ML16028A020: Difference between revisions

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(Created page by program invented by StriderTol)
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GJPM-OPS-2015-AR3 Radiation Control Emergency Plan  R - M  Station Blackout Electrical Power Determination GJPM-OPS-2015-AR4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
GJPM-OPS-2015-AR3 Radiation Control Emergency Plan  R - M  Station Blackout Electrical Power Determination GJPM-OPS-2015-AR4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:
* Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from


Date of Examination:  12/07/2015 Operating Test Number
Date of Examination:  12/07/2015 Operating Test Number
Line 53: Line 53:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR1  Revision 0 GJPM-OPS-2015AR1 Page 4 of 7  Loss of Shutdown Cooling, Time to 200°F Determination JPM Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR1  Revision 0 GJPM-OPS-2015AR1 Page 4 of 7  Loss of Shutdown Cooling, Time to 200°F Determination JPM Notes: (Notes to Evaluator)
None. Task Overview:
None. Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task has the student to estimate time to reach 200°F following loss of shutdown cooling. Critical tasks are underlined, italicized, and denoted by an (*)
This task has the student to estimate time to reach 200°F following loss of shutdown cooling. Critical tasks are underlined, italicized, and denoted by an (*)
Step 1:  05-1-02-III-1, Attachment 1
Step 1:  05-1-02-III-1, Attachment 1
* Using given information, determines time to boil is approximately [[estimated NRC review hours::4 hours]]. Standard:  The operator determines using procedure 05 02-III-1 Attachment I, Figure 2 that there are about [[estimated NRC review hours::4 hours]] to 200°F
* Using given information, determines time to boil is approximately 4 hours. Standard:  The operator determines using procedure 05 02-III-1 Attachment I, Figure 2 that there are about 4 hours to 200°F
. Cue:  None. Notes:  SAT / UNSAT
. Cue:  None. Notes:  SAT / UNSAT


Line 129: Line 129:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR2  Revision 0 GJPM-OPS-2015AR2 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR2  Revision 0 GJPM-OPS-2015AR2 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will perform a Fire Door Alarm Check using the information provided in the initiating ques. The operator will discover tech spec door OC208 is INOP, tech spec door 1A212 is OPERABLE but requires a WR to fix the closing mechanism, and non
The operator will perform a Fire Door Alarm Check using the information provided in the initiating ques. The operator will discover tech spec door OC208 is INOP, tech spec door 1A212 is OPERABLE but requires a WR to fix the closing mechanism, and non
-tech spec door 1A604 also requires a WR to fix the security alarm timing and a rust patch. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
-tech spec door 1A604 also requires a WR to fix the security alarm timing and a rust patch. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 146: Line 146:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR2  Revision 0 GJPM-OPS-2015AR2 Page 5 of 7 Step 2:  06-OP-SP64-M-0043
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR2  Revision 0 GJPM-OPS-2015AR2 Page 5 of 7 Step 2:  06-OP-SP64-M-0043
* Complete the surveillance coversheet section 3.1 by checking boxes for:
* Complete the surveillance coversheet section 3.1 by checking boxes for:
  (1) Partial procedure complete,  (2)* Tech Spec Acceptance Criteria Unacceptable, and  (3)* All other steps/data Unacceptable
(1) Partial procedure complete,  (2)* Tech Spec Acceptance Criteria Unacceptable, and  (3)* All other steps/data Unacceptable
. Standard:  Checks appropriate boxes.
. Standard:  Checks appropriate boxes.
Cue:  Notes:  SAT / UNSAT Step 3:  06
Cue:  Notes:  SAT / UNSAT Step 3:  06
Line 220: Line 220:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR3  Revision 0 GJPM-OPS-2015AR3 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR3  Revision 0 GJPM-OPS-2015AR3 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will use the provided electrical prints to prove that removing fuses, C71
The operator will use the provided electrical prints to prove that removing fuses, C71
-F14A and C71-27D, causes a Division 1 half scram
-F14A and C71-27D, causes a Division 1 half scram
Line 305: Line 305:
:  Station Blackout Table 1 Determination Notes: (Notes to Evaluator)
:  Station Blackout Table 1 Determination Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will use Table 1 of the Loss of AC ONEP to determine the load requirements to run RHR A. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
The operator will use Table 1 of the Loss of AC ONEP to determine the load requirements to run RHR A. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Step 1:  05-1-02-I-4 Table 1
Step 1:  05-1-02-I-4 Table 1
Line 353: Line 353:
ES-301 Administrative Topics Outline Form ES-301-1  Facility:  Grand Gulf Nuclear Station Date of Examination:  12/7/2015  Examination Level:  RO SRO    Operating Test Number:  LOT-201 5 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - D  Determine Firewatch Requirements GJPM-OPS-2015-AS1  Conduct of Operations R - N  Manual On-Line Risk Assessment GJPM-OPS-2015-AS2 Equipment Control R - D  Tagout Removal Approval GJPM-OPS-2015-AS3 Radiation Control R - D  Review Liquid Radwaste Discharge Permit GJPM-OPS-2015-AS4 Emergency Plan  R - N  Emergency Classification GJPM-OPS-2015-AS5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
ES-301 Administrative Topics Outline Form ES-301-1  Facility:  Grand Gulf Nuclear Station Date of Examination:  12/7/2015  Examination Level:  RO SRO    Operating Test Number:  LOT-201 5 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - D  Determine Firewatch Requirements GJPM-OPS-2015-AS1  Conduct of Operations R - N  Manual On-Line Risk Assessment GJPM-OPS-2015-AS2 Equipment Control R - D  Tagout Removal Approval GJPM-OPS-2015-AS3 Radiation Control R - D  Review Liquid Radwaste Discharge Permit GJPM-OPS-2015-AS4 Emergency Plan  R - N  Emergency Classification GJPM-OPS-2015-AS5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:
* Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank  (N)ew or (M)odified from
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank  (N)ew or (M)odified from


Date of Examination:  12/07/2015 Operating Test Number
Date of Examination:  12/07/2015 Operating Test Number
Line 394: Line 394:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS1  Revision 0 GJPM-OPS-2015CR1 Page 4 of 13 Determine Fire Watch Requirements Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS1  Revision 0 GJPM-OPS-2015CR1 Page 4 of 13 Determine Fire Watch Requirements Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The student will determine the required TRM Fire Watch actions for impairing a required fire water sprinkler system
The student will determine the required TRM Fire Watch actions for impairing a required fire water sprinkler system
. Sequence is not critical.
. Sequence is not critical.
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:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS1  Revision 0 GJPM-OPS-2015CR1 Page 7 of 13  Task Standard(s)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS1  Revision 0 GJPM-OPS-2015CR1 Page 7 of 13  Task Standard(s)
:  Candidate determines fire watch requirement for inoperability of sprinkler system N1P64D142A is to establish a continuous firewatch with backup fire suppression equipment in DG breezeway area 1D301 and an hourly fire watch patrol for Div 1 DG room 1D310 within one hour.
:  Candidate determines fire watch requirement for inoperability of sprinkler system N1P64D142A is to establish a continuous firewatch with backup fire suppression equipment in DG breezeway area 1D301 and an hourly fire watch patrol for Div 1 DG room 1D310 within one hour.
  (It is acceptable for the Candidate to establish a continuous fire watch patrol for Div 1 DG room 1D310 within one hour in lieu of an hourly firewatch patrol
(It is acceptable for the Candidate to establish a continuous fire watch patrol for Div 1 DG room 1D310 within one hour in lieu of an hourly firewatch patrol
.)  SAT / UNSAT Remember to record stop time
.)  SAT / UNSAT Remember to record stop time


Line 460: Line 460:
20: 4.6; 2.2.17: 3.8 Safety  Function
20: 4.6; 2.2.17: 3.8 Safety  Function
: Equipment Control
: Equipment Control
[10CFR55.4 3b (5)] Performance
[10CFR55.4 3b (5)] Performance
:  Actual  Reference(s)
:  Actual  Reference(s)
: 01-S-18-6, Risk Assessment of Maintenance Activities Handout(s)
: 01-S-18-6, Risk Assessment of Maintenance Activities Handout(s)
Line 491: Line 491:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS2  Revision 0 GJPM-OPS-2015AS2 Page 4 of 7  Manual Risk Assessment Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS2  Revision 0 GJPM-OPS-2015AS2 Page 4 of 7  Manual Risk Assessment Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The candidate will determine the Plant Safety Index risk color for the given plant conditions using 01
The candidate will determine the Plant Safety Index risk color for the given plant conditions using 01
-S-18-6 Attachment IV.
-S-18-6 Attachment IV.
Line 568: Line 568:
:  Tagout Approval Notes: (Notes to Evaluator)
:  Tagout Approval Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will determine the proper isolations for the LPCS Jockey Pump.
The operator will determine the proper isolations for the LPCS Jockey Pump.
Critical tasks are underlined, italicized, and denoted by an (*)
Critical tasks are underlined, italicized, and denoted by an (*)
Line 665: Line 665:
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5-AS4  Revision 1 4/22/13 Page 4 of 7  Review Liquid Radwaste Discharge Permit Notes: (Notes to Evaluator)
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5-AS4  Revision 1 4/22/13 Page 4 of 7  Review Liquid Radwaste Discharge Permit Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by Operations Supervision following a controlled release of liquid radwaste. Three errors have been introduced somewhere within sections 1 through 5 of the Discharge Permit.
This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by Operations Supervision following a controlled release of liquid radwaste. Three errors have been introduced somewhere within sections 1 through 5 of the Discharge Permit.
Critical step s are underlined, italicized, and denoted by an (*)
Critical step s are underlined, italicized, and denoted by an (*)
Line 785: Line 785:
ELAPSED TIME*                 
ELAPSED TIME*                 


              (minutes)
(minutes)
VALVES OPEN VALVES SHUT       
VALVES OPEN VALVES SHUT       


Line 916: Line 916:
ELAPSED TIME*                 
ELAPSED TIME*                 


              (minutes)
(minutes)
VALVES OPEN VALVES SHUT       
VALVES OPEN VALVES SHUT       


Line 1,001: Line 1,001:


Ref DATA SHEET I RADWASTE RELEASE INOP RADWASTE MONITOR PRE
Ref DATA SHEET I RADWASTE RELEASE INOP RADWASTE MONITOR PRE
-RELEASE ANALYSIS SAFETY RELATED        INITIALS    $ 5.2  Tank minimum recirculation of  [[estimated NRC review hours::2 hours]] met MW 5.3.1.b(1)
-RELEASE ANALYSIS SAFETY RELATED        INITIALS    $ 5.2  Tank minimum recirculation of  2 hours met MW 5.3.1.b(1)
Sample contains Resin and Chemistry Management Notified MW  5.3.1.b(2)
Sample contains Resin and Chemistry Management Notified MW  5.3.1.b(2)
Sample does not contain Resin N/A    $ 5.4.2  First Sample all significant peaks identified MW    $ 5.5.2  Second Sample all significant peaks identified MW    $ 5.6.1  ODCM dose limits are not exceeded.
Sample does not contain Resin N/A    $ 5.4.2  First Sample all significant peaks identified MW    $ 5.5.2  Second Sample all significant peaks identified MW    $ 5.6.1  ODCM dose limits are not exceeded.
Line 1,074: Line 1,074:
SB-125 1.79e-07 4.44e-08 YES LA-140 6.04e-08 2.56e-08 YES RB-88 7.85e-07 4.28e-07 YES ZN-65 2.14e-07 4.43e-08 YES C0-60 5.71e-07 3.11e-08 YES  TOTAL:  1.81e-06 F il e: 1 Sequen c e: 99999  F ilena m e: 00xxxxxx-01.pdf I nc lude d i n repo r t. EN D O F F I L E A T T A CH MENTS Date of Examination:  12/07/2015 Operating Test Number
SB-125 1.79e-07 4.44e-08 YES LA-140 6.04e-08 2.56e-08 YES RB-88 7.85e-07 4.28e-07 YES ZN-65 2.14e-07 4.43e-08 YES C0-60 5.71e-07 3.11e-08 YES  TOTAL:  1.81e-06 F il e: 1 Sequen c e: 99999  F ilena m e: 00xxxxxx-01.pdf I nc lude d i n repo r t. EN D O F F I L E A T T A CH MENTS Date of Examination:  12/07/2015 Operating Test Number
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS5  Revision 0 GJPM-OPS-2015AS5 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S5 JPM Title:  Emergency Event Classification Facility Number:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS5  Revision 0 GJPM-OPS-2015AS5 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S5 JPM Title:  Emergency Event Classification Facility Number:
_______ N/A  ___                  
_______ N/A  ___
          (If Bank or Modified from Bank)
(If Bank or Modified from Bank)
JPM Attributes:
JPM Attributes:
New Modified Direct from bank Time Critical 15 min  Alternate Path Validation Time:    10 min  Prepared By:
New Modified Direct from bank Time Critical 15 min  Alternate Path Validation Time:    10 min  Prepared By:
Line 1,110: Line 1,110:
Only the initial conditions for the specific scenario performed by the student as CRS is to be given to the student.
Only the initial conditions for the specific scenario performed by the student as CRS is to be given to the student.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
An event classification JPM is required of all licensed SROs not qualified as an Emergency Director in accordance with the Emergency Preparedness Plan.
An event classification JPM is required of all licensed SROs not qualified as an Emergency Director in accordance with the Emergency Preparedness Plan.
Tasks: Critical steps are underlined, italicized, and denoted by an (*)
Tasks: Critical steps are underlined, italicized, and denoted by an (*)
Line 1,160: Line 1,160:
* Type Codes Criteria for RO / SRO
* Type Codes Criteria for RO / SRO
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)  
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
ES-301 Control Room/In
ES-301 Control Room/In
-Plant Systems Outline Form ES-301-2  Facility:  GRAND GULF NUCLEAR STATION Date of Examination:  12/7/2015  Exam Level:  RO SRO-I        SRO-U        Operating Test No.:  LOT 2015  Control Room Systems
-Plant Systems Outline Form ES-301-2  Facility:  GRAND GULF NUCLEAR STATION Date of Examination:  12/7/2015  Exam Level:  RO SRO-I        SRO-U        Operating Test No.:  LOT 2015  Control Room Systems
Line 1,179: Line 1,179:
* Type Codes Criteria for RO / SRO
* Type Codes Criteria for RO / SRO
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)  
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
ES-301 Control Room/In
ES-301 Control Room/In
-Plant Systems Outline Form ES-301-2  Facility:  GRAND GULF NUCLEAR STATION Date of Examination:  12/7/2015  Exam Level:  RO SRO-I        SRO-U        Operating Test No.:  LOT-2015  Control Room Systems
-Plant Systems Outline Form ES-301-2  Facility:  GRAND GULF NUCLEAR STATION Date of Examination:  12/7/2015  Exam Level:  RO SRO-I        SRO-U        Operating Test No.:  LOT-2015  Control Room Systems
Line 1,198: Line 1,198:
* Type Codes Criteria for RO / SRO
* Type Codes Criteria for RO / SRO
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)  
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
Date of Examination:  12/07/2015 Operating Test Number
Date of Examination:  12/07/2015 Operating Test Number
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015 S 1  Revision 0 9/14/2015 Page 1 of 12 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 1 JPM Title:  Reset Recirc FCV Runback Facility Number: __GJPM-OPS-B3313____________
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015 S 1  Revision 0 9/14/2015 Page 1 of 12 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 1 JPM Title:  Reset Recirc FCV Runback Facility Number: __GJPM-OPS-B3313____________
                      (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min Prepared By:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min Prepared By:
Line 1,244: Line 1,244:
All controls will be from panel P680 in the Main Control Room.
All controls will be from panel P680 in the Main Control Room.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task resets a Recirc FCV runback following a trip of B RFP. When the operator depresses the RECIRC PMP B CAV INTLK RESET pushbutton, Recirc FCV B will ramp open from a malfunction. The operator must notice and report uncontrolled FCV opening and attempt to stop it. The CRS will direct shutdown of HPU B. The operator will take action to shutdown HPU B, shutdown the B Recirc Pump or shut the B33
This task resets a Recirc FCV runback following a trip of B RFP. When the operator depresses the RECIRC PMP B CAV INTLK RESET pushbutton, Recirc FCV B will ramp open from a malfunction. The operator must notice and report uncontrolled FCV opening and attempt to stop it. The CRS will direct shutdown of HPU B. The operator will take action to shutdown HPU B, shutdown the B Recirc Pump or shut the B33
-F067B from P680 which will terminate the power excursion. In the event the operator elects to perform all steps for FCV B first, all steps associated with FCV A become not applicable, and the JPM may be ended when the HPU for FCV B has been shut down
-F067B from P680 which will terminate the power excursion. In the event the operator elects to perform all steps for FCV B first, all steps associated with FCV A become not applicable, and the JPM may be ended when the HPU for FCV B has been shut down
Line 1,319: Line 1,319:
Date of Examination:  12/7/201 5 Operating Test Number
Date of Examination:  12/7/201 5 Operating Test Number
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5CR 2  Revision 0 9/14/2015 Page 1 of 9 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015CR2 JPM Title:  Defeat Feed Pump Level 9 Trips Facility Number: _GJPM-OPS-EOP006____________
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5CR 2  Revision 0 9/14/2015 Page 1 of 9 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015CR2 JPM Title:  Defeat Feed Pump Level 9 Trips Facility Number: _GJPM-OPS-EOP006____________
                      (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min Applicant: ________________________________
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min Applicant: ________________________________
Line 1,362: Line 1,362:
RFPT reset controls and indications are on P680.
RFPT reset controls and indications are on P680.
Panel P612 is in the Main Control Room Task Overview:
Panel P612 is in the Main Control Room Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task defeats the High Reactor Water Level trip of the Reactor Feed Pumps, which under certain conditions is directed by the EOPs to maintain adequate core cooling.
This task defeats the High Reactor Water Level trip of the Reactor Feed Pumps, which under certain conditions is directed by the EOPs to maintain adequate core cooling.


Line 1,456: Line 1,456:
All controls and indications for this task are on panel 1H13
All controls and indications for this task are on panel 1H13
-P 601. Task Overview:
-P 601. Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is to perform a slow close on MSIV B21
This task is to perform a slow close on MSIV B21
-F028A. Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Student should manually close all remaining MSIVs (7) using handswitches on P601 panel.
-F028A. Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Student should manually close all remaining MSIVs (7) using handswitches on P601 panel.
Line 1,565: Line 1,565:
All controls and indications for this task are on panel 1H13
All controls and indications for this task are on panel 1H13
-P6 01 and P870. Task Overview:
-P6 01 and P870. Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task requires the ability to manually start the only ECCS
This task requires the ability to manually start the only ECCS
-qualified high pressure injection system.
-qualified high pressure injection system.
Line 1,591: Line 1,591:
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5 S 4  Revision 0 9/14/2015 Page 7 of 13 Step 5:  06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 w VERIFY the following has occurred
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5 S 4  Revision 0 9/14/2015 Page 7 of 13 Step 5:  06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 w VERIFY the following has occurred
:  (2) F012, HPCS MIN FLO TO SUPP POOL, OPENS as discharge pressure indicated on PI-R601, HPCS PMP DISCH PRESS, increases above 130 psig.
:  (2) F012, HPCS MIN FLO TO SUPP POOL, OPENS as discharge pressure indicated on PI-R601, HPCS PMP DISCH PRESS, increases above 130 psig.
(3) HPCS Room Cooler Fan has started USING indication above HPCS PMP RM CLR T51-B001 handswitch on Panel 1H13
(3) HPCS Room Cooler Fan has started USING indication above HPCS PMP RM CLR T51-B001 handswitch on Panel 1H13
-P870-5C. (4) SSW LOOP C (HPCS SSW) on Panel 1H13
-P870-5C. (4) SSW LOOP C (HPCS SSW) on Panel 1H13
-P870-5C started automatically.
-P870-5C started automatically.
Line 1,698: Line 1,698:
- Containment Venting Notes: (Notes to Evaluator)
- Containment Venting Notes: (Notes to Evaluator)
: 1. This task is performed from the control room to vent the primary containment via 6
: 1. This task is performed from the control room to vent the primary containment via 6
-inch ventilation lines with no Containment or Secondary Containment Isolation signal present.  
-inch ventilation lines with no Containment or Secondary Containment Isolation signal present.
: 2. EP-1 attachments are maintained in a special file box normally located in or in the close proximity of the Emergency Locker in the Control Room behind the P601 panel.
: 2. EP-1 attachments are maintained in a special file box normally located in or in the close proximity of the Emergency Locker in the Control Room behind the P601 panel.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
Performance of this task vents the primary containment via 6
Performance of this task vents the primary containment via 6
-inch ventilation lines with no Containment or Secondary Containment Isolation signal present for M41 and E61 valves.
-inch ventilation lines with no Containment or Secondary Containment Isolation signal present for M41 and E61 valves.
Line 1,775: Line 1,775:
Date of Examination:  12/7/201 5 Operating Test Number
Date of Examination:  12/7/201 5 Operating Test Number
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S7  Revision 0 9/14/2015 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 7 JPM Title:  Reactor Manual Scram Switch Test Facility Number: __GJPM-OPS-C7105____________
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S7  Revision 0 9/14/2015 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 7 JPM Title:  Reactor Manual Scram Switch Test Facility Number: __GJPM-OPS-C7105____________
                      (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min
Line 1,812: Line 1,812:
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S7  Revision 0 9/14/2015 Page 4 of 11 Reactor Manual Scram Switch Test Notes: (Notes to Evaluator)
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S7  Revision 0 9/14/2015 Page 4 of 11 Reactor Manual Scram Switch Test Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will perform 06
The operator will perform 06
-OP-1C71-W-0001 (Reactor Manual Scram Switch Test).
-OP-1C71-W-0001 (Reactor Manual Scram Switch Test).
Line 1,925: Line 1,925:
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S8  Revision 0 9/14/2015 Page 4 of 15 Manual Start of SSW A Notes: (Notes to Evaluator)
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S8  Revision 0 9/14/2015 Page 4 of 15 Manual Start of SSW A Notes: (Notes to Evaluator)
All controls and indications for this task are on panel P870. Task Overview:
All controls and indications for this task are on panel P870. Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is a manual startup SSW 'A' and isolate the reported leak by shutting E12-F005A or securing SSW 'A' Pump.
This task is a manual startup SSW 'A' and isolate the reported leak by shutting E12-F005A or securing SSW 'A' Pump.


Line 2,193: Line 2,193:
__ GJPM-OPS-R2108____________
__ GJPM-OPS-R2108____________


          (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  30 min    Prepared By:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  30 min    Prepared By:
Line 2,299: Line 2,299:
:  LOT 20 15 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015PS-7  Revision 0 GJPM-OPS-2015PS-7 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-7  JPM Title:  PERFORM ATTACHMENT III OF SHUTDOWN FROM REMOTE SHUTDOWN PANEL ONEP Facility Number:
:  LOT 20 15 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015PS-7  Revision 0 GJPM-OPS-2015PS-7 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-7  JPM Title:  PERFORM ATTACHMENT III OF SHUTDOWN FROM REMOTE SHUTDOWN PANEL ONEP Facility Number:
__ N/A____________
__ N/A____________
                                                                                  (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time
New Modified Direct from bank Time Critical Alternate Path Validation Time
Line 2,609: Line 2,609:
A. Initialization
A. Initialization
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 4. Set the Simulator to IC-101 and perform switch check (Using Quick Reset in Director).
: 4. Set the Simulator to IC-101 and perform switch check (Using Quick Reset in Director).
Line 2,641: Line 2,641:
Power  9 5%    M OC  EOOS  GREEN Planned Evolutions this shift:
Power  9 5%    M OC  EOOS  GREEN Planned Evolutions this shift:
SSW A is operating per 04  03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.
SSW A is operating per 04  03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.
Rotate power on electrical bus 17AC from transformer ESF 12 to ESF  
Rotate power on electrical bus 17AC from transformer ESF 12 to ESF
: 21. C. Allow the crew to perform pre
: 21. C. Allow the crew to perform pre
-shift brief and review procedures for planned evolutions.
-shift brief and review procedures for planned evolutions.
Line 2,661: Line 2,661:
. BOP Using ESF BUS 17AC SOI , 04-1-01-R21-1 7 , section 4.3.2, performs the following:
. BOP Using ESF BUS 17AC SOI , 04-1-01-R21-1 7 , section 4.3.2, performs the following:
: a. ENSURE XFMR ESF 21 energized up to Bus Feeder Breaker 152-1705 as follows:
: a. ENSURE XFMR ESF 21 energized up to Bus Feeder Breaker 152-1705 as follows:
  (1) CHECK CLOSED J5206 FDR to XFMR ST
(1) CHECK CLOSED J5206 FDR to XFMR ST
-21  (2) CHECK CLOSED 552-2105 Bus 21R FDR FRM XFMR ST-21  (3) CHECK indicator 2R25
-21  (2) CHECK CLOSED 552-2105 Bus 21R FDR FRM XFMR ST-21  (3) CHECK indicator 2R25
-R603 34.5 kV voltage  (4) CHECK CLOSED 552-2104 Bus 21R FDR to XFMR ESF 21 (5) CHECK CLOSED 152-2902 FDR FRM XFMR ESF 21
-R603 34.5 kV voltage  (4) CHECK CLOSED 552-2104 Bus 21R FDR to XFMR ESF 21 (5) CHECK CLOSED 152-2902 FDR FRM XFMR ESF 21
Line 2,667: Line 2,667:
(6) CHECK ENERGIZED status light is On.
(6) CHECK ENERGIZED status light is On.
: b. TURN ON the Sync switch for Breaker 152
: b. TURN ON the Sync switch for Breaker 152
-1705 BUS 17AC FDR FRM XFMR ESF 21.
-1705 BUS 17AC FDR FRM XFMR ESF 21.
: c. CHECK that the sync scope comes up to 12 o'clock  
: c. CHECK that the sync scope comes up to 12 o'clock  
+ 10°.
+ 10°.
: d. ATTEMPT to CLOSE 152-1705 Bus 17AC feeder from ESF 21.
: d. ATTEMPT to CLOSE 152-1705 Bus 17AC feeder from ESF 21.


Line 2,722: Line 2,722:
TIME Position Applicant's Actions or Behavior BOP Performs surveillance 06
TIME Position Applicant's Actions or Behavior BOP Performs surveillance 06
-OP-1R21-W-0001 Attachment II.
-OP-1R21-W-0001 Attachment II.
  (See attachment 1)
(See attachment 1)
CRS Performs surveillance 06-OP-1R21-W-0001 Attachment III Page 6 of 6 only.  
CRS Performs surveillance 06-OP-1R21-W-0001 Attachment III Page 6 of 6 only.
(See attachment 1)
(See attachment 1)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 10 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 10 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 2,750: Line 2,750:
BOP Ensures all MSIV solenoid lights are energized and all MSIV pilot solenoids indicate amperage on panels 1H13
BOP Ensures all MSIV solenoid lights are energized and all MSIV pilot solenoids indicate amperage on panels 1H13
-P622 and P623.
-P622 and P623.
(Candidate will have to go behind the P807 panel and ask the Booth operator the status of indication due to P622 and P623 are not simulated in the Simulator.
(Candidate will have to go behind the P807 panel and ask the Booth operator the status of indication due to P622 and P623 are not simulated in the Simulator.


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 11 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 11 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 2,868: Line 2,868:
TIME Position Applicant's Actions or Behavior BOP Performs the following on P601 Panel
TIME Position Applicant's Actions or Behavior BOP Performs the following on P601 Panel
:  Inhibit ADS o Places ADS INHIBIT switches to the INHIBIT position Override HPCS injection by performing the following:
:  Inhibit ADS o Places ADS INHIBIT switches to the INHIBIT position Override HPCS injection by performing the following:
  (1) While HOLDING HPCS SYS INJECTION VLV (E22
(1) While HOLDING HPCS SYS INJECTION VLV (E22
-F004) handswitch in "CLOSE" position, ARM AND DEPRESS the manual system initiation push
-F004) handswitch in "CLOSE" position, ARM AND DEPRESS the manual system initiation push
-button for HPCS.  (2) AFTER indication of pump start, THEN TRIP the HPCS pum p.  (3) ENSURE the HPCS pump AND E22-F004 valve override alarms are sealed in.
-button for HPCS.  (2) AFTER indication of pump start, THEN TRIP the HPCS pum p.  (3) ENSURE the HPCS pump AND E22-F004 valve override alarms are sealed in.
Line 2,920: Line 2,920:
IF time does NOT permit closing of valves, THEN TRIP reactor feed pump(s) AND/OR condensate/condensate booster pump(s) to prevent injection.
IF time does NOT permit closing of valves, THEN TRIP reactor feed pump(s) AND/OR condensate/condensate booster pump(s) to prevent injection.
IF time permits closing of valves:
IF time permits closing of valves:
  (1) IF S/U level control in service, THEN CLOSE the S/U level control valve AND/OR N21-F040 IF necessary.
(1) IF S/U level control in service, THEN CLOSE the S/U level control valve AND/OR N21-F040 IF necessary.
  (2) IF S/U level control is NOT in service, THEN ALIGN Feedwater for S/U level control with S/U level control valve closed.
(2) IF S/U level control is NOT in service, THEN ALIGN Feedwater for S/U level control with S/U level control valve closed.
Per step L
Per step L
-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches  
-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches  
Line 2,935: Line 2,935:
ATWS (cont.)
ATWS (cont.)
TIME Position Applicant's Actions or Behavior BOP Terminates Low pressure ECCS systems by performing the following per 02
TIME Position Applicant's Actions or Behavior BOP Terminates Low pressure ECCS systems by performing the following per 02
-S-01-43, Transient Mitigation Strategy.  
-S-01-43, Transient Mitigation Strategy.
(1) ARM AND DEPRESS the manual system initiation push
(1) ARM AND DEPRESS the manual system initiation push
-button for selected division.
-button for selected division.
(2) AFTER indication of pump(s) start, THEN TRIP the pump(s).
(2) AFTER indication of pump(s) start, THEN TRIP the pump(s).
(3) CLOSE the associated injection valve(s).
(3) CLOSE the associated injection valve(s).
(4) ENSURE the associated pump(s) and valve(s) override alarms are sealed in.
(4) ENSURE the associated pump(s) and valve(s) override alarms are sealed in.
(5) REPEAT these steps for the other division.
(5) REPEAT these steps for the other division.
For Division 1 ECCS:
For Division 1 ECCS:
Low Pressure Core Spray system RHR 'A' LPCI system For Division 2 ECCS RHR 'B' LPCI system RHR 'C' LPCI system Per step L
Low Pressure Core Spray system RHR 'A' LPCI system For Division 2 ECCS RHR 'B' LPCI system RHR 'C' LPCI system Per step L
Line 2,978: Line 2,978:
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
-66 gpm after charging pressure is normal.  
-66 gpm after charging pressure is normal.
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
-66 gpm. Per 04-1-01-C11-1, Control Rod Drive SOI, Attachment VIII:
-66 gpm. Per 04-1-01-C11-1, Control Rod Drive SOI, Attachment VIII:
Line 2,997: Line 2,997:
TIME Position Applicant's Actions or Behavior CRS Directs for injection of Standby Liquid Control per Hard Card BOP Initiates Standby Liquid Control by performing the following per 04 01-C41-1 Section 5.3:
TIME Position Applicant's Actions or Behavior CRS Directs for injection of Standby Liquid Control per Hard Card BOP Initiates Standby Liquid Control by performing the following per 04 01-C41-1 Section 5.3:
: a. OBTAIN SLC Initiation keys from the Shift Manager's key cabinet, INSERT keys into SLC PMP A AND B key switches on 1H13
: a. OBTAIN SLC Initiation keys from the Shift Manager's key cabinet, INSERT keys into SLC PMP A AND B key switches on 1H13
-P601 AND TURN each momentarily to the START position (spring return to normal).
-P601 AND TURN each momentarily to the START position (spring return to normal).
: b. CHECK that system initiation has occurred by OBSERVING the following:
: b. CHECK that system initiation has occurred by OBSERVING the following:
(1) F001A AND F001B STORAGE TANK OUTLET valves OPEN as indicated on 1H13
(1) F001A AND F001B STORAGE TANK OUTLET valves OPEN as indicated on 1H13
-P601.  (2) Squib Valves F004A AND F004B fire as indicated by the following on 1H13
-P601.  (2) Squib Valves F004A AND F004B fire as indicated by the following on 1H13
-P601:  (a) White SQUIB VALVE READY light is Off.
-P601:  (a) White SQUIB VALVE READY light is Off.
(b) Annunciator "SLC SYS A AND B OOSVC" Alarms.
(b) Annunciator "SLC SYS A AND B OOSVC" Alarms.
(c) Amber status light SQUIB A AND B LOSCONT OR PWR LOSS is On.
(c) Amber status light SQUIB A AND B LOSCONT OR PWR LOSS is On.
(3) SLC Pumps A AND B start WHEN the associated storage tank outlet valves open as indicated by red pump running lights on 1H13
(3) SLC Pumps A AND B start WHEN the associated storage tank outlet valves open as indicated by red pump running lights on 1H13
-P601.  (4) The following RWCU valve(s) CLOSE:  (a) SLC A initiated  
-P601.  (4) The following RWCU valve(s) CLOSE:  (a) SLC A initiated  
- 1G33-F004 CLOSES (1H13-P680)  (b) SLC B initiated  
- 1G33-F004 CLOSES (1H13-P680)  (b) SLC B initiated  
- 1G33-F001 (1H13
- 1G33-F001 (1H13
-P680) AND 1G33-F251 (1H13
-P680) AND 1G33-F251 (1H13
-P870-9C) CLOSE  c. CHECK that SLC injection to the reactor by OBSERVING the following:
-P870-9C) CLOSE  c. CHECK that SLC injection to the reactor by OBSERVING the following:
(1) SLC pump discharge pressure exceeds reactor pressure as indicated by SLC PMP A/B DISCH PRESS indicator.
(1) SLC pump discharge pressure exceeds reactor pressure as indicated by SLC PMP A/B DISCH PRESS indicator.
  (2) SLC tank level is lowering as indicated on SLC STOR TK LVL indicator 1H13
(2) SLC tank level is lowering as indicated on SLC STOR TK LVL indicator 1H13
-P601.  (3) Nuclear instrumentation on 1H13
-P601.  (3) Nuclear instrumentation on 1H13
-P680 indicates reactor power level is lowering.   
-P680 indicates reactor power level is lowering.   
Line 3,022: Line 3,022:
ATWS (cont.)
ATWS (cont.)
TIME Position Applicant's Actions or Behavior BOP d. Monitor Reactor Power AND INSERT SRMs AND IRMs prior to reactor power going downscale on APRMs.
TIME Position Applicant's Actions or Behavior BOP d. Monitor Reactor Power AND INSERT SRMs AND IRMs prior to reactor power going downscale on APRMs.
: e. WHEN directed by the EPs to secure SLC injection, TURN the running SLC pump key switch(es) to the STOP position.
: e. WHEN directed by the EPs to secure SLC injection, TURN the running SLC pump key switch(es) to the STOP position.
: f. As soon as possible, RETURN the SLC System to STANDBY in accordance with Section 4.1.
: f. As soon as possible, RETURN the SLC System to STANDBY in accordance with Section 4.1.
Recognizes and reports SLC is NOT injecting due to low discharge pressure
Recognizes and reports SLC is NOT injecting due to low discharge pressure
Line 3,075: Line 3,075:
: c. ENSURE Instrument Air is available.
: c. ENSURE Instrument Air is available.
: d. OPEN RFP A(B) DISCH VLV N21
: d. OPEN RFP A(B) DISCH VLV N21
-F014A(B).
-F014A(B).
: e. DEPRESS the RFPT A(B) TRIP RESET pushbutton.
: e. DEPRESS the RFPT A(B) TRIP RESET pushbutton.
    (1) IF the reactor feed pump turbine W ill NOT reset, PERFORM the following Step Locally:
(1) IF the reactor feed pump turbine W ill NOT reset, PERFORM the following Step Locally:
    (a) WHEN the oil system is operating, GRAB AND HOLD the Local Reset Lever for approximately 1 minute (This fills the circuit).  
(a) WHEN the oil system is operating, GRAB AND HOLD the Local Reset Lever for approximately 1 minute (This fills the circuit).
: f. To place RFP in service, PERFORM one of the following:
: f. To place RFP in service, PERFORM one of the following:
      (1) IF Turbine is OFFLINE, THEN RAISE pump speed USING the RAISE pushbutton until governor position is approx. 60%
(1) IF Turbine is OFFLINE, THEN RAISE pump speed USING the RAISE pushbutton until governor position is approx. 60%
OR as required to obtain discharge pressure approx. 250 psig above reactor pressure.
OR as required to obtain discharge pressure approx. 250 psig above reactor pressure.
(2) IF Turbine is ONLINE, THEN RAISE pump speed USING the RAISE pushbutton as required to obtain discharge pressure approx. 250 psig above reactor pressure.
(2) IF Turbine is ONLINE, THEN RAISE pump speed USING the RAISE pushbutton as required to obtain discharge pressure approx. 250 psig above reactor pressure.
(3) IF desired to establish Feedwater flow without Startup Level Controller in service, THEN CONTROL Feedwater flow with RAISE AND LOWER pushbuttons as required.
(3) IF desired to establish Feedwater flow without Startup Level Controller in service, THEN CONTROL Feedwater flow with RAISE AND LOWER pushbuttons as required.


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 31 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 31 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 3,095: Line 3,095:
Maintain reactor water level using Startup Level Control Valve with a band of
Maintain reactor water level using Startup Level Control Valve with a band of
     -70" to -1 91" wide range Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.
     -70" to -1 91" wide range Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.
(Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 32 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 32 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 3,111: Line 3,111:
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
-66 gpm after charging pressure is normal.  
-66 gpm after charging pressure is normal.
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
-66 gpm.  (Critical TASK in BOLD)
-66 gpm.  (Critical TASK in BOLD)
Line 3,133: Line 3,133:
Reset Scram signal (Division 1 only)
Reset Scram signal (Division 1 only)
Allow Scram Discharge Volume to drain Arm and depress Manual Scram pushbuttons.
Allow Scram Discharge Volume to drain Arm and depress Manual Scram pushbuttons.
(Division 1 only)
(Division 1 only)
Normal Drive Reset Scram signal (Division 1 only)
Normal Drive Reset Scram signal (Division 1 only)
Select control rod Select gang drive mode depress IN TIMER SKIP pushbutton until control rods indicate 00 Following an ATWS, insert control rods by manual scram and/or norma l rod insertion prior to exiting EP
Select control rod Select gang drive mode depress IN TIMER SKIP pushbutton until control rods indicate 00 Following an ATWS, insert control rods by manual scram and/or norma l rod insertion prior to exiting EP
Line 3,174: Line 3,174:


YES/NO    (LOCATION)
YES/NO    (LOCATION)
(ACCEPTANCE (LOCATION)  
(ACCEPTANCE (LOCATION)
(ACCEPTANCE
(ACCEPTANCE


CRITERIA)  
CRITERIA)  
Line 3,187: Line 3,187:
* JACKSON kV SR27-SR-R600 Hz DISPATCHER
* JACKSON kV SR27-SR-R600 Hz DISPATCHER


(H13-P807)               
(H13-P807)               


           $ FRANKLIN   
           $ FRANKLIN   
Line 3,213: Line 3,213:
- Bus 11R to ESF 15AA, 16AB & 17AC                       
- Bus 11R to ESF 15AA, 16AB & 17AC                       


34.5kV Bus A-B =                  (1) $ 552-1105 Closed 11R Volts B-C =                  (1) 1R25-EI-R603  C-A =            
34.5kV Bus A-B =                  (1) $ 552-1105 Closed 11R Volts B-C =                  (1) 1R25-EI-R603  C-A =
    (1) $ 552-1104 Closed (H13-P807-1B)  (31.05-37.95kV)
(1) $ 552-1104 Closed (H13-P807-1B)  (31.05-37.95kV)
Bkr 152-1514
Bkr 152-1514
* Inc Voltage (3952-4576)
* Inc Voltage (3952-4576)
Line 3,222: Line 3,222:
  $ 152-1902 Closed Inc Voltage (3952-4576)
  $ 152-1902 Closed Inc Voltage (3952-4576)
* Note:  For these breakers VERIFY voltage is available to the ESF Bus by placing the Sync switch on 1 H13-P864 OR 1H13-P601 for the designated breaker to ON AND RECORDING incoming voltage.                    RETURN Sync switch to OFF after taking reading.
* Note:  For these breakers VERIFY voltage is available to the ESF Bus by placing the Sync switch on 1 H13-P864 OR 1H13-P601 for the designated breaker to ON AND RECORDING incoming voltage.                    RETURN Sync switch to OFF after taking reading.
  (1) Voltage indication from 1R25
(1) Voltage indication from 1R25
-EI-R603 is NOT required to meet Tech Spec acceptance criteria.
-EI-R603 is NOT required to meet Tech Spec acceptance criteria.
Voltage indication is met by acceptable incoming voltage for breakers  152
Voltage indication is met by acceptable incoming voltage for breakers  152
Line 3,238: Line 3,238:
34.5kV Bus A-B =                  (1) $ 552-2105 Closed                       
34.5kV Bus A-B =                  (1) $ 552-2105 Closed                       


21R Volt B-C =                
21R Volt B-C =
  (1)                                         
(1)                                         


2R25-EI-R603  C-A =              
2R25-EI-R603  C-A =
    (1) $ 552-2104 Closed                       
(1) $ 552-2104 Closed                       


(H13-P807-4B) (31.05-37.95kV)                                         
(H13-P807-4B) (31.05-37.95kV)                                         


Bkr 152-1501
Bkr 152-1501
Line 3,307: Line 3,307:
RWP #                                          3.0 TES T RESULTS  3.1 Test Completion:  (CHECK one in each category.)
RWP #                                          3.0 TES T RESULTS  3.1 Test Completion:  (CHECK one in each category.)
Entire procedure completed                                    [  ]    Partial procedure completed    [  ]
Entire procedure completed                                    [  ]    Partial procedure completed    [  ]
Tech Spec Acceptance Criteria Acceptable            [  ]    Unacceptable                          
Tech Spec Acceptance Criteria Acceptable            [  ]    Unacceptable
[  ]  All other steps/data Acceptable                                [  ]    Unacceptable                          [  ]
[  ]  All other steps/data Acceptable                                [  ]    Unacceptable                          [  ]


Line 3,500: Line 3,500:
Appendix D Scenario Outline Form ES-D-1  NRC 2015 Scenario 2 Page 7 of 7  Revision 0 9/21/2015  Critical Task Number Description Bas i s 1  Open at least 7 SRVs when RPV water level is between  
Appendix D Scenario Outline Form ES-D-1  NRC 2015 Scenario 2 Page 7 of 7  Revision 0 9/21/2015  Critical Task Number Description Bas i s 1  Open at least 7 SRVs when RPV water level is between  
-160" and -190". If an injection source is available but the decreasing RPV water level trend cannot be reversed before RPV water level drops to the Minimum Steam Cooling RPV Water Level (-191 in.), emergency RPV depressurization is required to permit injection from low head systems, maximize flow from available injection sources, and minimize the flow through any primary system break.
-160" and -190". If an injection source is available but the decreasing RPV water level trend cannot be reversed before RPV water level drops to the Minimum Steam Cooling RPV Water Level (-191 in.), emergency RPV depressurization is required to permit injection from low head systems, maximize flow from available injection sources, and minimize the flow through any primary system break.
(per 02-S-01-40, EP Technical Bases) 2  After Emergency Depressurization, restore and maintain RPV level above -191" using available injection systems prior to exiting EP-2. The Minimum Steam Cooling RPV Water Level is the lowest RPV water level at which the covered portion of the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500°F.
(per 02-S-01-40, EP Technical Bases) 2  After Emergency Depressurization, restore and maintain RPV level above -191" using available injection systems prior to exiting EP-2. The Minimum Steam Cooling RPV Water Level is the lowest RPV water level at which the covered portion of the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500°F.
(per 02-S-01-40, EP Technical Bases) 3  When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig. Take manual actions (in accordance with procedure direction, if available) when automatic actions do not occur.
(per 02-S-01-40, EP Technical Bases) 3  When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig. Take manual actions (in accordance with procedure direction, if available) when automatic actions do not occur.
(per EN-OP-120, Operator Fundamentals Program). 300 psig is bases on maximum discharge pressure for RHR LPCI systems B and C injection is 285 psig.
(per EN-OP-120, Operator Fundamentals Program). 300 psig is bases on maximum discharge pressure for RHR LPCI systems B and C injection is 285 psig.
* Critical Task (As defined in NUREG 1021 Appendix D)
* Critical Task (As defined in NUREG 1021 Appendix D)


Line 3,508: Line 3,508:
A. Initialization
A. Initialization
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 4. Set the Simulator to IC-10 2 and perform switch check (Using Quick Reset in Director).
: 4. Set the Simulator to IC-10 2 and perform switch check (Using Quick Reset in Director).
Line 3,562: Line 3,562:
== Description:==
== Description:==
Start RHR 'A' in Suppression Pool Cooling TIME Position Applicant's Actions or Behavior CRS Directs BOP to start RHR 'A' system in Suppression Pool cooling mode.
Start RHR 'A' in Suppression Pool Cooling TIME Position Applicant's Actions or Behavior CRS Directs BOP to start RHR 'A' system in Suppression Pool cooling mode.
BOP Using RHR SOI, 04 01-E12-1, section 5.2.2, performs the following on P601 panel:  (1) START SSW A with flow through RHR A heat exchangers in accordance with SOI 04 01-P41-1, if not already in service.
BOP Using RHR SOI, 04 01-E12-1, section 5.2.2, performs the following on P601 panel:  (1) START SSW A with flow through RHR A heat exchangers in accordance with SOI 04 01-P41-1, if not already in service.
  (2) START RHR RM A FAN COIL UNIT on 1H13
(2) START RHR RM A FAN COIL UNIT on 1H13
-P870.  (3) OPEN OR CHECK OPEN F003A, HX A OUTL VLV. NOTE Opening of F024A causes LPCI A Mode of RHR to be inoperable.
-P870.  (3) OPEN OR CHECK OPEN F003A, HX A OUTL VLV. NOTE Opening of F024A causes LPCI A Mode of RHR to be inoperable.


(4) START RHR A PMP.
(4) START RHR A PMP.


(5) OPEN F024A, RHR A TEST RTN TO SUPP POOL.
(5) OPEN F024A, RHR A TEST RTN TO SUPP POOL.
  (6) THROTTLE F048A, HX A BYP VLV as needed for suppression pool cooling.
(6) THROTTLE F048A, HX A BYP VLV as needed for suppression pool cooling.
IF needed to further reduce suppression pool cooling, THEN THROTTLE F003A, HX A OUTL VLV after F048A is full Open.
IF needed to further reduce suppression pool cooling, THEN THROTTLE F003A, HX A OUTL VLV after F048A is full Open.
  (7) CHECK F064A is still Closed, OR has Closed when RHR PMP A FLO exceeded 1000 gpm.
(7) CHECK F064A is still Closed, OR has Closed when RHR PMP A FLO exceeded 1000 gpm.
CRS Enters Tech Spec 3.5.1 condition A
CRS Enters Tech Spec 3.5.1 condition A


Line 3,601: Line 3,601:
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
-66 gpm after charging pressure is normal.  
-66 gpm after charging pressure is normal.
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
-66 gpm. CRS Enters Control Rod/Drive Malfunctions ONEP, 05-1-02-IV-1  ATC Monitors for Accumulator Faults before standby pump start By monitoring for HCU TROUBLE (P680
-66 gpm. CRS Enters Control Rod/Drive Malfunctions ONEP, 05-1-02-IV-1  ATC Monitors for Accumulator Faults before standby pump start By monitoring for HCU TROUBLE (P680
Line 3,779: Line 3,779:
Manually starts LPCS pump using handswitch on P601 panel Dispatch operators to standby E21
Manually starts LPCS pump using handswitch on P601 panel Dispatch operators to standby E21
-F005, LPCS injection valve, be prepared to open manually upon request.
-F005, LPCS injection valve, be prepared to open manually upon request.
  (Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 19 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 19 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 3,793: Line 3,793:
Division 2 EDG starts with cooling water When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig.
Division 2 EDG starts with cooling water When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig.
CRS Directs Division 2 ECCS to be manually initiated.
CRS Directs Division 2 ECCS to be manually initiated.
(Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 20 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 20 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 3,801: Line 3,801:
== Description:==
== Description:==
False Hotwell low level signal TIME Position Applicant's Actions or Behavior ATC Recognizes all Condensate Pumps trip.
False Hotwell low level signal TIME Position Applicant's Actions or Behavior ATC Recognizes all Condensate Pumps trip.
(This will also cause all condensate booster pumps to trip and Feed pumps to trip)
(This will also cause all condensate booster pumps to trip and Feed pumps to trip)
Determines trip is from a false Low Condenser Level by observing P680-2A-E9, CNDSR HTWL LVL LO.
Determines trip is from a false Low Condenser Level by observing P680-2A-E9, CNDSR HTWL LVL LO.
Uses ARI P680
Uses ARI P680
Line 3,848: Line 3,848:
-F042B handswitch At approximately 300 psig reactor pressure, RHR PMP B DISCH FLO indication, E12
-F042B handswitch At approximately 300 psig reactor pressure, RHR PMP B DISCH FLO indication, E12
-R603B, is indicating injection flow.
-R603B, is indicating injection flow.
(Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 23 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 23 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 3,867: Line 3,867:
Condensate Maintain RPV water level within band  
Condensate Maintain RPV water level within band  
-30" to +50" Wide Range.
-30" to +50" Wide Range.
  (Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 24 of 23  Revision 0 9/21/2015  TERMINATION Once reactor water level is being controlled in band or as directed by Lead Evaluator:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 24 of 23  Revision 0 9/21/2015  TERMINATION Once reactor water level is being controlled in band or as directed by Lead Evaluator:
Line 3,987: Line 3,987:
A. Initialization
A. Initialization
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 4. Set the Simulator to IC-10 3 and perform switch check (Using Quick Reset in Director).
: 4. Set the Simulator to IC-10 3 and perform switch check (Using Quick Reset in Director).
Line 4,050: Line 4,050:
CRS Directs BOP to restore cooling water to Fuel Pool Cooling and Cleanup Heat exchangers.
CRS Directs BOP to restore cooling water to Fuel Pool Cooling and Cleanup Heat exchangers.
BOP Performs the following to restore cooling to the Fuel Pool Cooling and Cleanup Heat Exchangers:
BOP Performs the following to restore cooling to the Fuel Pool Cooling and Cleanup Heat Exchangers:
: a. To place Both heat exchangers in service, PERFORM the following (Initial Condition: CCW Cooling to Both FPHXs is OOSVC):  
: a. To place Both heat exchangers in service, PERFORM the following (Initial Condition: CCW Cooling to Both FPHXs is OOSVC):
(1) OPEN OR VERIFY OPEN F028A AND F032A, FPHX A Inlet AND Outlet valves, USING their respective handswitches CLG WTR INL TO FPHX A [2C] AND CLG WTR OUTL FM FPHX A [2C]. (2) OPEN F105 AND F205 by SIMULTANEOUSLY HOLDI NG Both of their respective handswitches, CCW SPLY TO FPHX A/B [2C] AND CCW RTN FM FP HX A/B [2C], to the OPEN position until alarm Clears (1H13
(1) OPEN OR VERIFY OPEN F028A AND F032A, FPHX A Inlet AND Outlet valves, USING their respective handswitches CLG WTR INL TO FPHX A [2C] AND CLG WTR OUTL FM FPHX A [2C]. (2) OPEN F105 AND F205 by SIMULTANEOUSLY HOLDI NG Both of their respective handswitches, CCW SPLY TO FPHX A/B [2C] AND CCW RTN FM FP HX A/B [2C], to the OPEN position until alarm Clears (1H13
-P870 Section 2A Grid B
-P870 Section 2A Grid B
-1). (3) OPEN F203 USING CCW INBD INL TO FPHX B [2C] handswitch.
-1). (3) OPEN F203 USING CCW INBD INL TO FPHX B [2C] handswitch.
(4) OPEN F028B USING CCW OUTBD INL TO FPHX B [8C] handswitch.
(4) OPEN F028B USING CCW OUTBD INL TO FPHX B [8C] handswitch.
(5) OPEN F032B USING CCW INBD INL FM FPHX B [8C] handswitch.
(5) OPEN F032B USING CCW INBD INL FM FPHX B [8C] handswitch.
(6) OPEN F204 USING CCW OTBD OUTL FM FPHX B [2C] handswitch.
(6) OPEN F204 USING CCW OTBD OUTL FM FPHX B [2C] handswitch.


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 7 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 7 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Line 4,208: Line 4,208:
o Reactor Mode SW in SHUTDOWN.
o Reactor Mode SW in SHUTDOWN.
o All Rods are Inserted. o Reactor power is 0%. o Reactor water level and trend.
o All Rods are Inserted. o Reactor power is 0%. o Reactor water level and trend.
(Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 15 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 15 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Line 4,240: Line 4,240:
: 1. ARM AND DEPRESS RCIC MAN INIT pushbuttons
: 1. ARM AND DEPRESS RCIC MAN INIT pushbuttons
: 2. VERIFY SSW A is running with adequate flow path.
: 2. VERIFY SSW A is running with adequate flow path.
(SSW A in unavailable due to loss of 15AA)
(SSW A in unavailable due to loss of 15AA)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 17 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 17 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Line 4,248: Line 4,248:
== Description:==
== Description:==
Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.)  ATC/BOP Recognizes and reports Drywell pressure rising and reactor water level lowering. When Drywell pressure reaches 1.39 psig, verifies and reports ECCS initiations.
Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.)  ATC/BOP Recognizes and reports Drywell pressure rising and reactor water level lowering. When Drywell pressure reaches 1.39 psig, verifies and reports ECCS initiations.
(Division 2 ECCS is the only division available due to Div 1 and 3 has no power) Recognizes and reports the following:
(Division 2 ECCS is the only division available due to Div 1 and 3 has no power) Recognizes and reports the following:
RHR 'C' pump has tripped RHR 'B' pump is running, however multiple MOVs have no power due to loss of 16BB3.
RHR 'C' pump has tripped RHR 'B' pump is running, however multiple MOVs have no power due to loss of 16BB3.
CRS Re-enters EP-2 and enters EP-3 due to drywell pressure.
CRS Re-enters EP-2 and enters EP-3 due to drywell pressure.
Line 4,330: Line 4,330:
GJPM-OPS-2015-AR3 Radiation Control Emergency Plan  R - M  Station Blackout Electrical Power Determination GJPM-OPS-2015-AR4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
GJPM-OPS-2015-AR3 Radiation Control Emergency Plan  R - M  Station Blackout Electrical Power Determination GJPM-OPS-2015-AR4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:
* Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from


Date of Examination:  12/07/2015 Operating Test Number
Date of Examination:  12/07/2015 Operating Test Number
Line 4,364: Line 4,364:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR1  Revision 0 GJPM-OPS-2015AR1 Page 4 of 7  Loss of Shutdown Cooling, Time to 200°F Determination JPM Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR1  Revision 0 GJPM-OPS-2015AR1 Page 4 of 7  Loss of Shutdown Cooling, Time to 200°F Determination JPM Notes: (Notes to Evaluator)
None. Task Overview:
None. Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task has the student to estimate time to reach 200°F following loss of shutdown cooling. Critical tasks are underlined, italicized, and denoted by an (*)
This task has the student to estimate time to reach 200°F following loss of shutdown cooling. Critical tasks are underlined, italicized, and denoted by an (*)
Step 1:  05-1-02-III-1, Attachment 1
Step 1:  05-1-02-III-1, Attachment 1
* Using given information, determines time to boil is approximately [[estimated NRC review hours::4 hours]]. Standard:  The operator determines using procedure 05 02-III-1 Attachment I, Figure 2 that there are about [[estimated NRC review hours::4 hours]] to 200°F
* Using given information, determines time to boil is approximately 4 hours. Standard:  The operator determines using procedure 05 02-III-1 Attachment I, Figure 2 that there are about 4 hours to 200°F
. Cue:  None. Notes:  SAT / UNSAT
. Cue:  None. Notes:  SAT / UNSAT


Line 4,440: Line 4,440:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR2  Revision 0 GJPM-OPS-2015AR2 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR2  Revision 0 GJPM-OPS-2015AR2 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will perform a Fire Door Alarm Check using the information provided in the initiating ques. The operator will discover tech spec door OC208 is INOP, tech spec door 1A212 is OPERABLE but requires a WR to fix the closing mechanism, and non
The operator will perform a Fire Door Alarm Check using the information provided in the initiating ques. The operator will discover tech spec door OC208 is INOP, tech spec door 1A212 is OPERABLE but requires a WR to fix the closing mechanism, and non
-tech spec door 1A604 also requires a WR to fix the security alarm timing and a rust patch. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
-tech spec door 1A604 also requires a WR to fix the security alarm timing and a rust patch. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Line 4,457: Line 4,457:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR2  Revision 0 GJPM-OPS-2015AR2 Page 5 of 7 Step 2:  06-OP-SP64-M-0043
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR2  Revision 0 GJPM-OPS-2015AR2 Page 5 of 7 Step 2:  06-OP-SP64-M-0043
* Complete the surveillance coversheet section 3.1 by checking boxes for:
* Complete the surveillance coversheet section 3.1 by checking boxes for:
  (1) Partial procedure complete,  (2)* Tech Spec Acceptance Criteria Unacceptable, and  (3)* All other steps/data Unacceptable
(1) Partial procedure complete,  (2)* Tech Spec Acceptance Criteria Unacceptable, and  (3)* All other steps/data Unacceptable
. Standard:  Checks appropriate boxes.
. Standard:  Checks appropriate boxes.
Cue:  Notes:  SAT / UNSAT Step 3:  06
Cue:  Notes:  SAT / UNSAT Step 3:  06
Line 4,531: Line 4,531:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR3  Revision 0 GJPM-OPS-2015AR3 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AR3  Revision 0 GJPM-OPS-2015AR3 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will use the provided electrical prints to prove that removing fuses, C71
The operator will use the provided electrical prints to prove that removing fuses, C71
-F14A and C71-27D, causes a Division 1 half scram
-F14A and C71-27D, causes a Division 1 half scram
Line 4,616: Line 4,616:
:  Station Blackout Table 1 Determination Notes: (Notes to Evaluator)
:  Station Blackout Table 1 Determination Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will use Table 1 of the Loss of AC ONEP to determine the load requirements to run RHR A. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
The operator will use Table 1 of the Loss of AC ONEP to determine the load requirements to run RHR A. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)
Step 1:  05-1-02-I-4 Table 1
Step 1:  05-1-02-I-4 Table 1
Line 4,664: Line 4,664:
ES-301 Administrative Topics Outline Form ES-301-1  Facility:  Grand Gulf Nuclear Station Date of Examination:  12/7/2015  Examination Level:  RO SRO    Operating Test Number:  LOT-201 5 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - D  Determine Firewatch Requirements GJPM-OPS-2015-AS1  Conduct of Operations R - N  Manual On-Line Risk Assessment GJPM-OPS-2015-AS2 Equipment Control R - D  Tagout Removal Approval GJPM-OPS-2015-AS3 Radiation Control R - D  Review Liquid Radwaste Discharge Permit GJPM-OPS-2015-AS4 Emergency Plan  R - N  Emergency Classification GJPM-OPS-2015-AS5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
ES-301 Administrative Topics Outline Form ES-301-1  Facility:  Grand Gulf Nuclear Station Date of Examination:  12/7/2015  Examination Level:  RO SRO    Operating Test Number:  LOT-201 5 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - D  Determine Firewatch Requirements GJPM-OPS-2015-AS1  Conduct of Operations R - N  Manual On-Line Risk Assessment GJPM-OPS-2015-AS2 Equipment Control R - D  Tagout Removal Approval GJPM-OPS-2015-AS3 Radiation Control R - D  Review Liquid Radwaste Discharge Permit GJPM-OPS-2015-AS4 Emergency Plan  R - N  Emergency Classification GJPM-OPS-2015-AS5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:
* Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank  (N)ew or (M)odified from
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank  (N)ew or (M)odified from


Date of Examination:  12/07/2015 Operating Test Number
Date of Examination:  12/07/2015 Operating Test Number
Line 4,705: Line 4,705:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS1  Revision 0 GJPM-OPS-2015CR1 Page 4 of 13 Determine Fire Watch Requirements Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS1  Revision 0 GJPM-OPS-2015CR1 Page 4 of 13 Determine Fire Watch Requirements Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The student will determine the required TRM Fire Watch actions for impairing a required fire water sprinkler system
The student will determine the required TRM Fire Watch actions for impairing a required fire water sprinkler system
. Sequence is not critical.
. Sequence is not critical.
Line 4,731: Line 4,731:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS1  Revision 0 GJPM-OPS-2015CR1 Page 7 of 13  Task Standard(s)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS1  Revision 0 GJPM-OPS-2015CR1 Page 7 of 13  Task Standard(s)
:  Candidate determines fire watch requirement for inoperability of sprinkler system N1P64D142A is to establish a continuous firewatch with backup fire suppression equipment in DG breezeway area 1D301 and an hourly fire watch patrol for Div 1 DG room 1D310 within one hour.
:  Candidate determines fire watch requirement for inoperability of sprinkler system N1P64D142A is to establish a continuous firewatch with backup fire suppression equipment in DG breezeway area 1D301 and an hourly fire watch patrol for Div 1 DG room 1D310 within one hour.
  (It is acceptable for the Candidate to establish a continuous fire watch patrol for Div 1 DG room 1D310 within one hour in lieu of an hourly firewatch patrol
(It is acceptable for the Candidate to establish a continuous fire watch patrol for Div 1 DG room 1D310 within one hour in lieu of an hourly firewatch patrol
.)  SAT / UNSAT Remember to record stop time
.)  SAT / UNSAT Remember to record stop time


Line 4,771: Line 4,771:
20: 4.6; 2.2.17: 3.8 Safety  Function
20: 4.6; 2.2.17: 3.8 Safety  Function
: Equipment Control
: Equipment Control
[10CFR55.4 3b (5)] Performance
[10CFR55.4 3b (5)] Performance
:  Actual  Reference(s)
:  Actual  Reference(s)
: 01-S-18-6, Risk Assessment of Maintenance Activities Handout(s)
: 01-S-18-6, Risk Assessment of Maintenance Activities Handout(s)
Line 4,802: Line 4,802:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS2  Revision 0 GJPM-OPS-2015AS2 Page 4 of 7  Manual Risk Assessment Notes: (Notes to Evaluator)
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS2  Revision 0 GJPM-OPS-2015AS2 Page 4 of 7  Manual Risk Assessment Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The candidate will determine the Plant Safety Index risk color for the given plant conditions using 01
The candidate will determine the Plant Safety Index risk color for the given plant conditions using 01
-S-18-6 Attachment IV.
-S-18-6 Attachment IV.
Line 4,879: Line 4,879:
:  Tagout Approval Notes: (Notes to Evaluator)
:  Tagout Approval Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will determine the proper isolations for the LPCS Jockey Pump.
The operator will determine the proper isolations for the LPCS Jockey Pump.
Critical tasks are underlined, italicized, and denoted by an (*)
Critical tasks are underlined, italicized, and denoted by an (*)
Line 4,976: Line 4,976:
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5-AS4  Revision 1 4/22/13 Page 4 of 7  Review Liquid Radwaste Discharge Permit Notes: (Notes to Evaluator)
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5-AS4  Revision 1 4/22/13 Page 4 of 7  Review Liquid Radwaste Discharge Permit Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by Operations Supervision following a controlled release of liquid radwaste. Three errors have been introduced somewhere within sections 1 through 5 of the Discharge Permit.
This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by Operations Supervision following a controlled release of liquid radwaste. Three errors have been introduced somewhere within sections 1 through 5 of the Discharge Permit.
Critical step s are underlined, italicized, and denoted by an (*)
Critical step s are underlined, italicized, and denoted by an (*)
Line 5,096: Line 5,096:
ELAPSED TIME*                 
ELAPSED TIME*                 


              (minutes)
(minutes)
VALVES OPEN VALVES SHUT       
VALVES OPEN VALVES SHUT       


Line 5,227: Line 5,227:
ELAPSED TIME*                 
ELAPSED TIME*                 


              (minutes)
(minutes)
VALVES OPEN VALVES SHUT       
VALVES OPEN VALVES SHUT       


Line 5,312: Line 5,312:


Ref DATA SHEET I RADWASTE RELEASE INOP RADWASTE MONITOR PRE
Ref DATA SHEET I RADWASTE RELEASE INOP RADWASTE MONITOR PRE
-RELEASE ANALYSIS SAFETY RELATED        INITIALS    $ 5.2  Tank minimum recirculation of  [[estimated NRC review hours::2 hours]] met MW 5.3.1.b(1)
-RELEASE ANALYSIS SAFETY RELATED        INITIALS    $ 5.2  Tank minimum recirculation of  2 hours met MW 5.3.1.b(1)
Sample contains Resin and Chemistry Management Notified MW  5.3.1.b(2)
Sample contains Resin and Chemistry Management Notified MW  5.3.1.b(2)
Sample does not contain Resin N/A    $ 5.4.2  First Sample all significant peaks identified MW    $ 5.5.2  Second Sample all significant peaks identified MW    $ 5.6.1  ODCM dose limits are not exceeded.
Sample does not contain Resin N/A    $ 5.4.2  First Sample all significant peaks identified MW    $ 5.5.2  Second Sample all significant peaks identified MW    $ 5.6.1  ODCM dose limits are not exceeded.
Line 5,385: Line 5,385:
SB-125 1.79e-07 4.44e-08 YES LA-140 6.04e-08 2.56e-08 YES RB-88 7.85e-07 4.28e-07 YES ZN-65 2.14e-07 4.43e-08 YES C0-60 5.71e-07 3.11e-08 YES  TOTAL:  1.81e-06 F il e: 1 Sequen c e: 99999  F ilena m e: 00xxxxxx-01.pdf I nc lude d i n repo r t. EN D O F F I L E A T T A CH MENTS Date of Examination:  12/07/2015 Operating Test Number
SB-125 1.79e-07 4.44e-08 YES LA-140 6.04e-08 2.56e-08 YES RB-88 7.85e-07 4.28e-07 YES ZN-65 2.14e-07 4.43e-08 YES C0-60 5.71e-07 3.11e-08 YES  TOTAL:  1.81e-06 F il e: 1 Sequen c e: 99999  F ilena m e: 00xxxxxx-01.pdf I nc lude d i n repo r t. EN D O F F I L E A T T A CH MENTS Date of Examination:  12/07/2015 Operating Test Number
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS5  Revision 0 GJPM-OPS-2015AS5 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S5 JPM Title:  Emergency Event Classification Facility Number:
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015AS5  Revision 0 GJPM-OPS-2015AS5 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S5 JPM Title:  Emergency Event Classification Facility Number:
_______ N/A  ___                  
_______ N/A  ___
          (If Bank or Modified from Bank)
(If Bank or Modified from Bank)
JPM Attributes:
JPM Attributes:
New Modified Direct from bank Time Critical 15 min  Alternate Path Validation Time:    10 min  Prepared By:
New Modified Direct from bank Time Critical 15 min  Alternate Path Validation Time:    10 min  Prepared By:
Line 5,421: Line 5,421:
Only the initial conditions for the specific scenario performed by the student as CRS is to be given to the student.
Only the initial conditions for the specific scenario performed by the student as CRS is to be given to the student.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
An event classification JPM is required of all licensed SROs not qualified as an Emergency Director in accordance with the Emergency Preparedness Plan.
An event classification JPM is required of all licensed SROs not qualified as an Emergency Director in accordance with the Emergency Preparedness Plan.
Tasks: Critical steps are underlined, italicized, and denoted by an (*)
Tasks: Critical steps are underlined, italicized, and denoted by an (*)
Line 5,471: Line 5,471:
* Type Codes Criteria for RO / SRO
* Type Codes Criteria for RO / SRO
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)  
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
ES-301 Control Room/In
ES-301 Control Room/In
-Plant Systems Outline Form ES-301-2  Facility:  GRAND GULF NUCLEAR STATION Date of Examination:  12/7/2015  Exam Level:  RO SRO-I        SRO-U        Operating Test No.:  LOT 2015  Control Room Systems
-Plant Systems Outline Form ES-301-2  Facility:  GRAND GULF NUCLEAR STATION Date of Examination:  12/7/2015  Exam Level:  RO SRO-I        SRO-U        Operating Test No.:  LOT 2015  Control Room Systems
Line 5,490: Line 5,490:
* Type Codes Criteria for RO / SRO
* Type Codes Criteria for RO / SRO
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)  
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
ES-301 Control Room/In
ES-301 Control Room/In
-Plant Systems Outline Form ES-301-2  Facility:  GRAND GULF NUCLEAR STATION Date of Examination:  12/7/2015  Exam Level:  RO SRO-I        SRO-U        Operating Test No.:  LOT-2015  Control Room Systems
-Plant Systems Outline Form ES-301-2  Facility:  GRAND GULF NUCLEAR STATION Date of Examination:  12/7/2015  Exam Level:  RO SRO-I        SRO-U        Operating Test No.:  LOT-2015  Control Room Systems
Line 5,509: Line 5,509:
* Type Codes Criteria for RO / SRO
* Type Codes Criteria for RO / SRO
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank  (E)mergency or abnormal in
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)  
-plant  (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
(P)revious 2 exams (R)CA  (S)imulator 4-6 / 4-6 / 2-3      /
Date of Examination:  12/07/2015 Operating Test Number
Date of Examination:  12/07/2015 Operating Test Number
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015 S 1  Revision 0 9/14/2015 Page 1 of 12 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 1 JPM Title:  Reset Recirc FCV Runback Facility Number: __GJPM-OPS-B3313____________
:  LOT 2015 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015 S 1  Revision 0 9/14/2015 Page 1 of 12 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 1 JPM Title:  Reset Recirc FCV Runback Facility Number: __GJPM-OPS-B3313____________
                      (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min Prepared By:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min Prepared By:
Line 5,555: Line 5,555:
All controls will be from panel P680 in the Main Control Room.
All controls will be from panel P680 in the Main Control Room.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task resets a Recirc FCV runback following a trip of B RFP. When the operator depresses the RECIRC PMP B CAV INTLK RESET pushbutton, Recirc FCV B will ramp open from a malfunction. The operator must notice and report uncontrolled FCV opening and attempt to stop it. The CRS will direct shutdown of HPU B. The operator will take action to shutdown HPU B, shutdown the B Recirc Pump or shut the B33
This task resets a Recirc FCV runback following a trip of B RFP. When the operator depresses the RECIRC PMP B CAV INTLK RESET pushbutton, Recirc FCV B will ramp open from a malfunction. The operator must notice and report uncontrolled FCV opening and attempt to stop it. The CRS will direct shutdown of HPU B. The operator will take action to shutdown HPU B, shutdown the B Recirc Pump or shut the B33
-F067B from P680 which will terminate the power excursion. In the event the operator elects to perform all steps for FCV B first, all steps associated with FCV A become not applicable, and the JPM may be ended when the HPU for FCV B has been shut down
-F067B from P680 which will terminate the power excursion. In the event the operator elects to perform all steps for FCV B first, all steps associated with FCV A become not applicable, and the JPM may be ended when the HPU for FCV B has been shut down
Line 5,630: Line 5,630:
Date of Examination:  12/7/201 5 Operating Test Number
Date of Examination:  12/7/201 5 Operating Test Number
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5CR 2  Revision 0 9/14/2015 Page 1 of 9 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015CR2 JPM Title:  Defeat Feed Pump Level 9 Trips Facility Number: _GJPM-OPS-EOP006____________
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5CR 2  Revision 0 9/14/2015 Page 1 of 9 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015CR2 JPM Title:  Defeat Feed Pump Level 9 Trips Facility Number: _GJPM-OPS-EOP006____________
                      (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min Applicant: ________________________________
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min Applicant: ________________________________
Line 5,673: Line 5,673:
RFPT reset controls and indications are on P680.
RFPT reset controls and indications are on P680.
Panel P612 is in the Main Control Room Task Overview:
Panel P612 is in the Main Control Room Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task defeats the High Reactor Water Level trip of the Reactor Feed Pumps, which under certain conditions is directed by the EOPs to maintain adequate core cooling.
This task defeats the High Reactor Water Level trip of the Reactor Feed Pumps, which under certain conditions is directed by the EOPs to maintain adequate core cooling.


