ML19210A351
ML19210A351 | |
Person / Time | |
---|---|
Site: | Three Mile Island ![]() |
Issue date: | 10/15/1976 |
From: | METROPOLITAN EDISON CO. |
To: | |
Shared Package | |
ML19210A347 | List: |
References | |
NUDOCS 7910290582 | |
Download: ML19210A351 (11) | |
Text
{{#Wiki_filter:. EVALUATIC:i CF FCTE'iTIAl REACTCE VESSEL CVIEFEESSURIZATIC:I
- 1. Purpose The purpose of this evaluatien is to examine the system design and operation for susceptability to everpressurization events during start-up and shutdevn and to determine the pressure respense of the Reactor Ccolant System (RCS) to pctential events which cause pressure increases.
- 2. Events Evaluated The events examined in this evaluation vere:
- a. Erreneous actuation of the High Pressure Injection (EFI) System.
- b. Erreneous opening of the core flood tank discharge valve.
- c. Errcnecus additien of nitrogen to the pressurizer.
- d. Makeup control valve (takeup to the ECS) fails full open.
- e. All pressurizer heaters erreneously energized,
- f. Temporary less of the Decay Heat Be=cval System's capability to re=cve decay heat frc= the ECS.
- g. Thermal expansion of RCS after starting an EC pump due to stcred thermal energy in the steam generator.
- 3. Results of Event Evaluation 3.1 General Fcr events which cause the RCS pressure to increase, the pressure vill increase significantly faster in a "sclid water" system than it vill in a systa= with a stea= cr gas space. The RCS always cperates with a stes: cr gas space in the pressurizer; no cperations involve a "sclid water" condition, other than system hydrctest.
Ccnsidering the nodest rate of pressure rise (because of non-solid pressuriser) frc= the events and the high level alar =s in the pressurizer that would ner ally alert the cperater, it is reasonable to expect the cperator to terminate the event prier te reaching an everpressurizaticn ecndition. EcVever, without operator action, the pilot actuated relief valve 1ccated on the pressurizer vill terminate any pressure increase. A dual setpcint is utilized fer this valve tc provide overpressure protection during startup and shutdcun ecnditions. The lever setpoint is enabicd by actuatien of a switch in the centrol rec =. Characteristics of this valve at the lever setpoint are: Cpen Setpcint SSC FSIG Close Se:pcint 500 FSIG -
'l910290
3.1 General - continued Ste1= capacity at 550 PSIG 25,985 lb/hr Equivalent liquid insurge volume rate into pressurizer 2,650 GFM Liquid capacity 3 550 PSIG SCO GFM Nitregen capacity ? 550 PSIG 32,k20 lb/hr Equivalent liquid insurge volume rate into pressurizer 2,350 GFM All events invclving insurge to the pressurizer were evaluated with the pressuri:er and takeup tank water levels initially at high levels. For the pressurizer, a water level at the high high level alarm setpoint was used. The relationship of this level to the cther pressuriser water level setpcints is: 0" LC0" Level Indicating range 315" High high level alarm 260" High level alarm 220" Normal level 200" Lev level alarm 80" Lev level interlock (heater cut-cut) and alarm For the makeup tank, which is the normal suction source for the makeup / EPI pump, a water level at the high level alarm setpoint was used. The relationship of this level to the other takeup tank level setpoints is: 0"-100" Level Indicating range 86" High level alarm 73" Normal level 55" Lov level alarm The initial pressurizer level used fer the event does not affect the peak pressure reached; it caly affects the rate of precoure increase. 3.2 Erreneous Actuatien of the HPI System This event is not credible because the circuit breakers for the clcsed HP injecticn motor operated valves are " racked cut" during the plant cocidevn prior to startup of the Decay Heat Re= oval System. These valves are "U-716A, 3, C, & D on SAR Figure 9-3. Startup of the Decay Heat Re=cval Syste= cecurs at an RCS temperature of 250cy, 3.3 Errenecus Cpening cf the Core Flced Tank Discharge Valve This event is not credible because this vsive is closed and the circuit breaker for the =cter operator is " racked cut" iuring the plant eccl-devn before the RC3 pressure is decreased to 600 PSIG. 1488 T27
3.4 Erreneous Addition of Nitregen to the Pressurizer It is not credible that this event can overpressurice the RCS. Nitregen
, is added to the pressurizer during plant eccidevn at an RCS pressure of 50 PSIG er less. The nitregen source is two banks of six tettles each. *4ith the pressurizer water level at the High High level alarm setpoint and pressure at 50 PSIG, erroneous addition of the contents cf all twelve bottles to the pressurizer vculd cnly increase the pressure to 195 PSIG.
