ML20147C649

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One,Unit-II,Simulator Operability Test
ML20147C649
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/03/1987
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20147C583 List:
References
ERC871030, NUDOCS 8801190305
Download: ML20147C649 (32)
v • d • e


Text

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ERC871030 12/03/87 ARKANSAS NUCLEAR ONE UNIT - II SIMULATOR OPERABILITY TEST DATE: PERFORMED BY:

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ERC871030 12/03/87 UP'T 2 OPERABILITY TEST FOREWORD The Simulato.- Operability Test will oe performed annually. The collected data will be evaluated, discrepar des, if any, explained and attached to the Annual Simulator Report.

An Operability Test is not a Performance Test. The Performance Test demonstrated the Simulator's fidelity by comparing simulator calculated values to actual or predicted plant data and demonstrated ability to comply with ANS-3.5, 1985. The Simulator Modification Control Guidelines are designed to maintain the Simulator's fidelity. The Operability Test will provide the data to document satisfactory simulator performance.

It is required that all malfunctions listed in ANS-3.5, 1985, 3.1.2 be tested every 4 years and a minimum of 25% tested each year. The lists provided are sugcested and do not have to be followed, however, the aforementioned requirement must be met. ,

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ERC871030 12/03/87 SIMULATOR OPERABILITY TEST 1.0 DISCUSSION The purpose of the Simulator Operability Test is to:

1) Verifv overall simulator model completeness and integration,
2) Verify simulator performance against steady state criteria,
3) Verify simulator performance against transient criteria, and
4) Test a minimum of 25% of malfcqctions in ANS-3.5, 1985, 3.1.2 The Simulator Operability Test will be conducted annually and a report detailing evaluation of data, discrepancies, and required modifications will be written.

2.0 REFERENCE (S) 2.1 ANS-3.5, 19G5, 5.4.2 ANS NPP Simulators for 0 erator Training 2.2 Regulatory Guide 1.149 Rev. 2 2.3 ANO Unit II Simulator Performance Test 2.4 ANO Unit II Instructor Aids Manual 3.0 EQUIPMENT 3.1 None 4.0 INITIAL CONDITIONS 4.1 Steady State - as stated in procedure 4.2 Transients - 100%, MOL, EQXE (10-2) or as stated in procedure 5.0 ACCEPTANCE CRITERIA 5.1 Steady State 3.1.1 At 100% rated power, simulator computed values shall not vary more than i 2% of range over a 60 minute period.

5.1.2 Simulator computed values of critical parameters shall agree with the reference plant within i 2% of range and shall not detract from training.

5.1.3 Simulator computed values of non-critical parameters shall agree with the reference plant within i 10% of range and shall not detract from training.

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ERC871030  !

  1. 12/03/87 >

5.2 Transient 5.2.1 Observable changes in the parameters correspond in direction to those expected from plant data or best estimates data and do not violate'the physical laws of nr.ture.

6.0 NON-ACCEPTANCE OF SIMULATOR RESULTS 6.1 Steady State ,

6.1.1 Non-acceptance is defined as numerous simulator computed values outside the range set forth'in Section 5.1.

d.1.2 Non-acceptance shall halt the routine training involving such operations. Discrepancies shall be recorded, models enhanced, and retested as required.

6.2 Transient  ;

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Simulator results do not have to parallel source data,

, 6.2.1 however, observable differences, those that would detract from positive training, and those declared unacceptable by evaluation based on acceptance criteria, will not be used for routine training. ,

7.0 PROCEDURE 7.1- Obtain Data Initialize to 20% rated power (IC-4) 7.1.1 7.1. 2 Increase and Stabalize Power at 30% ,

7.1. 3 Start data log #3 7.1.4 Record problem time from instructor station screen i

, 7.1.5 Run for 20 minutes Stop r 7.1.6 Secure data log  ;

{ 7.1. 7 Initialize to 50% rated power (IC-9) 7.3.8 Increase and stabalize power at 60%. ,

7.1. 9 Start data log #2 7.1.10 Record problem time from instructor station screen

