ML051940473

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Attachment 2-E, DAR-OA-05-3, Revision 0, Report of SBLOCA Analyses with Degraded ECCS Flow After RAS Performed for Arizona Public Service in Support of Palo Verde Nuclear-Generating Station Units 1, 2, and 3
ML051940473
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 02/28/2005
From: Janke M, Rigby S, Upton T
Westinghouse
To:
Office of Nuclear Reactor Regulation
References
DAR-OA-05-3, Rev 0
Download: ML051940473 (152)
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ATTACHMENT 2-E DAR-OA-05-3, Revision 0 Report of SBLOCA Analyses with Degraded ECCS Flow After RAS Performed for Arizona Public Service in Support of Palo Verde Nuclear-Generating Station Units 1, 2, and 3 (Propriay)

REDACTED VERSION

Westingh6uS6 Propo6urys Class 3 REDACTED VERSION DAR-OA-05-3 Rev. 0 Page 1 WESTINGHOUSE ELECTRIC COMPANY LLC DAR-OA-05-3 Revision 0 REPORT OF SBLOCA ANALYSES WITH DEGRADED ECCS FLOW AFTER RAS PERFORMED FOR ARIZONA PUBLIC SERVICE IN SUPPORT OF PALO VERDE NUCLEAR GENERATING STATIONS UNITS 1, 2, & 3 February 2005 Originator:

see bottom of page Date:

Mark C. Janke, Westinghouse Electric Company LLC Technical Reviewer_

see bottom of page Date:

Tyler Upton, Westinghouse Electric Company LLC Management Approval: see bottom of page Date:

Stephen P. Rigby, Manager Operations Analysis, Westinghouse Electric Company LLC 02005 Westinghouse Electric Company LLC Official record electronically approved in EDMS 2000.

WESTINGHOUSE ELECTRIC COMPANY LLC

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Table of Contents 1.0 Background / Purpose...............................

4 2.0 Code Description...............................

6 3.0 Case Descriptions & Input Parameters...........................

7 3.1 Common Initial Conditions and Plant Parameters........................................

7 3.1.1 Initial Plant Conditions......................

7 3.1.2 ECCS Parameters.....................

.8 3.2 Break Parameters.......

9.....

9 3.3 Core Decay Heat.................... :

9 3.4 Containment Spray Pumps....................

10 3.5 Operator Actions...........

12 3.6 Sensitivity Cases...........

13 3.6.1 Sensitivity Case 1: [

13 3.6.2 Sensitivity Case 2:

13 3.6.3 Sensitivity Case 3:

....... 13 3.6.4 Sensitivity Case 4:1[.....

13 3.6.5 Sensitivity Case 5:1 14 j

3.6.6 Sensitivity Case' 6:[

14 3.6.7 Sensitivity Case 7:

....... 14 4.0 1

1..............

5 5.0 Case Results 17 5........I 17 5.2 Discussion of Individual Case Results...................................................................;......S........ 20 5.2.1 Series I & 2 Cases: Cold Discharge Leg (CDL) Breaks.20 5.2.2 Series 3 & 4 Cases: Suction Leg (SL) Breaks

.23 5.2.3 Series 5 Cases: Sensitivity Cases 25 5.3 Case Summary.27 6.0 Conclusions...................................................................................................................29 7.0 Figures........

30 7.1 Series 1: CDL Breaks, Failed HPSI after RAS 30 7.1.1 CDL-1......

30 7.1.2 CDL-2......

33 7.1.3 CDL-3......

38 7.1.4 C D L4...................................................................................................................................

C.43 7.1.5 CDL-5...

47 7.1.6 CDL-6....

51 7.1.7 CDL-7...

55 7.1.8 CDL-8.

58 7.1.9 CDL-9......

60 7.1.10 CDL-10....

62 7.2 Series 2: CDL Breaks, Degraded HPSI after RAS

.64 7.2.1 CDL-1 DH (Case not Required).......................

64 7.2.2 CDL-2 DH (Case not Required).......................

64 7.2.3 CDL-3 DH.........

65 7.2.4 CDL4 DH..........

68 7.2.5 CDL-5 DH......

71 7.2.6 CDL-6 DH......

74 7.2.7 CDL-7 DH......

77 7.2.8 CDL-8 DH.,

80 7.2.9 CDL-9 DH.........

