD.
2.2.3.1 Power Forced 'Mode This option is exercised for cases. in which the core average power transient is known. The input power transient, P(t); is normalized to the initial core average power level, so that in Equation (2) (12a) When this option is used, all calculations associated with the point kinetics model are bypassed. The power transient is input in the form of a table set as shown in Figure 5. The input'values of time are measured from t = 0. Linear interpolations between table values are performed for TPDA(1) < t< TPDA(NTPOW). Outside this range, 1.0 TPDA(1) p(t) = (12b) POWER(NTPOW) t > TPDA(NTPOW) 2-13
NAI, 76-67 Revision 0 July 19, 1976 Power (NTPOW) Po er 1 ower (2 o er (NTPO t, sec TPD (1) TPD (2) TPDA ( TPOW-1) TPDA (NTPOW) FIGURE 5 POWER FORCED MODE INPUT 2-14
NAI 76-67 Revision 2 March 15, 1977 The example shown in Figure 5 is not typical, since POWER(l) g 1.0 and TPDA(1) 9 0.0, but is intended to indicate the general manner in which this table set is utilized in the program. 2.2.3.2 Point Kinetics Model In the point kinetics model, the transient is assumed to begin at t =,0. ! The point kinetics equations including decay heat are given by IT' an = n at RL eff [k (1-g) - 1] + AA ( 1 ) ) C X. RL 1+a i i (13a) i=1 and aC. at 1 = vg.i ~ YiK
- C A.; i=1,...,IT (13b) a=a IT i=1 8
B
-1 (13c) aq.
;at .
= y.n 1
- A.q.
11 ; i = 1, ..., IDH (13d) IDH IDH Z = (1 - z y.)n + z A.q. (13e) i=1 i=1 The major feedback mechanisms; Doppler, moderator tem-perature (enthalpy), and boron; are included in the evaluation of k ff. In addition, reactivity insertions to rod motion are taken into account. Thus eff'ue ff DOP ENT BORON IN (isa)
+ ~kS(t) + 'kCRC The Doppler reactivity is obtained from either 4KDDD
= {1 + DK1 <a>}DK2 (~<T T> - 8 TDK3 (14b) 2-15
N NAI 76-67 Revision 0 . July 19, 1976 or an interpolation/extrapolation in an input table of reactivity versus average fuel temperature. The mod-erator reactivity is obtained from either
~kENT
= (AK <h> + BK <h> 2 + CK) or a table of reactivity versus normalized coolant density.
Here,-<a> and <h> are the core average void fraction and coolant enthalpy, respectively; <Tf> is the volume average fuel temperature in K; and T's the bulk coolant (sink) temperature in K. The boron contribution depends on the total boron mass in the coolant and is given by
= DKBC x bCORE x (~CORE/~CORE 0) hkBORON where DKBC is the reactivity coefficient corresponding to the initial core coolant density.
ak<N is the sum of the initial Doppler, enthalpy, and boron reactivities, and the reactivity insertion hkRS>. akRS< is input as either a step change or a ramp change in reactivity as shown in Figure 6. These reactivity insertions begin at t = 0. The initial Doppler and enthalpy terms are included here to balance the reac-tivity at t = 0, so the core is just critical at .that time. akS(t) represents the scram reactivity and is input in table set form as shown in Figure 7. Note that the input values of time are measured with respect to TSCRAM, so that LkS(t)=0 for t < TSCRAM. Linear inter-polations between table values are performed for TDSA(l) < t - TSCRAM < TSDA(NTSCRAM). Outside this range, 2-16
NAI 76-67 Revision 0 July 19, 1976 STEP (IK=O) RSTEP > 0 RSTEP < 0 RAMP (IK=1) t= TD + RTOT/RRAMP RRAMP > 0 RTOT > 0 [RRAMP = ak/St] 0.0 RRAMP < 0 RTOT < 0
= TD + RTOT/RRAMP t, sec t=o FIGURE 6 STEP OR RAMP REACTIVITY INPUT 2-17
0 "tj 0
NAI 76-'67 Revision 0 Ju1y 19, 1976 OKSCRM (NTSCRM-1) DKSCRM (NTSCRM) t,sec OKSCRM(l) DKSCR (2) TSDA 1 TSDA(2) TSOA(NTSCRM-1) TSDA NTSCRM t = TSCRAM FIGURE 7 SCRAM REACTIVITY INPUT 2-18
NAI 76-67 Revision 0 July 19, 1976 DKSCRM(l) t - TSCRAM < TSDA(1) (14 ) DKSCRM(NTSCRM) t - TSCRAM > TSDA(NTSCRM) An option is provided to determine TSCRAM. If ISCRAM > 1, the input value for TSCRAM is used. If ISCRAM = 1, TSCRAM is based on the reactor protective system trips. In this case, TSCRAM is set equal to the time the trip setpoin4's reached plus the corresponding trip delay time. The trips which are simulated in DYNODE-P/2 are discussed in Section 2.6.2. ak is the reactivity change due to control rod motion CRC produced by the control rod controller (see Section 2.7.4.5). 2.3 Reactor Coolant S stem This section describes the models used in DYNODE-P/2 to represent the regions of the reactor coolant system (RCS) excluding the core. Included are discussion of the conservation and state equations, geometry representations, the pressurizer model, and the system flow distribution. 2.3.1 Conservation E uations and E uation of State The RCS (excluding the core and pressurizer) is divided into regions (control volumes) of constant volume (see Section 2.3.2). The conservation of mass and energy equations for volume i are based on the following differential equations. 2-19
NAI 76-67 Revision 0 November 4, 1976 "at ah W AaZ ah + Jltdp 1 Q (16) These equations're integrated over':.a;fixed volume V-1 to yield: dh. W. (h.1 - h. ) dt 1 1 m 1
+My dt /J1 m.
+ (17)
~(h,, -.,I,.) dill.
The inlet and outlet enthalpies are based on the average control volume enthalpies, so that h 1
=h. 1 (1B)
In the above equations, p is the RCS pressure ob-tained from the pressurizer model, and Q; is the heat removal from sources external to the RCS.. The only external source considered in DYNODE-P/2 is the heat transfer between tube and shell sides of the steam generator (see Section 2.4). The last term on the right
',a hand side of (17) is included to conserve energy as fluid is transported between the hot leg and the pressurizer (see Section 2.3.3).
The entire coupled set of Eqs (17) are integrated over a time step simultaneously assuming a fixed heat sink. 'ased on the new enthalpies and the pressure at the beginning of the time step, the specific volumes for each control volume are calculated from'..the water pro-2-20
.It NAI 76-67 Revision 0 July 19, 1976 perties in Reference 2. These specific volumes in con-junction with the volumes are used to compute the new control volume masses. The differences between the new masses and those at the beginning of the time step form the remaining component in the calculation of the surge line flow for that time step (see Section 2.3.3). For the cold leg, the mass and energy are adjusted for the charging, letdown, pressurizer spray, and high pressure safety injection flows. This adjustment is made prior to calculating the surge line flow. The representation for these systems are discussed later. The conservation of boron equation for all regions in the RCS (excluding the pressurizer) are: M (bin bout) 1 1 1 1 3t (i9a) mi The inlet and outlet boron concentrations are given by the control volume averages, so that bout = b (19b) 1 1 The boron concentrations in the cold and hot leg regions are adjusted for the charging, letdown, spray, safety injection, and surge line flow. 2.3.2 Control Volume Re resentations The RC system is represented by control volumes as shown in Figures 8 and 9. Figure 8 corresponds to NSSS designs in which there are two cold legs per steam generator (LCE 9 0), and Figure 9, in which there is one cold leg per steam generator (LCE = 0). 2-21
LOOP 2 LOOP 1 UPPER PLENUM INACTIVE PRESSURIZER REGION STEAN GENERATOR STEAM GENERATOR TUBES TUBES 10 UPPER SG INLET HOT LEG ,SG INLET SG OUTLET SG OUTLET PLENUM HOT LEG 2 PLENUM PLENUM ll PLENUM PLENUM 9 8 1 3 5 I I I COLD LEG A I 12 W2A CORE COLD LEGS 6 COLD LEG B 13 W2B LOWER PLENUM W2 = W2A + W2B 14 15 CONTROL VOLUME NAME MKI M NUMBER M Q X Wo th Vla Cn V FIGURE 8 REPRESENTATION OF NSSS WITH TWO COLD LEGS PER STEAM GENERATOR 4l
LOOP 2 LOOP 1 UPPER PLENUM INACTIVE 1 PRESSURIZER REGION I STEAM GENERATO STEAM GENERATOR TUBES I TUBES 10 I UPPER I HOT LEG SG OUTLET SG INLET PLENUM SG INLET SG OUTLET PLENUM I HOT LEG 2 PLENUM PL/N 8 3 PLENUM 1 5 I COLD LEG 13 W2 CORE COLD LEG 6 WT LOWER PLENUM 14 15 FIGURE 9 REPRESENTATION OF NSSS WITH ONE COLD LEG PER STEAM GENERATOR
0 NAI 76-67 Revision 0 July 19, 1976 For simulation of plants with more than two loops, the loops which behave identically are grouped together to form an effective loop. For plants with two cold legs per steam generator, the cold legs in Loop 1 are com-bined as shown in Figure 8. 2.3.3 Pressurizer The RC system pressure is taken as the pressurizer pressure as long as there is liquid in the pressurizer. The pressurizer model is identical to the TOPS model. except that wall condensation is ignored (Reference 3) as long as steam and liquid are present. This is a non-equilibrium model in which the conservation of mass, energy, and volume are solved. fate the uuaar Are,'Iygep persons simultaneously. These equations are: d (2oa) dt w surge surge spray spray
+ (h -h s ra )
f Wspray h hG- f G
-W ec h
g
-~J dVw+ ~wG + ~heater dt dt surge spray spray (20b) hG hf ec (2oc) dt SV. RV spray hG- hf ) hG
+ W ec h
g
- ~
J 'VG dt
- q wG (21a) 2-24
NAI 76-67 Revision 5 April 19, 1978 dmG f (h h ra } t -(WSV + WRV Wspray s ) (21b) G f ec dVG
" dV (21c)
The surge line flow is completely mixed with the lower region fluid and is based on the expansion or contraction of the fluid in the remainder of the RCS (see Sections 2.2.2 and 2.3. 1). Thus, the surge flow is given by dm. (20d) 1 where the sums are taken over all other fluid regions of the RCS. The surge enthalpy is taken as the hot leg enthalpy when flow is into the pressurizer and as the pressurizer liquid enthalpy when flow is out. The evaporation-condensation flow is given by W = KA(p t(T ) - p) (22a) where (22b) 0.0425. 1096/ T +460 w for evaporation K(lb/sec-ft -psi) = 0.0001 for condensation The desuperheating heat transfer between the two regions is given by UWGA(TG
- TW) (23a)
QWG where UWG
= 9.0 Btu/sec ft F (23b) an g~G 0,0 (23c) 2-25
~ 4 NAI 76-67 Revision 0 July 19, 1976 The pressurizer heater and spray representations are dis-cussed in Section 2.7.2. The enthalpy of the spray flow is the cold leg enthalpy. The steam flows through the safety and relief valves are based on the same model. For the relief valves, the steam flow is 2p 1/2 RV RV 2 (24a)
~G,("./A )RV where RV RVl RV2 RVl (24b) 0 < FRV < 1 0 (24c)
Similar expressions apply for the safety valves. This set of equations is integrated to yield the mass, and internal energy of each regi on as a function of time. The pressure is calculated from an iteration procedure which considers both regions simultaneously at a common pressure. This procedure which is identical to TOPS forces the sum of the region volumes to coincide with the fixed total pressurizer volume. DYNODE-P/2 calculates the boron concentration of the pressurizer liquid and takes into account the changes due to the surge and spray flows. The surge line boron concentration is that of the hot leg when the flow is into the pressurizer and the pressurizer liquid value when it is out of the pressurizer. The spray concentration is that of the cold leg. The boron is treated as being non-volatile, so that the boron remains in the lower region during evaporation. 2-26
NAI 76-67 Revision 3 Mar ch .'25," '1977 If the pressurizer is full (mG
= 0), the liquid flow through the relief and safety values, WWR, is computed from either Equations (24a) using vW in place of vG or from an interpolation/extrapolation in table input set for mass flow rate per unit area versus pressure at constant enthalpy. In this latter case, the effect of variations in the liquid enthalpy from the curve ref-erence value is taken into account through use of an additional factor; namely i l + 3 ( G ) fh> - h
~
In ei ther case, Equati on (24b) i s repl aced wi th RV P RV1 ( 'V1 (24d) i.e.; the valves are assumed to open linearly over a 10K range of the lift pressure. For a full pressurizer, Eqs (20) are replaced with dU dt surge surge spray spray (25a) WR W ~heater w 3t (25b) surge spray WR and Equati ons (21) are i gnored. The boron concen trati on is adjusted for the water relief. Once the pressurizer empties (mW=O), the RCS pressure is based on either the average fluid properties in the core and RCS. loops or the fluid properties of the upper plenum inactive region -for the remainder of the transient. This latter option is used if the inactive region is included (VUP>0.0) and ICIRCU=2 and is des-cribed in Section 2.3.5. For the first option, the effective volume for these pressure calculations is computed from the total internal energy and mass in 2-27
NAI 76-67 Revision 3 March 25, 1977 these regions at the time the pressurizer empties. This volume is very nearly equal to the actual total volume of these regions. If the fluid in these regions is contracting, no surge line flow is permitted, and the mass addition to the other regions is obtained from the upper plenum region. The upper plenum inactive region (See Figures 8 and 9) is used for this purpose if this volume is included (VUP >0.0); otherwise the upper plenum, Volume 1, is used. If the 2-27a
NAI 76-67 Revision 4 September 26, 1977 fluid is expanding, the excess fluid is put into the pressurizer in the form of steam. The pressure is not allowed to drop below the saturation pressure correspond-ing to the maximum local enthalpy in these regions during this period. 2.3.4 RCS Flow Rates The transient RCS flow rates may either be specified by the user (IPUMP = 0) or computed from the conservation 4 of momentum (IPUMP P 0). For the former cases in which the NSSS design has one cold leg per steam generator (see Figure 9), the flow rates in each loop (Wl and W2) are specified individually. for cases involving NSSS plants with two cold legs per steam generator (Figure 8), the individual loop flows and the flow in cold leg 8 of Loop 2 are specified. In all cases, the core flow (WT) is the sum of the loop flows (Wl and W2). The flow 'in Loop 1 is assumed to be always greater than zero. The flow in Loop 2 is arbitrary (positive or negative), but Wl + W2 ) 0, otherwise WT < 0. All flows can be specified either by table sets or by equation fits of the following form. The flow fit for Loop I is Wl = Wl (1 + WX1 x t + WX2 [exp(WX3 x t)]) (26) i(> + WX2) where t is measured wi th respect to 0. Similar expressions hold for the Loop 2 and Loop 2 Cold Leg B flows. The flows may be specified in terms of mass or volumetric rates. If volumetric rates are specified, the mass flows in each loop are based on the corresponding cold leg specific volumes. 2-28
NAI 76-67 Revision 4 September 26, 1977 If the dynamic flow option is selected (IPUMP 9 0), the conservation of momentum equations for the RCS flow rates and the conservation of angular momentum for the RCS pumps are solved. Figures 9AA and 988 show the schematical diagrams for the two types of loop configura-tions corresponding to Figures 8 and 9, respectively. Figures 9AA and 988 also identify the pump numbering system and the loop fluid inertial factors, (L/A)', and pressure loss coefficients, K's. All pumps are assumed to have the same hydraulic characteristics and identical pump motors. 2-28aa
~ ~ NAI 76-67 4 'evision September 26, 1977 Loop 2 Loop 1 K2 K) (L/A)2 (L/A)I "Rv M2 = W2A + W2B (L/A)Ry MT = Ml+ M2 K2B W2A (L/A)2B K2B W2B (L/A)2B Figure 9AA REPRESENTATION OF NSSS WITH TWO COLD LEGS PER STEAM GENERATOR FOR DYNAMIC FLOW CALCL'LATIONS 2-28bb
1 NAI 76 67 ReViS10A 4 September 26, 1977 Loop 2 Loop 1 K2 K1 (VA)2 (L/A)1 Rv (LiA)R W1 WT = W1 + W2 Figure 9BB REPRESENTATION OF NSSS WITH ONE COLD LEG PER STEAM GENERATOR FOR DYNAMIC FLOW CALCULATIONS 2-28cc
NAI 76-67 Revision 4 September 26, 1977 For the loop configuration with two cold legs per steam generator, loop segments 2A and 28 are assumed to have the same fluid inertial factors, (L/A)28 and pressure loss coefficients, K28. In general, the conservation of momentum equation for loop 1 is: (L)* dH. (26a) where (L/A).1 is the effective loop inertial factor which includes the core fluid and ap. is the total loop pressure rise. The corresponding conservation of angular momentum is deal I.i dt
~
= T.
i (26b) where I. is 1 the total inertia of pump i and its motor and T. is the corresponding total torque. 1 For the loop configuration with two colds per steam generator, the loop pressure rises are: P1 pump 1 ~ RV K1W1 IW1 I (26c) Ppg= Pp,pp - ~- 28
'2A 2P1 28 2A~ 2A~
28'8'
- hpP, b,p (26d)
(26e) 28 pump 3 2p28 P2 'RV K2W2~W2~ + . pas (26f) P2 2-28dd
HAI 76-67 Revision 4 September 26, 1977 where KRy WTIW Ry (26g) 2p1 and ap = pa - p (Refer to Figure 9AA for locations a aB g and 8). Also, from continuity, dM2 dW2A + dM2B (26h) dt dt Thus, the momentum equations governing the flow rates W2, W , and W along with Eq. (26h) represent a set of four equations in four unknowns; namely, dW , dM dW , and ap . This set can be reduced to two equations dt dt dt in terms of dW2A and dW2B
~t dt For the loop configuration with one cold leg per steam generator, the loop pressur e pressure rises are:
K.W lM. 1
~pi ppump i pRV (26l) 2pi where ap is given by Eq (26g).
It should be noted that the gravity heads are neglected in the loop momentum equations, since they are small for practical transient analyses. Thus, conditions of natural circulation cannot be represented properly and should be avoided. In general, the .total (net) pump torque is given by: T = T . - T.hi- - T.. - T . (26')
~
ml Tl Wl 2-28ee
4 HAI 76-67 Revision 4 September 26, 1977 where the terms on the right hand side represent the contributions due to the motor, hydraulics, friction, and windage, respectively. The motor torque, which is a function of the motor speed when the power is on, is set to zero if the motor is off or if the pump shaft is assumed to be either locked or sheared. The hydraulic torque is discussed later. The friction and windage torques are given by nf Tf - Cf I~/ Rl (26k) and T = C fo,/~RI {261) where ~R is the rated pump speed. Any pump motor may be either on ar off initially, but at least one pump in the system must be on. However, for the loop configuration with two cold legs per SG, if only one pump is on initially in Loop 2, the Loop 2B pump must'be the one which'ts.on. Six types of pump transients are permitted; namely o Continuous steady-state operation (constant speed) o Pump motor trip o Pump shaft seizure (locking) o Pump shaft break (shearing) o Pump motor startup o Specified time-dependent speed. Any pump may experience any of the above transients with individual specification for the time at which each pump begins its transient; however, all pumps experiencing the last type are assumed to have the same speed versus time behavior. When a pump shaft shears, the inertia I for that pump is changed to reflect the decoupling between the pump and the flywheel and motor, and the windage torque is set to zero. 2-28ff
HAI 76 67 Revision 4 September 26, 1977 The hydraulic characteristics of the pump are represented by the homologous relationships for centrifugal pumps (See Section V.5 of Reference 5). The homologous representation relates the dimensionless pump head, h, and dimensionless hydraulic torque, b, in terms of the dimensionless speed, a, and dimensionless volumetric flow, v, which are developed from the pump four-quadrant curves. These relationships are shown in Figures 9CC and 9DD for single phase flow through the pump along with the four curve type identifications. These curves yield the pump charac-teristics for all possible values of pump speed and flow (including normal and reverse directions). Table 1 A gives a clearer definition for each pump head curve type. The corresponding table for the torque curves is identical with b replacing h. 'The dimensionless parameters are given in terms of the rated values by: a ~/"R
~ = Q/QR h = H/HR (26m) b ~ T/TR The pump head and hydraulic torque are thus found by: computing a and v for the given conditions; finding either h/a 2 and b/a 2 (if a > v) or h/v 2 and b/v 2 (v > a); calculating h and b; and using these results in H=hHR (26n) and R'R (26o) where p and pR are the actual and rated fluid densities, respectively.
The pump pressure rise is given by pump (26p) 2-28gg
NAI 76-67 Revision 4 September 26, 1977 h . h 2 2 v a 01 a > v 0 ~ +1 0 0 0 Figure 9CC Homologous Pump Head Relationship S
NAI 76-67 Revision 4 September 26, 1977 pO a, v 0 a -.I 0 0
"1.0 0
Figure 9DD Homologous Hydraulic Torque Relationship 2>28jj
NAI 76-67 Revision 4 September 26, 1977 TABLE 1A HOMOLOGOUS CURVE TYPE IDENTIFICATIONS Curve Ratio Which Curve
.is Between Name Type -1 and 1 1 >0 >0 /a h/a2 HAN 1 >0 <0 v/a h/a2 HAD 2 >p >0 a/v h/v2 HVN 2
0 . . a/v h/v2 HVR 3 <p <0 v/a '/a~ HAT 3 ~ <0 >0 v/a h/a~ HAR <0 <0 a/v h/v2 HVT >0 <0 a/v h/v~ HVD h 2-28jj NAI 76-67 Revision 4 September 26, 1977 Finally, an option is available which allows pumps to rotate backwards (reverse speed). Pumps with sheared shafts and pumps with specified time-dependent speeds are always allowed to rotate backwards. 2-28kk h r 0 NAI 76-67 Revision 3 March 25, 1977 2.3.5 U er. Plenum Inactive 'Re'ion The representation of the upper plenum inactive region (dead volume) as shown in Figures 9A and 98 is optional. This region is included, if the user specified volume, VUP, is greater than 0.0. Two options are available for representing the circulation flow between the downcomer, inactive region, and upper plenum. In either case, these circulation flows transport energy and boron with no net mass transport. Mass transport out of the inactive region is assumed to occur only after the pressurizer is emptied and the RCS fluid is contracting as described in Section 2.3.3 above. For the first circulation flow option (ICIRCU=O or 2), the circulation flow path as shown in Figure 9A is from the downcomer through the inactive region and into the upper plenum. II For the second option (ICIRCU=l), two independent path types are assumed as shown in Figure 9B; one between the down-comer regions and the inactive region, and one between the upper plenum and the inactive region. If ICIRCU=2, the RCS pressure is based on the inactive region fluid properties after the pressurizer empties. For this case, the effective volume for this region is calculated from the internal energy and mass in this region at the time the pressurizer empties. This volume is very nearly equal to the actual inactive region volume. For this pressure calculation, the following two assumptions are made for the inactive region:
- 1. The process is constant specific volume.
- 2. The fraction FFUPIV of the pseudo-energy removal rate (the RCS mass contraction rate times the inactive region enthalpy) is removed.
