ML20209F187

Fort St Vrain Steam Generator Temps During Interruption of Forced Cooling from 105% Power

ML20209F187
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/18/1986
From:	Bagierek A, Cadwallader G, Silady F GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20209F168	List: ML20209F164 ML20209F187
References
908784, TAC-63576, NUDOCS 8704300223
Download: ML20209F187 (70)

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SUMMARY

TITLE FSV STEAM GENERATOR TEMPERATURES SURING QR30 2

APPROVAL LEVEL IOFC FRON 105% POWER h88 0N Ol5CIPUNE SYSTERI 00C. TYPE PROJECT ED ISSUE

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Appendix A 62 N6082 Calc Review Rpt B1 1*

Attachment I ST7942 130 Attachment II ST5364 51 Attachment III ST1356 129 Attachment IV ST2939 52 Total 433 (Cct:puter cutput not distributed)

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1o 908784 N/C TABLE OF CONTENTS Pagg 1.

INTRODUCTION.

3 2.

METHOD AND ASSUMPTIONS....

3 3

RESULTS AND DISCUSSION.

5 4.

RE FERENCES..........

5 TABLES 1.

RATSAM Computer Runs Supporting This Analysis 8

FIGURES 1.

R4TSAM Model of FSV Primary System.................

4 2.

FSV Steam Generator Temperatures - Case 1 (Wet) 6 3

FSV Steam Generator Temperatures - Case 2 (Dry) 7 APPENDIX A.

RATSAM Model Revisions.......................

A-1 B.

Calculation Review Report B-1 1

Page 2

i 908784 N/C 1.

INTRODUCTION A calculation has been performed to determine the bulk temperatures versus time within the active regions of the Fort St. Vrain steam generator modules during an Interruption of Forced Cooling (IOFC) of up to five hours following a reactor scram from 105 percent of rated power.

2.

METHOD AND ASSUMPTIONS The RATSAM computer code (Ref.1) was used to evaluate the primary coolant system transient conditions during an IOFC frca 1055 power. Given an appropriate forcing function, the program calculates the time-dependent pressure, temperature, and flow throughout the primary system, taking into account the convection and conduction heat transfer between coolant, core, and steam generators. Radiation heat transfer is not considered.

The version of the code used was that version stored in the GA Technologies Archive Library as RATSAM6/CNTB (Reference No. SYSD-2.200).

The initial conditions and system geometry were modelled via a series of control volumes, or nodes, and interconnecting flow paths. The model of Ref. 2 was revised for this analysis, to incorporate more detail into the steam generators. The revised model is shown in Fig.1.

The revisi6ns are documented in Appendix A.

The revisions were made so that temperatures within various active regions of the steam generator modules could be determined during the IOFC.

The model is configured to include normal flow paths around the primary system as well as bypass or leakage flow paths. The normal circuit is for primary coolant flow to pass from the top plenum through parallel flow paths down through the core into the bottom plenum, and downward through the steam generator modules. When flow exits the steam generators it passes into a lower plenum that feeds the circulators. The circulators push the primary coolant into the lower cavity around the steam generators, then upward through an annulus around the core, back to the top plenum. Mosc of the flow follows this circuit. However, some of the flow that is pumped through ti.c circulators 4

leaks back into the lower plenum through seals in the top of the lower cavity floor. This is modelled as flow path 18 in Fig. 1.

Also, a flow bypass path is modeled where flow can pass through seals into the bottom plenum from the annulus around the core. This is modelled as path 17.

The transient that was considered was an immediate loss of forced circulation. On the primary side this was modelled by tripping all circulators at time t=0, letting them coast down quickly by assigning them 10%

of their inertia, then breaking them to a stop. The flapper valves were allowed to close, and the resultant natural convection flows through components (nodes) were calculated.

Recirculation flows within a component were not considered.

On the secondary side two different scenarios were analyzed. Case 1 assumes that the secondary side is isolated within eight seconds of the trip.

