ML20211E110
| ML20211E110 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/26/1987 |
| From: | Atkisson R, Fekete M, Geaney G PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20211D893 | List: |
| References | |
| EE-EQ-0023, EE-EQ-0023-RA, EE-EQ-23, EE-EQ-23-RA, TAC-63576, NUDOCS 8702240238 | |
| Download: ML20211E110 (63) | |
Text
. _ _ _ . .
pub llC FORT ST. VRAIN NUCLEAR GENERATING STATION 79 7 gggfy
$ ) SCIVlCG" PUBUC SERVICE COMPANY OF COLORADO BEGINEERING EVALUATION OF THE PROCEDORE TO RECOVER FROM AN ACTUATION OF THE l
STEAM LINE RUPTURE DETECTION / ISOLATION SYSTEN FOR POWER LEVELS THROOGB P2 E5-50-0023 REV. A EIII.II.M
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Prepared By: M /
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Datie Proto-Power Corporation
. / II II R.JV Atkisson, Jr. I Date Proto-Power Corporation Reviewed By:
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/MSAf W. Geaney
/!23!87 d Date Proto-Power Corporation Verifled By: /[24 [8 */
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i Date Approved By: Nk b NUCLEAR DS$IGN NRERGER Date 87 G702240230 070217 PDH ADOCK 05000267 F PDH FORueCl312 22 364 l
6 FORT ST. VDAIN NUCLEAR GENERATING STATION
, Pubil3 0.99fVlCO' pusuc sanvics compam or cos.onano e E'-:2-ec z ey e CHECK LIST OF DESIGN VERIFICATION QUESTIONS FOR DESIGN REVIEW METHOD MGE YES NO N/A
- 1. Were the inputs correctly selected and incorporated into design ?
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- 2. Are assumptions necessary to perform the design activity adequately described and reasonaole)
Where necessary, are the assumptions identified for subsequent re-venfications when the detailed design activities are completed?
- m y L) LJ LJ 3. Are the appropriate quality and quality assurance requirements specified?
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- 4. Are the applicable codes standards and regulatory requirements including issue and addenda i
1 property identified and are their requirements for design met?
l 2 5. Have applicable construction and operating experience been considered?
UCC 6. Have the design interf ace requirements been satisfied?
b 7. Was an apprognate design method used?
l b 8. Is the output reasonable compared to inputs?
f CC 9. Are the specified parts equipment, and processes suitable for the required application? l
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- 10. Are the specified matenals compatible with each other and the doesgn environmental conditions to which the matenal will be exposed? }
2 11. Have adequate maintenance features and requirements been specrfied?
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" "n g 12. Are accessibility and other design provisions adequate for performence of needed maintenance and sepait? f R
" g 13. Has adequate accessibility been provided to perform the in service inspection expected to be required dunng the plant life?
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- 14. Has the design properly considered radiation exposure to the public and plant personnel?
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l U "~n7 15. Are the acceptance entena incorporated in the design documents sufficient to allow verification that desegn requirements have been satisfactonly accomplished?
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F U g 16. Have adequate pre-operational and subsequent penodic test requirements been apprognateiv specified? ;
w JL 7 17. Are adequate handling, storage, cleaning and shipping requirements specified?
2 18. Are adequate identification requirements specified?
U3 19. Are requirements for record preparation review, approval, retention, etc., adequately specifie#
NOTE: If the answer to any question is no. provide additionalinformation and resolution below.
RESOLUTION OF DESIGN DEFICIENCIES UNCOVERED OURING THE DESIGN VERIFICATION PROCESS Ab ddauce.s woe ;M.hed b y 7Gs mew, A urm
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ENGINEERING IVALDATION OF TER PROCEDORE TO RECOTER FRON A5 ACTUATION OF TEE STRAN LIM RUPTURE DETECTION /ISOIATION SYSTEN FOR POWER LEVEIA THROUGE P2 E5-30-0023 REV. A Prepared By:
PROTO-POWER CORPORATION 591 Poquonnock Road Groton, Connecticut 06340 l
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6 85-2Q-0023 e REV. A TABLE OF COtrFElrr5 SECTION PAGE 1.0 PURPOSE 1 2.0
SUMMARY
1 3.0 SCOPE 2 4.0 APPROACH 2 4.1 Background 2 4.2 Procedure 3 I
5.0 EVALUATION 4 5.1 Background 4 5.2 Verification of HELB and Integrity of the 5 Fire Water Flow Path 5.3 Filling of the Flow Path with Fire Water 7 5.4 Verification of Fire Water Flow 9 5.5 Resumption of Forced Circulation 10 5.6 Time Required to Re-Establish Forced 11 Circulation
6.0 CONCLUSION
S 14
7.0 REFERENCES
14 8.0 ATTACHMENTS 16 8.1 Outline of Recovery Procedure from SLRDIS Actuation Using Fire Water Cooling 8.2 SLRDIS Recovery Flow Chart Outline 8.3 Figure 1 - Status of EES Flow Path Af ter SLRDIS Actuation 8.4 Figure 2 - Fire Water Flow Path for Recovery From a HEL3 r
i EE-EQ-0023 REV. A ENGINEERING EVALOATION OF TER PROCEDURE TO RECOVER FROM AN ACTUATION OF TER STEAM LINE RUPTURE DETECTION / ISOLATION SYSTEN FOR POWEA LEVELS TEROOGE P2 1.0 PURPOSE The engineering evaluation was performed to develop the technical basis for a procedural outline for the recovery f rom an actuation of the Steam Line Rupture Detection / Isola-tion System (SLRDIS). The evaluation addresses recovery f rom both a spurious actuation of SLRDIS, and an actuation due to a H igh Energy Line Break (HELB), involving the resumption of forced cooling of the core after a 1-1/2 hour period of interruption. The evaluation pertains only to re-establishing cooling water flow to the EES section of one steam generator. Other actions required for safe shutdown (i.e., establishing flow to the pelton wheel and the circulator bearings) are not addressed. This engineering evaluation addresses safe shutdown cooling for power levels through P2 percent, and is based on analyses performed by Proto-Power and GA Technologies, References 7.1 and 7.2.
There are several potential sources of cooling water which could be used for safe shutdown cooling following a HELB.
However, the Equipment Qualification (EQ) basis flow paths for the resumption of forced cooling for power levels through P2 involve using fire water to drive one circulator and to provide cooling water to the EES section of one steam generator. These flow paths utilize environmentally quali-fled equipment if the equipment is subject to the harsh environment caused by the HELB. This evaluation will address the procedure for safe shutdown cooling using fire water only.
2.0 SMY Attachments 8.1 and 8.2 are the outline of a procedure and the flow chart for the recovery from the actuation of SLRDIS using fire water cooling following a HELB.
Recovery from a HELB with fire water cooling would involve using flow paths similar to those described in the FSV FSAR as modified by the flow path changes detailed in Eng ineer-ing Evaluation EE-EQ-0011 (Reference 7.3), SR-6-0 (Reference 7.5) and this engineering evaluation (use of the main steam vent valves). The EES section of one steam generator will
, . EE-EQ-0023 REV. A be relied upon for safe shutdown cooling for all high energy line break locations. The fire water flow would discharge through one new main steam vent path (HV-22821 (HV-22822)]
for any break location.
The procedural outline developed requires that the initia-tion of fire water flow to the steam generator begin no later than 69 minutes after the loss of forced circulation, thereby assuring that the resumption of forced cooling will commence no later than 1-1/2 hours af ter the accident. Up to this time, other methods of resuming forced circulation
( i .e . , feedwater) could be attempted.
3.0 SCOPE The FSAR for FSV, (Reference 7.4), specifies that the EES section of one steam generator is adequate for safe shutdown cooling using fire water, after a 1-1/2 hour interruption of forced circulation. EE-BQ-0011 and SR-6-0 ( Re f e re nce 7. 5 ) ,
define existing fire water cooling flow paths. 10CFR50.49 (Reference 7.6) specifies the accident scenario assumptions and guidelines for safe shutdown following a HEL8. The References 7.1 and 7.2 analyses demonstrate the adequacy of EES cooling for flow paths and safe shutdown coolina conditions considered in this engineering evaluation. The scope of this evaluation was to develop a safe shutdown procedural outline within the requirements and guidelines of the above referenced documents. This procedural outline will be of suf ficient detail to be used in the development of the detailed emergency procedures.
4.0 APPROACE 4.1 Bacheround Detection of a high energy line break by SLRDIS will result in the automatic initiation of several actions:
o Closure of forty-four (44) valves by SLRDIS resulting in loss of primary coolant circulation and secondary coolant heat removal.
l o Reactor scram.
o Turbine and circulator trip and resultant closure of several additional valves in the secondary coolant system.
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35-50-0023 REY. A t
These actions will result in isolation of sections of the feedwater and main steam piping which could be used for safe shutdown cooling.
Recovery from actuation of SLRDIS would require the followings o Verification of a HELS i
o Re-establishing forced circulation after a p
, spurious actuation, or o Verification of the integrity of the fire water flow paths o Alignment of the selected fire water flow path i
o Filling of the flow path piping and steam generator EES section with fire water o
Initiation and verification of fire water cooling through the flow path l o Resumption of forced primary coolant circulation i
j 4.2 procedure i
i System PI drawings, system descriptions and CN-2176 1
(Re ference 7.7) were reviewer! to determine the plant '
j status and secondary system valve positions af ter actuation of SLRDIS. The PI drawings and Master Equipment List (MEL, Reference 7.8) were used to determine the existing instrumentation located in the fire water flow path piping that could be used for verification of piping integrity. Por piping sections r which did not have qualified pressure instrumentation '
i instal' led, alternate schemes were developcd to verif y piping integrity. This included the use of non-quali-fled instrumentation located in the building in which the NELS did not occur, or the opening of a qualified valve to communicate a non-instrumented section with an instrumented section. These documents were then ,
l reviewed to determine the instrumentation available which could be used to determine cooling water conditions leaving the steam generator, consistent with the requirement to rely on only instrumentation i that is qualified if located in the harsh environment.
