ML18064A698

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Nonproprietary Rev 1 to Palisades Loss of Load Analysis.
ML18064A698
Person / Time
Site: Palisades Entergy icon.png
Issue date: 03/31/1995
From: Nutt W
SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:
Shared Package
ML18064A697 List:
References
EMF-93-086(NP), EMF-93-086(NP)-R01, EMF-93-86(NP), EMF-93-86(NP)-R1, NUDOCS 9504180301
Download: ML18064A698 (23)
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I EMF-93-086(NP)

Revision 1 I

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I Palisades Loss of Load Analysis I

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'I March 1995 I

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Siemens Power Corporation I i Nuclear Division

~1r 9504180301 950412-~

" ' ~DR; ' ~DO~K osoo~B~s* :_

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I, Siemens Power Corporation - Nuclear Division I EMF-93-086(NP)

Revision 1 Issue Date: 3/31/95 I

I Palisades Loss of Load Analysis

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I) Prepared by:

I W. T. Nutt I Reload Analysis Nuclear Engineering I

.I Analysis Contributor:

S. E. Cole*

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I *March 1995 I /smg I'

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I CUSTOMER DISCLAIMER IMPORTANT NOTICE REGARDING CONTENTS ANO USE OF THIS DOCUMENT I

PLEASE READ CAREFULLY Siemens Power Corporation's warranties and representations concerning the subject matter of this document are those set fonh in the Agre11ment between Siemens Power Corporation andthe Customer pursuant to which this document is issued. Accordingly, except as otherwise expressly provided in such Agreement, neither Siemens Power Corporation nor any person acting on its behalf makes any warranty or representatiOn, ex*

pressed or implied, with respect' to the accuracy, completeness, or useful-ness of the information contained in this document, or that the use of any information, apparatus, method or process disclosed in this document will not infringe privately owned rights; or assumes any liabilities with respect to the use of any information, apparatus, method or process disclosed in this document.

The information contair:ied herein is for the sole use of the Customer.

In order to avoid impairment of the rights of.Siemens Pow~r Corporation in patents or inventions which may be included in the information contained in this document, the recipient. by its acceptance of this document, agrees not to publish or make public use (in the patent use of the term) of such information until so authorized in writing by Siemens Power.Corporation or until six (6) months following termination or expiration of the aforesaid Agreement and any extension thereof, _ unless expressly provided in the Agreement. No rights or licenses in or to any patents are implied by the furnishing of this document.

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Revision 1 Page i I Table of Contents I Section I . 1 .0 EVENT DESCRIPTION ............... *. . . . . . . . . . . . . . . . . . . . . . . : . 1-1 2.0 DEFINITION OF EVENTS ANALYZED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1

1. 3.0 ANALYTICAL METHODOL_OGY ........... *' .- . . . . . . . . . . . . . . . . . . . . 3-1

.I 4.0 ANALYSIS RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . 4-1

5.0 CONCLUSION

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6.0 REFERENCES

..... : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 I.

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Revision 1 Page ii I List of Tables I Table Page I 3.1 Safety Valve Setpoints and Capacities .............. ; . . . . . . . . . . . . . : . 3-2 4.1 Event Summary for the Loss of External Load Event ... ; ........ *. . . . . . . . . 4-2 I

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  • 1 List of Figures
  • 1, Figure Page.

I. 4. 1 Reactor Power for Loss of External Load 4-3

.,, 4.2 Core Average Heat Flux for Loss of External Load .................. : . . . .

