ML112212227

Scenario Guide 2a, Loss of Fw/W HPCI Inop.

ML112212227
Person / Time
Site:	Duane Arnold
Issue date:	08/13/1990
From:	IES Utilities, (Formerly Iowa Electric Light & Power Co)
To:
Shared Package
ML112212226	List: ML112212225 ML112212227 ML112212228 ML112212229
References
NUDOCS 9011050028, PROC-900813
Download: ML112212227 (20)

Text

Attachment 2 NG-90-2548 Rev. 0, 08/10/90 DUANE ARNOLD ENERGY CENTER NRC REQUALIFICATION EXAM SIMULATOR EVALUATION SCENARIO GUIDE NUMBER 2a TITLE: Loss of FW/W HPCI INOP Reference Leg Leak - IA3 Lockout DEVELOPED BY:

N Dat /

OPERATIONS SUPERVISOR APPROVAL:

Name Date TRAINING SUPERVISOR APPROVAL:

Name Date 90C1 1050C2E: . 11, FEIR ~~J (((()~

VFT:

Evaluation Scenario Guide 2a

Rev. 0, 08/10/90 OBJECTIVES A. TERMINAL OBJECTIVE:

The operator, acting as a member of a shift operating crew, must demonstrate competence in performance of license duties required to protect the public health and safety while operating the plant in accordance with approved instructions and procedures.

B. ENABLING OBJECTIVES:

1. Following a pre-shift brief, each crew member will be able to provide a detailed plant status report to include:

a. Status of safety-related systems, running equipment, and inoperable equipment.

b. STPs in progress and any existing LCOs.

c. Pertinent night orders and planned evolutions.

2. Using plant installed instrumentation and plant procedures, as well as information obtained by operating personnel outside the Control Room, the operating crew will correctly diagnose plant problems.

3. The OSS will be able to use appropriate plant procedures to ensure completion of immediate actions and direct subsequent actions as required.

4. When using plant procedures, the NSOE/ANSOE will be able to:

a. Locate the proper section of the procedure.

b. Follow the procedure correctly.

c. Locate and observe installed instrumentation.

d. Analyze system response.

e. Direct plant operators (Second ANSOE and Auxiliary Operators).

f. Inform the OSS when complete.

5. While operating in accordance with the Emergency Operating Procedures, the OSS will:

a. Identify all EOP entry conditions.

b. Direct the NSOE/ANSOE to perform required actions for control of reactor power, level, pressure, or containment parameters.

c. Specify the plant systems to be used to control plant parameters.

d. Evaluate changes in plant conditions against current actions being taken and make corrections as necessary.

6. When directed by the OSS to perform actions in accordance with the Emergency Operating Procedures, the NSOE/ANSOE will:

a. Utilize the systems designated by the OSS.

Evaluation Scenario Guide 2a I

Rev. 0, 08/10/90

b. Monitor system performance; i.e., pressure flow, etc.

c. Inform the OSS immediately when a system becomes unavailable for further use.

d. Inform the OSS of plant trends in response to actions taken.

7. Given a set of plant conditions, the OSS will be able to comply with the requirements of Technical Specifications and the Administrative Procedures.

8. The OSS will be able to utilize the Emergency Plan to properly:

a. Evaluate plant conditions and determine the emergency classification.

b. Ensure requisite notifications are made.

9. The STA will assist the operating crew as required to:

a. Ascertain that plant response is as predicted in the UFSAR during transients, accidents, and plant emergencies and report abnormalities to the OSS.

b. Provide technical assistance and perform whatever activities are deemed necessary by the OSS because of specific plant conditions.

c. Review the status of inoperable equipment to determine whether the loss of the equipment is a situation addressed by Technical Specifications requiring specific action by the plant staff.

10. The crew members will demonstrate effective communications, exchanging complete and relevant information in order to make team decisions in a timely manner.

11. The NSOE/ANSOE will be able to perform the following operator actions, in response to plant events:

a. IPOI-5 Immediate Actions for Scram.

b. Initiate Torus Cooling with a LPCI initiation signal present.

c. Operate ECCS Systems to restore RPV level.

d. Emergency depressurize when directed.

Evaluation Scenario Guide 2a 2

Rev. 0, 08/10/90 NARRATIVE

SUMMARY

During operation at rated power, the crew is scheduled to perform STP 45D002 HPCI INOP PACKAGE, because HPCI failed its operability test last shift due to a faulty EGM Controller and is inop. The 'A' CRD pump is inop for motor bearing replacement.