,82 7.2.10 CDL-10 DH......................................t............................................................................ 84 7.3 Series 3: SL Breaks Failed HPSI after RAS 86 7.3.1 SL-1.

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PROPRIn ETARY REDACTED VERSION Westinghouse Proprietary Class 3 DAR-OA-05-3 Rev. 0 Page 3 7.3.2 SL-2...

90 7.3.3 SL-3 94 7.3.4 SL-4...

99 7.3.5 SL-5...

103 7.3.6 SL-6..

1.I06 7.3.7 SL-7..

1.I09 7.3.8 SL-8...

112 7.3.9 SL-9...

114 7.3.10 SL-10..

115 I 7.4 Series 4: SL Breaks, Degraded HPSI after RAS.

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96 7.4.1 SL-1 DH (Case not Required).......................

116 7.4.2 SL-2 OH (Case not Required)1.....................

16 7.4.3 SL-3 DH..

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SL-40DH..11.....

9 7.S. SL-5 DH................

121 7.4.6 SL-6 OH...1..............

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7.4.7 SL-7 DH 127 7.4.8 SL-8 DH 2..............

9 7.4.9 SL-9 DH...............

131 7.4.10 SL-10 DH 133 7.5 Series 5: Sensitivity Cases, Failed HPSI after RAS, 2' SL Breakk.135 7.5.1 SL-27F CD 135 7.5.2 SL-2 1 HPSI...............

137 7.5.3 SL-2 SIT Gamma = 1................

140 7.5.4

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-PROPRI ETARY-Westinghouse Proprietary Class 3

=ae DAR-OA-05-3 Rev. 0 REDCTD ERIO Page 4 1.0 - Background / Purpose This report' was 'prepared by Westinghouse Electric Co. for Arizona Public Service (APS) in support of Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 & 3. This analysis is part of a project to determine the past operability of the PVNGS units with air in the Emergency Core Cooling System (ECCS) suction lines' to-the containment sump.;

If a Loss of Coolant Accident (LOCA) were to occur with air in the ECCS pump suction line to the sump, it Is postulated that the High Pressure Safety Injection (HPSI) pump operability could be compromised due to air binding in the pump volute. This is postulated to occur at the time of the Recirculation Actuation Signal (RAS), when the HPSI and containment spray pump(s) suction shifts from the Refueling Water Tank (RWT) to the containment sump.

Two different scenarios of HPSI pump degradation have been analyzed. In the first scenario, LOCA's of various break sizes are analyzed with complete failure of the HPSI pumps after RAS initiation. Since the Low Pressure Safety Injection (LPSI) pumps de-energize at RAS, the plant operator is assumed to restart one LPSI pump to maintain Reactor Coolant System (RCS) makeup flow, in accordance with plant emergency operating procedures. In the second scenario, the same LOCA transients are analyzed with degraded HPSI pump flow, for a duration of four minutes, after which the air in the pumps has been discharged into the system and pump performance is considered to return to normal. For this second scenario, there is no operator action to restart a LPSI pump.

The degraded HPSI flow condition is based upon pump performance tests performed for this project at Wylie Corporation which is documented in an APS letter to the NRC, # 102-05195-GRO/DGMWRAS, dated 12/2712004.

Since this analysis is Intended to look at past operation, best estimate conditions are assumed. This analysis is in no way considered to be part of the PVNGS licensing basis nor has it been performed to satisfy any requirements of 1 OCFR50.46.

The purpose of this report is to describe any detrimental effects (core uncovery) that occur or are exacerbated by the HPSI pump degradation (total loss of operability and I or degraded operation) during various small and medium break size LOCA events.

Break sizes of I to 10 inches in diameter are analyzed in both the cold discharge leg (CDL) and the Reactor Coolant Pump (RCP) Suction Leg (SL).

Breaks smaller than one inch are not analyzed because they do not cause a Containment Spray Actuation Signal. Thus, sprays pumps are not needed and the time to RAS is sufficiently long to allow a plant cooldown and shift to shutdown cooling. For these small breaks, pressurizer level is regained without RCS water levels dropping below the level of the hot legs. Breaks greater than 10 inches in diameter are not analyzed because RCS pressure is well below the LPSI pump shutoff head at the time of RAS. Therefore, flow from the LPSI pump, restarted by the operator after RAS, is greater than normal HPSI pump flow from two pumps. Thus, break sizes greater than 10 inches in diameter are not considered limiting.