4.3 Pressurizer Pressure for Loss of External Load . .. . . . . . . . . . . . . . . . . . . . . .

4-4 4-5 4.4 Pressurizer Liquid Volume for Loss* of External Load . . . . . . .. . . . . . . . . . . . . 4-6 I* 4.5 *Primary Coolant System Mass Flow Rate for Loss of External Load . . . . . . . . . . 4-7 I, 4.6 Primary Coolant System Temperatures for Loss of External Load . . . . . . . . . . . 4-8

4. 7 Reactivity for Loss of External Load ......... ." ...* ......... -. . . . . . . . . . 4-9 I
  • 4.8 Secondary Pressure for Loss of External Load . . . . . . . . . . . . . . . . . . . . . . . . 4-10
  • 1~ 4.9 Steam Generator Secondary Fluid Mass for L~ss of External Load 4-11 1.

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,, Loss of External Load With 25% Steam Generator Tube Plugging I 1.0 EVENT DESCRIPTION A Loss of External Load event (Event 15.2.1) is initiated by either a loss of external electrical I' load or a turbine trip. Upon either of these two conditions, the turbine stop valve is assumed

  • to rapidly close (0.1 second). Normally, a reactor trip would occur on a turbine trip; however, I to calculate a conservative system response, the reactor trip on turbine trip is disabled. The steam dump system (atmospheric dump valves - ADVs) is assumed to be unavailable. These I assumptions allow the Loss of External Load event to bound the consequences of Event 15.2.2 (Turbine Trip - steam dump system unavailable) and Event 15.2.4 (Closure of
1. both MSIVs - valve .cl.osure time is > 0.1 second).

I The Loss of External Load event primarily challenges the acceptance criteria for both primary and secondary system pressurization and DNBR. The event results in an increase in the I primary system temperatures due to an increase in the secondary side temperature. As the primary system temperatures increase, the coolant expands into the pressurizer causing an I

  • increase in the pressurizer pressure. The primary *system is protected against overpressurization by the pressurizer safety and relief valves. Pressure relief on the secondary I side is afforded by the steam line safety/relief valves. Actuation of the primary and secondary system safety valves -limits the magnitude of the primary system -temperature and pressure I increase.

I With a positive BOC moderator temperature coefficient, increasing primary system temperatures re.suit in an increase in core power. The increasing .Primary side temperatures and power reduces the margin to thermal limits (i.e., DNBR limits) and challenges the DNBR I acceptance criteria.

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Revision 1 Page 2-1 1* 2.0 DEFINITION OF EVENTS ANALYZED I The objectives in analyzing this event are to demonstrate that the primary pressure relief

  • capacity is sufficient to limit the pressure to less than 110% (2750 psia) of the design I pressure and that the secondary side pressure relief capacity is capable of limiting the pressure to less than 110% (1100 psia) of design pressure. A steam generator tube plugging I level of 25 % is assumed for the analysis. No credit is taken for direct reactor trip on turbine trip, the turbine bypass sy.stem or the steam dump system. Also, credit from the pressurizer I PORVs is conservatively excluded from this analysis. In general, the parameters and

. equipment operational states are selected to maximize the system pressure.

I A loss of load event also challenges thermal margin limits. H.owever, Reference 1 disposed I this subevent as being bounded by other more limiting AOO events. Thus, the DNBR for this event is not evaluated.

I The Loss of External Load is credible only for rated power and power operation events

.1 because there is no load on the turbine at other rea'ctor conditions. The rated power conditions bound the consequences for other reactor power operating conditions because of

  • 1 the increased stored energy. The higher the stored energy in. the primary system, the more severe the consequences of this event.

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  • Revision 1 Page 3-1 I 3.0 ANALYTICAL METHODOLOGY I ANF-RELAP was used in accordance with Siemens Power Corporation's approved methodology. (21 The capacities and setpoints_used_ in the _a_nalysis for the pressurizer and main I steam safety valves are summarized in. Table 3.1.

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I Table 3.1 I

Safety Valve Setpoints and Capacities I

I Nominal Setpoint (psia) .

Setpoint with 3% Error (psi a)

Flow at Opening*

(lb/hr)

Flow at Accumulation

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I I Pressurizer Safety Relief Valves .

