ML20082Q743
| ML20082Q743 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/01/1982 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20082Q736 | List: |
| References | |
| 5500B:1, FR-C.1, NUDOCS 8312120323 | |
| Download: ML20082Q743 (54) | |
Text
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%, , , , , s am., i i.w.... o I RESPONSE TO INADEQUATE HP - Basic FR C.1
- CORE COOLING 1 Sept.,1982 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
-dH!!A4 If RWST level reaches !L) , align SIsystem for cold leg recirculation per ES-1.3, TRANSFER TO COLD LEG RECIRCULA TION FOLLOWING LOSS OF REACTOR COOLANT.
I 1 Check Accommistor Isoistion Valve
$tstus:
- a. Power available to isolation volve a. Restore power to isolation volves.
- b. Isolation volves - OPEN b. Open isolation volve.
2 Check RCP Support Condition;:
- a. Conditions available for running a. Try to establish conditions an RCP - [ Enter plant specific list] for running an RCP.
l 3 Reestablish High Pressure 51 Flow l To RCS:
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- c. Charging /S! pump breaker a. Try to start pumps. -
indicator lights - LIT
.b. High-head Si pump breaker b. Try to start pumps.
lights - LIT
- c. Si vc!ves - PROPER EMERGENCY c. Manually open or close valves AllGNMENT - [ Enter plant specific as appropriate.
list]
- d. Try to start - [ Enter plant specific list]
f 1
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(1) Enter plant specific value corresponding to R WSTswitchover alarm, in plant specific units.
8312120323 831109 t of 7 PDR ADOCK 05000423 A PDR
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- 5 e ' " *' n ..< o t RESPONSE TO INADEQUATE FR-C.1 HP Basic CORE COOLING (Cont.) 1 Sept.,1982 STEP ACTION / EXPECTED RESPONSE - RESPONSE NOT OBTAINED -
Kf!ALC Alternate water sourcesfor AFWpumps will be
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necessary if CST levelis low.
4 Geek Steam Generster Levels:
( o. Narrow range level - GREATER c. E less than 3 %, THEN maintain THAN $ % full AFW flow until ncrrow range levelis greater than & %.
- b. Throttle AFW flow to maintcin narrow range level at pL %
5 Check Low head 51 Pump Status:
- a. Low-head 51 pump breaker a. Manually ste-t pumps.
Indicator lights - LIT
- b. 51 valves - PROPER EMERGENCY b. Manually open er close volves AllGNMENT - (Enter plant as appropriate.
i specific list)
Low-head pumps should not be run longer than 2 without CCW.
6 ! Check Core Exit TCs:
- a. Temperature - LESS THAN 1200*F o. E greater than 1200'F, THEN go to step 10.
7 Check Containment Conditions:
- a. Containment pressure - NORMAL o. IF high, THEN go to step 8. ,
I b. Containment radiation - NORMAL b. E high, THEN go to step 8.
- c. Containment recirculation sump c. IF high, THEN go to step 8.
' level - NORMAL d.E all containment conditions normal, THEN go to E-0, REACTOR TRIP OR
(- SAFETY INJECTION, STEP 18 (1) Enter plant spec $c value showing leveljust in narrow range including allowanns for normal channel accuracy, past accident transmitter errors and reference leg process errors.
. (2) Enter plant sperfe value corresponduty to no-lood steam generator levelincludsng allowancesfor post-ocesdent transmater errors and reference leg process errors.
(3) Enter plant spec $e time.
2 of 7 l l
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Nu-L.- *
, c... / Tit 6et FR'C 1
( RESPONSE 70 INADEQUATE 0-CORE COOLING (Cont.) HP Basic
- 1 Sept.,1982 1
7 { STEP
( - fi ACTION / EXPECTED RESPONSE L
[ RESPONSE NOT OBTAINED 8 _
Check RVLIS Narrow Range Indication:
- a. RVLIS ncrrow range - LESS THAN m g a. E greater than m , _THE go to E-1, LOSS OF REACTOR COOLANT,
, STEP 1.
9 Check Core Exit TCs:
- a. Temperature - GREATER THAN 700*F
- o. E less than 700'F, TH_Eji go to E-1, LOSS OF REACTOR COOLANT, STEP 1.
NOTE sample Continue in step 10. with this guideline while n obtaining hydroge 10 Check Containment Hydrogen i Concentration:
- c. Dispatch plant ch,emist to obtain hydrogen sample
- b. Hydrogen concentration - LESS .
THAN 4% IN DRY AIR b. Consult TSC for further recover,/
! octions.
NCTE Steps 11 through 21 provide instructionsfor depressuration.depressuring RCS using steam generator secon _
11 8
Check Accumulator Statva:
i c. Accumulator isolation volve - OPEN
- o. E cccumulators have been previously isolated, E_EN go to step 17.
- b. Accumulator gas - HAS NOT BEEN VENTED i b.1 accumulators have been #
! previously vented, or are being vented, M go to step 16.
1 I
nn (U Enterplant spectfic value which L 3H f t ee above bottom of activtfuelin core with zero voidfractson pl I-
, ut uncertainties, 3 of 7 __
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" 5 ""*' i .., o. j RESPONSE TO INADEQUATE ' HP Basic FR-C.1 CORE COOLING (Cont.) 1 Sept.,1982
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STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -
12 Check RCS Yent Paths
- a. Power available to PORV block valves a. Restore power to block valves.
_ . _ . . _ _ _ . close its block valve.
- c. Block volves - OPEN c. Open block valve unless it was closed to isolate a faulty PORV.
13 Rapidly Decrease Steam Generator Pressure To _$ Psig:
- a. Dump steam to condenser a. Dump steam with steam generator
- 1) [ Enter plant specific steps] PORVs.
E steam generator pressure cannot
~be 'dtcrc:ased to 9 psig, THEN go to step 22. OBSER VE NOTES ,
PRIOR TO STEP 22.
14 Check RCS Hot Leg Temperatures:
_ a. A't lecst two temperatures - c.f NOT less than 400'F, THEN go LESS THAN 400*F to step 22. OBSER VE NOTES PRIOR TO STEP 22.
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15 Stop All RCPs.
16 isolete All. Aceumulators:
l a. Close all accumulator isolation a. For any accumulator that con
, valv.es not be isolated, vent accumulator gas to less than 9 psig. Do not proceed to st p 17 until the venting is completed. Continue to monitor core exit TCs.E temperature exceeds 1200'F, THEN go to step
- 22. OBSER VE NOTES PRIOR TO STEP 22.
