ML20207K441
| ML20207K441 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/23/1986 |
| From: | Potter R GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML20207K390 | List: |
| References | |
| 909268, 909268-IA, TAC-63576, NUDOCS 8701090422 | |
| Download: ML20207K441 (184) | |
Text
{{#Wiki_filter:CPT Roll 2127 (A) GA 1485 gnty 10/02) M Technologies Inca ISSUE
SUMMARY
TITLE O R&D EES C00LDOWN FROM 39% AND 78% POWER USPIG APPROVAL LEVEL 2 CONDENSATE OR FIREWATER (1.5 HOUR DELAY) O aS gg DISCIPLINE SYSTEM 00C. TYPE PROJECT [ DOCUMENT NO. ISSUE N0/LTR. I 01 CFL 1900 L 909268 A f QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SEISMIC CATEGORY ELECTRICAL CLASSIFICATIJN I i I FSV-I FSV-I N/A l APPROVAL h ISSUE DATE PREPARE 0 ENGINEERING FUNDING APPLICABLE DES RIPTION/ CWBS NO. PROJEg PROJECT N/C DEC 09 m R.C. Potter A.Shenoy . .' A.J. Kennedy Initial Release r* {fyy[a psmg A/t/fL
,pg2970106 L 80 t ' A DEC 3 3195 R.C.P tt z' Release basis N CN-005652
/NN# 2970 106 CONTINUE ON GA FORM 1485-1 NEXTINDENTURED l DOCUMENTS l N6757 See page la for pagination (Computer output not distributed) 8701070422 DR 861230 ADOCK 05000267 PDR REV Codput er out put: not
( evf. sed skows SH cudrer,t revision onr ol$onlyf ( REV l SH 29 30 31 32 33 34 35 36 37 :8 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 j REV l SH 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 20 22 24 25 26 27 18 19 21 23 28 (LUTTENBBR. WOR) 39,30 (SR-7344) PAGE 1 0F5101 I
909268-A ISSUE
SUMMARY
(CONT.) Issue Summary = 2 27 SUPERHEAT Computer Runs = 1083 2-42 = 41 ST2919 (31 pages) Calc. Review Report = 2 ST2060(j0pages) Appendix A = 56 ST4226 (30 pages) Appendix B = 79 ST5508 (31 pages) Appendix C = 3 ST4605 (30 pages) ST3009 (29 pages) 5 RECA Computer Runs = 1248 ST5555 (31 pages) ST9268 (250 pages) ST1713 (30 pages) ST3986 (250 pages) ST8137 (28 pages) ST2204 (249 pages) ST8019 (26 pages) ST1115 (248 pages) ST8674 (30 pages) ST9193 (251 pages) ST1903 (28 pages) ST3962 (28 pages) 5 TAP Computer Runs = 2221 ST7998 (28 pages) ST0260 (443 pages) ST2213 (30 pages) ST4411 (446 pages) ST3564 (28 pages) ST0823 (447 pages) ST4745 (33 pages) ST0640 (442 pages) ST6321 (31 pages) ST0496 (443 pages) ST3864 (30 pages) ST5177 (30 pages) 5 SUPERHEAT Computer Ruits = 217 ST6656 (28 pages) ST8373 (30 pages) ST8621 (31 pages) ST1001 (30 pages) ST8075 (30 pages) ST6401 (28 pages) ST7960 (30 pages) ST0278 (29 pages) ST1418 (30 pages) ST0249 (34 pages) ST2394 (30 pages) ST3615 (36 pages) ST5117 (28 pages) ST4045 (30 pages) ST6956 (31 pages) ST6924 (30 pages) 5 HOT
- MODULE Computer Runs = 135 ST6986 (31 pages)
ST8080 (27 pages) ST7040 (30 pages) ST8913 (27 pages) ST7093 (33 pages) ST0906 (27 pages) ST7119 (31 pages) ST3404 (26 pages) ST7149 (33 pages) FSV851 (28 pages) ST7179 (32 pages) ST7207 (31 pages) 1 SNIFFS Computer Run = 14 ST6196 TOTAL = 5101 i Page la
909268/A CONTENTS
- 1.
SUMMARY
.................................................. 4
- 2. INTRODUCTION ............................................. 6 3 ANALYSES ................................................. 7 3.1 Water ~ Side-Pressure Drop Evaluation ................ 7 3.2 Secondary System Evaluation . . . . . . . . . . . . . . . . . . . . . . . . 8 3.3 Primary Side Evaluation ............................ 9 34 Ho t Mod ule An aly s i s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 4
RESULTS .................................................. 11
- 5. CONCLUSIONS .............................................. 41
- 6. REFERENCES ............................................... 42 IND EP EN D EN T R E VI EW . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 APPENDIX A: WATER SIDE FLOW PATHS AND PRESSURE DROP CALCULATIONS ..................................... A-1 APPENDIX B: TAP, RECA, AND SUPERHEAT RESULTS ................. B-1 APPENDIX C: STOR AGE OF COMPUTER ANALYSIS . . . . . . . . . . . . . . . . . . . . . 0-1 FIGURES 4-l a Maximum fuel temperature, 518 gpm case . . . . . . . . . . . . . . . . . . . 16 4-1 b Maximum fuel temperature, 707 gpm case . . . . . . . . . . . . . . . . . . . 17 4-1 c Maximum fuel temperature, 832 gpm case . . . . . . . . . . . . . . . . . . . 18 4-Id Maximum fuel temperature, 39.2% power, 308'F temperature . 19 4-le Maximum fuel temperature, 74% power, 308'F temperature .. . 20 4-2a Steam generator helium inlet temperature, 518 gpm case ... 21 4-2b Steam generator helium inlet temperature, 707 gpm case ... 22 4-2c Steam generator helium inlet temperature, 832 gpm case ... 23 4-2d Steam generator average module helium inlet temperature, 39.2% power, 355'F temperature ........................... 24
~4-2e Steam generator average module inlet ' temperature, 745 power, 355*F temperature ............................. 25 4-3a circulator helium flow rate, 518 gpm case . . . . . . . . . . . . . . . . 26 4-3b Circulater helium flow rate, 707 gpm case ................ 27 4-3c Circulator helium flow rate, 832 gpm case . . . . . . . . . . . . . . . . 28 4-3d Circulator helium flow rato. 39.2% power, 308'F temperature 29 4-3e Circulator helium flow rate, 741 power, 308'F temperature 30 4-4 a Primary sys tem pressure, 518 gpm case . . . . . . . . . . . . . . . . . . . . 31 4-4b Primary system pressure, 707 gpm case .................... 32 4-4 c Primary system pres sure , 83 2 gpm case . . . . . . . . . . . . . . . . . . . . 33 4-4d Primary system pressure, 39.2% power, 308'F temperature .. 34 4-4e Primary system pressure, 74% power, 308'F temperature . . . . 35 8-Sa Hot module inlet helium temperature, 518 gpm case . . . . . . . . 36 Page 2
909268/A CONTENTS (CONT.) 4-Sb Hot module inlet helium temperature, 707 gpm case ........ 37 4-5c Hot module inlet helium temperature, 832 gpm case ........ 38 4-5d Hot module inlet helium temperature, 39.2% power, 308aF temperature ........................................ 39 4-Se Hot module inlet helium temperature, 74% power, 308aF temperature ........................................ 40 A-1 Emergency cooling using firewater pump (open loop) ....... A-3 A-2 Appendix R cooling using condensate pump (closed loop) ... A-4 A-3 Appendix R cooling using firewater pump (closed loop) .... A-5 TABLES 4-1 EES cooldown from 77.9 % power . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 4-2 EES cooldown from 39.2% and 74% power .................... 15 l
909268/A
- 1.
SUMMARY
Cooldown transients from a nominal 755 feedwater flow (77.95 power), after a 1-1/2 h interruption of forced cooling, were studied using the TAP, RECA, and SUPERHEAT computer codes. Cases were obtained at 518, 707, and 832 spm water flow to the EES section of one steam generator loop. Two different water flow paths were evaluated (as specified in the Fort St. Vrain 10CFR50, Appendix R evaluation), a i closed loop condensate flow path with 518 gpm flow, a closed loop firewater flow path with 707 gpm flow, and an open loop firewater flow path with 832 gpm flow. Other conditions included in these transients were helium flow adjusted to maintain 400*F steam generator water exit temperature and approximately 250 psig indicated steam generator exit pressure (consistent with emergency procedures) for condensate cooling or 300*F and approximately 75 psig for firewater cooling. The liner cooling system was assumed to be unavailable. The purpose of this study was to determine the expected (operator controlled) transients for the 1-1/2 h delay cooldown and to evaluate these transients with regard to possible excess fuel temperature. The results from the TAP transient predictions showed that a cooldown can be obtained from approximately 70% (72% power) feedwater flow with condensate or from 75% feedwater flow with firewater. The helium flow required to maintain subcooled conditions varied between a minimum of 0.9%(Rf lb/s) and a max'imum of 3.8 % (37 lb/s) at the end of the transient. This is within the operating range of a single circulator on Pelton wheels. Peak fuel temperatures as predicted by the RECA code were-less than 2900*F for condensate cooled case, and were 2706*F for the 707 gpm and 2511*F for the 832 spm firewater cooled case. These are below the FSAR 2900*F limit. Primary coolant pressure stayed below the PCRV relief valve setpoint for all cases. ; 1 l Page 4
l
~
l 4 909268/A t Based on the above results, it was concluded that an acceptable EES l cooldown from 77.95 power can be obtained using firewater flow and from about 725 using ' condensate flow. i ) i a 4 i
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909268/A
- 2. INTRODUCTION This study supersedes the study documented in Ref.1. In Ref. 1, a firewater cooldown, after a 1-1/2 h interruption of forced cooling, was obtained from an initial 785 power. The purpose of this study is to evaluate a similar cooldown from 78% power using either condensate or firewater flow Larough the EES. In all cases it was assumed that the operators followed the operating procedures specified in Ref. 2 (Safe Shutdown and Cooling with Highly Degraded Plant Conditions.) These procedures specify that condensate or firewater flow is established to the EES bundle and the pre-flash tank inlet valve is adjusted to maintain a steam generator pressure of approximately 250 psig for condensate cooling or 75 psig for firewater cooling. The pressure would be read from PI-22129 (Loop 1) or PI-22130 (Loop 2) by the operator on I-05 in the control room. Also, the circulator speed is adjusted to maintain an EES outlet te=perature of about 400*F for condensate cooling or 300'F for firewater cooling.
Page 6
909268/A 3 ANALYSES Several computer codes were used to perform the evaluation of the EES cooldown. Steam generator performance was obtained using the TAP (Transient Analysis Program) ccde. For detailed core performance, the RECA (Reactor Emergency Cooling Analysis) code was used. The SUPERHEAT code was used to determine required helium flow rates for input to the REC A code. Also, the SUPERHEAT code providcd a more accurate steam generator water side pressure drop. Hot and cold helium temperatures during the 1-1/2 h delay were cbtained from a previous analysis that used the RATSAM code. The overall water side pressure drop calculations were performed by Proto-Power (see Ref.1) and checked by GA using hand calculations and the SNIFFS code. Consistent with FSAR analyses, early versions of the verified TAP and RECA codes were used for this analysis. The following sections briefly discuss the analysis performed in evaluating the EES cooldown cases. 3.1 Wa ter Side Pressure Drop Evaluation A critical parameter in the evaluation of the EES cooldown is the water side (secondary side) pressure drop. This pressure drop includes the line and valve pressure drops from the supply pump (either condensate or firewater pumps) to the steam generator, the pressure drop in the steam generator, and the pressure drop of the steam lines from the steam generator to the condenser or back to the supply pump. Appendix A cescribes the three secondary side flow paths for the EES water flow. The overall pressure required to pass the water flow through these flow paths must be within the availtble pressure capability of the water supply pumps. Appendix A also shows the condensate and firewater pump head versus flow curves used in the pressure drop evaluation. The required pressure drop of the secondary side is the sum of the pressure decps described above. The water side flow and pressure drops Page 7
909268/A were determined by Proto-Power Corporation and verified by GA using the network analysis program, SNIFFS. Also, the available ipressure at the steam generator inlet (feedwater ring header) plotted as a function of firewater flow through the steam gecerator was determined by i Proto-Power. This curve is also presented in Appendix A. The steam generator pressure drop was evaluated by using the SUPERHEAT code. ~ 3.2 Secondary System Evaluation The heat transfer and pressure drop for the secondary side of steam generator (water / steam) was evaluated using the TAP (Ref. 4) and ' the SUPERHEAT (Ref. 6) codes. TAP is a single loop transient analysis model of the entire plant and SUPERHEAT is a steady-state model of the steam generator. The TAP code was used primarily to evaluate the steam generator transient performance, however, the TAP heat transfer results were verified by comparison with the SUPERHEAT results. The SUPERHEAT code was used primarily to obtain helium flows for input to the RECA code and to obtain an accurate calculation of the steam generator
- water / steam side pressure drop.
In order to obtain proper secondary system evaluation, the following calculational procedure was used:
- 1. Helium flow rates were determined from the SUPERHEAT code.
The SUPERHEAT calculation was performed for different time points in the cooldown transient to determine the required helium flow necessary to maintain die required water temperature at the steam generator outlet. These flow rates were then used as input for the RECA code.
- 2. Steam generator helium inlet temperatures obtained from the RECA code were used as input to the TAP code to evaluate steam generator performance. Circulator inlet helium temperatures Page 8
909268/A obtained from the TAP code were used as input to the RECA code. l l 4 3 During the initial 1-1/2 h delay period (interruption of j forced cooling), some reverse flow occurs in the primary i coolant loop due to natural convection. A previous analysis i of this effect was performed with the RATSAM code (see 1 Ref. 3 ) . Hot and cold helium temperatures were estimated based on results from this study and were input to TAP and
- RECA for the 1-1/2 h delay period.
1 4. The SUPERHEAT steam generator performance results were I evaluated at the peak helium temperature time points and were j j verified by comparing to the TAP results. 1 1 33 Primary Side Evaluation
- . The core cooling evaluation was performed using the RECA code.
j RECA is a detailed model of the FSV core which provides calculations of the helium and solid temperatures throughout the 37 fuel regions. Helium flow rates from the SUPERHEAT code and circulator inlet helium temperature from the TAP code were input to the RECA code and the steam j generator helium inlet temperatures from HECA were input to the TAP f code. 34 Hot Module Analysis 1 l The inlet helium temperature for a given steam generator module could be higher or lower than the core exit plenus average temperature j due to- flow and temperature imbalances among the various regions and the j relative location of a given module to specific core regions. In addi-tion the gas entering a given module may not necessarily be well .aixed, ] i.e. , some fraction may be at a higher temperature than the mean module j inlet and some may be at a lower temperature. Additional mixing can 2r > 5 4 4 Page 9
. . . . _ . - . . _ ._ - . _ _ _ _ _ _ . . . . ~ _ . _ _ _ _ _ . _ _ _ _ . . . . - - , - _ _ . , . . . . . - _ _ . . _ . _ _ . .
1 909268/A ! occur as the gas flows through the steam generator due to turbulence and cross flow paths resulting from tube bundles and other flow path obstacles. Test data for turbulent flow conditions indicate that an induced hot streak will dissipate to approximately 6% of its initial value by the time it reaches die reheater bundle. .The gas temperature profile at the reheater tube bundle inlet will, therefore, be relatively flat at the module average inlet temperature. With a hot module it is likely d1at boiling will occur, which could result in reduced water flow and increased tube temperature in the hottest module. To evaluate U11s condition a hot module analysis was performed using the HOT
- MODULE code. The RECA, TAP, and SUPERHEAT codes were also used to evaluate the hottest module temperature and to study a revised operating condition to prevent boiling in the hottest module.
1 Page 10
i
! 909268/A 4 4. RESULTS l I
1 Table 4-1 presents the overall results from the computer codes i including the Proto-Power pressure calculations. The sequence of events for diese cases was as follows: i i, . 1. A reactor trip occurs at 1 s into the transient, helium flow i was ramped to zero in 5 s, and feedwater flow was ramped to ' zero in 2 s. I f 2. As a conservative assumption the steam generator pressure was assumed to be depressurized early in the transient. Beginning ] at I s into transient, the steam generator outlet pressure was camped from normal 2600 psig to 250 psig or 75 psig in
; approximately 500 s. )
l 3 A 1-1/2 h delay occurred with no feedwater or helium flow. ' 4 At 1-1/2 h into the transient, the water supply pump was assumed to be started and the flow to the steam generators was i j ramped to full flow in 5 min.
- i
- 5. The EES. outlet water pressure was maintained via the main
- steam bypass pressure control valve utroughout the cooldown 4 transient. i 1
4
- 6. The helium circulator with pelton wheel drive was started at 100 min into the transient after firewater or condensate flow to the EES was at full flow.
- 7. Helium flow was adjusted to maintain the required water temperature at the EES outlet.
f { 8. The liner cooling system was assumed to be unavailable. )
- 9. The thermal capacity of the reheater module in the active loop was ignored.
j Page 11 I
909268/A TABLE 4-1 EES C00LDOWN FRCH 77.9% POWER 518 gpm 707 gpm 832 gom Primary Side Results (RECA): Min. cold helium temo. , *F (input) 156. 85. 80. Circulator helium flow, 5 (input) 1 3 to 3.7 1.4 to 3.7 1.7 to 3.8 Max. fuel temp. , *F 2857. 2706. 2511. Max; avg. module S.G. helium inlet temp., 'F 1314 1323 1333 Max. hot module S.G. helium inlet temp;, *F 1415. 1426. 1437. Steam Generator Results: Outlet water temp., *F 400. 300. 300. Inlet water temperature, *F (input) 156. 85. 80. Water flow, spa (input) 518; 707. 832. g,) Max. circulator inlet temp. , *F 200. 130; 125. (,) Max. economizer outlet tube temp. , 'F 175; 100. 90.- Max; superheater outlet tube temp. , *F 400; 300. 300. S.G. outlet pressure,
' psia (S.G. ring header) 288.4 123.5 107 S.G. outlet ' pressure, psia (at PI-22129/22130) 268.4 103.4 87 3 S.G. pressure drop, paid 13.2 22.6 30.4 S G; inlet pressure, psia 301.6 146.1 137.4 g ;t'Homodule outlet boiling margin *F 0 0 0 Calculated Results:
Total pump flow, gpm 643 832. 957. S.G. water flow, spa 518. 707. 832. S.G; outlet pressure, paia
'(at PI-22129/22130) 268.4(b) 103.4(b) 85.1(b)
Required S.G. inlet pressure, psia 301.6 146.1 135.2 Available S.G. inlet pressure, psia 299.9(b) 145.7(b) 141.5(b)
- Maximum during EES cooldown is well below the nominal steady-state operating temperature.
