ML062970325
| ML062970325 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/26/2006 |
| From: | Caruso J Operations Branch I |
| To: | Constellation Energy Group |
| Sykes, Marvin D. | |
| References | |
| 50-317/06-301, 50-318/06-301, ES-301, ES-301-2 50-317/06-301, 50-318/06-301 | |
| Download: ML062970325 (113) | |
Text
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 System / JPM Title
Facility: Calvert Cliffs Units 1 & 2 Exam Level (circle one): RO / SRO-I / SRO-u Date of Examination: 8/28/06 - 9/1/0t Operating Test Number:
2006 Type Code*
A,MS D,S M,S I
- e. RHR / Respond to Loss of Shutdown Cooling Pumps (NRC-05)
- g. NI / Perform Excore Calibration (NRC-07)
I A,D,L,S A,M,S A,MS A,NS
Safety Function 1
D S 2
D,E,R 6
4 (secondary:
(A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank r 9 l i ; 8 / < 4 (E)mergency or abnormal in-plant 2 1 1 2 112 1 (N)ew or (M)odified from bank including 1(A) 2 2 / 2 2 / 2 1 i 3 I i; 3 I s 2 (randomly selected) 2 l / z 1 / 2 1
' (L)ow-Power 2 1 1 2 1 1 2 1 (P)revious 2 exams (S)imulator 1 (R)CA 4 (primary) 6 7
8 I
D I
8 11 k. IA / Compressor Startup On Loss of Normal Cooling (NRC-I 1)
All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
II
- Type Codes Criteria for RO I SRO-I I SRO-U NUREG 1021 REVISION 9
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 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
Date of Examination: 8/28/06 - 9/1/0t Operating Test Number:
2006 System / JPM Title Type Code*
Safety I
Function
_ _ _ ~
~
~
A M s 1
11 c. ECCS / Respond to Spurious SlAS (NRC-03)
I M,S I
3
~
~~
~
- e. RHR / Respond to Loss of Shutdown Cooling Pumps (NRC-05)
A,D,L,S 4 (secondary:
4 (primary)
A,MS 6
- g. NI / Perform Excore Calibration (NRC-07)
A,NS 7
~
D S 8
4 11 j. AC / Restore Reactor MCCs and Instrument Buses (NRC-IO)
I D,E,R I
6
~~
1)espond to Lowering Refuel Pool Level (NRCG)
I N,R 1
8
~~
~
All control room (and in-plant) systems must be different and sewe different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes I
Criteria for RO I SRO-I I SRO-U (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
( W A (S)imulator 4-6 14-6 12-3 s 9 1 s 8 1 s 4 2 1 1. 2 1 / 2 1 2 1 1. 2 1 1 2 1 2 2 1 2 2 1 2 1 s 3 I i 3 I s 2 (randomly selected) 2 I l 2 1 1 2 1 NUREG 1021 REVISION 9
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2
I--
Facility: Calvert Cliffs Units 1 & 2 Exam Level (circle one): RO / SRO-I / SRO-U Control Room Systems" (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
Date of Examination: 8/28/06 - 9/1/OE Operating Test Number:
2006 System / JPM Title
- Type Codes (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
( W A (S)imulator Criteria for RO / SRO-I / SRO-U 4-6 / 4-6 12-3 9 i ~ a i ~ 4 L 1 / L 1 1 2 1 L 1 1 2 1 / r l L 2 / 2 2 / 2 1 s 3 I s 3 I s 2 (randomly selected)
L 1 1 2 1 / 2 1
- b.
- e.
- f.
- g.
I Type Code*
Safety Function I
in-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
I.
11 j. AC / Restore Reactor MCCs and Instrument Buses (NRC-IO)
~
I-pond to Lowering Refuel Pool Level (NRC-12)
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:
Task Number: 202.006 K/A
Reference:
024.AA1.17 (3.9,3.9)
Respond to Inadvertent Dilution While Critical (SOER 94-2)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
4 Plant:
READ TO THE EXAMINEE:
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.
InitiatinP Cue:
You are performing the duties of the Unit 1 RO/CRO. 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-01 Page 1 of 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure F O ~ I 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.
Start with IC-13. Lower power to 97% with CEAs inserted to 105".
Use System Lineup (26) Command VCT-CONC(1) = 400 to simulate placing a deborating demin in service. This pop up dialog screen can be used to set the VCT value to any desired concentration. Set the concentration in both lines of the dialog box. Save and then close the dialog box and ensure the system lineup now corresponds to the desired value. Execute the file and allow power to start rising.
Insert malfunction CEDSOOS for Shim Switch failure after CEAs are at 105".
Setup trigger fiie to trip the breaker for CVC-514-MOV (Bkr 52-10425).
The file should actuate remote function to open MCC breaker for CVC-514 when its handswitch is positioned to OPEN. If no remote function for the breaker, then have trigger a) override CVC-514 green hs light (1ZL514G) off, b) override CVC-514 red hs light (1ZL514Rl) off, c) override CVC-514 red hs light (1ZL514R2) off, d) override CVC-514 white hs light (lXL514W) off, e) override CVC-514 hs to the close position.
Run simulator until power begins to rise, then freeze. Reset the VCT concentration back to 897 ppm using system lineup.
- 3.
- 4.
- 5.
NRC-01 Page 2 of 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- 6.
When the applicant has placed CV-520 in bypass to remove the 1Xs from service, execute the VCT concentration file to stop the deboration.
NRC-01 Page 3 of 9 NUREG-1021, 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-512 is shut.
- 2.
Places HS-2520 to BYPASS on 1C07 and BYP position indication illuminated for CVC-520.
B.
CONTROL REACTOR POWER
- 1.
IF the rate of power rise can NOT be stopped,...
No action required at present time.
- 2.
Control the rise in power using CEAs and/or boration:
I CUE: CRS directs you 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 m Transient Inserti Selects Manual Sequential or Manual Group (and CEA Group V) and attempts to insert CEAs to control power rise. Recognizes that CEAs are not inserting.
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.
1 Examiner Note:
CVC-5 14 indication lost. Simulator setup will trip CVC-5 14-MOV breaker when examinee takes handswitch to open position.
- b.
Open the BA DIRECT Places HS-25 14 in open and checks indication for CVC-514. Recognizes CVC-5 14 does not open. Examinee should inform CRS.
M/U valve, 1-CVC-5 14-MOV NRC-0 1 Page 4 of 9 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) 1 Examiner Note:
If RO applicant asks CRS for guidance, CRS will direct examinee to follow the procedure.
0.1 IF this boration flowpath is Refers to Attachment (1).
NOT available, THEN attempt alternate methods of boration PER ATTACHMENT (1)
BORATING THE RCS NOTE:
The following eight methods of boration are arranged in order of preference.
The method used should be based on equipment availability.
- 1. IF the RCS is to be borated by ANY of the following methods, THEN proceed to the appropriate step:
Step 3, Page 3, BORATING FROM THE BASTs USING THE GRAVITY FEED VALVES
- 3.
BORATING FROM THE BASTs USING THE GRAVITY FEED VALVES
- a.
Check that the BAST(s) are available.
Places HS-226X and Y to stop and check stopped indication on BA Pps Examinee 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.
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.
- c.
Turns handswitch for CVC-501 to CLOSE position. Verifies has both red and green indicating lights lit.
Verifies CVC-50 1 fully closes by observing red handswitch lights out.
No action required.
- d. IF the RCS is on Shutdown Cooling, THEN verify that the boration flowpath is aligned to a RCS leg with Shutdown NRC-0 1 Page 5 of 9 NUREG-1021, Revision 9
STANDARD ELEMENT
(* = CRITICAL STEP)
Cooling flow CAUTION: Anytime the RCS temperature is less than 365°F AND Pressurizer level is greater than or equal to 170 inches, only ONE Charging Pump is allowed to be operated.
CUE:
If asked for guidance, CRS directs examinee to use the running charging pump and to NOT use the idle charging pumps.