(1) Enter plant spectfw value which is 200 psis plus instrument uncertaintus.
(2) Refer to background document.
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RESPONSE TO INADEQUATE FR C.1 M BaAic CORE COOLING (Cont.) 1 Sept.,1982 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED t
17 Rapidly Decrease Steam Generator Pressure To Atmospheric Pressure:
- a. Dump steam to condenser a. Dump steam with steam (Enter plant specific steps) generator PORVs.
18 Verify Low. heed 51 Flow:
- a. [ Enter plant specific steps) a. Manually start pumps and align valves as appropriate.
19 Check RCP Status:
20 Check Core Cooling:
- b. RVLIS narrow range indication - b. Do not proceed until RVLIS narrow GREATER THAN $ range greater than !11 21 Go To E.1, LOSS OF REACTOR COOLANT, STEP 13.
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(1) Enter plant specWe value which is top of core plus instrument uncertaussses.
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g, RESPONSE TO INADEQUATE
) HP Basic
( CORE COOLING (Cont.) 1 Sept.,1982 STEP ACTION / EXPECTED RESPONSE
- RESPONSE NOT OBTAINED -
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NOTE e steps 22 through 31 provide a methodfor depressuri:.ing the RCS in the event secondary depressuri:ation is not effective.
e If the capabilityfor dumping steam is restored
( while performing steps 22 through 31t then, return to step 11.
e Normal conditions are desired but not requiredfor starting RCPs.
22 Check Core Exit TCs:
IF_ ccre exit TCs greater than 1200*F and all available RCPs running, THEN open all pressurizer PORVs and block valves.
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1200*F and all pressurizer PORVs and block valves are open, THEN open all other RCS vent paths to e
containment.
23 Initiate Depressurization Of Steam Generators To Atmospheric Pressure:
(Enter plant specific steps]
s 24 Check Steam Generator Levels:
- a. Narrow range level - GREATER a. IF less than /11 %; THEN maintain THAN !!! % full AFW flow until narrow range levelis greater than $ %.
- b. Throttle AFW flow to maintain narrow range level at E %
(1) Enterplant spectfic value showing leveljust un narrow range including allowancesfor normal channel accuracy, past-amdent transmstrer errors and reference leg process errves.
(2) Enter plant speczfic value corresponding to no-load steam generator levelincludsnt allowancesfor post-acendent transmitter errors and reference leg proms errors.
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- i RESPONSE TO INADEQUATE PR C*1 HP Bas.ic CORE COOLING (Cont.) 1 Sept.,1982 2
l
- - STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -
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25 Verify Low hood 51 Flow:
- a. [ Enter plant specific steps) a. Manually stort pumps and align volves as op;,ropriate. Do not proceed until at least intermittent
! I low-head 51 f'ow is verified.
26 isolete All Accumuistors:
- a. Cicse oil occumulator isolation a. For any occumulator that con not volves be isolated, vent occumulator gas to less than H psig. Do not proceed until the venting is completed.
27 Check RCS Hot Leg Temperatures:
l c. At least two temperatures - a. f NOT less than 350*F, THEN I
LESS THAN 350*F do not proceed until at least two temperatures less than 350*F.
28 Stop All RCPs.
29 Verify Low. head Si Flow:
- a. [ Ester plant specific steps) a.1 continuous low-head 51 flow connot be verified, THEN return to step 22. OBSER VE NOTES PRIOR TO STEP 22.
30 Check Core Cooling:
i c. Core exit TCs - LESS THAN o. Do not proceed until core exit
! (- 400*F TCs less than 400*F.
- b. RVLIS narrow range indication - b. Do not proceed until RVLis narrow GREATER THAN 3 range greater than E.
31 Go To E 1, LOSS OF REACTOR COOLANT, STEP 13.
- END -
(1) Refer to background docwnent.
(2) Enter plant specific value which is top of core plus instrument uncertaustses.
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BACKGROUND INFORMATION FOR WESTINGHOUSE EMERGENCY RESPONSE GUIDELINES 1
FR-C.1 RESPONSE TO INADEQUATE CORE COOLING f Revision: HP-Basic-l September 1, 1982 i
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i FR-C.1 I
i 5500B:1
SECTION I - Introduction
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The purpose of this guideline is to restore adequate core cooling and to minimize possible core damaged. First, an attempt is made to provide high head safety injection. If this is successful, the operator is .
instructed to return to the emergency operating guidelines. If some source of high pressure water cannot be made available, the operator is instructed to reduce the primary system pressure by depressurizing the secondary. Initially, this will provide accumulator water for core recovery and later, low-head SI will be injected, to provide long tein core coolig. If the steps of this procedure are successful, the operator will return to the ERGS to complete the cooldown of the plant.
SECTION II - Symptoms This section describes the symptoms used to detemine the onset of inadequate core cooling. First, the most direct method of detemining inadequate core cooling is described. This method requires five core exit themocouples to be hotter than 1200 0F. The second and third methods of detemining the onset of inadequate core cooling use vessel
- level. These symptoms are referred to as anticipatory symptoms since they prgdict inadequate core cooling, prior to its occurrance.
Symptom 1 - Core Exit Themocouples greater than 1200 0F (FR-C.1)
This symptom alone, is sufficient to diagnose a condition of inadequate core cooling. For this symptom, five centrally located themocouples
( must have a temperature exceeding 12000F. This guideline assumes that the core exit themocouple temperature indications will be available to the operator. These themocouples should be located above the hottest regions of the core. The following criteria should be used to detemine i which themocouples to use.
FR-C.1 Page: 1 Rev: HP-Basic 5500B:1 _
1.
One thermocouple should be located as close as possible to the 3
geometric center of the cort.
2.
The other four thermocouples should be located one per quadr the highest power assemblies in each quadrant.
_ The outer two rows of assemblies should be excluded, since they can receive significa 5 cooling from steam generator drainage due to refluxing. The thermo-couples should be selected at each refueling to assure that the highest power assemblies are always being used.
i The hot leg RTDs cannot be solely used to determine a condition of inadequate core cooling.
cooling WCAPs(1,2) Analyses presented in the inadequate core
, show that the hot leg RTDs react too slowly to determine that the core is not being adequately cooled.
three reasons. This occurs for First, the steam entering the upper plenum mixes with water returning from the steam generator tubes.
passes into the hot legs. This cooler steam then Secondly, the water flowing through the hot legs could interfere with the RTD temperature measurements. Lastly, the RTDs at best would determine the average core exit temperature. The core exit themocouples would determine the local core exit temperature
- above the hottest regions of the core.