Line 5,767: Line 5,767:
All controls and indications for this task are on panel 1H13
All controls and indications for this task are on panel 1H13
-P 601. Task Overview:
-P 601. Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is to perform a slow close on MSIV B21
This task is to perform a slow close on MSIV B21
-F028A. Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Student should manually close all remaining MSIVs (7) using handswitches on P601 panel.
-F028A. Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Student should manually close all remaining MSIVs (7) using handswitches on P601 panel.
Line 5,876: Line 5,876:
All controls and indications for this task are on panel 1H13
All controls and indications for this task are on panel 1H13
-P6 01 and P870. Task Overview:
-P6 01 and P870. Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task requires the ability to manually start the only ECCS
This task requires the ability to manually start the only ECCS
-qualified high pressure injection system.
-qualified high pressure injection system.
Line 5,902: Line 5,902:
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5 S 4  Revision 0 9/14/2015 Page 7 of 13 Step 5:  06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 w VERIFY the following has occurred
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-201 5 S 4  Revision 0 9/14/2015 Page 7 of 13 Step 5:  06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 w VERIFY the following has occurred
:  (2) F012, HPCS MIN FLO TO SUPP POOL, OPENS as discharge pressure indicated on PI-R601, HPCS PMP DISCH PRESS, increases above 130 psig.
:  (2) F012, HPCS MIN FLO TO SUPP POOL, OPENS as discharge pressure indicated on PI-R601, HPCS PMP DISCH PRESS, increases above 130 psig.
(3) HPCS Room Cooler Fan has started USING indication above HPCS PMP RM CLR T51-B001 handswitch on Panel 1H13
(3) HPCS Room Cooler Fan has started USING indication above HPCS PMP RM CLR T51-B001 handswitch on Panel 1H13
-P870-5C. (4) SSW LOOP C (HPCS SSW) on Panel 1H13
-P870-5C. (4) SSW LOOP C (HPCS SSW) on Panel 1H13
-P870-5C started automatically.
-P870-5C started automatically.
Line 6,009: Line 6,009:
- Containment Venting Notes: (Notes to Evaluator)
- Containment Venting Notes: (Notes to Evaluator)
: 1. This task is performed from the control room to vent the primary containment via 6
: 1. This task is performed from the control room to vent the primary containment via 6
-inch ventilation lines with no Containment or Secondary Containment Isolation signal present.  
-inch ventilation lines with no Containment or Secondary Containment Isolation signal present.
: 2. EP-1 attachments are maintained in a special file box normally located in or in the close proximity of the Emergency Locker in the Control Room behind the P601 panel.
: 2. EP-1 attachments are maintained in a special file box normally located in or in the close proximity of the Emergency Locker in the Control Room behind the P601 panel.
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
Performance of this task vents the primary containment via 6
Performance of this task vents the primary containment via 6
-inch ventilation lines with no Containment or Secondary Containment Isolation signal present for M41 and E61 valves.
-inch ventilation lines with no Containment or Secondary Containment Isolation signal present for M41 and E61 valves.
Line 6,086: Line 6,086:
Date of Examination:  12/7/201 5 Operating Test Number
Date of Examination:  12/7/201 5 Operating Test Number
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S7  Revision 0 9/14/2015 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 7 JPM Title:  Reactor Manual Scram Switch Test Facility Number: __GJPM-OPS-C7105____________
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S7  Revision 0 9/14/2015 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 7 JPM Title:  Reactor Manual Scram Switch Test Facility Number: __GJPM-OPS-C7105____________
                      (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min
New Modified Direct from bank Time Critical Alternate Path Validation Time:  15 min
Line 6,123: Line 6,123:
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S7  Revision 0 9/14/2015 Page 4 of 11 Reactor Manual Scram Switch Test Notes: (Notes to Evaluator)
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S7  Revision 0 9/14/2015 Page 4 of 11 Reactor Manual Scram Switch Test Notes: (Notes to Evaluator)
Task Overview:
Task Overview:
  (Detailed description of task)
(Detailed description of task)
The operator will perform 06
The operator will perform 06
-OP-1C71-W-0001 (Reactor Manual Scram Switch Test).
-OP-1C71-W-0001 (Reactor Manual Scram Switch Test).
Line 6,236: Line 6,236:
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S8  Revision 0 9/14/2015 Page 4 of 15 Manual Start of SSW A Notes: (Notes to Evaluator)
:  LOT 201 5 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015S8  Revision 0 9/14/2015 Page 4 of 15 Manual Start of SSW A Notes: (Notes to Evaluator)
All controls and indications for this task are on panel P870. Task Overview:
All controls and indications for this task are on panel P870. Task Overview:
  (Detailed description of task)
(Detailed description of task)
This task is a manual startup SSW 'A' and isolate the reported leak by shutting E12-F005A or securing SSW 'A' Pump.
This task is a manual startup SSW 'A' and isolate the reported leak by shutting E12-F005A or securing SSW 'A' Pump.


Line 6,504: Line 6,504:
__ GJPM-OPS-R2108____________
__ GJPM-OPS-R2108____________


          (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  30 min    Prepared By:
New Modified Direct from bank Time Critical Alternate Path Validation Time:  30 min    Prepared By:
Line 6,610: Line 6,610:
:  LOT 20 15 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015PS-7  Revision 0 GJPM-OPS-2015PS-7 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-7  JPM Title:  PERFORM ATTACHMENT III OF SHUTDOWN FROM REMOTE SHUTDOWN PANEL ONEP Facility Number:
:  LOT 20 15 Facility:  Grand Gulf Nuclear Station JPM Number:  GJPM-OPS-2015PS-7  Revision 0 GJPM-OPS-2015PS-7 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-7  JPM Title:  PERFORM ATTACHMENT III OF SHUTDOWN FROM REMOTE SHUTDOWN PANEL ONEP Facility Number:
__ N/A____________
__ N/A____________
                                                                                  (If Bank or Modified from Bank
(If Bank or Modified from Bank
) JPM Attributes:
) JPM Attributes:
New Modified Direct from bank Time Critical Alternate Path Validation Time
New Modified Direct from bank Time Critical Alternate Path Validation Time
Line 6,920: Line 6,920:
A. Initialization
A. Initialization
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 4. Set the Simulator to IC-101 and perform switch check (Using Quick Reset in Director).
: 4. Set the Simulator to IC-101 and perform switch check (Using Quick Reset in Director).
Line 6,952: Line 6,952:
Power  9 5%    M OC  EOOS  GREEN Planned Evolutions this shift:
Power  9 5%    M OC  EOOS  GREEN Planned Evolutions this shift:
SSW A is operating per 04  03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.
SSW A is operating per 04  03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.
Rotate power on electrical bus 17AC from transformer ESF 12 to ESF  
Rotate power on electrical bus 17AC from transformer ESF 12 to ESF
: 21. C. Allow the crew to perform pre
: 21. C. Allow the crew to perform pre
-shift brief and review procedures for planned evolutions.
-shift brief and review procedures for planned evolutions.
Line 6,972: Line 6,972:
. BOP Using ESF BUS 17AC SOI , 04-1-01-R21-1 7 , section 4.3.2, performs the following:
. BOP Using ESF BUS 17AC SOI , 04-1-01-R21-1 7 , section 4.3.2, performs the following:
: a. ENSURE XFMR ESF 21 energized up to Bus Feeder Breaker 152-1705 as follows:
: a. ENSURE XFMR ESF 21 energized up to Bus Feeder Breaker 152-1705 as follows:
  (1) CHECK CLOSED J5206 FDR to XFMR ST
(1) CHECK CLOSED J5206 FDR to XFMR ST
-21  (2) CHECK CLOSED 552-2105 Bus 21R FDR FRM XFMR ST-21  (3) CHECK indicator 2R25
-21  (2) CHECK CLOSED 552-2105 Bus 21R FDR FRM XFMR ST-21  (3) CHECK indicator 2R25
-R603 34.5 kV voltage  (4) CHECK CLOSED 552-2104 Bus 21R FDR to XFMR ESF 21 (5) CHECK CLOSED 152-2902 FDR FRM XFMR ESF 21
-R603 34.5 kV voltage  (4) CHECK CLOSED 552-2104 Bus 21R FDR to XFMR ESF 21 (5) CHECK CLOSED 152-2902 FDR FRM XFMR ESF 21
Line 6,978: Line 6,978:
(6) CHECK ENERGIZED status light is On.
(6) CHECK ENERGIZED status light is On.
: b. TURN ON the Sync switch for Breaker 152
: b. TURN ON the Sync switch for Breaker 152
-1705 BUS 17AC FDR FRM XFMR ESF 21.
-1705 BUS 17AC FDR FRM XFMR ESF 21.
: c. CHECK that the sync scope comes up to 12 o'clock  
: c. CHECK that the sync scope comes up to 12 o'clock  
+ 10°.
+ 10°.
: d. ATTEMPT to CLOSE 152-1705 Bus 17AC feeder from ESF 21.
: d. ATTEMPT to CLOSE 152-1705 Bus 17AC feeder from ESF 21.


Line 7,033: Line 7,033:
TIME Position Applicant's Actions or Behavior BOP Performs surveillance 06
TIME Position Applicant's Actions or Behavior BOP Performs surveillance 06
-OP-1R21-W-0001 Attachment II.
-OP-1R21-W-0001 Attachment II.
  (See attachment 1)
(See attachment 1)
CRS Performs surveillance 06-OP-1R21-W-0001 Attachment III Page 6 of 6 only.  
CRS Performs surveillance 06-OP-1R21-W-0001 Attachment III Page 6 of 6 only.
(See attachment 1)
(See attachment 1)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 10 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 10 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 7,061: Line 7,061:
BOP Ensures all MSIV solenoid lights are energized and all MSIV pilot solenoids indicate amperage on panels 1H13
BOP Ensures all MSIV solenoid lights are energized and all MSIV pilot solenoids indicate amperage on panels 1H13
-P622 and P623.
-P622 and P623.
(Candidate will have to go behind the P807 panel and ask the Booth operator the status of indication due to P622 and P623 are not simulated in the Simulator.
(Candidate will have to go behind the P807 panel and ask the Booth operator the status of indication due to P622 and P623 are not simulated in the Simulator.


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 11 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 11 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 7,179: Line 7,179:
TIME Position Applicant's Actions or Behavior BOP Performs the following on P601 Panel
TIME Position Applicant's Actions or Behavior BOP Performs the following on P601 Panel
:  Inhibit ADS o Places ADS INHIBIT switches to the INHIBIT position Override HPCS injection by performing the following:
:  Inhibit ADS o Places ADS INHIBIT switches to the INHIBIT position Override HPCS injection by performing the following:
  (1) While HOLDING HPCS SYS INJECTION VLV (E22
(1) While HOLDING HPCS SYS INJECTION VLV (E22
-F004) handswitch in "CLOSE" position, ARM AND DEPRESS the manual system initiation push
-F004) handswitch in "CLOSE" position, ARM AND DEPRESS the manual system initiation push
-button for HPCS.  (2) AFTER indication of pump start, THEN TRIP the HPCS pum p.  (3) ENSURE the HPCS pump AND E22-F004 valve override alarms are sealed in.
-button for HPCS.  (2) AFTER indication of pump start, THEN TRIP the HPCS pum p.  (3) ENSURE the HPCS pump AND E22-F004 valve override alarms are sealed in.
Line 7,231: Line 7,231:
IF time does NOT permit closing of valves, THEN TRIP reactor feed pump(s) AND/OR condensate/condensate booster pump(s) to prevent injection.
IF time does NOT permit closing of valves, THEN TRIP reactor feed pump(s) AND/OR condensate/condensate booster pump(s) to prevent injection.
IF time permits closing of valves:
IF time permits closing of valves:
  (1) IF S/U level control in service, THEN CLOSE the S/U level control valve AND/OR N21-F040 IF necessary.
(1) IF S/U level control in service, THEN CLOSE the S/U level control valve AND/OR N21-F040 IF necessary.
  (2) IF S/U level control is NOT in service, THEN ALIGN Feedwater for S/U level control with S/U level control valve closed.
(2) IF S/U level control is NOT in service, THEN ALIGN Feedwater for S/U level control with S/U level control valve closed.
Per step L
Per step L
-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches  
-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches  
Line 7,246: Line 7,246:
ATWS (cont.)
ATWS (cont.)
TIME Position Applicant's Actions or Behavior BOP Terminates Low pressure ECCS systems by performing the following per 02
TIME Position Applicant's Actions or Behavior BOP Terminates Low pressure ECCS systems by performing the following per 02
-S-01-43, Transient Mitigation Strategy.  
-S-01-43, Transient Mitigation Strategy.
(1) ARM AND DEPRESS the manual system initiation push
(1) ARM AND DEPRESS the manual system initiation push
-button for selected division.
-button for selected division.
(2) AFTER indication of pump(s) start, THEN TRIP the pump(s).
(2) AFTER indication of pump(s) start, THEN TRIP the pump(s).
(3) CLOSE the associated injection valve(s).
(3) CLOSE the associated injection valve(s).
(4) ENSURE the associated pump(s) and valve(s) override alarms are sealed in.
(4) ENSURE the associated pump(s) and valve(s) override alarms are sealed in.
(5) REPEAT these steps for the other division.
(5) REPEAT these steps for the other division.
For Division 1 ECCS:
For Division 1 ECCS:
Low Pressure Core Spray system RHR 'A' LPCI system For Division 2 ECCS RHR 'B' LPCI system RHR 'C' LPCI system Per step L
Low Pressure Core Spray system RHR 'A' LPCI system For Division 2 ECCS RHR 'B' LPCI system RHR 'C' LPCI system Per step L
Line 7,289: Line 7,289:
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
-66 gpm after charging pressure is normal.  
-66 gpm after charging pressure is normal.
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
-66 gpm. Per 04-1-01-C11-1, Control Rod Drive SOI, Attachment VIII:
-66 gpm. Per 04-1-01-C11-1, Control Rod Drive SOI, Attachment VIII:
Line 7,308: Line 7,308:
TIME Position Applicant's Actions or Behavior CRS Directs for injection of Standby Liquid Control per Hard Card BOP Initiates Standby Liquid Control by performing the following per 04 01-C41-1 Section 5.3:
TIME Position Applicant's Actions or Behavior CRS Directs for injection of Standby Liquid Control per Hard Card BOP Initiates Standby Liquid Control by performing the following per 04 01-C41-1 Section 5.3:
: a. OBTAIN SLC Initiation keys from the Shift Manager's key cabinet, INSERT keys into SLC PMP A AND B key switches on 1H13
: a. OBTAIN SLC Initiation keys from the Shift Manager's key cabinet, INSERT keys into SLC PMP A AND B key switches on 1H13
-P601 AND TURN each momentarily to the START position (spring return to normal).
-P601 AND TURN each momentarily to the START position (spring return to normal).
: b. CHECK that system initiation has occurred by OBSERVING the following:
: b. CHECK that system initiation has occurred by OBSERVING the following:
(1) F001A AND F001B STORAGE TANK OUTLET valves OPEN as indicated on 1H13
(1) F001A AND F001B STORAGE TANK OUTLET valves OPEN as indicated on 1H13
-P601.  (2) Squib Valves F004A AND F004B fire as indicated by the following on 1H13
-P601.  (2) Squib Valves F004A AND F004B fire as indicated by the following on 1H13
-P601:  (a) White SQUIB VALVE READY light is Off.
-P601:  (a) White SQUIB VALVE READY light is Off.
(b) Annunciator "SLC SYS A AND B OOSVC" Alarms.
(b) Annunciator "SLC SYS A AND B OOSVC" Alarms.
(c) Amber status light SQUIB A AND B LOSCONT OR PWR LOSS is On.
(c) Amber status light SQUIB A AND B LOSCONT OR PWR LOSS is On.
(3) SLC Pumps A AND B start WHEN the associated storage tank outlet valves open as indicated by red pump running lights on 1H13
(3) SLC Pumps A AND B start WHEN the associated storage tank outlet valves open as indicated by red pump running lights on 1H13
-P601.  (4) The following RWCU valve(s) CLOSE:  (a) SLC A initiated  
-P601.  (4) The following RWCU valve(s) CLOSE:  (a) SLC A initiated  
- 1G33-F004 CLOSES (1H13-P680)  (b) SLC B initiated  
- 1G33-F004 CLOSES (1H13-P680)  (b) SLC B initiated  
- 1G33-F001 (1H13
- 1G33-F001 (1H13
-P680) AND 1G33-F251 (1H13
-P680) AND 1G33-F251 (1H13
-P870-9C) CLOSE  c. CHECK that SLC injection to the reactor by OBSERVING the following:
-P870-9C) CLOSE  c. CHECK that SLC injection to the reactor by OBSERVING the following:
(1) SLC pump discharge pressure exceeds reactor pressure as indicated by SLC PMP A/B DISCH PRESS indicator.
(1) SLC pump discharge pressure exceeds reactor pressure as indicated by SLC PMP A/B DISCH PRESS indicator.
  (2) SLC tank level is lowering as indicated on SLC STOR TK LVL indicator 1H13
(2) SLC tank level is lowering as indicated on SLC STOR TK LVL indicator 1H13
-P601.  (3) Nuclear instrumentation on 1H13
-P601.  (3) Nuclear instrumentation on 1H13
-P680 indicates reactor power level is lowering.   
-P680 indicates reactor power level is lowering.   
Line 7,333: Line 7,333:
ATWS (cont.)
ATWS (cont.)
TIME Position Applicant's Actions or Behavior BOP d. Monitor Reactor Power AND INSERT SRMs AND IRMs prior to reactor power going downscale on APRMs.
TIME Position Applicant's Actions or Behavior BOP d. Monitor Reactor Power AND INSERT SRMs AND IRMs prior to reactor power going downscale on APRMs.
: e. WHEN directed by the EPs to secure SLC injection, TURN the running SLC pump key switch(es) to the STOP position.
: e. WHEN directed by the EPs to secure SLC injection, TURN the running SLC pump key switch(es) to the STOP position.
: f. As soon as possible, RETURN the SLC System to STANDBY in accordance with Section 4.1.
: f. As soon as possible, RETURN the SLC System to STANDBY in accordance with Section 4.1.
Recognizes and reports SLC is NOT injecting due to low discharge pressure
Recognizes and reports SLC is NOT injecting due to low discharge pressure
Line 7,386: Line 7,386:
: c. ENSURE Instrument Air is available.
: c. ENSURE Instrument Air is available.
: d. OPEN RFP A(B) DISCH VLV N21
: d. OPEN RFP A(B) DISCH VLV N21
-F014A(B).
-F014A(B).
: e. DEPRESS the RFPT A(B) TRIP RESET pushbutton.
: e. DEPRESS the RFPT A(B) TRIP RESET pushbutton.
    (1) IF the reactor feed pump turbine W ill NOT reset, PERFORM the following Step Locally:
(1) IF the reactor feed pump turbine W ill NOT reset, PERFORM the following Step Locally:
    (a) WHEN the oil system is operating, GRAB AND HOLD the Local Reset Lever for approximately 1 minute (This fills the circuit).  
(a) WHEN the oil system is operating, GRAB AND HOLD the Local Reset Lever for approximately 1 minute (This fills the circuit).
: f. To place RFP in service, PERFORM one of the following:
: f. To place RFP in service, PERFORM one of the following:
      (1) IF Turbine is OFFLINE, THEN RAISE pump speed USING the RAISE pushbutton until governor position is approx. 60%
(1) IF Turbine is OFFLINE, THEN RAISE pump speed USING the RAISE pushbutton until governor position is approx. 60%
OR as required to obtain discharge pressure approx. 250 psig above reactor pressure.
OR as required to obtain discharge pressure approx. 250 psig above reactor pressure.
(2) IF Turbine is ONLINE, THEN RAISE pump speed USING the RAISE pushbutton as required to obtain discharge pressure approx. 250 psig above reactor pressure.
(2) IF Turbine is ONLINE, THEN RAISE pump speed USING the RAISE pushbutton as required to obtain discharge pressure approx. 250 psig above reactor pressure.
(3) IF desired to establish Feedwater flow without Startup Level Controller in service, THEN CONTROL Feedwater flow with RAISE AND LOWER pushbuttons as required.
(3) IF desired to establish Feedwater flow without Startup Level Controller in service, THEN CONTROL Feedwater flow with RAISE AND LOWER pushbuttons as required.


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 31 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 31 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 7,406: Line 7,406:
Maintain reactor water level using Startup Level Control Valve with a band of
Maintain reactor water level using Startup Level Control Valve with a band of
     -70" to -1 91" wide range Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.
     -70" to -1 91" wide range Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.
(Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 32 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 1 Page 32 of 35  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 7,422: Line 7,422:
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
-66 gpm after charging pressure is normal.  
-66 gpm after charging pressure is normal.
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
-66 gpm.  (Critical TASK in BOLD)
-66 gpm.  (Critical TASK in BOLD)
Line 7,444: Line 7,444:
Reset Scram signal (Division 1 only)
Reset Scram signal (Division 1 only)
Allow Scram Discharge Volume to drain Arm and depress Manual Scram pushbuttons.
Allow Scram Discharge Volume to drain Arm and depress Manual Scram pushbuttons.
(Division 1 only)
(Division 1 only)
Normal Drive Reset Scram signal (Division 1 only)
Normal Drive Reset Scram signal (Division 1 only)
Select control rod Select gang drive mode depress IN TIMER SKIP pushbutton until control rods indicate 00 Following an ATWS, insert control rods by manual scram and/or norma l rod insertion prior to exiting EP
Select control rod Select gang drive mode depress IN TIMER SKIP pushbutton until control rods indicate 00 Following an ATWS, insert control rods by manual scram and/or norma l rod insertion prior to exiting EP
Line 7,485: Line 7,485:


YES/NO    (LOCATION)
YES/NO    (LOCATION)
(ACCEPTANCE (LOCATION)  
(ACCEPTANCE (LOCATION)
(ACCEPTANCE
(ACCEPTANCE


CRITERIA)  
CRITERIA)  
Line 7,498: Line 7,498:
* JACKSON kV SR27-SR-R600 Hz DISPATCHER
* JACKSON kV SR27-SR-R600 Hz DISPATCHER


(H13-P807)               
(H13-P807)               


           $ FRANKLIN   
           $ FRANKLIN   
Line 7,524: Line 7,524:
- Bus 11R to ESF 15AA, 16AB & 17AC                       
- Bus 11R to ESF 15AA, 16AB & 17AC                       


34.5kV Bus A-B =                  (1) $ 552-1105 Closed 11R Volts B-C =                  (1) 1R25-EI-R603  C-A =            
34.5kV Bus A-B =                  (1) $ 552-1105 Closed 11R Volts B-C =                  (1) 1R25-EI-R603  C-A =
    (1) $ 552-1104 Closed (H13-P807-1B)  (31.05-37.95kV)
(1) $ 552-1104 Closed (H13-P807-1B)  (31.05-37.95kV)
Bkr 152-1514
Bkr 152-1514
* Inc Voltage (3952-4576)
* Inc Voltage (3952-4576)
Line 7,533: Line 7,533:
  $ 152-1902 Closed Inc Voltage (3952-4576)
  $ 152-1902 Closed Inc Voltage (3952-4576)
* Note:  For these breakers VERIFY voltage is available to the ESF Bus by placing the Sync switch on 1 H13-P864 OR 1H13-P601 for the designated breaker to ON AND RECORDING incoming voltage.                    RETURN Sync switch to OFF after taking reading.
* Note:  For these breakers VERIFY voltage is available to the ESF Bus by placing the Sync switch on 1 H13-P864 OR 1H13-P601 for the designated breaker to ON AND RECORDING incoming voltage.                    RETURN Sync switch to OFF after taking reading.
  (1) Voltage indication from 1R25
(1) Voltage indication from 1R25
-EI-R603 is NOT required to meet Tech Spec acceptance criteria.
-EI-R603 is NOT required to meet Tech Spec acceptance criteria.
Voltage indication is met by acceptable incoming voltage for breakers  152
Voltage indication is met by acceptable incoming voltage for breakers  152
Line 7,549: Line 7,549:
34.5kV Bus A-B =                  (1) $ 552-2105 Closed                       
34.5kV Bus A-B =                  (1) $ 552-2105 Closed                       


21R Volt B-C =                
21R Volt B-C =
  (1)                                         
(1)                                         


2R25-EI-R603  C-A =              
2R25-EI-R603  C-A =
    (1) $ 552-2104 Closed                       
(1) $ 552-2104 Closed                       


(H13-P807-4B) (31.05-37.95kV)                                         
(H13-P807-4B) (31.05-37.95kV)                                         


Bkr 152-1501
Bkr 152-1501
Line 7,618: Line 7,618:
RWP #                                          3.0 TES T RESULTS  3.1 Test Completion:  (CHECK one in each category.)
RWP #                                          3.0 TES T RESULTS  3.1 Test Completion:  (CHECK one in each category.)
Entire procedure completed                                    [  ]    Partial procedure completed    [  ]
Entire procedure completed                                    [  ]    Partial procedure completed    [  ]
Tech Spec Acceptance Criteria Acceptable            [  ]    Unacceptable                          
Tech Spec Acceptance Criteria Acceptable            [  ]    Unacceptable
[  ]  All other steps/data Acceptable                                [  ]    Unacceptable                          [  ]
[  ]  All other steps/data Acceptable                                [  ]    Unacceptable                          [  ]


Line 7,811: Line 7,811:
Appendix D Scenario Outline Form ES-D-1  NRC 2015 Scenario 2 Page 7 of 7  Revision 0 9/21/2015  Critical Task Number Description Bas i s 1  Open at least 7 SRVs when RPV water level is between  
Appendix D Scenario Outline Form ES-D-1  NRC 2015 Scenario 2 Page 7 of 7  Revision 0 9/21/2015  Critical Task Number Description Bas i s 1  Open at least 7 SRVs when RPV water level is between  
-160" and -190". If an injection source is available but the decreasing RPV water level trend cannot be reversed before RPV water level drops to the Minimum Steam Cooling RPV Water Level (-191 in.), emergency RPV depressurization is required to permit injection from low head systems, maximize flow from available injection sources, and minimize the flow through any primary system break.
-160" and -190". If an injection source is available but the decreasing RPV water level trend cannot be reversed before RPV water level drops to the Minimum Steam Cooling RPV Water Level (-191 in.), emergency RPV depressurization is required to permit injection from low head systems, maximize flow from available injection sources, and minimize the flow through any primary system break.
(per 02-S-01-40, EP Technical Bases) 2  After Emergency Depressurization, restore and maintain RPV level above -191" using available injection systems prior to exiting EP-2. The Minimum Steam Cooling RPV Water Level is the lowest RPV water level at which the covered portion of the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500°F.
(per 02-S-01-40, EP Technical Bases) 2  After Emergency Depressurization, restore and maintain RPV level above -191" using available injection systems prior to exiting EP-2. The Minimum Steam Cooling RPV Water Level is the lowest RPV water level at which the covered portion of the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500°F.
(per 02-S-01-40, EP Technical Bases) 3  When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig. Take manual actions (in accordance with procedure direction, if available) when automatic actions do not occur.
(per 02-S-01-40, EP Technical Bases) 3  When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig. Take manual actions (in accordance with procedure direction, if available) when automatic actions do not occur.
(per EN-OP-120, Operator Fundamentals Program). 300 psig is bases on maximum discharge pressure for RHR LPCI systems B and C injection is 285 psig.
(per EN-OP-120, Operator Fundamentals Program). 300 psig is bases on maximum discharge pressure for RHR LPCI systems B and C injection is 285 psig.
* Critical Task (As defined in NUREG 1021 Appendix D)
* Critical Task (As defined in NUREG 1021 Appendix D)


Line 7,819: Line 7,819:
A. Initialization
A. Initialization
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 4. Set the Simulator to IC-10 2 and perform switch check (Using Quick Reset in Director).
: 4. Set the Simulator to IC-10 2 and perform switch check (Using Quick Reset in Director).
Line 7,873: Line 7,873:
== Description:==
== Description:==
Start RHR 'A' in Suppression Pool Cooling TIME Position Applicant's Actions or Behavior CRS Directs BOP to start RHR 'A' system in Suppression Pool cooling mode.
Start RHR 'A' in Suppression Pool Cooling TIME Position Applicant's Actions or Behavior CRS Directs BOP to start RHR 'A' system in Suppression Pool cooling mode.
BOP Using RHR SOI, 04 01-E12-1, section 5.2.2, performs the following on P601 panel:  (1) START SSW A with flow through RHR A heat exchangers in accordance with SOI 04 01-P41-1, if not already in service.
BOP Using RHR SOI, 04 01-E12-1, section 5.2.2, performs the following on P601 panel:  (1) START SSW A with flow through RHR A heat exchangers in accordance with SOI 04 01-P41-1, if not already in service.
  (2) START RHR RM A FAN COIL UNIT on 1H13
(2) START RHR RM A FAN COIL UNIT on 1H13
-P870.  (3) OPEN OR CHECK OPEN F003A, HX A OUTL VLV. NOTE Opening of F024A causes LPCI A Mode of RHR to be inoperable.
-P870.  (3) OPEN OR CHECK OPEN F003A, HX A OUTL VLV. NOTE Opening of F024A causes LPCI A Mode of RHR to be inoperable.


(4) START RHR A PMP.
(4) START RHR A PMP.


(5) OPEN F024A, RHR A TEST RTN TO SUPP POOL.
(5) OPEN F024A, RHR A TEST RTN TO SUPP POOL.
  (6) THROTTLE F048A, HX A BYP VLV as needed for suppression pool cooling.
(6) THROTTLE F048A, HX A BYP VLV as needed for suppression pool cooling.
IF needed to further reduce suppression pool cooling, THEN THROTTLE F003A, HX A OUTL VLV after F048A is full Open.
IF needed to further reduce suppression pool cooling, THEN THROTTLE F003A, HX A OUTL VLV after F048A is full Open.
  (7) CHECK F064A is still Closed, OR has Closed when RHR PMP A FLO exceeded 1000 gpm.
(7) CHECK F064A is still Closed, OR has Closed when RHR PMP A FLO exceeded 1000 gpm.
CRS Enters Tech Spec 3.5.1 condition A
CRS Enters Tech Spec 3.5.1 condition A


Line 7,912: Line 7,912:
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
: d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54
-66 gpm after charging pressure is normal.  
-66 gpm after charging pressure is normal.
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
: e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54
-66 gpm. CRS Enters Control Rod/Drive Malfunctions ONEP, 05-1-02-IV-1  ATC Monitors for Accumulator Faults before standby pump start By monitoring for HCU TROUBLE (P680
-66 gpm. CRS Enters Control Rod/Drive Malfunctions ONEP, 05-1-02-IV-1  ATC Monitors for Accumulator Faults before standby pump start By monitoring for HCU TROUBLE (P680
Line 8,090: Line 8,090:
Manually starts LPCS pump using handswitch on P601 panel Dispatch operators to standby E21
Manually starts LPCS pump using handswitch on P601 panel Dispatch operators to standby E21
-F005, LPCS injection valve, be prepared to open manually upon request.
-F005, LPCS injection valve, be prepared to open manually upon request.
  (Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 19 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 19 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 8,104: Line 8,104:
Division 2 EDG starts with cooling water When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig.
Division 2 EDG starts with cooling water When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig.
CRS Directs Division 2 ECCS to be manually initiated.
CRS Directs Division 2 ECCS to be manually initiated.
(Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 20 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 20 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 8,112: Line 8,112:
== Description:==
== Description:==
False Hotwell low level signal TIME Position Applicant's Actions or Behavior ATC Recognizes all Condensate Pumps trip.
False Hotwell low level signal TIME Position Applicant's Actions or Behavior ATC Recognizes all Condensate Pumps trip.
(This will also cause all condensate booster pumps to trip and Feed pumps to trip)
(This will also cause all condensate booster pumps to trip and Feed pumps to trip)
Determines trip is from a false Low Condenser Level by observing P680-2A-E9, CNDSR HTWL LVL LO.
Determines trip is from a false Low Condenser Level by observing P680-2A-E9, CNDSR HTWL LVL LO.
Uses ARI P680
Uses ARI P680
Line 8,159: Line 8,159:
-F042B handswitch At approximately 300 psig reactor pressure, RHR PMP B DISCH FLO indication, E12
-F042B handswitch At approximately 300 psig reactor pressure, RHR PMP B DISCH FLO indication, E12
-R603B, is indicating injection flow.
-R603B, is indicating injection flow.
(Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 23 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 23 of 23  Revision 0 9/21/2015 Op-Test No:  NRC LOT 2015 Scenario No:
Line 8,178: Line 8,178:
Condensate Maintain RPV water level within band  
Condensate Maintain RPV water level within band  
-30" to +50" Wide Range.
-30" to +50" Wide Range.
  (Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 24 of 23  Revision 0 9/21/2015  TERMINATION Once reactor water level is being controlled in band or as directed by Lead Evaluator:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 2 Page 24 of 23  Revision 0 9/21/2015  TERMINATION Once reactor water level is being controlled in band or as directed by Lead Evaluator:
Line 8,298: Line 8,298:
A. Initialization
A. Initialization
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
: 4. Set the Simulator to IC-10 3 and perform switch check (Using Quick Reset in Director).
: 4. Set the Simulator to IC-10 3 and perform switch check (Using Quick Reset in Director).
Line 8,361: Line 8,361:
CRS Directs BOP to restore cooling water to Fuel Pool Cooling and Cleanup Heat exchangers.
CRS Directs BOP to restore cooling water to Fuel Pool Cooling and Cleanup Heat exchangers.
BOP Performs the following to restore cooling to the Fuel Pool Cooling and Cleanup Heat Exchangers:
BOP Performs the following to restore cooling to the Fuel Pool Cooling and Cleanup Heat Exchangers:
: a. To place Both heat exchangers in service, PERFORM the following (Initial Condition: CCW Cooling to Both FPHXs is OOSVC):  
: a. To place Both heat exchangers in service, PERFORM the following (Initial Condition: CCW Cooling to Both FPHXs is OOSVC):
(1) OPEN OR VERIFY OPEN F028A AND F032A, FPHX A Inlet AND Outlet valves, USING their respective handswitches CLG WTR INL TO FPHX A [2C] AND CLG WTR OUTL FM FPHX A [2C]. (2) OPEN F105 AND F205 by SIMULTANEOUSLY HOLDI NG Both of their respective handswitches, CCW SPLY TO FPHX A/B [2C] AND CCW RTN FM FP HX A/B [2C], to the OPEN position until alarm Clears (1H13
(1) OPEN OR VERIFY OPEN F028A AND F032A, FPHX A Inlet AND Outlet valves, USING their respective handswitches CLG WTR INL TO FPHX A [2C] AND CLG WTR OUTL FM FPHX A [2C]. (2) OPEN F105 AND F205 by SIMULTANEOUSLY HOLDI NG Both of their respective handswitches, CCW SPLY TO FPHX A/B [2C] AND CCW RTN FM FP HX A/B [2C], to the OPEN position until alarm Clears (1H13
-P870 Section 2A Grid B
-P870 Section 2A Grid B
-1). (3) OPEN F203 USING CCW INBD INL TO FPHX B [2C] handswitch.
-1). (3) OPEN F203 USING CCW INBD INL TO FPHX B [2C] handswitch.
(4) OPEN F028B USING CCW OUTBD INL TO FPHX B [8C] handswitch.
(4) OPEN F028B USING CCW OUTBD INL TO FPHX B [8C] handswitch.
(5) OPEN F032B USING CCW INBD INL FM FPHX B [8C] handswitch.
(5) OPEN F032B USING CCW INBD INL FM FPHX B [8C] handswitch.
(6) OPEN F204 USING CCW OTBD OUTL FM FPHX B [2C] handswitch.
(6) OPEN F204 USING CCW OTBD OUTL FM FPHX B [2C] handswitch.


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 7 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 7 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Line 8,519: Line 8,519:
o Reactor Mode SW in SHUTDOWN.
o Reactor Mode SW in SHUTDOWN.
o All Rods are Inserted. o Reactor power is 0%. o Reactor water level and trend.
o All Rods are Inserted. o Reactor power is 0%. o Reactor water level and trend.
(Critical TASK in BOLD)
(Critical TASK in BOLD)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 15 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 15 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Line 8,551: Line 8,551:
: 1. ARM AND DEPRESS RCIC MAN INIT pushbuttons
: 1. ARM AND DEPRESS RCIC MAN INIT pushbuttons
: 2. VERIFY SSW A is running with adequate flow path.
: 2. VERIFY SSW A is running with adequate flow path.
(SSW A in unavailable due to loss of 15AA)
(SSW A in unavailable due to loss of 15AA)


Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 17 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Appendix D Required Operator Actions Form ES-D-2  NRC 2015 Scenario 3 Page 17 of 20  Revision 0 9/22/2015  Op-Test No:  NRC LOT 2015 Scenario No:
Line 8,559: Line 8,559:
== Description:==
== Description:==
Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.)  ATC/BOP Recognizes and reports Drywell pressure rising and reactor water level lowering. When Drywell pressure reaches 1.39 psig, verifies and reports ECCS initiations.
Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.)  ATC/BOP Recognizes and reports Drywell pressure rising and reactor water level lowering. When Drywell pressure reaches 1.39 psig, verifies and reports ECCS initiations.
(Division 2 ECCS is the only division available due to Div 1 and 3 has no power) Recognizes and reports the following:
(Division 2 ECCS is the only division available due to Div 1 and 3 has no power) Recognizes and reports the following:
RHR 'C' pump has tripped RHR 'B' pump is running, however multiple MOVs have no power due to loss of 16BB3.
RHR 'C' pump has tripped RHR 'B' pump is running, however multiple MOVs have no power due to loss of 16BB3.
CRS Re-enters EP-2 and enters EP-3 due to drywell pressure.
CRS Re-enters EP-2 and enters EP-3 due to drywell pressure.

Revision as of 10:29, 27 April 2019

2015-12 Draft Op Tests
ML16028A020
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 12/14/2015
From: Vincent Gaddy
Operations Branch IV
To:
Entergy Operations
References
50-416/15-012, 50-417/15-012
Download: ML16028A020 (350)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 12/7/201 5 Examination Level: RO SRO Operating Test Number: LOT-201 5 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - M Loss of Shutdown Cooling, Time to 200F Determination GJPM-OPS-2015-AR1 Conduct of Operations R - D Fire Door Surveillance GJPM-OPS-2015-AR2 Equipment Control R - N Electrical Print Reading (Determine effect of removing fuses in RPS system)

GJPM-OPS-2015-AR3 Radiation Control Emergency Plan R - M Station Blackout Electrical Power Determination GJPM-OPS-2015-AR4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015-AR1 JPM Title: Loss of Shutdown Cooling, Time to 200°F Determination JPM JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review: Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 2 of 7 Loss of Shutdown Cooling, Time to 200°F Determination JPM Time Critical Alternate Path Validation Time:

30 Min Setting: Classroom Type: RO Task: CRO-E12-11 K&A: 2.4.11- 3.4/3.6 Safety Function:

N/A Performance:

Actual Reference(s):

05-1-02-III-1 Handout(s) 05-1-02-III-1 # Manipulations:

N/A # Critical Steps:

1 Simulator Setup/Required Plant Conditions

None Safety Concerns
None. Task Standard
Determine the time to 200°F in the reactor following the loss of shutdown cooling IAW 05-1-02-III-1.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

On day 5 of a refueling outage the following conditions exist: Preparation for drywell head removal is in progress.

Reactor water level is being maintained 245" to 255" Shutdown Range.

Reactor coolant temperature is 1 4 5°F. RHR A is lined up and providing shutdown cooling through the E12

-F053 A. Neither RHR nor ADHR is available due to the situation.

RWCU is available.

Initiating Cue(s):

Determine the time available before reactor coolant temperature reaches 200°F

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 4 of 7 Loss of Shutdown Cooling, Time to 200°F Determination JPM Notes: (Notes to Evaluator)

None. Task Overview:

(Detailed description of task)

This task has the student to estimate time to reach 200°F following loss of shutdown cooling. Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-1-02-III-1, Attachment 1

  • Using given information, determines time to boil is approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Standard: The operator determines using procedure 05 02-III-1 Attachment I, Figure 2 that there are about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 200°F

. Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 5 of 7 Task Standard(s)
Determine the time to 200°F in the reactor following the loss of shutdown cooling IAW 05-1-02-III-1. SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015A R1 JPM Title: Loss of Shutdown Cooling, Time to 200°F Determination JPM Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

On day 5 of a refueling outage the following conditions exist: Preparation for drywell head removal is in progress.

Reactor water level is being maintained 245" to 255" Shutdown Range.

Reactor coolant temperature is 1 45°F. RHR A is lined up and providing shutdown cooling through the E12

-F053A. Neither RHR nor ADHR is available due to the situation.

RWCU is available.

Initiating Cue(s):

Determine the time available before reactor coolant temperature reaches 200°F

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015-AR2 JPM Title: Fire Doors Surveillance Facility Number:

GJPM-OPS-2011AR1____ (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time:

15 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 2 of 7 Electrical Print Reading Setting: Classroom Type: RO Task: CRO-P64-NORM-7 K&A: 2.1.20 (4.6/4.6) 2.2.12 (3.7/4.1)

Safety Function

NA Time Required
20 minutes Time Critical: No Faulted: No Performance
Actual Reference(s)
06-OP-SP64-M-0043, Fire Doors Alarm Check Handout(s)
06-OP-SP64-M-0043, Procedure Body 06-OP-SP64-M-0043, Fire Doors Alarm Check (Attachment 1 prepared)
  1. Manipulations
NA # Critical Steps
2 Simulator Setup/Required Plant Conditions
None Safety Concerns: None Date of Examination: 12/07/2015 Operating Test Number
LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant is operating at rated power.

06-OP-SP64-M-0043 step 5.2.1 and 5.2.2 are performed as required by another operator.

The CRS directs you to perform a partial 06-OP-SP64-M-0043, Fire Doors Alarm Check on the following doors: (1) Elect Pen Rm 1A221 door number 1A212, (2) Emerg S/D Rm OC208A door number OC208, and (3) Sec Ctmt Door 1A604.

You note the following items during your inspection:

o Elect Pen Rm 1A221 door 1A212:

Door does not latch after being fully opened and allowing the closure mechanism to pull the door shut; however, when you pull the door it latches.

Does not alarm upon opening.

o Emerg S/D Rm OC208A door OC208:

Has a deep gouge/dent 10" long on one side on the bottom right quadrant but does not penetrate the door skin.

Seam has separated next to the 10" gouge.

Alarms after 30 seconds upon opening.

o Sec Ctmt Door 1A604:

Has a rust patch on the A ux Building Roof side that has left a 3 in 2 hole in the skin of the door (the inside door skin is not damaged).

Has not alarmed 4 minutes after opening.

Initiating Cue(s):

Complete the attached 06

-OP-SP64-M0043, Fire Doors Alarm Check surveillance, including all portions of Attachment 1 Cover Sheet sections 2.0 and 3.0. Only mark Tech Spec Acceptance Criteria as Acceptable if REQUIRED by 06-OP-SP64-M-0043 surveillance procedure. Note reasons for marking Tech Spec Acceptance Criteria or other steps/data in the test results section as "Acceptable" or "Unacceptable" on the back of the surveillance coversheet.

All prerequisites are verified met.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will perform a Fire Door Alarm Check using the information provided in the initiating ques. The operator will discover tech spec door OC208 is INOP, tech spec door 1A212 is OPERABLE but requires a WR to fix the closing mechanism, and non

-tech spec door 1A604 also requires a WR to fix the security alarm timing and a rust patch. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06-OP-SP64-M-0043

  • The operator evaluates the given conditions for each fire door given in the initiating cues and determines the following:
  • Tech Spec Door 1A212 Tech Spec Acceptance Criteria is "Unacceptable," and step 5.2.6 other steps/data is "Unacceptable" because the closing mechanism will not shut the door without assistance (see note for step 5.2.6).
  • Tech Spec Door OC208 fails step 5.2.5c; however, the Tech Spec Acceptance Criteria for this surveillance is "Acceptable" (see note for step 5.2.5). The other steps/data is "Unacceptable".

Tech Spec Door OC208 is INOP since it fails step 5.2.5c.

  • Door 1A604 is not a Tech Spec door; therefore, Tech Spec Acceptance Criteria is NA. Step 5.2.5a data is "Unacceptable" because the outside door skin is visibly damaged with a hole > 3/16".

Standard: The deficiencies noted above are recorded on the surveillance cover sheet.

Cue: Notes: This meets the requirement for step 3.2 on the surveillance coversheet. Any words that demonstrate an equivalent understanding is acceptable.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 5 of 7 Step 2: 06-OP-SP64-M-0043
  • Complete the surveillance coversheet section 3.1 by checking boxes for:

(1) Partial procedure complete, (2)* Tech Spec Acceptance Criteria Unacceptable, and (3)* All other steps/data Unacceptable

. Standard: Checks appropriate boxes.

Cue: Notes: SAT / UNSAT Step 3: 06

-OP-SP64-M-0043 Complete the surveillance coversheet sections 2.1, 2.2 and 3.3 Standard: Circle for the plant being in Mode 1 and record themselves as performer with the date and time.

Cue: Notes: JPM is completed when the operator completes the surveillance package coversheet.

SAT / UNSAT Task Standard(s)

The operator determines that the Tech Spec Acceptance Criteria is "Unacceptable" and that All other steps/data is "Unacceptable" per 06-OP-SP64-M-0043. SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AR2 JPM Title: Fire Doors Surveillance Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

Give this page to the student Initial Condition(s):

The Plant is operating at rated power.

06-OP-SP64-M-0043 step 5.2.1 and 5.2.2 are performed as required by another operator.

The CRS directs you to perform a partial 06-OP-SP64-M-0043, Fire Doors Alarm Check on the following doors: (1) Elect Pen Rm 1A221 door number 1A212, (2) Emerg S/D Rm OC208A door number OC208, and (3) Sec Ctmt Door 1A604.

You note the following items during your inspection:

o Elect Pen Rm 1A221 door 1A212: Door does not latch after being fully opened and allowing the closure mechanism to pull the door shut; however, when you pull the door it latches.

Does not alarm upon opening.

o Emerg S/D Rm OC208A door OC208:

Has a deep gouge/dent 10" long on one side on the bottom right quadrant but does not penetrate the door skin.

Seam has separated next to the 10" gouge.

Alarms after 30 seconds upon opening.

o Sec Ctmt Door 1A604:

Has a rust patch on the Aux Building Roof side that has left a 3 in 2 hole in the skin of the door (the inside door skin is not damaged).

Has not alarmed 4 minutes after opening.

Initiating Cue(s):

Complete the attached 06

-OP-SP64-M0043, Fire Doors Alarm Check surveillance, including all portions of Attachment 1 Cover Sheet sections 2.0 and 3.0. Only mark Tech Spec Acceptance Criteria as Acceptable if REQUIRED by 06-OP-SP64-M-0043 surveillance procedure. Note reasons for marking Tech Spec Acceptance Criteria or other steps/data in the test results section as "Acceptable" or "Unacceptable" on the back of the surveillance coversheet.

All prerequisites are verified met.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 1 of 7 GGNS 2012 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5AR 3 JPM Title: Electrical Print Reading Facility Number:

N/A (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time:

15 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 2 of 7 Electrical Print Reading Setting: Classroom Type: RO/SRO Task: SRO-ADMIN-ADMIN-48/CRO-ADMIN-005 K&A: 2.2.15 (3.9/4.3)

Safety Function

N/A Time Required
15 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
E-1173-019 Handout(s)
E-1173-019 # Manipulations
N/A # Critical Steps
1 Group: N/A Simulator Setup/Required Plant Conditions
None Safety Concerns
None Date of Examination: 12/07/2015 Operating Test Number
LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is operating at rated power.

I&C wants to replace fuses C71

-F14A and C71

-27D. Initiating Cue(s):

Determine what effect removing C71

-F14A and C71

-27D will have on the plant.

This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will use the provided electrical prints to prove that removing fuses, C71

-F14A and C71-27D, causes a Division 1 half scram

. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: E-1173-019

  • Using E-1173-019, determine the effect of removing fuses, C71

-F14A and C71-27D.

  • Removing C71

-F14A will de

-energize K14A and K14E relays inserting a Division 1 half scram.

  • Removing C71

-27D will de

-energize the white light for Reactor Scram Trip Logic "D".

Standard: Removing C71

-F14A will de

-energize K14A and K14E relays inserting a Division 1 half scram.

Removing C71-27D will de

-energize the white light for Reactor Scram Trip Logic "D". Cue: Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 5 of 7 Task Standard(s)
The operator will use the provided electrical prints to prove that removing fuses, Removing C71

-F14A will de

-energize K14A and K14E relays inserting a Division 1 half scram.

Removing C71

-27D will de

-energize the white light for Reactor Scram Trip Logic "D". SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015A R 3 JPM Title: Electrical Print Reading Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: __________________________________

__________________

Examiner's Signature:

___________________________________________________

Give this page to the student

Initial Condition(s):

The plant is operating at rated power.

I&C wants to replace fuses C71

-F14A and C71

-27D.

Initiating Cue(s):

Determine what effect removing C71

-F14A and C71

-27D will have on the plant.

This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 1 of 7 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015-AR 4 JPM Title: Station Blackout Table 1 Determination JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min

Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By: Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 2 of 7 Admin Task: Station Blackout Table 1 Determination Setting: Classroom Type: RO Task: NA K&A: 2.4.11 (4.0/4.2) 2.1.20 (4.6/4.6) 2.1.25 (3.9/4.2)

Safety Function

NA Time Required
15 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
Loss of AC Power ONEP, 05 02-I-4 Handout(s)
Loss of AC Power ONEP, 05-1-02-I-4 # Manipulations
NA # Critical Steps
1 Group: NA Simulator Setup/Required Plant Conditions
None Safety Concerns
None Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 3 of 7 Initial Condition(s):

The Plant has experienced a station blackout concurrent with a LOCA.

The HPCS pump is not available for operation.

Division 3 diesel generator is supplying power to the 1 5 A A bus.

Initiating Cue(s):

Determine how many KW must be available on the 17AC bus in order to support the operation of FPCCU supplemented with RHR A including all auxiliary and support systems

. Do not include HPCS Diesel Auxiliaries as a requirement to support FPCCU and RHR A operation.

All prerequisites are verified met.

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 4 of 7 Admin Task

Station Blackout Table 1 Determination Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will use Table 1 of the Loss of AC ONEP to determine the load requirements to run RHR A. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-1-02-I-4 Table 1

  • The operator determines the following required essential loads for FPCCU and RHR A operation:
  • SSW Pump 997 KW
  • RHR A Pump 803 KW
  • ESF SWGR Battery Fans 122 KW ESF Battery Charger 110 KW
  • ECCS Room Cooler 8 KW
  • SSW O/A Fan 40 KW
  • FPCCU Pump 124 KW Total require d KW available = 2647.5 or 2537.5 if Battery Charger was included.

Standard: Determines the correct loads and total required power to run FPCCU and RHR A. Cue: Notes: Accommodations for rounding errors are acceptable.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 5 of 7 Task Standard(s)

The operator determines a minimum of 2537.5 KW is required to operate FPCCU and RHR A. SAT / UNSAT Name: ___________________________

Time Start: _______

Time Stop: _______

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 6 of 7 Applicant:

____________________________________________________________

JPM Number: GJPM-OPS-2015AR4 JPM Title: Station Blackout Table 1 Determination Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________

___________

______________

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Give this page to the student Initial Condition(s):

The Plant has experienced a station blackout concurrent with a LOCA.

The HPCS pump is not available for operation.

Division 3 diesel generator is supplying power to the 15AA bus.

Initiating Cue(s):

Determine how many KW must be available on the 17AC bus in order to support the operation of FPCCU supplemented with RHR A including all auxiliary and support systems.

Do not include HPCS Diesel Auxiliaries as a requirement to support FPCCU and RHR A operation.

All prerequisites are verified met.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 12/7/2015 Examination Level: RO SRO Operating Test Number: LOT-201 5 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - D Determine Firewatch Requirements GJPM-OPS-2015-AS1 Conduct of Operations R - N Manual On-Line Risk Assessment GJPM-OPS-2015-AS2 Equipment Control R - D Tagout Removal Approval GJPM-OPS-2015-AS3 Radiation Control R - D Review Liquid Radwaste Discharge Permit GJPM-OPS-2015-AS4 Emergency Plan R - N Emergency Classification GJPM-OPS-2015-AS5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (N)ew or (M)odified from

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 1 of 13 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5 A S 1 JPM Title: Determine Firewatch Requirements

_ Facility Number: GJPM-OPS-A2013AS2 (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time:

25 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review: Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 2 of 13 Determine Fire Watch Requirements Setting: Classroom Type: SRO Task: S RO- NO-035 K&A: Generic 2.1.8: (3.4/4.1); 2.2.22: (4.0/4.7);2.1.25: (3.9/4.2); 2.4.25: (3.3/3.7) Safety Function:

Conduct of Operations [10CFR55.45a(12)]

Performance:

Actual Reference(s):

02-S-01-17, Control of Limiting Conditions for Operation 02-S-01-27, Operations Philosophy 06-OP-SP64-D-0044 Daily Fire Door Checks TRM 6.2.3, Fire Systems

-Spray and Sprinkler Systems P&ID M0035B Drawing A0634 UFSAR App. 9A, Fire Hazards Analysis Handout(s):

Copy of Tech Specs/TRM Section 6.2

.3 02-S-01-17, Control of Limiting Conditions for Operation P&ID M0035B Drawing A0634 UFSAR App. 9A, Fire Hazards Analysis for rooms 1D301 and 1D310 (ATTACHED)

  1. Manipulations:

N/A # Critical Steps:

2 Simulator Setup/Required Plant Conditions

None Safety Concerns
None Task Standard(s)
Candidate determines fire watch requirement for inoperability of sprinkler system N1P64D142A is to establish a continuous firewatch with backup fire suppression equipment in DG breezeway area 1D301 and an hourly fire watch patrol for Div 1 DG room 1D310 within one hour

. (It is acceptable for the Candidate to establish a continuous fire watch patrol for Div 1 DG room 1D310 within one hour in lieu of an hourly firewatch patrol

.)

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 3 of 13 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at rated power.

Valve 1P64F123A, DSL GEN MAN PRE

-ACT D142A ISOL, is being tagged closed for preventive maintenance on sprinkler system 1P64D142A. Initiating Cue(s):

As CRS, you are directed to determine the Fire Watch requirements associated with this work.

Use the references provided.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 4 of 13 Determine Fire Watch Requirements Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The student will determine the required TRM Fire Watch actions for impairing a required fire water sprinkler system

. Sequence is not critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 5 of 13 Critical steps are underlined, italicized, and denoted by an (*)

Sequence is not critical.

Step 1: TRM 6.2.3

  • Candidate uses provided references to identify the sprinkler 1P64D142A is required operable by TR 6.2.3 to protect DG corridor room 1D301, which is an area housing redundant Safe Shut Down equipment

. Standard:

Determines a continuous fire watch with backup fire suppression equipment must be established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of closing valve 1P64F123A for room 1D301 per TRM 6.2.3 Condition A, Action A.1

. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 6 of 13 Step 2: TRM 6.2.8
  • Candidate uses provided references to identify the sprinkler 1P64D142A is required operable by TR 6.2.3 to also protect Div 1 DG room 1D310, which is an area that does NOT house redundant Safe Shut Down equipment

. Standard: Determines an hourly fire watch patrol must be established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of closing valve 1P64F123A for room 1D301 per TRM 6.2.

3 Condition A, Action A.2. If the candidate specifies establishing a continuous fire watch

, with or without backup fire suppression equipment

, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for 1D310, this is acceptable.

Cue: None Notes: TR 6.2.3 specifies 1P64D142A protects redundant Safe Shutdown Equipment. The Fire Hazards Analysis specifies area 1D301 houses Div 1 and Div 2 equipment, and area 1D310 only houses Div 1 equipment; therefore, only an hourly firewatch patrol is required fo r area 1D310. But since TR6.2.3 does not make this distinction, the candidates electing a continuous firewatch for 1D310 is acceptable.

. SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 7 of 13 Task Standard(s)
Candidate determines fire watch requirement for inoperability of sprinkler system N1P64D142A is to establish a continuous firewatch with backup fire suppression equipment in DG breezeway area 1D301 and an hourly fire watch patrol for Div 1 DG room 1D310 within one hour.

(It is acceptable for the Candidate to establish a continuous fire watch patrol for Div 1 DG room 1D310 within one hour in lieu of an hourly firewatch patrol

.) SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 8 of 13 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AS1 JPM Title: Determine Firewatch Requirements Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

__________________________________________

_________

Give this page to the student Initial Condition(s):

The plant is at rated power.

Valve 1P64F123A, DSL GEN MAN PRE

-ACT D142A ISOL, is being tagged closed for preventive maintenance on sprinkler system 1P64D142A. Initiating Cue(s):

As CRS, you are directed to determine the Fire Watch requirements associated with this work.

Use the references provided.

Give this page to the student

Give this page to the student

Give this page to the student

Give this page to the student

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S 2 JPM Title: Manual On-Line Risk Assessment_

Facility Number:

GJPM-OPS-A2012-1AS1________ (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 2 of 7 Manual Risk Assessment Setting: Classroom Type: SRO Task: SRO-ADMIN-054 K&A: Generic 2.1.25: 4.2; 2.1.

20: 4.6; 2.2.17: 3.8 Safety Function

Equipment Control

[10CFR55.4 3b (5)] Performance

Actual Reference(s)
01-S-18-6, Risk Assessment of Maintenance Activities Handout(s)
01-S-18-6, Risk Assessment of Maintenance Activities
  1. Manipulations
N/A # Critical Steps
1 Simulator Setup/Required Plant Conditions
None Safety Concerns
None Task Standard(s)
Determines the Plant Safety Index risk color is YELLOW in accordance with 01

-S-18-6.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at 100% power.

Maintenance activities are in progress replacing P75

-F-16A (Fuel Oil Day TK supply to DG engine drive and DG Fuel Oil Booster Pumps).

Building Operator reports breaker 152

-1503 (SSW PMP A) is tripped with heat damage. No other equipment is affected.

The EOOS computer program is not available.

All other equipment and structures are operable.

Initiating Cue(s):

Determine the Plant Safety Index risk color manually in accordance with 01

-S-18-6, provided.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 4 of 7 Manual Risk Assessment Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The candidate will determine the Plant Safety Index risk color for the given plant conditions using 01

-S-18-6 Attachment IV.

Tasks: Critical steps are underlined, italicized, and denoted by an (*)

Step 1: 01-S-18-6

  • Determines the Plant Safety Index risk color using 01

-S-18-6 Attachment 4

. Standard: Candidate performs a manual analysis in accordance with 01

-S-18-6 step 5.5.1a. Candidate reviews 01

-S-18-6 Attachment 4 page 2 and determines the combination of Emergency Diesel Generator A (P75) and SSW A (P41) out of service, the risk color is Yellow.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 5 of 7 Task Standard(s)
Determines the Plant Safety Index risk color is YELLOW in accordance with 01-S-18-6. SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AS2 JPM Title: Manual On-Line Risk Assessment Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

Give this page to the student

Initial Condition(s):

The plant is at 100% power.

Maintenance activities are in progress replacing P75

-F-16A (Fuel Oil Day TK supply to DG engine drive and DG Fuel Oil Booster Pumps).

Building Operator reports breaker 152

-1503 (SSW PMP A) is tripped with heat damage. No other equipment is affected.

The EOOS computer program is not available.

All other equipment and structures are operable.

Initiating Cue(s):

Determine the Plant Safety Index risk color manually in accordance with 01

-S-18-6, provided.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 1 of 8 GGNS 2012 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S3 JPM Title: Tagout Approval____

Facility Number: GJPM-OPS-2012AS3 (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 30 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 2 of 8 Tagout Approval Setting: Classroom Type: RO Task: CRO-ADMIN-05 K&A: 2.2.13 (4.1/4.3), 2.2.41 (3.5/3.9)

Safety Function: N/A Performance:

Actual Reference(s):

EN-OP-102 (Protective and Caution Tagging) 04-1-01-E21-1 (Low Pressure Core Spray System SOI) E-1182-7 M-1087 Handout(s):

EN-OP-102 04-1-01-E21-1 E-1182-7 M-1087 Tagout Tags Sheet (Attached)

  1. Manipulations:

N/A # Critical Steps:

1 Group: N/A Simulator Setup/Required Plant Conditions

None Safety Concerns
None Task Standard(s)
The operator indentifies the tagout lacks the required isolations per EN

-OP-102.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 3 of 8 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is in MODE 4

. The LPCS jockey pump is to be replaced.