"A" Loop of Torus cooling is on with A and C RHR pumps running. "C" RHR pump trips which puts crew in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Tech Spec. LCO with HPCI INOP.

A leak develops in the "A" GEMAC reference leg (CC-4561). This produces a small break LOCA inside containment, but more significantly the leak causes increasing level on LI-4561 and LI-4559. Feedwater level control is selected to "B" level LI-4560 so there is no initial impact on actual RPV level. When indicated level on LI-4561 and 4559 reaches 211" a trip of the turbine and both RFPs occurs. The turbine trip produces a reactor scram and EOC RPT.

Turbine Bypass valves fail close so that LLS valves PSV 4401 and 4407 will open to control pressure. RCIC will be lost when it starts. When drywell pressure increased to 2 psig bus IA3 will be lost due to a bus lockout. Drywell spray valve 1902 will not operate when required.

Other systems respond as expected, but high pressure makup from RCIC and CRD is insufficient to maintain RPV level above + 15". Emergency depressurization will be required due to high drywell temperature resulting from Drywell spray failure, and to allow restoration of level using RHR and Core Spray. Depressurizing will cause entry into the RPV saturation curve, requiring RPV Flooding.

Evaluation Scenario Guide 2a 3

Rev. 0, 08/10/90 SIMULATOR SETUP

1. GENERAL INSTRUCTIONS

a. Initialize the simulator to IC-20. CHECK MALFUNCTION FILE ESG 2 per (2).

b. Place the simulator in Run.

c. Place the A RHR loop in Torus cooling, place both ESW pumps in service.

d. Ensure that all annunciators are acknowledged and the plant is stable.

e. Advance the chart paper in the recorders.

f. Tag out HPCI Aux Oil in P-T-L pump and Isolation Valves closed. Remove light bulbs to simulate breakers opened if overrides not working.

g. Tag out 'A' CRD pump.

2. LIST OF MALFUNCTIONS Verify E8 is RCVPM02404 >.1 and El I is PCPDWG > 2 and Type RMF ESG2.

Time Malfunction No. Malfunction Title F ET Delay F. Ramp '

Sev Sev.

O HPO2 HPCI Turbine Trip 0 TCO6A BPV #1 F/C 0%

0 TCO6B BPV #2 F/C 0%

0 RDIlA A CRD pump trip.

10-15 RR27A "A" GEMAC Ref 100 4 min.

leak MS02 Ell 1% 120 sec.

2 EDO8C IA3 Lockout ElI psig DW 0 RCO6 Steam leak RCIC E8 30 5 1 mn as

_ sec is 5 RHOIC RHR pump trip Evaluation Scenario Guide 2a 4

Rev. 0, 08/10/90

3. LIST OF OVERRIDES Type ROR ESG2 TAG ET DEL OR VALUE ZDIRHHS1902 close ZLOHPHS2238 [Red] off AN: ICO3C[25] off ZLOHPHS2238 [Green] off ZLOHPHS2299 off ZLOHPHS2239 [Green] off ZLORDHSl807A [Red] off ZLOHPHS2239 [Red] off ZLORDSH 1807A [White] off ZLOHPHS2256 [Green] off ZLORDHSl807A [Green] off ZLOHPHS2256 [Red] off ZLOHPMO2238 [Green] off ZLOHPMO2238 [Red] off ZLOHPMO2239 [Green] off ZLOHPMO2239 [Red] off ZAOHPPI2207 0 Evaluation Scenario Guide 2a 5

Rev. 0, 08/10/90 LIST OF CRITICAL TASKS CRITICAL TASKS RO/SRO

1. Declare 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO IAW T.S. 3.5.D. A OSS

2. Declare Unusual Event (Tech. Spec. - Shutdown) A OSS

3. Notify State/County within 15 minutes. B OSS Notify NRC within I hour.

4. Directs Emergency Depressurization when drywell temperature cannot A OSS be maintained < 280'F.

5. Initiate Emergency depressurization when directed. NSOE

6. Direct level restoration by establishing minimum flooding pressure. A OSS

7. Restore level by injecting with systems as necessary to establish ANSOE minimum flooding pressure when directed.

8. When manual control of Bypass valves is attempted, recognize failure ANSOE of valves to open.

9. Declare Alert. A OSS

10. Notify State and County within 15 minutes. (TC) B OSS Notify NRC within one hour.

11. Evacuate the plant if an alert is declared. B OSS

12. Direct Torus Spray before Drywell pressure reaches 9 psig. A OSS

13. Initiate Torus spray when directed. NSOE Note: Specific critical tasks may be assigned to specific individuals; however, any crew member may perform the task without causing a failure of the assigned individual.