- 7.3.11 Run for 20 minutes Stop Time

7.1.12 Secure data log 7.1.13 Initialize to 100% rated power (IC-1) 7.1.14 Stabilize power ,

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7.1.15 Start data log #1 -

7.1.16 Record problem time from instruction station screen  !

7.1.17 Run for 70 minutes Stop Time 7.1.18 Secure data log  ;

7.1.19 Freeze simulator ,

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ERC871030 12/03/87 7.2 Delogging Data 7.2.1 30% Raled Power 7.2.1.1 Establish the following Delog Tableaux 7.2.1.2 Print and plot each tableau at 26 second in-tervals for 20 minutes 7.2.1.3 Attach data TABLEAU 1 - 30%

ACCEPTANCE CRITERIA

  1. Tag # Actual Min Max Description Simulated Values Min Max 46 2IR-9624 231.9 207.9 255.9 rn/ Gross 66 #CV-5993 29.6 27.6 31.6 Core Thermal Power 87 #T-4611-2 545.4 542.6 548.2 Loop A T C

86 #T-4611-1 547.2 544.4 550 Loop B T C

85 #T-4610-1 563.7 560.7 566.7 Loop A T H 94 #T-4717-B 555.5 545.5 565.5 Tav 82 #T-1023 345.3 335.3 355.3 FW Temp 36 2PI-4624-2 2243 2223 2263 Pzr Press l

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ERC871030 12/03/87 TABLEAU 2 - 30%

ACCEPTANCE

, CRITERIA

  1. tag # Actual Min Max Description Simulated Values Min Max 35 2LI-4627-1 46.36 44.3 48.3 Pzr Level 89 #T-4622 655.3 641.3 669.3 Pzr Temp 65 #CRAVG6 150 120 150 GR6 Rod Ht.

I 2LI-1031-1 70.24 68.2 72.2 S/G Lv1. _

2 2PI-1041-1 944.2 920.2 968.2 S/G Press.

47 2TR-0200 538.8 522.8 554.8 S/G Temp.

5 2FR-1029 1736K 1596K 1876K FW Flow 6 2FR-1030 1724K 1584K 1864K Stm Flow 7.2.2 60 % Rated Power 7.2.2.1 Establish the following Delog Tableaux 7.2.2.2 Print and plot each tableau at 26 second intervals for 20 minutes 7.2.2.3 Attach data 6

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TABLEAU 1 - 60%

ACCEPTANCE CRITERIA

, #_ Tag # Actual Min Max Description Simulated Values Min Max 46 2IR-9624 524.11 500.1 548.1 MW Gross 66 #CV-5993 60.32 58.32 62.32 Core Thermal Power 87 #T-4611-2 549.6 546.8 552.4 Loop A T C

86 #T-4611-1 550.6 547.8 553.4 Loop B T C 85 #T-4610-1 582.9 579.9 585.9 Loop A Tg 94 #T-4717-B 566 562 570 Tav 82 #T-1023 402.6 392.6 412.6 FW Temp 36 2PI-4624-2 2247 2227 2267 Pzr Press TABLEAU 2 - 60%

ACCEPTANCE CRITERIA

  1. Tag # Actual Min Max Description Simulated Values Min Max 35 2LI-4627-1 52.7 50.7 54.7 P r Level 89 #T-4622 656.8 642.8 670.8 Pzr Temp _

65 CRAVG 6 141 120 150 GR6 Rod lit. _

1 2LI-1031-1 70.26 68.26 72.26 S/G Level ,

2 2PI-1041-1 931.1 907.1 055.1 S/G Press 47 2TR-0200 535.9 519.9 551.9 S/G Temp 5 2FR-1029 3606K 3466K 3746K FW Flow 6 2FR-1030 3534K 3494K 3774K Stm Flow __

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ERC871030 12/03/87 7.2.3 100% Rated Power 7.2.3.1 Establish the following Delog Tableaux 7.2.3.2 Print and plot each tableau at 80 second intervals for 60 minutes 7.2.3.3 Attach data TABLEAU 1 - 100%

ACCEPTANCE CRITERIA

  1. Tag # Actual Min Max Description Simulated Values Min Max 46 2IR-9624 928.01 904 952 MW Gross 66 #CV-5993 100 98 102 Core Thermal Power 87 #T-4611-2 552.04 549.2 554.8 Loop A T C

86 #T-4611-1 553.6 550.8 556.4 Loop B T C 85 #T-4610-1 606.7 603.7 609.7 Loop A T H

94 07-4717-B 580 576 584 Tav 82 #T-1023 447.9 437.9 457.9 FW Temp 36 2PI-4624-2 2249 2229 2269 Pzr Press 8

