ML062750262
| ML062750262 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/20/2006 |
| From: | Caruso J Operations Branch I |
| To: | |
| Sykes, Marvin D. | |
| References | |
| Download: ML062750262 (110) | |
Text
ES-30 1 Control Room/ln-Plant Systems Outline Form ES-301-2 System / JPM Title
Type Code*
Safety Function A,MS 1
~
- 1) e. RHR / Respond to Loss of Shutdown Cooling Pumps (NRC-05) 1 A,M,S I 4 (primary)
D S 2
M S 3
A,D,L,S 4 (secondary;
~
A,MS 6
- g. NI / Perform Excore Calibration (NRC-07)
A,NS 7
D S 8
I( k. IA / Compressor Startup On Loss of Normal Cooling (NRC-11)
I D
I 8
E,N,R 4
D,E,R 6
- Type Codes (A)ltemate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)
(WCA (P)revious 2 exams (S)imulator NUREG 1021 REVISION 9 Criteria for RO I SRO-I I SRO-U 4 6 14-6 12-3
< 9 i r 8 / s 4 2 1 1 2 1 / 2 1 r l J 2 1 / 2 1 2 2 / 2 2 / > 1 s 3 I s 3 I 5 2 (randomly selected) 2 1 1 2 112 1
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Units 1 & 2 Exam Level (circle one): RO / SRO-I / SRO-u Date of Examination: 8/28/06 - 9/1/OE Operating Test Number:
2006 i
11 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
~
- d. ANV / Respond to Loss of Condensate e 5% Power (NRC-04)
- e. RHR / Respond to Loss of Shutdown Cooling Pumps (NRC-05)
A,D,L,S 4 (secondary)
A,MS 4 (primary)
A,MS 6
System / JPM Title
- g. NI / Perform Excore Calibration (NRC-07)
Type Code*
Function A,NS 7
D S 8
11 a. CVCS / Respond to Inadvertent Dilution While Critical (NRC-01)
I A,M,S I
1
~~
(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power
( W A 1 (N)ew or (M)odified from bank including 1 (A) 1 (P)revious 2 exams (S)imulator II b.
- k. FH / Respond to Lowering Refuel Pool Level (NRC-12)
I I
6 N,R 8
- Type Codes Criteria for RO I SRO-I I SRO-U 11 i. AFW / Align Fire Water to AFW Pp Suction (NRC-09) 1 E,N I
4 4-6 I 4-6 I 2 - 3 5 9 1 s 8 1 s 4 2.ll2.ll2.1 z l i > l l 2. 1 2 2 1 2 2 1 2 1 5 3 I i; 3 I i; 2 (randomly selected) z l l > l l 2. 1 NUREG 1 0 2 1 REVISION 9
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 System / JPM Title Type Code*
Safety Function
A,MS 1
- e.
- f.
- g.
1 7
-~
I I
A,D,L,S 4
- Type Codes 11 Implant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
Criteria for RO I SRO-I / SRO-U
6
~~
~
l F H / k e s p o n d to Lowering Refuel Pool Level (NRC-12)
I NJi I
8
~~~
I ( Q E o n t r o l room (and in-plant) systems must be different and serve different safely functions; (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (S)imulator
( R P 4-6 I 4-6 12-3 s 9 I s 8 / r 4 2 1 I 2 1 / 2 1 2 1 / 2 1 1 2 1
- ? 212 2 1 2 1 2 1 I ; ? 1 / 2 1 s 3 /
3 / s 2 (randomly selected)
NUREG 1021 REVISION 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-01 Task
Title:
Respond to Inadvertent Dilution While Critical (SOER 94-2)
[Alternate Path]
Task Number: 202.006 K/A
Reference:
024.AA1.17 (3.9,3.9)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
.I Plant:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
Unit 1 is in Mode 1 at 97% power.
Regulating CEAs are inserted to 105 for MTC testing.
Reactor power unexpectedly begins to increase.
Initiating Cue:
You are performing the duties of the Unit 1 ROKRO. The CRS directs you ta respond per AOP-lA,Section V.
Task Standard:
Initiate fast boration to control reactor power in accordance with AOP-lA, Inadvertent Boron Dilution.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
NRC-0 1 Page 1 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:
None General
References:
- 1.
- 2.
- 3.
- 4.
AOP-1 A, "Inadvertent Boron Dilution", Revision 3 Dwg 61075 Sheet 33B for CVC-514-MOV, Revision 2 NO-1-201, "Calvert Cliffs Operating Manual", Revision 17 PR-1-103, "Use of Procedures", Revision 5 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
NRC-01 Start with IC-13. Lower power to 97% with CEAs inserted to 105".
Use System Lineup (26) Command VCT-CONC(1) = 0 to simulate placing a deborating demin in service. Execute the file and allow power to start rising.
Insert malfunction CEDSOOS for Shim Switch failure after CEAs are at 105".
Run simulator until power begins to rise, then freeze. Reset the VCT concentration back to initial concentration using system lineup.
Ensure 11 CC Hx in service and 12 CC PP running (matches setup for Disable and tag out 13 Charging Pump.
Load REF CMD SET at 89.7.
When the applicant has placed CV-520 in bypass to remove the IXs from service, execute the VCT concentration file to stop the deboration.
When the applicant attempts to open CVC-514-MOV, use Remote Function for CVC-514-MOV (Bkr 52-10425) to OPEN the breaker.
JPM NRC-OS).
Page 2 of 8 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Locates AOP-1A Section V actions Same as element.
V.
A.
STOP THE PRIMARY SOURCES OF DILUTION
- 1.
Stop any makeup to the RCS.
Verifies RC M/U Pps are not running, CVC-5 12 is shut.
- 2.
Places HS-2520 to BYPASS on IC07 and BYP position indication illuminated for CVC-520.
B.
CONTROL REACTOR POWER
- 1.
IF the rate of power rise can NOT be stopped,...
Control the rise in power using CEAs and/or boration:
No action required at present time.
- 2.
I d T d i r e c t s y o u to insert CEAs 5 inches and then fast borate for 10 seconds.
I CAUTION CEAs must be maintained above the Transient Insertion Limits PER Tech Spec 3.1.6. to maintain SDM.
necessary while maintaining the CEAs above the Transient Insertion Limit.
not inserting.
0 Insert CEAs as Selects Manual Sequential or Manual Group (and CEA Group V) and attempts to insert CEAs to control power rise. Recognizes that CEAs are I CUE: CRS acknowledges and directs you to attempt to fast borate for 10 seconds.
I 0
Borate the RCS as necessary by completing the following actions:
- a.
Shut the VCT M/U valve, Checks green position indication 1-cvc-512-cv light on for CVC-512 on 1C07.
Examiner Note:
CVC-5 14 indication lost. Simulator Operator will simulate tripping CVC-5 14-MOV breaker when applicant takes handswitch to OPEN position.
- b.
Open the BA DIRECT Places HS-25 14 in open and checks indication for CVC-514. Recognizes CVC-514 does not open. Applicant M/U valve, 1-CVC-5 14-MOV NRC-01 Page 3 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) informs CRS.
Examiner Note:
If RO applicant asks CRS for guidance, CRS will direct applicant to follow the procedure and fast borate for 10 seconds using only the running charging Pump.
0.1 IF this boration flowpath is NOT available, THEN attempt alternate methods of boration PER ATTACHMENT (1)
BORATING THE RCS Refers to Attachment (1).
NOTE:
The following eight methods of borat,m are arranged in order of pre The method used should be based on equipment availability.
erence.
- 1. IF the RCS is to be borated by ANY of the following methods, THEN proceed to the appropriate step:
Places HS-226X and Y to stop and check stopped indication on BA Pps 0
Step 3, Page 3, BORATING FROM THE BASTs USING THE GRAVITY F'EED VALVES Applicant should select the gravity feed option because it is the first method in sequence which can be performed. Boration using BA pumps is not a viable option because of CVC-5 14 failed closed.
- 3.
BORATING FROM THE BASTs USING THE GRAVITY FEED VALVES
- a.
Check that the BAST(s) are available.
Verifies adequate level in one or both BASTs.
Turns handswitch(es) for CVC-508 and/or CVC-509 to OPEN position, verifies both red and green indicating lights lit, and releases handswitch(es)
(which spring return(s) to AUTO position). Verifies valve(s) fully open by observing green handswitch light(s) out.
Turns handswitch for CVC-501 to CLOSE position. Verifies has both red and green indicating lights lit.
Verifies CVC-501 fully closes by NRC-01 Page 4 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CNTICAL STEP)
CAUTIl observing red handswitch lights out.
- d. IF the RCS is on Shutdown Cooling, THEN verify that the boration flowpath is aligned to a RCS leg with Shutdown Cooling flow.
No action required.
N: Anytime the RCS temperature is less than 365°F AND Pressurizer,eve1 is greater than or equal to 170 inches, only ONE Charging Pump is allowed to be operated.
When informed of procedural requirement to start all charging pumps, CRS directs applicant to deviate from procedure and to use only the running charging DumD and NOT the idle charging DurnDs.
I Examiner Note:
Procedure requires all charging pumps. However, applicant was directed earlier to "fast borate" for 10 seconds to control the reactivity addition event.
All charging pumps running will cause an excessive boration, resulting in an unnecessary plant transient.
Recognizes that procedure step conflicts with directions and informs CRS.
- f. Verify Charging Flow by observing Monitors BAST level.
BAST level lowering.
(1)
If desired, stop the CHG PP(s)
No additional pumps were started.
Places CVC-501 handswitch in OPEN, observes the red and green handswitch lights lit, places handswitch in AUTO, observes green light out when valve fully open.
Turns handswitch the open gravity feed valves, CVC-508 and/or CVC-509 to CLOSE position, verifies both red and green indicating lights lit, and releases handswitch(es)
(which spring return@) to AUTO position). Verifies valve(s) fully close by observing green NRC-01 Page 5 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) handswitch light(s) out.
CAUTION: Turbine load or steam demand should not be raised if an inadvertent boron dilution event is in progress.
- 3.
Maintain T C ~ L D on program by No action required.
performing the following appropriate steps:
e Adjust TBVs or ADVs e
Reduce Turbine load
- 4.
Notify the SO-BP of any No action required.
electrical load changes.
Examiner Note:
This JPM is completed when boration has been completed and Tc and load have been checked per AOP-1A Steps V. No further actions are required.
The applicant is expected to end the JPM.
TIME STOP NRC-01 Page 6 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-01 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-0 1 Page 7 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANT'S CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
- 3.
Unit 1 is in Mode 1 at 97% power.
Regulating CEAs are inserted to 105" for MTC testing.
Reactor power unexpectedly begins to increase.
INITIATING CUE:
You are performing the duties of the Unit 1 ROKRO. The CRS directs you to respond per AOP-lA,Section V.
NRC-0 1 Page 8 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-02 Task
Title:
Align HPSI for Core Flush via Pressurizer Injection Task Number: 201.058 WA
Reference:
Oll.EA1.11 (4.2,4.2)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
4 Plant:
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
EOP-5 implemented.
A loss of coolant accident has occurred.
RCS pressure is 18 PSIA with CETs indicating 233°F.
SIAS actuated 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> ago.
Initiating Cue:
The CRS directs you, the CRO, to perform EOP-5, Block Step AE, "Commence Core Flush".
Task Standard:
Establish core flush flow via pressurizer injection.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
NRC-02 Page 1 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Required Materials:
None General
References:
- 1.
- 2.
EOP-5, Loss of Coolant Accident, Revision 21 EOP Attachment 10, High Pressure Safety Injection Flow, Revision 18 Time Critical Task:
No Validation Time:
20 minutes Simulator Setup:
- 1.
IC-13,100% power
- 2.
