ML20210T686

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Rev a to Engineering Evaluation of Reanalysis of FSAR Accidents/Transients Relying on EES Cooling. W/Four Oversize Drawings
ML20210T686
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 02/05/1987
From: Collette P, Geaney G
PROTO-POWER MANAGEMENT CORP.
To:
Shared Package
ML20210T661 List:
References
EE-22-0007, EE-22-0007-RA, EE-22-7, EE-22-7-RA, TAC-63576, TAC-66574, NUDOCS 8702180280
Download: ML20210T686 (47)
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1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Art-Acamw i 0 SCrylCC" PUZLIC CERVICE C'ZMPANY CF CT.LCRADD To 3 8*70 Q ENGINEERING EVALUATION OF THE REANALYSIS OF FSAR ACCIDENTS / TRANSIENTS RELYING ON EES COOLING EE-22-0007 REVISION A Prepared by de bo. 4,I987 P. H. Collet'te Date Proto-Power Corporation Reviewed by '

y G. W. Geehey 1!fDate7 Proto-Power Corporation Verified by WI t!I!87

' Da'te Approved by W L!F!O 7 NUCLEAR LICENSING MANAGER Date 50 7 hD D P

Fonuto3r2 22 3us

FORT ST. VRAIN NUCLEAR GENERATING STATION Public PUBUC SERVICE COMPANY OF COLORADO _cw EE -2.1- oco 1 O Service ~ CHECK LIST OF DESIGN VERIFICATION s e rz s v is s e u A QUESTIONS FOR DESIGN REVIEW METHOD M HH" YES NO N/A h 1. Were the inputs correctly selected and incorporated into design?

2. Are assumptions necessary to perform the design activity adequately described and reasonable?

Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed?

b 3. Are the appropriate quality and quality assurance requirements specified?

4. Are the applicable codes, standards and regulatory requirements including issue and addenda properly identified and are their requirements for design met?

b 5. Have applicable construction and operating experience been considered?

6. Have the design interface requirements been satisfied?

E 7. Was an appropriate design method used?

b 8. Is the output reasonable compared to inputs?

9. Are the specified parts, equipment, and processes suitable for the required application?

g 10. Are the specified materials compatible with each other and the design environmental conditions to which the material will be exposed?

h 11. Have adequate maintenance features and requirements been specified?

12. Are accessibility and other design provisions adequate for performance of needed maintenance and repair?

g 13. Has adequate accessibility been provided to perform the in-service inspection expected to be required during the plant life?

3 14. Has the design properly considered radiation exposure to the public and plant personnel?

g 15. Are the acceptance criteria incorporated in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished?

16. Have adequate pro-operational and subsequent periodic test requirements been appropriately specified?
17. Are adequate handling, storage, cleaning and shipping requirements specified?

b 18. Are adequate identification requirements specified?

k 19. Are requirements for record preparation review, approval, retention, etc., adequately specified?

NOTE: If the answer to any question is no, provide additionalinformation and resolution below.

RESOLUTION OF DESIGN DEFICIENCIES UNCOVERED DURING THE DESIGN VERIFICATION PROCESS Nocl4he,.m c. i e_ y W Ace (omdN LS bCV I Sih A c( 66 *2 7 -600'] ,

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Form l Al 344 224095

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ENGINEERING EVALUATION OF THE REANALYSIS OF FSAR ACCIDENTS / TRANSIENTS RELYING ON EES COOLING EE-22-0007 REVISION A l

Prepared By i

PROTO-POWER CORPORATION l 591 Poquonnock Road Groton, Connecticut 06340 l February 4, 1987 i

l i

EE-22-0007 REV. A INDEX PAGE 1.0 PURPOSE 1

2.0 BACKGROUND

AND

SUMMARY

OF RESULTS 2 2.1 Background 2 2.2 Summary of Results 3 3.t SCOPE 4 4.0 REANALYSIS APPROACH 4 5.0 EVALUATION 5 5.1 Feedwater Cooldown of DBA-2 5 5.2 Fire Water Cooldown 7 5.3 Condensate Cooldown 10 5.4 Other Feedwater Cooldowns 12 a

i

6.0 CONCLUSION

14 r

7.0 REFERENCES

15 i

! 8.0 ATTACHMENTS l

l ATTACHMENT A - Proto-Power Calculation No. 94-01, i dated 1/30/87, " Reanalysis of PSAR Accidents / Transients Relying on i EES Cooling"

l EE-22-0007 REV. A ENGINEERING EVALUATION OF .

THE REANALYSIS OF FSAR I ACCIDENTS / TRANSIENTS RELYING ON EES COOLDOWN 1.0 PURPOSE The purpose of this engineering evaluation is to provide a review and reanalysis of various accidents described in the Fort St. Vrain FSAR (Reference 7.1) which rely on a steam generator economizer-evaporator-superheater (EES) section for shutdown cooling, with cooling water supplied by a ,

condensate or fire water pump. These accidents are listed I and described as Cases 2 through 6 in Table 1A of this evaluation. Review and reanalysis of these accidents is warranted because of recent analyses which concluded that previously analyzed flow conditions and temperature profiles for the fuel and primary coolant reported in the FSAR for ,

Safe Shutdown Cooling from 105% reactor power with fire  !

water after a 90 minute interruption of forced cooling cannot be achieved. This deficiency, which was originally reported in Licensee Event Report (LER) No.86-026 (Reference 7.2), was found to be caused by incomplete original analysis which did not fully consider the fire I water pump capacity or the actual secondary flow path i required for secondary heat removal. Part of the corrective action for LER 86-026 was a commitment to perform a review and a reanalysis, as necessary, of the various FSAR acci-dents relying on fire water or condensate cooling using an EES section. This engineering evaluation fulfills that commitment for reactor power levels up to 83.2 percent.

In conjunction with the Safe Shutdown Cooling analysis described above, potential concerns associated with re-storing flow through a hot steam generator af ter an inter-ruption in cooling have been identified. As a result of these concerns, this evaluation also reviews and reanalyzes the DBA-2 rapid depressurization accident with restoration of feedwater flow through an EES steam generator section after a 60 minute cooling interruption. This scenario is listed as Case 1 on Table 1 A. The scenario is based on the F5AR section 14.11 discussion of DBA-2, with supplemental details concerning a 60 minute delay in cooling provided in Reference 7.3.

Finally, this evaluation reviews other FSAR accident /transi-ent analyses which rely on shutdown cooling using feedwater to an EES section of a steam generator. This review will compare the scenarios listed in Table 1B of this evaluation with other analyses which have been performed in order to demonstrate the adequacy of the feedwater analyses.

EE-22-0007 REV. A

2.0 BACKGROUND

AND

SUMMARY

OF RESULTS

2.1 Background

This engineering evaluation of accident and transient scenarios has been performed to confirm FSAR analyses in light of the recent analysis performed on FSV Safe Shutdown Cooling. systems. Deficiencies in the FSAR cooldown analyses were recently identified during reanalysis of the Safe Shutdown Cooling path to incorporate a piping modification implemented to support the Environmental Qualification (EQ) program.

This recent analysis identified specific problems with Safe Shutdown Cooling from 105% reactor power using both the reheaters and the EES sections after a 90 minute interruption of forced circulation.

Reheater Safe Shutdown Cooling design deficiencies were reported in LER 86-020, Reference 7.4. The LER identified a design omission which could lead to primary coolant temperatures which exceed the allow-able limits for steam generator tube temperatures and helium circulator inlet temperatures. As a result of the reheater cooldown reanalysis, which concluded that the reheaters do not provide adequate capability for Safe Shutdown Cooling above 39 percent power, PSC, in Reference 7.5, has proposed an amendment to the Fort St. Vrain Facility Operating License to eliminate relying on the reheaters for Safe Shutdown Cooling.

The EES deficiencies were also uncovered as a result of Safe Shutdown Cooling reanalysis. The reanalysis determined that the flow conditions and temperature profiles reported in the FSAR for Safe Shutdown Cooling with fire water to the EES after a 90 minute Inter-ruption of Forced Cooling (IOFC) cannot be achieved following operation at 105% reactor power, considering the actual fire water pump capacity and piping con-figuration. Establishing 3% primary coolant flow at the restart of forced cooling causes boiling in the steam generator tubes, and due to the relatively low pressures available using the fire water (or condensate pumps), the specific volume of the low pressure steam in the secondary side of the steam generator increases significantly. These conditions result in decreased mass flow and secondary side heat removal, and the heat removal rate reported in the FSAR analysis is not achievable. Further analysis was performed which was based on controlling helium circulator speed to maintain a constant EES secondary coolant outlet EE-22-0007 REV. A temperature at subcooled conditions, as reported in Reference 7.6. This analysis concludes that each EES section provides adequate capacity for Safe Shutdown Cooling from power levels up to 87.5 percent.

In order to evaluate the maximum power level at which shutdown cooling can be performed using an EES section without exceeding the allowable maximum fuel tempera-ture and without boiling in the steam generator, the Appendix R cooldown flow paths were also analyzed in Reference 7.6.

The limiting Appendix R cooldown analysis, which relies on the condensate system for secondary heat removal from the EES section, was found to provide adequate capability for shutdown cooling, after a 90 minute IOFC, from power levels up to 83.2 percent reactor power.

In general, the results of these analyses necessitated .

review of other abnormal cooling scenarios presented in the FSAR to determine if similar conditions of in-adequate secondary side cooling with an EES section exist. The analysis performed as part of this evalu-ation evaluates the available secondary heat removal capacity of each cooldown method ( feedwater, fire water and condensate) for specific FSAR accidents / transients as listed in Tables 1A and 1B and concludes that adequate cooling exists for shutdown from 83.2% reactor power.

2.2 Summary of Results Condensate and Fire Water Cooling The results of this evaluation are summarized on Table

2. Reanalysis of the shutdown cooling using fire water and condensate in the EES section (Cases 2 thru 6 on Table 1A) concludes that the heat removal capacity is limited by secondary side (water) flow through the steam generators, rather than by the primary (helium) flow conditions previously evaluated in the PSAR. The heat removal rates determined for the fire water and condensate cooling exceed the heat removal rate established for the limiting operating condition of C3.2% reactor power in accordance with the Appendix R condensate cooling analysis of Reference 7.6. There-fore, the PSAR conclusions for Cases 2 through 6 of Table 1A are adequate for at least 83.2 percent power.

EE-22-0007 REV. A Feedwater Cooling for DBA-2 The results of the DBA-2 accident with a 60 minute interruption in cooling (Table 1A, Case 1) are also reported in Table 2. The analysis of the secondary side heat removal, with feedwater cooling of the EES section confirms that the water side heat removal supports the primary side heat removal rate established in the Reference 7.3 analysis. As a result, the DBA-2 accident analysis presented in the FSAR and in Reference 7.3 remains unchanged (i.e., cooldown from 105% reactor power is adequate).

Other Feedwater Cooling Scenarios The feedwater scenarios presented in Table IB have been reviewed with respect to normal plant operating conditions, cooling system components and flow paths, and recent cooldown analyses. Based on this evalu-ation, the scenarios in which forced cooling is not interrupted are considered valid from 105% reactor power as presented in the FSAR. The evaluation also concludes that the scenario of FSAR Section 14.4.4.2 (Table 1B), which includes a 30 minute IOFC, is adequate for cooldown from the Appendix R cooldown limitation of 83.2% reactor power.

3.0 SCOPE The Fort. St. Vrain FSAR includes six transients listed in Table 1A as cooldown scenarios which rely on the EES section of the steam generator for reactor heat removal. Analysis has been performed to reassess the secondary side heat removal for these cooldown modes. The reevaluation of transients relying on feedwater listed in Table IB is accomplished by comparing these scenarios with normal operating conditions and other recent shutdown cooling analyses.

4.0 REANALYSIS APPROACH l

The flowpaths for each of the transients has been based on information provided in the PSAR, and in Fort St. Vrain Procedures, References 7.7, 7.8 and 7.9. It is noted that specific cooldown flowpaths for each of these scenarios are not currently provided in detail in the PSAR. Accordingly, the flowpaths selected for the purpose of analysis are con-sidered to be representative of those which were previously analyzed in the PSAR and more significantly, those that

! would be used should the actual accident conditions occur at l the plant.

L

EE-22-0007 REV. A These transients utilize three different cooling sources; feedwater, condensate, and fire water.

Once flowpaths are determined, the cooling system flowrates and corresponding heat removal capacities which can be achieved with each scenario are determined using the same approach developed as part of the PSV EQ program by Proto-Power for EES and Reheater flow analysis. The analysis is performed using two computer programs, PRDRNEW and FSVSGNEW, iteratively, to evaluate the fluid flow and heat transfer capacity through the cooldown path.

5.0 EVALUATION 5.1 Feedwater Cooldown [ Case 1: DBA-2]

5.1.1 DBA-2 Cooldown Scenario DBA-2 is the rapid depressurization of the primary coolant system resulting from the postulated simultaneous failure of both primary and secondary PCRV penetration closures in that penetration affording the largest flow area.