ERC871030 12/03/87 TABLEAU 2 - 100%

ACCEPTANCE CRITERIA

_#_ Tag # Actual Min Max Description Simulated Values Min Max 35 2LI-4627-1 60 58 62 Pzr Level 89 #T-4622 654.88 640.8 668.8 Pzr Temp _

65 #CRAVG 6 147 120 150 GR6 Rod Ht 1 2LI-1031-1 70.0 68 72 S/G Level 2 2PI-1041-1 918 894 942 S/G Press 47 2TR-0200 530 514 546 S/G Temp 5 2FR-1029 6306K 6166K 6446K FW Flow 6 2FR-1030 6305K 6165K 6445K Stm Flow 7.3 Tape Save 7.3.1 Record Tape Serial No.

8.0 FINAL CONDITIONS Steady State data is collected, tape saved, and data attached to this procedura.

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ERC871030 12/03/87 ATTACHMENT E-1 30% RATED POWER 10

ERC871030 12/03/87 ATTACHMENT E-2 60% RATED POWER I

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ERC871030 12/03/87 ATTACHMENT E-3 100% RATED POWER i

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l ERC871030 12/03/87 7.2 Transient Procedure NOTE: Af ter initiation of transient, Operators are to take ap-propriate actions as directed.

NOTE: All transients are to be carried to a stable plant condition.

7.2.1 Perform the following transients:

7.2.1.1 _ Turbine Trip / Reactor Trig, High MSR Lovel (LER 86-11) 7.2.1.2 Initialize to 100% (IC-1) 7.2.1.3 Start data log #4

7. 2.1. 4 Insert Malfunction SSV0417 = 0 and SSV0418 = 0 7.2.1.5 Record Data for 10 Minutes 7.2.1.6 When stable conditions are reached, freeze simulator 7.2.2 "A" MSIV Closure (2CV-1010-1) 7.2.2.1 Initialize to 100% (IC-1) 7.2.2.2 Start Data log #5 7.2.2.3 Insert Malfunction SHV1010 = 0 7.2.2.4 Record Data for 10 minutes 7.2.2.5 When stable conditions are reached, freeze simulator.

7.2.3 Main Turbine Runback 7.2.3.1 Initialize to 100% (IC-1) 7.2.3.2 Start Data Log #61 7.2.3.3 Insert Malfunction X:SW 7800 7.2.3.3.1 At 2 minutes after runback commences remove malfunction X:SW 7800 7.2.3.4 Record Data for 10 minutes 7.1.3.5 When stable plant conditions are reached, freeze simulator.

7.2.4 Loss of Main Circulating Water 7.2.4.1 Initialize to 67% power (iC-1) 7.2.4.2 Start Data log #7 7.2.4.3 Insert Malfunction X:CR3101 and X:CR3102 7.2.4.4 Record Data for 10 minutes 7.2.4.5 When stable plant conditions are reached, freeze simulator, 14

ERC871030 12/03/87 7.2.5 Reactor Trip, "D" RCP Trip (LER 86-7) '

7.2.5.1 Initialize to 100% (IC-1) 7.2.5.2 Start Data Log #8 7.2.5.3 Insert Malfunction X:P.0 0604  !

7.2.5.4 Record Data for 10 minutes 7.2.5.5 When stable plant conditions are reached, freeze simulator.

7.2.6 Reactor Trip, "A" S/G Level Low 7.2.6.1 Initialize to 100% (IC-1) 7.2.6.2 Start data log #9 7.2.6.3 Place both MFRV in manual 7.2.6.4 Slowly close "B" MFRV .

7.2.6.5 When stable plant conditions are reached, freeze the simulator 7.2.7 Partial Loss of Off-Site Power (Natural Circulation) 7.2.7.1 -Initialize to 100% (IC-1) 7.2.7.2 Start data log #10 7.2.7.3 Place 6900 volt aux. leads on S/U XFMR #3 7.2.7.4 Place 4160 volt aux loads on Aux. XFMR 7.2.7.5 Insert malfunction X:EA8902 7.2.7.6 Record data for 10 minutes 7.2.7.7 When stable conditions are reachad, freeze simulator 7.2.8 Steam Line Break (100%)

