ML112212228
| ML112212228 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/13/1990 |
| From: | IES Utilities, (Formerly Iowa Electric Light & Power Co) |
| To: | |
| Shared Package | |
| ML112212226 | List: |
| References | |
| NUDOCS 9011050029, PROC-900813-01 | |
| Download: ML112212228 (15) | |
Text
Attachment 3 NG-90-2548 Rev. 0, 07/16/90 DUANE ARNOLD ENERGY CENTER NRC REQUALIFICATION EXAM SIMULATOR EVALUATION SCENARIO GUIDE NUMBER 17 TITLE: MSL Rupture Outside Primary Containment DEVELOPED BY:
OPERATIONS SUPERVISOR APPROVAL:
TRAINING SUPERVISOR APPROVAL:
Name Name Date Date Date Name 901105)029 901024 FDR AOIICK0500331 V
PDC Evaluation Scenario Guide 17
Rev. 0, 07/16/90 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.
bT 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 17 1
Rev. 0, 07/16/90
- 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.
I1. The NSOE/ANSOE will be able to perform the following operator actions, in response to plant events:
- a.
Diagnoses failed Group 5 isolation.
- b.
Maintains RPV level above + 15".
Evaluation Scenario Guide 17 2
Rev. 0, 07/16/90 NARRATIVE
SUMMARY
The plant is operating at 100% power. No LCO's currently exist. All major plant equipment is operable.
An inadvertent RCIC initiation occurs and causes a small Fuel cladding failure. Radiation levels will increase slightly and RWCU HX Room ARM will alarm, requiring entry into EOP-3.
A leak in the RWCU heat exchanger room occurs and MO 2700 fails to isolate. The RWCU leak causes ARM's to alarm in more than one area. The operators will enter EOP-1, reduce power and scram the reactor. The scram will fail and the ATWS EOP will be entered.
Emergency depressurization caused by ARM's above max safe setpoints per EOP-3 will be required. Rods will insert when ED is directed.
Evaluation Scenario Guide 17 3
Rev. 0, 07/16/90 SIMULATOR SETUP
- 1.
GENERAL INSTRUCTIONS
- a.
Reset to I.C. 14
- b.
Verify rod pull sheet correct.
- 2.
LIST OF MALFUNCTIONS Verify E3 is RDPACC <1460 Type RMF ESG17 Time Malfunction Malfunction Title ET Delay F.
Ramp No.
Sev.
Sev.
0 MS28A MO 2700 Fails to isolate 0
RM01 ARM Upscale E3 75%
8 42 RE9156 mn.
0 RMOI ARM Upscale E3 90%
8 55 RE9157 mm.
0 RMO1 ARM Upscale E3 75%
12 30 RE9167 mm.
0 RM01 ARM Upscale E3 80%
12 32 RE9169 mn.
0 RM01 ARM Upscale E3 75%
12 30 RE9176 mn.
RPO5B RPS manual scram fail 0
RP05D RPS fuses fail 0
RPO5E Scram switches fail 2
RCO8 Inadvertent RCIC initiation 5
RXO1 Fuel Cladding 3%
2 Failure min.
10 CUl0 Leak in RWCU 2%
10 HX Room min.
Evaluation Scenario Guide 17 4
Rev. 0, 07/16/90
- 3.
LIST OF OVERRIDES ROR ESG 17 for MO 2700 fail to isolate/RCIC Auto Initiation.
Time Override Value t = 0 RWCU Inboard Isol. Valve MO 2700 OPEN Handswitch t = 0 MO 2700 Red light-lC04 ON t = 0 MO 2700 Red light-PC Mimic ON t = 0 MO 2700 Green light-lC04 OFF t = 0 MO 2700 Green light-PC Mimic OFF t = 0 AN: IC05A[8]
OFF (Delete if level drops to Lo-Lo)
Evaluation Scenario Guide 17 5
Rev. 0, 07/16/90 LIST OF CRITICAL TASKS Evaluation Scenario Guide 17 CRITICAL TASKS RO/SRO
- 1.
Declare 7 day LCO per TS 3.5.E.2 A OSS
- 2.
Recognize MO 2700 fails to isolate and attempt to isolate.
NSOE
- 3.
Directs manual scram when any area reaches its max. safe operating A OSS limit.
- 4.
Manually scrams Reactor when directed.
ANSOE
- 5.
Recognize that all rods did not fully insert.
ANSOE
- 6.
Perform Alternate Rod Insertion procedures per EOP-C section 5.0 B OSS as directed.