Examiner Note:
Procedure requires all charging pumps. However, examinee 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.
- e.
- f. Verify Charging Flow by observing BAST level lowering.
Recognizes that all charging pumps running is not appropriate for current plant conditions. Informs CRS and asks for guidance.
Monitors BAST level.
(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(s) to AUTO position). Verifies valve(s) fully close by observing green handswitch light(s) out.
CAUTION: Turbine load or steam demand should not be raised if an inadvertent boron dilution event is in progress.
NRC-0 1 Page 6 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- 3.
Maintain T C ~ L D on program by No action required.
performing the following appropriate steps:
Adjust TBVs or ADVs Reduce Turbine load
- 4.
Notify the SO-BP of any electrical load changes.
No action required.
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 operator is expected to end the JPM.
TIME STOP NRC-0 1 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-01 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
~
Examinee Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-0 1 Page 8 of 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'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-1 A,Section V.
NRC-0 1 Page 9 of 9 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:
Task Number: 201.058 WA
Reference:
Oll.EA1.11 (4.2,4.2)
Align HPSI for Core Flush via Pressurizer Injection Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
.I Plant:
READ TO THE EXAMINEE:
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 100 PSIA with CETs indicating 310°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 AD, "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-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet 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
STANDARD ELEMENT
(* = CRITICAL STEP)
TIME START Identify and locate EOP-5, Step AD.
Same as element.
- 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:
Determines core flush is required.
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 available.
Checks HPSI pumps and determines 11 and 13 HPSI pumps are running (Red light on, Green light off, normal running amps).
Open the SI TO C H G m 1 -CVC-269-MOV.
"b lit, green light out Places HS in open, verifies red light C.
IF' CIS has actuated, Determines CIS has actuated.
AND IA CNTMT ISOL valve, 1-IA-2080-MOV is shut, THEN perform the following actions :
.,?......; *'
"-.--,,..A,.
.I I
NRC-02 Page 3 of 7 Places 1-HS-2080A in OVERRIDE.
Places 1-HS-2080 in OPEN, verifies red light lit, green light out.
Places HS-518 and HS-519 in CLOSE, verifies green lights lit, red lights out.
NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Open AUX SPRAY valve, 1-.
cvc-517-cv." 1 -
- h.
IF 13 HPSI PP is available, THEN perform the following actions:
(1)
Verify 13 HPSI PP is running (4)
(5)
IF approximately 150 Verify 11 or 12 HPSI PP is running.
GPM is NOT indicated THEN initiate Hot Leg Injection.
5
- 1.
IF 13 HPSI is NOT available...
- 2.
WHEN Pressurizer Injection OR Hot 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 I
- Press-urizer or HotTeg hjection and Cold Leg Injection by tl?ofiling the MAIN HPSI HDR NRC-02 Page 4 of 7 Adjusts HIC-100 to 0% output, observes lOOE and 1OOF green lights lit, red lights out.
Observes 656-MOV red light lit, green light off.
Places CVC-517 HS in OPEN, verifies red light lit, green light off.
Determines step is applicable.
Checks 13 HPSI PP indicating lights and amps.
Places SI-653 HS in CLOSE, verifies green light lit, red light out.
Places HS in CLOSE for 617,627, 637,647, verifies green lights lit, red lights out.
Checks 11 HPSI PP indicating lamps and amps.
Determines Hot Leg Injection is not required.
Verifies flow is 2150 GPM on 1-EA-2 12.
Determines step is NA.
Detehines step is applicable.
Checks or places control switches for the MAIN HPSI HDR valves in OVERRIDE by pulling up on handle.
NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- c.
Ensure CET temperatures remain constant or lowering.
Throttles MAIN PSI HDR valves to match Cold Leg injection flow to Pressurizer injection flow.
Refers to Attachment (10) and determines that minimum flow of 385 GPM is required. Checks total HPSI flow, and equally raises Cold Leg injection flow as required to meet the Attachment (10) requirement.
Monitors CET temperature and 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 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-02 Page 6 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
- 3.
- 4.
EOP-5 implemented.
A loss of coolant accident has occurred.
RCS pressure is 100 PSIA with CETs indicating 310°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 AD, "Commence Core Flush".
NRC-02 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-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 EXAMINEE:
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 3 at 38OoF, 800 psia. Two RCPs are in service.
A heatup to hot standby conditions is in progress.
OP-2, Step 6.56 has been completed.
Initiating Cue:
You are performing the duties of the Unit 1 ROKRO.
Task Standard:
Reset the spurious SIAS and terminate injection.
EvaIuation 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.
Required Materials:
NRC-03 Page 1 of 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet None General
References:
- 1.
- 2.
- 3.
- 4.
- 5.
1COS-ALM, "ESFAS 11 Alarm Manual", Revision 34 (Window G05)
EOP Attachment 2, "SIAS Verification Checklist", Revision 18-ESFAS Drawing 61058 and 58A, Revision 35 (1-LD-058, OSSA)
Drawing 61076 Sheet 14B, Control Ckt for 1-PS-5464-CV Dampierre Spurious SI Event, IAEA Nuclear Safety Review for 2003 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
- 1.
- 2.
- 3.
RCS at 380°F, 800 psia, 2 RCPs in operation. Complete OP-2 through Step 6.56.
Open RCS Sample Isolation 1-PS-5464-CV Setup to override the SIAS B Manual Actuation pushbutton at 1C10 depressed. Override will be initiated after the examinee has reviewed the cue, the operating procedure, the control boards and has "taken the watch".
NRC-03 Page 2 of 9 NUREG-102 1, Revision 9
ELEMENT STANDARD
(" = CRITICAL STEP)
TIME START
~~
examinee has "taken the watch", simulator booth operator will insert the Manual SIAS B override and then remove the override after SIAS actuates.
Locate and reference Alarm Manual for Same as element.
1CO8, G-05.
RESPONSE
1.a.
IF the reactor trips,
- b.
DETERMINE the validity of the SIAS by observing alternate channels of indication for the same parameter.
Check containment pressure parameters on 1C09.
Check pressurizer pressure parameters on 1C06.
Determines step is N/A.
Checks Containment pressure indications for pressure > 2.8 psig for 1C09. Determines pressure c 2.8 psig.
Checks Pressurizer pressure indications for pressure e 1740 psia on 1C06. Determines pressure < 1740 and rising.
1 CUE:
Acknowledge report from the applicant.
I Determines that SIAS actuation is not valid. Reports conclusion to CRS or SM..
CUE: SWCRS acknowledges invalid SIAS. Permission is granted to reset SIAS.
C.
IF the SIAS is invalid OR inadvertent, THEN, with Shift Manager OR Control Room Supervisor
Obtains approval to reset SIAS-B.
1 CUE: IF requested to reset SIAS locally, THEN the CRS directs reset from CR due to no additional resources.
NRC-03 Page 3 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
CUE: CRS advises utilizing EOP Attachments to reset SIAS.
I 0
Reference EOP Attachment (2) and References EOP Attachment (2).
reposition handswitch to post-accident position for equipment indicated with an asterisk (*).
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.
- b.
C.
- d.
- e.
- f.
11 and 13 HPSI PPs RUNNING 1 1 and 12 LPSI PPs RUNNING 11 and 12 CS PPs RUNNING MAIN HPSI HDR valves:
1 -SI4 16-MOV 1 -SI-626-MOV 1-SI-636-MOV 1-SI-646-MOV AUX HPSI HDR valves:
1-SI-617-MOV 1-SI-627-MOV 1-SI-637-MOV 1 -SI-647-MOV LPSI HDR valves:
1 -SI4 15-MOV 1 -SI-625-MOV 1-SI-635-MOV 1-SI-645-MOV Page 4 of 9 OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN 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.
NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- 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-614-MOV OPEN 1-SI-624-MOV OPEN 0
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.
0 1-SRW-1582-CV OPEN 0
1-SRW-1585-CV OPEN 1-SRW-1590-CV OPEN 1-SRW-1593-CV OPEN
- 1.