Insert Malfunction RCS001. Run the simulator until RAS, perform EOP-5, Block Step V, then freeze the simulator.
NRC-02 Page 2 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CNTICAL STEP)
TIME START Identify and locate EOP-5, Step AE.
- 1. IF the elapsed time from SIAS actuation is between 8 and 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, AND ANY of the following conditions exist:
RCS subcooling is less than 30°F based on CET temperatures Pressurizer level is less than 30 inches { 90)
RVLMS indicates level below the top of the hot leg THEN commence core flush by lining up for Pressurizer Injection as follows:
- a.
Check TWO HPSI PPs are avai 1 ab1 e.
-
- L..4.L3.-.-b.
. Open the SI TO. CHG. HDR valve, 1
1-CVC-269-MOV.
C.
IF CIS has actuated, AND IA CNTMT ISOL valve, 1-IA-2080-MOV is shut, THEN perform the following actions:
Same as element.
Determines core flush is required.
Checks HPSI pumps and determines 11 and 13 HPSI pumps are running (Red light on, Green light off, normal running amps).
Places HS in open, verifies red light lit, green light out Determines CIS has actuated.
Places 1-HS-2080A in OVERRIDE.
Places 1-HS-2080 in OPEN, verifies red light lit, green light out.
Places HS-5 18 and HS-5 19 in CLOSE, verifies green lights lit, red lights out.
NRC-02 Page 3 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Adjusts HIC-100 to 0% output, observes 1OOE and lOOF green lights lit, red lights out.
Observes 656-MOV red light lit, green light off.
valve, 1-SI-656-MOV7 is open.
Places CVC-517 HS in OPEN, verifies red light lit, green light off.
- h.
IF 13 HPSI PP is available, THEN perform the following actions:
Determines step is applicable.
(1)
Verify 13 HPSI PP is running and amps.
Checks 13 HPSI PP indicating lights Places SI-653 HS in OVERRIDE CLOSE, verifies green light lit, red light out.
Shut AUX HPSI HDR Places HS in CLOSE for 617,627, 637,647, verifies green lights lit, red lights out.
(4)
(5)
IF approximately 150 Determines Hot Leg Injection is not Verify 11 or 12 HPSI PP is running.
and amps.
GPM is NOT indicated required.
THEN initiate Hot Leg Checks 11 HPSI PP indicating lamps Verifies flow is 2150 GPM on 1-Injection.
HA-212.
- 1.
IF 13 HPSI is NOT available...
Determines step is NA.
- 2.
WHEN Pressurizer Injection OR Hot Determines step is applicable.
Leg Injection is in progress, AND HPSI PPs are being used for Cold Leg Injection, THEN perform the following actions:
- a.
Balance the flow between Throttles MAIN HPSI HDR valves Pressurizer or Hot Leg Injection and Cold Leg Injection by throttling the MAIN HPSI HDR as needed to balance Cold Leg injection flows.
NRC-02 Page 4 of 7 NUREG-1021, Revision 9
ELEMENT
(* = CRITICAL STEP)
STANDARD valves:
1 -SI-61 6-MOV 1 -SI-626-MOV 1-SI-636-MOV 1 -SI-646-MOV LUIIIII rrD __ b.
Maintain the minimum flow Refers to Attachment (10) and
.<,.ICI?"%
iy heat (lo),
determines that minimum flow of 385 GPM is required. Checks total E SAFETY HPSI flow, and equally raises Cold Leg injection flow as required to meet the Attachment (10) requirement. Determines at least 150 gpm flow is going to the pressurizer (upper limit of charging flow instrument) plus indicated flow to the loops on total HPSI flow instrument.
- c.
Ensure CET temperatures remain Monitors CET temperature and constant or lowering.
determines temperatures are slowly lowering.
TIME STOP Examiner Note:
The task is complete when the operator has determined that CET temperatures are lowering after initiation of core flush flow. No further actions are required.
NRC-02 Page 5 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-02 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-02 Page 6 of 7 NUREG-1021, Revision 9
INITIAL CONDITIONS:
- 1.
- 2.
- 3.
- 4.
EOP-5 implemented.
A loss of coolant accident has occurred.
RCS pressure is 18 PSIA with CETs indicating 233°F.
SIAS actuated 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> ago.
INITIATING CUE:
The CRS directs you, the CRO, to perform EOP-5, Block Step AE, Tormnence Core Flush".
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANT'S CUE SHEET NRC-02 Page 7 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Facility: Calvert Cliffs 1&2 Job Performance Measure No. : NRC-03 Task
Title:
Respond to Spurious Safety Injection Actuation Signal Task Number: 048.028 WA
Reference:
006.A2.13 (3.9,4.2)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
.I Plant:
READ TO THE APPLICANT:
I will expIain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
Unit 1 is in Mode 3 at 38OoF, 800 psia. Four RCPs are in service.
A heatup to hot standby conditions was in progress, but was suspended 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago to perform plant maintenance.
OP-1, Step 6.5 has been completed. Currently at Step 6.6.
Initiating Cue:
You are performing the duties of the Unit 1 RO/CRO.
Task Standard:
Reset the spurious SIAS and terminate injection.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
NRC-03 Page 1 of 9 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:
Provide curves from OP-1, "Plant Startup From Cold Shutdown:
Figure 4, "RCS P/T Limits - 4 RCPs Running" Appendix 1, Pressurizer Heatup Log" Appendix 2, "RCS Heatup Log" e
e e
General
References:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
lCOS-ALM, "ESFAS 11 Alarm Manual", Revision 34 (Window G05)
EOP Attachment 2, "SIAS Verification Checklist", Revision 18 ESFAS Drawing 61058 and SSA, Revision 35 (l-LD-OSS,058A)
Drawing 61076 Sheet 14B, Control Ckt for 1-PS-5464-CV Dampierre Spurious SI Event, IAEA Nuclear Safety Review for 2003 OP-1, "Plant Startup From Cold Shutdown", Revision 52 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
- 1.
- 2.
- 3.
- 4.
RCS at 380"F, 800 psia, 4 RCPs in operation. Complete OP-1 through Step 6.5.
Open RCS Sample Isolation 1-PS-5464-CV.
Enter malfunction esfa003-02 on F1.
After applicant begins the JPM, initiate a spurious Train B SIAS signal by inserting Malfunction ESFA003-02 via F1. REMOVE MALFUNCTION after it has been initiated.
- Figure 4, "RCS P/T Limits - 4 RCPs Running"
- Appendix 1, Pressurizer Heatup Log"
- Appendix 2, "RCS Heatup Log" Display Pressure-Temperature curves on Plant Computer CRT on 1C04.
- 5.
Provide curves from OP-1:
- 6.
NRC-03 Page 2 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Examiner Note:
After applicant has "taken the watch", simulator booth operator will initiate a spurious Train B SIAS by inserting Malfunction ESFA003-02. Booth operator will then REMOVE the malfunction, so that applicant will be able to reset the signal later.
1.a.
- b.
Locate and reference Alarm Manual for Same as element.
lC08, G-05.
RESPONSE
IF the reactor trips, DETERMINE the validity of the SIAS by observing alternate channels of indication for the same parameter.
parameters on 1CO9.
Check containment pres sure e
Check pressurizer pressure parameters on 1C06.
Determines step is N/A.
Checks Containment pressure indications for pressure > 2.8 psig for lCO9. Determines pressure <
2.8 psig.
Checks Pressurizer pressure indications for pressure < 1740 psia on 1C06. Determines pressure < 1740 and rising.
CUE: Acknowledge report from the applicant.
Determines that SIAS actuation is not valid. Reports conclusion to CRSorSM..
CUE: SM/CRS acknowledges invalid SIAS. (For RO applicants only), CRS directs you to respond per ALM 1C08 Window G-05, "ACTUATION SYS SIAS TRIP".
I C.
the SIAS is invalid OR Obtains approval to reset SIAS-B.
inadvertent, THEN, with Shift Manager OR Control Room Supervisor
G NRC-03 Page 3 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
CUE: IF requested to reset SIAS locally, THEN the CRS directs reset from CR due to no r-additional resources.
CUE: IF applicant requests permission to stop 13 HPSI Pump and/or 12 Charging Pump, the CRS authorizes placing the pump handswitches in PTL.
I CUE: CRS advises utilizing EOP Attachments to reset SIAS.
I e
Reference EOP Attachment (2) and reposition handswitch to post-accident position for equipment indicated with an asterisk (*).
References EOP Attachment (2).
Requests permission to reset the SIAS signal from the SM or CRS.
Repositions equipment handswitches indicated with an asterisk (*) to their post accident positions.
- a.
11 and 13 HPSI PPs RUNNING
- b.
11 and 12 LPSI PPs RUNNING C.
11 and 12 CS PPs RUNNING
- d.
1 -SI-6 16-MOV OPEN 1-SI-626-MOV OPEN 1-SI-636-MOV OPEN 1-SI-646-MOV OPEN
- e.
1-SI-617-MOV 1-SI-627-MOV 1-SI-637-MOV 1-SI-647-MOV
- f.
1-SI-615-MOV 1-SI-625-MOV 1-SI-635-MOV NRC-03 Page 4 of 9 OPEN OPEN OPEN OPEN May check HPSI PPs running by red lights lit.
May check LPSI PPs running by red lights lit.
May check CS PPs running by red lights lit.
May check valves open by red lights lit.
May check valves open'by red lights lit.
May check valves open by red lights lit.
OPEN OPEN OPEN NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) 1-SI-645-MOV OPEN
- g.
May check valves closed by green lights lit.
1-SI-618-CV SHUT 1-SI-628-CV SHUT 1-SI-638-CV SHUT 1-SI-648-CV SHUT
- h.
SIT OUT valves:
May check valves open by red lights lit.
1-SI-6 14-MOV OPEN 1-SI-624-MOV OPEN 1-SI-634-MOV OPEN 1-SI-644-MOV OPEN
- 1.
SIT RECIRC TO RCDT valve, 1-SI-661-CV SHUT light lit.
11,12, 13 & 14 CNTMT AIR CLRs RUNNING IN LOW May check valve closed by green May check fans running in low by slow speed lights lit.
- j.
- k.
CNTMT CLR EMER OUT valves:
May check valves open by red lights lit.
1-SRW-1582-CV OPEN 1-SRW-1585-CV OPEN 1-SRW-1590-CV OPEN 1-SRW-1593-CV OPEN
- 1.
11,12 and 13 IODINE FILT FANS May check fans running by red RUNNING lights lit.
- m.
RCDT PP CNTMT ISOL valve, 1 -RCW-4260-CV SHUT light lit.
May check valve closed by green
- n.
WGS CNTMT ISOL valves:
May check valves closed by green light lit.
1-WGS-2180-CV SHUT 1-WGS-2181-CV SHUT Repositions 5292-CV handswitch to CLOSE.
. 1-CRM-5291-cv SHUT 1-CRM-5292-CV SHUT NRC-03 Page 5 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
P.
CNTMT NORMAL SUMP DRN May check valves shut by green valves:
lights lit.
1-EAD-5462-MOV SHUT 1-EAD-5463-MOV SHUT Repositions PS-5464-CV handswitch to CLOSE.
May check valves shut by green lights lit.
- r.
H2 PURGE ISOL valves:
1-HP-6900-MOV SHUT 1 -HP-690 1 -MOV SHUT 1 C07
- a.
L/D CNTMT ISOL valves:
1-cvc-515-cv SHUT May reposition CVC-5 15 handswitch to CLOSE.
-^*
Repositions CVC-5 16 handswitch to CLOSE.
May check pumps running by red lights lit.
- b.
11, 12 and 13 CHG PPs RUNNING C.