- 7.
Manually insert rods as directed.
ANSOE
- 8.
Maintain RPV level above + 15".
ANSOE
- 9.
Direct Emergency Depressurization when 2 like parameters in more A OSS than one area exceeds max safe operating limits.
- 10.
Initiate Emergency Depressurization when directed.
NSOE
- 11.
Declare a SITE EMERGENCY.
A OSS
- 12.
Notify State/County within 15 minutes, NRC within one hour.
B OSS 6
Rev. 0, 07/16/90 SHIFT TURNOVER PLANT CONDITIONS: 100% reactor power, limiting control rod pattern.
EQUIPMENT STATUS: No inop equipment.
Evaluation Scenario Guide 17 7
0 0
0
-J TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED ACTIONS/BEHAVIOR T = 0 min.
Verify required malfunctions are Crew familiarizes themselves with the plant conditions.
inserted per the Table for T = 0.
(Event trigger E3 is the scram).
T = 2 min.
Insert malfunction RCO8 Crew responds to RCIC initiation by:
(Inadvertent RCIC initiation).
Tripping RCIC after verifying adequate core cooling.
Act as SANSOE if crew wants RCIC "A" OSS declares RCIC inop and enters a 7 day LCO.
room investigated. After 2 min.
report everything is normal.
After crew trips RCIC and system is shutdown:
Override ON: ICO5B E7 (RCIC Auto Initiated)
Override OFF: ICO4C D5 (RCIC Lo Suction Trip)
Insert malfunction RCO2 (RCIC Turbine Trip)
Delete malfunction RCO8 (Inadvertent initiation)
Delete override of ICO5A A8 (Reactor Lo Lo Level Trip)
T = 5 min.
Insert malfunction RXO1 (Fuel Crew responds to Rx Bldg. ARM Hi Rad Alarm (ICO4B Cladding Failure), 3% severity over A-6):
a 2 minute ramp rate.
At Panel ICll, monitor ARM's - note RWCU HX Room is alarming.
Send an Operator to investigate locally.
Enter EOP 3 and continue monitoring ARM's.
Note: * = Critical Task tb 0
'0 C
C.
fs TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED ACTIONS/BEHAVIOR T = 10 min.
Insert malfunction CUIO (Leak in Crew responds to Steam Leak Detection Alarms (lCO4B RWCU Hx room, 2% severity, B-4 and D-4) 10 minute Ramp rate)
At Panel 1C21, monitor temps - note RWCU temp.
alarms Act as SANSOE to investigate the RWCU Hx room. After Two NSOE: Recognizes MO 2700 fads to isolate and minutes report:
attempts to isolate.
Water and steam are coming out "A" OSS: Directs manual Scram when any area of the door.
Can hear flow noise in the room.
rahsismx aeoeaiglmt ANS CTE:
Manually Scrams Reactor when directed.
- ANSOIE:
Recognizes that all rods did not fully insert.
Crew responds to failure to Scram.
OSS directs other actions be taken to scram the Reactor per ATWS [OP and/or EOIP C's.
NSS directs RPV level maintaied above + 15".
- " OSS directs ADS be locked out.
S ecSS directs EHC pressure set lowered to 880 psig and stabilizes pressure with the Main Turbine or other systems as required.
- B OISS: Perform Alternate Rod Insertion procedures per [OP-C section 5.0 as directed.
ANSOE: Manually insert rods as directed.
NSiE:
Maintains RPV level above + 15".
"A" OSS: Declares a Site Emergency.
"B" OSS: Notifies state and county within 15 minutes, and NRC within I
hour.
0 0
.4 0"
0
on n
TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED ACTIONS/BEHAVIOR T = 20 min.
Verify ARM malfunctions have inserted and are active (RMO1 RE 9156, 9157, 9167, 9169, 9176).
When ED is directed, vent scram air
- header:
IMF RD13 at 100%.
A OSS: Directs ED when 2 like parameters in more than one area exceed max. safe operating limits.
A OSS: Directs injection into RPV secured except Boron, CRD, and RCIC.
NSOE: Initiates ED when directed.
Crew recognizes rods inserting.
A OSS exits ATWS EOP and re-enters EOP-I after all rods verified inserted.
A OSS directs level restoration to 170-211 inches.
T = 40 min.
After ED complete, ramp (After ED) malfunctions RMO1RE 9156, 9157, 9167, 9169, 9176 from Asis to 50%
over 15 minutes.