Proto-Power results, available pressure is slightly below required pressure for 518 and 707 gpa cases. This is due to a slightly higher steam generator pressure drop from SUPERHEAT than was calculated by Proto-Power. D11s Was Considered insignificant. Degrees of subcooling at exit of hot module. Page 12
i 909268/A The operating points shown in Table 4-1 are from the transient performance at the peak temperatures and at point of maximum module temperature deviation. The results show that the EES cooldown can be ] performed satisfactorily within the head capability of the supply pump. l The peak average steam generator helium inlet temperature was 1333*F for 832 spm case and peak fuel temperature was 2857'F from the RECA code for ] the 518 gpm case. Figures 4-1 through 4-5 present the transient results for the three
- EES cooldown cases from 77.9% power. Figure 4-1 a through c presents l
the maximum futi temperature which shows the 2857'F peak fuel temperature at about 6 h into the transient for the 518 gpm case. Figure 4-2 a through c shows the steam generator helium inlet temperature predicted by the RECA code. Figure 4 -3 a through c shows i the helium flow required to maintain the required steam generator water ! outlet tenperature. Figure 4-4 a through c shows the primary system
- pressure. The pressure remains below the PCRV pressure relief valve setpoint throughout the transient for all three cases. Figure 4-5 a through c shows the steam generator inlet helium temperature for the
- j. average and hot modules. The maximum values are 1333*F and 1500*F, 1
l respectively for the 832 gpm case. Based on the fuel temperatures, the most limiting case was judged to be the 518 gpm case. 1 ! Although an average temperature-of 300*F for firewater cooldown and 1 j 400*F for condensate cooldown is maintained at the EES outlet, some of f the modules were operating with hotter helium temperatures from the 1 core. As shown in Table 4-1 all three cases were boiling (0*F boiling margin) in the hot module, as discussed in Appendix A. An additional analysis was performed for 355 and 705 feedwater flow using the ! SUPERHEAT code. Based on an updated Proto-Power analysis shown in j Appendix A the water flow was increased from 518 to 527 gpm. For both j cases the average steam generator outlet temperature was reduced to 1 i i j Page 13
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909268/A about 308'F to avoid boiling in the hottest module. EES cooldown cases were run with the RECA, TAP, and SUPERHEAT for both cases. Table 4-2 shows these results. The results in Table 4-2 show that the 70% case was not acceptable due to maximi's fuel temperature exceeding the 2900*F FSAR limit. However, the 355 case was well below this limit. Both cases were less than or equal to water saturation temperature in the hot module. The estimated maximum power from which an acceptable EES cooldown could be performed with the 308'F steam generator exit temperature and 527 gpm condensate flow was about 725. Figures 4-Id and e through 4-5d and e present the RECA transient results for the two cases shown in Table 4-2. 1 Curves from the TAP and RECA runs and tables from the SUPERHEAT code runs for the five cases in Tables 4-1 and 4-2 are presented in Appendix B. Page 14
. . ._~ ~ . . __ __
909268/A I
- TABLE 4-2 EES C00LDOWN FROM 39.2% AND 74.0% POWER 4
39.25 Power 74.0% Power i Primary Side Results (RECA): Min. core inlet helium temp., 139. 139.
'F (input) , Circulator helium flow, % (input) 1.1 to 3.8 0.9 to 3.2 Max. fuel temp., 'F 2040. 2931.
J Max. avg. module S.G. helium 1082, 1264, inlet temp. , 'F Max. hot module S.G. helium 1169. 1367. inlet temp., *F' Steam Generator Results: Outlet water temperature, 'F 308. 308. l Inlet water temperature, 'F (input) 139. 139. Water flow, gpm (input) 5 27. 5 27 . ! Max. circulator inlet temp. , 'F 190. 190. Max. superheater outlet 400. 400.
, tube temp., 'F S.G. outlet pressure, 288.5 288.5
' psia (S.G. ringheader)
S.G. outlet ' pressure, 269. 269. psia (at PI-22129/22130) S.G. pressure drop, paid 12.8 12.8 S. G. inlet pressure, psia 301 3 301.3
~
, Hot' module boiling margin, 'F 17. 0 (at
' saturation) l .
Calculated Results: Total pump flow, gpm 652. 652.. ' S.G. water flow, spm 527. 5 27. S;G. outlet pressure, 269; 269.
' psia (at PI-22129/22130) i Required S.G. inlet pressure, psia Available S.G. inlet pressure, psia 301 3(a) 299.9 301 3(a) 299.9 .
) (* Based on Proto-Power results, available pressure to slightly below l required pressure. This is due to higher steam generator pressure drop from SUPERHEAT than was calculated by Proto-Power. This was , considered insignificant. i l 1
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i ? Page 15 1 _ . _ . , _ - - ,. _ . - - ___._-~_.-- _._,_. _ _._-._ _ ,_.- ~ . _ - _ _ _ _ _
909268/A 1 i mormas mis w istasais esca na ru rtou as convis sie m i MAXIMUM FUEL TEnpERaTURE 3000 raax l
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fig 4-1a. Maximum fuel temperature. 518 spm case Page t6
909268/A am enses is,is,= is..iies seca ne av rum as eseums m em MAXIMUM FUEL TEMPERATURE 2750 [ _' TMAX
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E. - S' - F . 2006 a 1750 , , , 9 2 4 6 8 le TIME, HOURS Fig. 4-1b. Maximum fuel temperature, 707 gpm case Page 17
909268/A 818kST8804 lle**est 08:58s32 Pgu g.3 M terc, gES COOLING. 77.3s pgugg MAXIMUM FUEL TEMPERATURE
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1000-- D - E " G F . 0 . , I i l l O a 4 6 8 10 TIME (H) l 3 Fig. 4-1 c. Maximum fuel temperature, 832 gpm case l l l i Page 18 1
909268/A 2 i l mm stisse sae:7,# pimiu un staan nov, ces coeue.c.'sa, can ., a, , l l MAXIMUM FUEL TEMPERATURE 2200 i TMAX 2000 y N D E - G 1800 _/ ( R E - E
- S 1600 i
i F . 1 1400 l -
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1200 , 0 2 4 6 3 10
- TIME, HOURS l
1 I t i Fig. 4-1d. Maximum fuel temperature, 39.25 power. 308aF temperature i i i i i l l 1 Page 19 ( l l l l l l
909268/A laaeogT9403 85/80'es 43e44s43 tee sm. Ett CLS. 537 epi 3eer. Mt MAXIMUM FUEL TEMPERATURE , 3000 TMAX
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E S - p 2000-1589 . . u . . a 0 2 4 6 8 10 TIME, HOURS l Fig. 4-le. Maximum fuel temperature, 74% power, 355'F ten:perature Page 20
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909268/A aw. m mes is,is,es is m.is sea m av ruu as coeuas ses == SG INLET HELIUM TEMPERATURE 1500 TAVOTF
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909268/A f i l meu isetwas is..iiw asca m av atou ess c w. m am SG INLET HEl.IUM TEMPERATURE 1500 TAVOTF p : 1 ll lG 1960 R - E E S . p See 0- . . . 9 2 4 6 8 19 TIME, HOURS Fig. 4-2 b. Steam generator helium inlet temperature, 707 gpm case t Page 22
909268/A l f 4 i ens >qvagee itsee,es essgesas Pets t.S se tapt. EES eseL3MS. W.Se PEMEA j j 4 SG INLET HELIUM TEMPE."4ATURE 1540-i 7 1 E - r M . P E R 1990 A T U' . j R ~ E
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, . g 0 2 4 6 8 le TIME (H) i i Fig. 4-2c. Steam generator average module helium inlet temperature, 832 spm case Page 23
909268/A I i u I awe *0tlll8 leeltete States 44 M e STEen PL4W. 8E8 C00 LING. M t 4Mt at see r STEAM GENERATOR IHLET HELIUM TEMPERATURE 1500 TAVOTF D 1000 IN J E < G ' R . E ' E ! S . F 500 s
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9 O 0 i . . . . ; [
; 9 2 4 6 8 10 ;
TIME, HOURS i 1 1 Fig. 4-2d. Steam generator average module inlet temperature. 39.25 power, 308'F temperature I . i Page 24 1
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I 909268/A l l wem sarewes saus .s m m. as us. en em seer. n M ERATURE i 15.. TAV0TF C
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TIME, HOURS l l l Fig. 4-2e. Steam generator average module inlet temperature, 74% power, 308*T temperature
- Page 25
909268/A 8488*tf9464 tisssses leaagent atC4 71s FU FLCU LES C004tNG $$$ CMI CIRCULATOR HELIUM FLOU RATE 40
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909368/A i tweettees 64/89,94 ttsettee asca 76e N Flatl $80 44848888. 747 GMI CIRCULATOR HELIUM FLOW RATE 40
~
, , FLOHTX c
30 - L - B S
/ 29 -
S - L it t ... . . , , 9 2 4 6 3 it TIME, HOURS Fig. 4-3 b. Circulator helium flow rate, 707 spm case Page 27
l 909268/A awe.ituee u o ,= wissin uca m rv em its coniae. su e CIRCULATOR HELIUM FLOW RATE 40 FLOHTX 30 ' . L B S
/ 20 l' i
C J " 10 O W 0, 0 , 9 2 4 6 3 te TIME, H0tJRS Fig. 4-3c. Circulator helium riow rate, 832 spm case Page 28
909268/A l l 1
**,s iis narit,m i s . . u n. ,, n. , ,, , , ,,, , ,, ,, ,, ,, , j CIRCULATOR HELIUM FLOW RATE
~
,; FLOHTX
.' W ^
30
/ .
L 8 S
/ 20 S - r E -
C .
~
gg L . g - - _ 8 2 i 4 6 3 gg TIME, HOURS Fig. 14-3d. Circulator helium flow rate, 39.25 power, 308'F temperature , Page 29 l
909268/A am mim sa,m,m 2 . sin ne sm, ses ets. m a w. :: CIRCULATOR HELIUM FLOW RATE 40
~
FLOHTX
. O
~
/
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/ 20 S -
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, 7 0- .- - - - , . , , , ,
9 2 4 6 8 10 TIME, HOURS Fig. 4-3e. Circulator helium flow rate. 745 power, 308'F temperature Page 30
909268/A 1 me=neses innees is mens seen m eu nau sas assume sie een PRIMARY SYSTEM PRESSURE 794 PHPSI
~
J See w- , l P l
$ 594 1
A - i 400 Q - t . Me , , , , , e a 4 6 3 10 TIME, HOURS l L l l Fig. 4-4a. Primary ayatem pressure. 518 gpm case l r f l l l Page 31 1
909268/A l nm.enew is,ie,m isiesim aca ne av etw us soeum, as wa PRIMARY SYSTEM PRESSURE 700
- PHPSI GM --
w~ P S 500 1 A - 400 - k-
-e -
300 , , , , , 9 2 4 8 3 it TIME, H00R$ I l Fig. 4-4b. Primary system pressure, 707 spm case l l l Page 32
909268/A I l l l ensam u. == mess.m == = m mm we une m. me me PRIMARY SYSTEM PRESSURE 1 7
)
see
..[ F '
P l S 544 , I - l A - 400 i
~
( , A : ; I 340 , , i . . i i e 2 4 s a gg TIME, HOURS l l Fig. 4-40. Primary system pressure. 832 spa case l , 1
\
Page 33
909268/A p g9gggg 33,37,30 11688844 388 8W ** II' ' '
'let - PRIMARY SYSTEM PRESSURE
. PHPSI Get a
, g-P '
s 544 I - A - 444 '
- x h _
N , 344 ---- . i g ' a 4 6 3 14 T!HE, HOURS Fig. 4-4d, Primary system pressure. 39.25 power, 308er temperature 6 Page 34
909268/A S.0. INLtf it PS. - 75% FW FLOW - 518 QPM AT 400 F WATER 1see Legend i [; ..., u.t ......
- ies. -
.,sa.a m - t .
P e r - e 1000 1 t . r -, e - 7se , D - . e - g - se0 - F - 250 -' ' ' i i 0 2 4 6 8 10 18 Time, Hours Fig. 4-5a. Hot rnodulo inlet helium tertperature, 518 gpm case Pago 36
909268/A 1500 S.s. INtti TEMPS. - 754 FW FLOW - 707 GPM AT 300 F WATER L* send l1ase [l . . . . . ' ..t .... .
, a'JiWF.1;i a
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909268/A S G. INLET TEMPS - 752 FW FLOW - 838 OPM AT 399 F WATER 1500 Legend
~ (
f(" * . , , Het Medute T 1250 - i . ............ t
'.- K Avf Module
\
e 1000 - r '
~
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t u 750 r - . e - - p 500 -
~ '
e - g - p 9 g I I I i t t 0 2 4 6 8 10 la Time, Hours Fig. 4-50. Hot module inlet helium temperaturet 832 gpm case Page 38
909268/A i l t - 1 1200 354 FW X1 527 GPM AT 308 F WATER WITH NEW MODEL g Legend f ,, 7 l Het Module
, 1000 ,
' m Avg Medute ' p . e i a 800 \ \ i t ., u . l r , 1 e 600 i ', i D . e . 9 i 400 5..'- !. F - A 299 ' ' '
,l 0 2 4 6 8 19 Time, Hours 12 T
Fig. 4-5 d. Hot module inlet helium temperature. 39.25 power. 308'F temperature i I i i l t Page 39 i I _ . _ _ . . . _ _ . - . _ _ . . _ _ _ . . _ . - - _ . _ , _ _ . _ . _ - . ~ . _ _ _ _ _ _ _ . . . _ . _ , _ - - _ _ . .
l l 909268/A 5 l l l 1 704 FU Xi 527 GPM AT 308 F WATER 1400 l Legend 1 i . f , Hot Module I
- 1200
; '. Avg n.dute s '
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i P t e . a 1000 , s . u . '. r . See i, N D - *
. 600
( F . 400 i 0 2 4 6 8 10 12 Time, Hours i f Fig. 4-Se. Hot module inlet helium temperature, 745 power, j 308aF temperature , i l 5 l Page 40 l q
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909268/A
- 5. CONCLUSIONS From the results shown in Table 4-1 it was concluded that a satisfactory EES cooldown can be obtained from 75% feedwater flow (77.95 i power). This cooldown.can be performed with firewater flow to the EES bundle using a closed loop arrangement for water supply (as specified in
- the Fort St. Vrain 10CFR50, Appendix R evaluation). The cooldown can j also be performed using firewater from an open loop arrangement for e water supply. 1 An interpolation of d3e results in Table 4-2 indicate that a satisfactory EES cooldown can be obtained from approximately 70%
feedwater flow (725 power) with condensate flow to the EES bundle. This is also from a closed loop arrangement as specified in the Fort St. Vrain 10CFR50, Appendix R evaluation. 1 The pressure required 'to supply the water to the EES is within the l capability of the condensate and the firewater pumps. Maximum core fuel temperatures and steam generator tube temperatures are within the allowable limits for these components. 1 For the condensate cooldown it is recommended that the 400*F control setpoint at the steam generator exit be lowered to 3088F to provide more subcooled margin, i.e., prevent boiling at steam generator outlet. i 4 i e 1 1 I 1
- Page 41 1
i
909268/A
- 6. REFERENCES 1
l
- 1. CFL 909120 N/C, " Firewater Cooldown From 78% Power Using EES (1-1/2 Hour Delay)," by R. C. Potter, dated November 11, 1986.
- 2. " Safe Shutdown and Cooling with Highly Degraded Plant Conditions,"
Public Service of Colorado Document SSCHDPC Issue 14 (Fort St. Vrain Plant Operating Procedures Manual - Abnormal Procedures for Shutdown Cooling), dated October 7,1985.
- 3. SAM :113 :GJC:77, "PCRV Depressurization Analysis During LOFC - FSV (105%' Power, 2 h delay through as-built train with rerouted 2 in pipe)," from G. J. Cadwallader to G. C. Bramblett, dated May 3, 1977.
4 J78-6048-TR-1, " Review of the Fort St. Vrain Transient Analysis Program (TAP)," by James R. Carlson, JAYCOR, dated July 1978.
- 5. GA-A13613. "RECA2-A Program for Daermal Analysis of HTGR Emergency Cooling Transients, Program Description," by J. F. Peterson.
] 6. GA-D14776, " Steam Generator Daermal Performance Models and Data Reduction," by D. P. Carosella, dated February 1978.
- 7. CFL 909113 N/C, " Firewater Cooldown Using One Reheater Module," by R. C. Potter, November 1986.
e Page 42
GA154:i(R EV.11l80) 909268-A CALCULATION REVIEW REPORT EES C00LDOWN FROM 39% AND 78% POWER USING CONDENSATE OR FID.EWATER (1.5 HOUR DELAY) QAL LEVEL I DISCIPLINE SYSTEM 00 C. TYPE PROJECT DOCUMENT NO. ISSUE NO./LTR. I 01 CFL 1900 909268 N/C INDEPENDENT REVIEWER: NAME T. W. Chan/G. Cadwallader ORGANIZATION (647) System Design and Plant Dynamics Branch REVIEWER SELECTION APPROVAL: BR MGR A. Shenoy MS h DATE W /O' '
~
U R EVIEW METHOD: YES NO ERROR DETECTED ARITHMETIC CHECK LOGIC CHECK ' Med M/d 2-ALTERNATE METHOD USED SPOT CHECK PERFORMED COMPUTER PROGRAM USED Zirra -h> esas v See Alcre I,3
- 3,,,,,1- h> nq P, $upun-- f ^^ W',,,. -
amov&cE r*A j Oh,s H6tr o - g (J U, , t/g REMARKS: (ATTACH LIST OF DOCUMENTS USE0 IN REVIEW) d _::=f Ll21/%
- t. Can intet teir,perature duo b '"' h" / .'* /, fis '>' [.7.*
ti haar de/3 wa s Ili'*F ho law re/he s'"fh', 767ed132 CI'M c.aes. Duy i e insu' L/ temperah<re and a verage cere N"f'*'" u ere. too loa, bar by yrohably 2 to S"f eg. //.t ctreaxs as.A ner bd a fk tc'd-
.Tnstea4 on13 & cold downficwlar h kfup h WR The 5'M GPtt use.y cha.nnels shcuId have hr3 er eaffef f&n'Pir'l"'dh a>a s ascr.ect, dcirclusims aN tr 'f a Ils'rfcA-
- 2. first' Pdrajraph on p.t/ i,rdicasts raat rne sd Gl'p1 case sh s ps//, pecic ferrp.r.wres .
