ML100880258
| ML100880258 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 09/21/2009 |
| From: | Garchow S Operations Branch IV |
| To: | |
| References | |
| CN-2009-09 | |
| Download: ML100880258 (22) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Cooper Nuclear Station__________
Date of Examination: _9/21/2009___
Examination Level: RO X SRO Operating Test Number: __________
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations S, D, P Obtain and Interpret a GARDEL Periodic Case Conduct of Operations NOT TESTED Equipment Control R, D Determine isolation boundaries for REC pump wearing ring replacement.
Radiation Control R,D Radiation Protection Table top scenario Emergency Procedures/Plan R, N Determine RPV water level instrumentation availability during LOCA conditions NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Cooper Nuclear Station__________
Date of Examination: _9/21/2009___
Examination Level: RO SRO X Operating Test Number: __________
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R, D Issue a Fire Impairment Conduct of Operations R, D Determine if Shift Staffing requirements are adequate for mode change Equipment Control R, D Review Jet Pump Operability Test Radiation Control R, D Review and Approve a Liquid Radioactive Waste Discharge Permit Emergency Procedures/Plan M, S, P EAL Table Top (will be upon completion of scenario #1)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Cooper Nuclear Station____________
Date of Examination: _9/21/2009____
Exam Level: RO X SRO-I SRO-U Operating Test No.: ______________
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a.
Respond to a Trip of a Reactor Recirc Pump (Alternate Path)
A,D,S 1
- b. Perform quick Restart of RFPT B (Hard Card) (Alternate Path)
A,M,P,S 2
- c.
High Pressure Coolant Injection / Manually Initiate EN,M,S, L 4
- d. Verify group 3 Primary Containment Isolation (Alternate Path)
A,D,S 5
- e.
Transfer of 4160V Bus 1G from DG2 to Emergency Transformer D,L,P,S 6
- f.
Install EOP PTMs 57, 58, 59, 60 D, S 7
A,EN,M,S,L 9
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
Manually Vent the Scram Air Header E,D,P,R 1
- j.
Respond to No Break Power Panel Failure (Alternate Path)
A,D 6
- k. Inject Fire Water into RHR (Level control)
D,E 2
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Cooper Nuclear Station____________
Date of Examination: _9/21/2009____
Exam Level: RO SRO-I SRO-U X Operating Test No.: ______________
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a.
- b.
- c. High Pressure Coolant Injection / Manually Initiate EN,M,S,L 4
- d.
- e.
- f.
- g.
A,EN,M,S,L 9
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j. Respond to No Break Power Panel Failure (Alternate Path)
A,D 6
- k. Inject Fire Water into RHR (Level control)
D,E 2
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Cooper Nuclear Station____________
Date of Examination: _9/21/2009____
Exam Level: RO SRO-I X SRO-U Operating Test No.: ______________
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a.
Respond to a Trip of a Reactor Recirc Pump (Alternate Path)
A,D,S 1
- b. Perform quick Restart of RFPT B (Hard Card) (Alternate Path)
A,M,P,S 2
- c.
High Pressure Coolant Injection / Manually Initiate EN,M,S, L 4
- d. Verify group 3 Primary Containment Isolation (Alternate Path)
A,D,S 5
- e.
Transfer of 4160V Bus 1G from DG2 to Emergency Transformer D,L,P,S 6
- f.
Install EOP PTMs 57, 58, 59, 60 D, S 7
- g.
A,EN,M,S,L 9
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
Manually Vent the Scram Air Header E,D,P,R 1
- j.
Respond to No Break Power Panel Failure (Alternate Path)
A,D 6
- k. Inject Fire Water into RHR (Level control)
D,E 2
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Cooper Date of Exam:
9/21/2009 Operating Test No.:
Scenarios 1 (SPARE) 2 3
4 CREW POSITION CREW POSITION CREW POSITION CREW POSITION M
I N
I M
U M(*)
A P
P L
I C
A N
T E
V E
N T
T Y
P E
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
T O
T A
L R
I U
RX 1
1 1
1 0 NOR 1
1 1
1 1 I/C 3
1 4
4 4 2 MAJ 1
1 2
2 2 1 RO 1 X
SRO-I SRO-U TS 0
0 2 2 RX 1
1 1
1 0 NOR 1
1 1
1 1 I/C 3
3 6
4 4 2 MAJ 1
1 2
2 2 1 RO 2,3 X
SRO-I SRO-U TS 0
0 2 2 RX 1
1 1
1 0 NOR 1
1 1
1 1 I/C 3
1 4
4 4 2 MAJ 1
1 2
2 2 1 RO 4 X
SRO-I SRO-U TS 0
0 2 2 RX 1
1 1
1 0 NOR 1
1 1
1 1 I/C 3
3 6
4 4 2 MAJ 1
1 2
2 2 1 RO 5,7 X
SRO-I SRO-U TS 0
0 2 2
Instructions:
- 1.