Evaluation Scenario Guide 2a 6

Rev. 0, 08/10/90 SHIFT TURNOVER PLANT CONDITIONS: The plant is operating at rated power.

EQUIPMENT STATUS: HPCI was just declared inop last shift due to a faulty EGM controller. HPCI turbine cannot be used because of overspeed potential. All other valves/components not tagged out by HPCI tagout can be used. 'A' CRD pump is inop due to a bad motor bearing.

All STPs for HPCI inop package (45D002) are complete except RCIC operability (45E001-LCO). "A" loop of RHR is in Torus cooling for RCIC operability.

Evaluation Scenario Guide 2a 7

S TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED ACTIONS/BEHAVIOR T = 0 When the operators have OSS directs RCIC operability STP per Tech Specs. C C

familiarized themselves with the Os

= current plant conditions. OSS verifies prerequisite, authorizes STP.

S

-I 5.

C, ____________________________ Conduct RCIC Valve Operability checks.

= T = 5 minutes Activate Malfunction RHOIC A 055: Determines RHR pump inoperable.

I' S Auxiliary Operator: Report that the pump breaker lockout relay is A OSS: Declare 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO lAW Tech. Spec. 3.5.1 tripped and the time overcurrent relay is tripped.

Note: 'A' pump may trip on Runout; it can be restarted if trip clear: EDO5 clear, then reset.

As SANSOE report that the C RHR pump coupling is broken.

Function as security and outside A 055: Declare unusual event.

agencies as notifications are made.

• B OSS: Notify state/county within 15 minutes, and

______________________NRC within I hour.

When All Activate malfunction RR27A at calls are being 100% on 4 minute ramp to initiate made or GEMAC "A" Reference Leg Leak.

30 minutes after RHR pump C is tripped.

Note:

• Critical task involved.

O

TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED ACTIONS/BEHAVIOR 4 C

Crew responds to Turbine Trip, Reactor Scram, Loss of 0

Feedwater. 00 C

A 0co: Enter EOP- I on low reactor level and high

0. reactor pressure.

NSOE: Manually initiate RCC when ordered.

A OSS: Enter EOP-3 on RCIC Room or steam tunnel high temperatures .

Crew responds to increasing Drywell pressure.

a May vent drywell per 01 573.

If drywell vented prior to 2 psig then

• May depressurize at normal cooldown rates.

insert malfunction ED08C bus lA3 a Recognize LLS is cycling.

lockout, and MS02 at l1% with 120 sec ramp. Act as Aux and report bus A OSS: Directs RCIC be used for level restoration and lockout is tripped and nothing else investigates level indication failure.

wrong, except "C" RHR pump. If electricians are present A3, "wil NSOE: Places Torus Cooling in service.

have the electricians check the bus".

• A OSS: Direct Torus Spray before Drywell Pressure reaches 9 psig.

• NSOE: Initiate Torus spray when directed.

• ANSOE: When manual control of Bypass valves is attempted, recognize failure of valves to open.

Instructor act as SANSOE and close Crew monitors containment parameters.

V-19-48 in Torus if required.

Crew recognizes loss of IA3 bus and investigates bus lockout.

IQ

4 C TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED ACTIONS/BEHAVIOR 4 t 40 minutes If "B" and "D' RHR pumps trip on

• A OSS: Direct Drywell spray prior to 280 or after C runout, they can be reset: EDO5 Torus pressure exceeds 9 psig if allowed by DSIL.

C 00

= clear, then reset.

C

• Recirc secured C

0 DW Fans secured a:

I..)

• NSOE: Recognizes MO-1902 cannot be opened.

• Informs OSS cannot spray drywell.

• A OSS: Direct Emergency Depressurization when Drywell Temperature cannot be maintained < 2800 F.

• NSOE: Initiate Emergency Depressurization when directed.

• ANSOE: Restore level by injecting with systems as necessary to establish minimum flood pressure when directed

• A OSS: Declare an Alert

• B OSS: Notify State/County within 15 minutes.

Notify NRC within I hour.

• B OSS: Evacuate the plant if an alert is declared.

Terminate scenario when minimum flooding pressure has been established and stabilized.