2-28a , 1 0 NAI 76-67 Revision 3 March 25, 1977 UPPER PLENUM I INACTIVE REGION I I I I I WT* )FDCIV. I I W2* FFDCIV W1* lFFDCI V I I I I I UPPER I I I PLENUM I I REGION I I WT DOWNCOMER REGIONS FIGURE 9A - UPPER PLENUM INACTIVE REGION REPRESENTATION (ICIRCU=O or 2} / UPPER PLENUM I / INACTIVE REGION 1 I I I W2(" FFDCIV WT* FFUPIV Wl* FFDCIV l I I I I I I I UPPER I PLENUM REGION DOWNCOMER REGIONS FIGURE 9B - UPPER PLENUM INACTIVE REGION REPRESENTATION (ICIRCU=,l) 2-28b 0 NAI 76-67 Revision 0 July 19, 1976 2.4 Steam Generators This section describes the models provided in DYNODE-P/2 for sim-ulation of both the .U-Tube Steam Generator (UTSG) and Once-Through Steam Generator (OTSG) designs. For each design, the geometric representation, and the heat transfer and dynamic models are described. 2.4.1 'U-'Tube 'Steam 'Gener'ator 2.4.1.1 ~Geometr Figure 10 is a schematic of the geometry of a typical UTSG as modeled in DYNODE-P/2. 2.4.1.2 Heat Transfer The heat transfer coefficient, USG, from the tube to shell side is based on: 0 RCS coolant to tube inside surface - Forced convection (Dittus-Boelter with a minimum valve of 5.0 Btu/hr ft F) 0 Tube inside to outside surface - Slab heat conduction o Tube outside surface to shell side water - Nucleate Boiling (Thorn) o Fouling factor - User specified These heat transfer correlations are evaluated from the local temperatures and properties. The total steam generator heat transfer rate is given by x x aT>m (27a) USG. x ~i SGA. FSG,. 2-29 j s. e NAI 76-67 Revision 0 July 19, 1976 WSGR j WSGS Relief Valves I t Safety Val ves VOLSG ARESG DSGS Steam hg Main Feedwater ~ Auxiliary WF, HFD (WAXFM Feedwater + WAXFS) DSG SGFA 0 Tubes Outlet Plenu Inlet Plenum W1 FIGURE 10 SCHEMATIC OF U-TUBE STEAM GENERATOR 2-30 NAI 76-67 Revision 0 July 19, 1976 where bT< is the log-mean temperature difference from tube.-to she1T si'de. The factor F is given by G FSG = AR x FTC (27b) where AR is a constant factor calculated during initial-ization such that the steam generator heat load matches the core power at that time (see Section 2.8.3). FTC accounts for changes in the heat transfer ar'ea as the tubes become uncovered during the transient and is proportional to the mixture level.. The mixture level model is discussed in the following section. An option has been provided (IFLGT) for determining the initial shell side temperature (and 'hence pressure). If the input temperature TS is used only as an initial guess, the above model is used to calculate USG. If the input value of TS is used to set the shell side pressure, then USG is based on forced convection from the RCS coolant to the tube inside surface plus an effective resistance from the tube inside surface to the shell side coolant. This latter resistance is calculated during initialization to match the steam generator heat load and the core power and is held constant during the transient. The fouling factor is ignored 'in this case. If reverse heat transfer (shell to tube side) is calcu-lated, the heat transfer rate as calculated from the above model is multiplied by the user specified reverse heat transfer factor. 2.4..3 ~II i dd The conservation of mass, energy, and volume are solved for the shell side of the steam generators. Under all conditions, the water and steam are assumed to be saturated 2-31 0 NAI 76-67 Revision 0 July 19, 1976 and in equilibrium. Figure 10 shows the mass flows and enthalpies which are considered in these conser-vation equations. An option (ISGOPT) is provided for calculating the pressure and temperature responses of the shell side under transient conditions. When the temperature option is selected, the transient temperature is computed from the model discussed in Reference 4. When the enthalpy option is selected, the transient pressure is computed for the equilibrium state of the steam and water based on the specific volume and enthalpy. In either case, the saturated water properties are given in the form of table sets based on the ASME 1967 Steam Tables. The'team which is generated on the shell side due to heat addition and flashing is assumed to be produced in the two-phase region as indicated in Figure 10. This steam is allowed to rise to the mixture level, ZMIX, where it is separated into the steam"region. The mixture level representation in DYNODE-P/2 is the same as the bubble rise model in Reference 5 except that the Wilson correlation (Reference 6) is used to calculate the bubble rise velocity. In this representation, the mass of the steam entrapped in the mixture, m b, is calculated from the following expression: gb'ntegrating dm dm b = ~+w dt st (2sa) t ARESG vBUB b FBUB ZMIX where W is the total out flow from the steam dome, tot m is the total steam mass, and FBUB is a factor calculated during the initialization. m gbb is limited between 0.0 and m . 2-32 NAI 76-67 Revision 0 July 19, 1976 The bubble p gb (z) density is =y 'x ZMIX assumed to be distributed as (28b) where m b y = 2C (28c) m 0< a (1-C)+ x = 2c,(~g - +)m g < 1 (28d) (1+C) ~-Cp mb o V o g where a m is the average mixture void fraction, and C is the user specified bubble rise gradient parameter. The Wilson correlation expresses the-void fraction as a function of the bubble rise velocity as P 3.32. a=C 1 -P (28e) Pf C2 BUB 0.5 ~Pg Pg where BUB C1 = 0.75, C2 = 0.78; 0 5 > 5 5 (28f) f g BUB C] 0 136 C2 1 78 Lg J~l 0 5 < 5 5 (28g) 2-33 NAI 76-67 Revision 0 July 19, 1976 Eq (28e) is inverted to express VBUB as a function of a. The mixture level is obtained from ZMIX = V /ARESG (29a) where = + (29b) V m bv mfvf and the water level is HTRLVL = mfvf/ARESG (29c) where mf is the total liquid mass. 2.4.2 Once-Throu h Steam Generator 2.4.2.1 ~Geometr Figure ll is a schematic of the geometry of a typical OTSG as modeled in DYNODE-P/2. 2.4.2.2 Heat Transfer The total heat transfer from tube to shell side is the sum of the heat transfer to the subcooled, saturated, and superheat regions on the shell side. The heat transfer coefficient from the RCS coolant to the tube inside surface is calculated from the Dittus-8oelter forced convection correlation. Heat transfer through the tube walls is based on slab heat conduction. The shell side heat transfer correlations which are used are: 2-34 Py iXAI 76-67 Revision 0 July 19, 1976 WSGS 1 t Safety Inlet Plenum Relief Valves Valves WS ~ hg ~sup ~sup VOLSG ARESG hg DSGS ~sat TUBEH SGA DSG SGFA hf sub Auxiliary Feedwater 3,b ~sub (WAXFM + WAXFS) Iiain Feedwater WF,HFD utlet Plenum FIGURE ll SCHEMATIC OF ONCE-THROUGH STEAN GENERATOR 2-35 NAI 76-67 Revision 0 July 19, 1976 o Subcooled - Forced convection (Dittus-Boelter with minimum of 5.0 Btu/hr ft F) o Saturated - Nucleate Boiling (Thorn) o Superheated - Forced convection (Dittus-Boelter) A single fouling factor is applied to each region. All heat transfer coefficients are evaluated from the local temperatures and properties. The heat transfer to the subcooled region is given by sub. ~sub Usub x SGA x x ARsub x aTsub (30a) ~B~H where aT sub ub is the difference between the tube=side outlet and shell'ide subcooled, temperatures. The constant factor AR ub is calculated during initialization so that the steam generator heat load matches the core power at that time (see Section 2.8.3). The heat transfer to the saturated and superheat regions are combined to yield - (30b) ~SS q t+~ USS x SGA - sub x ARss x aTss x Ll ><> < ] where aT>> is the difference in the average tube. side and the saturated shell side temperatures. The constant factor ARSS is calculated in the same manner as AR b. sub'-36 NAI 76-67 Revision 0 July 19, 1976 For reverse heat transfer, the user supplied reverse heat transfer factor multiplies Eqs (30). 2.4.2.3 ~i 3 1 The conservation of mass, energy, and volume equations are solved for the shell side for the subcooled, saturated, and superheat regions. In this model, the saturated and superheat regions are treated as being saturated and in equilibrium; i.e., the superheat effect on the thermal dynamic model is neglected. The boundary between the subcooled and saturated regions is taken as the location where the fluid enthalpy reaches hf., and the boundary between the saturated and superheat regions, where it reaches h . For the subcooled region; h =P[hf +hfj (31a) so that dh sc 1 dhfw+ >hf (31b) 2 dt Sp dt .dm = t-(hf - hf )"f - sub +m ( " - "~)] sc dt J dt /(hf - h ) (31c) 2-37 0 NAI 76-67 Revision 0 July 19, 1976 and .dV .dm sc dt sc dt (31d) W and h are total feedwater (main plus auxiliary) flow and corresponding average enthalpy. For the combined saturated and superheat region, the equations for the steam and water phases are dm =W-W (32a) dmf dt =W fw dm dt -W ev (32b) dv "dv (32c) >v Svf W ev = W s o g -W fw v f - m ~+m g ap f ap d dt + dm (~f - ~sc)3/(~ - ~f) (32d) dUf dill Q +h~Wf -Wh -~h ht,. dv p ss (32e) J dt In these expressions, W represents the rate at which saturated liquid is evaporated, W is the total steam flow o'ut of the generator, and Uf is the total internal energy of the saturated liquid and steam. 2-38 NAI 76-67 Revision 0 July 19, 1976 The above set of equations is solved for dp/dt which is integrated to yield the transient shell side pressure. In addition, the mass and volume equations are integrated. The subcooled length is given by b m ~sc/ARESG (33) The transient saturated length is computed from the total saturated liquid volume assuming that the enthalpy varies linearly from hf to h over this region (uniform heat flux assumption). The water level is computed as the total liquid (sub-cooled plus saturated) volume divided by ARESG. The water property curve-fits of Reference 2 are used on the secondary side of the OTSG model. 2.4.3 Main Feedwater S stem The main feedwater system is treated identically for both the UTSG and OTSG. The initial feedwater inlet enthalpy is specified by the user, and the program com-putes the initial feedwater flow (and steam flow) based on the initial steam generator heat load. For the transient conditions, changes in the feedwater flow and enthalpy can be specified individually for each steam generator by the user through input table sets of a(WfJWf ) and ahf versus time. 2-39 NAI 76-67 Revision 0 July 19, 1976 Alternately, changes in the feedwater flow which re-flect the feedwater controller action to match the water level and the power dependent level demand signal can be considered (see Section 2.7.4.1). In this case, the feedwater flow to each generator is controlled independently. The feedwater enthalpy is assumed constant. The main feedwater to both SG's is isolated during a transient if a safety injection actuation signal is generated (see Section 2.6.1.2) or one of the following signals is actuated for either generator: o Low steam generator pressure High steam generator water level < Low core average temperature coincident with a reactor scram actuation signal Following the isolation signal, the feedwater flow is ramped down to a minimum value WFOMIN over the time in-terval FWRMPT and feedwater controller action is not permitted. These quantities are user specified. Feed-water isolation is not considered, if the transient feedwater flow and enthalpy are specified for either steam generator. The auxiliary feedwater systems are described in Section 2.7.1. 2.4.4 Main Steam S stem Relief and Safet Valves Each SG has an identical set of relief and safety valves located before the steam line isolation valve (see Figures 10 and 11). The steam flow through each valve is based on the same model. For the relief valves in steam generator i, 2-40 NAI 76-67 Revision 0 July 19, 1976 pSG1 1/2 WSGRi FSGRV g- SGRV x NSG (34a) 1 where .. (PSG....PSGRV ) (34b) ~O,y - ,y SGRV. 2 1 0 < FSGRV < 100 (34c) 1 and NSG is the total number of steam generators re-1 presented by loop i. Similar expressions apply to the safety valves. 2.5 Main Steam S stem This section describes the models provided in DYNODE-P/2 for representing the main steam system. The geometric represen-tations, the main steam line isolation and check valves, the steam dump and bypass valves., and the turbine valves are dis-cussed. In addition, the dynamic pressure model, transient covered;- =-- " power demand simulation, and main steam system break model are An option has been provided, (ISTFLW), which allows the user to neglect the main steam system representation. When this option is exercised, the flow through'he main steam line isolation valves is set equal to the total feedwater flow (main plus auxiliary). Also, if this option is used, the input temperatures for the steam generator shell sides are used to set the initial shell side pressures for U-tube steam generators (IFLGT = I). 2-41 NAI 76-67 Revision 0 July 19, 1976 P thr Turbine WSTB Stop Valves Control Valves Dump Valve ~ WSD Main Steam Line WSB VSL Bypass Valve WSH VS eader Pipe Main Steam Line Check Valve Main Steam Line Isolation Valve SH WS1 WS2 Safety Valves Safety Valves Relief Valves Relief Valves SG SG SG LOOP 1 LOOP 2 FIGURE 12 SCHEMATIC OF MAIN STEAM SYSTEM WITH ONE MAIN STEAM LINE TO TURBINE 2-42 NAI 76-67 Revision 0 July 19, 1976 p thr Turbine WSTB1 WSTB2 Stop Valves Control Valves Dump Valves WS01 WSD2~ ~WSB1 WSB2~ VSL2 VSL1 Bypass Valves PSL2 PSL1 lain Steam Lines WSH1 WSH2 VSH2 VSH1'SHl Header Pipes PSH2 WS1 WS2 S Li Check Valves Main Steam Line Isolation Valves Safety Valves Safety Val ves Relief Valves Relief Valves SG SG LOOP 1 LOOP 2 FIGURE 13 SCHEMATIC OF MAIN STEAM SYSTEM WITH TWO MAIN STEAM LINES TO TURBINE 2-43 NAI 76-67 Revision 0 July 19, 1976
- 2. 5.1 ~Geometr Two types of ma1n steam system piping can be represented in DYNODE-P/2 as shown in Figures 12 and 13. The geometry selection is made by the user through the input parameter Lss.
2.5.2 'Main 'Steam'Line 'Isolation 'and Check Valves The initial main steam line isolation valve positions are arbitrary (between full open and full closed) and specified k by the user. The actuation signal for main steam line isolation-valve closure is optional based on user specification. The signal can be ignored or can be generated by one of the following two sets of conditions occurring generation: in'ither 0 Either Hi-.Hi. steam line flow. or. Hi steam line flow and low core average temperature in coincidence:with a. safety injection actuation. o Low steam generator pressure. Closure of the isolation valves begins following the user specified delay time after the 'actuation signal and is linear with time. The time delays and closure rates can be different for the two valves. The check valves are simulated by prohibiting back flow from the header pipes into. the steam generator. The flow through these valves is goyet'ned by the momentum equation dWS K wsfwst~ V SL gSG (35a) SL Gt SG SH 2-44 NAI 76-67 Revision 1 January 18, 1977 The area in the inertia factor ESL = (L/A)SL and the area ASL are varied in direct proportion to the main steam line isolation valve area. The integration of Eq (35a),is carried out over a time step evaluating the flows on the right hand side at the end of the step. The flow from the header pipe into the main steam line is obtained from a similar solution to WSHfWSH(v - (35b) ISH ~t (PSH PSL) (~A )SH 2 gSH Eqs (35a) and (35b) are not used, if either a turbine runback or a turbine power demand transient (see Section 2.5.5) are simulated. In these cases, WS and WSH are obtained from the product of the initial flows and the fractional turbine demand. 2.5.3 'team Oum 'and'B ass Valves QC The steam dump and bypass valves are represented in-dividually for each steam line. These valves may be initially open. The user specifies these valve positions for each line. Each valve in each line .is treated separately. 2-45 NAI 76-67 Revision 1 January 18, 1977 The dump and bypass valves are modeled in an identical manner, so that the following discussion which relates to the dump valves also applies to the bypass valves. A dump valve area is automatically controlled in one of the following modes based on user specifications: o Maximum of high steam line pressure and high core average temperature. . o High steam line pressure before scram actuation and maximum of high steam pressure and high core average temperature T after scram. When controlling on core average temperature, the highest auctioneered temperature is used. The options for selecting the temperature sensor locations in the RCS are described in Section 2.6.2. Alternately, dump valve opening can be initiated follow-ing the user specified actuation signal and is linear . with time 2-45a NAI 76-67 Revision 1 January 18, 1977 The valve opening rates. can be diferent for the valves in. each line. In addition, the f'r.action of valve opening can be limited through user specifications. The dump flow rates are given by MSD = MSH x x FD AD (36) where MSH is the initial steam lfee flow rate, FD is the total valve capacity, and AD fs the fractional open area of the valve. 2.5.4 'Turbine '.Control 'and 'Sto 'Valves The turbine control and stop valves; are represented individually for each steam line aed can all be treated separately. The initial turbine centrol valve positions for each line are specified by the .user. The initial stop valve'ositions are assumed fai11 open. The control valve position during tahe transient can be adjusted to match the turbine pow~ demand (see Section 2.5.5) or to simulate a turbine neiback. In this latter case, the user specifies the time at which runback is initiated and runback level.'or either case, the flow through the turbine valves is set equal to the product of the ~ initial flow and the fractional turbine demand. Stop valve closure (turbine trip) can be actuated by one of the following signals: o Overspeed - Turbine power demand ~exceeds the specified setpoint. Note: This signal aEso generates a reactor scram actuation signal if the setpoint for Trip 7 > 0.0 (see Section 2.6.2.1). 4 < A reactor scram actuation. 2-46 NAI 76-67 Revision 1 January 18, 1977 The stop valves begin to close linearTy witli time follow-ing the specified time delay after the actuation signal. The time delay, closure rate, and fraction of valve closure are specified independently for each steam line. The steam flow to the turbine for each line is given by the solution to the momentum equation. WSTB[WSTB(v dWSTB L~h~ZT ~ This equation is solved in the same manner as Eq. (33a). ATB is the fraction turbine flow area relative to the initial area (minimum of control and stop areas), and pthr is the constant turbine throttle pressure (calcu-lated from the initial flow conditions and valve posi-tions). The inertia factor varies inversely with A B. No back flow from the turbine into the steam line is permitted,, 2.5.5 Power Demand A turbine power demand transient can be simulated in DYNODE-P/2 through a user specified table of demand versus time. This table is input in the same manner as the core power forced table (see Section 2.2.3.1). If the table set is not entered, the power demand is held constant at the initial value. This turbine power demand is used to control the main steam system flows, to set the core average temperature demand for the control rod controller (see Section 2.7.4), and to determine the actuation signal for turbine stop valve closure (overspeed trip). 2-47 NAI 76-67 Revision 0 July 19, 1976 2.5.6 Main Steam S stem Break DYNODE-P/2 provides simulation of a break in the main steam, system;.'he break'an:be placed..in one of the fol Towing' oca doris".'." I < In the steam line between the steam generator outlet and the steam line isolation valve. < In the steam header pipe. < In the main steam line. o In the main feedwater pipe between the isolation valve and the steam generator inlet. In any case, the break is on the Loop 2 side of the main steam system. The user specifies the time the break is assumed to occur, the duration of the break. opening, and the e'ffective break area. The break flow is given by WBREAK = A (t) x G(h,p) (38) where AB Breakk(t) is assumed to vary linearly with time, and G(h;p) is the mass flow rate per unit area. G is evaluated from an interpolation/extrapolation in the Moody leak flow tables as programmed in RELAP4 (Ref-erence 5) based on the enthalpy and pressure at the break location. For a break in the steam pipe, perfect moisture separation in the steam generator is assumed. The break flow is added to the other flows out of the region in which the break is located i n considering the mass and energy balances. 2-48 D t NAI 76-67 Revision 0 July 19, 1976 2.5.7 D namic Pressure Model The initial pressures in the main steam system are cal-culated by DYNODf-P/2 during the initialization segment (see Section 2.8.5) based on the initial flow conditions and valve positions by setting the time derivative to zero in the momentum equations. The transient pressure responsesio'f;.,the-steam.i>no=pipe. regions are calculated from the'.conservation'of mass, energy, and volume. The steam flow rates into and out of each region are calculated from the previous equa-tions. For a typical region i, dms dt J zeal ij.. (39a) dUi z(hW).. dt . ij (39b) and the volume is constant. The sums are taken over all the flows entering (positive) and leaving (negative) the region. The specific volume and internal energy are used to eval-uate the region pressure based on the water properties of Reference 2. The pressures in the main steam line regions are not allowed to drop below atmospheric pressure during de-pressurization accidents. 26 ~f This section describes the simulation of the high pressure safety injection system (HPSIS) and the reactor protective system (RPS) as simulated in DYNODf-P/2. For each, the components and the actuation systems are described. The remaining systems simulated are described in Section 2.7. 2-49 ~ ~
- f
NAI 76-67 Revision 5 April 19, 1978 2.6.1 Hi h Pressure Safet In'ection S stem The HPSIS. delivers water to the. RCS during accidents in which the RCS coolant volume is reduced. 2.6.1.1 The HPSIS consists of a high head pump which delivers water to the cold legs of the RCS (see Figure 1) follow-ing an actuation signal. The delivery characteristics of the pump (head-capacity) are specified by a table. set of flow: rate versus RCS pressure.. Interpolation/extrapolation in the table set is performed based on the pressurizer pressure. Negative flows are not permitted. If the delivery of more than one pump is desired, the head-capacity curve must include the total flow rate which is desired. The enthalpy and boron concentration of the safety injection water is specified by the user. Provisions have been made in the model to allow the boron concentration in the safety injection line (between the concentrated borated water storage tank (BWST) and the RCS injection point) to initially have a different boron concentration relative to the BWST water. In this case, the user specifies the water mass and concentration in the line and this concentration is used unti 1 the water mass is swept out. This effect simulates transport delay be-tween the BWST and the RCS. 2.6.1.2 A~i Ai The HPSIS actuation signal is generated automatically when the pressurizer pressure and water level exceed their set-2-50 e I NAI 76-67 Revision 5 April 19, 1978 points. The actuation logic is optionally either an or or an and, i.e. one of the following two conditions: Low pressurizer pressure. or low pr essurizer water level Low pressurizer pr essure coincident with low pressurizer water level... The actuation signal can ~iso..be i,nitiatedDy=usee. speci.fi.cation..-=- The water delivery to the RCS begins after the specified delay time following the- actuation signal,. 2,5.2 Reactor Protective System The RPS is designed to scram the reactor during tran-sients and accidents to prevent or mitigate fuel damage. The use of the RPS is optional in DYNODE-P/2. The set of trip functions which are simulated in DYNODE-P/2 are listed in Table 1. In addition, if the turbine trips on cverspeed (see Section 2.5.4), a reactor trip is also actuated if it has not yet been generated bv some other actuation signal and the setpo nt for trip 7 > 0.0. Alternately, the user may specify the time at which scram actuation occurs. Trips relating to the steam generator secondary side are actuated if th. set-point is reached in either generator. The control rod react'ivity insertion begins after 'ihe appropriate time delay fol!owing the actuation s.gna:. For a turbin overspeed trip, the trip delay time specified for Trip 7 in Table 1 is used. The trip setpoints for the first ten trips. in Table 1 are constants as specified. by the user. The overpower and overtemperature trip setpoints are variables which depend on the core average tempera;ure and pressure as described below. 2-51 NAI 76-67 Revision 1 January 18, 1977 Two options are available for simulating the overpower and overtemperature yT trips. The first option consists of using the steady-state lines as shown in Figures 14 and 15. In this case, the core average temperature, aT , is used with 14 to generate the Overpower aT trip setpoint for hT core'igure core. When the sensed aT core exceeds the setpoint, a trip actuation occurs. Simi lari ly, T and the RCS pressure are used with Figure 15 to generate the Overtemperature aT trip setpoint for Tcore'his calculation is performed in the following manner. The user specifies the setpoint lines at various constant pressures. The setpoint. on LT for a given T core is calcu-lated as a function of pressure. An interpolation/extrapolation is performed to determine the trip setpoint corresponding to the current pressurizer pressure. When the sensed LlTco core exceeds the setpoint, a trip signal is generated. The second option consists of dynamic simulations of the setpoint generators. In-this case, the time - dependent setpoints are calculated from the following expressions: T Setpoint Overpower ( ) Top 4 "5 i S. (f t3s) ave core (4oa) and overtemperature( ' 1 2 - - 1 ( coe ( )- (1 + <2s) +K3 (p (s) -po ) (4ob) 2 -51a NAI 76-67 Revision 5 April 19, 1978 These equations express the setpoints as a function of the frequency domain variable s. The corresponding equations in the time domain are obtained by Laplace transform inversions which are the expressions programmed in DYNODE-P/2. The gains Kl through K6 and time constants v>, and v3 are input parameters. The overpower aT setpoint is calculated assuming K 6 = 0.0 when T core < T o and the rate/lag term is not allowed to increase the setpoint. In addition, options are available for selecting the temperature sensor locations and the trip logic as described below. T core and aT core are given by Tave core 'ot (T cold) /2 (40c) and d T = Th - T (40d) old where Th t hot and Tcold ld are the sensed temperatures which are based on either the reactor vessel upper and lower plenum temperatures, the hot and cold leg temperatures, or the steam generator inlet and out-let plenum temperatures, respectively. llhen the latter two sets of sensor locations are selected, two sets of temperatures and corre-sponding trip set points are calculated, one for each of the two loops. For these cases, the user may opt'for a trip signal generation either when either loop aT core exceeds the corresponding setpoint or only when the Loop 1 LTcore exceeds the setpoints. This latter option is provided to simulate multi-trip logic circuits for plants with three or more loops. The calculated fluid temperatures corresponding to the sensor locations are delayed and then lagged to simulate 5 transport delay and sensor response times in computing the sensed hot and cold temperatures for use in Eqs (40). It should be noted that the T core described above is also used as input to the steam dump and bypass valve controllers, the control rod controller, and the main feedwater and steam line isolation activation systems. In cases where the sensors are placed in the 2-5lb NAI 76-67 Revision 5 April 19, 1978 ave core is used as input to these loops, the highest auctioneered T control systems. 2-51bb NAI 76-67 Revision 1 January 18, 1977 In addition, auctioneering is used to select the highest sensed lowest aT p to test for the actuation of the core and the control rod controller prohibit signal. 2-51 c NAI 76-67 Revision 0 July 19, 1976 TABLE 1 RPS TRIP FUNCTIONS TRIP'NUMBER TRIP "FUNCTION High neutron power. High pressurizer pressure Low pressurizer pressure High pressurizer level Low pressurizer pressure Low-Low steam generator water level Turbine Trip - High steam generator level 8 Low reactor coolant flow 9 High power to flow ratio 10 High core outlet temperature 11 Overpower aT 12 Overtemperature aT 2-52 NAI 76-67 Revision 0 July 19, 1976 OPDTTN Slope = OPOTSL OPDTDT core OP DTTA Tave core FIGURE 14 OVERPOWER aT TRIP 2-53 NAI 76-67 Revision 5 April 19, 1978 It should be noted that when the RPS is simulated, DYNQOE-P/2 utilizes all the trips in Table l. If the user desires to ignore any of these trips, the trip setpoints, must be set at a level which is outside the range over which the corresponding parameter varies during the transient. The program logic is structured so that the earliest scram time (time at which setpoint is reached plus delay time) is used to begin the scram reactivity insertion. 2.7 Additional S stens This section describes the remaining systems which are simulated in'YHODE-P/2. For each system, the component actuation, and controls are discussed. 2.7.1 Auxi 1 i ar Feedwater 'I The auxiliary feedwater system consists of a motor and a steam-turbine driven feedwater pump. Each type of pump is represented and treated separately. 2-54 NAI 76-67 Revision 0 July 19, 1976 lope = OTDTSL(I) OTDTDT(I)- core OTDTTA( I ) OTDTP R( I ) OTDTPR( I+1) OTDTP R( I+2) Tave core FIGURE 15 OVERTEMPERATURE aT TRIP 2-55 0 NAI 76-67 Revision 0 July 19, 1976 Each pump has its own head-capacity curve consisting of a user specified data set of flow versus steam generator pressure. These head-capacity curves are given in terms: of the flow per steam generator. and the flow is obtained by interpolation/extrapolation in these table sets. The enthalpy of the water from each pump is specified separately. Automatic actuation of each auxiliary feedwater pump occurs under the following conditions: o At the time of HPSIS actuation. o At the time main feedwater is totally isolated in either steam generator (zero main feedwater flow). < Low-Low steam generator water level (RPS Trip 6 setpoint) in either steam generator. When this latter actuation signal is generated, auxiliary feedwater to the steam generator in which the actuation signal was generated is not permitted. Alternately, each auxiliary feedwater pump can be actuated at a pre-specified time which is input by the user. Auxiliary feedwater delivery begins after the specified time delay following the actuation signal. 2.7.2 Pressurizer Heaters and S ra s The pressurizer heater system contains a propor ional and a back-up bank of heaters. The heater output is controlled by the pressurizer pressure and water level. The pressure control is shown in Figure 16. The level control takes precedence over the pressure con-trol when either the high or the low water level setpoint is reached. If the water level exceeds the high level 2-56 NAI 76-67 Revision 0 July 19,. 1976 QPHM Back-up Bank Slope = QPHR Proporti onal Bank PPHL PPHH Pressure FIGURE 16 PRESSURIZER HEATER PRESSURE CONTROL 2-57 NAI 76-67 Revision 0 July 19, 1976 setpoint, all the heaters are turned on and the heat out-put is gPHM. If the water level drops below the low level setpoint, the heaters are turned off. The pressurizer spray system allows water from the cold leg to flow into the pressurizer steam region (see Figure 1). The spray system is controlled by the pressurizer pressure as shown in Figure 17. 2.7.3 Char in and L'etdown The charging and letdown systems are connected to the cold leg as shown in Figure 1. These systems are controlled by the pressurizer water level. The charging system is turned on when the level falls be-low the setpoint, and water is pumped at constant rate. The enthalpy and boron concentration of this water is specified by the user. The letdown flow control is shown in Figure 18. 2.1.4 ~1S This section describes the main feedwater and control rod control systems. 2.7.4.1 Main Feedwater Controller The main feedwater controller adjusts the feedwater flow to match the steam generator water level to the water level demand. The water level demand is based on the core power and is obtained from an interpolation/extra-polation the user specified table of water level demand versus power. Feedwater control for each steam generator is separate. This controller is bypassed if the feedwater flows and enthalpies are specified by the user for either steam generator. 2-58 NAI 76-67 Revision 0 July 19, 1976 PSRN PPSPON PPSP/1R Pressure FIGURE 17 PRESSURIZER SPRAY PRESSURE CONTROL 2-59 NAI 76-67 Revision 0 July 19, 1976 PLDMRg PWLLON PWLLMR Pressurizer Water Level FIGURE 18 LETDOWN FLOW CONTROL 2-60 NAI 76-67 Revision 0 July 19, 1976 The difference between the water level and the demand is the error signal e. The feedwater water flow is given by t WF(t) = WF +. t [WF(t )]dt (4Ia) where a St WF = -WF 0 x C fw fwl vfw <(t) (4Ib) fwl fw2 ) fw2 where Cf fw is the controller constant, and ~fwl and T f 2 are the lead and 1 ag time constants, respecti vely. fw2 No controller action is permitted if the error signal is within the controller deadband. The magnitude of the feedwater flow is limited to be less than the user specified maximum value. Feedwater control is not permitted following a feed-water i sol ati on actuati on si gnal . 2.7.4.2 Control Rod Controller In Eq (14a), hk C is the change in reactivity produced by the control rod controller. This controller adjusts the rod position to correct the input error signal to the controller. Control on either the core average tem-perature or the power level is permitted. In either case, (42a) CRC t ~ CRC 0 where 2-61 0 NAI 76-67 Revision 1 ~ N1 0'42b) January 18, 1977 3 St [ak CRC j = -C CRC
- c. (t) CRCl CRC2
"'CRC1 CRC2 ~ (1 ) CRC2 t/vCRC2 eye(y) dy where c is the error signal, TCRC1 and vCRC2 are the lead and lag time constants, and CCRC is the controller constant. halo contro'er action is taken if the error signal is within the deadband spec.'fied by the user. Controller action is also prohibi ted under any of the following conditions: 0 After a scram actuation signal. 0 Low power level setpoint. Highest'auctioneered sensed LT core within a specified 0 margin of the lowest auctioneered overpower trip setpoint. 0 core within a specified Highest auctioneered sensed dT margin of the lowest auctioneered overtemperature trip setpoint. The last two prohibits are inoperative, if the RPS is not used. Also, a control rod withdrawal prohibit following a turbine runback can be optionally specified by the user.
- 2. 8 Ini ti al i zati on This section describes the initialization which is performed by and systems based o.i DYilODE-P/2 for each of the model components tne speci fi e" i ni ti al conditions .