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301 Transient and Event Checklist Form ES-301-5 Facility:
Cooper Date of Exam:
9/21/2009 Operating Test No.:
Scenarios 1
2 3
4 CREW POSITION CREW POSITION CREW POSITION CREW POSITION M
I N
I M
U M(*)
A P
P L
I C
A N
T E
V E
N T
T Y
P E
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
T O
T A
L R
I U
RX 1
1 1
1 0 NOR 1
1 1
1 1 I/C 3
1 4
4 4 2 MAJ 1
1 2
2 2 1 RO 6 X
SRO-I SRO-U TS 0
0 2 2 RX 1
1 1
1 0 NOR 1
1 1
1 1 I/C 3
3 6
4 4 2 MAJ 1
1 2
2 2 1 RO SRO-I 2,3 SRO-U TS 3
3 0
2 2 RX 1
1 1
1 0 NOR 1
1 1
1 1 I/C 3
2 5
4 4 2 MAJ 1
1 2
2 2 1 RO SRO-I 1 X
SRO-U TS 2
2 0
2 2 RX 0
1 1 0 NOR 1
1 2
1 1 1 I/C 3
1 4
4 4 2 MAJ 1
1 2
2 2 1 RO SRO-I SRO-U 2,3 X
TS 3
3 0
2 2 Instructions:
- 1.
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301 Transient and Event Checklist Form ES-301-5 Facility:
Date of Exam:
Operating Test No.:
Scenarios 1
2 3
4 CREW POSITION CREW POSITION CREW POSITION CREW POSITION M
I N
I M
U M(*)
A P
P L
I C
A N
T E
V E
N T
T Y
P E
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
T O
T A
L R
I U
RX 0
1 1 0 NOR 1
1 1
1 1 I/C 3
3 4
4 2 MAJ 1
1 2
2 1 RO SRO-I SRO-U 1 X
TS 3
3 0
2 2 RX 1
1 0 NOR 1
1 1 I/C 4
4 2 MAJ 2
2 1 RO SRO-I SRO-U TS 0
2 2 RX 1
1 0 NOR 1
1 1 I/C 4
4 2 MAJ 2
2 1 RO SRO-I SRO-U TS 0
2 2 RX 1
1 0 NOR 1
1 1 I/C 4
4 2 MAJ 2
2 1 RO SRO-I SRO-U TS 0
2 2 Instructions:
- 3.
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 4.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301 Competencies Checklist Form ES-301-6 Facility: Cooper Nuclear Station Date of Examination: 9/21/09 Operating Test No.:
SRO-U X ATCO RO X SRO-I X
SRO-U RO SRO-I SRO-U SCENARIO SCENARIO SCENARIO SCENARIO Competencies 1
2 3
4 1
2 3
4 1
2 3
4 1
2 3 4 Interpret/Diagnose Events and Conditions 3,4, 5,6, 7,8 3,4, 5,6, 7,8 3,4, 5,6, 7
2,3, 4,5, 7,8, 9,10 3,5, 7
4,5, 6,
7,8 3,4, 6,7 3,4, 5,7, 8,9, 10 4,6, 7,8 1,3, 5,6, 7
5,6 2,4, 7,8, 9,10 Comply With and Use Procedures (1) all all all all 2,3, 5, 7 2,4, 5,6, 7
2,3, 5,6, 7
3,4, 5,6, 8,9, 10 1,4, 6,
7,8 1,3, 5,6, 7
1,5, 6
1,3, 4,
7,8, 9,10 Operate Control Boards (2) na na na na 2,3, 5,7 2,4, 5,7, 8
2,3, 4,5, 6,7 6,8, 9,10 1,4, 6,
7,8 1,3, 5,6, 7
1,5, 6
1,2, 3,5, 7,8, 9,10 Communicate and Interact all all all all all all all all all all all all Demonstrate Supervisory Ability (3) all all all all na na na na na na na na Comply With and Use Tech. Specs. (3) 3,5 2,3 3,4 2,3 na na na na na na na na Notes:
(1)
Includes Technical Specification compliance for an RO.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
Appendix D Scenario Outline Form ES-D-1 Initial Conditions: 10 to 12% Core Thermal Power, Reactor Startup in process.