The FSAR evaluation of this event is included in Section 14.11, and has been expanded in Reference 7.3 to include the effects of an IOFC of up to 60 minutes. The accident does create a harsh Reactor Building environment, and equipment in that building which is not environmentally qualified is assumed to be inoperable after the accident. Since the accident is considered hypothetical, no additional single failures are postulated.

l In order to provide adequate primary coolant circulation with a depressurized PCRV, two circulators must be driven at high speed. The PSAR analysis evaluated cooldown using high pressure feedwater for circulator operation at 8000 RPM. Ileat removal is accomplished by providing feedwater to an EES section of a j steam generator.

5.1.2 Peedwater Cooldown Flowpath The flowpath used in the analysis of this accident is shown on Drawing No. 7511494-PP-15 Rev. A and is included with Attachment A.

Since the PSAR scenario does not postulate any equipment failures, all of the normally used I and environmentally qualified equipment is considered available, i

1 1

EE-22-0007 REV. A Condensate is pumped from the condenser via one 60% capacity condensate pump and supplied to the motor driven feedwater pump. For analysis purposes, the condensate flowpath was evaluated with flow bypassing major components such as the demineralizer, air ejectors and the low pressure feedwater heaters. This was done primarily to simplify and expedite the

, analysis. The analysis demonstrates, however, that the condensate system with the 60% pump operating has more than adequate capacity for the flowpath analyzed. The analysis has conservatively assumed the condenser is at atmospheric pressure, and that feedwater is at 200*F temperature. However, condenser vacuum would be expected during this accident since bypass flash tank steam would be available for the condenser hogging and air ejectors.

Condenser vacuum, if available, would tend to increase flow by lowering the downstream pressures.

\ The feedwater pump discharge is directed to one EES section and two pelton. wheel drives via the

, emergency feedwater header. After passing through the steam generator, the heated feedwater is discharged from the EES section

, via the main steam bypass line, and is directed

_ through the desuperheater, bypass flash tank, and the emergency bypass flash tank drain to the condenser.

5.1.3 Feedwater Cooldown Results for DBA-2 Analysis The Attachment A analysis of primary and secondary side steam generator heat balance, the results of which are summarized in Table 2, concludes that the feedwater system has adequate capacity to remove the primacy side heat load. The DBA-2 primary side (helium) heat load, after a 60 minute IOFC, is 76.4 x 106 BTU /hr. This heat load is due to a primary coolant flow rate of 38,448 lbs/hr (Table 3-8 of Reference 7.10: 2 circulators in a loop at 8000 RPM), with a steam generator inlet helium temperature of 1800*F (per Reference 7.3) and a steam generator helium outlet temperature of 200*P. With these primary conditions, the Attachment A analysis calculated a 1500 gpm feedwater flow, which was more than adequate for secondary cooling. Based on these primary side conditions, feedwater, with a 200*F inlet

=_

EE-22-0007 REV. A temperature, exits the EES section as a subcooled liquid at 301.9'F and 790 psia. This outlet pressure provides 216*F of subcooling in the steam generator.

This cooldown scenario could be expected to result in some hot steam generator modules since the harsh Reactor Building environment would be assumed to cause the feedwater trim valves to fail open. Hot modules result from localized regions of the core which have higher than average heat fluxes. Normally, uniform secondary coolant outlet temperatures from each EES module are obtained by. adjusting the feedwater trim valves with increased flow biased to the hot modules. The hot module heat load for the conditions evaluated in Reference 7.6 with cooldown after operation at 83.2%

reactor power, can be determined to be approxi-mately 22% higher than that for the nominal heat load. This distribution of heat load is assumed to be generally applicable to the conditions evaluated in this analysis. With the DBA-2 cooling watercinlet and outlet tempera-ture of 200*F and 301.9'F' reported above, and assuming the same hot module heat distribution reported in Reference 7.6, a 22% water tempera-ture rise through the hot module would result in a maximum outlet temperature of about 324*P.

Since 194*F of subcooling is maintained on the hot module, no boiling in the steam generator would occur. It is noted that two-phase flow does occur downstream of the steam generators as the pressure falls below the saturation pressure of the heated feedwater.

As a result of the Attachment A analysis performed to determine the secondary side flow l rates and heat removal capacity discussed above, the conclusions of DBA-2 accident l analysis, as reported in the PSAR and in Reference 7.3, remain unchanged.

5.2 Fire Water Cooldown [ Case 3 - Abnormal Shutdown]

l f ,

I l 5.2.1 Abnormal Shutdown Cooling This accident is based on the discussion of shutdown cooling after the loss of normal cooling presented in Section 14.4.2.1 of the PSAR. Although the PSAR does not specifically ,

discuss an IOFC with this scenario, some delay would be required to initiate fire water flow.

I i= 1; I.

v , - -. - . - , . ,-

EE-22-0007 REV. A '

This delay should, however, be significantly less than the 90 minutes delay associated with Safe Shutdown Cooling.

i For this scenario, the PSAR assumes all three feedwater pumps are inoperable, and shutdown

-cooling may be accomplished using either fire water or condensate pumps for helium circula-tion and heat removal.

The FSAR evaluation of this abnormal cooling i scenario is not part of any specific accident scenario and no active or passive failures of equipment are postulated.

The FSAR analysis concluded that one fire water pump would provide adequate heat removal as  ;

well as 3% of the normal primary coolant '

, circulation via one circulator with boosted fire water to the pelton wheel drive. The FSAR analysis reports a peak average core outlet helium temperature of 1530*F, with a maximum l fuel temperature of 2050*F.

J.

5.2.2 Fire Water Flowpath i The fire water . cooldown flow path is shown on U Drawing No. 7511494-PF-13 Rev. A ,- and is included with Attachment A. Fire water is aligned to one loop of the EES section via the emergency . condensate header. The steam generator discharge is aligned to the Bypass Flash Tank (BFT) via the main steam bypass line and then discharged to the condenser via the BFT drain. A fire water inlet temperature of 80*F, which is consistent with the Reference 7.6 analysis, was used in the calculations.

Fire water returned to the condenser, which is assumed to be at atmospheric pressure, is drained to the Turbine Building sump via V-4165. The fire water is used in a once-through open loop cooling. The flow path is similar to cooldown option "L" in Reference 7.7. ,

L Table 3-9 of the circulator technical manual, Reference 7.10, indicates a 121 gpm flowrate of boosted fire water to a single pelton wheel is necessary to obtain the 3% helium flow assumed i in the FSAR analysis. For analysis purposes, a 175 gpm pelton wheel flowrate was conserva-l tively assumed.

j . - - - - -

EE-22-0007 REV. A 5.2.3 Fire Water Flowpath Analysis Results The Attachment A analysis demonstrates fire water cooling of an EES section of the steam generators is capable of removing a 86.7 x 106 BTU /hr heat load, with an 795 gpm flowrate exiting the steam generator at 300*F with 20*F subcooling in the steam generators. The analysis results are summarized in Table 2. The subcooling is within the margin of newly speelfied outlet temperature instrumentation, which is expected to have an accuracy of + 8'F.

.The corresponding steam generator outlet pressure, as sensed at PT-22129 (typical), is 83 psia.

A 300*F steam generator outlet temperature was used in the analysis. This outlet temperature i would be controlled by varying the operating circulator speed.

An average peak inlet helium temperature of 1530*F reported in the FSAR for this scenario was used in the analysis. No hot module effect is considered since the feedwater trim valves would be operational during this scenario. The flow model used in this analysis includes the effects of feedwater trim valve throttling.

The maximum flowrate, as calculated in Attach-ment A, with these conditions, is limited to 795 gpm since two-phase flow occurs in the lower pressure piping downstream of the steam generators. This flowrate was obtained without throttling any control valves, other than biasing the feedwater trim valves to control i hot modules.

The heat removal capacities of the fire water system during this scenario are not specifi-cally reported in the FSAR analysis, and the results of this analysis and the FSAR analysis cannot be directly compared. However, in-I spection of the FSAR Figure 14.4-3, which shows j helium flow and helium temperatures at the

, inlet and outlet of the steam generator, allows j calculation of the fire water heat removal ,

capacity assumed available in the FSAR analysis. The heat removal capacity assumed to be available in the FSAR as calculated from Figure 14.4-3 is approximately 180 x 10 6 BTU /hr, and is significantly higher than the cooling actually available on the secondary l

EE-22-0007 REV. A side. This discrepancy is due to the assump-tions utilized in the original FSAR analysis.

The FSAR analysis assumed that primary coolant side controlled shutdown cooling, and there-fore, the secondary side heat removal was not modeled.

The heat removal capacity of 86.7 x 106 BTU /hr obtained in the analysis does, however, exceed the heat removal capacity for the 83.2 percent reactor power cooldown analysis reported in Reference 7.6. Table 2-1 of Reference 7.6 shows a limiting heat load of 73.5 x 106 BTU /hr, based on the limiting Appendix R cooldown after a 90 minutes IOFC. Since the heat removal capacity calculated herein t provides additional cooling capacity over the Appendix R case, and since a 90 minute IOFC is not postulated for this event, fire water cooling for the Abnormal Coolins scenario of Case 3 (FSAR paragraph 14.4.2.1) exceeds the limiting Appendix R conditions. The fire water cooldown scenario is therefore adequate for cooldown from 83.2 percent reactor power.

5.3 Condensate Cooldown [ Cases 2, 4, 5, 61 5.3.1 Condensate Cooldown Scenarios The four condensate cooldown cases listed in Table 1A of this evaluation have been analyzed in the FSAR. Although each of these scenarios has a different background, the same condensate cooldown flowpath is utilized.

One condensate cooldown analysis was performed for all of these scenarios since the secondary side flowpath, not the primary side, has been shown to be the limiting condition for heat removal.

Case 2, FSAR Section 14.4.2.1, Abnormal Shutdown Cooling, is essentially the same scenario evaluated in Section 5.2 of this evaluation, except, condensate rather than fire water is used for cooldown after a postulated loss of feedwater. The abnormal shutdown cooling scenario of Case 2 is, in fact, the FSAR safety evaluation of the event discussed in FSAR Section 10.3.7, which is listed as Case 6 on Table 1A.

r EE-22-0007 REV. A In Cases 4 and 5, condensate is used for helium circulation and heat removal after a coincident Loss of Outside Electric Power (LOEP) and Main Turbine Trip. In case 4, feedwater is utilized for cooling during the first 25 minutes, at which time the condensate system, with 2 circulators operating, is used to continue the cooldown. Case 5 differs from Case 4 in that only one standby diesel generator is assumed operable, and the switch to condensate, with one circulator operating, is at 35 minutes. A review of the cooldown profiles for Cases 4 and 5, shown in FSAR Figures 10.3-1 and 10.3-2, respectively, show that significant helium temperature reductions, to about 750*F, have occurred by the time the condensate cooling is established.

Since the heat removal requirements are significantly higher for Case 2, (and 6), this case was chosen for analysis. The results of this analysis are considered valid for Cases 4 and 5 since they are bounded by the Case 2 which relies solely on condensate rather than an initial cooldown via the higher capacity feedwater and steam systems.

5.3.2 Condensate Cooldown Flowpath The PSAR analysis of Case 2 considered cooldown using one 12-1/2% condensate pump for primary coolant circulation and heat removal via the EES section of one steam generator. Process Flow Diagram No. 7511494-PF-14 Rev. A, included in Attachment A, shows the flowpath from the main condenser, through a condensate pump, to the emergency condensate header. The conden-sate is directed through one EES loop of the steam generator and returns to the condenser via the same path used in the fire water flow analysis. This flowpath is similar to Option E of Reference 7.7.

Although discussions with plant personnel indicate that condenser vacuum should be maintainable with air and hogging ejectors operable via flash tank or auxiliary boiler steam, the pressure is conservatively assumed to be atmospheric. A 100*F condenser outlet temperature is assumed.

EE-22-0007 REV. A 5.3.3 Condensate Cooldown Results The steam generator heat removal capacity was found to be 73.6 x 10 6 BTU /hr, with a 510 gpm flowrate exiting the steam generator with 14.5*F subcooling. The analysis results are summarized in Table 2. The steam generator outlet temperature for this analysis was assumed to be controlled to 390*F by varying the operating circulator speed. The steam generator outlet pressure, as sensed at PT-22129 (typical) is 255.8 psia.

A 175 gpm flowrate to a circulator pelton wheel drive was considered in the flow analysis.

A 1520*F average peak helium temperature was taken from the PSAR for this scenario. Also, there were no hot module concerns since the feedwater trim valves would be operable.

The steam generator flowrate is limited to 510 gpm as the 390*F condensate approaches its saturation pressure in the superheater. The flow becomes two-phase downstream of the steam generators as the pressure in the piping falls below the saturation pressure of the heated condensate.

The heat removal capacity assumed in the PSAR can be determined from Figure 14.4-2, which gives helium flowrates and temperatures during the cooldown. The peak heat removal capacity assumed to be available, as determined from the PSAR curves, is approximately 259 x 106 BTU /hr.