G

Rev. 0, 08/10/90 REFERENCES PROCEDURE SECTION PROCEDURE REVISION Surveillance Test Procedures STP 45E001-Q RCIC Operability 4 Operating Instructions OI-149RHR 5.2 14 OI-416RHR-SW 4.0 5 01-150 RCIC 6.0 9 01-152 HPCI 5.1 14 Integrated Plant Operating Instructions 3.1, 3.2 IPO 5 4 Emergency Operating Procedures EOP-1 All 0 EOP-2 T/T 0 Emergency Inst.

EPIP 1.1, 1.2 57 Abnormal Operating Procedures AOP 301 Possible EOP Contingencies Emergency Depressurization RPV Flood Alternate Level Control Evaluation Scenario Guide 2a 11I

Rev. 0, 08/10/90 DAEC TASKS ENTRY CONDITION: LEAK IN GEMAC REFERENCE LEG CC-4561 K/A System/Evolution Ability No. RO/SRO 216000 Nuclear Boiler Instrumentation A2.03 3.0/3.1 A3.01 3.4/3.4 A4.01 3.3/3.1 ENTRY CONDITION: MAIN TURBINE GENERATOR TRIP (> 30% POWER)

K/A System/Evolution Ability No. RO/SRO 295005 Abnormal Plant Evolution AAl.01 3.1/3.3 AAl.02 3.6/3.6 AA1.04 2.7/2.8 AA1.05 3.6/3.6 AA1.07 3.3/3.3 AA2.04 3.7/3.8 AA2.07 3.5/3.6 AA2.08 3.2/3.3 DAEC TASKS ENTRY CONDITION: MAIN TURBINE GENERATOR TRIP (> 30% POWER)

DAEC System RO Task No. SRO Task No.

RECIRC (C) C.0002 C.0002 ADS/LLS (D) D.0002 D.0002 TURBINE (V) V.00 16 V.0016 RPS (KKK) KKK.0030 KKK.0030 IPOIs (SSS) SSS.0004 SSS.0004 EOPs (TTT) TTT.0011 TTT.0011 Evaluation Scenario Guide 2a 12

Rev. 0, 08/10/90 ENTRY CONDITION: ANY AUTO REACTOR SCRAM SIGNAL - FULL SCRAM K/A System/Evolution Ability No. RO/SRO 212000 RPS AAl.01 4.2/4.2 A1.06 3.4/3.4 A1.07 3.4/3.4 A 1.08 3.4/3.3 A1.11 4.1/4.2 A2.20 4.4/4.4 A3.01 4.2/4.2 A3.03 3.9/3.8 A3.04 3.9/3.9 A3.05 3.6/3.6 A3.07 4.1/4.1 SG #13 4.3/4.4 SG #14 295006 SCRAM Abnormal Plant Evolution AAl.01 4.2/4.2 AAl.02 3.9/3.8 AA1.03 3.7/3.7 AA l.04 3.1/3.2 AA1.05 4.2/4.2 AA 1.06 3.5/3.6 AA l.07 4.1/4.1 AA2.01 4.5/4.6 AA2.02 4.3/4.4 AA2.03 4.0/4.2 AA2.04 4.1/4.1 AA2.05 4.6/4.6 AA2.06 3.5/3.8 SG #6 4.1/4.2 SG #10 4.1/4.2 SG #ll 4.3/4.5 SG #12 3.8/4.4 DAEC TASKS ENTRY CONDITION: ANY AUTO REACTOR SCRAM SIGNAL - FULL SCRAM DAEC System RO Task No. SRO Task No.

IPOIs (SSS) SSS.0004 SSS.0004 Evaluation Scenario Guide 2a 13

Rev. 0, 08110/90 ENTRY CONDITION: LPCI LOOP SELECTION 2 PSIG/119.5" RPV LEVEL NO FAILURES K/A System/Evolution Ability No. RO/SRO 203000 RHR/LPCI: Injection Mode Al.01 4.2/4.3 A2.16 4.4/4.5 A3.01 3.8/3.7 A3.05 4.4/4.4 A3.06 3.7/3.6 A3.07 4.2/4.6 A3.08 4.1/4.1 DAEC TASKS ENTRY CONDITION: LPCI LOOP SELECTION 2 PSIG/1l9.5" RPV LEVEL NO FAILURES DAEC System RO Task No. SRO Task No.