Turnover: Reactor Startup is in progress GOP 2.1.1 Step 4.17.1; NPP 10.13 Section 4; OP 2.2.77 through Section 1of Attachment 1. Continue the power ascension to 25%
Thermal Power using control rods Group 40 Step 40. Diesel Surveillance 6.1DG.102 is in progress at section 4 step 4.53 with the #1 DG loaded to 3400Kw paralleled to the F bus. First order of business is to shift Reactor Equipment Cooling Pumps. The C REC pump has just been repaired and needs to be placed in service and D removed from service.
Facility CNS Scenario No.:
NRC 1 Op-Test No.:
Examiners:
Operators:
Event No.
Timeline Event Type*
Event Description 1
0 N
Shift REC D to C per OP 2.2.65.1 2
10 R
Pull control rods to increase power from 10% to 25%
3 25 I,TS LPRM Failure upscale 4
30 C
CRD Flow Control Valve Fails closed 5
37 C,TS HCU Accumulator inop 6
45 C
SRV Opens and sticks open 7
50 M
SRV Vacuum breaker leaking 8
60 C
RHR Containment Spray logic failure
Scenario Summary The scenario begins with Cooper station at approximately 12% power with a Reactor startup in progress.
The first task for the crew to perform after they assume the watch is a shifting of the D REC to the C REC for a normal evolution to assist maintenance following repairs of the C pump.
Following the REC pump shifting, the crew will raise power by pulling control rods until power is approximately 15%.
During the power ascension the LPRM fails upscale requiring the RO to recognize it, report and bypass it in accordance with the Instrumentation procedure. This is a Tech Spec 3.3.1.1 call for the CRS.
After the Tech Spec call for the LPRM the running CRD Flow Control Valve fails causing the RO to follow the guidance in the annunciator procedure and shift the Flow Control Valves.
As pressure lowers on the CRD System, one HCU Accumulator becomes inoperable due to a ruptured internal seal and the HCU must be isolated. The CRS will declare that CRD Accumulator inoperable per Tech Specs 3.1.5 Condition A.
After the crew has performed all the required actions for the inoperable HCU, C SRV will fail open and stick. Requiring the crew to enter abnormal procedure 2.4SRV in an attempt to close the SRV. The vacuum breaker associated with that SRV begins to leak into the DW causing primary containment pressure to rise slowly. The crew will respond and manually Scram the unit as pressure rises to 1.5 psig in containment. As pressure continues to rise, Torus cooling and sprays are required to be initiated.
When Containment sprays are placed in service the first RHR loops spray logic will fail requiring the operator to start another loop of RHR Containment Spray.
The scenario ends when Reactor pressure and level are being maintained and containment cooling and sprays are in service.
Appendix D Scenario Outline Form ES-D-1 Initial Conditions: Near the End of the Operating Cycle at 95% power and rising power to 100%. EDG 1 running unloaded for break-in run after maintenance.
Turnover: Immediately after shift turnover, the crew will synchronize EDG 1 to 4160 F bus and conduct an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> full load run. Then the crew will raise reactor power to rated using Reactor Recirc.
Facility Cooper Nuclear Station Scenario No.: NRC 2 Op-Test No.:
Examiners:
Operators:
Event No.
Time line Event Type*
Event Description 1
0 N
Synchronize and Load EDG 1 per procedure 2
10 R
Raise Power with RR to rated power 3
20 C
Main Turbine Gland Seal regulator fails closed.
4 25 I, TS APRM B fails at 100%
5 35 C, TS Condensate Pump A Trip, A RR Pump Fails to run back 6
45 C, TS HPCI inadvertent Initiation 7
60 M
Main turbine vibration increase resulting in Turbine Trip Required, Reactor Manual Scram (ATWS no rods move).
Non Critical Busses fail to fast transfer on Turbine Trip 8
70 C
SLC Pump A starts then trips immediately
Scenario Summary The scenario begins with Cooper station at 95% power near the end of the current operating cycle. With EDG 1 running unloaded after maintenance to replacing 1 piston.
After shift turnover, the BOP will synchronize and load Diesel 1 to 4000 kW for post maintenance testing following a piston replacement per 2.2.20.1 Diesel Generator Operations, beginning at Step 5.23.
When DG 1 is being loaded the Doniphan Control Center will call to request a main generator load rise to 780 MWe. The crew will raise power IAW 2.1.10 Station Power Changes section 6 to 780MWe.
The next event is a Main Turbine Gland Seal regulator failing closed. The crew will respond per the alarm card, 2.4TURB, and 2.4VAC to address lowering Main Condenser Vacuum. Crew actions from 2.4TURB Attachment 6 Sealing Steam Trouble:
Will restore gland sealing steam and vacuum will begin to recover.
When requested be the lead evaluator the next event will commence.