Therefore, the hot leg RTDs should not be used to detemine the onset of inadequate core cooling.
However, a high reading (greater than the normal operating temperature with the , reactor tripped, would be an indication that the operator
.should pay close attention to the core exit thermocouples.
Symptom 2 - Anticipatory Symptom on Vessel Level with RCPs Running (FR-C.2) i This symptom requires that two conditions exist with at least one reactor coolant pump running.
, These conditions are:
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i FR-C.1 Page: 2 5500B:1 Rev: HP-Basic
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- 1. The containment conditions must be abnomal. (This step is used to detemine if the RCS conditions are the result of a LOCA. If a LOCA has occurred the containment conditions would be abnomal, since considerable amounts of RCS inventory would be lost to the contain-
[ ment. Since this guideline is written assuming that a LOCA has occurred, its use for a non-LOCA transient would not be effective and may result in increased core damage.)
- 2. The narrow range vessel level must have a reading of just less than I
100 percent. (This is only applicable to plants having a Westing-house design Reactor Vessel Level Instrumentation System (RYLIS).)
Each plant should review its specific RYLIS design and modify the guidelines accordingly. A narrow range indicated level of 100 percent is equivalent to an average system void fraction of 50 percent, with all RCPs running.)
Under these conditions the core would be completely covered by a two-phase mixture at a pressure just above the secondary pressure. Thus, the themocouples would be reading saturation temperature and show no signs that i: tadequate core cooling could occur in a few minutes. The
- com wou.1d remain adequately cooled under these conditions as long as the pumps continued to run. However, if the pumps were trinped or if they fajled, the core could be totally uncovered in a matter of minutes.
Thus it is imperative that the operator proceed imediately to the inadequate core cooling guideline as soon as these conditions occur.
Symptom 3 - Anticipatory Symptom on Yessel Level with RCPs Stopped
( (FR-C.1)
. This symptom requires that three conditions exist with all reactor coolant pumps stopped.
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- l. The containment conditions must be abnomal. (This step is used to detemine if the RCS conditions are the result of a LOCA. If a LOCA
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i FR-C.1 Page: 3 Rev: HP-Basic 5500B:1
I has occurred th9 containment conditions '
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considerable amounts of the RCS inventory wwould be ab tainment.
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occurred, its use for a non-LOCA .
g that a LOCA hastransie and may result in increased corewould .
damage not be) effective
- 2.
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- The narrow 35 percent. range vessel level must have design Reactor Vessel Level Instrumentat aving Westinghouse plant should review its specific RVLIS desionEach lines accordingly.
System (RV 35 percent with all RCPs stopped is equiva level in the core of 3.5 feet plus uncert i ent to a collapsed i a nties.
sufficient, under nominal conditions This to result level is i level of at the midplane of the core, nassuming 2.5 feet.
a collapsed liquid resulting mixture w6uld just cover percent, thethe entiAs re core.)
3.
The 700 F. core exit themocouples must have readi (Tnis is to assure that the core hasngs greater than that the level gauge is not giving an e uncovered slowly and -
rroneous indication.)
Unless all of these conditions exist the inade'quate core cooling guidelines, the operator should not proceed the core can quickly become completely u However, under these co cooling c'ould occur in a matter of minutes.ncovered and inade exist, guideline.
cooling the operator should imediately proceed tThus, if these co o the inadequate core 1
An inadequate core cooling transient can .
t breaks and over various timeoccur frames for various sizes of
, The analyses presented, in the inadequate co, depending upon eq NON-UHI plant's"'
re cooling WCAPs for UHI and lost.
In addition, for the four inch break, assumed that hig
, the accumulators were FR-C.1 55008:1 Page: 4 Rey: HP-Basic
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assumed to be isolated. The possible transients that could result in this condition could never be totally described in any document due to the many possible combinations of break sizes and equipment failures that could occur. Therefore, this document will only describe the effects of the recovery actions on the RCS. These effects will be described in tems of instrument response. If further infomation is desired about the transients used to develop.the inadequate core cooling guidelines, the WCAPs contain all pertinent infomation. These reports i include infomation about the transients from the time the bmak opens until the core is completely recovered. This document addresses recovery from inadequate core cooling, rather than the possible transients that could lead to this condition.
Each. recovery technique will be discussed along with the expected instrument responses in the paragraphs below. The most important
. instruments in tems of this guideline, are the core exit themocouples and the vessel level gauge. The core exit themocouples are important because they quickly respond to core heat-up and cool-down. The vessel level gauge shows the amount of inventory remaining in the reactor vessel. The first recovery technique to be discussed is the high-head *
. SI recov~ery.
. If the high-head SI system was shut-off inadvertently or failed to start or the system wasn't aligned properly, the high-head SI system could result in imediate com recovery. If some other high-pressure source of water can be aligned quickly, this could also result in a fast recovery of the com. In this case water would be added to the cold
( legs and then flow to the downcomer. Since the core had just reached 1200 F, this water will soon quench and recover the core. The effects of this re'covery technique on system instruments will be discussed below.
( The core exit themocouples should initially show a slight increase in temperature as steam, in the hottest portions of the core, is forced past the themocouple by an advancing two-phase mixture. When the FR-C.1 Page: 5 Rev: HP-Basic 55008:1
two-phase mixture reachGs the themocouples they will cool rapidly. The vessel level will behave erratically until the core is completely covered by a two-phase mixture. Then, the level should increase slowly. However, it is possible that the high-head SI could condense a sufficient amount of steam to cause the accumulators to partially inject.
- If this occurs, the operator may see a very rapid incmase in I '
the level indication.
The second method of core recovery is secondary depressurization. As the secondary depressurizes, the steam in the steam generator tubes on
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the primary side is condensed. This results in a depressurization of the primary system. As the steam condenses in the tubes, the local prtssure drops. This causes more steam to be pulled into the tubes, where it is and condensed. This continues and the pressure in the upper plenum begins to drop. This, in turn, causes the fluid located in the lower plenum and the downcomer to be pulled into the core. When this occurs, the core is quenched. Later the primary pressure reaches the set-point pressure of the accumulators and they begin to inject and add water to the system. This will provide sufficient cooling until the pressure can be reduced below the shut-off head of the low-head safety
- injection system. .