Only the two cold leg break locations are analyzed because any breaks in the hot leg would allow venting of steam produced in the reactor core directly to the containment, without need for loop seal clearing or WESTINGHOUSE ELECTRIC COMPANY LLC

REDACTED VERSION Westinghouse Proprietary Class 3 TROPMETAR DAR-OA-05-3 Rev. 0 Page 5 draining. RCS depressurization occurs without depressing water level below the top of the core. Thus, cold side breaks are limiting regarding core uncovery. A sensitivity case with a break in the pressurizer was performed to verify the limiting nature of cold leg breaks.

This report was prepared according to Westinghouse Procedure WP 4.25, Rev.

2, 11/30/04, and is supported by Westinghouse Calculation Note CN-OA-05-1, Rev. 0, dated 02/11/05.

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DAR-OA-05-3 Rev. 0 Page 6 2.0 Code Description The Westinghouse CENTS computer code has been utilized for this analysis.

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U 3.0 3.1 3.1.1 Case Descriptions & Input Parameters COMMON INITIAL CONDITIONS AND PLANT PARAMETERS Initial Plant Conditions w

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Pate 8 3.1.2 ECCS Parameters The initial ECCS conditions and assumptions are the same for all cases except the sensitivity cases. These parameters are as follows.

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i...PROPRIAR Westinghouse Propietary Class 3 REDACTED VERSION DAR-OA-05-3 Rev. 0 Page 12 3.5 OPERATOR ACTIONS Operator actions are in accordance with the APS emergency operating procedures. In particular, the Loss of Coolant Accident Procedure [

1 was used to determine the simulated operator responses to the transient. The actions taken are similar for all the cases analyzed, though the timing of some actions is different for each case. The actions are summarized as follows:i WESTINGHOUSE ELECTRIC COMPANY LLC

PRODAR REDACTED VERSION Westinghouse Proprietary Class 3 DAR-OA-05-3 Rev. 0 Page 13 3.6 SENSITIVITY CASES Seven sensitivity cases have been analyzed to support this analysis.

The sensitivity cases are intended to show the effects on overall case acceptability for those parameters which play an important role in the transient and could vary in some significant way from the values chosen for the various series of cases.

Details are discussed below.

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5.2 DISCUSSION OF INDIVIDUAL CASE RESULTS In the discussion below, the failed HPSI and degraded HPSI cases are discussed together.

Prior to RAS these cases are identical. After RAS, it is useful to compare how the relative ECCS flows affect the remainder of the events.

A review of the figures showing ECCS flow provides some perspective on the overall effect of degraded HPSI flow for four minutes, after RAS. As an example, for the [ I CDL break with degraded HPSI, Figure 7.2.3.3 shows the ECCS flow.

RAS occurs shortly after [

I seconds. A visual review of the degraded HPSI flow indicates that the depleted flow is a very small portion of the integrated flow over the course of the event. It would be expected to have very little effect on event results. This fact is supported by the Sensitivity case I 1 which shovw' that nominal vs. degraded HPSI flow does not significantly change case results.

I 5.2.1 Series I & 2 Cases: Cold Discharge Leg (CDL) Breaks CDL -1 WESTINGHOUSE ELECTRIC COMPANY LLC

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Westinghouse Proprietary Class 3 REDACTED VERSION DAR-OA-05-3 Rev. 0 Page 29 6.0 Conclusions The series of cases described above show that degraded HPSI flow caused by the air in the ECCS sump suction line will not lead to situations where core uncovery would occur. Two cases with total HPSI pump failure at RAS led to some partial core uncovery for an extended period of time, due to a depletion of RCS inventory. Those were the 3" and 4" CDL breaks. There were no cases with degraded HPSI pump flow which had any partial core uncovery associated with the degraded ECCS flow.

There were some additional cases, both failed and degraded HPSI flow cases, that showed short periods of partial uncovery due to loop seals filling and clearing; however, this phenomenon is expected for both CDL and SL breaks and is not due to the degraded flow in the ECCS system. This was verified by Sensitivity Case 7.

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7.0 Figures 7.1 SERIES 1: CDL BREAKS, FAILED HPSI AFTER RAS 7.1.1 CDL-1 U

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