This heat removal capacity is far in excess of the actual calculated heat removal capability of the secondary side.

Since the actual calculated secondary side heat removal capacity of 73. 6 x 106 BTU /hr exceeds the Appendix R limiting condition of 73.5 x 106 BTU /hr for 83.2 percent reactor power the use of condensate cooling for this power level is justified.

5.4 Feedwater Cooldown The ability to safely remove heat from the reactor, using feedwater, is discussed in FSAR Sections 10.3.3, 14.4.2, 14.4.3.2 and 14.4.4.2. A review of each of these scenarios follows.

EE-22-0007 REV. A 5.4.1 FSAR Paragraph 10.3.3, 14.4.2 Review Section 10.3.3 entitled, " Loss of Reactor Generated Steam" discusses plant operation following a steam line rupture in either loop or in common main steam or reheat steam piping.

The evaluation of a common reheat line break assumes plant cooldown is accomplished using a feedwater pump. The Safety Evaluation for this accident is reported in FSAR Section 14.4.2.

FSAR Section 14.4.2 entitled, " Cooling with One Water-Turbine Driven Circulator Driven by Feedwater - Normal Helium Pressure" is the cooldown evaluation of an accident resulting in the complete loss of steam for circulator operation. This is the accident analyzed in Section 10.3.3 and discussed above.

This scenario is similar to the EES cooldowns previously discussed in this evaluation, with the major difference between the feedwater versus the fire water / condensate cooldowns being the increased feedwater capacity. The feedwater pump capacity, rated for 1770 gpm at 3315 psig, is significantly higher than a small condensate pump (580 gpm at 307 psig) or fire water pump (1500 gpm at 125 psig) capacity.

Additionally, it is noted that a single feedwater pump is used for normal plant startup and shutdown. Furthermore, the plant can be operated at one-third capacity (33% power) with a single feedwater pump. From FSAR Figure D.1-9, the peak decay heat load at shutdown is less than 4%, and drops exponentially. Hence, it is evident that a feedwater pump will provide the necessary heat removal capacity when utilized for shutdown cooling using essentially the same flow path as used for normal operation without an interruption in cooling. FSAR Section 10.3.3 will be revised, however, since the discussion of Saf e Shutdown Cooling following a steam line rupture is not consistent with the latest philosophy developed during the Environmental Qualification Program.

As a result of the EQ program, feedwater would only be available following certain reactor building line breaks, and would not be relied upon for Safe Shutdown Cooling following a HELB.

EE-22-0007 REV. A 5.4.2 FSAR Paragraph 14.4.3.2 Review FSAR Paragraph 14.4.3.2 is the evaluation of the maximum credible helium leak coupled with the loss of steam to the circulators. This analysis is bounded by DBA-2, which has been evaluated with feedwater used for helium circulation and heat removal. This analysis, discussed in Paragraph 5.1 of this evaluation, concludes that a single feedwater pump will

. provide adequate heat removal following full power operation and a one hour interruption in cooling after a complete depressurization of the PCRV.

5.4.3 FSAR Paragraph 14.4.4.2 Review FSAR Paragraph 14.4.4.2 entitled, " Total Interruption of Coolant Flow for 30 Minutes",

is the Safety Evaluation for feedwater cooling after a 30 minute interruption of forced cooling (IOFC). The use of feedwater for recovery following a 30 minute IOFC is justi-fied by comparison to the Reference 7.6 analysis of shutdown cooling using EQ or Appendix R flowpaths while operating at 83.2 percent reactor power. In the Reference 7.6 analysis, a 90 minute IOFC was analyzed with cooling provided by either a condensate or fire water pump with cooling flow through an EES section of a steam generator. Based solely on the significantly increased feedwater pump capacity versus the smaller condensate and fire water pumps, it is concluded that feedwater cooling, via one EES section, will provide adequate cooling following a 30 minute IOFC from 83.2 percent reactor power.

6.0 CONCLUSION

6.1 On the basis of this evaluation, it is concluded that condensate and fire water cooldown scenarios described in the FSAR, listed as Cases 2 through 6 in Table 1 A, and reevaluated herein will be adequate for shutdown cooling from the Appendix R limit of 83.2 percent reactor power.

o.2 The ability to cooldown the reactor from full power operation with two circulators driven by feedwater af:er a DBA-2 accident (Case 1 of Table 1A), as dencribed in the FSAR and in Reference 7.3, has been ccnfirmed by this evaluation.

, , _ ._.-~ __ _ _ _ _ __ _ _ _

EE-22-0007 REV. A l

l 6.3 Based on comparison to the Attachment A calculations supporting fire water, condensate, and feedwater cooling, feedwater is considered to be adequate for cooldown from 105% reactor power following transients described in the FSAR Sections 10.3.3, 14.4.2, and 14.4.3.2. On the same comparison basis, the FSAR transient discussed in Section 14.4.4.2 is considered adequate for cooldown from 83.2 percent reactor power.

7.0 REFERENCES

7.1 Fort St. Vrain Updated Final Safety Analysis Report (FSAR), Revision 4.

7.2 PSC Letter P-86587, J.W. Gahm to Document Control Desk, USNRC,

Subject:

Licensee Event Report,86-026, Final Report, October 17, 1986.

7.3 GA Technologies Report No. 908338, Issue A, dated October 31, 1985, "FSV:DBA No. 2 Rapid Depressuri-zation/ Blowdown, Delayed Forced Circulation Cooling."

7.4 PSC Letter P-86513, J.W. Gahm to Document Control Desk, USNRC,

Subject:

Licensee Event Report,86-020, Prelimi-nary Report, August 11, 1986.

7.5 PSC Letter P-87002, R.O. Williams Jr. to H.N. Berkow,

Subject:

" Proposed Technical Specification Change Eliminating Reliance on Reheater Section of the Steam Generator for Safe Shutdown Cooling," January 15, 1987.

7.6 GA Technologies Report No. 909269, Issue A (Draft),

"EES Cooldowns for EQ and Appendix R Events with Vent Lines (1.5 Hour Delay)."

7.7 Fort St. Vrain Procedure, " Safe Shutdown Cooling with Highly Degraded Conditions" (SSCHDPC), Issue 14, dated October 7, 1985.

7.8 Fort St. Vrain Procedure, " Abnormal Procedures for Shutdown Cooling" (APSC), Issue 6, dated January 11, 1983.

7.9 Fort St. Vrain Procedure, Emergency Procedure B-1,

" Reactor Scram (Without Two Loop Trouble)", Issue 52, dated August 14, 1984.

7.10 Fort St. Vrain Helium Circulator Technical Manual, GA Document No. GA-A10349, Revision C, dated August 1977.

EE-22-0007 REV. A TABLE 1A FSAR ACCIDENTS / TRANSIENTS FOR REANALYSIS OF EES C00GXM4 FSAR COOLING DELAY IN CASE SECTIN FIGURE DESCRIPTIN MkTER m.TW FIDEPATH POR mm.TE WATER 1 14.11.2.2 14.11-13 DBA-2 RAPID DEPRESSURIZATIN-THO FEEDWATER 60 MIN. FEEDWATER PUMPS 'IO EES VIA HELIUM CIRCULA'IORS ON FEEDWATER EMERGENCY PEEDWATER HEADER,

'IHRU EES 'IO BYPASS FIASH TANK VIA DESUPERHEATERS, AtO 'INEN 'IO MAIN COWENSER VIA FLASH TANK DRAINS.

2 14.4.2.1 14.4-2 ABNORMAL SIRTIDOWN COOLING CONDENSA'IE Note 1 12-1/2% COWENSATE PUMP 'IO HELIUM CIRCUIA'IOR ON CONDENSATE EES VIA EMERGENCY CONDEN-SATE HEADER, 'IHRLi EES '1D BYPASS FLASH TANK VIA DE-SUPERHEATERS A!O 'IEEN 'IO MAIN 00tOENSER VIA FLASH TANK DRAINS.

3 14.4.2.1 14.4-3 ABNORMAL SHUTDOl@i COOLIE FIREWATER Note 1 FIREWATER PUMPS 'IHRU EMER-HELIUM CIRCUIA'IOR ON BOOSTED GENCY C0tOENSATE HEADER, FIREWATER 'IHRU EES 'IO BYPASS FLASH TANK VIA DESUPERHEATERS AND

'IHEN 'IO MAIN 00tOENSER VIA FLASH TANK DRAINS.

4 10.3.1 10.3-1 COINCIDENTAL IOSS OF OLTISIDE CONDENSA'IE Note 1 SAE AS 2 ABOVE.

POWER AND MAIN 'IURBINE TRIP -

SWI'IGI FRCM STEAM 'IO CONDENSATE

'IO 'INO HELIUM CIRCUIA'IORS AFTER 25 MINLTIES 5 10.3.2 10.3-2 SAME AS 4 ABOVE, BUT ONLY 1 CONDENSATE Note 1 SAME AS 2 ABOVE.

10.3.4 STANDBY GENERATOR - SWI'IGI FRCM STEAM 10 CONDENSATE 'IO ONE HELIUM CIRCUIATOR AFTER 35 MIN.

6 10.3.7 SINLTANEOUS IOSS OF 3 FEEDWATER CONDENSATE Note 1 SAME AS 2 ABOVE.

(Note 2) PUMPS - ONE HELIUM CIRCUIATOR m CONDENSATE

EE-22-0007 REV. A TABLE 1B FSAR ACCIDENTS / TRANSIENTS REVIEWED FOR EES COOLING ADEQUACY FSAR COOLING DELAY IN SECTION DESCRIPTION WATER COOLING 10.3.3 Loss of Reactor Generated Steam Feedwater Note 1 1 I

14.4.2 Cooling with One Water Turbine (Note 3) Circulator Driven by Feedwater l

14.4.3.2 Maximum Credible Helium Leak Feedwater Note 1 14.4.4.2 Total Interruption of Coolant Feedwater 30 Minutes Flow for 30 Minutes l

l Notes for Table 1A and Table 1B

1. No delay specified in FSAR. A minimal IOFC may result from transient event or shutdown cooling alignment.
2. FSAR Section 14.4.2.1 is the Safety Evaluation for the Section 10.3.7 scenario.
3. FSAR Section 14.4.2 is the Safety Evaluation for the Section 10.3.3 scenario.

EE-22-0007 REV. A.

TABLE 2 ANALYSIS RESULTS 4

FEEDWATER DBA-2 FIRE WATER CONDENSATE-(Case 1) (Case 3) (Cases 2,4,5 & 6)

Secondary Cooling Flowrate, GPM 1500 795 510 Steam Generator Helium Inlet, *F 1800 1530 1520 Steam Generator Helium Outlet, *F 200 80.3 100.3 Steam Generator Water Inlet, *F 200 80 100 Steam Generator Water Outlet, *F 301.9 299.3 390 Minimum Steam Generator Pressure, psia 800.7 90.5 261.5 Steam Genera?.or Outlet Pressure, psia 790 83.1 255.8 (at PT-22129, typical)

Steam Generator Subcooling, *F 216 20 14.5 Heat Removal, BTU /hr x 106 76.4 86.7 73.6

W EE-22-0007 REV. A

. ATTACHMENT A CALCul.ATION COVER SHEET PROTO-P0llER CORPORATION TITLE: REANALYSIS OF FSAR ACCIDENTS / TRANSIENTS RELYING ON EES COOLING CALCULATION NO : 94-01, Rev. A FILE NO.: '7511494 -

R. R. Shultz CALCULATED BY DATE If26/87 CHECKED BY P. H. Collette DATE /SO/87

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1. PURPOSE
2. BACKGROUND
3. APPROACH
4. RESULTS
5. REFERENCES ATTACHMENTS: 1. Computer Input Files and Printouts -

PSAR Shutdown Cooling using Fire Water, 175 GPM Pelton Wheel Flow

2. Computer Input Files and Printouts -

FSAR Shutdown Cooling using Conden-sate, 175 GPM Pelton Wheel Flow

3. Computer Input Files and Printouts -

FSAR Shutdown Cooling using Feed-water, 830 GPM Pelton Wheel Flow

4. Drawing No. 7511494-PF-13, Rev. A
5. Drawing No. 7511494-PF-14, Rev. A
6. Drawing No. 7511494-PF-15, Rev. A

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1. PURPOSE ,

i To determine the secondary cooling water flow rates and pressures through the three separate cooling water flow paths identified in the PSAR and described in EE-22-0007. I Also, to determine the heat removal rates associated with each of the three cooling water flow paths.

2. BACKGROUND Three separate, alternate steam generator flow paths have been developed for shutdown cooling. These flow paths have been developed in accordance with the FSV FSAR and are described in EE-22-0007.

I

3. APPROACH The computer program "PRDRNEW" and approach of Reference (b) were used to determine the system pressure drop of the three FSAR flow paths. The computer p;pgram 'FSVSGNEW', Reference (c), was used to determine secoidary coolant temperatures within the steam generator sections and the heat removal rate through the steam generators.