I.n Scf, fAe 93 2 CrP/17 ca.se Aa5 yje fr G Virk e Tricirl c 's.se ra fto- /t s'/Ss, ihlet' 16mperafure. (I 33's F), j'sr-oe. 4%y/esr
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- 3, (*. ore sr/et lampenhore, :Likr .s+rf of EE6 cocinj ufas erroasecas < Spvxt/}ed' 0,- ??i'.
p: " e n e-. ?hes dic/ ur a<respd n fa-pvin/ues Som C4P. (f4Dr? a'as i reran w bl estrected iApur for resa/f, rep,,.uj ),e,e;,,,)ft%0 l l I eee a i e ga p Sn m > its%cufC $ th'm. 2 % . (/ t1/23/S& , CALCULATIONS FOUND TO BE VAll0 AND ONCLUSl S TO BE C0 ECT: l 4 'W t.t/f/% INDEPENDENT REVIEWER de/IS/ v4<4 - DATE /'42/ 8 6 l 7 SIGNATURE
/
Page 43
G A 1343G EV.11/8u) 909268-A CALCULATION REVIEW REPORT EES C00LDOWN FROM 39% AND 78% POWER USING CONDENSATE OR FIREWATER (1.5 HOUR DELAY) QAL LEVEL I OlSCIPUNE SYSTEM 00C TYPE PROJECT DOCUMENT NO. ISSUE NOJLTR. I 01 CFL 1900 909268 A INDEPENDENT REVIEWER: NAME T 'mn/Tng hr ORGANIZATION (647) SYSTEM DESIGN AND PLANT DYNAMICS BRANCH REVIEWER SELECTION APPROVAL: BR MGR A. Shenoy ATE I 9' N REVIEW METHOD: YES NO ERROR DETECTED ARITHMETIC CHECK f LOGIC CHECK / N* ALTERNATE METHOD USED SPOT CHECK PERFORMED ' COMPUTER PR00 RAM USED
~~
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l REMARKS: (ATTACH UST OF DOCUMENTS USED IN REVIEW)
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CALCULATIONS FOUND TO BE VAllu AND CONCLUSIONS TO BE CORRECT: INDEPENDENT REVIEWER d '
/
DATE /1/U /86 ' - SIGNATURE ,/ Page 44
909268/A APPENDIX A A-1 WATER SIDE FLOW PATHS AND PRESSURE DROP CALCUL.5? IONS A-2 HOT MODULE ANALYSIS I Page A-1 l t
909268/A 1 APPENDIX A-1 WATER SIDE FLOW PATHS AND PRESSURE DROP CALCULATIONS WATER SIDE FLOW PATHS Three different secondary coolant configurations are considered in this analysis. These configurations are illustrated in Figs. A-1, A-2 and A-3 Starting at point A and going to point B in each of these figures the flow path is common for all three of the configurations. The remainder of the flow path in each of daese configurations establishes the difference in the flow configuration, the flow rates, and the temperatures and pressures in the secondary coolant system. For illustration purposes Loop I is being treated as the operating loop. The following piping elements make up dae flow path from point A to point B.
)
Starting at point A, flow goes through the following elements: valves: V31239, HV-2257, V2257, flow element: FE-2205 and valve FV-2205. Between valves V31239 and HV-2257 125 gpm branches off to the Pelton wheel. FV-2205 is connected to the common pipe line which supplies flow to the six steam generator modules. The inlet line to each module contains a trim valve and a flow measurement element. After leaving the six modules a common pipe line is connected to the main steam pipe line. Under normal operating conditions the main pipe line would connect to the main turbine. During emergency operation the
- cooling water flows through one, two or three parallel connected valves PV 2229, PV 22129 and PV 22153. From the three valves the flow goes through the desuperheater (S-5201-A) and valve V5205. After this point i
each of the flow paths vary as described below. For all three cases the flow is regulated by controlling steam generator back pressure at PI 22129. Page A-2 l l
909268/A TO PELTou WNEEL dtSGrad FV-1105 832 G PIA HV- 22 77 ' H V-3 tt1E b FE.*1105 V1251 V'3tt39 b SuTEm 4d % - (: , .45 V AL V E3 8* DISCHARGE TO Arah To Loor E4 TO TURBINE# 0 S ,,,
' 8L3 P5IA $p Ng4 22 ZS
.Q 51 2 -
4 1 , g g ,3 : a m.~ Ftoln C00LluG wkrEt Pouc 80*F u DE5 urEtHEkT EE 51 4 5518 i- A VERT TO AT th 1 .3 r$1A q m usEt g
. 51 5 V 5 Lot. V3130 3 BI:fa g ~
5Tm. G Eli. v s ts7 Hv3 0 v31301-Tttm Fth5R ThWE. FWIS \ V 3Z307 Ei.EnEnis a >W 4 No Ft.ow lu.TMast Pif ts I Fig. A-1. Emergency cooling with EES using firewater pump (open loop) Page A-3 l . _ _ _- __ . _ . _ _ .._._~._ . _ _ . . _ _ _ _ _ . _ . . . .. .-. . _ , . , _ . . _ _ _ . _ _ .
909268/A TO PELTOM WilEEl. (i ts G rn) FV-1105 14V -2237 H V-31191 HV3133-Z b FE-2205 V1251 M V31139 b. V11199 b V3tl7
-{> <3 D=d N,
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2G8.4 PSR FKOM ZZ 29 Q ._ 51 2 , Jk 8-g C.0 M UE N S ATE PUMP Bl *3 L d 400 *F DES urEtHEkT EE nom PELTO M _ WHEEL. Bi . 4 s sto t- A V3Z l OS 515 > h V5 tot , e LV -3250- 2. lS Wb b l ST m. G EN. vstse E W HE AT LE m0 %l156 'F liEhT Eit.ithuGEE E 420t T V3El07 V t. E 5 Ft.0W H'/-3 Z10 - r,
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EL EIAEllTS
- S IS (a Pin
-4 ' NO Ft.0 w tu.THESE ptPts Fig. A-2. Appendix R :ooling with EES using condensate pump (closed loop)
Page A-4 I
1 l 909268/A i
.TO PEl.Tou WllEEl. Q15 GPld pv-tto s uv 2237 wv sitzt
] j g b lN X --f><1E.b FE.* Z205 V1251 V3tI39 14 51ST E rA g3g gpm
--t> < CrJ >@ 45 "'" -
To tooP Ir4 TO TUltBINEI 1 O ' 101.4 P5in M O g p g4 22 ZS ] .
.Q Bt 2 - J J
& 1RghTdK. j 85 ' f-
.Q B l .3 ~ ' -
f 300 'F - 3 702 CouDEUS ATE SIORAGE DE3 0rEtllEkT EE TAN % SERVICE WATER RETutN q Bl . 4 5510 n- A PUMP $.f 00Lt MG T00Et
. . 51 5 I
--o- LV -3250- 2.
l I -*' ' STIA. G EH. vstas 8 * " E " 7 '"" D L IG4'F llEhT E tt.lt ht&ER. E 4 2 07. T V 5 FLOW H V-3 Z 2 0 - r, V1 E 1 O ~T . Ct. EMEUTS 'hd '
-1 NO Ft.0 W IM'.'TA ES E PIPLS 707 G M Fig. A-3. Appendix R cooling with EES using firewater pump (clor.ed loop)
Page A-5
909268/A The following describes the cooling configuration for the portion of the piping which is not common for all three cases. , OPEN LOOP EMERGENCY COOLING USING FIREWATER PUMPS: The firewater pumps draw 80*F water from pits which communicate directly with the main cooling tower basin at the total rate of 957 gpm (125 gpm to the Pelton wheel and 832 gpm to the steam generator). This water is routed through a series of System 45 valves. From System 45 it is connected to HV-31122, from this point it flows through the steam generators as described above. Af ter leaving the steam generator about 100 gpm is vented to the atmosphere at point C via electromatic valve PV 22167 (not shown) . After leaving valve V5202 at point B, the water flows through the flash tank (T-5201) and is vented to the condenser via a 6 in. line. The condenser is at atmospheric pressure. The following elements make up this flow path: Valve V5287, flash tank T-5201, flow element FE-3219, valves HV3250, V32307. V32302, V32303, and condenser E-4101. For this configuration the water pressure at PI 22129 is controlled to maintain subcooling. The steam generator outlet temperature is regulated to a maximum of 300*F by controlling helium circulator speed. CLOSED LOOP APPENDIX R COOLING USING THE CONDENSATE PUMP The condensate pump delivers a total flow of 643 gpm (125 gpm to the Pelton wheel and 518 gpm to the steam generator) at 300.4 psia and 156*F. The flow goes through four valves prior to reaching point A; V3117, HV-3133-2, V31299 and HV31191. From point B the flow goes through valves V5288, HV3220-6, V32107, decay heat removal heat exchanger E-4202, valves LV-3250-2 and V32108. Page A-6
909268/A The decay heat heat exchanger reduces the water temperature from 400*F to 156'F. Downstream of valve V32108 the Pelton wheel flow returns to the loop. From this point the flow returns to the condensate pump. The pressure at PI 22129 is adjusted to prevent boiling of the 400'F water at the steam generator outlet. CLOSED LOOP APPENDIX R COOLING USING THE FIREWATER PUMP The firewater pump obtains water at 85'F from the cooling tower and discharges it at 148 psia. The total flow is 832 gpm (125 gpm to the Pelton wheel and 707 gpm to the steam generator) . From the pump, water flows through 14 system 45 valves and valve HV-31122 to point A. After leaving point B the flow goes through the following elements: Valves V5288, HV-3220-6, V32107, decay heat removal heat exchanger E-4202, valves LV-3250-2, V32108, the condensate storage tank, the service water return pump, a cooling tower and the valves which are part l of this equipment. The decay heat removal heat exchanger cools the water from 300*F to 164*F. The cooling tower further cools the water to 85'F. The pressure at PI 22129 is adjusted to prevent boiling in the loop. 1 Page A-7 l
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Page A-10
..__ .. __ . . . ._ _ . . . - m _ _ . . _ _ _ . _ _ _ . _ _ . . . - . _ _ . - ____m - . _ . _
e 1
** . -- 909268/A PROTO POWER CORPORATION ^ SL*53&o4, CORPORA TION
$91 P00UONNOCK ROAD GROTCN. CONNECTICUT 06340 (203) 446 9725 File: 7511482 October 31, 1986
, Mr. Jack Kennedy 4
General Atomic Technology 10955 John Jay Jopkins Drive
; San Diego, CA 92121
Dear Mr. Kennedy:
Enclosed is Proto-Power's Calculation No. 82-08. ' This calculation determines the cooling water flow rate, steam generator back pressure and condensate inlet temperature for the Appendix R flow paths, Train A (condensate flow) and Train B
; (firewater flow). Each Train has been analyzed for two different i valve alignment conditions: )
O PV-22153 open, and PV-2229 and PV-22129 closed. This is the valve alignment analyzed in
, the Appendix R Evaluation performed by Tenera.
O PV-22153, PV-2229 and PV-22129 open. This is consistent with the EQ flowpath, and obviously
! results in a higher flow rate.
In support of the XI power level, the calculated flow rates resulting from the specific Appendix R valve alignments should be used. The firewater flow path from the firewater pumps to the emergency condensate header is through the o r ig inal firewater supply piping, as analyzed in the Appendix R Evaluation. For the EQ 4 flow path, the flow is instead through the new bypass line via
- HV-4518 and HV-4519.
l l l J i Page A-11
909268/A I l 1 \ t Mr. Jack Kennedy ; i General Atomic Technology 10/31/86 Page Two l l If you have any questions on the enclosed calculation, please call me at (203) 446-9725. Sincerely,
- G. W. Geaney, Manager Engineering Services I
MP:bac Enclosure
, cc: K. Dvorak /PSC I
F. Tilson/PSC
, 1 l
l 1 r Page A-12 l l i
909268/A CALCULATION COVER SHEET PROT 0-P0llER CORPORATION l l l l TITLE: APPENDIX R SAFE SHUTDOWN COOLING FOR PSC - FORT ST. VRAIN CALCULATION NO.: 82-08 FILE NO.: 7511482 i I a
. S. Tombesi/
f CALCULATED BY P. Breglio DATE 10-31-86 CHECKED BY M. Fekete DATE 10-31-as Page A-13
9092eo N/C .i e i CONTENTS
- 1. PURPOSE
- 2. BACKGROUND
- 3. METHOD
- 4. RESULTS
- 5. REFERENCES ATTACBMENTS: 1. Computer Input Files and Printouts - Train A
- 2. Computer Input Files and Printouts - Train B
- 3. Drawing No. 7511482-PF-10
- 4. Drawing No. 7511482-PF-11 l
1 i 9 Page A-14
i 909268/A
' "C*82-08 1 or 3 PROTO POWER CORPORATION onio rna GROTON, CONNECTICUT MM omre 10-31-86 S. Tombesi 7511482 CUENT PROJECT Public Service Co. of CO Fort St. Vrain
- SUBJECT Appendix R - Safe Shutdown Cooling i
i I i
- 1. PURPOSE To determine the secondary cooling water flow rates through the two separate cooling water flow paths identified in Reference (a) for safe shutdown cooling following a major
.i (10CFR50, Appendix R) fire.
l
- 2. BACKGROUND Two separate, alternate steam generator flow paths have been developed for safe shutdown cooling following a major fire _.
, These flow paths have been developed in accordance with the
! requirements of 10CFR50, Appendix R. A description of these flow paths, and their evaluation for compliance with
- 10CFR50, Appendix R is presented in Reference (a) .
i One flow path, Train A, is from one 12-1/24 condensate pump, through the EES section of one steam generator, the decay l heat removal exchanger (for heat removal from the con-3 densate) and back to the condensate pump. The other flow path, Train B, is from the d iesel-d riven firewater pump,, through the EES section of one steam generator, the decay heat removal exchanger (for heat removal from the the firewater), the condensate storage tanks, service water ! return pump, the main cooling tower ( for additional heat 1 removal from the firewater) and back to the fire water pump. The Reference (a) flow paths are through PV-22153. However, the flow path for cooldown following an EQ event is through i PV-22153, PV-22129 and PV-2229, in parallel, to maximize cooling water flow. This calculation will address both flow
, through PV-22153 only and flow through all three valves in
- parallel.
The manufacturer of the decay heat removal exchanger recommended that two phase flow (low quality steam) in the , heat exchanger be avoided to preclude the potential of high
- shellside velocity induced tube vibration and resultant l damage. Therefore, LV-3250-2 will be throttled to main-tained subcooled conditions at the heat exchanger inlet.
l This is consistent with Reference (a). Page A-15
909268/A cuc w 8 2-0 8 *** "G8 2 3 o, PROTO POWER CORPORATION I GROTON, CONNECTICUT oa.a a,
'^ y' ,
out 10-31-86 S. Tombesi #
- 7511482 cuENT Public Service Co. of Coloradc PRO.ECT Fort St. Vrain Appendix R - Safe Shutdown Cooling
- 3. METHOD The computer program and approach of Reference (b) were used for determining system pressure drop. The computer program FSVSG, Reference (c), was used to determine coolant tempera-tures within the steam generator, assuming 125 GPM pelton
, wheel flow and 1300*F helium inlet temperature.
Firewater inlet temperature to the steam generator is assumed to be 85*F. Decay heat exchanger performance was determined with the computer program HEATX, Reference (d). This program calculates firewater outlet temperature and condensate outlet temperature. Condensate outlet tempera-ture is also the inlet temperature of the steam generator 1 for Train A. The sections of the flow paths for Train A and Train B, and associated hydraulic resistances are detailed on Attachment 3 ( D r awing, No . 7511482-PF-10) and 4 (Drawing No . 7511482-PF-11) respectively. j This information was used to create the computer inputs files for the analysis.~ Each flow path was analyzed with flow through only PV-22153, and also with flow through PV-2229, PV-22129 and PV-22153 (in parallel). LV-3250-2 was throttled, by reducing the valve Cy, in the input file to maintain saturated liquid (approx imately 5
- F subcooled) conditions at the heat exchanger inlet. For Train A, system l
pressure is based on conservatively assuming empty conden-sate storage tanks, and thus 12.3 psia condensate pump inlet pressure. For Train B, the condensate storage tank must be full to allow firewater outlet flow through the tank overflow line. Thus, firewater enters the tank against a static pressure of 22.3 psia. The results of the analysis are presented in Attachments 1 and 2 for Trains A and B, respectively. Page A-16
-~_ - - _ _ _ . . _ _ _ - _ _ - _ - - - . . - -. _ _ . - - _ - - _
909268/A l i j PROTO POWER CORPORATION cAtc s oa.c.saron 82-08 l "'" "3 c. 3 oars GROTON, CONNECTICUT /7) tie # 10-31-86
- S. Tombesi 7511482 CUENT PROJECT Public Service Co. of G, Fort St. Vrain M ECT Appendix R - Safe' Shutdown Cooling i
- 4. RESULTS Train A 1
1 Flow through PV-22153 Flow - 518 GPM ' i Steam Generator Backpressure - 268.4 psia
; Steam Generator Inlet Temperature - 156*F ,$
Flow through PV-2229, PV-22129 & PV-22153 l Flow - 529 GPM
- ' Steam Generator Backpressure - 264 psia Steam Generator Inlet Temperature - 158 *F i
Train B 1 Flow through PV-22153 j Flow - 707 GPM Steam Generator Backpressure - 103.4 psia . l Steam Generator Inlet Temperature - 85 "F ' Flow through PV-2229, PV-22129 & PV-22153 Flow - 758 GPM Steam Generator Backpressure - 98.6 psia Steam Generator Inlet Temperature - 85 *F 4
- 5. REFERENCES A. Appendix R Evaluation: Fort St. Vrain Nuclear Generating Station, Revision 3, dated April 1, 1985.