Tho initial conditions relat',ng to plant operation which are level and dis-specified for each case cons'.st of: core pow r tribution; pressurizer pressure and water level; core inlet steam enthalpy; RCS loop flow rates; boron concentration; th l p.'-, ies and, wa er levels; e generator temperatures, ice iwa er entha ~ ~ an d main steam system valve positions. 2-Ci 9 NAI 76-67 Revision 0 July 19, 1976 2.8. 1 Core The initialization consists of solving the set of differ-ential equations with all time derivatives set equal to zero. The variables which are initialized are the fuel rod temperatures, the axial coolant enthalpy and mass distribution, and the delay neutron and decay heat precursor concentrations. In the case of the fuel rod temperatures, an iteration procedure is required, since the oxide conductivity and heat capacity are temperature dependent. Convergence of this process is to a built-in criterion of 0.1 C for all oxide and cladding nodes. k ff is set to unity. 2-8.2 Reactor'Coolant S stem The enthalpy distribution for all regions of the RC system (excluding the core and pressurizer) is calculated from the initial core inlet and outlet enthalpies, and the initial loop flow rates and steam generator heat loads. The initial SG heat load split for the two loops is assumed to be proportional to the absolute value of the loop flow rates. The initial flow in Loop l.must be greater than zero, while the Loop 2 flows can be either positive or negative. However, Wl + W2 = WT > 0. The mass and temperature distributions are calculated from the enthalpy distribution and the initial pressur-izer pressure. The initial pressurizer water and steam are assumed to be saturated at the initial pressurizer pressure. 2-63 NAI 76-67 Revision 4 September 26, 1977 The initial boron concentration of the water in all regions of the RC system (including the core and pressurizer) is assumed to be uniform at the value specified by the user. The pressurizer steam is assumed to be boron free. If the dynamic pump option is selected, the program will initialize the pump speeds and rated pump head, HR, for the given initial flow and pump status conditions. This initialization consists of solving the loop momentum and pump speed equations given in Section 2.3.4 with all time derivative set to zero. In performing this initialization, the input values for the loop flow rates are used for those loops in which the pumps are specified to be initially running. The flows in idle loops are calculated from the conservation of momentum equations. It should be noted that at least one pump must be running initially. The rated pump head is determined from the condition that the pump pressure rise must balance the loop pressure losses. Similarly, the initial pump speeds are calculated by balancing the motor torque against the net losses (hydraulic, friction, and windage). Pumps which are initially idle have zero initial speeds. 283 ~i3" The initializations of the shell side of the steam. generators and the main steam system are performed simul-taneously. This is necessary, since these regions are thermal-hydraulically coupled. The initialization for both types of steam generators is similar'. Thus, this procedure is described only for the UTSG design. The procedure begins with the SG shell side. The heat load for each generator is set".on the basis of the RCS loop flows as described in the previous section. The heat transfer coefficients are computed as described in 2-64 0 4 NAI 76~67 Revision 4 Septem5er 26, 1977 Section 2.4. 1.2. aT is calculated from Eq (27a) with AR = 1.0. Since the tube side temperature is known from the RC system initialization, this sets the shell side temperature and hence pressure along with the saturation properties. From the heat load, feedwater enthalpy, and h , the initial steam flow is computed for each generator, The initial feedwater flow is set equal to the steam flow. The steam flow sets the pressure drop between each steam generator outlet and the corresponding steam line header pipe and hence the header pipe pressure. If there is only one main steam line to the turbine (see Figure 12), the header pipe is a common pressure region as seen by both generators. Hence, the header pressures as'computed for both generators must be equal. If these 2-64a NAI 76-67 Revision 2 March 15, 1977 pressures differ by more than 0.15, the steam generator shell side; pressures are adjusted to force the- header pressures to be equal and the saturation properties are evaluated at the new pressures. With the new saturation temperatures, the effective UA of each generator is com-puted. The AR factors are then calculated from the ratio of the effective to the actual UA. The above procedure is repeated until the two header pressures agree to within 0.15. If there are two main steam lines to the turbine (Figure 13), the common pressure region is the turbine throttle. Thus, for this case, the procedure is as described above except that the additional pressure drop from the header pipe to the turbine is also included in these considerations. Once the region pressures have-been co'mputed, 'the masses and enthalpies are set based on the saturated properties and the initial water levels in the steam generators are obtained from the mixture heights and void fractions. The bubble rise factor, F>UB, is calculated so that the time derivative of the bubble mass is zero. It should be noted that the initial flow distribution within the main steam system takes into account the specified initial valve positions. DYNODE-P/2 solves the core differential equations for the fuel rod temperatures, coolant channel enthalpies, and point kinetics simul-taneously utilizing the Runge-Kutta-Merson method (References 7 and 8) with variable time steps. The time steps are selected automatically within the program based on the estimated truncation error. If the maximum relative truncation error exceeds the user supplied accuracy limit ACCURC, the time step is halved and the integration is repeated; if the ) 2-65 (t NAI 76-67 Revision 4 September 26, 1977 maximum error is less than ACCURC/32, the time step is doubled for the next integration. The user specifies the minimum and maximum time step sizes allowed. for each case as described below as well as the print interval size. If the dynamic pump option is selected, the loop momentum and pump speed equations are integrated simultaneously using the Runge-Kutta - Merson integration method. These integrations are performed simultaneously with the RCS equations which describe the entha'lpy distribution. In this manner, the loop flows are updated continuousl for use in the RCS enthalpy transport equations. 1 This same integration method is employed to solve the set of simul-taneous differential equations which describe the enthalpy and boron concentration distribution in the remainder of the RCS, excluding the pressurizer. All other differential equations are sol ved by expl i ci t integrati on. The core and the RCS differential equations are integrated over separate time step sizes ~ The program automatically selects the 'ptimal time step for each set of equations. Figure 19 demonstrates the manner in which the variable minimum time step (DELIN) and the print interval (OELLP) are specified by the user. The set OELMX(I) specify the maximum RCS time step during the transient and are input in the same manner. The minimum time step for the core integration is obtained by dividing the minimum RCS value by the user specified 2 integer NOKIN. The time step size for the main steam system equations is obtained by dividing the current RCS time step size by the user specified integer NOSTM( I). The time step for the RCS integration is also utilized to solve all the remaining differential equations for the RCS. 2-66 NAI 76-67 Revision 4 September 26, 1977 For stability reasons, it is recommended that for transient calcula-tions the maximum specified time step should satisfy the following relationship: m~ OELMX < min (> } (e3) 1 where the set i includes all the RCS regions. 2-66a 0 NAI 76-67 Revision 0 July 19, 1976 oELrN(3) OELIN 2 oELrN(NO IM-1 ) DELIN(l ) DEL'IN NOTIM aQJ A dJ N Vl S gp CL a Cl C '~ I ~ r 'I O ~ Pn OELLP 2 OELLP NOT IM-1) ELLP 3) OELLP 1) OELLP NOTIM t,sec t=o ENDTIM(1) ENOTIM(2) ENDTIM(NOTIM-1) ENoTrM(NOTrM) FIGURE 19 TIME STEP AND PRINT INTERYAL INPUT 2-67 0 NAI 76-67 Revision 2 Harch 15, 1977 3.0 INPUT DESCRIPTION This section describes the input to DYNODE-P/2. All input formats are . fixed and all integer data must be right adjusted. Columns 71-80 are available on all input cards for specification of arbitrary alphanumeric identification information. Program restrictions for integer variables are included. All cards must be input for each problem, except as noted below, even though the data may not be utilized in that problem. Problems may be batched simply by stacking data decks. The control cards and their use are described in Appendix B. Card 1 Title FIeId Format Variable Descri tion units 1-80 10A8 Problem Title Card 2 - Control Variables 1-5 I5 IK - Reactivity Insertion Type IK = 0 Step IK = I Ramp 6-10 I5 IT - Number of delayed neutr on groups IT< 6 11-15 r5 IDH'- Number of decay heat precursor groups 0< IDH< 12 16-20 I5 IPLT - Plot Option IPLT = 0 No Plots IPLT = I Plots 21-25 I5 NOTItt - Number of time step and print interval data sets 1 < NOTIN < 20 26-30 I5 NOKIN - Parameter used to set minimum core time step. If NOKIN < 0, NOKIN set = 10. 31-40 E;0.0 ACCURC - Accuracy limit for truncation error associated with Runqe-Kutta-Merson integration. If ACCURC <0.0, default value is 1.0E-6. 41-50 E10.0 TT - Problem end time (seconds) 3-1 NAI 76-67 Revision 2 March,,15, 1977 Card 3 - Plot Control Card Omit if IPLT j 1 on Card 2 Field Fomat Variable'-Data'nits 1-5 r5 IPTC (1) 6-10 I5 IPTC (2) 51-55 I5 IPTC (11) IPTC (I) =" ( Variable I is not plotted 1 Variabl.e I is plotted Variable Ueita 1 Relative Power 2 RCS Pressure psla 3 keff 4 Core Average Heat Flux Btu/hr-ft2 5 Average Fuel Temperature oF 6 Maximum Fuel Temperature oF 7 Total SG Heat Load (Btu/sec-pin) 8 Pressurizer Water Level ( feet ) 9 ~ Core Flow Rate (ibm/hr-pin) 10 Core Inlet Enthalpy (Btu/ibm) ll Pressurizer Safety and Relief Flow (ibm/sec-pin) Card 4 - Time Ste and Print Interval Sizes (see Figur e 19) 1-10 E10.0 ENDTIM(I) - End time for current time step and print interval sizes (seconds) 11-20 E10.0 DELIN(I) - Minimum RCS time. step size (seconds) 3-2 0 0 NAI 76-67 Revision 3 March 25, 1977 21-30 E10.0 DELLP(I) : Print interval size (seconds) 31-40 E10.0 DELMX(I) Maximum RCS time step size (seconds) (If DELMX(I) < 0.0, default to DELLP ( I )/2) 41-45 I5 N$ STM(I) Number of main steam system time steps per RCS time step (If NASTM(I) < 0, default to N)STM( I) =10) . NOTE: If ISTFLll)0(Card 20), NHPD/0 (Card 75), or TRBT>0.0(Card 51), NOSTM(I-) is defaulted to 1. NOTE: Card Type 4 must be repeated NOTIM times. 3-2a 0 P NAI 76-67 Revision 0 .July 19, 1976 Card 5 - Geometr Data Field Format Variable'-'Data units ' 1-5 I5 - Number of nodes in oxide region 3 <M<8 6-10 I5 NS - Number of axial nodes in coolant 3 <NS<12 11-20 E10. 0 SEGL - Axial coolant node length (feet) 21-30 E10.0 RIN - Inner cladding radius (cm) 31-40 E10. 0 ROUT - Outer cladding radius (cm) 41-50 E10. 0 AF - Coolant flow area per fuel rod (ft2) 51-60 E10. 0 HP - Height of fuel oxide per unit length (gm/cm) 61-70 E10. 0 RHC - Cladding density (gm/cc) Card 6 - Geometr Data Continued 1-10 E10. 0 DE - Channel equivalent diameter for ONB I calculations (feet) 11-20 E10.0 DEH - Channel heated equivalent diameter for DNB calculations (feet). Note: In Equations (lib) and (llc), 0e 12 x OEH DEH > 0.0 12x DE DEH < 0 0 and QDNB2 = 1. 0 OEH < 0.0 Card 7 - Heat Transfer Data 1-10 E10. 0 ACP - Oxide Heat Capacity constant in Eq. (3a) (joules/gm-'C) 11-20 E10.0 BCP - Oxide Heat Capacity constant in Eq. (3a) (joules/gm-'C ) 21-30 E10.0 A - Oxide Conductivity constant in Eq. (3b) (watts/cm) 3-3 NAI 76-67 Revision 0 July 19, 1976 Fie'I d Format Variable - Data units 31-40 E10.0 B - Oxide Conductivity constant in Eq. (3b) ('c) 41-50 E10. 0 C - Oxide Conductivity constant in Eq. (3b) (watts/cm-'C -'K ) 51-60 E10. 0 CPC - Cladding heat capacity (joules/gm -'C) 61-70 El 0. 0 KC - Cladding conductivity (watts/cm -'C) Card 8 - Heat Transfer Data - Continued 1-10 E10.0 HG - Initial Fuel-Cladding gap heat transfer 0 coefficient (watts/cm2 - 'C) 11-20 E10. 0 AHG - Linear Temperature Coefficient of HG'(watts/cm - C) 21-30 E10.0 BHG - Quadratic Temperature Coefficient of HG (watts/cm - C) 31-40 E10. 0 HF - Initial Cladding surface heat transfer coefficient (watts/cm2 - 'C) 41-50 E10.0 CHFFR - DNB heat flux margin factor. If CHFFR < 0.0, CHFFR set = 1.0 Card 9 - Void/ ualit Data 1-5 75 OPTSLP - Sl'ip correlation option (see Secti on 2.2. 2) OPTSLP = 0 Constant Slip Model OPTSLP = I Variable Slip Model 11-20 E10. 0 SLIP - Constant slip. 21-30 E10. CC1 - Void/quality coefficient. CC2 - Void/quality coefficient. 0'10. 31-40 0 41-50 E10.0 CC3 - Void/quality coefficient. 51-60 E10.0 CC4 - Void/quality coefficient. 3-4 0 NAI 76-67 Revision 5 April 19, 1978 Card 10 - Primar S stem Data I If ENI > 0.0, initial coolant enthalpy at core inlet (BTU/Lbm) If ENI ~ 0.0, core inlet temperature ('F). 11-20 E10. 0 PRO - Initial Pressurizer pressure (psia) 21-30 El o. 0 Ml - Initial Coolant flow in Loop 1 (units specified by LF on Card 57) 31-40 E10. 0 W2 - Initial Coolant flow in Loop 2 (units specified by LF) 41-50 E10.0 W2CB - Initial Coolant flow in Loop 28 (units specified by LF) (M2CB set to W2, if LCE = 0 on card 57) 51-60 E10. 0 BORCON - Initial Coolant Boron Concentration (ppv) Card ll - Power Level and Kinetics Parameters 1-10 E10. 0 PO Initial power level per unit volume of oxide (watts/cc) 11-20 E10.0 AA - Conversion factor in Eq (13a) (joules/ fission) 21-30 E10. 0 RL - Prompt neutron lifetime in Eq (13a) (seconds) 31-40 E10.0 BT - Effective total delay neutron fraction which equals 8 in Eq (13a) 41-50 E10.0 NU - Fast neutrons per fission which equals v in Eq (13b) 51-60 E10. 0 ALPHA - Equals a defined by Eq (13c) Card 12 - Reacti vi t Coef fici ents 1-10 E10. 0 AK - Enthalpy reactivity factor in Eq (14c) (1 bm/Btu) 11-20 E10. 0 BK - Enthalpy reactivity factor in Eq (14c) (ibm/Btu)2 21-30 E10. 0 CK - Enthalpy reactivity factor in Eq (14c) 3-5 I, D NAI 76-67 Revision 0 duly 19, 1976 Flel d 'Foraiao 'Var'iable'-Data'nits 31-40 E10.0 DK1 - Doppler reactivity factor in Eq (14b) 41-50 E10. 0 DK2 - Doppler reactivity factor in Eq (14b) (1/~K). 51-60 E10.0 DK3 - Doppler reactivity factor in Eq (14b) 61-70 E10. 0 DKBC - Boron reactivity Coefficient (1/PPM) Note: AK, BK and CK are not used if NORO P 0 DK1, DK2 and DK3 are not used if NOTF g 0 Card 13 - Reactivit versus: Coolant Densit 0 tion 1-5 I5 NORD - Number of points for the Neactivity vs coolant Density Table. Card 14 - Reactivit versus Coolant Densit Table 1-10 E10. 0 ROTB(I) - Coolant density (normalized) DKRO(I) - &eactivity 11-20 E10. 0 Note: Card Type 14 is repeated times and ROTB(I) '< ROTB(I + NORD 1) Card 15 - Reactivit versus Avera e Fuel Tem erature 0 tion 1-5 NOTF - Number of points for the LReactivity vs Fuel Temperature Table. Card 16 - Reactivit versus Avera e Fuel Tem erature Table . 1-10 E10.0 TFTB(I) - Fuel Temperature ('C) 11-20 El o. 0 OKTF(I) - LReactivity Note: Card Type 16 is repeated NOTF times and TFTB(I) < TFTB(I + 1) Card 17'-'Reactor'Coolant 'System'olume Data 1-10 E10.0 VL(l) - Upper Plenum (ft3 /pin) 11-20 E10.0 VL(2) - Loop 1 Hot Let (ft3/pin) 3-6 NAI 76-67 Revision 3 March 25, 1977 Fi el d Format Variable -'Data units 21-30 E10. 0 YL(3) - Steam Generator 1 Inlet Plenum (ft /pin) 31-40 E10. 0 VL(4) - Steam Generator 1 Tubes (ft /pin) 41-50 E10.0 VL(5) - Steam Generator 1 Outlet Plenum (ft3/pin) 51-60 E10. 0 YL(6) - Loop 1 Cold Leg (ft /pin) Card 18 - Reactor'Coolant'S'stem Volume Data 1-10 E10. 0 VL(7) - Loop 1 Downcomer (ft3 /pin) 11-20 E10.0 YL(8) - Loop 2 Hot Leg (ft /pin) 21-30 E10. 0 VL(9) - Steam Generator 2 Inlet Plenum (ft3/pin) 31-40 E10. 0 VL(10) - Steam Generator 2 Tubes (ft /pin) 41-50 E10. 0 YL(ll) - Steam Generator 2 Outlet Plenum (ft3/pin) 51-60 E10.0 VL (12) - Loop 2 Col d Leg A ( ft /pi n) I Note: Volume 12 neglected if LCE = 0 on Card 57. Card 19 - Reactor'Coolant S stem Volume Data 1-10 El o. 0 VL(13) - Loop 2 Cold Leg B (ft /pin) 11-20 E10.0 VL(14) - Loop 2 Downcomer (ft /pin) 21-30 E10.0 VL(15) - Lower Plenum (ft /pin) 31-40 E10.0 VPLC - Core Volume (ft3/pin) 41-50 E10.0 VUP Upper Plenum Inactive Region Yolume (ft /pin) NOTE: If YUP < 0.0, this region is ignored Card 19A - U er Plenum Inactive. Region Data (Omit if YUP < 0.0) E10.0 FFDCIY - Loop flow fraction which is circulated between downcomer and inactive region 11-20 E10.0 FFUPIV - RCS flow fraction which is circulated between upper plenum and inactive region 21-30 E10.0 HUP - Inactive region initial enthalpy (Btu/ibm) NOTE: If HUP = 0.0; HUP set equal to initial reactor, vessel outlet enthalpy. If HUP <0."; HUP set equal to initial reactor vessel inlet enthalpy 3-7 NAI 76-67 Revision 3 March 25, 1977 31-35 I5 ICIRCU - Inactive region circulation flow option ICIRCU = 0 or 2; circulation from downcomer to upper plenum ICIRCU = 1; circulation between downcomer and inactive region and between upper plenum and inactive region are independent NOTE.; lf ICIRCU=2, the RCS pressure i,s, based on the.'inactive region fluid properties. 20 - Steam Generator 0 tions 'ard 1-5 IS IFLGT(1) , Loop 1 Initialization Option for U-Tube Steam Generator Model 6-10 I5 IFLGT(2) - Loop 2 Initialization Option for U-Tube Steam Generator Model 0 Input Temperature TS(I) used for initial guess IFLGT(I) 1 Input Temperature TS(I) used to set initial secondary side side pressure. If ISTFLM P 0, IFLGT(I) is defaulted to l. 3-7a 0 NAI 76-67 Revision 0 July 19, 1976 Field Format Variable - Data units 11-15 I5 ISGOPT - U-Tube Steam Generator Model Option ISGOPT = 1 Temperature Integration ISGOPT = 2 Enthalpy Integration 16-20 ISGUOT - UTSG/OTSG option ISGUOT = 0 For UTSG ISGUOT = 1 For OTSG 21-25 I5 ISTFLW - Main steam system representatio*ri option. If ISTFLW = 0, Main steam system is represented. If ISTFLW g 0, Main steam system is not; repre-sented and the. main steam line flow equ'als the total feedwater flow. Card 21 - Steam Generator Data 1-10 E10. 0 SGNUM(l) - Number of S.G. in Loop 1 11-20 E10.0 SGNUM(2) - Number of S.G. in Loop 2 Card 22 - Steam Generator Data 1-10 E10.0, VOLSG(I) - S.G. shell side volume (FT3/pin) 11-20 E10.0 ARESG(I) - S.G. shell side flow area (FT2/pin) 21-30 E10.0 SGA(I) - S.G. Heat Tr'ansfer Area (FT2/PIN) 31-40 E10. 0 SGFA(I ) - S.G. tube side flow area (FT2/PIN) 41-50 E10.0 ZMIX(I) - S.G. Initial Mixture Level for U-Tube S.G. only (feet) 51-60 E10.0 TS(I) - Initial shell side Temperature ('F) E10. 0 HFD(I) - S.G. Initial Feedwater Enthalpy (Btu/ibm) Card 23 - Steam Generator Data 1-10 E10. 0 SLKA2(I) - Steam Line K/A2 with isolation valve. full open from steam dome to header [(PIN/FT2)]2 11-20 FIVO(I) - Initial Fraction Isolation Valve open 3-8 e ~ ' NAI 76-67 Revision 0 July 19, 1976 Field For m'at 'Variable'-Data'nits 21-30 E10. 0 SUBLEN(I) - Initial Subcooled Length for OTSG only (FT) 31-40 E10.0 SATLEN(I) - Initial Saturated Length for OTSG only (FT) 41-50 E10. 0 AVSG(I) - Initial average SG void fraction for UTSG only. Note: Cards 22 and 23 are repeated for each steam generator Card 24 - Steam Generator Data 1-10 E10. 0 DSG - Tube Side Hydraulic Diameter (FEET) 11-20 E10. 0 TUBEH - Tube Height (FEET) 21-30 E10. 0 TUBEDX - Tube Wall Thickness (FEET) 31-40 E10. 0 RFOUL - Heat Transfer Fouling Factor 41-50 E10. 0 REYERS - Reverse Heat Transfer Factor 51-60 El o. 0 DSGS - Shell Side Hydraulic Diameter (FEET) 61-70 E10. 0 CO - Bubble rise gradient parameter for UTSG only. Card 25 - Steam Generator Relief Valve Data 1-10 E10. 0 RKA2 - Relief valve K/Area2 (PIN - SG/FT ) 11-20 E10.0 PSGR1 - Shell side- pressure at which relief valves begin to open (PSIA) 21-30 E10. 0 PSGR2 - Shell side pressure at which relief valves are full open (PSIA) Card 26 - Steam Generator Safet Valve Data 1-10 El o. 0 SKA2 - Safety valve K/Area 2 (PIN 22 SG/FT ) 11-20 El o. 0 PSGSl - Shell side pressure at which safety valves begin to open (PSIA) 21-30 E10.0 PSGS2 - Shell side pressure at which safety valves are full open (PSIA) 3-9 NAI 76-67 Revision 0 July 19,,1976 Card 27 - Steam Line Geometr 0 tion and Inertia Factors Field For raat Variable - Data unitsr 1-5 I5 LSS - Number of Main Steam Lines to Turbine (LSS = 1 or 2) 11-20 E10. 0 XISL(1) - Inertia factor (L/A). from steam dome to header for steam generator 1 (PIN/FT) 21-30 E10. 0 XISH(1) - Inertia factor (L/A) from header to main steam line for steam generator 1 (PIN/FT) 31-40 E10. 0 XIST(l) - Inertia factor (L/A) from main steam line to turbine for steam generator 1 (PIN/FT) 41-50 E10.0 XISL(2) (PIN/FT) 51-60 E10. 0 XISH(2) (PIN/FT) 61-70 El o. 0 XIST(2) (PIN/FT) Card 28 - Steam Line Geometr Data 1-10 E10.0 VSH( I) - Steam header line volume (FT /PIN) 11-20 E10. 0 VSL(I) - Main Steam line volume (FT3/PIN) 21-30 E10.0 SHKA2(I) - K/A from header to main steam line (PIN/FT2)2 31-40 E10.0 STKA2(I) - K/A from main steam line to turbine with turbine valves full open (P IN/FT2) 2 Note: Card 28 is repeated LSS times. Card 29 - Steam Line B ass Valve Data 1-10 E10.0 SBPFR(I) - Bypass Capacity per main steam line (fraction of initial steam line flow) 11-20 E10.0 FRBPOP(I) - Initial fraction bypass valves open 3-10 NAI 76-67 Revision 0 July 19, 19'76 Field Variable - Data units 21-30 E10.0 FRBPA(I) - Fraction of bypass valve which can be varied during the transient 31-40 E10.0 DABPDT(I) - Bypass"valve opening rate for core average temperature control (1/ F) 41-50 E10.0 DABPDP(I) - Bypass valve opening rate for steam line pressure control (1/psi) 51-60 E10.0 STBP(I) - Bypass valve actuation time signal (sec) 61-70 E10.0 VORBP(I) - Bypass valve opening rate (1/sec) Note: Card 29 is 'repeated LSS times. In addition to the above implied limits, the fractional valve area is restricted between 0 and l. Card 30 - Steam Line Dum Valve Data 1-.10 E10.0 SDPFR(I) - Dump capacity per main steam line (fraction of initial steam flow) 11-20 E10.0 FROPOP(I) - Initial fraction dump open 21-30 E10.0 FRDPA( I) - Variable dump fracti on 31-40 E10.0 DADPOT(I) - Dump valve opening rate for core average temperature control (1/ F) 41-50 E10.0 OADPOP(I) - Dump valve opening rate for steam 1-ine pressure control (1/psi) 51-60 E10.0 STDP (I ) - Dump va ve actuati on time s i gnal 1 (sec) 61-70 E10.0 VORDP(I) - Dump valve opening rate (1/sec) Note: Card 30 is repeated LSS times. See note for Card 29 for area limits. Card 31 - Turbine Control Valve Data l-lo E10.0 FRCVC(I) - Initial fraction control valve closed 11-20 E10.0 FRCVA'(I) - Variable control valve fraction 21-30 El o. 0 VCRCV(I) - Control valve closure rate (1/sec) 31-40 E10.0 TDCV(I) - Control valve closure time delay following actuation signal (seconds) Note: Card 31 is repeated LSS times. 3-11 1 NAI 76-67 Revision 0 July 19, 1976 Card 32 - Turbine Sto Valve Data Field Format Variable - Data'nits 1-10 E10. 0 VCRSV(I) - Stop valve closure rate (1/sec) 11-20 E10. 0 FRSV(I) - Fraction of stop valve closure 21-30 E10. 0 TDSV(I) - Stop valve closure time delay following actuation signal (sec) Note: Card 32 is repeated LSS times. Card 33 - Main Steam Line Isolation Valve Data 1-10 E10. 0 YCRATE(I) - MSIV closure rate (1/sec) 11-20 E10. 0 TDMSV( I) - MSIY closure time delay following actuation signal (sec) Note: Card 33 is required for both steam generators. Card 34 - Pressurizer Data 1-10 E10.0 VPSPR - Initial Pressurizer Steam Volume (FT /PIN) 11-20 El o. 0 VPLPR - Initial Pressurizer Liquid Volume (FT3/P IN) 21-30 E10.0 MTRLVL - Initial Pressurizer Mater Level (FEET) Card 35 - Pressurizer Relief Valve Data 1-10 E10.0 RYKA2 - Relief Valve K/A (PIN/FT2)2 11-20 E10.0 PRELF1 - Reactor coolant system pressure at which'elief valves begin to open (PSIA) 21-30 E10.0 PRELF2 - Full Open pressure (PSIA) Card 36 - Pressurizer Safet Valve Data 1-10 E10.0 SVKA2 - Safety Valve K/A (PIN/FT ) 3-12 0 0 NAI 76-67 Revision 0 July 19, 1976 Fie1d Format Variable - Data units 11-20 E10.0 PSAFTl - Reactor coolant system pressure at which safety valves begin to open (PSIA) 21-30 E10.0 PSAFT2 - Full open pressure (PSIA) Card 37 - Pressurizer Heater Data 1-10 E10. 0 PPHH - Pressure at which heaters are turned on (PSIA) 11-20 E10.0 PPHL - Low end of proportional heater range (PSIA) 21-30 E10. 0 PWLHON - High pressurizer water level setpoint - heaters on (FT) 31-40 E10.0 PWLHOF - Low Pressurizer water level setpoint - heaters off (FT) 41-50 E10.0 gPHR - Proportional heater ramp rate (BTU/SEC - PSIA-PIN) 51-60 E10.0 qPHM - Maximum heater heat rate (BTU/SEC-P IN) Card 38 - Char in S stem Data 1-10 E10.0 PWLCON - Low Pressurizer level setpoiht'or RCS charging flow on (FEET) 11-20 E10.0 PCR - RCS charging flow rate (LBM/Sec-PIN) 21-30 E10.0 ENCHR - Enthalpy of Charging water (BTU/LBM) 31-40 E10.0 BNCHR - Boron concentration of charging water (PPM) Card 39 - Lefdown S stem Data 1-10 E10.0 PWLLON - High pressurizer level setpoint for'eginning of- letdown flow-(FEET) 11-20 E10. 0 - PWLLMR - Pressurizer level for maximum letdown flow (FEET)- . 