1 1,12 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.
0 1-WGS-2180-CV SHUT 1-WGS-2181-CV SHUT Repositions 5292-CV handswitch to CLOSE.
-.. Y \\.r <e., I 1 -CRM-529 1 -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
- 4.
RCS SAMPLE ISOL valve, May check valve shut by green 1-PS-5464-CV SHUT light lit.
- r.
H2 PURGE ISOL valves:
May check valves shut by green lights lit.
1-HP-6900-MOV SHUT 1 -HP-690 1 -MOV SHUT 1C07
- b.
11,12 and 13 RUNNING C.
VCT OUT valve, 1 -CVC-50 1-MOV SHUT
- d.
VCT M/U valve, 1-cvc-512-cv SHUT
- e.
BA DIRECT M/U valve, 1-CVC-5 14-MOV OPEN
- f.
11 and 12 BA PPs RUNNING
- g.
BAST GRAVITY FD valves:
NRC-03 1 -CVC-508-MOV OPEN 1-CVC-509-MOV OPEN
- h.
BAST RECIRC valves:
1-cvc-510-cv SHUT 1-cvc-511-cv SHUT Page 6 of 9 lights lit.
May check valve closed by green light lit.
May check valve closed by green light lit.
May check valve open by red light lit.
May check pumps running by red lights lit.
May check valves open by red lights lit.
May check valves closed by green lights lit.
NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Repositions CVC-505 handswitch to CLOSE.
1-CVC-506-CV SHUT CUE:
Tell examinee the rest of Attachment (2) is complete.
CUE:
When SIAS "B" reset PB depressed, alarm is clear.
Verifies "Actuation Sys SIAS Tripped" alarm annunciator 1C08 G-05 is clear (green).
CUE:
IF permission requested, CRS will direct examinee to stop injection pumps which started on the spurious SIAS.
Return components to their normal or desired status.
Requests CRS permission to stop injection pumps (12, 13 HPSI PPs, 12 CHG PP, 12 LPSI PP)
Places 12 HPSI PP handswitch in STOP, observes green light, lowering discharge pressure Places 13 HPSI PP handswitch in STOP, observes green light, lowering discharge pressure Places 12 CHG PP handswitch in STOP, observes green light, lowering discharge pressure 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 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-03 Page 8 of 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
- 3.
Unit 1 is in Mode 3 at 380°F, 800 psia. Two RCPs are in service.
A heatup to hot standby conditions is in progress.
OP-2, Step 6.5G has been completed.
INITIATING CUE:
You are performing the duties of the Unit 1 RO/CRO.
NRC-03 Page 9 of 9 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form 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 Task Number: 202.037 WA
Reference:
056.A2.04 (2.6,Z.S)
Method of testing:
Simulated Performance:
Actual Performance:
.(
Classroom:
Simulator:
.I Plant:
READ TO THE EXAMTNEE:
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 at 2% power during a plant startup.
13 Condensate Pump is danger tagged.
11 and 12 Condensate Pumps were in operation when both pumps tripped. Various alarms on 1C03, C-01 and C-02 (11 & 12 CONDS PUMP OIL FLOW LO) came in at the same time.
The running feed pump, 11 SGFP, tripped on low suction pressure.
- 4.
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 e5 % power, lower power to ~
1
~
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 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:
None General
References:
- 1.
AOP3G, 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 -2% power (no higher than 2.5%).
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-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START I CUE:
Begin at Step VI.A.1.
I Identify and locate AOP-3G, Step VI.A.l.
Same as element.
A.
DETERMINE IF A REACTOR TRIP IS REQUIREiD.
- 1.
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.
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.
- 1
~~
-~
If asked, the CRS does not desire to start any SGFPs due to the tripped condensate pumps.
- 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) e The standby SGFP is available There is sufficient time available to start the standby SGFP
- 2.
IF time does NOT permit starting the standby SGFP, Determines step is N/A. (Tripped SGFP cannot be restarted.)
NRC-04 Page 3 of 10 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
CUE:
If asked, the CRS does not desire to start any Condensate Booster Pumps due to the tripped Condensate pumps.
- 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.
CUE:
CRS directs that starting the tripped Condensate pumps not be attempted.
- a. 1 IF a backup Condensate Determines no backup pumps are Pump did NOT start, available since 13 Condensate pump THEN, with the approval of is tagged out.
the SWCRS, 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.
Proceeds to Step 5 based on direction of CRS.
NRC-04 Page 4 of 10 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
NOTE:
- 5.
IF Main Feedwater flow has been
- restored, to Step 6.
Determines step is N/A and proceeds 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, 1C05 andor 1C06, and TBV operation.
adjusting TBVs e
adjusting ADVS to maintain the following temperature band:
IF the Reactor is Determines Tc is within 2°F of
- critical, program.
THEN within 2°F of program TCOLD e
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:
(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-4521-CV 12 SG 1 -AFW-4530-CV 1-AFW-4531-CV Page 5 of 10 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Places handswitches 4070 and 4071 to OPEN and checks position indication for MS-4070A, 4071A, 4070, and 407 1.
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)
(12AFW) 1-HC-3987A 1 -HC-3989A a.1 Initiate AFW using 13 AFW PP as follows:
(1)
Verify open the motor driven Verifies OPEN AFW Block train SG AFW Block valves:
valves; l-AFW-4522,4523,4532, 4533-CV on 1C04. [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.
(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-1021, 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"F/hr 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).
Monitors SG level and adjusts flow controller setpoint to maintain SG level.
1 -FIC14525A (12 SG) 1-FIC-4535A
- b.
(11SG)
FW-4516 and 4517.
(12 SG)
Places handswitches 4516 and 4517 to SHUT, on 1C03 and checks position indication for 1-FW-4516-MOV 1-FW-4517-MOV
- c.
Notify Plant Chemistry that Notifies Plant Chemistry.
the AFW System is in service.
Red Inserts CEAs and/or borates to 1%.
reduce Reactor Power. Monitors Reactor Power, on 1C05
- 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:
1 CUE:
The CRS directs maintaining Reactor critical.
I 0
Maintain power less than Monitors Reactor Power, on 1C05.
1 % while attempting to restore the Main Feedwater System.
NRC-04 Page 7 of 10 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME STOP TERMINATING CUE:
This JPM is complete when S/G levels are between -24 and +30 inches and Reactor power is being maintained less than 1%. No further actions are required. The evaluator 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 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee 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 EXAMINEES CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
- 3.
Unit 1 is at 2% power during a plant startup.
13 Condensate Pump is danger tagged.
11 and 12 Condensate Pumps were in operation when both pumps tripped. Various alarms on 1C03, C-01 and C-02 (1 1 & 12 CONDS PUMP OIL FLOW LO) came in at the same time.
The running feed pump, 11 SGFP, tripped on low suction pressure.
- 4.
- 5.
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:
Task Number: 202.026 WA
Reference:
025.AA1.03 (3.4,3.3)
Respond to Loss of Shutdown Cooling Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
4 Plant:
~~
~
READ TO THE EXAMINEE:
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 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 115°F and 130 psia with a bubble in the pressurizer.
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 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure FOIITI ES-C-1 Worksheet Required Materials:
- 1.
Copy of alarm response for Window SM-66 of 1CMB-ALM, "Fire Systems Alarm Manual", Revision 40, Page 74 of 295.
General
References:
- 1.
- 2.
AOP-3B, "Abnormal Shutdown Cooling Conditions", Revision 22 lCMB-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.
Unit 1 in Mode 5 with a pressurizer bubble. RCS is at 115°F / 130 psia.
Use Malfunction SI003, "LPSI Pump Breaker Failure" to trip bkr on overcurrent when 11 LPSI pump is started by examinee.
Ensure 12 LPSI PP is in operation on SDC.
Align 11 LPSI PP for SDC with pump off.