Initiating Cue(s):

As CRS you are tasked to verify the adequacy of the proposed tagout for work on the LPCS Jockey Pump. The LPCS pump will be tagged separately.

For the purpose of this task restoration configuration is not required.

Document errors or inadequate boundaries.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 4 of 8 Admin Task
Tagout Approval Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will determine the proper isolations for the LPCS Jockey Pump.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: EN-OP-102 5.3[2](e)/Att. 9.2 The operator must determine minimum Tagout boundaries to include:

E21-F032 (LPCS Jockey Pump Suction)

E21-F034 (LPCS Jockey Pump Disch Stop Check)

E21-F035 (LPCS Jockey Pump Minimum Flow)

E21-FX020 (Supp Pool Level Transmitters Fill) 52-151108 (LPCS JKY PMP)

HS M 611 (Control Room Handswitch

) E21-F223 (Jockey Pump Discharge Drain/Pump Vent)

E21-F224 (Jockey Pump Discharge Drain/Pump Vent)

E21-F225 (Jockey Pump Suct Test Conn Isol) E21-F226 (Jockey Pump Suct Test Conn Isol)

Standard: Determines the appropriate boundaries.

Cue: Notes: The valves listed are the minimum required valves required to perform work. Any combination of valves that adequately isolates the LPCS Jockey Pump and provides a drain or vent path will meet the requirements of this step (including extra valves and breakers). SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 5 of 8 Step 2: EN-OP-102 5.3[4]
  • The Operator documents the following:
  • E21-F034 is required to be CLOSED to isolate the LPCS Jockey Pump Discharge.
  • E21-F226 is required to be OPEN to complete the drain path (in line with E21-F225).
  • E21-FX020 is required to be CLOSED to isolate the Supp. Pool Level Transmitters Fill.

E21-F223 and E21

-F224 are required to be OPEN to establish a vent path.

E21-F011 is not required for this tag.

Standard: Documents deficiencies.

Cue: Notes: These requirements can be specifically found in EN

-OP-102 Attachment 9.2 sections 1.1 and 2.1 and Attachment 9.3 sections 1.1 and 1.4. Any words that demonstrate an equivalent understanding is acceptable.

The task is complete when the operator determines the adequacy for this Tagout.

SAT / UNSAT Task Standard(s)

The operator indentifies the tagout lacks the required isolations per EN

-OP-102. SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 6 of 8 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AS3 JPM Title: Tagout Approval Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

Give this page to the student

Initial Condition(s):

The plant is in MODE 4

. The LPCS jockey pump is to be replaced.

Initiating Cue(s):

As CRS you are tasked to verify the adequacy of the proposed tagout for work on the LPCS Jockey Pump. The LPCS pump will be tagged separately.

For the purpose of this task restoration configuration is not required.

Document errors or inadequate boundaries.

NUCLEAR MANAGEMENT MANUAL N ON-QUALITY RELATED EN-OP-102-01 REV. 7 INFORMATIONAL USE PAGE 7 OF 26 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________

TAGOUT: ___XXXX________ Tag Serial No. Tag Type Equipment Equipment Description Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/Removal Tag Notes 1 D 52-151108 LPCS JKY PMP 15B11 2 OPEN 2 D HS M611 LPCS Jockey Pump Handswitch 1H13-P601 1 NUET AFTER STOP 3 D E21-F032 LPCS Jockey Pump Suction Area 9 Elevation 93' 4 CLOSED 4 D E21-F 011 LPCS MIN FLO TO SUPP POOL 1H13-P601 3 AUTO AFTER CLOSE 5 D E21-F035 LPCS Jockey Pump Minimum Flow Area 9 Elevation 93' 5 CLOSED 6 D E21-F225 Jockey Pump Suct Test Conn Isol Area 9 Elevation 93' 5 OPEN 7 D E21-F226 Jockey Pump Suct Test Conn Isol Area 9 Elevation 93' 5 CLOSED Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-AS4 JPM Title: Review Liquid Radwaste Discharge Permit Facility Number:

N/A __________ (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 20 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 2 of 7 Review Liquid Radwaste Discharge Permit Setting: Classroom Type: SRO Task: SRO-NO-10 K&A: 2.3.6: 3.1 Safety Function
9 Performance
Actual Reference(s)
01-S-08-11, Radioactive Discharge Controls 06-CH-SG17-V-00 34, Radwaste Release INOP Monitor Pre-Release Analysis OCDM 6.3 Handout(s)
LRW Discharge Permit with 06

-CH-SG17-V-00 34 Att. I completed and 01

-S-08-11 Att. I with Parts 1, 2, 3, 4, and 5 completed with errors OCDM 6.3 # Manipulations

N/A # Critical Steps
1 Simulator Setup/Required Plant Conditions
None Safety Concerns
None Task Standard(s)
Reviews the data recorded in Parts 1, 2, 3, 4, and 5 of the LRW Discharge Permit provided using 01

-S-08-11 and identifies at least 2 of the 3 errors.

Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant Chemistry technician has presented completed surveillance 06-CH-SG17-V-0034, Radwaste Release INOP Monitor Pre

-Release Analysis, including a Batch Liquid Radwaste Discharge Permit

, to you for Operations Supervision review and approval. Initiating Cue(s):

You are the Control Room Supervisor. Perform the review for the Part 5 Operations Supervisor signoff of the Batch Liquid Radwaste Discharge Permit associated with completed surveillance 06

-CH-SG17-V-0034 for the recently completed discharge.

REFER TO THE LIQUID RADWASTE DISCHARGE PERMIT PROVIDED.

Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 4 of 7 Review Liquid Radwaste Discharge Permit Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by Operations Supervision following a controlled release of liquid radwaste. Three errors have been introduced somewhere within sections 1 through 5 of the Discharge Permit.

Critical step s are underlined, italicized, and denoted by an (*)

Step 1: 01-S-08-11

  • Reviews the Batch Liquid Radwaste Discharge Permit package provided per the requirements of 01

-S-08-11 to determine if the discharge was performed in accordance with the requirements of 01

-S-08-11. Standard: Reviews the data recorded in Parts 1, 2, 3, 4, and 5 of the LRW Discharge Permit provided using 01

-S-08-11 and identifies at least 2 of the 3 following errors: In Part 2, the "Radiochemist

" signoff for independent verification required for Effluent Radiation Monitor Inoperable had been N/A'd.

In Part 4, the "Shift Manager

" signoff granting permission to discharge had not been obtained.

In Part 5, the "Average Dilution Flow

" during the discharge was lower than the required minimum dilution flow prescribed in Section 3.

Cue: None Notes: All values recorded in Parts 1, 2, and 3 derive from pages 1 and 2 of the computer generated Liquid Pre

-Release Permit Report in 06

-CH-SG17-V-00 34 Att I SAT / UNSAT

Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 5 of 7 Task Standard(s)
Reviews the data recorded in Parts 1, 2, 3, 4, and 5 of the LRW Discharge Permit provided using 01

-S-08-11 and identifies at least 2 of the 3 errors.

SAT / UNSAT Remember to record stop time

Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 6 of 7 Applicant:

____________________________________________________________

JPM Number: GJPM-OPS-2015AS4 JPM Title: Review Liquid Radwaste Discharge Permit Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 1 of 4 Revision 1 4/22/13 Page 1 of 7 BATCH LIQUID RADWASTE DISCHARGE PERMIT YY-MM-DD-17 Part 1 Pre-Relea se Pr ocessing Release Number*

Date Today Time 0700 Tank to be released*

FDST-A Volume* 28 56 0 gal Tank is isolated. Recirculation started Today / 0100 Date/Time Dilution flow 9900 gpm Radwaste monitor background reading*

  • N/A (LCO 1-TS-XX-0073) cpm (Monitor reading is less than 10,800 cpm)
  • LRW Rad Monitor is INOP under this LCO

Clyde Small

_____________________

Operator (Performer)

Asterisked* items above verified Frank Zapp_____________________

Operator (Verifie r)

Radwaste monitor background reading verified John Doe #30588 Today / 0400 Operations Supervision /Date/Time

________________________________________________________

Part 2 Pre-Release Analysis

20XX192

Batch Number Sample Date Today Time 0830 Minimum recirculation time is met RC #30471 One Total Suspended Solids (TSS) sample has been collected and analyzed for the month: Yes X Initials RC #30471 No N/A TSS N/A mg/l (< 30mg/l) The radioactive liquid from the tank designated above is within the ALARA criteria of 10CFR50 App I as defined by surveillance 06

-CH-SG17-P-0041, 06-CH-SG17-V-0034, or 06-CH-SP41-P-0035 and may be released.

Rupert Colada

  1. 30007 Radiochemist

Independent Verification if Effluent Radiation Monitor Inoperable.

N/A Radiochemist Comments:

no limits exceeded

Should be signed, not N/A'd DO NOT GIVE TO STUDENT EVALUATOR COPY

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 2 of 4 Revision 1 4/22/13 Page 2 of 7 BAT CH LIQUID RADWASTE DISCHARGE PERMIT Part 3 Monito r Setpoint Calibr ation Batch Number (from Part 2) 20XX192 Setpoints Adjusted to:

Minimum Blowdown Flow Rate Setpoint (Circ Water Blowdown Flow Setpoint) 2250 gpm Maximum Tank Discharge Flow Rate Setpoint (Liquid Radwaste Effluent Flow Setpoint) 100 gpm Effluent Monitor Alarm Setpoint N/A (LCO 1-TS-XX-0073) cpm (Hi) Effluent Monitor Trip Setpoint N/A cpm (Hi-Hi) Micheal Wildfire

  1. 30864 / Today I&C Technician Date S. Nugent #30255 / Today Verified Date Copies of Pages 1 and 2 of this permit have been placed in the Control Room Setpoint Logbook, and

The previous Pages 1 and 2 have been removed.

Micheal Wildfire

  1. 30864 / Today I&C Technician Date S. Nugent #30255 / Today Verified Date

Part 4 Releas e A uthorization The designated tank may be released provided the discharge and dilution flows meet the setpoint criteria.

/

Shift Manager Date

Part 5 Release Valve lineup Verified H. Casey #30114 / D. McCormick

  1. 30435 Independent Verification

if Radiation Monitor Inop From Step 6.4.2e(2):

On the date of release , prior to opening SG17

-F355 DRAIN BASIN ISOL VLV, have chemistry verify the Total Suspended Solids analysis for this tank has been completed or is not required.

The Total Suspended Solids analysis for this tank has been completed.

Not Required_

Rupert Colada

  1. 30007 / Today Radiochemist Date DO NOT GIVE TO STUDENT EVALUATOR COPY Should be signed, not blank GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 3 of 4 Revision 1 4/22/13 Page 3 of 7 Part 5 (cont) BATCH LIQUID RADWASTE DISCHARGE PERMIT Radiati on Monitor R eading Before release N/A cpm Maximum during release N/A cpm Average during release*

N/A cpm Tank Level Before 28560 After*

762 Gallons Released*

27798 Average Release Rate (Tank Discharge Rate GPM)*

92.66 Flo w Rate Indication During Disc harge a) Maximum Radwaste Tank Effluent Flow*

94 gpm If G17 FR-R011, tank discharge flow rate recorder, is inop flow must be estimated at intervals not to exceed every four hours.

N/A /

Start N/A /

Approx. Middle

N/A /

End Flow Time b) Average Dilution Flow*

2000 gpm (appx)

Circulation Water Blowdown Flow, monitor Operable Inoperable Discharge Canal Flow Other dilution water source (specify):

N/A If dilution flow monitor is inop, flow must be estimated at intervals not to exceed every four hours.

N/A / Start N/A / Approx. Middle

N/A / End Flow Time DO NOT GIVE TO STUDENT EVALUATOR COPY Should be greater than minimum setpoint 2250 gpm listed in Part 3

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 4 of 4 Revision 1 4/22/13 Page 4 of 7 BATCH LIQUID RADWASTE DISCHARGE PERMIT LCO No.: N/A

DATE AND TIME

ELAPSED TIME*

(minutes)

VALVES OPEN VALVES SHUT

Today 0930 Today 1430 300

TOTAL 300 Monitor flushed HC#30114 H. Casey #30114

Initials Operator (Performer)

Asterisked* items above verified D. McCormick

  1. 30435_______________

Operator(Verifier)

__________________

Operations Supervision

Comments:

Par t 6 Post-Release Analysis The post-release analysis is based on actual data recorded during the release

Comments:

/

Radiochemist Date

DO NOT GIVE TO STUDENT EVALUATOR COPY Operations Supv signoff block

Give this page to the student

Initial Condition(s):

The Plant Chemistry technician has presented completed surveillance 06-CH-SG17-V-0034, Radwaste Release INOP Monitor Pre

-Release Analysis, including a Batch Liquid Radwaste Discharge Permit, to you for Operations Supervision review and approval.

Initiating Cue(s):

You are the Control Room Supervisor. Perform the review for the Part 5 Operations Supervisor signoff of the Batch Liquid Radwaste Discharge Permit associated with completed surveillance 06

-CH-SG17-V-0034 for the recently completed discharge.

REFER TO THE LIQUID RADWASTE DISCHARGE PERMIT PROVIDED.

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 1 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT YY-MM-DD-17 Part 1 Pre-Relea se Pr ocessing Release Number*

Date Today Time 0700 Tank to be released*

FDST-A Volume* 28 56 0 gal Tank is isolated. Recirculation started Today / 0100 Date/Time Dilution flow 9900 gpm Radwaste monitor background reading*

  • N/A (LCO 1-TS-XX-0073) cpm (Monitor reading is less than 10,800 cpm)
  • LRW Rad Monitor is INOP under this LCO.

Clyde Small______________________

Operator (Performer)

Asterisked* items above verified Frank Zapp

________________________

Operator (Verifier)

Radwaste monitor background reading verified John Doe #30588 Today / 0400 Operations Supervision /Date/Time

________________________________________________________

Part 2 Pre-Release Analysis

20XX192

Batch Numbe r Sample Date Today Time 0830 Minimum recirculation time is met RC #30471 One Total Suspended Solids (TSS) sample has been collected and analyzed for the month: Yes X Initials RC #30471 No N/A TSS N/A mg/l (< 30mg/l) The radioactive liquid from the tank designated above is within the ALARA criteria of 10CFR50 App I as defined by surveillance 06

-CH-SG17-P-0041, 06-CH-SG17-V-0034, or 06-CH-SP41-P-0035 and may be released.

Rupert Colada

  1. 30007 Radiochemist Independent Verification if Effluent Radiation Monitor Inoperable.

N/A Radiochemist

Comments:

no limits exceeded

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 2 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT Part 3 Monito r Setpoint Calibr ation Batch Number (from Part 2) 20XX192 Setpoints Adjusted to:

Minimum Blowdown Flow Rate Setpoint (Circ Water Blowdown Flow Setpoint) 2250 gpm Maximum Tank Discharge Flow Rate Setpoint (Liquid Radwaste Effluent Flow Setpoint) 100 gpm Effluent Monitor Alarm Setpoint N/A (LCO 1-TS-XX-0073) cpm (Hi) Effluent Monitor Trip Setpoint N/A cpm (Hi-Hi) Micheal Wildfire

  1. 30864 / Today I&C Technician Date

S. Nugent #30255 / Today Verified Date

Copies of Pages 1 and 2 of this permit have been placed in the Control Room Setpoint Logbook, and

The previous Pages 1 and 2 have been removed.

Micheal Wildfire

  1. 30864 / Today I&C Technician Date

S. Nugent #30255 / Today Verified Date

Part 4 Releas e A uthorization The designated tank may be released provided the discharge and dilution flows meet the setpoint criteria.

/

Shift Manager Date

Part 5 Release Valve lineup Verified H. Casey #30114 / D. McCormick #30435 Independent Verification

if Radiation Monitor Inop From Step 6.4.2e(2):

On the date of release , prior to opening SG17

-F355 DRAIN BASIN ISOL VLV, have chemistry verify the Total Suspended Solids analysis for this tank has been completed or is not required.

The Total Suspended Solids analysis for this tank has been completed.

Not Required_

Rupert Colada

  1. 30007 / Today Radiochemist Date

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 3 of 4 Part 5 (cont) BATCH LIQUID RADWASTE DISCHARGE PERMIT Radiati on Monitor R eading Before release N/A cpm Maximum during release N/A cpm Average during release*

N/A cpm Tank Level Before 28560 After*

762 Gallons Released*

27798 Average R elease Rate (Tank Discharge Rate GPM)*

92.66 Flo w Rate Indication During Disc harge a) Maximum Radwaste Tank Effluent Flow*

94 gpm If G17 FR-R011, tank discharge flow rate recorder, is inop flow must be estimated at intervals not to exceed every four hours.

N/A /

Start N/A /

Approx. Middle

N/A /

End Flow Time

b) Average Dilution Flow*

2000 gpm (appx)

Circulation Water Blowdown Flow, monitor Operable Inoperable Discharge Canal Flow Other dilution water source (specify):

N/A If dilution flow monitor is inop, flow must be estimated at intervals not to exceed every four hours.

N/A / Start N/A / Approx. Middle N/A / End Flow Time

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 4 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT LCO No.: N/A

DATE AND TIME

ELAPSED TIME*

(minutes)

VALVES OPEN VALVES SHUT

Today 0930 Today 1430 300

TOTAL 300 Monitor flushed HC#30114 H. Casey #30114

Initials Operator (Performer)

Asterisked* items above verified D. McCormick

  1. 30435_______________

Operator(Verifier)

__________________

Operations Supervision

Comments:

Par t 6 Post-Release Analysis The post-release analysis is based on actual data recorded during the release

Comments:

/

Radiochemist Date

Facilit y: GG N G R A N D G UL F N U CLEAR Wo r k O rder Package Unit: 1 P rojec t: 0XXXXXX 01 Prio r it y: 4 A W/O Dspln: CHEM Plan n e r: RONEAL O'N EA L R O N A LD W/O Title: 0 6CHSG17-V-0 0 3 4 LIQUID RADW AS T E INOP MONI T OR PRE RELEASE W/O T as k Title: 0 6 C HSG17-V-00 3 4 L IQ U ID RA D W AS T E IN O P MONI T OR PRE RELEASE T as k Dspln: CHE M Complete d B y: Rpt: Date: W/O T ype: Jo b Type: P k g T ype: T I PMC11 XX/XX/20XX W O OD En t e rgy Wor k O r de r T as k W ritte n T o P a g e 1 o f 2 Facilit y: D i vision: Equipm ent: E q ui p Name: GGN Unit: 1 Area: Component:

O p S ys: S ys/C l s: Wo r k Item: Equip.Tag: U T C: Catalo g ID: 06 CH S G 17-V-0034 G P R O Eqt. List: Alt: Tbl/Brkdwn: U CR: 6 (P a s t 1 2 m o) Op s Re v ie w Re q d: N C R Co m m R e q d: NO T I F Y W OR K CON T RO L C E N T E R V I A PHON E PRIO R T O STAR T O F W ORK Location: Cost Centr: NSCC2 . A c t i v i t y: PRSS Use r Def: F 5PPNRMSTK P e r cen tage: 100.000000 Ac ct N o: G L GG 1 E q u ip m e n t I n fo rmation Q G roup: Sa f et y Class: Mainte nanc e Rel: Manu f act ur e r: Se r ia l Number: Wor k Orde r T as k Inst ructio n s ***DESCR IPTION*** Mode l Number: 0 6CHSG17-V-0 0 3 4 LIQUID RADW AS T E INOP MONI T OR PRE RELEASE ***DESCR IPTIO N END*** *** W OR K AC T I V IT Y *** CHEM - 0 6-CH-SG17-V-0 0 3 4 *** W O R K A C TIVI T Y E N D *** Re w or k/Appro v al Deficienc y T a g N o: Loc: T a g Remo ved: Rewor k Job: N Commen t s: T as k Req u i reme n ts F A C. GGN GGN REG/REQ ES T. D OSE? R W P V A LUE 1 SR W P C O MM E N T S G E NE R A L R W P D O S E ES TIMA T E: 0.0 01 Q C Req u ir e me nts/Com m e n ts NO Q C REQUIRE M EN T S FOR T HE W ORK O RDER TASK Facilit y: GG N G R A N D G UL F N U CLEAR Wo r k O rder Package Unit: 1 P rojec t: 0XXXXXX 01 Prio r it y: 4 A W/O Dspln: CHEM Plan n e r: RONEAL O'N EA L R O N A LD W/O Title: 0 6CHSG17-V-0 0 3 4 LIQUID RADW AS T E INOP MONI T OR PRE RELEASE W/O T as k Title: 0 6 C HSG17-V-00 3 4 L IQ U ID RA D W AS T E IN O P MONI T OR PRE RELEASE T as k Dspln: CHE M Complete d B y: Rpt: Date: W/O T ype: Jo b Type: P k g T ype: T I PMC11 XX/XX/20XX W O OD En t e rgy Refe rence s/Doc u me n t Info rmation P a g e 2 o f 2 T ype/Subt y pe: PRO Number: 06C H S G 17-V-0034 Sh eet: 0 Title/Desc: 213 7 S T O R A G E L O C A T I O N: 12051 0 090 Image: T ype/Subt y pe: W O Number: W O-003129 7 5 Sh eet: Title/Desc: 0 6CHSG17-V-0 0 3 4 LIQUID RADW AS T E INOP MONI T OR PRE RELEASE A u t h o r i zation Image: Early Start D at e: 20XX-XX-XX Ea r l y Finis h Date: 20XX-XX-XX La t e S t a r t Date: Lat e Fi n is h D ate: Majo r Failu r e/Actio n T aken Majo r Failu r e: Actio n Taken: Deficienc y T a g L oc: Deficienc y T a g No.: C o m p l e t i o n C ommen t s o n W o r k P er f ormed Commen t s Date By T y pe Date B a t c h 20XX192. S a t. L C O 1-T S-XX-0073 20XX-XX-XX KW I LSON 20XX-XX-XX Remo v e d (Y/N):

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE X QA RECORD 06-CH-SG17-V-0034 Revision: 106 RT = B6.61 NON-QA RECORD Attachment I Page 1 of 2 INITIALS NUMBER OF PAGESl DATE Page RELATED DOCUMENT

RTYPE B6.61 NUMBER =

Ref SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Radwaste Release Inop Radwaste Monitor Pre-Release Analysis Technical Specification:

SR 6.11.1.1 for Function 6.11.1

-1.A, Table 6.11.1

-1 Notes c & d, LCO 6.3.9 Condition B

1.0 IMPACT

STATEMENT

1.1 Performance

of this procedure has no impact on plant operation.

2.0 PROC EDURE 2.1 Plant Mode is (circle one): 1 2 3 4 5

2.2 Permission

to begin the test Not Applicable

Shift Supervisor/Date

2.3 Performed

for LCO #

1-TS-XX-073 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category)

Entire procedure completed [ ] Partial procedure completed [ ]

Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable [ ]

All other steps/data Acceptable [

] Unacceptable [ ]

3.2 TCNs in effect during performance (list):

none

3.3 Comments

Batch 20XX192

3.4 Test performed by M. Wildfire

Date/Time Today / 0500 4.0 DEFICIENCIES CR Issued #

LCO Entered #

WR Issued #

5.0 APPROVAL

Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]

Shift Supv/Mgr

Date Comments:

CONCURRENCE Chemistry Manager

Date GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE X QA RECORD 06-CH-SG17-V-0034 Revision: 106 RT = B6.61 NON-QA RECORD Attachment I Page 2 of 2 INITIALS NUMBER OF PAGESl DATE Page RELATED DOCUMENT

RTYPE B6.61 NUMBER =

Ref DATA SHEET I RADWASTE RELEASE INOP RADWASTE MONITOR PRE

-RELEASE ANALYSIS SAFETY RELATED INITIALS $ 5.2 Tank minimum recirculation of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> met MW 5.3.1.b(1)

Sample contains Resin and Chemistry Management Notified MW 5.3.1.b(2)

Sample does not contain Resin N/A $ 5.4.2 First Sample all significant peaks identified MW $ 5.5.2 Second Sample all significant peaks identified MW $ 5.6.1 ODCM dose limits are not exceeded.

MW 5.6.2 Whole Body Dose Current Admin. Limit Limit Exceeded Chemistry Supervision Notified Tank Will Be Reprocessed Decision To Discharge Documented Initials 2.43E3 mrem 1.0E-2 mrem Yes/No Yes/NA Yes/No/NA Yes/NA MW Highest Organ Dose Current Admin. Limit Limit Exceeded Chemistry Supervision Notified Tank Will Be Reprocessed Decision To Discharge Documented Initials 4.19E-3 mrem 3.3E-2 mrem Yes/No Yes/NA Yes/No/NA Yes/NA MW $ 5.8 Composite Sample Saved MW 5.10.3 Unused Permit Record #

N/A Deleted MW Comments :

Batch 20XX192, no limits exceeded _ ____LCO 1-TS-XX-0073 _____________________________________

___________________________________________________________________

___________________________________________________________________

Reviewed :

Micheal Wildfire Date: Today RETDAS v3.5.0 <GGN> CANBERRA Page - 1 Date/Time:

xx/xx/20xx xx:xx seekeriD: Retdas LIQUID PRE-RELEASE PERMIT REPORT Permit Number: 20xx192 Release ID: 1 SAMPLE TANKS Release Mode: 2 Batch Status: P Pre-Release Comments: FDST-A for Discharge (V-34 1st sample) === RELEASE DATA ======================================================

Estimated tank volume to be released (gal)....................

.28560 Average dilution flow available (gpm).........................

.2500 Allocation percentag e.........................................

.100 Dilution flow assigned to permit (gpm)........................

.2500 === NUCLIDE DATA ======================================================

Nuclide ZN-65 Undiluted uCi/ml lO*EC Percent of lO*EC 4.28E-01 w C0-60 RB-88 SB-125 5.71E-07 2.14E-07 7.85E-07 1.79E-07 3.00E-05 5.00E-05 4.00E-03 3.00E-04 1.90E+OO 1.96E-02 5.97E-02 LA-140 6.04E-08 9.00E-05 6.71E-02 --------- -------- Gamma 1.81E-06 H-3 4.67E-03 1.OOE-02 4.67E+Ol FE-55 2.17E-06 1.OOE-03 2.17E-01 --------- -------- Beta 4.67E-03 --------- -------- Total 4.67E-03 Diluted D&EG Concentration:

O.OOE+OO D&EG Concentration Limit Not Exceeded RETDAS v3.5.0 <GGN> CANBERRA Page - 2 Date/Time:

xx/xx/20xx xx:xx seekeriD: Retdas LIQUID PRE-RELEASE PERMIT REPORT Permit Number: 20XX192 === RELEASE CALCULATIONS

==================================

Minimum dilution facto r.......................................

.9.88E-01 Min. dilution flowrate setpoint(Circ Water Blowdown Flow)(gpm).2.25E+03 Maximum tank discharge flowrate setpoint(Effluent Flow)(gpm)...1.00E+02 === SETPOINT DATA ===================================================== Entered background (cpm)......................................

.0.OOE+OO Alarm Setpoint (cpm)..........................................

.NA Trip Setpoint (cpm)...........................................

.NA --- I&C SE TPOINT VOLTAGES ============================================= Minimum blowdown flow trip voltage setpoint (vdc)............

.1.720E+OO Desired blowdown flow trip voltage setpoint (vdc).............

1.729E+OO Maximum blowdown flow trip voltage setpoint (vdc).............

1.737E+OO Minimum tank effluent flow trip voltage setpoint (vdc)........4.950E+OO Desired tank effluent flow trip voltage setpoint (vdc)........4.975E+OO Maximum tank effluent flow trip voltage setpoint (vdc)........5.OOOE+OO Minimum radiation monitor alarm voltage setpoint (vdc)........O.OOOE+OO Desired radiation monitor alarm voltage setpoint (vdc)........0.OOOE+OO Maximum radiation monitor alarm voltage setpoint (vdc)........O.OOOE+OO Minimum radiation monitor trip voltage setpoint (vdc).........O.OOOE+OO Desired radiation monitor trip voltage setpoint (vdc).........O.OOOE+OO Maximum radiation monitor trip voltage setpoint (vdc).........O.OOOE+OO === PERMIT INSTRUCTIONS

===================================

RETDAS v3.5.0 <GGN> CANBERRA Page - 3 Date/Time:

xx/xx/20xx xx:xx seekeriD: Retdas Q3 - Admin. Any Organ ADULT LIVER 3.38E-02 3.75E+OO 9.01E-01 Q3 - Admin. Total Body ADULT 1.56E-02 1.13E+OO 1.39E+00 Q3 - TS Any Organ ADULT LIVER 3.38E-02 S.OOE+OO 6.76E-01 LIQUID PRE-RELEASE PERMIT REPORT Permit Number: 20XX192 === PERMIT DOSE BY ORGAN AND AGE GROUP (mrem) ===============================*===

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 5.85E-04 1.66E-03 9.66E-05 1.06E-03 1.47E-04 1.34E-03 O.OOE+OO 8.11E-04 === PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) =============

QUARTER 3 ==========

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 1.11E-02 3.38E-02 8.08E-04 2.19E-02 1.30E-03 2.54E-02 O.OOE+OO 1.56E-02 === SITE DOSE LIMIT ANALYSIS ===================================================

Period-Limit Age Group Organ Dose (mrem) Limit (mrem) Max % of Limit Critical Pathway: Fresh Water Fish - Comm. (FFCM) Q3 - TS Total Body ADULT 1.5 6E-02 1.50E+OO 1.04E+OO Critical Pathway: Fresh Water Fish - Comm. (FFCM) === PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) =================

2012 ===========

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 2.72E-01 5.74E-01 6.62E-03 3.05E-01 3.38E-02 2.77E-01 O.OOE+OO 3.07E-01 === SITE DOSE LIMIT ANALYSIS ===================================================

Period-Limit Age Group Organ Dose (mrem) Limit (mrem) Max % of Limit 2012 - Admin. Any Organ ADULT LIVER 5.74E-01 7.50E+OO 7.65E+OO 2012 - Admin. Total Body ADULT 3.07E-01 2.25E+OO 1.36E+01 2012 - TS Any Organ ADULT LIVER 5.74E-01 1.00E+01 5.74E+OO Critical Pathway: Fresh Water Fish - Comm. (FFCM) 2012 - TS Total Body ADULT 3.07E-01 3.00E+OO 1.02E+01 Critical Pathway: Fresh Water Fish - Comm. (FFCM)

Analyzed: xx/xx/xx xx:xx:xx by mwildfire *******************************************************************************

SEEKER G A M M A A N A L Y S I S R E S U L T S PS Version 1.8.5 Entergy, Inc Grand Gulf Nuclear Station *******************************************************************************

Page 1 SAMPLE TANKS Liquid Sample Analysis Sample ID: FDST-A for Discharge (V-34 1st sample) Sampling Start: Sampling Stop: Buildup Time. Sample Size . Collection Efficiency 09/04/12 05:55:00 09/04/12 05:55:00 O.OOE+OOO Hrs . l.OOE+003 ml 1.0000 Counting Start: Decay Time. Live Time Real Time . Spc. File . 09/04/12 06:08:30 2.25E-001 Hrs 1800 Sec 1801 Sec .20120904014.SPC Energy(keV)=

0.50 + FWHM(keV) 0.61 + Detector #: 4 (Detector 4) O.SOO*Ch + 7.61E-08*ChA2 + O.OOE+OO*ChA3 09/04/12 O.Oll*En + 6.03E-04*EnA2 + 0.00E+00*EnA3 11/17/05 Where En= Sqrt(Energy in keV) Search Sensitivity:

1.00 I Sigma Multiplier:

1.00 I Search Start/End:

0/4095 PEAK SEARCH RESULTS PK. ENERGY ADDRESS NET/MDA UN- C.L. BKG FWHM # (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG 1 112.37 223.92 10 10 16 40 0.47 NET< CL 2 175.90 351.08 47 13 19 53 1.28 Wide Pk 3 427.79 855.19 45 11 15 33 0.96 4 463.41 926.48 25 9 13 22 0.93 5 486.72 973.13 20 8 11 20 1.17 6 661.64 1323.14 13 9 13 28 0.58 NET< CL 7 897.79 1795.61 17 9 14 28 0.69 8 1115.39 2230.92 39 8 9 12 1.83 9 1173.28 2346.71 209 15 8 9 1.46 10 1332.58 2665.33 167 14 7 8 1.46 Page 2 Analyzed: xx/xx/xx xx:xx:xx by mwildfire *******************************************************************************

SEEKER L I B R A R Y S E A R C H R E S U L T S Version 2.3.1 Entergy, Inc Grand Gulf Nuclear Station *******************************************************************************

Library File:. .LRWLIB.LIB (LRW Library) Library Match Resolution.

Minimum Score . 1.2S I Decay Limit (Halflives)

......8.0 0.S 0 I Decay Correction.

. . . . . . . . . ON ===============================================================================

LIBRARY SEARCH RESULTS Pk. Energy Net Expected Peaks % Abn. No. (keV) Counts Nuclide Net Counts Found Found SCORE FLAG -------------------------------------------------------------------------------

2 17S.90 47 SB-12S 21 3 of s 60.79 1.11 3 427.79 4S SB-12S 94 3 of s 60.79 1.11 4 463.41 2S ----- SPLIT 11 463.41 16 SB-12S 16 3 of s 60.79 1.11 AutoAdd 12 463.41 9 -GS 1 3 8 1 of 3 22.44 0.72 AutoAdd s 486.72 20 LA-140 1 of s 31.0S 0.81 7 897.79 17 RB-88 1 of 2 39.62 0.90 8 111S.39 39 ZN-6S 1 of 2 100.00 1.00 NI-6S 1 of 2 38.69 0.39 9 1173.28 209 C0-60 186 2 of 2 100.00 1.so 10 1332.S8 167 C0-60 187 2 of 2 100.00 1.so Page 3 Analyzed: xx/xx/xx xx:xx:xx by mwildfire 1173.23 1332.51 CS-138 462.70 XE-133 81.00 NP-239 106.13 CE-144 133.53 M0-99 140.51 TC-99M 140.51 CE-141 145.45 RE-188 155.03 RA-226 185.99 XE-133M 233.20 XE-135 249.79 CR-51 320.07 I-131 364.48 ZN-69M 438.63 ******************************************************************************* SEEKER F I N A L A C T I V I T Y R E P 0 R T Version 2.3.1 Entergy, Inc Grand Gulf Nuclear Station ******************************************************************************* SAMPLE TANKS Liquid Sample Analysis Sample ID: FDST-A for Discharge (V-34 1st sample) Sampling Start: 09/04/12 05:55:00 I Counting Start: 09/04/12 06:08:30 Sampling Stop: 09/04/12 05:55:00 I Decay Time. 2.25e-001 Hrs Buildup Time. . Sample Size . . 0.OOe+OOO Hrs . ..1.00e+003 ml I I Live Time . . Real Time . . 1800 Sec 1801 Sec Collection Efficiency

. . . . 1.0000 I Spectrum File .20120904014.SPC Cr. Level Confidence Interval: 95 % I Det. Limit Confidence Interval: 95 % Detector #: 4 (Detector 4) Efficiency File: 1LMBS004.EFF (1 Liter Marinelli Det 4) Eff=l0A[-5.36E+01 +6.72E+Ol*L

+-2.87E+Ol*LA2

+4.04E+00*LA3]

Eff.= EXP[9.73E-01 + -8.82E-01

  • En+ O.OOE+OO
  • EnA2] Above Coinc. Sum File: ....1LMBS004.CSF (lLMB DET #4 CSF File) 07/21/11 290.00 keV Library File: ......LRWLIB.LIB LSF File: ........LRWLLD.LSF (LRW Library) (LRWLLD) MEASURED or MDA CONCENTRATIONS N L ENERGY E Concentration Critical Hal f life L % Nuclide (keV) T (uCi/ml MDA Level (hrs) D ECL -------------------------------------------------------------------------------

SB-125 427.95 1.79E-07 +- 4.44E-08 1.27E-07 5.82E-08 2.43E+04 0.06 176.29 I.D. . . . . 2.43E+04 463.51 I.D. . . . . . 2.43E+04 LA-140 487.03 6.04E-08 +- 2.56E-08 7.96E-08 3.56E-08 3.07E+02 0.07 RB-88 898.03 7.85E-07 +- 4.28E-07 1.39E-06 6.32E-07 2.97E-01 ZN-65 1115.50 2.14E-07 +- 4.43E-08 1.08E-07 4.64E-08 5.85E+03 0.43 C0-60 Average:x 5.71E-07 +- 3.llE-08 4.62E+04 1.90 6.04E-07 +- 4.38E-08 5.14E-08 2.18E-08 4.62E+04 5.38E-07 +- 4.40E-08 5.48E-08 2.30E-08 4.62E+04 . I.D. . 5.37E-01 MDA 6.70E-08 3.04E-08 1.27E+02 MDA 8.08E-08 3.68E-08 5.65E+Ol MDA 1.61E-07 7.34E-08 6.82E+03 MDA 1.99E-08 9.14E-09 6.62E+Ol MDA 2.03E-08 9.30E-09 6.62E+Ol MDA 3.13E-08 1.41E-08 7.77E+02 MDA 1.14E-07 5.17E-08 1.70E+Ol MDA 5.22E-07 2.36E-07 1.40E+07 MDA 2.24E-07 1.02E-07 5.42E+01 MDA 2.45E-08 1.11E-08 9.08E+OO MDA 2.llE-07 9.26E-08 6.65E+02 MDA 3.18E-08 1.42E-08 1.93E+02 MDA 3.42E-08 1.53E-08 1.38E+Ol Page 4 Analyzed: xx/xx/xx xx:xx:xx by mwildfire ===============================================================================

MEASURED or MDA CONCENTRATIONS

===================================================================

N L ENERGY E Concentration Critical Halflife L % Nuclide (keV) T (uCi/ml MDA Level (hrs) D ECL W-187 479.57 MDA 1.09E-07 4.70E-08 2.39E+01 RU-103 497.08 MDA 3.49E-08 1.54E-08 9.44E+02 I-133 529.50 MDA 2.67E-08 1.11E-08 2.03E+01 BA-140 537.38 MDA 1.07E-07 4.35E-08 3.07E+02 AS-76 559.10 MDA 7.51E-08 3.29E-08 2.63E+01 CS-137 661.62 MDA 4.95E-08 2.20E-08 2.64E+OS ZR-95 724.18 MDA 6.78E-08 2.81E-08 1.55E+03 NB-95 765.82 MDA 3.49E-08 1.47E-08 8.44E+02 CS-134 795.76 MDA 5.22E-08 2.26E-08 1.81E+04 C0-58 810.75 MDA 4.70E-08 2.07E-08 1.70E+03 CS-136 818.50 MDA 4.43E-08 1.93E-08 3.12E+02 MN-54 834.81 MDA 4.93E-08 2.18E-08 7.49E+03 MN-56 846.60 MDA S.OSE-08 2.19E-08 2.58E+OO SC-46 889.26 MDA 5.22E-08 2.30E-08 2.01E+03 AG-llOM 937.48 MDA 1.52E-07 6.65E-08 6.00E+03 I-135 1260.41 MDA 1.44E-07 5.66E-08 6.61E+OO FE-59 1291.56 MDA 7.12E-08 2.57E-08 1.08E+03 NA-24 1368.55 MDA 2.39E-08 7.38E-09 1.50E+01 SR-92 1383.90 MDA 4.82E-08 1.84E-08 2.71E+OO SB-124 1691.04 MDA 7.74E-08 2.79E-08 1.44E+03 MEASURED TOTAL: 1.81E-06 +- 5.73E-07 uCi/ml 2.46E+OO ===============================================================================

UNKNOWN,SUM or ESCAPE PEAKS ===============================================================================

PK. ENERGY ADDRESS NET UN- C.L. BKG FWHM # (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG 1 112.37 223.92 10 10 16 40 0.47 Deleted 4 463.41 926.48 25 9 13 22 0.93 SPLIT 6 661.64 1323.14 13 9 13 28 0.58 Deleted ===============================================================================

NET/MDA PEAK RESULTS PK. # ENERGY (keV) ADDRESS CHANNEL NET/MDA COUNTS UN- CERTAINTY C.L. COUNTS BKG COUNTS FWHM (keV) FLAG 13 81.00 161.14 29 0 13 36 0.76 14 106.13 211.44 30 0 14 38 0.79 15 133.53 266.28 31 0 14 41 0.82 16 140.51 280.25 32 0 15 44 0.83 17 140.51 280.25 32 0 15 44 0.83 18 145.45 290.14 27 0 12 29 0.84 19 155.03 309.31 29 0 13 36 0.85 20 185.99 371.28 28 0 13 32 0.88 21 233.20 465.77 32 0 15 39 0.93 22 249.79 498.97 28 0 13 30 0.94 23 320.07 639.62 22 0 10 18 1.01 Page 5 Analyzed: xx/xx/xx xx:xx:xx by mwildfire ===============================================================================

NET/MDA PEAK RESULTS ===============================================================================

PK. ENERGY ADDRESS NET/MDA UN- C.L. BKG FWHM # (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG -------------------------------------------------------------------------------

24 364.48 728.50 25 0 11 23 1.05 25 438.63 876.89 26 0 12 23 1.11 26 479.57 958.82 19 0 8 12 1.15 27 497.08 993.85 22 0 10 16 1.17 28 529.50 1058.73 16 0 7 9 1.19 29 537.38 1074.50 15 0 6 7 1.20 30 559.10 1117.96 22 0 10 18 1.22 31 661.62 1323.10 24 0 11 21 1.30 32 724.18 1448.27 16 0 7 8 1.35 33 765.82 1531.58 17 0 7 10 1.39 34 795.76 1591.49 20 0 9 14 1.41 35 810.75 1621.48 22 0 10 17 1.42 36 818.50 1636.98 21 0 9 15 1.43 37 834.81 1669.61 23 0 10 18 1.44 38 846.60 1693.20 20 0 9 14 1.45 39 889.26 1778.55 23 0 10 18 1.49 40 937.48 1875.02 22 0 10 18 1.52 41 1260.41 2520.99 13 0 5 4 1.77 42 1291.56 2583.29 10 0 4 2 1.80 43 1368.55 2737.28 7 0 2 1 1.86 44 1383.90 2767.98 11 0 4 4 1.87 45 1691.04 3382.20 10 0 3 2 2.10 Page 006 , . Analyzed: xx/xx/xx xx:xx:xx by mwildfire ===============================================================================

R E T D A S A N A L Y S I S v2.4.0 ===============================================================================

SAMPLE TANKS Liquid Sample Analysis Nuclide uCi/ml +- uCi/ml Transfer? ========================================================================

SB-125 1.79e-07 4.44e-08 YES LA-140 6.04e-08 2.56e-08 YES RB-88 7.85e-07 4.28e-07 YES ZN-65 2.14e-07 4.43e-08 YES C0-60 5.71e-07 3.11e-08 YES TOTAL: 1.81e-06 F il e: 1 Sequen c e: 99999 F ilena m e: 00xxxxxx-01.pdf I nc lude d i n repo r t. EN D O F F I L E A T T A CH MENTS Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S5 JPM Title: Emergency Event Classification Facility Number:

_______ N/A ___

(If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical 15 min Alternate Path Validation Time: 10 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ben Nadolny 9/15/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 2 of 7 Emergency Event Classification Setting: Classroom Type: SRO Task: SRO-A&E-015 K&A: 2.4.41 - 2.9/4.6 Safety Function
Emergency Procedures/Plan Performance
Actual Reference(s)
10-S-01-1 Handout(s)
EAL flow charts from 10

-S-01-1 10-S-01-1 (available)

  1. Manipulations
N/A # Critical Steps
1 Simulator Setup/Required Plant Conditions
None Safety Concerns
None Task Standard(s)
Within 15 minutes, classifies the event as
for SCENARIO #1 a SITE AREA EMERGENCY per EAL SS3 Date of Examination: 12/07/2015 Operating Test Number
LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

Based on the scenario you just participated in:

Scenario #1

- ATWS >4% power Feedwater line break in Drywell Initiating Cue(s):

Classify the event.

This JPM is time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 4 of 7 Emergency Event Classification Notes: (Notes to Evaluator)

Only the initial conditions for the specific scenario performed by the student as CRS is to be given to the student.

Task Overview:

(Detailed description of task)

An event classification JPM is required of all licensed SROs not qualified as an Emergency Director in accordance with the Emergency Preparedness Plan.

Tasks: Critical steps are underlined, italicized, and denoted by an (*)

Step 1: 10-S-01-1

  • For Scenario #1 Classify the event as a SITE AREA EMERGENCY Standard: For Scenario #1: EAL SS3 (SITE AREA EMERGENCY)

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 5 of 7 Task Standard(s)
Within 15 minutes, classifies the event as:

for SCENARIO #1 a SITE AREA EMERGENCY per EAL SS3 SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AS5 JPM Title: Emergency Event Classification Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

Give this page to the student

Initial Condition(s):

Based on the scenario you just participated in:

Scenario #1

- ATWS >4% power Feedwater line break in Drywell Initiating Cue(s):

Classify the event.

This JPM is time critical.

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 12/7/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 2015 Control Room Systems

-I; 2 or 3 for SRO

-U System / JPM Title Type Code*

Safety Function a. 202001 A4.02 (3.5/3.4) Reset Recirc FCV Runback GJPM-OPS-201 5 S 1 A - D - S 1 b. 259001 A3.10 (3.4/3.4), Defeat Feed Pump Level 9 Trips GJPM-OPS-2015CR2 D - C - L 2 c. 239001 A2.11 (4.1/4.3), Slow Closing MSIV GJPM-OPS-2015 S 3 A - N - S 3 d. 209002 A1.01 (3.6/3.7), Performing HPCS Quarterly Functional Test, GJPM

-OPS-S 4 A - D - EN - S 4 e. 223001 A4.06 (4.0/4.0), Containment Venting GJPM-OPS-2015CR5 C - D - E - L 5 f. 212000 A4.02 (3.6/3.7), Reactor Manual Scram Switch Test, GJPM-OPS-2015 S 7 A - D - S 7 g. 400000 A4.01 (3.1/3.0), Manual Start of SSW 'A' System , GJPM-OPS-2015 S 8 A - M - S 8 h. 272000 A4.02 (3.0/3.0), Perform Area Radiation Monitor Functional Test, GJPM

-OPS-2015 s 9 D - S 9 In-Plant Systems

-I); (3 or 2 for SRO

-U) i. 262001 A2.11 (3.2/3.6), Reset Undervoltage Lockouts on BOP Buses, GJPM

-OPS-2015PS-6 D - R - L 6 j. 295016 A1.07 (4.2/4.3), Perform Attachment III of Shutdown From Remote Shutdown panel ONEP, GJPM

- OPS-2015PS-7 D - E - EN - L 7 k. 2.1.30: (4.4/4.0), Manually Initiate Fire Protection to the 'B' RPS Motor Generator Room, GJPM

-OPS-2015PS8 A - E - N 8

-I control room (and in

-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in

-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 /

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 12/7/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 2015 Control Room Systems

-I; 2 or 3 for SRO

-U System / JPM Title Type Code*

Safety Function a. 202001 A4.02 (3.5/3.4) Reset Recirc FCV Runback GJPM-OPS-201 5 S 1 A - D - S 1 b. 259001 A3.10 (3.4/3.4), Defeat Feed Pump Level 9 Trips GJPM-OPS-2015CR2 D - C - L 2 c. 239001 A2.11 (4.1/4.3), Slow Closing MSIV GJPM-OPS-2015 S 3 A - N - S 3 d. 209002 A1.01 (3.6/3.7), Performing HPCS Quarterly Functional Test, GJPM

-OPS-S 4 A - D - EN - S 4 e. 223001 A4.06 (4.0/4.0), Containment Venting GJPM-OPS-2015CR5 C - D - E - L 5 f. 212000 A4.02 (3.6/3.7), Reactor Manual Scram Switch Test, GJPM-OPS-2015 S 7 A - D - S 7 g. 400000 A4.01 (3.1/3.0), Manual Start of SSW 'A' System , GJPM-OPS-2015 S 8 A - M - S 8 In-Plant Systems* (3 for RO); (3 for SRO

-I); (3 or 2 for SRO

-U) i. 262001 A2.11 (3.2/3.6), Reset Undervoltage Lockouts on BOP Buses, GJPM

-OPS-2015PS-6 D - R - L 6 j. 295016 A1.07 (4.2/4.3), Perform Attachment III of Shutdown From Remote Shutdown panel ONEP, GJ PM- OPS-2015PS-7 D - E - EN - L 7 k. 2.1.30: (4.4/4.0), Manually Initiate Fire Protection to the 'B' RPS Motor Generator Room, GJPM

-OPS-2015PS8 A - E - N 8

-I control room (and in

-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in

-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 /

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 12/7/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT-2015 Control Room Systems

-I; 2 or 3 for SRO

-U System / JPM Title Type Code*

Safety Function a. 202001 A4.02 (3.5/3.4) Reset Recirc FCV Runback GJPM-OPS-201 5 S 1 A - D - S 1 b. 239001 A2.11 (4.1/4.3), Slow Closing MSIV GJPM-OPS-2015 S 3 A - N - S 3 c. 212000 A4.02 (3.6/3.7), Reactor Manual Scram Switch Test, GJPM-OPS-2015 S 7 A - D - S 7 In-Plant Systems

-I); (3 or 2 for SRO

-U) d. 262001 A2.11 (3.2/3.6), Reset Undervoltage Lockouts on BOP Buses, GJPM

-OPS-2015PS1 D - R - L 6 e. 2.1.30: (4.4/4.0), Manually Initiate Fire Protection to the 'B' RPS Motor Generator Room, GJPM

-OPS-2015PS8 A - E - N 8

-I control room (and in

-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in

-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 /

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 1 of 12 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 1 JPM Title: Reset Recirc FCV Runback Facility Number: __GJPM-OPS-B3313____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min Prepared By:

Exam Developer Date Ops Review: 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

2 nd Validation by Ops Validation Crew Date Approved By:

Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 2 of 12 Reset Recirc FCV Runback Time Critical Alternate Path Validation Time:

30 Min Setting: Simulator Type: RO Task: CRO-B33(2)-8; CRO-B33(2)-1 K&A: 202001 A4.02 (3.5/3.4) 202002 A4.08 (3.3/3.3)

Safety Function:

1 - Reactivity Control Performance:

Actual Reference(s):

04-1-01-B33-1, Rev 150 Handout(s) 04-1-01-B33-1, Section 6.6

  1. Manipulations:

5 # Critical Steps:

5 Simulator Setup/Required Plant Conditions

Reset Simulator to IC

-104 Run Schedule file 2015 NRC JPM MASTER OR Reset to any full power IC.

Manually trip B RFP.

Reset tripped RFP IAW 6.6.61.a Prerequisite.

Allow Recirc FCV runback to occur and conditions to steady out.

Assign trigger 1 to trigger file fcvb_cav_pb Insert malfunction rr173b at 3 to activate on event trigger 1 Override annunciator P680

-4A1-C4, RECIRC FCV B PARTIAL CLOSE/RFP TRIP to ON so that it will not clear.

Safety Concerns

None. Task Standard
Actions have been taken to reset Recirc FCV runback and to stop Recirc FCV B from opening in response to the Recirc Flow Control Valve malfunction.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 3 of 12 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant was operating at full power when B Reactor Feed Pump tripped.

A Recirc FCV runback occurred.

Power and core flow show entry into the OPRM Trip Enabled Region.

Reactor Engineering is assessing power distribution, FCBB and thermal limits Another reactor operator has the THI watch.

The 'B' RFPT tip has been resolved and 'B' RFPT has been reset.

Initiating Cue(s):

The CRS directs you to reset the Recirc FCV A and B Runback in accordance with section 6.6 0f SOI 04 01-B33-1.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 4 of 12 Reset Recirc FCV Runback Notes: (Notes to Evaluator)

All controls will be from panel P680 in the Main Control Room.

Task Overview:

(Detailed description of task)

This task resets a Recirc FCV runback following a trip of B RFP. When the operator depresses the RECIRC PMP B CAV INTLK RESET pushbutton, Recirc FCV B will ramp open from a malfunction. The operator must notice and report uncontrolled FCV opening and attempt to stop it. The CRS will direct shutdown of HPU B. The operator will take action to shutdown HPU B, shutdown the B Recirc Pump or shut the B33

-F067B from P680 which will terminate the power excursion. In the event the operator elects to perform all steps for FCV B first, all steps associated with FCV A become not applicable, and the JPM may be ended when the HPU for FCV B has been shut down

.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 5 of 12 Reset Recirc FCV Runback Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: 04-1-01-B33-1, Step 6.6.1 a Reactor vessel level is greater than low level alarm setpoint AND/OR Both Feed pumps are reset.

Standard: Checks vessel level is > 32" Narrow Range.

Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 6 of 12 Step 2: 04-1-01-B33-1, Step 6.6.2 a
  • USING Recirc Loop A(B) FLO CONT, LOWER signal output until one of the following occurs: (1) % Limiter Error is zero; OR (2) % Servo Error is zero; OR (3) FCV motion is noticed in the CLOSE direction; OR (4) A reduction in associated loop flow is noticed.

Standard: Lowers Recirc Loop A(B) Flo Cont until one of the listed items is satisfied

. Cue: If student uses slow detent, cue the candidate that fast detent may be used as desired.

Notes: SAT / UNSAT Step 3: 04-1-01-B33-1, Step 6.6.2 b

  • PRESS RECIRC PUMP A(B) CAV INTLK RESET pushbutton.

Standard: Depresses the Recirc pump A(B) Cav. Interlock Reset pushbutton on P680.

Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 7 of 12 Step 4 04-1-01-B33-1, Step 6.6.2 c OBSERVE "RECIRC FCV A(B) PARTIAL CLOSE/RFP TRIP" annunciator Resets.

Standard: Observes "RECIRC FCV A(B) PARTIAL CLOSE/RFP TRIP" annunciator Resets, P680-3A-D1 Cue: None Notes: SAT / UNSAT Step 5 04-1-01-B33-1, Step 6.6.2 a

  • USING Recirc Loop B(A) FLO CONT, LOWER signal output until one of the following occurs: (1) % Limiter Error is zero; OR (2) % Servo Error is zero; OR (3) FCV motion is noticed in the CLOSE direction; OR (4) A reduction in associated loop flow is noticed.

Standard: Lowers Recirc Loop B(A) Flo Cont until one of the listed items is satisfied

. Cue: If student uses slow detent, cue the candidate that fast detent may be used as desired.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 8 of 12 Step 6: 04-1-01-B33-1, Step 6.6.2 b
  • PRESS RECIRC PUMP A(B) CAV INTLK RESET pushbutton.

Standard: Depresses RECIRC PMP B CAV INTL RESET pusbutton.

Cue: None. Notes: Trigger 1 will automatically insert when pushbutton is depressed.

OR After Reset pushbutton is depressed insert "Trigger 1".

SAT / UNSAT Step 7: 04-1-01-B33-1, Step 6.6.2 c OBSERVE "RECIRC FCV B(A) PARTIAL CLOSE/RFP TRIP" annunciator Resets.

Standard: Checks for annunciator P680

-4A1-C4, RECIRC FCV B PARTIAL CLOSE/RFP TRIP resetting but observes it remains in alarm. Observes FCV B opening, servo error, and limiter error changing.

Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 9 of 12 Step 8: 04-1-01-B33-1 Recognizes 'B' FCV is drifting open Standard: Recognizes 'B' FCV is drifting open by observing valve position indicator moving in the open direction.

Cue: If asked for guidance, as CRS direct operator to perform actions to stop valve movement

. Notes: SAT / UNSAT Step 9: 04-1-01-B33-1

  • Trip Recirc Pump B Hydraulic Power Unit to stop valve movement

. Standard: Arms and depresses HPU B SHUTDN pushbutton on P680.

Cue: None Notes: Armed collar pushbutton on P680 section 3C. This action will stop valve movement.

After HPU is shutdown the evaluator may stop the JPM.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 10 of 12 Task Standard(s)
Actions have been taken to reset Recirc FCV runback and to stop Recirc FCV B from opening in response to the Recirc Flow Control Valve malfunction.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 11 of 12 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 1 JPM Title: Reset Recirc FCV Runback Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

The plant was operating at full power when B Reactor Feed Pump tripped.

A Recirc FCV runback occurred.

Power and core flow show entry into the OPRM Trip Enabled Region.

Reactor Engineering is assessing power distribution, FCBB and thermal limits Another reactor operator has the THI watch.

The 'B' RFPT tip has been resolved and 'B' RFPT has been reset.

Initiating Cue(s):

The CRS directs you to reset the Recirc FCV A and B Runback in accordance with section 6.6 0f SOI 04 01-B33-1.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 1 of 9 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015CR2 JPM Title: Defeat Feed Pump Level 9 Trips Facility Number: _GJPM-OPS-EOP006____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min Applicant: ________________________________

Examiner:

_________________________________

Performance Time:

________________________

Performance Rating:

SAT UNSAT Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Benny White 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Comments:

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 2 of 9 Defeat Feed Pump Level 9 Trips Time Critical Alternate Path Validation Time: 15 min Setting: Control Room Type: RO Task: CRO-EP-006 K&A: 259001 A3.10 3.4/3.4 Safety Function:

2 - Reactor Water Inventory Control System Performance:

Simulated Reference(s):

05-S-01-EP-1/Attachment 6 Handout(s) 05-S-01-EP-1 Attachment 6

  1. Manipulations:

6 # Critical Steps:

4 Simulator Setup/Required Plant Conditions

Control Room operating panels and backpanel P612 is accessible, with permission from the Shift Manager to panels for inspection only.

Safety Concerns

Possible electric shock while inspecting interior of panels

- Do not break the plane of any panels (student should use an appropriate indicating device to identify component/connection locations).

Task Standard

The Reactor Feed Pump Level 9 trips are defeated in accordance with 05-S-01-EP-1, Attachment 6 steps 2.1 thru 2.
4.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 3 of 9 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

EOP's have been entered

. Initiating Cue(s):

You have been directed to perform steps 2.1 through 2.

4 of EP Attachment 6.

Another operator will complete the remaining steps of this attachment when directed.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 4 of 9 Defeat Feed Pump Level 9 Trips Notes: (Notes to Evaluator)

RFPT reset controls and indications are on P680.

Panel P612 is in the Main Control Room Task Overview:

(Detailed description of task)

This task defeats the High Reactor Water Level trip of the Reactor Feed Pumps, which under certain conditions is directed by the EOPs to maintain adequate core cooling.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 5 of 9 Critical tasks are underlined, italicized, and denoted by an (*)

Sequence for the following steps is not critical unless otherwise denoted

. Step 1: 05 02-I-1 OBTAIN EOP Attachment 6 from Control Room emergency locker.

Standard: Locates Control Room Emergency Locker Locates Attachment No. 6 Cue: None Notes: Once candidate has located the emergency locker and the correct Attachment, give the paper copy of Attachment 6.

SAT / UNSAT Step 2: 05-S-01-EP-1, Att. 6, 2.1

  • Remove relay C34-K7J. Standard: Locates relay C34

-K7J in panel P612, Bay B, 3rd row from top, 1st relay from left

. Simulates removal by describing unclipping and pulling the relay

. Cue: Relay C34-K7 J is removed

. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 6 of 9 Step 3: 05-S-01-EP-1, Att. 6, 2.2
  • Remove relay C34-K7G Standard: Locates relay C34

-K7G in panel P612, Bay B, 3rd row from top, 2nd relay from left .

Simulates removal by describing unclipping and pulling the relay.

Cue: Relay C34-K7G is removed Notes: SAT / UNSAT Step 4: 05-S-01-EP-1, Att. 6, 2.

3

  • Remove relay C34-K7A Standard: Locates relay C34

-K7A in panel P612, Bay B, 2nd row from top, 1st relay from left

. Simulates removal by describing unclipping and pulling the relay Cue: Relay C34-K7 A removed Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 7 of 9 Step 5: 05-S-01-EP-1, Att. 6, 2.4
  • Remove relay C34

-K7F Standard: Locates relay C34

-K7F in panel P612, Bay B, 3rd row from top, 3rd relay from left

. Simulates removal by describing unclipping and pulling the relay

. Cue: Relay K34-K7F is removed Notes: SAT / UNSAT Task Standard(s)

The Reactor Feed Pump Level 9 trips are defeated in accordance with 05

-S-01-EP-1, Attachment 6 steps 2.1 thru 2.

4. SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 8 of 9 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015CR 2 JPM Title: Defeat Feed Pump Level 9 Trips Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ______________________

______________________________

Examiner's Signature:

____________________________________________________

Give this page to the student

Initial Condition(s):

EOP's have been entered

. Initiating Cue(s):

You have been directed to perform steps 2.1 through 2.

4 of EP Attachment 6.

Another operator will complete the remaining steps of this attachment when directed.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 1 of 10 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5 S 3 JPM Title:

Slow Closing MSIV Facility Number:

N/A (If Bank or Modified from Bank) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time:

15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review: Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Christopher Baxter 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 2 of 10 Slow Closing MSIV Setting: Simulator Type: RO Task: CRO-B21-SU/SD-0 0 1 K&A: 239001: A2.11 (4.1/4.3); A 3.01 (4.2/4.1); A4.01 (4.2/4.0) Safety Function:

3 - Reactor Pressure Control Performance:

Actual Reference(s):

04-1-01-B21-1 Handout(s) 04-1-01-B21-1 (5.4) # Manipulations:

4 # Critical Steps:

4 Simulator Setup/Required Plant Conditions

Reset Simulator to IC

-106 Run schedule file 2015 NRC JPM Master Safety Concerns

None Task Standard
Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Perform actions to ensure a Group 1 MSIV isolation by manually closing all MSIVs.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 3 of 10 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at approximately 50%

power. Initial startup after refueling outage.

MSIV, B21-F028A, was reworked during the outage

. Initiating Cue(s):

The CRS directs you to perform a slow closing of MSIV B21

-F028A, using 04-1-01-B21-1, Nuclear Boiler System SOI, section 5.4

. After MSIV B21

-F028A reaches full closed place handswitch for B21

-F028A to the CLOSE position.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 4 of 10 Slow Closing MSIV Notes: (Notes to Evaluator)

All controls and indications for this task are on panel 1H13

-P 601. Task Overview:

(Detailed description of task)

This task is to perform a slow close on MSIV B21

-F028A. Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Student should manually close all remaining MSIVs (7) using handswitches on P601 panel.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 5 of 10 Critical steps are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-B21-1, Step 5.4.2 a

  • PLACE associated MSIV handswitch on 1H13

-P601 to TEST Standard: Places handswitch for B21

-F028A on 1H13

-P601 to the TEST position.

Cue: None Notes:

SAT / UNSAT Step 2: 04-1-01-B21-1, Step 5.4.2 a

  • DEPRESS MSIV TEST pushbutton. Holding pushbutton slow closes valve fully.

Standard: Depresses and holds the MSIV TEST pushbutton until B21

-F028A indicates full close, indicated by green light on red light off.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 6 of 10 Step 3: 04-1-01-B21-1, Step 5.4.2 b
  • IF desired, WHEN MSIV is fully CLOSED, PLACE MSIV handswitch from TEST to CLOSE, THEN RELEASE pushbutton.

Standard: After B21-F028A reaches the full closed position, places B21

-F028A handswitch to the CLOSE position.

Cue: None Notes: When handswitch is placed in the CLOSE position a steam line break will occur inside the Main Steam Tunnel.

SAT / UNSAT Step 4: EN-OP-120, Att. 9.2 Recognize a Group 1 MSIV isolation signal

. Standard: Recognizes a Group 1 MSIV isolation signal by observing the following alarms: P601-18A(19A)-A3 and A4, MSL PIPE TNL CH A (B,C,D) TEMP HI Cue: None Notes: Operating Fundamental Monitoring

- Verify and report automatic system actuations or response, which includes operator actions if the plant has not responded as expected.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 7 of 10 Step 5: EN-OP-120, Att. 9.2 Recognize Group 1 MSIV isolation did not occur.

Standard: Recognizes all remaining (7) MSIVs are open.

Cue: If operator reports a failure of a Group 1 isolation; respond as the CRS, "I understand failure of Group 1 isolation;" also if asked the ATC will place the Mode Switch to shutdown."

Notes: Student may report EP

-4 entry condition.

Operating Fundamental Monitoring

- Verify and report automatic system actuations or response, which includes operator actions if the plant has not responded as expected.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 8 of 10 Step 6: EN-OP-120, Att. 9.2
  • Place all remaining MSIV handswithes (7) to the CLOSE position.

Standard: Places all remaining MSIV handswit ches (7) to the CLOSE position.

Cue: After all MSIVs (8) MSIVs are in the closed position evaluator can end the JPM and tell the student end of task.

Notes: Operating Fundamental Monitoring

- Verify and report automatic system actuations or response, which includes operator actions if the plant has not responded as expected.

SAT / UNSAT

Task Standard(s)

Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Perform actions to ensure a Group 1 MSIV isolation by manually closing all MSIVs. SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 9 of 10 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 3 JPM Title: Slow Closing MSIV Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Give this page to the student Initial Condition(s):

The plant is at approximately 50%

power. Initial startup after refueling outage.

MSIV, B21-F028A, was reworked during the outage.

Initiating Cue(s):

The CRS directs you to perform a slow closing of MSIV B21

-F028A, using 04 01-B21-1, Nuclear Boiler System SOI, section 5.4.

After MSIV B21

-F028A reaches full closed place handswitch for B21

-F028A to the CLOSE position.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 1 of 13 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 4 JPM Title: Performing HPCS Quarterly Functional Test Facility Number:

N/A (Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ken Haley 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 2 of 13 Performing HPCS Quarterly Functional T est Time Critical Alternate Path Validation Time:

1 0 Min Setting: Simulator Type: RO Task: CRO-E22-008, 010 K&A: 209002: A1.01-3.6/3.7; A4.01

- 3.7/3.7 Safety Function:

4 - Heat Removal from Reactor Core Performance:

Actual Reference(s):

06-OP-1E22-Q-0005, Rev. 1 20 EN-OP-115, Rev.

13 02-S-01-27, Rev 51 Handout(s) 06-OP-1E22-Q-0005 # Manipulations:

5 # Critical Steps:

4 Simulator Setup/Required Plant Conditions

Reset Simulator to IC

-107 Run Schedule File 2015 NRC JPM Master Ensure HPCS MOV test witch in normal. HPCS system OOSVC lit.