3.5 Makeup Centrol Valve (=akeup tc the RCS) Fails Full Cpen This valve is MU-717 cn SAR Figure 9-3 and is autc=atically centrolled by the pressurizer level centrclier. The pressure respense of the RCS to this event is shcvn on Figure 1. If it is assu=ed that the cperatcr dces net take action to tar =inate the event during the pressure increase, the peak RCS press tre is limited to 550 PSIG by the pressurizer pilot actuated relief valve. Initial cenditiens used for the analysis were:
- a. 315" pressurizer water level (high high alar = setpoint)
- b. 86" makeup tank vater level (high level alar =)
- c. 32" GPM total seal injection flew to RC pu=ps (autc=atically controlled)
- d. h5" GPM letd.'un flew frc= RCS to makeup tank
- e. no spray into pressurizer (normally there vould be)
Figure ene depicts two pressure response curves. One is for an initial RC3 pressure of 275 FSIG. This is the RCS nressure at which the Decay Heat Re=cval Syste= is started up during plant eccidevn er at which the RC pumps are started during plant heatup. Pressurizer water level vould ner= ally be abcut 220" instead of the 215" used in the analysis. The higher level used in the analysis increases the rate of pressure rire. The cther pressure response curve en Figure 1 is fer an initial RCS pressure of 100 PSIG. This is abcut the levest RCS pressure at which the Makeup Sycten vould be in operation. Relief through the pressurizer relief valve vill te terminated by cperatcr acticn (stcp =akeup pump cr close makeup line isclation valve MU-718) or withcut operator action when the makeup tank vater velu=e is exhausted. Feak insurge rate into the pressurizer is 2L5 GF3. In additien to the alar =s shcvn en Figure 1, other alar =s and indications which would alert and aid the operator in evaluating the event are:
- a. Pressurizer high level alar =(s)
(with initial level telev high high setpoint which vculd te nornal).
- b. Highe *han ner=al =akeup line flev rate indicaticn
- c. Lcver than normal =akeup pump discharge pressure
- d. Full cpen indicating light for makeup valve
- e. High temperature alar: for relief valve discharge line (after relief valve relieves)
- f. Higher than ncr=al RCS pressure indi:aticn
- g. Higher than normal pressuri:er level indication 1488 428
-a.
3.6 All Pressurizer Heaters Errenecusly Energized The pressure respense of the RCS to this event is shown en Figure 2. If it is assu=ed that the operator dces not take action to terminate the event during the pressure increase, the peak RCS pressure is limited to 550 PSIG by the pressurizer pilot actuated relief valve. An initial pressurizer water level of 90 inches (10 inches abcve lov) level heater cut-cut interleck) was used because the lever water level results in the fastest pressure increase. Even with the icv level, the pressure increase is very sicv. The pressurizer water level vill not change during this event as it is being autc=atically centrolled. The heaters are generating 1625 lbs of stea= per hcur in the 500 to 550 PSIG range. In addition to the alar =s shcun en Figure 2, other alar s and indications which vculd alert and aid the operator in evaluating the event are:
- a. Higher than ncr=al RCS pressure indicatien.
- b. Higher than normal letdevn flev rate indicatien to =akeup tank (due to increasing RCS pressurizer)
- c. Higher than ner=al makeup line flev rate indication due to increasing letdevn flev rate,
- d. High temperature alar = for relief valve discharge line (after relief valve relieves)
- e. The "Cn" indicating lights " lit" for all pressurizer heater banks Relief through the pressurizer relief valve vill be ter=inated by operator action (de-energize heaters). Withcut cperator action, the heaters vill be de-energized when the pressurizer water level drops to the heater cut-cut interlock set point. Since pressuri:er water level is en autc=atic centrc1, water is transferred aute-
=atically frc= the =akeup tank to the RCS to replace that which is 1 cst through the relief valve. Fcr an initial =akeup tank level at the high alar = setpoint, it would take six (6) hours to e=pty the =akeup tank and thus result in pressuriser water level decreasing to the heater " cut-cut" setpcint.