21-30 E10. 0 PLDMR - Maximum letdown flow (LBM/SEC-PIN) 3-13 NAI 76-67 Revision 0 July 19, 1976 Card 40 - Pressurizer S ra Data Fr'ord For orat Variable -'ata units)PSPON 1-10 El 0.0 - High Pressurizer Pressure Set-point for Sprays ON (PSIA) 11-20 E10.0 PPSPMR - Pressurizer Pressure for maximum spray flow (PSIA) 21-30 E10.0 PSRM - Maximum spray flow (LBM/SEC-PIN) Card 41 - Pressurizer Water Relief Data 1-5 I5 NOWTRR - Number of Data Pairs (0 < NOWTRR < 10) If NOWTRR = 0, water relief based on Eq (24a) 11-20 E10.0 ARELF - Relief Valve Area (FT2/PIN) 21-30 E10.0 ASAFT - Safety Valve Area (FT2/PIN) 31-40 E10.0 DISCCF - Discharge Coefficient 41-50 E10.0 HWTRRF - Curve reference water enthalpy (BTU/LBM) 51-60 E10.0 DGWRDH - Slope of mass flow vs. enthalpy (LBM/BTU) Card 42 - Pressurizer Water Relief Table 1-10 E10.0 PGWTRR(2) - Pressure (PSIA) 11-20 E10.0 PGWTRR(1) - Water relief flow rate (LBM/FT2-SEC) 21-30 E10.0 PGWTRR(4) 31-40 E10.0 PGWTRR(3) Card set 42 is repeated until NOWTRR data pairs are entered. There are three data pairs per card. 3 ]4 0 NAI 76-67 Revision 5 April 19, 1978 Card 43 - Safet In 'ection Data Fi el d Format Variable - Data units 1-5 I5 NOSIN - Number of flow vs. pressure data points (0 < NOSIN < 25) 6-10 IS IESFAS - Safety injection actuation logic option. If IESFAS' 0, exceeding pressurizer level or pressure setpoint will initiate signal. If IESFAS g 0 , exceeding both pressurizer level and pressure setpoints required to initiate signal. 11-20 E10.0 SILP - Low Pressure Actuation Setpoint (PSIA) 21-30 E10.0 SILL - Low Pressurizer Level Actuation Setpoint (FEET) 31-40 E10.0 SITIM - Input Actuation Time Signal. If SITIM < 0.0, actuation is generated by either low pressure or low level signal. (sec) 41-50 E10.0 SITD - Time delay following actuation signal (SEC) 51-60 E10.0 ENSINJ - Enthalpy of safety injection water (BTU/LBM) 61-70 E10.0 BORSIN - Boron concentration of safety injection water (PPM) (See note on Card 44). Card 44 - Safet In ection Line Data 1-10 E10.0 SILMAS - Coolant mass in safety injection line. (LBM/PIN) . 11-20 E10.0 SILBRN - Initial boron concentration in safety injection line (PPM), NOTE: The HPCI water injected into the RCS will have a boron concentration of SILBRN, until the total injected mass equals SILMAS. After this time, the concentration is taken as BORSIN. 3-15 NAI 76-67 Revision 5 April 19, 1978 Card 45 - Sa fet In 'ecti on Flow vs. Pressure Table 1-10 E10.0 PSINT(1) - RCS pressure (PSIA) 11-20 E10.0 WSINT(1) - Safety injection flow (LBM/SEC-PIN) 21-30 E10.0 PSINT(2) 31-40 E10.0 WSINT(2) 3-15a NAI, 76-67 Revision 5 April 19, 1978 Field Format Variable - Data units Note: PSINT(I) < PSINT(I+1) Card Type .45 is repeated until NOSIN data pairs are entered with three pairs per card. Card 46 - Motor Driven Auxiliar Feedwater Pum Data 1-5 I5 NOAXFM - Number of Flow vs. Pressure Data points (0 < NOAXFM <. 25) 11-20 E10.0 TAXFWM - Actuation time signal. If TAXFWM < 0.0, actuation signal is generated by safety injection signal, main feedwater isolation, or low steam generator level. (sec) 21-30 E10.0 TDAXFM - Time delay following actuation signal (SECS) 31-40 E10.0 HAXFM - Feedwater Enthalpy (BTU/LBM) 41-50 E10,0 FAXFW(1) - Auxiliary feedwater factor for SG1 51-60 E10.0 FAXFW(2) Card'.47 - Motor Driven Auxiliar Feedwater Table 1-10 E10.0 PAXFWM(I) - S.G. Shell Side Pressure (PS IA) 11-20 E10.0 WAXFWM(I) - Auxiliary Feedwater Flow (LBM/HR-PIN-SG) Note: Card Type 47 is repeated NOAXFM times. PAXFWM(I) < 'PAXFWM(I+1 ) Card 48 - Steam Turbine Drive Auxiliar Feedwater Pum Data 1-5 I5 NOAXFS - Number of Flow vs Pressure Data Points (0 < NOAXFS < 25) 11-20 El o. 0 TAXFWS - Actuation time signal (SECS) (see note for TAXFWM on Card 46) 21-30 E10.0 TDAXFS - Time delay following actuation signal (SECS) 31-40 E10.0 HAXFS - Feedwater Enthalpy (BTU/LBM) 3-16 NAI 76-67 Revision 1 Jaliuarp, TH, 1977 Field Format Variable - Data uni is) Card 49..- Steam Turbine Driven Auxiliar Feedwater Table 1-10 E10.0 PAXFWS(I) - S.G. Shel', Side Pressure (PSIA) 11-20 E10. 0 WAXFWS.'(I) - Auxiliary feedwater flow (LBM/HR-P IN-SG) Note: Card Type 49 is repeated NOAXFS times. PAXFWS(I) < PAXFWS(7+1 i. Card 50 - Dum and B ~ass Control S stem Data Field Format Variable - Da i:a (uni t=- '; 1-5 IDBOPT - Temperature - Pressure-Time control option IDPOPT < 0 actuation on t.im signal IDBOPT = 0 control cn maximum of high TAV and high Psec IDBOPT > 0 control on high Psec before reactor trip and maximum of high TAV and high Psec after trip 11-20 E10.0 TARO - Dump control reference core average temperature ('F) 21-30 E10.0 PARD - Dump control re ercnce steam line average pressu "e (PSIA) 31-40 E10.0 TARB - Bypass control r fer rce core average temperature ( F) 41 50 EIO.O PARB - Bypass control reference steam line average pressure (PSlt'-.) Card 53, - Turbine Valve Controls 1-10 E10. 0 PDOSPD - Stop Valve Ove" s;.;:-:ed Closure SetpOint (fraotiOn Oi I: ll polaer) 11-20 E10.0 TRBT - Turbine Runback Jn"',t",:,tion Tim . If TROT < 0 turbin.. runback ignored. (sec, 21-3O E10.0 TRBL - Turbine Runback P wr Le!el Set-posnt (1-raction of Initial Power) If TRBL <0, a control rod withdrawal prohibit is initiated following the turbine runback signal. 3 17 NAI 76-67 Revision 0 July 19, 1976 Field 'Format Variable - Oata'nits. Card SS - Hain Steam Line and Main Feedwater isolation Control 1-5 I5 IOPSLI - Main steam line isolation signal option IOPSLI = 0 ignore IOPSLI = 1 Signal generated on either hi-hi steam flow or hi steam flow plus low Core average temperature coincident with safety injection actuation IOPSLI = 2 Signal on low shell side pressure. 11-20 E10.0 HIHIWS - HI-HI Steam Flow Setpoint - (Fraction of Initial Flow) 21-30 E10.0 HIWS - HI Steam Flow Setpoint (Fraction of Initial Flow) 31-40 E10.0 TALO - Low Core Average Temperature Setpoint ('F) 41-50 E10.0 PSECLO - Low Shell Side Pressure Setpoint (PSIA) Note: Only the last two setpoints are used for main feedwater isolation and are used irregardless of IOPSLI. Card 53 - Feedwater Control S stem Data 1-5 I5 NOLYSL - Number of S.G. Water Level vs. Power Level Data Pair's E10.0 POPFFW - Ratio of Initial Power to Full Power 21-30 E10.0 WFDMIN - Minimum Feedwater Flow after trip (Fraction of Initial Flow) 31-40 E10. 0 FWRMPT - Feedwater ramp down time (SECS) 41-50 E10.0 TDFWIS - Time Delay for Feedwater ramp down (SECS) 51-60 E10.0 WFDMAX - Maximum feedwater flow (Fraction of Initial Flow) 3-18 0 NAI 76-67 Revision 0 July 19, 1976 Field Format Variable - Data units Card 54 - Feedwater Control S stem Data Omit if NOLVSL = 0 1-10 E10.0 WTLDB - Water Level Controller Dead Band (FEET) 11-20 E10. 0 CONLVL - Water Level Controller Constant (1/FT-SEC) 21-30 E10. 0 TAULY2 - Water Level Lag Time Constant (SEC) 31-40 E10.0 TAULVl - Water Level Lead Time Constant (SEC) Card 55 - Water Level vs. Power Level Table 1-10 E10.0 POWL(l) - Power Level (Fraction of Full Power) 11-20 E10. 0 WTL(l) - S.G. Water Level (FEET) 21>>30 E10. 0 POWL(2) 31-40 E10. 0 WTL(2) Note: POWL(I) ( POWL(I+1) Card Type 55 is repeated until NOLVSL data pairs are entered with three pairs per card. Card 56 - Control Rod Controller 1-5 I5 IOPCRC - Controller Option IOPCRC = 0 ignore IOPCRC = 1, rod insertion to match core average temperature IOPCRC = 2, rod insertion to match power level demand 11-20 E10. 0 - 'AVRFZ Zero Power Core Reference Average Temperature ( F) 3-19 NAI 76-67 Revision 5 April 19, 1978 Field Format Variable - Data units 21-30 E10.0 TAVRFF - Full Power Core Reference Average Temperature ('F) 31-40 E10.0 POPFCR - Ratio of Initial Power To Full Power 41-50 E10.0 PRSTOP - Low Power Level Rod Stop Signal Setpoint (Fraction of Full Power) 51-60 E10.0 DTMPOT - Margin Below the Overtemperature Trip Point at which Control Rod Motion is Stopped ('F) 61-70 E10.0 DTMPOP - Margin Below the Overpower Trip Point at which Control Rod Motion is Stopped ('F) Card 57 - Control Rod Controller Data Omit if IOPCRC = 0 Field Format Variable - Data'nits 1-10 E10.0 CRCDB - Controller Average Temperature Dead Band ('F) 11-20 El 0. 0 CONCRC - Controller Average Temperature Constant ('F - SEC) 21-30 E10.0 TAUCR2 - Control Rod Lag Time Constant (SEC) 31-40 E10.0 TAUCRl - Control Rod Lead Time Constant (SEC) 41-50 E10.0 CRCPDB - Controller Power Level Dead Band (Fraction of Full Power) 51-60 E10.0 CONCRP - Controller Power Level Constant (1/full power-sec) 61-70 El 0.0 DKDTMX - Maximum controller reactivity insertion or withdrawal rate (1/sec). If DKDTMX ( 0.0; default is 1.0E+20. 3-20 NAI 76-67 Revision 5 April 19, 1978 Card 58 - Transient Flow Control Parameters 1 I5 NOTAB5 - Number of Loop 1 Flow vs. time data sets (Curve fit if 0) 0 < NOTAB5 < 50 6-10 I5 NTB4 - Number of Loop 2 Flow vs. time data sets (Curve fit if 0) 0 '< NTB4 < .50 3-20a NAI 76-67 Revision 4 September 26, 1977 Field Format Variable - Data units 11-15 I5 NTB3 - Number of Loop 2 Cold Leg 8 Flow vs. time data sets (Curve fit if 0 and LCE = 1) 0 < NTB3'< 50 16-20 I5 LCE - RC system cold leg geometry option If LCE = 0, cold leg region 12 is ignored. If LCE 9 0, cold leg region 12 is included. 21-25 I5 LF- Flow rate units input option LF = 1 Mass flow input (Lbm/>>> h). LF = 0 Volumetric flow input, (F t3/'pin- hr) 26-30 I5 NFl - Number of Feedwater Flow and Enthalpy . vs. Time data. points for SGl. 0 < NFl < 25 31-35 I5 NF2 - Number of Feedwater Flow and Enthalpy vs. Time data points for SG2 0 < NF2 < 25 36-40 I5 IPUMP If IPUMP = 0, RCS flow rates are specified and dynamic pump model is ignored. If IPUMP P 0, dynamic pump model is included and RCS loop flows are calculated from momentum equations. Card 59 - RCS Loo 1 Flow Transient Table Omit if NOTAB5 = 0 or IPUMP P 0 1-10 E10.0 TJ5(I) - Time point for coolant flow in. Loop 1 measured from 0 (secs ) 11-20 E10.0 WJ5( I) - Loop 1 coolant flowr:at;TJ5 in, units specified by LF Card Type 59 is repeated until NOTAB5 data pairs are entered with three pairs per card. 3"21 NAI 76 67 Revision 4 September 26, 1977 Card 60 - RCS Loo 2 Flow Transient Table Omit if NTB4 = 0 or IPUMP f0 l4 1-10 E10.0 TV4(r) - Time see Card 59 ~ 11-20 E10.0 uz4(I) - Flow comments 3-2'i a NAI 76-67 Revision 4 September 26, 1977 Field Format Variable - Data units Card 61 - RCS Loo 2 Cold Le B Flow Transient Table Omit if NTB3 = 0, LCE = 0, or IPUMP P 0 1-10 El o. 0 TJ3( I ) see Card 59 11-20 E10.0 WJ3( I) comments Card 62 - RCS Loo 1 Flow Transient Curve Omit if NOTAB5 p 0 or Ip~p p 0 1-10 E10.0 WX1 Coefficient. of linear term (Sec-1) 11-20 E10.0 WX2 Coefficient of exponential term 21-30 E10.0 EX3 Coefficient of exponent (Sec-1) Card 63'- RCS Loo 2 Flow Tr'ansient Curve Omit if NTB4 9 0 or EPUNP P 0 1-10 E10.0 WY1 11-20 E10.0 WY2 see Card 62 cotanents 21-30 E10.0 WY3 Card 64. - RCS'j oop'2'Cold Le '8'Transient.'Curve'" Omit if LCE = 0, NTB3.( 0, or IPUNP P 0 1-10 E10.0 WZ1 11-20 E10.0 WZ2 see Card 62 comments 21-30 E10.0 WZ3 Card 64A* - Pum and Motor Data In ut Options 1-5 I5 HPPH(l) - Number of data entries for homologous pump head curve type l.'-21 6-10 I5 HPPH(2) 11-15 I5 HPPH(3) 16-20 I5 HPPH(4) 21-25 I5 HPPT(l) - Number of data entries for homologous pump hydraulic torque curve type l. <21 26-30 I5 HPPT(2) 31-35 I5 HPPT(3) 36-40 I5 HPPT(4)
- Note: Cards 64A through 64L are omitted if IPUMP = 0.
3-22 NAI 76-67 Revision 4 September 26, 1977 Field Format Yariable'-'Data units 41-45 I5 NPMT - Number of data entries for pump motor torque curve. < 20 If NPMT ~ 0, this curve is zeroed out. 46-50 I5 IRP - Reverse pump speed option. If IRP=O, reverse speed not permitted. If IRP/0, reverse speed allowed. Note: If NPPH or NPPT -0, this curve type is zeroed out. Card 648 - Pum and Motor Data 0 tions 1-5 I5 NPPL(l) - Total number of pumps in Loop 1 6-10 I5 NPPL(2) - Total number of pumps either Loop 2 (LCE.=O) or Loop segment 2A(LCE/0). 11-15 I5 NPPL(3) - Total number of numps in Loop segment 28 (LCEPO) 16-20 I5 IPSTAT(l) - Initial pump motor status for pumps in Loop 1. If IPSTAT=O, motor off If IPSTAT=l, motor on 21-25 I5 IPSTAT(2) 26-30 I5 IPSTAT(3) Card 64C - Homolo ous Pum Head Data 1-10 E10.0 GH(1,1)- v/a First data pair 11-20 E10.0 HOG(1,1)- h/ez for Curve Type 1 21-30 E10.0 GH(1,2)- v/a Second data pair 31-40 E10.0 ~ HOG(1,2)- h/az for Curve Type 1 3-22a NAI 76-67 Revision 4 September 26, l977 Field format Variable - Data units Card 64C - Homolo ous Pum Head Data continued E10,0 GH(1,NPPH(1))- v/0, Last data pair for '10,0, HOG(1,NPPH(l) )-h/a Curve Type 1 1-10 E10.0 GH(2,1)- a/v First data pair for 11-20 E10.0 HOG(2,1)- h/vz Curve Type 2 E10.0 GH(4, 0'PH(4) ) a/v /Last data pair E10.0 HOG(4,NPPH(4)) h/v'2I For .Curve Type 4 Notes: For each curve type I, GH( I,J)<GH( I,J+1). Each curve type begins on a new card. The data is entered with three pair per card. If NPPH(I )'-0, Curve Type I is omitted and the curve is zeroed out. Card 64D - Homolo ous Pum H draulic Torque~Data 1-10 E10. 0 GZ(1,1)- v/a /First data paid for E10.0 TOG(1,1)- b/azjCurve Type 1 '1-20 E10,0 GZ(4,NPPT(4)) a/v /Last data pair E10.0 TOG(4,NPPT(4)) b/u2$ for Curve Type 4 Note: See notes for Card 64C, Card 64E - Motor Tor ue Data 1-10 E10.0 AM(1) Relative motor speed (Fraction of rated pump speed) EIO.O TMOA(1) Relative motor torque (Fraction of rated pump hydraulic torque) E10.0 AM(NPMT) E10. 0 TMOA(NPMT) Note: If NPMT~O, this data is omitted and the motor torque is zeroed out. The data is entered with three pairs per card. 3-22b NAI 76 67 Revision 4 September 26, 1977 Fi el d For~at Variable:-':Data'(units) Card 64F - Rated'Pum Data 1-10 E10.0 RAT/ - Rated volumetric flow per pump (gpm/pin) 11-20 E10.0 RATT - Rated pump hydraulic torque (1bf-ft) 21-30 E10.0 RATS - Rated pump speed (rad/sec) 31-40 E10.0 RATD - Rated pump fluid density (ibm/ft3 ) Card 646 - Pum Inertia and Tor ue Data 1-10 E10.0 PIHERT - Pump inertia (ibm-ft2 ) 11-20 E10.0 FINERT - Flywheel and motor inertia (ibm-ft ) 21-30 EIO.O FRIGG - Coefficient for friction torque losses=C (lbf-ft) f 31-40 E10.0 FRICE - Exponential factor for friction losses = nf. 41-50 E10.0 WIHDC - Coefficient for windage torque losses = Cw (lbf-ft). 51-60 E10.0 WINDE - Exponential factor for windage losses = n . w Card 64H - Loo Fluid Inertia Factors 1-10 E10. 0 XINE1 - Loop 1 inertia factor, (L/A)1 (pin/ft) 11-20 E10.0 XINE2 (L/A), (pin/ft) 21-30 E10.0 XINE2B (L/A)2B (pin/ft) 31-40 E10.0 XINERV (L/A)RV (pin/ft) Card 64I - Loo Pressure Loss Coefficients 1-10 E10.0 PDC1 - Loop 1 loss coefficient K1 (pin/ft ) 11-20 E10.0 PDC2. - K2 (pin/ft ) 21-30 E10.0 PDC28 - K2B (pin/ft2 ) 2 31-40 E10.0 PDCRV - KRV (pin/ft ) 22c NAI 76-67, Revision 4 September 26, 1977 Field 'Format l/ariabIe'Data units Card'64J -'Pum Transient S ecification 1-10 110 IPTRCN(1) - Transient type for pump 1, 11-20 E10. 0 TDPTR(1) - Time delay for pump transient to begin measur ed from t=0. (sec) . 41-50 I10 IPTRCN(3) 51-60 E10.0 TDPTR (3) Note: IPTRCII ~T 0 None (constant speed) 1 Pump motor trip 2 'ump shaft lock 3' Pump shaft shear Pump motor startup 5 Time-dependent speed specified Card 64K - Time De endent S eed Paris (Omit Card 64K if IPTRCN g 5) 1-5 I5 NPSPVT - Number of time-dependent speed data pairs, 1-NPSPVP-25 Card 64L' Time De endent S eed S ecification (omit Card 64L if IPTRCN g 5) 1-10 E10.0 TIMPSP(l). - Time measured from TDPTR, (sec) 11-20 E10.0 PSPTIM(1) - Relative pump speed (Fraction of rated). 4 4 E10.0 TIMPSP(HPSPVT) - Time measured from TDPTR (sec) E10.0 PSPTIH(HPSPVT) - Relative pump speed ( Fraction of rated) Note: There are three data pairs per card, 3-22d 0 NAI 76-67 Revision 4 September 26, 1977 Field Format Variable - Data units Card 65 - Steam Generator 1 Transient Feedwater Data 1-10 E10.0 TFDl(I) - Time measured from 0 (SEC) 11-20 E10.0 WFWl( I) - Flow change from Initial Flow (Fraction of Initial Flow) 21-30 E10.0 HFH1(I) - Enthalpy Change from Initial value (BTU/LBN) Card Type 65 is repeated NFl times. 3-22e b 4 NAI 76-67 Revision 0 July 19, 1976 Field Format Variable - Data units Card 66 - Steam Generator 2 Transient Feedwater Data 1-10 E10.0 TFD2(I) - Time (SEC) 11-20 E10.0 WFW2(I) - Flow change (Fraction Initial) 21-30 E10.0 HFW2(I) - Enthalpy change (BTU/LBM) Card Type 66 is repeated NF2 times. Card 67 - Main Steam S stem Break Data e 1-5 I5 ISLBLC - Break Location ISLBLC = 0 Ignore ISLBLC < 0 The break is located in the main feedwater pipe of SG2 ISLBLC = 1 The break is located between SG outlet and the isolation valve in SG2 ISLBLC = 2 The break is located in the header pipe beyond the isolation valve ISLBLC = 3 The break is located in the main steam line section 11-20 E10. 0 ASLB - Break Area (FT /PIN) 21-30 E10 .0 BREAKT - Time at which break begins (SEC) 31-40 E 10. 0 BRKOPT - Time duration of break opening (SEC) 41-50 E10.0 BRAKHT - Feedwater pipe break elevation for UTSG only (FT) Card 68 - Reactivit Transient Data 1-10 E10.0 RSTEP - Step change in reactivity ($ ) 11-20 E10.0 RRAMP - Ramp Insertion rate ($ /sec) 21-30 E10.0 RTOT - Total ramp insertion ($ ) Card 69 - Scram 0 tions 1-5 I5 ISCRAM - Scram option ISCRAM = 0 No scram reactivity input ISCRAM = 1 Scram reactivity inserted following a trip signal ISCRAM > 1 Scram reactivity insertion signal at TSCRAM 3-23 e NAI 76-67 Revision 5 April 19, 1978 t Format Variable. - Data (units I5 ATSCRM - Number of tab'le:sets of scram reactivity 1 < NTSCRM < 25 E10.0 TSCRAth - Input time for scram insertion '. 'signal (SEC) I5 ISENSR - Temperature sensor location option ISENSR = 0 Reactor vessel plenums = + I Hot and cold legs = + 2 Steam generator plenums For ISENSR >o, an overpower or overtemperature aT trip signal is generated when the setpoint is exceeded in either loop. For ISENSR <0, an overpower or overtemperature aT trip signal is generated only when the setpoint in Loop 1 is exceeded. I5 ITRPTY - Overpower and overtemperature aT setpoint simulation option ITRPTY = 0, steady-state trip lines ITRPTY = I, dynamic trip calculation. E10.0 TDLYTH - Time delay for hot side temperature sensors (sec). If TDLYTH < 0.0, default is 0.0 E10.0 TDLYTC - Time delay for cold side temperature sensors (sec). If TOLYTC < 0.0, default is 0.0 E10.0 TLAGTH - Time constant for hot side temperature sensor lag (sec). If TLAGTH < 0.0, default is 0.0. E10.0 TLAGTC - Time constant for cold side temperature sensor lag (sec). If TLAGTC < 0.0, default is 0.0. 3-24 NAI 76-67 Revision 5 April 19, 1978 Card 70 - Reactor Protective S stem Parameters. Omit if ISCRAM P 1 1-10 E10.0 TRIP(I) - Trip I setpoint 11-20 E10.0 TDTRIP(I) - Time delay for scram insertion following Trip I (SEC) Trio Function,, Units High neutron power (Fraction of Initia'I Power) 2 High Pressurizer Pressure (PSI~)
- 3. Low Pressurizer Pressure ,~ (PSra) 4 '5 High Pressuriz r Level (FEET)
Low.Pressurizer Level (FEET) 6 Low-Low Steam Generator Level (FEET) 7 Turbine Trip - HI S.G. Level (FEET) 3-24aa NAI 76-67 Revision 1 January 18, 1977 8 Low Reactor Coolant Flow (Fraction of Initial Flow) 9 High Power to Flow ratio (Fraction of Initial P/F ratio) . 10 High Core Outlet Temperature ('F). Note: 'f TRIP(7) < 0.0, reactor trip signal from turbine overspeed trip is ignored and this trip function is ignored. Card 70 is repeated 10 times. Card 71 - Over ower Delta T Tri Parameters Omit if p 1 or ITRPTY 1 1-1 0 E10. 0 OPDTTM - Maximum Delta T ('F) 11-20 E10.0 OPDTDT - Data Point D'elta T ('F) 41-50'SCRAM 21-30 E10.0 OPDTTA - Data Point Average T ('F) 31-40 '10.0 OPDTSL - Slope of Del,ta T vs. Ave T E10.0 TDTRIP(11) - Trip Time Oelay (sec) Card'71'A'Over'wer'Delta'T*Tri 'Parameters Omit if ISCRAM g 1, or ITRPTY 0 1-10 E10.0 OPDTO - Reference overpower aT (aT P in Eq (40a)) ( F) 11-20 E10.0 OPDTAO - Reference overpower aT core average temperature (T in Eq (40a)) ( F) 21-30 E10. 0 OPDTAU - Rate/lag time constant (T3 in Eg (40a)) (sec) 31-40 E10.0 OPDTK4 - Basic gain (K4 in Eq (40a)) 41-50 E10.0 OPDTK5 - Rate/lag gain (K5 in Eq (40a)) (1/ F) 51-60 E10.0 OPDTK6 - Core average temperature gain (K6 in Eq (40a)) (1/ F) Card 71 B Over ower Delta T Tri Parameters Omit if ISCRAM j 1, or ITRPTY = 0 1-10 E10.0 TDTRIP (ll) - Overpower aT trip time delay (sec) 3-24a 0 NAI 76-67 Revision ] January 18, 1977 Format Variable - Data (units) r Overtem~erature . Delta T Trip Parameters SCRAM f 1, or ITRPTY = 1 T5 NPOTDT - Numbe. of Constant Pressure Cur!es 0 c NPOTDT < 10 E10. 0 TDTRIP (12) - scrip T~me Delay Card 73 - Overtem erature Delta T Curves Omit if ISCRAM g I, or ITRPTY = .1 1-10 E10.0 OTDTPR(I) - RC system pressure corresponding to curve I (PSIA) 11-20 E10.0 OTDTDT(I) - Delta T Data point on curve I ('F) 21-30 E10. 0 OTDTTA(I) - Averaoe T Data point on curve I ('F) 31-40 E10. 0 OTDTSL( I) - Slope of D lta T vs. Average T for cui ve I. Card Type 73 is repeated NPOTDT times. Note that. OTDTPR(I) < OTDTPR(I+1) ~ ~ ~ << Card 73 A - Overtem erature Delta T Tri Parameters Omit of ISCRAM g I, ITRPTY = 0 1-10 E10.0 OTDTO - Reference overtemperature aT (zT in Eq (40b)) ( F) 11-20 E10.0 OTDTAO - Reference overtemperature aT core average temperature (T in EQ (40b)) ( F) 21-30 E10.0 OTDTAU1 - Lead time constant (vl in Eq (40b)) (sec) 31-40 E10.0 OTDTAU2 - Lag time constant (v2 in Eq (40b)) (sec) E10.0 OTDTK1 - Basic gain (Kl in Eq (40b)) 51-60 E10.0 OTDTK2 - Core average timperature gain (K2 in Eq (40b)) (1/'F) 3-25 0 NAI 76-67 Revision 1 January 18, 1977 Card 73 B - Overtem erature Delta T Tri Parameters Omit if ISCRAM P 1, or ITRPTY = 0 1-10 E10.0 OTDTK3 - Pressure gain (K3 ig Eq (40b)) (1/psi) 11-20 E10.0 OTDTPO - Reference pressure (p in Eq (40b)) (psia) 21-30 E10.0 TDTRIP (12) - Overtemperature aT trip time delay (sec) 'I Card 74 - Scram Reactivit Table (See Figure 7) Card 74 is included only when ISCRAM r'. ~ 1-10 E10.0 TSDA(l) - Time point for scram reactivity measured from TSCRAM (seconds) 11-20 E10.0 DKSCRM(l) - Scram reactivity at time TSDA(l) 21-30 E10.0 TSDA(2) 31-40 E10.0 DKSCRH(2) Card Type 74 is repeated until the NTSCRM Data pairs ar entered with three data pairs per card. Card 75 - Transient Power Demand Data 1-5 I5 t<OPD - Number of Data Pair 0 < HOPD < 25 11-20 E10. 0 POPF - Fraction of Initial to full power 3-25a NAI 76-67 Revision 0 July 19, 1976 Card 76' Transient Power Demand Table Fieid Format Variable - Data units 1-10 E10.0 TPOD(1) - Time into transient measured from zero (secs) 11-20 E10. 0 POD(l) - Power demand (Fraction of Initial Power) 21-30 E10.0 TPOD(2) 31-40 E10.0 POD(2) Card Type 76 is repeated until NOPD data pairs are entered with three pairs per card. Card 77 - Power Forced Mode 0 tion 1-5 I5 IPOW - Power forced mode option IPOW = 0 Kinetics calculated IPOW = 1 Power forced mode 6-10 I5 NTPOW - Number of table sets of power vs. time 1 < NTPOW < 25 Card 78 - Power Transient In ut (See Figure 5) Card Type 78 is included only when IPOW = l. 1-10 E10.0 TPDA(1) - Time point for relative power measured from t = 0 (Seconds) 11-20 E10. 0 POWER(l) - Power level relative to initial value at time TPDA(l) E10.0 TPDA(2) 31-40 E10.0 POWER(2) Card Type 78 is repeated until the NTPOW data pairs are entered with three data pairs per card. 3-26 0, 0 NAI 76-67 Revision 0 July 19, 1976 Card 79 - Radial Heat Generation Data Field Format Yariable Data units 1-5 I5 IOPRAO - Input option for radial heat generation profile in fuel region IOPRAO = 0; No input and a uniform distribution is used. IOPRAD g 0; input entire radial profile 11-20 E10.0 PRAO - Radial pin power peaking factor If PRAO < 0.0, default = 1.0 21-30 E10.0 FW - Fraction of total core power generated directly in core coolant channel. Card 80 - Axial Heat Flux Profile 1-10 E10.0 AXF(l) - Axial flux factor for node at the bottom- of cor e 11-20 E10.0 AXF(2) E10,0 AXF(NS) Card Type 80 is repeated until NS values of AXF have been entered with a maximum of six values per card. Note: The Program normalizes the input values to an average of 1.0. Card 81 - Radial Heat Generation Profile Omit if IOPRAD = 0 1-10 E10.0 RAD(l) - Radial heat generation factor for ~ 'central fuel node 11-20 E10,0 RAO(2) E10.0 RAO(M) Note: The input values are <omalpze3: to an average value of 1.0 There are six entries per card. 3-27 NAI 76-67 Revision, 0 July 19,. 1976 Card 82 Dela Neutrons Deca Constants Fie1d Format Variable - Data units 1-10 E10. 0 AX(l) - Decay constant for first delay group which is equaI to Xl in Eq (13b) (1/seconds) 11-20 E10.0 Ax(z) E10.0 AX(IT) Card 83 - De1a Neutron Fractions 1-10 E10. 0 BX(1) - Fractional yield of first delay group neutrons per fission which equals 81 in Eq (13b) 11-20 E10,0 ox(z) E10.0 ex(IT) Card 84 - Deca Heat Deca Constants Omit if IDH = 0 1-10 E10.0 ALg(1) - Decay constant for first decay heat group which equals hl in Eq (13d) (1/SEC) 11-20 E10.0 ALP(2) E10. 0 ALq(IDH) There are six entries per card Card 85 - Decay Heat Fractions Omit if IDH = 0 1-10 E10.0 AAg(l) - Energy fraction for first decay heat group which equals yl in Eq (13d) 11-20 E10.0 AAq(z) E10. 0 There are six entries per card AAg( IDH) 3-28:. ~ g NAI 76-67 Revision 0 July 19, 1976
- 4. 0 OUTPUT" DESCRIPTION The printed output from DYNODE-P/2 is in the following format:
o Version identification information o Input section o Transient output data o Summary output data Descriptions of each segment are presented below. In addition, plots of the summary output can be requested through input specification and the control cards (see Appendix B).