In tems of instrument response, the operator should notice a rapid decrease in the core exit TCs. In addition the operator should notice a
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rapid rise in the vessel level. Both of these indications give strong evidence that the core has oeen recovered. The hot leg RTDs can also be used to determine if the cort has been cooled by the depressurization.
i The third method of recovery is to start reactor coolant pumps, in order '
to force the remaining fluid inventory through the core. The system can operate for a very long time under these condtions before problems would ari se. Even when the RCS contains only steam, the RCPs can keep the core cool indefinitely. Figure 1 presents a series of curves showing hot leg temperatures at various system pressures with all RCPs running 4
FR-C.1 Page: 6 Rev: HP-Basic r 5500B:1
s and the secondary at 1106 psig. This figure also shows the time required for the system to loose all of its liquid inventory for various break sizes. It is easy to see, that even for a four inch break, the core temperature will remain below 12000F unless the system pressure
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g drops below the low-head shut-off pressure of about 150 psig. In that case, low-head SI will inject prior to reaching 1200 0F. However, this method does not supply a permanent recovery since reactor coolant pumps cannot be run indefinitely at very low pmssures. For this reason the
, secondary pmssum must eventually be reduced in order to assum long '
tem core cooling.
This transient will look considerably different from the other recovery transients in tems of instrument response. The core exit themocouples should cool rapidly cool rapidly and then start to rise again very slowly. The vessel level indication should increase to a value less than full scale, and then start to decrease slowly as inventory is depleted. When the accumulators begin to inject, the additional water will only serve to slow the inventory loss. Thus the RCS will depres-surize more slowly and the instrument responses will slow.
The last reconnended method of recovery is the opening of pressurizer PORVs. , This step will only work in a very few cases. This is an attempt to increase the release from the RCS sufficiently to allow the RCS to depressurize. In most cases the PORVs will not remove a suffi-cient amount of steam to aid in the depressurization. However, opening the PORYs may allow the accumulators to inject momentarily. This may give the operator additional time to depressurize the secondaries and i provide long tem core cooling.
l The instruments in this case will respond similiarly to the secondary depressurization, only at a much slower rate. However, the core exit l
i temperature may increase significantly before the accumulators are able l to inject w'ter into the RCS. When this occurs, the core will quench and the RCS will repressurize, teminating accumulator injection. The l
l t
FR-C.l Page: 7 Rev: HP-Basic l 5500B:1
s core will again heat-up as the RCS depressurizes. This behavior will continue until the break and the PORVs can remove all of the decay heat being generated in the core, or until some other recovery method is sucessful.
In conclusion, the most direct approach is best, that is, restarting the high-head SI system or supplying the RCS with high-pressure injection from some other source. The second choice is to depressuize the second-ary in order to depressurize the primary and establish low-head safety injection. The third choice provides forced convection core cooling, using the remaining inventory, by starting the RCPs. The last method is to directly depressurize the primary by opening the PORVs. These last ,
two methods are only temporary measures for many break sizes and will not provide for long term cooling. In addition, the operator is only
. instructed to use these methods when the core exit TCs exceed 1200 F, since both of these methods increase system inventory losses and could result in worse conditions, if not activated at the proper time.
SECTION III - Description of Specific Guideline Steps, Notes & Cautions ,
Guideline FR-C.1 -
l Caution Preceding Step 1 This caution instructs the operator to align the SI system for cold leg recirculation, using guideline ECA-1 (The Transfer to Recirculation Guideline), when the Refueling Water Storage Tank (RWST) level reaches l the switchover alann. If the sprays are running and the RCS is fairly
_ empty, the RWST level may decrease rapidly when the system is 4
deprtssurized. However, if the spray pumps are not running and if the @
RCS is nearly full, the RWST level will decrease very slowly. Thus, the operator must carefully watch the RWST level and initiate switchover to cold leg recirculation, when the low level alars is reached.
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FR-C.1 Page: 8 Rev: HP-Basic 55008:1
l Step 1 g
This step instructs the operator to check the accumulator isolation valve status. .The valves should be open and operable. If power is not currently available to the accumulator isolation valves, power must be restored. If the isolation valves are closed the valves should be opened as soon as possible. However, the operator should proceed with subsequent steps of this guideline, while attempting to restore power or open valves.
t The accumulator isolation valves will be used in later steps of the guideline and they must be operable. In addition the accumulator water will be used in following steps in order to recover the reactor core. Thus, the isolation valves should be open.
Step 2 This step instructs the operator to check the RCP support conditions. The operator should verify that the support conditions are available to run the reactor coolant pumps. If these conditions -
are not available, the operator should attempt to establish them, while proceeding with subsequent steps of this guideline.
l It should be noted that the RCPs may not be needed in this guide-line. In addition, if the RCPs are requireo, they will be started even if all of the support conditions are not available. Thus, the operator should only attempt to establish minimum required systems l for operating the RCPs. Each plant should review it's specific l
equipment requirements and incorporate them into the guidelines.
Step 3 l
l This step instructs the operator to reestablish High Pressure SI flow to the RCS. If the makeup system is functioning correctly, the FR-C.1 Page: 9 Rey: HP-Basic 5500B:1
1 com wculd be inadequately cooled. Thus, this system should be checked to identify any malfunctions. First, the charging and high-head SI pumps should be checked to assure that they art operat-i ng. If they are stopped, they should be started. If the pumps are running, the operator should check for proper emergency valve align-ment. If the system is not aligned properly the operator should
. attempt to manually open and close valves to supply the RCS with water. If this cannot be accomplished immediately, the operator should proceed with subsequent steps while attempting to complete this step. ,
In addition, the operator is instructed to start alternate pumps which could possibly supply the RCS with high pressum water. One example of a high pressure pump would be a PD pump. Each plant should review its available equipment and enter a plant specific list into this step of the guidelines.
Caution Preceeding Step 4 This caution warns the operator that he may be required to find -
alternate sourres of Auxiliary Feed Water (AFW), if his Condensate Storage Tank (CST) level is low.
This is egtremely important, in this guideline, since the secondary will
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be used to recover the core. If AFW is lost, the steam generators will dry out and the RCS will repressurize. Since high-head SI is unavail-able, the. RCS will also dry out.