Steam generator " hot module" effects were incorporated into the analyses of the cooldown flow paths using fire water and condensate. The " hot module" effects were modeled by throttling the steam generator inlet trim valves to yield an average valve flow coefficient (Cv) of 33.6 as calculated in Reference (d). For the analysis of the cooldown flow path using feedwater, the trim valves were assumed to be wide open since they are not environmentally qualified and they are located in the Reactor Building which is considered to be a harsh environment during the DBA-2 accident.

The flow path and associated hydraulic resistances for the cooldown flow path using fire water are shown on Proto-Power Drawing No. 7511494-PF-13, Rev. A. This information was used to create the computer input files for the analysis.

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The fire water cooldown flow path is from one fire water pump to the EES sections of one loop via the emergency i condensate header, from the EES sections to the bypass flash l tank via the desuperheater, and then from the bypass flash  ;

tank to the main condenser via the flash tank drains.  :

The flow path and associated hydraulic resistances for the '

cooldown flow path using condensate are shown on Proto-Power Drawing No. 7511494-PF-14, Rev. A.

i The condensate cooldown flow path is from one 12-1/2% >

condensate pump to the EES sections of one loop via the emergency condensate header, from the EES sections to the bypass flash tank via the desuperheater, and then from the bypass flash tank to the main condenser via the flash tank 9 drains. j

( The flow path and associated hydraulic resistances for the

( cooldown flow path using feedwater are shown on Proto-Power Drawing No. 7511494-PF-15, Rev. A.

The feedwater cooldown flow path is from the motor driven feedwater pump to the EES sections of one loop via the emergency feedwater header, from the EES sections to the bypass flash tank via the desuperheater and then from the bypass flash tank to the main condenser via the flash tank drains.

The feedwater cooldown flow path analysis also included the path from the main condenser to the feedwater pump suction via a 60% condensate pump.

4. RESULTS Fire Water Cooling Detailed results of the analysis of the EES cooldown flow path using fire water are presented in Attachment 1. For this analysis, fire water temperature and helium temperature entering the steam generator were 80*F and 1530*F respectively. The pelton wheel flow was 175 GPM.

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, 4 k g gg ( jyL jgg In the analysis of the cooldown flow path using fire water, ,

the steam generator water outlet temperature was fixed at 299.3*F by varying circulator speed. With a flow rate of 795.0 GPM through the steam generators, the heat removal rate was 86.7 x 106 BTU /hr.

The results of the analysis of the cooldown flow path using fire water are summarized in Table A.

TABLE A Cooling Water Fire Water Flow Throttled No Stm. Gen. Water Flow, GPM 795.0 Pelton Wheel Flow, GPM 175.0 Stm. Gen. Inlet Temp.(Water), *F 80.0 Stm. Gen. Outlet Temp.(Water), *F 299.3 Stm. Gen. Inlet Temp.(Helium), *F 1530.0 Stm. Gen. Outlet Temp.(Helium), *F 80.3 Heat Removal Rate, BTU /HR 86.7 x 106 Subcooling in Stm. Gen., *F 20.0 Minimum Pressure in Stm. Gen., PSIA 90.5 Stm. Gen. Outlet Pressure, PSIA 83.1 at PT-22129 Computer Sheets, Attachment 1

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.,oe ~o atvuta f4 7gjj49 CUENT PROJECT P6AR ERAeIv> LING i Condensate Cooling Detailed results of the analysis of the EES cooldown flow path using condensate are presented in Attachment 2. For this analysis the condensate temperature and helium tempera-ture entering the steam geterator were 100*F and 1520*F respectively. The Pelton wheel flow used was 175.0 GPM.

I In the analysis of the cooldown flow path using condensate, i a steam generator water outlet temperature of 390.3 was  !

used. At this temperature, a maximum flow rate of 510.0 GPM l could be passed through the system while maintaining i approximately 15'F of subcooling in the steam generator. l PV-2229 and HV-3250 were throttled to maintain subcooling in I the steam generator and to maintain pressure below the setpoint of the pressure relief valves downstream of the l bypass flash tank. The heat removal rate with these conditions was found to be 73.6 x 106 BTU /hr.

The results of the analysis of the cooldown flow path using condensate are summarized in Table B.

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7gjj494 CUENT PROJECT susseCT pg49 g[gg gfjg,fjg TABLE B Cooling Water Condensate Flow Throttled Yes Stm. Gen. Water Flow, GPM 510.0 Pelton Wheel Flow, GPM 175.0 Stm. Gen. Inlet Temp.(Water), *F 100.0 Stm. Gen. Outlet Temp.(Water), *F 390.3 Stm. Gen. Inlet Temp.(Helium), *F 1520.0

( Stm. Gen. Outlet Temp.(Helium), 'F 100.3 Heat Removal Rate, BTU /HR 73.6 x 106 Subcooling in Stm. Gen, "F 14.5 Minimum Pressure in Stm. Gen., PSIA 261.5 Stm. Gen. Outlet Pressure, PSIA 255.8 at PT-22129 Computer Sheets, Attachment 2 Feedwater Cooling for DBA-2 Detailed results of the analysis of the EES cooldown for DBA-2 using feedwater are presented in Attachment 3. For this analysis, the feedwater temperature and helium tempera-ture entering the steam generator were 200*F and 1800*F respectively. Per the PSAR (Table 4.2.3), a pelton wheel flow of 415 GPM per circulator is sufficient to drive two machines at 8000 RPM and provide 38,448 lb/hr (total) of helium circulation with the PCRV depressurized.

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F5AR EES CooLil)6 In the analysis of the cooldown flow path using feedwater, the helium and feedwater conditions described in the FSAR were used as inputs for the computer program 'FSVSGNEW' to determine a steam generator water outlet temperature of 301.9'F. The water flow rate through the steam generator was 1500 GPM. HV-31119, FV-2205, PV-22129, and HV-3250 were throttled to avoid actuation of the pressure relief valves downstream of the bypass flash tank. LCV-3175-1 was throttled to avoid actuation of the dearating feedwater pressure relief valve.

The results of the analysis of the cooldown flow path using feedwater are summarized in Table C.

TABLE C Cooling Water Feedwater Flow Throttled Yes Stm. Gen. Water Flow, GPM 1500.0 1

Pelton Wheel Flow, GPM 830.0 Stm. Gen. Inlet Temp.(Water), *F 200.0 Stm. Gen. Outlet Temp.(Water), *F 301.9 Stm. Gen. Inlet Temp.(Helium), *F 1800.0 Stm. Gen. Outlet Temp.(Helium), *F 200.0 Heat Removal Rate, BTU /HR 76.4 x 106 Subcooling in Stm. Gen., *F 216.0 Minimum Stm. Gen. Pressure, PSIA 800.7 Stm. Gen. Outlet Pressure, PSIA 790.0 at PT-22129 Computer Sheets, Attachment 3

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5. REFERENCES
a. FSV FSAR, Revision 4, Sections 14.11.2.2, 14.4.2.1
b. PPC Calculation 82-01, "EES Safe Shutdown Cooling for PSC - Fort St. Vrain," Sept. 11, 1986
c. PPC Computer Program "FSVSGNEW"
d. PPC Calculation 82-14, "EES Hot Module Compensation by Trim Valve Throttling", Jan. 27, 1987
      • FILE: FSARPF13.DAT ***

SECTION -

ID -WDIV- K(FIX)- K(VAR)- EPS - EL -FL.- TF - MIN - MAX 55 1 : 1 17 ,10.020, 0.1, 9.1, 649.3,1.500D-4, 11.6, 1, 80.0, NA , NA 2 17 - 6 , 7.981, 0.1, 3.1, 77.6,1.500D-4, 17.2, 1, 80.0, NA , NA 3 6-7 , 7.981, 1, .91, 61.4,1.500D-4, 0.2, 1 80.0, NA , NA 4 : 7-8 , 7.870, 1, 4.9, 30.1,1.500D-4, 0.3, 1, 80.0, NA , NA 5: 8-9 , 9.516, 1, 37.8, 59.7,1.500D-4, 4.3, 1, 80.0, NA , NA 6: 9- 10 , 9.172, 1, .98, 136.3,1.500D-4, -60.6, 1, 80.0, NA , NA 7 : 10 - 11 , 9.172,1.81, .42, 94.2,1.500D-4, -0.3, 1, 80.0, NA , NA 8 : 11 - 12 , 3.152, 6, 2.4, 102.1,1.500D-4, 9.0, 1, 80.0, NA , NA 9 :TV-2227-6, 3.152, 6, 0.0, 0.0,1.500D-4, 0.0, 6, 80.0, 33.6, 0.9 10: 12 - 18 , 3.150, 6, .62, 0.0,1.500D-4, 0.0, 1, 80.0, NA , NA 11: 18 - 19 , 3.346, 6, .59, 26.20,1.500D-4, -4.6, 1, 80.0, NA , NA 12: 19 - 20 , 0.886, 108, 104.25, 495.3,8.202D-5, 27.0, 1, 80.0, NA , NA 13: 20 - 21 , 0.874, 108, 0.01, 12.22,8.202D-5, 0.9, 1, 80.0, NA , NA 14,: 21 - 22 , 0.893, 324, .72, 0.00,8.202D-5, 0.0, 1, 80.0, NA , NA 15: 22 - 23 , 0.724, 324, 209.5, 26.02,8.202D-5, 2.2, 1, 80.0, NA , NA -

16: 23 - 23A, 0.724, 324, 0.00, 1184.6,8.202D-5, 0.0, 1, 81.9, NA , NA 17: 23A- 23B, 0.724, 324, 0.00, 1283.0,8.202D-5, 4.8, 1, 81.9, NA , NA 18: 23B- 24 , 0.724, 324, 0.00, 0.00,8.202D-5, 0.0, 1, 81.9, NA , NA 19: 24 - 24A, 0.550, 324, 0.11, 1818.0,8.202D-6, 2.7, 1, 101.2, NA , NA 20: 24A- 25 , 0.550, 324, 0.00, 0.00,8.202D-6, 0.0, 1, 101.2, NA , NA 21: 25 - 26 , 0.590, 324, .77, 166.8,8.202D-6, 4.6, 1, 118.7, NA, , NA 22: 26 - 26A, 0.590, 324, 0.00, 1540.1,8.202D-6, -3.3, 1, 209.4, NA , NA 23: 26A- 27 , 0.590, 324, 0.00, 0.00,8.202D-6, 0.0, 1, 209.4, NA , NA 24: 27 - 28 , 0.590, 324, 1.34, 270.1,8.202D-6, -11.0, 1, 300.0, NA , NA 25: 28 - 29 , 0.768, 108, 0.12, 15.31,8.202D-6, -0.9, 1, 300.0, NA , NA 26: 29 - 30 , 0.969, 108, 1.48, 525.6,8.202D-6, -27.0, 1, 300.0, NA , NA 27: 30 - 31 , 3.803, 6, .66, 23.0,1.500D-4, 4.6, 1, 300.0, NA , NA 28: 31 - 32 , 5.826, 6, 1.3, 208.2,1.500D-4, 49.0, 1, 300.0, NA , NA 29: 32 - 32A, 9.586, 6, 2.9, 4.2,1.500D-4, 0.0, 1, 300.0, NA , NA 30: 32A- 32B, 9.586, 3, 0.3, 16.0,1.500D-4, 0.0, 1, 300.0, NA , NA 31: 32B- 33 , 9.586, 2, .04, 4.3,1.500D-4, 0.0, 1, 300.0, NA , NA 32: 33 - 33A,10.820, 2, 0.3, 2.8,1.500D-4, 0.0, 1, 300.0, NA , NA 33: 33A- 34A,10.820, 1.5, 0.3, 21.3,1.500D-4, 0. 0, 1, 300.0, NA , NA 34: 34A- 34B,10.820, 1.2, .3, 13.4,1.500D-4, 0.0, 1, 300.0, NA , NA 35: 34B- 35 ,10.820, 1, 42, 14.6,1.500D-4, 0.0, 1, 300.0, NA , NA 36: 35 - 36 , 5.826, 2, 2.12, 38.1,1.500D-4, 0.0, 1, 300.0, NA , NA 37: PV-2229 , 5.826, 2, 0.0, 0.0,1.500D-4, 0.0, 6, 300.0, 299.0, 0.9 38: 36 - 39 ,11.540, 1, .7, 47.6,1.500D-4, 0.0, 1, 300.0, NA , NA 39: 39 - 40 ,10.114, 1, 0.2, 11.1,1.500D-4, 18.8, 1, 300.0, NA , NA 40: 40 - 41 ,12.500, 1, 1.2, 70.9,1.500D-4, 15.7, 1, 300.0, NA , NA 41: 41 - 42 ,14.312, 1, .9, 40.1,1.500D-4, 3.7, 1, 300.0, NA , NA 42: 42 - 43 ,21.562, 1, 0.0, 6.2,1.500D-4, 11.1, 1, 300.0, NA , NA 43: 43 - 44 ,21.562, 1, 0.0, 2.5,1.500D-4, 4.5, 1, 300.0, NA , NA 44: 44 - 45 ,14.000, 1, 1.1, 9.4,1.500D-4, -1.1, 1, 300.0, NA , NA 45: 45 - 46 , 7.625, 1, 2.14, 182.6,1.500D-4, -48.2, 1, 300.0, NA , NA 46: 46 - 47 , 7.625, 1, 15.2, 39.3,1.500D-4, -5. 5 , 1, 300.0, NA , NA 47: 47 - 48 , 5.761, 1, 0.67, 5.2,1.500D-4, 0.0, 1, 300.0, NA , NA 48: HV-3250 , 5.761, 1, 0.0, 0.0,1.500D-4, 0.0, 6, 300.0, 409.0, 0.9 49: 48 - 49 , 6.065, 1, 2.42, 170.2,1.500D-4, -22.0, 1, 300.0, NA , NA 50: 49 - 50 , 6.065, 1, 5.55, 10.9,1.500D-4, 0.0, 1, 300.0, NA , NA 51: 50 - 51 , 6.065, 1, 1.1, 37.6,1.500D-4, 4.8, 1, 300.0, NA , NA 52: 51 - 52 , 6.065, 1, 0.57, 21.6,1.500D-4, 0.7, 1, 300.0, NA , NA 53: 52 - 53 , 6.065, 1, 1.71, 6.92,1.500D-4, -3.5, 1, 300.0, NA , NA 54: 53 - 54 , 7.981, 1, 2.73, 1.26,1.500D-4, 10.5, 1, 300.0, NA , NA 55: 54 - 55 , 0.500, 166, 0.00, 0.00,1.500D-4, 0.0, 6, 300.0, 5.67, 0.9

%-a Rev.A ATTACH.1 PA6E 1 d:$

FLOW = 794.88 GFM AT 80 AF?