Safety Concerns

None Task Standard
The HPCS pump is started for full test return flow, Suppression Pool to Suppression Pool, when both Main Feed Pumps trip and HPCS fails to auto initiate. Student must manually initiate HPCS and open the E22

-F004.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 3 of 13 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

06-OP-1E22-Q-0005, HPCS Quarterly Functional Test, Attachment 1 is in progress at step 5.2.2 t. SSW C is in STANDBY All Prerequisites are met Initiating Cue(s):

The CRS directs you to continue with 06

-OP-1E22-Q-0005, HPCS Quarterly Functional Test, Attachment 1

.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 4 of 13 Performing HPCS Quarterly Functional T est Notes: (Notes to Evaluator)

All controls and indications for this task are on panel 1H13

-P6 01 and P870. Task Overview:

(Detailed description of task)

This task requires the ability to manually start the only ECCS

-qualified high pressure injection system.

This task demonstrates the ability to operate HPCS in the "test return" mode, which puts HPCS flow in a loop from and to the Suppression Pool, one of its two suction sources. HPCS is operated in this mode for surveillance and post

-maintenance testing.

As HPCS is placed in the test return mode the system will experience a fail to initiat e and a fail to inject once manually initiated. This will require to arm and depress the initiation pushbutton and then manually open the E22

-F004.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 5 of 13 Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 t PLACE the SSW DIV 3 MOV TEST switch in the TEST position.

Standard: Places the SSW DIV 3 MOV TEST switch in the TEST position.

Cue: None Notes: SAT / UNSAT Step 2: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 u OBSERVE that "SSW DIV 3 MOVS IN TEST MODE" annunciator, 1H13

-P870-5A-G2, Alarms. Standard: Observes that "SSW DIV 3 MOVS IN TEST MODE" annunciator, 1H13

-P870-5A-G2, Alarms. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 6 of 13 Step 3: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 v OBSERVE that SSW D3 MOV IN TEST STATUS light energizes.

Standard: Observes that SSW D3 MOV IN TEST STATUS light energizes.

Cue: None Notes: SAT / UNSAT Step 4: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 w

  • START HPCS pump using HPCS PUMP handswitch AND VERIFY HPCS pump starts.

Standard: Operator starts the HPCS Pump utilizing its handswitch on P601 and observes pump indicating lights shows a pump start.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 7 of 13 Step 5: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 w VERIFY the following has occurred
(2) F012, HPCS MIN FLO TO SUPP POOL, OPENS as discharge pressure indicated on PI-R601, HPCS PMP DISCH PRESS, increases above 130 psig.

(3) HPCS Room Cooler Fan has started USING indication above HPCS PMP RM CLR T51-B001 handswitch on Panel 1H13

-P870-5C. (4) SSW LOOP C (HPCS SSW) on Panel 1H13

-P870-5C started automatically.

Standard: Operator checks items listed by observing the indications stated. Cue: None Notes: SAT / UNSAT Step 6: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 x OPEN FX019 Standard: Operator request a plant operator to open E22-FX019. Cue: When requested to open E22-FX019, report the valve is open.

Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 8 of 13 Step 7: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 y
  • THROTTLE F023 as necessary to achieve a flow of approximately 7200 gpm (tolerance: >7176 to 7255 gpm) as indicated on HPCS PUMP FLOW indicator 1E22

-FI-R603. Standard: Operator opens E 22-F0 23 to achieve desired flow

. Cue: Upon reactor scram, give scram report, "Mode switch is in Shutdown, Reactor Water Level is

-20" Wide Range and lowering, All rods are in."

Notes: As F0 23 is opening , a trip of both reactor feed pumps will occur. This will result in a failed initiation of HPCS

. The operations contained in the remainder of this JPM are not contained in the HPCS surveillance or SOI. SAT / UNSAT Step 8: 04-1-01-E22-1 The operator recognizes the failed initiation.

Standard: Operator recognizes failed initiation of HPCS by observing system indications on P601 and reports failure to the CRS.

Cue: Act as CRS and acknowledge the operators report.

Notes: Operator may elect to take action to initiate HPCS injection prior to reporting failure to CRS. This is acceptable.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 9 of 13 Step 9: 02-S-01-27, Step 6.6.3 a
  • USING HPCS MAIN INIT pushbutton on 1H13

-P601 by ROTATING collar to the ARMED position AND PUSHING red button

. Standard: Rotates the collar to the ARMED position and pushes the red button

. Cue: None Notes: SAT / UNSAT Step 10:

02-S-01-27, Step 6.6.3 b The operator recognizes the E22

-F004 (HPCS Injection Valve) fails to open. Standard: Operator recognizes failed injection of HPCS by observing system indications on P601 and reports failure to the CRS.

Cue: Act as CRS and acknowledge the operators report.

Notes: Operator may elect to take action to inject HPCS prior to reporting failure to CRS. This is acceptable.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 10 of 13 Step 11:

02-S-01-27, Step 6.6.3 c

  • OPEN E22-F004 (HPCS Injection Valve)

. Standard: Opens the E22-F004 using its handswitch on P601 and observing its red light is o n and its green light is o ff. Cue: None Notes: Once the E22F004 is opened the evaluator may stop the JPM.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 11 of 13 Task Standard(s)
The HPCS pump is started for full test return flow, Suppression Pool to Suppression Pool, when both Main Feed Pumps trip and HPCS fails to auto initiate. Student must manually initiate HPCS and open the E22

-F004. SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 12 of 13 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 4 JPM Title: Performing HPCS Quarterly Functional Test Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Give this page to the student

Initial Condition(s):

06-OP-1E22-Q-0005, HPCS Quarterly Functional Test, Attachment 1 is in progress at step 5.2.2 t.

SSW C is in STANDBY All Prerequisites are met Initiating Cue(s):

The CRS directs you to continue with 06

-OP-1E22-Q-0005, HPCS Quarterly Functional Test, Attachment 1.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 1 of 10 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015CR5 JPM Title:

EP-1 Attachment 14

- Containment Venting Facility Number:

GJPM-OPS-EOP14 (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By: Mike Starnes 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 2 of 10 EP-1 Attachment 14

- Containment Venting Time Critical Alternate Path Validation Time:

30 Min Setting: Control Room Type: RO Task: CRO-EP-014 VENT CONTAINMENT (EP

-1 Attachment 14)

K&A: 295024 EA1.18 [3.6/3.6]

Safety Function

2 Performance
Simulated Reference(s)
05-S-01-EP-1, Attachment 14 Handout(s)
05-S-01-EP-1, Attachment 14
  1. Manipulations
5 # Critical Steps
5 Simulator Setup/Required Plant Conditions
None Safety Concerns
None. Task Standard
Actions have been taken to vent containment

.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 3 of 10 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

EP 2 and 3 have been entered.

Reactor level is being maintained between +

50 to -30 inches.

Reactor pressure is being maintained between 800 to 10 60 psig with SRVs.

Drywell pressure is below 1.0 psig.

No Containment or Secondary Containment Isolation signal is present for M41 and E61 valves. The emergency director has been notified that an unfiltered release will occur during venting of the containment.

Initiating Cue(s):

You have been directed to perform containment venting per EP

-1 Attachment 14 steps 2.2 through 2.6.

This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 4 of 10 EP-1 Attachment 14

- Containment Venting Notes: (Notes to Evaluator)

1. This task is performed from the control room to vent the primary containment via 6

-inch ventilation lines with no Containment or Secondary Containment Isolation signal present.

2. EP-1 attachments are maintained in a special file box normally located in or in the close proximity of the Emergency Locker in the Control Room behind the P601 panel.

Task Overview:

(Detailed description of task)

Performance of this task vents the primary containment via 6

-inch ventilation lines with no Containment or Secondary Containment Isolation signal present for M41 and E61 valves.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 5 of 10 EP-1 Attachment 14

- Containment Venting Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: 05 02-I-1 OBTAIN EOP Attachment 14 from Control Room emergency locker.

Standard: Locates Control Room Emergency Locker Locates Attachment No. 14 Cue: None Notes: Once candidate has located the emergency locker and the correct Attachment, give the paper copy of Attachment 6.

SAT / UNSAT Step 2: 05-S-01-EP-1, Step 2.2 Open M41F037 CTMT CLG VENT EXH AUX BLDG OTBD ISOL on 1H13

-P870-8C. Standard: Simulates opening valve M41

-F037 by turning the valve's handswitch on P870 in the clockwise direction.

Cue: For valve M41-F037, the red light is on and the green light is off.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 6 of 10 Step 3: 05-S-01-EP-1, Step 2.3
  • Open M41F036 CTMT CLG VENT EXH AUX BLDG INBD ISOL on 1H13

-P870-2C. Standard: Simulates opening valve M41

-F036 by turning the valve's handswitch on P870 in the clockwise direction.

Cue: For valve M41-F036, the red light is on and the green light is off.

Notes: SAT / UNSAT Step 4: 05-S-01-EP-1, Step 2.4

-P870-4C. Standard: Simulates opening valve E61

-F057 by turning the valve's handswitch on P870 in the clockwise direction.

Cue: For valve E61

-F057, the red light is on and the green light is off.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 7 of 10 Step 5 05-S-01-EP-1, Step 2.5 Open E61F056 PURGE EXH CTMT INBD ISO VLV on 1H13

-P870-10C. Standard: Simulates opening valve E61

-F056 by turning the valve's handswitch on P870 in the clockwise direction.

Cue: For valve E61

-F056, the red light is on and the green light is off.

Notes: SAT / UNSAT Step 6 05-S-01-EP-1, Step 2.6

  • Start one or both Containment Exhaust Charcoal Filter Train fans by placing CTMT CLG EXHAUST FAN A AND/OR B handswitches to start.

Standard: Simulates starting one or both Containment Exhaust Charcoal Filter Train fans by placing CTMT CLG VENT EXHAUST FAN A AND/OR B handswitch to START on P842. Cue: For one or both Containment Exhaust Charcoal Filter Train fans, the red light is on and the green light is off.

Notes: At least one fan is required to be running so that associated fan supply and discharge dampers open to complete the flow path.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 8 of 10 Task Standard(s)
Actions have been taken to vent containment.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 9 of 10 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015CR 5 JPM Title:

EP-1 Attachment 14

- Containment Venting Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ______________

______________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

EP 2 and 3 have been entered.

Reactor level is being maintained between +

50 to -30 inches.

Reactor pressure is being maintained between 800 to 10 6 0 psig with SRVs.

Drywell pressure is below 1.0 psig.

No Containment or Secondary Containment Isolation signal is present for M41 and E61 valves. The emergency director has been notified that an unfiltered release will occur during venting of the containmen

t. Initiating Cue(s):

You have been directed to perform containment venting per EP

-1 Attachment 14 steps 2.2 through 2.6.

This task is not time critical.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 7 JPM Title: Reactor Manual Scram Switch Test Facility Number: __GJPM-OPS-C7105____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min

Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Christopher Baxter 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 2 of 11 Reactor Manual Scram Switch Test Setting: Simulator Type: RO Task: CRO-C71-OFFNORM-005 K&A: 212000 A2.03 (3.3/3.5), A4.02 (3.6/3.7) 2.1.30 (4.4/4.0), 2.1.20 (4.6/4.6)

Safety Function: 7 Performance:

Actual Reference(s):

06-OP-1C71-W-0001 (Reactor Manual Scram Switch Test Surveillance)

Handout(s):

06-OP-1C71-W-0001 # Manipulations:

5 # Critical Steps:

4 Simulator Setup/Required Plant Conditions

Load IC 104 and schedule file 2015 NRC JPM Master.

Safety Concerns

None Task Standard
Reactor is scrammed per 05 02-IV-1, Control Rod/Drive Malfunctions ONEP.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 3 of 11 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is operating at 67%. Initiating Cue(s):

The CRS directs you to perform 06

-OP-1C71-W-0001. All prerequisites are verified met.

Start with Data Sheet 1 and go in order through Data Sheet 4.

This task is not time critical.

You are the on watch ATC.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 4 of 11 Reactor Manual Scram Switch Test Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will perform 06

-OP-1C71-W-0001 (Reactor Manual Scram Switch Test).

When the operator depresses the first manual scram switch, nine control rods will scram due to a blown pilot solenoid fuse on the individual HCU units.

The operator should recognize nine scramed rods and scram the reactor

. Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06

-OP-1C71-W-0001 step 5.1 OBTAIN Shift Supervision's permission to start. Performer to RECORD Test Start Time on Data Package Cover Sheet.

Standard: Records the start time on the Surveillance Cover Sheet.

Cue: If the operator asks permission to begin the surveillance, inform the operator that the CRS has given permission to begin.

Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 5 of 11 Step 2: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.2 VERIFY the following lights are ON to ensure that NO RPS trip signals are present:

RPS DIV 1 SCRAM SOL VLV 1A AND 1B lights ON (5C1) RPS DIV 2 SCRAM SOL VLV 2A AND 2B lights ON (7C1)

RPS DIV 3 SCRAM SOL VLV 3A AND 3B lights ON (5C1) RPS DIV 4 SCRAM SOL VLV 4A AND 4B lights ON (7C1)

Standard: Observes white scram solenoid valve lights lit.

Cue: Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 6 of 11 Step 3: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.3

  • ARM the Div 1 MAN SCRAM Switch (5C1) by rotating the collar clockwise. VERIFY alarm RPS MAN SWITCH PERM is received (5A

-B3) RPS MAN SWITCH SCRAM PERM alarm is ON Standard: Rotates switch collar.

Cue: Notes: SAT / UNSAT Step 4: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.4

  • Depress the MAN SCRAM Switch which was previously Armed.

Standard: Depress MAN SCRAM Switch.

Cue: Notes: When the manual scram switch is depressed, two control rods will scram. SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 7 of 11 Step 5: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.5 VERIFY the following:

RPS SCRAM SOL VLVs lights 1A, 3A, on (5C1)

AND 2A, 4A on (7C1) are OFF RPS SCRAM SOL VLVs lights 1B, 3B, on (5C1)

AND 2B, 4B on (7C1) are ON RX SCRAM TRIP alarm is received (7A

-A2) RX MAN SCRAM TRIP alarm is received (7A

-A3) Standard: Observes indications listed.

Cue: Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 8 of 11 Step 6: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.5.4

  • Depress pushbutton SCRAM VLV (6C) AND VERIFY that NO scram valves are Open, as indicated by a green LED being OFF for all CRD/HCUs on the rod display map (6D) that are NOT tagged out.

Standard: Determines that two Control Rods have scramed.

Cue: Notes: Control Rods 28-17, 28-49, 52-33, 12-33, 36-17, 36-49, 28-33, 44-25, and 44-41 have scramed.

Once the operator determines that rods have scramed the operator should enter the Control Rod/Drive Malfunctions ONEP. SAT / UNSAT Step 7: Control Rod/Drive Malfunctions ONEP step 2.4

.2

. Standard: Rotates the mode switch counter clockwise to shutdown.

Cue: Notes:

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 9 of 11 Task Standard(s)
Reactor is scrammed per 05 02-IV-1, Control Rod/Drive Malfunctions ONEP.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 10 of 11 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 7 JPM Title: Reactor Manual Scram Switch Test Follow-Up Questions & Answers: Comments: Performance Rating

SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Revision 0 9/14/2015 Page 11 of 11 Give this page to the student

Initial Condition(s):

The plant is operating at 67%. Initiating Cue(s):

The CRS directs you to perform 06

-OP-1C71-W-0001. All prerequisites are verified met.

Start with Data Sheet 1 and go in order through Data Sheet 4.

This task is not time critical.

You are the on watch ATC.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 1 of 15 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 8 JPM Title: Manual Start of SSW A Facility Number:

N/A (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Christopher Baxter 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 2 of 15 Manual Start of SSW A Time Critical Alternate Path Validation Time:

1 5 Min Setting: Simulator Type: RO Task: CRO-P41-1, 3 K&A: 400000: A4.01 3.1/3.0 2.1.20: 4.6/4.6 Safety Function:

8 - Plant Service Systems Performance:

Actual Reference(s):

04-1-01-P41-1/4.2 Handout(s) 04-1-01-P41-1/4.2 # Manipulations:

6 # Critical Steps:

5 Simulator Setup/Required Plant Conditions

Reset Simulator to any IC. Load schedule file, 2015 NRC JPM Master.

Safety Concerns

None Task Standard
SSW 'A' is running with F064A (SSW INL TO CR A/C A) closed or SSW A pump tripped.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 3 of 15 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

SSW A is in STANDBY.

Initiating Cue(s):

Prerequisites are complete The CRS directs you to manually start SSW

'A' (controlled start) per P41

-1 SOI, Section 4.2

. Your supervisor wants flow through the RHR 'A' heat exchangers, 'A' Control Room A/C, and the 'A' ESF Switchgear Room Coolers.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 4 of 15 Manual Start of SSW A Notes: (Notes to Evaluator)

All controls and indications for this task are on panel P870. Task Overview:

(Detailed description of task)

This task is a manual startup SSW 'A' and isolate the reported leak by shutting E12-F005A or securing SSW 'A' Pump.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 5 of 15 Critical tasks are underlined, italicized, and denoted by an (*)

Sequence for the following steps is not critical unless otherwise denoted

. Step 1: 04 01-P41-1 Place SSW A MOV TEST Switch to the TEST posit ion. Standard: Places SSW A MOV TEST Switch in the TEST position Cue: None Notes: Not a step in the procedure but is a precaution and limitation.

SAT / UNSAT Step 2: 04-1-01-P41-1, 4.2.2 a (1)

CHECK OPEN F006A, SSW PMP A RECIRC VLV.

Standard: Checks open P41

-F006A by observing its red light is on and its green light is off. Cue: None Notes: Switch should be in the AUTO position already. SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 6 of 15 Step 3: 04-1-01-P41-1, 4.2.2 a (2)
  • START SSW PMP A Standard: Starts SSW Pump A by rotating its spring

-return switch clockwise to START, and verifies it running by observing its red light is on and its green light is off. Cue: None Notes: SAT / UNSAT Step 4: 04-1-01-P41-1, 4.2.2 a (3)

Standard: Opens P41-F001A by rotating its spring

-return switch clockwise to OPEN, and verifies it open by observing its red light is on and its green light is off Cue: None Notes:

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 7 of 15 Step 5: 04-1-01-P41-1, 4.2.2 a (4)(a)

Standard: Opens P41-F014A by rotating its spring

-return switch clockwise to OPEN, and verifies it open by observing its red light is on and its green light is off Cue: None Notes: SAT / UNSAT Step 6: 04-1-01-P41-1, 4.2.2 a (4) (b)

OPEN OR CHECK OPEN F068A, RHR HX OUTL VLV.

Standard: Checks open P41

-F068A by observing its red light is on and its green light is off Cue: None Notes: P41F068A is normally open.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 8 of 15 Step 7: 04-1-01-P41-1, 4.2.2 a (5)

Standard: Opens P41-F005A by rotating its spring

-return switch clockwise to JOG OPEN and holding it in this position until the valve is full open as indicated by its red light on and its green light off Cue: None. Notes: SAT / UNSAT Step 8: 04-1-01-P41-1, 4.2.2 a (6)

. Standard: Closes P41

-F006A by rotating its spring

-return switch counter

-clockwise to CLOSE, and verifies it closed by observing its green light is on and its red light is off Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 9 of 15 Step 9: 04-1-01-P41-1, 4.2.2 b START SSW CLG TWR FAN A AND B. Standard: Starts SSW Cooling Tower Fan A and B by rotating its spring

-return switch clockwise to START, and verifies its running by observing its red light is on and its green light is off Cue: None Notes: SAT / UNSAT Step 10: 04-1-01-P41-1, 4.2.2 c (1)

  • OPEN F081A, SSW OUTL FM CR A/C A Valve.

Standard: Opens P41-F081A by rotating its spring

-return switch clockwise to OPEN and verifies the valve is full open as indicated by its red light on and its green light off.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 10 of 15 Step 1 1: 04-1-01-P41-1, 4.2.2 c (2)
  • CLOSE F074A, PSW OUTL FM CR A/C A Valve.

Standard: Closes P41

-F074A by rotating its spring

-return switch counter

-clockwise to CLOSE, and verifies it closed by observing its green light is on and its red light is off.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 11 of 15 Step 1 2: 04-1-01-P41-1, 4.2.2 c (3)
  • OPEN F064A, SSW INL TO CR A/C A Valve.

Standard: Opens P41-F064A by rotating its spring

-return switch clockwise to OPEN and verifies the valve is full open as indicated by its red light on and its green light off.

Cue: Notes: When the F064A is fully open, the SSW flow indication will begin to lower and the SSW LOOP A LEAK HI (P870

-1A-E1) alarm will alarm. SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 12 of 15 Step 8: EN-OP-120, Attachment 9.2, Monitoring and Control. 02-S-01-43 section 6.4.1
  • Recognizes isolable leak downstream of F064A and isolates the leak by shutting F064A (SSW INL TO CR A/C A)

OR removes driving force of leak by securing the SSW A pump.

Standard: Closes P41

-F064A by rotating its spring

-return switch counter-clockwise to CLOSE, and verifies it closed by observing its green light is on and its red light is off

. OR Secures SSW A pump by rotating its spring return switch counter clockwise to TRIP and verifies it green light is on and its red light is off.

Cue: If requested to (per 04 02-1H13-P870-1A-E1): Check flow mismatch of SSW Loop A discharge and return flow per computer points, report PDS is out of service.

Dispatch an operator to determine where leak is and isolate if possible, report building operator sees water spraying on A CR A/C unit from piping downstream of F064A.

Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 13 of 15 Task Standard(s)
SSW 'A' is running with F064A (SSW INL TO CR A/C A) closed or SSW A pump tripped.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 14 of 15 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 8 JPM Title: Manual Start of SSW A Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Give this page to the student Initial Condition(s):

SSW A is in STANDBY.

Initiating Cue(s):

Prerequisites are complete The CRS directs you to manually start SSW

'A' (controlled start) per P41

-1 SOI, Section 4.2

. Your supervisor wants flow through the RHR 'A' heat exchangers, 'A' Control Room A/C, and the 'A' ESF Switchgear Room Coolers.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 1 of 21 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 9 JPM Title: Perform Area Radiation Monitor Functional Test Facility Number:

GJPM-OPS-D2101 (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By: Ben Nadolny 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 2 of 21 Perform Area Radiation Monitor Functional Test Time Critical Alternate Path Validation Time:

1 5 Min Setting: Simulator Type: RO Task: CRO-D21-003 K&A: 272000: A4.02

- 3.0/3.0 Safety Function

9 - Radioactivity Release / 7

- Instrumentation Performance

Actual Reference(s)
04-1-03-D21-1 Attachment I Handout(s)
04-1-03-D21-1 Attachment I, pages 1

-3, marked up to perform test for D21K601 # Manipulations

11 # Critical Steps
8 Simulator Setup/Required Plant Conditions
Reset simulator to any IC and load schedule file 2015 NRC JPM Master Override annunciator P680

-4A1-E6 OFF. Safety Concerns

None Task Standard
ARM D21K601 functional test is complete.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 3 of 21 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at rated power.

I&C has completed repair work on D21K601, RHR Room A Area Radiation Monitor, and the ARM is ready for Operations retest.

. Initiating Cue(s):

The SRO with the Command Function has directed you to perform EPI 04 03-D21-1 Attachment I for D21K601 as a retest.

Use the retest package provided.

Another operator is assigned to manage any associated alarms on H13

-P680 Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 4 of 21 Manual Start of SSW A Notes 1. All controls and indications for this task are on backpanel 1H13

-P844. Task Overview This task is to perform the Monthly Area Radiation Monitors Functional Test for RHR Room A ARM.

The evaluator will role play as the P680 operator responding to the expected AREA RAD PANEL P844 alarm (P680

-4A1-E6) that occurs as a result of this testing. That alarm is overridden OFF in this JPM to prevent interrupting concurrent JPMs within the control room main panel area.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 5 of 21 Critical tasks are underlined, italicized, and denoted by an (*)

Sequence for the following steps is not critical unless otherwise denoted.

Step 1: EPI 04-1-03-D21-1, Step 7.1.1 Signs Test Performer on the data package cover sheet of 04 03-D21-1 Attachment I.

Standard: Signs, dates, and times Test Performer block on the Data Package Cover Sheet.

Cue: None Notes: SAT / UNSAT Step 2: EPI 04-1-03-D21-1 Attachment I, Step 7.2.2a

  • SELECT OFF on Function switch

. Standard: Selects OFF on Function switch of D21K601 by rotating the switch counter

-clockwise to OFF, then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 6 of 21 Step 3: EPI 04-1-03-D21-1 Attachment I, Step 7.2.3a Observes AREA RADIATION MONITORING SYSTEM FAILURE annunciator on 1H13

-P844. Standard: Observes annunciator AREA RADIATION MONITORING SYSTEM FAILURE alarms (P844-2A-A5), then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT Step 4: EPI 04-1-03-D21-1 Attachment I, Step 7.2.4a Observes AREA RAD PNL P844 TROUBLE annunciates on 1H13-P680. Standard: Requests the ACRO to verify AREA RAD PNL P844 TROUBLE annunciates on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is in alarm. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 7 of 21 Step 5: EPI 04-1-03-D21-1 Attachment I, Step 7.2.5a Checks Fail Safe green light extinguished.

Standard: Observes the green FAIL SAFE indicator/CHECK SOURCE pushbutton on the monitor face of D21K601 backlight is off, then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT Step 6: EPI 04-1-03-D21-1 Attachment I, Step 7.2.6a

  • SELECT OPERATE on Function switch Standard: Selects OPERATE on Function switch of D21K601 by rotating the switch clockwise to OPERATE, then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 8 of 21 Step 7: EPI 04-1-03-D21-1 Attachment I, Step 7.2.7a CHECK FAIL SAFE green light illumintated.

Standard: Verifies FAIL SAFE green light is lit.

Cue: None. Notes: SAT / UNSAT Step 8: EPI 04-1-03-D21-1 Attachment I, Step 7.2.8a Resets AREA RAD PNL P844 TROUBLE annunciator on P680.

Standard: Requests the ACRO to reset AREA RAD PNL P844 TROUBLE annunciator on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is reset. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 9 of 21 Step 9: EPI 04-1-03-D21-1 Attachment I, Step 7.2.9a
  • Displays recorder point #1 on recorder D21R600.

Standard: Displays recorder point #1 on recorder D21R600 on P844 by depressing the up or down arrow keys until PT#1 is displayed, or by depressing 01 on the number keypad and depressing enter, then initials the step on the EPI Attachment I

. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 10 of 21 Step 10: EPI 04-1-03-D21-1 Attachment I, Step 7.2.10a
  • Depresses and holds the yellow TEST ALARM pushbutton

. Standard: Depresses and holds the yellow TEST ALARM pushbutton on the bottom of the monitor face

. Cue: None Notes: SAT / UNSAT Step 11: EPI 04-1-03-D21-1 Attachment I, Step 7.2.11a OBSERVE meter indication AND point #1 on Recorder R600 travel upscale.

Standard: Verifies meter indication on D21K601 and point # 1 on Recorder D21R600 on P844 travel fully upscale.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 11 of 21 Step 12: EPI 04-1-03-D21-1 Attachment I, Step 7.2.12a OBSERVE respective "RADIATION HIGH" annunciator on 1H13

-P844. Standard: Verifies annunciator EMERGENCY CORE COOLING ROOM RADIATION HIGH alarms (P844

-A-D4).. Cue: None Notes: SAT / UNSAT Step 1 3: EPI 04-1-03-D21-1 Attachment I, Step 7.2.13a Observes AREA RAD PNL P844 TROUBLE annunciates on 1H13-P680. Standard: Requests the ACRO to verify AREA RAD PNL P844 TROUBLE annunciates on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is in alarm. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 12 of 21 Step 8: EPI 04-1-03-D21-1 Attachment I, Step 7.2.14a
  • Releases the yellow TEST ALARM pushbutton Standard: Releases the yellow TEST ALARM pushbutton on the bottom of the monitor face, then initials the associated steps on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT Step 8: EPI 04-1-03-D21-1 Attachment I, Step 7.2.15a Checks red High Alarm light illuminated.

Standard: Observes the red HIGH ALARM indicator/RESET pushbutton on the monitor face of D21K601 backlight is on, then initials the step on the EPI Attachment I. Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is in alarm. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 13 of 21 Step 16: EPI 04-1-03-D21-1 Attachment I, Step 7.2.16a DEPRESS AND RELEASE red HIGH ALARM/RESET pushbutton

. Standard: Depresses and releases the red HIGH ALARM indicator/RESET pushbutton on the bottom of the monitor face, then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT Step 17: EPI 04-1-03-D21-1 Attachment I, Step 7.2.17a Checks red High Alarm light extinguished.

Standard: Observes the red HIGH ALARM indicator/RESET pushbutton on the monitor face of D21K601 backlight is off, then initials the step on the EPI Attachment I. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 14 of 21 Step 18: EPI 04-1-03-D21-1 Attachment I, Step 7.2.18a Resets AREA RAD PNL P844 TROUBLE annunciator on 1H13-P680. Standard: Requests the ACRO to reset AREA RAD PNL P844 TROUBLE annunciator on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is reset. Notes: SAT / UNSAT Step 19: EPI 04-1-03-D21-1 Attachment I, Step 7.2.19a Resets RADIATION HIGH annunciator on 1H13-P844. Standard: Resets annunciator RADIATION HIGH (P844

-A-D4), then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 15 of 21 Step 20: EPI 04-1-03-D21-1 Attachment I, Step 7.2.20a
  • Depresses and holds green FAIL SAFE indicator/CHECK SOURCE pushbutton AND OBSERVE that meter indication AND point #1 on Multipoint Recorder R600 Both indicate an increase in count rate THEN RELEASE green FAIL SAFE/CHECK SOURCE pushbutton.

Standard: Depresses and holds the green FAIL SAFE indicator/CHECK SOURCE pushbutton on the monitor face of D21K601 and verifies that meter indication and point # 1 on Multipoint Recorder R600 both indicate an increase in count rate, then releases the green FAIL SAFE indicator/CHECK SOURCE pushbutton and initials the step on the EPI Attachment I.

Cue: None Notes: This step will cause a high alarm if the check source pushbutton is held long enough to produce 100 mr/hr, which actually takes only a few seconds.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 16 of 21 Step 21: EPI 04-1-03-D21-1 Attachment I, Step 7.2.21a
  • PLACE AND HOLD Funcion switch to ALARM. . Standard: Rotates the function switch clockwise to ALARM and holds it Cue: None Notes: The SOI step implies the switch will spring return to OPERATE, but depending on the particular ARM, the switch may have to be rotated manually back to OPERATE, as is true for this ARM. SAT / UNSAT Step 22: EPI 04-1-03-D21-1 Attachment I, Step 7.2.22a
  • VERIFY meter indication travels to the setpoint of 100mR/hr

. Indicated value Should be within +/- 20% of the specified value.

. Standard: Verifies that meter indication travels to the alarm setpoint of 100 mr/hr (+/

- 20 mr/hr) and initials the step on the EPI Attachment I.

Cue: None Notes: The SOI step implies the switch will spring return to OPERATE, but depending on the particular ARM, the switch may have to be rotated manually back to OPERATE, as is true for this ARM.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 17 of 21 Step 23: EPI 04-1-03-D21-1 Attachment I, step 7.2.23a
  • RELEASE Function switch AND OBSERVE indication decreases to NORMAL.

Standard: Releases Function switch and verifies indication decreases back to normal

. Cue: None Notes: SAT / UNSAT Step 24: EPI 04-1-03-D21-1 Attachment I, Step 7.2.24a DEPRESS red HIGH ALARM/RESET pushbutton to clear any spurious alarm.

Standard: Depresses and releases the red HIGH ALARM indicator/RESET pushbutton on the bottom of the monitor face

. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 18 of 21 Step 25: EPI 04-1-03-D21-1 Attachment I, Step 7.2.25a Resets AREA RAD PNL P844 TROUBLE annunciator on P680.

Standard: Requests the ACRO to reset AREA RAD PNL P844 TROUBLE annunciator on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is reset. Notes: SAT / UNSAT Step 8: EPI 04-1-03-D21-1 Attachment I Completes the data package cover sheet of 04 03-D21-1 Attachment I.

Standard: Signs and dates Test Performed by blocks and checks Acceptable or Acceptable with Comments on the Data Package Cover Sheet. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 19 of 21 Task Standard(s)
ARM D21K601 functional test is complete

. SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 20 of 21 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015CR 9 JPM Title: Perform Area Radiation Monitor Functional Test Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Give this page to the student Initial Condition(s):

The plant is at rated power.

I&C has completed repair work on D21K601, RHR Room A Area Radiation Monitor, and the ARM is ready for Operations retest.

. Initiating Cue(s):

The SRO with the Command Function has directed you to perform EPI 04 03-D21-1 Attachment I for D21K601 as a retest.

Use the retest package provided.

Another operator is assigned to manage any associated alarms on H13

-P680 Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-6 JPM Title: RESET UNDERVOLTAGE LOCKOUTS ON BOP BUSES Facility Number:

__ GJPM-OPS-R2108____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 30 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 2 of 11 Reset Undervoltage Lockouts on BOP Buses Time Critical Alternate Path Validation Time:

30 Min Setting: Plant (Inside CAA)

Type: NLO Task: NOB-R21-008 K&A: 2.1.30: 4.4/4.0; 262001 A2.11: 3.2/3.6 295003 AA1.01: 3.7/3.8 Safety Function:

Electrical (6)

Performance

Actual Reference(s):

ONEP 05-1-02-I-4 section 3.3.12e Handout(s):

ONEP 05-1-02-I-4 section 3.3.12e

  1. Manipulations:

6 # Critical Steps:

6 Group #: 1 Simulator Setup/Required Plant Conditions

Area is accessible Safety Concerns
Do NOT operate plant equipment.

Task Standard

Bus 13AD and 12HE bus undervoltage lockout devices are reset.

.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 3 of 11 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

BOP Transformer 11B locked out on Sudden Pressure and deenergized 34.5 KV Bus 12R.

BOP Buses 12HE and 13AD lost power.

Control room operators have reenergized bus 12HE and bus 13AD from alternate feeders powered by BOP Transformers 12A and 12B per Loss of AC Power ONEP.

Major loads powered from these buses cannot be restored until bus under voltage lockout devices are reset at the busses.

Initiating Cue(s):

You have been directed to reset all bus under voltage lockout device s on bus 12HE and bus 13AD.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 4 of 11 Reset Undervoltage Lockouts on BOP Buses Notes 1. Bus 13AD and 12HE may be restored in any order. Bus order is not critical.
2. Bus undervoltage lockout devices may be reset in any order. BUV device order is no t critical. 3. The operator must be able to recognize the difference between a BUV and an overcurrent lockout device and should not attempt to reset an overcurrent lockout device for this task.

Task Overview:

This task is to reset bus undervoltage lockout devices on affected bus auxiliary panels after bus reenergization. This task is performed to allow large electrical loads to be restarted on affected buses. GGNS plant scram on February 11, 2005 required this task to be performed.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 5 of 11 Reset Undervoltage Lockouts on BOP Buses Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: Locate 4.16KV bus 13AD.

Standard: Locates bus 13AD in the electrical switchgear room in area 4 elevation 133' of the turbine building.

Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 6 of 11 Step 2:
  • Reset bus undervoltage lockout devices on bus auxiliary cubicle

.

  • Relay 186-BV1 reset.
  • Relay 186-BV2 reset.
  • Relay 186-BV3 reset.
  • Relay 186-BV4 reset.

Standard: Rotates handle of bus undervoltage device clockwise until it clicks vertical.

Cue: As each BUV device handle is rotated, cue the operator that the handle clicks vertical. Notes: BUV Relays have Red and White labels under them.

SAT / UNSAT Step 3: Observes white continuity light is on.

Standard: Operator observes white continuity light is on.

Cue: White light is lit.

Notes: White light comes on when the last BUV device is reset.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 7 of 11 Step 4: Locate 4.16KV bus 12HE.

Standard: Locates bus 12HE in the electrical switchgear room in area 4 elevation 113' of the turbine building. Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 8 of 11 Step 5:
  • Reset bus undervoltage lockout devices on bus auxiliary cubicle

.

  • Relay 286-BV1 reset.
  • Relay 286-BV2 reset.

Standard: Rotates handle of bus undervoltage device clockwise until it clicks vertical.

Cue: As each BUV device handle is rotated, cue the operator that the handle clicks vertical. Notes: BUV Relays have Red and White labels under them.

SAT / UNSAT Step 6: Observes white continuity light is on.

Standard: Operator observes white continuity light is on.

Cue: White light is lit.

Notes: White light comes on when the last BUV device is reset.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 9 of 11 Task Standard(s)
Bus 13AD and 12HE bus undervoltage lockout devices are reset.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 10 of 11 Applicant: _____________________________________________________________

JPM Number: GJPM-OPS-2015 PS-6 JPM Title: Reset Undervoltage Lockouts on BOP Buses Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ________________

____________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

BOP Transformer 11B locked out on Sudden Pressure and deenergized 34.5 KV Bus 12R.

BOP Buses 12HE and 13AD lost power.

Control room operators have reenergized bus 12HE and bus 13AD from alternate feeders powered by BOP Transformers 12A and 12B per Loss of AC Power ONEP.

Major loads powered from these buses cannot be restored until bus under voltage lockout devices are reset at the busses.

Initiating Cue(s):

You have been directed to reset all bus under voltage lockout device s on bus 12HE and bus 13AD.

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-7 JPM Title: PERFORM ATTACHMENT III OF SHUTDOWN FROM REMOTE SHUTDOWN PANEL ONEP Facility Number:

__ N/A____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time

2 0 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By: Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 2 of 11 Perform Attachment III of Shutdown from Remote Shutdown Panels ONEP Time Critical Alternate Path Validation Time:

30 Min Setting: Plant (Outside CAA

) Type: NLO Task: NOB-ADMIN-024; CRO-ADMIN-008; CRO-C61-001 K&A: 295016 AA1.07: 4.2/4.3; AK2.02: 4.0/4.1 2.1.30: 4.4/4.0 Safety Function

Instrumentation (7)

Performance

Simulate Reference(s)
05-1-02-II-1, Attachment III Handout(s)
05-1-0 2-II-1 # Manipulations
13 # Critical Steps
10 Group #: 1 Simulator Setup/Required Plant Conditions
Control building

- Division 1 switchgear room is accessible Safety Concerns

Do NOT operate plant equipment.

Task Standard

Separate the Division 1 equipment from the Main Control Room for safe shutdown.

.

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 3 of 11 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant has been scrammed.

A fire exists in the Main Control Room.

The Control Room Supervisor has evacuated the Main Control Room and established control of the plant at the Remote Shutdown Panels.

Initiating Cue(s):

You have been directed to complete the handswitch lineup per Attachment III of 05 02-II-1. This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 4 of 11 Perform Attachment III of Shutdown from Remote Shutdown Panels ONEP Notes: 1. Panels may be operated in any order. The sequencing is NOT CRITICAL.
2. This JPM is considered a Low Power JPM due to the requirement to scram the plant prior to manning the Remote Shutdown Panels.
3. This JPM is an Abnormal Operating Procedure outside of the CAA.

Task Overview:

This task is to align the Alternate Shutdown Panels in the Division 1 switchgear room of the Control Building per 05 02-II-1 Attachment III separating the Main Control Room from the Division I equipment for safe shutdown in the event of a fire or security event in the Main Control Room.

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 5 of 11 Perform Attachment III of Shutdown from Remote Shutdown Panels ONEP Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: 0 5-1-02-II-1, Attachment 3, 3.2.5 a a.

  • OBTAIN key from RSD room locker AND PLACE Transfer Switch for Lockout Transfer Relay C61-HSS-M150 at 1H22

-P152 (Area 25A, El. 111') to ON position

. Standard: Operator obtains the key to the locked switch cover for C61

-HSS-M150 key from the RSD locker.

Cue: You have the key

. C61-HSS-M150 is in the ON position.

Notes: The key is located in the locker in the Division 2 Remote Shutdown Room. Once the candidate identifies where the key is located this is sufficient.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 6 of 11 Step 2: 0 5-1-02-II-1, Attachment 3, 3.2.5 a b OBSERVE that Lockout Transfer Relays R1 through R36 trip to LOCKOUT position.

Standard: Observes Lockout Relays R1 through R36 trip to the LOCKOUT (TRIP) position. Cue: Lockout Relays R1 through R36 are in the LOCKOUT (TRIP) position. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 7 of 11 Step 3: 0 5-1-02-II-1, Attachment 3, 3.2.5 a c
  • PLACE the following handswitches at 1H22

-P299 (Area 25A, Elev 111') to LOCAL position:

-1511) PORT GIBSON

-1501/ESF XFMR NO. 11 152

-1514)SWYD

-1508)

-BTRY RM VENT SYS)

Standard: Places the above handswitches to LOCAL.

Cue: Handswitches are in LOCAL.

Notes: DO NOT ALLOW PIN TO BE REMOVED.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 8 of 11 Step 4: 0 5-1-02-II-1, Attachment 3, 3.2.5 ad PLACE OR VERIFY each component on panel 1H22

-P299 is in the desired position.

Component DESIRED POSITION

-HSS-M565 Closed 152-1513, 1C61

-HSS-M566 Closed 152-1512, 1C61

-HSS-M567 Closed 152-1504, 1C61

-HSS-M568 Closed 480V LCC 15BA5, 1C61

-HSS-M569 Closed Q1Y47-F002A-A As Required (Open IF Y47-C001A running)

Q1Y47-F003A-A As Required (Close on high SSW A Pumphouse temp)

Q1Y47-F001A-A As Required (Open IF Y47-C001A running)

Q1Z77-F036A-A As Required (Opens on high temperature)

Q1Z77-C001A-A Running (Red Light ON)

Standard: Verifies and records indications and compares to desired position.

Cue: As indicated.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 9 of 11 Step 5: 0 5-1-02-II-1, Attachment 3, 3.2.5ae NOTIFY RSD SRO of any component NOT in desired position on panel 1H22

-P299. Standard: Notifies RSD SRO all components are in desired position on panel 1H22

-P299 and Attachment 3 is complete.

Cue: None Notes: SAT / UNSAT Task Standard(s): Separate the Division 1 equipment from the Main Control Room for safe shutdown SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 10 of 11 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015 PS-7 JPM Title: PERFORM ATTACHMENT III OF SHUTDOWN FROM REMOTE SHUTDOWN PANEL ONEP Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

The plant has been scrammed.

A fire exists in the Main Control Room.

The Control Room Supervisor has evacuated the Main Control Room and established control of the plant at the Remote Shutdown Panels.

Initiating Cue(s):

You have been directed to complete the handswitch lineup per Attachment III of 05 02-II-1. This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-8 JPM Title: MANUALLY INITIATE FIRE PROTECTION TO THE 'B' RPS MOTOR GENERATOR ROOM Facility Number:

__ GJPM-OPS-P6405A (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 30 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number
LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 2 of 11 MANUALLY INITIATE FIRE PROTECTION TO THE 'B' RPS MOTOR GENERATOR ROOM Time Critical Alternate Path Validation Time:

30 Min Setting: Plant (Outside CAA

) Type: NLO Task: AON-P64-001; NOB-R20-002 K&A: 2.1.30: 4.4/4.0 2.4.26: 3.19/3.6 Safety Function

Plant Systems (8)

Performance

Simulate Reference(s)
04-1-01-P64-3 Handout(s)
04-1-01-P64-3 Section 5.2
  1. Manipulations
6 # Critical Steps
6 Group #: 2 Simulator Setup/Required Plant Conditions
Area is accessible Safety Concerns
Do NOT operate plant equipment.

DO NOT ALLOW CANDIDATE TO OPEN THE PULL STATION.

Task Standard

The CO2 System for 'B' RPS Motor Generator room has been actuated. .

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 3 of 11 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

A fire has been detected in the 'B' RPS Motor Generator room. Fire Brigade has been dispatched Initiating Cue(s):

You have arrived at the scene as a member of the Fire Brigade and you hear no CO 2 flow going to the room.

The Fire Brigade Leader has directed you to initiate CO 2 flow.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 4 of 11 Manually Initiate Fire Protection to 'B' RPS Motor Generator Room Notes 1. The operator may feel the need to don Fire Turnout Gear. Cue the operator to simulate this action.

Task Overview:

This task is to manually initiate the Fire Suppression System for the 'B' RPS Motor Generator room locally. This is done to extinguish the fire.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 5 of 11 Manually Initiate Fire Protection to 'B' RPS Motor Generator Room Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: 04-1-01-P64-3, 5.2.2 a. (1)

  • PULL the PULL handle on the pushbutton station to break the glass

. Standard: Operator breaks the glass.

Cue: Glass is broken.

Notes: DO NOT ALLOW CANDIDATE TO OPERATE THE PULL HANDLE.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 6 of 11 Step 2: 04-1-01-P64-3, 5.2.2 a. (1)
  • Momentarily DEPRESS pushbutton to INITIATE an automatic timed released of CO

². Standard: Operator depresses the pushbutton.

Cue: You hear no flow of CO

2. Notes: SAT / UNSAT Step 3: 04-1-01-P64-3, 5.2.2 b. (1)(a)
  • MANUALLY FLOOD the CO² Header as follows: REMOVE the pin from the Master Valve Manual SVF373 Release Lever located near the 10 ton CO

² Storage Unit Standard: Operator removes the pin

. Cue: Pin is removed.

Notes: DO NOT ALLOW PIN TO BE REMOVED.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 7 of 11 Step 4: 04-1-01-P64-3, 5.2.2 b. (1)(b)
  • PLACE the Manual Release Lever to the OPEN position. Standard: Rotates the lever to the open position.

Cue: You hear CO2 flow.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 8 of 11 Step 5: 04-1-01-P64-3, 5.2.2 b. (2)
  • BREAK glass with the small handle provided at the station Standard: Operator breaks the glass.

Cue: Glass is broken.

Notes: DO NOT ALLOW CANDIDATE TO OPERATE THE PULL HANDLE.

SAT / UNSAT Step 6: 04-1-01-P64-3, 5.2.2 b. (2)

  • ROTATE the arm inside to the OPEN position to release CO

² for the amount of time specified on each station.

Standard: Operator rotates the arm to the OPEN position.

Cue: Flow of C02 to the room has started.

Notes: SAT / UN SAT Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 9 of 11 Task Standard(s)
The CO2 System for 'B' RPS Motor Generator room has been actuated SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 10 of 11 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015 PS-8 JPM Title: Manually Initiate Fire Protection to 'B' RPS Motor Generator Room Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

A fire has been detected in the 'B' RPS Motor Generator Room. Fire Brigade has been dispatched Initiating Cue(s):

You have arrived at the scene as a member of the Fire Brigade and you hear no CO 2 flow going to the room.

The Fire Brigade Leader has directed you to initiate CO 2 flow.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 1 of 7 Revision 0 9/21/2015 Facility:

Grand Gulf Nuclear Station Scenario No.:

1 Op-Test No.: NRC LOT 201 5 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________

____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Rotate Power to bus 17AC from ESF 12 to ESF 21

. 2. Respond to a loss 17AC with a Diesel Generator failure

. 3. Loss of EPA breaker on 'B' RPS.

4. Trip of the 'B' RPS Alternate Power Supply with Inadvertent SCRAM of 4 Control Rods 5. Respond to low Main Turbine Lube Oil Pressure and Main Turbine Trip and Reactor Scram 6. Take actions for a n ATWS. 7. RCIC Steam line break with failure to auto isolate with manual isolation available.
8. Respond to a Feedwater line B rupture inside Drywell with ability to isolate and restore feedwater Initial Conditions:

Operating at 9 5% power. Inoperable Equipment:

None Turnover:

The plant is at 95% following a sequence exchange. SSW A is operating in preparation for weekly chemical addition. Planned activities for this shift are:

Rotate Power to 17AC from ESF 12 to ESF 21. There is no out of service equipment and EOOS is GREEN. It is a division 1 work week.

Scenario Notes:

This scenario is a NEW Scenario.

Validation Time: 60 minutes

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 2 of 7 Revision 0 9/21/2015 Event No. Malf. No. Event Type f Event Description 1 N (BOP) Rotate Power to 17AC from ESF 12 to ESF 21.(SOI 04-1-01-R21-17) 2 DI_1E22M716 n41140c C (BOP) A (CREW) TS (CRS) Respond to a loss of 17AC with a failure of Division 3 Diesel Generator (Loss of AC Power ONEP, 05 02-I-4; Tech Spec 3.8.1 condition B

) 3 c71077b C (ATC) C (BOP) A (CREW) Loss of EPA breaker on RPS 'B' (Loss of One or Both RPS Buses, 05 02-III-2) 4 LO_1C71M607B DI_1C71M607B ZO25025_40_33 ZO25025_40

-25 ZO25025_32

-37 ZO25025_32

-21 C (ATC) R (ATC) A (CREW) TS (CRS) Trip of the 'B' RPS Alternate Power Supply with Inadvertent SCRAM of 4 Control Rods (Control Rod/Drive Malfunctions ONEP, 05 02-IV-1; Reduction in Recirculation Flow Rate ONEP, 05 02-III-3, Tech Spec TR 3.1.5) 5 tc093 AO_1N34R600 DI_1N34M661 DI_1N34M662 p680_10a_c_1 M/A (CREW) Respond to Low Main Turbine Lube Oil Pressure (ARI 1H13-P680-10A-C2) Respond to Reactor Scram and/or Main Turbine Trip (Reactor Scram and Turbine Generator Trip ONEPS, EP

-2) 6 c11164 M (CREW) ATWS (EP-2A) 7 e51050 Att. 3 C (BOP) RCIC steam line break with failure to auto isolate, manual isolation available. (EN

-OP-120, 02-S-01-43, EP-4) 8 fw171b C (ATC) Feedwater line B rupture inside Drywell with ability to isolate and restore feedwater (EP

-3) f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

  • Repeated task from last 2 NRC exams.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 3 of 7 Revision 0 9/21/2015 Quantitative Attributes Table Normal Events 1 E OP Contingency Procedures Used 1 Total Malfunctions 7 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 Abnormal Events 4 Critical Tasks 4 Major Transients 2 Instrument/Component Failures 5 E O Ps Used (Requiring measurable action) 2 Reactivity Manipulations 1

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 4 of 7 Revision 0 9/21/2015 SCENARIO ACTIVITIES:

Rotate power on bus 17AC from transformer ESF 12 to ESF 21

A. After turnover contact CRS to perform power swap for Bus 17AC. (Event 1) B. Using 04-1-01-R21-17, SOI for 17AC bus, the BOP will rotate power from ESF Transformer 12 to normal source of ESF 21.

Loss of Bus 17AC with a Division 3 Diesel Generator failure:

A. 30 seconds after power has been swapped on bus 17AC, incoming feeder 152

-1705 will trip causing a loss of 17AC. Div 3 D/G will fail to start. (Event 2) B. The crew will take the actions per Loss of AC Power ONEP by energizing the 17AC bus from an alternate feeder

. C. If sent to investigate 152-1705, as Electrical Maintenance wait 3 minutes then report problem is unknown and a work order is required.

D. The CRS will determine that TS 3.8.1 Condition B 4 applies and require surveillance 06-OP-1R21-W-0001 Attachment II.

Loss of EPA Breaker on 'B' RPS A. When the crew has addressed all required Tech Specs and/or at the direction of the lead evaluator, trigger Event 3 to cause EPA breaker C71-S003 D to trip. (This is different from previous exams due to the failure of Electrical Protection Assemblies the RPS M/G will continue to run.)

B. The ATC will recognize and report a Division 2 half scram and determine a loss of 'B' RPS. C. The BOP will respond to the back panel area and determine a loss of power to the 'B' RPS. D. If sent to investigate loss of RPS 'B', wait 3 minutes and report C71-S003D has tripped on undervoltage

. E. CRS will enter the Loss of One or Both RPS Buses ONEP to transfer power to the alternate source

. F. The BOP will transfer 'B' RPS power to alternate sourc e G. The ATC will reset half scram

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 5 of 7 Revision 0 9/21/2015 Trip of the 'B' RPS Alternate Power Supply with Inadvertent SCRAM of 4 Control Rods A. When the crew has addressed all required Tech Specs and the subsequent actions of the Loss of One or Both RPS Buses ONEP and/or at the direction of the lead evaluator, trigger Event 4 to cause a trip 'B' RPS Alternate Power Supply

. B. The ATC will recognize and report a Division 2 half scram and determine a loss of 'B' RPS, also recognize and report 4 Control Rods have SCRAMMED.

C. The ATC will reduce core flow to 70 Mlbm/hr per 05 02-IV-1, Control Rod/Drive Malfunctions section 2.4.

D. The BOP will respond to the back panel area and determine a loss of power to the

'B' RPS. E. The CRS will enter 05-1-02-IV-1, Control Rod/Drive Malfunctions ONEP and 05-1-02-III-3, Reduction in Recirc Flowrate ONEP and Tech Specs TR 3.1.5 Condition A

. F. The ATC will plot current position on the Power to Flow map.

The BOP will verify the plot. G. If sent to investigate loss of RPS 'B', wait 3 minutes and report both EPA breakers for Alternate source, C71-S003H and S003F are tripped on undervoltage.

H. If sent to investigate alternate supply for RPS 'B' at 52

-164227, report breaker is tripped free.

Low Main Turbine Lube Oil Pressure A. When Reactor parameters have stabilized and/or at the direction of the lead evaluator, trigger Event 5 to cause a reduction in Main Turbine Lube Oil Pressure

. B. The crew will recognize a reduction in Main Turbine Lube Oil pressure by alarms and indication.

Main Turbine Trip / Reactor Scram A. Approximately 1 minute after Main Turbine Low Lube Oil pressure alarm the Main Turbine will trip

. B. The crew will recognize a Main Turbine Trip C. The crew will take actions of the Main Turbine Trip and Reactor Scram ONEPs.

D. The CRS will enter EP

-2 Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 6 of 7 Revision 0 9/21/2015 ATWS, 15% (Will maintain >5% power)

A. The crew will recognize control rods will fail to fully insert due to hydraulic block (Event 6). (This is different than other previous used ATWS malfunctions due to severity is at 15%)

B. The CRS will enter EP

-2A. Feedwater piping 'B' will rupture inside the drywell

A. Five minutes after the scram signal, Feedwater Line B will rupture in the Drywell (Event 7). (This is different than other previous used malfunctions due to the leak can be isolated and Feedwater can be restored.)

B. ATC secures all condensate and feedwater. The ATC has the ability to close B21

-F065B to isolate the leak and restore Feedwater and Condensate to feed the reactor. RCIC steam line break with failure to auto isolate A. Eight minutes after the scram signal, RCIC Steam Line will break (Event 8). (This is different than other previous used malfunctions due to the leak can be manually isolated and steam leak stopped.)

B. The BOP will recognize and report indications of a RCIC steam line break and entry into EP-4. C. The BOP will recognize failure to auto isolate D. The BOP will manually isolate the RCIC system by closing E51

-F063 and F064.

E. The CRS will enter EP

-4. Termination:

A. Once rod movement has occurred and reactor water level is being controlled in band or as directed by Lead Evaluator:

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 7 of 7 Revision 0 9/21/2015 Critical Task Number Description Basis 1 Per step L

-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches -70" wide range Water level must be lowered to reduce subcooling and prevent instabilities.

2 Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.

If not performed properly would result is direct adverse consequences or significant degradation in the mitigative capability of the plant. Correct performance prevents degradation of any barrier to fission product release (i.e. a n emergency depressurization will be required) 3 Isolate all systems (RCIC) discharging outside the primary CTMT through a break, except systems needed for fire suppression or EP actions prior to any other area exceeding its Max safe value in table 10 of EP

-4 If a RCIC steam leak with failure to isolate occurs, then RCIC should be shutdown and isolated unless required to assure adequate core cooling.

This is to prevent an unmonitored release and loss of fission product barrier.

4 Following an ATWS, insert control rods by manual scram and/or normal rod insertion prior to exiting

EP-2A. Positive confirmation that the reactor will remain shutdown under all conditions is best obtained by verifying that all control rods are inserted to or beyond position

02. Position 02 is the "Maximum Subcritical Banked Withdrawal Position," defined to be the greatest banked rod position at which the reactor will remain shutdown under all conditions.

. (per 02-S-01-40, EP Technical Bases)

  • Critical Task (As defined in NUREG 1021 Appendix D)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 1 of 35 Revision 0 9/21/2015 Simulator Setup:

A. Initialization

1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
4. Set the Simulator to IC-101 and perform switch check (Using Quick Reset in Director).
5. Click on "Open" in the Schedule window and Open Schedule File "201 5 NRC Scenario 1.sch" (in the Schedule Directory)
6. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 2 of 35 Revision 0 9/21/2015 7. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)

8. Take the simulator out of freeze.
9. Log on to all simulator PDS and SPDS computers.
10. Verify or perform the following:

IC-101 APRM's are turned on (4,1,2,3)

Ensure the MOC rod movement sequence available at the P680.

Advance all chart recorders and ensure all pens inking properly.

Clear any graphs and trends off of SPDS.

Ensure SSW A is aligned properly per 04-1-03-P41-1, SSW A Chemical Addition Run

. Marked up copy of 03 01-2 Att. II to step 6.7.3 , Power Ascension From 60% to Full Power, is placed on CRS desk.

Marked up copy up to step 7.7 of 04 03-P41-1, SSW A Chemical Addition Run, is placed on CRS desk.

Ensure bus 17AC is aligned to transformer ESF 12.

Marked up copy up to step 4.3.2 b of 04 01-R21-17, ESF Bus 17AC.

11. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

12. Place the simulator in Freeze.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 3 of 35 Revision 0 9/21/2015 B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 4 of 35 Revision 0 9/21/2015 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 9 5% M OC EOOS GREEN Planned Evolutions this shift:

SSW A is operating per 04 03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.

Rotate power on electrical bus 17AC from transformer ESF 12 to ESF

21. C. Allow the crew to perform pre

-shift brief and review procedures for planned evolutions.

D. Bring the crew into the Simulator, place the simulator is in RUN.

E. Allow the crew to walk down panels.

F. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 5 of 35 Revision 0 9/21/2015 SCENARIO ACTIVITIES:

Start SBT report and any other required recording devices.

Emergency Classification:

Site Area Emergency on SS3.

Op-Test No: NRC LOT 201 5 Scenario No:

1 Event No:

1 Event

Description:

Rotate power on bus 17AC from transformer ESF 12 to ESF 21 TIME Position Applicant's Actions or Behavior CRS Directs BOP to swap power on 17AC bus per 04-1-01-R21-17, ESF Bus 17AC SOI from transformer ESF 12 to transformer ESF 21

. BOP Using ESF BUS 17AC SOI , 04-1-01-R21-1 7 , section 4.3.2, performs the following:

a. ENSURE XFMR ESF 21 energized up to Bus Feeder Breaker 152-1705 as follows:

(1) CHECK CLOSED J5206 FDR to XFMR ST

-21 (2) CHECK CLOSED 552-2105 Bus 21R FDR FRM XFMR ST-21 (3) CHECK indicator 2R25

-R603 34.5 kV voltage (4) CHECK CLOSED 552-2104 Bus 21R FDR to XFMR ESF 21 (5) CHECK CLOSED 152-2902 FDR FRM XFMR ESF 21

(6) CHECK ENERGIZED status light is On.

b. TURN ON the Sync switch for Breaker 152

-1705 BUS 17AC FDR FRM XFMR ESF 21.

c. CHECK that the sync scope comes up to 12 o'clock

+ 10°.

d. ATTEMPT to CLOSE 152-1705 Bus 17AC feeder from ESF 21.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 6 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

1 (cont.) Event

Description:

Rotate power on bus 17AC from transformer ESF 12 to ESF 21 (cont.) TIME Position Applicant's Actions or Behavior NOTE: Annunciator in the next step is P601

-16A-C1 e. IF 152-1705 Closes AND the original feed breaker Trips, THEN the bus is energized AND transfer is complete. WHEN the original feeder breaker trips, an annunciator for feeder tripping is received. This is reset by TAKING the original tripped breaker handswitch to the TRIP position AND releasing. SKIP Steps 4.3.2g through 4.3.2k.

f. PLACE Sync switch to OFF.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 7 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 201 5 Scenario No:

1 Event No:

2 Event

Description:

Loss of 17AC Power TIME Position Applicant's Actions or Behavior BOP Recognize loss of 17AC bus from the following annunciators:

P601-16A E1 - 4.16KV BUS 17AC INCM FDR 152

-1705 TRIP G1 - 480V MCC 17B01 UNDERVOLT H1 - HPCS SYS NOT READY FOR AUTO START A2 - HPCS DSL ENG TRIP F2 - HPCS SYS UNDERVOLT D3 - HPCS DSL ENG TROUBLE E4 - HPCS JKY PMP DISCH PRESS LO P870-5A: G1 - DG13 FUEL OIL SFER PMP CONT PWR FAIL E2 - SSW DIV 3 OOSVC F1 - DG13 TRIP UNIT TROUBLE F2 - SSW LOOP C LEAK HI Recognizes 17AC is de

-energized and Division 3 EDG has failed.

Performs immediate operator actions from Loss of AC Power ONEP

Energize affected bus through an alternate feeder breaker or its respective diesel generator.

Restores power to 17AC from an alternate source by closing one of the following feeder breakers:

152-1704, 17AC FDR FM ESF 12 152-1706, 17AC FDR FM ESF 11 Verifies BUS 17AC is energized by restoration of indicating lights on the HPCS system and the following annunciators are reset:

P601-16A-G1 - 480V MCC 17B01 UNDERVOLT P601-16A F2 - HPCS SYS UNDERVOLT P601-16A-E4 - HPCS JKY PMP DISCH PRESS LO P870-5A- G1 - DG13 FUEL OIL SFER PMP CONT PWR FAIL P870-5A- E2 - SSW DIV 3 OOSVC P870-5A- F1 - DG13 TRIP UNIT TROUBLE P870-5A- F2 - SSW LOOP C LEAK HI

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 8 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

2 (cont.) Event

Description:

Loss of 17AC Power (cont.)

TIME Position Applicant's Actions or Behavior BOP Refers to Alarm Response Instruction for the following alarms:

P601-16A E1 - 4.16KV BUS 17AC INCM FDR 152

-1705 TRIP G1 - 480V MCC 17B01 UNDERVOLT H1 - HPCS SYS NOT READY FOR AUTO START A2 - HPCS DSL ENG TRIP F2 - HPCS SYS UNDERVOLT D3 - HPCS DSL ENG TROUBLE E4 - HPCS JKY PMP DISCH PRESS LO CRS Enters Loss of AC Power ONEP and ensures Immediate operator actions are performed.

Dispatches plant operator to investigate failure of Div 3 Diesel Generator and 17AC bus. Booth If sent to 17AC bus, report as Electrical Maintenance and report 152

-1705 has an 86 device lockout trip. Any more work will require a work order.

If sent to Div 3 D/G report the following alarms on P118

-1A:: A1 - HIGH CRANKCASE PRESSURE A2 - FAIL TO START / RUN B3 - UNIT TRIP / LOCKOUT CRS Determines Tech Spec 3.8.1, AC Sources

- Operating, condition B applies One required DG inoperable for reasons other than Condition F.

72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time Require surveillance Plant AC and DC Electrical Power Distribution Weekly Lineup, 06-OP-1R21-W-0001 Attachment II and III to be performed per required action B.1 Perform SR 3.8.1.1 for OPERABLE required offsite circuit (s)

. Within one hour. Direct plant operator to place Division 3 Diesel in Maintenance Mode.

Booth If requested to place Div. 3 D/G in Maintenance Mode trigger event 25 and notify Control Room that Div. 3 D/G is in Maintenance.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 9 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

2 (cont.) Event

Description:

Loss of 17AC Power (cont.)

TIME Position Applicant's Actions or Behavior BOP Performs surveillance 06

-OP-1R21-W-0001 Attachment II.

(See attachment 1)

CRS Performs surveillance 06-OP-1R21-W-0001 Attachment III Page 6 of 6 only.

(See attachment 1)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 10 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

3 Event Description

Loss of Electric Power Assembly breaker on 'B' RPS Normal Feed
TIME Position Applicant's Actions or Behavior ATC Recognizes and reports half scram on Division 2 side from the following P680 annunicators 4A2-D4 - HCU TROUBLE 7A-A2 - RX SCRAM TRIP Division 2 SCRAM SOL VLV white indicating lights out.

CRS Enters 05-1-02-III-2, Loss of One or Both RPS Buses.

Directs BOP to transfer RPS 'B' to Alternate power source Directs plant operator to investigate.

Enters Tech Spec TR 3.1.5 for Control Rod Scram Accu. alarm until half scram is reset. May enter 3.3.8.2 Cond. A, POT ENTIAL BOP Per 05-1-02-III-2, Loss of One or Both RPS Buses:

On Panel 1H13

-P610 IDENTIFY RPS bus that is de

-energized by EITHER Generator "A" Normal Feed Available light out OR Generator "B" Normal Feed Available light out.

Responds to P610.

Recognizes and reports loss of power to 'B' RPS by observing Generator "B" Normal Feed Available light out.

BOP Per 05-1-02-III-2, Loss of One or Both RPS Buses:

Places MG SET B TRANSFER switch on 1H13

-P610 to available power source. (Alternate)

ATC Per 05-1-02-III-2, Loss of One or Both RPS Buses:

Reset half

-scram using HS

-M601 B and D on Panel 1H13

-P680 by placing switches momentarily to reset.

Verifies Division 2 SCRAM SOL VLV white indicating lights energize.

BOP Ensures all MSIV solenoid lights are energized and all MSIV pilot solenoids indicate amperage on panels 1H13

-P622 and P623.

(Candidate will have to go behind the P807 panel and ask the Booth operator the status of indication due to P622 and P623 are not simulated in the Simulator.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 11 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

3 (cont.) Event Description

Loss of Electric Power Assembly breaker on 'B' RPS Normal Feed (cont.)
TIME Position Applicant's Actions or Behavior Booth If ask to investigate 'B' RPS Motor Generator set, wait 3 minutes and report as plant operator that M/G set is still operating and only one EPA breaker is tripped, C71

-S003D. Breaker is tripped on undervoltage.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 12 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

4 Event Description

Loss of Alternate Power Supply to 'B' RPS with 4 Control Rods Scram.