Step 4 This step instructs the operator to check the steam generator levels.
Since the secondary system will be used to recover the core, it is 1
important to maximize primary to secondary heat transfer. This is '
done by keeping the steam generator tubes covertd at all tioes.
I FR-C.1 Page: 10 Rev: HP-Basic 5500B:1
Therefore, the operator is instructed to maintain full AFW flow until a narrow range indication is obtained. Then, the AFW flow should be throttled to maintain no-load steam generator level. The operator should proceed with subsequent steps, of this guideline, while attempting to complete this step.
Step 5 This step instructs the operator to check the low-head SI pump status. Since the RCS will be depmssurized in the subsequent steps, the low-head SI pumps should be running. If they are stopped, they should be started. At the same time the operator should check to see that valves are in proper alignment for injec-tion. If this is not the case, valves should be manually opened and closed to provide RCS injection. The operator should proceed with subsequent steps while attempting to complete this step.
This guideline assumes that some low-head injection water can be i supplied to the RCS, If water cannot be delivered to the RCS and if 5
the RCS continues to loose inventory, it's obvious that significant -
core. damage will eventually occur.
CautioneAf ter Step 5 This caution warns the operator that the low-head SI pumps should not be run indefinitely without cooling. In some plants the low-head SI pumps can be run for only twenty minutes without cooling. In other plants
( these pumps can be run for days without cooling. Thus, a plant specific value of time should be entered in this caution. It is expected that the low-head SI pumps will be injecting before they would have to be stopped.
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FR-C.1 Page: 11 Rev: HP-Basic l 55008:1
s Steps 6 through 9 These steps check the symptoms of inadequate core cooling. If one of the preceeding steps has resulted in core recovery, the operator should return to step 18 of E-0 (The Reactor Trip or Safety Injection Guide-line) or step 1 of E-1 (The loss of Reactor Coolant Guideline). The I subsequent recovery steps of this guideline could cause severe damage to many major pieces of equipment including the RCPs and the reactor vessel. Thus, this guideline should not be used unless the core is in danger of severe damage. 3 Step 6 This step instructs the operator to check the core exit thermo-0 couples. If the core is still hot (1200 F) the operator is instructed to continue with step 10 of this guideline. However, if 0
the core is relatively cool (less than 1200 F) the operator should determine if one of the preceding steps has recovered the core.
This will be done in steps 7 through 9 of this guideline.
Step 7 This step instructs the operator to check the containment condi-i tions., If the containment conditions are normal, the previous steps have sufficiently cooled the core and the operator is instructed to return to step 18 of E-0 (The Reactor Trip or Safety Injection Guideline). If the containment conditions are abnormal, one of the anticipatory symptoms may have been used to send the operator to this guideline. Thus the operator should check to see if the anticipatory symptoms still exist. This will be done in steps 8 through 9 of this guideline.
+
FR-C.1 Page: 12 Rev: HP-Basic 55008:1
, , , , - , - ---74.-r - .,----~.,,-r ye,,
1 l
Step 8 l l
This step instructs the operator to check the narrow range vessel level. If the level is indicated to be gmater than 3.5 feet above
, the bottom of the active fuel plus uncertainties, the vessel has been refilled, to some extent, by one of the preceeding steps and the operator is instructed to return to step 1 of E-1 (The Loss of Reactor Coolant Guideline). If the level is still below 3.5 feet plus uncertainties, the operator is instructed to check the core exit thennocouples, to detemine if the fluid leaving the core is superheated.
Step 9 This step instructs the operator to check the com exit themo-couples to determine if the fluid leaving the core is superheated.
If the core exit themocouples are reading greater than 7000 F, the fluid leaving the com is superheated. If this is the case, the
- operator will continue with this guideline. If the core exit themocouples are reading less than 700 0F, tne core has been -
~
recovered and the operator is instructed to return to step 1 of E-1 (The Loss of Reactor Coolant Guideline).
Note Preceeding Step 10 This note tells the operator to continue with recovery actions while obtaining a ttydrogen sample from the containment. This may take a
! substantial amount of time and the hydrogen will continue to be produced until the core is cooled. Thus the operator should procede with following steps of the guideline to recover the com.
I I Step 10 This step instructs the operator to obtain a sample of hydrogen from the containment. When the zirconium fuel cladding reaches very high 1 I l
FR-C.1 Page: 13 Rev: HP-Basic i 55008:1
temperatures, it reacts with water and produces hydrogen. The hydrogen then travels through the RCS and is eventually released through the break. When the hydrogen level reaches a concentration of about 4% it becomes very explosive. If a spark would occur under these conditions the containment could possibly be " ruptured". When a sufficiently large leak path is opened the radioactive gases in
+
the containment would be released into the atmosphere. While this is very unlikely to occur, consideration must be given to the possible consequences of this event and therefore the plant TSC should be contacted to determine the appropriate actions. ;
Note Preceeding Step 11 This note points out that steps 11 through 21 provide instructions for depressurizing the RCS, by depressurizing secondary.
9 As the steam generator secondary sides depressurize, steam will be pulled into the tubes on the primary side and condensed. This will rapidly drop primary system pressure and the two-phase mixture in the lower plenum and downcomer will be pulled into the core. This will -
quench a large portion of the core, prior to accumulator injection. As the secondary continues to depressurize, the primary pressure will closely follow the secondary pressure. This is due to the extremely high heat, transfer associated with steam condensation. Thus, if the accumulators are available, a large amount of water will be added to the cort, as soon as, the secondary pressure drops below the accumulator setpoint.,
Step 11 -
This step instructs the operator to check the accumulator status.
If the ai:cumulators are ready to inject, the operator is instructed to continue in the guideline. If the accumulators have been /
isolated, tne operator is instructed to skip to step 17. If the FR-C.1 Page: 14 Rev: HP-Basic 55003:1
. s accumulator gas has been or is being vented, the operator is instructed to skip to step 16.
This is done for two reasons. First, the steps from 12 through 16 are intended to establish accumulator injection. If the accumu-lators can not inject, there is no reason to execute these steps.
Secondly, it is possible, that steps 12 though 16 may have been executed earlier and the operation was not successful. If this l occurs, the operator is sent to another portion of this guideline which may return the operator to this step. In that case, there is no mason to repeat steps 12 through 16, if the primary has '
previously depressurized to 200 psig.