USE PUMP CURVE [OR ENTER PRESSURE] (Y/N):Y?

TYPE OF PUMP (ENTER NO. FROM 1 TO 5): 1 ?

PUMP (S) ARRANGEMENT (ONE=0 - PARALLEL =1 - SERIES =2): 0?

ADDITIONAL FLOW (USE WDIV=0.1 IN INPUT FILE!)= 175 GPM?

FLOW 8 PUMP = 969.88 GPM AT 80.0xF PUMP HEAD = 104.02 FT/ STAGE FILE FSARPF13.DAT - NO. OF SECTIONS = 55 - TWO-PHASE SECTIONS

  • DIVIDER = 10 SECTION ID K FLOW P(IN) P(OUT) 1 : 1 - 17 10.020 19.4 482,314 146.6 139.6 2: 17 - 6 7.981 4.3 482,314 139.6 131.0 3: 6-7 7.981 1.9 395,288 131.0 130.6 4 : 7-8 7.870 5.4 395,288 130.6 129.5 ,

5: 8-9 9.516 38.8 395,288 129.5 124.3 6 : 9- 10 9.172 3.2 395,288 124.3 150.1 7 : 10 - 11, 9.172 2.1 218,391 150.1 150.1 8: 11 - 12 3.152 4.4 65,881 150.1 145.4 9 :TV-2227-6 3.152 0.0 65,881 145.4 129.9 Wcr= 181,366 10: 12 - 18 3.150 0.6 65,881 129.9 129.8 11: 18 - 19 3.346 1.1 65,881 129.8 131.6 12: 19 - 20 0.886 117.2 3,660 131.6 108.5

    • PRESS <CR> TO CONTINUE **

SECTION ID K FLOW P(IN) P(OUT) 13: 20 - 21 0.874 0.3 3,660 108.5 108.0 14: 21 - 22 0.898 0.7 1,220 108.0 108.0 15: 22 - 23 0.724 210.3 1,220 108.0 101.9 16: 23 - 23A 0.724 37.1 1,220 101.9 101.0 17: 23A- 23B 0.724 40.2 1,220 101.0 98.0 18: 23B- 24 0.724 0.0 1,220 98.0 98.0 19: 24 - 24A 0.550 47.4 1,220 98.0 93.4 20: 24A- 25 0.550 0.0 1,220 93.4 93.4 21: 25 - 26 0.590 5.0 1,220 93.4 91.1 22: 26 - 26A 0.590 33.7 1,220 91.1 90.5 23: 26A- 27 0.590 0.0 1,220 90.5 90.5 24: 27 - 28 0.590 6.7 1,220 90.5 94.5 25: 28 - 29 0.768 0.4 3,660 94.5 94.8 26: 29 - 30 0.969 10.7 3,660 94.8 104.8 27: 30 - 31 3.803 1.1 65,881 104.8 102.8 28: 31 - 32 5.826 4.8 65,881 102.8 83.2 29: 32 - 32A 9.586 3.0 65,881 83.2 83.2 30: 32A- 32B 9.586 0.5 ~131,763 83.2 83.2 31: 32B- 33 9.586 0.1 197,644 83.2 83.2 32: 33 - 33A 10.820 0.3 197,644 83.2 83.2 33: 33A- 34A 10.820 0.6 263,525 83.2 83.2 34: 34A- 34B 10.820 0.5 329,407 83.2 83.2

    • PRESS <CR> TO CONTINUE **

%-OI REV A ATTACH. i PAGE 20F4

SECTION ID K FLOW P(IN) P(OUT) 35: 34B- 35 10.820 0.6 395,288 83.2 83.1 36: 35 - 36 5.826 2.7 197,644 83.1 82.7 37: PV-2229 5.826 0.0 197,644 82.7 80.8 Wer= 591,853 38: 36 - 39 11.540 1.4 395,288 80.8 80.7 39: 39 - 40 10.114 0.4 395,288 80.7 73.2  ;

40: 40 - 41 12.500 2.2 395,288 73.2 66.9 X: IN= 0.00 OUT= 0.01 41: 41 - 42 14.312 1.5 395,288 66.9 65.7 X:IN= 0.01 OUT= 0.15  ;

42: 42 - 43 21.562 0.1 395,288 65.7 63.6 X IN= 0.15 OUT= 0.40  ;

43: 43 - 44 21.562 0.0 395,288 63.6 62.9 X: IN= 0.40 OUT= 0.48 44: 44 - 45 14.000 1.2 395,288 62.8 62.9 X:IN= 0.49 OUT= 0.48 45: 45 - 46 7.625 4.8 395,288 62.1 69.8 X IN= 0.58 OUT= 0.00 46: 46 - 47 7.625 15.8 395,288 69.8 68.4 47: 47 - 48 5.761 0.7 395,288 68.4 67.9 48 'HV-3250 5.761 0.0 395,288 67.9 63.8 Wcr= 440,701 l 49: 48 - 49 6.065 5.0 395,288 63.8 69.7

{

50: 49 - 50 6.065 5.7 395,288 69.7 66.3 X: IN= 0.00 OUT= 0.06 6 51: 50 - 51 6.065 1 '. 7 395,288 66.3 62.5 X:IN= 0.06 OUT= 0.47 52: 51 - 52 6.065 0.9 395,288 62.5 60.3 X:IN= 0.47 OUT= 0.68 53: 52 - 53 6.065 1.8 395,288 60.3 51.7 X IN= 0.68 OUT= 1.71 54: 53 - 54 7.981 2.7 395,288 51.7 43.7 X:IN= 1.71 OUT= 2.81 55: 54 - 55 0.500 0.0 2,381 38.3 24.0 Wcr= 2,48' o* PRESSURE AT END OF SYSTEM = 24.0 PSIA l REPEAT WITH NEW CONDITIONS (Y/N)? 3 L

[

t t

1 i

i W-a REY.A ATTACH 1 2 AGE 30F4

MASS FLOW RATE OF HELIUM .....: 8024 LBS/HR/ MOD = 13.4 LBS/SEC TOTAL TOTAL LOOP FLOW RATE OF WATER : 794.88 GPM @ 80 AF = 65,881.3 LBS/HR/ MODULE SATURATION PRESSURE...........: 90.5 PSIA SATURATION TEMPERATURE........: 320.75 AF HEAT OF EVAPORATION ..........: 894.43 BTU /LB HEAT CAPACITY OF WATER .......: 1 BTU /LB/xF HEAT CAPACITY OF STEAM........: CF= .5 BTU /LB/xF FF= .5 BTU /LB/xF HELIUM..: IN=1530.0 xF OUT= 80.3 xF WATER...: IN= 80.0 xF OUT= 299.3 xF AS WATER AEC(1)= 755.0 (100.00%) HEAT = 0.0*10^6 U= 32.0 AEC(2)= 876.5 ( 0.00%) HEAT = 0.2*10^6 U= 30.6 AEC(3)= 888.0 (100.00%) HEAT = 2.3*10^6 U= 30.9 AEC(4)= 863.0 (100.00%) HEAT = 11.9*10^6 U= 36.6 TOTAL HEAT RATE = 86.7*10^6 BTU /HR ( EC= 86.7 )

    • PRESS ANY LEY TO CONTINUE FOR TEMPERATURE DETAILS **

SECTION # 1

  • EC*H20: 80.0 TO 80.3 -HE: 82.5 TO 80.3 (Re=2113) -WL 80.2, DT= 0.0 SECTION # 2
  • EC*H20: 80.3 TO 83.7 -HE: 104.7 TO 82.5 (Re=2094) -WL: 82.6, DT= 0.2 SECTION # 3
  • EC*H20: 83.7 TO 118.7 -HE: 336.2 TO 104.7, (Re=1916) -WL: 106.8, DT= 3.7 SECTION # 4
  • EC*H20: 118.7 TO 299.3 -HE 1530.0 TO 336.2 (Re=1491) -WL: 275.4, DT=74.8 ENTER DIFFERENT HELIUM TEMPERATURE:

%-01 REV. A ATTAdl.1 PAGE 4 OF4

I

      • FILE: FSARPF14.DAT ***

SECTION -

ID -WDIV- K(FIX)- K(VAR)- EPS -

EL -FL.- TF - MIN - MAX '

63 1 3500 - 502,18.812, 0.1, 0.82, 0.77,1.500D-4, -1.21, 1, 100.0, NA , NA 2 :502 - 552,22.624, 0.1, 0.36, 1.4,1.500D-4, 0.0, 1, 100.0, NA , NA 3 3552 - 402,11.938, 0.1, 1.07, 12.9,1.500D-4, -1.75, 1, 100.0, NA , NA 4 :402 - 403,10.020, 0.1, 1.75, 5.30,1.500D-4, 0.0, 1, 100.0, NA , NA 5 :COND12PMP, NA , 0.1, 0.0, 0.0,1.500D-4, 0.00, 9, 100.0, 2, NA l 6 3404 - 405, 7.981, 0.1, 2.80, 9.6,1.500D-4, 4.25, 1, 100.0, NA , NA f 7 3405 - 406, 6.065, 0.1, 1.60, 24.1,1.500D-4, 10.9, 1, 100.0, NA , NA B 3406 - 407, 7.981, 0.1, 1.75, 85.9,1.500D-4, 1.5, 1, 100.0, NA , NA 9 3407 - 6 , 7.981, 0.1, 1.13, 36.2,1.500D-4, 17.2, 1, 100.0, NA , NA 10: 6-7 , 7.981, 1, .91, 61.4,1.500D-4, .23, 1, 100.0, NA , NA 11: 7-8 , 7.870, 1, 4.9, 30.1,1.500D-4, .33, 1, 100.0, NA , NA 12: 8-9 , 9.516, 1, 6.6, 59.7,1.500D-4, 4.3, 1, 100.0, NA , NA 13: FV-2205 , 9.516, 1, 0.0, 0.0,1.500D-4, 0.0, 6, 100.0, 485.0, 0.9 14: 9 - 10 , 9.172, 1, .98, 136.3,1.500D-4, -60.6, 1, 100.0, NA , NA 15: 10 - 11 , 9.172,1.81, 42, 94.2,1.500D-4, -0.3, 1, 100.0, NA , NA 16: 11 - 12 , 3.152, 6, 2.4, 102.1,1.500D-4, 9.0, 1, 100.0, NA , NA 17:TV-2227.-6, 3.152, 6, 0.0, 0.0,1.500D-4, 0.0, 6, 100.0, 33.6, 0.9 18: 12 - 18 , 3.150, 6, .62, 0.0,1.500D-4, 0.0, 1, 100.0, NA , NA 19: 18 - 19 , 3.346, 6, .59, 26.2,1.500D-4, -4.6, 1, 100.0, NA , NA 20: 19 - 20 , 0.386, 108, 104.30, 495.3,8.202D-5, 27.0, 1, 100.0, NA . , NA 21: 20 - 21 , 0.874, 108, 0.01, 12.2,8.202D-5, 0.9, 1, 100.0, NA , NA g 22: 21 - 22 , 0.898, 324, .72, 0.0,0.202D-5, 0.0, 1, 100.0, NA , NA 23: 22 - 23 , 0.724, 324, 209.50, 26.0,8.202D-5, 2.2, 1, 100.0, NA , NA 24: 23 - 23A, 0.724, 324, 0.00, 2467.3,8.202D-5, 4.8, 1, 103.1, NA , NA 25: 23A- 23B, 0.724, 324, 0.00, 0.0,8.202D-5, 0.0, 1, 103.1, NA , NA 26: 23B- 24 , 0.724, 324, 0.00, 0.0,8.202D-5, 0.0, 1, 103.1, NA , NA 27: 24 - 244, 0.550, 324, 0.11, 1818.0,8.202D-6, 2.7, 1, 135.2, NA , NA 28: 24A- 25 , 0.550, 324, 0.00, 0.0,8.202D-6, 0.0, 1, 135.2, NA , NA 29: 25 - 26 , 0.590, 324, .77, 166.8,8.202D-6, 4.6, 1, 164.1, NA , NA J 30: 26 - 26A, 0.590, 324, 0.00, 1540.1,8.202D-6, -3.3, 1, 277.1, NA , NA A 31: 26A- 27 , 0.590, 324, 0.00, 0.0,8.202D-6, 0.0, 1, 277.1, NA , NA 32: 27 - 28 , 0.590, 324, 1.34, 270.1,8.202D-6, -11.0, 1, 390.0, NA , NA 33: 28 - 29 , 0.768, 108, 0.12, 15.3,8.202D-6, -0.9, 1, 390.0, NA , NA 34: 29 - 30 , 0.969, 108, 1.48, 525.6,8.202D-6, -27.0, 1, 290.0, NA , NA 35: 30 - 31 , 3.803, 6, .66, 23.0,1.500D-4, 4.6, 1, 390.0, NA , NA 36: 31 - 32 , 5.826, 6, 1.26, 208.2,1.500D-4, 49.0, 1, 390.0, NA , NA 37: 32 - 32A, 9.586, 6, 2.9, 4.2,1.500D-4, 0.0, 1, 390.0, NA , NA 38: 32A- 32B, 9.586, 3, 0.3, 16.0,1.500D-4, 0.0, 1, 390.0, NA , NA 39: 32B- 33 , 9.586, 2, .04, 4.3,1.500D-4,. 0.0, 1, 390.0, NA , NA 40: 33 - 33A,10.820, 2, 0.3, 2.8,1.500D-4, 0.0, 1, 390.0, NA , NA i 41: 33A- 34A,10.820, 1.5, 0.3, 21.3,1.500D-4, 0.0, 1, 390.0, NA , NA l 42: 34A- 34B,10.820, 1.2, .3, 13.4,1.500D-4, 0.0, 1, 390.0, NA , NA