RHR System (L) L.0002 L.0002 Evaluation Scenario Guide 2a 14

Rev. 0, 08/10/90 ENTRY CONDITION: RCIC INITIATION AT 119.5" RPV LEVEL K/A System/Evolution Ability No. RO/SRO 217000 RCIC A3.01 3.5/3.5 A3.02 3.6/3.5 A3.03 3.7/3.6 A3.04 3.6/3.5 A3.05 3.9/3.9 A3.06 3.5/3.4 DAEC TASKS ENTRY CONDITION: RCIC INITIATION AT 119.5" RPV LEVEL DAEC System RO Task No. SRO Task No.

RCIC (H) H.0003 H.0003 1.0009 H.0009 Evaluation Scenario Guide 2a IS

Rev. 0, 08/10/90 ENTRY CONDITION: REACTOR LOW WATER LEVEL (< 170").

K/A System/Evolution Ability No. RO/SRO 295031 Emergency Plant Evolution EA1.01 4.4/4.4 EA1.02 4.5/4.5 EA1.03 4.4/4.4 EAl.05 4.3/4.3 EA1.06 4.4/4.4 EA1.07 3.7/3.7 EAIl1O 3.6/3.7 EA1.12 3.9/4.1 EA2.01 4.6/4.6 EA2.03 4.2/4.2 EA2.04 4.6/4.8 SG #6 4.1/3.9 SG #10 4.0/3.8 SG #11 4.2/4.6 SG #12 3.9/4.5 Evaluation Scenario Guide 2a 16

Rev. 0, 08/10/90 ENTRY CONDITION: DW PRESSURE > 2 PSIG - TORUS WATER TEMP > 95 0 F K/A System/Evolution Ability No. RO/SRO T/T-I A1.01 4.0/4.0 219000 RHR/LPCI Torus/Suppression Pool Cooling Al.02 3.5/3.5 Mode A1.08 3.7/3.6 A2.14 4.1/4.3 A4.01 3.8/3.7 A4.02 3.7/3.5 A4.05 3.4/3.4 A4.06 3.9/3.7 A4.09 3.4/3.3 A4.14 3.7/3.5 SG #9 4.2/3.8 SG #13 3.9/3.7 PC/P-4 A1.01 3.8/3.9 230000 RHR/LPCI Torus/Suppression Pool Spray A2.15 4.0/4.1 M ode A4.01 3.7/3.5 A4.02 3.8/3.6 A4.05 3.2/3.1 A4.06 4.0/3.9 A.409 3.6/3.3 A4.16 3.8/3.8 DAEC TASKS ENTRY CONDITION: DW PRESSURE > 2 PSIG - TORUS WATER TEMP > 950 F DAEC System RO Task No. SRO Task No.

RHR (L) L.0009 L.0009 L.0016 L.0016 ADMIN (UUU) UUU.0050 UUU.051 UUU.0053 Evaluation Scenario Guide 2a 17

Rev. 0, 08/10/90 ENTRY CONDITION: HIGH DW TEMPERATURE K/A System/Evolution Ability No. RO/SRO 295028 HIGH DW TEMPERATURE EA 1.01 3.8/3.9 EA 1.03 3.9/3.9 EA 1.04 3.9/4.0 EA 2.01 4.0/4.1 EA 2.02 3.8/3.9 EA 2.03 3.7/3.9 SG #6 3.9/3.8 SG #11 4.2/4.4 SG #12 3.8/4.3 DAEC TASKS ENTRY CONDITION: HIGH DW TEMPERATURE DAEC System RO Task No. SRO Task No.

RHR (L) L.0016 L.0016 EOP's (TTT) TTT.0012 TTT.0012 TTT.0016 TTT.0016 TTT.0021 TTT.0021 TTT.0020 TTT.0020 Evaluation Scenario Guide 2a 18

Rev. 0, 08/10/90 ENTRY CONDITION: STEAM LEAK IN RCIC ROOM K/A System/Evolution Ability No. RO/SRO 295032 High Secondary Containment Area EA 1.01 3.6/3.7 Temperature EA 1.02 3.4/3.5 EA 1.03 3.7/3.7 EA 1.05 3.7/3.9 EA 2.01 3.8/3.8 EA 2.02 3.3/3.5 EA 2.03 3.8/4.0 SG #6 3.8/3.7 SG #1l 4.1/4.2 SG #12 3.6/4.4 DAEC TASKS ENTRY CONDITION: STEAM LEAK IN RCIC ROOM DAEC System RO Task No. SRO Task No.

EOP's (TTT) TTT.0013 TTT.0013 RCIC (H) H.0027 H.0027 Evaluation Scenario Guide 2a 19