VCT OUT valve, May check valve closed by green 1-CVC-50 1-MOV SHUT light lit.
- d.
VCT M/U valve, May check valve closed by green 1-cvc-512-cv SHUT light lit.
- e.
BA DIRECT M/U valve, May check valve open by red 1 -CVC-5 14-MOV OPEN light lit.
- f.
11 and 12 BA PPs RUNNING May check pumps running by red lights lit.
5 BAST GRAVITY F D valves:
May check valves open by red lights lit.
1-CVC-508-MOV OPEN 1-CVC-509-MOV OPEN
- h.
BAST RECIRC valves:
May check valves closed by green lights lit.
. 1-cvc-510-cv SHUT
. 1-cvc-5 1 1 - c v SHUT NRC-03 Page 6 of 9 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Repositions CVC-505 handswitch to CLOSE.
1-CVC-506-CV SHUT CUE: Inform applicant the rest of Attachment (2) is complete.
Depresses SIAS B reset pushbutton on lCl0 Channel B ON.
Verifies "Actuation Sys SIAS Tripped" alarm annunciator 1C08 G-05 is clear (green).
CUE: IF permission requested, CRS will direct applicant to stop injection pumps which started on the spurious SIAS.
Return components to their normal or desired status.
- STOP 12 LPSI PP Requests CRS permission to stop injection pumps (12, 13 HPSI PPs, 12 CHG PP, 12 LPSI PP)
Places 12 LPSI PP handswitch in STOP, observes green light, lowering discharge pressure Places 13 HPSI PP handswitch in STOP, observes green light, lowering discharge pressure, before entering non-operating area of RCS P/T curve.
Places 12 CHG PP handswitch in STOP, observes green light, lowering discharge pressure, before entering non-operating area of RCS P/T curve.
TIME STOP TERMINATING CUE:
This JPM is complete when SIAS-B is reset, 12 HPSI PP is off, 13 HPSI PP is off, 12 CHG PP is off.
NRC-03 Page 7 of 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-03 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
UNSAT Result:
SAT Examiners Signature and Date:
NRC-03 Page 8 of 9 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANT'S CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
- 3.
Unit 1 is in Mode 3 at 380°F, 800 psia. Four RCPs are in service.
A heatup to hot standby conditions was in progress, but was suspended 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago to perform plant maintenance.
OP-1, Step 6.5 has been completed. Currently at Step 6.6.
INITIATING CUE:
You are performing the duties of the Unit 1 ROKRO.
NRC-03 Page 9 of 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure FOITI ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-04 Task
Title:
Respond to Loss of Condensate at Less Than 5% Power [Alternate Path]
Task Number: 202.037 WA
Reference:
056.A2.04 (2.6,2.8)
Method of testing:
Simulated Performance:
Actual Performance:
.(
Classroom:
Simulator:
4 Plant:
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
Unit 1 is at 4.5 % power during a plant startup.
13 Condensate Pump is danger tagged.
11 and 12 Condensate Pumps were in operation when both pumps tripped. Multiple alarms on 1C03 came in at the same time.
I The running feed pump, 11 SGFP, tripped on low suction pressure.
Initiating Cue:
You are performing the duties of the Unit 1 CRO. The CRS directs you to respond per AOP-3G,Section VI.
Task Standard:
Take actions for a pump trip when c5 % power, control SG levels between -24" and +30".
Evaluation Criteria:.
- 1.
All critical steps completed.
- 2.
- 3.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
NRC-04 Page 1 of 10 NUREG-1021, Revision 9
Appendix C Job Performance Measure FOITII ES-C-1 Worksheet
- 4.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials :
None General
References:
- 1.
AOP-3G, Malfunction of Main Feedwater System, Revision 9 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
- 1.
- 2.
- 3.
- 4.
- 5.
Establish stable conditions at -45% power.
Tag out 13 Condensate Pump.
Insert Malfunctions CD004-01 and FW004-01 to trip 11 and 12 Condensate Pumps and 11 SGFP.
Ensure 11 AFW Pump is aligned for service.
Assign Trigger 1 as ms-4070A-open.
Assign malfunction AFW001-01 to T1, which will trip 11 AFW Pump when the AFW MS admission CVs are opened.
NRC-04 Page 2 of 10 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START I
~~
I CUE:
Begin at Step V1.A. 1.
A.
B.
Identify and locate AOP-3G, Step VI.A.l.
DETEMNE IF A REACTOR TRIP IS REQUIRED.
- 1.
Same as element.
IF' SG level is approaching (-)50
- inches, Monitors S/G levels, on 1C03.
Determines Step is N/A at this time, and proceeds to Step B.
ESTABLISH A SOURCE OF FEEDWATER.
CAUTION: Excessive feeding at low power conditions will affect TCOLD and Reactivity.
PZR level and RCS pressure can be affected.
CAUTION: A severe waterhammer may result if Main Feedwater flow is restored after it has been stopped for greater than 80 minutes.
If asked, the CRS does not desire to start any SGFPs due to the tripped condensate I
pumps.
- 2.
- 1.
IF the following conditions exist:
Determines step is N/A. (Standby SGFP is not available due to loss of A SGFP has tripped condensate pumps)
The standby SGFP is available There is sufficient time available to start the standby SGFP IF time does NOT permit starting the standby SGFP, Determines step is N/A. (Tripped SGFP cannot be restarted.)
Page 3 of 10 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
If asked, the CRS does not desire to start any Condensate Booster Pumps due to the tripped Condensate pumps.
I 3,
IF a Condensate Booster Pump has Determines Condensate Booster
- tripped, Pumps are not available (no Condensate Pumps operating).
Proceeds to Step 4.
- 4.
IF a Condensate Pump has tripped, THEN perform the following actions:
Determines step is applicable.
- a.
IF a backup Condensate Determines no backup pumps are Pump starts automatically, available.
THEN ensure that the pump is NOT affected by the failure mode.
ALTERNATE ACTIONS CAUTION: Starting a pump without determining the cause of the failure could initiate a common mode failure.
1 CUE:
If asked, CRS directs attempt to start the tripped Condensate pumps.
I NRC-04
- a. 1 IF a backup Condensate Pump did NOT start, THEN, with the approval of the SM/CRS, attempt to start the backup Condensate Pump.
a.2 IF a backup Condensate Pump will NOT start, THEN, with the approval of the SWCRS, attempt to start the tripped Condensate Pump.
Attempts pump start. Determines no pumps will operate.
Proceeds to Step 5 based on direction of CRS.
Page 4 of 10 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- 5.
IF Main Feedwater flow has been res tored, to Step 6.
Determines step is N/A and proceeds NOTE:
Restoration of Main or Auxiliary Feedwater will affect RCS T,,,,.
- 6.
Control RCS TCOLD by using ANY of the following methods, as applicable:
Monitors Tc, IC05 and/or lC06, and TBV operation.
0 adjusting TBVs 0
adjusting ADVS to maintain the following temperature band:
0 IF the Reactor is Determines Tc is within 2°F of
- critical, program.
THEN within 2°F of program %OLD a
IF the Reactor is Determines step is N/A.
NOT critical,
- 7.
IF Main Feedwater flow will NOT be restored,
THEN perform the following actions :
Determines step is applicable.
- a.
Initiate AFW using 11 or 12 AFW PP as follows:
NRC-04 (1)
Verify open the steam Verifies OPEN AFW Block valves; driven train SG AFW Block Valves:
4531-CV on 1C04.
l-AFW-4520,4521,4530, 11 SG 1-AFW-4520-CV 1 -AFW-452 1 -CV 12 SG 1 -AFW-4530-CV 1 -AFW-453 1 -CV Page 5 of 10 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Places handswitches 4070 and 4071 to OPEN and checks position indication for MS-4070AY 4071A, 4070, and 407 1.
1 -MS-407 1 A-CV I Examiner Note:
AFW Pp aligned for service, trips when steam supply valves are opened.
I (3)
Adjust and maintain 11 or 12 Determines step can not be AFW PP discharge pressure at completed. Refers to Alternate least 100 PSI greater than SG Actions.
pressure using the AFW PP SPEED CONTRs:
(11AFW)
(1)
Verify open the motor driven Verifies OPEN AFW Block train SG AFW Block valves:
valves; l-AFW-4522,4523,4532, 4533-CV on lC04. [5]
11 SG
. 1-AFW-4522-CV
. 1-AFW-4523-CV 12 SG
. 1-AFW-4532-CV
. 1-AFW-4533-CV CAUTION: 13 AFW PP flow limit is 575 GPM.
S PP.
(3)
Ensure the feedwater Monitors RCS temperature and flowrate does NOT cause RCS cooldown to exceed necessary.
the following limits for any lowers flow controller setpoint if NRC-04 Page 6 of 10 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) one hour: [BO1261
>256"F 100"F/hr 106°F to 256°F 4O"F/hr 406°F 35"Flhr CAUTION: Total AFW flow should NOT exceed 600 GPM per unit (300 GPM per unit when feeding both Units from either Unit 1 OR Unit 2).
1-FIC-4525A (12 SG) 1 -FIC-45 35A
- b.
(11 SG)
(12SG)
Places handswitches 4516 and 4517 to SHUT, on 1C03 and checks position indication for FW-4516 and 4517.
1-FW-45 16-MOV 1-FW-45 17-MOV
- c.
Notify Plant Chemistry that Notifies Plant Chemistry.
the AFW System is in service.
Inserts CEAs and/or borates to reduce Reactor Power. Monitors Reactor Power, on IC05
- 8.
IF AFW is maintaining SG levels Monitors S/G levels.
between (-)24 inches and (+)30
- inches, THEN, with the approval of SWCRS, perform ONE of the following:
I CUE:
The CRS directs maintaining Reactor critical.
a Maintain power less than Monitors Reactor Power, on lC05.
1% while attempting to restore the Main Feedwater System.
NRC-04 Page 7 of 10 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME STOP TERMINATING CUE:
This JPM is complete when applicant has adjusted 13 AFW pump for maximum flow and has initiated action to lower Reactor power to less than 1%. No further actions are required. The examiner is expected to end this JPM.
NRC-04 Page 8 of 10 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-04 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-04 Page 9 of 10 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
- 3.
- 4.
Unit 1 is at 4.5% power during a plant startup.
13 Condensate Pump is danger tagged.
11 and 12 Condensate Pumps were in operation when both pumps tripped. Multiple alarms on 1C03 came in at the same time.
The running feed pump, 11 SGFP, tripped on low suction pressure.
I INITIATING CUE:
You are performing the duties of the Unit 1 CRO. The CRS directs you to respond per AOP-3G,Section VI.
NRC-04 Page 10 of 10 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.:
NRC-05 Task
Title:
Respond to Loss of Shutdown Cooling [Alternate Path]
Task Number: 202.026 WA
Reference:
025.AA1.03 (3.4,3.3)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
.I Plant:
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ini ti a1 Conditions :
- 1.
- 2.
Unit 1 is in Mode 5 and has been shutdown for 5 days.
12 LPSI PP is running on SDC. 11 LPSI PP is aligned for SDC operation and is not running.
RCS is at 140°F and 150 psia with a bubble in the pressurizer.
- 3.
Initiating Cue:
You are performing the duties of the Unit 1 RO/CRO.
Task Standard:
Stop 12 LPSI pump and re-establish RCS temperature control with SDC using 11 CS Pump.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
NRC-05 Page 1 of 10 NUREG-1021, Revision 9
~~
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:
- 1.
Copy of alarm response for Window SM-66 of lC24B-ALM, "Fire Systems Alarm Manual", Revision 40, Page 74 of 295.
General
References:
- 1.
- 2.