! 43: 34B- 35 ,10.820, 1, .42, 14.6,1.500D-4, 0.0, 1, 390.0, NA , NA 44: 35 - 36 , 5.826, 1, 3.00, 37.6,1.500D-4, 0.0, 1, 390.0, NA , NA 45: PV-2229 , 5.826, 1, 0.0, 0.0,1.500D-4, 0.0, 6, 390.0, 78.6, 0.9 46: 36 - 39 ,11.540, 1, .7, 47.6,1.500D-4, 0.0, 1, 390.0, NA , NA l 47: 39 - 40 ,10.114, 1, 0.2, 11.1,1.500D-4, 18.8, 1, 390.0, NA , NA f i

48: 40 - 41 ,12.500, 1, 1.2, 70.9,1.500D-4, 15.7, 1, 390.0, NA , NA 49: 41 - 42 ,14.312, 1, .9, 40.1,1.500D-4, 3.7, 1, 390.0, NA , NA 50: 42 - 43 ,21.562, 1, 0.0, 6.2,1.500D-4, 11.1, 1, 390.0, NA , NA

~

i i

%-CI RGV. A ATTACH.2 l

l PAGE 1 OF6

51: 43 - 44 ,21.562, 1, 0.0, 2.5,1.500D-4, 4.5, 1, 390.0, NA , NA 52: 44 - 45 ,14.000, 1, 1.1, 9.4,1.500D-4, -1.1, 1, 390.0, NA , NA 53: 45 - 46 , 7.625, 1, 2.14, 182.6,1.500D-4, -48.2, 1, 390.0, N4 , NA 34: 46 - 47 , 7.626, 1, 15.2, 39.3,1.500D-4, -5.5, 1, 390.0, NA , NA 55: 47 - 48 , 5.761, 1, 0.7, 5.21,1.500D-4, 0.0, 1, 390.0, NA , NA 56: HV-3250 , 5.761, 1, 0.0, 0.0,1.500D-4, 0.0, 6, 390.0,128.55, 0.9 57: 48 - 49 , 6.065, 1, 2.42, 170.2,1.500D-4, -22.0, 1, 390.0, NA , NA 58: 49 - 50 , 6.065, 1, 5.55, 10.9,1.500D-4, 0.0, 1, 390.0, NA , NA 59: 50 - 51 , 6.065, 1, 1.1, 37.6,1.500D-4, 4.8, 1, 390.0, NA , NA 60: 51 - 52 , 6.065, 1, 0.57, 21.6,1.500D-4, 0.7, 1, 390.0, NA , NA 61: 52 - 53 , 6.065, 1, 1.71, 6.92,1.500D-4, -3.5, 1, 390.0, NA , NA i 62: 53 - 54 , 7.625, 1, 2.73, 1.26,1.500D-4, 10.5, 1, 390.0, NA , NA 63: 54 - 55 , 0.500, 166, 0.00, 0.00,1.500D-4, 0.00, 6, 390.0, 5.67, 0.9 510 N

12.3 175 i,

s

%-ofREV.A ATTACH.2 PME 20F6

FLOW = 510 GPM AT 100 AF7 3 USE PUMP CURVE [OR ENTER PRESSURE] (Y/N):N7 STARTING PRESSURE = 12.3 PSIA 7 .

ADDITIONAL FLOW (USE WDIV=0.1 IN INPUT FILE!)= 175 GPM? r i

FILE:FSARPF14.DAT - NO. OF SECTIONS = 63 - TWO-PHASE SECTIONS

  • DIVIDER = 10 SECTION ID K FLOW P(IN) P(OUT) 1 :500 - 502 18.812 0.0 340,645 12.3 12.8 2 3502 - 552 22.624 U. 4 340,645 12.8 12.8 3 3552 - 402 11.938 1.3 340,645 12.8 13.5 4 3402 - 403 10.020 1.8 340,645 13.5 13.4 5 COND12PMP .1.000 0.0 340,645 13.4 292.0 6 3404 - 405 7.981 3.0 340,645 292.0 289.8 7 :405 - 406 6.065 2.0 340,645 289.8 284.3  :

I 8 :406 - 407 7.981 3.1 340,645 284.3 283.3 9 :407 - 6 7.981 1.7 340,645 283.3 275.7 10: 6-7 7.981 1.9 253,619 275.7 275.4 11: 7-8 7.870 5.4 253,619 275.4 274.9 12: 8-9 9.516 7.6 253,619 274.9 272.8 13: FV-2205 9.516 0.0 253,619 272.8 271.7 Wcr=3,585,764 14: 9- 10 9.172 3.2 253,619 271.7 297.6 15: 10 - 11 9.172 2.1 140,121 297.6 297.7

    • PRESS <CR> TO CONTINUE **

SECTION ID K FLOW P(IN) P(OUT) 16: 11 - 12 3.152 4.5 42,270 297.7 293.5 17:TV-2227-6 3.152 0.0 42,270 293.5 287.1 Wcr= 257,703 i 18: 12 - 18 3.150 0.6 42,270 287.1 287.0  !

19: 18 - 19 3.346 1.1 42,270 287.0 289.0 20: 19 - 20 0.886 117.7 2,348 289.0 272.6 21: 20 - 21 0.874 0.3 2,348 272.6 272.2 22: 21 - 22 0.898 0.7 783 272.2 272.2 23: 22 - 23 0.724 210.4 783 272.2 269.1 24: 23 - 23A 0.724 80.5 783 269.1 266.2 25: 23A- 23B 0.724 0.0 783 266.2 266.2 26: 23B- 24 0.724 0.0 783 266.2 266.2 27: 24 - 24A O.550 48.7 783 266.2 263.6 28: 24A- 25 0.550 0.0

  • 783 263.6 263.6 29: 25 - 26 0.590 5.1 783 263.6 261.5 30: 26 - 26A O.590 34.3 783 261.5 262.0 31: 26A- 27 0.590 0.0 783 262.0 262.0 32: 27 - 28 0.590 6.8 783 262.0 266.0 33: 28 - 29 0.768 0.4 2,348 266.0 266.3 34: 29 - 30 0.969 10.8 2,348 266.3 276.1 35: 30 - 31 3.803 1.1 42,270 276.1 274.3 36: 31 - 32 5.826 4.7 42,270 274.3 255.9 37: 32 - 32A 9.586 3.0 42,270 255.9 255.9 o* PRESS <CR) TO CONTINUE **

Hoi REV. A i ATTACH.2 P AGE 3OF6

/

l SECTION ID K FLOW P(IN) P (OUT's 38: 32A- 32B 9.586 0.5 84,540 255.9 .255.9 'i ,

39: 32B- 33 9.586 0.1 126,810 255.9 .255.9 40: 33 - 33A 10.820 0.3 126,810 255.9 '255.9 41: 33A- 34A 10.820 0.6 169,079 255.9 255.9 42: 34A- 34B 10.820 0.5 211,349' 255.9 7255.8 433-34B- 35 10.820 0.6 253,619 255.8 P255.8 44: 35 - 36 5.826 3.6 253,619 255.8 - 254.8 (

i 45: PV-2229 5.826 0.0 253,619 254.8 206.7 Wcr= 253,754 ,

46: 36 - 39 11.540 1.4 253,619 206.7 206.7 X:IN= 0.69 O'JT= 0.70 47: 39 - 40 10.114 0. 4 253,619 206.6 203.0 X:IN= 0.70 DaT= 'O.89 48: 40 - 41 12.500 2.2 253,619 203.0 200.2 X IN= 0.89 007,=4 1.03 49: 41 - 42 14.312 1.5 253,619 200.2 199.6 X IN= 1.03 OLE =/ 1.06 50: 42 - 43 21.562 0.1 253,619 199.6 197.8 X:IN= 1.06 OLC= 1.16 21.562 0.0 253,619 197.8 197.1 X:IN= 1.16 OUT= 1.19 51 43 - 44 1.19 52: 44 - 45 14.000 1.2 253,619 197.1 197.2 X:IN= 1.19 OUT=

53: 45 - 46 7.625 4.8 253,619 196.9 203.8 X: IN= 1.20 OUT=, 0.85 34: 46 - 47_ 7.626 15.8 253,619 203.8 201.5 X:IN= 0.85 OUT= 0.97 55: 47 - 48 . ' 5.'7 61 0.8 253,619 201.0 200.4 X IN?,1.00 OUT= 1.03 0.0 253,619 200.4 159.8 Wcr=' 253,529 56: (HV-3250 5.761 57: 48 - 49 6.065 5.0 253,619 159.8 153.0 X IN= 3.31 OUT= 3.71 58: 49 - 50 6.065 5.7 253,619 153.0 141.9 X IN= 3.71 OUT= 4.37 59: 50 - 51 6.065 1.7 253,619 141.9 137.9 X:IN= 4.37 OUT= 4.62

    • PRESS <CR) TO CONTINUE **

SECTION ID K FLOW P(IN) P(OUT) 60: S1 - 52 6.065 0.9 253,619 137.9 135.8 X IN= 4.62 OUT= 4.75 613,52 - 53 6.065 1.8 253,619 135.8 131.3 X:IN= 4.75 OUT= 5.03 62: 53 - 54 7.625 2.7 253,619 131.3 128.0 X:IN= 5.03 OUT= 5.25 0.500 0.0 1,528 126.8 123.1 Wcr= 5,710 63: 54 - 55

    • FLOW CHOKED AT VALVE (S) **

REPEAT WITH NEW CONDITIONS (Y/N)?

I r

q ?N. '

r v

94 -01 REV. A ATTACH.2 9 AGE 60F6

      • FILE: FSPF14CH.DAT ***

SECTION -

ID -WDIV- K(FIX)- K(VAR)- EPS -

EL -FL.- TF - MIN - MAX ,

7

1 48 - 49 , 6.065, 1, 2.42, 170.2,1.500D-4, -22.0, 3, 400.0, NA ,364.1 ,

23 49 - 50 , 6.065, 1, 5.55, 10.9,1.500D-4, 0.0, 3, 400.0, NA , NA j 3: 50 - 51 , 6.055, 1, 1.1, 37.6,1.500D-4, 4.8, 3, 400.0, NA , NA 4 : 51 - 52 , 6.065, 1, 0.57, 21.6,1.500D-4, 0.7, 3, 400.0, NA , NA q 5: 52 - 53 , 6.065, 1, 1.71, 6.92,1.500D-4, -3.5, 3, 400.0, NA , NA 6 : 53 - 54 , 7.625, 1, 2.73, 1.26,1.500D-4, 10.5, 3, 400.0, NA , NA 7 : 54 - 55 , 0.500, 166, 0.00, 0.00,1.500D-4, 0.00, 7, 400.0, 5.67, 0.9 496.1 N

172.1 0

FLOW = 510 GPM AT 100 xF?