It should be noted, that if the isolation valves are closed, the operator is instructed to proceed to step 17, but if the accumulator
- is vented, the operator is instructed to proceed to step 16.
Step 16 will assure that most of the nitrogen is vented from the accumulator, before allowing the operator to continue to step 20.
If the isolation valves are closed, the nitrogen doesn't have to be l vented. .
l -
Step 12 e
L .
l l This step instructs the operator to check the RCS vent paths. Since 1
the RCS is loosing inventory, the vent paths should be checked to determine if this loss can be isolated. First, the operator is instructed to assure that the PORY block valves can be operated.
( This is done to assum that a leaking PORY can be isolated. In i addition one of the subsequent recovery actions may call for the operator to open the PORVs in ortler to reduce the primary system pressure. Thus, the block valves may also have to be opened. The i mmaining portion of this step instructs the operator to isolate all l vent paths from the RCS.
FR-C.1 Page: 15 Rev: HP-Basic 55008:1
4 s
Step 13 This step instructs the operator to rapidly decrease steam generator pressure to 200 psig plus instrument uncertainties. The operator should use condenser steam dump, if available. If the condenser isn't available, the secondary PORYs should be used. If the !
secondary cannot be depressurized, the operator is instructed to go to step 22.
The operator should use either method to dump steam at a maximum rate. However, the steam should be dumped in a controlled manner so that the secondaries don't drop below the desired pressum of 200 psig plus instrument inaccuracies. The purpose of this step is to cause the accumulators to inject a maximum amount of water, without injecting any nitrogen. Thus, the RCS pressure must not drop below 200 psig.
If any of the steam generators are known to have significant leak- ~
age, and if the steam generators can be depressurized separately, only intact steam generators should be depressurized. If all steam -
generators have some leakage, the one which is believed to have the smallest leak, should be used for depressurization.
'e
. Step 14 This step instructs the operator to check the RCS hot leg tempera-ture. The hot leg temperature is used, in this step, to detennine the effectiveness of the secondary depressurization. If a tempera- .
ture .of 4000 F is indicated, on at least two RTDs, the core has been recovered and the RCS has been depressurized, l 1
The operator should check, at this point, to be sure that the ,
I
~
secondary pressure has been reduced properly. If the secondary isn't depressurized sufficiently, step 16 should be repeated. If FR-C.1 Page: 16 Rev: HP-Basic 55008:1
the secondary is depressurized, then the depressurization step did not recover the cort. This could be for either of two reasons.
First, the RCS may not have depressurized or secondly, the depres-surization may not have brought in a sufficient amount of accumu-lator water. In either case the operator is instructed to proceed i to step 25 of the guideline.
Step 16 should cause a large amount of accumulator water to be injected into the core. Thus, the hot legs should contain a two-phase mixture, at about the same pressure as the secondary. If the 0
hot leg temperature is still above 400 F, either the hot legs contain a saturated mixture at a higher pressure, or they contain superheated vapor.
If the RCS didn't depressurize, the primary to secondary heat transfer has been effected. This may be due to hydrogen in the primary side of steam generator tubes. ' Hydrogen would be formed during a reaction between the zirtonium fuel cladding and water, at high temperatures. With hydrogen in the steam generator tubes, the primary pressure will drop very slowly or it may start to rise. If -
the " primary pressure is dropping slowly, it is possible that the core will recover without further actions. However, if the RCS I pressure begins to rise, the operator will only be able to cool the core by starting the reactor coolant pumps. The pumps will forte the hydrogen to flow out of the steam generator tubes and re-establish primary to secondary heat transfer. This should cause
~t he primary system to depressurize and the accumulators to inject.
I If the RCS did depressurize when the secondary was depressurized, and the hot leg temperatures remained above 4000 F, then the accumulators didn't inject a sufficient amount of water to cool the core. If this happens, the operator may be able to isolate the accumulators and depressurize the RCS to obtain low-head SI water.
FR-C.1 Page: 17 Rev: HP-Basic 55008:1
In either of the two cases above, the operator will be instructed to proceed to step 22 of this guideline, so that he can start RCPs, if I necessary.
Two RTDs are used to detennine the success of the depressurization, to assure that one RTD is not giving an erroneous reading. )
Step 15 This step instructs the operator to stop the RCPs. This 10 done to )
prevent the pumps from being damaged by the next depressurization.
During the next depressurization the RCS pressure will drop well below the minimum pressure required for RCP operation. In addition, accumulator injection could possibly damage the pumps if slug flow l occurs.
( Step 16 This step instructs the operator to isolate all of the accumu- -
lators. The operator should attempt to close the accumulator isola-tion valves. If this cannot be done, the operator should attempt to vent the accumulator nitrogen to atmosperic pressure. The operator
_, . should not proceed with subsequent steps of this guideline until the accumulators have been isolated or vented. Each plant should deter-mine if the accumulator pressure measurement would be available. If it istnavailable, alternate means of detennining accumulator vent, should be incorporated in this guideline.
)
The operator is instructed to proceed to step 22, if the core exit 0
thennocouples exceed 1200 F while the accumulators are being vented.
l l
)
FR-C.l Page: 18 Rev: HP-Basic 55008:1 l
s
/
The accumulators should be vented to atmospheric pressure. This prevents nitrogen from being injected into the RCS. During the next step of this guideline, the secondary will be depressuMzed to
_ atmospheric pressure. The RCS will eventually refill and reach an equilibrium pressure where the low-head SI flew is equal to the flow through the break. However, the RCS pressure could approach atmospheric pressure befom it reaches equilibrium. Therefore, to -
eliminate the possibility of nitrogen injection, the 3ccumulators I
must be depressurized to atmospheric pressure.
This step is of extreme importance due to the nature of this transient. For large LOCAs, the accumulators inject nitrogen into the RCS, which is then released through the break with little consequence.
In small LOCAs with high-head SI, the RCS pressure never drops sufficiently for the nitrogen to be injected. The following steps of this guideline depressurize the RCS to the point where nitrogen i would be injected. Nitrogen injected into the RCS may accumulate in the steam generator tubes and greatly reduce primary to secondary -
heat- transfer. If this happens, the reactor coolant pumps must be started in order to re-establish heat transfer, and must continue to
_. runfuntil the nitrogen is removed through the break, the vessel head i vent, or the pressurizer PORVs. This could take a considerable amount of time. Thus, caution should re exercised to minimize the l
l possibility of injecting nitrogen into the RCS.