AOP-3B, "Abnormal Shutdown Cooling Conditions", Revision 22 lC24B-ALM, "Fire Systems Alarm Manual", Revision 40 (Window SM-lC09-ALM, "", Revision 35 (Window H-21, "11 LPSI PP 0 SIAS BLOCKED AUTO START")
NO-1-200, "Control of Shift Activities", Revision 31 (Section 5.18, "Equipment Control")
66, "U-1 WEST ECCS PP RM 118 CNTMT RECIRC PIPE TUNNEL")
- 3.
- 4.
Time Critical Task:
No Validation Time:
20 minutes Simulator Setup:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
NRC-05 Unit 1 in Mode 5 with a pressurizer bubble. RCS is at 140'F / 150 psia.
Ensure 12 LPSI PP is in operation on SDC.
Stop 11 LPSI Pump.
Reduce FIC-306 to 3000 gpm in AUTO.
Adjust HIC-3657 to 27.5%.
Adjust CC HX Flow Controllers HIC-5206 and HIC-5208 to 20%.
Enter MALFUNCTIONS as follows:
9 SIOO3-01, "11 LPSI Pump Breaker Failure" (will trip when started)
> FIRE001, "Fire Alarm" on F1 9 SIOO3-02, "12 LPSI Pump Breaker Failure on F2
> CWOO2-01, "Screen Clog" at 0% on F3 (to initiate trigger T1)
Page 2 of 10 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- 8.
Enter REMOTE FUNCTIONS as follows:
> SI-314 to OPEN on T1
> SI-444 to OPEN on T1
- 9.
Enter OVERRIDES as follows:
> 1C02 Window B-38 "TURB TROUBLE" alarm ON NRC-05 Page 3 of 10 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START SIM OPER:
After applicant has received cue, Activate F1, to initiate fire alarm.
CUE: Inform applicant that Alarm Window SM-66 has actuated on Fire Panel 1C24B and hand applicant a copy of the alarm response for the alarm window.
- 1.
Smoke or flame detected in Unit 1 ECCS Pump Rooms 1 18 (West Room) or Containment Recirculation Pipe Tunnel Room 122.
Determines step is applicable.
- a.
DISPATCH an operator and/or Dispatches an operator and/or the Fire and Safety Watch to the west pump room and the pipe tunnel to Fire and Safety Watch (FASW) to the Unit 1 ECCS Pump Room 118 (West Room) and Containment investigate.
Recirculation Pipe Tunnel Room 122 to investigate the cause of alarm
- b.
IF a fire exists, THEN IMPLEMENT ERPIP 3.0.
CUE: Operator reports heavy smoke, but no flames, issuing from the motor vents on 12 LPSI Pump.
1 SIM OPER: Activate F2, to insert malfunction SIOO3-02, "12 LPSI Pump Breaker Failure" on 30 second time delay.
Conclusion Informs CRS of field report of heavy smoke from 12 LPSI motor.
Recommends stopping 12 LPSI.
CUE: CRS acknowledges report. If applicant recommends stopping 12 LPSI, then CRS should direct stopping 12 LPSI. If no recommendation, CRS should ask applicant if he/she has any recommendations. If no, then CRS should direct stopping 12 LPSI. Pump will automatically trip 30 seconds after report of smoke.
Page 4 of 10 Takes 12 LPSI PP handswitch to STOP, releases handswitch.
Observes green light lit and red light out. Observes amps go to zero.
Informs CRS.
NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
CUE: CRS directs applicant to respond to the loss of SDC starting at AOP-3BY Step IV.A.6 Locates AOP-3B, Step IV.A.6.
Same as element.
IV.A.6.
IF SDC is lost due to failure of the operating LPSI PP, AND the cause will NOT result in a common mode failure, THEN complete the following actions:
Determines step is applicable.
Monitors SI-651 and 652 position indication on 1C09. Observes alarm windows clear. Determines that the 12 LPSI Pump failure will not result in a common mode failure.
- a.
Place the failed PP handswitch in PULL TO LOCK.
PTL.
Places 12 LPSI PP handswitch in
- b.
IF RCS purification is in service, THEN place IX BYP valve handswitch 1-HS-2520 in the BYP position.
Verifies HS-2520, on 1C07 is in BYP position.
Lowers output of HIC-657 on 1C09 to zero or places HS-3657 on 1C09 to CLOSE. Checks position indication for SI-657.
Shifts FIC-306 on 1C08 to MANUAL.
Adjusts output of FIG-306 to 95%.
- f.
Verify BOTH RAS OVERRIDE Checks position on HS-302XA and 302YA on 1C08 and 1C09.
If not in OVERRIDE position, places HS in OVERRIDE.
switches in OVERRIDE:
0 11 LPSI PP RAS OVERRIDE, 1HS-302XA 0 12 LPSI PP RAS OVERRIDE, 1 -HS-302Y A.
CAUTION: Before starting the standby LPSI PP, the cause for the running LPSI PP failure should be determined to preclude a common mode failure.
[CUE:
If necessary, CRS will inform applicant that cause appears to be motor internal fault. A common mode failure is not suspected.
- g.
Start the standby LPSI PP.
Places 11 LPSI PP handswitch in START. Observes breaker open NRC-05 Page 5 of 10 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) green light on. Acknowledges 1CO9 Window H-21 in alarm. Informs CRS.
g.1.
IF the standby LPSI PP does NOT Refers to Step B.
- start, THEN PROCEED to Step B, Page 17 CUE: CRS reports Step B to be performed by alternate operator. CRS directs you to perform I
Step c.5.
C.5.
IF NO LPSI PPs are available, THEN align the CS PPs for cooling.
Determines step is applicable.
CAUTION: To prevent CS PP shaft seal and bearing damage, RCS temperature shall be less than 120°F OR the associated ECCS Pump Room Air Cooler shall be functional.
- a.
Verify RCS temperature less than 120°F OR the associated ECCS PP Room Air Cooler is functional.
Checks CET temperatures on 1C05 or checks that ECCS PP Room Air Coolers are not 00s.
CAUTION: To prevent over pressurization of the ECCS PP suction headers, RCS pressure shall be less than 170 PSIA.
- b.
Check that RCS pressure is less than 170 PSIA.
Checks RCS pressure on PI-103 and/or PI-103-1 on 1C06.
Determines pressure < 170 psia.
C.
Check that the SDC HDR RETURN ISOL valves are open:
Verifies position of valves on 1C09 1-SI-651-MOV 1 -SI-652-MOV
- d.
Shut Places handswitches to CLOSE.
Verifies valves close by observing green lights on, red lights off.
- e.
Isolate CS PP Min Flow to the RWT:
(1)
Place the SI IRC Places HS-3659A and 3660A on tches 1CO9 in the ON position. Checks lockout lights on HS-3659 and 3660 are out.
NRC-05 Page 6 of 10 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Places HS-3659 and 3660 on 1C09 OL inCLOSE.
I CUE:
Examiner Note:
When requested to locally open valves, Activate F3, to open SI-3 14 and SI-444
~~
When dispatched, PO reports SI-314 and 444 are open.
- f.
- g.
- h.
- 1.
J.
- k.
- 1.
C, ves:
0 11 CS PP Discharge
- valve, 1-SI-3 14 0
11 LPSI PP NORM SUCT ISOL valve, 1-SI-444 IF 12 CS PP is desired for SDC, Shut the S/D COOLING TEMP CONTR valve, 1-SI-657-CV.
Place the SHUTDOWN CLG FLOW CONTR, 1-HC-306, in MANUAL.
Adjust the output of the SHUTDOWN CLG FLOW CONTR, 1-HC-306, to 95%.
NRC-05 Page 7 of 10 Determines step is applicable.
Dispatches PO to open SI-3 14 and SI-444.
Determines step is N/A.
Verifies output of HIC-657 is zero or HS-3657 is in CLOSE. Checks position indication for SI-657.
Verifies FIC-306 in MANUAL.
Verifies output of FIC-306 is 95%.
Starts 11 CS Pump, observes running indications.
Slowly lowers output of FIC-306.
Checks flow indication for FIC-306.
Lowers output until flow indicates 1500-2000 GPM.
NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) b: The CRS desires to have FIC-306 in Auto.
Examiner Note:
If applicant does not adjust auto setpoint on FIC-306, flow will attempt to control at previous setpoint of 3000 gpm. Per system description, Containment Spray Pumps are designed to pump approximately 1400 gpm in injection mode.
- m.
Place the SHUTDOWN CLG Adjusts flow setpoint on FIC-306 to match existing flow, then places FLOW CONTR, 1-FIC-306, in AUTO, if desired.
HC-306 to AUTO.
1 CUE: The CRS desires to restore RCS temperature to 140 O F. When SI-657-CV is throttled open, inform applicant that temperature is slowly lowering on TR-351.
n If HS-3657 is in CLOSE, places HS-ve, 3657 to AUTO. Raises output of HIC-657. Checks SDC temperature slowly lowering (TR-351 on 1C09).
TERMINATING CUE:
This JPM is complete when SDC has been restored using a CS Pump. The examiner is expected to end the JPM after applicant adjusts SI-657-CV. No further actions are required.
TIME STOP NRC-05 Page 8 of 10 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-05 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-05 Page 9 of 10 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
Unit 1 is in Mode 5 and has been shutdown for 5 days.
12 LPSI PP is running on SDC. 11 LPSI PP is aligned for SDC operation and is not running.
50 psia with a bubble in the pressurizer.
- 3.
RCS is at 140°F and INITIATING CUE:
You are performing the duties of the Unit 1 ROKRO.
NRC-05 Page 10 of 10 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Facility: Calvert Cliffs 1&2 Job Performance Measure No.:
NRC-06 Task
Title:
Task Number: 024.006 K/A
Reference:
064.K4.02 (3.9,4.2)
Parallel 1A DG to 4kV Bus 11/17 [Alternate Path]
Method of testing:
Simulated Performance:
Actual Performance:
4 C1 as sroom:
Simulator:
4 Plant:
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
h i ti a1 Conditions :
- 1.
- 2.
- 3.
1A Diesel Generator has been emergency started from the Control Room and is running unloaded.
1A Diesel Generator output breaker is open.
The Initial Conditions and General Precautions of 01-21A have been met.
Initiating Cue:
You are performing the duties of the Unit 1 CRO. The CRS directs you to parallel 1A Diesel Generator to 4kV Bus 11 per OI-21A, beginning at Step 6.3.B.1, and load the generator to 4.5 MW for testing.
Task Standard:
Parallel and load 1A Diesel Generator in accordance with 01-21A and trip the engine after receiving report about 10-10 lube oil pressure.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
NRC-06 Page 1 of 8 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- 4.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
None General
References:
- 1.
- 2.
- 3.
01-21, "1A Diesel Generator", Revision 19 1ClSA-ALM, "1A Diesel Generator Control Board Alarm Manual", Revision 2, Window AAOl lClSS-ALM, "1A Diesel Generator Local Control Panel Alarm", Revision 7, Window SL64 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
IC-19,80% power.
Verify sync scope has been recently calibrated.
Emergency start 1A DG by depressing 1-HS-1707.
Adjust incoming volts higher than running volts.
Adjust frequency for faster than desired in FAST direction.
Start 12 Control Room W A C Fan.
Override 1C18A Alarm Window AAO1, "1A DG" to ON on Trigger T1.
Override 1C17 Alarm Window M6, "1A DG CONTR BOARD 1C18A" to ON on Trigger T1.
Enter malfunction cwOO2-01 on F1.
- 10. Activate F1 after lCOS "SEQUENCER INITIATED" annunciator alarms (after applicant has paralleled the DG).
NRC-06 Page 2 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Identify and locate OI-21A, Step 6.3.B. 1.
Same as element.