The next event is APRM B slowly failing upscale over approximately 2 minutes. The crew will respond IAW alarm response procedures. Once the crew has determined the B APRM channel is failed they will bypass the APRM using the alarm card guidance.
Tech Spec potential LCOs exists for T.S. 3.3.1.1 (RPS Instrumentation) Table 3.3.1.1-1 Function 2, TLCO 3.3.1 for Rod Blocks, and TLCO 3.3.3 PAM.
When the Tech Specs have been addressed or as requested by the lead evaluator the next event will commence.
The next event is a Main Condensate Booster Pump 1A trip with a failure of Reactor Recirc Pump A to runback. At this power level the Reactor Recirc pumps should run back towards 45% and stop once Condensate pressure restores. The crew will identify the trip and enter 2.4MC-RF to address the tripped MCB Pump. The RO will identify A RR pump has failed to run back. This will require entry into 2.4RR. The crew must take actions to station a licensed operator at RRMG set A to manually control RR speed.
Due to the failure to runback RR flow is mismatched and Tech Spec 3.4.1.1 is applicable and must be entered. This requires matching loop flows within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
When the Tech Specs have been addressed or as requested by the lead evaluator the next event will commence.
The next event is a HPCl inadvertent start. The crew will recognize the initiation signal is not valid and will trip HPCl (immediate operator action). The crew will enter 2.4CSCS,
for the inadvertent HPCI start. The crew will be required to maintain the HPCI aux oil pump in PTL to maintain HPCI secured. This renders HPCI INOP and the SRO will reference Tech Specs. Tech Spec LCO 3.5.1 condition C is applicable and requires verification that RCIC is operable within one hour and HPCI must be restore within 14 days. HPCI will not auto start for the rest of the scenario, but may be started manually if needed.
When the Tech Specs have been addressed or as requested by the lead evaluator the next event will commence.
The next event is Main Turbine vibrations requiring a Turbine trip. The crew should enter 2.4TURB. Vibrations continue to rise and when the crew attempts to scram the reactor an ATWS occurs. The turbine is tripped and pressure control is hindered by the limited capacity of the bypass valves. The crew starts RCIC for level control and stops and prevents the other feed systems. This action will aid in reducing reactor power.
On the Turbine trip non-vital 4160 buses will not transfer to the Start up transformer.
This results in loss of the balance of plant equipment for pressure control and level control. The crew must control these parameters using SRVs and ECCS systems.
When SLC pumps are started, SLC A will trip approximately 1 minute after starting.
The crew is able to insert all control rods by resetting the scram and draining the volume and re-scramming the reactor.
The scenario is terminated when all rods are inserted and reactor level and pressure are being controlled in the assigned bands.
Appendix D Scenario Outline Form ES-D-1 Initial Conditions: Near the End of the Operating Cycle at 75% power and lowering power to 70%.
Turnover: Immediately after shift turnover, the crew will shift DEH Pumps for scheduled maintenance. Following the shifting of the DEH pumps commence a power decent to 70% using Reactor Recirc flow to accommodate Doniphans request for load..
Facility Cooper Nuclear Station Scenario No.:
NRC 3 Op-Test No.:
Examiners:
Operators:
Event No.
Time Line Event Type*
Event Description 1
0 N
Shift DEH Pumps 2
5 R
Decrease reactor power from 75% to 70% using RR.
3 15 I, TS APRM B fails downscale 4
20 I, TS A RR flow instrument fails downscale 5
40 C,TS A RR Pump Trip 6
45 M
Medium Steam Leak in Drywell / Loss of off-site power on Scram/ Emergency Depressurize 7
50 C
RCIC Trips on Over-speed
Scenario Summary The scenario begins with Cooper station at 75% power near the end of the current operating cycle with a power decent in progress.
After shift turnover, the BOP will shift DEH pumps for scheduled maintenance, The standby pump is started and the running pump is secured in accordance with Operating Procedure 2.2.20 Section 5.
When the DEH pumps have been shifted the crew will continue the power decent from 75% to 70% power using Reactor Recirculation flow in accordance with Operating Procedure 2.1.10.
The next event is APRM B failing downscale. The crew will respond IAW alarm response procedures. Once the crew has determined the B APRM channel is failed they will bypass the APRM using the alarm card guidance. Tech Spec potential LCOs exists for T.S. 3.3.1.1 (RPS Instrumentation) Table 3.3.1.1-1 Function 2, TLCO 3.3.1 for Rod Blocks, and TLCO 3.3.3 PAM.