( Step 17 j' This step instructs the operator to depressurize the secondary to l atmospheric pressure. The operator should use condenser steam dump,
! if it's available. If not, he should use the secondary PORYs. The operator should dump steam at a maximum rate until the RCS is placed l on the Residual Heat Removal (RHR) system. When the RHR system is put into use, the secondary valves can be closed.
l FR-C.1 Page: 19 Rev: HP-Basic 5500B:1
s Step 18 This step instructs the operator to verify low-head SI flow. If low-head SI flow cannot be verified, tne operator is instructed to
_ manually start the low-head SI pumps and to align valves as appropriate to supply the RCS with water. I The low-head flow should be verified by either direct flow indica-tion or by the low-head SI pump discharge pressure being less than the shut-off head of the low-head SI pump. Each plant should evalu- l ate the preferred indication and define this in the guideline, along with the shut-off pressurt of the low-head SI pumps.
Initially, the low-head SI flow should L near rinnout, then the flow will reduce to match break flow. If the break is very small, the flow required to match break flow may be so small that the RCS pressure could approach the shut-off head of the low-head SI pumps.
If this occurs the low-head flow is verified.
Step 19 .
This step instructs the operator to check the RCP status. If the operator has followed this guideline without having to go to step
, 22, tHb pumps will be stopped and the operator can continue to step
- 20. However, if the operator had to go to step 22 during the execu-tion of these guidelines, the pumps may be running and, at this time they should be stopped.
If th,e RCS pressure increases above the shut-off pressure of the low-head SI pumps, after the RCPs are stopped, the core exit thermocouples should be monitored very closely.
FR-C.1 Page: 20 Rey: HP-Basic 5500B:1
Step.20 This step instructs the operator to check for adequate core
'~
- cooli ng. If the core exit thennocouples are reading less than 0
400 F and the reactor vessel narrow range level indication is greater than the top of the core plus instrument inaccuracies, the operator is instructed to go to step 14 of E-1 (The Loss of Reactor Coolant Guideline) in step 21. The operator must monitor these conditions until the criteria am met befom proceeding to step 21.
1 If the core temperature should rise above 12000 F, the operator is instructed to go to step 22 of this guideline.
The vessel level indication of the top of the core plus instrument inaccuracies assures that the core is completely covered, since the core is filled with a two-phase mixture. In addition core exit 0
thennocouples at 400 F, assure that there is little superheated steam in even the hottest regions of the core.
Step 21 -
This step instructs the operator to go step 14 of E-1 (The Loss of
~"
Reactor Coolant Guideline). This is done, when the core has been returned to a stable and cool condition.
First Note Preceeding Step 22
( This note points out that steps 22 through 31 provide instructions for using reactor coolant pumps to keep the reactor core cool, while attempting .to depressurize the secondary. The pumps should not be started unless the core is in danger of being damaged (core exit
, thennocouples mading greater than 12000 F).
FR-C.1 Page: 21 Rev: HP-Basic 55008:1
Running RCPs does provide very effective core cooling. Even with the entiri RCS containing only steam, the RCPs can keep the core well below '
12000 F. However, as more inventory is lost from the RCS, the pressure will drop below the value required to keep the pumps running. If this occurs the reactor coolant pump bearings and seals may be destroyed.
This will have two effects. First, the pumps will stop running and the i core temperature will increase rapidly. Secondly, due to the seals and bearings being destroyed, the leak path through the pump may increase sufficiently to allow the RCS to deprtssurize and low-head SI may begin to flow into the core.
Second Note Preceeding Step 22 This note infoms the operator that if the capability for dumping steam is restored, while perfoming steps 22 through 31 the operator should return to step 11.
Third Note Preceeding Step 22 This note informs the operator that nomally required conditions for -
starting a reactor coolant pump are not a necessity for this guideline.
Pumps may have to be started to save the core, under conditions where their lifq expectancy will be greatly reduced. The operator may have to bypass interlocks nomally used to protect the pump and he may have to start the pump at very low pressures < It should be clear that in this case, the. core may be damaged severely, if the RCPs are not started.
Step 22 This step instructs the operator to check the core exit themo-couples. If their temperature exceeds 12000 F, during the remain-ing steps of this guideline, the operator should return imediately to this step. The purpose of this step is to assure that the core temperature remains below 12000F. If the temperature rises above i
FR-C.1 Page: 22 Rev: HP-Basic 55008:1
s
, 1200 F, the operator is instructed to start an additional reactor coolant pump. If all of the available reactor coolant pumps am 0
running and the temperatum remains above 1200 F, the operator is
_ instructed to open all pmssurizer PORVs and block valves. If the temperature continues to rise, the operator is instructed to open
(
all other RCS vent paths to the containment. One example of an additional vent path is the vessel head vent. Other vent paths would be plant specific and should be included explicitly in the plant guidelines. If at this point the com temperature continues I
to rise, the operator should initiate containment spray, hydrogen mcombiners, and other systems associated with CLASS 9 events.
As was stated earlier, in the explanation of the first note to this step, the RCPs provide effective cooling of the mactor core. In order to illustrate this effectiveness, figure 1 shows the core exit temperature, as a function of time, for various system pressures, with the secondaries at 1106 psig and the RCS containing only steam. Thus, the pressurizer PORVs and other vent paths into the i containment, should only be needed if the RCPs cannot be run.
It should be noted that opening PORVs and other vent paths will only be effective in very few cases. This futher emphasizes the need to
_. staft RCPs, whether or not the nonnally requimd systems are available.
If'the operator has opened all vent paths from the RCS into the containment and has all of the available RCPs running and the core
( exit temperature continues to rise, the core will be damaged severely. This will msult in large quantities of hydrogen being released into the containment. Thus, the operator should start his containment sprays and prepare for a CLASS-9 event.
i FR-C.1 Page: 23 Rev: HP-Basic 55008:1
l s
Step 23
)
This step instructs the operator to depressurize the secondaries to atmospheric pressure. The operator should use condenser steam dump, if it's available. If not, he should use the secondary PORVs. The operator should dump steam at a maximum rate, until the RCS is )
placed on the Residual Heat Removal (RHR) system. When the RHR system is put into use, the secondary valves can be closed.
If neither condenser steam dump or secondary PORVs art available, I the operator should use any plant specific means of removing water or steam from the steam generators. These could include, opening the blowdown lines or allowing the steam driven AFW pump to run at its maximum rate.