USE PUMP CURVE [OR ENTER PRESSURE 3 (Y/N):N?

STARTING PRESSURE = 134.59 PSIA?

ADDITIONAL FLOW (USE WDIV=0.1 IN INPUT FILE!)= 0 GPM?

FILE:FSPF14CH.DAT - NO. OF SECTIONS = 7 - TWO-PHASE SECTIONS

  • DIVIDER = 10 SECTION ID M FLOW P(IN) P(OUT) 1 : 48 - 49 6.065 5.0 253,619 134.6 121.2 X: IN= 4.88 OUT= 5.74 2: 49 - 50 6.065 5.7 253,619 121.2 98.2 X:IN= 5.74 OUT= 7.44 3: 50 - 51 6.065 1.7 253,619 98.2 88.7 X: IN= 7.44 OUT= 8.19 4 : 51 - 52 6.065 0.9 253,619 88.7 82.7 X:IN= 8.19 OUT= 8.65 5: 52 - 53 6.065 1.8 253,619 82.7 66.6 X: IN= 8.65 OUT= 10.11 6: 53 - 54 7.625 2.7 253,619 66.6 53.7 X: IN=10.11 OUT= 11.51 7: 54 - 55 0.500 0.0 1,528 47.7 28.9 Wcr= 1,548
    • PRESSURE AT END OF SYSTEM = 28.9 PSIA REFEA1 WITH NEW CONDITIONS (Y/N)?

l 4 4 - 0 1 R EV. 4 ATTACH.2 PAGE BoF6

MASS FLOW RATE OF HELIUM .....: 6960 LBS/HR/ MOD = 11.6 LBS/SEC TOTAL TOTAL LOOP FLOW RATE OF WATER : 510 GPM O 100 AF = 42,269.9 LBS/HR/ MODULE SATURATION PRESSURE...........: 261.5 PSIA SATURATION TEMPERATURE........: 404.66 AF HEAT OF EVAPORATION ..........: 821.09 BTU /LB HEAT CAPACITY OF WATER .......: 1 BTU /LB/AF HEAT CAPACITY OF STEAM........: CF= .5 BTU /LB/xF PF= .5 BTU /LB/xF HELIUM..: IN=1520.0 .=F OUT= 100.3 xF WATER...: IN= 100.0 xF OUT= 390.3 xF AS WATER AEC(1)= 755.0 (100.00%) HEAT = 0.0*10^6 U= 29.0 AEC(2)= 876.5 ( 0.00%) HEAT = 0.2*10^6 U= 27.9 AEC(3)= 888.0 (100.00%) HEAT = 2.4*10^6 U= 28.5 AEC(4)= 863.0 (100.00%) HEAT = 9.6*10^6 U= 33.8 TOTAL HEAT RATE = 73.6*10^6 BTU /HR ( EC= 73.6 )

    • PRESS ANY REY TO CONTINUE FOR TEMPERATURE DETAILS **

SECTION # 1

  • EC*H20s 100.0 TO 100.6 -HE: 103.1 TO 100.3 (Re=1788) -WL: 100.4, DT= 0.0 SECTION # 2
  • EC*H20: 100.6 TO 106.2 -HE: 130.6 TO 103.1 (Re=1767) -WL: 104.2, DT= 0.2 SECTION # 3
  • EC*H20: 106.2 TO 164.1 -HE: 413.6 TO 130.6 (Re=1587) -WL: 142.8, DT= 4.0 SECTION # 4
  • EC*H20: 164.1 TO 390.3 -HE:1520.0 TO 413.6 (Re=1256) -WL: 344.8, DT=62.6 ENTER DIFFERENT HELIUM TEMPERATURE:

94-01 REV.A ATTACN.2.

PAGE 6OF6

      • FILE: FSARPF15.DAT ***

SECTION -

ID -WDIV- K(FIX)- K(VAR)- EPS - EL -FL.- TF - MIN - MAX 57 1 : FEED-WP , 8.602, .1, 0.00, 000.0, NA , 0.0, 9, 200.0, 5 , NA 2 3627 - 628, 8.602, .1, 7.81, 98.1,1.500D-4, 4.0, 1, 200.0, NA , NA 3: HV-31119, 7.870, .1, 0.0, 0.0,1.500D-4, 0.0, 6, 200.0, 60.0, 0.9 4 3628 - 629, 7.870, .1, 3.0, 146.4,1.500D-4, -6.6, 1, 200.0, NA , NA 5 3629 - 8 , 4.063, 1, 10.5, 228,9,1.500D-4, 19.3, 1, 200.0, NA , NA 6: 8-9 , 9.516, 1, 6.6, 59.7,1.500D-4, 4.3, 1, 200.0, NA , NA 7: FV-2205 , 9.516, 1, 0.0, 0.0,1.500D-4, 0.0, 6, 200.0, 80.0, 0.9 8: 9- 10 , 9.172, 1, .98, 136.3,1.500D-4, -60.6, 1, 200.0, NA , NA 9 : 10 - 11 , 9.172,1.81, .42, 94.2,1.500D-4, -0.3, 1, 200.0, NA , NA 10: 11 - 12 , 3.152, 6, 2.4, 102.1,1.500D-4, 9.0, 1, 200.0, NA , NA l 11:TV-2227-6, 3.152, 6, 0.0, 0.0,1.500D-4, 0.0, 6, 200.0, 105.0, 0.9 12 12 - 18 , 3.150, 6, .62, 0.0,1.500D-4, 0.0, 1, 200.0, NA , NA 13: 18 - 19 , 3.346, 6, .59, 26.2,1.500D-4, -4.6, 1, 200.0, NA , NA 14: 19 - 20 , 0.886, 108, 104.30, 495.3,8.202D-5, 27.0, 1, 200.0, NA , NA 15: 20 - 21 , 0.874, 108, 0.01, 12.2,8.202D-5, 0.9, 1, 200.0, NA , NA 16: 21 - 22 , 0.898, 324, .72, 0.0,8.202D-5, 0.0, 1, 200.0, NA , NA 17: 22 - 23 , 0.724, 324, 209.50, 26.0,8.202D-5, 2.2, 1, 200.0, NA , NA 18: 23 - 23A, 0.724, 324, 0.00, 2467.3,8.202D-5, 4.8, 1, 200.3, NA , NA 19: 23A- 23B, 0.724, 324, 0.00, 0.0,8.202D-5, 0.0, 1, 200.3, NA , NA 20: 23B- 24 , 0.724, 324, 0.00, 0.0,8.202D-5, 0.0, 1, 200.3, NA , NA 21: 24 - 24A, 0.550, 324, 0.11, 1818.0,8.202D-6, 2.7, 1, 204.6, NA , NA 22: 24A- 25 , 0.550, 324, 0.00, 0.0,8.202D-6, 0.0, 1, 204.6, NA , NA 23: 25 - 26 , 0.590, 324, .77, 166.8,8.202D-6, 4.6, 1, 208.6, NA , NA 24: 26 - 26A, 0.590, 324, 0.00, 1540.1,8.202D-6, -3.3, 1, 255.3, NA , NA 25: 26A- 27 , 0.590, 324, 0.00, 0.0,8.202D-6, 0.0, 1, 255.3, NA , NA 26: 27 - 28 , 0.590, 324, 1.34, 270.1,8.202D-6, -11.0, 1, 301.9, NA , NA 27: 28 - 29 , 0.768, 108, 0.12, 15.3,8.202D-6, -0.9, 1, 301.9, NA , NA 28: 29 - 30 , 0.969, 108, 1.48, 525.6,8.202D-6, -27.0, 1, 301.9, NA , NA 29: 30 - 31 , 3.803, 6, .66, 23.0,1.500D-4, 4.6, 1, 301.9, NA , NA 30: 31 - 32 , 5.826, 6, 1.26, 208.2,1.500D-4, 49.0, 1, 301.9, NA , NA 31: 32 - 32A, 9.586, 6, 2.9, 4.2,1.500D-4, 0.0, 1, 301.9, NA , NA 32: 32A- 32B, 9.586, 3, 0.3, 16.0,1.500D-4, 0.0, 1, 301.9, NA , NA 33: 32B- 33 , 9.586, 2, .04, 4.3,1.500D-4, 0.0, 1, 301.9, NA , NA 34: 33 - 33A,10.820, 2, 0.3, 2.8,1.500D-4, 0.0, 1, 301.9, NA , NA 35: 33A- 34A,10.820, 1.5, 0.3, 21.3,1.500D-4, 0.0, 1, 301.9, NA , NA 36: 34A- 349,10.820, 1.2, .3, 13.4,1.500D-4, 0.0, 1, 301.9, NA , NA 37: 34B- 35 ,10.820, 1, .42, 14.6,1.500D-4, 0.0, 1, 301.9, NA , NA 38: 35 - 36 , 4.411, 1, 2.20, 55.5,1.500D-4, 0.0, 1, 301.9, NA , NA 39: PV-22129, 4.411, 1, 0.0, 0.0,1.500D-4, 0.0, 6, 301.9, 81.0, 0.9 40: 36 - 39 ,11.540, 1, .7, 47.6,1.500D-4, 0.0, 1, 301.9, NA , NA 41: 39 - 40 ,10.114, 1, 0.2, 11.1,1.500D-4, 18.8, 1, 301.9, NA , NA 42: 40 - 41 ,12.500, 1, 1.2, 70.9,1.500D-4, 15.7, 1, 301.9, NA , NA 43: 41 - 42 ,14.312, 1, .9, 40.1,1.500D-4, 3.7, 1, 301.9, NA , NA 443.42 - 43 ,21.562, 1, 0.0, 6.2,1.500D-4, 11.1, 1, 301.9, NA , NA 45: 43 - 44 ,21.562, 1, 0.0, 2.5,1.500D-4, 4.5, 1, 301.9, NA , NA 46: 44 - 45 ,14.000, 1, 1.1, 9.4,1.500D-4, -1.1, 1, 301.9, NA , NA 47: 45 - 46 , 7.625, 1, 2.14, 182.6,1.500D-4, -48.2, 1, 301.9, NA , NA 48: 46 - 47 , 7.626, 1, 15.2, 39.3,1.500D-4, -5.5, 1, 301.9, NA , NA 49: 47 - 48 , 5.761, 1, 0.7, 5.21,1.500D-4, 0.0, 1, 301.9, NA , NA 50: HV-3250 , 5.761, 1, 0.0, 0.0,1.500D-4, 0.0, 6, 301.9, 91.0, 0.9 51: 48 - 49 , 6.065, 1, 2.42, 170.2,1.500D-4, -22.0, 1, 301.9, NA , NA 52: 49 - 50 , 6.065, 1, 5.55, 10.9,1.500D-4, 0.0, 1, 301.9, NA , NA 53: 50 - 51 , 6.065, 1, 1.1, 37.6,1.500D-4, 4.8, 1, 301.9, NA , NA 54: 51 - 52 , 6.065, 1, 0.57, 21.6,1.500D-4, 0.7, 1, 301.9, NA , NA 55: 52 - 53 , 6.065, 1, 1.71, 6.92,1.500D-4, -3.5, 1, 301.9, NA , NA 56: 53 - 54 , 7.625, 1, 2.73, 1.26,1.500D-4, 10.5, 1, 301.9, NA , NA 57: 54 - 55 , 0.500, 166,' O.00, 0.00,1.500D-4, 0.00, 6, 301.9, 5.67, 0.9

%O RnA ATT Am. 3 PAGE 1 oF 6

FLOW = 1500 GPM AT 100 xF7 USE PUMP CURVE [OR ENTER PRESSURE] (Y/N):N?

STARTING PRESSURE = 91.6 PSIA 7 ADDITIONAL FLOW (USE WDIV=0.1 IN INPUT FILE!)= 830 GPM7 FILE:FSARPF15.DAT - NO. OF SECTIONS = 57 - TWO-PHASE SECTIONS

  • DIVIDER = 10 SECTION ID K FLOW P(IN) P(OUT) 1 : FEED-WP 8.602 0.0 1,123,394 91.6 2832.1 2 627 - 628 8.602 9.2 1,123,394 2832.1 2820.6 3: HV-31119 7.870 0.0 1,123,394 2820.6 1364.9 Wcr=1,404,683 4 3628 - 629 7.870 5.1 1,123,394 1364.9 1359.9 5 :629 - 8 4.063 14.3 723,215 1359.9 1224.5 6: 8-9 9.516 7.4 723,215 1224.5 1220.5 7: FV-2205 9.516 0.0 723,215 1220.5 881.1 Wcr=1,228,880 8: 9 - 10 9.172 2.9 723,215 881.1 905.4 9: 10 - 11 9.172 1.8 399,566 905.4 905.4 g 10: 11 - 12 3.152 4.2 120,536 905.4 898.7 g 11:TV-2227-6 3.152 0.0 120,536 898.7 893.2 Wcr=1,381,829 -

12: 12 - 18 3.150 0.6 120,536 893.2 892.8 13: 18 - 19 3.346 1.1 120,536 892.8 894.2

    • FRESS <CR> TO CONTINUE **

SECTION ID K FLOW P(IN) P(OUT) 14: 19 - 20 0.886 115.1 6,696 894.2 843.9  !