- 4. 1 Version Identification This segment of output writes the following information:
- 1. Program name
- 2. Version identification Number and date
'4.2 ~in ut The input for the run is written in this segment. The input variables are grouped according to the input formats. Each variable is described along with its program symbol and appro-priate units. Identification of option selections is also wri tten. 4.3 For the initial time (t=0) and each time step at which the output is requested, the following data is written. The units of all variables are included in the output. 4-1 0 NAI 76-67 Revision,5 April 19, 1978
- 1. First data block
- a. Problem Title Repeated on. each- page
- b. Time
- c. Pressurizer Pressure
- d. Core coolant flow rate
- e. Total core energy generated from t=O
- f. System time step number
- g. Current system time step size
- h. Total core power
- i. Relative neutron power If the kinetics option is selected, the following are included:
- j. Time derivative of the neutron power
- k. akIN + akS 1'KDOp
- m. QkENT BORON oe DkCRC
'eff
- q. Power Demand If decay heat generation is considered,
- r. Fission power
- s. Decay heat power This is followed by:
- t. The current core computational time step
- u. The core time step number
- v. The number of times the RCS arid core time steps were halved and doubled from the last print.
2; Fuel" Rod Temperature-Black - The temperature for each radial node in the oxide and cladding is pr'inted. Average oxide and cladding temperatures are in-cluded. The temperatures in both 'F and 'C are included. 4-2 ~ ~ 4 t 0 l A NAI 76 67 Revision 4 September 26, 1977
- 3. Axial Coolant Data Block The coolant enthalpy, the heat flux, the DNB heat flux, the ONB ratio, and the coolant mass are printed for each axial coolant node. Numerical average values for the enthalpy and heat flux are also included.
- 4. Precursor Concentration Data Block The delay neutron precursor concentrations are written for each delay neutron group when the kinetics option is selected.
- 5. Reactor Coolant System Data Block The RCS (excluding core and pressurizer) mass, enthalpy,.specific volume, boron concentration, and temperature distribution and the total enthalpy and mass are written.
In addition, the RCS loop flow distribution, the HPSIS, charging, letdown and main steam break flows are printed. If the dynamic flow model is used, the pump speeds, heads, and net torques are written.
- 6. Core Data Block The core coolant total mass, flow rate, inlet and exit enthalpies, average density and enthalpy, core-to-coolant, heat transfer, temperatures, trip set points, and average boron concentration, and integrated direct coolant enerqy deposition are written.
- 7. Pressurizer Data Block The pressurizer masses, enthalpies,.temperatures, volumes and internal energies for the upper and lower regions, the water level, surge line flow rate, relief and safety valve flow rates, heater and spray rates, integrated surge line flow and energy, and average liquid boron concentration are written. In addition, the saturation properties at the current pressure are printed.
- 8. Steam Generator Shell Side Data Block The heat load, pressure, temperature, effective UA, feedwater 4-3
NAI 76-67 Revision 4 September 26, 1977 ll. Additional Output Messages Additional messages which provide warnings and other useful information to the user include:
- a. Initialization - The number of iterations required to initialize the fuel and cladding temperatures and the 4-4a
4 4 VI NAI 76-67 Revision 5 April 19, 1978 flow and enthalpy, flow rates for the steam line, relief and safety valves, water level, mixture level for UTSG, subcooled and saturated region lengths for OTSG, mass distribution, average void fraction, bubble rise velocity, total enthalpy, integrated heat transfer and net fluid flow energy out, volume errors associated with the pressure calculation which are greater than 0.001K, integrated net fluid flow, and fluid properties are printed for each steam qenerator.
- 9. Main Steam System Oata Block The pressure, mass, enthalpy,.and flow distributions are written for all regions in the main steam system.
- 10. RCS Totals The total fluid mass,, energy, and enthalpy, and total boron mass in the RCS loops, the core, and the pressurizer are written along with the:.corresponding sums. for the total RCS.
, The integrals of the product of the flow and the enthalpy into and out of the RCS loops and the core are written. The integrated mass and energy additions and losses for the RCS from the pressurizer relief and safety valves, the pressurizer sprays and heaters, and the chargring, letdown, and HPSI systems are printed. The total energy deposition in the oxide region of the fuel rod is written along with the stored energy in the fuel and cladding. The individual contributions from the core and the -RCS loops to the surge line mass and energy transport are written. The values for the current contribution per system time step and the total integrals are given. 10a. Loop Flow and Pump Speed Parameters If the dynamic flow model is used, loop pressure drops and pump torques and pressure rises are printed for each loop. NAI 76-67 Revision 0 July 19, 1976 main steam system are printed along with the steam generator AR and FBUB factors.
- b. Occurrence of DNB - When DNB is calculated to occur at any axial coolant node, a message is written which 'iden-tifies the axial location and time of occurrence.
- c. Occurrence of Rewetting - When rewetting (pre-CHF) is calculated to occur, a message is written which identifies the location and time of occurrence.
- d. Trip and Actuation Signals - Messages are written to inform the use of the times of occurrence for reactor trip, main feedwater isolation, safety -injection actuation, auxiliary feedwater actuation, main steam line isolation, and turbine trip.
- e. Pressure Non-Convergence - A message is written if the pressure calculation fails to converge within 50 iterations.
- f. Effective RCS.Volume - If the pressurizer empties, the effective RCS volume used for the pressure calculations after that time (see Section 2.3.3) is written.
4.4 ~EO << After the entire transient output has been written, a summary output data block is printed. The summary data includes: time, relative neutron power, pressurizer pressure, k ff, core average flux, average and maximum fuel temperatures, total steam eff'eat generator heat load, core inlet flow and enthalpy, relief plus safety valve flow, and pressurizer water level. Each variable is listed corresponding to each time the transient output was written. In addition, the maximum transient relative power and pr essurizer pressure and their corresponding times of occurrence are printed. 4-5 0 NAI 76-67 Revision 5 April 19, 1978 A summary table is provided which identifies all the trip signals (RPS, Main feedwater Isolation, Safety Injection Actuation, Auxiliary Feedwater Actuation, Main Steam Line Isolation, and Turbine Trip) which occurred during the course of the transient and the time of occurrence of each. 4-6 NAI 76-67 Revision 5 April 19, 1978 5.0 SAMPLE PROBLEM The input and output from a sample problem are given on the following pages. The first three pages are a listing of the input cards, and the remaining pages are select portions of the output. The fourth and fifth pages show the version identification segment. The next twelve pages are the input segment with the last of these containing the output of the initialization segment. The next four pages present the transient output segment for the initial time (t=0), and the next four, for t=1.0 seconds. The final two pages present the suranary output block. 5-1 TfST no 0 C ~Anni Fn> ])YNA['F-P/? WITH I)YNAHIC F].OW 4'OOFL I] 0 n 1 1 10 0 ~ 1 ]0 ].n sTEAAY STAT 2 12 1 ~ 0 474?2 ~ 53<94 ~ An)?44 7 '634 6 ~ 5041 .04497 o.n 6 n,?46Re A.n 42.n]7 2??.803.9 635E-]3 o,33n]2 0.17458 7 0 62460 o.n 0 0 F 066?1 1 ~ 0 8 0 n.n o.o 0 ' n.n 9 , 54m.RS 2250 2112.745 1056.367 800 ' ]0 6.773 ?7 1 '3632 '93E>>1? -50.0 n.n ?7 'f-060 '0721. 0.0 ).nR '6-31.0 1 ~ 46 0.1163 -3 ll 12 0 13 i ' 004R5346 ]446E-038 44 RQF-03 ]5 0]6463 F 07?3E<<O34 2?44F-03 ~ ~ A4?]SR ~ 4489E ~ 0210754 '245E-03 Sent 03 ~ 02591 0 0 ]I 18 .0)295 .AAR?3 .0263375 ~ 0 1493 ]9 1 ) 1 0 0 20 2 1 ?1 . 3? 1963. 3847F.-n3 2, 77446. 6688f -04 989 516 0 415 4 22-1 '].455)f AR ).o n.n ~ n.o 0 ~ 506 ~ ~ 23-1 )609R)~6924F-03 1 ~ 38723 '344F. 04 6'89 516 ' 415 ' 2?-2 ',5 ~ R?OSE OR 1 ~ 0 n 0 0 ' 0 ~ 506 23-2 ~ 0646 3],?684 '667F-03 Oo]0 Oo]422 0 ' ?4 '?.7?) E+)2 1050 )AS] 25 '3 ~ 3)A4E ]0 1100 1145 ?6 1 6 '4RE 05 ' 229F 05 2 '78E 061 ' 296E 06 0~0 0 ' 27 8 ~ 318E-03 4 '83E-07'66AF 074 '6&4F. 07 ?8 0 ~ 4203 0~0 )~0 ~ 069 ~ 005 oo ~. oo 29 -,n.n in. n O.O 1 ~ A O.n n.n 0~0 0 0 0 0 0 ' 0 ~ 0 30 ~ 31 i!.n +4).n 0 0 32 to.? 0 ~ 0 33 in ~ 2 o.n 33-2 .n?s?644 .n)53?5 1? ~ R4Re 34 I) 1252E 13 ?350 ?35] 35 3 ]59RE ]? ?Sno ?501 36
- 223o 22oo )3.6??77 T.no]? .o 0039466 ~ A3848 37
]? ~ 75 1 569E-04 479 F 50 800 ' 38 ,13 ~ 0 13 ~ 038 1 94?E-04 39 2275 ?3251 9670f-03 40 6.7? E-07 1 273F,-06 0 F 855 736 -n.oo8 41 .]750. >R33 ~ 6SR?. )065?, 2nnn. 3250 '5379 7241. ~ '567 '000 Roon~ 21172 42 1 42 2 ,~Ann. 'o. n )3 ?7n34. 1730. o.n enon. 5.584 32414. 0~0 ~ 0 '000 '5 '0000'6483 '00 42-3 43 44 0 3 '47F-03 200 3 '35F-03 3 '2?F-03 '90 45-1 56n 2.R]nF.-o3 715 2o498F,-03 855 ? ~ 186f.-03 4S-? 975 1 873f,-n3 1075 1,56]F-03 1160 1.249E-03 45-3 1235 9 367E-04 1283 6 '45f-04 ]330 3 '22E-04 45-4 1360 0 45-5 0 n.n o.n )Rn.n 0 ~ 0 0 ~ 0 2 ' 1 0 46 o 7o.9 4R 1 547 )020 547 1020 50 o.n -0.75 51 0 5?. 3 02 0 0 4,0 0 0 05 53 '.n 1 ~ ~ 1 ~ -0.2~7? -1800 ~ 200 54 .?)?6 0.20 28.1526 '.024 1 ~ 50 28 '526 55 1 551 ' 57R ~ 29 1 ~ 0 0 15 5 ' 5 ' 56 0,7S 0.1?6 -515 ~ 40 0 ~ 0 57 1 1 0 1 0 0 58 13 l ]? 14 9 ]O 6 52 2 l 0 N-R ) ~ 0 ' ~ 2 ~ OQ 55 0 '0 n.n 2.73 ]e?3 ~A ~ 3? 2 ~ ?.0 <0 7 ]A 7-]8 0,46 0.46 ]~?4 1 ~ ?.4 0 '2 0280 )223 ')e)7 0 AD ?0 0.60 0 '0 1 ~ ) 2?4 ]o)0 7-]C 7-)0 ) ~ On ].An 7-1 r. ] nn n.nn -O ~ Ol n.nn n.nn -0 ~ 96 7-?A O ~ 0.40 ]0 -Q.nn 0 ~ 24 AD O.R3 20 -0 ~ 8] 0 '0 0 30 0.65 0 '0 n,nn 7 ?8 7-PC n.80 0 37 ) F 00 ) 00' 7-?.]) '].nn O.nn -n.nl F Qn A.nn -0 ~ 16 7 3A 0.]0 4Q -0 '2 O.nn n.20 n.60 -n.n6 0 ~ '] O ~ 28 0 ~ ?0 0 F 00 0 ~ 4?. 7 38 7-3C 0 A.RA -).nn 0 ~ 3 c2F sn -0 0 '9 F 88 0 '4 3 '0 ].Qn 0 '4 0 '9 F 80 7 30 7 4A -n.60 2 ~ 47 -n.46 2 '0 0 '0 ) 73 7 4P '3 '462 . ~ n.OA ].4n A,37 0 80 0 0 7 4C 0.%0 '0 0 0 6) 68 O.SR 00 0 0 '4 F '9 n,64 0~ 7 4A 7-4F 0 1 -] 2 00 ?,98 -O.O2 F 40 -O,hn ) ~ 87 8 )A 0 '6)0 ) 60 ]0 -0 '4 1 40 01 AD n.ln 20 1 ~ ?1 '6 8-) R 8-]C A~ n,?0 A.RO 0 ~ Q.n) 9? 0 0 ~ 0.30 AQ '000 1 ~ 0 0 '0 '900 0.40 n.en 0 0 '9 ]on? 8-)n 8-1 f n.nn 02 8 ]F -0 '7 1 ~ 1 ~ 1 ~ l -].r20 O.nn -O.nl 0 00 n.nn 8-?A -0 '3 -0 '8
- F A.]n ' -0 AD ?6 8-?R 0.40
-).rn -0 '1 O.nn -0 AD 0 '420 0 '0 Q.nn AD 3Q ) F n.nn 00 1 QO 8-2C A.?s Q.r n -0.60 -0 '6 0 '0 ~ O.RO 01 0 0 '70] n.sn 00 -0 1 ~ 0 '500 11 8 3A 8-38 8-3C 2 '0 '0 ~ 1 ~ ~ -].AO ?,9R -AD 91 -n,80 2 8 4A '2 2 2,4? -n.60 2.25 -0 F 00 8 48 n.nn ] 1.4? F 11 n.60 0 6] 0 '0 0 '5 8-4C 8-40 1+OS ~ -]020. OQ ) ~5 -3 ' 0 F 90 10 1 ~ -1.5 5 0 '5 100 ' 3sn -1 ~ 5 9A 9R 2 '9 n,s +4'6 0 '9) 1 ~ +5]2R.66 +Sn,]?02 4' +42 ' 10 ~ 0 1 ~ 0 1] 0 '066 F+60 ~ 4 )3 3 6+60 ~ 4533 6+6).3?2 F.+4 64-H I 0 '40 F+82os60 'F+82 ~ 560 6+8) 324 F+7 64-I I 0 0~0 0 0 ~ 0 n n.o n 67 ] n.n 0 ~ 0 0~0 68 230 ' -2 69 1 18 ~ 5 70" 1 2400 ]on .70 ?. '9C,684+)3~ 1700 ) ~0 1 ~ l,n 0 70 3 70 4 70 5 '?.389 1 ' 70-6 ] IE.r 39 1 ~ 0 70 7 ~ 8? ~ 6 ?n-8 70-9 ] ) ~ 55 an +?Onion +?00 ', 578.0 )AD 0 0 '2 0 '0068 ?A<<ln 7]-A ? 3 7)-B ~ Ri.9 s?R.n ?A.o 3 ' 1 095 0 ~ 0) 07 73 P ~ n.000453 2?50.n 2.3 73-R 0 '-0 1 A.n 0.?-n.nnn)770 A.s-o.Ann~3]0 0 '-0 6-0 '002655 74 ] 0 0003R40 0 0007080 74-? 0 '-0 '009?35 ~ n.8-0.nnl?390 ~ ~ n,n-n.nn]s930 74-3 A t .n-~.rn?I? . l-n,no4>14',:-O.AAC4aao l.9-n.n 17?S75 ?e?-0 '176IIS I ~ I-0 no?" ~ 1,4-o,on< ~98s I 7-0 ~ Oll"?80 ~ >oo-0 F 017."?30 ?,3 .0 IOI77AOII I.?-o nn344Is I F8 0 2 '-0 ~ I.'~-0.'no~6375 F 0154875 F 0175230 74 74>>8 74-6 74-7 74-8 75 0 77 0 I ~ 0 0 ~ A?6 79 ~ 58 9? I ~ 07 I. ~ 17 i+22 1~?3 80 I ?? I 17 I ~ 10 ~ 99 ~ 84 ~ 47 80 ?. A ~ 01?4 0 ~ O'105 0.111 0 ~ 301 I ~ 13 F 00 82 .OOA22 .nn148 ~ 00137 .AA?84 ~ 00096 ~ 00034 83 I ~ 7 I2 A 5774 6 '43E-02 6 ~ 2148-03 4 '39E-04 4 '10E-05 84-1 5 ~ 344E-A6 5 ~ 7?6 E-07 I 036E-07 2 959I'-08 7 '85E 'ln 84-2 0 00299 A.n0825 0 ~ AI%50 O.A1935 0 ~ 01165 0 ~ 00645 85-1 0 '0231 0 '0164 0 ~ 00085 O.onn43 0.00057 85-2 CII I I NT lL I T 1 C< 5FP V Ice. CCNTFP F.003 FXE'CIST lVF. RONLFVS Rn XXXX XXXX 'XXXXXXX XXXXxXXXX XXXXXXXXXXX xZXX XXXXXXX XxxXXxxxxxxxxx POCKVlLLF ~ Nn ~ 20852 XXXX XXXX XrrXXXXXXXXXX XXXXXXXXXXXXXXX < 3011 ~br -AO1n XXXX XXXX XXXX xxxr XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXXXXXXXXX XXXX XXXX XXXX XXXXXXXXXXX XXXX XXXX XXXX XXXXXXXXXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX CCCCCCr. nnnnnnn XXXX XXXX XXXX XXXX C n n XXXX XXXX XXXX XXXX C CCCCC 000DDD 0 XXXX XXXX XXXX XXXX XXXX XXXX C C n 0 XXXX XXXX XXXX XXXX XXXX XXXX I C 0 n 0 XXXX XXXX XXXX XXXX XXXX XXXX II c ccccrc Dnnrnn 0 XXXXXXXXXXXXXXX XXXXXXXXXXXXX XXXXXXXXXXXXXXX C C 0 0 XXXXXXXXXXXXX XXXXXXXXXXX XXXXXXXXXXXXX CCCCCCC Dnnonnn CONTROL 0 A T A C 0 R P 0 R A T I 0 N XXXXXXXXXXX XXXXXXXXX XXXXXXXXXXX I aeoeaeoeoeeooaeooaaoeeoaoeeeeaooaeaooeoeoooo oeeoaeaaeooo<<a>>oooo>>>>so>>ooooeeaoooooooaoaooo eo oo ea oo ae aa ee DYNODKP 2 es eo oe ea oa ee oa eo VFRSTON = 2.OOO eo a>> oa <<o as ai 4 oo ooeoeooooeooooeeaooeaoeoooeoeaoeoaoeceaooaoa oeoiaoeea&aoeeeaeeoooeoaeeeeeaoaeoeoooos>>oooo DlbW -i' 5 ~O Ch I LD W Ch v . Vl CO NNCLEAR ASSOCIATES DYNOOE I P VERSION 2 VERSION OATE I 4-19 78) ~ ~ TEST CASE FOR DYNODF-P/7 WITH DYNAHIC FLOW MODFL STEADY STATE DYNODE-I<<P INPUT VALVES I s Cr<<TPOI. VARI ARLf5 <<I AFA I'Fcav <<FAT PPFCUPSA >c ACTIVITY TIISFATTow - IK TOH'l 0 II~ GEOMFTAY DESCRIPTION WU<<RFR Of fUEL REGIONS wu<<AFA nF AxlaL sEGHEwTs - H - ws l,oono 5 12 Mn ~ nF I Fg AYEO IIFIJTAOtl CPS ~ -IT 6 LFWGTH OF AXIAL SEGMFWT SEGL FT PLOT OPT Tntt IPI.T n ItINFA RADIUS OF FIJEL CLAD AIN ~ 4747. CI4 ttUMPfA nf nFL AWn LP DATA SFTS-NOTT<< OVTFA RADIUS OF FUEL CLAD-ROUT ~ 5359 CM NIIMAFP cnr F. CAL T I ME STEPS/OEL IN TS-NOK IN I o 1 FLOW AREA PER PIN - AF ~ 12440E-02 FT<<2 RK<<ERSotl ACC<<PACT-ACC<<AC .lonnnnF.-05 WEIGHT nF FUEL PELLET - WP 7 '634 GH/CH OF LENGTH TI<<E LIMTT FOP co<<r LFTF FUN-TT l.nooo SFC DENSITY Of CLADDING - RHC 6 '041 GH/CC I c<<awwEL EoulvaLENT DIAMFTER-DE ~ 44970E-01 FT HEATED EOIJIVALENT DIAMETER DEH 0 FT 7 THE STFP atlD PAIFIT INTEPVAL SETS ~ I ENOT )It I I ) DFI. Iw I I ) DELL'P I I ) OELHX T I ) NOSTH(I) SFC SFC SEC SE C MSL STP I 0.0000 F 001 0 .1000 1000 10 IIIFUEL<<FAT TPA>ISFFR DATA MEAT CAPACITv CURVE - ACP 24686E+00 WT SEC/GM C IV ~ SYSTE<<DESCRIPTION INTT COPE ltlLET ENTHALPY ENI 548 '500 BT<</LRH FIJET HEAT r.-nt r I TY c<<PVE>> ACP 0 ~ ~ wT SEC/GM-C4o2 INITIAL LOOP I FLO'WRATE - ul 2 I 12'450 LPM/PIN-HP F<<FL Cot'I'IJCT I V I T Y Cn<<ST ANTS A 42+0170 'wT/Ctl INITIAL LOOP 2 FLOWRATE' W2 1056 ~ 3670 LRM/PIN-HA F<<EI Co<<nlll T I V I I Y CONSTANTS 8 ?22.Anon C F<<FL Cn<<n<<CT lvl TY CONSTANTS-C ~ 39635E-)2 WT/C<< C Kaa3 fOR LF = I THE FLOII RATE IS INPUT IN LBH/PTN-HR CLAn HEAT CAPACITY - CPC ~ 3301 WT-SEC/C)M-C SYSTEH PRFSSURE - PRO 2250 F 0000 PSIA cLan cownllc7 lv TTY - Kc '1746 wT/CM C Cntln<<CTANCf OF <<n? CLAn GAP-HG ~ 6246 WT/CM"O?-C INIT BORON CONCENTATN-ROACON 800 ~ 0000 PPH LTNFAA Tft P COFFF OF HG AMG 0 ~ wT/CMOBS? C ottan&c TFMP COEFF OF MG AHG 0 ~ wT/CH++2 C cl.ao To rnnl at T cot;nucTawcE-Hf 3 '662 IIT/CHO~2<<C CHF FACTC'P CHFFR l,noon V~ PhYSICAL COIISTANTS VI ~ VOID/OIJALITY CONSTANTS PowfP 47 I'TME 7EPo Pn ?71.1360 'WT /CC SLIP CALCIJLATION OPTION-OPTSLP 0 cntlvFAslnN cnNsTANT - na - ~ 3?393F-lo WT-SEC/F I SS ION CONSTANT SLIP VALUE - S).IP lo6000 PROMPT WFIITPnw L'I FFTIME - AL ~ 27000E-04 SEC CONSTANT TERM - Ccl 0 ~ 0000 FFF ~ OFI.AY IIEIJTPott FRACTION-RT ~ 72looF.