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  • RV-1039 2,580.0 2,657.4 230,447 237,360 I~

RV-1040 '2,540.0 2,616.2 226,874 233,680 RV-1041 '2,500.0 2,575.0 223,30,1 230,000 Main Steam Safety Relief Valves (8 per Bank) I Bank 1

  • Bank 2 1000 1020 1030 1050.6 3,779,417 3,855,006 3,892,800 3,970,656 I

Bank 3 1040 1071.2 3,930,594 4,048,512

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  • Assumes valve fully open at setpoint plus 3 % error. I
    • Accumulation is 3 % above setpoint.

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Revision 1 Page 4-1 I 4.0 ANALYSIS RESULTS I The maximum primary pressurization case initiates with a* rapid closure of the turbine stop valve in 0.1 *seconds. Steam line pressure increal)es until the safety relief valves open at I 10.55 seconds. *The maximum pressure in the steam generators of 1040.8 psia is achieved at 13.80 seconds. The maximum required steam line relief valve flow capacity to control the I secondary-side pressure is about. 3.8 Mlbm/hr.

I The pressurization of the secondary side results in decreased primary to secondary. heat transfer, and a substantial rise in primary system temperature. A primary coolant temperature I . . .

increase of about 15.1 °F has occurred by 9.50 seconds. This results in a large insurge into the pressurizer, compre'ssing the *steam space and pressurizing _the primary system. The I reactor trips on high pressure with rods beginning to insert at 7. 25 second~, and the pressurizer safety valves open at 10.80 seconds. The increase in coolant temperature also I causes the core power to rise to 2671.2 MWt due to positive moderator feedback. The transient is terminated shortly after reactor scram due to decreasing primary coolant I temperature* and pressure.

I The capacity of one valve is enough to contain the pressurizer pressure to a maximum of.

2575.9 psia. The maximum primary system pressure is 2614.9 psia occurring at I 10.90 seconds. The maximum PCS pressure is less than the 2750 psia limit. The. responses of key system variables are given in Figures 4.1 to 4.9. The sequence of events is given in I Table 4.1.

I The secondary side pressure relief valves contain sufficient capacity to limit the pressure to less than 110% (1100 psia) of design pressure.

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I Table 4.1 I

Event Summary for the Loss of External Load Event I

Event Time (sec)

I Turbine Trip Pressurizer Heaters on 0.00 0.00 I

Charging Flow on 133 gpm 2

0.00 *.1 Peak Core Average Heat Flux 168,830 Btu/hr-ft 0.10 Reactor Scram (High P'ressure)

Peak Power Level 2671.2 MWt 7.25 7.90 I

Steam Line Safety Valves Open Pressurizer Safety Valv*es Open 10.55 10.80 I

Peak PCS Pressure Peak Core Average Temperature 2614.9 psia 584.74 °F 10.90 11.85 I

Peak Steam Generator Pressure 1040.8 13.80 I

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2.tOO.O

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QJ 2000.0 J 800.0

!t 0

0..

... 1200.0.

...,0 u

<

.8.0

i::

4.0 0.0 2.0 4.0 6.0 8.0 10.0 12.0 14.0 18.0 18.0 20.0 m

Time (sec) s::

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"'tJ

c (1)

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Q) < 0 Figure 4.2 co -* co Cl>~. m oz

.J::.::l Core Average Heat Flux for Loss of External Load* .f:. ~ :E

2600.0

. 2400.0 4i' rn

-p.. 2300.0 2200.0 2100.0.

2000.0 1900

  • 0 t_...___._~~-...._.._..._L_-._.._._~L.o-£-....__.~e..i_.o.._,L-.&._1~0~.oi-....._._1~2~.~o_._~1~4-.o.&-J.__._1~8~.o.__._._1_e~.~o~~.._.20.o 0.0 20 40 8 Time (sec)

Figure 4.3 Pressurizer Pressure for Loss of External Load

1126.0 1100.0

_.. 1075.0 I.")