7.2.8.1 Initialize to 100% (IC-1) 7.2.8.2 Start data log #11 7.2.8.3 Insert malfunction XRSG3701 or XRSG3702 - 100% '

7.2.8.4 Record data for 10 minutes 7.2.8.5 When stable conditions are reached, freeze simulator 7.2.9 LOCA (100%)

7.2.9.1 Initialize to 100% (IC-1) 7.2.9.2 Start data log #12 ,

7.2.9.3 Insert malfunction XRRC0301, XRRC0302, XRRC0303, l or XRRC0304 (100%)

7.2.9.4 Record data for 10 minutes 7.2.9.5 When stable conditions are reached, freeze j simulator 7.3 Delogging Data 7.3.1 Print out required parameter values at I second intervals l 7.3.2 Plot required parameters 1

7.3.3 Compare simulator computed values to plant or predicted j values 14

ERC871030 12/03/87 7.4 Data Tableaux <

7.4.1 Establish tableaux for transient data  ;

7.4.1.1 Turbine Trip / Reactor trip, High'MSR Level (Log 4) -

  1. Tag # Min Max Description l 35 2LI-4627-1 0 100 Pzr Level 36 2PI-4624-2 1500 2500 Prz Pressure 85 #T-4610-1 525 625 Loop A T 17 2JR-9005-1 0 110 NeutronY1ux(%)

1 2LI-1031-1 0 100 "A" S/G Level 2 2PI-1041-1 0 1200 "A" S/G Pressure 4 86 #T-4611-1 525 625 Loop B T C

87 #T-4511-2 525 625 Loop A T C

7.4.1.2 "A" MSIV Closesure (Log 5)

  1. Tag # Min Max Description 35 2LI-4627-1 0 100 Pzr Level 36 2PI-4624-2 1500 2500 Pzr Pressure 85 #T-4610-1 SI 625 Loop A T 90 #T-4710-1 525 625 Loop B T H H

86 #T-4611-1 525 625 Loop B T 87 #T-4611-2 525 625 Loop A T c 17 2JR-9005-1 0 110 Neutronflux(%)

i 1 2LI-1031-1 0 100 "A" S/G Level 3 2LI-1131-1 0 100 "B" S/G Level 2 2PI-1041-1 0 1200 "A" S/G Fressure  ;

4 2PI-1141-1 0 1200 "B" S/G Pressure

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ERC871030 12/03/87 7.4.1.3 Main Turbine Runback (Log 6)

  1. Tag # Min Max Description 35 2LI-4627-1 0 100 Pzr Level 36 2PI-4624-2 1500 2500 Pzr Pressure 85 #T-4610-1 525 625 Loop A T 17 2JR-9005-1 0 110 NeutronN1ux(%)

1 2LI-1031-1 0 100 "A" S/G Level 2 2PI-1041-1 0 1200 S/G Pressure 86 #T-4611-1 525 625 Loop B T c

87 #T-4611 525 625 Loop A T e

7.4.1.4 Loss of Main Circulating Water (Log 7)

  1. Tag # Min Max Description 35 2LI-4627-1 0 100 Pzr Level 36 2PI-4624-2 1500 2500 Pzr Pressure 85 #T-4610-1 525 625 Loop A T 17 2JR-9005-1 0 110 Neutronflux(%)

1 2LI-1031-1 0 100 "A" S/G Level 2 2PI-1041-1 0 1200 "A" S/G Pressure 86 2PI-1041-1 525 625 Loop B T 100 2PIS-0605 0 15 Condens8rVacuum 7.4.1.5 Reactor Trip, "D" RCP TRIP (Log 8)

  1. _ Tag # Min Max Description 35 2LI-4627-1 0 100 Pzr Level 36 2PI-4624-2 1500 2500 Pzr Pressure 85 #T-4610-1 525 625 Loop A T H

90 #T-4710-1 525 625 Loop B T H

86 #T-4611-1 525 625 Loop B T c

87 #T-4611-2 525 625 Loop A T 1 2LI-1031-1 0 100 "A"S/Gfevel 2 2PI-1041-1 0 1200 "A" S/G Pressure 72 #CV-9199 0 .13E7 Loop A RCS Flow 73 #CV-9200 0 .13E7 Loop B RCS Flow I 74 #CV-9201 0 .13E7 Loop C RCS Flow 75 #CV-9202 0 .13E7 Loop D RCS Flow 17 2JR-9005-1 0 110 Neutron Flux (%)

3 2LI-1131-1 0 100 "B" S/G Level 4 2PI-1141-1 0 1200 "B" S/G Pressure i

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ERC871030 12/03/87 7.4.1.6 Reactor Trip, "A" S/G Level (Log 9)