-n2 LINEAR COEFFICIENT - CC2 0 ~ 0000 FAST ttfllTAONS/FISSIO I - NU 2 '600 OUAORATIC COEfFICIENT - CC3 0 ~ 0000 TOT I AX ( I ) /PT) ~tli)-), 1= 1 6-ALPIIA 1<<4600 CUBIC COEFFICIENT - CC4 0 ~ 0000 FtlT<<ALPY PE'CTTV'TTY FO, AK ~ 67730E-oa LB/RTU EIITHALPY-PfaCTIVTTY Fo~ - BK 0~ (LA/RTU)oa2 FNTHALOY-pfACT lvl TY Fo. - cK 0 ~ (D nnPPLFA COEFFICIENT FO ~ DKl 0 ~ 5 4 M nonnF 0? ~e ~e oo>pLEA cnEfFIcTFNT Eo OK2 ~ 1 nopp~LEA cnEFFlcTENT Eo ~ DK3 )0000E+01 POAnt, RFAcTIvITY coEFF DKRc ~ ~ ~ 1 ) 630E-03 I/PPM ~O Ch I Ch '4 Vl NIJMREA of FNTAIES IN AEACTTVITY VS DFNSITY TABLE (NERO) = 0 CO WIJMHER OF ENTRIES Iw RFACTIVITY VS FUFL TEMP TABLE INOTF) = 0 0 VII PRIMARY COOLANT SYSTFH VOLUHFS voLUHE No. vnLUHE tlA!'E vn LURE - FTO+3/PIN 1 IIPPQ PLFNt) ~ 48<34F-0) 2 Hni 1.EG l 1 ~ 6)446E-02 3 S" 1 HOT PN ~ 84489F-02 4 STH Gf N L 1 ~ 42)sof-01 5 sr,l cLn ptt ~ 84489f.-02 6 rLn LEG Ll ~ 25o)OF 01 7 nkcn<R L 1 ~ 1 64 60F.-O) 8 HnT LFG L? ~ 30723F 02 9 Sr,? HnT PN ~ 4??44F. 02 10 STH GEN L2 21075f -01 11 SG? CLO PN ~ 4??45E-02 13 tLO LEG L2 ~ 1?950E-01 14 nNCOHR L2 ~ 82300E-02 15 LnWR PLEIN ~ 26338f 01 r.nPF. ~ 14930E-01 SU~MARY OF PCS VOLItwE INPl)T DATA pcs l.nops ~ 2362) 0)F. 00 FT3/P lb cnRE )493000f-0) FT3/PIN PPESS ~ 4058<40F. 0) FT3/PIN TOTAL ~ 2917295f + 00 FT3/P IN CJl I CO PRESS))RIZER OATA PPFSSllRIZER STEAM VOL o VPSPR ,0253 F7++3/PIN PRESSUPIZER LIO))IO VOL ~ - VPLPR ~ 0153 FT+O3/PIN INITIAL PRESS 'wTP LEVEL-WTRLVL 12 '686 FF.ET RFLIFF VALVF. K/AOO2 - RVKA2 ~ ll?52E+14 {PIN/FT2) 2 PRESS PFLIEF VALVE OPEtt-PRELF1 23SO ~ 0000 PSIA RFLIEF VALVE FULL OPEN -PRFLF2 235) F 0000 PSIE SAFETY VALVE K/a+o2 SVKA? ~ 31595 E + 13 t P IN/FT2) 2 PRESS SAFETY VALVE. OPEtt-PSAFT) 2500 '000 PAID SAFETY VALVE FULL OPEN -PSAFT2 2501 0000 PSIA PRESS SETPOINT HEATfRS ON PPHH 2230 F 0000 PS)A Lnk PRFSS PROPS HTR RANGE-PPHL 2200 F 0000 PSIA LFVEL SETPOINT HTRS ON -PWLHON 13 '228 F F.ET LFVFL SFTPOINT HTRS OFF-PWLHOF 7 '012 FFET PRnPORT HEATER RAMP RATE -OPHR ~ 39466E-03 BTlt/SEC-PSI- PIN WAXY HFATER HEAT RATE OPHH ~ 38480E-01 BTU/SEC-PIN Lok PRFSS LEVEL CHRG Ott-PWLCON 12 '500 F F.ET PRESS ct ARGING PaTE - PCR ~ 15690E-03 LA/SFC-PIN CHARGlNG WATER FNTHALPY EHCHR ~ 47950E+03 ATlt/LB ~ 80000E+03 PPH CHARGINr, AnRON CONCENTO BNCHR HI PRESS LFVEL LETON ON-P'WLLON 13 F 0000 FFET Cl tb 8 LFVEL fOR HAX LTON RATE PWLLHR Hax pRFss LETonwN RaTE - pLOHR 13.0380 FEET 19420E-03 LR/SEC"PIN ~ 4ll '4 pREss sETpoINT spRAY oN-ppspoN ~ 2275 F 0000 PSIA ~O ChI Ch PRESS fOR HAX SPRAY RATE-PPSPMR ?325 F 0000 PSIA v 4 HAX PRESS SPRAY RATE - PSRH ~ 19670E 02 LB/SEC PIN Ol CO t PPF SS)IPIZFR 'WATER RFLIfF TABLE INPUT NUHAEP. OF OATA PAIRS - NOWTRR ) I h t RF{. IF VALVF ARFA ARF{,F <<67zoonf-o6 FT2/pltt SAFE ALVE AREA - ASAFT ,I?7300E-05 FT2/1>IP n]sc GE COFFFICIfttT - l:IsccF ;p5snoof.no COPVF RFFEP>tCf FNTHALPY-HWTRRF Byu/L]t '73600'nf+03 SLOPE rLOW 'IS Et)T>{ALPY -{)OWPOH -tt nnnnof-n2 1/{BTU/LB) PPF SSI)PE Pass FLnw RATF. {PSIA) {LP/FT?-SEC) I .17snnonF n4 ~ ASS?QQQE<<04 2 .200noaoF. 04 .V?4 ]nnnE.(4 3 .Zsnvnnnf n4 .Rnnonoof r>4 4 .2833nonF+n4 ,]o552onf ns 5 .32innnnF<<04 ~ 1537900f+r>S 6 .4nnooonF+n4 ~ ?117200F.+05 7 ~ 5000000F+04 ~ 2703400F.+05 8 .60onnonF+o4 ~ 3?41400f+05 9 .TnnonooF+n4 ~ 3648300E+05 ~AFFTY INJFCTION SYSTrN PAPAMETFPS tlUM{IFP OF OATA POlttTS-PPFSS)FLO))-NOSIN 13 L(>W PPE SS ACTI)ATION S I GttAL S ILP)730 ~ 00 PS I A LOW LFVEL Acvttav]ntt slGNAL - SILL 5.se FEET ACTI)a T 10 "t T 1>>F, S lntlAL S I T IH 0~ Sf C ACTUATION TI>> E Of LAY - 5ITO .]SQQOF +02 SEC SAFETY INJFCTION ENTHALPY-Ft{SINJ ]oooof+03 BTU/LB SAFETY INJFCT Intl ROPON Ctt-HORS ltt ~ 20000f <<05 PPN I-;AFETY INJFCT ~ LINF. WTR t<<ASS-S IL)>AS 0 ~ LB/PIN SAFETY INJFCT LINE RORON CONC ~ -SILBRN 0 ~ PPH rsfaS nr T]hatt - IFSFAS = n. SIGNAL ON EITHER PRESSURE OR LEVEL I PRFSSttP{'{ I ) FLOW{1) {PSIA) (LB/SfC-P IN) 1 n.noooon 374700E-02 2on.oonoon .3435nof-o? 3 39n.nooono .31?2noF.-o2 56n.oonnoo .?8]nnnF-o2 v]s.noonno .2498nof-0? 85~ ~ QGQOQQ ~ 2]8600E 0?. 7 97s,oooo(>n ]87300f 02 ]Qvs.onnoon .]sr lnoE-0? o t]60.nononn .]?490oE-02 10 ]235 000000 F ~ 936700f-03 ]283.OOOOnO .6?45oof-o3 12 133o.ooonoo .312200E-03 13 ]360 ~ nonnoo 0 ~ STEAN GENERATOR DATA u-Tl)ttf STEA) GFt>fRATnRS - ISGUOT = 0 STFAN I ENFPATOP Sf CONOARY SIOF OPT Intt-ISGOPT 1 Svfat -GFNERATOR 1 STEAN GENERATOR 2 lt>ITIDI.17ATION OPT In>t-IFI GT 1 >tt>MRER {)F SG IN t @OP-Sr Nltl" ~ ? QonnnoE+ 01 . ]ooononF+n] Svts GFN SFrt)>O VOLUSF-VOLSG ~ 32196r>QE+nn 1609800F+00 FT3/PIN SFCNOPY SIOr. APFA - ARFSG ~ 3384700E-02 ~ ~ 1692400F. 02 FT2/PIN Hf AT TPANAF) P AREA SGA ?774400E+nl ~ 1387200F. +0]FT2/P IN ST>t GFN T{IAF FLOW AREasrF ~ 66(>8800E-03 .33344ooE-n3FT2/PIN INITIAL NIXTUPE HGT - ZHIX ~ 5698900E+02 ~ 5698900E+02 FEET .0 0 I>.'I T . SFC, S'lf F TFt!P 15 ~ '.i16AAAAE+A3 F 5160 00E+A3 F IHI FOkATFR ENTHbl.PY HFO ~ 4 l 540(inF+ A3 ~ 4 1 AF.+03 FI7(t/(.8 STFAi It(F K/Aoa2 SLKA? , ) 4s5)nnF.+ 09 ~ 56., OF+A@ (PIN/F72)2 'f N ~ FPAC I SOVALVF OPEN-F I V ,)noonnnF+(>> ~ 100000OF+Al i tiI T I AL Sri AVF. VOID - AVSG ,506nn(inEtnn ~ 5060000E+00 sjFDH r. t!FRATDR HEAT TPDNsFER oajn. HY')PAUL IC DIAN. TFR - DS(i . 64'OE -A 1 FT T! IRF HF I GHT TIIHFH . 31?68E 02 F T Tl!AE THIC~t:FSS TIIPFOX . < It 67F -A2 FT Fo>>I Itir. FDCTAR - RFOUL pEVE~sF HT Tpatt FAGTAR-RFYFRs 100AAF.+An SEC SI E HYOPAI!LIC OIAHTP-OSGS ~ )4??At. 00 FT I'IIRRLF RISF GRAD IFt!T PDRHTR-Co RAAOOE+00 PFLIEF AND SAFFTY vALvF ODTa REL)EF VALVF.S SAFFTY VALVES t /DRED~~2 - KA2 ~ 27?)AOOE 13 ~ 331040AF. 11 (pjN/FT?)2/sG pEss vaLvFs opFNIt!G-psnl . 105ononE 04 ej)OOOOOE+04 PSIA ppFss vALVFs FIILLopEtt-psG2 .105)nooF+04 ~ 114500AF+04 ps I A Hajtt STFAH SYSTFH f)ATA N!I'l5EP Halt! STFAH LINFS TO TURBINF - I.SS 1 STFAH GEN 5'fEA< FLOW OPTION ISTFLW LOOP 1 LOOP 2 NFPT ",4 (L/A) 5(i OUT HF ADEP X I SL (P jt>/F T) ~ 66480F+06 . 13296E+07 iI i INERTIA (L/a)HFDOF~-HSL - XISIIIPIN/FT) .42?9nE+n6 I Itic RT ja (I./4) <SI.-TIIRRINF X 1ST (P IN/FT) ?5780F+07 CSI STEAN HEA(IFP LINE VOLUHF -VSH (FT3/PI>') ~ 83180F-02 I I>a IN STFAH I It!F V<LUt F VSL (FT3/Plt') ~ 45830E-01 C) S(FDH liEAAFR K/Doo7 SHKD2 (PIN/FT?)? ~ ?6660F+08 HA jt! STEAH I INF. K/4>>2-STKA2(PIt'/FT2) 2 43684F+08 pyc ass capAcj Ty >FR HAIN sTH LINF.-RRpFR ~ 47030E+00 IN'fTIAL FPD(.T Int> <YPass OPE'N FPRPOP n. VAPIDRI.E RYPASS FRACTION FRBPA ~ 10000F+01 PyPDSS FPDCT APFD-TEHP RATE'DASHPOT(1/F) ~ 6900AE-OI ay>ASS FRAT ARF A->>Fs RATF-OiDFPDP (1/PSI) ~ 50000E-02 RYPASS ACT!lATIAN T IHE Slrt(DL - STRP (SFC) 0~ RYPASS V*LVF OPFNING PATF. -VORRP(1/SEC) n. OIIHP ( DPACI TY PFP HA'fN STH LINE'PPFR 0~ INITIAL FPDCTIAt! 0!IHP OPFti - FPOVAP 0 ~ VDAI ".I'.LF OIJHP FRACTION FPOPA 0 ~ ('IIHP FPACT ARED-TEMP RATF - OaflPOT (1/F) n. OUi P FRACT APED-PRES PATF -OAOPDP () /PS I ) n. OI!HP 4(.TUATIOFI Tl<F SIGNAL - STI P(SEC) 0 ~ O(IMP VDLVF OPFtijHr PATF - VOROP (I/SEC) 0~ INITIAI, FPACT CONTROL VALVFS CLOSO-FRCVC 0 ~ VtPI APSE CANTPAI.VAI VF FPACT ION FPCVD ~ 1000AF+01 CntlTAAL VDI \'F CI OSIIPF PATE-VCRCV ( I /SFC) 0 roNTRDL vnLvF c(.s T j>F DFLAY-Tocv (sFc) n. STOP VDLVF. CI OS(!PF PDTF.-VCRSV (I/SFC) .lnoooF+n5 FPDCTIA!i nF STOP VaLVF CLOSURE - FPSV ~ 10000E+Ol STOP V LVF CLOSIIRF. T IHF. DELAY-TOSV(SEC) 0 ~ ICSIV CLASI>PF RATE - VCPATF (1/SEC) ~ 20000E+00 ~ 20000E+00 Hsjv cLos>>RF. TIHF. OFLay-TDHsv (sEc) 0 ~ 0 ~ CANT(tOL SYSTFH DATA Dtl>P~ PYPASS CONTPOI.S Tf HP~SS CONTI'Ol. OPT lntl - IOI'OPT 1 PFF AVf Tft P Dill P cnNTPnl - fARfl ~ 547onooF 03 F PFF STH P>FSS OUH> CONTROL PARD .10?nnoof+o4 ps)a RFF AVE TFHP PYPASS COIITPOI TAR4 ~47nnoof+03 'F tIFF ST> PPFSS RYPASS CONTPOL - PARR ~ 10?OOOOF+04 PSIA TUF RINF VALVE rot:TRnl.S ATnp vAI.vF nvFpspEFO cLosUpf-poospo 1200000E+01 FRc Fp TUWRltIE RU"l4ACK I'IITI AT Iti T ICE-TRPT 0 ~ SF.C TUPP INE RIItIRACK POWFP LF VEL TRRL ~ 7500000E+00 FRC IN STf AH LINL ISOLATION CONTROL SIGNAL OPTION - InPSL I 0 HI-HI STEAI" FLAW - HIHIWS -0 ~ FPAC INITIAL Hl STf AH Fl OW H'IW< 0~ FPAC INI I IAL Lnu copE AvF TEHp - TALD -0, F Lnw SFCO>>OAr Y SIDF. PRESSURE-PSECLO -n.0000 PS)A FFFOWCTfR CONTROL Hill RF P OF WATER LFVFL VS POWFR LfVfL DATA PAIRS - NOI.VSI 3 RATIO INITIAL POWER TO FULL POWER POPFFW ~ 102000E+Ol I4)tl)MUV FFFDWATFP FLO'W AFTER TPIP-WFDHIN 0 ~ FRAG IN Ffl nWATER Ptl:P DOWN TIME - FWR>PT ~ 400000E+0)SEC TI~E DELAY FFfOWATEP PAHP DOWN TOFWIS 0 ~ SEC HAXIMIIH FFFDI ATFR FLOW - hFDMAX ~ 105000f 01 FRAC INIT FLOW MATEP LE If'nt)TPOLIf R PFAD RAND-WTLOP 10 FEET WATER - LEVFL rONTPnl.LEP CotlSTANT-CONLVL ~ ?57200E+00 I /FT-SEC ~ WATER LEVFL I.AG T I "E CntlSTANT - TAIILV2>>,180000E+04 SFC WATER LEVFL LEAD TIVE CONSTANT- TAULVl .200000E+03 SEC POWER LFVFL WATFP LEVFL IF'ULL POW) IFFET) 1 0 ~ 24?)26nftn? ? .2noooooF.on .28)s26of+02 3 . )SOOnOOF.+nl .2815260f+n? cnNTRnL Rnn cnNTROLLFR F:OHTPPL Rnn CONTPOLLFP OPTION IOPCRI 1 ?fpn pnwftt pEFFpFNcE coRf Avf THp-TAvpfz 55) ~ oono F FIILI. Pnwftt PFFFRENCE CORE AVE Tl"P-TAVPFF 578 '900 F >ATIO INITIAL POWFR TO FULI, POVEP-POPFCP ,1000000E 01 l.nW POWER LFVFL Ftnn STOP SIGNAL - PPSTOP , 1500000E+00 FRC FP HAPGItl OVERTt P TRIP FOR POP STOP- DTHPOT 5 ~ 0000 F ~'*>G)tt nvf ppwp TRIp FOR poo sTop DTHpnp 5.onno F rntlTPOLLF> AVE TFIAP DEAD RAND - CRCDB ~ 7500 F cnNTpnl LFp AvF. TF' rnwsTANT - cnHcpc . 1?60oooF.-05 1/F-sEc CONTROL ROD LAG T I'4F CONSTANT TAIICR? 1500000E t 02 SFC CO~IIROL Rnn I fAD TIHE CON TANT - TAIICP) ~ 4000000E<02 SEC CONTROLLEP POWER I FVFL DFAD RAtID CPCPDR 0 ~ FPC fP coNTRGLLFR pnwER LFYFL coNsTANT -cotlcpp 0 ~ 1/(FR FP-SEC) MAX IMUI4 CONTPOLLER PEACT I VI TY RATF. - DKDTHX 1000000E+21 1/SEC POO WITHORAWL IS RLOCKED AFTfR TURBINE RUNBACK tn W I ~ Ih ~O I v Vl tQ CO X ~ TRANSIENT DATA ! PCS (.DDP F(.A)'5 CALC(JLATEO WIT)J tinHOLOCOU5 PUHP HPI)EL RCS CD(.() LFG GFOHETRY OPTION-LCE 0 P(J)4P DPTI(N PAR;t FTER - IPUHP I HO)iOLOGOJJS CURVES i PU<iP HEAO CURVES C(JRVE T YPF I COt)TA iNS 13 DATA PA IRS J CH(l ~ J) HOG (1 i J) I - ~ )AAAOOAE+OI ,355OOAAF+Ol 2 -.6OOOAAAE AO .2T300AAF+OI -.3? AAArtnF.+AO 220000AF+Ol 4 - ~ IR00AAAE+00 ~ .2OAOOOAF+Ol 5 0 ~ .IV30AOAE+OI 6 .2AAOOOAF+00 .15000AAF 01 7 .4eOAAOAF+00 ~ 124000AF+01 .R .5?OAOOAF..AO .123OOOAF Ol 9 ~ 600AAAAEioo .1?4OAAAF+Ol 10 .66nnnnOE+OO ~ I24AAOAF+Ol ll ~ Aoooot)OF+00 ~ I I TOOOAF. +01 I?. .9OAAOAAF. AO . 11OAAOAF+Ol 13 ~ IOOOOOAF~OI ,IOAOOAAF+01 CURVE TYPF ? CDttTA IJJS 11 OATA PAIRS J Gt< (7 ~ J) HOG(? ~ J) I -.IrAOAOAE+Al n. 2 -.IOAAOOOE-Ol 0 ~ 3 A~ -.960OAAAF+OO . I OOOOOAF..OO - ~ 9000000F+00 5 .?OAOAAOF. 00 -.RIAOOAAF+OO .30AAAAAE.OO -.TOnOAOAF.OO V '4OAOOAOF+00 -,54n'OAAAF+OO R .53AOAOAF+00 ~ 300000AF+00 9 . ~ 6500000E+Ao 0 ~ lo .RoonAAAF. 00 ~ 37000AOF+00 11 . IOOAOOOF..AI ~ 1000000E~OI CURVE rYPF. 3 COt.'TWINS 12 OATA PAIRS I J CiH (3e J) HAG(3e J) -.IAAOOOAF Al 0 ~ 2 -.IoooonnE-Al n. 3 0 ~ . 160AAOAF+AO 4 ~ I (i A 0 0 0 i) F + 0 0 -~ l?AOAAOF+00 I 5 .?OAAAOOE OO -iboooAOAF 01 6 .?J nnnOAF+AO 0 ~ .40nnnAOF.OO .90AAAAAF-ol a .600AOOOE.OO .31AOAOAF+An 9 .VOAAOAAF.+AO .42OOOOOF.+AO lO .ROAAAOAE+AO .SOAOAOAF OO 11 ~ RRAOAOOE+00 ~ 54AOAOAF OO 12 IOAOOOOF+OI ~ 5900000F+00 0 CIIP V YDF ri CONTA 'I tiS 14 OATA PA)PS OH (4 ~ J) IIOCi (4 ~ J) 1 -.)onnnooF.A) .355nnnnF. +nl ? -,pnnanooF. oa ,32nnnnnE+ol 3 -.74nannnF+00 ,2800AAAF +01 4 -.hnnnnnnF..no .247noorF+n) -..r hnnnnn.-+nn .22nnnnI'( +01 6 -.?nnononF..AO . Iv30nnnF +nl 7 n, .)4nnnnaF.O) 8 .3VOnOnnF+AO .Ronnnnar.+oo .4 3annrinF..na .vr,nnnnriF'+oo 10 .~nnannnE+on .68nnnnAF no 11 .58000AAE.AO .r4nnnnAF.+00 12 .r,4nnnooF+oo ~ 620AAAAF +00 13 .vononnnE on .6)nnrInnE+OO 14 .)oonnnnE+ol ,59nooonE.nn Ti)PQUE CUP VF S CLIRVE T YPF 1 CO)IT A IGNIS 17 OATA PAIRS J 87 (1 ~ J) TO(i (1 i J) 1 -. loonrnnF.nl ~ 298000AF+01 ? -.8?norinoF.ino .2400AAAF+0) 3 -,hnoonoaF+Aa ~ 187AAOAI+01 4 -.4ennnnnF.+OO .lhoonn(E+nl -.34nonnnF..no .1400nnnF +0 1 ' -.?onnonoF..nn .12) anon'l - ~ Ioonnn(IF+no , 1 1 nnnnnf +O1 0 ~ .10)nOOrF ia) . )nnonnoF no .9hnononF+on 10 .?nnnnnnF.-AA .92onnnnF +on ll .3anonnnF+oo .4noaanoF+00 .90(ionons +oo .89nnnnoF+00 1? 13 .50OOOOOE.OO .9lnnonnF+00 14 .vnnnnnnF.+no .99onoonF+no IS .s nnonnnE+oo . ln2onnnF+ol 16 .900nnnnE.no . 102AOAI'F'+01 17 .)00000AE+0) ~ 10AAOAAF+0) CUPVE TYP E ? COI!TAILS OATA r AIRS J ri7 (2.J) 'TOO(? ~ J) -. loonr'nnE+ol n. 1 ? -. lonoaonF.-nl 0 ~ 8 n. -.87onnnoF+nn 4 . lonnnnnF, no -.v6nononF +no .?nnnnnnE oo -.630onnn( +on 6 .3nnonnnF+oo -.48onnnnF. on 7 .40AAAAAF. no -.31nnnnnF+on 8 .7400nnnE no ~ 400000AF+On 9 . lonnnonE.nl . lonnoanF +Ol CuRVE TYPF. 3 Cni"TAILS OATA PAIRS J Oi7 (3 i J) TOO(3iJ) 1 -.)onnnnn.-.nl 0 ~ 2 -. )nOOnnnF.-OI 0 ~ 3 0 ~ -.loonoaoF nl .?Sr,nnnnE.no -.6ooooonF+nn 5 .4ononnoF+na -.3vonno(iE+on 6 .5000AOOF+00 -.2snnorinF +an 7 .hoooannF nn -.16nnnonF+no .AonoaonE.AO - ~ 100AAA(!E-nl 9 ~ 1000AOOE+Al ~ 1)oaanaf+00 0 e CIIRV YPF 4 CAN'IAINS 10 DATA PAllrS J rr7 l4 ~ Jl TOG I4 e J) 1 -.)nnnnonF. Al .29<<nnnnF+ol 2 -.9)onnooF+no .2anonnnf.o) 3 -.<<OnonnoF r,o .26nnnnAF+OI -.70AAAOAE+An .242nnnAFio) 5 -.6oononnE.no .225nnnAF+Ol 6 - ~ 4200000F+00 ~ 20000AAF+Ql 7 0 ~ .142noonF+O) 8 .6AAAAOAE on .61onoo'rE on 9 .OOOAAAOF+00 .35nnonnE+nn 10 .)OOAAOAEiol . )loonnnF+on MOTOR TORO)IF. r UP v E tlUMRER nf DATA PAIRS-NPMT 6 J AM(J) TMOA l J) 1 -. lnnnonnF..o3 ~ ISAOAAAFinl .9AOOOOOE+on .1500nnnE+nl 3 ~ 9500AAAF+00 .300noonF+01 4 ~ 1 05000 AF+ rr 1 -.300AAOAFio) ~ IIOAAOOE+Ol -. 1500nnAF+ol ~ r I ) .IonononF+o3 -. 150oonnF+01 REVFRSE SPF FD NOT PERMITTED {IRP EO 0) CSI tr'Itlr8ER OF PUMPS IN LOOPS AND INITIAL PUMP STATUSES I LOOo NPPL IPSTAT 1 2 1
- 2. 1 1 r ATEo PUMP PARAMFTFRS FOP A SINGLF. PUIr>
PATED VOl IIMFTRIC FLOP - RATO ?79onnnE 01 GPM/PIN PATED PUMP TORAllE RATT .I<)OOAOE+05 LBF-FT PATED PI,'Ir P SP F fl f R A7 5 .1?566noE.n3 RAD/sEC RATED PIJMP FLUID OFNSITY-RATO,4720nnnE+02 LRH/FT3 PIIMP t "IO IrnTOR INFRTIAS ANO TOPOUF PARAMETERS PIIMP I'rlfRT I A - PINFRT ~ 5nnnonnE'+04 L8M-FT2 r').YlrHFEL ANn MOTOR IIIFRTIA-FINFRT 6SAAOAOE+05 LBM FT2 FRICTION T>ROIIF. COFFFICIFHT-FPICC ~ 1?A200AE+04 LBF-FT F~ICTION TORAUE FXPONENT - FRICE .2nnooonE+01 WINOACE TOPI)UE COFFF I CIENT-)IINOC 0 ~ L8F-FT NINOAGF TOPOUE FXPANFNT - WlhDE 1000000E+Ol l.nop DATA
- l. A OP INFPT I'XINF) Lnss coEF {pnc) CI
( "I ln 3o r-r (PIN/FT) (PIN/FT?) rr 2 1 .9066AAOF n6 ~ 6400000E~08 ~in~ ~ Ch 4 )33GOOF+06 ~ ?560AOOE+09 ~O I 'R VFSSL )3?2AOOE+0'5 . 132400oE+na re K Ch AD .Vl V lO ~ PIIMP TRANS IFIIT SPFCIF I CAT IONS LOOP TRAILS IENT TIME DELAY CO TYPF TDPTR IPTI'CN I SEC) 1 . G 0 ~ ~ I >>n LOOP ] T1> ~ . Af"~~t'oft>T FEFA<ATFR It!PIIT h!F]= 0 t!n LOOP ? T T>>F I'f Rf t>ofhT FF FA!i'ATER It!PI'T - NF?= 0 II Ph'ACT IVITY ". Tft> It<<SI'f 7 Tnt' I K=A) - t>STFP n.nono 4 RAI~P ft4<frvlob ( fK=I ) CRAt>P n.nnnn ~/5fc TATAL VA>>p REACTIVITY - PTOT o,noon f, Oi>TIO>i - ISCRA>> RCRt>'CRnn> ) ni>TTOri Frp InOP SFt SO(> I,OCATInti Taft4FP <<? r" I TA-T Tr]P CAI C!ILt Tfnh OPTIC>ti I RPTY 'ilv I Fr TF>>P 5> >RCR I!FLAY I IMF -TAI YTH-0 ~ SEC ri!Ln I.FG Tf<<P- S<.4SOF PFLAY Tf<<E -TOI YTC-A. Sfc <>snR L<r. T I iif. Cot S-TLAC TC-0 ~ RF.C T f' f f'FLAY AR SCRn>> - TS('RAF! 4<<<<<<444<<oo t!ii 'RFP AF RATA VAIP5 - t TQCR<<? 4 ~ t><ACTCR t>POTFCTT>>> 5YSTF>> PAPA> FTFRS T Tl> IP i!it>CT I r ii TRIP <FT Pnlt'T AEI.AY TTMF (REC) I> f G<<>>EI'TROti t>t>VFR (Ff AC ft IT I AI.) aa . >>MOAF+n] ~ 5onnhf;+Ao I (6>i PVS SSttt>(7FP I VFRSI)i>f (PS t 4) a<<ao .?Wihhi>04 .Tnnnhh +n] I n"" t>t>F SRI>fi f'lfR f'Pfssl!Ri. (p< f 4) <<oaa .)vhrAF+OA . ) OnnhF + n] t>pf SCt>R I 7( t> ( FVFL (f F'f T) <<aoaoaa ~ ]00]lF+fi? .Inhhnf+0] rrfSSI!(>17F n>> RTit.i P f I VI I. (rf F I) aoaaai 4 ~ S5PAOF+0] 'I? IR<>F+ 07 .)nnnnE+o] c I AK-I if>EPATOR~LFVF I (FFFT) .]Onnof +o] Vl' T>>i>+ It!i TRIP - <<I 5 G I EVEL (F ff T) <<a ~ 3> 63i>f ~ 0? .)Annhf+n] f:fn('TAP i.nnt ANT FI.AI< (FRAC f til I) .(vnnnf+oo .60000E+on (Jl lilt:M Pt>"'Ft>/FLnl'Ft>AC ] ti I I f AI. ) 4<<<<44 ~ .]AAAAF+2] 0 ~ ]hi > lr4 rrRF Olivt F I Tft>PFRATI.'IIF (F)*a<<a ] oooni=.+? ) 0 ~ t>>>f >Pr.'if P nf LTA 'I TR 'f P PARAPET FRR to> T>>4( OFLTA I - nprvh i S ~ 4(ihh F >n ~ It AI T Avc, - nt>rTAA <vp.hnhn F PATF/I AG T fi CO><<IST 'i!T f OPATAII )n.nnno 5EC CAST( ":Al>! - nPOT<< ].))hnn i>5TE/I 40 AA f t.' npnTKS n?noo /F Tf PF PAT(!Pf ( 4] t ~ ~ OPATK> .Anhhonnn /F TRIP I>ELnv Tft<F - T(Tf>]t>l))) ?.3nnn 5FC <>>FRTF>"Pf'PATlipf o>FTF('S
- .n>nfh I. I FI T>' ( TATA r.i-.c>onn f t t>>>la AI. T 4>>G - nTATAA 57h ~ nohA F I rAO I 1<<F Cn'USTA !T OTATAII] ?A.nnnr SFc T l>>E Cn'>sTAMT - ATf>TAI>2 3.oonn sfc t> ~ Slr Cnfn - rTI T<] ].nn>5nn T>>>p" P<T<<t>F i>AT>'TATK?