Re f e rence 7.7 was also reviewed to determine e.h e actions required to reset SLRDIS and ensure valves are '
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EE-EQ-0023 REV. A i
not inadvertently opened either when the SLRDIS panels are reset or other SLRDIS valves are opened. Re fe ren-ces 7.5 and 7.9 thru 7.12 were reviewed for technical input and for consistency with this engineering evaluation.
- The Re f erences 7.1 and 7.2 analyses were reviewed to ensure the safe shutdown cooling co nd it ions and requirements specified in these analyses are con-sistent with the safe shutdown procedural outline. The accuracy of the instrumentation relied upon in this >
safe shutdown procedural outline must also be consis-tent with the Reference 7.2 analysis requirements.
The period of time required to take all actions necessary to establish fire water cooling using a steam generator was then determined. Each procedural step to re-establish forced circulation was identi-fied, and the time-to-complete dete rmined . Several o f these steps could be done prior to, or in parallel with, attempting to establish cooling with sources other than fire water. However, initiation of fire water flow to the steam generator must begin in suf ficient time to support the resumption of forced circulation within 1-1/2 hours following SLRDIS actuation. Therefore, the maximum time available for the operator to attempt to initiate alternate cooling flow paths was determined.
Existing procedures for establishing fire water flow
' to the pelton wheel of a circulator would be utilized, and therefore, this evaluation need not address in detail establishing fire water to the pelton wheel, other than the sequencing of this event. Requirements for the control of circulator speed to ensure adequate core cooling, however, is included in the evaluation.
5.0 EVAMIATICE 5.1 ancheroemd The evaluation was conducted to determine the major events and sequencing of events to recover from a j SLRDIS actuation, including the resumption of forced circulation using fire water, following a HELB. An evaluation ot each major event is presented, includ-ing justification for the actions required during the event.
EE-EQ-0023 REV. A 5.2 Verification of BELS and Integrity of the Fire Water '
Flow Path Af ter actuation of SLRDIS, the operator will attempt to locate the break using both qualified and non-qualified instrumentation. The SLRDIS panel will only identify the building in which the break occurr.ed. To meet the intent of 10CFR50.49 for fire water cooling, the operator must have the capability of determining if thepath, flow break occurred and in a section thus determine whichof a water fire fire water flow paths are available for safe shutdown cooling. For electrical equipment and instrumentation located in the harsh environment resulting f rom the HELB, only qualified items can be assumed to be available for use.
CN-2473, Re f e rence 7. 21, will modify the lower right corner of the lamicold legend labels of selected control room instrumentation to incorporate special EQ demarcation identified below. This CN is based on the evaluation of Reference 7.16.
Demarcation Definition White Dot Instrumentation is qualified and may be relied upon following any HELB.
letter "R" Instrumentation is not qualified but may be relied upon for a Turbine Building HELB.
letter "T" Instrumentation is not qualified but may be relied upon for a Reactor Building HELB.
References 7.3 and 7.5 specify the EQ flow path to be through the EES section o f one steam generator, the main steam bypass and superheat depressurization valves (PV-2229, PV-22129 and PV-22153 for Loop 1:
PV-2230, PV-22130 and PV-22154 for Loop 2; the flash tank (T-5201), and then vented to atmosphere via HV-5252. However, both EES loops utilize a common section of line downstream of each EES loop depressur-ization valve. Therefore, a HELB located in this common line would result in discharge of the EES-heated fire water in either the Reactor or Turbine Building. To preclude this occurrence, alternate EES cooling paths were developed, utilizing new vent 5-
,. EE-EQ-0023 REY. A valves (HV-22819, HV-22821 (HV-22820, HV-22822)),
located in each steam generator EES outlet header,
- upstream of the loop superheater stop check valves.
Therefore, the flow path through the new vent valves will be used for recovery from all HELBs in the Reactor and Turbine Buildings.
Reference 7.2 specifies required instrumentation accuracies for indicating EES outlet pressure and average outlet temperature, to ensure adequate core cooling and prevent steaming in the steam generator (discussed further in Section 5.5). The Reference 7.13 evaluation of existing instrumentation indicate that these accuracy requirements could not be met using existing instrumentation. New local pressure gauges (PI-22129-2 (PI-22130-2)] and local dial temperature indicators [TI-22823 (TI-22824)] are to be installed in the Turbine Building and Reactor Build-ing, respectively, to provide the accuracy required.
This instrumentation will be used for monitoring fire water cooling flow only, and not used for determining integrity of the fire water flow path.
Reference 7.7 identifies the forty-four valves which are closed by SLRDIS actuation and the hand switches which control valve position. Appropriate system PI drawings and system descriptions identify the valves which close on turbine trip. This information was reviewed and used to develop the Attachment 8.3 (Figure 1) system diagram depicting valve positions in the cooling paths following SLRDIS actuation. Figure I also identifies existing pressure instrumentation which could be used for verification of the integrity of the isolated piping in the cooling water flow paths.
Table 1 of Attachment 8.1 specifies the forty-four valves closed by SLRDIS, and the associated reset
! actions required to allow the operator to open each i valve individually. This includes the resetting of the SLRDIS rack I-93543, Logics A and 8. To ensure
' that a valve closed by SLRDIS will not inadvertently open by SLRDIS or valve reset actions, each valve is I
to be actuated " closed" by use of the associated hand switches, i
The unqualified thermal overload relay contacts for 4
motor operated valves fed f rom Motor control Center s located in the harsh environment must be bypassed, either by pressing the thermal overload bypass pushbuttons HS-9219-1, HS-9220-1 and HS-9208-1 located
{ ._ __- - - - - = = - - _ - . - _-. - __ - ..
. l BE-EQ-0023 3 RBV. A on I-15 for Turbine Plant MCC 1, ~2 and 3 for a Turbine Building break or pushbuttons HS-9229-1, HS-9230-1 and BS-9231-1 IB, located on I-15 for Reactor Plant MCC 1A, IC, 2 and 3 for a Reactor Building break. The concern is that an environmentally induced failure of these contacts could preclude required operat ion o f a valve following a HELB.
For a break in the Reactor Building, the two 500 VPM Moisture Monitor Modules and the three Reactor Pressure Transmitte located in'I-10 (PPS), rs .PT-1108, PT-1109 and PT-1110, must be removed to ensure that a loop shutdown will not occur due to the environment-ally induced failure of the associated unqualified field devices.
the hot For a break in the Turbine Building, reheat activity monitor modules, RIS-93250-10, RIS-93250-11, RIS-93251-10, RIS-93251-11, RIS-93252-10 and RIS-93252-11 must be removed to ensure that a loop trouble trip will not occur due to an environmentally induced failure of the associated unqualified field devices.
required by These actions7.15 References have andbeen 7.16.determined to be Table 2 of Attachment 8.1 specifies procedures to verify integrity of piping sections in the fire water flow paths. All required instrumentation located in a harsh environment when required for use in verifying piping integrity are qualified.
integrity of the piping used for safeVerification shutdown withof fire water cooling could be conducted without requir-ing access to the harsh environment, except for the verification of integrity of the emergency condensate line following a Turbine Building HELB. Appendix I of Reference 7.4 states that pipe whip of a failed high energy line in the Turbine Building could cause a rupture of the emergency condensate line. Access into the Turbine Building is required to verif y emergency condensate line integrity, by observing line pressure indicated on local pressure gauge PI-31204 (located on the emergency condensate line adjacent to V-31239) .
If the emergency condensate line has ruptured, fire water must be aligned to the emergency feedwater header in accordance with Reference 7.14.
5.3 Filline of the Flow path with Fire Water once the operator has selected the flow path (utiliz-ing either Loop 1 of Loop 2), based on break location and equipment availability, the operator will begin the flow path filling process.
EE-EQ-0023
,. REY. A The pressures in the sections of piping isolated by '
SLRDIS will be significantly above the f tre water pump i
shutoff head. Therefore, prior to establishing fire water cooling flow, the flow path from the emergency condensate isolation valve to the flow path outlet must be depressurized. Loop pressure would first be '
reduced by dumping the EES loop to the steam / water dump tank, T-2201. System interlocks prevent dump valve HV-2215 (HV-2218) from opening if the same loop feedwater flow control valve FV-2205 (FV-2206) is open. However, the flow control valve should be open to allow for depressurization between the feedwater block and flow control valves. Therefore, loop depressurization should be via HV-2217 (HV-2216).
Valves TV-2227-1 thru -6 (TV-2228-1 thru -6) should be opened prior to initiating the dump to facilitate depressurization downstream of these valves. To open a failed dump valve or the other dump valve in that loop, the valve relay (i.e., CR-2215 for HV-2215 typical) located in I-10, bay 800, must be actuated by manually pressing the relay. Upon completion of loop 1
dump, the final loop pressure would be approximately
' 196 psia, as specified in Reference 7.17. The loop new main steam vent valve would then be opened for final depressurization to atmosphere. This procedure will also allow the operator to verify the operability of secondary coolant valves in the flow path, with i
the exception of the emergency condensate (or feed-water) isolation valve.
Filling the flow path should begin with flooding the '
i voided piping between HV-4 518 and HV-4 519, by using fire water from the fire water storage tank. This
! will prevent the possibility of water hammer occurring during start-up of the fire water pump due to air i trapped in the discharge line between these two
! valves. Portions of the fire water system not
- required for safe shutdown cooling will be isolated i
from the fire water cooling flow path by closing l EV-4520 and HV-45201. This will prevent fire water i being diverted to any sprinklers activated due to the elevated ambient temperature.a caused by the HELB.
1 A minimum of one fire water pump will be used to fill the flow path. The fire water pump sould be started l and then HV-4519 opened. (This proudure for aligning j and filling condensate and fire watar lines does not apply if the emergency feedwater line is utilized.
Rather, Reference 7.14 would apply.) The appropelate I
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+
EE-EQ-0023 REV. A emergency condensate (or feedwater) isolation valve would then be ope ned , initiating flow into the flow path.
Fire water will fill and cool the steam generator and piping. Due to the elevated temperatures of the piping and steam generator, steaming will in it ially occur in the flow path. As cooling flow continues, steaming at the steam generator outlet will stop.