TIME Position Applicant's Actions or Behavior Recognizes and reports half scram on Division 2 side from the following P680 annunicators 4A2-D4 - HCU TROUBLE 4A2-E4 - CONT ROD DRIFT 7A-A2 - RX SCRAM TRIP Division 2 SCRAM SOL VLV white indicating lights out.

Recognizes and reports 4 Control Rods have Scram from the following P680 Indications:

4A2-E4 - Cont Rod Drift alarm SCRAM VLV back lit pushbutton on section 6C of P680 ACKN HCU FAULT back lit pushbutton on section 6C of P680 HCU FAULT back lit pushbutton on section 6C of P680 ROD DRIFT back lit pushbutton on section 6C of P680 Depresses any or all of the following pushbuttons to determine which control rods have moved:

SCRAM VLV back lit pushbutton on section 6C of P680 HCU FAULT back lit pushbutton on section 6C of P680 ROD DRIFT back lit pushbutton on section 6C of P680 Recognizes and reports the following control rods have scrammed in due to SCRAM VLV light and position is at 00.

40-33 40-25 32-37 32-21 Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 13 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

4 (cont.) Event Description

Loss of Alternate Power Supply to 'B' RPS with 4 Control Rods Scram (cont.).

TIME Position Applicant's Actions or Behavior ATC Performs immediate operator actions of Control Rod/Drive Malfunction ONEP, 05-1-02-IV-1: If more than one but less than eight Control Rods have scrammed, then Reduce Core flow to 70 Mlbm/hr.

Using both Recirc LOOP A CONT and LOOP B CONT, B33

-K603A & B, move the slide switches to the full left (i.e. fast detent) and verify core flow is lowering using B33

-R613 indicator of TOT JP FLO.

Maintain loop flow mismatch in Recirc system within 5% (2230 gpm)

When 70 Mlbm/hr is reached release the slide switches B33

-K603A & B. Plot location on Power / Flow map Reports location of OPRM TRIP ENABLE region.

Performs THI watch with no concurrent duties.

CRS Enters Control Rod/Drive Malfunction ONEP, 05 02-IV-1 Directs ATC to perform immediate operator actions Notify STA/Reactor Engineering to perform a MON Calculation Enters Reduction in Recirc System Flow Rate ONEP, 05 02-III-3 Directs ATC to plot current position on the Power

- Flow map. Enters (re

-enter) Loss of One or Both RPS Buses ONEP, 05-1-02-III-2 BOP Verifies and reports ATC plot of power /flow to be in the OPRM TRIP ENABLE region Per 05-1-02-III-2, Loss of One or Both RPS Buses:

On Panel 1H13

-P610 IDENTIFY RPS bus that is de

-energized by EITHER Generator "A" Normal Feed Available light out OR Generator "B" Normal Feed Available light out.

Responds to P610.

Recognizes and reports loss of power to 'B' RPS by observing Generator "B" Alternate Feed Available light out.

CRS After reactor power and core flow is stable directs ATC to have concurrent duties. Dispatches operator to RPS 'B' to investigate loss of RPS power.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 14 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

4 (cont.) Event Description

Loss of Alternate Power Supply to 'B' RPS with 4 Control Rods Scram (cont.).

TIME Position Applicant's Actions or Behavior Booth If requested to investigate loss of RPS 'B' power, wait 3 minutes and report Alternate Power Supply EP A breakers are tripped on undervoltage.

CRS Dispatch operator to MCC 16B42 and investigate breaker number 27.

Booth If requested to investigate 52

-164227, wait 3 minutes and report breaker is in the trip free position.

ATC Monitor for Control Rod drifts, due to ROD DRIFT alarm and status light will be sealed in due to the 4 controls scram.

CRS Direct ATC to monitor for Control Rod Drift.

Dispatch plant operator to isolate affected Control Rods per 04 01-C11-1, Control Rod Drive SOI Enter Tech Spec TR 3.1.5

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 15 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

5 Event Description

Low Main Turbine Lube Oil Pressure TIME Position Applicant's Actions or Behavior ATC Recognizes and Reports Low Main Turbine Lube Oil Pressure:

P680-10A-C2, TURB LUBE OIL PRESS LO alarm Indicator N34

-R600, TURB BRG OIL PRESS, is lowering from normal (150 psig to 40 psig)

. Verifies Auto start of AC Auxiliary Oil Pumps A/B/C BOP Refers to ARI P680

-10A-C2, TURB LUBE OIL PRESS LO Per ARI Auto actions, Verifies Auto start of AC Auxiliary Oil Pumps A/B/C CRS Verifies actions per ARI

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 16 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

5 Event Description

Main Turbine Trip / Reactor Scram TIME Position Applicant's Actions or Behavior ATC Recognizes and reports Main Turbine lube oil pressure low by the following indications:

P680-10A-C 1, TURB LUBE OIL PRESS TRIP alarm Recognizes and reports Main Turbine Trip Recognizes and reports Reactor Scram. Performs immediate operator actions for Turbine and Generator Trip, 05 02-I-2, and Reactor Scram, 05 02-I-1, ONEPs Place the Mode SW to SHUTDOWN

. Provides a scram report:

o Reactor Mode SW in SHUTDOWN.

o All Rods are NOT Inserted (Hyd Block ATWS).

o Reactor power is initially above 5%.

o Reactor water level and trend.

Ensure Main Turbine Stop and Control Valves are CLOSED Ensure Both Generator Output Breakers are OPEN CRS Enters Turbine and Generator Trip, 05 02-I-2, and Reactor Scram, 05 02-I-1, ONEPs Enters EP-2 RPV Control Verifies Reactor Mode Switch is in SHUTDOWN Evacuates affected areas

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 17 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

5 (cont.) Event

Description:

Main Turbine Trip / Reactor Scram (cont.) TIME Position Applicant's Actions or Behavior ATC Assumes Reactor water level control duties.

Aligns Condensate/Feedwater to Startup level control valve per hard card, 04 01-N19-1. IF two RFPTs are in operation, THEN TRIP one by DEPRESSING TRIP pushbutton.

CLOSE the following valves:

a. N21-F009A, FW HTR 6A OUTL VLV
b. N21-F009B, FW HTR 6B OUTL VLV.

OPEN the following valves:

a. N21-F001, SU FCV OUTL ISOL VLV.
b. N21-F010A, HP FW HTR STRNG A SU OUTL VLV.
c. N21-F010B, HP FW HTR STRNG B SU OUTL VLV.

VERIFY CLOSED the following valves:

a. N21-F513, X WTR LVL SU CONTR Valve (per controller 1C34

-LK- R602) b. N21-F510, FW CU RECIRC VLV

c. N21-F040, FW SU BYP VLV IF one RFPT is in service, THEN SELECT OR ENSURE in SPEED AUTO with discharge pressure approximately 250 psid above reactor pressure.

OPEN / VERIFY OPEN RFP A(B) DISCH VLV N21

-F014A(B) for at least one pump.

ADJUST N21-F513, RX WTR LVL SU CONT valve, as necessary in MANUAL OR AUTO to maintain desired Reactor level. N21

-F040 AND/OR N21-F009A(B) May be OPEN/CLOSED as necessary to augment flow.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 18 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 201 5 Scenario No:

1 Event No:

6 Event

Description:

ATWS TIME Position Applicant's Actions or Behavior ATC Recognizes and reports Hydraulic Block ATWS (During Scram Report)

CRS Exits EP-2 and Enters EP-2A and directs the following actions:

Verify Reactor Recirc pumps transferred to LFMG Verify ARI/RPT initiation Inhibit ADS Override HPCS injection ATC Performs the following on P680 panel

Verify Reactor Recirc pumps transferred to LFMG o Verifies Recirc pump breaker alignment is for slow speed operation (CB 3, 4, & 5 open

, CB 1 and 2 closed) if not then depress TRANSFER TO LFMG pushbutton.

Verify ARI/RPT initiation o Verifies light indication on ARI/RPT shows initiation OTBD VALVES LOGIC INIT.

INBD VALVES LOGIC INIT.

RPT LOGIC INIT.

OR o A rm s and depresses ATWS ARI/RPT MAN TRIP CHANNEL 1 AND CHANNEL 2 pushbuttons.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 19 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Performs the following on P601 Panel

Inhibit ADS o Places ADS INHIBIT switches to the INHIBIT position Override HPCS injection by performing the following:

(1) While HOLDING HPCS SYS INJECTION VLV (E22

-F004) handswitch in "CLOSE" position, ARM AND DEPRESS the manual system initiation push

-button for HPCS. (2) AFTER indication of pump start, THEN TRIP the HPCS pum p. (3) ENSURE the HPCS pump AND E22-F004 valve override alarms are sealed in.

CRS Directs to verify the following:

Isolations o If level 2 isolation has occurred direct to restore Aux Building Diesel Generators

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 20 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Verifies the following dependent on plant conditions:

If level 2 isolation has occurred and directed by the CRS to restore the Aux Building then perform the following per 05-1-02-III-5, Automatic Isolations ONEP, Attachment II

1) IF Plant Air compressors are available, THEN OPEN/CHECK OPEN the following Instrument Air valves on 1H13

-P870: Section 3C P53-F001 (After 30 sec T.D.)

Section 9C P53-F007 (After 30 sec T.D.)

2) IF all Drywell temperatures are less than 200F (CRD cavity temperature excluded) AND Drywell Chillers are available, THEN RESTORE Drywell Chilled Water as follows:
a. IF required, RE-ENERGIZE MCC's 15B42 AND 16B42 on 1H13-P864. b. AFTER a 30 second time delay, OPEN the following valves on 1H13

-P870: Section 3C P72-F121 P72-F122 P72-F125 Section 9C P72-F123 P72-F126 P72-F124 c. ENSURE at least one Drywell Chilled Water pump is running. d. ENSURE Drywell Coolers are in operation.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 21 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP 3) IF Drywell Chilled Water is NOT restored per previous step, THEN STOP DW CHLD WTR PMP A AND B, IF running. 4) The following valves Will NOT close due to being gagged open. As time permits, give these valves an OPEN signal to lift actuator off of gag.

Section 3C P53-F026A Section 9C P53-F026B 5) REFER to Att. IV for Auxiliary Building restoration of Plant Service Water and Plant Chill Water isolations as required.

6) REFER to system SOI's when time permits to ensure complete system restoration.

If Diesel Generators received a start signal then verify proper operation and cooling water being supplied.

o Ensure Diesel running indication o Ensure SSW A/B/C are aligned to provide cooling water to running diesel generators.

SSW pump running A/B/C SSW Discharge Valves are open P41

-F001A/B SSW Supply to Diesel Generators Valves are open P41

-F018A/B SSW Return Valves to Basin are open P41

-F005A/B, P41

-F011.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 22 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior CRS Directs installation of Attachment 8 Directs reactor water level to be lowered by terminate and prevent all RPV injection except for Boron, CRD and RCIC

. Directs a level band of

-70" to -130" wide range.

Directs installation of Attachments 12 Booth When asked to install EP attachments:

Select Remotes on Director Select EP ATT folder at bottom of page.

Select desired attachment Select Install. When Attachment is complete notify CRS ATC Terminates feedwater injection by performing the following per 02

-S-01-43, Transient Mitigation Strategy:

IF time does NOT permit closing of valves, THEN TRIP reactor feed pump(s) AND/OR condensate/condensate booster pump(s) to prevent injection.

IF time permits closing of valves:

(1) IF S/U level control in service, THEN CLOSE the S/U level control valve AND/OR N21-F040 IF necessary.

(2) IF S/U level control is NOT in service, THEN ALIGN Feedwater for S/U level control with S/U level control valve closed.

Per step L

-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches

-70" wide range Controls Reactor water level using Feedwater Startup Level Control Valve within given band of

-70" to -130" wide range.

CRITICAL TASK IN BOLD

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 23 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Terminates Low pressure ECCS systems by performing the following per 02

-S-01-43, Transient Mitigation Strategy.

(1) ARM AND DEPRESS the manual system initiation push

-button for selected division.

(2) AFTER indication of pump(s) start, THEN TRIP the pump(s).

(3) CLOSE the associated injection valve(s).

(4) ENSURE the associated pump(s) and valve(s) override alarms are sealed in.

(5) REPEAT these steps for the other division.

For Division 1 ECCS:

Low Pressure Core Spray system RHR 'A' LPCI system For Division 2 ECCS RHR 'B' LPCI system RHR 'C' LPCI system Per step L

-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches

-70" wide range CRS Directs for pressure control to be maintained by Main Steam Bypass valves with a pressure band of 800 psig to 1060 psig.

Directs for Main Turbine Pressure control to lower pressure setpoint on the Main Turbine to 900 psig.

BOP Lowers Main Turbine Pressure Reference setpoint to 900 psig and maintains pressure band of 800 psig to 1060 psig.

Depresses the PRESS REF LOWER pushbutton on P680

-9C. Monitors N32

-R610 TURB STM PRESS DEMAND indication on P680

-9B When 900 psig is indicated releases PRESS REF LOWER pushbutton.

CRITICAL TASK IN BOLD

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 24 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior CRS Directs CRD system to be aligned for MAX Flow.

Directs installation of Attachments 18, 19, and 20 (performed by I&C)

Booth When asked to install EP attachments:

Select Remotes on Director Select EP ATT folder at bottom of page.

Select desired attachment Select Install. When Attachment is complete notify CRS

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 25 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 201 5 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Maximizes CR D system for flow by performing the following per 04 01-C11-1, Control Rod Drive SOI, Attachment VIII:

IF no CRD pumps are initially running, THEN a CRD pump Must be started per ONEP 05-1-02-IV-1 prior to performing the following steps.

All controls are located on panel 1H13

-P601-22B OR 22C. Per ONEP 05-1-02-IV-1 to restart 1 st pump: IF running CRD pump trips, THEN START standby CRD pump as follows: a. IF required, RE-ENERGIZE MCC's 15B42 AND 16B42 on 1H13

-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.

d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54

-66 gpm after charging pressure is normal.

e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54

-66 gpm. Per 04-1-01-C11-1, Control Rod Drive SOI, Attachment VIII:

1. ENSURE oil pump is running on the non

-running CRD Pump A(B).

2. With one CRD pump already running, THEN START standby CRD PMP A(B). 3. PLACE CRD SYS FLO CONT C11

-R600 in MANUAL.

4. USING CRD SYS FLOW CONT C11

-R600, fully OPEN C11-F002A(B), CRD FLO CONT VLV.

5. IF maximizing CRD for flow, THEN FULLY OPEN C11-F003, CRD DRIVE WTR PRESS CONT VLV.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 26 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior CRS Directs for injection of Standby Liquid Control per Hard Card BOP Initiates Standby Liquid Control by performing the following per 04 01-C41-1 Section 5.3:

a. OBTAIN SLC Initiation keys from the Shift Manager's key cabinet, INSERT keys into SLC PMP A AND B key switches on 1H13

-P601 AND TURN each momentarily to the START position (spring return to normal).

b. CHECK that system initiation has occurred by OBSERVING the following:

(1) F001A AND F001B STORAGE TANK OUTLET valves OPEN as indicated on 1H13

-P601. (2) Squib Valves F004A AND F004B fire as indicated by the following on 1H13

-P601: (a) White SQUIB VALVE READY light is Off.

(b) Annunciator "SLC SYS A AND B OOSVC" Alarms.

(c) Amber status light SQUIB A AND B LOSCONT OR PWR LOSS is On.

(3) SLC Pumps A AND B start WHEN the associated storage tank outlet valves open as indicated by red pump running lights on 1H13

-P601. (4) The following RWCU valve(s) CLOSE: (a) SLC A initiated

- 1G33-F004 CLOSES (1H13-P680) (b) SLC B initiated

- 1G33-F001 (1H13

-P680) AND 1G33-F251 (1H13

-P870-9C) CLOSE c. CHECK that SLC injection to the reactor by OBSERVING the following:

(1) SLC pump discharge pressure exceeds reactor pressure as indicated by SLC PMP A/B DISCH PRESS indicator.

(2) SLC tank level is lowering as indicated on SLC STOR TK LVL indicator 1H13

-P601. (3) Nuclear instrumentation on 1H13

-P680 indicates reactor power level is lowering.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 27 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP d. Monitor Reactor Power AND INSERT SRMs AND IRMs prior to reactor power going downscale on APRMs.

e. WHEN directed by the EPs to secure SLC injection, TURN the running SLC pump key switch(es) to the STOP position.
f. As soon as possible, RETURN the SLC System to STANDBY in accordance with Section 4.1.

Recognizes and reports SLC is NOT injecting due to low discharge pressure

. CRS Directs installation of Attachment 28 (performed by Mechanical Maint.)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 28 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

7 Event

Description:

RCIC steam line break with failure to auto isolate TIME Position Applicant's Actions or Behavior BOP Recognize and report steam line break in the RCIC room by the following Alarms on the P601

-21A panel:

H2 - RCIC PIPE/EQUIP AMBIENT TEMP HI H3 - G3 - RCIC EQUIP AREA TEMP HI Recognize and report EP

-4 entry condition. (P601

-21A-G3) Recognize automatic actions did not occur by observing E51

-F063 and F064, Steam Supply Valves did not close.

Perform actions that should have occurred automatically but did not.

Place handswitch for E51

-F063 and F064 to the CLOSE position on P601 panel section 21C Report to the CRS that RCIC isolation has completed manually with F063 and F064 have closed.

Isolate all systems (RCIC) discharging outside the primary CTMT through a break, except systems needed for fire suppression or EP actions prior to any other area exceeding its Max safe value in table 10 of EP

-4 CRS Enter EP-4 Monitor EP

-4 Operating and Max safe values Direct a manual isolation of RCIC

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 29 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

8 Event

Description:

Feedwater Line 'B' rupture in the Drywell TIME Position Applicant's Actions or Behavior ATC Recognize symptoms of a FW Line B rupture in the Drywell.

As indicated by high feed flow to the reactor in B feed water line a nd near zero feed water flow in A feed water line. Also indicated by rising DW pressure and temperature and drywell floor drain sump level and temperature alarms on 1H13

-P680-8A1. Perform the following:

Report the Feed water leak to the CRS.

Trip all condensate pumps. (This is necessary to immediately stop the leak in the drywell.)

Isolate the 'B' FW line by closing the B21

-F065B to allow feedwater to feed the reactor through the 'B' feedwater line

. o Depresses the CLOSE pushbutton for the B21

-F065B on the P680 panel.

Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.

CRS Directs ATC to isolate the Feedwater break by closing B21

-F065B and restore level. (Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 30 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

8 (cont.) Event

Description:

Feedwater Line 'B' rupture in the Drywell (cont.) TIME Position Applicant's Actions or Behavior ATC After B21-F065B gets full closed perform the following:

Restart at least 2 Condensate pumps o Depress the START pushbutton for the desired pump Restart at least 2 Condensate Booster pumps o Depress the START pushbutton for the desired pump Restart 1 Reactor Feedwater pump by performing the following:

RESTORE one Reactor Feed Pump to operation as follows:

a. ENSUR E RFPT A(B) CONTROLS "MANUAL" pushbutton is backlit.
b. VERIFY an AC lube oil pump is running for RFPT to be restarted.
c. ENSURE Instrument Air is available.
d. OPEN RFP A(B) DISCH VLV N21

-F014A(B).

e. DEPRESS the RFPT A(B) TRIP RESET pushbutton.

(1) IF the reactor feed pump turbine W ill NOT reset, PERFORM the following Step Locally:

(a) WHEN the oil system is operating, GRAB AND HOLD the Local Reset Lever for approximately 1 minute (This fills the circuit).

f. To place RFP in service, PERFORM one of the following:

(1) IF Turbine is OFFLINE, THEN RAISE pump speed USING the RAISE pushbutton until governor position is approx. 60%

OR as required to obtain discharge pressure approx. 250 psig above reactor pressure.

(2) IF Turbine is ONLINE, THEN RAISE pump speed USING the RAISE pushbutton as required to obtain discharge pressure approx. 250 psig above reactor pressure.

(3) IF desired to establish Feedwater flow without Startup Level Controller in service, THEN CONTROL Feedwater flow with RAISE AND LOWER pushbuttons as required.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 31 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

8 (cont.) Event

Description:

Feedwater Line 'B' rupture in the Drywell (cont.)

TIME Position Applicant's Actions or Behavior ATC g. IF desired, THEN SELECT SPEED AUTO

h. IF transferring to Startup Level Control, THEN RETURN to Attachment VII.

Maintain reactor water level using Startup Level Control Valve with a band of

-70" to -1 91" wide range Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 32 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior CRS Verifies installation of Attachments 18, 19 and 20 then directs to Scram and Drive Control rods.

Directs BOP to maximize CRD for pressure Following an ATWS, insert control rods by manual scram and/or normal rod insertion prior to exiting EP

-2A BOP Maximize CRD for pressure by performing the following per 04 01-C11-1, Attachment VIII:

IF no CRD pumps are initially running, THEN a CRD pump Must be started per ONEP 05-1-02-IV-1 prior to performing the following steps.

All controls are located on panel 1H13

-P601-22B OR 22C. Per ONEP 05-1-02-IV-1 to restart 1 st pump: IF running CRD pump trips, THEN START standby CRD pump as follows: a. IF required, RE-ENERGIZE MCC's 15B42 AND 16B42 on 1H13

-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.

d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54

-66 gpm after charging pressure is normal.

e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54

-66 gpm. (Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 33 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Per 04-1-01-C11-1, Control Rod Drive SOI, Attachment VIII:

1. ENSURE oil pump is running on the non

-running CRD Pump A(B).

2. With one CRD pump already running, THEN START standby CRD PMP A(B). 3. PLACE CRD SYS FLO CONT C11

-R600 in MANUAL.

4. USING CRD SYS FLOW CONT C11

-R600, fully OPEN C11-F002A(B), CRD FLO CONT VLV.

5. IF maximizing CRD for pressure , THEN FULLY CLOSE C11-F003, CRD DRIVE WTR PRESS CONT VLV, to maximize drive water pressure. NOTE:If CRD system is already maximized for FLOW only step 5 above will be performed.

Inserts Control Rods by Scram and normal lnsert drive by:

Manual Scram:

Reset Scram signal (Division 1 only)

Allow Scram Discharge Volume to drain Arm and depress Manual Scram pushbuttons.

(Division 1 only)

Normal Drive Reset Scram signal (Division 1 only)

Select control rod Select gang drive mode depress IN TIMER SKIP pushbutton until control rods indicate 00 Following an ATWS, insert control rods by manual scram and/or norma l rod insertion prior to exiting EP

-2A (Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 34 of 35 Revision 0 9/21/2015 TERMINATION Once rod movement has occurred and reactor water level is being controlled in band or as directed by Lead Evaluator:

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 35 of 35 Revision 0 9/21/2015

Attachment 1 06-OP-1R21-W-0001, ATTACHMENTS II & III

Revision 0 9/21/2015 36 of 46 GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II Page 1 of 4 Model WO#

50289936 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Plant AC and DC Electrical Power Distribution Weekly Lineup Technical Specifications: SR 3.8.1.1 1.0 IMPAC T STATEMENT 1.1 Performance of this procedure has no impact on plant operation.

2.0 PROCEDURE

2.1 Plant Mode is (circle one): 1 2 3 2.2 Test Start Time

/ /

Performer / Date Time

2.3 Radiation

Protection Revie w

RWP # 3.0 TES T RESULTS 3.1 Test Completion: (CHECK one in each category.)

Entire procedure completed [ ] Partial procedure completed [ ]

Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable [ ]

All other steps/data Acceptable [ ] Unacceptable [ ]

3.2 Inop Electrical Equipment (include LCO #)

3.3 Comments

3.4 Test performed by Date/Time

/

4.0 DEFICIENCIES

CR Issued # LCO Entered # WR Issued # 5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]

Shift Supervision Date CONCURRENCE Operations Management Date GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II Page 2 of 4 Page XRef Revision 0 9/21/2015 37 of 46 DATA SHEET I PLANT AC AND DC ELECTRICAL POWER DISTRIBUTION WEEKLY LINEUP SAFETY RELATED (Step 5.2.2) Div 1, 2 & 3 Offsite Feeders OFFSITE ENERGIZED VOLTAGE RECORDED FREQUENCY RECORDED INITIALS FEEDER INDICATOR VOLTAGE INDICATOR FREQUENCY

YES/NO (LOCATION)

(ACCEPTANCE (LOCATION)

(ACCEPTANCE

CRITERIA)

CRITERIA)

BAXTER

500 kV FREQ.

$ WILSON

  • JACKSON kV SR27-SR-R600 Hz DISPATCHER

(H13-P807)

$ FRANKLIN

  • (496-525kV)*** or Pine Bluff Dispatcher (58.5-61.8Hz)

x 27.64

152-1511 = kV

115kV LINE 152-1611 (120.75-

$ PORT GIBSON

  • 152-1704 112.13) kV
  • To determine status of offsite feeders, CONTACT load dispatcher. Ensure that the feeders are independently energized from the grid, such that the loss of one feeder would NOT result in the loss of another. ** To determine voltage of the Port Gibson 115kV line, record ESF 12 incoming voltage at Bus 15AA, 16AB OR 17AC placing the Sync switch for the designated breaker to ON. MULTIPLY this reading by 27.64 for equivalent feeder voltage. RETURN Sync switch to OFF after taking reading

. *** Allowable Value of minimum voltage is

>491 kV for operability of Offsite Feeders. This value is based on analysis of the Class 1E ESF buses AND includes an allowance for instrument uncertainty associated with the voltage measurement in the switchyard. Extended operation beyond the normal continuous operating limits Should be evaluated AND caution Should be taken when starting large loads under these conditions.

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II Page 4 of 4 Page XRef Revision 0 9/21/2015 38 of 46 DATA SHEET I (Continued)

PLANT AC AND DC ELECTRICAL POWER DISTRIBUTION WEEKLY LINEUP SAFETY RELATED

RECORDED

VOLTAGE REQUIRED ACTUAL INSTRUMENT ACCEPTANCE BREAKE R POSITION POSITION INITIALS COMMENTS (LOCATION)

CRITERIA Service Transformer 11

- Bus 11R to ESF 15AA, 16AB & 17AC

34.5kV Bus A-B = (1) $ 552-1105 Closed 11R Volts B-C = (1) 1R25-EI-R603 C-A =

(1) $ 552-1104 Closed (H13-P807-1B) (31.05-37.95kV)

Bkr 152-1514

  • Inc Voltage (3952-4576)

Bkr 152-1601 *

$ 152-1901 Closed Inc Voltage (3952-4576)

Bkr 152-1706 *

$ 152-1902 Closed Inc Voltage (3952-4576)

  • Note: For these breakers VERIFY voltage is available to the ESF Bus by placing the Sync switch on 1 H13-P864 OR 1H13-P601 for the designated breaker to ON AND RECORDING incoming voltage. RETURN Sync switch to OFF after taking reading.

(1) Voltage indication from 1R25

-EI-R603 is NOT required to meet Tech Spec acceptance criteria.

Voltage indication is met by acceptable incoming voltage for breakers 152

-1514, 152-1601, AND 152-1706. SELECT phase of bus to be monitored by use of the voltage select switch. INSURE voltage select switch is NOT left in OFF.

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II Page 4 of 4 Page XRef Revision 0 9/21/2015 39 of 46 DATA SHEET I (Continued)

PLANT AC AND DC ELECTRICAL POWER DISTRIBUTION WEEKLY LINEUP SAFETY RELATED (Step 5.2.2)

RECORDED

VOLTAGE REQUIRED ACTUAL INSTRUMENT ACCEPTANCE BREAKER POSITION POSITION INITIALS COMMENTS (LOCATION)

CRITERIA Service Transformer 21

- Bus 21R to ESF 15AA, 16AB & 17AC

34.5kV Bus A-B = (1) $ 552-2105 Closed

21R Volt B-C =

(1)

2R25-EI-R603 C-A =

(1) $ 552-2104 Closed

(H13-P807-4B) (31.05-37.95kV)

Bkr 152-1501

  • Inc Voltage (3952-4576)

Bkr 152-1614 *

$ 152-2901 Closed

Inc Voltage (3952-4576)

Bkr 152-1705 *

$ 152-2902 Closed

Inc Voltage (3952-4576) 115 kV Line to ESF 15AA, 16AB & 17AC

$ J3885 Closed

N/A N/A

Bkr 152-1511

  • Inc Voltage (3952-4576)

Bkr 152-1611 *

$ 152-1903 Closed

Inc Voltage (3952-4576)

Bkr 152-1704 *

$ 152-1904 Closed

Inc Voltage (3952-4576)

  • Note: For these breakers VERIFY voltage is available to the ESF Bus by placing the Sync switch on 1H13

- P864 OR 1H13-P601 for the designated breaker to ON AND RECORDING incoming voltage.

RETURN Sync switch to OFF after taking reading. (1) Voltage indication from 2R25

-EI-R603 for Bus 21R is not required to meet Tech Spec acceptance criteria. Voltage indication is met by acceptable incoming voltage for breakers 152

-1501, 152-1614, AND 152-1705. SELECT phase of bus to be monitored by use of the voltage select switch. INSURE voltage select switch is NOT left in OFF.

ACCEPTANCE CRITERIA REFERENCE TECHNICAL SPECIFICATION REQUIRED ACTION(S)

IF ACCEPTANCE CRITERIA NOT MET FOR: SR 3.8.1.1

- Mode 1, 2, 3

- LCO 3.8.1 - Condition A, C, D two of the above circuits between the offsite

transmission network AND the onsite Class 1E

distribution system are Operable; correct breaker

lineup AND power available.

Revision 0 9/21/2015 40 of 46 GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment III Page 1 of 6 PAGE XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Operability Checksheet Technical Specifications: LCO 3.8.1, Required Action B.2

1.0 IMPAC

T STATEMENT 1.1 Performance of this procedure has no impact on plant operation.

2.0 PROCEDURE

2.1 Plant Mode is (circle one): 1 2 3 2.2 Test Start Time

/ /

Performer / Date Time

2.3 Radiation

Protection Review

RWP # 3.0 TES T RESULTS 3.1 Test Completion: (CHECK one in each category.)

Entire procedure completed [ ] Partial procedure completed [ ]

Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable

[ ] All other steps/data Acceptable [ ] Unacceptable [ ]

3.2 Comments

3.3 Test performed by Date/Time

/

4.0 DEFICIENCIES

CR Issued #

LCO Entered # WR Issued #

5.0 APPROVAL

Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]

Shift Supervisor. Date Comments:

CONCURRENCE Operations Management Date

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II I Page 2 of 6 Page XRef Revision 0 9/21/2015 41 of 46 DATA SHEET I OPERABILITY CHECKSHEET SAFETY RELATED 5.3.2 WHEN Div 1 D/G is declared Inop THEN the following items Shall be verified Operable per LCO 3.8.1, Required Action B.2.

OPERABLE INITIALS (YES/NO) 1. LPCI mode of RHR B System

2. LPCI mode of RHR C System
3. CTMT Spray mode of RHR B System
4. Suppression Pool Cooling mode of RHR B System
5. Shutdown Cooling mode of RHR B System (required in mode 3 only)
6. Suppression Pool Makeup System, Div 2
7. CTMT AND Drywell Isolation valves (Tables TR3.6.1.3

-1 AND TR3.6.5.3-1, Section 1), Div 2 (does NOT include AOVs OR closed/deenergized MOVs)

8. Post LOCA vacuum breaker AND Drywell purge vacuum relief subsystem, Div 2
9. Secondary CTMT Isolation valves (Table TR3.6.4.2

-1), Div 2 (does NOT include AOVs OR closed/deenergized MOVs)

10. Standby Gas Treatment B System
11. Hydrogen Recombiner System, Div 2
12. CTMT AND Drywell Hydrogen Ignition System, Div 2
13. Control Room Emergency Filtration System, Div 2
14. MSIV Leakage Control System, Div 2
15. FW Leakage Control System, Div 2

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OPERABILITY CHECKSHEET SAFETY RELATED OPERABLE INITIALS (YES/NO) 16. RHR B Room HVAC

17. RHR C Room HVAC
18. ESF SWGR Room HVAC, Div 2
19. Standby Liquid Control System, Div 2 20. Drywell Purge Compressor, Div 2
21. Battery Charger, Div 2 (either 1B4 or 1B5)
22. Safeguard Switchgear and Battery Room Ventilation, Div 2
23. HPCS System
24. Control Room Air Conditioning System, Div 2
25. Standby Service Water, Div 2 NOTE IF Safeguard Switchgear AND Battery Room Ventilation ,Div 2,is Inop, AFTER four hours ENTER Tech. Spec. LCO ACTION for TS 3.8.4, 3.8.5, 3.8.7 AND/OR 3.8.8 as applicable unless An engineering determination be made in accordance with Generic letter 91

-18 that the Degraded Z77 functi on Will maintain the power distribution system OPERABLE under the Current condition.

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II I Page 4 of 6 Page XRef Revision 0 9/21/2015 43 of 46 DATA SHEET II OPERABILITY CHECKSHEET SAFETY RELATED 5.3.2 WHEN Div 2 D/G is declared Inop THEN the following items Shall be verified Operable per LCO 3.8.1, Required Action B.2.

OPERABLE INITIALS (YES/NO) 1. LPCS System

2. LPCI mode of RHR A System
3. CTMT Spray mode of RHR A System
4. Suppression Pool Cooling mode of RHR A System
5. Shutdown Cooling mode of RHR A System (required in mode 3 only)
6. Suppression Pool Makeup System, Div 1
7. CTMT AND Drywell Isolation valves (Tables TR3.6.1.3

-1 AND TR3.6.5.3-1, Section 1), Div 1 (does NOT include AOVs OR closed/deenergized MOVs)

8. Post LOCA vacuum breaker AND Drywell purge vacuum relief subsystem, Div 1
9. Secondary CTMT Isolation valves (Table TR3.6.4.2

-1), Div 1 (does NOT include AOVs OR closed/deenergized MOVs)

10. Standby Gas Treatment A System
11. Hydrogen Recombiner System, Div 1
12. CTMT AND Drywell Hydrogen Ignition System, Div 1
13. Control Room Emergency Filtration System, Div 1
14. MSIV Leakage Control System, Div 1
15. FW Leakage Control System, Div 1

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II I Page 5 of 6 Page XRef Revision 0 9/21/2015 44 of 46 DATA SHEET II (Continued)

OPERABILITY CHECKSHEET SAFETY RELATED OPERABLE INITIALS (YES/NO) 16. LPCS Room HVAC

17. RHR A Room HVAC
18. ESF SWGR Room HVAC, Div 1
19. Standby Liquid Control System, Div 1
20. Drywell Purge Compressor, Div 1
21. Battery Charger, Div 1 (either 1A4 or 1A5)
22. Safeguard Switchgear and Battery Room Ventilation, Div 1
23. HPCS System
24. Control Room Air Conditioning System, Div 1
25. Standby Service Water, Div 1 NOTE IF Safeguard Switchgear AND Battery Room Ventilation ,Div 1,is Inop, AFTER four hours ENTER Tech. Spec. LCO ACTION for TS 3.8.4, 3.8.5, 3.8.7 AND/OR 3.8.8 as applicable unless An engineering determination Can be made in accordance with Generic letter 91

-18 that the Degraded Z77 function WILL maintain the power distribution system OPERABLE under the Current condition.

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II I Page 6 of 6 Page XRef Revision 0 9/21/2015 45 of 46 DATA SHEET III OPERABILITY CHECKSHEET SAFETY RELATED 5.3.2 WHEN Div 3 D/G is declared Inop THEN the following items Shall be verified Operable per LCO 3.8.1, Required Action B.2.

OPERABLE INITIALS (YES/NO) 1. LPCS System AND any two of the following:

LPCI mode of RHR A, B, C

2. Automatic Depressurization System (A OR B)

Give this page to the CRS

` Crew Turnover:

Turnover the following conditions:

Power 9 5% M OC EOOS GREEN The plant is currently in Power Ascension from 65% power for sequence exchange. Reactor Engineering is performing calculations and will notify you when to continue to raise power.

SSW A is operating per 04 03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.

Planned Evolutions this shift:

Rotate power on electrical bus 17AC from transformer ESF 12 to ESF 21.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 1 of 7 Revision 0 9/21/2015 Facility:

Grand Gulf Nuclear Station Scenario No.:

2 Op-Test No.: NRC LOT 201 5 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________

____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Start RHR A in Suppression Pool Cooling
2. Respond to a trip of RHR 'C' Jockey pump
3. Respond to a trip of CRD pump A

. 4. Respond to CRD Accumulator Faults. 5. Respond to a Suppression pool leak in RHR pump A suction piping while operating in Suppression Pool Cooling

. 6. Respond to both Heater Drain Pump Trip

. 7. Respond to Reactor Instrument Line Failure

8. Respond to Logic Power Failure to LPCS/RHR A
9. Division 2 ECCS High Drywell Pressure fail to Initiate
10. Respond to a Hotwell low level signal

. Initial Conditions:

Operating at 100% power.

Inoperable Equipment:

None Turnover:

The plant is at 100%. RCIC is tagged for maintenance. LCO 3.5.3 Condition A has been entered, HPCS is verified OPERABLE. Planned activities for this shift are:

Start RHR 'A' in Suppression Pool Cooling mode SSW A is operating in preparation for weekly chemical addition.

Scenario Notes:

This scenario is a NEW Scenario. Validation Time: 60 minutes

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 2 of 7 Revision 0 9/21/2015 Event No. Malf. No. Event Type f Event Description 1* N (BOP) TS (CRS) Start RHR 'A' in Suppression Pool Cooling (04 01-E12-1, Tech Spec 3.5.1 Condition A

) 2 DI_1E12M601C TS (CRS) RHR 'C' Jockey Pump Trip (Tech Spec 3.5.1 Condition C) 3* c11028a C (BOP) A (CREW) Respond to a Trip of CRD pump 'A' (CRD Malfunction ONEP, 05-1-02-I V-4) 4* z024_024_32_17 z024_024_36_21 C (ATC) A (CREW) Respond to two HCU Accumulator low pressure fault (SOI 04-1-01-C11-1; ARI 04-1-03-P680-4A2-D4) 5 ct218a C (BOP) TS (CRS) Respond to Suppression pool leak from RHR 'A' suction line

. (EP-3 & 4, EN-OP-115, Conduct of Operations, Tech Spec 3.6.2.2 Low suppression pool level Cond A) 6 fw231a & b C (ATC) A (CREW) R (ATC) Respond to both Heater Drain Pumps trip , (Loss of Feedwater Heating 05 02-V-5; Reduction in Recirculation System Flow Rate ONEP, 05 02-III-3) 7 rr062 M (CREW) Respond to Reactor Instrument Line Failure (EP-2) 8 r21219 r21220 I (CREW) Respond to Logic Power Failure to LPCS/RHR 'A' (Alarm Response Instruction, 04-1-03-P601-21A-H8, LPCS OOSVC) 9 rr040f rr041f I (CREW) Division 2 ECCS High Drywell Pressure fails to initiate , (EN-OP-120). 10 p680_2a_e_9 fw115a, b & c I (CREW) Respond to a false Hotwell low level signal (EP-2 , Alarm Response Instruction 04 03-P680-2A-E9, CNDSR HTWL LVL LO) f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

  • Repeated task from last 2 NRC exams.

Quantitative Attributes Table Normal Events 1 E O P Contingency Procedures Used 2 Total Malfunctions 7 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 Abnormal Events 4 Critical Tasks 3 Major Transients 1 Instrument/Component Failures 7 E O Ps Used (Requiring measurable action) 2 Reactivity Manipulations 1

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 3 of 7 Revision 0 9/21/2015 SCENARIO ACTIVITIES:

Start RHR 'A' in Suppression Pool Cooling A. After Crew has taken shift contact the CRS to place RHR 'A' in Suppression Pool Cooling beginning with step 5.2.2 a. (Event 1)

B. When Test Return to Supp Pool Valve E21-F024A is opened the CRS will determine that Tech Spec 3.5.1 Condition A applies.

RHR 'C' Jockey Pump Trip A. After Crew has placed suppression pool cooling in service, Tech Specs have been addressed and/or at the direction of the lead evaluator trigger Event 2 to cause RHR 'C' Jockey Pump breaker (52

-161135) to trip.

B. Crew will respond using Alarm Response Instructions.

C. If asked to investigate pump trip, wait 3 minutes and report breaker 52

-161135 is in the trip free condition.

D. CRS will declare RHR

'C' INOP and determine Tech Spec 3.5.1 Condition C applies.

E. Crew will rackout the breaker for RHR 'C' pump, 152-1609, to protect the piping.

Trip of CRD pump 'A'

A. After Tech Specs have been addressed and RHR 'C' pump breaker is racked out and/or at the direction of the lead evaluator trigger Event 3 to cause CRD pump 'A' to trip.

B. Crew will enter CRD Malfunction ONEP and perform immediate actions to start standby CRD Pump.

C. If asked to investigate pump trip:

1. Wait 3 minutes and respond as a Plant Operator and report "no apparent reason for pump trip and motor is hot to the touch
2. Wait 3 minutes and respond as Electrical Maintenance and report breaker 152

-

1505 has a 186 device tripped with Instantaneous flags on all three phases.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 4 of 7 Revision 0 9/21/2015 Two HCU Accumulator low pressure faults.

A. During the CRS pump trip of event 2 two HCU accumulators will indicate low pressure (Event 4) 1. One accumulator will clear when the standby pump is started.

2. If asked to provide local accumulator pressure, wait 5 minutes and report as plant operator that HCU 32

-17 is 1620 psig and HCU 36

-21 is 15 80 psig. B. The CRS will instruct to recharge HCU 36

-21 per ARI and SOI, 04 01-C11-1. C. No Tech Spec is required due to >1520 psig.

Suppression Pool Leak from RHR 'A' suction line.

A. After Immediate and Subsequent actions of CR D Malfunction ONEP and Tech Specs have been addressed and/or at the direction of the lead evaluator trigger Event 5 to cause a leak on the suction line of RHR 'A' system.

B. A leak will develop on the downstream side of the RHR MOV suction valve E12

-F004A. C. Crew should trip RHR 'A' pump and close suction valve E12

-F004A to isolate the leak. 1. After E12-F004A is closed the leak will stop.

D. The CRS should enter EP

-3 due to suppression pool water level below 18.34 FT.

E. The CRS should enter EP-4 due to Hi

-Hi RHR 'A' room sump and RHR 'A' room flooded. F. The CRS will determine that Tech Spec 3.6.2.2 Condition A applies due to low suppression pool level

. No other tech spec on 3.5.1 due to RHR 'A' was already INOP. Both Heater Drain Pumps Trip A. After EPs and Tech Specs have been addressed and/or at the direction of the lead evaluator trigger Event 6 to cause both Heater Drain Pumps to trip.

B. Crew will enter Loss of Feedwater Heating

, Feedwater System Malfunctions, and Reduction in Recirculation System Flow Rate ONEP s. C. Crew will reduce core flow to 70 Mlbm/hr per immediate operator actions.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 5 of 7 Revision 0 9/21/2015 Reactor Instrument Line Failure A. After all immediate and subsequent actions of ONEPS have been addressed and/or at the direction of the lead evaluator trigger Event 7 to cause Reactor Below Core Plate pressure instrument line break.

Drywell pressure will slowly rise causing the crew to take action to place the mode switch in SHUTDOWN.

B. Crew will enter EP

-2, EP-3, Turbine Trip and Reactor Scram ONEPs.

C. The leak propagate s into a Reactor Recirc line break that cause reactor level to reduce. LPCS / RHR 'A' Logic Power Failure A. The crew will recognize and respond to a fail to initiate on LPCS and RHR 'A' (Event 8) B. The crew will manually start the LPCS system (per ARI P601-21A-H8, LPCS SYS OOSVC, step 4.6) and manually (locally) open the injection valve

. Division 2 ECCS High Drywell Pressure fail to initiate A. One of the two drywell pressure transmitters for Division 2 ECCS to auto initiate fails low (Event 9), Div 2 ECCS will not auto initiate requiring the crew to manually initiate the Division 2 ECCS system. (RHR B only, RHR C is unavailable due to jockey pump loss)

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 6 of 7 Revision 0 9/21/2015 False Hotwell Level Low A. Two minutes after Mode Switch is taken to SHUTDOWN, a false Hotwell level low will occur (Event 10) causing a trip of all Condensate pump which will cause a trip of all Condensate Booster pumps and Feedwater pumps.

B. This failure will cause a loss of all high pressure feed systems.

C. Reactor water level will lower to <

-160" requiring an Emergency Depressurization.

D. Crew will restore reactor water level with LPCS (If manually started), RHR 'B' and HPCS (if injection valve is manually opened) Termination:

A. After Reactor water level is restored by LPCS, RHR 'B' and HPCS systems and is being controlled in band or as directed by Lead Evaluator Take the simulator to Freeze and turn horns off. Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow-up questions are asked.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 7 of 7 Revision 0 9/21/2015 Critical Task Number Description Bas i s 1 Open at least 7 SRVs when RPV water level is between

-160" and -190". If an injection source is available but the decreasing RPV water level trend cannot be reversed before RPV water level drops to the Minimum Steam Cooling RPV Water Level (-191 in.), emergency RPV depressurization is required to permit injection from low head systems, maximize flow from available injection sources, and minimize the flow through any primary system break.

(per 02-S-01-40, EP Technical Bases) 2 After Emergency Depressurization, restore and maintain RPV level above -191" using available injection systems prior to exiting EP-2. The Minimum Steam Cooling RPV Water Level is the lowest RPV water level at which the covered portion of the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500°F.

(per 02-S-01-40, EP Technical Bases) 3 When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig. Take manual actions (in accordance with procedure direction, if available) when automatic actions do not occur.

(per EN-OP-120, Operator Fundamentals Program). 300 psig is bases on maximum discharge pressure for RHR LPCI systems B and C injection is 285 psig.

  • Critical Task (As defined in NUREG 1021 Appendix D)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 1 of 23 Revision 0 9/21/2015 Simulator Setup:

A. Initialization

1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
4. Set the Simulator to IC-10 2 and perform switch check (Using Quick Reset in Director).
5. Click on "Open" in the Schedule window and Open Schedule File "201 5 NRC Scenario 2.sch" (in the Schedule Directory)
6. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 2 of 23 Revision 0 9/21/2015 7. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)

8. Take the simulator out of freeze.
9. Log on to all simulator PDS and SPDS computers.
10. Verify or perform the following:

IC-10 2 APRM's are turned on (4,1,2,3)

Ensure the MOC rod movement sequence available at the P680.

Advance all chart recorders and ensure all pens inking properly.

Clear any graphs and trends off of SPDS.

Ensure SSW A is aligned properly per 04-1-03-P41-1, SSW A Chemical Addition Run

. Marked up copy up to step 7.7 of 04 03-P41-1, SSW A Chemical Addition Run, is placed on CRS desk.

Marked up copy up to step 5.2.2 a of 04-1-01-E12-1 , Residual Heat Removal System

. Ensure CRD pump 'A' is in operation.

Ensure suppression pool temperature is 85 degrees F with alarms P870

-

3A-E4 and 10A

-E4. Ensure RCIC is tagged out of service RCIC OOSVS switches in the OOSVC position.

11. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

12. Place the simulator in Freeze.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 3 of 23 Revision 0 9/21/2015 B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 4 of 23 Revision 0 9/21/2015 Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 5 of 23 Revision 0 9/21/2015 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 100% M OC EOOS 10.0 GREEN Suppression Pool Temperature is 85

°F RCIC is tagged for maintenance. LCO 3.5.3 Condition A has been entered, HPCS is verified OPERABLE.

SSW A is operating per 04 03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.

C. Planned Evolutions this shift:

Place RHR 'A' in Suppression Pool Cooling. Operations Work Control and Duty Manager have been notified

. D. Allow the crew to perform pre

-shift brief and review procedures for planned evolutions.

E. Bring the crew into the Simulator, place the simulator is in RUN.

F. Allow the crew to walk down panels. G. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 6 of 23 Revision 0 9/21/2015 SCENARIO ACTIVITIES:

Start SBT report and any other required recording devices.

Emergency Classification:

Alert on FA1 (RC2). Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

1 Event

Description:

Start RHR 'A' in Suppression Pool Cooling TIME Position Applicant's Actions or Behavior CRS Directs BOP to start RHR 'A' system in Suppression Pool cooling mode.

BOP Using RHR SOI, 04 01-E12-1, section 5.2.2, performs the following on P601 panel: (1) START SSW A with flow through RHR A heat exchangers in accordance with SOI 04 01-P41-1, if not already in service.

(2) START RHR RM A FAN COIL UNIT on 1H13

-P870. (3) OPEN OR CHECK OPEN F003A, HX A OUTL VLV. NOTE Opening of F024A causes LPCI A Mode of RHR to be inoperable.

(4) START RHR A PMP.

(5) OPEN F024A, RHR A TEST RTN TO SUPP POOL.

(6) THROTTLE F048A, HX A BYP VLV as needed for suppression pool cooling.

IF needed to further reduce suppression pool cooling, THEN THROTTLE F003A, HX A OUTL VLV after F048A is full Open.

(7) CHECK F064A is still Closed, OR has Closed when RHR PMP A FLO exceeded 1000 gpm.

CRS Enters Tech Spec 3.5.1 condition A

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 7 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

2 Event

Description:

RHR 'C' Jockey Pump Trip TIME Position Applicant's Actions or Behavior BOP Recognizes and reports RHR 'C' Jockey pump trip by the following indications:

P601-17A alarms C4, RHR PMP C DISCH. PRESS ABNORMAL.

H3, RHR C SYS OOSVC JKY PMP OVERLD/PWRLOSS status light on 17B RHR 'C' Jockey Pump handswitch shows green and amber indication CRS Directs BOP to send operator to investigate.

BOP Directs operator and or electrical maintenance to investigate breaker 52

-161135. Booth If ask to investigate, wait 3 minutes and report as operator or electrical maintenance that breaker 52

-161135 is in the trip free position. Any other investigation will require a work order.

CRS Enters Tech Spec 3.5.1 Condition C Enters Tech Spec 3.3.6.4 Condition C Directs Plant operator to rack out RHR 'C' pump breaker, 152

-1609, to prevent any auto start due to no jockey pump running.

Booth If ask to rack out breaker 152

-1609, wait 5 minutes, trigger event 30 and report as operator that 152

-1609 breaker for RHR pump 'C' is racked out.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 8 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

3 Event

Description:

CRD pump 'A' trip TIME Position Applicant's Actions or Behavior BOP Recognize and notify crew loss of CRD pump 'A'

. Performs immediate operator actions from CRD Malfunctions ONEP and Starts standby pump by performing the following:

IF running CRD pump trips, THEN START standby CRD pump as follows: a. IF required, RE-ENERGIZE MCC's 15B42 AND 16B42 on 1H13

-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.

d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54

-66 gpm after charging pressure is normal.

e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54

-66 gpm. CRS Enters Control Rod/Drive Malfunctions ONEP, 05-1-02-IV-1 ATC Monitors for Accumulator Faults before standby pump start By monitoring for HCU TROUBLE (P680

-4A2-D4) alarm and/or HCU FAULT back lit pushbutton on RCIS control panel (P680

-6C) Monitors for Control Rod Drift after pump start.

By monitoring for CONT ROD DRIFT (P680

-4A2-E4) alarm and/or ROD DRIFT back lit pushbutton on RCIS control panel (P680

-6C) Booth If dispatched wait 3 minutes and report the following:

As Plant operator report 'A' CRD pump motor hot to the touch.

As Electrical Maintenance and report breaker 152

-1505 186 device is tripped with Instantaneously flags on all three phases

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 9 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

4 Event

Description:

HCU Accumulator Low Pressure Fault

TIME Position Applicant's Actions or Behavior ATC Receives HCU TROUBLE alarm on P680, Recognizes and reports Two HCU Accumulator Faults (32

-17 & 36-21) prior to standby pump starting, by depressing HCU FAULT pushbutton on P680.

After HCUs are identified the ATC should depress ACK N HCU FAULT per ARI P680-4A2-D4 to reset the HCU TROUBLE alarm and seal in the RCIS red indication .

Reports one Accumulator Fault (32-17) clears after standby pump starts.

Reports one Accumulator Fault (36

-21) is still sealed in.

BOP Dispatches Plant Operator to HCUs to investigate Fault alarms.

Booth If dispatched wait 4 minutes and report the following HCU pressures:

36-21 1610 psig 32-17 15 80 psig CRS Directs plant operator to recharge accumulator 32-17. Determines no Tech Specs apply due to pressure is above min of 1520 psig

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 10 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

5 Event

Description:

Suppression Pool Leak from RHR 'A' Suction Line TIME Position Applicant's Actions or Behavior BOP Recognizes Suppression Pool Leak from RHR 'A' by receiving RHR ROOM FLOODED alarm on P870

-2A-E1. Verifies with ATC that RHR RM 'A' Sump Level Hi

-Hi alarm is also in.

Reports to CRS/Crew entry into EP

-4. Trips RHR 'A' pump and closes E12

-F004A per 02

-S-01-43, Transient Mitigation Strategy.

Monitors and reports Suppression Pool level.

ATC Reports RHR RM 'A' Sump Level Hi

-Hi P680-8A1-A2 Reports to CRS/Crew entry into EP

-4. CRS Enters EP-4 when either alarm RHR ROOM FLOODED alarm on P870

-2A-E1 or RHR RM 'A' Sump Level Hi

-Hi P680-8A1-A2 is received.

Enters EP-3 when suppression pool level is <18.34 ft.

Directs the BOP to isolate the leak.

Enters Tech Spec 3.6.2.2 on Low Suppression Pool level, Tech Spec 3.6.1.7, RHR Containment Spray Tech Spec 3.6.2.3, RHR Suppression Pool Cooling Directs to raise Suppression Pool water level using normal P11 SOI.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 11 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

6 Event

Description:

Both Heater Drain Pumps Trip TIME Position Applicant's Actions or Behavior ATC Recognizes and reports Both Heater Drain Pumps Trip by the following indications:

P680-1A alarms A7 - HTR DR PMP A TRIP A8 - HTR DR PMP B TRIP P680-1C indications HTR DR PMP A handswitch green indication HTR DR PMP B handswitch green indication Perform immediate actions of Loss of Feedwater Heating ONEP, 05 02-V-5: Reduce Core Flow to 70 Mlbm/hr using both Recirc LOOP A CONT and LOOP B CONT, B33

-K603A & B, move the slide switches to the full left (i.e. fast detent) and verify core flow is lowering using B33

-R613 indicator of TOT JP FLO.

Maintain loop flow mismatch in Recirc system within 5% (2230 gpm)

If / When 70 Mlbm/hr is reached release the slide switches B33

-K603A & B. Note: Due to the partial loss of suction to the Feedwater pumps, Feedwater pump suction pressure will lower causing a trip of 'A' Feedpump.)

After Feedpump A trips and reactor water level reduces to the low alarm setpoint a Reactor Recirc FCV Runback will occur.

Release the Recirc Loop flow controllers and verify the runback completes.

CRS Enters Loss of Feedwater Heating ONEP, 05 02-V-5 and Reduction in Recirculation System Flow Rate ONEP, 05 02-III-3 and Feedwater Malfunction ONEP, 05 02-V-7 ATC After plant is stable, plots on Power to Flow map per Reduction in Recirculation System Flow Rate ONEP, 05 02-III-3, to determine region of operation.

Determines operation in the OPRM Trip Enable region and assumes THI watch with no concurrent duties.

BOP Verifies ATC plot on power to flow map.

Determines operation in the OPRM Trip Enable region

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 12 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

6 (cont.) Event

Description:

Both Heater Drain Pumps Trip (cont.) TIME Position Applicant's Actions or Behavior CRS After feedwater temperature, reactor power and core flow is stable directs ATC to have concurrent duties.

Dispatch plant operator to reset hi vibration alarm on Feedpump 'B' Booth If requested, reset hi vibration alarm on 'A' RFPT.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 13 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

7 Event

Description:

Reactor Instrument Line Failure TIME Position Applicant's Actions or Behavior ATC Recognizes and reports rising Drywell Pressure by the following indications:

PDS Computer point trend up P870 alarms P680 alarms o 4A1-A6 o 4A1-A7 o 8A1-B7 o 8A1-D7 P680 indicator B33

-UR-R613 RX CORE dP full upscale CRS Directs ATC to manually scram the reactor prior to exceeding scram setpoint

. Enters Turbine and Generator Trip, 05 02-I-2, Reactor Scram, 05-1-02-I-1, ONEPs and EP

-2 ATC Performs immediate operator actions for Turbine and Generator Trip, 05 02-I-2, and Reactor Scram, 05 02-I-1, ONEPs Place the Mode SW to SHUTDOWN as directed.

Provides a scram report:

o Reactor Mode SW in SHUTDOWN. o All Rods are Inserted. o Reactor power is 0%. o Reactor water level and trend.

Ensure Main Turbine Stop and Control Valves are CLOSED Ensure Both Generator Output Breakers are OPEN CRS Enters EP-2 RPV Control and EP

-3 Containment Control Verifies Reactor Mode Switch is in SHUTDOWN Evacuates affected areas

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 14 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

7 (cont.) Event

Description:

Reactor Instrument Line Failure (cont.) TIME Position Applicant's Actions or Behavior ATC Assumes Reactor water level control duties.

Aligns Condensate/Feedwater to Startup level control valve per hard card, 04 01-N19-1. IF two RFPTs are in operation, THEN TRIP one by DEPRESSING TRIP pushbutton.

CLOSE the following valves:

a. N21-F009A, FW HTR 6A OUTL VLV
b. N21-F009B, FW HTR 6B OUTL VLV.

OPEN the following valves:

a. N21-F001, SU FCV OUTL ISOL VLV.
b. N21-F010A, HP FW HTR STRNG A SU OUTL VLV.
c. N21-F010B, HP FW HTR STRNG B SU OUTL VLV.

VERIFY CLOSED the following valves:

a. N21-F513, X WTR LVL SU CONTR Valve (per controller 1C34

-LK- R602) b. N21-F510, FW CU RECIRC VLV

c. N21-F040, FW SU BYP VLV IF one RFPT is in service, THEN SELECT OR ENSURE in SPEED AUTO with discharge pressure approximately 250 psid above reactor pressure.

OPEN / VERIFY OPEN RFP A(B) DISCH VLV N21

-F014A(B) for at least one pump.

ADJUST N21-F513, RX WTR LVL SU CONT valve, as necessary in MANUAL OR AUTO to maintain desired Reactor level. N21

-F040 AND/OR N21-F009A(B) May be OPEN/CLOSED as necessary to augment flo

w.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 15 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

7 (cont.) Event

Description:

Reactor Instrument Line Failure (cont.) TIME Position Applicant's Actions or Behavior CRS Directs the BOP to Initiate each of the following which should have initiated but did not: Isolations ECCS initiation Emergency Diesel Generator BOP Verifies the following:

ECCS initiation (All on P601) o HPCS pump running with injection valve E22

-F004 open o LPCS pump running with injection valve E21

-F005 closed o RHR 'B' pump running with injection valve E12

- F042B closed Reports ECCS status to CRS:

o HPCS pump running with E22

-F004 breaker tripped no indication on valve o LPCS pump not running, E21

-F005 is closed. Recognize and report Logic Power Failure.

o RHR 'B' pump running with injection valve closed.

o RHR 'A' and 'C' not available.

Auxiliary Building / Containment / Drywell isolations (All on P870)

Reports isolation has gone to completion using the isolation status board as a quick reference and verifying the following alarms o P870 -9A-A4 & B3 o P870 -3A-A4 & B3 Emergency Diesel Generator start with cooling water Ensure Diesel running indication Ensure SSW A/B/C is aligned to provide cooling water to running diesel generators.

o SSW pump running A/B/C o SSW Discharge Valves are open P41

-F001A/B o SSW Supply to Diesel Generators Valves are open P41

-F018A/B o SSW Return Valves to Basin are open P41

-F005A/B, P41

-F011. Reports to CRS Emergency Diesel Generators start with cooling water Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 16 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

7 (cont.) Event

Description:

Reactor Instrument Line Failure (cont.) TIME Position Applicant's Actions or Behavior CRS Directs ATC to maintain Reactor Water level with a band of +11.4" to +53.5" ATC Using Startup level control valve supplied by Condensate and Feedwater in manual maintains level within band of +11.4" to +53.5"

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 17 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

8 Event

Description:

Logic Power Failure to LPCS/RHR A Logic TIME Position Applicant's Actions or Behavior BOP Recognize and report LPCS/RHRA Logic power failure from the following indications:

P601-21A-H8, LPCS OOSVC alarm P601-21B LPCS status light, LPCSLOGIC PWR FAIL LPCP PUMP handswitch has Green and Amber lights energized (pump not running).

P601-21B, LPCS/RHR A INIT light not energized.

Refers to ARI for P601

-21A-H8 for directions with logic power failure:

IF LPCS Power Failure status light is illuminated, THEN the following manual start of LPCS are effected as follows:

4.6.1 RHR A Can be manually started from P601 AND RSP. 4.6.2 Manual opening of E12

-F042A is from RSP only.

4.6.3 RHR A May be placed in Suppression Pool Cooling from P601 AND RSP with manual alignment of SSW A.

4.6.4 INITIATE

RCIC with ARM AND DEPRESS pushbuttons (RCIC Will NOT Auto Start).

4.6.5 E21-F005 CANNOT be opened manually OR automatically from P601 (Must be opened locally).

4.6.6 Containment

spray CANNOT be initiated automatically OR locally. 4.6.7 NO DIV I LOCA signal is received by LSS, D/G 11, ADS A, CGCS A, SSW A, OR RCIC. 4.6.8 E12-F064A will NOT open OR close automatically.

CRS Directs BOP to perform the following:

Manually start LPCS pump and ensure min flow valve opens.

Dispatch operators to be on standby to manually open E21

-F005 injection valve. Do NOT open before 476 psig reactor pressure.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 18 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

8 (cont.) Event

Description:

Logic Power Failure to LPCS/RHR A Logic (cont.)

TIME Position Applicant's Actions or Behavior BOP When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig.

Manually starts LPCS pump using handswitch on P601 panel Dispatch operators to standby E21

-F005, LPCS injection valve, be prepared to open manually upon request.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 19 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

9 Event

Description:

Division 2 ECCS High Drywell Pressure Fail to Initiate TIME Position Applicant's Actions or Behavior BOP Recognizes and reports a Division 2 ECCS (RHR 'B' and 'C')

failure to initiate on High Drywell pressure.

Per EN-OP-120, BOP will arm and depress the LPCS/RHR A MAN INIT pushbutton on P601

-21B Verifies the following:

RHR B pump starts and runs on minimum flow.

Division 2 EDG starts with cooling water When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig.

CRS Directs Division 2 ECCS to be manually initiated.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 20 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

10 Event

Description:

False Hotwell low level signal TIME Position Applicant's Actions or Behavior ATC Recognizes all Condensate Pumps trip.

(This will also cause all condensate booster pumps to trip and Feed pumps to trip)

Determines trip is from a false Low Condenser Level by observing P680-2A-E9, CNDSR HTWL LVL LO.

Uses ARI P680

-2A-E9 to determine that removal of relay N19 63X

-1/N105 will defeat the Hotwell low level trip on the Condensate system

o If desired by Shift Supervision, REMOVE relay N19 63X

-1/N105 will defeat the Hotwell low level trips. (1H13

-P849 Bay C, third row of relays from the top, sixth relay from the left).

Booth Do not defeat low Hotwell level trip until Emergency Depressurization has occurred. If requested to remove relay and after ED has occurred delete malfunctions with Event 8 CRS Enters Alternate Level Control leg of EP

-2 Directs to Inhibit ADS Verifies injection systems Calls for Table 2 systems to be lined up.

Directs ATC to monitor reactor water level as a critical parameter with frequent updates.

Directs for E22

-F004 to be manually opened BOP Inhibits ADS on P601 by taking ADS A MANUAL INHIBIT and ADS B MANUAL INHIBIT handswitches to the INHIBIT position and verifying the following indication:

P601-18A-H2, ADS/SRV A OOSVC alarm P601-19A-H2, ADS/SRV B OOSVC alarm White status light above each handswitch

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 21 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

10 (cont.) Event

Description:

False Hotwell low level signal (cont.) TIME Position Applicant's Actions or Behavior BOP Provides ECCS update and injection systems using ECCS status hard card.

Feedwater Currently unavailable HPCS pump running F004 Injection valve has no power LPCS Injection valve local manual operation only RHR A Unavailable due to leak RHR B pump running RHR C Unavailable due to loss of Jockey pump Dispatches operators to manually open E22

-F004, HPCS Injection valve locally. Booth If ask to manually open E22

-F004, wait 3 minutes and report attempting to open. ATC Monitors Reactor Water level, giving frequent updates Notifies CRS when

-160" Wide Range is met.

CRS At <-160" Wide range but before level reaches

-191" Fuel Zone an Emergency Depressurization is required.

Enters Emergency Depressurization leg of EP

-2 Verifies Suppression Pool level is above 10.5 ft.

Directs 8 ADS/SRVs opened.

Open at least 7 SRVs when RPV water level is between

-160" and -190".

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 22 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

10 (cont.) Event

Description:

False Hotwell low level signal (cont.) TIME Position Applicant's Actions or Behavior ATC/BOP Opens 8 ADS.SRVs on P601 by taking the following handswitches to the OPEN position:

B21-F041K B21-F047L B21-F041F B21-F047A B21-F051C B21-F051A B21-F041C B21-F051B Open at least 7 SRVs when RPV water level is between -160" and -190". Booth If requested to remove relay N19 63X

-1/N105 to bypass Lo Hotwell level trip on the condensate system, DELETE the malfunction in event 10 and report relay is removed.

If requested to manually open E22

-F004, HPCS Injection valve, report valve will not open manually CRS Directs to monitor for injection from Low ECCS systems If requested to remove relay N19 63X

-1/N105 to bypass Lo Hotwell level trip on the condensate system direct ATC to restart Condensate system and inject.

BOP Verify RHR 'B' injection valve E12-F04 2 B open s at 476 psig Reactor Pressure by the following P601 indication:

P601-17A-C3, LPCI B/C INJ VLV RPV PRESS LO alarm Red indication for valve E12

-F042B handswitch At approximately 300 psig reactor pressure, RHR PMP B DISCH FLO indication, E12

-R603B, is indicating injection flow.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 23 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

10 (cont.) Event

Description:

False Hotwell low level signal (cont.) TIME Position Applicant's Actions or Behavior Booth If requested to manually open E21

-F005, LPCS Injection valve, report valve will not open. ATC If requested to remove relay N19 63X

-1/N105 to bypass Lo Hotwell level trip on the condensate system, restart the condensate system.