r.Alii - nrrTK3 .n)r.vnnnn .nnhAS300 /psl /f f>i>FSP(iRE >1<<F T t t I. RF FS5 - nT(>TPn 22sn.norm PSIA T>>lt nFLAv Tloif - TrTRIp(1?) ? 30hn SF C S<RA>> Rf ACTI>]ITY Vs T I t-'F TA>lLF T ]i'i (cf C) PFA( I IVT TY . ) Anhhf +(.n n. ~ ?hnnnfino - ~ 17 fhhF-03 .30000<.00 - ~ ?65~OF-03 onnr.nn -,3~ nnF-i 3 AA n'c -.<>]OOc-0? .'Anonym,nn .7nrnnF.-n3 ~ 'I Annftho - ~ 'i7>~OF O3 ~ >AOAAF+OA ~ )?'1<OF n? .~Armor.no - ~ )~43OF-n? .)nnorr+A) v)?4nf'-r? ~ ])Onnr~o) ~ ?ANRAF n? .1?OnnF+nl ~ 34/ ]SE ~ 13OAAF+A) -.433'.gf-n? ~ 1 4 A OAF+ A ] -.<3+FRf -0? .)=nonF+nl - 6637%F-A? ~ .]~none nl -.A4A6AF-A? .jznons .Ol - ))32>E-0] ~ .]Annnr+n] - ~ )64&OF<<A] .)cnnnF+o] AD )7?58F.-A] .?AnnnF+ol -.17'5?3F-O] .?1nooF+o) -.]7<?3f-A] .??Anne.o) )76]2F-n] .? lnoof ~n] -, ] /70OE-Ol KI>>FTICS O~TIO>> SELECTED - IPn~~ n ~ ~ INPUT ARPAYS ACADIA( PEAKING FACTAR - PPAO = I.QQOQOQO FPACTION PDWFR GFNEPATEO IN COOLAI')T FW ~ 0260000 RELATIVE FlUX (AXF IK) ~ K=) ~ NS) INPUT VALIIFS NORMALIZED ) ~ +Ann ~ 5810 ? 9?OO ~ 9215 3 l. 07no 1 0718 4 1 1700 1 ~ 1720 i ) ~ ??00 1 '220 h I ?300 ~ 1 2321 7 1.??00 1 ?220 8 1 F 1700 1~1720 9 1 ~ loon I ~ 1018 10 ~ 9900 ~ 9917 ll 12 ~ 8400 F 4700 ~ 8414 ~ 4708 RADIAL HEAT GENERATION PPOFILE IN FUEL ROO I RAOI I) ).onnono i.nonnno l.nnonno 4 1 ~ nonnno 1 ~ 000000 OF,LAY NFUTRON DATA DECAY I 1 rsFc) FI SSION YIELOS IAX {I)~ I =) s IT) I AX II)~l=l ~ IT) 1 . 0124on 1 ~ 000220 ? .03nsnn 2 ~ 0014AO 3 .liinnn ~ 001370 4 ~ 301000 4 ~ 002840 5 1 .13nono ~ 000960 6 3 .oonooo ~ 000340 nFCAY FIFAT PPECURSOR DATA OECAY CDNSTAIT l)rSEC) ENFRGY FRACTION I ALOII) AAnll) 1 ~ 1772QOF ni ~ ?99nnnF.-02 2 ~ 577annF+nn .825nnoE-02 3 ~ 6743QQF-nl .)isnonF-ni .h?14onE-n2 ~ )93~00E-n) 5 4734QQE-Q3 . 1)6<nnE -n I 6 .4A)nnnF-n4 .645nnnF-0? I .~344QOF-ns .231QOQF -n2 8 ~ 87?hooF. 0> . 16 4n On f. -n 2 9 ~ 103600E-08 ~ A5Qnopf 03 ~ \ 10 ~~ ,7~5OOOF-n7 ,75RSOOF-OO r ,430nnnf -O3 ,~TOOOOE-n3 ooaoooaaooooaoooaoaaooaaaooaooooaaoaaoaoooaaoaoaao PUMP INITIALI?ATIONPAPAMFTFPS RATED PUMP MFA'4545??E 03 FFFT PUMP SPEED VOLUHITPIC FLO< FLOW IPnn/SFC) (GPH/P I II) (LH/HR-P IN) ~ )?31469E+03 ~ ? 8)442) E Ol ?1 12745Eo 04 ~ 1?35460F+03 ~ 28)4407F+ 01 ~ 1056367E+04 aooaaooaoaooooooaaooaoaaooaaaooooaoaooooooooooooao NUMBER OF ITFRATIONS FOR INITIALIZATIONOF FUEL AND CLAD TEHPS ~ NUMBFR OF ITEPATIONS FOR INITIALIZATIONOF FUEL AND CLAD TEHPS ~ NUMRFR OF ITFRATIONS FOR INITIALIZATIONOF PRIHARY AND SECONDARY SYSTEM VARIABLES 2 STEAM GENFRATOR HEAT TPANSFER AREA FACTORS aaoooo ARI= 1+0000 AR2= I F 0000 U-TUBE SG RURRLE RISE FACTORS aooao FRU81= ~ 23274Eool FBUB2< ~ 23273E+OI TEST CASE FOP IIYtIODE-P/2 HI TH DYNAMIC FLOIt HODFL STEADY STATE OOORO>> 7 IMF= 0 ~ nnn SiEC PPFSSIiPE= 7?Sn ~ 00 PS)A FLOW"- 3) f 9 ~ 11 LB/HP PIN INTEGRATED ENERGY= 0 ~ )IT SEC/CC 0 y O A fi T IMF STFP tlin4AEP= 0 TIMF STEP SIZE-OFI.= ~ ) 00 00E-07 SEC pnIFp- ABSOLI'TF= ~ ?7114F 03 VT/CC PFI ATIVE= 10000E+01 DFP I VAT I VE>> 0~ WT/CC SEC REAI TIVITY- TI>E I'lST= 193169E 02 $ OOPPI FP= ~ 90171) F 00 $ ENTHALPY= ~ 551087E+0) $ BORON= el29043E+02 $ Cot TROLLF~= n. $ I EFFECTIVE= l.nnnooon . POHER I)ELAND= .loonnoF+ol FPC IN FISS) ON POIIER= ?7) )3f F 03 VT/CC DECAY HEAT"- ~ 189768E+02 I:T/CC CAPE COMP>>TAT ION T I HE STFP = 0 ~ SEC AND NUMPFR 0 PCS TIME STEP DOUBLED FROM I.AST PRINT = 0 RCS TIME STEP HALVED FROM LAST PRINT = 0 COPF. TIMF STFP DOUBLED FROM LAST PRINT = 0 CORE TIME STEP HALVED FROM LAST PRINT "- 0 Ox)OE At!0 CI.ADO ltIGi TE'MPFPATURES IF) IC) ) )4SO 978S 788 '214 ? 1?99 'l305 704 '058 3 1153.6780 623 )S45 4 10)9.60?2 548 f 679 895.n302 479.4612 AVCi 1163 ~ 7439 628 '022 I 1 639 '814 337 '341 620 '750 I ? 3?7.0417 ~ Vl AVG 630 0282 332.2379 1 F>>THALPY IBTU/LR) FLUx IRTIt/t<P-FT+>2) ADNRMIlIRTU/HR FT+ o2) PNBR MASS ILBM/PIN) 1 .55067AF n3 1 F 10?199E+nh .)ononoE+o7 1 0 ~ 1 ~ 581019F.-01 7 ~ S55405F,+03 2 ~ )6?)09E+06 2 . )onnooF.+07 ? 0 ~ ~ 577994F-0) 3 F 56)676Fin3 3 .)PA540E+06 3 .)nnoooF+07 3 0 ~ 3 ~ 57369?F.-ol ~ 56&73SFi03 4 ~ ?nf lf )Fioh .)OnnnOF+O7 4 0~ .568t)ebF-0) 5 ~ 57f 7hhF+03 5 ~ 2) 497)E+ oh 5 .)nnnnoE+07 5 0~ 5 .563hhTF-nl 6 58 )987F+03 6 ~ 716733E+n6 6 .)nnnnoF+07 6 0~ 6 ~ 5582)AF, 01 7 ~ 5<)70AF+03 7 .?)4<7)E+06 7 . lnnnonE+07 7 0~ 7 .552hhf,E-O) 8 .S99239F+03 8 ~ 206)61E+06 8 . )nnoonF+o7 8 0~ 8 ~ 54 7151E-01 9 ~ 60639')F+03 ~ 193826E+06 9 100000E+07 9 0~ 9 ~ 5418)9E"Ol 10 .6)2979F+03 ln 174444E+06 lo . )onnooE+07 10 0 ~ 10 .53683nF-ol ll ~ 6)8746F.+03 l) ~ 148013E+of 828 1 f 7E+ 05i
- 1) ~ )00000E+07 ll 0 ~ 11 ~ 532397E 01 1? F 62?A74F+03 1? ~ 12 ~ 100000E+07 12 0 ~ 12 ~ 529187E-0 1 A VCi ~ 5873RnF+03 AVG ~ 175912E+ob TOTAL ~ 666343E+00 PRF'CURSOR Cnt>CFNTRATION I 1/CC)
) ~ 3653?F+ 17 2 999)hF 12 3 7<4)4F+)2 tn ~ ~ 194?AF+')2 M 4 ~ 7493Fi) S<w Ao Ao 5 f ~ ) 1 ? 33 3fiF+ 1 0 ~ ~. CA ~O R ~ v Ol 4 CO e TFST Chsf fPP OYt!AC'f.-P/?. <)TH OYND>>IC. Fl 0" HOOF L, - STED()Y ST4TE iiOhma o.nno sfr II AAP PDPD!FTI PS ; Vnl. I t~f DVF FtiTHDI,PY i hSc SPF ('AI ltNF pnpnN CNc T f >>f kn Ttlkf ( I> Tl!/I.rt) (L! /PIH) (F T3/I.P) ( P P ll ) (F) i I!PPR Pl fNtii ~ f?44F+03 ~ ?ot.hf +01 ~ 735ff-01 . Annnf +n3 ~ f Of 4F+03 HAT I.rr. I I f?44f+03 .?f.nf f +nn ~ 7356F.-A] .Anrnf+na ~ f.A64f+03 I sr.) iinT pN ~ 6744F+A3 .3S>>hf .nn ~ 23c<F-0] .Iinnnf+03- . f nhnf+n3 4 FT>> r:fti ~ Safff+03 ~ ) Achf + 0) ~ 7236f. n), .ttnpnf+n~ ~ )79?F.+tl3 I cr) rl A PN ~ c4t 9E.+03 ~ 3054E+OA ~ 2)37F.-A] .Rnonfin3 .Ssn?E+n3 BASSA?F+03 r.t n I.fr. LI ~ c4pnF+03 ~ ]7'I?I +01 ~ 7137F.-A) .itonnf+01 ~ SSO?F.+03 7 ni;rni p l.] .cnpnF+n3 ~ 770'lf 00 .?]37f n) .Aonof.+n3 V, eAT I fr- I 7 ~ 6744F+03 .13hr f+nn ~ 23sff 0] .Hnnnf+n", ~ fofnf+03 n sr.? I-PT pit ~ 6744E~03 .17A3F+nn ~ 23c6F-0] .hnnOF+03 ~ w064F+03 10 c T>> CI'il I.? ~ sp6wf+03 ~ 9474f+00 ~ 7736f ti] .t)onnf+na ~ 57ri2E+03 I) S62 cl n pt! 1977E + n(i ~ 2137F-Ci) .Rnn( F+03 ~ SSO?F+03 CI.A I r l.?4 .f n6ne+nn SDRQF+03'S4I 13 9F+03 ~ 7137f-n] .(Inoof+Aq ~ SSO?F+03 14 niirni p L?. .cntinf n3 .34c) f.nn ~ ?) 37f 01 .Rnnnf+nq f ~ 55 (i? + 03 ) c L(il'4 Pl f ~ c4}44f+03 .]23?f+n) ~ 7) 37F.-A] Annnf+A3 ~ SSCi? f+03 o5&66f+03 .6663E nn 7?4)E-01 .Annnf+ns NN'ALF ~ ~ 5792F. + 03 t nnp DRAFTYFI.AMS r tiA Plt'~P SPFFAS ~ Hf DOS ~ Dt!O Tnt nllfS lnnp fl.nw SPEFO Hfnn NF T T nit OIIF Ptt>>P (I.P/HR-P Tt ) (QDO/Sf (') (FFF 7) (LAF-FT) 1 ~ 711?74Sf 04 ~ 123S4f nf in3 ?79H254f'+03 -.330047RE+0? 2 .)nc6367F.nn ~ .123S469F, i 3 ~ ~ ??9477OF+08 - ~ 3304)5)F+A? 4 Vl c I"!JFi Y Tnti Fl.nk= n ~ I Ii/Sf. C-P IN I @D-C) CHh rl '" FLAh= A. LP/SFC-Plh LFTOAtrti FLOI.'= 0. Lh/SFC-P IN rnPE vhnlhPLf s cnpf >>nss= .666w4F nn I.p/pit! cnpe FLnk= .3]6<)f n4 Lp/Hp-RIN Cnp~ l>>I,FT F'O'Tt hL PY= ~ c464sf. +03 RTtt/Lfi CAPF AI!TLFT f NTHDLPY= ~ 67436E+03 PTI!/LA rnpf nVE OrriSITY= ~ Ii4f3)f~02 LP/FT3 CARE DVE Ft!THDLPY= ~ SI!664F+ 03 l)TU/LP CARE COOL itfDT T>f NS 0~ Pllt/c IN Cnpf 1>>LET TFHp (F) "- 5sn,?) CORF OIITLf 'I TE'
>P (F) = 578 ~ 29 VFSSe I. Oi L Th I (F ) = 56 DCTI!DL OFLTh-T(F) nvfpanttfR SFTpnINT(F) AVERTE tpFRDTIIRE SFTPAINT(F) Sf<<SEr Dvf Tf>p (F) I.nnp ] 56 '57 f2 '34 6].n39 5>it ~ ?h7 I nnp- 56 ~ 157 62.n30 61 ~ 039 <74 2I.'7 ( ApF. hfdf <nt Att CAhli.FtiT RATIO"t= I'.Ao Anno PPH COALntiT OIPFCT FNFPGY OEPASITION ' 4 III/P IN PPF SS!iP17FP VDP'IDRLFS rPPcS STED i PDSS= .)6A3i!4e.inn LA/alN PPFSs LTA>>DSS= .fi6693?F+AO LO/PIN cTI. h!< FNTVDLPY= ) ) 174) F+04 PTI!/L ft Lint!TO Et(THD( I Y= .7n344f f+03 IiTII/L4 CTC t N VilLli>>F = .? 76440F-n] FT3/pl>>." L IOIIIO VAL!!>>f, "-,1'3?SOOF.-O] FTAIP It! cT<h'> TNT<<NDL FNFpCY PrhCS I ln I FVEI = .)?Pnnhf+0? FFE7 =,]f 475(i?F 03 pTII/PTN L IO!) IO INTERflnl. FNFRAY = ~ 3974?4] E+03 St!!I(if LINF FI.AS'= 0 ~ LH/SEC-PIN* ei Tlt/P Tb CI pf(.IF C vnt >>f FLnh= 0 ~ I I /Sf C-P] ti sAFETY vnLvF. Fl ctti= 0 I P/Sf C PIN sapnY Fl nu= 0 LA/SEC-PTN ! FDTFR khTF= AD AT(I/SFC-I IN l.p/p]w I(ITFL'RDTFo s>>RGF Ll<<f ENERGY= n. 1tiTE rphTFA S>>R( F I.1NF FLAN= 0 ~ ~ 6S<R7) F+03 LTA!JIO TffiPFRDTIIRF= ~ fi5f 47)F+03 f I'Tlt/P TN =~O~ Ql STc ntt Tr tiPFRDT!!PE = pp<SS I IA, bnpOt! Cnttrf t TRDT inn= F ~ Aoonf +(3 pat ~ N ClhtI V Vl SDTIIPDT lot! PPAPFRTIFS Hr,= 11]7 ~ A)4 IF= 703.446 Vr=..lc75?43 Vf= .n?7n314 TSnT= 6Sf.A7n9 OO 0 I e TEST CASE FOR DYNODE"P/? WITH DYI<AHIC FLO)t HODEL. STpD$ STATE DDDDD 7 IIIF= O ~ Onn SEC ST EAH GENERATAR VAPIARLES STEAH Gf I"ER4TOR STEAN GFNERATOR 2 HEAT I nat) (PTtIISFC-PIN) 44 3) 7(!6Ev 02 ~ 221559)E+02 sFC<n sfoF ppEssUDF(pSID) ~ 7h53>>3)Ei03 ~ 78S3933F+A3 sfrNR SIDF TF>>r FI>DTIIRE(F) .5)60AAAF.+n3 .5)6nnonFin3 (I >DPFD tBTII/>>R F P ftt) ~ 2759379E+04 ~ 1379683E+04 FFFOWDTER FflffiaLPY(PTII/LR) ~ 4154AAGE 03 .4154onoE o3 FEFOWt TER Ft.nw (t.>l/HP-f>IN) ~ 2033A?8Ev03 ~ 1016909F+03 Dltx Ft>>'TR FLnW (LR/t>R-P IN) 0 ~ 0~ S Tf 4'4 L IMF Ft.nw (LR/HI>-P it)) ~ ?0338?8E+03 .1016909Ein3 DFLIFF VAI VF FLAW(LR/t>R-P) 0 ~ 0 ~ SAFETY VALvF FLnl'(LR/fit>-P) 0 ~ C~ SsfrNA sIOF waTFP LFYFL(FT) ~ ?8)5757F+0? ~ 2815757E+n2 >> I X TIIPE HF IRHT (FFF T) .5( 98~noE n2 .5698900F.+n2 STFD>> FIIR>ILF ><4SS (t.>l>'/P I at) ~ )678)48E+on ~ 839098(IF.-A) AVE HIXTUPF AVOID EPACT)Of> .Sol nnnoE+nn ~ 5060000E+00 PIII>RLF It I'SF VFLOCI TY (FT/5) .46?&443Ein) .4628442E+nl TATL SAT L ln I4ASS(LR>>IP It() ~ 457764?E+AI ~ 2288889E+Al TATDL STFA>'DSS ((.Rf>/PIN) .3(I973?2E.AO ~ 1948638E+00 ~ INT LnaO R( c Sr, (RTII/PIN) 0 ~ 0~ TAT FIITHA(.PY-HFGT(RTU/P IN) ~ 2789094E'+04 ~ ) 394578F. + 04 'ftl7 Loan SC'-HSL (>IT(I/PIN) 0, 0 ~ ItIT >4455 FLOW (LRH/PIN) 0 ~ 0 ~ FL(>ID PROPERTIES 5AT L I 0 E>>THALPY (RTII/LR) 507)> )SEvn3 ~ 5071416E+03 AT Lfn SPFC VAL (FT3/LR) ,?Op)S9sE-0) ~ 2081596Evo) SAT ST>> ENTHDLPY (RTU/LB) ~ 11997S)E+04 ~ 119975)E+04 SDT STH SPFC VOL (FT3/LR) ~ 5816096E+00 ~ 5816094E+00 >vA IN ST Fat4 SYSTF>> VAR I DR(,FS STFA I IDIF >IF DOE 0 PPF SSURf.'"PSH (VSI 4) 7562658?E+03 STEal> LftIF PDFSSURF-PSL (PSIA) ~ 74387037E+03 TIIIIRIHE-THPnTTI.F PI>FSSII>>F.-PTHP tPSIA) 72307033F+03 STF 49 t. ftIF Hf AC)FP F(.AW WSH(t 8/HP Ptl) ~ 30507365F+03 STFDI> TUDF INF Ft.nw-t>>STP (t. f /HR-PIN) ~ 30507365f.v03 5 fFAH RYpa<5 FLO'w 'WSR (LP/HP PIN) 0 ~ STFA>~ nl)HP FLnw - WSO (LP/HR-Pltt) Oi HFDAER STFDH MASS XH5H (LB/PIN) .)379f>264E-OI MAIN STFDH I fNE'ASS XHSL (LB/PIN) v 74715282E-01 HFAOFP ENTHALPY HSH (PTV/LB) ~ 11999226E+04 HAIN STEDH LINE Fr(THALPY-I:SL(BTU/(.)I) 12001554E+04 M CD W wg ~O Ql I ~W v Ch Vl lD (X> TEST CASF. FOP AYNODE-P/? WITH DYNA)IIC FLOW MODEL STEADY STATE %%Ra s- 7 ItlF= 0 ~ nnn SFC ll".5 TOTAL FttTHALP IFS ~ ENFRGIES ~ AND MASSES ENTHhi PY FMEPGY PASS / r 8 TII p IN ) I ci Tlt/> I "ll {LR</PIN) LnAPS ~ 6) 58697F+04 ~ 606 03?7E+04 1061545E+02 COIt E .300~055F+03 .3846rI79E+n3 .6663426E+nn PPFSS ~ 578085QF+03 ~ 56118?3E+03 ~ 7273165E+00 TATAL .7)?7r88F O4 .7OO6197E 04 .120O911E+02 RAPAN >>ASS AISTPIIIUTIAN AND TATA) IN RCS ILR</Pltl) LOOP TOTAL= ~ 8492361E-02 CORE'OTAL= ~ 5330741E-03 PRES TOTAL= ~ 4535459E 03 RCS TOTAL= ~ 947898IE-02 ENFPGY INTA LOOPS = n. EtlEPGY OUT OF LOOPS ~ 0 ~ FtJFPGY INTA CA)IE = 0 ~ ENERGY OUT OF COPE = 0 ~ S I I P Ci E F NE It Ci Y ANA MASS r:nPF. H,M = 0 ~ 0 ~ LAAP H,tt = n. 0 ~ CAPE INTGS 0 ~ n. L:)OP It!TGS 0 ~ 0~ INTEI)PALS I tIASS ANO FNFRGY) FOR PCS PASS ENFRGY I LRM/P I N) (BTU/PIN) P>>FSS RELIFF VALVFS 0 ~ 0 ~ PitCSS SAFFTY VALVES n. 0 ~ PPFSS SPRAY SYSTF>> 0 ~ n. PPFSS HEATFRS 0 ~ PCS CHARGIt'8 SYSTFN n. 0 ~ PC.S LF.TDAW>> SVSTF.tl 0 ~ 0 ~ HriSI SYSTF.I~ n. oi Et>FRGY DEPOSITED IN AII IAF = 0 ~ BTU/PIN TOTAL STORED ENERGY IN FUEL ROD = ~ 4289191E+03 BTU/PIN FtlFPGY STAIIFA Itt OXIDE "- ~ 3804372F+03 8TU/PIN ENERGY STARED IN CLAD > ~ 4848190E+02 BTU/PIN L'IAP FLOW AtlA PUMP SPFEA PARAI ETEfIS REACTOR VFSSFL PRFSSURE DROP .23r6504E+0? PSI LAAP PrtFSSIIPF CHANGES TARAUES (PSI) rLBF FT) PIIHP R I SF. I AAP APOP MOTOR HYAPAULIC WINDAGE FRICTION 746tt664Ein2 74S0653F+02 19271 18E+ 05 -.1814?27E+n5 -o.. 1161914E+04 1 2 .7468716E 0? ~ .7450600F+02 ~ ~ 1927118E+05 -.1814231E+n5 -0. - ~ 1161914E+04 e 0 TFST CAS FOR DYNODE p/7 wITK DYNAHIC FLOW HODEL STEADY STATF o- TIFF= I ~ nn<< SFC TIHF STFP H<<H&f P"- PRESSUPF= 25 2?49 '9 PSIA TI>E STEP 517F.-DFL"- FLOW= 3171,?2 La/HP PIN iv3000E-AI 6 sEc IN RATED ENEPGY= NTE GRA ~ 27112E+03 'lT-SEC/CC POWER ARSAL<<TF.'= 7711AE>>03 WT/CC RFLATIVE= 99<&SF. Oo DFRIVATIVE= ~ 35359E-.01 WT/CC<<SEC pFA(".7 IVITY T I <F'.<CT= 193) 6~F Oi.' DOPPLFR= ~ 901686F 00 '%NTHAI PY= ~ 551068E+0 068E+Ol S5 E<ORON= E< R ~ 129046E>>02 $ C<'NTROL<.F>= 0 ~ . % YEFFECTIVF= ~ 9999991 pnvFR n;~AND= . )nnnnoF+ol Fpc IN FISSIO>> PnvFR= .271096E>>03 WT/CC DECAY HEAT= ~ 189766E+02 WT/CC cnRE cn~P<<TATInN TIHE STEP= . lovo?aF.-ol SE'c AND NUHRFR 138 PCS TIHF STEP DOURLED FROH LAST PRINT RCS TIHE STEP HALVED FROH LAST PRINT = 0 CO<<F TIHF SZFP DOUBLED FPOH LAST PRINT = 7 COBE TINE STEP HALVED FROH LAST PRINT = 2 7&ate OXIDE AND CLADDING TFHPERAT<<PES <F) tr.) 1 1450 <<f 61 3145, ? 1?99 ~ 9153 704 3974 3 1153.6599 623 1444 4 10)9.5813 548 6563 5 895 '071 479 '484 AVG 1163+82S9 628 '922 1 639 '5?4 337 '180 670 64S4 327 '2SP .vr. 33P,??16 PO Ff<THALPY<HTU/LR) FLUX<RT<</<