15: 20 - 21 0.874 0.3 6,696 843.9 843.4 16: 21 - 22 0.898 0.7 2,232 843.4 843.4 17: 22 - 23 0.724 210.1 2,232 843.4 824.8 18: 23 - 23A 0.724 59.9 2,232 824.8 817.7 19: 23A- 23B 0.724 0.0 2,232 817.7 817.7 20: 23B- 24 0.724 0.0 2,232 817.7 817.7 21 24 - 24A 0.550 35.3 2,232 817.7 807.6 22: 24A- 25 0.550 0.0 2,232 807.6 807.6 23: 25 - 26 0.590 4.0 2,232 807.6 804.9 24: 26 - 26A 0.590 28.7 2,232 804.9 800.7 25: 26A- 27 0.590 0.0 2 732 800.7 800.7 ,

26: 27 - 28 C.590 6.2 2,232 800.7 803.8 27: 28 - 29 0.768 0.4 6,696 803.8 803.9 28: 29 - 30 0.969 9.8 6,696 803.9 812.2 29: 30 - 31 3.803 1.1 120,536 812.2 810.0 30: 31 - 32 5.826 4.6 120,536 810.0 790.3 31: 32 - 32A 9.586 3.0 120,536 790.3 790.2 t 32: 32A- 32B 9.586 0.5 241,072 790.2 790.2 ,

33: 328- 33 9.586 0.1 361,608 790.2 790.2 34: 33 - 33A 10.820 0.3 361,608 790.2 790.2

    • PRESS <CR) TO CONTINUE **

H-01 Rtv A ATTACH. 3 PA6E 2 or6

SECTION ID K FLOW P(IN) P(OUT) 35: 33A- 34A 10.820 0.6 '482,143 790.2 790.2 36: 34A- 34B 10.820 0.5 602,679 790.2 790.1 37: 348- 35 10.820 0.6 723,215 790.1 790.0 38: 35 - 36 4.411 3.1 723,215 790.0 769.1 39: PV-22129 4.411 0.0 723,215 769.1 421.5 Wcr= 927,450 40: 36 - 39 11.540 1.3 723,215 421.5 421.3 41: 39 - 40 10.114 0.4 723,215 421.3 413.7 42: 40 - 41 12.500 2.2 723,215 413.7 407.3 43: 41 - 42 14.312 1.4 723,215 407.3 405.7 44: 42 - 43 21.562 0.1 723,215 405.7 401.3 45: 43 - 44 21.562 0.0 723,215 401.3 399.5 46: 44 - 45 14.000 1.2 723,215 399.5 399.9 47: 45 - 46 7.625 4.8 723,215 399.9 415.4 48: 46 - 47 7.626 15.8 723,215 415.4 405.7 49: 47 - 48 5.761 0.8 723,215 405.7 403.9 50: HV-3250 5.761 0.0 723,215 403.9 128.5 Wcr= I23,759 51: 48 - 49 6.065 5.0 723,215 128.5. 127.8 52: 49 - 50 6.065 5.7 723,215 127.8 117.0 53: 50 - 51 6.065 1.7 723,215 117.0 111.9 54: 51 - 52 6.065 0.9 723,215 111.9 110.0 55: 52 - 53 6.065 1.8 723,215 110.0 107.9 56: 53 - 54 7.625 2.7 723,215 107.9 101.7

    • PRESS <CR> TO CONTINUE **

SECTION ID K FLOW P(IN) P(OUT) 57: 54 - 55 0.500 0.0 4,357 101.7 99.1 Wcr= 15,130

    • PRESSURE AT END OF SYSTEM = 0.0 PSIA REPEAT WITH NEW CONDITIONS (Y/N)? .

%-01 RIN A ATTACH.3 EA6ESoF4

      • FILE: FSAR1PF15.DAT ***

SECTION -

ID -WDIV- K(FIX)- K(VAR)- EPS -

EL -FL.- TF - MIN - MAX 25 1 3500 - 502,18.812, 1, 0.82, 0.77,1.500D-4, -1.21, 1, 200.0, NA , NA 2 :502 - 504,22.624, 1, 0.00, 5.8,1.500D-4, 0.0, 1, 200.0, NA , NA 3 3504 - 506,18.812, 1, 1.53, 11.9,1.500D-4, 0.0, 1, 200.0, NA , NA 4 :COND60PMP, NA , 1, 0.00, 0.00, NA , 0.00, 9, 200.0, 5 , NA 5 3508 - 510,11.938, 1, 1.86, 16.4,1.500D-4, 11.75, 1, 200.0, NA , NA 6 3510 - 512,13.124, 1, 0.39, 12.04,1.500D-4, 0.00, 1, 200.0, NA , NA 7 :512 - 609, 13.25, 1, 0.99, 34.9,1.500D-4, 15.1, 1, 200.0, NA , NA 8 3609 - 610, 12.00, 1, 5.62, 26.3,1.500D-4, 6.25, 1, 200.0, NA , NA 9 2610 - 611, 13.25, 1, 0.00, 3.82,1.500D-4, 0.0, 1, 200.0, NA , NA 10:611 - 612, 12.00, 1, 5.30, 29.3,1.500D-4, -5.15, 1, 200.0, NA , NA 113612 - 613, 13.25, 1, 1.30, 151.4,1.500D-4, -10.1, 1, 200.0, NA , NA 123613 - 614, 10.02, 1, 1.55, 13.1,1.500D-4, -4.35, 1, 200.0, NA , NA 13:614 - 615, 13.25, 1, 0.73, 64.3,1.500D-4, 14.75, 1, 200.0, NA , NA 0.7, 14.7,1.500D-4, 8.0, 1, 200.0, NA , NA 14:615 - 616, 13.25, 1, 15:LCV3175-1, 13.25, 1, 0.00, 0.0,1.500D-4, 0.0, 6, 200.0, 160.0, .9 16:616 - 617, 13.25, 1, 0.37, 31.8,1.500D-4, -1.92, 1, 200.0, NA , NA  !

5.7, 11.3,1.500D-4, 0.0, 1, 200.0, NA , NA 17:617 - 618, 12.00, 1, 0.37, 64.2,1.500D-4, -0.5, 1, 200.0, NA , NA 18:618 - 619, 13.25, 1, 5.8, 15.9,1.500D-4, 0.42, 1, 200.0, NA , NA 19:619 - 620, 12.00, 1, 0.0, 1.7,1.500D-4, 0.0, 1, 200.0, NA , NA 20:620 - 621, 13.25, 1, 5.7, 20.3,1.500D-4, 0.0, 1, 200.0, NA , NA 21:621 - 622, 12.00, 1, 5.8, 281.6,1.500D-4, 107.1, 1, 200.0, NA , NA 22:622 - 623, 13.25, 1, 34.2, 00.0,1.500D-4,-21.83, 1, 200.0, NA , NA 23:623 - 624, 13.25, 1, 3.29, 187.0,1.500D-4,-100.2, 1, 200.0, NA , NA 24:624 - 625, 15.25, 1, 0.87, 50.3,1.500D-4, -8.92, 1, 200.0, NA , NA 25:625 - 626, 10.02, 1,

'I i

l

%D Rrv A kTTAcH. S PA6E 4 OF 6

.- __. . .. . _ . . .. . _ = _ .

FLOW = 2330 -GPM AT 200 xF?

USE PUMP CURVE COR ENTER PRESSURE] (Y/N):N?

STARTING PRESSURE = 12.3 PSIA?

ADDITIONAL FLOW (USE WDIV=0.1 IN INPUT FILE!)= 0 GPM?

FILE:FSAR1PF1.DAT - NO. OF SECTIONS = 25 - TWO-PHASE SECTIONS

  • DIVIDER = 10 SECTION ID K FLOW P(IN) P(OUT) 1 3500 - 502 18.812 0.8 1,123,394 12.3 12.8 l 2 350? - 504 22.624 0.1 1,123,394 12.8 12.8 3 3504 - 506 18.812 1.7 1,123,394 12.8 12.7 4 COND60PMP 1.000 0.0 1,123,394 12.7 322.4 5 3508 - 510 11.938 2.1 1,123,394 322.4 316.9 6 3510 - 512 13.124 0.6 1,123,394 316.9 316.8 -

7 :512 - 609 13.250 1.5 1,123,394 316.8 310.2 f^

E :609 - 610 12.000 6.0 1,123,394 310.2 305.9 9 3610 - 611 13.250 0.1 1,123,394 305.9 305.9 10:611 - 612 12.000 5.7 1,123,394 305.9 306.5 11:612 - 613 13.250 3.3 1,123,394 306.5 310.0 12: 613 - 614 10.020 1.7 1,123,394 310.0 310.8 13:614 - 615 13.250 1.6 1,123,394 310.8 304.4 j

    • PRESS <CR> TO CONTINUE ** i l

SECTION ID K FLOW P(IN) P(OUT) 14:615 - 616 13.250 0.9 1,123,394 304.4 300.9 15 LCV3175-1 13.250 0.0 1,123,394 300.9 96.2 Wcr=1,203,414 16:616 - 617 13.250 0.8 1,123,394 96.2 96.8 ,

17:617 - 618 12.000 5.9 1,123,394 96.8 95.2 l 18:618 - 619 13.250 1.2 1,123,394 95.2 95.1 19:619 - 620 12.000 6.0 1,123,394 95.1 93.3 l I

20:600 - 621 13.250 0.0 1,123,394 93.3 93.3 21:621 - 622 12.000 6.0 1,123,394 93.3 91.6 22:622 - 623 13.250 9.6 1,123,394 91.6 45.0 23:623 - 624 13.250 34.2 1,123,394 45.0 47.6 24:624 - 625 15.250 5.8 1,123,394 47.6 88.8 25:625 - 626 10.020 1.6 1,123,394 88.8 91.6

    • PRESSURE AT END OF SYSTEM = 91.6 PSIA REPEAT WITH NEW CONDITIONS (Y/N)?

I Ob ATTAG 3 PA6e sok6

r MASS FLOW RATE OF HELIUM .....: 6408 LDS/HR/ MOD =10.7 LBS/SEC TOTAL TOTAL LOOP FLOW RATE OF WATER : 1500 GPM 8 100xF = 125000 LBS/HR/ MODULE SATURATION PRESSURE...........: 800.7 PSIA  ;

SATURATION TEMPERATURE........: 518.2 AF i HEAT OF EVAPORATION ..........: 688.9 BTU /LB HEAT CAPACITY OF WATER .......: 1 BTU /LB/xF HEAT CAPACITY OF STEAM........: CF= .5 BTU /LB/rF PF= .5 BTU /LB/xF HELIUM..: IN=1800.0 AF OUT= 200.029 xF WATER...: ENTERING AT 200.0 xF EXITING AT 301.9 xF AS WATER I

HEAT = 0.0*10^6 U= 29.4 i AEC(1)= 755.0 (100.00%)

AEC(2)= 876.5 ( 0.00%)

. HEAT = 0.1*10^6 U= 27.9 AEC(3)= 888.0 (100.00%) HEAT = 1.0*10^6 U= 27.6 AEC(4)= 863.0 (100.00%) HEAT = 11.7*10^6 U= 33.6 TOTAL HEAT RATE = 76.4*10^6 BTU /HR (ECON = 76.4+EVAP= 0.0+SH= 0.0)

    • PRESS ANY L'EY TO CONTINUE FOR TEMPERATURE DETAILS *
  • 1 SECTION # 1
  • EC*H20: 200.0 TO 200.0 -HE: 200.4 TO 200.0 (Re=1474) -WL: 200.0, DT= 0.0 SECTION # 2
  • EC*H20: 200.0 TO 200.5 -HE: 207.6 TO 200.4 (Re=1470) -WL: 200.4, DT= 0.1 SECTION # 3
  • EC*H20: 200.5 TO 208.6 -HE: 334.9 TO 207.6 (Re=1417) -WL: 206.6, DT= 1.9 SECTION # 4
  • EC*H20: 208.6 TO 301.9 -HE:1800.0 TO 334.9 (Re=1131) -WL: 310.8, DT=75.2 ENTER DIFFERENT HELIUM TEMPERATURE:

14-01 REV. A ATTK H.3 PA6E 6cF 6

- -a - & -

y s 4

OVERSIZE l DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF OVERSIZE PAGE,' FILMED ON APERTURE CARDS APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-8989

_ . -_.. --__ _ _._.- _ -____

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