1 B. PPC Calculation 82-01, "EES Safe Shutdown Cooling for PSC - Fort St. Vrain", dated September 11, 1986. C. PPC Computer Prog ram "FSVSG" . t Analyze ca Nat E c ' nghPE"daYed a 689.58Fr W,AT%6 i o l Page A-17
1 ope) py'- 22/53 r -
- ~=
444 FILE: TRAIN-A.DAT ***
;: =- ' ' :- - 90 w -A SECTION -
10 -WOIV- K(FIX)- K(VAR)- EPS - EL -FL.- TF - 111f 4 - MAX 55 1 : 306-400 , 7.981, 1, 3.5, 133.4,1.5000-4, -3.5, 1, 156.0, NA , NA 2: 400-401 , 7.981, 0.5, 2.1, 27.6,1.5000-4, -12.8 1, 156.0, NA , NA 3: 401-402 ,12.000, 0.5, 0.1, 1.5,1.5000-4, 0.0, 1, 156.0, NA , tJA 4 : 402-403 ,10.020, 0.5, 1.6, 5.1,1.5000-4, 0.0, 1, 156.0, NA , NA 5: COND Ft1P, NA , 0.5, 0.0, 0.0, NA , 0.0, 9, 156.0 2 , NA 6: 404-405 , 7.981, 0.5, 3.5, 9.6,1.5000-4, 4.3, 1, 156.0, NA , NA 7: 405-406 , 6.065, 0.5, 1.9, 24.1.1.5000-4, 10.9. 1, 156.0, NA , NA 8: 406-407 , 7.981, 0.5, 4.1, 85.9,1.5000-4, 1.5, 1, 156.0, NA , NA 9: 407- 6 , 7.981, 0.5, 1.7, 36.2,1.5000-4, 17.2, 1, 156.0, NA , NA 10: 6-7 , 7.981, 0.5, 2.5, 61.4.1.5000-4, 0.5, 1, 156.0, NA , NA 11: 7-S , 7.870, 1, 5.0, 29.9.1.5000-4, 0.0, 1, 156.0, NA , NA 12: 8-9 , 9.516, 1, 38.6, 68.1,1.5000-4, 4.3, 1, 156.0, NA , NA 13: 9 - 10 , 9.172, 1, 2.7, 136.3,1.5000-4, -60.6, 1, 156.0, NA , NA 14: 10 - 11 , 9.172,1.81, 1.8, 94.2,1.5000-4, -0.3, 1, 156.0, NA , NA 15: 11 - 12 , 3.152, 6, 12.8, 102.1,1.5000-4, 9.0, 1, 156.0, NA , NA 16: 12 - 18 , 3.150, 6, 1.16, 0.00,1.5000-4, 0.0, 1, 156.0, NA , NA . 17: 19 - 19 , 3.346, 6, 1.20. 26.20,1.5000-4, -4.6, 1, 156.0, NA , NA 18: 19 - 20 , 0.886, 100, 104.50, 500.80,8.2020-5, 27.0, 1, 156.0, IJA , NA 19: 20 - 21 , 0.874, 108, 0.01, 12.22,8.2020-5, 0.9 1, 156.0, NA , NA 20: 21 - 22 , 0.898, 324, 1.44, 0.00,8.2020-5, 0.0, 1, 156.0, NA , NA 21: 22 - 23 , 0.724, 324, 210.10, 26.02,8.2020-5, 2.3, 1, 156.0, NA , NA 22: 23 - 23A, 0.724, 324, 0.00,2444.30,8.2020-5, 4.8, 1, 160.0, NA , NA 23: 22A- 238, 0.724, 324, 0.00, 0.00,8.2020-5, 0.0, 1, 160.0, NA , NA 24: 2?S- 24 , 0.724, 324, 0.00, 0.00,8.2020-5, 0.0, 1, 160.0, NA , UA 25: 24 - 244, 0.550, 324, 0.21,1821.70,8.202D-6, 2.7, 1, 187.0, NA , NA 26: 24A- 25 , 0.550, 324, 0.00, 0.00,8.2020-6, 0.0, 1, 187.0, NA , NA 27: 25 - 26 , 0.590, 324, 1.64, 166.78,8.202D-6, 4.6, 1, 212.5, NA , NA 20: 26 - 26A, 0.590, 024, 0.00,1541.40,8.2020-6, -3.3, 1, 306.0, NA , NA 29: 26A- 27 , 0.590, 324, 0.00, 0.00,8.2020-6, 0.0, 1, 306.0, NA , NA 30: 27 - 28 , 0.590, 324, 2.60, 270.10,8.2020-6, -11.0, 1, 400.0, NA , IJA 31: 29 - 29 , 0.768, 108, 0.14, 15.31,8.2020-6, -0.9, 1, 400.0, NA , NA 32: 29 - 30 , 0.969, 109, 2.25, 525.60,8.2020-6, -27.0, 1, 400.0, NA , NA 30: 30 - 31 , 3.603, 6, 1.27, 23.03,1.5000-4, 4.6, 1, 400.0, NA , IJA 34: 31 - 32 , 5.826, 6, 2.7, 208.2,1.5000-4, 49.0, 1, 400.0, NA , ilA 35: 32 - 32A, 9.586, 6, 3.2, 4.2.1.5000-4, 0.0, 1, 400.0, NA , NA 36: 32A- 328, 9.586, 3, 0.3, 16.0,1.5000-4, 0.0, 1, 400.0, NA , NA 37: 328- 33 , 9.566, 2, 0.1, 4.2,1.5000-4, 0.0, 1, 400.0, NA , NA 33: 33 - 33A,10.820, 2, 0.3, 2.8,1.5000-4, 0.0, 1, 400.0, NA , NA 39: 33A- 34A,10.820, 1.5, 0.6, 3.6,1.5000-4, 0.0, 1, 400.0, NA , NA 40: 34A- 348,10.820, 1.2, 1.1, 13.4.1.5000-4, 0.0, 1, 400.0, UA , NA 41: 348- 35 ,10.820, 1, 0.6, 14.2,1.5000-4, 0.0, 1, 400.0, NA , NA 42: 35 - 36 , 5.826, 1, 3.0, 37.6,1.5000-4, 0.0, 1, 400.0, NA , NA 43: FV-2229 , 5.826, 1, 0.0, 0.0,1.5000-4, 0.0, 6, 400.0, 248.0, 0.9 44: 36 - 39 ,11.540, 1, 1.5, 47.6,1.5000-4, 0.0, 1, 400.0, NA , NA 45: 39 - 40 ,10.114, 1, 0.5, 11.1.1.5000-4, 18.8, 1, 400.0, NA , NA 46: 40 - 41 ,12.500, 1, 2.3, 70.9.1.5000-4, 15.7, 1, 400.0, NA , NA 47: 41 -300 ,14.312, 1, 0.0, 2.9,1.5000-4, 0.0, 1, 400.0, NA , NA 48: 300-301 , 4.026, 1, 6.3, 264.7,1.5000-4, -32.8, 1, 400.0, NA , IJA 49: 301-302 , 7.981, 1, 3.8 137.0,1.5000-4, -6.0, 1, 400.0, NA , NA 50:HV-3200-6, 7.981, 1, 0.0, 0.0,1.5000-4, 0.0, 6, 400.0, 870.0, 0.9 51: 302-303 , 7.981, 1, 1.7, 20.9,1.5000-4, -3.8, 1, 400.0, NA , NA I 52: DECAY HX, 7.981, 1, 56.2, 0.0.1.5000-4, -4.3, 1, 278.0, NA , NA l 53: 304-305 , 6.065, 1, 3.3, 93.4,1.5000-4, -4.1, 1, 156.0, NA , NA 54:LV-3250-2, 6.065, 1, 0.0, 0.0,1.5000-4, 0.0, 6, 156.0, 34.15, 1.0 55: 305-306 , 6.065, 1, 3.9, 214.7,1.5000-4, -3.2, 1, 156.0, NA , NA Page A-18
- *- !-S 909268/A g .C .:,
ri], - l PA6rd" 2 GEh FLOW = 518 GPM AT 100F7 USE PUMP CURVE COR ENTER PRESSURE 3 (Y/N):N? STARTING PRE 3SURE = 12.3 PSIA? FELTON WHEEL FLOW = 125 GPM? FILE: TRAIN-A.DAT - NO. OF SECTIONS = 55 - TWO-PHASE SECTION5' DIVIDER = 10 SECTION ID K FLOW P(IN) P(0UT) 1 : 306-400 7.981 5.6 259,000 12.3 13.4 2: 400-401 7.981 2.5 321,500 13.4 18.5 3: 401-402 12.000 0.1 321,500 18.5 18.5 4 : 402-403 10.020 1.7 321,500 18.5 18.4 5: COND PMP 1.000 0.0 321,500 18.4 300.4 6: 404-405 7.981 3.6 321,500 300.4 298.2 7: 405-406 6.065 2.3 321,500 298.2 292.7 8: 406-407 7.981 5.4 321,500 292.7 291.5 9: 407- 6 7.981 2.3 321,500 291.5 283.9 10: 6-7 7.981 3.4 321,500 283.9 283.3 11: 7-8 7.870 5.5 259,000 283.3 282.9 12: 8-9 9.516 39.7 259,000 282.9 279.5 13: 9 - 10 9.172 4.8 259,000 279.5 305.0
** PRESS <CR) TO CONTINUE **
r SECTION 10 K FLOW P(IN) P(OUT) 14: 10 - 11 9.172 3.4 143,094 305.0 305.1 15: 11 - 12 3.152 14.7 43,167 305.1 300.0 16: 12 - 18 3.150 1.2 43,167 300.0 299.9 17: 18 - 19 3.346 1.7 43,167 299.9 301.8 18: 19 - 20 0.886 117.0 2,398 ,301.8 285.3 19: 20 - 21 0.874 0.3 2,398 285.3 284.9 20: 21 - 22 0.898 1.4 799 264.9 284.9 21: 22 - 23 0.724 210.9 799 284.9 281.7 22: 23 - 23A 0.724 71.7 799 281.7 278.9 23: 23A- 238 0.724 0.0 799 278.9 278.9 24: 228- 24 0.724 0.0 799 278.9 278.9 25: 24 - 24A 0.550 44.6 799 278.9 276.3 26: 24A- 25 0.550 0.0 799 276.3 276.3 27: 25 - 26 0.590 5.6 799 276.3 274.3
' 28: 26 - 26A 0.590 33.3 799 274.3 274.7 29: 26A- 27 0.590 0.0 799 274.7 274.7
. 30: 27 - 28 0.590 8.0 799 274.7 278.6 31: 28 - 29 0.768 0.4 2,398 278.6 278.9 32: 29 - 30 0.969 11.5 2,398 278.9 288.6 33: 30 - 31 3.803 1.7 43,167 288.6 286,8 34: 31 - 32 5.826 6.2 43,167 286.8 268.5
** PRESS (CR) TO CONTINUE **
l l Page A-19 [
v p;- Q , # E / 909268/A i% c, c : Cr ', f SECTION 10 K FLOW P(IN) P(OUT) 35: 32 - 32A 9.586 3.3 43,167 268.5 268.5 06: 32A- 328 9.586 0.5 66,333 268.5 268.5 37: 328- 33 9.586 0.2 129,500 268.5 268.5 38: 33 - 33A 10.820 0.3 129,500 268.5 268.5 09: 32A- 34A 10.820 0.7 172,667 268.5 268.4 40: 34A- 348 10.820 1.3 215,833 268.4 260.4 41: 348- 35 10.820 0.8 259,000 268.4 268.4 42: 35 - 36 5.826 3.6 259,000 266.4 267.3 43: PV-2229 5.826 0.0 259,000 267.3 262.2(W= 725,320 OP= 39.8 X= 0.9) 44: 36 - 39 11.540 2.2 259,000 262.2 262.2 45: 39 - 40 10.114 0.7 259,000 262.2 255.2 46: 40 - 41 12.500 3.3 259,000 255.2 249.3 47: 41 -300 14.312 0.0 259,000 249.3 249.3 48: 300-301 4.026 10.7 259,000 249.3 247.3 49: 301-302 7.981 5.8 259,000 247.3 249.0 50:HV-3220-6 7.981 0.0 259,000 249.0 248.6(W=2,016,687 DP= 25.0 X= 1.1) 51: 302-303 7.981 2.0 259,000 248.6 249.9 52: DECAY HX 7.981 56.2 259,000 249.9 247.1 53: 304-3')5 6.065 4.8 259,000 247.1 247.8 54:LV-3250-2 6.065 0.0 259.000 247.8 12.7(W= 263,698 OP=243.7 X= 0.2) 55: 305-306 6.065 7.3 259,000 12.7 12.4
** FRE55URE AT END OF SYSTEM = 12.4 PSIA REFEAT WITH NEW CON 0!TIONS (Y/N)?
Page A-20 _ _ _ , . . . -- * ~ - '
_ _, . . . . . -- .._ 909268/A j:q)-ggy' hi-2.2./ 2 R ,"/~' 4 4 -Q ;
' ~R L'
-- '%~=^. ' '
i
*** FILE: TRAIN-A.DAT ***
PS. r :.= G 1 i J SECTION - 10 -WO!V- K(FIX)- K(VAR)- EPS - EL -FL.- TF - MIN - MAX i 55 i 1: 306-400 , 7.981, 1, 3.5, 133.4.1.5000-4, -3.5, 1, 158.0, NA , NA t 2: 400-401 , 7.981, 0.5, 2.1, 27.6.1.5000-4, -12.8, 1, 158.0, NA , NA : 3: 401-402 ,12.000, 0.5, 0.1, 1.5.1.5000-4, 0.0, 1, 158.0, NA , NA 4 : 402-403 ,10.020, 0.5, 1.6, 5.1,1.5000-4, 0.0, 1, 158.0, NA , NA 5: CONO PNP, NA , 0.5, 0.0, 0.0, NA , 0.0, 9, 158.0 2 , NA j 6: 404-405 , 7.981, 0.5, 3.5, 9.6.1.5000-4, 4.3, 1, 158.0, NA , NA i 7: 405-406 , 6.065, 0.5, 1.9, 24.1,1.5000-4, 10.9. 1, 158.0, NA , NA j 8: 406-407 , 7.981, 0.5, 4.1, 85.9,1.5000-4, 1.5, 1, 158.0, NA , NA i 9: 407- 6 , 7.981, 0.5, 1.7, 36.2.1.5000-4, 17.2, 1, 158.0, NA , NA
- 10: 6-7 , 7.981, 0.5, 2.5, 61.4.1.5000-4, 0.5, 1, 158.0, NA , NA
! 11: 7-8 , 7.870, 1, 5.0, 29.9.1.5000-4, 0.0, 1, 158.0, NA , NA l 12: 8-9 9.516, 1, 38.6, 68.1.1.5000-4, 4.3, 1, 158.0, NA , NA i 13: 9 - 10 , 9.172, 1, 2.7, 136.3.1.5000-4, -60.6, 1, 158.0, NA , NA l 14: 10 - 11 , 9.172,1.81, 1.8, 94.2.1.5000-4, -0.3, 1, 158.0, NA , NA 15: 11 - 12 , 3.152, 6, 12.8 102.1.1.5000-4, 9.0, 1, 158.0, NA , NA - 16: 12 - 18 , 3.150, 6, 1.16, 0.00,1.5000-4, 0.0, 1, 158.0, NA , NA 17: 18 - 19 , 3.346, 6, 1.20, 26.20,1.5000-4, -4.6. 1, 158.0, NA , NA ] 18: 19 - 20 , 0.886, 108, 104.50, 500.80,8.2020-5, 27.0, 1, 158.0, NA , NA j 19: 20 - 21 , 0.874, 108, 0.01, 12.22,8.2020-5, 0.9, 1, 158.0, NA , NA 1 20: 21 - 22 , 0.898, 324, 1.44, 0.00,8.2020-5, 0.0, 1, 158.0, NA , NA l 21: 22 - 23 , 0.724, 324, 210.10, 26.02.8.2020-5, 2.3, 1, 158.0, NA , NA 22: 23 - 23A, 0.724, 324, 0.00,2444.30,8.2020-5, 4.8, 1, 161.0, NA , NA l; 23: 23A- 238, 0.724, 324, 0.00, 0.00,8.2020-5, 0.0, 1, 161.0, NA , NA 24: 238- 24 , 0.724, 324, 0.00, 0.00,8.2020-5, 0.0, 1, 161.0, NA , WA i 25: 24 - 24A, 0.550, 324, 0.21,1821.70,8.2020-6, 2.7 1, 189.0, NA , NA i 26: 24A- 25 , 0.550, 324, 0.00, 0.00,8.2020-6, 0.0, 1, 189.0, NA , NA ! 27: 25 - 26 , 0.590, 324, 1.64, 166.78,8.2020-6, 4.6, 1, 214.0, NA , NA 28: 26 - 26A, 0.590, 324, 0.00,1541.40,8.2020-6, -3.3, 1, 307.0, NA , NA