The next event is an A Reactor Recirc Flow Instrument failure upscale. The crew will recognize the flow comparator mismatch and that the APRMs on the A side are now non-conservative with regards to APRM Flow Bias Scram setpoints. Tech Spec LCO exists for T.S. 3.3.1.1 Required Action A.1 and C.1 Trip capability is not maintained for function 2.b. requiring the crew to place a manual half scram in on the A Channel in accordance with procedure 4.5 section 5.
The next event is a Reactor Recirc pump A Shaft Binding with Pump Trip. The crew will respond per the alarm card and enter Abnormal Procedure 2.4RR. With the rod line set in the initial conditions, this trip will not cause the plant to enter the stability exclusion region of the power to flow map. There will be a flow mismatch between the pumps requiring the tripped pump to be declared inoperable in accordance with Tech Spec 3.4.1 B.1 The next event is the Major Event where a medium steam leak develops in the Drywell, requiring a reactor scram on high drywell pressure. When the plant scrams the Main Turbine will trip and when it does the Startup Transformer will trip as well, resulting in a loss of all off-site power until the Diesel Generators start and automatically re-energize the Emergency Busses. The Crew will use HPCI and RCIC to control Reactor water level and SRVs to control Reactor Pressure. The steam leak in containment will require the crew to monitor and control PC Pressure using first Torus Sprays and then Drywell Sprays. The crew will have to Emergency Depressurize the vessel because HPCI will not be able to maintain level.
RCIC turbine will trip 3 seconds after RCIC is started (manual or automatically). The operator will report the RCIC trip to the CRS and dispatch a building operator to investigate the turbine trip.
Because the Startup Transformer is lost on the turbine trip the Condensate and Circ Water Systems will be unavailable for use for cooldown and pressure and level control.
The crew must control these parameters using SRVs and ECCS systems.
The scenario is terminated when Drywell Sprays are being used to control Primary Containment Pressure and temperatures and a Reactor Cooldown has been commenced to limit the amount of heat rejected to primary containment. Also Reactor water level should be maintained within the assigned band.
Appendix D Scenario Outline Form ES-D-1 Facility: Cooper Nuclear Station Scenario No.: NRC 4 Op-Test No:
Examiners:
Operators:
Initial Conditions:
The plant is operating at ~60% power during Start up.
Turnover:
After the crew has assumed the watch, Complete RFP B startup (Pump is Idling at 1250 RPM), continue pulling rods to achieve 550 MWe for start up when requested by load dispatcher.
Event No.
Timeline Event Type*
Event Description 1
T=0 N
Complete RFP B startup to automatic 2
T=30 R
Raise Reactor Power with Control Rods 3
T=40 I
RBM Failure 4
T=50 C
CRD Pump A trip 5
T=60 C
Loss of Power to RWCU-MO-15 6
T=70 M
RWCU Leak in RB (Can not Isolate) 7 T=75 C
All MT Bypass Valves fail closed 8
T=80 C
1 ADS Valve fails to open on ED
Scenario Description The plant is operating at ~60% power.
After the Crew assumes the watch the crew will complete start up of RFP B from IDLE to automatic.
Load dispatcher will contact the control room requesting power increase to 500 MWe.
During control rod withdrawal the A RBM will fail upscale resulting in a Rod Block. The RBM will be required to be bypassed to continue rod withdrawal. CRS will declare RBM A INOP which results in a potential LCO for 3.3.2.1.
After the RBM is bypassed and TS call has been made CRD pump A trips. The crew will respond per the alarm card and manually shut the CRD Flow Control Valves. Once the CRD FCVs are shut they will start CRD pump B and manually restore CRD flow. If an accumulator alarm is received Tech Spec 3.1.5 would be applicable. If the crew takes actions in a timely manner no accumulator alarms will be received and no Tech Specs are applicable.
When requested by the lead evaluator the next event will commence.
Shortly after the crew completes actions for restoring CRD system, RWCU pump A trips on low flow and RWCU-MO-15 looses power. CRS will evaluate TS and determine LCO 3.6.1.3 Condition A and TS 3.3.3.1 Condition A applies.
After the crew has addressed RWCU system and TS, a leak will develop on RWCU in the Reactor Building. RWCU-MO-18 will not shut and RWCU-MO-15 has no power so the leak is not isolable. This will result in the crew entering EOP-5A, and since the leak can not be isolated EOP-1A.
When the crew scrams the Reactor the Main turbine bypass valves will fail closed this prevents the crew from being able to anticipate Emergency Depressurization.
When required by EOP-5A to Emergency Depressurize (ED) one SRV (ADS valve) will fail to open. The operator will identify this and open an additional SRV to ensure 6 are open.
The scenario may be terminated when ED is complete and reactor water level is being controlled in the assigned band.