  1. Tag # Min Max Description 35 2LI-4627-1 0 100 Pzr Level 36 2PI-4624-2 1500 2500 Pzr Pressure 85 #T-4610-1 525 625 Loop A T 3 2LI-1131-1 0 100 "B"S/GOevel 1 2LI-1031-1 0 100 "A" S/G Level 2 2PI-1041-1 0 1200 "A" S/G Pressure 86 #T-4611-1 525 625 Loop B T 17 2JR-9005-1 0 110 Neutronflux(%)

6 2FP.-1029/30 0 6,500,000 A S/G Feed Flow 8 2FR-1129/30 0 6,500,000 B S/G Feed Flow 7.4.1.7 PARTIAL Loss of Offsite Power (Natural Circulation)

(Log 10)

  1. _ Tag # Min Max Description 35 2LI-4627-1 0 100 Pzr Level 4

36 2PI-4624-2 1500 2500 Pzr Pressure 4 2PI-1141-1 0 1200 S/G B Pressure 3 2LI-1131-1 0 100 S/G B Level 1 2LI-1031-1 0 100 S/G A Level 2 2PI-1041-1 0 1200 S/G A Pressure 85 #T-4610-1 525 625 Loop A T H

90 #T-4710-1 525 625 Loop B T H

72 #CV-9199 0 .13E7 Loop A RCS Flow 73 #CV-9200 0 .13E7 Loop B RCS Flow 74 #CV-9201 0 .13E7 Loop C RCS Flow 75 #CV-9202 0 .13E7 Loop D RCS Flow 17 2JR-9005-1 0 110 Neutron Flux (%)

86 #T4611-1 525 625 Loop B T c

87 #T-4611-2 525 625 Loop A T 7.4.1.8 Steam Line Break (100%) (Log 11)

  1. Tag # Min Max Description 36 2PI 4624-2 900 2300 Pzr Pressure 2 2PI-1041-1 0 1200 S/G A Pressure 4 2PI-1141-1 0 1200 S/G B Pressure 35 2LI-4627-1 0 100 Pzr Level 85 #T-4610-1 350 625 Loop A T H

90 #T-4710-1 350 625 Loop B T 57 2PI-5602-2 0 60 Cont.Pr$ssure 58 2TI-5664-2 0 309 Cont. Temperature 17

ERC871030 12/03/87 7.4.1.9 LOCA (100%) (Log 12)

  1. Tag # Min Max Description 57 2PI-5602-2 0 60 Cont. Pressure 58 2TI-5664-2 0 300 Cont. Temperature 36 2PI-4624-2 0 2400 Pzr Pressure 2 2PI-1041-1 0 1200 S/G A Pressure 4 2PI-1141-1 0 1200 S/G A Pressure 35 2LI-4627-1 0 100 Pzr Level 85 #T-4610-1 350 625 Loop A T H

90 #T-4710-1 350 625 Loop 8 T H

7.5 Tape Save 7.4.1 Record Tape Serial No.

8.0 FINAL CONDITIONS Transient tests have been run, data collected, attached, and saved.

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ERC871030 12/03/87 ATTACHMENT B-1 TURBINE TRIP / REACTOR TRIP /HIGH MSR LEVEL 19

ERC871030 12/03/87 ATTACHMENT B-2 "A" MSIV CLOSURE I

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ERC871030 12/03/87 ATTACHMENT B-3 MAIN TURBINE RUNBACK t

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ERC871030 12/03/87 ATTACHMENT B-4 LOSS OF MAIN CIRC WATER

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ERC871030 12/03/87 ATTACHMENT B-5

-"D" RCP TRIP f

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ERC871030 12/03/87 ATTACHMENT B-6 RX TRIP "A" S/G LEVEL 24

ERC871030 12/03/87 ATTACHMENT 8-7 LOSS OFF SITE POWER (N/C) l l

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ERC871030 12/03/87 I

ATTACHMENT B-8 l STEAM LINE BREAK (100%)

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ERC871030 12/03/87 ATTACHMENT B-9 LOCA (100%)

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3 E2C871030 12/63/87 7.3 Malfunctions NOTE: Testing all of ANS-3.5, 1985, 3.1.2 malfunctions is required every 4 years. To ensure this is done, a cinimum of 25% of the malfunctions are to be tested each year.