3.7 Te=porary Less of Decay Heat Re=cval Systems Capability to Pe=cve Eecay Heat Frc= the RCS The pressure response of the RCS to this event is shcvn en Figure 3. If it is assumed that the cperater dces net taxe acticn to terminate the event during the pressure increase, the peak RCS pressure is li=1ted to 550 PSIG by the pressurizer pilct actuated relief valve. Less cf decay heat re=cval capability could caly be caused by less of ficv in the Decay Heat Re=cval System er in the eccling water syste= serving the Decay Heat Re= oval System. Icss of ficv in either syste= veuld i==ediately actuate lcv fiev slar=(s), thus alerting the operator. Relief thrcugh the pre;suri er relief valve vill be terminated by crerster acticn restering the decay heat re=cval function. Insurge rate into the pressurizer is 98 GPM in tv.e 500 to 550 PSIG pressure range. Conditicns used in this pressur' response analysis were:
'2h s
. 3.7 centinued
- a. Event cecurs during eccidown after startup cf Decay Heat Re:cyal Syste and shutdevn cr stest generaters
- b. Pressurizer level at 315 inches, ncr ally it vould te near 220 inches
- c. Cooldovt co the Decay Heat Re:cval Syste: " cut-in" temperature at 100 F/Er, this prcduces maxi =ut decay heat generation rate
- d. All decay heat abscrted by reacter ecclant, no heat abscrbed by the retal ec ponents er by the stes: generaters. Actually, these are heat absorbing sinks
- e. 32 GPM total seal injection flow to RC pu=ps (autecatically centrolled)
- f. h5 GPM initial letdevn frc RCS to makeup tank
- g. No spray into pressurizer 3.8 Start of an RC Pump with Stered Thermal Energy in CTSG Secondary Several postulated situations have been examined which may lead to primary fluid expansion due to energy abscrptien frc= het CTSG secondary water after start of an RC pump. The tv0 types of situations which lead to possible RCS pressurizatico have been identified as fcilows:
Type A. Filling of CTSG seccndary side with hot water with subsequent start of an RC pump, and Type B. Restart of an RC pump during heatup fc11cving a period of stagnant (no flow) ccnditicns. 3.3.1 Start of an RC Pump Under Type A Ccnditien Figure number h presents results of RCS pressure versus time for the vorst case Type A (see abcve) condition. Initial conditions for this transient are a result of filling cf the stea generaters with feedvater at h2CF. This temperature is a result of the failure of the feedvater heating centrols causing auxiliary steam flow to the heatera to produce a feedvater temperature in excess of the allevable value cf 225 F for CTSG fill operations. The temperature of the feedvater in the CTSG seccndary side following the filling operatien reaches a temperature of 2LO F as dces the primary water centained in the RCS at elevatiens greater than the icver CTSG tubesheet. This is a result of the heating of CTSG tubes and primary water during CTSG filling where heated primary water circulates to a limited extent thrcugh the RCS. At the end of the filling cperatien, the RCS va:er 1ccated telev the GCSG 1cver tubesheet remains at the initial value of ILCF. The primary syste pressure versus time as shewn in Figure h is based en an initial pressurizer level at the maximum value of the high-high level alar: for a 177 FA plant. The initial pressuri:er level is ner ally kept much lever to sinimize the heating require-ments fer raising the pressurizer terperature and pressure in prepara*.icn for starting an RC pump. The initial pressure is 3CC PSIG, the ner al pressure required prier to starting an RC purp. 3c credit 1488 330
-E.
3.8.1 continued has been taken for pressurizer level centrol. The pressuri er level increased during the transient by 3C inches; the level vould have to rise an additional 70 inches bercre entering the upper head. Cther conditiens of primary and secondary te=peratures which may exist prier to starting of an RC pump have been evaluated and are bcunded by the results cf Figure L. These ccnditiens include the situaticn where the feedvater temperature entering the CTSG's during filling cperatiens is at the ner=al maximu= value of 225F but the operator fills the stea= generaters beycnd the =aximum allevable level and ec=pletely fills the steam generators. In addition, the results presented here tcund the case where the initial RCS te=perature is SCF tefore filling the steam generaters. 3.8.2 Start of at RC Pump Under Type 3 Ccnditien Figure number 5 presents results of RCS pressure versus time for the Type B conditiene (see abcve). Initial ecnditiens fer this transient are a renuit of the accu =ulatica cf pucp seal injecticn and =akeup inject!.on water in the RC cold leg piping during stagnant (no flev) eenditions. Although the cperator is required to initiate a cocidcun of the RCS if RC pumps are incperable and RC te=perature >25CF (Plant Limit and Precautions), the assu=ption is made that the cperator fails to do so while alleving takeup and seal injection water temperature to drop to SCF, which is below the =inimum value of RC te=perature less 12CF. The cold water is assumed to accumulate in the RC cold leg piping without mixing with het RC vater. The RC pump is started following a pericd of one hour of stagnant (no flev) ccnditiens in the RC Syste=. The primary system pressure versus time as shown in Figure 5 is based en an initial pressurizer level at the maximum value of the high-high level alar = for a 177 FA plant. The initial pressure is h50 PSIG vhich is apprcximately midway between the Tech Spec and RC pu=p :TPSH pressure limits at 275F. :io credit has been taken fer pressurizer level centrol. The decrease in pressurc at apprcximately 2 minutes is a result of het RC primary fluid entering a steam generator which has been eccled by the pase.a.ge of the slug of Icv temperature RC fluid (the mixing of RC fluid and heat transfer through the CTSG tubing brings the RC fluid to a constant te=perature and prcduces a net centraction of the fluid and a decrease in system pressure at final equilibriu: conditiens). The pressurizer level increases during the transient by 13 inches; the level veuld have to rise an additional 87 inches before entering the upper head. L. ?cnclusiens The preceding evaluation and analysis de=cnstrates that the reacter vessel is protected frc= cverpressuri:atien during e7ents which cause increasing pressure. 1488 331
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