0 RFI SIOxx to OPEN 11 LPSI SDC Suction 1-SI-441 0
RFI SI028 to CLOSE 11 CS PP Suction 1-SI-314 0 RFI SI007 to CLOSE 11 LPSI PP Suction 1-SI-444 NRC-05 Page 2 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
~~
~~~
CUE: Inform examinee that Alarm Window SM-66 has actuated on Fire Panel 1C24B. Provide applicant with copy of the alarm response for the alarm window.
TIME START
- 1.
Smoke or flame detected in Unit 1 ECCS Pump Rooms 11 8 (West Room) or Containment Recirculation Pipe Tunnel Room 122.
Determines step is applicable.
- a.
DISPATCH an operator and/or Dispatches an operator andor 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 I
PP.
Conclusion Informs CRS of field report of heavy smoke from 12 LPSI motor.
Recommends stopping 12 LPSI.
CUE: CRS acknowledges report. If examinee recommends stopping 12 LPSI, then CRS should direct stopping 12 LPSI. If no recommendation, CRS should ask examinee if he/she has any recommendations. If no, then CRS should direct stopping 12 LPSI.
Takes 12 LPSI PP handswitch to STOP, releases handswitch.
Observes green light lit and red light out. Observes amps go to zero.
Informs CRS.
1 CUE: CRS directs examinee to respond to the loss of SDC starting at AOP-3B, Step IV.A.6
~~
~
Locates AOP-3B7 Step IV.A.6.
Same as element.
NRC-05 Page 3 of 9 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL, STEP)
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.
C.
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 FTC-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:
11 LPSI PP RAS OVERRIDE, 1HS-302XA 12LPSIPPRAS OVERRIDE, 1-HS-302YA.
CAUTION: Before starting the standby LPSI PP, the cause for the running LPSI PP failure should be determined to preclude a common mode failure.
If necessary, CRS will inform examinee that cause appears to be motor internal fault. A common mode failure is not suspected.
I
- g.
Start the standby LPSI PP.
Places 11 LPSI PP handswitch in START. Observes breaker open green light on. Acknowledges 1C09 Window H-21 in alarm. Informs CRS.
NRC-05 Page 4 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) g.1.
IF the standby LPSI PP does NOT Refers to Step 3.
- 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
StepC.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.
Check that the SDC HDR RETURN ISOL valves are open:
Checks RCS pressure on PI-103 andor PI-103-1 on 1C06.
Determines pressure < 170 psia.
Verifies position of valves on 1CO9 C.
1 -SI-65 1 -MOV 1 -SI-652-MOV
- d.
Places handswitches to CLOSE.
Verifies valves close by observing green lights on, red lights off.
- e.
Isolate CS PP Min Flow to the RWT:
Places HS-3659A and 3660A on 1C09 in the ON position. Checks lockout lights on HS-3659 and 3660 are out.
NRC-05 Page 5 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Places HS-3659 and 3660 on 1C09 in CLOSE.
1 CUE:
I Examiner Note:
Simulator booth operator will need to open use remote functions to open SI-314 and SI-444 (Rm SI028, RFI SI007))
I CUE:
When dispatched, PO reports SI-314 and 444 are open.
I 0
11 CS PP Discharge
- valve, 1-SI-314 11 LPSI PP NORM SUCT ISOL valve, 1-SI-444
- g.
IF 12 CS PP is desired for SDC,
- h.
Shut the S/D COOLING TEMP CONTR valve, 1-SI-657-CV.
- 1.
Place the SHUTDOWN CLG FLOW CONTR, 1-FIC-306, in MANUAL.
j-Adjust the output of the SHUTDOWN CLG FLOW CONTR, 1-FIC-306, to 95%.
Determines step is applicable.
Dispatches PO to open SI-314 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%.
- k.
Starts 11 CS Pump, observes running indications.
- 1.
Slowly lowers output of FIC-306.
Checks flow indication for FIC-306.
Lowers output until flow indicates 6,
1500-2000 GPM.
NRC-05 Page 6 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
CUE:
The CRS desires to have FIC-306 in Auto.
- m.
Place the SHUTDOWN CLG Places RC-306 to AUTO.
FLOW CONTR, 1-FIC-306, in AUTO, if desired.
I CUE: The CRS desires to restore RCS temperature to 115 O F.
I If HS-3657 is in CLOSE, places HS-3657 to AUTO. Raises output of HIC-657. Checks SDC temperature slowly lowering (TR-351 on 1CO9).
- 6.
IF RCS temperature can NOT be maintained using one CS PP, AND RCS level is above the 37.6 foot elevation, Determines one CS Pp is able to maintain RCS temperature.
TERMINATING CUE:
This JPM is complete when SDC has been restored using a CS Pump. The evaluator is expected to end the JPM. No further actions are required.
TIME STOP NRC-OS Page 7 of 9 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion NRC-05 Job Performance Measure Number:
Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee Response:
UNSAT Result:
SAT Examiners Signature and Date:
NRC-05 Page 8 of 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEES 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.
RCS is at 115°F and 130 psia with a bubble in the pressurizer.
- 3.
INITIATING CUE:
You are performing the duties of the Unit 1 ROKRO.
NRC-05 Page 9 of 9 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-06 Task
Title:
Task Number: 024.006 WA
Reference:
064.K4.02 (3.9,4.2)
Parallel 1A DG to 4kV Bus 11/17 Method of testinv:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
4 Plant:
READ TO THE EXAMINEE:
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.
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 1.0 MW for testing.
Task Standard:
Parallel and load 1A Diesel Generator in accordance with 01-21A and trip the engine after receiving report about high crankcase 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 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:
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 AIarm",
Revision 7, Window SL61 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
- 1.
IC-13,100% power.
- 2.
- 3.
- 4.
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 NRC-06 Page 2 of 7 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START CAUTION:
- 1.
Identify and locate OI-21A, Step 6.3.B. 1.
When the DG is paralleled to the bus, the Shutdown Sequencer will start 11 and 12 Post-LOCI Filter fans and stop the KitchedToilet Exhaust fan.
Same as element.
IF desired, ALIGN the Control Room HVAC as follows:
VERIFY lC22,O-RI-5350 Same as element "CONTR RM VENT" is clear.
0 PLACE the KitchedToilet Exhaust Same as element Fan Handswitch, 0-HS-5359, to OFF.
0 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 12 Post-LOCI Filter Fan &
Damper handswitch, 0-HS-5353 0
Control Room HVAC Units in the following alignment:
ICUE:
Extra operator will ensure 12 CR HVAC is in operation.
PREFERRED ALIGNMENT-12 CR HVAC in operation OR e
11 CR HVAC in operation with the Control Room chiller Unit secured.
2, IF IA DG received an emergency start
- signal, depresses 1-HS-1708 pushbutton at THEN DEPRESS 1A DG SLOW START, 1-HS-1708, pushbutton, to clear the emergency start signal.
Determines step is applicable and 1C18A to clear 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).
NRC-06 Page 3 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
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 SEQUENCER LOADS, lists equipment that receives an auto start signal from the Shutdown Sequencer when the 1A DG output breaker is closed.
- 10.
- 11.
NOTE:
- 12.
CAUTION:
NRC-06 Closes generator breaker when synchroscope needle reaches the 12 oclock position 5 degrees.
Verifies approximately 0.70 M W load on 1A DG.
CHECK 1CO8 annunciator, SEQUENCER INITIATED alarms.
Checks SEQUENCER INITIATED alarm on 1C08.
CHECK 1C17 annunciator RAD MON PANEL lC22 a l m s (N/A if 0-RI-5350 is bypassed.)
Check RAD MON PANEL 1C22 alarm on lC17.
rhe Control Room Vent RMS alarm, 0-RI-5350, may NOT be lit.
BYPASS lC22,0-RI-5350 CONT RM VENT REMOVE the Sync Stick AND RETURN to Home Base.
Same as element.
Do NOT exceed limits of 5.400 MW, 500 KVARS, AND 752 amps.
Page 4 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- 13. RAISE MW AND KVAR loads concurrently to the desired levels PER the following:
- a.