CAUTION: When the DG is paralleled to the bus, the Shutdown Sequencer will start 11 and 12 Post-LOCI Filter fans and stop the Kitchefloilet Exhaust fan.
- 1. IF desired, ALIGN the Control Room W A C as follows:
VERIFY lC22,O-RI-5350 Same as element "CONTR RM VENT" is clear.
/CUE:
Kitchen / Toilet Fan Handswitch 0-HS-5359 is in OFF.
I 0
PLACE the Kitchefloilet Exhaust No action required. Handswitch is Fan Handswitch, 0-HS-5359, to OFF.
located outside of control room.
START the Post-LOCI filter fans Same as element by placing the handswitches to START AND LOG the starting time in the Charcoal Filter Log.
0 11 Post-LOCI Filter Fan &
Damper handswitch, 0-HS-5352 0
12 Post-LOCI Filter Fan &
Damper handswitch, 0-HS-5353 Control Room HVAC Units in the following alignment:
[CUE:
RO will log Post-LOCI filter fan start time in the Charcoal Filter Log.
START the Post-LOCI filter fans Same as element by placing the handswitches to START AND LOG the starting time in the Charcoal Filter Log.
11 Post-LOCI Filter Fan &
Damper handswitch, 0-HS-5352 0
12 Post-LOCI Filter Fan &
Damper hands wi tc h, 0-HS-5 3 5 3 Control Room HVAC Units in the following alignment:
NRC-06 Page 3 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
PREFERRED ALIGNMENT-Verifies 12 CR W A C in operation 12 CR HVAC in operation OR 11 CR HVAC in operation with the Control Room chiller Unit secured.
- 2.
1A DG received an emergency start Determines step is applicable and 1C18A to clear start signal.
- signal, depresses 1-HS-1708 pushbutton at THEN DEPRESS 1A DG SLOW START, 1-HS-1708, pushbutton, to clear the emergency start signal.
CAUTION: 1A DG should NOT be paralleled with 11/17 4KV Bus during periods when power is suspect (for example, during a severe storm).
Inserts sync stick into sync jack at 152-1703 (lC18A).
- 4. MOMENTARILY PLACE 1A DG Same as element at 1C18A.
SPEED CONTR, 1-CS-1705, to RAISE OR LOWER.
- 5. CHECK the Synchroscope and Sync Same as element.
Lights are operating on 1C18B.
Lowers incoming volts using 1-CS-1704.
Lowers incoming frequency to obtain slowly using 1-CS-1705.
CAUTION: TABLE 1, SHUTDOWN SEOUENCER LOADS, lists equipment that receives an auto start signal from the Shutdown Sequencer when the 1A DG output breaker is closed.
- 8.
Closes generator breaker when synchroscope needle reaches the 12 oclock position 2 5 degrees.
- 9.
Verifies approximately 0.70 M W load on 1A DG.
NRC-06 Page 4 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- 10. CHECK 1C08 annunciator, "SEQUENCER Checks "SEQUENCER INITIATED" alarms.
INITIATED" alarm on 1C08.
- 11. CHECK 1C17 annunciator "RAD MON Check "RAD MON PANEL PANEL 1C22" alarms (N/A if 0-RI-5350 is bypassed.)
1C22" alarm on 1C17.
NOTE:
The Control Room Vent RMS alarm, 0-RI-5350, may NOT be lit.
BYPASS lC22,O-RI-5350 "CONT RM VENT"
- 12. REMOVE the Sync Stick AND RETURN Same as element.
to Home Base.
CAUTION: Do NOT exceed limits of 5.400 MW, 500 KVARS, AND 752 amps.
- 13. RAISE MW AND KVAR loads concurrently to the desired levels PER the following:
Takes speed control switch to raise generator load until load is at least 1.0 MW.
Examiner Note:
1C18A Alarm Window AAO1, "1A DG" shortly after receiving 1C08 "SEQUENCER INITIATED" alarm.
Informs CRS. Contacts PO at 1A DG for further information.
CUE:
Plant Operator at 1A Diesel Generator reports that alarm is Window SL64, "LUBE OIL PRESS LO LO". Local lube oil pressure indicator shows 26 psi and lowering.
Refers to IC188 ALM.
Recognizes that condition exceeds automatic trip setting for 1A DG. Informs CRS.
Recommends manual trip.
NRC-06 Page 5 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL, STEP)
TIME STOP 1 TERMINATING CUE:
This task is complete when 1A Emergency Diesel Generator has been tripped in response to report of low lube oil pressure.
NRC-06 Page 6 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-06 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-06 Page 7 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
- 3.
1A Diesel Generator has been emergency started from the Control Room and is running unloaded.
1A Diesel Generator output breaker is open.
The Initial Conditions and General Precautions of 01-21A have been met.
INITIATING CUE:
You are performing the duties of the Unit 1 CRO. The CRS directs you to parallel 1A Diesel Generator to 4kV Bus 11 per OI-21A, beginning at Step 6.3.B.1, and load the generator to 4.5 MW for testing.
NRC-06 Page 8 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
Calvert Cliffs 1&2 Job Performance Measure No.:
NRC-07 Task
Title:
Perform Excore Calibration [Alternate Path]
Task Number: xxx.xxx WA
Reference:
015.A1.01 (353.8)
Method of testing:
Simulated Performance:
Actual Performance:
.(
Classroom:
Simulator:
.(
Plant:
~~
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
Unit 1 is in Mode 1 at 80% power, equilibrium conditions.
Delta-T power pot settings were checked per OP-3, "Normal Operations", Step 6.1.1.2.b and determined to be greater than acceptable tolerances.
Initiating Cue:
You are performing the duties of the Unit 1 ROKRO. In accordance with OP-3, "Normal Operations", Step 6.1.1.2.c(2), the CRS directs you to perform a NI calibration PER 01-30.
Task Standard:
Perform NI Calibration IAW 01-30.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Page 1 of 13 NUREG-1021, Revision 9 NRC-07
Appendix C Job Performance Measure Form ES-C-1 Worksheet NUC PWR YO CHAN Required Materials:
- 1.
- 2.
- 3.
Plant Setpoint File, system #94.
Plant Setpoint File, system #58.
Unit One Nuclear Instrumentation Calibration Data Sheet with "as found" values filled in as shown in the table below.
NUC PWR NUC PWR DELTA T DELTA T PWR V
POTSET PWR%
POT SET A
I 79.2 1
I 0.512 I
79.1 I
0.404 General
References:
- 1.
- 2.
- 3.
OP-3, "Normal Power Operation", Revision 55 01-30? "Nuclear Instrumentation, Revision 23 OI-50A, "Plant Computer", Revision 5 Time Critical Task:
No Validation Time:
25 minutes Simulator Setup:
- 1.
- 2.
On the plant computer:
Initialize simulator in IC-19 at 80% power (2160 MWth), MOL.
Select POINT MODIFY from the POINT PROCESSING MENU Enter a value of 76.5 for Point ID PAK0026 (RCP heat input constant) to reduce calculated thermal output by -60 MWth.
- 3.
- 4.
Run simulator to stabilize the PC thermal power calculations (PA912, PA911).
Set ALL RPS Channels to the "misadjusted" as-found values, shown in Table 1 of this JPM under the "Required Materials" heading.
NRC-07 Page 2 of 13 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- 5.
Place the DVM METER INPUT Switch on ALL RPS channels in the NUCLEAR POWER position.
NRC-07 Page 3 of 13 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START CAUTION:
Reactor thermal power level must be maintained constant throughout the calibration procedure.
Computer point status is indicated by a quality tag in the column between the VALUE and ENG UNITS columns.
NOTE:
0. -
IF the quality tag status column is blank AND theconstants associated with the point are correct AND the value for PA912 is consistent with related plant parameters, THEN the point is considered in service AND reliable.
This procedure contains reactivity sensitive steps, actions, or consequences. Caution should be used to control plant parameters that affect reactivity.
CAUTION:
Locates 01-30, Section 6.3 IF the Plant Computer is in service, THEN CHECK the reliability of PA912, 16 Minute Average Reactor Thermal Output calculation, as follows:
- a.
CHECK the quality tag column for computer point PA912.
Same as element.
Determines step is applicable.
- 1.
Observes computer point PA912.
Determines that no quality tag applied.
- b.
CHECK the following computer No action required.
points are updating properly:
0 Fllll F1121 0
P1013A 0
P1013B 0
P1023A P1023B 0
P4490 P4495 P3991 0
P4008 0
S3968 (Unit 1 only) 0 S3975 (Unit 1 only) 0 S8002 (Unit 2 only) 0 S8042 (Unit 2 only)
Observes the points. Determines they are updating properly.
NOTE:
Plant Computer Group 087 is reserved for the constants used in PA91 1, 2 Minute Average Reactor Thermal Output, which is used to generate PA912, 16 Minute Average Reactor Thermal Output.
I CUE:
When asked, provide copy of Plant Setpoints File, system #94.
I I
NRC-07 Page 4 of 13 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
~~
CUE:
If applicant requests further guidance of CRS upon discovering a constant is not set correctly, then inform applicant he is to to take actions as directed by procedure.
for the Plant Computer points li&d below:
e IF the plant is below 95% Rx Ewer (2565 MWth),
THEN CHECK the values of the Feedwater Flow Correction Factors are set to a value of 1.0 IF the plant is at 95% Rx Power (2565 MWth), OR greater, THEN CHECK the values of the Feedwater Flow Correction Factors match those listed on the Shift Turnover Sheet value of 1.0 OR e
are set to a P T F l l O O, 11/21 FW Flow Correction Factor Calls up each point. Compares constant value in computer to plant setpoint file. Determines that Point PAK0022 does not match setpoint file value.
Checks point values. Determines points correctly set at 1.O NRC-07 Page 5 of 13 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL, STEP)
FTF1200, 12/22 FW Flow Correction Factor
- e. -
IF the quality tag column for computer point PA912 is blank AND its value is consistent with related plant parameters AND all of the constants used in PA91 1 agree with the Plant Setpoint File, THEN USE computer calculation PA912 for core thermal power in this calibration.
Determines that will not use PA9 12 because of constant PAK0022 disagreement.
Determines constant does not agree.
Goes to Section 6.5.
If applicant goes to Section 6.5, then CRS informs him that Section 6.5 has been completed with manual secondary calorimetric result of 2162 MWth=80.07%
I
- 3.
Calculate the required trip unit input No action required.
voltage as follows:
- a.
PA912 is used, No action required.
THEN OBTAIN the value from the Plant Computer for PAPCNTPW OR DIVIDE PA912 value by 27 Am RECORD this number in the NUCLEAR INSTRUMENTATION CALIBRATION log sheet as CALCULATED POWER Logs 80.07 MWth in procedure.
NRC-07 Page 6 of 13 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL, STEP)
Divides 80.07 by 20.
VOLTS in procedure.
Logs 4.0037 NOTE:
0 Signoff spaces are provided for placekeeping only, complete only for channels requiring calibration. (N/A blocks for channels not calibrated)
Excore NI Power Range Safety Channel As Found data is collected one entire channel at a time, with the channels selected in any order.
0 Inform applicant that as-found data has been taken per Step 4 and is recorded on the data sheet. Direct applicant to continue at Step 5 for RPS Channel A only.
I
- 5.
DETERMINE the difference between the Records differences:
following for each channel:
Calc-Delta T = 1.O CALC PWR % AND DELTA T PWR m
Calc-Nuc = 0.8 YO CALC PWR % AND NUC PWR %
- 6.
IF any of the following apply, THEN PROCEED to step 8:
Proceeds to step 8.
Powerc70%
PA912 does NOT have a good quality point Either difference calculated in step 5 is
> to 1/2% for a specific channel CAUTION:
Calibration of an Excore NI Power Range Safety Channel renders the channel inoperable AND requires entry into Tech Spec 3.3.1 Action Statement.