7.3.1 Test the following malfunctions annually at BOL and E0L to evaluate inherent Core characteristics:

2. Small Steam Leak
3. Dropped CEA
4. Loss of SDC Flow
5. Loss of One MFWP
  • 6. T/G Runback (Loss of ACW to SWC)
  • These malfunction will be recorded on tape, saved, plotted and attached with the traasient data.

A. Main Steam Line Break - Tape Serial

1) BOL - Log #13 (Start )(Stop )
2) E0L - Log #14 (Start )(Stop )
8. T/G Runback
1) BOL - Log #15 (Start );. top )
2) E0L - Log #16 (Start )(Stop )

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ERC871030 12/03/87 7.3.2 Test the following malfunctions during Year 1 (1989) at M0L:

Malfunction I . C. Severity

1. 0 LOCA (In CVCS) 1 2.0 Loss of CCW to L/D Hx 1
3. 0 Defeat Selected Group Rod Motion 15 4.0 Loss of all Feedwater 1 5.0 Loss of Both MFW Pumps 1 6.0 MFRV Failed Closed 1 7.0 Loss of S.W. Pump 1 8.0 Main Genertaor Trip 1 9.0 Main Turbine Trip 1 _

10.0 Stuck CEA 15 11.0 Degraded Rod Motion 15 12.0 Loss of Stator Cooling 1 13.0 Defeat CEA Command 15 14.0 Small Steam Leak (Down-stream MSIVs) 1 15.0 Pzr BU Htrs On 1 16.0 Loss of Turbine L.O. 1 17.0 Indavertent SIAS 1 29

ERC871030 12/03/87 7.3.3 Test the following malfunctions during Year 2 (1990) at MOL Malfunction I.C. Severity

1. 0 Uncontrolled CEA Group Withdrawal 15 2.0 SGTR (>CCP Capacity) 1 3.0 SGTR (<CCP Capacity) 1 4.0 LOCA (Large:Inside Cont.) 1 5.0 LOCA (<CCP Capacity:Inside Cont.) 1 6.0 MSLB (Large:Inside Cont.) 1 7.0 Feedwater Controller Failure 1 8.0 MSLB (Large: Downstream MSIV's) 1 9.0 Pzr Steam Space feak (Large) 1 10.0 Pzr Safety Valve Failed Open 1 11.0 Pzr Spray Valve Failed Open 1 12.0 Dropped CEA 1 13.0 Loss of SDC Flow 10 14.0 Ejected CEA 1 15.0 Vacuum Pump Fail 1 16.0 LPSI Pump Fail 10 7.3.4 Test the following malfunctions during Year 3 (1991) at MOL:

Malfunction I.C. Severity 1.0 Loss nf 1 MFW Pump (A Pump) 1

2. 0 MFRV Failed Open 1 3.0 Failure of Reactor Trip 1 4.0 Emergency Boration 15 30

ERC871030 12/03/87 Malfunction I . C. Severity 5.0 Lot,s of A.C. Busses 1 6.0 Loss of 0.C. Busses 1 7.0 Turbine Bypass Valve Failed Open 17 8.0 Blackout 1 9.0 Loss of S.W. To SDC Hx 10 10.0 Loss of S.W. To Indiviaual Components 1 11.0 Loss of "A" Heater Drain Pump 1 12.0 Condensate Pump Trip 1 13.0 Gland Seal Fiiled 1 7.3.5 Test the following malfunctions during ear 4 (1992) at MOL:

Malfunction I.C. Severity 1.0 High RCS Activity (Failed Fuei) 1

2. 0 Loss of Protection System Channel 1 3.0 Loss of EDG (Surveillance) 1 4.0 Loss of CCW Pump 1 5.0 Total Loss of CCW 1 6.0 1 Linear Safety Channel Failed High 1 7.0 2 Linear Safety channels Failed High 1 __

8.0 Loss of C1g Wtr - RCP 1 9.0 2P78 Failure 1 10.0 2P7A Failure 1 __

11.0 Loss of Instrument Air 1 31

ERC871030 12/03/87 ,

Malfunction I.C. Severity 12.0 T/G Runback (loss of ACW SWC)

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13.0 Uncontrolled Rod Withdrawal /

Insertion 14.0 FW Line Break 1 15.0 Turbine High Vibration 1 16.0 Chargirig Pump Fail 1 i

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