Takes speed control switch to raise generator load until load is at least 1.0 M W.
]Examiner Note:
1C18A Alarm Window AAO1, "1A DG" will annunciate when load is 500 Informs CRS. Contacts PO at 1A DG for further information.
CUE:
Plant Operator at 1A Diesel Generator reports that alarm is "CRANKCASE PRESS HI". Local crankcase pressure indicator shows 2.65 inches of water.
TIME STOP Refers to IC188 ALM.
Recognizes that conditions exceed automatic trip setting for 1A DG. Informs CRS.
Recommends manual trip.
Manually trips 1A DG.
This task is complete when 1A Emergency Diesel Generator has been tripped in response to report of high crankcase pressure.
I TERMINATINGCUE:
NRC-06 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-06 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-06 Page 6 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEES 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 1.O MW for testing.
NRC-06 Page 7 of 7 NUREG-102 1, Revision 9
Appendix C Job Performance Measure FOITI ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-07 Task
Title:
Perform Excore Calibration Task Number: xxx.xxx WA
Reference:
015.A1.01 (3.5,3.8)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
Simulator:
J Plant:
READ TO THE EXAMINEE:
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.
NRC-07 Page 1 of 15 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:
- 1.
- 2.
- 3.
Plant Setpoint File, system #94.
Plant Setpoint File, system #58.
Nuclear Instrumentation Calibration log sheet.
General
References:
- 1.
- 2.
- 3.
OP-3, "Normal Power Operation", Revision 55 01-30, "Nuclear Instrumentation, Revision 23 01-50A, "Plant Computer", Revision 5 Time Critical Task:
No Validation Time:
15 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 Point ID PAKOO22 Enter a value such that the calculated thermal output drops by -60 MWth.
Run simulator to stabilize the PC thermal power calculations (PA912, PA911).
- 3.
NRC-07 Page 2 of 15 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START CAUTION:
NOTE:
0 e
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.
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.
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:
Fllll F1121 P1013A P1013B P1023A P 1023B P4490 P4495 P399 1 P4008 S3968 (Unit 1 only)
S3975 (Unit 1 only)
S8002 (Unit 2 only)
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.
1 CUE:
When asked, provide copy of Plant Setpoints File, system #94.
I NRC-07 Page 3 of 15 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
Calls up each point. Compares constant value in computer to plant setpoint file. Determines that Point PAK0022 does not match setpoint file value below:
0 IF the plant is below 95% Rx Power (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), QFJ 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 PTF1100, 11/21 FW Flow Correction Factor PTF1200, 12/22 FW Flow Correction Factor NRC-07 Page 4 of 15 Checks point values. Determines points correctly set at 1.0 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- 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.
CUE:
If examinee 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%
Determines constant does not agree.
Goes to Section 6.5.
Logs 80.07 MWth in Divides 80.07 by 20.
VOLTS in procedure procedure.
Logs 4.0037 NRC-07 Page 5 of 15 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
IBRATION log sheet as CAL.
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
- 4.
OBTAIN As Found data for each channel requiring calibration, by performing steps
- a. through f. for a specific channel.
RECORD all data in the As Found section of the NUCLEAR INSTRUMENTATION CALIBRATION log sheet.
- a.
RECORD the NUCLEAR PWR Records dial setting for selected No action required.
CALIBRATE Potentiometer Dial channel.
setting (FIGURE 1 - Item D).
- b.
RECORD the AT PWR Records dial setting for selected CALIBRATE Potentiometer Dial channel.
setting (FIGURE 1 - Item E).
C.
PLACE the DVM METER INPUT switch (FIGURE 1 - Item B) in MEmR INPUT Places switch in METER INPUT.
Momentarily DEPRESS each of the Reference Voltage Pushbuttons (FIGURE 1 - Item A) AND CHECK the DVM readings within the following limits:
Depresses each of the reference voltage pushbuttons. Verifies readings with prescribed ranges.
PUSHBUTTON DVM VOLTS READING
+10
(+) 9.990 to (+)10.010
- 10
(-) 9.990 to (-)lO.OlO ZERO
(+) 0.010 to (+)0.010 (1) IF any DVM reading is out of
- range, THEN INITIATE an IR to calibrate the DVM AND STOP calibration of this channel until the DVM is calibrated.
- e.
CHECK the DVM Scaling No action required.
Amplifier as follows:
NRC-07 Page 6 of 15 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
(1) PLACE the DVM METER INPUT switch (FIGURE 1 - Item B) in AT PWR AND RECORD the DVM reading as DELTA T PWR %.
Same as element.
(2) DEPRESS AND HOLD the pushbutton (FIGURE 1 - Item C)
AND ALLOW the DVM to stabilize.
Same as element.
METER READING-CALIBRATE (3) CHECK the DVM reading between 199 and 201%.
Same as element.
(4) RELEASE the METER READING Same as element.
- CALIBRATE pushbutton.
(5) IF the DVM reading is out of
- range, THEN INITIATE an IR to calibrate the DVM Scaling Amplifier AND STOP calibration of this channel until the DVM Scaling Amplifier is calibrated.
(6) PLACE the DVM METER INPUT switch (FIGURE 1 - Item B) in NUCLEAR PWR AND RECORD the DVM reading m C
PWR %.
No action required.
(7) DEPRESS AND HOLD the pushbutton (FIGURE 1 - Item C)
AND ALLOW the DVM to stabilize.
(8) CHECK the DVM reading between 199 and 201%.
Same as element.
METER READING-CALIBRATE Same as element.
(9) RELEASE the METER READING Same as element.
- CALIBRATE pushbutton.
(10)E the DVM reading is out of
- range, THEN INITIATE an IR to calibrate the DVM Scaling Amplifier AND STOP calibration of this channel until the DVM Scaling Amplifier is calibrated.
No action required.
NRC-07 Page 7 of 15 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL, STEP)
CUE:
Cue examinee that Steps a. through f have been completed for the other 3 channels.
Proceed with remaining steps ONLY for this channel.
- f.
REPEAT Steps a. through f. for the next NI channel until As Found data is obtained for all channels requiring calibration.
- 5.
DETERMINE the difference between the following for each channel:
CALC PWR % AND DELTA T PWR CALC PWR % AND NUC PWR %
any of the following apply, THEN PROCEED to step 8:
- 6.
Records dial setting for selected channel.
Records differences:
Calc-Delta T = ????
Calc-Nuc = 2% ???
Proceeds to step 8.
Power<70%
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.
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 No action required.
Inserts keys in designated trip units.
Turns to bypass trip unit. Observes bypass lights on the each unit.
NRC-07 Page 8 of 15 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
I
~~~
~
~
~~
RO has independently verified that trip units 1,2,7,8 & 10 are bypassed.
- b.
INDEPENDENTLY VERIFY that RPS Trip Units 1,2,7,8 & 10 are bypassed.
C.
PLACE the Linear Power Drawer Operate - Test switch in ZERO for the channel to be calibrated.
AND OBSERVE DVM reading.
IF the DVM reading is 2. I%,
THEN PERFORM the following:
- f.
(1)
STOP the calibration (2)
NOTIFY the CRS (3)
INITIATE an IR to investigate AND REPAIR the channel.
- g.
PLACE the Linear Power Drawer Operate - Test switch in OPERATE.
- h.
Momentarily DEPRESS the Reset pushbutton on the front of the Linear Power Drawer
- i. -
IF tripped, THEN RESET VOPT AND RPS Trip Units 1,2 and 10 AND associated Control Room annunciators.
NRC-07 Page 9 of 15 Asks for independent verification.
Same as element.
Same as element.
Same as element.
No action required.
Same as element.
Same as element.
Same as element.
Same as element.
NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
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 element.
Same as element.
Same as element.
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 IGH 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.
- 1.
PLACE the DVM M E E R INPUT Same as element.
switch in METER INPUT.
(1) 1(2)C05 annunciator "POWER Same as element.