I CUE:
CRS and other RO have entered TS 3.3.1 for inoperable NI channel for calibration. I
- 8.
IF directed by step 6, or if desired, THEN CALIBRATE each channel requiring calibration, by performing Steps
- a. through af. For a specific channel.
RECORD all data in the As Left section of the NUCLEAR INSTRUMENTATION CALIBRATION log sheet (unless otherwise specified).
No action required.
Stri Inserts keys in designated trip units.
NRC-07 Page 7 of 13 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL, STEP)
Turns to bypass trip unit. Observes bypass lights on the each unit.
CUE:
RO has independently verified that trip units 1,2,7,8 & 10 are bypassed.
- b.
INDEPENDENTLY VERIFY that Asks for independent verification.
RPS Trip Units 1,2,7, 8 & 10 are bypassed.
C.
PLACE the Linear Power Drawer Same as element.
Operate - Test switch in ZERO for the channel to be calibrated.
Same as element.
Gii
&,A
^ L ENSURE the DVM METER Same as element.
- e.
- f.
- g.
- h.
- 1.
NRC-07 INPUT switch in NUCLEAR PWR AND OBSERVE DVM reading.
IF the DVM reading is 2 1%,
THEN PERFORM the following:
No action required.
(1)
STOP the calibration (2)
NOTIFY the CRS (3)
INITIATE an IR to investigate AND REPAIR the channel.
PLACE the Linear Power Drawer Operate - Test switch in OPERATE.
Same as element.
Momentarily DEPRESS the Reset pushbutton on the front of the Linear Power Drawer Same as element.
IF tripped, Same as element.
THEN RESET VOPT AND RPS m n i t s 1, 2 and 10AND Page 8 of 13 NUREG-1021, Revision 9
STANDARD ELEMENT
(* = CRITICAL STEP) associated Control Room annunciators.
Same as element.
NOTE:
Each end of the male connector of the portable Calibration Cable is designed so that it will only fit in to it's respective receptacle.
Same as Same as Records element.
element.
3.976V.
section of the NUCLEAR INSTRUMENTATION CALIl3RATION log sheet.
NOTE:
Clockwise rotation of the potentiometers lowers the DVM reading and counterclockwise rotation raises the reading.
CAUTION: Potentiometer adjustments must be stopped immediately if 1(2)C05 annunciator "POWER LEVEL HIGH CHANNEL PRE-TRIP" alarms while adjusting a potentiometer.
Adjusts potentiometer to obtain reading on DVM equal to value calculated in Step 6.3.b.3.c. (4.0037, rounded to 4.00)
NRC-07 Page 9 of 13 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- 1.
PLACE the DVM METER INPUT Same as element.
switch in METER INPUT.
(1) IF 1(2)C05 annunciator "POWER TRIP" alarms while the potentiometer is being adjusted, THEN STOP the adjustment AND ENSURE the test switch alignment is correct.
Same as element.
LEVEL HIGH CHANNEL PRE-
- 0.
P-4-
- r.
S.
U.
V.
(2) IF 1(2)C05 annunciator "POWER LEVEL HIGH CHANNEL PRE-TRIP" alarmed AND the test switch alignment is correct, THEN REQUEST IM to check the HIGH POWER Trip Unit pre-trip AND trip setpoints on that channel.
LOCK the locking device on the NUCLEAR PWR CALIBRATE potentiometer.
IF the DVM reading changed while locking the Dotentiometer above.
THEG GO ITO step 1 [as in LIMA].
RECORD the DVM reading as NUC PWR (V),
RECORD the NUCLEAR PWR CALIBRATE potenti,ometer setting as NUC PWR POT SET.
PLACE the DVM METER INPUT switch in NUCLEAR PWR AND RECORD the DVM reading as Nuc PWR %.
PLACE the AT, TMLP CALCULATOR MODE switch in OPERATE.
the Trip Test cable was used, THEN DISCONNECT the RPS Trip Test cable from the I-n POWER Trip Unit.
IF the portable Calibration Cable was used, THEN PERFORM the following:
0 Disconnect the Calibration Cable Same as element Same as element.
Same as element.
Same as element.
Same as element.
Same as element.
Same as element.
Same as element.
NRC-07 Page 10 of 13 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) from the module drawer 0 Disconnect the Calibration Cable from the RPS HI PWR Trip Unit.
NOTE:
The deviation meter will fluctuate due to noise in the AT Power Channels.
Nuclear Power and AT Power DVM readings are equal at the zero mark.
Same as Same as Same as element.
element.
element AT PWR CALIBEATE potentiometer.
z, IF the DVM reading changed while locking the potentiometer above, THEN GO TO Step u.
CALIBRATE potentiometer setting to the As Found AT PWR CALIBRATE potentiometer setting AND the Plant Setpoint File, system #58.
No action required.
aa.
COMPARE the AT PWR Compares actual 0.428 to the tolerance of & 0.01 on setting of 0.431 (0.421 to 0.441).
ab.
IF the AT PWR CALIBRATE Determine setting is within potentiometer setting is outside the tolerance listed in the Plant Setpoint File THEN REFER to APPENDIX B for appropriate actions.
tolerance.
TERMINATING CUE:
This JPM is complete one channel calibration is complete. Inform applicant that task is complete when applicant has determined that Delta T Power settings are within tolerance band.
TIME STOP NRC-07 Page 11 of 13 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-07 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-07 Page 12 of 13 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANT'S CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
Unit 1 is in Mode 1 at 80% power, equilibrium conditions.
Delta-T power pot settings were checked per OP-3, "Norrnal Operations", Step 6.1.I.2.b and determined to be greater than acceptable tolerances.
INITIATING CUE:
You are performing the duties of the Unit ROKRO. In accordance with OP-3, "Normal Operations", Step 6.1.1.2.c (2)' the CRS directs you to perform a NI calibration PER 01-30.
NRC-07 Page 13 of 13 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-OS Task
Title:
Shift Component Cooling Heat Exchangers Task Number: 015.003 WA
Reference:
008.A4.01 (3.3,3.1)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
.I Plant:
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
Unit 1 is at 97% power.
11 CC Heat Exchanger is in service.
InitiatinP Cue:
You are performing the duties of the Unit 1 CRO. The CRS directs you to shift Component Cooling Heat Exchangers per the 01 in preparation for tagging out 11 Salt Water Header.
Task Standard:
Shift CC Heat Exchangers to place 12 HX in service and 11 HX in standby in accordance with 01-16.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
NRC-08 Page 1 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:
None General
References:
- 1.
01-16, "Component Cooling System", Revision 30 Time Critical Task:
No Validation Time:
10 minutes Simulator Setup:
- 1.
- 2.
Start with IC-13. Lower power to 97% (matches initial conditions for Ensure 11 CC HX in service and 12 CC PP running.
NRC-08 Page 2 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START
)CUE:
Initial Conditions and General Precautions are satisfied. Begin at Step 6.4.B.
CAUTION: RCS boron concentration will be affected when CVCS ion exchangers are returned to service if the letdown heat exchanger outlet temperature has changed since they were bypassed [BO2701 0
Lower Letdown system temperature will add positive reactivity.
0 Higher Letdown system temperature will add negative reactivity JCUE:
The CRS desires the CVCS Ion Exchangers to be bypassed.
]CUE:
The RO will log stop time in the CVCS Ion Exchanger and Filter Log.
NOTE TO EVALUATOR:
If asked, the CRS and the RO will ensure proper documentation (Locked Valve Deviation Sheets, etc) for the evolution.
- 1.
IF it is desired to bypass the CVCS ion exchangers, THEN PLACE IX BYPASS AND RECORD stop time in the CVCS Ion Exchanger and Filter Log. [BO0181 [BO2701 OPEN the Component Cooling Heat Exchanger outlet on the heat exchanger being placed in service:
RO will log stop time BYPASS, l-CVC-520-CV, to
- 2.
Verifies that 1-CC-3826-CV is open.
11 CC HX CC OUT, 1-CC-3824-CV 12 CC HX CC OUT, 1-CC-3826-CV THROTTLES 12 CC HX SW FLOW CONTR 1-HIC-5208 to match the output on 11 CC HX SW FLOW CONTR 1-HIC-5206.
NRC-08 Page 3 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(" = CRITICAL STEP)
CUE:
If asked, inform applicant that a dedicated operator has been assigned per the plaque on 1C13.
Closes 1-CC-3824-CV. Places 11 and 13 CC Pump in PTL in accordance with 1C13 plaque guidance.
Operator checks annunciator clear.
DISCH PRESS LO" annunciator clear.
NOTE:
For optimum Reactor Coolant Pump seal life and performance, controlled bleed off temperature must be maintained between 110 OF and 200 O F.
- 6.
SHUT the component Cooling Heat Exchanger saltwater outlet on the heat exchanger being removed from service:
(N/A if needed OPEN to maintain SW PP minimum flow requirements)
Evaluates Total SW flow and SHUTS 11 CC HX SW FLOW CONTR, 1-HIC-5206.
11 CC HX SW FLOW CONTR, 1-HIC-5206 12 CC HX SW FLOW CONTR, 1 -HIC-5208 NOTE:
If Component Cooling Heat Exchanger outlet temperature can NOT be maintained at approximately 95 OF, it is permissible to operate as low as 70 "F'. Operation below 70 "I? requires an engineering evaluation.
NRC-08 Page 4 of 7 Monitors CC temperature and adjusts 12 CC HX SW FLOW CONTR, 1-HIC-5208 as needed.
NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TERMINATING CUE: This task is complete when applicant has adjusted CC HX saltwater flow.
TIME STOP NRC-08 Page 5 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-OS Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-08 Page 6 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
Unit 1 is at 97% power.
11 CC Heat Exchanger is in service.
INITIATING CUE:
You are performing the duties of the Unit 1 CRO. The CRS directs you to shift Component Cooling Heat Exchangers per the 01 in preparation for tagging out 11 Salt Water Header.
NRC-08 Page 7 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-09 Task
Title:
Align Fire Water to AFW Pump Suction Task Number: xxx.xxx WA
Reference:
061.K4.01 (4.1,4.2)
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
A loss of all feedwater event is in progress on Unit 2.
The crew is implementing EOP-3.
Initiating Cue:
Method of testing:
Simulated Performance:
4 Actual Performance:
Classroom:
Simulator:
Plant:
4 Task Standard:
Align fire water to #23 AFW Pump suction per EOP Attachment 8.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
NRC-09 Page 1 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:
- 1.
Unit 2 EOP Attachment 8, "Maintain AFW Pump Suction Supply and CST Inventory", Revision 17 (Pg 2 of 5)
General
References:
- 1.
- 2.
Unit 2 EOP Attachment 8, "Maintain AFW Pump Suction Supply and CST Inventory", Revision 17 Unit 2 EOP-3, "Loss of All Feedwater", Revision 17 Time Critical Task:
No Validation Time:
5 minutes Simulator Setup:
None NRC-09 Page 2 of 6 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRTTICAL STEP)
TIME START NOTE:
CAUTION:
The following substeps are different methods, listed in preferred order, which may be used to line up an alternate supply to auxiliary feedwater pump suction.
Each available method should be attempted until a source of water has been established.
Before transferring AFW Pump suction to an alternate supply, the possibility of suction line or CST rupture should be considered.
[CUE:
The CRO reports that 23 AFW PP handswitch is in PULL TO LOCK.
- b.
Align the Fire System to 23 AFW PP suction as follows:
No action required.
(1) PLACE 23 AFW PP in PULL TO LOCK.
Calls Control Room. Requests 23 AFW PP Handswitch to be placed in PTL.