Cooling of the steam generator should continue unti il the fire water outlet temperature is lowered to 165 F, as indicated on TI-22823 (TI-22824). This will ensure that steaming in the steam generator will not occur when primary coolant flow is re-established. As discussed in Section 5.5, steaming in the steam generator with primary coolant flowing through the steam generator will result in an increase in system pressure drop, and reductions in fire water flow and heat removal. This will raise steam generator metal temperatures. If steaming results in a significant flow reduction, steam generator tube damage could occur. The reduced cooling water flow rate would reduce decay heat removal and possibly result in core damage. Reference 7.18 specifled a system cooldown time of 14 minutes, utilizing the flash tank vent HV-5252. The cooldown time associated with the shorter run through the main steam vent would be less.
TI-22823 (TI-22824) are not permanently installed in TW-22823 ( TW-2 2 8 2 4 ),, as the instrumentation is not rated for the 1000 F main steam temperature. The indicator should not be installed in its thermowell until all steaming has stopped at the exit of the main steam vent as visually evidenced. This will ensure that the ind icato r will not be damaged by h ig h temperature steam.
5.4 Verification of Fire Water Flow Verification of fire water flow, and the actual flow i
rate should be determined by use of the qualified flow element located in the inlet piping to each steam generator section. Required instrumentation are id ent i f ied in Table 3, and shown on Figures 1 and 2 (Attachments 8.3 and 8.4). Depending on break location, this will also verify that the emergency condensate (or feedwater) isolation valve has opened .
The circuitry for valve position indication for any valve is not qualified.
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EE-EQ-0023 REV. A ;
5.5 Resumption of Forced Circulation Resumption of forced circulation by 'se of a pelton wheel driven circulator should not begin until the cooling water outlet temperature conditions specified in paragraph 5.3 have been met. This will ensure the maximum heat removal capacity of the steam generator while maintaining acceptable steam generator tube metal temperatures when forced circulation is resumed.
Existing applicable emergency procedures should be used to establish primary coolant flow.
FSV FSAR states that a helium flow rate of approxi-mately 3% of design flow rate would be required to remove suf ficient decay heat to ensure sa fe shutdown .
However, recent analysis performed by Proto-Power and GA Technologies indicates that for this helium flow rate, excessive steaming will occur in the EES section during the initial period of forced circulation. On a mass flow basis, the pressure drop resulting from steam flow is significantly higher than for water flow. Therefore, steaming will result in an increase in system pressure drop, and a reduction in fire water flow. The analysis concludes that the flow rate would be significantly reduced, thereby not prov id ing sufficient cooling of the EES section tubes and the core fuel. Tube metal and fuel temperatures would rise significantly, and tube and fuel damage could occur. Therefore, to avo id steaming in any EES module, the circulator speed, and thus primary coolant flow, should,be slowly increased and controlled to maintain 257 F liquid conditions at the steam genera-tor EES outlet, as indicated on TI-22823 (TI-22824).
The main steam vent valve must be throttled as required to maintain 64 psig at the EES outlet, as indicated on PI-22129-2 (PI-22130-2). Refe rences 7.1 and 7.2 have demonstrated that sufficient core heat removal would be provided with temporarily reduced helium flow to prevent fuel damage, and ensure safe shutdown. This procedure is similar to the existing procedures for safe shutdown and cooling under highly degraded conditions ( Reference 7.14 ) .
Fire water conditions leaving an EES section should be monitored using instrumentation identified on Table 3.
The calculated flow rate to the steam generator after steaming has stopped and primary coolant flow has been re-established is approximately 1000 GPM (500,000 lb/hr) as verified for the Figure 2 flow path by analysis performed by Proto-Power, Reference 7.1.
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- EE-EQ-0023 '
REV. A 5.6 Time Required to Re-Establish Forced Circulation The time required to re-establish forced circulation with fire water cooling and one fire water driven circulator has been evaluated based on the Outline of the Recovery Procedure from SLRDIS Actuation Using Fire Water Cooling for Power Levels Through P2 (Attachment 8.1) and the time constraints for operator action specified in Reference 7.19. The use of the emergency condensate header is assumed. No action by the operator has been assumed to occur for ten minutes following the HELB. During this time, the operator will be determining the status of the plant includ ing the verification of the HELB. Subsequently, each operator initiated action has been assumed to require one minute to complete, with the following two exceptions: 1) five minutes to open a manual valve, and 2) actual time to complete a repetitive set of actions (i.e., actuating closed the forty-four SLRDIS valves), as determined by testing, or conservatively estimated plus one minute for operator decision.
Table 7.1-1 of Amendment 36 to the FSV Technical Specifications, Re fe rence 7.20, requires the minimum shift crew composition to be one senior shif t super-visor plus three reactor operators, one equipment operator and one auxiliary tendor. One person less than this minimum requirement is allowed for a period of two hours. Assuming that during the recovery the shift supervisor will be directing the recovery actions (and not performing any recovery actions) and the crew is one person less than that specified in Table 7.1-1, two Control Room operators would be available in the Control Room, and two add it iona l personnel would be available to perform actions in areas of the plant not in the harsh environment.
These ' personnel would be performing actions in parallel, when appropriate, to initiate safe shutdown.
Therefore, up to four actions could be performed simultaneously.
Based on these requirements and the results of analyses performed to determine flow path venting and fill rates, the anticipated time required to re-estab-lish forced cooling to the Loop 1 EES Section has been d ete rm ined . A Reactor Bu ild ing break has been assumed, although the time-to-complete is not signifi-cantly dependent upon building break location.
EE-EQ-0023 REV. A
'IUIRL !
Ppn N m 4L TDE TDE AEEGETIGEi/
S'tW ACTIGI (NIN. ) (NDI. ) CX30mitS 1 Verification of HEIB 10 10 Performed within the initial and determination of 10 minute period of plant building with HEIB. status review.
2 Verify flow path 10 Per Table 1 reset action integrity:
for W-2205 and W-2206.
- actuate closed 44 6 valves Time required to actuate
- reset SIRDIS (*) and 3 closed 44 valves is based bypass thermal over- on test.
load contacts (*)
- renove two 500 VPM 3 Nisture Monitor Modules and Reactor Pressure Transnitters PT-1108 thru PT-1110 (*)
- open W-2205 and 1 W-2206 (*)
3 Depressurize EES path 11 HV-22821 to be opened when
- own TV-2227-1 3 systen pressure is approxi-thru -6 (*) mately 196 psia.
- open dtznp valve 1 HV-2217 (HV-2216) (*,**)
- depressurim EES 1
- close dtznp valve 1
- open HV-22821 5 4 Fill pipe between 0 Line fills while valve is HV-4518 & B7-4519 opening; closing V-45945 is
- open. HV-4518 5 optional. Performed in
- close V-45945 0 parallel with Step 3.
l 5 Close HV-4520 and 5 0 Performed in parallel with V-45201 (*) Step 3.
6 Start one fire eter 1 0 Motor driven pump is planp. started. Performed in parallel with Step 3.
7 Start second fire 0 0 Optional, water planp, if available.
1 1
EE-EQ-0023 ;
REV. A
'10!RL PPn a m 4L TDE TIME SMP ASSGETIGE/
ACTIGi (MDi. ) (MIN.) Q30mffS 8 Open HV-4519 5 5 9 Open emergency 1 1 condensate isolation valve HV-2237.
TIME TO Ermar.rm FIRE MTIR FII3t - IBWIGREY CGmsesRATE PBGR
= 37 MD m ES 10 Fill and cool steam 14 14 generator.
11 Establish fire e ter 1 1
'Ihis action is the opening flow to circulator. of the final valve in the flow path to the pelton wheel. Other valves were opened in parallel in previous steps.
12 Control circulator 0 0 spegd to maintain 257 F liquid condi-tion at EES outlet.
Maintain 64 peig at EES outlet.
TDS TO ES'5mr.rm yGICE PRIMMtr CIRCG[ATIGI = 52 MDmES
- Two actions performed in parallel.
Put HS-93315 (HS-93316) in Auto, HS-22109 (HS-22110) in Dtutp.
The total time required to perform steps 1 through 12 and resume forced circulation, with no active fail-ures, is 52 minutes. Worst case active f ailure would be the failure o f the emergency condensate isolation valve HV-2237 (HV-2238) to open. Depending on break location and operator judgement, the operator may either manually open the failed closed emergency condensate isolation valve, or cooldown utilizing the other loop steam generator's EES section. Manual opening of the emergency condensate isolation valve wo uld increase time-to-complete by approximately 5 minutes to 57 minutes. Use of the other EES section would require loop depressurization by repeating step 3 for the other loop. System depressurization and
- EE-EQ-0023 REV. A realignment for cooldown using the other EES loop would take 6 minutes. Increasing the total time-to- '
complete to 58 minutes, which is significantly less than the 90 minutes maximum specified in the FSAR for safe shutdown cooling.
During performance of Steps 1 through 8, the operator could also be attempting to re-establish cooling flow with preferential cooling water sources, such as feedwater or condensate. Ho we v e r , the operator must commit to the use of fire water cooling in sufficient time to ensure initiation of fire water flow to the steam generator within 90 minutes af ter the HELB. As the time to complete step 9 is one minute and account-ing for manual opening of a failed emergency conden-sate isolation valve (5 minutes) , conservatively the operator must begin filling the steam generator with fire water by opening the emergency condensate system isolation valve (Step 9) no later than 69 minutes after SLRDIS actuation.
6.O COIOCLUSIONS Resumption of forced circulation, utilizing either fire water cooling flow path shown on Attachment 8.4 and fire water to power the pelton wheel of one circulator, could be initiated within the 1-1/ 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> requirement specified in the PSAR, utilizing the procedural outline of Attachment 8.1.
All equipment that would be used for safe shutdown cooling and are located in the harsh environment are environmentally qualified.