LEVEL HIGH CHANNEL PRE-TRIP" alarms while the potentiometer is being adjusted, THEN STOP the adjustment AND ENSURE the test switch alignment NRC-07 Page 10 of 15 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) is correct.
(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.
NOTE:
- 0.
LOCK the locking device on the Same as element NUCLEAR PWR CALIBRATE potentiometer.
IF the DVM reading changed while locking the potentiometer above,
- p.
Same as element.
THEN GOTO Step 1 [as in LIMA].
- q.
RECORD the DVM reading as Same as element.
Nuc PWR (V),
- r.
RECORD the NUCLEAR PWR Same as element.
CALIBRATE potentiometer setting as NUC PWR POT SET.
S.
PLACE the DVM METER INPUT Same as element.
switch in NUCLEAR PWR AND RECORD the DVM reading as Nuc PWR %.
- t.
PLACE the AT, TM/LP Same as element.
CALCULATOR MODE switch in OPERATE.
- u. -
IF the Trip Test cable was used, THEN DISCONNECT the RPS Trip Test cable from the HI POWER Trip Unit.
Same as element.
- v.
IF the portable Calibration Cable Same as element.
was used, THEN PERFORM the following:
from the module drawer 0 Disconnect the Calibration Cable 0 Disconnect the Calibration Cable from the RPS HI PWR Trip Unit.
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.
NRC-07 Page 11 of 15 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
. Same as element.
Same as element.
Same as element Y.
Z.
aa.
ab.
ac.
ad.
AT PWR CALIBfiTE potentiometer.
IF the DVM reading changed while locking the potentiometer above, THEN GO TO Step u.
COMPARE the AT PWR CALIBRATE potentiometer setting to the As Found AT PWR CALIBRATE potentiometer setting AND the Plant Setpoint File, system #5 8.
IF the AT PWR CALIBRATE potentiometer setting is outside the tolerance listed in the Plant Setpoint File THEN REFER to APPENDIX B for appropriate actions.
RECORD the DVM reading as DELTA T PWR %.
RECORD the AT PWR CALIBRATE potentiometer setting as DELTA T PWR POT SET.
Same as element.
Same as element.
No action required.
Same as element.
Same as element.
Depresses reset pushbuttons.
Observes trip units reset and annunciators clear.
Rotates and removes keys.
NRC-07 Page 12 of 15 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL, STEP)
TERMINATING CUE:
This JPM is complete one channel calibration is complete. Inform examinee that task is complete after removal of trip bypass keys from calibrated channel.
TIME STOP NRC-07 Page 13 of 15 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-07 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee Response:
Result:
SAT TJNSAT Examiners Signature and Date:
NRC-07 Page 14 of 15 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'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, "Normal Operations", Step 6.1 L2.b and determined to be greater than acceptable tolerances.
INITIATING CUE:
You are perfonning the duties of the Unit 1 ROKRO. In accordance with OP-3, "Normal Operations", Step 6.1.I.2.c(2), the CRS directs you to perform a NI calibration PER 01-30.
NRC-07 Page 15 of 15 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:
~imu~ator: J Plant:
READ TO THE EXAMINEE:
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.
Unit 1 is at 100% power.
- 2.
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 0 1 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 Resuired Materials:
None General
References:
- 1.
01-16, "Component Cooling System", Revision 30 Time Critical Task:
No Validation Time:
10 minutes Simulator Setup:
- 1.
Reset to IC-13,100% power.
- 2.
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.
I 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
]CUE:
The CRS desires the CVCS Ion Exchangers to be bypassed.
1 NOTE TO EVALUATOR:
If asked, the CRS and the RO will ensure proper documentation (Locked Valve Deviation Sheets, etc) for the evolution.
- 1.
- 2.
NRC-08 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:
Records stop time in log BYPASS, l-CVC-520-CV, to 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 2 CC HX SW FLO CONTR 1-HIC-5208 to match the output on 11 CC HX SW FLOW CONTR 1-HIC-5206.
Page 3 of 7 NUREG-1021, Revision 9 7
ELEMENT STANDARD
( = CRITICAL, STEP)
CUE:
The CRS does not desire a dedicated operator stationed. The CRS desires to keep the B-Train CC Pump (12) in service.
- 5.
CHECK ( 1C 13) COMPT CLG PPS DISCH PkESS-Lo annunciator clear.
Closes 1 -CC-3824-CV. Places 1 1 and 13 CC Pump in FTL in accordance with IC13 plaque guidance.
Operator checks annunciator clear.
NOTE:
For optimum Reactor Coolant Pump seal life and performance, controlled bleed off temperature must be maintained between 110 F and 200 9.
SHUT the component Cooling Heat Evaluates Total SW flow and s H u T s 1 1 c c H x s w F L o w exchanger being removed from service:
CONTR, 1-HIC-5206.
(N/A if needed OPEN to maintain SW PP minimum flow requirements) 11 CC HX SW FLOW CONTR,
- 6.
Exchanger saltwater outlet on the heat 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 OF. Operation below 70 F 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-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
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
- 8.
IF the CVCS ion exchangers were bypassed in Step B. 1, THEN PERFORM the following:
Operator determines that step is applicable.
)CUE:
Letdown temperatures have stabilized and are less than 120'F.
- a.
CHECK the Letdown heat Operator checks temperature at exchanger outlet temperature 1C07.
has stabilized less than or equal to 120°F.
520-CV, to AUTO AUTO RECORD the flowrate in the CVCS Ion Exchanger and Filter Log for the in service ion exchanger and filter.
[BOO 181
- b.
PLACE IX BYPASS, 1-CV-Operator places 1-CVC-520-CV in C.
Operator logs flowrate in log.
TERMINATING CUE:
This task is complete when 1-CVC-520-CV is placed in AUTO.
No further actions are required.
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-08 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
~~
~
Examinee Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-08 Page 6 of 7 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEES CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
Unit 1 is at 100% 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:
Task Number: XXX.XXX WA
Reference:
061.K4.01 (4.1,4.2)
Align Fire Water to AFW Pump Suction Method of testing:
Simulated Performance:
4 Actual Performance:
Classroom:
Simulator:
Plant:
4 READ TO THE EXAMINEE:
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.
I Initiating Cue:
You are an extra RO on-shift, assigned as the Operations Technical Advisor.
The CRS directs you to align the fire system to #23 AFW Pump per EOP, Step 4.b.
~
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
(* = CRITICAL, 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.
pUE:
The CRO reports that 23 AFW PP handswitch is in PULL TO LOCK.
I
- b.
Align the Fire System to 23 AFW PP suction as follows:
(1) PLACE 23 AFW PP in PULL TO LOCK.
No action required.
Calls Control Room. Requests 23 AFW PP Handswitch to be placed in PTL.
]CUE:
Valve stem fully lowered. Handwheel will not turn any further.
Removes locking device. Turns handwheel clockwise until stem fully lowered.
]CUE:
Fire hose is connected to hose station and at pump suction hose fitting.
f?\\
P'nNNCi'C'T 'fire hn& hptyeen
-2 Locates hose station. Pulls hose out.
" iQitd Lays flat, no kinks or folds. Screws in.
A i
X, tools ;.P hose onto hose fitting on pump suction.
]CUE:
2-AFW-180 valve stem is fully raised. Handwheel will not turn.
1
..- Turns valve handwheel counterclockwise. Observes stem fully rise.
ICUE:
Fire hose discharge valve stem is fully raised. Handwheel will not turn any further. I Turns valve handwheel counterclockwise. Observes stem fully rise.
NRC-09 Page 3 of 6 NUREG-1021, Revision 9
ELEMENT
(" = CRITICAL STEP)
STANDARD I CUE:
CRS / CRO acknowledges that 23 AFW PP suction is aligned to fire svstem..
Calls Control Room. Informs CRS or CRO that 23 AFW PP suction is aligned to fire system.
TERMINATING CUE:
TIME STOP Task is complete when fire system is aligned to pump suction.