>>>2) ODHBNl< (8TU/HR-FT>>>>2) DNPR HASS (L8H/PIN) ~ 550677F+A3 1 107P03F+06 17f 41?F+07 I ,177606Fin2 I .Salo?nF-ol i 2 3 4 ~ 55540)F .561f 6pF+03 ~ S6A7 7. A3 'F + n 3 4 .lf?115E+06 .1<<P547E+06 ~ 206169E+06 3, 2 4 ~ 172574E 07 1675?3F+07 161893E+07 2 3 4 ~ ~ )06449F+A2 88R474Ftn) .785?28Fin) 2 3 4 ~ ~ 577896F-01 573697E-01 .568894E-ol 5 .57625AF+03 5 .?)4~79F+06 5 155950E+07 5 .7254nSE+Al 5 .563678E-ol 6 ~ 5&3967F+03 6 ~ 2)f 741F+06 6 )49928E+07 6 .691723F.+Ol 6 .5582:42E-Al-7 ~ 5<<)6<<4F+03 7 ~ 71 4979E+ 06 7 143612E+07 7 e 66801 IF+01 I ~ SS?683F Ol 8 ~ 599?)?F+03 8 .?nf169E n6 8 e136318F+07 8 ~ 661)8)g+Al 8 ~ 547171F-Ol 9 6nf 36PF 03 9 )<<3834F+06 9 ~ 1?9955E+07 9 ~ 670429E+nl 9 s54184?F"Al 10 ~ 61?946F+03 10 1744~0E+06 10 ~ 122887F+07 10 7044 09F>>ol 10 ~ 536855E-01 11 17 .61871)F+n3 .62?83AF. n3 ll 17 1480)PE~06 ~ A?P198E+05 ll 12 )15653E+07 .91606SE+06 ll 12 ~ .781323F+nl ~ 110607E+02 11 .53?424E-ol 12>>529215E-Ol AVG ~ 58737AF>>03 AVG 175919E+06 TOTAL ~ 666361E+00 pRFcUpson rnNcFNTpATIDN I 1/cc) ~ 3653?F>>12 WAIL 2 ~ <<9<< I SF+ I P (M tn W 4, 3 S ~PS414F+) 2 19427F+17. ~ 1749?F+11 ~ Ul~ Cl ~ 0K Ch <C< 6 ~ 23334F>>ln CJI tQ CQ 0 'h e TEST Sf. f AP, AYNAOF-P/? 4IT>t l)YNAh'Ir FI.A>'nnf I - E> STF*DY STATE oaceo- 7lt>n= ).Ann Sf ( I Ann Panb>>FIMPS vnl ><<>F avf F t>THDLP v t>ASS Sl E r vnt.u>!F <<Anne> rvr., TE'!PI RATI)RF (>'Tl>/I,s>>) tl >>/Pth') IFT>>/I <<) (noN) IF) 1 >IPoo PI Ft>8 ~ 4 p 4 3 F. + 0 3 .2n> Of +ol . ?3~6F -n) ~ >> )OAF+A.>> ~ (044F+03 >tAT I rr- I. 1 ~f P44f+o3 .>gn>>f +oo ~ ?38nC h] AAAOE~A3 40> 4F+03 Qo] > (IT PN f-24 4F t 0 t ..>S>>at . Ar. ~ ?3Sf F-0] .>>An(;F+ni ~ 6064F+03 O'I>> fit N L 1 .S>>et E+03 ~ ) At'QF +('] .?236F-n) .AnnrF+O3 ~ ~(Q?F+03 Snl rt n PN c>4>>QE~A3 ~ 3QNlj, f y on .P]37F'-nl .>tnt>nftn3 . ssopf+ n3 r.l r> I rr- L) ~ S4,l<>E+03 ]P]PF +ol ~ p]37F-0] .>>nooftn~ .SSO?ftn3 7 ANCA>'o ~ S44>>fcn3 ~ 77r'>f nn ~ P]37F A) .>>AAAF.A~ ~ SSOPF.+03 >-nT t.r(; Lo ~ f paaf +03 ,130> 1+no ~ ?3<nf-n] .AnnOF+n3 ~ t>044f+03 Q S02 >>AT P'. ~ ~ 6p4 4 E + A.>> ~ ]TQ>f +no . Pi<<.f-nl ~ AAOAF.+Aq ~ 4nf4F+03 ] t> ET>> OFN I.P .Sf>FOF+n3 ~ 94?af +On ~ P?3> F A 1 .-!AOnF+A3 ,57QPF+03 ll )3 r.l.n rl n lr rN LPA .c48QE n3 ~ c 4(>of+03 ~ ] tt77f + A A f nchnf +On .P]37F.-A) ~ ? 137F-0 1 .>>9OOE+n3 .>Innofin3 ~ SSOPF+03 SRA?E+03 ~ ~ ]4 n>:rn> p ~ S4 (< 9 F. +0 3 34<) f +no ~ ?]37F.-ol .AO(nf..n3 ~ 55A?F+03 I. AnP Pl. FNH c 4FQF+03 ~ l?3?F+nl ~ ?137F. 01 .OonnF+n3 5502F+03 rnnf ~ Q866fcO3 ~ 6464F+(>0 ~ P?4)E-nl .>>OOAF+n3 ~ 579?E+03 LAAP FLA'>>9 Ah>A PU"n SPFFOS ~ HEAI)S A>>n Tnt>nuc S I nno +I r>> QPFF() >if an h ET TAPA>>F CJl PJ (L>>/>>P-PI>') (RAA/SEC) (Ff E'T I (LAF fT) 1 .P) 14067F'+At .1?35469E.+n3 .?296323F+03 28S?5))Eon? )AS7)S?E A4 , 1?3S469f'+A3 ~ P?QSQ7?F+03 ?76851 ]F + np. Q.AFFTY I>!,)Fr 7Inh'I.AI = 0. I.8/SF C-P IN C>ta>tri'I>AS Ft,nv 0 ~ Ll'/SEC-Pl>l LETOO)>>>> FI.AN= 0 ~ LR/SF'C-o IN rncf VA8148LFs CARF > ASS= ~ f4636F. AO Li IOIN ('('PE FLOM= .3171?F+04 LP/>!R-OIN It>LE T Ft T>>ALOY= ~ >4885F+03 I'Tl>/LR COPF OI>TI FT fNTI>ALPY= ~ 6243?f +03 RTU/LR cnpF AvF AF>-s]Tv= .446'>2F+0? 18/F T3 CAPE, AVE ENT>>ALov= 5446PE+03 RTI>/LR CARF. COOL >EAT TPah>S 64743?E+02 RTU/Pill ms F. I>>LFT TFPr (F)= SSA.?] CORE nuTI FT TE'~P(F)= 6nf.36 VESSFI. AVE Tf'cP(F) = 578.P9 VESStL DFI TA T(F) = ArTI>AI. t.FI.TA-TIF) AVEPPO)IEP SETPOlh>T (F) AVFRTF'FRAT>lsf. SFTPOINT(F) SFh'SFO AVE TFI>P (F) ( t>A~' Sc ~ ] 4A 6? ~ 034 6] >A?5 ~74 '91 I. Anne Sn ]44 6P 03) 6]oo]F s7>),?93 rnnf 4VF OnnnN ('0 >> FNTPAT IAN= t'Oo ~ AAAO PP!4 rnnl.aNT nloFCT ENFnnv l)FPASITION .17?8o)E+01 >>>TURPIN > nc'sz>>n(7FP Vat>IA<l>.FS > n>'SS STF..<<>>AQS= .] 0384F+An I.I:/( IN Pt>f SS l ]A>>ASS= ~ Sf f Q?3F'+nn LR/PIN STFac> FNT'al,oY= ~ 11178lf 04 PTI>/I P L I A>I]t) Fh>74ALPY= 703446f 03 nT>> /LH QTF AN VOL<<>IF =,?S?6449<-O] FT3/PI> L loll]O 'VALI>h'F. = ]53>4QAF-0] fT3/P IN QTc'4>> Ic>>TFR>>AI Fh'Fi>rv = .) F87".O',Ein3 oTU/PIN Llnllln INTF oh>41 F.'>nttrv = ~ 39?4176E+A3 RTU/PIN ooFQS I IC.'.FVFI,"- .]?>>f>PSF np. Ff ET Sl>rF L]ttf F(.A>'= - 230"67f-na LP/QEC-Pt>l 2 cJ 0> ~ ol I \EF Val.yn Fl A)t= 0 ~ I,</Sf r. PIN Sf FETY VALVF. Fl 0'>t= 0 ~ L8/SE'C-PIN t (>-> QO> AY Fl.n"= O ~ Lt /SEC PI>' 'lh>TFrnaT<(> 5>IRGF Llh>f FI Alt= ~ 936475< -0 i LP/PIN EATFR RATE= 0 ~ l>TI>/SFC-P]N TNTEORATFD Sl>IIGF LINF FNE ROY>c ~ 66157HE-02 bTU/Plhl ~ >>s 4 T F 4 I T E" o F n 4 T U8 F. = > ~ 6 S 48 7 0 F + 0 3 F L I AllI D T f"'P fR A T I >P F. = ~ 656 87 0 E + 0 3 F ~ ~O Ch oPFSS IIA AOPAN <<l>>CFNTRAT ION=,(>nnnf 03 PP>t U CJ> Qt>T>)RATIO>> PROOFRTIES CO Hn>> 1117 P)5 NF= 703 ~ 445 v(.= . 1875?54 vF= .027n314 TsaT= 656.8703 CO II TEST CASF. FOP DYNODf-P/2 W 1TH DYNAHIC FLOW HODfl. STEADY STATE TIHF:= ].Ann SFC STF. AH GfNE'RATOQ VARtARLES S I fAH CFIIFQATOR I STFAH CFNFRATOR 2 HF n T I.OAR ( RT<</SEC-P I II) ,4c,3?n3nf+n? ~ 2?]6]37E+02 SFCrrn 51 [if QQESSIIQF. (PS I A) ~ 7853906F+03 ~ 78539?RE+03 sf cN[t 5 I OF TFMAFP ATrlRF. (F ) .5]59cr)6E+n3 ~ 5159999F.+03 IroAQE A IRTUIBP-F PIN) ~ 27595RFF.+A4 ~ ]379806E+04 FFrOWATFQ FNTIrbl PY IRTII/LR) .4]54nnnf, n3 .4]54nnnE n3 FFFOWOTFQ FLAW (LR/IIR->Irr) ~ 2033r ? 8F + 03 ~ 1016909E+03 A(IX FowTQ FLOW (Crt/>Q-PIN) 0~ 0~ %YEA> l.lHF FLnw(LR/HP-Pttr) ~ 20339A6E+03 ~ 10170))E+03 QFLIF F VALVF. FLOW (L'8/HP.-P) 0 ~ 0 ~ snFETY vnl.vF F(.ow (I p/Hp-p) 0 ~ 0~ SFC>O SIOF WATFR LFVFL(FT) ~ 2A)5?SOE+A2 ~ 2815250E+02 H[XTIIPF. >FICiHT (FEFT) ~ 5699A59F+02 ~ 5699083fin2 STFAH RUHR( f PASS(Lr)t</PIN) ~ ]67tt?38f+00 ~ 8391536F.-AI AVF. trIXT(rF AVO10 FRACTtON F 50/n]49f+(ro ~ 506017IE+AA R<<RQI.F. RISE VELOCtTY(FT/SI ~ 462847lf+Al ~ 4628466F+Al TOT(. SAT I IO PASS(l RM/PIN) ~ 4577( 33E+A] ~ 2?88883f i 0] TOTAL STE Ar'ASS (I.RH/PIN) ~ 3&973I2E+no ~ ]948638E+00 IttT LOAO PCS-S(i (QTU/PIN) ~ 443]649E+0? ~ 2? 15962F.+A2' TOT F WTHALPY-<<F'CT ( Q TU/P IN) ~ ?789086E+04 1394576f + 04 It'T LAAO sf'"wsL (RT(r/p lw) ~ 44324?9E A? ~ 22]6?51f+02 IWT vn<S FI.PW (LRI1/PIN) ~ )019449F-04 ~ 5495203E-0'5 =Ll(IO PPOPFQTIFS SAT LIA FNTHALPY (ATlt/LR) ~ 507]<I]f+A3 ~ 5071415F+A3 snT Llo spFc voL (FT3/LR) ,?08]~95F.-A] ~ 208]595E-Al snf sTH FNTI ALpY (RT<</LR) ~ 11997S]E+nn ~ ))9975]f~04 SAT STH SPEC VOL (FT3/I.R) ~ 58]6])8E 00 ~ 5816098F+00 >A IW STFAH SYSTf< VAR IAPI.F 5 STEO~ Ltt(F HEADER f QESSUQF-PSH(PS]A) ~ 756?5844f+03 STFAH L INF QQESSUQF PSL (Ps I c ) .743an88]E+03 Trt>r)Iaaf THr(OTTLF PQFSSUQF-PTHR (PSIA) ~ 72307033E+03 . TFA> I. INF HFoof P FLAM-PSH (LR/HP-Ptr) ~ 305]AOATEi03 STEn'I TIIRRINF. Fl OW-WSTP (I.R/HP-f'Irr) .3oso3666E+n3 STEh> RYPASS FI.OW ii~58 (LP/HR P]h) 0 sTFA ~ nuwp FLow - wso (Lp/HR-pit ) o Hf AC.E R -SI F nr4 HASS - x HSII (L R/V I ~ ) ~ ) 3[to]382E 01 '<Dirt STFA," LINE -wnSS-XtrSL (Le/PIN) ~ 7474] 1] lE 01 HFAOER c".WTHALPY - HSH (RT(r/L8) ~ 11997509E+04 >AIW STEAH Llt:f. ENTHALPY HSL(&TU/LII) ~ 11998925E+04 fD W C M ~rir N ~ Ch ~o re% Ol I v Ul LD On TEST CASE FOR DYNODE-P/2 WITH DYNAHlC FLOW HODEL STEAPY STAff aaaaa 7INF.= ] onnn SEC RCS TOTAL FHTHALP I ES i FNERGIFS AND I'ASSES Ft)THALPY FNEPCY HASS (BTII/7 ] lt) (RTU/PIN) (LBM/P IN) Li)OPS ~ 6]5&702F+04 ~ 6060332E+04 1061544E+02 rnPE 39nnn3nF+03 . 846JIh4F+O3 ~ 6663607F+00 JiPF SS ~ 57&074?F 03 561]757F.+03 ~ 7273072E+00 TOTAL 7]27ht]5E+04 ~ 7006]<4E+04 ,]2009))E<02 IIORON MASS DISTRIBUTION AND TOTAL IN RCS (LBM/PIN) LOOP TOTAL= ~ 8497354F.-O? CORE TOTAL= ~ 5330886E 03 PRES TOTAL= ~ 4535384E-03 RCS TOTAL~ ~ 947898]E"02 Ft'FRGY INTO LOOPS = ~ 549JI862Ev0~ ENFRGY OUT OF LOOPS > ~ 4833992F+03 FI.FRGY INTo corF = .4834007E+03 FNERGY OUT OF CORE = ~ 5498878E+03 SIJRCE EtIERGY Atto HhSS COPE H AH - ~ 5S>2997E 03 - ~ 7851355F-06 LOOP H,H = - ~ 46+50')2E 03 - ~ 667434 1E-06 COJiE IMTGS ~ ]?S4836E-01 - ~ ]8]3335E-04 I.noP INTGS ~ 593?SJIOE-02 ~ 876(I606F.-05 I g I>>TFGrcLS (MASS AND FNFRGY) FOR RCS MASS ENERGY (LBH/PIN) (BTU/PIN) PPFSS PFL IFF VAI.VFS 0 ~ 0~ PPF+S SAFFTY VALVFS 0 ~ 0 ~ PRESS SPRAY SYSTF> 0 ~ 0~ PRFSS HEATFnS 0 ~ PCS CHARGING.SYSTEM 0 ~ 0 ~ RCS LETOOVN SYSTEH 0 ~ 0 ~ >>PS I SYSTFJi 0 ~ 0 ~ FtlE JIGY J)EPDSITFD I>> OXIDE = ~ 6473408E 02 PTU/PIN TOTAL STORED ENERGY IN FUEL ROD -"~ 4289]07Ea03 BTU/PIN FIJERGY STORED ltt OX IOE = ~ 380431?F+ 03 PTIJ/PIN FNERGY STORED IN CLAD = ~ 4847953E+02 BTU/PIN LOOP FLOW AND PUH> SPFED PARAMETERS PFACTDP VESSEL PRESSIJRE DROP ~ 2369658E+02 PSI LnOP JiPFSSltiIF. CHANGES TDPOIJES (PS I ) (LBF-FT) pt>>ip plsF Loo( Drop tiDTOR HYDRAULIC WINDAGE FRICTION .7c,i?373F n2 .7460]t?E n2 ~ ]+27))BE+05 -.]8]3779Fan5 -O. ~ ))6]9]4E+04 ? ,7<i]7]f.a O? .746]33SE n2 ~ ]927))tifi05 ]8]3605Fin5 -0 ~ ~ ))6]9]4Ev04 T )ref C) P fLA7)vf r>ref P ppf55(r.c)A) ICEFFE.CT TVF. AyF F (A/)if?) RVF FUEL <F) HAx FUEL(F) s8 Lnon<nis) 0> .)AAAAOAF+0) ,225nnorE+r4 .)nnonnof n) 2lF+06 ~ ))r3844E+A4 ~ )450979fin4 i6646797E<02 .')Ann ,nO ~ )normo)F.+0) ;??Snnnnf+04 , loonnnof+nl .175 )92F+06 ~ ))63844Ft04 ~ )450979E+04 ~ 664703?E+02 ~2AAAOI}0 ~ )OOAAAAE+01 t? 2 5 0 ni 0 0> F. + 04 , ) nonnnnf io) o)759)97F+06 ))63844E>04 ~ 1450979E+ 04 ~ 6647?38F.+02 ~ 30000F+00 ~ 9999705if+nn ,??snonnF+n4 ,99999cef..nn 1759?47F+O6 ,1163843F+n4 ~ 1450979E+ 04 ~ 6647425E+02 4A{loAF+00 ~ CC9C437fvnn .2250AAAF+n4 ~ 9999998fvno ~ )759?)7Fin6 ~ 1 1 6384 )F. + 04 ~ 1450978E+04 ~ 6647584f.t02 .Snnnnf.oo ~ 999928&Eton ,??499cr>Eqn4 ~ 99999cSE+Ao -1759243E+O6 ~ ))63840E+04 ~ )450977F+04 ~ 6647734fi02 ~ 6AQAAF+00 ~ 999C)9AFvon ~ ?2499cPF.+04 ~ 999c995E+00 ~ )7S92)7F+06 ~ )163837E+04 ~ 145i0976E+04 6647853E+02 ~ 7OAQOF.+00 c998887Fvon ~ ?249996E+04 ~ 9999993E'+no ~ )759230ft06 ~ ) l63835E+04 ~ 1450974E+04 .664795?E+02 .8nonoF+oo C99r)r)nee+00 ~ 22499c>>E+04 ~ 999999?E+00 ~ )759705F+06 ~ 116383?E+04 .)450972fvn4 ~ 6648037E+02 ~ 9noninE+QQ ~ 999>)87?E+00 .2249993E+04 ~ 999999)F+00 .17592)nE+o6 ~ 1163829E+04 ~ )450969E+04 ~ 6648103E+02 ~ 10000E+Ql ~ 9998513E+00 ~ 22499~ )E+ 04 ~ 999999) f+00 ~ 1 759 1 87E'+ 06 ~ 1163826E+04 ~ 145Q966E+04 ~ 6648167E+02 Vl I TIME~) cnRE FLnw]) iM-p) COPF IN )l(R/L) PLF iSFTY f'LOW P WT~VL IFT) 0, ~ 314~11>F+04 54pplinr +Ag ]?~OF+ n? ,]nnnnF+on ~ 318946] F + 04 ;5444~AAE+n3 f} ~ i)?RfHAAF+0?
- ?nnnnE.OA ,3]70797F+04 .54445AAE+n3 n, ;1?4'484iE~n?
.3nnnnEioo ~ 3] f067]F.i04 .54P45AAEin3 n, ]28li460F>02 ~ 4AAAAF+00 ]170757F+04 ,544450AF.~A3 n, ,]248850Fin2 ,5AAAAEino ~ 31708AAF+A4 ~ Si4845nnf t fl3 n. ~ ]2444I 4F+02 .i nnnrF+nO ,'3]7non]F o4 3]7]048F 04 .s484snnE+n3 ~ 54885nng+03 0 ~ .]288&56F+02 ]288855f+07 .70nnoE Oo ~ 0 ~ .4nnnnF+00 ~ 3]7))']OF+04 ~ 548850AE+03 0 ~ ]286853F+02 ~ QAOOOE+00 .317] 18nF+n4 .s48asnnE+n3 0 ~ ]288 85]F+02 ~ ]AOOOF.+Ol ~ 3]7]2]9E+04 ~ 548850AE+03 n. .]286848E+02 MA>]NUN TRANSIENT POWER AND PRESSURE'ELATIVF. Pn>ER (FRACT ~ INITIAL)= ~ 10000E+Ol AT e 1 ] 300E+00 SEC PRESSURE OPSIA)= ~ 225AOE+04 AT 0~ SEC
SUMMARY
OF TRIP SICiNALS GFNFRATED OURING TRANSIENT Cl1 I 0>
NAI 76-67 Revision 0 July 19, 1976
6.0 REFERENCES
- 1. R. C. Kern, "DYNODE-P: A Reactor Core Transient Simulator for Pressurized Water Reactors," NAI 76-37, March 15, 1976.
- 2. L. J. Agee, "Functional Fits of Steam Table Data," EPRI Memorandum, April 6, 1976.
- 3. J. A. Redfield and S. G. Margolis, "TOPS - A Fortran Program for the Transient Thermodynamics of Pressurizers," WAPD-TM-545, December 1965.
- 4. H. G. Hargrove, MARVEL - A Digital Computer Code for Transient Analysis of a Multiloop PWR System," WCAP-7909, October 1972.
- 5. K. V. Moore and W. H. Rettig, "RELAP4 - A Computer Program for Transient Thermal-Hydraulic Analysis," ANCR-1127 Rev. 1, March 1975.
- 6. J. F. Wilson, et.al. "The Velocity of Rising Steam in a Bubbling Two-Phase Mixture," ANS Trans. Vol:. 5, 1962, p 151.
- 7. ORD Program Number 9060, F. D. Hammerling, Program Author.
- 8. H. R. Martens, "Comparative Study of Digital Integration Methods,"
Simulation, February 1969, pp 87-94. 6-1
NAI 76-67 Revision 0 Ju1y 19, 1976 APPENDIX A NOMENCL'ATURE
~I NAI 76-67 Revision 4 September 26, 1977 '~Smbo 1 Heat transfer area Valve flow area flow Coolant flow area AA Conversion factor AR Steam generator heat transfer factor ARESG Cross sectional area of steam generator shell side AXF Axial heat flux profile Boron concentration Homologous hydraulic pump torque Heat capacity Delay neutron precursor density Controller constant Torque coefficient C Bubble rise gradient parameter 0 Equivalent hydraulic diameter f(r) Radial heat generation profile f(z) Axial heat flux profile Fraction Conversion factor Mass flux Enthalpy Homologous pump head Pump head Clad coolant heat transfer coefficient A-.l
NAI 76-67 Revision 4 September 26, 1977 '~Smbol HG Oxide-clad gap heat transfer coefficient Inertia 14 Conversion factor Conductivity eff Effective multiplication factor ak Change in reactivity Pressure drop coefficient a, L Length sL Axial Coolant node length Coolant mass Fission power density Torque exponential factor Number of steam generators Number of RCS pumps ) 4 Pressure Normalized core power density Decay heat precursor concentration Heat generation or removal rate Volumetric flow rate Radial coordinate Heat generation fraction RL Prompt neutron lifetime SGA Steam generator heat transfer area Time Temperature A-2
NAI 76-67 Revision 4 September 26, 1977 'Smbol 'H Torque 14 TSCRAM Time at which scram rod motion begins Problem end time hT Rm Log-mean temperature difference Internal energy Effective heat transfer coefficient Total integral energy Vel oci ty Volume Mass flow rate WBREAK Main steam system break flow WF Feedwater flow Wl RCS Loop 1 flow rate W2 RCS Loop 2 flow rate W2B Cold Leg B Loop 2 flow rate Hain steam line flow WSB Bypass valve flow WSD Dump valve flow WSGR STeam generator relief valve flow WSH Steam header pipe flow WSTB Turbine steam flow Core inlet flow rate intercept slope Axial coordinate in coolant channel
NAI 76-67 Revision 4 September 24, 1977 Descri tion Total core power density Void fraction Dimensionless pump speed Effective delay neutron fraction Decay heat fraction Change in variable x Error signal Delay neutron decay constant Decay heat decay constant Neutrons per fission L~ ~ Specific volume Dimensionless volumetric flow rate 14 Heat flux Density Surface tension of saturated water Controller time constant guality Pump speed
NAI 76-67 Revision 4 September 26, l977 Subscri ts BORON Boron Break Main steam system break BUB Bubble Cladding core Core C Core CRC Control rod controller 0 Dump valve DNB Departure from nucleate boiling DOP Doppler ec Evaporation-condensation ev Evaporation ENT Enthalpy EU Equivalent uniform exit Exit conditions f Fuel f Saturated liquid f friction fg Saturated liquid and steam fw Feedwater g Saturated vapor gap Oxide-cladding gap gb Gas bubbles G Mater vapor h hydraulic heater Pressurizer heaters Delay neutron or decay heat precursor group Coolant region 1 RCS loop index inlet Inlet conditions IN Initial Doppler, enthalpy and boron plus insertion J Cladding node K Coolant node Subcooled liquid m Mixture A-5
NAI 76 67 Revision 4 September 26, 1977 Subscri ts motor Oxide node Initial value Pressurizer pump pump ref Reference value R Rated RSI Ramp or step insertion RV Pressurizer relief valves RV Reactor Vessel Fuel rod surface s Steam sat Saturated sc Subcooled spray Pressurizer spray ss Saturated plus superheated sub Subcooled sup Superheated surge Surge line S Scram SG Steam generator SH Steam header SL Steam line SV Pressurizer safety valves thr Turbine, throttle tot Total TB Turbine TC Steam generator tube covery UP Upper plenum Coolant Mater W Windage WG Water-vapor WR Water relief A-6
NAI 76-67 Revision 4 September 26, 1977 Subscri ts Lead Lag Steam Generator outlet plenum Reactor Vessel inlet plenum Su erscri ts ave Average in Inl et out Outlet Absolute temperature
NAI 76-67 Revision 0 November 4, 1976 APPENDIX 8 CONTROL CARDS AND THEIR USE
0 NAI 76-67 Revision 5 April 19, 1978 CONTROL CARDS AND THEIR USE The following set of control cards is used to execute DYNODE-P Version 2 on the CYBERNET 7600. The XXXX items signify user supplied values. for the YYYY items, contact NAI's Production Code Section. XXX,TXXX,STHFZ. ACCHUNT,XXXXXXX-XXX STAGE(A,PRE,HY,VSN=YYYYY) LABEL(A,R,L=YYYYYY) COPYBF(A,OYNQD) UNLOAD(A) REWIND(DYN0D) DYNSD. EQR CARD DATA CARDS EQF CARD EgR The EgR card is a 7-8-9 punch in Column 1) EgF The EgF card is a 6-7-8-9 punch in Column 1)
4 Ir, 1 I}}