I
7.0 REFERENCES
7.1 Proto-Power Calculation No. 82-03,. Rev. B, "EES Safe Shutdown Cooling for PSC - Fort St. Vrain (3. Main Steam Vent Flow Path)"
GA Technolog ies Document No. 909269, Issue N/C, "EES
~
l 7.2 Cooldown for EQ and Appendix R Events with Vent Lines (1.58 Delay)"
7.3 Eng inee r ing Evaluation EE-EQ-0011, Rev. C, " Safe Shutdown Forced Circulation Path for Environmental Qualification Following a High Energy Line Break" 7.4 Fort St. Vrain (FSV) Updated Final Safety Analysis Report (FSAR) i
- ' ^^
- EE-EQ-0023 REV. A 7.5 SR-6-0, Issue 0, "Model for Equipment Required for Safe Shutdown Cooling Following a HELB" '
7.6 10CFR50.49 7.7 CN-2176 7.8 FSV Master Equipment List (MEL), dated July 28, 1986 7.9 Engineering Evaluation EE-EQ-0013, Rev. B, " Accidents Resulting in Harsh Environment Areas at Fort St.
Vrain" ,
7.10 Engineering Evaluation EE-EQ-0016, Issue A, " Isolation of Condensate and Feedwater Line Breaks" 7.11 Eng inee r ing Evaluation EE-EQ-0014, Rev. G, " Safety Analysis Report, Steam Line Rupture Detection / Isola-tion System" 7.12 Engineering Evaluation EE-EQ-0021, Rev. C, " Engineer-ing Evaluation of the Consequences of a Wrong Loop Dump Following a High Energy Line Break" 7.13 Proto-Power letter to PSC, dated January 16, 1987.
7.14 PSC Document SSCHDPC, Issue 14, " Safety Shutdown and Cooling with Highly Degraded Conditions" 7.15 Engineering Evaluation EE-EQ-0004, Rev. E, " Eng inee r-ing Evaluation of the Interaction and Effects of Non Qualified Components on the Operation of the Plant Protective System and Evaluation of the Environmental Qualification Requirements for the Post Acc id e n t Monitoring Instrumentation" 7.16 Engineering Evaluation EE-EQ-0045, Rev. A, " Eng inee r-ing Evaluation of the Environmental Qualification Status of Control and Indication Devices on the Fort St. Vrain Main Control Board"
'7.17 FSV System Description 22-1, Issue T 7.18 Proto-Power Calculation No. 82-10, Rev. , "EES Flooding Time With Fire Water" 7.19 PSC Letter P-85456 to the NRC, with Attachments 7.20 PSV Technical Specifications, Amendment 36 7.21 CN-2473 EE-EQ-0023 REV. A 8.O ATTSCWIEWPS 8.1 Outline of Recovery Procedure f rom SLRDIS Actuation Using Fire Water Cooling 8.2 SLRDIS Recovery Flow Chart Outline 8.3 Figure 1 - Status of EES Flow Path After SLRDIS Actuation 8.4 Figure 2 - Fire Water Flow Path for Recovery From a HELB.
1 1
.2_ . _ . . . - _ _ . _ . _ . - . , _ - _ . - _ - _ _ _ _ _ - _ , . . _ . . _ .
EE-EQ-0023 REV. A ATPACEMENT 8.1 OUTLINE OF RECOVERY PROCEDORE FROM SLRDIS ACTUATION USING FIRE WATER COOLING FOR POWER LEVELS THROOGB P2
- 1. Determine the building ( reactor or turbine) the steam line rupture has occurred in, as indicated on the SLRDIS panel .
2.
Actuate closed all forty-four valves closed by SLRDIS, to ensure that the valves do not inadvertently open when SLRDIS and other relays are reset. Refer to Table 1.
- 3. For a Reactor Building break, bypass the thermal overload relay contacts for motor operated valves fed by Reactor Plant MCC 1 A, 1B, 1C, 2 and 3 by pressing the thermal overload bypass pushbuttons (HS-9229-1, HS-9230-1 and HS-9231-1) located on I-15.
For a Turbine Building break, bypass the thermal overload relay contacts for motor operated valves fed by Turbine Plant MCC 1, 2 and 3, by pressing the thermal overload bypass pushbuttons (HS-9219-1, HS-9220-1 and HS-9208-1) located on I-15.
- 4. Reset SLRDIS rack I-93543, Logics A and B.
- 5. For a Reactor Building break, remove the two 500 VPM moisture monitor modules and the three reactor pressure transmitters ( PT-110 8, PT-1109 and PT-1110) located in I-10 (PPS). ,
hor a Turbine Building brhak, remove the six hot reheat activity monitor modules, RSS-93250-10 and -11, RIS-93251-10 and -11, and RIS-93252-10 ar?d -11 from I-10 (PPS).
- 6. Determine the integrityof!the portions of the secondary coolant system which could be used for safe shutdown cooling with fire water, using the pressure instrumentation and procedures identififd in Table 2. If the emergency conden-i, sate line has rupturpd, line up fire water to the emergency feedwater header add the pelton wheel in accordance with
" Safe Shutdown and Choling with Highly Degraded Conditions" (SSCliDPC), in lieu c'* Steps 8, 9 and 12.
6 m
- - ~ ~
1 EE-EQ-0023 REV. A I.
- 7. Depressurize the flow path to be used for cooldown to the emergency condensate (or feedwater) isolation valve. The flow path is shown on Attachment 8.4. Vent the EES section to atmosphere by first opening FV-2205 (FV-2206) if not previouly
-6).
opened, and open TV-2227-1 thru -6 (TV-2228-1 thru Dump the loop inventory to the steam / water dump tank by opening HV-2217 (HV-2216). Close the dump valve when equalibrium pressure of approximately 196 psia is attained (in approximately one minute). Then open HV-22821 (HV-22822) in the EES loop used for cooling for final depressurization to atmosphere. Monitor pressure gauges in the venting flow path to verify that the entire flow path has been vented. If 4
the flow path can not be vented due to valve f ailure, either the failed valve should be manually opened, or the next available flow path option should be vented. To open a failed dump valve or the other dump valve in the loop,-
manually close the associated relay (i.e., CR-2215 for HV-2215 typical). To access the relays, remove the ventila-tion grill from the back of I-10, bay 800.
- 8. Close HV-4520 and V-45201 to isolate the portions of the fire water system not in the cooling flow path.
9.
Fill the piping between HV-4518 and HV-4519 by opening HV-4518. The fire water storage tank should be used to fill the piping. Close valve V-45945 when piping is filled.
- 10. Start one fire water pump.
- 11. Start the second fire water pump. This will increase the cooling water flow rate, although the flow rate with one pump operating is adequate.
- 12. Open HV-4519.
i 13. Fire water flow to the steam generator must be initiated
' within sixty-nine (69) minutes after loss of forced circula-tion by opening the emergency condensate isolation valve
[HV-2237 (HV-2238)} or the emergency feedwater isolation valve [HV-2203 (HV-2204)].
14.
l Install TI-22823 (TI-22824) in TW-22823 (TW-22824) after steaming has stopped at the main steam vent outlet. When t
the cooling water temperature leaving the steam generator is reduced to 165 F, as indicated on TI-22823 (TI-22824),
re-establish primary coolant flow. Establish flow to the pelton wheel using one emergency water booster pump. Slowly increase primary coolant flow, while maintaining 257 F at the EES outlet using the above temperature instrumentation .
Throttle the main steam vent [HV-22821 (HV-22822)] to maintain 64 psig at the EES outlet, as indicated on PI-22129-2 (PI-22130-2).
EE-EQ-0023 REV. A 15.
Verify adequate cooling water flow to the steam generator by monitoring appropriate
- 3. instrumentation identified in Table Flow rate af ter steaming has stopped is approximately 500,000 lb/hr (1000 GPM) ,
to the EES.
- 16. If forced circulation using fire water cooling can not be established, ated.
liner cooling using fire water must be initi-
. -..__,___---,r.. _-_-__ . _ ..- .._ . - - _ .
EE-EQ-0023 I REV. A PAGE 1 of 3 ATTACENENT 8.1 TABLE 1 VALVES CIASED BY SLRDIS AND ASSOCIATED RESET ACTIONS TAG ACTUATION RESET NO. LOOP DESCRIPTION RETHOD(1) ACTION SV-2105 1 CIRC 1A SPEED CONT LOOP 1 CT A&B SV-2106 2 (2)
CIRC 1C SPEED CONT LOOP 2 CT A&B (2)
SV-2111 1 CIRC 1B SPEED CONT LOOP 1 CT A&B SV-2112 2 (2)
CIRC ID SPEED CONT LOOP 2 CT A&B (2) .
SV-2109 1 CIRC 1A WATER TURB CONT LOOP 1 CT A&B SV-2110 2 (2)
CIRC IC WATER TURB CONT LOOP 2 CT A&B (2)
SV-2115 1 CIRC 1B WATER TURB CONT LOOP 1 CT A&B SV-2116 2 (2)
CIRC 1D WATER TURB CONT LOOP 2 CT A&B (2)
HV-2109-1 1 CIRC 1A WATER TURB SUP LOOP 1 CT A&B HV-2110-1 2 (2)
CIRC IC WATER TURB SUP LOOP 2 CT A&B (2)
HV-2115-1 1 CIRC IB WATER TURB SUP LOOP 1 CT A&B HV-2116-1 2 (2)
CIRC 1D WATER TURB SUP LOOP 2 CT A&B (2)
HV-2109-2 1 CIRC 1A WATER TURB DISCH HV-2110-2 2 LOOP 1 CT A&B (2)
CIRC 1C WATER TURB DISCH LOOP 2 CT A&B (2)
HV-2115-2 1 CIRC IB WATER TURB DISCH LOOP 1 CT A&B HV-2116-2 2 (2)
CIRC 1D WATER TURB DISCH LOOP 2 CT A&B (2)
HV-2201 1 FW INLET HV-2202 LOOP 1 XCR (2) 2 FW INLET LOOP 2 XCR (2)
FV-2205 1 FW CONTROL LOOP 1 XCR FV-2206 2 (2)
HV-2203 1 EMER FW INLET LOOP 1 XCR (2)
HV-2204 2 EMER FW INLET LOOP 2 XCR (2)
HV-2223 1 SHT STM STOP CHECK LOOP 1 CT A&B (2)
HV-2224 2 SBT STM STOP CHECK LOOP 2 CT A&B (2)
PV-2229 1 SHT STM BYPASS LOOP 1 XCR (3)
PV-2230 2 SHT STM BYPASS LOOP 2 XCR (4)
HV-2292 2 SBT STM STARTUP BYPASS LOOP 2 XCR (4)
HV-2293 1 SHT STM STARTUP BYPASS LOOP 1 XCR (3)
HV-2241 1 RHT STM BYPASS LOOP 1 XCR (3)
HV-2242 2 RHT STM BYPASS LOOP 2 XCR (4)
PV-2243 1 RHT STM BYP PRESS RATIO LOOP 1 XCR (3)
CONT PV-2244 2 RHT STM BYP PRESS RATIO LOOP 2 XCR (4)
CONT
EE-EQ-0023 REV. A PAGE 2 of 3 ATFACHNElff 8.1 TABLE 1 VALVES CLOSED BY SLRDIS AND ASSOCIATED RESET ACTIONS '
TAG NO.