! 29: 26A- 27 , 0.590, 324, 0.00, 0.00,8.2020-6, 0.0, 1, 307.0, NA , NA j 30: 27 - 28 , 0.590, 324, 2.60, 270.10,8.2020-6, -11.0, 1, 400.0, NA , NA i
31: 28 - 29 , 0.768, 108, 0.14, 15.31,8.2020-6, -0.9, 1, 400.0, NA , NA 32: 29 - 30 , 0.969, 108, 2.25, 525.60,8.2020-6, -27.0, 1, 400.0, NA , NA
! 03; 30 - 31 , 3.803, 6, 1.27, 23.03,1.5000-4, 4.6, 1, 400.0, NA ,
34: 31 - 32 , 5.826, NA
- 6, 2.7, 208.2,1.5000-4, 49.0, 1, 400.0, NA , NA 1
35: 32 - 32A, 9.586, 6, 3.2, 4.2.1.5000-4, 0.0, 1, 400.0, NA , NA I 36: 32A- 328, 9.586, 3, 0.3, 16.0.1.5000-4, 0.0, 1, 400.0, NA , NA 37: 328- 33 , 9.586, 2, 0.1, 4.2.1.5000-4, 0.0; 1, 400.0, NA , NA 38: 33 - 30A,10.820, 2, 0.3, 2.8,1.5000-4, 0.0, 1, 400.0, NA , NA 39: 30A- 34A,10.820, 1.5, 0.6, 3.6.1.5000-4, 0.0, 1, 400.0, NA , NA 40: 34A- 348,10.820, 1.2, 1.1, 13.4.1.5000-4, 0.0, 1, 400.0, NA , NA J 41: 348- 35 ,10.820, 1, 0.6, 14.2,1.5000-4, 0. 0,' 1, 400.0, NA , NA
, 42: 35 - 36 , 5.826, 2, 3.0, 37.6.1.5000-4, 0.0, 1, 400.0, NA , NA i 43: PV-2229 , 5.826, 2, 0. 0, 0.0,1.5000-4, 0.0, 6, 400.0, 299.0, 0.9 44: 36 - 39 ,11.540, 1, 1.5, 47.6.1.5000-4, 0.0, 1, 400.0, NA , NA i 45: 39 - 40 ,10.114, 1, 0.5, 11.1.1.5000-4, 18.8 1, 400.0, NA , NA 1
46: 40 - 41 .12.500, 1, 2.3, 70.9.1.5000-4, 15.7, 1, 400.0, NA , NA l 47: 41 -300 ,14.312, 1, 0.0, 2.9,1.5000-4, 0.0, 1, 400.0, NA , NA i 48: 300-301 , 4.026, 1, 6.3, 264.7,1.5000-4, -32.8 1, 400.0, NA , NA 1 49: 301-302 , 7.981, 1, 3.8 137.0.1.5000-4, -6.0, 1, 400.0, NA , NA 4 50:HV-3220-6, 7.981, 1, 0.0, 0.0,1.5000-4, 0.0, 6, 400.0, 870.0, 0.9 j 51: 302-303 , 7.981, 1, 1.7 20.9,1.5000-4, -3.8 1, 400.0, NA , NA 52: DECAY HX, 7.981, 1, 56.2, 0.0,1.5000-4, -4.3, 1, 279.0, NA , NA i 53: 304-305 , 6.065, 1, 3.3, 93.4.1.5000-4, -4.1, 1, 158.0, NA , NA
! 54:LV-3250-2, 6.065, 1, 0.0, 0.0,1.5000-4, 0.0, 6, 158.0, 34.95, 1.0 55: 305-306 , 6.065, 1, 3.9, 214.7,1.5000-4, -3.2, 1, 158.0, NA , NA i
l 1 1 i Page A-21 ? _
U
,_ .j 909268/A k U/-:~// h!T /
76 6~ CF G FLOW = 529.5 GPM AT 100F7 USE FUMP CURVE COR ENTER PRESSURE] (Y/N):N? STARTING ~ PRESSURE = 12.3 PSIA 7 FELTON WHEEL FLOW = 125 GPM7 FILE: TRAIN-A.DAT - NO. OF SECTIONS = 55 - TWO-PHASE SECTIONS' DIVIDER = 10 SECTION 10 K FLOW P(IN) P(OUT) 1 : 306-400 7.981 5.6 264,750 12.3 13.3 2: 400-401 7.981 2.5 327,250 13.3 18.5 3: 401-402 12.000 0.1 327,250 18.5 18.5 4 : 402-403 10.020 1.7 327,250 18.5 18.4
; 5: CONO PMP 1.000 0.0 327,250 18.4 296.8 6: 404-405 7.981 3.6 327,250 296.8 294.5 7: 405-406 6.065 2.3 327,250 294.5 289.1 8: 406-407 7.981 5.4 327,250 289.1 287.8 9: 407- 6 7.981 2.3 327,250 287.8 280.2 10: 6-7 7.981 3.4 327,250 280.2 279.6 11: 7-8 7.870 5.5 264,750 279.6 279.1 12: 8-9 9.516 39.7 264,750 279.1 275.7 13: 9 - 10 9.172 4.8 264,750 275.7 301.2
** PRES 3 <CR) TO CONTINUE **
SECTION ID K FLOW P(IN) P(OUT) 14: 10 - 11 9.172 3.4 146,271 301.2 301.3 15: 11 - 12 3.152 14.7 44,125 301.3 296.1 16: 12 - 18 3.150 1.2 44,125 296.1 296.0 17: 18 - 19 3.346 1.7 44,125 .296.0 297.9 18: 19 - 20 0.886 116.9 2,451 297.9 281.2 19: 20 - 21 0.874 0.3 2,451 281.2 280.8 20: 21 - 22 0.898 1.4 817 280.8 280.8 21: 22 - 23 0.724 210.9 817 280.8 277.5 22: 23 - 23A 0.724 71.3 817 277.5 274.6 . 23: 22A- 238 0.724 0.0 817 274.6 274.6 24: 238- 24 0.724 0.0 817 274.6 274.6 25: 24 - 24A 0.550 44.3 817 274.6 272.0 26: 24A- 25 0.550 0.0 817 272.0 272.0 27: 25 - 26 0.590 5.6 817 272.0 270.0 28: 26 - 26A 0.590 33.1 817 270.0 270.4 29: 26A- 27 0.590 0.0 817 270.4 270.4 30: 27 - 28 0.59) 8.0 817 270.4 274.3 01: 28 - 29 0.768 0.4 2,451 274.3 274.5 32: 29 - 30 0.969 11.4 2,451 274.5 284.2 33: 30 - 31 3.803 1.7 44,125 284.2 282.4 34: 31 - 32 5.826 6.2 44,125 282.4 264.1
** PRESS <CR) TO CONTINUE ** l l
l Page A-22 l
909268/A kII$dNUE/ T i
#6 6 0/: 6, SECTION 10 K FLOW P(IN) P(OUT) 05: 32 - 32A 9.586 3.3 44,125 264.1 264.1 36: 32A- 328 9.586 0.5 88,250 264.1 264.1 37: 328- 33 9.586 0.2 132,375 264.1 264.1 38: 33 - 33A 10.820 0.3 132,375 264.1 264.1 39: 33A- 34A 10.820 0.7 176,500 264.1 264.1 40: 34A- 348 10.820 1.3 220,625 264.1 264.1 41: 348- 35 10.820 0.8 264,750 264.1 264.0 42: 35 - 36 5.826 3.6 132,375 264.0 263.8 43: PV-2229 5.826 0. 0' 132,375 263.8 262.8(W= 842,142 DP= 36.9 X= 1.0) 44: 36 - 39 11.540 2.2 264,750 262.8 262.8 45: 39 - 40 10.114 0.7 264,750 262.8 255.8 46: 40 - 41 12.500 3.3 264,750 255.8 249.9 47: 41 -300 14.312 0.0 264,750 249.9 249.9 48: 300-301 4.026 10.7 264,750 249.9 247.3 49: 301-302 7.981 5.8 264,750 247.3 249.0 50:HV-3220-6 7.981 0.0 264,750 249.0 248.6(W=2,014,505 OP= 24.9 X= 1.1) t 51: 302-303 7.981 2.0 264,750 248.6 249.8 52: DECAY HX 7.981 56.2 264,750 249.8 246.8 53: 304-305 6.065 4.8 264,750 246.8 247.4 54:LV-3250-2 6.065 0.0 264,750 247.4 12.8(W= 269,486 OP=243.1 X= 0.2) 55: 305-306 6.065 7.3 264,750 12.8 12.4
** PRESSURE AT END OF SYSTEM = 12.4 PSIA REPEAT WITH NEW CONDITIONS (Y/N)?
[ i l l I 1 l l l l l Page A-23
909268/A - Mun -4.w 4
~)9()- 2. 2. /5' 3 CPE%{
t
*** FILE: TRAIN-B.DAT *** '
-WDIV- Kt.F1X)- K(VAR)- - NAX SECTION -
10 EPS - EL -FL.- 1F - MIN 50 1 : 1 - 17 .10.000, 0.5, 19.0, 649.3.1.5000-4, 10.8. 1, 85.0, NA , UA 2: 17 - 7 , 7.981, 0.5, 7.5, 139.0.1.5000-4, 17.7, 1, 85.0, NA , N4 3: 7-8 . 7.870, 1, 5.0, 29.9.1.5000-4, 0.0, 1, 85.0, NA , UA 4 : 8-9 , 9.516, 1, 38.6, 68.1,1.5000-4, 4.3, 1, 85.0, NA , NA 5: 9 - 10 , 9.172, 1, 2.7, 136.3.1.5000-4, -60.6, 1, 85.0, NA , NA 6: 10 - 11 , 9.17?.1.81, 1.8, 94.2.1.5000-4, -0.3, 1, 85.0, NA , NA 7 : 11 - 12 , 3.152, 6, 12.8, 102.1.1.5000-4, 9.0, 1 ,. 85.0, NA , NA
'S: 12 - 18 , 3.159, 6, 1.16, 0.00,1.5000-4, 0.0, 1, 85.0, NA , NA 9: 18 - 19 , 3.346, 6, 1.20, 26.20,1.5000-4, -4.6, 1, 85.0, NA , NA 10: 19 - 20 , 0.886, 108, 104.50, 500.80,8.2020-5, 27.0, 1, 85.0, NA , NA 11: 20 - 21 , 0.874, 198, 0.01, 12.22,8.2020-5, 0.9. 1, 85.0, NA , NA 12: 21 - 22 , 0.898, 324, 1.44, 0.00,8.2020-5, 0.0, 1, 85.0, NA , NA 13: 22 - 23 , 0.724, 324, 210.10, 26.02,8.2020-5, 2.3, 1, 85.0, NA , NA 14: 23 - 2?A, 0.724, 304, 0.00,2444.30,8.2020-5, 4.8. 1, 87.4, NA , NA 15: 23A- 238, 0.724, 324, 0.00, 0.00,8.2020-5, 0.0, 1, 87.4, NA , UA i
16: 238- 24 , 0.724, 324, 0.00, 0.00,8.2020-5, 0.0, 1, 87.4, NA , UA i' 17: 24 - 24A, 0.550, 324, 0.21,1821.70,8.2020-6, 2.7, 1, 109.3, NA , NA 18: 24A- 25 , 0.550, 324, 0.00, 0.00,8.2020-6, 0.0, 1, 109.3, HA , NA 19: 25 - 26 , 0.590, 324, 1.64, 166.78,8.2020-6, 4.6, 1, 128.8, NA , NA i 20: 26 - 26A, 0.599, 324, 0.00,1541.40,8.2020-6, -3.3, 1, 214.4, NA , NA I 21: 26A- 27 , 0.590, 324, 0.00, 0.00,8.2020-6, 0.0, 1, 214.4, NA , NA 22: 27 - 28 , 0.590, 324, 2.60, 270.10,8.2020-6, -11.0, 1, 300.0, NA i NA i 23: 28 - 29 , 0.768, 108, 0.14, 15.31,8.2020-6, -0.9. 1, 300.0, NA , NA l 24: 29 - 30 , 0.969, 108, 2.25, 525.60,8.2020-6, -27.0, 1, 300.0, NA , UA l 25: 30 - 31 , 3.803, 6, 1.27, 23.03.1.5000-4, 4.6, 1, 300.0, UA , NA l 26: 31 - 32 , 5.826, 6, 2.7, 208.2.1.5000-4, 49.0, 1, 300.0, NA , NA 27: 32 - 32A, 9.586, 6, 3.2, 4.2,1.5000-4, 0.0, 1, 300.0, NA , UA 28: 32A- 32D, 9.586, 3, 0.3, 16.0,1.5000-4, 0.0, 1, 000.0, NA , NA 29: 328- 33 , 9.586, 2, 0.1, 4.2,1.5000-4, 0.0, 1, 300.0, NA , NA 30: 33 - 33A,10.829, 2, 0.3, 2.8,1.5000-4, 0.0, 1, 300.0, NA , NA 31: 33A- 34A 10.820, 1.5, 0.6, 3.6,1.5000-4, 0.0, 1, 300.0, NA , NA 32: 34A- 34H,10.820, 1.2, 1.1, 13.4,1.5000-4, 0.0, 1, 300.0, NA , NA 39: 348- 35 ,10.829, 1, 0.6, 14.2.1.5000-4, 0.0, 1, 000.0, NA , NA 34: 35 - 36 , 5.826, 1, 3.0, 37.6,1.5000-4, 0.0, 1, 300.0, NA , NA 35: PV-2229 , 5.826, 1, 0.0, 0.0,1.5000-4, 0.0, 6, 300.0, 248.0, 0.9 , 36: 36 - 39 ,11.540, 1, 1.5, 47.6,1.5000-4, 0.0, 1, 300.0, NA , NA' 37: 39 - 40 ,10.114, 1, 0.5, 11.1,1.5000-4, 18.8, 1, 300.0,- NA , NA 3S: 40 - 41 ,12.500, 1, 2.3, 70.9,1.5000-4, 15.7, 1, 300.0, NA , NA 39: 41 -300 ,14.312, 1, 0.0, 2.9,1.5000-4, 0.0, 1, 300.0, NA , NA 40: 300-301 , 4.026, 1, 6.3,. 264.7,1.5000-4, -32.8. 1, 300.0, NA , NA 41: 301-302 , 7.981, 1, 3.8, 137.0,1.5000-4, -9.8. 1, 300.0, NA , NA 42:HV-3220-6, 7.981, 1, 0.0, 0.0,1.5000-4, 0.0, 6, 300.0, 870.0, 0.9 43: 302-303 , 7.981, 1, 1.7, 20.9,1.5000-4, -3.8. 1, 300.0, NA , NA 44:CECAY HX, 7.981, 1, 56.2, 0.0.1.5000-4, -4.3, 1, 232.0, NA , UA 45: 304-305 , 6.065, 1, 3.3, .93.4.1.5000-4, -4.1, 1, 164.0, NA , NA 46:LV-3250-2, 6.065, 1, 0.0, 0.0,1.5000-4, 0.0, 6, 164.0, 124.0, 0.9 47: 305-306 , 6.065, 1, 3.9, 214.7,1.5000-4, -3.2, 1, 164.0, UA , NA 48:'306-307 , 7.981, 0.5, 0.5, 13.0,1.5000-4, 0.0, 1, 164.0, UA , UA 49: 307-308 ,12.009, 0.5, 2.8, 12.5,1.5000-4, 2.4, 1, 164.0, UA , NA 50: 303-309 ,12.000, 0.5, 2.7, 39.8,1.5000-4, 12.2, 1, 164.0, UA , NA l Page A-24 l
l
.~ ~M c,/., /_ 9J9268/A
- l
.~ g', l FLOW = 707 GFil AT 1055 ? N EO $ .