Restart at least 2 Condensate pumps o Depress the START pushbutton for the desired pump Restart at least 2 Condensate Booster pumps o Depress the START pushbutton for the desired pump CRS Direct to control RPV water level within a band of

-30" to +50" Wide Range.

After Emergency Depressurization, restore and maintain RPV level above

-191" using available injection systems prior to exiting EP

-2. BOP/ATC After Emergency Depressurization, restore and maintain RPV level above

-191" using available injection systems prior to exiting EP

-2. Using RHR 'B' and if requested the following systems:

Condensate Maintain RPV water level within band

-30" to +50" Wide Range.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 24 of 23 Revision 0 9/21/2015 TERMINATION Once reactor water level is being controlled in band or as directed by Lead Evaluator:

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Revision 0 9/21/2015 Give this page to the CRS ` Crew Turnover:

Turnover the following conditions:

Power 100% M OC EOOS GREEN Suppression Pool Temperature is 85

°F RCIC is tagged for maintenance. LCO 3.5.3 Condition A has been entered, HPCS is verified OPERABLE.

SSW A is operating per 04 03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition Planned Evolutions this shift:

Place RHR 'A' in Suppression Pool Cooling mode

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 1 of 7 Revision 0 9/22/2015 Facility:

Grand Gulf Nuclear Station Scenario No.: 3 Op-Test No.:

NRC LOT 201 5 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________

____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Component Cooling Water Pump 'A' trip with Failure of Standby pump to Auto Start

. 2. MCC 17B01 Trip, HPCS System INOP

3. IRM Channel 'A' fails upscale
4. Loss of Power to ESF 15AA, with Diesel Generator restoring Bus

. 5. IRM Channel 'E' fails downscale

6. Condensate Booster Pump 'A' Trip

. 7. Component Cooling Water Pump 'B' and 'C' trip 8. Mode Switch Failure to Scram

. 9. Loss of Offsite Power with 15AA lockout

10. Division 2 Diesel Generator Fails to Auto Energize 16AB

. Initial Conditions:

Reactor startup in progress.

Reactor pressure is 400 psig Reactor power is 4% Inoperable Equipment:

None Turnover: A reactor startup is in progress.

Step 8 3 of Control Rod Movement Sequence is complete SJAE 'B' is in warm up 04 N62-1 step 4.2.2r Step 3 2 of Attachment XV in 03 01-1 The Condensate system is lined up as follows:

CFFF is in service Precoat Filters are not in service 4 Deepbed demins are in service Preps are being made to start the first Reactor Feedwater Pump Severe Weather is in the area, Tornado Watch is in affect Scenario Notes:

This scenario is a modified version of the 201 4 NRC Exam Scenario 5 (spare scenario, not used). Validation Time (60-90 min): 70 min Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 2 of 7 Revision 0 9/22/2015 Event No. Malf. No. Event Type f Event Description 1 p42151a C (BOP) A (CREW) Component Cooling Water Pump 'A' Trip with Failure of Standby Pump to Auto Start (05-1-02-V-1, Loss of Component Cooling Water ONEP, EN

-OP-120, 02-S-01-43) 2 R21142DD TS (CRS) MCC 17B01 Trip, HPCS System INOP (Tech Specs 3.5.1, 3.8.1, Loss of AC Power ONEP, 05 02-I-4) 3* c51004a C(ATC) TS (CRS) IRM Channel 'A' fails upscale (ARI P680-5A-A8, Tech Specs 3.3.1.1 and 3.3.2.1 potential) 4 DI_1R21M606A C (BOP) A (CREW) Loss of Power to ESF Bus 15AA with Diesel Restoring Bus (Loss of AC Power, 05 02-I-4, Loss of Instrument Air, 05 02-V-9 and Automatic Isolations, 05 02-III-5 ONEPs) 5 c5100 5 e TS (CRS) IRM Channel 'E' fails downscale (Tech Specs 3.3.1.1 and 3.3.2.1) 6 fw118a C (ATC) A (CREW) Condensate Booster Pump Trip (05-1-02-V-7, Feedwater System Malfunctions ONEP) 7 p42151b p42151c M (CREW) Component Cooling Water pumps 'B' and 'C' trip (05-1-02-V-1, Loss of Component Cooling Water , 05-1-02-I-1, Reactor Scram; 05 02-I-2, Turbine and Generator Trips ONEP, EP-2) 8 DI_1C71M602 C (ATC) Mode Switch Failure (EN-OP-115) 9 r21135 r21139e M (CREW) Loss of Offsite Power with ESF bus 15AA lockout (Loss of AC Power ONEP, 05 02-I-4) 10 n41142b C (BOP) Division 2 EDG fails to auto energize ESF Bus 16AB (Loss of AC Power ONEP, 05 02-I-4) f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

  • Repeated task from last 2 NRC exams.

Quantitative Attributes Table Normal Events 0 E OP Contingency Procedures Used 1 Total Malfunctions 8 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 Abnormal Events 6 Critical Tasks 2 Major Transients 2 Instrument/Component Failures 6 E O Ps Used (Requiring measurable action) 1 Reactivity Manipulations 0

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 3 of 7 Revision 0 9/22/2015 SCENARIO ACTIVITIES:

Component Cooling Water pump 'A' trip A. After turnover and/or at the direction of the lead evaluator, trigger Event 1 to cause CCW pump 'A' to Trip

. B. Standby CCW pump '

B' will fail to auto start

. C. The crew (BOP) will take the actions per EN-OP-120 and 05-1-02-V-1, Loss of Component Cooling Water ONEP and manually start the standby pump

. D. The CRS will enter 05-1-02-V-1, Loss of Component Cooling Water ONEP

. MCC 17B01 trip

A. After immediate, subsequent actions of all associated ONEPs have been addressed and at the direction of the lead evaluator, trigger Event 2 to cause a MCC 17B01 trip. B. The crew will recognize loss of 17B01 due to loss of power to HPCS MOVs and HPCS service water system.

C. The CRS will enter Loss of AC Power ONEP, and determine that TS 3.8.7Condition D1 and 3.5.1 Condition B applies. IRM Channel 'A' fails upscale A. After Tech Specs have been addressed and at the direction of the lead evaluator, trigger Event 3 to cause IRM channel 'A' to fail full upscale.

B. The crew will recognize a division 1 half scram and rod block.

C. The crew will perform action per ARI by bypassing the IRM channel and resetting the half scram condition.

D. The CRS will direct the bypassing of the IRM channel and the resetting of the half scram. E. The CRS will determine that NO Tech Specs are entered at this time but will refer to Tech Specs 3.3.1.1 and 3.3.2.1. Three channels are required.

CRS may enter a potential LCO.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 4 of 7 Revision 0 9/22/2015 Loss of Power to ESF bus 15AA with EDG Restoring Power:

A. When Tech Specs have been addressed and any briefs are complete, at the Lead Evaluator's discretion, trigger Event 4 to cause incoming feeder breaker 152

-15 14 to trip removing power to 15AA.

B. The crew will respond using 0 5-1-02-I-4, Loss of AC Power ONEP.

C. The BOP will verify EDG powers bus 15AA and restore Instrument Air to the Containment by opening P53

-F00 1 on P870 using 05 02-V-9, Loss of Instrument Air ONEP. (P53

-F00 1 fails closed on loss of power and must be manually re-opened) D. The CRS should also enter 05 02-III-5, Automatic Isolations ONEP and 05-1-02-III-1, Inadequate Decay Heat Removal ONEP (due to the loss of Fuel Pool Cooling and Cleanup)

. E. The CRS will determine that Tech Spec 6.4.1, Continuous conductivity monitoring applies. IRM Channel 'E' fails downscale A. After Tech Specs have been addressed, Immediate and subsequent actions of ONEPs and at the direction of the lead evaluator, trigger Event 5 to cause IRM channel 'E' to fail downscale. B. The crew will recognize 'E' IRM in the downscale indication with a control rod block

. C. The crew will perform action per ARI, but cannot bypass the IRM channel due to one is already bypassed in that division

. D. The CRS will determine that Tech Specs 3.3.1.1 and 3.3.2.1 apply. Condensate Booster Pump 'A' trip A. After all Tech Spec actions has been address and/or at the direction of the lead evaluator, trigger Event 6 to cause Condensate Booster Pump 'A' to trip.

B. The crew (ATC) will take action per 05 02-V-7, Feedwater System Malfunctions ONEP and manually start the 'B' or 'C' Condensate Booster Pump

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 5 of 7 Revision 0 9/22/2015 Loss of Component Cooling Water Pumps 'B' and 'C' A. After immediate, subsequent actions of all associated ONEPs have been addressed and at the direction of the lead evaluator, trigger Event 7 to cause CCW pumps 'B' and 'C' to trip.

B. The crew (ATC) will recognize the complete loss of CCW system, per 05 02-V-1, Loss of Component Cooling Water ONEP immediate action place the Mode switch to SHUT DOWN and trip Reactor Recirc Pumps

. Mode Switch Failure A. When the ATC places the Mode Switch to SHUTDOWN the mode switch will fail in STARTUP (Event 8), no scram signal will be present.

B. The ATC will manually scram the reactor by arming and depressing the 4 RPS Manual Scram Pushbuttons per EN-OP-115. C. The Crew will enter Scram and Turbine and Generator Trips ONEPs Loss of All Offsite Power with bus 15AA lockout

A. Two minutes after the mode switch is taken to shutdown all offsite power will be lost (Event 9).

B. The Crew will recognize bus 15AA will be locked out and remain de

-energized.

C. The CRS will enter EP

-2, and call for RCIC to be started to maintain level.

D. A small Recirc loop leak will occur.

Division 2 EDG fails to Auto Energize ESF Bus 16AB

. A. The BOP will recognize Failure of Division 2 EDG to auto energize bus 16AB (Event 1 0). B. The BOP will recognize Division 2 EDG is running and manually close the EDG feeder breaker to 16AB 152

-1608 from P864

. C. The BOP will verify the EDG powers the bus and recognize that Feeder breaker to 16BB3 is not closed by Green light on handswitch and alarm on P864

-2A-E3 D. The BOP will verify SSW B is supplying cooling water

. E. Dispatch operator and/or electrical to investigate loss of 16BB3.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 6 of 7 Revision 0 9/22/2015 F. 16BB3 feeds 16B31 MCC that supplies power to RHR 'B' valves required for injection.

G. Recognizes that RHR 'C' pump trip.

H. Dispatch operator and/or electrical to investigate RHR pump 'C' trip.

I. After 5 minutes or when water level reaches

-100 inches notify CRS that problem with 16BB3 has been found and waiting for control room to re

-energize also RHR 'C' pump problem has been corrected and ready for restart.

Termination:

A. Once RPV is restored within band or as directed by Lead Evaluator

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 7 of 7 Revision 0 9/22/2015 Critical Task Number Description Bas i s 1 Restore Instrument Air to the Containment prior to two or more control rods drifting.

When control rods to drift this could cause uneven flux distribution throughout the core which in turn could have detrimental effects reducing the margin of reactor safety limits.

2 When Reactor Mode Switch fails, manually insert a scram by depressing the RPS MANUAL SCRAM PUSHBUTTONS or Manual initiate ATWS/ARI prior to installing Attachment 21, "De

-energize scram solenoids.

Ensuring a reactor scram prevents entry into EP-2A (ATWS) procedure that would cause the crew to take compensatory actions that would complicate the event mitigation strategy.

3 Restore RHR B and/or C injection prior to level reaching TAF.

Maintaining adequate core cooling.

  • Critical Task (As defined in NUREG 1021 Appendix D)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 1 of 20 Revision 0 9/22/2015 Simulator Setup:

A. Initialization

1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
4. Set the Simulator to IC-10 3 and perform switch check (Using Quick Reset in Director).
5. Click on "Open" in the Schedule window and Open Schedule File "201 5 NRC Scenario 3.sch" (in the Schedule Directory)
6. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 2 of 20 Revision 0 9/22/2015 7. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)

8. Take the simulator out of freeze.
9. Log on to all simulator PDS and SPDS computers.
10. Verify or perform the following:

IC-10 3 APRM's are selected to IRM with NO digital readout.

Ensure the MOC rod movement sequence available at the P680.

Advance all chart recorders and ensure all pens inking properly.

Clear any graphs and trends off of SPDS.

Marked up copy of 03 01-1 Att. XV to step 30, Cold Shutdown to Generator Carrying Minimum Load Reactor Heatup and Pressurization, is placed on CRS desk.

Marked up copy of Control Rod Movement Sequence sheet completed through step 83.

11. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

12. Place the simulator in Freeze.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 3 of 20 Revision 0 9/22/2015 B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 4 of 20 Revision 0 9/22/2015 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 4% M OC EOOS GREEN Planned Evolutions this shift:

Continue with Plant Startup Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

C. Allow the crew to perform pre-shift brief and review procedures for planned evolutions.

D. Bring the crew into the Simulator, place the simulator is in RUN.

E. Allow the crew to walk down panels.

F. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 5 of 20 Revision 0 9/22/2015 SCENARIO ACTIVITIES:

Start SBT report and any other required recording devices.

Emergency Classification:

Site Area Emergency on SS6. Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

1 Event

Description:

Component Cooling Water Pump 'A' Trip with Failure of Standby Pump to Auto Start TIME Position Applicant's Actions or Behavior BOP Recognizes and reports trip of CCW pump 'A'.

P870-5A-B1, C1 & C2 P870-8A-E1, and B1 P870-2A-B1 Report failure of standby pump to start and manually starts standby pump '

B' per EN-OP-115 and EN

-OP-120 Verifies CCW header pressure returns to normal using P870 CCW Header pressure indicator P42-R600. ATC Recognizes and reports the following alarms:

P680-3A, A5, D5, A11, &

D11, CRS Enters Loss of CCW ONEP, 05 01-V-1 Directs the BOP to start standby pump

. Monitor CCW system parameters May enter Inadequate Decay Heat Removal ONEP for loss of cooling to Fuel Pool Cooling and Cleanup.

Booth If directed to investigate CCW pump 'A', wait 3 minutes and report locally motor is hot to the touch.

If directed to investigate pump breaker 52

-11506, wait 3 minutes and report overcurrent trip with lockout.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 6 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

1 (cont.) Event

Description:

Component Cooling Water Pump 'A' Trip with Failure of Standby Pump to Auto Start (cont.)

CRS Directs BOP to restore cooling water to Fuel Pool Cooling and Cleanup Heat exchangers.

BOP Performs the following to restore cooling to the Fuel Pool Cooling and Cleanup Heat Exchangers:

a. To place Both heat exchangers in service, PERFORM the following (Initial Condition: CCW Cooling to Both FPHXs is OOSVC):

(1) OPEN OR VERIFY OPEN F028A AND F032A, FPHX A Inlet AND Outlet valves, USING their respective handswitches CLG WTR INL TO FPHX A [2C] AND CLG WTR OUTL FM FPHX A [2C]. (2) OPEN F105 AND F205 by SIMULTANEOUSLY HOLDI NG Both of their respective handswitches, CCW SPLY TO FPHX A/B [2C] AND CCW RTN FM FP HX A/B [2C], to the OPEN position until alarm Clears (1H13

-P870 Section 2A Grid B

-1). (3) OPEN F203 USING CCW INBD INL TO FPHX B [2C] handswitch.

(4) OPEN F028B USING CCW OUTBD INL TO FPHX B [8C] handswitch.

(5) OPEN F032B USING CCW INBD INL FM FPHX B [8C] handswitch.

(6) OPEN F204 USING CCW OTBD OUTL FM FPHX B [2C] handswitch.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 7 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

2 Event

Description:

MCC 17B01 Trip TIME Position Applicant's Actions or Behavior BOP Recognizes and reports MCC 17B01 Trip by the following:

P601-16A-F1, G1, E4 alarms HPCS system indication P870-5A-E2, F1, F2, G1 alarms CRS Enters Loss of AC Power ONEP, 05 02-I-4 Recognizes HPCS system is INOP Directs Division 3 Diesel Generator to be placed in MAINTENANCE due to loss of cooling water pump.

Directs HPCS pump breaker 152

-1702 be racked out (down) due to loss of jockey pump.

Enters Tech Specs

3.8.7 Condition

D1

3.7.2 Condition

A1

3.5.1 Condition

B Booth If requested to investigate loss of 17B01, wait 3 minutes and report feeder breaker 152

-1703 is tripped with an 86 lockout device

. If requested to place Div 3 D/G in maintenance, wait 3 minutes and trigger event 30 , notify control room that Division 3 D/G is in Maintenance.

If requested to rackout HPCS pumps breaker 152-1702, wait 3 minutes and trigger event 28 , notify control room that the HPCS pump breaker 152

-1702 is racked out.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 8 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

3 Event

Description:

IRM Channel 'A' Fails upscale TIME Position Applicant's Actions or Behavior ATC Recognize and report division 1 half scram and indication of IRM 'A' full scale.

Receives the following P680 alarms: RPS CH A IRM UPSC TRIP INOP (5A-A8) IRM UPSC ALM (7A-A9) CONT ROD WITHDRAWL BLOCK (4A2-C5) HCU TROUBLE (4A2

-D4) RX SCRAM TRIP (7A-A2) NEUTRON MON SYS TRIP (7A-B3) Recognizes and reports the following:

Division 1 half scram.

Control Rod Block IRM channel '

A' indicating full upscale.

CRS Directs ATC to bypass IRM 'A' and reset division 1 half scram per ARI P680

-5A-A8 Refers to Tech Specs 3.3.1.1 and 3.3.2.1 and determine NO Tech Specs are in affect at this time, however, a potential LCO could be used.

Contacts I&C for investigation on IRM 'A'.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 9 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

3 (cont) Event

Description:

IRM Channel 'A' Fails upscale (cont.)

TIME Position Applicant's Actions or Behavior ATC Bypasses IRM 'A' using ARI P680

-5A-A8: 3.2 Observe the IRM recorders on 1H13

-P680. If IRM A or IRM E are not upscale, the alarm is due to inoperative equipment. Perform the following:

3.2.1 Bypass

the affected IRM channel until the cause of the inoperative condition is corrected.

3.2.2 Check

the module on 1H13

-P669 to help determine the cause of the INOP.

Reset the half scram using ARI P680

-5A-A8: 3.4 Reset the Half

-Scram by momentarily placing the RPS DIV 1 SCRAM RESET switch to the RESET position.

Verifies the following alarms are clear:

RPS CH A IRM UPSC TRIP INOP (5A

-A8) IRM UPSC ALM (7A

-A9) CONT ROD WITHDRAWL BLOCK (4A2

-C5) HCU TROUBLE (4A2

-D4) RX SCRAM TRIP (7A

-A2) NEUTRON MON SYS TRIP (7A

-B3) Booth If requested to investigate IRM 'A', wait 5 minutes and report unknown reason and work order is required for more investigation.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 10 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

4 Event

Description:

Loss of ESF Bus 15AA with Diesel Generator Restoring power TIME Position Applicant's Actions or Behavior BOP Recognizes and reports loss of 15AA.

Loss of indication on all 15AA components Loss of lighting inside the control room Multiple alarms on P864

-1A Within 10 seconds recognizes and reports Division 1 EDG has started and is supplying power to the 15AA bus.

Component indication returns Control room lighting returns to norma l Breaker 152

-1508, Feeder breaker from EDG Division 1, is closed Verifies SSW 'A' is supplying cooling water to EDG Division 1 SSW Pump 'A' is running P41-F001A, pump discharge OPEN P41-F005A, SSW system return to basin, OPEN P41-F018A, SSW supply to EDG Division 1, OPEN Recognize and report Division 1 Containment / Drywell isolation.

Verifies P53

-F001 closed on loss of power Re-opens P53-F001 per 05-1-02-V-9, Immediate Operator Actions o Determine cause for loss of Instrument Air and Attempt to restore. Restore Instrument Air to the Containment prior to two or more control rods drifting.

CRS Directs the BOP to verify power is restored to 15AA.

Directs the BOP to restore instrument air to the containment / Drywell.

Directs ATC to monitor for Control Rod Drifts Enters the following ONEPs:

Loss of AC Power, 05 02-I-4 Automatic Isolations, 05 02-III-5 Loss of Instrument Air, 05 02-V-9 Inadequate Decay Heat Removal, 05 02-III-1 Dispatch personnel to determine reason for loss of 15AA (Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 11 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

4 (cont.) Event

Description:

Loss of ESF Bus 15AA with Diesel Generator Restoring power (cont.) TIME Position Applicant's Actions or Behavior Booth If requested to investigate loss of 15AA, wait 3 minutes and report breaker 152

-151 4 has tripped.

CRS Directs BOP to initiate SBGT per Loss of AC Power ONEP:

3.1.5 IF Aux building isolation dampers closed on loss of power THEN DEPRESS SGTS DIV 1(2) MAN INIT pushbuttons (A AND C for Division 1, B AND D for Division 2).

Directs BOP to restore systems from isolation per Automatic Isolations ONEP step 3.5.3, and Attachment II BOP Manually initiates SBGT by performing the following:

3.1.5 IF Aux building isolation dampers closed on loss of power THEN DEPRESS SGTS DIV 1(2) MAN INIT pushbuttons (A AND C for Division 1, B AND D for Division 2).

CRS Directs BOP to perform the following from the Loss of AC Power ONEP

Reset NSSSS isolation logic Open/check open P41

-F239 and F240 BOP Performs the following per loss of AC Power ONEP

3.1.8 On 1H13-P601 panel, RESET respective DIV 1 (2) NSSSS isolation logic IF possible. Depresses the NSSSS INBD ISOL RESET and NSSSS OTBD ISOL RESET pushbuttons.

Verifies alarm P601

-E4, MSIV DR VLV TRIP INIT, resets.

3.1.9 IF power was lost to Bus 15AA, THEN OPEN/CHECK OPEN the following valves on P870-1C: a. 1P41-F239 b. 1P41-F240 Booth If requested to reset RCIS, wait 3 minutes and trigger event 29, notify control room that RCIS is reset.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 12 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

5 Event

Description:

IRM 'E' Fails Downscale TIME Position Applicant's Actions or Behavior ATC Recognizes and reports IRM 'E' fails downscale by the following P680 alarms and indication:

4A2-C5, CONT ROD WITHDRAWAL BLOCK 7A-B9, IRM DNSC IRM 'E' indicator full downscale 7C2, DOWNSCALE status light.

CRS Determines the following Tech Spec: 3.3.1.1 Condition A1 TRM 3.3.2.1 Directs I&C to investigate IRM 'E' Booth If requested to investigate IRM 'E', wait 3 minutes and report cannot determine problem will require a work order.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 13 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

6 Event

Description:

Condensate Booster Pump 'A' Trip TIME Position Applicant's Actions or Behavior ATC Recognizes and reports Condensate Booster Pump

'A'[ Trip Starts available Condensate Booster pump per ONEP 05 02-V-7, Feedwater Malfunctions ONEP 2.2 IF Reactor water level is lowering OR a Condensate pump, Condensate Booster pump OR Heater Drain pump has tripped, THEN PERFORM the following as required to maintain Reactor water level : 2.2.1 REDUCE Reactor Core Flow to 70 Mlbm/hr with Reactor Recirculation flow, MAINTAINING within power to flow limitations.

2.2.2 INITIATE

RCIC. 2.2.3 START standby Condensate, Condensate Booster, AND Reactor Feed Pumps as needed.

Depresses START pushbutton for Condensate Booster Pump 'B' or 'C'.

Verifies Reactor water level rising and being maintained by Startup Level Control Valve.

CRS Enters 05-1-02-V-7, Feedwater System Malfunctions ONEP.

Directs ATC to start standby Condensate Booster Pump Booth If dispatched by control room, wait 3 minutes and report problem unknown, can't be repaired without work order.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 14 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

7 & 8 Event

Description:

Component Cooling Water Pumps 'B' and 'C' trip

/ Mode Switch Failure BOP Recognizes and reports Total Loss of CCW. ATC Performs the following per Loss of CCW ONEP immediate Operator Actions:

2.1 If a complete loss of CCW occurs, Then perform the following:

2.1.1 Manually

SCRAM the reactor.

2.1.2 Manually

TRIP Reactor Recirc Pumps.

Places the Mode switch to SHUTDOWN Recognizes and reports MODE switch failure.

Arms and Depresses 4 RPS Manual Scram pushbuttons When Reactor Mode Switch fails, manually insert a scram by depressing the RPS MANUAL SCRAM PUSHBUTTONS or Manual initiate ATWS/ARI prior to installing Attachment 21, "De

-energize scram solenoids.

Trips the Reactor Recirc Pumps on the P680 by depressing CB2 TRIP pushbutton or depressing the STOP LOCK push button on CB5 CRS Enters Loss of CCW ONEP (Total Loss)

Directs ATC to manually scram the reactor and trip Reactor Recirc Pumps

. Enters Turbine and Generator Trip, 05 02-I-2, Reactor Scram, 05 02-I-1, ONEPs and EP

-2 ATC Performs immediate operator actions for Turbine and Generator Trip, 05 02-I-2, and Reactor Scram, 05 02-I-1, ONEPs Place / Verify the Mode SW to SHUTDOWN as directed.

Provides a scram report:

o Reactor Mode SW in SHUTDOWN.

o All Rods are Inserted. o Reactor power is 0%. o Reactor water level and trend.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 15 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

7 & 8 (cont.)

Event

Description:

Component Cooling Water Pumps 'B' and 'C' trip / Mode Switch Failure (cont.) CRS Directs ATC to maintain level control with a level band of

+11.4" to +53.5" Narrow Range ATC Maintains reactor water level with startup level control and the Condensate system. (already on the startup level control valve)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 16 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

9/10 Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB CREW Recognize and report loss of offsite power.

CRS Enters Loss of AC Power ONEP, 05 02-I-4 BOP Recognize ESF buses 15AA and 16AB are not energized by their respective Diesel Generator.

Per Loss of AC Power ONEP, 05 02-I-4, immediate operator actions

2.1 ENERGIZE

affected bus through an alternate feeder breaker OR its respective diesel generator.

Attempts to close Diesel Generator feeder breaker to 15AA, 152

-1508. Recognize and reports 152-1508 did not close and ESF bus 15AA is lockout and will not energize Attempts to close Diesel Generator feeder breaker to 16AB, 152-1608. Recognize and reports 152

-1608 closes and 16AB is energized.

Recognizes and reports LCC 16BB3 did not re

-energize. CRS Directs plant operator and/or electrical to investigate loss of 16BB3.

Directs ATC to maintain reactor water level using RCIC at a band of 11.4" to 53.5" Booth If requested to investigate loss of 16BB3 LCC, wait 3 minutes and report as plant operator or electrical that feeder breaker 52

-16301 has tripped and are investigating the cause.

ATC Monitors Reactor water level and initiates RCIC when required to maintain reactor water level in band by performing the following:

1. ARM AND DEPRESS RCIC MAN INIT pushbuttons
2. VERIFY SSW A is running with adequate flow path.

(SSW A in unavailable due to loss of 15AA)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 17 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

9/10 (cont.) Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.) ATC/BOP Recognizes and reports Drywell pressure rising and reactor water level lowering. When Drywell pressure reaches 1.39 psig, verifies and reports ECCS initiations.

(Division 2 ECCS is the only division available due to Div 1 and 3 has no power) Recognizes and reports the following:

RHR 'C' pump has tripped RHR 'B' pump is running, however multiple MOVs have no power due to loss of 16BB3.

CRS Re-enters EP-2 and enters EP-3 due to drywell pressure.

Directs to verify:

Initiations Isolations Emergency Diesel Generator start.

Request ECCS status report.

Directs plant operator and/or electrical to investigate RHR 'C' trip.

BOP Verifies the following:

ECCS initiation Auxiliary Building / Containment / Drywell isolations Emergency Diesel Generator start with cooling water Reports to CRS Booth If requested to investigate RHR 'C' pump trip, wait 3 minutes and report as plant operator and / or electrical that breaker 152-1609 has tripped and are investigating the cause.

ATC Recognizes and reports reactor water level lowering with RCIC injection.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 18 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

9/10 (cont.)

Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.) CRS Enters Alternate Level Control leg of EP

-2 Directs to Inhibit ADS Calls for Table 2 systems to be lined up.

o Attachment 26 through any or all of the following:

LPCS, HPCS, and RHR 'A' Directs ATC to monitor reactor water level as a critical parameter with frequent updates.

ATC Reports lowering level trend

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 19 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

9/10 (cont.)

Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.) TIME Position Applicant's Actions or Behavior Booth If crew has requested electrical to investigate breaker 52

-16301, when reactor water level reaches -100" wide range, contact control room with the following information:

Delete malfunction for 16BB3 trip 52-16301 feeder breaker to 16BB3 has been repaired Ready for the control room to attempt to close the breaker.

Restore RHR B and/or C injection prior to level reaching TAF CRS Direct s BOP to close 52

-16301 breaker to energize LCC 16BB3.

BOP Closes breaker 52

-16301 on panel P864

-2C. Verifies breaker closes and components gain indication of power.

CRS Directs ATC to verify injection from RHR 'B'. ATC Verifies and reports E12

-F042B, RHR Injection valve, auto opens or manually open the valve.

Verifies and reports injection flow on P601

-17B using E12

-R603B Booth If crew has requested electrical to investigate RHR 'C' pump, contact control room with the following information:

Delete RHR 'C' pump trip Report that breaker 152

-1609 is repaired and ready for start attempt.

CRS Directs BOP start RHR 'C' pump (if needed for level control)

. (Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 20 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

9/10 (cont.)

Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.) BOP Starts RHR 'C' pump on P601 panel

. Places handswitch for RHR 'C' pump to STOP then to START.

Verifies and reports pump starts and E12

-F042C is Open.

Verifies and reports injection flow on P601

-17B using E12

-R603 C Restore RHR B and/or C injection prior to level reaching TAF CRS Directs ATC to maintain reactor water level with a band of

-30" to + 50" wide range using the following systems:

RHR 'B" RHR 'C' RCIC (Critical TASK in BOLD)

TERMINATION Once reactor water level is being controlled in band or as directed by Lead Evaluator:

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Revision 0 9/22/2015 Give this page to the CRS ` Crew Turnover:

Turnover the following conditions:

Power 4% Mode 2 M OC EOOS GREEN A reactor startup is in progress.

Step 8 3 of Control Rod Movement Sequence is complete SJAE 'B' is in warm up 04 N62-1 step 4.2.2r The Condensate system is lined up as follows:

CFFF is in service Precoat Filters are not in service 4 Deepbed demins are in service

Planned Evolutions this shift:

Continue with plant startup per IOI

-1 Attachment XV step 30.

Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 12/7/201 5 Examination Level: RO SRO Operating Test Number: LOT-201 5 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - M Loss of Shutdown Cooling, Time to 200F Determination GJPM-OPS-2015-AR1 Conduct of Operations R - D Fire Door Surveillance GJPM-OPS-2015-AR2 Equipment Control R - N Electrical Print Reading (Determine effect of removing fuses in RPS system)

GJPM-OPS-2015-AR3 Radiation Control Emergency Plan R - M Station Blackout Electrical Power Determination GJPM-OPS-2015-AR4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from (N)ew or (M)odified from

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015-AR1 JPM Title: Loss of Shutdown Cooling, Time to 200°F Determination JPM JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review: Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 2 of 7 Loss of Shutdown Cooling, Time to 200°F Determination JPM Time Critical Alternate Path Validation Time:

30 Min Setting: Classroom Type: RO Task: CRO-E12-11 K&A: 2.4.11- 3.4/3.6 Safety Function:

N/A Performance:

Actual Reference(s):

05-1-02-III-1 Handout(s) 05-1-02-III-1 # Manipulations:

N/A # Critical Steps:

1 Simulator Setup/Required Plant Conditions

None Safety Concerns
None. Task Standard
Determine the time to 200°F in the reactor following the loss of shutdown cooling IAW 05-1-02-III-1.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

On day 5 of a refueling outage the following conditions exist: Preparation for drywell head removal is in progress.

Reactor water level is being maintained 245" to 255" Shutdown Range.

Reactor coolant temperature is 1 4 5°F. RHR A is lined up and providing shutdown cooling through the E12

-F053 A. Neither RHR nor ADHR is available due to the situation.

RWCU is available.

Initiating Cue(s):

Determine the time available before reactor coolant temperature reaches 200°F

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 4 of 7 Loss of Shutdown Cooling, Time to 200°F Determination JPM Notes: (Notes to Evaluator)

None. Task Overview:

(Detailed description of task)

This task has the student to estimate time to reach 200°F following loss of shutdown cooling. Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-1-02-III-1, Attachment 1

  • Using given information, determines time to boil is approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Standard: The operator determines using procedure 05 02-III-1 Attachment I, Figure 2 that there are about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 200°F

. Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 5 of 7 Task Standard(s)
Determine the time to 200°F in the reactor following the loss of shutdown cooling IAW 05-1-02-III-1. SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR1 Revision 0 GJPM-OPS-2015AR1 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015A R1 JPM Title: Loss of Shutdown Cooling, Time to 200°F Determination JPM Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

On day 5 of a refueling outage the following conditions exist: Preparation for drywell head removal is in progress.

Reactor water level is being maintained 245" to 255" Shutdown Range.

Reactor coolant temperature is 1 45°F. RHR A is lined up and providing shutdown cooling through the E12

-F053A. Neither RHR nor ADHR is available due to the situation.

RWCU is available.

Initiating Cue(s):

Determine the time available before reactor coolant temperature reaches 200°F

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015-AR2 JPM Title: Fire Doors Surveillance Facility Number:

GJPM-OPS-2011AR1____ (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time:

15 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 2 of 7 Electrical Print Reading Setting: Classroom Type: RO Task: CRO-P64-NORM-7 K&A: 2.1.20 (4.6/4.6) 2.2.12 (3.7/4.1)

Safety Function

NA Time Required
20 minutes Time Critical: No Faulted: No Performance
Actual Reference(s)
06-OP-SP64-M-0043, Fire Doors Alarm Check Handout(s)
06-OP-SP64-M-0043, Procedure Body 06-OP-SP64-M-0043, Fire Doors Alarm Check (Attachment 1 prepared)
  1. Manipulations
NA # Critical Steps
2 Simulator Setup/Required Plant Conditions
None Safety Concerns: None Date of Examination: 12/07/2015 Operating Test Number
LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant is operating at rated power.

06-OP-SP64-M-0043 step 5.2.1 and 5.2.2 are performed as required by another operator.

The CRS directs you to perform a partial 06-OP-SP64-M-0043, Fire Doors Alarm Check on the following doors: (1) Elect Pen Rm 1A221 door number 1A212, (2) Emerg S/D Rm OC208A door number OC208, and (3) Sec Ctmt Door 1A604.

You note the following items during your inspection:

o Elect Pen Rm 1A221 door 1A212:

Door does not latch after being fully opened and allowing the closure mechanism to pull the door shut; however, when you pull the door it latches.

Does not alarm upon opening.

o Emerg S/D Rm OC208A door OC208:

Has a deep gouge/dent 10" long on one side on the bottom right quadrant but does not penetrate the door skin.

Seam has separated next to the 10" gouge.

Alarms after 30 seconds upon opening.

o Sec Ctmt Door 1A604:

Has a rust patch on the A ux Building Roof side that has left a 3 in 2 hole in the skin of the door (the inside door skin is not damaged).

Has not alarmed 4 minutes after opening.

Initiating Cue(s):

Complete the attached 06

-OP-SP64-M0043, Fire Doors Alarm Check surveillance, including all portions of Attachment 1 Cover Sheet sections 2.0 and 3.0. Only mark Tech Spec Acceptance Criteria as Acceptable if REQUIRED by 06-OP-SP64-M-0043 surveillance procedure. Note reasons for marking Tech Spec Acceptance Criteria or other steps/data in the test results section as "Acceptable" or "Unacceptable" on the back of the surveillance coversheet.

All prerequisites are verified met.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will perform a Fire Door Alarm Check using the information provided in the initiating ques. The operator will discover tech spec door OC208 is INOP, tech spec door 1A212 is OPERABLE but requires a WR to fix the closing mechanism, and non

-tech spec door 1A604 also requires a WR to fix the security alarm timing and a rust patch. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06-OP-SP64-M-0043

  • The operator evaluates the given conditions for each fire door given in the initiating cues and determines the following:
  • Tech Spec Door 1A212 Tech Spec Acceptance Criteria is "Unacceptable," and step 5.2.6 other steps/data is "Unacceptable" because the closing mechanism will not shut the door without assistance (see note for step 5.2.6).
  • Tech Spec Door OC208 fails step 5.2.5c; however, the Tech Spec Acceptance Criteria for this surveillance is "Acceptable" (see note for step 5.2.5). The other steps/data is "Unacceptable".

Tech Spec Door OC208 is INOP since it fails step 5.2.5c.

  • Door 1A604 is not a Tech Spec door; therefore, Tech Spec Acceptance Criteria is NA. Step 5.2.5a data is "Unacceptable" because the outside door skin is visibly damaged with a hole > 3/16".

Standard: The deficiencies noted above are recorded on the surveillance cover sheet.

Cue: Notes: This meets the requirement for step 3.2 on the surveillance coversheet. Any words that demonstrate an equivalent understanding is acceptable.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 5 of 7 Step 2: 06-OP-SP64-M-0043
  • Complete the surveillance coversheet section 3.1 by checking boxes for:

(1) Partial procedure complete, (2)* Tech Spec Acceptance Criteria Unacceptable, and (3)* All other steps/data Unacceptable

. Standard: Checks appropriate boxes.

Cue: Notes: SAT / UNSAT Step 3: 06

-OP-SP64-M-0043 Complete the surveillance coversheet sections 2.1, 2.2 and 3.3 Standard: Circle for the plant being in Mode 1 and record themselves as performer with the date and time.

Cue: Notes: JPM is completed when the operator completes the surveillance package coversheet.

SAT / UNSAT Task Standard(s)

The operator determines that the Tech Spec Acceptance Criteria is "Unacceptable" and that All other steps/data is "Unacceptable" per 06-OP-SP64-M-0043. SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR2 Revision 0 GJPM-OPS-2015AR2 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AR2 JPM Title: Fire Doors Surveillance Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

Give this page to the student Initial Condition(s):

The Plant is operating at rated power.

06-OP-SP64-M-0043 step 5.2.1 and 5.2.2 are performed as required by another operator.

The CRS directs you to perform a partial 06-OP-SP64-M-0043, Fire Doors Alarm Check on the following doors: (1) Elect Pen Rm 1A221 door number 1A212, (2) Emerg S/D Rm OC208A door number OC208, and (3) Sec Ctmt Door 1A604.

You note the following items during your inspection:

o Elect Pen Rm 1A221 door 1A212: Door does not latch after being fully opened and allowing the closure mechanism to pull the door shut; however, when you pull the door it latches.

Does not alarm upon opening.

o Emerg S/D Rm OC208A door OC208:

Has a deep gouge/dent 10" long on one side on the bottom right quadrant but does not penetrate the door skin.

Seam has separated next to the 10" gouge.

Alarms after 30 seconds upon opening.

o Sec Ctmt Door 1A604:

Has a rust patch on the Aux Building Roof side that has left a 3 in 2 hole in the skin of the door (the inside door skin is not damaged).

Has not alarmed 4 minutes after opening.

Initiating Cue(s):

Complete the attached 06

-OP-SP64-M0043, Fire Doors Alarm Check surveillance, including all portions of Attachment 1 Cover Sheet sections 2.0 and 3.0. Only mark Tech Spec Acceptance Criteria as Acceptable if REQUIRED by 06-OP-SP64-M-0043 surveillance procedure. Note reasons for marking Tech Spec Acceptance Criteria or other steps/data in the test results section as "Acceptable" or "Unacceptable" on the back of the surveillance coversheet.

All prerequisites are verified met.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 1 of 7 GGNS 2012 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5AR 3 JPM Title: Electrical Print Reading Facility Number:

N/A (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time:

15 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 2 of 7 Electrical Print Reading Setting: Classroom Type: RO/SRO Task: SRO-ADMIN-ADMIN-48/CRO-ADMIN-005 K&A: 2.2.15 (3.9/4.3)

Safety Function

N/A Time Required
15 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
E-1173-019 Handout(s)
E-1173-019 # Manipulations
N/A # Critical Steps
1 Group: N/A Simulator Setup/Required Plant Conditions
None Safety Concerns
None Date of Examination: 12/07/2015 Operating Test Number
LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is operating at rated power.

I&C wants to replace fuses C71

-F14A and C71

-27D. Initiating Cue(s):

Determine what effect removing C71

-F14A and C71

-27D will have on the plant.

This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 4 of 7 Fire Doors Surveillance Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will use the provided electrical prints to prove that removing fuses, C71

-F14A and C71-27D, causes a Division 1 half scram

. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: E-1173-019

  • Using E-1173-019, determine the effect of removing fuses, C71

-F14A and C71-27D.

  • Removing C71

-F14A will de

-energize K14A and K14E relays inserting a Division 1 half scram.

  • Removing C71

-27D will de

-energize the white light for Reactor Scram Trip Logic "D".

Standard: Removing C71

-F14A will de

-energize K14A and K14E relays inserting a Division 1 half scram.

Removing C71-27D will de

-energize the white light for Reactor Scram Trip Logic "D". Cue: Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 5 of 7 Task Standard(s)
The operator will use the provided electrical prints to prove that removing fuses, Removing C71

-F14A will de

-energize K14A and K14E relays inserting a Division 1 half scram.

Removing C71

-27D will de

-energize the white light for Reactor Scram Trip Logic "D". SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AR3 Revision 0 GJPM-OPS-2015AR3 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015A R 3 JPM Title: Electrical Print Reading Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: __________________________________

__________________

Examiner's Signature:

___________________________________________________

Give this page to the student

Initial Condition(s):

The plant is operating at rated power.

I&C wants to replace fuses C71

-F14A and C71

-27D.

Initiating Cue(s):

Determine what effect removing C71

-F14A and C71

-27D will have on the plant.

This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 1 of 7 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015-AR 4 JPM Title: Station Blackout Table 1 Determination JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min

Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By: Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 2 of 7 Admin Task: Station Blackout Table 1 Determination Setting: Classroom Type: RO Task: NA K&A: 2.4.11 (4.0/4.2) 2.1.20 (4.6/4.6) 2.1.25 (3.9/4.2)

Safety Function

NA Time Required
15 minutes Time Critical
No Faulted: No Performance
Actual Reference(s)
Loss of AC Power ONEP, 05 02-I-4 Handout(s)
Loss of AC Power ONEP, 05-1-02-I-4 # Manipulations
NA # Critical Steps
1 Group: NA Simulator Setup/Required Plant Conditions
None Safety Concerns
None Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 3 of 7 Initial Condition(s):

The Plant has experienced a station blackout concurrent with a LOCA.

The HPCS pump is not available for operation.

Division 3 diesel generator is supplying power to the 1 5 A A bus.

Initiating Cue(s):

Determine how many KW must be available on the 17AC bus in order to support the operation of FPCCU supplemented with RHR A including all auxiliary and support systems

. Do not include HPCS Diesel Auxiliaries as a requirement to support FPCCU and RHR A operation.

All prerequisites are verified met.

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 4 of 7 Admin Task

Station Blackout Table 1 Determination Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will use Table 1 of the Loss of AC ONEP to determine the load requirements to run RHR A. Tasks: Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 05-1-02-I-4 Table 1

  • The operator determines the following required essential loads for FPCCU and RHR A operation:
  • SSW Pump 997 KW
  • RHR A Pump 803 KW
  • ESF SWGR Battery Fans 122 KW ESF Battery Charger 110 KW
  • ECCS Room Cooler 8 KW
  • SSW O/A Fan 40 KW
  • FPCCU Pump 124 KW Total require d KW available = 2647.5 or 2537.5 if Battery Charger was included.

Standard: Determines the correct loads and total required power to run FPCCU and RHR A. Cue: Notes: Accommodations for rounding errors are acceptable.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 5 of 7 Task Standard(s)

The operator determines a minimum of 2537.5 KW is required to operate FPCCU and RHR A. SAT / UNSAT Name: ___________________________

Time Start: _______

Time Stop: _______

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Revision 0 GJPM-OPS-2015A R 4 Page 6 of 7 Applicant:

____________________________________________________________

JPM Number: GJPM-OPS-2015AR4 JPM Title: Station Blackout Table 1 Determination Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________

___________

______________

Date of Examination: 12/07/2015 Operating Test Number:

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015A R 4 Give this page to the student Initial Condition(s):

The Plant has experienced a station blackout concurrent with a LOCA.

The HPCS pump is not available for operation.

Division 3 diesel generator is supplying power to the 15AA bus.

Initiating Cue(s):

Determine how many KW must be available on the 17AC bus in order to support the operation of FPCCU supplemented with RHR A including all auxiliary and support systems.

Do not include HPCS Diesel Auxiliaries as a requirement to support FPCCU and RHR A operation.

All prerequisites are verified met.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 12/7/2015 Examination Level: RO SRO Operating Test Number: LOT-201 5 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations R - D Determine Firewatch Requirements GJPM-OPS-2015-AS1 Conduct of Operations R - N Manual On-Line Risk Assessment GJPM-OPS-2015-AS2 Equipment Control R - D Tagout Removal Approval GJPM-OPS-2015-AS3 Radiation Control R - D Review Liquid Radwaste Discharge Permit GJPM-OPS-2015-AS4 Emergency Plan R - N Emergency Classification GJPM-OPS-2015-AS5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (N)ew or (M)odified from

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 1 of 13 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5 A S 1 JPM Title: Determine Firewatch Requirements

_ Facility Number: GJPM-OPS-A2013AS2 (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time:

25 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review: Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 2 of 13 Determine Fire Watch Requirements Setting: Classroom Type: SRO Task: S RO- NO-035 K&A: Generic 2.1.8: (3.4/4.1); 2.2.22: (4.0/4.7);2.1.25: (3.9/4.2); 2.4.25: (3.3/3.7) Safety Function:

Conduct of Operations [10CFR55.45a(12)]

Performance:

Actual Reference(s):

02-S-01-17, Control of Limiting Conditions for Operation 02-S-01-27, Operations Philosophy 06-OP-SP64-D-0044 Daily Fire Door Checks TRM 6.2.3, Fire Systems

-Spray and Sprinkler Systems P&ID M0035B Drawing A0634 UFSAR App. 9A, Fire Hazards Analysis Handout(s):

Copy of Tech Specs/TRM Section 6.2

.3 02-S-01-17, Control of Limiting Conditions for Operation P&ID M0035B Drawing A0634 UFSAR App. 9A, Fire Hazards Analysis for rooms 1D301 and 1D310 (ATTACHED)

  1. Manipulations:

N/A # Critical Steps:

2 Simulator Setup/Required Plant Conditions

None Safety Concerns
None Task Standard(s)
Candidate determines fire watch requirement for inoperability of sprinkler system N1P64D142A is to establish a continuous firewatch with backup fire suppression equipment in DG breezeway area 1D301 and an hourly fire watch patrol for Div 1 DG room 1D310 within one hour

. (It is acceptable for the Candidate to establish a continuous fire watch patrol for Div 1 DG room 1D310 within one hour in lieu of an hourly firewatch patrol

.)

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 3 of 13 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at rated power.

Valve 1P64F123A, DSL GEN MAN PRE

-ACT D142A ISOL, is being tagged closed for preventive maintenance on sprinkler system 1P64D142A. Initiating Cue(s):

As CRS, you are directed to determine the Fire Watch requirements associated with this work.

Use the references provided.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 4 of 13 Determine Fire Watch Requirements Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The student will determine the required TRM Fire Watch actions for impairing a required fire water sprinkler system

. Sequence is not critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 5 of 13 Critical steps are underlined, italicized, and denoted by an (*)

Sequence is not critical.

Step 1: TRM 6.2.3

  • Candidate uses provided references to identify the sprinkler 1P64D142A is required operable by TR 6.2.3 to protect DG corridor room 1D301, which is an area housing redundant Safe Shut Down equipment

. Standard:

Determines a continuous fire watch with backup fire suppression equipment must be established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of closing valve 1P64F123A for room 1D301 per TRM 6.2.3 Condition A, Action A.1

. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 6 of 13 Step 2: TRM 6.2.8
  • Candidate uses provided references to identify the sprinkler 1P64D142A is required operable by TR 6.2.3 to also protect Div 1 DG room 1D310, which is an area that does NOT house redundant Safe Shut Down equipment

. Standard: Determines an hourly fire watch patrol must be established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of closing valve 1P64F123A for room 1D301 per TRM 6.2.

3 Condition A, Action A.2. If the candidate specifies establishing a continuous fire watch

, with or without backup fire suppression equipment

, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for 1D310, this is acceptable.

Cue: None Notes: TR 6.2.3 specifies 1P64D142A protects redundant Safe Shutdown Equipment. The Fire Hazards Analysis specifies area 1D301 houses Div 1 and Div 2 equipment, and area 1D310 only houses Div 1 equipment; therefore, only an hourly firewatch patrol is required fo r area 1D310. But since TR6.2.3 does not make this distinction, the candidates electing a continuous firewatch for 1D310 is acceptable.

. SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 7 of 13 Task Standard(s)
Candidate determines fire watch requirement for inoperability of sprinkler system N1P64D142A is to establish a continuous firewatch with backup fire suppression equipment in DG breezeway area 1D301 and an hourly fire watch patrol for Div 1 DG room 1D310 within one hour.

(It is acceptable for the Candidate to establish a continuous fire watch patrol for Div 1 DG room 1D310 within one hour in lieu of an hourly firewatch patrol

.) SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS1 Revision 0 GJPM-OPS-2015CR1 Page 8 of 13 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AS1 JPM Title: Determine Firewatch Requirements Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

__________________________________________

_________

Give this page to the student Initial Condition(s):

The plant is at rated power.

Valve 1P64F123A, DSL GEN MAN PRE

-ACT D142A ISOL, is being tagged closed for preventive maintenance on sprinkler system 1P64D142A. Initiating Cue(s):

As CRS, you are directed to determine the Fire Watch requirements associated with this work.

Use the references provided.

Give this page to the student

Give this page to the student

Give this page to the student

Give this page to the student

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S 2 JPM Title: Manual On-Line Risk Assessment_

Facility Number:

GJPM-OPS-A2012-1AS1________ (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 2 of 7 Manual Risk Assessment Setting: Classroom Type: SRO Task: SRO-ADMIN-054 K&A: Generic 2.1.25: 4.2; 2.1.

20: 4.6; 2.2.17: 3.8 Safety Function

Equipment Control

[10CFR55.4 3b (5)] Performance

Actual Reference(s)
01-S-18-6, Risk Assessment of Maintenance Activities Handout(s)
01-S-18-6, Risk Assessment of Maintenance Activities
  1. Manipulations
N/A # Critical Steps
1 Simulator Setup/Required Plant Conditions
None Safety Concerns
None Task Standard(s)
Determines the Plant Safety Index risk color is YELLOW in accordance with 01

-S-18-6.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at 100% power.

Maintenance activities are in progress replacing P75

-F-16A (Fuel Oil Day TK supply to DG engine drive and DG Fuel Oil Booster Pumps).

Building Operator reports breaker 152

-1503 (SSW PMP A) is tripped with heat damage. No other equipment is affected.

The EOOS computer program is not available.

All other equipment and structures are operable.

Initiating Cue(s):

Determine the Plant Safety Index risk color manually in accordance with 01

-S-18-6, provided.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 4 of 7 Manual Risk Assessment Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The candidate will determine the Plant Safety Index risk color for the given plant conditions using 01

-S-18-6 Attachment IV.

Tasks: Critical steps are underlined, italicized, and denoted by an (*)

Step 1: 01-S-18-6

  • Determines the Plant Safety Index risk color using 01

-S-18-6 Attachment 4

. Standard: Candidate performs a manual analysis in accordance with 01

-S-18-6 step 5.5.1a. Candidate reviews 01

-S-18-6 Attachment 4 page 2 and determines the combination of Emergency Diesel Generator A (P75) and SSW A (P41) out of service, the risk color is Yellow.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 5 of 7 Task Standard(s)
Determines the Plant Safety Index risk color is YELLOW in accordance with 01-S-18-6. SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS2 Revision 0 GJPM-OPS-2015AS2 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AS2 JPM Title: Manual On-Line Risk Assessment Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

Give this page to the student

Initial Condition(s):

The plant is at 100% power.

Maintenance activities are in progress replacing P75

-F-16A (Fuel Oil Day TK supply to DG engine drive and DG Fuel Oil Booster Pumps).

Building Operator reports breaker 152

-1503 (SSW PMP A) is tripped with heat damage. No other equipment is affected.

The EOOS computer program is not available.

All other equipment and structures are operable.

Initiating Cue(s):

Determine the Plant Safety Index risk color manually in accordance with 01

-S-18-6, provided.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 1 of 8 GGNS 2012 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S3 JPM Title: Tagout Approval____

Facility Number: GJPM-OPS-2012AS3 (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 30 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 2 of 8 Tagout Approval Setting: Classroom Type: RO Task: CRO-ADMIN-05 K&A: 2.2.13 (4.1/4.3), 2.2.41 (3.5/3.9)

Safety Function: N/A Performance:

Actual Reference(s):

EN-OP-102 (Protective and Caution Tagging) 04-1-01-E21-1 (Low Pressure Core Spray System SOI) E-1182-7 M-1087 Handout(s):

EN-OP-102 04-1-01-E21-1 E-1182-7 M-1087 Tagout Tags Sheet (Attached)

  1. Manipulations:

N/A # Critical Steps:

1 Group: N/A Simulator Setup/Required Plant Conditions

None Safety Concerns
None Task Standard(s)
The operator indentifies the tagout lacks the required isolations per EN

-OP-102.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 3 of 8 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is in MODE 4

. The LPCS jockey pump is to be replaced.

Initiating Cue(s):

As CRS you are tasked to verify the adequacy of the proposed tagout for work on the LPCS Jockey Pump. The LPCS pump will be tagged separately.

For the purpose of this task restoration configuration is not required.

Document errors or inadequate boundaries.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 4 of 8 Admin Task
Tagout Approval Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will determine the proper isolations for the LPCS Jockey Pump.

Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: EN-OP-102 5.3[2](e)/Att. 9.2 The operator must determine minimum Tagout boundaries to include:

E21-F032 (LPCS Jockey Pump Suction)

E21-F034 (LPCS Jockey Pump Disch Stop Check)

E21-F035 (LPCS Jockey Pump Minimum Flow)

E21-FX020 (Supp Pool Level Transmitters Fill) 52-151108 (LPCS JKY PMP)

HS M 611 (Control Room Handswitch

) E21-F223 (Jockey Pump Discharge Drain/Pump Vent)

E21-F224 (Jockey Pump Discharge Drain/Pump Vent)

E21-F225 (Jockey Pump Suct Test Conn Isol) E21-F226 (Jockey Pump Suct Test Conn Isol)

Standard: Determines the appropriate boundaries.

Cue: Notes: The valves listed are the minimum required valves required to perform work. Any combination of valves that adequately isolates the LPCS Jockey Pump and provides a drain or vent path will meet the requirements of this step (including extra valves and breakers). SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 5 of 8 Step 2: EN-OP-102 5.3[4]
  • The Operator documents the following:
  • E21-F034 is required to be CLOSED to isolate the LPCS Jockey Pump Discharge.
  • E21-F226 is required to be OPEN to complete the drain path (in line with E21-F225).
  • E21-FX020 is required to be CLOSED to isolate the Supp. Pool Level Transmitters Fill.

E21-F223 and E21

-F224 are required to be OPEN to establish a vent path.

E21-F011 is not required for this tag.

Standard: Documents deficiencies.

Cue: Notes: These requirements can be specifically found in EN

-OP-102 Attachment 9.2 sections 1.1 and 2.1 and Attachment 9.3 sections 1.1 and 1.4. Any words that demonstrate an equivalent understanding is acceptable.

The task is complete when the operator determines the adequacy for this Tagout.

SAT / UNSAT Task Standard(s)

The operator indentifies the tagout lacks the required isolations per EN

-OP-102. SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS3 Revision 0 GJPM-OPS-2015AS3 Page 6 of 8 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AS3 JPM Title: Tagout Approval Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

Give this page to the student

Initial Condition(s):

The plant is in MODE 4

. The LPCS jockey pump is to be replaced.

Initiating Cue(s):

As CRS you are tasked to verify the adequacy of the proposed tagout for work on the LPCS Jockey Pump. The LPCS pump will be tagged separately.

For the purpose of this task restoration configuration is not required.

Document errors or inadequate boundaries.

NUCLEAR MANAGEMENT MANUAL N ON-QUALITY RELATED EN-OP-102-01 REV. 7 INFORMATIONAL USE PAGE 7 OF 26 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: ___MANUAL___________

TAGOUT: ___XXXX________ Tag Serial No. Tag Type Equipment Equipment Description Equipment Location Place. Seq. Placement Configuration Place. 1st Verif Date/Time Place. 2nd Verif Date/Time Rest. Seq. Restoration Configuration Rest. 1st Verif Date/Time Rest. 2nd Verif Date/Time Placement/Removal Tag Notes 1 D 52-151108 LPCS JKY PMP 15B11 2 OPEN 2 D HS M611 LPCS Jockey Pump Handswitch 1H13-P601 1 NUET AFTER STOP 3 D E21-F032 LPCS Jockey Pump Suction Area 9 Elevation 93' 4 CLOSED 4 D E21-F 011 LPCS MIN FLO TO SUPP POOL 1H13-P601 3 AUTO AFTER CLOSE 5 D E21-F035 LPCS Jockey Pump Minimum Flow Area 9 Elevation 93' 5 CLOSED 6 D E21-F225 Jockey Pump Suct Test Conn Isol Area 9 Elevation 93' 5 OPEN 7 D E21-F226 Jockey Pump Suct Test Conn Isol Area 9 Elevation 93' 5 CLOSED Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-AS4 JPM Title: Review Liquid Radwaste Discharge Permit Facility Number:

N/A __________ (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 20 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 2 of 7 Review Liquid Radwaste Discharge Permit Setting: Classroom Type: SRO Task: SRO-NO-10 K&A: 2.3.6: 3.1 Safety Function
9 Performance
Actual Reference(s)
01-S-08-11, Radioactive Discharge Controls 06-CH-SG17-V-00 34, Radwaste Release INOP Monitor Pre-Release Analysis OCDM 6.3 Handout(s)
LRW Discharge Permit with 06

-CH-SG17-V-00 34 Att. I completed and 01

-S-08-11 Att. I with Parts 1, 2, 3, 4, and 5 completed with errors OCDM 6.3 # Manipulations

N/A # Critical Steps
1 Simulator Setup/Required Plant Conditions
None Safety Concerns
None Task Standard(s)
Reviews the data recorded in Parts 1, 2, 3, 4, and 5 of the LRW Discharge Permit provided using 01

-S-08-11 and identifies at least 2 of the 3 errors.

Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The Plant Chemistry technician has presented completed surveillance 06-CH-SG17-V-0034, Radwaste Release INOP Monitor Pre

-Release Analysis, including a Batch Liquid Radwaste Discharge Permit

, to you for Operations Supervision review and approval. Initiating Cue(s):

You are the Control Room Supervisor. Perform the review for the Part 5 Operations Supervisor signoff of the Batch Liquid Radwaste Discharge Permit associated with completed surveillance 06

-CH-SG17-V-0034 for the recently completed discharge.

REFER TO THE LIQUID RADWASTE DISCHARGE PERMIT PROVIDED.

Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 4 of 7 Review Liquid Radwaste Discharge Permit Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

This task is to perform the SRO review of the Batch Liquid Radwaste Discharge Permit performed by Operations Supervision following a controlled release of liquid radwaste. Three errors have been introduced somewhere within sections 1 through 5 of the Discharge Permit.

Critical step s are underlined, italicized, and denoted by an (*)

Step 1: 01-S-08-11

  • Reviews the Batch Liquid Radwaste Discharge Permit package provided per the requirements of 01

-S-08-11 to determine if the discharge was performed in accordance with the requirements of 01

-S-08-11. Standard: Reviews the data recorded in Parts 1, 2, 3, 4, and 5 of the LRW Discharge Permit provided using 01

-S-08-11 and identifies at least 2 of the 3 following errors: In Part 2, the "Radiochemist

" signoff for independent verification required for Effluent Radiation Monitor Inoperable had been N/A'd.

In Part 4, the "Shift Manager

" signoff granting permission to discharge had not been obtained.

In Part 5, the "Average Dilution Flow

" during the discharge was lower than the required minimum dilution flow prescribed in Section 3.

Cue: None Notes: All values recorded in Parts 1, 2, and 3 derive from pages 1 and 2 of the computer generated Liquid Pre

-Release Permit Report in 06

-CH-SG17-V-00 34 Att I SAT / UNSAT

Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 5 of 7 Task Standard(s)
Reviews the data recorded in Parts 1, 2, 3, 4, and 5 of the LRW Discharge Permit provided using 01

-S-08-11 and identifies at least 2 of the 3 errors.

SAT / UNSAT Remember to record stop time

Date of Examination:

12/07/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5-AS4 Revision 1 4/22/13 Page 6 of 7 Applicant:

____________________________________________________________

JPM Number: GJPM-OPS-2015AS4 JPM Title: Review Liquid Radwaste Discharge Permit Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 1 of 4 Revision 1 4/22/13 Page 1 of 7 BATCH LIQUID RADWASTE DISCHARGE PERMIT YY-MM-DD-17 Part 1 Pre-Relea se Pr ocessing Release Number*

Date Today Time 0700 Tank to be released*

FDST-A Volume* 28 56 0 gal Tank is isolated. Recirculation started Today / 0100 Date/Time Dilution flow 9900 gpm Radwaste monitor background reading*

  • N/A (LCO 1-TS-XX-0073) cpm (Monitor reading is less than 10,800 cpm)
  • LRW Rad Monitor is INOP under this LCO

Clyde Small

_____________________

Operator (Performer)

Asterisked* items above verified Frank Zapp_____________________

Operator (Verifie r)

Radwaste monitor background reading verified John Doe #30588 Today / 0400 Operations Supervision /Date/Time

________________________________________________________

Part 2 Pre-Release Analysis

20XX192

Batch Number Sample Date Today Time 0830 Minimum recirculation time is met RC #30471 One Total Suspended Solids (TSS) sample has been collected and analyzed for the month: Yes X Initials RC #30471 No N/A TSS N/A mg/l (< 30mg/l) The radioactive liquid from the tank designated above is within the ALARA criteria of 10CFR50 App I as defined by surveillance 06

-CH-SG17-P-0041, 06-CH-SG17-V-0034, or 06-CH-SP41-P-0035 and may be released.

Rupert Colada

  1. 30007 Radiochemist

Independent Verification if Effluent Radiation Monitor Inoperable.

N/A Radiochemist Comments:

no limits exceeded

Should be signed, not N/A'd DO NOT GIVE TO STUDENT EVALUATOR COPY

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 2 of 4 Revision 1 4/22/13 Page 2 of 7 BAT CH LIQUID RADWASTE DISCHARGE PERMIT Part 3 Monito r Setpoint Calibr ation Batch Number (from Part 2) 20XX192 Setpoints Adjusted to:

Minimum Blowdown Flow Rate Setpoint (Circ Water Blowdown Flow Setpoint) 2250 gpm Maximum Tank Discharge Flow Rate Setpoint (Liquid Radwaste Effluent Flow Setpoint) 100 gpm Effluent Monitor Alarm Setpoint N/A (LCO 1-TS-XX-0073) cpm (Hi) Effluent Monitor Trip Setpoint N/A cpm (Hi-Hi) Micheal Wildfire

  1. 30864 / Today I&C Technician Date S. Nugent #30255 / Today Verified Date Copies of Pages 1 and 2 of this permit have been placed in the Control Room Setpoint Logbook, and

The previous Pages 1 and 2 have been removed.

Micheal Wildfire

  1. 30864 / Today I&C Technician Date S. Nugent #30255 / Today Verified Date

Part 4 Releas e A uthorization The designated tank may be released provided the discharge and dilution flows meet the setpoint criteria.

/

Shift Manager Date

Part 5 Release Valve lineup Verified H. Casey #30114 / D. McCormick

  1. 30435 Independent Verification

if Radiation Monitor Inop From Step 6.4.2e(2):

On the date of release , prior to opening SG17

-F355 DRAIN BASIN ISOL VLV, have chemistry verify the Total Suspended Solids analysis for this tank has been completed or is not required.

The Total Suspended Solids analysis for this tank has been completed.

Not Required_

Rupert Colada

  1. 30007 / Today Radiochemist Date DO NOT GIVE TO STUDENT EVALUATOR COPY Should be signed, not blank GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 3 of 4 Revision 1 4/22/13 Page 3 of 7 Part 5 (cont) BATCH LIQUID RADWASTE DISCHARGE PERMIT Radiati on Monitor R eading Before release N/A cpm Maximum during release N/A cpm Average during release*

N/A cpm Tank Level Before 28560 After*

762 Gallons Released*

27798 Average Release Rate (Tank Discharge Rate GPM)*

92.66 Flo w Rate Indication During Disc harge a) Maximum Radwaste Tank Effluent Flow*

94 gpm If G17 FR-R011, tank discharge flow rate recorder, is inop flow must be estimated at intervals not to exceed every four hours.

N/A /

Start N/A /

Approx. Middle

N/A /

End Flow Time b) Average Dilution Flow*

2000 gpm (appx)

Circulation Water Blowdown Flow, monitor Operable Inoperable Discharge Canal Flow Other dilution water source (specify):

N/A If dilution flow monitor is inop, flow must be estimated at intervals not to exceed every four hours.

N/A / Start N/A / Approx. Middle

N/A / End Flow Time DO NOT GIVE TO STUDENT EVALUATOR COPY Should be greater than minimum setpoint 2250 gpm listed in Part 3

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 4 of 4 Revision 1 4/22/13 Page 4 of 7 BATCH LIQUID RADWASTE DISCHARGE PERMIT LCO No.: N/A

DATE AND TIME

ELAPSED TIME*

(minutes)

VALVES OPEN VALVES SHUT

Today 0930 Today 1430 300

TOTAL 300 Monitor flushed HC#30114 H. Casey #30114

Initials Operator (Performer)

Asterisked* items above verified D. McCormick

  1. 30435_______________

Operator(Verifier)

__________________

Operations Supervision

Comments:

Par t 6 Post-Release Analysis The post-release analysis is based on actual data recorded during the release

Comments:

/

Radiochemist Date

DO NOT GIVE TO STUDENT EVALUATOR COPY Operations Supv signoff block

Give this page to the student

Initial Condition(s):

The Plant Chemistry technician has presented completed surveillance 06-CH-SG17-V-0034, Radwaste Release INOP Monitor Pre

-Release Analysis, including a Batch Liquid Radwaste Discharge Permit, to you for Operations Supervision review and approval.