Steam / water is held in the steam generator and reheater tubes at conditions i

Page 3

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.h 908784 N/C close to normal operating pressure and temperature conditions. That is, j

i 50671he of steam / water are trapped in each loop at 2910 paia in the steaa 1

generator and 210 psia in the reheater, based on FLASH /GA results for case CRH-10G of Ref. 3 This water heats up or cools down during the 10FC i

I transient along with the tube metal. Case 2 assumes that no steam or water remains in the steam generator or reheater tubes. That is, the tubes are dry during the IOFC transient.

3 RESULTS AND DISCUSSION l

The bulk metal / water temperatures versus time in the active regions of j

the steam generator modules are shown in Figs. 2 and 3 for Case 1 (wet steam generator tubes) and Case 2 (dry S/G), respectively. Transient temperatures differ only slightly between Case 1 and Case 2.

With less heat capacity in Case 2, the temperature transient tends to proceed a bit more quickly. Case 2 temperatures decrease or increase a bit sooner than for Case 1.

The computer runs on which these figures are based are attached to this calculation, per Table 1.

Two heat removal mechanisms operate to cause the steam generator temperatures to generally decrease versus time during the IOFC. After the circulators stop and the flapper valves close, the temperature distribution around the primary circuit is such that the hot gases in the core tend to rise, causing the helium flow through the steam generators to reverse, so that a small upflow (~0.5 lba/s) of relatively cool gas passes through the steam generator and cools the metal tubes.

Additional heat is removed from the steam generator module through the shroud to the gas in the lower cavity around the steam generators. The lower cavity gas temperature cools initially to below 600*F, as it equilibrates with the cavity wall temperature. However,

'the cavity gas temperature tends to increase slowly later as the ste'am generators cool to it.

Any liner cooling that may be active in the lower cavity during an IOFC has been neglected for this analysis. Depending on actions taken by operators during the IOFC to reroute liner cooling to the upper core cavity, some liner cooling may be available in the lower cavity to keep the gas temperatures there below 600'F during the transient, so that the j

steam generators could continue to cool to a lower temperature than results l

when liner cooling is neglected.

4.

REFERENCES 1.

R. K. Derener and T. Shih, "RATSAM: A Computer Program to Analyze the Transient Behavior of the HTGR Primary Coolant System During Accidents."

l GA Technologies, Inc., Report GA-A13705, May 1977.

2.

G. J. Cadwallader, " Permanent Loss of Forced Circulation-FSV/105% Power, Conservative Core," Safety Analysis File SA-1304V, June 2,1977.

I 1

3 T. Chan, "FSV High-Energy Steam Pipe Rupture Thermal Hydraulic Analysis l-for Partial Line Breaks," Memo SD&PD:TWC:153:85, January 17, 1986.

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i Page 5

FIGURE 2

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FSV STEAM GENERATOR TEMPERATURES - CASE 1 (WET) 1000

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908784 N/C TABLE 1 RATSAM COMPUTER RUNS SUPPORTING THIS ANALYSIS Run ID Location Case 1. Run 1 ST7942 Feb. 28, 1986 Attachment I Case 1, Run 2 STS364 Mar. 3,1986 Attachment II Case 2 Run 1 ST1356, Mar. 3,1986 Attachment III Case 2. Run 2 ST2939, Mar. 4,1986 Attachment IV.

(

Page 8

908784 N/C APPENDIX A RATSAM MODEL REVISIONS The purpose of this Appendix is to document the input data generated for a revised RATSAM model. The revisions center on creating a mod'sl with six nodes through the steam generator instead of one. The revised model is shown in Fig. A-1.

The original model was documented in Ref.1.

Only the changes are documented here.

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CALCULATION SHEET

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CALCULATIONS FOR 9011/4 A//C EQUIP. NO.

PROJ.

CA LC. N O.