]CUE:
Valve stem fully lowered. Handwheel will not turn any further.
AFW PP Suction Valve, - Removes locking device. Turns
"^. handwheel clockwise until stem fully lowered.
m u 6
ICUE:
IExaminer Note:
Fire hose is connected to hose station and at pump suction hose fitting.
Key for locker on Turbine Building Operator key ring.
Locates hose station. Pulls hose out of st. Lays flat, no kinks or folds.
ose onto hose fitting on pump
[CUE:
2-AFW-180 valve stem is fullv raised. Handwheel will not turn.
1 Turns valve handwheel counterclockwise. Observes stem fully rise.
]CUE:
Fire hose discharge valve stem is fully raised. Handwheel will not turn any further. 1 Turns valve handwheel counterclockwise. Observes stem fully rise.
NRC-09 Page 3 of 6 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL, STEP) 1 CUE:
CRS / CRO acknowledges that 23 AFW PP suction is aligned to fire system.
Calls Control Room. Informs CRS or CRO that 23 AEW PP suction is aligned to fire system.
ITERMINATING CUE:
TIME STOP Task is complete when fire system is aligned to pump suction.
I NRC-09 Page 4 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-09 Applicant :
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
UNSAT Result:
SAT Examiners Signature and Date:
NRC-09 Page 5 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure FOITII ES-C-1 Worksheet APPLICANT'S CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
A loss of all feedwater event is in progress on Unit 2.
The crew is implementing EOP-3, "Loss of All Feedwater".
INITIATING CUE:
You are an extra RO on-shift, assigned as the Operations Technical Advisor. All other operators in the plant are busy with assigned tasks.
The CRS directs you to align the fire system to #23 AFW Pump per EOP, Step 4.b.
NRC-09 Page 6 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-10 Task
Title:
Task Number: 201.027 WA
Reference:
062.A2.05 (2.9,3.3)
Restore Reactor MCCs and Instrument Buses Method of testing:
Simulated Performance:
4 Actual Performance:
Classroom:
Simulator:
Plant:
.I READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
A fault in the switchyard resulted in a reactor trip on Unit 2.
EOP-7 was implemented because of 2A and 2B DGs failing to start and load their respective buses.
After a short delay, the OC DG has been aligned to 4kV Bus 24.
Initiating Cue:
You are performing the duties of the Unit 2 ABO. The CRS directs you to tie MCC-214 to MCC-204 in accordance with EOP-7, Block Step R.
Task Standard:
Tie MCC-214 to MCC-204 after 4kV Bus 24 is re-energized during a station blackout.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
NRC-10 Page 1 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials :
- 1.
Unit 2 EOP-7, Station Blackout, Revision 16, Pages 32 through 36.
General
References:
- 1.
Unit 2 EOP-7, Station Blackout, Revision 16 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
Not applicable. JPM simulated in the plant.
NRC-10 Page 2 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Locates and identifies EOP-7, Block Step R.
[CUE:
No fault is suspected on MCC-214.
CAUTION:
ATTEMPTS should NOT be made to re-energize a bus if a fault is suspected.
- 1.
IF MCC-204R or MCC-214R is de-energized, THEN perform the following actions :
- a.
IF MCC-214R is energized Determines that this step in N/A.
(MCC-204 is energized).
AND MCC-204R is NOT energized, Examiner Note:
4 KV Bus 24 has been re-energized, as stated in initial conditions, and is the normal supply to MCC-204R. Must use Step R. 1.b, beginning on EOP-7 Page 34 to tie "214 to 204" vice "204 to 214".
CAUTION:
Loads must be stripped from MCC-214R and MCC-204R to ensure 204R REACTOR MCC breaker, 52-2409 will NOT be overloaded.
- b.
IF MCC-214R is NOT energized AND MCC-204R is energized, THEN tie MCC-214R to MCC-204R as follows:
Determines that this step applies.
Goes to MCC-2 14 in Electrical Equipment Room, 69' Aux Bldg.
I CUE:
Handle is down.
1 NRC-10 Page 3 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
ICUE:
I CUE:
22 SALTWATER SYSTEM AIR COMPRESSOR is available.
Handle is in OFF position.
Verify SALTWATER Asks if 22 compressor is available and simulates opening the breaker for 21 compressor by turning the breaker handle counter clockwise to the OFF position.
I CUE:
22 BORIC ACID PUMP is available.
1 I CUE:
Handle is in OFF position.
(3)
Verify BORIC ACID PUMP Asks if 22 pump is available and OFF position
[CUE:
Handle is down.
Simulates opening the MCC breaker by handle down to the OFF position.
Examiner Note:
Procedure directs rotating bottom key, but keys are mounted side-by-side.
Should say rotate left key. Correctly identified as the "left" key in OI-27D, "Station Power 480V System", Step 6.12.B.13.b. Determined during JPM validation to be a minor problem. If applicant does not mention, then ask followup question after JPM about rules for procedure use. NO-1-201, "Calvert Cliffs Operating Manual", Step 5.1.B.l.c states "when steps are found which are incorrect, stop the job and consult with immediate supervision per PR-1-103, Use of Procedures.
CUE:
If applicant identifies procedure problem, inform applicant that Shift Manager has authorized a Drocedure deviation in order to meet the intent of the stem I CUE:
LEFT kev is rotated. Both kevs are removed.
Simulates rotating the left key and removing both keys.
NRC-10 Page 4 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
ICUE:
Key is inserted.
Simulates inserting key into interlock on face of Tie Bkr 52-2 1420 I CUE:
Key is rotated clockwise.
I Simulates rotating key clockwise.
I CUE:
Handle is up.
Close MCC-2 14R Tie Simulates closing the MCC breaker by pushing the breaker handle up to the ON position.
ICUE:
Key is inserted.
Goes to MCC-204 in 45' Aux Bldg Electrical Equipment Room.
Simulates inserting key into interlock on Tie Bkr 52-20420.
I CUE:
Key is turned clockwise.
Simulates turning key clockwise.
I CUE:
Handle is in ON position.
Simulates closing the MCC breaker by turning the breaker handle clockwise to the ON position.
TERMINATING CUE:
The JPM is complete when Breaker 52-20420 is closed. No further actions are required.
NRC-10 Page 5 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-10 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-10 Page 6 of 7 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
A fault in the switchyard resulted in a reactor trip on Unit 2.
EOP-7 was implemented because of 2A and 2B DGs failing to start and load their respective buses.
After a short delay, the OC DG has been aligned to 4kV Bus 24.
- 3.
INITIATING CUE:
You are performing the duties of the Unit 2 ABO. The CRS directs you to tie MCC-214 to MCC-204 in accordance with EOP-7, Block Step R.
NRC-10 Page 7 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Pedormance Measure No.: NRC-11 Task
Title:
Compressor Startup On Loss of Normal Cooling Task Number: 019.002 WA
Reference:
078.K1.04 (2.6,2.9)
Method of testing:
Simulated Performance:
4 Actual Performance:
Classroom:
Simulator:
Plant:
.I READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
Unit 2 is in Mode 3.
A loss of service water has occurred on Unit 2, resulting in a loss of instrument air due to a loss of air compressor cooling.
Initiating Cue:
You are performing the duties of an extra TBO qualified operator. The CRS directs you to line up alternate cooling to the Instrument Air Compressors from the fire system per the appropriate procedure.
Task Standard:
Align fire water cooling to the instrument air compressors per 01-19.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
NRC-1 1 Page 1 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:
- 1.
Unit 2 01-19, "Instrument Air", Revision 23 General
References:
- 1.
Unit 2 01-19, "Instrument Air", Revision 23 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
None NRC-11 Page 2 of 7 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Identify & locate 01-19, Section 6.4 Same as element.
CUE:
All initial conditions and precautions are met. A Fire System use permit has been obtained.
- 1.
OBTAIN a Fire System Use Permit.
Asks if Fire System Use Permit has been obtained.
- 2.
ALIGN the Fire Booster Pps as follows:
ICUE:
Booster pump starts.
- a.
PLACE BOOSTER JOCKEY Simulates placing HS-9600 in PUMP FIRE PROT/SYS, 0-HS-9600, in EXER.
EXER position (Pump and local handswitch located NE Turbine Bldg 12' on Unit 1 side).
I CUE:
When asked, 0-HS-6227 has been placed in PTL by the OSO.
- b.
PLACE MAIN PRESSURIZER Requests the OS0 or FASW to place 0-HS-6227 in PTL.
- 13,0-HS-6227 in PTL.
Locates valves, simulates operation and initiates AFW PP RM temperature monitoring as demonstrated by locating room temperature indicator 2-TI-5473 on the west wall of the TDAFW Pump Room (12' TI3 West Side).
NOTE:
Compliance with MN-1-110, TROUBLESHOOTING & PROCEDURE CONTROLLED ACTIVITIES, is required when using temporary hose connections.
The supply and discharge fire hoses are located in the AOP/EOP locker outside the SRW Room.
NRC-1 1 Page 3 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD 7
Examiner Note:
Applicant will locate a ladder in the cage east of the C02 Cardox Unit on the south end of Unit 2 TB 12' or from the toolroom in the Service Building on the 45'.
- 4.
ALIGN Fire Main to supply cooling water to the Instrument Air Compressors as follows:
- b.
CRACK OPEN Fire Main Supply Locates nearest Fire Main &
simulates connecting Fire Hose (Hose Station H-208, N of compressor).
Simulates flushing the Fire Hose.
to the hose connected in Step above AND purge fire main to a drain until clear water is discharged AND THEN SHUT the supply valve.
Simulates connecting fire hose at 2-SRW-182 and simulates opening the fire main supply valve.
- d.
CONNECT the drain hose to Auxiliary Water Return from Air Compressors, 2-SRW-184, AND floor drain.
DIRECT the hose to a floor drain.
Simulates connecting drain hose at 2-SRW-184 and routing to nearest
]CUE:
Hoses have been verified connected properly by the other TI30.
- e.
ENSURE that another TBO Requests verification of hose qualified operator VERIFIES the connection.
hoses connected properly.
LOG the connection of hose in the Turbine Building Operator's Log
- f.
Verbalizes logging the hose connections in the TI30 Log.
NRC-1 1 Page 4 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL, STEP)
CAUTION: Steps 4.g, 4h, 4.i and 4.j must be completed in a timely manner due to the Fire Main and Service Water System being cross-connected.
Locates and opens 2-SRW-184.
Locates and opens 2-SRW-182.
Locates and shuts 2-SRW-18 1.
Locates and shuts 2-SRW-183.
- 5.
IF the Instrument Air Compressors are
- shutdown, Determines that step is N/A.
NOTE:
Optimal Service Water return temperature is 110°F. SRW Return Temperature will be lower during colder months.
The LA Compressor TCV bypass valve SHALL be a minimum of ?&turn open under all normal operating conditions.
CUE:
21 Instrument Air Compressor is in service and SRW Outlet temperature is 103°F.
No adjustment is necessary.
- 6.
an Instrument Air Compressor is
- running, THEN MONITOR the Service Water Outlet Temperature maintaining temperature at 110°F (+lO"F)
Identifies proper TI and recognizes SRW outlet temperature is in the normal range (temperature indicator is upstream of 2-SRW-190 above the intercooler on N end of compressor).
TIME STOP TERMINATING CUE:
This JPM is complete when #21 Instrument Air Compressor Service Water Outlet temperature is checked. No further actions are required.
NRC-1 1 Page 5 of 7 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-1 1 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
~~~
~~
~~
~~
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-11 Page 6 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
Unit 2 is in Mode 3.
- 2.
A loss of service water has occurred on Unit 2, resulting in a loss of instrument air due to a loss of air compressor cooling.