Initiating Cue(s):

You are the Control Room Supervisor. Perform the review for the Part 5 Operations Supervisor signoff of the Batch Liquid Radwaste Discharge Permit associated with completed surveillance 06

-CH-SG17-V-0034 for the recently completed discharge.

REFER TO THE LIQUID RADWASTE DISCHARGE PERMIT PROVIDED.

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 1 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT YY-MM-DD-17 Part 1 Pre-Relea se Pr ocessing Release Number*

Date Today Time 0700 Tank to be released*

FDST-A Volume* 28 56 0 gal Tank is isolated. Recirculation started Today / 0100 Date/Time Dilution flow 9900 gpm Radwaste monitor background reading*

  • N/A (LCO 1-TS-XX-0073) cpm (Monitor reading is less than 10,800 cpm)
  • LRW Rad Monitor is INOP under this LCO.

Clyde Small______________________

Operator (Performer)

Asterisked* items above verified Frank Zapp

________________________

Operator (Verifier)

Radwaste monitor background reading verified John Doe #30588 Today / 0400 Operations Supervision /Date/Time

________________________________________________________

Part 2 Pre-Release Analysis

20XX192

Batch Numbe r Sample Date Today Time 0830 Minimum recirculation time is met RC #30471 One Total Suspended Solids (TSS) sample has been collected and analyzed for the month: Yes X Initials RC #30471 No N/A TSS N/A mg/l (< 30mg/l) The radioactive liquid from the tank designated above is within the ALARA criteria of 10CFR50 App I as defined by surveillance 06

-CH-SG17-P-0041, 06-CH-SG17-V-0034, or 06-CH-SP41-P-0035 and may be released.

Rupert Colada

  1. 30007 Radiochemist Independent Verification if Effluent Radiation Monitor Inoperable.

N/A Radiochemist

Comments:

no limits exceeded

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 2 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT Part 3 Monito r Setpoint Calibr ation Batch Number (from Part 2) 20XX192 Setpoints Adjusted to:

Minimum Blowdown Flow Rate Setpoint (Circ Water Blowdown Flow Setpoint) 2250 gpm Maximum Tank Discharge Flow Rate Setpoint (Liquid Radwaste Effluent Flow Setpoint) 100 gpm Effluent Monitor Alarm Setpoint N/A (LCO 1-TS-XX-0073) cpm (Hi) Effluent Monitor Trip Setpoint N/A cpm (Hi-Hi) Micheal Wildfire

  1. 30864 / Today I&C Technician Date

S. Nugent #30255 / Today Verified Date

Copies of Pages 1 and 2 of this permit have been placed in the Control Room Setpoint Logbook, and

The previous Pages 1 and 2 have been removed.

Micheal Wildfire

  1. 30864 / Today I&C Technician Date

S. Nugent #30255 / Today Verified Date

Part 4 Releas e A uthorization The designated tank may be released provided the discharge and dilution flows meet the setpoint criteria.

/

Shift Manager Date

Part 5 Release Valve lineup Verified H. Casey #30114 / D. McCormick #30435 Independent Verification

if Radiation Monitor Inop From Step 6.4.2e(2):

On the date of release , prior to opening SG17

-F355 DRAIN BASIN ISOL VLV, have chemistry verify the Total Suspended Solids analysis for this tank has been completed or is not required.

The Total Suspended Solids analysis for this tank has been completed.

Not Required_

Rupert Colada

  1. 30007 / Today Radiochemist Date

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 3 of 4 Part 5 (cont) BATCH LIQUID RADWASTE DISCHARGE PERMIT Radiati on Monitor R eading Before release N/A cpm Maximum during release N/A cpm Average during release*

N/A cpm Tank Level Before 28560 After*

762 Gallons Released*

27798 Average R elease Rate (Tank Discharge Rate GPM)*

92.66 Flo w Rate Indication During Disc harge a) Maximum Radwaste Tank Effluent Flow*

94 gpm If G17 FR-R011, tank discharge flow rate recorder, is inop flow must be estimated at intervals not to exceed every four hours.

N/A /

Start N/A /

Approx. Middle

N/A /

End Flow Time

b) Average Dilution Flow*

2000 gpm (appx)

Circulation Water Blowdown Flow, monitor Operable Inoperable Discharge Canal Flow Other dilution water source (specify):

N/A If dilution flow monitor is inop, flow must be estimated at intervals not to exceed every four hours.

N/A / Start N/A / Approx. Middle N/A / End Flow Time

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-08-11 Revision: 113 Attachment I Page 4 of 4 BATCH LIQUID RADWASTE DISCHARGE PERMIT LCO No.: N/A

DATE AND TIME

ELAPSED TIME*

(minutes)

VALVES OPEN VALVES SHUT

Today 0930 Today 1430 300

TOTAL 300 Monitor flushed HC#30114 H. Casey #30114

Initials Operator (Performer)

Asterisked* items above verified D. McCormick

  1. 30435_______________

Operator(Verifier)

__________________

Operations Supervision

Comments:

Par t 6 Post-Release Analysis The post-release analysis is based on actual data recorded during the release

Comments:

/

Radiochemist Date

Facilit y: GG N G R A N D G UL F N U CLEAR Wo r k O rder Package Unit: 1 P rojec t: 0XXXXXX 01 Prio r it y: 4 A W/O Dspln: CHEM Plan n e r: RONEAL O'N EA L R O N A LD W/O Title: 0 6CHSG17-V-0 0 3 4 LIQUID RADW AS T E INOP MONI T OR PRE RELEASE W/O T as k Title: 0 6 C HSG17-V-00 3 4 L IQ U ID RA D W AS T E IN O P MONI T OR PRE RELEASE T as k Dspln: CHE M Complete d B y: Rpt: Date: W/O T ype: Jo b Type: P k g T ype: T I PMC11 XX/XX/20XX W O OD En t e rgy Wor k O r de r T as k W ritte n T o P a g e 1 o f 2 Facilit y: D i vision: Equipm ent: E q ui p Name: GGN Unit: 1 Area: Component:

O p S ys: S ys/C l s: Wo r k Item: Equip.Tag: U T C: Catalo g ID: 06 CH S G 17-V-0034 G P R O Eqt. List: Alt: Tbl/Brkdwn: U CR: 6 (P a s t 1 2 m o) Op s Re v ie w Re q d: N C R Co m m R e q d: NO T I F Y W OR K CON T RO L C E N T E R V I A PHON E PRIO R T O STAR T O F W ORK Location: Cost Centr: NSCC2 . A c t i v i t y: PRSS Use r Def: F 5PPNRMSTK P e r cen tage: 100.000000 Ac ct N o: G L GG 1 E q u ip m e n t I n fo rmation Q G roup: Sa f et y Class: Mainte nanc e Rel: Manu f act ur e r: Se r ia l Number: Wor k Orde r T as k Inst ructio n s ***DESCR IPTION*** Mode l Number: 0 6CHSG17-V-0 0 3 4 LIQUID RADW AS T E INOP MONI T OR PRE RELEASE ***DESCR IPTIO N END*** *** W OR K AC T I V IT Y *** CHEM - 0 6-CH-SG17-V-0 0 3 4 *** W O R K A C TIVI T Y E N D *** Re w or k/Appro v al Deficienc y T a g N o: Loc: T a g Remo ved: Rewor k Job: N Commen t s: T as k Req u i reme n ts F A C. GGN GGN REG/REQ ES T. D OSE? R W P V A LUE 1 SR W P C O MM E N T S G E NE R A L R W P D O S E ES TIMA T E: 0.0 01 Q C Req u ir e me nts/Com m e n ts NO Q C REQUIRE M EN T S FOR T HE W ORK O RDER TASK Facilit y: GG N G R A N D G UL F N U CLEAR Wo r k O rder Package Unit: 1 P rojec t: 0XXXXXX 01 Prio r it y: 4 A W/O Dspln: CHEM Plan n e r: RONEAL O'N EA L R O N A LD W/O Title: 0 6CHSG17-V-0 0 3 4 LIQUID RADW AS T E INOP MONI T OR PRE RELEASE W/O T as k Title: 0 6 C HSG17-V-00 3 4 L IQ U ID RA D W AS T E IN O P MONI T OR PRE RELEASE T as k Dspln: CHE M Complete d B y: Rpt: Date: W/O T ype: Jo b Type: P k g T ype: T I PMC11 XX/XX/20XX W O OD En t e rgy Refe rence s/Doc u me n t Info rmation P a g e 2 o f 2 T ype/Subt y pe: PRO Number: 06C H S G 17-V-0034 Sh eet: 0 Title/Desc: 213 7 S T O R A G E L O C A T I O N: 12051 0 090 Image: T ype/Subt y pe: W O Number: W O-003129 7 5 Sh eet: Title/Desc: 0 6CHSG17-V-0 0 3 4 LIQUID RADW AS T E INOP MONI T OR PRE RELEASE A u t h o r i zation Image: Early Start D at e: 20XX-XX-XX Ea r l y Finis h Date: 20XX-XX-XX La t e S t a r t Date: Lat e Fi n is h D ate: Majo r Failu r e/Actio n T aken Majo r Failu r e: Actio n Taken: Deficienc y T a g L oc: Deficienc y T a g No.: C o m p l e t i o n C ommen t s o n W o r k P er f ormed Commen t s Date By T y pe Date B a t c h 20XX192. S a t. L C O 1-T S-XX-0073 20XX-XX-XX KW I LSON 20XX-XX-XX Remo v e d (Y/N):

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE X QA RECORD 06-CH-SG17-V-0034 Revision: 106 RT = B6.61 NON-QA RECORD Attachment I Page 1 of 2 INITIALS NUMBER OF PAGESl DATE Page RELATED DOCUMENT

RTYPE B6.61 NUMBER =

Ref SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Radwaste Release Inop Radwaste Monitor Pre-Release Analysis Technical Specification:

SR 6.11.1.1 for Function 6.11.1

-1.A, Table 6.11.1

-1 Notes c & d, LCO 6.3.9 Condition B

1.0 IMPACT

STATEMENT

1.1 Performance

of this procedure has no impact on plant operation.

2.0 PROC EDURE 2.1 Plant Mode is (circle one): 1 2 3 4 5

2.2 Permission

to begin the test Not Applicable

Shift Supervisor/Date

2.3 Performed

for LCO #

1-TS-XX-073 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category)

Entire procedure completed [ ] Partial procedure completed [ ]

Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable [ ]

All other steps/data Acceptable [

] Unacceptable [ ]

3.2 TCNs in effect during performance (list):

none

3.3 Comments

Batch 20XX192

3.4 Test performed by M. Wildfire

Date/Time Today / 0500 4.0 DEFICIENCIES CR Issued #

LCO Entered #

WR Issued #

5.0 APPROVAL

Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]

Shift Supv/Mgr

Date Comments:

CONCURRENCE Chemistry Manager

Date GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE X QA RECORD 06-CH-SG17-V-0034 Revision: 106 RT = B6.61 NON-QA RECORD Attachment I Page 2 of 2 INITIALS NUMBER OF PAGESl DATE Page RELATED DOCUMENT

RTYPE B6.61 NUMBER =

Ref DATA SHEET I RADWASTE RELEASE INOP RADWASTE MONITOR PRE

-RELEASE ANALYSIS SAFETY RELATED INITIALS $ 5.2 Tank minimum recirculation of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> met MW 5.3.1.b(1)

Sample contains Resin and Chemistry Management Notified MW 5.3.1.b(2)

Sample does not contain Resin N/A $ 5.4.2 First Sample all significant peaks identified MW $ 5.5.2 Second Sample all significant peaks identified MW $ 5.6.1 ODCM dose limits are not exceeded.

MW 5.6.2 Whole Body Dose Current Admin. Limit Limit Exceeded Chemistry Supervision Notified Tank Will Be Reprocessed Decision To Discharge Documented Initials 2.43E3 mrem 1.0E-2 mrem Yes/No Yes/NA Yes/No/NA Yes/NA MW Highest Organ Dose Current Admin. Limit Limit Exceeded Chemistry Supervision Notified Tank Will Be Reprocessed Decision To Discharge Documented Initials 4.19E-3 mrem 3.3E-2 mrem Yes/No Yes/NA Yes/No/NA Yes/NA MW $ 5.8 Composite Sample Saved MW 5.10.3 Unused Permit Record #

N/A Deleted MW Comments :

Batch 20XX192, no limits exceeded _ ____LCO 1-TS-XX-0073 _____________________________________

___________________________________________________________________

___________________________________________________________________

Reviewed :

Micheal Wildfire Date: Today RETDAS v3.5.0 <GGN> CANBERRA Page - 1 Date/Time:

xx/xx/20xx xx:xx seekeriD: Retdas LIQUID PRE-RELEASE PERMIT REPORT Permit Number: 20xx192 Release ID: 1 SAMPLE TANKS Release Mode: 2 Batch Status: P Pre-Release Comments: FDST-A for Discharge (V-34 1st sample) === RELEASE DATA ======================================================

Estimated tank volume to be released (gal)....................

.28560 Average dilution flow available (gpm).........................

.2500 Allocation percentag e.........................................

.100 Dilution flow assigned to permit (gpm)........................

.2500 === NUCLIDE DATA ======================================================

Nuclide ZN-65 Undiluted uCi/ml lO*EC Percent of lO*EC 4.28E-01 w C0-60 RB-88 SB-125 5.71E-07 2.14E-07 7.85E-07 1.79E-07 3.00E-05 5.00E-05 4.00E-03 3.00E-04 1.90E+OO 1.96E-02 5.97E-02 LA-140 6.04E-08 9.00E-05 6.71E-02 --------- -------- Gamma 1.81E-06 H-3 4.67E-03 1.OOE-02 4.67E+Ol FE-55 2.17E-06 1.OOE-03 2.17E-01 --------- -------- Beta 4.67E-03 --------- -------- Total 4.67E-03 Diluted D&EG Concentration:

O.OOE+OO D&EG Concentration Limit Not Exceeded RETDAS v3.5.0 <GGN> CANBERRA Page - 2 Date/Time:

xx/xx/20xx xx:xx seekeriD: Retdas LIQUID PRE-RELEASE PERMIT REPORT Permit Number: 20XX192 === RELEASE CALCULATIONS

==================================

Minimum dilution facto r.......................................

.9.88E-01 Min. dilution flowrate setpoint(Circ Water Blowdown Flow)(gpm).2.25E+03 Maximum tank discharge flowrate setpoint(Effluent Flow)(gpm)...1.00E+02 === SETPOINT DATA ===================================================== Entered background (cpm)......................................

.0.OOE+OO Alarm Setpoint (cpm)..........................................

.NA Trip Setpoint (cpm)...........................................

.NA --- I&C SE TPOINT VOLTAGES ============================================= Minimum blowdown flow trip voltage setpoint (vdc)............

.1.720E+OO Desired blowdown flow trip voltage setpoint (vdc).............

1.729E+OO Maximum blowdown flow trip voltage setpoint (vdc).............

1.737E+OO Minimum tank effluent flow trip voltage setpoint (vdc)........4.950E+OO Desired tank effluent flow trip voltage setpoint (vdc)........4.975E+OO Maximum tank effluent flow trip voltage setpoint (vdc)........5.OOOE+OO Minimum radiation monitor alarm voltage setpoint (vdc)........O.OOOE+OO Desired radiation monitor alarm voltage setpoint (vdc)........0.OOOE+OO Maximum radiation monitor alarm voltage setpoint (vdc)........O.OOOE+OO Minimum radiation monitor trip voltage setpoint (vdc).........O.OOOE+OO Desired radiation monitor trip voltage setpoint (vdc).........O.OOOE+OO Maximum radiation monitor trip voltage setpoint (vdc).........O.OOOE+OO === PERMIT INSTRUCTIONS

===================================

RETDAS v3.5.0 <GGN> CANBERRA Page - 3 Date/Time:

xx/xx/20xx xx:xx seekeriD: Retdas Q3 - Admin. Any Organ ADULT LIVER 3.38E-02 3.75E+OO 9.01E-01 Q3 - Admin. Total Body ADULT 1.56E-02 1.13E+OO 1.39E+00 Q3 - TS Any Organ ADULT LIVER 3.38E-02 S.OOE+OO 6.76E-01 LIQUID PRE-RELEASE PERMIT REPORT Permit Number: 20XX192 === PERMIT DOSE BY ORGAN AND AGE GROUP (mrem) ===============================*===

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 5.85E-04 1.66E-03 9.66E-05 1.06E-03 1.47E-04 1.34E-03 O.OOE+OO 8.11E-04 === PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) =============

QUARTER 3 ==========

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 1.11E-02 3.38E-02 8.08E-04 2.19E-02 1.30E-03 2.54E-02 O.OOE+OO 1.56E-02 === SITE DOSE LIMIT ANALYSIS ===================================================

Period-Limit Age Group Organ Dose (mrem) Limit (mrem) Max % of Limit Critical Pathway: Fresh Water Fish - Comm. (FFCM) Q3 - TS Total Body ADULT 1.5 6E-02 1.50E+OO 1.04E+OO Critical Pathway: Fresh Water Fish - Comm. (FFCM) === PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) =================

2012 ===========

Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 2.72E-01 5.74E-01 6.62E-03 3.05E-01 3.38E-02 2.77E-01 O.OOE+OO 3.07E-01 === SITE DOSE LIMIT ANALYSIS ===================================================

Period-Limit Age Group Organ Dose (mrem) Limit (mrem) Max % of Limit 2012 - Admin. Any Organ ADULT LIVER 5.74E-01 7.50E+OO 7.65E+OO 2012 - Admin. Total Body ADULT 3.07E-01 2.25E+OO 1.36E+01 2012 - TS Any Organ ADULT LIVER 5.74E-01 1.00E+01 5.74E+OO Critical Pathway: Fresh Water Fish - Comm. (FFCM) 2012 - TS Total Body ADULT 3.07E-01 3.00E+OO 1.02E+01 Critical Pathway: Fresh Water Fish - Comm. (FFCM)

Analyzed: xx/xx/xx xx:xx:xx by mwildfire *******************************************************************************

SEEKER G A M M A A N A L Y S I S R E S U L T S PS Version 1.8.5 Entergy, Inc Grand Gulf Nuclear Station *******************************************************************************

Page 1 SAMPLE TANKS Liquid Sample Analysis Sample ID: FDST-A for Discharge (V-34 1st sample) Sampling Start: Sampling Stop: Buildup Time. Sample Size . Collection Efficiency 09/04/12 05:55:00 09/04/12 05:55:00 O.OOE+OOO Hrs . l.OOE+003 ml 1.0000 Counting Start: Decay Time. Live Time Real Time . Spc. File . 09/04/12 06:08:30 2.25E-001 Hrs 1800 Sec 1801 Sec .20120904014.SPC Energy(keV)=

0.50 + FWHM(keV) 0.61 + Detector #: 4 (Detector 4) O.SOO*Ch + 7.61E-08*ChA2 + O.OOE+OO*ChA3 09/04/12 O.Oll*En + 6.03E-04*EnA2 + 0.00E+00*EnA3 11/17/05 Where En= Sqrt(Energy in keV) Search Sensitivity:

1.00 I Sigma Multiplier:

1.00 I Search Start/End:

0/4095 PEAK SEARCH RESULTS PK. ENERGY ADDRESS NET/MDA UN- C.L. BKG FWHM # (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG 1 112.37 223.92 10 10 16 40 0.47 NET< CL 2 175.90 351.08 47 13 19 53 1.28 Wide Pk 3 427.79 855.19 45 11 15 33 0.96 4 463.41 926.48 25 9 13 22 0.93 5 486.72 973.13 20 8 11 20 1.17 6 661.64 1323.14 13 9 13 28 0.58 NET< CL 7 897.79 1795.61 17 9 14 28 0.69 8 1115.39 2230.92 39 8 9 12 1.83 9 1173.28 2346.71 209 15 8 9 1.46 10 1332.58 2665.33 167 14 7 8 1.46 Page 2 Analyzed: xx/xx/xx xx:xx:xx by mwildfire *******************************************************************************

SEEKER L I B R A R Y S E A R C H R E S U L T S Version 2.3.1 Entergy, Inc Grand Gulf Nuclear Station *******************************************************************************

Library File:. .LRWLIB.LIB (LRW Library) Library Match Resolution.

Minimum Score . 1.2S I Decay Limit (Halflives)

......8.0 0.S 0 I Decay Correction.

. . . . . . . . . ON ===============================================================================

LIBRARY SEARCH RESULTS Pk. Energy Net Expected Peaks % Abn. No. (keV) Counts Nuclide Net Counts Found Found SCORE FLAG -------------------------------------------------------------------------------

2 17S.90 47 SB-12S 21 3 of s 60.79 1.11 3 427.79 4S SB-12S 94 3 of s 60.79 1.11 4 463.41 2S ----- SPLIT 11 463.41 16 SB-12S 16 3 of s 60.79 1.11 AutoAdd 12 463.41 9 -GS 1 3 8 1 of 3 22.44 0.72 AutoAdd s 486.72 20 LA-140 1 of s 31.0S 0.81 7 897.79 17 RB-88 1 of 2 39.62 0.90 8 111S.39 39 ZN-6S 1 of 2 100.00 1.00 NI-6S 1 of 2 38.69 0.39 9 1173.28 209 C0-60 186 2 of 2 100.00 1.so 10 1332.S8 167 C0-60 187 2 of 2 100.00 1.so Page 3 Analyzed: xx/xx/xx xx:xx:xx by mwildfire 1173.23 1332.51 CS-138 462.70 XE-133 81.00 NP-239 106.13 CE-144 133.53 M0-99 140.51 TC-99M 140.51 CE-141 145.45 RE-188 155.03 RA-226 185.99 XE-133M 233.20 XE-135 249.79 CR-51 320.07 I-131 364.48 ZN-69M 438.63 ******************************************************************************* SEEKER F I N A L A C T I V I T Y R E P 0 R T Version 2.3.1 Entergy, Inc Grand Gulf Nuclear Station ******************************************************************************* SAMPLE TANKS Liquid Sample Analysis Sample ID: FDST-A for Discharge (V-34 1st sample) Sampling Start: 09/04/12 05:55:00 I Counting Start: 09/04/12 06:08:30 Sampling Stop: 09/04/12 05:55:00 I Decay Time. 2.25e-001 Hrs Buildup Time. . Sample Size . . 0.OOe+OOO Hrs . ..1.00e+003 ml I I Live Time . . Real Time . . 1800 Sec 1801 Sec Collection Efficiency

. . . . 1.0000 I Spectrum File .20120904014.SPC Cr. Level Confidence Interval: 95 % I Det. Limit Confidence Interval: 95 % Detector #: 4 (Detector 4) Efficiency File: 1LMBS004.EFF (1 Liter Marinelli Det 4) Eff=l0A[-5.36E+01 +6.72E+Ol*L

+-2.87E+Ol*LA2

+4.04E+00*LA3]

Eff.= EXP[9.73E-01 + -8.82E-01

  • En+ O.OOE+OO
  • EnA2] Above Coinc. Sum File: ....1LMBS004.CSF (lLMB DET #4 CSF File) 07/21/11 290.00 keV Library File: ......LRWLIB.LIB LSF File: ........LRWLLD.LSF (LRW Library) (LRWLLD) MEASURED or MDA CONCENTRATIONS N L ENERGY E Concentration Critical Hal f life L % Nuclide (keV) T (uCi/ml MDA Level (hrs) D ECL -------------------------------------------------------------------------------

SB-125 427.95 1.79E-07 +- 4.44E-08 1.27E-07 5.82E-08 2.43E+04 0.06 176.29 I.D. . . . . 2.43E+04 463.51 I.D. . . . . . 2.43E+04 LA-140 487.03 6.04E-08 +- 2.56E-08 7.96E-08 3.56E-08 3.07E+02 0.07 RB-88 898.03 7.85E-07 +- 4.28E-07 1.39E-06 6.32E-07 2.97E-01 ZN-65 1115.50 2.14E-07 +- 4.43E-08 1.08E-07 4.64E-08 5.85E+03 0.43 C0-60 Average:x 5.71E-07 +- 3.llE-08 4.62E+04 1.90 6.04E-07 +- 4.38E-08 5.14E-08 2.18E-08 4.62E+04 5.38E-07 +- 4.40E-08 5.48E-08 2.30E-08 4.62E+04 . I.D. . 5.37E-01 MDA 6.70E-08 3.04E-08 1.27E+02 MDA 8.08E-08 3.68E-08 5.65E+Ol MDA 1.61E-07 7.34E-08 6.82E+03 MDA 1.99E-08 9.14E-09 6.62E+Ol MDA 2.03E-08 9.30E-09 6.62E+Ol MDA 3.13E-08 1.41E-08 7.77E+02 MDA 1.14E-07 5.17E-08 1.70E+Ol MDA 5.22E-07 2.36E-07 1.40E+07 MDA 2.24E-07 1.02E-07 5.42E+01 MDA 2.45E-08 1.11E-08 9.08E+OO MDA 2.llE-07 9.26E-08 6.65E+02 MDA 3.18E-08 1.42E-08 1.93E+02 MDA 3.42E-08 1.53E-08 1.38E+Ol Page 4 Analyzed: xx/xx/xx xx:xx:xx by mwildfire ===============================================================================

MEASURED or MDA CONCENTRATIONS

===================================================================

N L ENERGY E Concentration Critical Halflife L % Nuclide (keV) T (uCi/ml MDA Level (hrs) D ECL W-187 479.57 MDA 1.09E-07 4.70E-08 2.39E+01 RU-103 497.08 MDA 3.49E-08 1.54E-08 9.44E+02 I-133 529.50 MDA 2.67E-08 1.11E-08 2.03E+01 BA-140 537.38 MDA 1.07E-07 4.35E-08 3.07E+02 AS-76 559.10 MDA 7.51E-08 3.29E-08 2.63E+01 CS-137 661.62 MDA 4.95E-08 2.20E-08 2.64E+OS ZR-95 724.18 MDA 6.78E-08 2.81E-08 1.55E+03 NB-95 765.82 MDA 3.49E-08 1.47E-08 8.44E+02 CS-134 795.76 MDA 5.22E-08 2.26E-08 1.81E+04 C0-58 810.75 MDA 4.70E-08 2.07E-08 1.70E+03 CS-136 818.50 MDA 4.43E-08 1.93E-08 3.12E+02 MN-54 834.81 MDA 4.93E-08 2.18E-08 7.49E+03 MN-56 846.60 MDA S.OSE-08 2.19E-08 2.58E+OO SC-46 889.26 MDA 5.22E-08 2.30E-08 2.01E+03 AG-llOM 937.48 MDA 1.52E-07 6.65E-08 6.00E+03 I-135 1260.41 MDA 1.44E-07 5.66E-08 6.61E+OO FE-59 1291.56 MDA 7.12E-08 2.57E-08 1.08E+03 NA-24 1368.55 MDA 2.39E-08 7.38E-09 1.50E+01 SR-92 1383.90 MDA 4.82E-08 1.84E-08 2.71E+OO SB-124 1691.04 MDA 7.74E-08 2.79E-08 1.44E+03 MEASURED TOTAL: 1.81E-06 +- 5.73E-07 uCi/ml 2.46E+OO ===============================================================================

UNKNOWN,SUM or ESCAPE PEAKS ===============================================================================

PK. ENERGY ADDRESS NET UN- C.L. BKG FWHM # (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG 1 112.37 223.92 10 10 16 40 0.47 Deleted 4 463.41 926.48 25 9 13 22 0.93 SPLIT 6 661.64 1323.14 13 9 13 28 0.58 Deleted ===============================================================================

NET/MDA PEAK RESULTS PK. # ENERGY (keV) ADDRESS CHANNEL NET/MDA COUNTS UN- CERTAINTY C.L. COUNTS BKG COUNTS FWHM (keV) FLAG 13 81.00 161.14 29 0 13 36 0.76 14 106.13 211.44 30 0 14 38 0.79 15 133.53 266.28 31 0 14 41 0.82 16 140.51 280.25 32 0 15 44 0.83 17 140.51 280.25 32 0 15 44 0.83 18 145.45 290.14 27 0 12 29 0.84 19 155.03 309.31 29 0 13 36 0.85 20 185.99 371.28 28 0 13 32 0.88 21 233.20 465.77 32 0 15 39 0.93 22 249.79 498.97 28 0 13 30 0.94 23 320.07 639.62 22 0 10 18 1.01 Page 5 Analyzed: xx/xx/xx xx:xx:xx by mwildfire ===============================================================================

NET/MDA PEAK RESULTS ===============================================================================

PK. ENERGY ADDRESS NET/MDA UN- C.L. BKG FWHM # (keV) CHANNEL COUNTS CERTAINTY COUNTS COUNTS (keV) FLAG -------------------------------------------------------------------------------

24 364.48 728.50 25 0 11 23 1.05 25 438.63 876.89 26 0 12 23 1.11 26 479.57 958.82 19 0 8 12 1.15 27 497.08 993.85 22 0 10 16 1.17 28 529.50 1058.73 16 0 7 9 1.19 29 537.38 1074.50 15 0 6 7 1.20 30 559.10 1117.96 22 0 10 18 1.22 31 661.62 1323.10 24 0 11 21 1.30 32 724.18 1448.27 16 0 7 8 1.35 33 765.82 1531.58 17 0 7 10 1.39 34 795.76 1591.49 20 0 9 14 1.41 35 810.75 1621.48 22 0 10 17 1.42 36 818.50 1636.98 21 0 9 15 1.43 37 834.81 1669.61 23 0 10 18 1.44 38 846.60 1693.20 20 0 9 14 1.45 39 889.26 1778.55 23 0 10 18 1.49 40 937.48 1875.02 22 0 10 18 1.52 41 1260.41 2520.99 13 0 5 4 1.77 42 1291.56 2583.29 10 0 4 2 1.80 43 1368.55 2737.28 7 0 2 1 1.86 44 1383.90 2767.98 11 0 4 4 1.87 45 1691.04 3382.20 10 0 3 2 2.10 Page 006 , . Analyzed: xx/xx/xx xx:xx:xx by mwildfire ===============================================================================

R E T D A S A N A L Y S I S v2.4.0 ===============================================================================

SAMPLE TANKS Liquid Sample Analysis Nuclide uCi/ml +- uCi/ml Transfer? ========================================================================

SB-125 1.79e-07 4.44e-08 YES LA-140 6.04e-08 2.56e-08 YES RB-88 7.85e-07 4.28e-07 YES ZN-65 2.14e-07 4.43e-08 YES C0-60 5.71e-07 3.11e-08 YES TOTAL: 1.81e-06 F il e: 1 Sequen c e: 99999 F ilena m e: 00xxxxxx-01.pdf I nc lude d i n repo r t. EN D O F F I L E A T T A CH MENTS Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 1 of 7 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5-A S5 JPM Title: Emergency Event Classification Facility Number:

_______ N/A ___

(If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical 15 min Alternate Path Validation Time: 10 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ben Nadolny 9/15/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 2 of 7 Emergency Event Classification Setting: Classroom Type: SRO Task: SRO-A&E-015 K&A: 2.4.41 - 2.9/4.6 Safety Function
Emergency Procedures/Plan Performance
Actual Reference(s)
10-S-01-1 Handout(s)
EAL flow charts from 10

-S-01-1 10-S-01-1 (available)

  1. Manipulations
N/A # Critical Steps
1 Simulator Setup/Required Plant Conditions
None Safety Concerns
None Task Standard(s)
Within 15 minutes, classifies the event as
for SCENARIO #1 a SITE AREA EMERGENCY per EAL SS3 Date of Examination: 12/07/2015 Operating Test Number
LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 3 of 7 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

Based on the scenario you just participated in:

Scenario #1

- ATWS >4% power Feedwater line break in Drywell Initiating Cue(s):

Classify the event.

This JPM is time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 4 of 7 Emergency Event Classification Notes: (Notes to Evaluator)

Only the initial conditions for the specific scenario performed by the student as CRS is to be given to the student.

Task Overview:

(Detailed description of task)

An event classification JPM is required of all licensed SROs not qualified as an Emergency Director in accordance with the Emergency Preparedness Plan.

Tasks: Critical steps are underlined, italicized, and denoted by an (*)

Step 1: 10-S-01-1

  • For Scenario #1 Classify the event as a SITE AREA EMERGENCY Standard: For Scenario #1: EAL SS3 (SITE AREA EMERGENCY)

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 5 of 7 Task Standard(s)
Within 15 minutes, classifies the event as:

for SCENARIO #1 a SITE AREA EMERGENCY per EAL SS3 SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015AS5 Revision 0 GJPM-OPS-2015AS5 Page 6 of 7 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015AS5 JPM Title: Emergency Event Classification Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

___________________________________________________

Give this page to the student

Initial Condition(s):

Based on the scenario you just participated in:

Scenario #1

- ATWS >4% power Feedwater line break in Drywell Initiating Cue(s):

Classify the event.

This JPM is time critical.

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 12/7/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 2015 Control Room Systems

-I; 2 or 3 for SRO

-U System / JPM Title Type Code*

Safety Function a. 202001 A4.02 (3.5/3.4) Reset Recirc FCV Runback GJPM-OPS-201 5 S 1 A - D - S 1 b. 259001 A3.10 (3.4/3.4), Defeat Feed Pump Level 9 Trips GJPM-OPS-2015CR2 D - C - L 2 c. 239001 A2.11 (4.1/4.3), Slow Closing MSIV GJPM-OPS-2015 S 3 A - N - S 3 d. 209002 A1.01 (3.6/3.7), Performing HPCS Quarterly Functional Test, GJPM

-OPS-S 4 A - D - EN - S 4 e. 223001 A4.06 (4.0/4.0), Containment Venting GJPM-OPS-2015CR5 C - D - E - L 5 f. 212000 A4.02 (3.6/3.7), Reactor Manual Scram Switch Test, GJPM-OPS-2015 S 7 A - D - S 7 g. 400000 A4.01 (3.1/3.0), Manual Start of SSW 'A' System , GJPM-OPS-2015 S 8 A - M - S 8 h. 272000 A4.02 (3.0/3.0), Perform Area Radiation Monitor Functional Test, GJPM

-OPS-2015 s 9 D - S 9 In-Plant Systems

-I); (3 or 2 for SRO

-U) i. 262001 A2.11 (3.2/3.6), Reset Undervoltage Lockouts on BOP Buses, GJPM

-OPS-2015PS-6 D - R - L 6 j. 295016 A1.07 (4.2/4.3), Perform Attachment III of Shutdown From Remote Shutdown panel ONEP, GJPM

- OPS-2015PS-7 D - E - EN - L 7 k. 2.1.30: (4.4/4.0), Manually Initiate Fire Protection to the 'B' RPS Motor Generator Room, GJPM

-OPS-2015PS8 A - E - N 8

-I control room (and in

-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in

-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 /

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 12/7/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 2015 Control Room Systems

-I; 2 or 3 for SRO

-U System / JPM Title Type Code*

Safety Function a. 202001 A4.02 (3.5/3.4) Reset Recirc FCV Runback GJPM-OPS-201 5 S 1 A - D - S 1 b. 259001 A3.10 (3.4/3.4), Defeat Feed Pump Level 9 Trips GJPM-OPS-2015CR2 D - C - L 2 c. 239001 A2.11 (4.1/4.3), Slow Closing MSIV GJPM-OPS-2015 S 3 A - N - S 3 d. 209002 A1.01 (3.6/3.7), Performing HPCS Quarterly Functional Test, GJPM

-OPS-S 4 A - D - EN - S 4 e. 223001 A4.06 (4.0/4.0), Containment Venting GJPM-OPS-2015CR5 C - D - E - L 5 f. 212000 A4.02 (3.6/3.7), Reactor Manual Scram Switch Test, GJPM-OPS-2015 S 7 A - D - S 7 g. 400000 A4.01 (3.1/3.0), Manual Start of SSW 'A' System , GJPM-OPS-2015 S 8 A - M - S 8 In-Plant Systems* (3 for RO); (3 for SRO

-I); (3 or 2 for SRO

-U) i. 262001 A2.11 (3.2/3.6), Reset Undervoltage Lockouts on BOP Buses, GJPM

-OPS-2015PS-6 D - R - L 6 j. 295016 A1.07 (4.2/4.3), Perform Attachment III of Shutdown From Remote Shutdown panel ONEP, GJ PM- OPS-2015PS-7 D - E - EN - L 7 k. 2.1.30: (4.4/4.0), Manually Initiate Fire Protection to the 'B' RPS Motor Generator Room, GJPM

-OPS-2015PS8 A - E - N 8

-I control room (and in

-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in

-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 /

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 12/7/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT-2015 Control Room Systems

-I; 2 or 3 for SRO

-U System / JPM Title Type Code*

Safety Function a. 202001 A4.02 (3.5/3.4) Reset Recirc FCV Runback GJPM-OPS-201 5 S 1 A - D - S 1 b. 239001 A2.11 (4.1/4.3), Slow Closing MSIV GJPM-OPS-2015 S 3 A - N - S 3 c. 212000 A4.02 (3.6/3.7), Reactor Manual Scram Switch Test, GJPM-OPS-2015 S 7 A - D - S 7 In-Plant Systems

-I); (3 or 2 for SRO

-U) d. 262001 A2.11 (3.2/3.6), Reset Undervoltage Lockouts on BOP Buses, GJPM

-OPS-2015PS1 D - R - L 6 e. 2.1.30: (4.4/4.0), Manually Initiate Fire Protection to the 'B' RPS Motor Generator Room, GJPM

-OPS-2015PS8 A - E - N 8

-I control room (and in

-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in

-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 /

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 1 of 12 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 1 JPM Title: Reset Recirc FCV Runback Facility Number: __GJPM-OPS-B3313____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min Prepared By:

Exam Developer Date Ops Review: 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

2 nd Validation by Ops Validation Crew Date Approved By:

Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 2 of 12 Reset Recirc FCV Runback Time Critical Alternate Path Validation Time:

30 Min Setting: Simulator Type: RO Task: CRO-B33(2)-8; CRO-B33(2)-1 K&A: 202001 A4.02 (3.5/3.4) 202002 A4.08 (3.3/3.3)

Safety Function:

1 - Reactivity Control Performance:

Actual Reference(s):

04-1-01-B33-1, Rev 150 Handout(s) 04-1-01-B33-1, Section 6.6

  1. Manipulations:

5 # Critical Steps:

5 Simulator Setup/Required Plant Conditions

Reset Simulator to IC

-104 Run Schedule file 2015 NRC JPM MASTER OR Reset to any full power IC.

Manually trip B RFP.

Reset tripped RFP IAW 6.6.61.a Prerequisite.

Allow Recirc FCV runback to occur and conditions to steady out.

Assign trigger 1 to trigger file fcvb_cav_pb Insert malfunction rr173b at 3 to activate on event trigger 1 Override annunciator P680

-4A1-C4, RECIRC FCV B PARTIAL CLOSE/RFP TRIP to ON so that it will not clear.

Safety Concerns

None. Task Standard
Actions have been taken to reset Recirc FCV runback and to stop Recirc FCV B from opening in response to the Recirc Flow Control Valve malfunction.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 3 of 12 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant was operating at full power when B Reactor Feed Pump tripped.

A Recirc FCV runback occurred.

Power and core flow show entry into the OPRM Trip Enabled Region.

Reactor Engineering is assessing power distribution, FCBB and thermal limits Another reactor operator has the THI watch.

The 'B' RFPT tip has been resolved and 'B' RFPT has been reset.

Initiating Cue(s):

The CRS directs you to reset the Recirc FCV A and B Runback in accordance with section 6.6 0f SOI 04 01-B33-1.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 4 of 12 Reset Recirc FCV Runback Notes: (Notes to Evaluator)

All controls will be from panel P680 in the Main Control Room.

Task Overview:

(Detailed description of task)

This task resets a Recirc FCV runback following a trip of B RFP. When the operator depresses the RECIRC PMP B CAV INTLK RESET pushbutton, Recirc FCV B will ramp open from a malfunction. The operator must notice and report uncontrolled FCV opening and attempt to stop it. The CRS will direct shutdown of HPU B. The operator will take action to shutdown HPU B, shutdown the B Recirc Pump or shut the B33

-F067B from P680 which will terminate the power excursion. In the event the operator elects to perform all steps for FCV B first, all steps associated with FCV A become not applicable, and the JPM may be ended when the HPU for FCV B has been shut down

.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 5 of 12 Reset Recirc FCV Runback Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: 04-1-01-B33-1, Step 6.6.1 a Reactor vessel level is greater than low level alarm setpoint AND/OR Both Feed pumps are reset.

Standard: Checks vessel level is > 32" Narrow Range.

Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 6 of 12 Step 2: 04-1-01-B33-1, Step 6.6.2 a
  • USING Recirc Loop A(B) FLO CONT, LOWER signal output until one of the following occurs: (1) % Limiter Error is zero; OR (2) % Servo Error is zero; OR (3) FCV motion is noticed in the CLOSE direction; OR (4) A reduction in associated loop flow is noticed.

Standard: Lowers Recirc Loop A(B) Flo Cont until one of the listed items is satisfied

. Cue: If student uses slow detent, cue the candidate that fast detent may be used as desired.

Notes: SAT / UNSAT Step 3: 04-1-01-B33-1, Step 6.6.2 b

  • PRESS RECIRC PUMP A(B) CAV INTLK RESET pushbutton.

Standard: Depresses the Recirc pump A(B) Cav. Interlock Reset pushbutton on P680.

Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 7 of 12 Step 4 04-1-01-B33-1, Step 6.6.2 c OBSERVE "RECIRC FCV A(B) PARTIAL CLOSE/RFP TRIP" annunciator Resets.

Standard: Observes "RECIRC FCV A(B) PARTIAL CLOSE/RFP TRIP" annunciator Resets, P680-3A-D1 Cue: None Notes: SAT / UNSAT Step 5 04-1-01-B33-1, Step 6.6.2 a

  • USING Recirc Loop B(A) FLO CONT, LOWER signal output until one of the following occurs: (1) % Limiter Error is zero; OR (2) % Servo Error is zero; OR (3) FCV motion is noticed in the CLOSE direction; OR (4) A reduction in associated loop flow is noticed.

Standard: Lowers Recirc Loop B(A) Flo Cont until one of the listed items is satisfied

. Cue: If student uses slow detent, cue the candidate that fast detent may be used as desired.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 8 of 12 Step 6: 04-1-01-B33-1, Step 6.6.2 b
  • PRESS RECIRC PUMP A(B) CAV INTLK RESET pushbutton.

Standard: Depresses RECIRC PMP B CAV INTL RESET pusbutton.

Cue: None. Notes: Trigger 1 will automatically insert when pushbutton is depressed.

OR After Reset pushbutton is depressed insert "Trigger 1".

SAT / UNSAT Step 7: 04-1-01-B33-1, Step 6.6.2 c OBSERVE "RECIRC FCV B(A) PARTIAL CLOSE/RFP TRIP" annunciator Resets.

Standard: Checks for annunciator P680

-4A1-C4, RECIRC FCV B PARTIAL CLOSE/RFP TRIP resetting but observes it remains in alarm. Observes FCV B opening, servo error, and limiter error changing.

Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 9 of 12 Step 8: 04-1-01-B33-1 Recognizes 'B' FCV is drifting open Standard: Recognizes 'B' FCV is drifting open by observing valve position indicator moving in the open direction.

Cue: If asked for guidance, as CRS direct operator to perform actions to stop valve movement

. Notes: SAT / UNSAT Step 9: 04-1-01-B33-1

  • Trip Recirc Pump B Hydraulic Power Unit to stop valve movement

. Standard: Arms and depresses HPU B SHUTDN pushbutton on P680.

Cue: None Notes: Armed collar pushbutton on P680 section 3C. This action will stop valve movement.

After HPU is shutdown the evaluator may stop the JPM.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 10 of 12 Task Standard(s)
Actions have been taken to reset Recirc FCV runback and to stop Recirc FCV B from opening in response to the Recirc Flow Control Valve malfunction.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015 S 1 Revision 0 9/14/2015 Page 11 of 12 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 1 JPM Title: Reset Recirc FCV Runback Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

The plant was operating at full power when B Reactor Feed Pump tripped.

A Recirc FCV runback occurred.

Power and core flow show entry into the OPRM Trip Enabled Region.

Reactor Engineering is assessing power distribution, FCBB and thermal limits Another reactor operator has the THI watch.

The 'B' RFPT tip has been resolved and 'B' RFPT has been reset.

Initiating Cue(s):

The CRS directs you to reset the Recirc FCV A and B Runback in accordance with section 6.6 0f SOI 04 01-B33-1.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 1 of 9 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015CR2 JPM Title: Defeat Feed Pump Level 9 Trips Facility Number: _GJPM-OPS-EOP006____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min Applicant: ________________________________

Examiner:

_________________________________

Performance Time:

________________________

Performance Rating:

SAT UNSAT Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Benny White 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Comments:

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 2 of 9 Defeat Feed Pump Level 9 Trips Time Critical Alternate Path Validation Time: 15 min Setting: Control Room Type: RO Task: CRO-EP-006 K&A: 259001 A3.10 3.4/3.4 Safety Function:

2 - Reactor Water Inventory Control System Performance:

Simulated Reference(s):

05-S-01-EP-1/Attachment 6 Handout(s) 05-S-01-EP-1 Attachment 6

  1. Manipulations:

6 # Critical Steps:

4 Simulator Setup/Required Plant Conditions

Control Room operating panels and backpanel P612 is accessible, with permission from the Shift Manager to panels for inspection only.

Safety Concerns

Possible electric shock while inspecting interior of panels

- Do not break the plane of any panels (student should use an appropriate indicating device to identify component/connection locations).

Task Standard

The Reactor Feed Pump Level 9 trips are defeated in accordance with 05-S-01-EP-1, Attachment 6 steps 2.1 thru 2.
4.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 3 of 9 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

EOP's have been entered

. Initiating Cue(s):

You have been directed to perform steps 2.1 through 2.

4 of EP Attachment 6.

Another operator will complete the remaining steps of this attachment when directed.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 4 of 9 Defeat Feed Pump Level 9 Trips Notes: (Notes to Evaluator)

RFPT reset controls and indications are on P680.

Panel P612 is in the Main Control Room Task Overview:

(Detailed description of task)

This task defeats the High Reactor Water Level trip of the Reactor Feed Pumps, which under certain conditions is directed by the EOPs to maintain adequate core cooling.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 5 of 9 Critical tasks are underlined, italicized, and denoted by an (*)

Sequence for the following steps is not critical unless otherwise denoted

. Step 1: 05 02-I-1 OBTAIN EOP Attachment 6 from Control Room emergency locker.

Standard: Locates Control Room Emergency Locker Locates Attachment No. 6 Cue: None Notes: Once candidate has located the emergency locker and the correct Attachment, give the paper copy of Attachment 6.

SAT / UNSAT Step 2: 05-S-01-EP-1, Att. 6, 2.1

  • Remove relay C34-K7J. Standard: Locates relay C34

-K7J in panel P612, Bay B, 3rd row from top, 1st relay from left

. Simulates removal by describing unclipping and pulling the relay

. Cue: Relay C34-K7 J is removed

. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 6 of 9 Step 3: 05-S-01-EP-1, Att. 6, 2.2
  • Remove relay C34-K7G Standard: Locates relay C34

-K7G in panel P612, Bay B, 3rd row from top, 2nd relay from left .

Simulates removal by describing unclipping and pulling the relay.

Cue: Relay C34-K7G is removed Notes: SAT / UNSAT Step 4: 05-S-01-EP-1, Att. 6, 2.

3

  • Remove relay C34-K7A Standard: Locates relay C34

-K7A in panel P612, Bay B, 2nd row from top, 1st relay from left

. Simulates removal by describing unclipping and pulling the relay Cue: Relay C34-K7 A removed Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 7 of 9 Step 5: 05-S-01-EP-1, Att. 6, 2.4
  • Remove relay C34

-K7F Standard: Locates relay C34

-K7F in panel P612, Bay B, 3rd row from top, 3rd relay from left

. Simulates removal by describing unclipping and pulling the relay

. Cue: Relay K34-K7F is removed Notes: SAT / UNSAT Task Standard(s)

The Reactor Feed Pump Level 9 trips are defeated in accordance with 05

-S-01-EP-1, Attachment 6 steps 2.1 thru 2.

4. SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5CR 2 Revision 0 9/14/2015 Page 8 of 9 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015CR 2 JPM Title: Defeat Feed Pump Level 9 Trips Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ______________________

______________________________

Examiner's Signature:

____________________________________________________

Give this page to the student

Initial Condition(s):

EOP's have been entered

. Initiating Cue(s):

You have been directed to perform steps 2.1 through 2.

4 of EP Attachment 6.

Another operator will complete the remaining steps of this attachment when directed.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 1 of 10 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-201 5 S 3 JPM Title:

Slow Closing MSIV Facility Number:

N/A (If Bank or Modified from Bank) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time:

15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review: Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Christopher Baxter 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 2 of 10 Slow Closing MSIV Setting: Simulator Type: RO Task: CRO-B21-SU/SD-0 0 1 K&A: 239001: A2.11 (4.1/4.3); A 3.01 (4.2/4.1); A4.01 (4.2/4.0) Safety Function:

3 - Reactor Pressure Control Performance:

Actual Reference(s):

04-1-01-B21-1 Handout(s) 04-1-01-B21-1 (5.4) # Manipulations:

4 # Critical Steps:

4 Simulator Setup/Required Plant Conditions

Reset Simulator to IC

-106 Run schedule file 2015 NRC JPM Master Safety Concerns

None Task Standard
Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Perform actions to ensure a Group 1 MSIV isolation by manually closing all MSIVs.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 3 of 10 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at approximately 50%

power. Initial startup after refueling outage.

MSIV, B21-F028A, was reworked during the outage

. Initiating Cue(s):

The CRS directs you to perform a slow closing of MSIV B21

-F028A, using 04-1-01-B21-1, Nuclear Boiler System SOI, section 5.4

. After MSIV B21

-F028A reaches full closed place handswitch for B21

-F028A to the CLOSE position.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 4 of 10 Slow Closing MSIV Notes: (Notes to Evaluator)

All controls and indications for this task are on panel 1H13

-P 601. Task Overview:

(Detailed description of task)

This task is to perform a slow close on MSIV B21

-F028A. Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Student should manually close all remaining MSIVs (7) using handswitches on P601 panel.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 5 of 10 Critical steps are underlined, italicized, and denoted by an (*)

Step 1: 04-1-01-B21-1, Step 5.4.2 a

  • PLACE associated MSIV handswitch on 1H13

-P601 to TEST Standard: Places handswitch for B21

-F028A on 1H13

-P601 to the TEST position.

Cue: None Notes:

SAT / UNSAT Step 2: 04-1-01-B21-1, Step 5.4.2 a

  • DEPRESS MSIV TEST pushbutton. Holding pushbutton slow closes valve fully.

Standard: Depresses and holds the MSIV TEST pushbutton until B21

-F028A indicates full close, indicated by green light on red light off.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 6 of 10 Step 3: 04-1-01-B21-1, Step 5.4.2 b
  • IF desired, WHEN MSIV is fully CLOSED, PLACE MSIV handswitch from TEST to CLOSE, THEN RELEASE pushbutton.

Standard: After B21-F028A reaches the full closed position, places B21

-F028A handswitch to the CLOSE position.

Cue: None Notes: When handswitch is placed in the CLOSE position a steam line break will occur inside the Main Steam Tunnel.

SAT / UNSAT Step 4: EN-OP-120, Att. 9.2 Recognize a Group 1 MSIV isolation signal

. Standard: Recognizes a Group 1 MSIV isolation signal by observing the following alarms: P601-18A(19A)-A3 and A4, MSL PIPE TNL CH A (B,C,D) TEMP HI Cue: None Notes: Operating Fundamental Monitoring

- Verify and report automatic system actuations or response, which includes operator actions if the plant has not responded as expected.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 7 of 10 Step 5: EN-OP-120, Att. 9.2 Recognize Group 1 MSIV isolation did not occur.

Standard: Recognizes all remaining (7) MSIVs are open.

Cue: If operator reports a failure of a Group 1 isolation; respond as the CRS, "I understand failure of Group 1 isolation;" also if asked the ATC will place the Mode Switch to shutdown."

Notes: Student may report EP

-4 entry condition.

Operating Fundamental Monitoring

- Verify and report automatic system actuations or response, which includes operator actions if the plant has not responded as expected.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 8 of 10 Step 6: EN-OP-120, Att. 9.2
  • Place all remaining MSIV handswithes (7) to the CLOSE position.

Standard: Places all remaining MSIV handswit ches (7) to the CLOSE position.

Cue: After all MSIVs (8) MSIVs are in the closed position evaluator can end the JPM and tell the student end of task.

Notes: Operating Fundamental Monitoring

- Verify and report automatic system actuations or response, which includes operator actions if the plant has not responded as expected.

SAT / UNSAT

Task Standard(s)

Recognize High High temperature in Main Steam Tunnel without a Group 1 MSIV isolation. Perform actions to ensure a Group 1 MSIV isolation by manually closing all MSIVs. SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 3 Revision 0 9/14/2015 Page 9 of 10 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 3 JPM Title: Slow Closing MSIV Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Give this page to the student Initial Condition(s):

The plant is at approximately 50%

power. Initial startup after refueling outage.

MSIV, B21-F028A, was reworked during the outage.

Initiating Cue(s):

The CRS directs you to perform a slow closing of MSIV B21

-F028A, using 04 01-B21-1, Nuclear Boiler System SOI, section 5.4.

After MSIV B21

-F028A reaches full closed place handswitch for B21

-F028A to the CLOSE position.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 1 of 13 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 4 JPM Title: Performing HPCS Quarterly Functional Test Facility Number:

N/A (Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ken Haley 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 2 of 13 Performing HPCS Quarterly Functional T est Time Critical Alternate Path Validation Time:

1 0 Min Setting: Simulator Type: RO Task: CRO-E22-008, 010 K&A: 209002: A1.01-3.6/3.7; A4.01

- 3.7/3.7 Safety Function:

4 - Heat Removal from Reactor Core Performance:

Actual Reference(s):

06-OP-1E22-Q-0005, Rev. 1 20 EN-OP-115, Rev.

13 02-S-01-27, Rev 51 Handout(s) 06-OP-1E22-Q-0005 # Manipulations:

5 # Critical Steps:

4 Simulator Setup/Required Plant Conditions

Reset Simulator to IC

-107 Run Schedule File 2015 NRC JPM Master Ensure HPCS MOV test witch in normal. HPCS system OOSVC lit.

Safety Concerns

None Task Standard
The HPCS pump is started for full test return flow, Suppression Pool to Suppression Pool, when both Main Feed Pumps trip and HPCS fails to auto initiate. Student must manually initiate HPCS and open the E22

-F004.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 3 of 13 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

06-OP-1E22-Q-0005, HPCS Quarterly Functional Test, Attachment 1 is in progress at step 5.2.2 t. SSW C is in STANDBY All Prerequisites are met Initiating Cue(s):

The CRS directs you to continue with 06

-OP-1E22-Q-0005, HPCS Quarterly Functional Test, Attachment 1

.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 4 of 13 Performing HPCS Quarterly Functional T est Notes: (Notes to Evaluator)

All controls and indications for this task are on panel 1H13

-P6 01 and P870. Task Overview:

(Detailed description of task)

This task requires the ability to manually start the only ECCS

-qualified high pressure injection system.

This task demonstrates the ability to operate HPCS in the "test return" mode, which puts HPCS flow in a loop from and to the Suppression Pool, one of its two suction sources. HPCS is operated in this mode for surveillance and post

-maintenance testing.

As HPCS is placed in the test return mode the system will experience a fail to initiat e and a fail to inject once manually initiated. This will require to arm and depress the initiation pushbutton and then manually open the E22

-F004.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 5 of 13 Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 t PLACE the SSW DIV 3 MOV TEST switch in the TEST position.

Standard: Places the SSW DIV 3 MOV TEST switch in the TEST position.

Cue: None Notes: SAT / UNSAT Step 2: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 u OBSERVE that "SSW DIV 3 MOVS IN TEST MODE" annunciator, 1H13

-P870-5A-G2, Alarms. Standard: Observes that "SSW DIV 3 MOVS IN TEST MODE" annunciator, 1H13

-P870-5A-G2, Alarms. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 6 of 13 Step 3: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 v OBSERVE that SSW D3 MOV IN TEST STATUS light energizes.

Standard: Observes that SSW D3 MOV IN TEST STATUS light energizes.

Cue: None Notes: SAT / UNSAT Step 4: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 w

  • START HPCS pump using HPCS PUMP handswitch AND VERIFY HPCS pump starts.

Standard: Operator starts the HPCS Pump utilizing its handswitch on P601 and observes pump indicating lights shows a pump start.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 7 of 13 Step 5: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 w VERIFY the following has occurred
(2) F012, HPCS MIN FLO TO SUPP POOL, OPENS as discharge pressure indicated on PI-R601, HPCS PMP DISCH PRESS, increases above 130 psig.

(3) HPCS Room Cooler Fan has started USING indication above HPCS PMP RM CLR T51-B001 handswitch on Panel 1H13

-P870-5C. (4) SSW LOOP C (HPCS SSW) on Panel 1H13

-P870-5C started automatically.

Standard: Operator checks items listed by observing the indications stated. Cue: None Notes: SAT / UNSAT Step 6: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 x OPEN FX019 Standard: Operator request a plant operator to open E22-FX019. Cue: When requested to open E22-FX019, report the valve is open.

Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 8 of 13 Step 7: 06-OP-1E22-Q-0005, Att. 1 Step 5.2.2 y
  • THROTTLE F023 as necessary to achieve a flow of approximately 7200 gpm (tolerance: >7176 to 7255 gpm) as indicated on HPCS PUMP FLOW indicator 1E22

-FI-R603. Standard: Operator opens E 22-F0 23 to achieve desired flow

. Cue: Upon reactor scram, give scram report, "Mode switch is in Shutdown, Reactor Water Level is

-20" Wide Range and lowering, All rods are in."

Notes: As F0 23 is opening , a trip of both reactor feed pumps will occur. This will result in a failed initiation of HPCS

. The operations contained in the remainder of this JPM are not contained in the HPCS surveillance or SOI. SAT / UNSAT Step 8: 04-1-01-E22-1 The operator recognizes the failed initiation.

Standard: Operator recognizes failed initiation of HPCS by observing system indications on P601 and reports failure to the CRS.

Cue: Act as CRS and acknowledge the operators report.

Notes: Operator may elect to take action to initiate HPCS injection prior to reporting failure to CRS. This is acceptable.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 9 of 13 Step 9: 02-S-01-27, Step 6.6.3 a
  • USING HPCS MAIN INIT pushbutton on 1H13

-P601 by ROTATING collar to the ARMED position AND PUSHING red button

. Standard: Rotates the collar to the ARMED position and pushes the red button

. Cue: None Notes: SAT / UNSAT Step 10:

02-S-01-27, Step 6.6.3 b The operator recognizes the E22

-F004 (HPCS Injection Valve) fails to open. Standard: Operator recognizes failed injection of HPCS by observing system indications on P601 and reports failure to the CRS.

Cue: Act as CRS and acknowledge the operators report.

Notes: Operator may elect to take action to inject HPCS prior to reporting failure to CRS. This is acceptable.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 10 of 13 Step 11:

02-S-01-27, Step 6.6.3 c

  • OPEN E22-F004 (HPCS Injection Valve)

. Standard: Opens the E22-F004 using its handswitch on P601 and observing its red light is o n and its green light is o ff. Cue: None Notes: Once the E22F004 is opened the evaluator may stop the JPM.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 11 of 13 Task Standard(s)
The HPCS pump is started for full test return flow, Suppression Pool to Suppression Pool, when both Main Feed Pumps trip and HPCS fails to auto initiate. Student must manually initiate HPCS and open the E22

-F004. SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-201 5 S 4 Revision 0 9/14/2015 Page 12 of 13 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 4 JPM Title: Performing HPCS Quarterly Functional Test Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Give this page to the student

Initial Condition(s):

06-OP-1E22-Q-0005, HPCS Quarterly Functional Test, Attachment 1 is in progress at step 5.2.2 t.

SSW C is in STANDBY All Prerequisites are met Initiating Cue(s):

The CRS directs you to continue with 06

-OP-1E22-Q-0005, HPCS Quarterly Functional Test, Attachment 1.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 1 of 10 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015CR5 JPM Title:

EP-1 Attachment 14

- Containment Venting Facility Number:

GJPM-OPS-EOP14 (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By: Mike Starnes 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 2 of 10 EP-1 Attachment 14

- Containment Venting Time Critical Alternate Path Validation Time:

30 Min Setting: Control Room Type: RO Task: CRO-EP-014 VENT CONTAINMENT (EP

-1 Attachment 14)

K&A: 295024 EA1.18 [3.6/3.6]

Safety Function

2 Performance
Simulated Reference(s)
05-S-01-EP-1, Attachment 14 Handout(s)
05-S-01-EP-1, Attachment 14
  1. Manipulations
5 # Critical Steps
5 Simulator Setup/Required Plant Conditions
None Safety Concerns
None. Task Standard
Actions have been taken to vent containment

.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 3 of 10 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

EP 2 and 3 have been entered.

Reactor level is being maintained between +

50 to -30 inches.

Reactor pressure is being maintained between 800 to 10 60 psig with SRVs.

Drywell pressure is below 1.0 psig.

No Containment or Secondary Containment Isolation signal is present for M41 and E61 valves. The emergency director has been notified that an unfiltered release will occur during venting of the containment.

Initiating Cue(s):

You have been directed to perform containment venting per EP

-1 Attachment 14 steps 2.2 through 2.6.

This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 4 of 10 EP-1 Attachment 14

- Containment Venting Notes: (Notes to Evaluator)

1. This task is performed from the control room to vent the primary containment via 6

-inch ventilation lines with no Containment or Secondary Containment Isolation signal present.

2. EP-1 attachments are maintained in a special file box normally located in or in the close proximity of the Emergency Locker in the Control Room behind the P601 panel.

Task Overview:

(Detailed description of task)

Performance of this task vents the primary containment via 6

-inch ventilation lines with no Containment or Secondary Containment Isolation signal present for M41 and E61 valves.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 5 of 10 EP-1 Attachment 14

- Containment Venting Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: 05 02-I-1 OBTAIN EOP Attachment 14 from Control Room emergency locker.

Standard: Locates Control Room Emergency Locker Locates Attachment No. 14 Cue: None Notes: Once candidate has located the emergency locker and the correct Attachment, give the paper copy of Attachment 6.

SAT / UNSAT Step 2: 05-S-01-EP-1, Step 2.2 Open M41F037 CTMT CLG VENT EXH AUX BLDG OTBD ISOL on 1H13

-P870-8C. Standard: Simulates opening valve M41

-F037 by turning the valve's handswitch on P870 in the clockwise direction.

Cue: For valve M41-F037, the red light is on and the green light is off.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 6 of 10 Step 3: 05-S-01-EP-1, Step 2.3
  • Open M41F036 CTMT CLG VENT EXH AUX BLDG INBD ISOL on 1H13

-P870-2C. Standard: Simulates opening valve M41

-F036 by turning the valve's handswitch on P870 in the clockwise direction.

Cue: For valve M41-F036, the red light is on and the green light is off.

Notes: SAT / UNSAT Step 4: 05-S-01-EP-1, Step 2.4

-P870-4C. Standard: Simulates opening valve E61

-F057 by turning the valve's handswitch on P870 in the clockwise direction.

Cue: For valve E61

-F057, the red light is on and the green light is off.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 7 of 10 Step 5 05-S-01-EP-1, Step 2.5 Open E61F056 PURGE EXH CTMT INBD ISO VLV on 1H13

-P870-10C. Standard: Simulates opening valve E61

-F056 by turning the valve's handswitch on P870 in the clockwise direction.

Cue: For valve E61

-F056, the red light is on and the green light is off.

Notes: SAT / UNSAT Step 6 05-S-01-EP-1, Step 2.6

  • Start one or both Containment Exhaust Charcoal Filter Train fans by placing CTMT CLG EXHAUST FAN A AND/OR B handswitches to start.

Standard: Simulates starting one or both Containment Exhaust Charcoal Filter Train fans by placing CTMT CLG VENT EXHAUST FAN A AND/OR B handswitch to START on P842. Cue: For one or both Containment Exhaust Charcoal Filter Train fans, the red light is on and the green light is off.

Notes: At least one fan is required to be running so that associated fan supply and discharge dampers open to complete the flow path.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 8 of 10 Task Standard(s)
Actions have been taken to vent containment.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015CR 5 Revision 0 9/14/2015 Page 9 of 10 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015CR 5 JPM Title:

EP-1 Attachment 14

- Containment Venting Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ______________

______________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

EP 2 and 3 have been entered.

Reactor level is being maintained between +

50 to -30 inches.

Reactor pressure is being maintained between 800 to 10 6 0 psig with SRVs.

Drywell pressure is below 1.0 psig.

No Containment or Secondary Containment Isolation signal is present for M41 and E61 valves. The emergency director has been notified that an unfiltered release will occur during venting of the containmen

t. Initiating Cue(s):

You have been directed to perform containment venting per EP

-1 Attachment 14 steps 2.2 through 2.6.

This task is not time critical.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 7 JPM Title: Reactor Manual Scram Switch Test Facility Number: __GJPM-OPS-C7105____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 min

Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Christopher Baxter 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 2 of 11 Reactor Manual Scram Switch Test Setting: Simulator Type: RO Task: CRO-C71-OFFNORM-005 K&A: 212000 A2.03 (3.3/3.5), A4.02 (3.6/3.7) 2.1.30 (4.4/4.0), 2.1.20 (4.6/4.6)

Safety Function: 7 Performance:

Actual Reference(s):

06-OP-1C71-W-0001 (Reactor Manual Scram Switch Test Surveillance)

Handout(s):

06-OP-1C71-W-0001 # Manipulations:

5 # Critical Steps:

4 Simulator Setup/Required Plant Conditions

Load IC 104 and schedule file 2015 NRC JPM Master.