PAGE/ 5[,0'F PREPARED BY pg DATE REF. DOCUMENTS:

CHECKED SY DATE 1

2 CarbWsehr fourart I

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z.

t,J : 4914 rpm 20 I<e 96 05Y bWI^ 21 Actud.$. dO/'bt??!% OlAf~ll9'l&> r,,,2 (3 yy ) ' 2134,m = N GA N5aN tar 23 w = en. a s ci,- (pcanac,s...).] 24 Vor M M Speed baV2. 28 oA id 3 f 4*f A 3 0

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,. m. CALCULATION SHEET s. e4 2 m.v.w, CALCULATIONS FOR 90V7sn'/c EQUIP. NO. PROJ. CA LC. NO. PAGE / 570F PREPARED BY DATE REF. 00CUMENTS: CHECKED 8Y DATE .kt, f Q, Yet<.'s!d far.~5vff A$s46vn $ 4 4 M Ih E.'s w a f.z~.y Gr* & :4 C g lN r ~ J % C l 2 3 6 f>f 7 N % t 3 :-\\?/, f I.,2 ' 2 7 o 3 G A A' ' ?. ;, Ps o, m'=l.l.ftm/.cu., Ass m p:.2iss14,, g. 4 5 6p: y j( s ff' g. A P,oy .r.c (N4). 2'5s i32. :1) &$Ch) bMJ d 1 ,g c (s. t )' tre FM un y' = nug wm = x= n s x an' 12 y,ff,, gjg/7 83 G, = /e 14 15 p 1s 17 18 19 20 21 22 23 24 25 26 27 28 2s 30 31 32 33 34 35 36

9 # W d'/ ' .'a* > = < a v. o n, CALCULATIC N SHEET f.k~51 f///ffff %h$ h$h $h { PROJ. 1 CALC.NO. t i PAGE OF EQUIP. PREPARED SY / OATE REF. DOCUMENTS: ,h N N N N % lE N CHECKED BY DATE 4 o N N g $h h h h b h k 2 N D 3 hbh(s h h [ h a' M qQ h 4 w u x. ~ u g 8 Q t R R R R R 8 x 'A's's q 3 3 3 3 y S h A Ns s t e d b k 5 4 0 i N oNM* h t E h. ? $ N to "200 h hhhh h e 14 y s N g og d N1 w +' yy d. s s x L s t. x n h h ' ' ' 's BS I m o o o o o o i. 77{p N u N 4 g 2a gg g 2' k 4, b t S o g Q h*b N 4 S e k 3 M h 'o Q h k 22 b %' \\3 g kD kk QD k b C dD 23 9 k N $ a$k k t il a $ {e {, s

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CALCULATION SHEET 4/f1tW'/c-o 4 u. m.v. m u

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faf79'htllC-r p A-41 O HELIUM v W V ' IHLET v 3 REHEATER v I ALLOY 800 Ir _ r ' SANICRO 31 ) Cd= SUPERHEATERII @ s j Bi-METALLIC p ~ WELD p o g; x_g SUPERHEATER I p g

• 2 1/4 Cr-1 Mo STEEL g

EVAPORATOR L @l ECONOMlZER Cc= s HELIUM OUTLET r -- Q (typical) i/ o A W hsWo I _= J l.) Main Stea Main Steam ~ Inlet Reheater Outlet Steam i Figure 4-J. Steam Generator Arrangement

• e

l j ouwwav. mem CALCULATION REVIEW REPORT Pegs B-1 APPROVAL LEVEL TITLE: FSV STEAM GENERATOR TEMPERATURES DURING QAL-1 10FC FROM 105% POWER QAL LEVEL 10lSCIPLINE SYSTEM 00C. TYPE PROJECT 00CUMENT NO. ISSUE N01LTR. M 01 CFL 1900 908784 N/C INDEPENDENT REVIEWER: NAME l-Pu m 4W' Sa.felu 4Nb P4/$bihM ORGANIZATION M DATE PMCh_t REVIEWER SELECTION APPROVAL: BR MGR y yw. REVIEW METHOD: YES NO ERROR DETECTED / ARITHMETIC CHECK LOGIC CHECK / ALTERNATE METHOD USED / SPOT CHECK PERFORMED COMPUTER PROGRAM USED [ REMARKS: (ATTACH LIST OF DOCUMENTS USED IN REVIEW) e.uyeds.c \\aUs

• 'e sem s re v s.

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