QJ e l 050.0

->;j 0

1026.0 "tj

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...l l 000.0 976.0 960.0 L..i.........._._...1.-..................-L_._4-.L...Jl.......&..-.._._..._,...._.__,__._...._.&--l..__.._,__._-£.-.l.-l'--L_.__.__._...__._.__.__._....._.

0.0 2.0 4.0 8.0 e.o . 1 o.o *12.0 14.0 18.0 18.0 20.0 Time (sec)

Figure 4.4 Pressurizer Liquid V.olume for Loss of External Load

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- 0 Q) 140.0 91

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a

.c Q) cu 130.0

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- 0 f&..

. fl) fl) 120.0 CIS .

s . '

110.0 100.0 L-..1-L.....L.....l-.o..--!'--'--'-~

0.0 2.0 4.0

' 8.0 8.0

_.__._....._.._..__.__.__._...___..__..__._~......_.__.__._

10.0 12.0 14.0. 18.0 18.0 20.0 Time (sec) m s:"TI I

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0 w

""O Cl) I QI < 0

  • Figure 4.5 co -* CX)

Cl> !!?. 0) o-

~ :J z Primer)' Cool~nt System Mass Flow Rate for Loss of Externa*I Load ..'..J ..... ,:g

Average o - - o Cold Leg

  • Hol Leg 825.0

>< x Core Inlet f:s..

Q)

G> 800:0 bD G>

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G> 575.0

i cd L.

Q)

p. 660.0 e

G>

E-t 526.0 0.0 2.0 4.0 8.0 8.0 10.0 12.0 14.0 16.0 I 8.0 20.0 Time (sec) m s::

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D VJ

'"ti CD I Q) < 0 Figure 4.6 co -* CD CD !!!. 0>

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~ ::J z Primary Coolant System Temperatures for Loss of External Load 00 .... .3!

~-

0.0 l--...:......,-_ _ _ _ _ _ _---....

- -1.0

...,J CJ

-2.0

~

-3.0

-4.0 L....a.--L~...L.............__.._._~_._~L--1.--L.....;..a_...l-.._.._.__.____.__._.._.._.__.____.__._.._..._.,__.__.__._..&--L.-4_.__._.

0.0 2.0 4.0 6.0 8.0 10.0 12.0 14.0 16.0 18.0 20.0 m

Time (sec) s:

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co

'tJ CD JJ wI Ill < 0 Figure 4.7 co -* CX>

CD  !!?. 0>

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. Reactivity for loss of External load cO _. ~

l l.00.0 l 000.0 td fl> 900.0

._tl.

a.>

i rn fl>

a.> 800.0

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700.0 0.0 2.0 4.0 8.0 8.0 10.0 12.0 14.0 16.0 18.0 20.0 Time (sec)

Figure 4.8 Secondary Pressure for Loss of External Load

14.0

- 13.0

-.0 12.0 11.0 8.0 8.0 I 0.0 12.0 14.0 18.0 18.0 20.0 Time (sec)

Figure 4.9 Steam Generator Secondary Fluid Ma~s for Loss of External Load

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5.0 CONCLUSION

I The maximum pressurizer and secondary side pressure remain below 110% of. design pressure. Applicable acceptance criteria for the event are therefore met.

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6.0 REFERENCES

I 1. EMF-92-178, "Siemens Power Corporation Nuclear Division Palisades Cycle 11:

Disposition ano Analysis of Standard Review Plan Chapter 1 5 Events,"

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December 1992.

ANF-89-1 51 (P)(A), "ANF-Relap Methodology for Pressurized Water Reactors: Analysis I of Non-LOCA Chapter 15 Events," April 1992.

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  • EMF-93-086(NP)

Issue Date:

Revision 1 3/31/95 I

I Palisades Loss of Load* Analysis I

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Distribution I J. W. Hulsman CPCo/H.G. Shaw (6)

I Document Control (2)

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