I NRC-09 Page 4 of 6 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of CompIetion Job Performance Measure Number:
NRC-09 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-09 Page 5 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'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 K/A
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:
4 READ TO THE EXAMINEE:
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 6 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 6 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Locates and identifies EOP-7, Block Step R.
I 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.
AND MCC-204R is NOT energized, 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.
Simulates opening the MCC breakers by turning the breaker handles counter clockwise to the 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.
Asks if 22 pump is available and simulates opening the breaker for OFF position NRC-10 Page 3 of 6 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL. STEP)
Simulates opening the MCC breaker by turning the breaker handle counter clockwise to the OFF position.
Same as element.
Same as element.
Same as element.
Simulates closing the MCC breaker by turning the breaker handle clockwise to the ON position.
Same as element.
Same as element.
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.
TIME STOP NRC-10 Page 4 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion NRC-10 Job Performance Measure Number:
Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-IO Page 5 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEES CUE SHEET 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.
NRC-10 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-11 Task
Title:
Task Number: 019.002 WA
Reference:
078.K1.04 (2.6,2.9)
Compressor Startup On Loss of Normal Cooling Method of testing:
Simulated Performance:
d Actual Performance:
Classroom:
Simulator:
Plant:
d READ TO THE EXAMINEE:
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-1 1 Page 2 of 7 NUREG-1021, 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:
- a.
PLACE BOOSTER JOCKEY Simulates placing HS-9600 in PUMP FIRE PROT/SYS, 0-HS-9600, in EXER.
EXER position.
ICUE:
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.
- 3.
SHUT the following valves AND Locates valves, simulates operation MONITOR AFW room temperature PER TI30 log notes:
0 and initiates AFW PP RM temperature monitoring.
INLET.TO AUX FD PP RM CLR, 2-SRW-502 0
- CLR, 2-SRW-503 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-11 Page 3 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRJTICAL STEP)
- 4.
ALIGN Fire Main to supply cooling water to the Instrument Air Compressors as follows:
Locates nearest Fire Main &
simulates connecting Fire Hose.
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.
CONNEC'I Auxiliary Water Return from Air 2-SRW-184 and routing to nearest Compre&ors, 2-SRW-184, AND floor drain.
DIRECT the hose to a floor drain.
ICUE:
Hoses have been verified connected properly by the other TBO.
- 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 TBO Log.
NRC-1 1 Page 4 of 7 NUREG-102 1, 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 Locates Locates Locates and and opens 2-SRW-184.
opens 2-SRW-1 82.
shuts 2-SRW-181.
shuts 2-SRW-183.
and and Instrument Air Proceed with Step 6.
- 5.
the Instrument Air Compressors are Determines that step is N/A.
- shutdown, Compressor is running. I NOTE:
Optimal Service Water return temperature is 110°F. SRW Return Temperature will be lower during colder months.
The IA 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 112°F.
No adjustment is necessary.
- 6.
an Instrument Air Compressor is
- running, THEN MONITOR the Service Water Outlet Temperature maintaining temperature at 1 10°F (+lO"F)
Identifies proper TI and recognizes SRW outlet temperature is in the normal range.
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-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion NRC-1 1 Job Performance Measure Number:
Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee Response:
UNSAT Result:
SAT Examiners Signature and Date:
NRC-1 1 Page 6 of 7 NUREG-102 1, Revision 9
Appendix C Job Performance Measure FOITI ES-C-1 Worksheet 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.
EXAMINEES CUE SHEET NRC-1 1 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-12 Task
Title:
Task Number: XXX.XXX WA
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 EXAMINEE:
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.
- 4.
- 5.
Unit 1 is at 100% power. Unit 2 is in Mode 6 with fuel handling in progress.
The refuel machine operator has withdrawn a spent fuel assembly from the core into the refuel machine and has traversed to the upender.
The upender is in the vertical position in containment.
The refuel machine is currently positioned over the upender and the spent fuel assembly is suspended over the upender.
An announcement over the paging system reports water pouring onto the Unit 2 containment floor and lowering refuel pool level.
Initiating Cue:
You are the fuel handling supervisor and are directed to perform actions of AOP-6E, "Loss of Unit 2 Refueling Pool Level".
Task Standard:
Respond to loss of refueling pool level per AOP-6E.
Evaluation Criteria:
- 1.
All critical steps completed.
NRC-12 Page 1 of 11 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- 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.
Required Materials:
- 1.
- 2.
Unit 2 AOP-6E, "Loss of Unit 2 Refueling Pool Level", Revision 7, Pages 1 thru 16 and Attachment 2.
OI-25E, "Fuel Transfer System", Revision 18.
General
References:
- 1.
- 2.
AOP-6E, "Loss of Unit 2 Refueling Pool Level", Revision 7 OI-25E, "Fuel Transfer System", Revision 18.
Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
None NRC-12 Page 2 of 11 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Evaluator instructions: Begin JPM in spent fuel pool area CUE:
Provide copy of Unit 2 AOP-6E to examinee.
CUE:
You are the fuel handling supervisor on the refuel machine in Unit 2 Containment.
Describe your actions per AOP-6E, Step A.
A.
PLACE FUEL ASSEMBLY OR No action required.
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.
Supervisor or the CRS, ensure that ALL Fuel Assemblies are placed in a safe location:
- 2.
With direction from the Fuel Handling No action required.
- 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.
- b. IF a Fuel Assembly is partially No action required.
inserted into the upender, THEN insert it into the upender.
NOTE :
NRC-12 The Fuel Assembly may be ungrappled with the approval of the FHS after it is placed in an approved Core or SFP storage location.
Page 3 of 11 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) p u E :
Assembly is fully lowered into the upender and ungrappled.
I
- c. IF a Fuel Assembly is fully Directs lowering the spent fuel assembly withdrawn, THEN lower it into ANY of the following locations:
into the RFP Upender and ungrappling.
0 The Upender if indexed over it e The bottom of RFP Upender area (Do NOT upgrapple) 0 The bottom of the SFP Upender area (Do NOT An approved Core or SFP storage location ungrapple) e Lcm:
Power is secured to the Refueling Machine.
1
- 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.
Same as element.
B.
ISOLATE THE SFP FROM THE No action required.
RFP.
1 CUE:
Use 01-25E and the SFP Upender Console to demonstrate the upender operations.
I I CUE:
Upender carriage is in the SFP.
- 1.
IF the Transfer Carriage is in the RFP, THEN transfer it to the SFP PER 01-25E, FWEL TRANSFER SYSTEM
??? Need specifics on upender operation. Should initial conditions establish refuel crew composition and mode of upender operation???
NRC-12 Page 4 of 11 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
NOTE:
Shutting the Transfer Tube Gate Valve, 0-SFP-2, may be delayed if additional time is needed to place a Fuel Assembly in a safe location.
1 CUE:
Horizontal position indicating light is lit on SFP Upender Control Panel.
- 2.
WHEN the Transfer Carriage is in the SFP, THEN perform the following actions:
Observes horizontal position indicating light on the SFP Upender Control Panel.
- a.
Ensure that it is in the horizontal position.
CUE:
You (fuel handling supervisor) have exited the containment and are in the SFP area to direct and assist other refuel crew members.
JCUE:
Control Room reports both 11 and 12 Spent Fuel Pool Cooling Pumps are stopped. I
- b. Stop 11 and 12 SFP CLG PPs:
Contacts Control Room. Requests stop of 11 and 12 SFP cooling pumps.
0-HS-1994 0-HS-1995ungrapple)
)CUE:
Valve stem fully lowered. Handwheel will not turn.
- c. Shut the Transfer Tube Gate Turns handwheel in clockwise direction.
Valve, 0-SFP-2.
Observes valve stem lower. Reaches end of travel. Handwheel will not turn (CUE:
Position indicator points at CLOSE. Handwheel will not turn.
direction. Position indicator points to CLOSE. Handwheel will not turn any (1 1 SFP Pump) 0-SFP-103 further.