ACTUATION RESET LOOP DESCRIPTION METHOD (1) ACTION HV-2249 1 CIRC 1A TURB TRIP LOOP 1 CT A&B HV-2250 (2) 2 CIRC 1C TURB TRIP LOOP 2 CT A&B (2)
HV-2251 1 CIRC IB TURB TRIP LOOP 1 CT A&B HV-2252 2 (2)
CIRC ID TURB TRIP LOOP 2 CT A&B (2)
HV-2253 1 RHT STOP-CHECK LOOP 1 XCR HV-2254 2 (3)
RHT STOP-CHECK LOOP 2 XCR (4)
PCV-5201 -
AUX STM TO 150 PSIG HDR LOOP 2 XCR PCV-5213 -
AUX STM TO PRH (6)
LOOP 1 XCR (5)
PCV-5214-1 -
CRH TO 150 PSIG HDR LOOP 1 XCR PCV-5214 (5)
CRH TO 150 PSIG HDR LOOP 1 XCR (5)
PCV-5214 CRH TO 150 PSIG HDR LOOP 2 XCR ~(6)
PCV-5305 -
150 PSIG HDR TO DA LOOP 2 XCR (6)
(1) XCR indicates valve is actuated through an XCR module in PPS. CT indicates valve is actuated through Circulator Trip Logic portion of PPS.
(2) Requires:
- a. Return of temperature rate of rise to below setpoint.
- b. Reset of microprocessor at monitor ing and control rack (I-93543 Logic A and B~) .
- c. Reset via existing methods to recover from circulator Trip (or other existing logic in PPS) .
(3) Requires
- a. Return of temperature rate of rise to below setpoint.
- b. Reset of microprocessor at monitoring and control rack (I-93543' Logic A and B).
- c. Reset of XCR's via HS-93375A and t
HS-93375B for Loop 1 valves on main control board (I-05).
EB-EQ-0023 REV. DRAFT PAGE 3 of 3 AfrACBMENT 8.1 TABLE 1 VALVES CIASED BY SLRDIS AND ASSOCIATED RESET ACTIONS (4) Requires:
- a. Return of temperature rate of rise to below setpoint. -
b.
Reset of microprocessor at monitoring and control rack (I-93543 Logic A and B).
- c. Reset of XCR's via HS-93376A and HS-93376B for Loop 2 valves on main control board (I-05).
(5) Requires:
- a. Return of temperature rate of rise to l below setpoint.
b.
Reset of microprocessor at monitoring and control rack (I-93543 Logic A and B).
- c. Reset of XCR's via HS-93377A and HS-93377B for Loop I common valves on l
main control board (I-06).
(6) Requires:
! a. Return of temperature rate of rise to below setpoint.
- b. Reset of microprocessor at monitoring and control rack (I-93543 Logic A and B).
- c. Reset of XCR's via RS-93378A and SS-93378B for Loop common valves on main control board (I-06).
l
EE-EQ-0023 REV. A ATFACHNEt_rr S.1 TABLE 2 EXISTING INSTRUNENTATION INTEGRITY ABE) TO BE USED FOR 111E VERIFICATION OF AVAILABILITY OF FIRE NATER FI4)N PATHS RES COOLING IAOP PI ISOIATION POINTS INSTEINGERFFATIOhi QUALIFIED PROCEDORE 1 22-1 HV-2237 PT-22129-1 Yes 1. Verify integrity of 22-2 to PV-2205 piping between PV-2205 and HV-2223
- 2. Slowly open FV-2205 while monitoring pressure using PI-22129-1 1 22-1 FV-2205 to IIV-2223, PT-22129-1 Yes 1. Monitor PI-22129-1 22-2 PV-2229, PV-22129 PV-22153 2 22-6 HV-2238 PT-22130-1 Yes 1. Verify integrity of to FV-2206 piping between FV-2206 and liv-2224 using PI-22129-1
- 2. Slowly open FV-2206 while monitoring pressure using PI-22130-1 2 22-6 FV-2206 to HV-2224, PT-22130-1 Yes 1. Monitor PI-22130-1 22-7 PV-2230, PV-22130, PV-22154 Either 31-1 IIV-4519 to PI-31204 HV-2237, ilV-2238 N/A (*) For break in Turbine verify emergency con, densate line integrity using PI-31204.
- Mechanical Device
E3-BO-0023 4
REV. A ATTACBMENT S.1 TABIA 3 EXISTIMG IMSTRONEarTATION TO BE USED FOR THE DETERNIMATION OF COOLI_NG MATER CONDITIONS DURING FORCED COOLING FOLI4 WING A HELB HEAT EXCBAMGE SECTION PI MO. INSTRONEarr IIE)ICATOR NOMITORS EES Loop 1 22-2 N/A TI-22823 (New) EES Outlet Temp.
- 22-1 FT-2205 FR-2205 Plow 22-2 N/A PI-22129-2 (New) EES Outlet Pressure EES Loop 2 22-7 N/A TI-22824 ( New) EES Outlet Temp.
i 22-6 FT-2206 FR-2206 Plow 22-7 N/A PI-22130-2 (New) EES Outlet Pressure i
l l
l 1
1 t
EE-BQ-0023 REV. A i,
ATTACIDGDIT 8.2 f
SLRDIS RECOVERY FLON CHART SLRDIS ACTUATES l
1 f
{ BOTE i
PANEL PANEL PANELS I-93543 I-93544 ACTUATE, ALARMS ALARMS CLOSING SLRDIS VALVES 1f l f DETERMINE DETERMINE CAUSE OF CAUSE OF SINGLE PANEL SINGLE PANEL I I ALARM ALARM LOSS OF PORCED CIRCULATION BAS OCCURED
.i
.i I f i
REACTOR NO MANUAL
, TUREI SCRAM &
TRIP TRIP YES -
J I f IDENTIFY BUIIAING RB TE 1 f T
VERIFY FIRE METER VERIFY PIRE NATER FIANt PATE, PIPIEG FLON PATE, PIPING INTEGRITTs IIPFBGRITY; ACTUATE CMISE ACTUATE CICSED SLRDIS VALY M & SLRDIS VALVES &
RESET SLEDIS RESET SLRDIS PAKIL PANEL CCFf1503 05- CONTIEUR 05 SEY.tT 2 SEEET 2 Sheet 1 of 2
' EE-EQ-0023 ATTACHMENT 8.2 REV. A TYPICAL PLOW PATH FOR EITHER BUILDING BREAK LOCATION VENT SELECTED FLOW PATH TO ATESPEERE V
FILL FLOW PATH II ESTABLISH FLOW IN FIII WATER NO FLOW PATH YES II ESTABLISH FLOW TO CIBCULATOR NO IN LOOF USED FOR COOLING YES I f FORCED CIRCULATION ESMBLISHED If LINER COOLING Sheet 2 of 2
i FIRENATER I
INIJtT TO ATMOSPHERE 1 f W-2237 JL j(
j ((NV-2238) MDN TANK HV-22821 1 f
- HV-2215 (HV-22822)I k 1 f PV-22167 j (HV-2218)q f g HV-2217 j k(PV-22168)
HV-2201 TO f(HV-2216) HV-22819 2 Ik I k
'd (HV-2202) (HV-22820 HV-2293 l __
u2 v y p (HV-2292) i r, i m v, N EESl(2) fgl l
FV-2205 TV-2227-1 thru 6 HV-2223
- _ (Fv-2206) (TV-2220-1 thru 6) (BV-2224) i' THROTTLED l
[2. IV1* I CLOSED l l[3.] ) V PV-2229 .
I I HV-2203 30)
J k(HV-2204) 7' I 31204 !
PV-22129 I
(PV-22130)
- La vm i
' >zm
- 1. PI-22129-2 (PI-22130-2) (PV-221 ) 7
- 2. PI-22129-1 (PI-22130-1) g2 n
- 3. TI-22121-1 (TI-22122-1) 77 j #,a@
STATUS OF EES PLOW PATH E8 d w
( AFTER SLRDIS ACTUATION ,"
j FIGURE 1 w
i l
FIREWATER '
TO ATMOSPHERE
) sv-2237 O (sv-2238) mDw 93 ,g uv-22821 (W-22822) i nV-2215 y PV-22167
'(uV-221813 f 3 J k(PV-22168) sv-2201 TO j g f(BV-2217 II i
(av-2202) FR-2205 j ( BV-2216) (BV-22820 av-22819 (FR-2206) EV-2293 ..
> ", (sv-2292)
, M @ l(2) DNI FV-2205 TV-2227-1 thna 6 W-2223 j
(Fv-2206) (TV-2228-1 thru 6) (Ev-2224) l
- ~
m [ 1. I CLOSED i
- I I EV-2203 V (PV-2229 PV-2230)
E2
] j k(BV-2204) 7'
) l 3120 i
PV-27129 (PV-22130) ,,,
LJ
- v' ggm
>.A O>?