INITIATING CUE:
You are performing the duties of an extra TBO qualified operator. The CRS directs you to line up alternate cooling to the Instrument Air Compressors from the fire system per the appropriate procedure.
NRC-1 1 Page 7 of 7 NUREG-1021, Revision 9
Job Performance Measure Form ES-C-1 Appendix C Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-12 Task
Title:
Task Number: 202.055 K/A
Reference:
033.A2.03 (3.1,3.5)
Respond to Lowering Refuel Pool Level Method of testing:
Simulated Performance:
4 Actual Performance:
Classroom:
Simulator:
Plant:
.I READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
Unit 2 is at 100% power. Unit 1 is in Mode 6 with fuel handling in progress.
The refuel machine operator has withdrawn a fuel assembly from the core into the refuel machine.
The upender is in the vertical position in containment.
The refuel machine is currently positioned over the core with the fuel assembly fully raised in the mast.
Initiating; Cue:
You are the Fuel Handling Supervisor and the fuel handling machine operator and are directed to place the fuel assembly in the upender per 01-25C, section 6.4.B step 28 and section 6.3.B step 10.
Task Standard:
Respond to loss of refueling pool level per AOP-6E.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
All sequential steps completed in order.
NRC-12 Page 1 of 8 MJREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- 3.
- 4.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1.
Unit 1 AOP-6E, Loss of Unit 1 Refueling Pool Level", Revision 7, Pages 1 thru 16 and Attachment 2.
OI-25E, "Fuel Transfer System", Revision 18.01-25C " Refueling Machine" sections 6.3 and 6.4
- 2.
- 3.
General
References:
- 1.
- 2.
- 3.
AOP-6E, "Loss of Unit 1 Refueling Pool Level", Revision 7 OI-25E, "Fuel Transfer System", Revision 18.01-25C " Refueling Machine" sections 6.3 and 6.4 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
None NRC-12 Page 2 of 8 NUREG-102 1, Revision 9
- 28. WHEN Spotter has given permission to move, THEN Position the RFM over the specified upender cavity coordinates.
- 10. PERFORM SEMI-AUTOMATIC positioning of the RFM as follows:
Refers to section 6.3.B.Step10 to move RFM..
(Candidate may use thejoy sticks to manically move the RFM.)
touch pad.
CUE: WHEN the fuel assembly has been lowered into the upender carriage at least 12 inches, THEN inform the applicant that the refueling control room operator has been directed to enter AOP-6E, Loss of Refueling Pool Level, due to a report of water entering the containment lower level and the CRO noting a decreasing RFP level indication. Provide a copy of AOP-6E.
NRC-12 Page 3 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
A.
PLACE FUEL ASSEMBLY OR REACTOR VESSEL INTERNAL STRUCTURE IN A SAFE LOCATION.
WARNING: For a Refueling Pool seal failure caused by movement of the CSB or UGS there may NOT be adequate time available to place the CSB or UGS in a safe location before radiation levels become unsafe. [BO1691
- 1.
IF a Reactor Vessel Internal Structure No action required.
(upper guide structure or core support barrel) is suspended from the polar crane, THEN direct the Reactor Vessel Job Supervisor to place the structure in a safe location PER the applicable Technical Procedure AND PROCEED to step C.
NOTE :
Applicable sections of 01-25 may be referenced if manual operation of equipment is desired.
WARNING: Failure to maintain level above an irradiated Fuel Assembly may result in overheating of the assembly and extremely high radiation levels.
- 2.
With direction from the Fuel Handling No action required.
Supervisor or the CRS, ensure that ALL Fuel Assemblies are placed in a safe location:
- a. IF a Fuel Assembly is partially No action required.
inserted into the Core or a SFP storage location, THEN insert it into its Core or SFP storage location.
Lowers the spent fuel assembly into the UT Upender and ungrapples.
NOTE :
The Fuel Assembly may be ungrappled with the approval of the FHS after it is placed in an approved Core or SFP storage location.
[CUE:
Assembly is fully lowered into the upender and ungrappled.
- c. IF a Fuel Assembly is fully withdrawn, THEN lower it into ANY of the following locations:
0 The Upender if indexed over it NRC-12 Page 4 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) 0 The bottom of RFP Upender area (Do NOT upgrapple) 0 The bottom of the SFP Upender area (Do NOT ungrapple) 0 An approved Core or SFP storage location CUE:
White Power light is out, red heaters on light is on.
Note to examiner: Simulate securing power to the RFM, or the computer must be rebooted I
- 3.
WHEN the fuel assembly is in a safe location, THEN secure power to the Refueling Machine by pushing the POWER OFF button on the console.
Depresses POWER OFF pushbutton and verifies white light is off and red heaters on light is lit.
B.
ISOLATE THE SFP FROM THE No action required.
RFP.
CUE:
Use 01-25E and the SFP Upender Console to demonstrate the upender operations.
NRC-12 Page 5 of 8 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
I CUE:
Vertical light is out on RFM console.
- 1.
IF the Transfer Carriage is in the RFP, THEN transfer it to the SFP PER 01-25E, FUEL TRANSFER SYSTEM Transfers carriage to SFP, or refers to 01-25E Simulates placing the AUTO Run handswitch on the RFM to START.
OR Places the AUTO MANUAL keyswj tch in the LOCAL AUTO position.
Places the AUTO RUN handswitch on the Transfer Machine Console to START.
TERMINATING CUE:
Task is complete when the upender has been transferred to the SFP.
TIME STOP NRC-12 Page 6 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-12 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-12 Page 7 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS :
- 1. Unit 2 is at 100% power. Unit 1 is in Mode 6 with fuel handling in progress.
- 2. The refuel machine operator has withdrawn a fuel assembly from the core into the refuel machine.
- 3. The upender is in the vertical position in containment.
- 4. The refuel machine is currently positioned over the core with the fuel assembly fully raised in the mast.
INITIATING CUE:
You are the Fuel Handling Supervisor and the fuel handling machine operator and are directed to place the fuel assembly in the upender per 01-25C, section 6.4.B step 28 and section 6.3.B step 10.
NRC-12 Page 8 of 8 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-13 Task
Title:
Align Shutdown Cooling Locally During Control Room Fire Task Number: xxx.xxx WA
Reference:
068.AK3.18 (4.2,4.5)
Method of testing:
Simulated Performance:
4 Actual Performance:
Classroom:
Simulator:
Plant:
4 READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ini ti a1 Conditions:
- 1.
- 2.
- 3.
Unit 1 was at 100% power and Unit 2 was performing a normal cooldowi with shutdown cooling in service at 240°F RCS temperature.
A fire occurred in the control room.
AOP-9A, "Control Room Evacuation and Safe Shutdown Due to a Sever1 Control Room Fire" has been implemented and the control room has been evacuated.
Initiating Cue:
You are performing the duties of a qualified AB0 and have been directed to lineup Unit 2 for shutdown cooling per AOP-9A, Section DB. You have just completed Steps DB.l through DB.lO. Continue with Step DB.ll.
Task Standard:
Align Shutdown Cooling for operation per AOP-9A.
Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
NRC-13 Page 1 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- 4.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1.
Unit 2 AOP-9A, "Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire", Revision 13, Step DB, Pages 83,84 of 94.
General
References:
- 1.
Unit 2 AOP-9A, "Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire", Revision 13 Unit 2 OI-3A, "Safety Injection and Containment Spray", Revision 22 (Attachment 1, Valve Alignment)
OP-1, "Plant Startup From Cold Shutdown", Revision 52, Figure 7, "SDC Flow Control Valve, l-SI-306-CV, Position Indication Diagram
- 2.
- 3.
Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
None NRC-13 Page 2 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START CUE:
CUE:
Note to Examiner:
Provide copy of Unit 2 AOP-9A, Step DB, Page 83 of 94 to applicant.
Position indicator pointing at CLOSE. Handwheel will not turn any further.
SI-399-MOV located in overhead. Applicant is not expected to climb into overhead. Have applicant point out valve from the floor level and discuss actions to be taken.
- 1 1. Mgr~ually shut Shutdown cooling Heat Exchanger Recirculation, 2-SI-399-MOV. (5 hallway, N of Cntmt I
>-.e..
Sump Pushes down and holds manual disengage lever. Turns handwheel in clockwise direction. Observes position indicator rotate to close position.
Handwheel stops when valve fully closed. Releases lever.
]CUE:
Handwheel turns clockwise to its stop.
. Shut 2-IA-643 to isolate Instrument Air.?I i,, Turns handwheel clockwise several to Shutdown Cooling Temperature Con?r~i^~~ve~~-SI-ij57-CV.
~
,, -, -. [SE C
rotations until it stops.
CUE:
Note to Examiner:
Fitting is loosened. Air line is removed.
657-CV is a fail closed valve. Air will be released from disconnected line and the valve will travel closed.
With wrench, loosens air fitting on actuator for 657-CV by turning counter-clockwise. Removes air line at actuator.
CUE:
Note to Examiner:
Handwheel turned fully, stem has raised, handwheel will not turn any further.
Handwheel for 657 is turned counter-clockwise to remove gag. Valve will go move upward to fail position (closed) under spring pressure with no control air. If applicant turns handwheel clockwise, provide cues for valve stem travel in downward (open) direction.
Turns handwheel counter-clockwise.
Valve handwheel stops turning. No observed stem motion [valve closed when air line removed.]
I C E :
Handwheel turns clockwise to its stop.
Turns handwheel clockwise several NRC-13 Page 3 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) rotations until it stops.
CUE:
Note to Examiner:
Fitting is loosened. Air line is removed.
306-CV is a fail open valve. Air will be released from disconnected line and the valve will travel oDen.
16 at With wrench, loosens air fitting on actuator for 306-CV by turning counter-clockwise. Removes air line at actuator.
pUE:
Handwheel turned fully, stem has lowered, handwheel will not turn any further.
Manually shut
- _.-I 2-SI-306-CV.
[E CC Turns handwheel clockwise. Valve stem motion observed. Handwheel stops when valve is fully closed.
- 0 ICUE:
Position indicator pointing at OPEN. Handwheel will not turn any further.
Pushes down and holds manual disengage lever. Turns handwheel in counter-clockwise direction. Observes position indicator rotate to open position. Handwheel stops when valve fully open. Releases lever.
ICUE:
Position indicator pointing at CLOSE. Handwheel will not turn any further.
1 Shutdown Cooling Recirci Pushes down and holds manual p, 2-SI-662-MOV. [22.- disengage lever. Turns handwheel in clockwise direction. Observes position indicator rotate to close position.
Handwheel stops when valve fully closed. Releases lever.
pUE:
Position indicator pointing at CLOSE. Handwheel will not turn any further.
NRC-13 Page 4 of 7 Pushes down and holds manual disengage lever. Turns handwheel in clockwise direction. Observes position indicator rotate to close position.
Handwheel stops when valve fully closed. Releases lever.
NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CFUTICAL STEP)
ICUE:
2C43 acknowledges SDC lineup is complete.
- 21. Notifies 2C43 that the Shutdown Cooling lineup is complete.
Same as element.
~TEFWINATING CUE:
TIME STOP Task is complete when 2C43 informed that lineup is complete.
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Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-13 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
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Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANT'S CUE SHEET INITIAL CONDITIONS :
- 1.
Unit 1 was at 100% power and Unit 2 was performing a normal cooldown with shutdown cooling in service at 240°F RCS temperature.
A fire occurred in the control room.
AOP-9A, "Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire" has been implemented and the control room has been evacuated.
- 2.
- 3.
INITIATING CUE:
You are performing the duties of a qualified A B 0 and have been directed to lineup Unit 2 for shutdown cooling per AOP-9A' Section DB. You have just completed Steps DB. 1 through DB. 10. Continue with Step DB.11.
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