At this point the secondary should be depressurized by arty means available. Since this could take a considerable amount of time, the operator should proceed with steps 24 through 31, while waiting for -
t!.e secondary to depressurize.
The secondary should not be depressurized too rapidly, until the accumulators have been isolated, to prevent nitrogen injection.
Step 24 ?
This step instructs'the operator to check the steam generator level s. Since the secondary system is'being used to recover the cort, it is important 'to maximize pr' mary to' secondary heat .
tran s.rer. This it done by keeping the steam generator tubes covered at all times. There fort, the operator is instructed to maintain full AFW* flow until a narrow range level indication is obtained.
Then, the AFW flow should be throttled to maintain no-lo2d steam I
generator level. The operator should proceed with subsequent steps while attempting to complete this step.
1 FR-C.1 Page: 24 Rey: HP-Basic 55008:1
t Step 25 This step instructs the operator to verify low-head SI flow. If a
low-head SI flow cannot be verified, the operator is instructed to
, manually start the low-head SI pumps and to align valves as appropriate to supply the RCS with water.
The low-head flow should be verified by either direct flow indica-tion or by the low-head SI pump discharge pressure being less than I
the shut-off head of the low-head SI pump. Each plant should evalu-ate the preferred indication and define this in the guideline, along with the shut-off pressure of the low-head SI pumps.
If the RCPs are running, and the secondary nasn't been fully depressurized, the low-head SI flow will just match break flow. If the break is very small, the flow required tn match break flow may be so small that the RCS pressure will approach the shut-off head of the low-head pumps. If this occurs, the low-head flow may be inter-mittant, however this is sufficient to verify low-head SI flow.
It 15 very important to verify low-head SI flow as soon as it occu,rs, so that the next step (accumulator isolation) can be com-pl et'ed. Thus, the operator should proceed to stop 26 as soon as low-head SI is verified.
Step 26 i This step instructs the operator to isolate all of the accumu-lators. The operator should attempt to close the accumulator isolation valves. If this cannot be done, the o;er should then attempt to vent the accumulator nitrogen to atmosphtes pressure.
The operator should not proceed with subsequent steps of guideline, until the accumulators have been isolated or vented. Each plant FR-C.1 Page: 25 Rev: .HP-Basic 55008:1
should determine if the accumulator pressure measurement would be available. If it isn't available, alternate means of determining accumulator vent, sho'uld be incorporated in this guideline. The operator must return to step 22 f f the core exit thermocouples 0
- exceed 1200 F, while waiting for the accumulators to be vented.
The accumulators should be vented to atmospheric pressure. This is done to assure that accumulators won't inject nitrogen into the RCS. The secondaries are currently being depressurized to atmos-pheric prissure. Eventually the RCS will refill and reach an equil- !
ibrium pressure, where the low-head SI flow is equs1 to the flow through the break. However, the RCS may approach atmospheric pres-sure before it refills. Therefore, to limit the amount of nitrogen injected into the RCS, the accumulators must be depressurized to atmospheric pressure.
This step is of extreme importance due to the nature of this tran-sient. For large LOCAs, the accumulators inject nitrogen into the RCS, which is toen released through the break, with little consequence. In small LOCAs, the RCS pressure never drops -
sufficiently for the nitrogen to be injected. The preceeding steps of this guideline depressurize the RCS to the point where nitrogen could ,be injected. If this happens, the reactor coolant pumps must
- continue to run, until the nitrogen is removed. This could take a considerable amount of time. Thus, caution should he exen:ised to minimize the possibility of injecting nitrogen into the RCS.
Step 27 This step instructs the operator to check the hot leg temperature.
This is done to assure that the core is cool and that very little superheat remains in the RCS. Tnus, the operator must wait until ,
the hot leg temperature drops below 350 F, befort he can stop the RCPs (step 28).
o FR-C.1 Page: 26 Rev: HP-Basic 55008:1
I k
Two RTDs are used to detennine the success of the depressurization, to assure that one RTD is not giving an erroneous reading.
Step.28 i
This step instructs the operator to stop the RCPs. This step allows the operator to stop the pumps when they are no longer needed for
. cooli ng.
Step 29 This step instructs the operator to verify low-head SI flow. If continuous low-head SI flow cannot be verififed, the operator is instructed to go to step 22 of this guideline.
The low-head flow should be verified by either direct ' flow indica-tion or by the low-head SI pump discharge pressure being less than the shut-off head of the low-head SI pump. Each plant should evalu-ate the pmferred indication and define this in the guideline, along with the shut-off pressure of the low-head SI pumps.
Initially, the low-head SI flow should be steady; then the flow will reduce the match break flow. If the break is very small, the RCS pressum will approach the shut-off head of the low-head SI pumps.
If .this occurs low-head flow is verified.
Step 30
, This s,tep instructs the operator to check for adequate com cool-i ng. If the core exit thennocouples are mading less than 4000F and the mactor vessel narrow range level indication is greater than
! the top of the core plus instrument inaccuracies, the operator is instructed to go to step 14 of E-1 (The Loss of Reactor Coolant Guideline) in step 31. The operator must monitor those conditions FR-C.1 Page: 27 Rev: HP-Basic 5500B:1
s until the criteria are met, before proceeding to step 31. If the 0
core temperature should rise above 1200 F, while he is waiting the operator is instructed to return to step 22 of this guideline.
~
The vessel level indication of the top of the core plus instrument inaccuracies assures that the core is completely covered, since the core is filled with a two-phase mixture. In addition core exit 0
thermocouples at 400 F assure that there is little superheated steam in even the hottest regions of the core.
t Step 31 This step instructs the operator to go step 14 of E-1 (The Loss of Reactor Coolant Guideline). This is done, when the core has been returned to a stable and cool condition.
?
FR-C.1 Page: 28 Rev: HP-Basic 5500B:1
References
- 1. R. H. Mark, et. al. , " Inadequate Core Cooling Studies of Scenarios With Feedwater Available, for UHI Plants, Using the NOTRUMP Computer Code", WCAP-9763, Non-Proprietary, July 1980.
- 2. C. M. Thompson, et. al. , " Inadequate Core Cooling Studies of Scenarios With Feedwater Available, Using the NOTRUMP Computer Code", W AP-9754, Non-Proprietarf, June 1980.
I e
t i
FR-C.1 Page: 29 Rev: HP-Basic 5500B:1
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