- 1. PI-22129-2 (PI-22130-2)
PV-22153 k$
- 2. PI-22129-1 (PI-22130-1) (PV-22154)
L2 $U
- 3. TI-22121-1 (TI-22122-1) 7' PIRE WATER PLOW PATil FOR RECOVERY FROM A HELB FIGURE 2 w,
t
/, k T T A4.H M 6 4 T (e Te 7-%70f.7 CALCULATION COVER SHEET PROTO-P0llER CORPORATION TITLE: PRESSURE DROP PROGRAM CALCULATION NO.: 82-09 FILE NO.: ~ 7511482 CALCULATED BY s. Tombesi S( DATE II-I7-84 i
CHECKED BY M.J. Fekete "f4 ATE 11-77-8 6
t CALC NQ pgg pagg PROTO POWER CORPORATION os.c,mron o,1g GROTON, CONNECTICUT c
- _ -SS M.J.P. 79114A?
CUENT PROJECT PSC PCV Fn SUBJECT PRESSURE DROP FROGRAM PURPOSE The purpose of this calculation is to update the description of a program developed to calculate pressure drops, first documented in Calculation 82-01, dated 9-11-1986. Since then improvements have been made to some parts of the program - most notably the subroutines that calculate two-phase flow pressure drops - as a result of extensive use and further review.
This document stands alone as a description of the program as it exists today.
OVERALL DESCRIPTION The program "PRDRNEW" is capable of calculating pressure drops with flow of (A) liquid water, (B) water / steam two-phase, (C) steam through:
1 - PIPES AND TUBES 2- VALVES 3- EXPANSIONS AND CONTRACTIONS The program also calculates available pressure at the beginning of a system when a supply pump is specified, and pressure rises due to boosting pumps in the middle of a system. It does so by interpolating l
in tables of head rise vs. flow through the pump, which are stored l within the program and are derived from pump performance curves.
The flowpath to be analyzed must be broken down into sections, each with consistent physical and geometric characteristics. These sections are then used to create an input file.
I cauc ~
82-09 **'2 or i n PROTO POWER CORPORATION Oaio.sarca care GROTON, CONNECTICUT A T 11 t7 or AEwEWED JOS NO M.J.F. 7511492 CUENT PROJECT PSC FMV Pn SUBJECT PRESSURE DROP PROGRAM Flow rate through the path and/or pressure available at the start of the path can be varied until the pressure at the exit is as required or maximum (choked) flow is detected.
The input file also contains pertinent data - such as temperature and/or quality - on the fluid flowing in the section. (See Appendix A for a more detailed description of the format of the input file.)
t
a catc ~o 82-09 AEw PAGe 3 n', 3 0 PROTO POWER CORPORATION on,curaa aire S.T. 11-17-86 GROTON, CONNECTICUT AE vit WED M,J,y, AB C 7511482 CUENT pgg PROJNV EQ SUBJECT PRESSURE DROP PROGRAM REFERENCES
- 1. Flow of Fluids, Crane Tech. Paper No. 410.
- 2. GADR-110, Gulf General Atomic Co. , 1971.
- 3. A. Beroles et al., Two-Phase Flow and Heat Transfer in the Power Process Industries, Hemisphere, 1981.
- 4. W.M. Rohsenhow & J.P. Hartnett, eds., Handbook of Heat Transfer, McGraw-Hill.
- 5. W.L. Owens, "Two Phase Pressure Gradient", International Developments in Heat Transfer, Part II, ASME, pp. 363-368, 1981.
- 6. L.S. Tang, Boiling Heat Transfer and Two-Phase Flow, Kreiger Publishing Co., New Yo r k , 1975.
- 7. Y. -Y. Hsu and R.W. Graham, Transport Processes in Boiling and Two Phase Systems, Hemisphere, 1976.
- 8. O.J. Mendler, A.S. Rathbun, N.E. Van Huff, and A. Weiss,
" Natural Circulation Tests with Water at 800 to 2000 psia l
under Nonboiling , Local Boiling and Bulk Boiling Conditions",
Journal of Heat Transfer, Vol. 83, pp. 261-273, 1961.
- 9. B.M.Coulte r , Jr . , Compressible Flow Manual, Fluid Research, 1984.
- 10. C.F. Gerald, Applied Numerical Analysis 2nd Ed. , Addison-Wesley, 1980.
l
e l
l cate so 82-09 REv PAGE 4 or30 PROTO POWER CORPORATION os,Guroa care S.T. 11-17-86 GROTON, CONNECTICUT JOB N A E vit
- 11. Handbook for Control Valve Sizing, Masoneilan Bulletin 0Z1000E.
- 12. J.M. Delhaye , et al . , Thermohyd raulics of Two-Phase Systems for Industrial Design and Nuclear Engineering, McGraw-Hill, 1981.
- 13. Hans Gartmann, Delaval Eng inee r ing Handbook, 3rd Ed . ,
McGraw-Hill, 1970.
- 14. Consolidated Safety, Relief & Safety Relief Valves, Concoli-dated Valve Co. Brochure 1967.
catc ~ REv 82-09 Fa" 5 'c 30 PROTO POWER CORPORATION oa,os ,ron o rg GROTON, CONNECTICUT S.T. 11-17-86 M.J.F. 7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM ASSUMPTIONS AND EQUATIONS 1A. Liquid Flow 'through Pipe dpt =
d Pfr + O Pel = Total Pressure Drop, psid [1A.1]
By Ref. 1, Egn. 3-14:
W1 dpp = 2.797
- 10'
- vg* K [1A.1.a]
where l Specific volume of saturated liquid, ft 3 /lbm vf =
K = Pipe Hydraulic Resistance 2 (see App. B)
W = Mass Flow Rate, lbm/hr d = Pipe I.D., inches I
Az d p,; = [1A.1.b]
v*
g 144 1
New symbols are explained as they occur, t
2 Including fittings and bends.
4 catc ~
82-09
" 6 or30 PROTO POWER CORPORATION oassarca care GROTON, CONNECTICUT R T- 1 -'7-"'
M.J.F. 7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM where dz = z2-zi = Elevation Change, ft.
NOTE: If the pressure at the end of a liquid pipe section is detected by the program to be lower than saturation pressure at the temperature of the flowing liquid, the program proceeds as follows:
The section in question is split at the point where the pressure is calculated to be equal to the saturation pressure.
Pressure drops in the rest of the section and all remaining sections are then calculated using the two-phase flow equations, as described below.
IB. Two-Phase Flow Through Pipe The flow is taken to be adiabatic, i.e. at a constant total enthalpy, whereas thermodynamic enthalpy is allowed to vary.
The Homogeneous Method is employed, for the following reasons:
- 1) It is the method used by the GA steam generator codes (Ref. 2, part II, p. 1.4).
- 2) It is the most appropriate for low pressure, relatively high velocity steam-water mixtures (Ref. 3, p. 120 and Ref. 4 p. 14-3).
- 3) It is readily adapted to use in a computer code, since it is not a graphical method.
4 c4m 82-09 l* l **" 7 or 3 0 PROTO POWER CORPORATION me rm cars S.T. 1 1 - 1 7 - R f; GROTON, CONNECTICUT M.J.F. 7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM
- 4) It is the most suitable for low void fraction (very low quality) bubbly flow, as occurs when thermodynamic pressure drops below saturation (Ref. 5).
The Homogeneous Method (Ref. 6) assumes that both phases are traveling at the same speed and at thermodynamic equilibrium, i.e.
as a homogeneous mixture. Therefore the specific volume of the mixture (vm) can be expressed as in Reference 7:
vm
- Vf + x* (vg - vg) [1B.1) where x = mass quality vg = specific volume of saturated vapor, ft 3 /lbm The pressure gradient with the homogeneous flow assumption is as l
given in Ref. 5:
I v f G m G 9 9
(dP/dl)g = + (dy,/dl) + (1/vm ) (dz/dl) [1B.2}
2Dgg ge gg where P = Pressure, psf 1 = Length along the pipe, ft.
Two-Phase Friction Factor (see App. B) f 9=
l
catc % "'"
82-09 !" 8 or 3 0 PROTO POWER CORPORATION os, curon oare GROTON, CONNECTICUT E T- 11-17-AA M.J.F. 7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM G = Mass Velocity, lbm/(sec-ft2)
W/3600
=
(1r/4 ) * ( d/12 )
D = Pipe I.D., ft = d/12 ge = Proportionality Constant = 32.2 lbm-ft/(lbf-sec*)
g = Acceleration of gravity = 32.2 f t/sec2 Integrating over a short pipe length 4 1 (= 6 z), and adjusting units, we get:
W* W Az d p,= Cg*dK *
- v m,,,, + 2
- Cg*
- dv,+- (1B.3]
d d. (vg
- 144) where dp = pe - pi = Pressure Drop, psid pi = Pressure at the start of d 1, psia Pe = Pressure at the end of d 1, psia Cp g= Conversion Factor = 2.797
- 10-7 lbf-hr-in2 /(1bm-ft 3)
OK = = Flow Resistance Coef ficient D
I catc e. PAGE 82-09 lNV 9 or30 PROTO POWER CORPORATION misurm care GROTON, CONNECTICUT S.T. 11-17-86 M.J.F. " 7511482 CLIENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM v m, avg * (Vm,i + Vm,e)/2 = Average Specific Volume, ft 3 /lbm dv m
- Vm,e - Vm,i = Specific Volume Change, ft 3 /lbm
,/' ,
, dz = ze - zi = Elevation Change, ft.
. '/
.m- ./ -
~
~
Furthermore, by the 1st law of thermodynamics for adiabatic flow, with no work being done:
~. -
2 V;2. g V.
e g h; + + zj =
he+ + z. [18.4) 2Jg. Jge 2Jgc Jgg where h = Specific Enthalpy of Mixture, Btu /lbm e-> 4 W/3600 i
V=
- v,= Velocity, ft/sec.
l l
(7/4)(d/12)*
J = Unit Conversion = 778.2 ft-lbf/ Btu.