USE PUf1P CURVE COR EIJiER FRE55URE] (Y/N):Y? FIRE WATERt.=1), CorJOElJSATE(=2) OR IACM(=3) PUMP: 1? PUMP (S) ARRANGEitEf1T (Of4E=0 - PARALLEL =1 - SERIES =2): 0? PELTOf1 WHEEL FLOU = 125 GFM? FLOW 4 PUMP = 832.00 GPf1 AT 100F PU:1P HEAD = 104.57 FT/ STAGE FILE:TRAlfJ-B.DAT - fJ0. OF SECTIONS = 50 - TWO-PHASE SECTION5' DIVIDER = 10 SECTION 10 I: FLOW. F(IN) P(OUT) 1 : 1 - 17 10.020 29.4 416,000 147.7 140.8 2: 17 - 7 7.981 9.7 416,000 140.8 131.3 3: 7-S 7.870 5.5 353,500 131.3 130.5 ' a: 8-9 9.516 39.7 353,500 130.5 125.9 5: 9 - 10 9.172 4.9 353,500 125.9 151.7 6: 10 - 11 9.172 3.5 195,304 151.7 151.7 7: 11 - 12 3.152 14.8 58,917 151.7 145.5 8: 12 - 18 3.150 1.2 58,917 145.5 145.3 9: 18 - 19 3.346 1.7 58,917 145.3 147.1 10: 19 - 20 0.886 117.7 3,273 147.1 126.2 11: 20 - 21 0.874 0.3 3,273 126.2 125.8 12: 21 - 22 0.899 1.4 1,091 125.8 125.8
** PRE 58 <CR) TO CONTINUE **
i SECTION 10 K FLOW P(IN) P(OUT) 13: 22 - 23 0.724 210.9 1,091 125.8 120.7 14: 23 - 23A 0.724 77.2 1.091 120.7 117.1 15: 23A- 238 0.724 19 . 0' 1,091 117.1 117.1 16: 238- 24 0.724 '0 . 0 1,091 117.1 117.1 17: 24 - 24A 0.550 47.8 1,091 117.1 113.1 18: 24A- 25 0.550 0.0 1,091 113.1 113.1 19: 25 - 26 0.590 5.9 1,091 113.1 110.9 20: 26 - 26A 0.590 34.4 1,091 110.9 110.7 21: 26A- 27 0.590 0.0 1,091 110.7 110.7 22: 27 - 28 0.590 8.1 1,091 110.7 114.7 23: 28 - 29 0.768 0.4 3,273 114.7 115.0 24: 29 - 30 0.969 11.7 3,273 115.0 125.0 25: 30 - 31 3.803 1.7 58,917 125.0 123.1 26: 31 - 32 5.826 6.2 58,917 123.1 103.5 27: 32 - 32A 9.586 3.3 58,917 103.5 103.5 28: 32A- 320 9.586 0.5 117,833 103.5 103.5 29: 328- 33 9.586 0.2 176,750 103.5 103.5 30: 33 - 33A 10.820 0.3 176,750 103.5 103.5 31: 33A- 34A 10.820 0.7 235,667 103.5 103.5 32: 34A- 34H 10.820 1.3 294,583 103.5 103.4 33: 348- 35 10.820 0.8 353,500 103.4 103.4
** PRESS (CR) TO C0lJTINUE **
Page A-25
909268/A h ~~$ U'#ER's~ 2. lb 2 0f & 5ECT10N 10 K FLOW P(IN) P(OUT) 04: 35 - 36 5.826 3.6 353,500 103.4 101.5 35: PV-2229 5.826 0.0 353,500 101.5 92.6(W= 675,264 DP= 32.3 X= 0.0) 36: 36 - 39 11.549 2.2 353,500 92.6 92.6 37: 39 - 40 10.114 0.7 353.500 92.6 85.0 38: 40 - 41 12. 500 3.3 353,500 85.0 78.7 39: 41 -300 14.312 0.0 353,500 78.7 78.7 40: 300-301 4.026 10.7 353,500 78.7 67.0 41: 301-302 7.981 5.8 353,500 67.0 70.0 42:HV-3220-6 7.981 0.0 353,500 70.0 69.3(W=1,088,829 OP= 6.8 X:. 0.41 43: 302-303 7.981 2.0 353,500 69.3 70.5 44:0ECAY HX 7.981 56.2 353.500 70.5 64.1 45: 304-305 6.065 4.8 353,500 64.1 63.9 46:LV-3250-2 6.065 0.0 353,500 63.9 30.5(W= 423,134 OP= 47.7 X= 0.0) 47: 305-306 6.065 7.3 353.500 30.5 28.8 48: 306-307 7.981 0.7 416'000
, 28.8 28.7 49: 307-308 12.000 3.0 416,000 28.7 27.6 50: 308-309 12.000 3.3 416,000 27.6 22.3 ** PRES $URE AT END OF 5YSTEM = 22.3 PSIA
. REPEAT WITH NEW CONDITIONS (Y/N)? Page A-26
. 909268/A
~
_&Ef/)7 2 py 2zz9, 7y- 22./ 2 9, N - 2. 2./53 CFD) Y6 Y Cf~6
*** FILE: TRAIN-8.0AT ***
SECTION - 10 -WOIV- K(FIX)- K(VAR)- EPS - EL -FL.- TF - MIN - MAX 50 1 : 1 - 17 ,10.020, 0.5, 19.0, 649.3.1.5000-4, 10.8. 1, 85.0, NA , NA 2: 17 - 7 , 7.981, 0.5, 7.5, 139.0.1.5000-4, 17.7, 1, 85.0, NA , NA 3: 7-8 , 7.870, 1, 5.0, 29.9,1.5000-4, 0.0, 1, 85.0, NA , NA 4 : 8-9 , 9.516, 1, 38.6, 68.1.1.5000-4, 4.3, 1, 85.0, NA , NA 5: 9 - 10 , 9.172, 1, 2.7, 136.3.1.5000-4, -60.6, 1, 85.0, NA , NA 6: 10 - 11 , 9.172,1.81, 1.8, 94.2,1.5000-4, -0.3, 1, 85.0, NA , NA i 7 11 - 12 , 3.152, 6, 12.8 102.1.1.5000-4, 9.0, 1, 85.0, NA , NA 8: 12 - 18 , 3.150, 6, 1.16, 0.00,1.5000-4, 0.0, 1, 85.0, NA , NA 9: 18 - 19 , 3.346, 6, 1.20, 26.20,1.5000-4, -4.6, 1, 85.0, NA , NA 10: 19 - 20 , 0.886, 108, 104.50, 500.80,8.2020-5, 27.0, 1, 85.0, NA , NA , 11: 20 - 21 , 0.874, 108, 0.01, 12.22,8.2020-5, 0.9. 1, 85.0, NA , NA 12: 21 - 22 , 0.898, 324, 1.44, 0.00,8.2020-5, 0.0, 1, 85.0, NA , NA 13: 22 - 23 , 0.724, 324, 210.10, 26.02,8.202D-5, 2.2, 1, 85.0, NA , NA 14: 23 - 23A, 0. 724, 324, 0.00,2444.30,8.2020-5, 4.8, 1, 87.6, NA , NA 15: 23A- 238, 0.724, 324, 0.00, 0.00,8.2020-5, 0.0, 1, 87.6, NA , NA 16: 238- 24 , 0.724, 324, 0.00, 0.00,8.2020-5, 0.0, 1, 87.6, NA , NA 17: 24 - 24A, 0.550, 324, 0.21,1821.70,8.2020-6, 2.7, 1, 109.8, NA , NA 18: 24A- 25 , 0.550, 324, 0.00, 0.00,8.2020-6, 0.0, 1, 109.8, NA , NA 19; 25 - 26 , 0.590, 324, 1.64, 166.78,8.2020-6, 4.6, 1, 129.4, NA , NA 20: 26 - 26A, 0.590, 324, 0.00,1541.40,8.2020-6, -3.3, 1, 214.7, NA , NA 21: 26A- 27 , 0.590, 324, 0.00, 0.00,8.2020-6, 0.0, 1, 214.7, NA , NA 22: 27 - 28 , 0.590, 324, 2.60, 270.10,8.2020-6, -11.0, 1, 300.0, NA , NA 23: 28 - 29 , 0.768, 108, 0.14, 15.31,8.2020-6, -0.9 1, 300.0, NA , NA 24: 29 - 30 , 0.969, 108, 2.25, 525.60,8.2020-6, -27.0, 1, 300.0, NA , NA 25: 30 - 31 , 3.803, 6, 1.27, 23.03,1.5000-4, 4.6, 1, 300.0, NA , NA 26: 31 - 32 , 5.826, 6, 2.7 208.2.1.5000-4, 49.0, 1, 300.0, NA , NA 27: 32 - 32A, 9.586, 6, 3.2, 4.2.1.5000-4, 0.0, 1, 300.0, NA , NA 28: 32A- 328, 9.586, 3, 0.3, 16.0,1.5000-4, 0.0, 1, 300.0, NA , NA i 29: 320- 33 , 9.586, 2, 0.1, 4.2,1.5000-4, 0.0, 1, 300.0, NA , NA 30: 33 - 33A,10.820, 2, 0.3, 2.8,1.5000-4, 0.0, 1, 300.0, NA , NA 31: 33A- 34A,10.820, 1.5, 0.6, 3.6,1.5000-4, 0.0, 1, 300.0, NA , NA 32: 34A- 348,10.820, 1.2, 1.1, 13.4.1.5000-4, 0.0, 1, 300.0, HA , HA 33: 348- 35 ,10.820, 1, 0.6, 14.2.1.5000-4, 0.0, 1, 300.0, NA , NA 34: 35 - 36 , 5.826, 2, 3.0, 37.6,1.5000-4, 0.0, 1, 300.0, NA , NA 35: PV-2229 , 5.826, 2, 0.0, 0.0.1.5000-4 0.0, 6, 000.0, 299.0, 0.9 36: 36 - 39 ,11.540, 1, 1.5, 47.6.1.5000-4, 0.0, 1, 300.0, NA , NA 37: 39 - 40 ,10.114, 1, 0.5, 11.1.1.5000-4, 18.8, 1, 300.0, NA , NA 33: 40 - 41 ,12.500, 1, 2.3, 70.9,1.5000-4, 15.7, 1, 300.0, NA , NA 39: 41 -300 ,14.312, 1, 0.0, 2.9.1.5000-4, 0.0, 1, 300.0, NA , NA 40: 300-301 , 4.026, 1, 6.3, 264.7,1.5000-4, -32.8, 1, 300.0, NA , NA 41: 301-302 , 7.981, 1, 3.8, 137.0,1.5000-4, -9.8, 1, 300.0, NA , NA 42:HV-3220-6, 7.981, 1, 0.0, 0.0,1.5000-4, 0.0, 6, 300.0, 870.0, 0.9 43: 302-303 , 7.981, 1, 1.7, 20.9.1.5000-4, -3.8, 1, 300.0, NA , NA 44:0ECAY HX, 7.981, 1, 56.2, 0.0,1.5000-4, -4.3, 1, 235.5, NA , HA 45: 304-305 , 6.065, 1, 3.3, 93.4,1.5000-4, -4.1, 1, 171.0, NA , NA 46:LV-3250-2, 6.065, 1, 0.0, 0.0.1.5000-4, 0.0, 6, 171.0, 138.2, 0.9 47: 305-306 , 6.065, 1, 3.9, 214.7,1.5000-4, -3.2, 1, 171.0, NA , NA 48: 306-307 , 7.981, 0.5, 0.5, 13.0.1.5000-4, 0.0, 1, 171.0, NA , NA 49: 307-308 ,12.000, 0.5, 2.8, 12.5.1.5000-4, 2.4, 1, 171.0, NA , NA 50: 308-309 .12.000, 0.5, 2.7, 39.8,1.5000-4, 12.2, 1, 171.0, NA , NA l Page A-27
--i- w , - , - . - - -
-- - . - , , . ,,-,.v.--- -, .c _ _ _ - - - . - _ - - - - , - - -
h 0 305AI 2 FLOW = 758 GFt1 AT 100F: USE PUMP CURVE COR ENTER PRESSURE] (Y/N):Y? 4 g gj:: g FIRE WATER (=1), CONDENSATE (=2) OR IACM(=3) PUMP: 1? FUMP(S) ARRANGEMENT (ONE=0 - PARALLEL =1 - SERIES =2): 0? FELTON WHEEL FLOW = 125 GFM? FLOW 0 PUMP = 883.00 GPM AT 100F FUMP HEAD = 104.37 FT/ STAGE FILE: TRAIN-B.0AT - NO. OF SECTIONS = 50 - TWO-FHASE SECTIONS' DIVIDER = 10 SECTION 10 K FLOW PflN) P(OUT) 1 : 1 - 17 10.020 29.3 441,500 147.5 140.3 2: 17 - 7 7.981 9.7 441,500 140.3 130.5 3: 7-8 7.870 5.5 379,000 130.5 129.6 4 : 8-9 9.516 39.7 379,000 129.6 124.6 5: 9 - 10 9.172 4.9 379,000 124.6 150.3 6: 10 - 11 9.172 3.4 209,392 150.3 150.4 7 11 - 12 0.152 14.8 63,167 150.4 143.8 8: 12 - 18 3.150 1.2 63,167 143.8 143.6 9: 18 - 19 3.346 1.7 63,167 143.6 145.3 10: 19 - 20 0.886 117.6 3,509 145.3 123.1 11: 20 - 21 0.874 0.3 3,509 123.1 122.7 12: 21 - 22 0.898 1.4 1,170 122.7 122.7
** FRESS (CR> TO COtJTINVE **
SECTION ID K FLOW P(IN) P(OUT) 13: 22 - 23 0.724 210.9 1,170 122.7 116.9 l 14: 23 - 23A 0.724 76.1 1,170 116.9 113.2. 15: 23A- 238 0.724 0.0 1,170 113.2 113.2 l 16: 238- 24 0.724 0.0 1,170 113.2 113.2 17: 24 - 24A 0.550 47.0 1,170 113.2 108.8 18: 24A- 25 0.550 0.0 1,170 108.8 108.8 19: 25 - 26 0.590 5.8 1,170 108.8 106.6 , 20: 26 - 26A 0.590 33.9 1,170 106.6 106.1 1 21: 26A- 27 0.590 0.0 1,170 106.1 106.1 22: 27 - 2G 0.590 8.0 1,170 106.1 110.1 23: 28 - 29 0.768 0.4 3,509 110.1 110.4 24: 29 - 30 0.969 11.6 3,509 110.4 120.3 25: 30 - 31 3.803 1.7 63,167 120.3 118.3 26: 31 - 32 5.826 6.2 63,167 118.3 98.7 27: 32 - 32A 9.586 3.3 63,167 98.7 98.7 28: 32A- 328 9.586 0.5 126,333 98.7 98.7 29: 328- 33 9.586 0.2 189,500 98.7 98.7 30: 33 - 33A 10.820 0.3 189,500 98.7 98.7 31: 33A- 34A 10.820 0.7 252,667 98.7 98.7 32: 34A- 34H 10.820 1.3 315,833 98.7 98.6 33: 34F:- 35 10.820 0.8 379,000 98.6 98.6
** FRESS <CR) TO CONTINUE **
Page A-28
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N i~KNjnfM~~ 909268/A 5
?& & CE &
SECTION
^
ID K FLOW P(IN) P(OUT)
^4* 56 5.826 189,500 98.6 98.1 $si [5v-2259 5.826 3'.6 00 189,500 98.1 96.3(W= 778,293 OP= 29.5 X= 0.0) 36: 36 - 39 11.540 2.2 379,000 96.3 96.2 37: 39 - 40 10.114 0.7 379,000 96.2 88.7 38: 40 - 41 12.500 3.3 379,000 88.7 82.3 39: 41 -300 14.312 0.0 379,000 82.3 82.3 40: 300-301 4.026 10.7 379,000 82.3 67.0 41 *01-300 7 481 5.8 379,000 67.0 69.9 42iH D-3I202 6 7.'981 0.0 379,000 69.9 69.0CW=1,077,025 OP= .
6.7 X- 0.4) 40: 302-303 7.981 2.0 379,000 69.0 70.2 44:0ECAY HX 7.981 56.2 379,000 70.2 64.6 45 304-305 6.065 4.8 379,000 62.6 62.0 465LV-3250-2 6.065 0.0 379.000 62.0 31.1(W= 459,913 OP= 45.5 X= 0.0) 47: 305-306 6.065 7.2 379,000 31.1 28.9 48: 306-307 7.981 0.7 441,500 28.9 28.7 49: 307-308 12.000 3.0 441,500 28.7 27.6 50: 308-309 12.000 3.3 441,500 27.6 22.3 . 44 PRESSURE AT END OF SYSTEM = 22.3 PSIA . REFEAT WITH NEW CONDITIONS (Y/N)? Page A-29
909268/A
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. 909268/A PROTO. POWER CORPORATION ^$ g ga;,oA CCRPORATECN 591 POCUONNOCK RCAO GROTON. CONNECTICUT 06340 (203) 446-9725 File: 7511482 November 26, 1986 Mr. Jack Kennedy General Atomic Technologies 10955 John Jay Hopkins Drive San Diego, CA 92121
Dear Mr. Kennedy:
Enclosed are the following calculations: No. 82-12, Rev. -
, dated November 25, 1986, " Appendix R Safe Shutdown Cooling at X2 Power Level for Fort St. Vrain."
This calculation evaluates the use of the new flash tank vent and main steam vent during safe shutdown cooling following an Appendix R fire and supersedes the draft revision forwarded on November 21, 1986. Inventory depletion calculations were based on PCRV helium time temperature profiles in recent GAT TAP analyses. Pending completion of the GAT TAP runs for Appendix R at X2 power level, this calculation will be revised as required. No. 82-08, Rev. A, dated November 21, 1986, " Appendix R Safe Shutdown Cooling for PSC - Fort St. Vrain." This revised calculation, which is applicable for X1 power level, reflects our re-evaluation of the system resistances and refinements to our pressure drop program, and supersedes
" Revision " forwarded on October 31, 1986. This calcu-lation was revised to document higher achievable flow rates which may be beneficial in resolving hot module concerns.
Also enclosed is PPC Drawing No. 7511482-PF-01, Sheet 1, Rev. B, which incorporates revised system resistances for the fire water t flow path from point 3 through point 16 to point 6. Although this drawing provides reference data for several previously submitted Proto-Power Calculations , the line section modifica-tions in this drawing do not affect those previous calculations. This drawing has been changed only to be consistent with the enclosed Drawing No. 7511482-PF-10, Rev. A and 7511482-PF-11, Rev. A. Page A-36
~
909268/A Mr. Jack Kennedy November 26, 1986 If you have any questions, please do not hesitate to call me at (203) 446-9725. P Sincerely, U. M9 . G. W. Geaney, Manager Engineering Services MJF: mas Encl. cc: K. Dvorak P. Tilson l l 1 1 i i I 1 1 1 Page A-37
.__ -, _ ___ .. _ _ _ _ . _ . _ . . . - _ . - ~ . , _ . _ _ .
909268/A CALCULATION COVER SHEET PROTO-P0llER CORPORATION TITLE: APPENDIX R SAFE SHUTDOWN COOLING FOR PSC - FORT ST. VRAIN CALCULATION NO.: 82-08, Revision A FILE NO.: 7511482 CALCULATED BY P.M. Brealio DATE 11/21/86 CHECKED BY M.J. Fekete DATE 11/21/86 Page A-38
909268/A cxc m '" 82-08 ~~ A ""/ or f e PROTO POWER CORPORATION momron oare i GROTON, CONNECTICUT P. OnEe uo 16-21-86
///78 7511482 Q ENT ECT Public Service Co. of Colorado Fort St. Vrain SUBJECT Appendix R - Safe Shutdown Cooling l
CONTENTS
- 1. PURPOSE
- 2. BACKGROUND
- 3. METHOD
- 4. RESULTS
- 5. REFERENCES
~ ATTACHMENTS: 1. Computer Input Files and
(- . Printouts - Train A
- 2. Computer Input Files and Printouts - Train B
- 3. Drawing No. 7511482-PF-10, Rev. A
- 4. Drawing No. 7511482-PF-11, Rev. A l
t
.g Page A-39 l-
909268/A i
- cAtc NO 82-08 "'" A "" " 2 or#/ l PROTO POWER CORPORATION ono m on onE l GROTON, CONNECTICUT o me.on i s. 2 i-s 6
nEviEWEO JOB NO CUENT Public Service Co. of Colorado Fort St. Vrain Appendix R - Safe Shutdown Cooling h i
- 1. PURPOSE I To determine the secondary cooling water flow rates through the two separate cooling water flow paths identified in >
Reference (a) for safe shutdown cooling following a major 3 (10CFR50, Appendix R) fire. t i, 2. BACEGROUND Two separate, alternate steam generator flow paths have been developed for safe shutdown cooling following a major fire. i These flow paths have been developed in accordance with the requirements of 10CFR50, Appendix R. A description of these flow paths, and their evaluation for compliance with
. 10CFE50, Appendix R is presented in Reference (a) .
f One flow path, Train A, is from one 12-1/24 condensate pump, . through the EES section of one steam generator, the decay i heat removal exchanger (for heat removal from the con-densate) and back to the condensate pump. The other flow path, Train B, is from the diesel-driven firewater pump, through the EES section of one steam generator, the decay heat removal exchanger (for heat removal from the the firewater), the condensate storage tanks, service water return pump, the main cooling tower (for additional heat t removal from the firewater) and back to the fire water pump. The Enference (a) flow paths are through PV-22153. However,
., the flow path for cooldown following an EQ event is through i PV-22153, PV-22129 and PV-2229, in parallel, to maximize
!' cooling water flow. The original issue of this calculation addressed both flow through PV-22153 only and flow through all three valves in parallel. This revision will address ' flow only through PV-22153. The manufacturer of the decay heat removal exchanger recommended that two phase flow (low quality steam) in the heat exchanger be avoided to preclude the potential of high l
- shellside velocity induced tube vibration and resultant ;
d amage . Therefore, LV-3250-2 and V-32108 will be throttled i to maintained subcooled conditions at the heat exchanger inlet. This is consistent with Reference (a). I
- Page A-40 i
909268/A cAtc u 82-08 A PA Eg ory g- PROTO POWER CORPORATION o misaron oarE GROTON, CONNECTICUT P. BREtsLlo I n- it- % REVIEWED JC8 MJ 7511482 PROJECT CUENT Public Service Co. of Colorado Fort St. Vrain SUBJECT Appendix R - Safe Shutdown Cooling l
- 3. METHOD . -
l The computer program and approach of Reference (b) were used for determining system pressure drop. The computer program FSVSG, Reference (c), was used to determine coolant tempera-tures within' the steam generator, assuming 125 GPM pelton wheel flow and 1_40,0*F helium inlet temperature. Firewater inlet temperature to the steam generator is assumed to be 85*F. Decay heat exchanger performance was determined with the computer program HEATX, Reference (d). This program calculates firewater outlet temperature and condensate outlet temperature. Condensate outlet tempera-ture is also the inlet temperature of the steam generator for Train A. . h The sections of the flow paths for Train A and Train B, and associated hydraulic resistances are detai. led on Attachment 3 (Drawing No. 7511482-PF-10) and 4 (Drawing No. 7511482-PF-11), respectively. This information was used to create the computer inputs i files :for the analysis. Each flow path was analyzed with flow through only PV-22153. LV-3250-2 was throttled, by reducing the valve Cy in the input file, to maintain saturated liquid (approximately 2*F subcooled) conditions at the heat exchanger inlet. For Train A, system pressure is based on conservatively assuming empty condensate storage tanks, and thus 12.3 psia at the tie-in to the line from the storage tank. For Train B, the condensate storage tank must be full to allow firewater outlet flow through the tank overflow line. Thus, firewater enters the tank against a static pressure of 22.3 psia. The results of the analysis are presented in Attachments 1 and 2 for Trains A and B, respectively. C Page A-41
909268/A catc
- 82-08 REV g PAGE y oc / j
.- PROTO POWER CORPORATION oniomron omrE l- GROTON, CONNECTICUT P. EM66 L10 ll-Zl-8(o aEviEWED JOB W 7511482 CUENT ECT Public Service Co. of Colorado Fort St. Vrain Appendix R - Safe Shutdown Cooling
- 4. RESULTS Train A Flow through PV-22153 Flow - 527 GPM Steam Generator Backpressure - 266.3 psia Steam Generator Inlet Temperature - 162*F Steam Generator Outlet Temperature - 400*F Train B Flow through PV-22153 Flow - 785 GPM l Steam Generator Backpressure - 102.6 psia steam Generator Inlet Temperature - 35 *F Steam Generator Outlet Temperature - 300*F
- 5. REFEEENCES A. Appendix R Evaluation: Fort St. Vrain Nuclear Genera-ting Station, Revision 6, dated April, 1986.