T = 50 min.
When the reactor is shutdown with water level restored, pressure being intentionally lowered, or ED done, containment parameters under control, and the OSS has addressed the EPIP's, terminate the scenario by placing the simulator in Freeze.
X 0v G
Rev. 0, 07/16/90 REFERENCES PROCEDURE SECTION PROCEDURE REVISION Operating Instructions 01 150 (RCIC) 9 Integrated Plant Operating Inst IPOI 5 3.2 4
Annunciator Response Procedures ICO4B B-4, D-4, A-6 11 ICO5B E-7 12 Emergency Operating Procedures EOP I RC, RC/L, RC/P 0
EOP 3 S/T 0
EOP C's 5.0 11 Emergency Plant Implementing Procedures 1.1, 1.2, 1.3 60 Evaluation Scenario Guide 17 11I
Rev. 0, 07/16/90 ENTRY CONDITION: Any Auto Reactor Scram Signal - Full Scram K/A System/Evolution Ability No.
RO/SRO 212000 RPS A 1.06 4.2/4.2 A1.07 3.4/3.4 A1.08 3.4/3.4 A1.11 3.4/3.3 A2.20 4.1/4.2 A3.01 4.4/4.4 A3.03 4.2/4.2 A3.04 3.9/3.8 A3.05 3.9/3.9 A3.07 3.6/3.6 SG #13 4.1/4.1 SG #14 4.3/4.4 295006 Scram Abnormal Plant Evolution AAl.01 4.2/4.2 AAl.02 3.9/3.8 AA1.03 3.7/3.7 AAl.04 3.1/3.2 AA1.05 4.2/4.2 AA1.06 3.5/3.6 AA1.07 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 DAEC System RO Task No.
SRO Task No.
IPOI (SSS)
- SSS.004
- SSS.004 UUU.018 Admin (UTJU)
UUU.027 Evaluation Scenario Guide 17 12
Rev. 0, 07/16/90 ENTRY CONDITION: RCIC Initiation K/A System/Evolution Ability No.
RO/SRO RCIC System SG #1 3.7/4.0 SG #5 3.3/4.3 SG #6 2.7/3.8 SG #8 3.8/3.6 SG #14 4.0/3.6 ENTRY CONDITION: RWCU Unisolated Leak K/A System/Evolution Ability No.
RO/SRO High Secondary Containment Temperatures EA 1.01 3.6/3.7 EA 1.02 3.4/3.5 EA 1.05 3.7/3.9 EA 2.01 3.8/3.8 EA 2.03 3.8/4.0 SG #1 3.1/4.0 SG #5 3.8/3.7 SG #6 3.8/3.7 SG #9 3.8/3.6 SG #11 4.1/4.2 SG #12 3.6/4.4 ENTRY CONDITION:
K/A System/Evolution Ability No.
RO/SRO High Secondary Containment Area Radiation Levels EA 1.01 3.9/4.0 EA 1.05 3.9/4.0 EA 2.01 3.8/3.9 EA 2.03 3.7/4.2 SG #1 3.4/4.2 SG #2 3.1/4.5 SG #11 4.0/4.5 SG #12 3.8/4.4 Evaluation Scenario Guide 17 13
Rev. 0, 07/16/90 ENTRY CONDITION: Emergency Depressurization K/A System/Evolution Ability No.
RO/SRO Automatic Depressurization System A 1.04 4.1/4.2 A1.06 4.1/4.3 A2.01 4.1/4.3 A3.06 3.9/3.9 A3.08 4.2/4.3 A3.09 4.1/4.2 A4.01 4.4/4.4 A4.09 3.9/3.9 A4.12 4.2/4.3 SG #1 4.2/4.3 SG #9 4.4/4.1 SG #14 4.1/3.8 SG #15 4.2/4.4 ENTRY CONDITION:
K/A System/Evolution Ability No.
RO/SRO Low Reactor Water Level AAl.01 3.9/3.9 AA1.02 4.0/4.0 AA2.01 4.2/4.2 AA2.03 2.9/2.9 SG #6 3.9/3.9 SG #10 4.2/4.0 SG #1l 4.3/4.5 SG
- 12 3.8/4.4 DAEC TASKS ENTRY CONDITION:
SRO Task No.
ADS (D)
D.0002 D.0002 RHR (L)-
L.0009 L.0009 EOP's (TTT)
TTT.0012 TTT.0012 TTT.0020 TTT.0017 TTT.0021 Evaluation Scenario Guide 17 14