Noting that, by the assumption of homogeneous flow:
hm = hg + x (hg - hg) = h l
vm " Vf + X (Vg - Vf) = V
cate w "
82-09 l "" ' 10 cw 30 PROTO POWER CORPORATION c,ucisaron oare GROTON, CONNECTICUT S T- 11-17-86 M.J.F. " 7511482 CLIENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM letting 2.
(W/3600) 1 B= *
[( 7/4)(d/12)*] 2Jge, Je = g/Jgc and rearranging for xe, we have:
h;- he+J*e (z;- ze) +B* (vg -ve) xe= (1B.5]
(h g , - hf,e)
NOTE: hg,e and hg,e are functions of pe ONLY; v e is a function of pe AND xe For sections of pipe with no heat transfer, the program performs a stepwise integration 3 of Egn. [1B.2] by solv ing Eqns. (1B.3]
& [1B.5] simultaneously and iteratively until convergence , since the two equations are implic it in pe and x e.
If there is heat transfer, quality changes due to heating are more sig n if icant than those due to pressure change; therefore, the quality is taken as varying linearly f rom the beg inning of
! the section to the end, and Egn. [1B.3) is used by itself.
3 As suggested by Ref. 8 l
cAtc w 82-09
- ' ' " 11 or 30 PROTO POWER CORPORATION m o.wron oart GROTON, CONNECTICUT S.T. 11-17-86 M.J.F. 7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM Each section is divided into 10 subsections, so that O K = K/10 and Oz = EL/10 (see App. B for the definition of EL) .
NOTE: Although the number of subsections can be changed, dividing by 10 produces good results without slowing down processing speed too much.
IC. Steam Flow 'through Pipe 4 (i) ADIABATIC The Mach number at the beginning of a pipe section is calculated by means of the following equation 5:
(k-1) in M [1 + M#)"* = .2245 * *
(RT t /k) " [1C.1]
z 2 dp g 4
All equations and the nomenclature for this section and Sect. 3C are from Ref. 9.
5 Compressibility ef fects can be ignored at low pressures, i.e.,
if Pr ("P/ P. ) < 0.1 (p < 321 psia for steam). Thus Z2 1 in PV = ZRT.
cate w 82-09
"" 12 & 30 PROTO POWER CORPORATION mc.mron oate GROTON, CONNECTICUT Ai 11-17-AA M.J.F. 7511482 CLIENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM where:
M = Mach Number k = Isentropic Exponent = 1.3 for steam m = W/3600 = Mass Flow Rate, lbm/sec ps = Static ( i .e . The rmodynamic ) Pressure, psia R = Specific Gas Constant = 85. 76 lbf-ft for steam lbm *R Tt = Total (i.e . Stagnation) Temperature 6, *R The equation being implicit in M, it is solved recursively by the
" Method of Iteration" (Ref. 10).
For the first section only, M can also be found, if the user inputs the total pressure, by:
Ir+ 1
- M* [1 +
- M* ] 230 = .2245 O * (RTt /k) [1C.2]
2 d *pf where pg = Total (i.e. Stagnation) Pressure, psia 6
Input by means of the INPUT FILE (see App. B).
cAtc ~ 82-09 AEv PAGE 13 30 or PROTO POWER CORPORATION on,Gurca caTE GROTON, CONNECTICUT S.T. 11-17-86 REviE*E M.J.F. see w 7 511482 CUENT PSC i bV EQ SUBJECT PRESSURE DROP PROGRAM Then Ps p = ( 1C. 2.a ]
3
"'I
[1+ M1]
2 M2 is related to M 1 by the Fanno Eqns., valid for ad iabat ic flow 7-1 1 k+1 M,*[2+(k-1)Mf]
K= -
+
- In (1C.3]
k M,1 kM2 ' 2k Mg *[2+(k-1)M1]
with the pressure drop given by:
62 Mg ( 2 + ( k-1 ) M,1] L
= * (1C.4) g, Mg ( 2 + ( k- 1 ) M[] 1 Again, the " Method of Iteration" is employed to calculate M2-7 Subscript I refers to the beginning of a section and subscript 2 to the end.
cate w 82-09 " 14 or 30 PROTO POWER CORPORATION onomion care GROTON, CONNECTICUT S T- 11-17-A6 M.J.F. 7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM NOTE: If at any point the Mach Number is calculated to exceed 1, execution is interrupted and an appropriate message is printed. On the other hand, if M = 1 at a point, then the flow is potentially choked at that point. See Ref.3 ,
- p. 6-10, Problem 11.
(ii) NON-ADIABATIC When steam is being superheated, the following assumptions are made:
- 1. The flow is at low Mach No.; therefore non-heat-related compressibility ef fects can be ignored 8,
- 2. Specific volume of the steam is a simple (ideal gas) function of temperature - which is assumed to increase linearly between the value at the start and that at the end of a section - and pressure.
Thus, from Eq. [1B.3):
w* w* Az l
A p = Cg* K * * ( + 2
- Cg* *
(v,g - v,;)
s +
[1C.5]
d4 d4 14 4
- V, 8
The Mach Number is printed by the program, and the applicabil-ity of this assumption should be verified for each use.
cate w
-' l=v l pace 15 & 30 PROTO POWER CORPORATION m,oi.1 , care GROTON, CONNECTICUT S T. 11-17_u M.J.F. 7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM where R, (T;+ 459.7) v,,; =
- ft 3 /lbm 144 p; R, (Te + 459.7) v, g =
- ft 3 /lbm 144 pg v, =
( v ,,; +v ge )/2 ft 3 /lbm R, = Steam Gas Constant = 85.76 lbf-ft/(lbm *R)
Since the equation is implicit in pe, it is solved by iteration until convergence. As is done for two-phase flow, each section is divided into 10 subsections (see p.11).
2A. Liquid Flow Through valves 9 W*
dp = *
(1/Gf) [2A.1]
l s.
(500*Cy) 1 1
9 Equations (and Nomenclature) for valve pressure drops are from Reference 11; they are consistent with standard ISA Equations (see Ref. 11, p. 36).
l
CALC NO REW PAGE 16 & m PROTO POWER CORPORATION oniamron o ,rt GROTON, CONNECTICUT 4 T- 11 1,_oc M.J.F. 7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM where Cy = Valve Flow Coefficient (see App.B)
Gg = Specific Gravity at Flowing Temperature
- = (1/vf) = 1 @ 60*F 62.4 W is compared to Wcr, the critical flow rate:
Ww= 500
- C y
- Cp *
(Gg
- O p,) [2A.2) where Cp = Valve Critical Flow Factor 0 (see App. B) 1 also Pv' d p3 = p, - (0.96 - 0'.28 ) *p y (2A.3]
where p1 = Upstream Pressure, psia py = Vapor Pressure of vapor at flowing temperature, psia pc = Critical Pressure = 3206 psia for steam 10 Cp = FL in ISA Nomenclature.
CALC W 82-09 *
!" 17 or 30 I PROTO POWER CORPORATION mowm oars l GROTON, CONNECTICUT S T- 11-17-R6 '
M.J.F. ,7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM The corresponding critical pressure drop is:
APg = C ,*
- dp 3 (2A.4]
If W > Wc r, the program prints an appropriate message at the end.
NOTE: When W > Wcr, the flow must be reduced or the upstream pressure increased until W = Wcr, which is the maximum or
" choked" flow. This applies also to two-phase and steam flows through valves.
I 2B. Two-Phase Flow 'through Valves WA OP =
- vmi [2B.1]
f (63.3
- Cy) l Op g =C,* (P,/2) [2B.2}
(1/v ,)
If C ,* O p, > dp
- then (62.4 *Gg)
Wy = 63.3
- C y *
( o p,,, / v , )'/2- [2B.3}
otherwise Wcr is given by Eq. [2A.2} and O per by Eq. [2A.4}
l 82-09 l " 18 or 30 PROTO POWER CORPORATION momrm art GROTON, CONNECTICUT S.T. 11-17-86
"" M.J.F.
7511482 CUENT pgC N YSV EQ SUBJECT PRESSURE DROP PROGRAM 2C. Steam Flow W rough valves The equation W (1 + 0.0007 Tsh) 2.1*[ d p(p,+ p2)]'
can be rearranged, after recognizing that d p = p,- p2:
[W * (1 + 0.0007 T g)]
1 pg= fp -
f [2C.2]
(2.1
- Cy) where p2 = Downstream Pressure, psia Tsh = Steam Superheat, *F
= Flowing Temperature minus Saturation Temperature at p1 The critical flow is given by:
1.83
- C p* p,* Cy wer = [2C.3]
(1 + 0.0007 T5h) and dp y = 0.5
- C p *p, [2C.4]
catc w PAGE 19 82-09 lNV 30 PROTO POWER CORPORATION mourm o4rt GROTON, CONNECTICUT S.T. 11-17-86
- * " M.J.F. *
- 7511482 CUENT PROJ pgg bV EQ SUBJECT PRESSURE DROP PROGRAM 3A. Liquid Flow hrough Expansions and Contractione Pressure losses are included by incorporating an appropriate K (flow resistance coefficient) into the K for adjacent sections.
(See App. B.)
3B. Two-Phase Flow M rough Expansions and Contractions (i) EXPANSION II (Ref. 12., p. 247):
Gfs(1-s) (1-x) Rx 144 Ap = -
M] [3B.1)
- + *
[
EL- 1_M gg (Always negative, and therefore a pressure regain.)
where W /3600 G, = = Mass Velocity Upstream,1bm/(sec-in')
Ai (d,)*
s=-= - = Area Ratio I
' 2.
Ag (d t) l 11 In the present version of the program, the pressure gain through a two-phase flow expansion is always set to zero, for conservatism.