B. PPC Calculation 82-01, "EES Safe Shutdown Cooling for PSC - Fort St. Vrain", dated September II, 1986. C. PPC Computer Program "FSVSG". D. PPC Calculation 82-05, " Computer Program (HEATX) to Analyze Decay Heat Exchanger", dated October 17, 1986. 3 C Page A-42
909268/A CALC. 82-08, Rav. A ATTACHMENT 1 Page 1 of 3
*ma FILE: TRAIN-AK.DAF **=
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. NA , Na 30s ';7 - 28 , 0.54.s, 3.? l , 1.33, 270.10,8.202D-6, -11.H, 1, 4ea.0, Hs , MA 31: 28 - .' 4 , 0.bs, 1G0, 0.12, 15.31,8.202D-6, -0.9, 1, 400.0, ilA ,
Ni, 32 29 - 30 , 0 . %.9 , 108, 1.48, 525.6,8.202D-6, -27.D, 1, 400.0, IJA , TM 33 30 - 31 , '. . m a t , n, .66, 23.0,1.5000-4, 4.6, I, 400.6, NA , IN 34: 31 - 52 , 5.h.e, d, . 1.26, 208.2,1.5000-4, 44.0, I, 400.0, NA , Ns 35: 32 - 3?A, 9.56, 6, 2.9, 4.2,1.500D-4, u.0, !, 400.0, Na , NA 3n 32A ".2R, 9. % , 3, 0.3, 16.0,1.5000-4, 0.b, i, 400.0, NA , IM 37: 32H- M , v . base , ,,
.04, 4.3,1.500D-4, 0.0, 1, 4 G.O. 0, IM , NA 38: 33 - 33A,10.Vm , 2, 0.3, 2.8,1.5000-4, 0.0, I, 400.0, NA , im 39: 33A- 34A,10.hM, 1.5, 0.3, 21.3,1.500D-4, 0.0, 1, <'. 0 0 . 0 , NA , tu.
40: 34A- 34R,10.6:n, 1.2, .3, 13.4,1.500D-4, 0.0, 1, 400.0, NA , NA 41: 34(4- ' 4i. ,10. biln ,
. 1, 0.0, 8.82,1.500D-4, 0.6, i, 400.0, Na , N..
42: 34r - % , S.G;o, 1, 1.77, 59.8,1.500D-4, 0.0, I, 400.0, NA , 16 43: PV-22c4 , 5.6io, 1, 0.0, 0.0,1.500D-4, 0.0, 6, -160.0, 248.0, 0.4 44: 3o - 39 ,11.540, 1, .7, 47.6,1.500D-4, 0.0, 1, 400.0, NA , IM 45: 39 - 40 ,J0.lis, 1, 0.2, 11.1,1.500D-4, 18.0, i. 410VI . 0, Nn , Ib 46: 40 - 41 ,12. No , 1, 1.2, 70.9,1.5000-4, 15.7, I, 400.6, Na , N4 47: 41 -306 ,14.322, 3, 0.0, 2.9,1.500D-4, 0.0, I, 4021.0, NA , 16 4R: 300 ~.01 , 4. Gin, 1, 3.3, 264.7,1.500D-4, -32.8, 1, 400.0, ib , 16 49: 301-5a? , 7 .'ent , 1, 1.0, 137.0,1.500D-4, e . i?. , i, %0. 0, Nn , N.4 50:HV-3220-6, 7. 'i te l , 1, 0.0, 0.0,1.5000-4, 0.0, t., 4 0vi . 0 , 870.0, 0.9 51: 307-3M , 7. %i , 1, .6, 20.9,1.500D-4, -3.8, i, 400.0, NA , 14.
- ~ 2 : DEI n't Ita , 7. 4 3. s ., t, 56.2, 0.0,1.500D-4, -4.3, 1, TAl.0, No , Nie )
b3: c.wa aOS , 6. m b , 1, 1.3, 93.4,1.500D-4, - .e . 1 , i, 16'.b, Nse , Nn l 54:ev-3pn-2, m. w., ,, 0.0, 0.0,1.500D-4, 0.6, . , , i 6.. 0, 37. 4, .v l 65: 3H5-306 , o . W, , 1, 2.0, 214.7,1.5000-4, -3.2, 1, the.0, NA , im ! Page A-43 l
~n .- _ . __ - . _ . -
909268/A CALC. 82-08, Rnv. A ATTACEMENT 1 Page 2 of 3 FLOW = 527.1 bEM 61 1002F? USE PljMP t.tlRVE [144 dillLR PRFSSURE3 (Y/N):N? STAR 11r4G PhESSURE u 12.3 PSIA? PELTOt1 WHEEL FLOW-- 125 -8W'H? F I LE : 1 h A I N- AK . O.,1 - 141 (W SECTIONS = 55 - TWO-PHASF SF.tTi llit h. D i 'll OFiR= 10 SEC11014 10 K FLOW P(IN) P (OU I) 1 : 306-400 . 4a 3. 6 263,550 12.3 13.5 2 3 400-901 7.Out 1.6 326,050 13.5 18.7 3 401-402 l'.:.i M , t.2 326,050 18.7 18./ 4 x 402-403 l a. W211 1.0 326,050 18.7 18.6 5 : I;ONi> PMP 1. so. it.4 ks . 61 326,050 18.6 297.h 6 : 404-405 7.v6i 2.6 326,050 297.5 295.4 7: 405-406 a.Co5 2.0 326,050 295.4 290.0 8 : 406-407 ).991 3.1 326,050 290.0 289.0 9 : 407-- o 7.96i 1.7 326,050 289.0 261.5 10: 6 - 7 7.i64 1.9 326,050 281.5 281.1 11: 7 - 8 7.J,0 5.4 263,550 281.1 280.7 12: 8-9 %.51o 38.7 263,550 280.7 277.3 63: 4 - 16) 9.1/ ' 3.i 263,550 277.3 302.9 on FRES6 Eh > lo f ullill4Ut ** SFC1 Iui4 4o K FLOW P(IN) P (0111 ) 14: 10 - 11 5.172 2.0 145,608 302.9 303.0 15: 11 - 12 ~.152
> 12.3 43,925 303.0 298.0 16: 52 - la 3. IN O.6 43,925 298.0 29a.0 17: 15 - 49 . '.4 e 1.1 43,925 298.0 299.9 18: 19 - 20 Fr.666 116.5 2,440 299.9 283.3 19: 20 - 21 d>.h74 O.3 2,440 283.3 282.9 20: 21 - 22 6.8in O.7 813 282.9 282.9 21 22 - 23 A.724 210.3 813 282.9 279.6 22: 23 - 23A L.724 '4.4 813 279.6 279.2 23: 23A- 23H => . 7 2 4 37.2 813 279.2 276.7 24: 236- 24 i. 7 2's 0.0 813 276.7 276.7 25 24 - 244 va . T,50 44.1 813 276.7 274.1 26: 24A- 25 6.556 0.0 813 274.1 274.1 27: 25 - 26 ki.59u 4.7 813 274,1 272.1 28: 26 - 2eA n.M9u 33.1 813 272.1 272.5 29 264- 27 G 590 0,0 813 272.5 272.S 30 *!7 - 78
. s i . 5%i 6.7 813 272.5 276.4 31: 28 - 29 it. h h U.4 2,440 276.4 276.7 32: 29 - '.0 h e . 9 t.,9 10.7 2,440 276.7 2h6.4 l 33: 36 - 31 3. . hk,3 1.1 43,925 286.4 2H4.6 34: 31 ~'. 7 5.H76 4.7 43,925 784.6 266.4 j 1
e er F ittini, 4 t .R ) he i e asil li ttlf ** Page A-44 _=
909268/A
^ *
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ATTACHMENT 1 pig 3 3 of 3 SEC IIOri 1D K FLOW P(IN) P(Olji) 35: 32 - 42A 4.586 S.O 43,925 266.4 266.3 36: 32A- 32H 9.586 0.5 87,850 266.3 266.3 37: 328- 33 '/ . 586 U.1 131,775 266.3 266.3 . 38: 33 - 33A 10. 8','O 0.3 131,775 266.3 266.3 39: 33H- 34s 16.820 0.6 175,700 266.3 266.3 40: 34A- 34B 10.b20 0.5 219,625 266.3 266.3 41: 34H .T4C 10. u: 0 0.1 263,550 266.3 2e6.3 42: 34C- Sn 5.6?o 2.7 263,550 266.3 265.5 43: PV-2229 N.026 0.0 263,550 265.5 260. 2 Lucr = }I1,OUH 44: 36 - 39 11.540 1.4 263,550 260.2 260.2 45: 39 - 40 16.114 0.4 263,550 260.2 253.2 46: 40 - 41 l'd.500 ').2 263,550 253.2 247.3 47: 41 -300 14. J> 1.: 0.0 263,550 247.3 247.3 48: 300-301 4.O?6 7.7 263,550 247.3 249.0
- 7. 9fl1 3. 8 49: Sul-302 263,550 249.0 256.9 50 HV t2'/O-6 7.w31 0.0 263,550 250.9 250.4 Wer=,A/5,u90 51: 40^:-363 7.vd1 0.9 263,550 250.4 25t.8 52: DECAY HX 7.981 56.2 263,550 251.8 248.9 SX: 304-7.05 c,.uh5 2.8 263,550 248.9 249.9 54:1.v t?5H--? o . Ot.S 0.0 263,550 249.9 52.u Wer - n.4,bi1 55: 305- W. n. e5 6.4 263,550 52.0 52.1
** Ebt?SSithE Al EHo i+ SY5 TEM = 52.1 PSIA REPEAT WITH I4EW i;uraDIT D>f13 tY/N)?
i Page A-45
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909268/A CALC. 82-08, R3v. A ATTACHMENT 2 1 P3g3 2 cf 3 1 i d FLOW = ?S5.2$ GPM 4T 100rF7 - . liSE l lil1P a llRVE I.r4< t'HILR FRFSSURE3 (Y/N):Y7 FIRE WHIERt=1), i.Mi h el.14sa l li ( =2 ) OR IACM(=3) PUMPS 1 7 PUMP (5) AhRsNGeiMEl.'i uk4f?=0 - PARALLEL =1 - SERIES =2) : 07 FELT Ori WHEEL Fl.OW = 125 GPM7 Ft.UW w POMP = 913.15 AFM AT 100=F
- FilMP HEAD = 104./e FT/S1AhE.
FILE TRAIN-BK.041 - his. OF SECTIONS = 50 - TWO-PHASE $FCTliiil9'b4VIDER= 10 66 C1 iOri iis K FLOW P(IN) P ( O .li ) 1 : 1 - 17 146. d 0 19.4 455,125 146.9 140.1 2: 17 - 7 's.931 n.2 455,125 140.1 131.2
, 3 : e -8 'e . 8 /G M.4 392,625 131.2 130.2 i' 4 : u-9 4.S16 38.8 392,625 130.2 125.1 5: v - 10 < . 1 */ .: 3.2 392,625 125.1 150.8 6 : 10 - 11 9.17.:
.1 216,920 150.8 150.9 7 11 -
12 3.152 12.4 65,438 150.9 144*.6 8 12 - IG 3.150 0.6 65,438 144.6 144.5 9 : in-19 3. 34 c, 1.1 65,438 144.5 146.3 10: 19 - 20 0.8a6 117.1 3,635 146.3 123.3 11: 20 - 21 n.n74 0.3 3,635 123.3 122.9 12: 21 - 22 b.bwB 0.7 1,212 122.9 122.9
** FAhS5 < C R 'r 10 Cl 6NTINilE **
SECTIDH ID A FLOW P(IN) P(OUT) 13: 22 - 23 B.724 32.5 1,212 122.9 121.2 14 23 - 20A B.724 36.6 1,212 121.2 120.3 1 15 23A- 23B b.724 39.7 1,212 120.3 117.3 16: 23b- 24 a.724 0.0 1,212 117.3 117.3 17: 24 - 24A 0.550 46.7 1,212 117.3 112.7 18: 24A- 25 0.550 0.0 1,212 112.7 112.7 19: 25 - 26 0.590 4.9 1,212 112.7 1 10. fi
'20 : 2e - 26A B.590 33.7 1,212 118.5 109.9 21: 2eA- 27 6.590 0.0 1,212 189.9 109.9 22: 27 - 28 0.590 6.7 1,212 199.9 113.9 23: 20 - 29 w.?n8 0.4 3,635 113.9 114.2 24: 29 'O m.9o9 10.7 3,635 114.2 124.2 25: 30 - il 3.HG3 1.1 65,438 124.2 122.2 26: 31 - 32 5.826 4.8 65,438 122.2 102.6 27: 32 - 3?A 9.586 3.0 65,438 182.6 102.6 29: 326- 32H 9.59a G.5 130,875 102.6 102.6 29: 32b- 33 9.66n 0.1 196,313 182.6 102.6
- s 30: 33 - 33A 13.620 0.3 196,313 192.6 102.6 31: T.%- 749 in.810 0.6 261,750 182.6 102.6 32: 34(- 348 10.820 0.5 327,188 192.6 102.6 33: 348- 34C 10.820 0.1 392,625 102.6 102.6
- c. FI,Fhs J i'R - 1:1 t*0i1T liJilE **
i Page'A-47
. CALC. 82-08, R2v. A 909268/A ATTACHMENT 2 Paga 3 of 3 5
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SECTIOl1 AD E FLOW P(IN) P(OUI) 34: 34C- 3e 5.92s 2.7 392,625 102.6 100.8 35: PV-2229 5.826 0.0 392,625 100.8 69.9 Wer= 669,59b 36: 36 ~9 11.540 1.4 392,625 89.9 89.8 37: 39 - i,4 10.114 0.4 392,625 89.8 82.3 33: 40 - 41 12.501 2.2 392,625 82.3 76.0 39: 41 -3CS 19.312 0.0 392,625 76.8 7o.a 40: 300-301 4.6 6 7.7 392,625 76.0 67.1 41: 301-30 1.461 3.8 392,625 67.1 68.8 42 HV-3220-6, 7.981 0.0 392,625 68.8 67.9 Wer61,567,563 43: 302-303 7.961 b.9 392,625 67.9 69.3 "44 DECAv' HX /.961 56.2 392,625 69.3 61.0 45: 304-305 6.unn 2.8 392,625 61.B 6i.3 46:LV-3250-2 n.06M 0.0 392,625 61.3 30. 2 Wer = 4/s,213 47: 305-304, 6.065 5.4 392,625 39.2 26.8 40: 306-N07 7.481 0.5 455,125 28.8 28.6 49: 70/-0,ob 1.?.000 2.2 455,125 28.6 27.5 50: COO-0M 12.600 1.8 455,125 27.5 2?. 3 00 PRi?551shF e'.T tint OF S'rSTEM = 22.3 PSIA REPEA1 WITH IJFW f.Of41s tTIONS (Y/N)?
. Page A-48
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l 909268/A l l APPENDIX A-2 HOT MODULE ANALYSIS The analysis presented in the body of this report is based on the nominal module. The peak helium temperature at the start of the M cooldown transient into the hottest module may be as high as 150af hotter than the gas into the nominal module. As seen in Figures 4-5a through 4-5d the gas temperature spread between the hot and nominal modules increases during the transient, reaching a maximum value ] somewhere between 3.4 and 7.4 h. Since the 35% feedwater case is the limiting power level case, the hot module effect was investigated in detail for that case. For a nominal flow of 527 gpm, the net steam generator pressure drop (ringheader to ringheader) is about 12.8 paid. The pressure drop, due to gravity from the inlet ringheader to the active bundle, is greater than 12.4 paid. Since all modules must have the same pressure drop, a steaming module has only about 0.4 psid for friction and local losses. (the other modules have a pressure gain due to the downhill water flow in the exit leg) . As seen in computer run ST3962, with a water flow which is less than 10% of the nominal flow the low pressure drop cannot be met. Therefore, for the nominal 527 gpm it becomes necessary to reduce tne water outlet temperature, thus providing subcooling margin for the hot module. For this case, the heat removed by the steam generator must ce rejected via the decay heat removal heat exchanger. This heat exchanger will establish the combination of cold and hot leg temperatures for a given heat removal capacity. The heat Joad in the hot module is about 40% greater than the heat load in the nominal module. Treating the decay heat heat exchanger as having constant effectiveness (valid assumption due to no change in water flow), and being cooled with 80*F water the cold and hot leg temperatures were calculated to be 139aF and 308aF. Computer runs ST0249 and ST0278 contain SUPERHEAT analysis for the hot module and Page A- 55
909268/A nominal module at the point of maximum temperature spread as defined in Fig. 4-5d. The result of these runs show a hot module outlet temperature of 389'F. This temperature is 17aF below the saturation temperature for this case. e i
- The same secondary side operating conditions (139'F cold water temperature and 308'F hot water temperature) were applied to the 75%
feedwater case as presented in Table 4-2. The results for 755 feedwater are included in SUPERHEAT runs ST2911 and ST2489. l. l 1 l t Page A- 56
i I 909268/A i APPENDIX B TAP RECA, AND SUPERHEAT RESULTS Page B-1
rum *ST9468 11/1g/84 16:29:15 RECA 754 FW FLOW EES COOLING SIS CPM TEMPERATURES 3000
,,,_-D-- -~' -
- D----
- D.- ----..g,__ TIHPOS(core inlet)
.., v
. , g' ATOUTP(core outlet
....X.. ..- mixed-mean)
D 2000 f E gF TAVOTF(sc intet
~
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TIME, HOURS - N e O N y
RUN ST9868 11/19e86 16:29815 RECA '754 Fu FLOW EES COOLING stb GPM HEAT GENERATION AND REMOUAL RATES 150 SUMQ (ceneration) O 100 - HEATR(nemoval)
~ -----x -- - .