(12 SFP Pump) 0-SFP-107 CUE:
Control Room has performed actions of Steps C and D. Proceed to Step E. Unit 2 RWT is almost empty. Fill Unit 2 RFF' from Unit 1 RWT using 12 SFP Cooling PumD.
E.
FILL THE RFF' IF NECESSARY No action required.
- 1.
IF draining the Refueling Pool down No action required.
to the reactor vessel flange will uncover any portion of a fuel assembly OR will cause unacceptably high NRC-12 Page 5 of 11 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) radiation levels due to uncovering a Reactor Vessel Internal structure (upper guide structure or core support barrel), THEN makeup to the RFP by ONE of the following methods:
- a. IF the Unit 2 RWT is used, THEN proceed as follows:
No action required.
NOTE :
The use of ATTACHMENT (2), MAKEUP TO THE UNlT 2 REFUELING POOL FROM THE UNIT 1 RWT, will require Unit 1 to be placed in a Shutdown Mode PER the applicable Technical Specifications.
NOTE :
The following options for RFP fill are listed in descending order of priority.
Refers to Attachment 2.
(1) From the containment floor PER ATTACHMENT (l), MAKEUP TO THE REFUELING POOL FROM THE CONTAINMENT FLOOR.
(2) From the Unit 1 RWT PER ATTACHMENT (2), MAKEUP TO THE UNIT 2 REFUELING POOL FORM THE UNIT 1 RWT.
NOTE :
The use of this attachment will require Unit 1 to be placed in a Shutdown Mode PER the applicable Technical Specifications. If the Unit 1 RWT is used to meet Unit 1 TRM 15.1.3, the level must be maintained greater than 12 inches.
ICUE:
Unit 1 is in Mode 5.
Place Unit 1 in a Shutdown Mode as required by the applicable Technical Specifications.
- 1.
No action required.
- 2.
No action required.
\\CUE:
Existing SFF cooling lineup has been secured per 01-24B by ABO.
- a. Secure the existing SFT Cooling No action required.
Lineup PER the applicable 01-24 series operating instruction.
NRC-12 Page 6 of 11 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
I CUE:
For each of the valves, the position indicator points at CLOSE. Handwheel will not I Turns each handwheel in clockwise direction. Position indicator points to CLOSE. Handwheel will not turn any further.
]CUE:
Valves indicate shut.
- c. Verify shut the following valves:
Verifies valve position indicator at CLOSE. Cannot turn handwheel any farther in clockwise direction.
11 SFP Pump Suction from 1 1 RFP Valve, 0-SFP-190
[W Wall, S of 11 PPI 12 SFP Pump Suction from 21 RFP Valve, 0-SFP-187
[N of 12 PPI 11 SFP Pump Discharge, 0-
[Disch of 11 PPI 12 SFP Pump Discharge, 0-SFP-107 [Disch of 12 PPI SFP-103 (CUE:
Valves indicate open.
- d. IF the transfer is going to take place with 12 SFP Pump, THEN perform the following actions:
(1)Verify open the following manual valves:
12 SFP Cooler Inlet Valve, 0-SFP-119 [S End, 12 HX]
Page 7 of 11 No action required.
Verifies valve position indicator at OPEN. Cannot turn handwheel any farther in counter clockwise direction.
NRC-12 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) 0 12 SFP Cooler Outlet Valve, 0-SFP-120 [N End, 12 HX]
0 12 SFP Pump Suction from 21 SFP Valve, 0-SFP-199 [N of 12 PPI 0
11 SFP Pump Suction from 11 SFP Valve, 0-SFP-194 Wall, S of 11 PPI 0
21 W P Inlet Valve, 0-SFP-226
[SW Corner, 27' W Pen Rm]
]CUE:
Valves indicate open.. Person dispatched to 0-SFP-178 reports valve is open.
Turns handwheel counter-clockwise.
Verifies valve position indicator rotates to OPEN. Cannot turn handwheel any farther in counter-clockwise direction.
Contacts personnel to open 0-SFP-178 in containment. Should communicate concerns about changing dose rates in containment.
CAUTION: The SFP CLG PPs do NOT have minimum flow protection. The SFP Pump Discharge Valve is throttled two turns open to protect the SFP CLG PP.
p l E :
Valve is throttled two turns open.
1 Turns handwheel counter-clockwise two turns.
ICUE:
Control reports pump is started.
- Contacts Control Room. Requests start of 12 SFP CLG PP.
NRC-12 Page 8 of 1 1 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
I CUE:
Pressure is 135 PSIG. Pressure decreases to 100 PSIG as valve is throttled open.
I (5)Throttle 12 SFP Pump Discharge Throttles valve open while monitoring crease on discharge pressure ps when pressure indicates TERMINATING CUE:
Task is complete when discharge pressure has been adjusted to 100 PSIG.
TIME STOP NRC-12 Page 9 of 1 1 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-12 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
~~~
~
Examinee Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-12 Page 10 of 11 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
Unit 1 is at 100% power. Unit 2 is in Mode 6 with fuel handling in progress.
The refuel machine operator has withdrawn a spent fuel assembly from the core into the refuel machine and has traversed to the upender.
The upender is in the vertical position in containment.
The refuel machine is currently positioned over the upender and the spent fuel assembly is suspended over the upender.
An announcement over the paging system reports water pouring onto the Unit 2 containment floor and lowering refuel pool level.
- 3.
- 4.
- 5.
INITIATING CUE:
You are the fuel handling supervisor and are directed to perform actions of AOP-GE, "Loss of Unit 2 Refueling Pool Level".
NRC-12 Page 11 of 11 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:
Task Number: XXX.XXX WA
Reference:
068.AK3.18 (4.2,4.5)
Align Shutdown Cooling Locally During Control Room Fire Method of testing:
Simulated Performance:
4 Actual Performance:
Classroom:
Simulator:
Plant:
4 READ TO THE EXAMINEE:
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 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.
I 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.
Task Standard:
AIign 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.
- 2.
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)
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)
CUE:
Valve is closed.
Note to Examiner:
Handwheel for 657 is turned counter-clockwise to close. If examinee turns handwheel clockwise, provide cues for valve stem travel in open direction.
TIME START CUE:
CUE:
Provide copy of Unit 2 AOP-9A, Step DB, Page 83 of 94 to examinee.
You have just completed Steps DB.l. thru DB.lO. Continue with Step DB.ll.
CUE:
Position indicator pointing at CLOSE. Handwheel will not turn any further.
1 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.
1 Turns handwheel clockwise several 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.
shut 2-SI-657-CV. [S Turns handwheel counter-clockwise.
Valve handwheel stops turning. No observed stem motion [valve closed when air line removed.]
ICUE:
Handwheel turns clockwise to its stop.
Turns handwheeI clockwise several rotations until it stops.
NRC-13 Page 3 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
[CUE:
Fitting is loosened. Air line is removed.
Note to Examiner:
306-CV is a fail open valve. Air will be released from disconnected line and the valve will travel open.
With wrench, loosens air fitting on actuator for 306-CV by turning counter-clockwise. Removes air line at actuator.
]CUE:
Valve is shut.
1 ally shut 2-SI-306-CV.
Turns handwheel clockwise. Valve
' stem motion observed. Handwheel
stops when valve is fully closed.
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.
I CUE:
Position indicator Dointing at CLOSE. Handwheel will not turn anv further.
1 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.
I CUE:
Position indicator Dointing at CLOSE. Handwheel will not turn anv further.
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.
NRC-13 Page 4 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
ICUE:
2C43 acknowledges SDC lineup is complete.
- 21. Notifies 2C43 that the Shutdown Cooling lineup is complete.
Same as element.
TERMINATING CUE:
TIME STOP Task is complete when 2C43 informed that lineup is complete.
NRC-13 Page 5 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure FOIXI ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-13 Examinee:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Examinee Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-13 Page 6 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET
- 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 AB0 and have been directed to lineup Unit 2 for shutdown cooling per AOP-9A' Section DB.
NRC-13 Page 7 of 7 NTJREG-1021, Revision 9