1 i
l catc w REV PAGE 82-09 20 or 30 PROTO POWER CORPORATION 3 G uron 31, GROTON, CONNECTICUT ? T. 11-17-86 M.J.F. #
- 7511482 CLIENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM f,= 1/vg = Mass Density of Liquid, lbm/ft3 x = Mass Quality 1
0( = = Void Fraction (Ref. 4, p.14-2)
{g/fg * [(1-x)/xf1 f, = 1/v, = Ma s s Den s ity o f Va po r , lbm/ f t 3 (ii) CONTRACTION 12 (Ref. 12, p.250):
G* 144 dp= *
((1/Cc - 1) + 1 - 1/s*} *
[ 1 + x ( 16 /fc,.- 1)] *
---[3B.2) 2 9c c.
where W /3600
- G1 = = Mass Velocity Downstream, lbm/(sec-in2) i (Tr/4) *
(d g/12 )1 Ce =A c /Ag= Weisbach "Vera Contracta" Coefficient (Ref. 3, p . 142) 12 Also Ref. 3, p. 143.
82-09l*
- 21 or 30 PROTO POWER CORPORATION momrm an GROTON, CONNECTICUT S T- 11-17-a6 M.J.F. " 7511482 CUENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM NOTE: When flow is splitting or coming back together (only symmetric splitting is accommodated, i.e. , with equal flow in each branch), the effective area ratio is adjusted accordingly as follows:
If n pipes, each of diameter d t, are flowing into m pipes of diamecer d 2 , then A,
= (n/m) *
(d,/dz)
Ag and if A3>1 It is a contraction A2 Aj < 1 It is an expansion A2 3C. Steam Flow Through EXPANSIONS & CONTRACTIONS (i) EXPANSION 13 (Ref. 9, p. 4-5):
p,g A,M, 2 + (k-1)M,*
= *
[ ] V 2. (3C.1) p,3 AM 2 g 2 + (k-1)M 2 13 Adiabatic but not Isentropic l
O catc
- 82-09 aEv P** 22 y 30 PROTO POWER CORPORATION onioimron care GROTON, CONNECTICUT S.T. 11-17-86
"'** M.J.F. *
- 7511482 CUENT PROJ p
SUBJECT PRESSURE DROP PROGRAM with 2kC - [1 - 2 ( k+ 1 ) C*] '/S ~ '/2.
Mg = -
(3C.I.a]
- 2k*C -
(k-1) -
f where M n(1+(k-1)M*]'/S g- I C = [3C.1.b]
[1+kM,*+ (A 2 /A l -l)I NOTE: (p,g/p g ,) >1 typically 1
(ii) CONTRACTION I4 (Ref. 3, p. 4-6):
Ag M, 2 + (k-1) M ," _ k+t
-= *( ) 4(4-#) (3C.2)
A, Mt 2 + (k-1) M 2 l
which is solved for M2 by the Method of Iteration mentioned earlier. Then 1
' p** 2 + (k-1) M'*
.[ j * /(k-s) [3C.31 p,, 2 + (k-1) M* g NOTE: (pgg/p,,) < 1 typically l
14 Isentropic
82-09 l " 23 or 30 PROTO POWER CORPORATION ono mron un GROTON, CONNECTICUT S.T. 11-17-86
"" M.J.P. *
- 7511482 CUENT PSC SUBJECT PRESSURE DROP PROGRAM APPENDIX A This appendix describes the entries of a typical INPUT FILE.
SECTION : Consecutive Number and Point-to-Point Description of Each Section.
ID : Pipe inside diameter (in),
WDIV : Div id e r to split the total flow symmetrically. For example, if WDIV = 6, then 1/6 of the total flow goes through section.
K(FIX) : Geometric part of total resistance coefficient (K).
Independent of the Friction Factor.
K(VAR) : To be multiplied by the Friction Factor and added to K(FIX).
EPS : Absolute Roughness of pipe (ft). Used to calculate the Friction Factor. .
EL : Elevation change of section (ft) .
NOTE: Positive is UP.
FL : Type of flow -
- 1. Liquid in Pipe
- 2. Boiling in Pipe
- 3. Two-Phase in Pipe
- 4. Superheating in Pipe
i catc w 82-09 REv 30 l PAGE 2 4 muron pre !
PROTO POWER CORPORATION S.T. 11-17-86 '
GROTON, CONNECTICUT aEvutD M.J.F. Jos e 75114 82 CUENT PSC PROJgV EQ SUBJECT PRESSURE DROP PROGRAM
- 5. Steam in Pipe
- 6. Liquid through Valve
- 7. Two-Phase through Valve
- 8. Steam through Valve
- 9. Boosting Pump g : Flowing Temperature (*F)
MIN : if FL = 1 : Not used
= 2 : Quality at start of section
= 3 : Starting quality for first section; not used with subsequent sections
= 4 : Temperature at start of
' section l
i
= 5 : Not used
= 6,7,8 : Cy of Valve
= 9 : Type of Pump 15 15 1 = Fire Water Pump 2 = 12-1/2 % Condensate Pump 3 = IACM Pump 4 = Pelton Wheel Booster Pump
catc N "'*
82-09 '" 2 5 es 30 PROTO POWER CORPORATION ono w on care GROTON, CONNECTICUT R T- 11-17-a#
M.J.F. 7511482 CLIENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM MAX : if FL = 1,3,5,9 : Not used
= 2 : Quality at end of section
= 4 : Temperature at end of section
= 6,7,8 : Cp of Valve
I
)
catc
- 82-09 REW PAC,E 2 6 y 30 PROTO POWER CORPORATION oR,curoR oarE GROTON, CONNECTICUT S.T. 11-17-86 REviEWEo M.J.F. ** 7511482 CUENT pg PROJ fy gQ SUBJECT PRESSURE DROP PROGRAM APPENDIX B This appendix describes how the physical parameters describing the sections are arrived at.
- 1. Hydraulic Resistance K a) Pipe Runs 16:
L*f K=
d/12 where f= Friction f' actor L= Pipe Length, ft.
The friction factor is a function of Reynolds Number and pipe roughness.
l The Colebrook Equation is used (Ref. 13, p . 3-20):
1
= - 2
- log (6/3.7D) + [2.51/(Ref)}f 6
16 Input K(VAR) = L/(d/12) (see App. A)
[ _
catcNo 82-09 AEw PAGE 2 7 g, 30 PROTO POWER CORPORATION oac w on
11-17-86 GROTON, CONNECTICUT S*T*
REviE*EO M.J.F. Jos e 7 5114 82 PSC PROJgV EQ SUBJECT PRESSURE DROP PROGRAM where -
6 = Absolute Roughness, f t
= 0.00015 ft for steel pipe (Ref. I p. A-23)
D = d/12 = Pipe Inside Diameter, ft.
and, by Ref. 1, Eq. 3-3:
Re = 6.31
- W Y
where
/A= Absolute Viscosity, centipoise Viscosity is a strong function of temperature but a very weak one of pressure. Equations for viscosity of steam and of water have been derived as a function of temperature, by fitting a curve to the data in the table of Ref. 1, p. A-2.
For two-phase flow (Ref. 4, p. 14-3):
JA. = p for x < 0.7
=
(1-x)pL+x[G for x > 0.7 whe re " L" refers to water, "G" to steam and "tp" to two-phase.
The choice is made within the program based on the quality (x) at the start of a section; f tp is then calculated usingjotp-
ca.c % "
82-09 "'28 or 30 PROTO POWER CORPORATION oa.c,v ron onre ,
GROTON, CONNECTICUT R1 11-17 *'
M.J.F. 7511482 CLIENT PROJECT PSC FSV EO SUBJECT PRESSURE DROP PROGRAM b) Fittings , Bends and Non-Control Valves :
(Ref. 1, pp. A A-29,is used as a guide.)
K values for these components are geometry dependent, rather than flow dependent. Therefore, they are written in terms of fT, the friction factor at full turbulence.
The following are representative values for butt-welded fittings, based on Ref. 1:
90 Elbow / Bend =
14 fT 45 Elbow / Bend =
7fT TEE - Through Flow = 0 (Side branch not flowing)
TEE - Branch Flow = 30 fT (Through branch not flowing)
TEE - Branch or Through = 20 fT (other branch also flowing)
TEE - Converging =
60 fT l
75 fT j Gate Valves =
8fT l
l Globe Valves =
340 fT Existing data sheets or Manufacturer's information is used to calculate equivalent K's whenever possible.
The sum of all non-flow dependent K's for a section appears in the INPUT FILE as K(FIX) (see App. A, p. 23).
t cate " AEV 82-09 PAGE 29 os 30 PROTO POWER CORPORATION on.ouro. o,7, GROTON, CONNECTICUT S.T. 11-17-86
"'*'*' ra w M.J.F. 7511482 CUENT %
pgC SV EQ SUBJECT PRESSURE DROP PROGRAM
- 2. C, and C, of Control.and Relief Valves Examples of Derivation:
a) PV-22167: Electromatic Relief Valve (Consolidated Model 1538VX)
Since this valve is de s ig ned to relieve steam there is no published Cy. The manufacturer, when contacted, has advised that the following equation has been derived f rom test data:
Q =
3 8
- 0. 7
- A *(op/Gg)"'
where Q = Flow rate, GPM A = Flow Area within Valve
= 2.581 in.2 for #1538 VX Gg = Specific gravity at flowing temperature By comparison with Eq. 3-16 of Ref. 1, it can be seen that Cy = 38
- 0.7
- A
= 68.7 l Using equation (2A.2] on p. 16 for critical flow with the data in the table on p. 73 of Ref. 14 (100% capacity):
i Cp = 0.96 for this valve
t cA. c
- 30 82-09 lAEV P AGE 3 0 o, PROTO POWER CORPORATION @GiNATOR CATE GROTON, CONNECTICUT S.T. 11-17-86 "E*E*ED M.J.F. sce
- 7 5114 82 CtJENT pg PROJgV EQ SUBJECT PRESSURE DROP PROGRAM b) PV-2229:
Masoneilan Mod. 57-20721-AB, 6" Globe, Cy = 245 By Table I of Ref. 11, p. 7:
Cp = 0. 9 (Flow to Open)
= 0.85 (Flow to Close)
. . - . _ . - - - . - - - . . . . _ _ _ _ _ . _ . = . _ , - _ _ _ - , . _ . - _ . - - _ _ _ . . , - - - . . _ _ . - _ - - _ - _ _ - -
_ - ...___ _. - - _ - .