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N RUH=ST9268 11/19/86 16:29:15 REC 4 755 Fu FLOW EES C0OLING stb GPM CIRCULATOR HELIUM FLOU RATE 40 FLOHTX o m 30- # L B S -
/ 20-S E -
I c - L 10 - h e S 0 =0.0 y , , , j 0 2 4
- TIME, HOURS 6 8 10 '
a 8 n Z;
5 S.G. INLET TEMPS. - 754 FW FLOW - 518 GPM AT 400 F WATER 1500 Legend [ I. **'. Hot, Module T ............ e 1250 ,? . Avg Modute
., \
P - r l a 1000 . ",. i t u r g - 750 . D - e ', g - 500 ' F - N 0 2 4 6 8 10 12 g Time, Hours g
% n
909268/A
- o s:::
isc.: i::.c '. a s
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um. acm-518 GPM CASE-- FSV 1.5 HR OLY, 6 EES. 518 GPM COND. 400F.MST. ST02SO N0' LINER CLG. EES AT 262.3 PSIA. VAR HE FLOW, 7.90" BYPASS 11/18/8 FIGURE- FRAME..A CURVE 1 : FWT0f - TOTAL FEEDWATER FLOW iPERCENT OF RATE 3 = S401 CURVE.2 : FMf 0f - TOTAL HELluft FLOW.tPERCENT OF RATE 3 = 10351 CURVE 3 : PM - NELIUM PRE 3URE (PERCENT OF RA!ED 7003 CURVE 4 : PT - THR3f fLE PRES 3URE (PERCENT OF RATED z 2412) CURVE 5 : WC - REACTOR POWER : PERCENT OF RATED = 11 Page B-7 i
i 909268/A i I.5 33 } l
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00 5 C+03 i.a.04 :.$.g4 g,g,g4 fIM, stemec 518 GPM CASE - FSV'1.5 HR OLY, 6 EES. 518 GPM CONO. 400F.MST. ST0260 NO LINER CLG. EES.AT 262.3 PSI.A. VAR HE FLOW, 7.90%' BYPASS 11/18/8 FIGURE- FRAME B CURVE. 1.: CURVE.1 : TSCOA - STEAM !EMPERATURE AT ACflVE SMTR CUTLET (FI CURVE 1 : CURVE 4. fMC CORE INLET MELlUM. TEP.*ERATURE t ri CURVE 1 : TFW - FEEDMTER TEM *ERATURE t rl l CURVE i : Page B-8
909268/A
; ;-0; c::
. l l
l l l l l I l l l 1.5 03 1 1 l 1L_ _ _ l_ _ _ _ _1_ _ 1 0+03 i- ---. m O ' 3 E j \ . ;, . . . . . . . ... . . , s 5 5."+02 l 1,b-_ ~
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0.0 , 03 5 0+03 I.0+04 i.5 04 2.0+04 riv. 'z;* es SIS GPM CASE - FSV'1.5 HR OLY, 6 EES. 518 GPM CONO, 400F.MST. ST0260 NO LINER CLG. EES.AT 262.3 PSIA, VAR HE FLOW, 7.90% BYPASS 11/18/8 FIGURE- FRAME' O CURVE t : TTt20. ) - TUSE TEMERATURE AT GMTR 1 QUTLET IFl CURVE 2 : T0t20.01 - STERM .TEf*ERATURE At 3HTR 1 QUTLET IFl CURVE 3 : TTito.3 - TU8E TEr*ERATURE AT ACTIVE SHTR QUTLET (F) CURVE 4 : TTt 10.101. TU8E TEf?ERATURE AT MAIN STEAM MODULE QUTLET (F) CURVE 5 73t10.101- STEAM TEMPERATURE RT MAIN STEAM MODULE QUTLET (FI l l 1 Page B-9
909268/A 5* 1.5*03
~ '
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I - N b
-I 5 G+0:
3.0 . . . , . . . . . . . . . . . , 0.0 5 0 33 1 0+04 1.5-04 2.0 34 nx. ww.s SIS GPM CASE - FSV'1.5'HR OLY, 6-EES. 519 GPM COND. 400F.MST ST0260 NO LINER CLG, EES AT 262.3 PSIA, VAR HE FLOW, 7.90% SYPASS 11/19/9 F IGURE- FRAME E CURVE L CURVE 2 : TIRI A - TUSE .IEFJ'ERATURE. AT . ACTIVE RMTR INLET (F) CURVE 3 : TT3R02 - TU8E. TEt*ERATURE. AT ACTf vt.RMTR QUTLET IFl CURVE.4 = Page B-10 i
909268/A
; ^-:: :::
e t.5 03 c g I 7*F % T l / N \ l 1.0 03 l A N< N < I \ 5 l l l
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5: : &::::h::::';; 1 ! c.0 , 00 5.C+03 i.0+04 I.5 04 2.0+04 n.w. ames 518 GPM CASE - FSV 1.5 HR DLY, 6 EES, 518 GPM COND, 400F MST ST0260 NO LINER CLG. EES.AT 262.3 PSIA, VAR HE FLOW, 7.90% SYPASS 11/18/8 FIGURE- FRAME G CURVE L : YCONt33 - rt!XEC MELIUM TEF"'ERRfuRE Rf CORE QUTLET (F1 CURVE 2 : fMGM - MELIUtt. TEtt!'ERRfuRE .Rf RENERTER INLET IFl CURVE 3 : TM0t e l - NELIUtt TEf'PERATURE .RT REMERTER QUTLET trl . CURVE 4 fM0t31 - NELIUtt TEMPERRfURE RT SUPERMERTER 2 CUTLET-tFI CURVE 5 : fM0121 - MELIUff TEf'PERATURE Rf EVAPORATOR QUTLET IF) CURVE $ = TNGC - NELlutt.fEf PERATURE AT -3fERrf GENERATOR QUTLET IFl Page 8-11
909268/A
. ~-. r.::: u 6 4 dd ,
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- 1. +03
) '
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b bl: l - e $ 1 5 8 5 5 E 5.G*02 4 I I I 00 .......................y . ..... . . . . , . . . . ....... g C.0 5.G+03 I.0 04 .5+04 2 3+04 I tts, secoes 518 GPM CASE - FSV 1.5 HR OLY, 6 EES. 518 GPM CONO, 400F MST ST0260 NO LINER CLG. EES AT-262.3 PSIA, VAR HE FLOW, 7.80% YPASS 11/18/8 FIGURE- FRAME F CURVE 1 : T3Cr' - ttERGURED ttA!N STERrt TEft'ERATURE .tfl i CURVE 2 : CURVE 3 : TSCM . MR]N STEAri TEttPERA!URE.RT THRSTTLE (T) CURVE 4 : Page B-12
l 909268/A
~~
l l l l l 1 l 1 l l l l ' l l l l l l l 1 l l I I I i i i l I i l l l l l l l l l l l 1 1 I I l 1 1 1 I i ! i l i ' l I 700.0 k i i l I
\ l i I I i <
l I s I li i l I l l l l 1 i l l I I A\' I I I l I I I I " I l i I k l l l l l l ' 1 l I I I ( l l l l l 1 l
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~
l l 400.0 l l l I I I I ! l I I I l ! l I I I I l l l 1 l 5 I l i I i l j l f 5 I ! l l l l i I i l l l ~!** l I i l l l ' I i l l l i I I I l l l l l I I I I
=ca.:
I I I \\. I I I ( % ' . .I,....., i , j ,. . . . . . ....... .. i . . .,. . . . . I I I l l l l 100.0 00 5.G*03 1 0 04 I.5+04 2.0+04 ft w. cremes 518 GPM CASE - FSV't.5 HR DLY. 6 EES. 518 GPM CONO. 400F MST ST0260 NO LINER CLG. EES AT 262.3 PSIA. VAR HE FLOW. 7.90% BYPASS 11/18/8 t FIGURE- FRAME H ! CURVE I : 7ft20.11 - TUBE.fEf*f!RRTURE RT ECONOMllER QUTLET-tfl CURVE 2 : 700ft41 . MELIUff. TEft*ERATURE .RT CIRCULRf 0R INLET .t r l Page B-13
e SINGLE /FSV2 TH502777 06/03/79 DATE 112086 PAGE 27 6 518 GPM 1567 12.3 LP/5 pfAK HE T E MPE R A T UR E 4 6 e e ee e e e ee e e e ee e e e e e e ee e ee ee eee e e e e e e e ee e ee n ee e eee ee ee ee g S L'M M A R V 0F SifAM CENERATOR UNI T PE Rf 0RM ANCE
- easeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeseeeeeeeeeee
( SEC. TOT A L FLOW RATE TOT At EFFICIENET A V E R A G E t NO OF DUTY STEAM HEL IUM S T' E A N C0N D I T I ON 5 AVERAGE HELIUM MEAN ENTRANCE EXIT HELIUM S TE A M SIDE SIDE ENTH. TEMP. TEMPE RA TURE TUBE STEAM i PRES. FNTH. TEMP. PRES. INLET
- LBM/HR LeM/HR B TU /H R 2 I BIU/LBM DEG-F OUTLET TE MP. P.
PSIA B YU/L BM DEG-F PSIA DEG-F DE G-F DEG-F 1 PSI 1 1.341e02 7.839+02 1.879* e
*ee*
0.5 20.3............................................
- 98. 7 124.6 155.8 301.6 364 3 390.0 288.4 1311.8 171.0 391.
13. i E k T 4 4E UN I T *e** ( 7.240e03 4.233+04 1.015*07 20.3 98.7 124.6 155.8 301.6 364.3 4 390.0 288.4 1311.8 171.0 391. 13. i e i O ( e
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, SINGLE /FSV2 Tuse2777 06/03/79 DATE 112086 PAGE 28 4 518 GPM 156f 12.3 Le/S PEAK HE TE MPE R AT UR E STEAM PRESSURE TROP (PSI) 4
, SEC. ACCELERATION FRICTION Ih/OUT LO5! ELEVATION TOTAL *P DO PSI PSI g PSI PSI PSI
, 1 .00624 2.60063 8.47517 2 10204 13.18408 '
g AVEaAGE .00624 2.60063 8.47517 2.10204 13.18404 k o k o 4 k k 9 k
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RUN*ST3986 11/19/86 15:01:09 RECA 754 Fu FLOW EES C00LiffG, 787 CPit TEMPERATURES 3000 '
..-a-- _____-- TINPOS(core inlet) a.
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- 700 PHPSI w >
c 600 - kg# P - S 500 I - A - 400 - _' ( - A 300 -
- W w O 6 2 4 6 af 8 10 m TIME, HOURS L 8
.o g s
1 1 i i i w S.G. INLET TEMPS. - 754 FW FLOW - 707 GPM AT 300 F WATER 1 1500
~ l Legend
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FSV 1.5 HR OLY. 6 EES. 707 GPM CONO 300F MST ST4411 NO LINER CLG. EES AT 87.3 PSIA. VAR HE FLOW. 7.90%11/18/86 BYPASS FIGURE FRAME A CURVE.1.3 CU4WE.2.s FWT07 . f 0fRL PEEDWR!ER FLOW (PERCENT Or. $401tR?fD CURVE 1 : FM!0f . TOTRL MELIUM FLOW IPE9CE4f 0F tRTED 1006: PM . MEllyM P9E00URE ffERCENT or tR!EO 7001 CURVE.4 CURVE 5.3 PT - fMR0f fLE P9E000NE (PE9CE4f or MR!EO a 24123 WC - RERCf 0R POWER (PERCENT Of tR!ED s il Page B-21
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Page B-23 l
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00 , . 5.0*01 1 0+34 1.5 04 2.3 04 nm. acc s 707 GPM CASE - FSV 1. 5 HR DLY -G EES. 707 GPM COND. 300F MST S T441.1 l NO LINER CLG. EES AT 87.3 PSIA. VAR HE FLOW. 7.90% BYPASS- 11/19/86 FIGURE FRAME E CURVE 1.s CuAvE : TTRIA - TU8E. TEttPERATURE R! ACTJyt RNTR !NLET (f) CURVE 3.s CURVE.4 : TTOR3A .TU8E TEftPETRTURT 4! RCTJYE 9NTR QUTLE? (f) Page B-214
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00 00 5 0 03 1 0*04 i.5*04 2.0*04 f tN. 08Ci380$ 707 GPM CASE - FSV'1.5 HR OLY. 6 EES. 707 GPM COND. 300F MST ST4411 NO LINER CLG EES AT 87.3 PSIA. VAR HE FLOW. 7.90% BY.oASS 11/19/86 FIGURE- FRAME G CURVE 1.s VCONt 3 s - MIXE0 HEllUM TEP?ERATURE AT CORE QUTLET (FI CURVE 2 : TMGM - NELIUM. TEf'*ERATURE A! REME't!Et !NLEI (f) CURVE 3.3 TH0t41 - MELIUM TEP*EMA!URE A! REMEATER QUTLE! t r a CURVE.4 TH0f 31 - MELIUM TEf'.*E*ATURE A! SUPEtME A?ER 2 QUTLET IFl CURVE 5.s TM0t21 - MElluM TCP*Et A!URE R! EV APOR A?cR QUTLET (F) CURVE S s TNGC - HELIUM TEP*ERATURE AT OfEAM CENERATOR QUTLE! (F) Page B-26
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Page B-27
4 e SINGLE /fsW2 TNse2777 06/03/79 BATE 111986 PAGE 27 lb
, 707 6PM 857 13.9 Let$ PEAg NE TEMPEgATUAE
........................ee...e......... ...............
SUMMAAV Of STEAM GENERATOR UN s
....................................I.T PERFORMAmCE 4
SEC. TOTAL FLOW RATE TOTAL EfflCIENCV A W EN A EE 8 Of 3 1 GAM C0 h 9 IT ION $ AWERAGE WELIUP MEAk ho Dult STEAM NELIUM ENTRANCE Eali TEMPEgATuRE ILkE $1EAM k, NELIuM STEAM $3DE SIDE ENTW. TEMP. PAES. ENTH. TEMP. PRES. LeM/Na INLET cui tET TEMP.
- P.
LeM/NR STutNR 3 1 aiu/LbM SEE-f PSIA STutten sEG-f PSIA SEG-f DEG-f 3EG*f- PSI 1 1.515*02 1.089e03 2.269+05 14.9 .99.0 52.7. .84.3. ,146 261.1 1313.9 8 e... EN 1 1 aE DN I T .... 9 1..............2.1*6....123 5 97.( , 294. 23. k 8.182+0! 5,880+04 1.225e07 Id.9 99.0 52.7 146.1 261.1 291.6 54.3 123.5 1313.9 97.C 294 23. n 4 4 e
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RUN ST2244 11ee4i86 08:58 23 RECA 754 FW FLOU EES COOLING, 832 GPM l TEMPERATURES 3000
~ TINPOS (core inlet)
-g___. O
__--- .,' o ..
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D ' 2000 E _f a" - s n, TAVOTF (so inlet G , ___&.__.. avg. module) R - \ E % TMAX (Max. fuel)
----e - ---
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RUN=ST2244 11/44e86 64:S8:43 aECA 754 Fu FLOW EES COOLING, 832 GPM HEAT GENERATION AND REMOVAL RATES SUMQ(Generation)
^
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AUN ST22e4 11.04/86 08:58s23 RECA 754 FW FLOW EES COOLING. 332 CPR CIRCULATOR HELIUM FLOU RATE 40 g a FLOHTX _ n v 30 -- L B S -
- / 20-- /
S - E - C _ 10-0-;W 0. O , , , 2 m 0 2 4 6
- 8 10 TIME, HOURS
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I i i S.G. IHLET TEMPS - 754 FW FLOW - 832 GPM AT 300 F WATER l 1500 j Legend ,
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- M - MELIUM PREG 3URE (PCRCENT OF RATE 0 a 7001 CURVE 4 PT - THR0f fLE PRE 3GURE (PENCENT OF RATE 0 a 24121 CURVE 5 s WC - REACTOR POWER (PERCENT OF RATEC 11 Page B-35
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FIGURE FRAME H CURVE 1 7f(2011
- TUBE TEMPERATURE AT ECONOMIZER DUTLET (F1 CURVE 2 s TOUT (el - HELIUM TEMPERRfuRE Rf CIRCULATOR INLET (F1 Page B-41 i
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i l l 909268/A APPENDIX C STORAGE OF COMPUTER ANALYSIS l l l l l t l l l 1 Page C-1
i 909268/A i APPENDIX C STORAGE OF COMPUTER ANALYSIS l The results presented in Appendix A were generated with the TAP, RECA and SUPERHEAT codes. The SUPERHEAT code is stored in production file GA* PROD. SINGLE /2777FSV2 and the SNIFFS code is stored in production file GA* PROD.MYSNIFFS/3627 VEL. The basic TAP code is stored in the archive file SYSD1619. The RECA code, the TAP plot code and the runstreams (contained code changes and data changes) for all the computer runs described in this study are stored in archive file SYSD 4040. The computer runs made for this study are identified as follows: TAP RECA SUPERHEAT HOT
- MODULE 518 gpm case ST0260 ST9268 ST8373 ST8080 707 spm case ST4411 ST3986 ST1001 ST8913 832 gpm case ST0823 ST2204 ST6401 ST0906 39.25 power case ST0640 ST1115 ST0278 ST3404 74.0% power case ST0496 ST9193 ST3615 FSV851 The SUPERHEAT cases obtained to determine the helium flow rates for the 832 gpm case are defined in Ref. 1. The SNIFFS code cases used in the verification of the Proto-Power 832 spm case pressure drop calculations are also defined in Ref.1. The SUPERHEAT cases obtained to determine the helium flow rates for the other cases are as follows:
518 gpm 518 gpm Avg. Mod. Hot Mod. Case 5 -7 ( 707 gpm Case Case Case ST2919 ST4605 ST6956 ST8137 ST2213 ST3864 ST6924 ST8075 ST2060 ST3009 ST6986 ST8019 ST35f4 ST5177 ST7040 ST7960 ST4226 ST5555 ST7093 ST8674 ST4745 ST6656 ST7119 ST1418 ST5508 ST1713 ST7149 ST1903 ST6321 ST8621 ST7179 ST2394 ST7207 Page C-2
r-909268/A The SUPERHEAT runs made to study the hot module were: ST3962 ST5117 ST7998
- ST0249 ST4045-f The SNIFFS run made to verify the Proto-Power pressure drop i
i calculation was: I ST6196-M Page C-3
l ATTACHMENT 6 !%}}