Safety Concerns

None Task Standard
Reactor is scrammed per 05 02-IV-1, Control Rod/Drive Malfunctions ONEP.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 3 of 11 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is operating at 67%. Initiating Cue(s):

The CRS directs you to perform 06

-OP-1C71-W-0001. All prerequisites are verified met.

Start with Data Sheet 1 and go in order through Data Sheet 4.

This task is not time critical.

You are the on watch ATC.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 4 of 11 Reactor Manual Scram Switch Test Notes: (Notes to Evaluator)

Task Overview:

(Detailed description of task)

The operator will perform 06

-OP-1C71-W-0001 (Reactor Manual Scram Switch Test).

When the operator depresses the first manual scram switch, nine control rods will scram due to a blown pilot solenoid fuse on the individual HCU units.

The operator should recognize nine scramed rods and scram the reactor

. Critical tasks are underlined, italicized, and denoted by an (*)

Step 1: 06

-OP-1C71-W-0001 step 5.1 OBTAIN Shift Supervision's permission to start. Performer to RECORD Test Start Time on Data Package Cover Sheet.

Standard: Records the start time on the Surveillance Cover Sheet.

Cue: If the operator asks permission to begin the surveillance, inform the operator that the CRS has given permission to begin.

Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 5 of 11 Step 2: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.2 VERIFY the following lights are ON to ensure that NO RPS trip signals are present:

RPS DIV 1 SCRAM SOL VLV 1A AND 1B lights ON (5C1) RPS DIV 2 SCRAM SOL VLV 2A AND 2B lights ON (7C1)

RPS DIV 3 SCRAM SOL VLV 3A AND 3B lights ON (5C1) RPS DIV 4 SCRAM SOL VLV 4A AND 4B lights ON (7C1)

Standard: Observes white scram solenoid valve lights lit.

Cue: Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 6 of 11 Step 3: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.3

  • ARM the Div 1 MAN SCRAM Switch (5C1) by rotating the collar clockwise. VERIFY alarm RPS MAN SWITCH PERM is received (5A

-B3) RPS MAN SWITCH SCRAM PERM alarm is ON Standard: Rotates switch collar.

Cue: Notes: SAT / UNSAT Step 4: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.4

  • Depress the MAN SCRAM Switch which was previously Armed.

Standard: Depress MAN SCRAM Switch.

Cue: Notes: When the manual scram switch is depressed, two control rods will scram. SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 7 of 11 Step 5: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.5 VERIFY the following:

RPS SCRAM SOL VLVs lights 1A, 3A, on (5C1)

AND 2A, 4A on (7C1) are OFF RPS SCRAM SOL VLVs lights 1B, 3B, on (5C1)

AND 2B, 4B on (7C1) are ON RX SCRAM TRIP alarm is received (7A

-A2) RX MAN SCRAM TRIP alarm is received (7A

-A3) Standard: Observes indications listed.

Cue: Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 8 of 11 Step 6: 06

-OP-1C71-W-0001 Data Sheet 1 step 5.5.4

  • Depress pushbutton SCRAM VLV (6C) AND VERIFY that NO scram valves are Open, as indicated by a green LED being OFF for all CRD/HCUs on the rod display map (6D) that are NOT tagged out.

Standard: Determines that two Control Rods have scramed.

Cue: Notes: Control Rods 28-17, 28-49, 52-33, 12-33, 36-17, 36-49, 28-33, 44-25, and 44-41 have scramed.

Once the operator determines that rods have scramed the operator should enter the Control Rod/Drive Malfunctions ONEP. SAT / UNSAT Step 7: Control Rod/Drive Malfunctions ONEP step 2.4

.2

. Standard: Rotates the mode switch counter clockwise to shutdown.

Cue: Notes:

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 9 of 11 Task Standard(s)
Reactor is scrammed per 05 02-IV-1, Control Rod/Drive Malfunctions ONEP.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S7 Revision 0 9/14/2015 Page 10 of 11 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 7 JPM Title: Reactor Manual Scram Switch Test Follow-Up Questions & Answers: Comments: Performance Rating

SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Revision 0 9/14/2015 Page 11 of 11 Give this page to the student

Initial Condition(s):

The plant is operating at 67%. Initiating Cue(s):

The CRS directs you to perform 06

-OP-1C71-W-0001. All prerequisites are verified met.

Start with Data Sheet 1 and go in order through Data Sheet 4.

This task is not time critical.

You are the on watch ATC.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 1 of 15 GGNS 201 5 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 8 JPM Title: Manual Start of SSW A Facility Number:

N/A (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Christopher Baxter 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 2 of 15 Manual Start of SSW A Time Critical Alternate Path Validation Time:

1 5 Min Setting: Simulator Type: RO Task: CRO-P41-1, 3 K&A: 400000: A4.01 3.1/3.0 2.1.20: 4.6/4.6 Safety Function:

8 - Plant Service Systems Performance:

Actual Reference(s):

04-1-01-P41-1/4.2 Handout(s) 04-1-01-P41-1/4.2 # Manipulations:

6 # Critical Steps:

5 Simulator Setup/Required Plant Conditions

Reset Simulator to any IC. Load schedule file, 2015 NRC JPM Master.

Safety Concerns

None Task Standard
SSW 'A' is running with F064A (SSW INL TO CR A/C A) closed or SSW A pump tripped.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 3 of 15 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

SSW A is in STANDBY.

Initiating Cue(s):

Prerequisites are complete The CRS directs you to manually start SSW

'A' (controlled start) per P41

-1 SOI, Section 4.2

. Your supervisor wants flow through the RHR 'A' heat exchangers, 'A' Control Room A/C, and the 'A' ESF Switchgear Room Coolers.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 4 of 15 Manual Start of SSW A Notes: (Notes to Evaluator)

All controls and indications for this task are on panel P870. Task Overview:

(Detailed description of task)

This task is a manual startup SSW 'A' and isolate the reported leak by shutting E12-F005A or securing SSW 'A' Pump.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 5 of 15 Critical tasks are underlined, italicized, and denoted by an (*)

Sequence for the following steps is not critical unless otherwise denoted

. Step 1: 04 01-P41-1 Place SSW A MOV TEST Switch to the TEST posit ion. Standard: Places SSW A MOV TEST Switch in the TEST position Cue: None Notes: Not a step in the procedure but is a precaution and limitation.

SAT / UNSAT Step 2: 04-1-01-P41-1, 4.2.2 a (1)

CHECK OPEN F006A, SSW PMP A RECIRC VLV.

Standard: Checks open P41

-F006A by observing its red light is on and its green light is off. Cue: None Notes: Switch should be in the AUTO position already. SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 6 of 15 Step 3: 04-1-01-P41-1, 4.2.2 a (2)
  • START SSW PMP A Standard: Starts SSW Pump A by rotating its spring

-return switch clockwise to START, and verifies it running by observing its red light is on and its green light is off. Cue: None Notes: SAT / UNSAT Step 4: 04-1-01-P41-1, 4.2.2 a (3)

Standard: Opens P41-F001A by rotating its spring

-return switch clockwise to OPEN, and verifies it open by observing its red light is on and its green light is off Cue: None Notes:

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 7 of 15 Step 5: 04-1-01-P41-1, 4.2.2 a (4)(a)

Standard: Opens P41-F014A by rotating its spring

-return switch clockwise to OPEN, and verifies it open by observing its red light is on and its green light is off Cue: None Notes: SAT / UNSAT Step 6: 04-1-01-P41-1, 4.2.2 a (4) (b)

OPEN OR CHECK OPEN F068A, RHR HX OUTL VLV.

Standard: Checks open P41

-F068A by observing its red light is on and its green light is off Cue: None Notes: P41F068A is normally open.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 8 of 15 Step 7: 04-1-01-P41-1, 4.2.2 a (5)

Standard: Opens P41-F005A by rotating its spring

-return switch clockwise to JOG OPEN and holding it in this position until the valve is full open as indicated by its red light on and its green light off Cue: None. Notes: SAT / UNSAT Step 8: 04-1-01-P41-1, 4.2.2 a (6)

. Standard: Closes P41

-F006A by rotating its spring

-return switch counter

-clockwise to CLOSE, and verifies it closed by observing its green light is on and its red light is off Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 9 of 15 Step 9: 04-1-01-P41-1, 4.2.2 b START SSW CLG TWR FAN A AND B. Standard: Starts SSW Cooling Tower Fan A and B by rotating its spring

-return switch clockwise to START, and verifies its running by observing its red light is on and its green light is off Cue: None Notes: SAT / UNSAT Step 10: 04-1-01-P41-1, 4.2.2 c (1)

  • OPEN F081A, SSW OUTL FM CR A/C A Valve.

Standard: Opens P41-F081A by rotating its spring

-return switch clockwise to OPEN and verifies the valve is full open as indicated by its red light on and its green light off.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 10 of 15 Step 1 1: 04-1-01-P41-1, 4.2.2 c (2)
  • CLOSE F074A, PSW OUTL FM CR A/C A Valve.

Standard: Closes P41

-F074A by rotating its spring

-return switch counter

-clockwise to CLOSE, and verifies it closed by observing its green light is on and its red light is off.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 11 of 15 Step 1 2: 04-1-01-P41-1, 4.2.2 c (3)
  • OPEN F064A, SSW INL TO CR A/C A Valve.

Standard: Opens P41-F064A by rotating its spring

-return switch clockwise to OPEN and verifies the valve is full open as indicated by its red light on and its green light off.

Cue: Notes: When the F064A is fully open, the SSW flow indication will begin to lower and the SSW LOOP A LEAK HI (P870

-1A-E1) alarm will alarm. SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 12 of 15 Step 8: EN-OP-120, Attachment 9.2, Monitoring and Control. 02-S-01-43 section 6.4.1
  • Recognizes isolable leak downstream of F064A and isolates the leak by shutting F064A (SSW INL TO CR A/C A)

OR removes driving force of leak by securing the SSW A pump.

Standard: Closes P41

-F064A by rotating its spring

-return switch counter-clockwise to CLOSE, and verifies it closed by observing its green light is on and its red light is off

. OR Secures SSW A pump by rotating its spring return switch counter clockwise to TRIP and verifies it green light is on and its red light is off.

Cue: If requested to (per 04 02-1H13-P870-1A-E1): Check flow mismatch of SSW Loop A discharge and return flow per computer points, report PDS is out of service.

Dispatch an operator to determine where leak is and isolate if possible, report building operator sees water spraying on A CR A/C unit from piping downstream of F064A.

Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 13 of 15 Task Standard(s)
SSW 'A' is running with F064A (SSW INL TO CR A/C A) closed or SSW A pump tripped.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S8 Revision 0 9/14/2015 Page 14 of 15 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015 S 8 JPM Title: Manual Start of SSW A Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Give this page to the student Initial Condition(s):

SSW A is in STANDBY.

Initiating Cue(s):

Prerequisites are complete The CRS directs you to manually start SSW

'A' (controlled start) per P41

-1 SOI, Section 4.2

. Your supervisor wants flow through the RHR 'A' heat exchangers, 'A' Control Room A/C, and the 'A' ESF Switchgear Room Coolers.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 1 of 21 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 S 9 JPM Title: Perform Area Radiation Monitor Functional Test Facility Number:

GJPM-OPS-D2101 (If Bank or Modified from Bank)

JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 15 Min Prepared By:

Steve Reeves 9/1/2015 Exam Developer Date Ops Review:

Roy Purdy 9/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By: Ben Nadolny 9/14/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/14/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 2 of 21 Perform Area Radiation Monitor Functional Test Time Critical Alternate Path Validation Time:

1 5 Min Setting: Simulator Type: RO Task: CRO-D21-003 K&A: 272000: A4.02

- 3.0/3.0 Safety Function

9 - Radioactivity Release / 7

- Instrumentation Performance

Actual Reference(s)
04-1-03-D21-1 Attachment I Handout(s)
04-1-03-D21-1 Attachment I, pages 1

-3, marked up to perform test for D21K601 # Manipulations

11 # Critical Steps
8 Simulator Setup/Required Plant Conditions
Reset simulator to any IC and load schedule file 2015 NRC JPM Master Override annunciator P680

-4A1-E6 OFF. Safety Concerns

None Task Standard
ARM D21K601 functional test is complete.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 3 of 21 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant is at rated power.

I&C has completed repair work on D21K601, RHR Room A Area Radiation Monitor, and the ARM is ready for Operations retest.

. Initiating Cue(s):

The SRO with the Command Function has directed you to perform EPI 04 03-D21-1 Attachment I for D21K601 as a retest.

Use the retest package provided.

Another operator is assigned to manage any associated alarms on H13

-P680 Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 4 of 21 Manual Start of SSW A Notes 1. All controls and indications for this task are on backpanel 1H13

-P844. Task Overview This task is to perform the Monthly Area Radiation Monitors Functional Test for RHR Room A ARM.

The evaluator will role play as the P680 operator responding to the expected AREA RAD PANEL P844 alarm (P680

-4A1-E6) that occurs as a result of this testing. That alarm is overridden OFF in this JPM to prevent interrupting concurrent JPMs within the control room main panel area.

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 5 of 21 Critical tasks are underlined, italicized, and denoted by an (*)

Sequence for the following steps is not critical unless otherwise denoted.

Step 1: EPI 04-1-03-D21-1, Step 7.1.1 Signs Test Performer on the data package cover sheet of 04 03-D21-1 Attachment I.

Standard: Signs, dates, and times Test Performer block on the Data Package Cover Sheet.

Cue: None Notes: SAT / UNSAT Step 2: EPI 04-1-03-D21-1 Attachment I, Step 7.2.2a

  • SELECT OFF on Function switch

. Standard: Selects OFF on Function switch of D21K601 by rotating the switch counter

-clockwise to OFF, then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 6 of 21 Step 3: EPI 04-1-03-D21-1 Attachment I, Step 7.2.3a Observes AREA RADIATION MONITORING SYSTEM FAILURE annunciator on 1H13

-P844. Standard: Observes annunciator AREA RADIATION MONITORING SYSTEM FAILURE alarms (P844-2A-A5), then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT Step 4: EPI 04-1-03-D21-1 Attachment I, Step 7.2.4a Observes AREA RAD PNL P844 TROUBLE annunciates on 1H13-P680. Standard: Requests the ACRO to verify AREA RAD PNL P844 TROUBLE annunciates on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is in alarm. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 7 of 21 Step 5: EPI 04-1-03-D21-1 Attachment I, Step 7.2.5a Checks Fail Safe green light extinguished.

Standard: Observes the green FAIL SAFE indicator/CHECK SOURCE pushbutton on the monitor face of D21K601 backlight is off, then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT Step 6: EPI 04-1-03-D21-1 Attachment I, Step 7.2.6a

  • SELECT OPERATE on Function switch Standard: Selects OPERATE on Function switch of D21K601 by rotating the switch clockwise to OPERATE, then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 8 of 21 Step 7: EPI 04-1-03-D21-1 Attachment I, Step 7.2.7a CHECK FAIL SAFE green light illumintated.

Standard: Verifies FAIL SAFE green light is lit.

Cue: None. Notes: SAT / UNSAT Step 8: EPI 04-1-03-D21-1 Attachment I, Step 7.2.8a Resets AREA RAD PNL P844 TROUBLE annunciator on P680.

Standard: Requests the ACRO to reset AREA RAD PNL P844 TROUBLE annunciator on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is reset. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 9 of 21 Step 9: EPI 04-1-03-D21-1 Attachment I, Step 7.2.9a
  • Displays recorder point #1 on recorder D21R600.

Standard: Displays recorder point #1 on recorder D21R600 on P844 by depressing the up or down arrow keys until PT#1 is displayed, or by depressing 01 on the number keypad and depressing enter, then initials the step on the EPI Attachment I

. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 10 of 21 Step 10: EPI 04-1-03-D21-1 Attachment I, Step 7.2.10a
  • Depresses and holds the yellow TEST ALARM pushbutton

. Standard: Depresses and holds the yellow TEST ALARM pushbutton on the bottom of the monitor face

. Cue: None Notes: SAT / UNSAT Step 11: EPI 04-1-03-D21-1 Attachment I, Step 7.2.11a OBSERVE meter indication AND point #1 on Recorder R600 travel upscale.

Standard: Verifies meter indication on D21K601 and point # 1 on Recorder D21R600 on P844 travel fully upscale.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 11 of 21 Step 12: EPI 04-1-03-D21-1 Attachment I, Step 7.2.12a OBSERVE respective "RADIATION HIGH" annunciator on 1H13

-P844. Standard: Verifies annunciator EMERGENCY CORE COOLING ROOM RADIATION HIGH alarms (P844

-A-D4).. Cue: None Notes: SAT / UNSAT Step 1 3: EPI 04-1-03-D21-1 Attachment I, Step 7.2.13a Observes AREA RAD PNL P844 TROUBLE annunciates on 1H13-P680. Standard: Requests the ACRO to verify AREA RAD PNL P844 TROUBLE annunciates on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is in alarm. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 12 of 21 Step 8: EPI 04-1-03-D21-1 Attachment I, Step 7.2.14a
  • Releases the yellow TEST ALARM pushbutton Standard: Releases the yellow TEST ALARM pushbutton on the bottom of the monitor face, then initials the associated steps on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT Step 8: EPI 04-1-03-D21-1 Attachment I, Step 7.2.15a Checks red High Alarm light illuminated.

Standard: Observes the red HIGH ALARM indicator/RESET pushbutton on the monitor face of D21K601 backlight is on, then initials the step on the EPI Attachment I. Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is in alarm. Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 13 of 21 Step 16: EPI 04-1-03-D21-1 Attachment I, Step 7.2.16a DEPRESS AND RELEASE red HIGH ALARM/RESET pushbutton

. Standard: Depresses and releases the red HIGH ALARM indicator/RESET pushbutton on the bottom of the monitor face, then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT Step 17: EPI 04-1-03-D21-1 Attachment I, Step 7.2.17a Checks red High Alarm light extinguished.

Standard: Observes the red HIGH ALARM indicator/RESET pushbutton on the monitor face of D21K601 backlight is off, then initials the step on the EPI Attachment I. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 14 of 21 Step 18: EPI 04-1-03-D21-1 Attachment I, Step 7.2.18a Resets AREA RAD PNL P844 TROUBLE annunciator on 1H13-P680. Standard: Requests the ACRO to reset AREA RAD PNL P844 TROUBLE annunciator on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is reset. Notes: SAT / UNSAT Step 19: EPI 04-1-03-D21-1 Attachment I, Step 7.2.19a Resets RADIATION HIGH annunciator on 1H13-P844. Standard: Resets annunciator RADIATION HIGH (P844

-A-D4), then initials the step on the EPI Attachment I.

Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 15 of 21 Step 20: EPI 04-1-03-D21-1 Attachment I, Step 7.2.20a
  • Depresses and holds green FAIL SAFE indicator/CHECK SOURCE pushbutton AND OBSERVE that meter indication AND point #1 on Multipoint Recorder R600 Both indicate an increase in count rate THEN RELEASE green FAIL SAFE/CHECK SOURCE pushbutton.

Standard: Depresses and holds the green FAIL SAFE indicator/CHECK SOURCE pushbutton on the monitor face of D21K601 and verifies that meter indication and point # 1 on Multipoint Recorder R600 both indicate an increase in count rate, then releases the green FAIL SAFE indicator/CHECK SOURCE pushbutton and initials the step on the EPI Attachment I.

Cue: None Notes: This step will cause a high alarm if the check source pushbutton is held long enough to produce 100 mr/hr, which actually takes only a few seconds.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 16 of 21 Step 21: EPI 04-1-03-D21-1 Attachment I, Step 7.2.21a
  • PLACE AND HOLD Funcion switch to ALARM. . Standard: Rotates the function switch clockwise to ALARM and holds it Cue: None Notes: The SOI step implies the switch will spring return to OPERATE, but depending on the particular ARM, the switch may have to be rotated manually back to OPERATE, as is true for this ARM. SAT / UNSAT Step 22: EPI 04-1-03-D21-1 Attachment I, Step 7.2.22a
  • VERIFY meter indication travels to the setpoint of 100mR/hr

. Indicated value Should be within +/- 20% of the specified value.

. Standard: Verifies that meter indication travels to the alarm setpoint of 100 mr/hr (+/

- 20 mr/hr) and initials the step on the EPI Attachment I.

Cue: None Notes: The SOI step implies the switch will spring return to OPERATE, but depending on the particular ARM, the switch may have to be rotated manually back to OPERATE, as is true for this ARM.

SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 17 of 21 Step 23: EPI 04-1-03-D21-1 Attachment I, step 7.2.23a
  • RELEASE Function switch AND OBSERVE indication decreases to NORMAL.

Standard: Releases Function switch and verifies indication decreases back to normal

. Cue: None Notes: SAT / UNSAT Step 24: EPI 04-1-03-D21-1 Attachment I, Step 7.2.24a DEPRESS red HIGH ALARM/RESET pushbutton to clear any spurious alarm.

Standard: Depresses and releases the red HIGH ALARM indicator/RESET pushbutton on the bottom of the monitor face

. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 18 of 21 Step 25: EPI 04-1-03-D21-1 Attachment I, Step 7.2.25a Resets AREA RAD PNL P844 TROUBLE annunciator on P680.

Standard: Requests the ACRO to reset AREA RAD PNL P844 TROUBLE annunciator on P680.

Cue: As ACRO, tell the candidate P680 annunciator AREA RAD PNL P844 TROUBLE is reset. Notes: SAT / UNSAT Step 8: EPI 04-1-03-D21-1 Attachment I Completes the data package cover sheet of 04 03-D21-1 Attachment I.

Standard: Signs and dates Test Performed by blocks and checks Acceptable or Acceptable with Comments on the Data Package Cover Sheet. Cue: None Notes: SAT / UNSAT

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 19 of 21 Task Standard(s)
ARM D21K601 functional test is complete

. SAT / UNSAT Remember to record stop time

Date of Examination: 12/7/201 5 Operating Test Number

LOT 201 5 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015S9 Revision 0 9/14/2015 Page 20 of 21 Applicant:

__________________________________________________________________

JPM Number: GJPM-OPS-2015CR 9 JPM Title: Perform Area Radiation Monitor Functional Test Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________________________________________

Give this page to the student Initial Condition(s):

The plant is at rated power.

I&C has completed repair work on D21K601, RHR Room A Area Radiation Monitor, and the ARM is ready for Operations retest.

. Initiating Cue(s):

The SRO with the Command Function has directed you to perform EPI 04 03-D21-1 Attachment I for D21K601 as a retest.

Use the retest package provided.

Another operator is assigned to manage any associated alarms on H13

-P680 Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-6 JPM Title: RESET UNDERVOLTAGE LOCKOUTS ON BOP BUSES Facility Number:

__ GJPM-OPS-R2108____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 30 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By:

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 2 of 11 Reset Undervoltage Lockouts on BOP Buses Time Critical Alternate Path Validation Time:

30 Min Setting: Plant (Inside CAA)

Type: NLO Task: NOB-R21-008 K&A: 2.1.30: 4.4/4.0; 262001 A2.11: 3.2/3.6 295003 AA1.01: 3.7/3.8 Safety Function:

Electrical (6)

Performance

Actual Reference(s):

ONEP 05-1-02-I-4 section 3.3.12e Handout(s):

ONEP 05-1-02-I-4 section 3.3.12e

  1. Manipulations:

6 # Critical Steps:

6 Group #: 1 Simulator Setup/Required Plant Conditions

Area is accessible Safety Concerns
Do NOT operate plant equipment.

Task Standard

Bus 13AD and 12HE bus undervoltage lockout devices are reset.

.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 3 of 11 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

BOP Transformer 11B locked out on Sudden Pressure and deenergized 34.5 KV Bus 12R.

BOP Buses 12HE and 13AD lost power.

Control room operators have reenergized bus 12HE and bus 13AD from alternate feeders powered by BOP Transformers 12A and 12B per Loss of AC Power ONEP.

Major loads powered from these buses cannot be restored until bus under voltage lockout devices are reset at the busses.

Initiating Cue(s):

You have been directed to reset all bus under voltage lockout device s on bus 12HE and bus 13AD.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 4 of 11 Reset Undervoltage Lockouts on BOP Buses Notes 1. Bus 13AD and 12HE may be restored in any order. Bus order is not critical.
2. Bus undervoltage lockout devices may be reset in any order. BUV device order is no t critical. 3. The operator must be able to recognize the difference between a BUV and an overcurrent lockout device and should not attempt to reset an overcurrent lockout device for this task.

Task Overview:

This task is to reset bus undervoltage lockout devices on affected bus auxiliary panels after bus reenergization. This task is performed to allow large electrical loads to be restarted on affected buses. GGNS plant scram on February 11, 2005 required this task to be performed.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 5 of 11 Reset Undervoltage Lockouts on BOP Buses Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: Locate 4.16KV bus 13AD.

Standard: Locates bus 13AD in the electrical switchgear room in area 4 elevation 133' of the turbine building.

Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 6 of 11 Step 2:
  • Reset bus undervoltage lockout devices on bus auxiliary cubicle

.

  • Relay 186-BV1 reset.
  • Relay 186-BV2 reset.
  • Relay 186-BV3 reset.
  • Relay 186-BV4 reset.

Standard: Rotates handle of bus undervoltage device clockwise until it clicks vertical.

Cue: As each BUV device handle is rotated, cue the operator that the handle clicks vertical. Notes: BUV Relays have Red and White labels under them.

SAT / UNSAT Step 3: Observes white continuity light is on.

Standard: Operator observes white continuity light is on.

Cue: White light is lit.

Notes: White light comes on when the last BUV device is reset.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 7 of 11 Step 4: Locate 4.16KV bus 12HE.

Standard: Locates bus 12HE in the electrical switchgear room in area 4 elevation 113' of the turbine building. Cue: None. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 8 of 11 Step 5:
  • Reset bus undervoltage lockout devices on bus auxiliary cubicle

.

  • Relay 286-BV1 reset.
  • Relay 286-BV2 reset.

Standard: Rotates handle of bus undervoltage device clockwise until it clicks vertical.

Cue: As each BUV device handle is rotated, cue the operator that the handle clicks vertical. Notes: BUV Relays have Red and White labels under them.

SAT / UNSAT Step 6: Observes white continuity light is on.

Standard: Operator observes white continuity light is on.

Cue: White light is lit.

Notes: White light comes on when the last BUV device is reset.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 9 of 11 Task Standard(s)
Bus 13AD and 12HE bus undervoltage lockout devices are reset.

SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-6 Revision 0 GJPM-OPS-2015PS-6 Page 10 of 11 Applicant: _____________________________________________________________

JPM Number: GJPM-OPS-2015 PS-6 JPM Title: Reset Undervoltage Lockouts on BOP Buses Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ________________

____________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

BOP Transformer 11B locked out on Sudden Pressure and deenergized 34.5 KV Bus 12R.

BOP Buses 12HE and 13AD lost power.

Control room operators have reenergized bus 12HE and bus 13AD from alternate feeders powered by BOP Transformers 12A and 12B per Loss of AC Power ONEP.

Major loads powered from these buses cannot be restored until bus under voltage lockout devices are reset at the busses.

Initiating Cue(s):

You have been directed to reset all bus under voltage lockout device s on bus 12HE and bus 13AD.

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-7 JPM Title: PERFORM ATTACHMENT III OF SHUTDOWN FROM REMOTE SHUTDOWN PANEL ONEP Facility Number:

__ N/A____________

(If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time

2 0 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

Ronnie Walters 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By: Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 2 of 11 Perform Attachment III of Shutdown from Remote Shutdown Panels ONEP Time Critical Alternate Path Validation Time:

30 Min Setting: Plant (Outside CAA

) Type: NLO Task: NOB-ADMIN-024; CRO-ADMIN-008; CRO-C61-001 K&A: 295016 AA1.07: 4.2/4.3; AK2.02: 4.0/4.1 2.1.30: 4.4/4.0 Safety Function

Instrumentation (7)

Performance

Simulate Reference(s)
05-1-02-II-1, Attachment III Handout(s)
05-1-0 2-II-1 # Manipulations
13 # Critical Steps
10 Group #: 1 Simulator Setup/Required Plant Conditions
Control building

- Division 1 switchgear room is accessible Safety Concerns

Do NOT operate plant equipment.

Task Standard

Separate the Division 1 equipment from the Main Control Room for safe shutdown.

.

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 3 of 11 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

The plant has been scrammed.

A fire exists in the Main Control Room.

The Control Room Supervisor has evacuated the Main Control Room and established control of the plant at the Remote Shutdown Panels.

Initiating Cue(s):

You have been directed to complete the handswitch lineup per Attachment III of 05 02-II-1. This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 4 of 11 Perform Attachment III of Shutdown from Remote Shutdown Panels ONEP Notes: 1. Panels may be operated in any order. The sequencing is NOT CRITICAL.
2. This JPM is considered a Low Power JPM due to the requirement to scram the plant prior to manning the Remote Shutdown Panels.
3. This JPM is an Abnormal Operating Procedure outside of the CAA.

Task Overview:

This task is to align the Alternate Shutdown Panels in the Division 1 switchgear room of the Control Building per 05 02-II-1 Attachment III separating the Main Control Room from the Division I equipment for safe shutdown in the event of a fire or security event in the Main Control Room.

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 5 of 11 Perform Attachment III of Shutdown from Remote Shutdown Panels ONEP Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: 0 5-1-02-II-1, Attachment 3, 3.2.5 a a.

  • OBTAIN key from RSD room locker AND PLACE Transfer Switch for Lockout Transfer Relay C61-HSS-M150 at 1H22

-P152 (Area 25A, El. 111') to ON position

. Standard: Operator obtains the key to the locked switch cover for C61

-HSS-M150 key from the RSD locker.

Cue: You have the key

. C61-HSS-M150 is in the ON position.

Notes: The key is located in the locker in the Division 2 Remote Shutdown Room. Once the candidate identifies where the key is located this is sufficient.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 6 of 11 Step 2: 0 5-1-02-II-1, Attachment 3, 3.2.5 a b OBSERVE that Lockout Transfer Relays R1 through R36 trip to LOCKOUT position.

Standard: Observes Lockout Relays R1 through R36 trip to the LOCKOUT (TRIP) position. Cue: Lockout Relays R1 through R36 are in the LOCKOUT (TRIP) position. Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 7 of 11 Step 3: 0 5-1-02-II-1, Attachment 3, 3.2.5 a c
  • PLACE the following handswitches at 1H22

-P299 (Area 25A, Elev 111') to LOCAL position:

-1511) PORT GIBSON

-1501/ESF XFMR NO. 11 152

-1514)SWYD

-1508)

-BTRY RM VENT SYS)

Standard: Places the above handswitches to LOCAL.

Cue: Handswitches are in LOCAL.

Notes: DO NOT ALLOW PIN TO BE REMOVED.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 8 of 11 Step 4: 0 5-1-02-II-1, Attachment 3, 3.2.5 ad PLACE OR VERIFY each component on panel 1H22

-P299 is in the desired position.

Component DESIRED POSITION

-HSS-M565 Closed 152-1513, 1C61

-HSS-M566 Closed 152-1512, 1C61

-HSS-M567 Closed 152-1504, 1C61

-HSS-M568 Closed 480V LCC 15BA5, 1C61

-HSS-M569 Closed Q1Y47-F002A-A As Required (Open IF Y47-C001A running)

Q1Y47-F003A-A As Required (Close on high SSW A Pumphouse temp)

Q1Y47-F001A-A As Required (Open IF Y47-C001A running)

Q1Z77-F036A-A As Required (Opens on high temperature)

Q1Z77-C001A-A Running (Red Light ON)

Standard: Verifies and records indications and compares to desired position.

Cue: As indicated.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 9 of 11 Step 5: 0 5-1-02-II-1, Attachment 3, 3.2.5ae NOTIFY RSD SRO of any component NOT in desired position on panel 1H22

-P299. Standard: Notifies RSD SRO all components are in desired position on panel 1H22

-P299 and Attachment 3 is complete.

Cue: None Notes: SAT / UNSAT Task Standard(s): Separate the Division 1 equipment from the Main Control Room for safe shutdown SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 20 15 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-7 Revision 0 GJPM-OPS-2015PS-7 Page 10 of 11 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015 PS-7 JPM Title: PERFORM ATTACHMENT III OF SHUTDOWN FROM REMOTE SHUTDOWN PANEL ONEP Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

The plant has been scrammed.

A fire exists in the Main Control Room.

The Control Room Supervisor has evacuated the Main Control Room and established control of the plant at the Remote Shutdown Panels.

Initiating Cue(s):

You have been directed to complete the handswitch lineup per Attachment III of 05 02-II-1. This task is not time critical.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 1 of 11 GGNS 2015 NRC Operating Test Job Performance Measure JPM Number: GJPM-OPS-2015 PS-8 JPM Title: MANUALLY INITIATE FIRE PROTECTION TO THE 'B' RPS MOTOR GENERATOR ROOM Facility Number:

__ GJPM-OPS-P6405A (If Bank or Modified from Bank

) JPM Attributes:

New Modified Direct from bank Time Critical Alternate Path Validation Time: 30 min Prepared By:

Steve Reeves 6/24/2015 Exam Developer Date Ops Review:

Roy Purdy 7/8/2015 1 st Validation by Ops Rep or Ops Validation Crew Date Validated By:

John Copus 9/9/2015 2 nd Validation by Ops Validation Crew Date Approved By

Gabe Kimich 9/28/2015 Project Lead or Exam Team Lead Date Date of Examination: 12/07/2015 Operating Test Number
LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 2 of 11 MANUALLY INITIATE FIRE PROTECTION TO THE 'B' RPS MOTOR GENERATOR ROOM Time Critical Alternate Path Validation Time:

30 Min Setting: Plant (Outside CAA

) Type: NLO Task: AON-P64-001; NOB-R20-002 K&A: 2.1.30: 4.4/4.0 2.4.26: 3.19/3.6 Safety Function

Plant Systems (8)

Performance

Simulate Reference(s)
04-1-01-P64-3 Handout(s)
04-1-01-P64-3 Section 5.2
  1. Manipulations
6 # Critical Steps
6 Group #: 2 Simulator Setup/Required Plant Conditions
Area is accessible Safety Concerns
Do NOT operate plant equipment.

DO NOT ALLOW CANDIDATE TO OPEN THE PULL STATION.

Task Standard

The CO2 System for 'B' RPS Motor Generator room has been actuated. .

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 3 of 11 Name: ___________________________

Time Start: _______

Time Stop: _______

Initial Condition(s):

A fire has been detected in the 'B' RPS Motor Generator room. Fire Brigade has been dispatched Initiating Cue(s):

You have arrived at the scene as a member of the Fire Brigade and you hear no CO 2 flow going to the room.

The Fire Brigade Leader has directed you to initiate CO 2 flow.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 4 of 11 Manually Initiate Fire Protection to 'B' RPS Motor Generator Room Notes 1. The operator may feel the need to don Fire Turnout Gear. Cue the operator to simulate this action.

Task Overview:

This task is to manually initiate the Fire Suppression System for the 'B' RPS Motor Generator room locally. This is done to extinguish the fire.

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 5 of 11 Manually Initiate Fire Protection to 'B' RPS Motor Generator Room Critical tasks are underlined, italicized, and denoted by an (*)

NOTE: The sequence of the following steps is critical unless otherwise noted.

Step 1: 04-1-01-P64-3, 5.2.2 a. (1)

  • PULL the PULL handle on the pushbutton station to break the glass

. Standard: Operator breaks the glass.

Cue: Glass is broken.

Notes: DO NOT ALLOW CANDIDATE TO OPERATE THE PULL HANDLE.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 6 of 11 Step 2: 04-1-01-P64-3, 5.2.2 a. (1)
  • Momentarily DEPRESS pushbutton to INITIATE an automatic timed released of CO

². Standard: Operator depresses the pushbutton.

Cue: You hear no flow of CO

2. Notes: SAT / UNSAT Step 3: 04-1-01-P64-3, 5.2.2 b. (1)(a)
  • MANUALLY FLOOD the CO² Header as follows: REMOVE the pin from the Master Valve Manual SVF373 Release Lever located near the 10 ton CO

² Storage Unit Standard: Operator removes the pin

. Cue: Pin is removed.

Notes: DO NOT ALLOW PIN TO BE REMOVED.

SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 7 of 11 Step 4: 04-1-01-P64-3, 5.2.2 b. (1)(b)
  • PLACE the Manual Release Lever to the OPEN position. Standard: Rotates the lever to the open position.

Cue: You hear CO2 flow.

Notes: SAT / UNSAT

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 8 of 11 Step 5: 04-1-01-P64-3, 5.2.2 b. (2)
  • BREAK glass with the small handle provided at the station Standard: Operator breaks the glass.

Cue: Glass is broken.

Notes: DO NOT ALLOW CANDIDATE TO OPERATE THE PULL HANDLE.

SAT / UNSAT Step 6: 04-1-01-P64-3, 5.2.2 b. (2)

  • ROTATE the arm inside to the OPEN position to release CO

² for the amount of time specified on each station.

Standard: Operator rotates the arm to the OPEN position.

Cue: Flow of C02 to the room has started.

Notes: SAT / UN SAT Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 9 of 11 Task Standard(s)
The CO2 System for 'B' RPS Motor Generator room has been actuated SAT / UNSAT Remember to record stop time

Date of Examination: 12/07/2015 Operating Test Number

LOT 2015 Facility: Grand Gulf Nuclear Station JPM Number: GJPM-OPS-2015PS-8 Revision 0 GJPM-OPS-2015PS-8 Page 10 of 11 Applicant:

_____________________________________________________________

JPM Number: GJPM-OPS-2015 PS-8 JPM Title: Manually Initiate Fire Protection to 'B' RPS Motor Generator Room Follow-Up Questions & Answers

Comments: Performance Rating
SATISFACTORY UNSATISFACTORY Examiner's Name: ____________________________________________________

Examiner's Signature:

____________________

_______________________________

Give this page to the student Initial Condition(s):

A fire has been detected in the 'B' RPS Motor Generator Room. Fire Brigade has been dispatched Initiating Cue(s):

You have arrived at the scene as a member of the Fire Brigade and you hear no CO 2 flow going to the room.

The Fire Brigade Leader has directed you to initiate CO 2 flow.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 1 of 7 Revision 0 9/21/2015 Facility:

Grand Gulf Nuclear Station Scenario No.:

1 Op-Test No.: NRC LOT 201 5 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________

____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Rotate Power to bus 17AC from ESF 12 to ESF 21

. 2. Respond to a loss 17AC with a Diesel Generator failure

. 3. Loss of EPA breaker on 'B' RPS.

4. Trip of the 'B' RPS Alternate Power Supply with Inadvertent SCRAM of 4 Control Rods 5. Respond to low Main Turbine Lube Oil Pressure and Main Turbine Trip and Reactor Scram 6. Take actions for a n ATWS. 7. RCIC Steam line break with failure to auto isolate with manual isolation available.
8. Respond to a Feedwater line B rupture inside Drywell with ability to isolate and restore feedwater Initial Conditions:

Operating at 9 5% power. Inoperable Equipment:

None Turnover:

The plant is at 95% following a sequence exchange. SSW A is operating in preparation for weekly chemical addition. Planned activities for this shift are:

Rotate Power to 17AC from ESF 12 to ESF 21. There is no out of service equipment and EOOS is GREEN. It is a division 1 work week.

Scenario Notes:

This scenario is a NEW Scenario.

Validation Time: 60 minutes

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 2 of 7 Revision 0 9/21/2015 Event No. Malf. No. Event Type f Event Description 1 N (BOP) Rotate Power to 17AC from ESF 12 to ESF 21.(SOI 04-1-01-R21-17) 2 DI_1E22M716 n41140c C (BOP) A (CREW) TS (CRS) Respond to a loss of 17AC with a failure of Division 3 Diesel Generator (Loss of AC Power ONEP, 05 02-I-4; Tech Spec 3.8.1 condition B

) 3 c71077b C (ATC) C (BOP) A (CREW) Loss of EPA breaker on RPS 'B' (Loss of One or Both RPS Buses, 05 02-III-2) 4 LO_1C71M607B DI_1C71M607B ZO25025_40_33 ZO25025_40

-25 ZO25025_32

-37 ZO25025_32

-21 C (ATC) R (ATC) A (CREW) TS (CRS) Trip of the 'B' RPS Alternate Power Supply with Inadvertent SCRAM of 4 Control Rods (Control Rod/Drive Malfunctions ONEP, 05 02-IV-1; Reduction in Recirculation Flow Rate ONEP, 05 02-III-3, Tech Spec TR 3.1.5) 5 tc093 AO_1N34R600 DI_1N34M661 DI_1N34M662 p680_10a_c_1 M/A (CREW) Respond to Low Main Turbine Lube Oil Pressure (ARI 1H13-P680-10A-C2) Respond to Reactor Scram and/or Main Turbine Trip (Reactor Scram and Turbine Generator Trip ONEPS, EP

-2) 6 c11164 M (CREW) ATWS (EP-2A) 7 e51050 Att. 3 C (BOP) RCIC steam line break with failure to auto isolate, manual isolation available. (EN

-OP-120, 02-S-01-43, EP-4) 8 fw171b C (ATC) Feedwater line B rupture inside Drywell with ability to isolate and restore feedwater (EP

-3) f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

  • Repeated task from last 2 NRC exams.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 3 of 7 Revision 0 9/21/2015 Quantitative Attributes Table Normal Events 1 E OP Contingency Procedures Used 1 Total Malfunctions 7 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 Abnormal Events 4 Critical Tasks 4 Major Transients 2 Instrument/Component Failures 5 E O Ps Used (Requiring measurable action) 2 Reactivity Manipulations 1

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 4 of 7 Revision 0 9/21/2015 SCENARIO ACTIVITIES:

Rotate power on bus 17AC from transformer ESF 12 to ESF 21

A. After turnover contact CRS to perform power swap for Bus 17AC. (Event 1) B. Using 04-1-01-R21-17, SOI for 17AC bus, the BOP will rotate power from ESF Transformer 12 to normal source of ESF 21.

Loss of Bus 17AC with a Division 3 Diesel Generator failure:

A. 30 seconds after power has been swapped on bus 17AC, incoming feeder 152

-1705 will trip causing a loss of 17AC. Div 3 D/G will fail to start. (Event 2) B. The crew will take the actions per Loss of AC Power ONEP by energizing the 17AC bus from an alternate feeder

. C. If sent to investigate 152-1705, as Electrical Maintenance wait 3 minutes then report problem is unknown and a work order is required.

D. The CRS will determine that TS 3.8.1 Condition B 4 applies and require surveillance 06-OP-1R21-W-0001 Attachment II.

Loss of EPA Breaker on 'B' RPS A. When the crew has addressed all required Tech Specs and/or at the direction of the lead evaluator, trigger Event 3 to cause EPA breaker C71-S003 D to trip. (This is different from previous exams due to the failure of Electrical Protection Assemblies the RPS M/G will continue to run.)

B. The ATC will recognize and report a Division 2 half scram and determine a loss of 'B' RPS. C. The BOP will respond to the back panel area and determine a loss of power to the 'B' RPS. D. If sent to investigate loss of RPS 'B', wait 3 minutes and report C71-S003D has tripped on undervoltage

. E. CRS will enter the Loss of One or Both RPS Buses ONEP to transfer power to the alternate source

. F. The BOP will transfer 'B' RPS power to alternate sourc e G. The ATC will reset half scram

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 5 of 7 Revision 0 9/21/2015 Trip of the 'B' RPS Alternate Power Supply with Inadvertent SCRAM of 4 Control Rods A. When the crew has addressed all required Tech Specs and the subsequent actions of the Loss of One or Both RPS Buses ONEP and/or at the direction of the lead evaluator, trigger Event 4 to cause a trip 'B' RPS Alternate Power Supply

. B. The ATC will recognize and report a Division 2 half scram and determine a loss of 'B' RPS, also recognize and report 4 Control Rods have SCRAMMED.

C. The ATC will reduce core flow to 70 Mlbm/hr per 05 02-IV-1, Control Rod/Drive Malfunctions section 2.4.

D. The BOP will respond to the back panel area and determine a loss of power to the

'B' RPS. E. The CRS will enter 05-1-02-IV-1, Control Rod/Drive Malfunctions ONEP and 05-1-02-III-3, Reduction in Recirc Flowrate ONEP and Tech Specs TR 3.1.5 Condition A

. F. The ATC will plot current position on the Power to Flow map.

The BOP will verify the plot. G. If sent to investigate loss of RPS 'B', wait 3 minutes and report both EPA breakers for Alternate source, C71-S003H and S003F are tripped on undervoltage.

H. If sent to investigate alternate supply for RPS 'B' at 52

-164227, report breaker is tripped free.

Low Main Turbine Lube Oil Pressure A. When Reactor parameters have stabilized and/or at the direction of the lead evaluator, trigger Event 5 to cause a reduction in Main Turbine Lube Oil Pressure

. B. The crew will recognize a reduction in Main Turbine Lube Oil pressure by alarms and indication.

Main Turbine Trip / Reactor Scram A. Approximately 1 minute after Main Turbine Low Lube Oil pressure alarm the Main Turbine will trip

. B. The crew will recognize a Main Turbine Trip C. The crew will take actions of the Main Turbine Trip and Reactor Scram ONEPs.

D. The CRS will enter EP

-2 Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 6 of 7 Revision 0 9/21/2015 ATWS, 15% (Will maintain >5% power)

A. The crew will recognize control rods will fail to fully insert due to hydraulic block (Event 6). (This is different than other previous used ATWS malfunctions due to severity is at 15%)

B. The CRS will enter EP

-2A. Feedwater piping 'B' will rupture inside the drywell

A. Five minutes after the scram signal, Feedwater Line B will rupture in the Drywell (Event 7). (This is different than other previous used malfunctions due to the leak can be isolated and Feedwater can be restored.)

B. ATC secures all condensate and feedwater. The ATC has the ability to close B21

-F065B to isolate the leak and restore Feedwater and Condensate to feed the reactor. RCIC steam line break with failure to auto isolate A. Eight minutes after the scram signal, RCIC Steam Line will break (Event 8). (This is different than other previous used malfunctions due to the leak can be manually isolated and steam leak stopped.)

B. The BOP will recognize and report indications of a RCIC steam line break and entry into EP-4. C. The BOP will recognize failure to auto isolate D. The BOP will manually isolate the RCIC system by closing E51

-F063 and F064.

E. The CRS will enter EP

-4. Termination:

A. Once rod movement has occurred and reactor water level is being controlled in band or as directed by Lead Evaluator:

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 1 Page 7 of 7 Revision 0 9/21/2015 Critical Task Number Description Basis 1 Per step L

-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches -70" wide range Water level must be lowered to reduce subcooling and prevent instabilities.

2 Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.

If not performed properly would result is direct adverse consequences or significant degradation in the mitigative capability of the plant. Correct performance prevents degradation of any barrier to fission product release (i.e. a n emergency depressurization will be required) 3 Isolate all systems (RCIC) discharging outside the primary CTMT through a break, except systems needed for fire suppression or EP actions prior to any other area exceeding its Max safe value in table 10 of EP

-4 If a RCIC steam leak with failure to isolate occurs, then RCIC should be shutdown and isolated unless required to assure adequate core cooling.

This is to prevent an unmonitored release and loss of fission product barrier.

4 Following an ATWS, insert control rods by manual scram and/or normal rod insertion prior to exiting

EP-2A. Positive confirmation that the reactor will remain shutdown under all conditions is best obtained by verifying that all control rods are inserted to or beyond position

02. Position 02 is the "Maximum Subcritical Banked Withdrawal Position," defined to be the greatest banked rod position at which the reactor will remain shutdown under all conditions.

. (per 02-S-01-40, EP Technical Bases)

  • Critical Task (As defined in NUREG 1021 Appendix D)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 1 of 35 Revision 0 9/21/2015 Simulator Setup:

A. Initialization

1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
4. Set the Simulator to IC-101 and perform switch check (Using Quick Reset in Director).
5. Click on "Open" in the Schedule window and Open Schedule File "201 5 NRC Scenario 1.sch" (in the Schedule Directory)
6. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 2 of 35 Revision 0 9/21/2015 7. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)

8. Take the simulator out of freeze.
9. Log on to all simulator PDS and SPDS computers.
10. Verify or perform the following:

IC-101 APRM's are turned on (4,1,2,3)

Ensure the MOC rod movement sequence available at the P680.

Advance all chart recorders and ensure all pens inking properly.

Clear any graphs and trends off of SPDS.

Ensure SSW A is aligned properly per 04-1-03-P41-1, SSW A Chemical Addition Run

. Marked up copy of 03 01-2 Att. II to step 6.7.3 , Power Ascension From 60% to Full Power, is placed on CRS desk.

Marked up copy up to step 7.7 of 04 03-P41-1, SSW A Chemical Addition Run, is placed on CRS desk.

Ensure bus 17AC is aligned to transformer ESF 12.

Marked up copy up to step 4.3.2 b of 04 01-R21-17, ESF Bus 17AC.

11. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

12. Place the simulator in Freeze.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 3 of 35 Revision 0 9/21/2015 B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 4 of 35 Revision 0 9/21/2015 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 9 5% M OC EOOS GREEN Planned Evolutions this shift:

SSW A is operating per 04 03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.

Rotate power on electrical bus 17AC from transformer ESF 12 to ESF

21. C. Allow the crew to perform pre

-shift brief and review procedures for planned evolutions.

D. Bring the crew into the Simulator, place the simulator is in RUN.

E. Allow the crew to walk down panels.

F. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 5 of 35 Revision 0 9/21/2015 SCENARIO ACTIVITIES:

Start SBT report and any other required recording devices.

Emergency Classification:

Site Area Emergency on SS3.

Op-Test No: NRC LOT 201 5 Scenario No:

1 Event No:

1 Event

Description:

Rotate power on bus 17AC from transformer ESF 12 to ESF 21 TIME Position Applicant's Actions or Behavior CRS Directs BOP to swap power on 17AC bus per 04-1-01-R21-17, ESF Bus 17AC SOI from transformer ESF 12 to transformer ESF 21

. BOP Using ESF BUS 17AC SOI , 04-1-01-R21-1 7 , section 4.3.2, performs the following:

a. ENSURE XFMR ESF 21 energized up to Bus Feeder Breaker 152-1705 as follows:

(1) CHECK CLOSED J5206 FDR to XFMR ST

-21 (2) CHECK CLOSED 552-2105 Bus 21R FDR FRM XFMR ST-21 (3) CHECK indicator 2R25

-R603 34.5 kV voltage (4) CHECK CLOSED 552-2104 Bus 21R FDR to XFMR ESF 21 (5) CHECK CLOSED 152-2902 FDR FRM XFMR ESF 21

(6) CHECK ENERGIZED status light is On.

b. TURN ON the Sync switch for Breaker 152

-1705 BUS 17AC FDR FRM XFMR ESF 21.

c. CHECK that the sync scope comes up to 12 o'clock

+ 10°.

d. ATTEMPT to CLOSE 152-1705 Bus 17AC feeder from ESF 21.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 6 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

1 (cont.) Event

Description:

Rotate power on bus 17AC from transformer ESF 12 to ESF 21 (cont.) TIME Position Applicant's Actions or Behavior NOTE: Annunciator in the next step is P601

-16A-C1 e. IF 152-1705 Closes AND the original feed breaker Trips, THEN the bus is energized AND transfer is complete. WHEN the original feeder breaker trips, an annunciator for feeder tripping is received. This is reset by TAKING the original tripped breaker handswitch to the TRIP position AND releasing. SKIP Steps 4.3.2g through 4.3.2k.

f. PLACE Sync switch to OFF.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 7 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 201 5 Scenario No:

1 Event No:

2 Event

Description:

Loss of 17AC Power TIME Position Applicant's Actions or Behavior BOP Recognize loss of 17AC bus from the following annunciators:

P601-16A E1 - 4.16KV BUS 17AC INCM FDR 152

-1705 TRIP G1 - 480V MCC 17B01 UNDERVOLT H1 - HPCS SYS NOT READY FOR AUTO START A2 - HPCS DSL ENG TRIP F2 - HPCS SYS UNDERVOLT D3 - HPCS DSL ENG TROUBLE E4 - HPCS JKY PMP DISCH PRESS LO P870-5A: G1 - DG13 FUEL OIL SFER PMP CONT PWR FAIL E2 - SSW DIV 3 OOSVC F1 - DG13 TRIP UNIT TROUBLE F2 - SSW LOOP C LEAK HI Recognizes 17AC is de

-energized and Division 3 EDG has failed.

Performs immediate operator actions from Loss of AC Power ONEP

Energize affected bus through an alternate feeder breaker or its respective diesel generator.

Restores power to 17AC from an alternate source by closing one of the following feeder breakers:

152-1704, 17AC FDR FM ESF 12 152-1706, 17AC FDR FM ESF 11 Verifies BUS 17AC is energized by restoration of indicating lights on the HPCS system and the following annunciators are reset:

P601-16A-G1 - 480V MCC 17B01 UNDERVOLT P601-16A F2 - HPCS SYS UNDERVOLT P601-16A-E4 - HPCS JKY PMP DISCH PRESS LO P870-5A- G1 - DG13 FUEL OIL SFER PMP CONT PWR FAIL P870-5A- E2 - SSW DIV 3 OOSVC P870-5A- F1 - DG13 TRIP UNIT TROUBLE P870-5A- F2 - SSW LOOP C LEAK HI

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 8 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

2 (cont.) Event

Description:

Loss of 17AC Power (cont.)

TIME Position Applicant's Actions or Behavior BOP Refers to Alarm Response Instruction for the following alarms:

P601-16A E1 - 4.16KV BUS 17AC INCM FDR 152

-1705 TRIP G1 - 480V MCC 17B01 UNDERVOLT H1 - HPCS SYS NOT READY FOR AUTO START A2 - HPCS DSL ENG TRIP F2 - HPCS SYS UNDERVOLT D3 - HPCS DSL ENG TROUBLE E4 - HPCS JKY PMP DISCH PRESS LO CRS Enters Loss of AC Power ONEP and ensures Immediate operator actions are performed.

Dispatches plant operator to investigate failure of Div 3 Diesel Generator and 17AC bus. Booth If sent to 17AC bus, report as Electrical Maintenance and report 152

-1705 has an 86 device lockout trip. Any more work will require a work order.

If sent to Div 3 D/G report the following alarms on P118

-1A:: A1 - HIGH CRANKCASE PRESSURE A2 - FAIL TO START / RUN B3 - UNIT TRIP / LOCKOUT CRS Determines Tech Spec 3.8.1, AC Sources

- Operating, condition B applies One required DG inoperable for reasons other than Condition F.

72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time Require surveillance Plant AC and DC Electrical Power Distribution Weekly Lineup, 06-OP-1R21-W-0001 Attachment II and III to be performed per required action B.1 Perform SR 3.8.1.1 for OPERABLE required offsite circuit (s)

. Within one hour. Direct plant operator to place Division 3 Diesel in Maintenance Mode.

Booth If requested to place Div. 3 D/G in Maintenance Mode trigger event 25 and notify Control Room that Div. 3 D/G is in Maintenance.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 9 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

2 (cont.) Event

Description:

Loss of 17AC Power (cont.)

TIME Position Applicant's Actions or Behavior BOP Performs surveillance 06

-OP-1R21-W-0001 Attachment II.

(See attachment 1)

CRS Performs surveillance 06-OP-1R21-W-0001 Attachment III Page 6 of 6 only.

(See attachment 1)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 10 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

3 Event Description

Loss of Electric Power Assembly breaker on 'B' RPS Normal Feed
TIME Position Applicant's Actions or Behavior ATC Recognizes and reports half scram on Division 2 side from the following P680 annunicators 4A2-D4 - HCU TROUBLE 7A-A2 - RX SCRAM TRIP Division 2 SCRAM SOL VLV white indicating lights out.

CRS Enters 05-1-02-III-2, Loss of One or Both RPS Buses.

Directs BOP to transfer RPS 'B' to Alternate power source Directs plant operator to investigate.

Enters Tech Spec TR 3.1.5 for Control Rod Scram Accu. alarm until half scram is reset. May enter 3.3.8.2 Cond. A, POT ENTIAL BOP Per 05-1-02-III-2, Loss of One or Both RPS Buses:

On Panel 1H13

-P610 IDENTIFY RPS bus that is de

-energized by EITHER Generator "A" Normal Feed Available light out OR Generator "B" Normal Feed Available light out.

Responds to P610.

Recognizes and reports loss of power to 'B' RPS by observing Generator "B" Normal Feed Available light out.

BOP Per 05-1-02-III-2, Loss of One or Both RPS Buses:

Places MG SET B TRANSFER switch on 1H13

-P610 to available power source. (Alternate)

ATC Per 05-1-02-III-2, Loss of One or Both RPS Buses:

Reset half

-scram using HS

-M601 B and D on Panel 1H13

-P680 by placing switches momentarily to reset.

Verifies Division 2 SCRAM SOL VLV white indicating lights energize.

BOP Ensures all MSIV solenoid lights are energized and all MSIV pilot solenoids indicate amperage on panels 1H13

-P622 and P623.

(Candidate will have to go behind the P807 panel and ask the Booth operator the status of indication due to P622 and P623 are not simulated in the Simulator.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 11 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

3 (cont.) Event Description

Loss of Electric Power Assembly breaker on 'B' RPS Normal Feed (cont.)
TIME Position Applicant's Actions or Behavior Booth If ask to investigate 'B' RPS Motor Generator set, wait 3 minutes and report as plant operator that M/G set is still operating and only one EPA breaker is tripped, C71

-S003D. Breaker is tripped on undervoltage.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 12 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

4 Event Description

Loss of Alternate Power Supply to 'B' RPS with 4 Control Rods Scram.

TIME Position Applicant's Actions or Behavior Recognizes and reports half scram on Division 2 side from the following P680 annunicators 4A2-D4 - HCU TROUBLE 4A2-E4 - CONT ROD DRIFT 7A-A2 - RX SCRAM TRIP Division 2 SCRAM SOL VLV white indicating lights out.

Recognizes and reports 4 Control Rods have Scram from the following P680 Indications:

4A2-E4 - Cont Rod Drift alarm SCRAM VLV back lit pushbutton on section 6C of P680 ACKN HCU FAULT back lit pushbutton on section 6C of P680 HCU FAULT back lit pushbutton on section 6C of P680 ROD DRIFT back lit pushbutton on section 6C of P680 Depresses any or all of the following pushbuttons to determine which control rods have moved:

SCRAM VLV back lit pushbutton on section 6C of P680 HCU FAULT back lit pushbutton on section 6C of P680 ROD DRIFT back lit pushbutton on section 6C of P680 Recognizes and reports the following control rods have scrammed in due to SCRAM VLV light and position is at 00.

40-33 40-25 32-37 32-21 Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 13 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

4 (cont.) Event Description

Loss of Alternate Power Supply to 'B' RPS with 4 Control Rods Scram (cont.).

TIME Position Applicant's Actions or Behavior ATC Performs immediate operator actions of Control Rod/Drive Malfunction ONEP, 05-1-02-IV-1: If more than one but less than eight Control Rods have scrammed, then Reduce Core flow to 70 Mlbm/hr.

Using both Recirc LOOP A CONT and LOOP B CONT, B33

-K603A & B, move the slide switches to the full left (i.e. fast detent) and verify core flow is lowering using B33

-R613 indicator of TOT JP FLO.

Maintain loop flow mismatch in Recirc system within 5% (2230 gpm)

When 70 Mlbm/hr is reached release the slide switches B33

-K603A & B. Plot location on Power / Flow map Reports location of OPRM TRIP ENABLE region.

Performs THI watch with no concurrent duties.

CRS Enters Control Rod/Drive Malfunction ONEP, 05 02-IV-1 Directs ATC to perform immediate operator actions Notify STA/Reactor Engineering to perform a MON Calculation Enters Reduction in Recirc System Flow Rate ONEP, 05 02-III-3 Directs ATC to plot current position on the Power

- Flow map. Enters (re

-enter) Loss of One or Both RPS Buses ONEP, 05-1-02-III-2 BOP Verifies and reports ATC plot of power /flow to be in the OPRM TRIP ENABLE region Per 05-1-02-III-2, Loss of One or Both RPS Buses:

On Panel 1H13

-P610 IDENTIFY RPS bus that is de

-energized by EITHER Generator "A" Normal Feed Available light out OR Generator "B" Normal Feed Available light out.

Responds to P610.

Recognizes and reports loss of power to 'B' RPS by observing Generator "B" Alternate Feed Available light out.

CRS After reactor power and core flow is stable directs ATC to have concurrent duties. Dispatches operator to RPS 'B' to investigate loss of RPS power.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 14 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

4 (cont.) Event Description

Loss of Alternate Power Supply to 'B' RPS with 4 Control Rods Scram (cont.).

TIME Position Applicant's Actions or Behavior Booth If requested to investigate loss of RPS 'B' power, wait 3 minutes and report Alternate Power Supply EP A breakers are tripped on undervoltage.

CRS Dispatch operator to MCC 16B42 and investigate breaker number 27.

Booth If requested to investigate 52

-164227, wait 3 minutes and report breaker is in the trip free position.

ATC Monitor for Control Rod drifts, due to ROD DRIFT alarm and status light will be sealed in due to the 4 controls scram.

CRS Direct ATC to monitor for Control Rod Drift.

Dispatch plant operator to isolate affected Control Rods per 04 01-C11-1, Control Rod Drive SOI Enter Tech Spec TR 3.1.5

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 15 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

5 Event Description

Low Main Turbine Lube Oil Pressure TIME Position Applicant's Actions or Behavior ATC Recognizes and Reports Low Main Turbine Lube Oil Pressure:

P680-10A-C2, TURB LUBE OIL PRESS LO alarm Indicator N34

-R600, TURB BRG OIL PRESS, is lowering from normal (150 psig to 40 psig)

. Verifies Auto start of AC Auxiliary Oil Pumps A/B/C BOP Refers to ARI P680

-10A-C2, TURB LUBE OIL PRESS LO Per ARI Auto actions, Verifies Auto start of AC Auxiliary Oil Pumps A/B/C CRS Verifies actions per ARI

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 16 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

5 Event Description

Main Turbine Trip / Reactor Scram TIME Position Applicant's Actions or Behavior ATC Recognizes and reports Main Turbine lube oil pressure low by the following indications:

P680-10A-C 1, TURB LUBE OIL PRESS TRIP alarm Recognizes and reports Main Turbine Trip Recognizes and reports Reactor Scram. Performs immediate operator actions for Turbine and Generator Trip, 05 02-I-2, and Reactor Scram, 05 02-I-1, ONEPs Place the Mode SW to SHUTDOWN

. Provides a scram report:

o Reactor Mode SW in SHUTDOWN.

o All Rods are NOT Inserted (Hyd Block ATWS).

o Reactor power is initially above 5%.

o Reactor water level and trend.

Ensure Main Turbine Stop and Control Valves are CLOSED Ensure Both Generator Output Breakers are OPEN CRS Enters Turbine and Generator Trip, 05 02-I-2, and Reactor Scram, 05 02-I-1, ONEPs Enters EP-2 RPV Control Verifies Reactor Mode Switch is in SHUTDOWN Evacuates affected areas

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 17 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

5 (cont.) Event

Description:

Main Turbine Trip / Reactor Scram (cont.) TIME Position Applicant's Actions or Behavior ATC Assumes Reactor water level control duties.

Aligns Condensate/Feedwater to Startup level control valve per hard card, 04 01-N19-1. IF two RFPTs are in operation, THEN TRIP one by DEPRESSING TRIP pushbutton.

CLOSE the following valves:

a. N21-F009A, FW HTR 6A OUTL VLV
b. N21-F009B, FW HTR 6B OUTL VLV.

OPEN the following valves:

a. N21-F001, SU FCV OUTL ISOL VLV.
b. N21-F010A, HP FW HTR STRNG A SU OUTL VLV.
c. N21-F010B, HP FW HTR STRNG B SU OUTL VLV.

VERIFY CLOSED the following valves:

a. N21-F513, X WTR LVL SU CONTR Valve (per controller 1C34

-LK- R602) b. N21-F510, FW CU RECIRC VLV

c. N21-F040, FW SU BYP VLV IF one RFPT is in service, THEN SELECT OR ENSURE in SPEED AUTO with discharge pressure approximately 250 psid above reactor pressure.

OPEN / VERIFY OPEN RFP A(B) DISCH VLV N21

-F014A(B) for at least one pump.

ADJUST N21-F513, RX WTR LVL SU CONT valve, as necessary in MANUAL OR AUTO to maintain desired Reactor level. N21

-F040 AND/OR N21-F009A(B) May be OPEN/CLOSED as necessary to augment flow.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 18 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 201 5 Scenario No:

1 Event No:

6 Event

Description:

ATWS TIME Position Applicant's Actions or Behavior ATC Recognizes and reports Hydraulic Block ATWS (During Scram Report)

CRS Exits EP-2 and Enters EP-2A and directs the following actions:

Verify Reactor Recirc pumps transferred to LFMG Verify ARI/RPT initiation Inhibit ADS Override HPCS injection ATC Performs the following on P680 panel

Verify Reactor Recirc pumps transferred to LFMG o Verifies Recirc pump breaker alignment is for slow speed operation (CB 3, 4, & 5 open

, CB 1 and 2 closed) if not then depress TRANSFER TO LFMG pushbutton.

Verify ARI/RPT initiation o Verifies light indication on ARI/RPT shows initiation OTBD VALVES LOGIC INIT.

INBD VALVES LOGIC INIT.

RPT LOGIC INIT.

OR o A rm s and depresses ATWS ARI/RPT MAN TRIP CHANNEL 1 AND CHANNEL 2 pushbuttons.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 19 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Performs the following on P601 Panel

Inhibit ADS o Places ADS INHIBIT switches to the INHIBIT position Override HPCS injection by performing the following:

(1) While HOLDING HPCS SYS INJECTION VLV (E22

-F004) handswitch in "CLOSE" position, ARM AND DEPRESS the manual system initiation push

-button for HPCS. (2) AFTER indication of pump start, THEN TRIP the HPCS pum p. (3) ENSURE the HPCS pump AND E22-F004 valve override alarms are sealed in.

CRS Directs to verify the following:

Isolations o If level 2 isolation has occurred direct to restore Aux Building Diesel Generators

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 20 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Verifies the following dependent on plant conditions:

If level 2 isolation has occurred and directed by the CRS to restore the Aux Building then perform the following per 05-1-02-III-5, Automatic Isolations ONEP, Attachment II

1) IF Plant Air compressors are available, THEN OPEN/CHECK OPEN the following Instrument Air valves on 1H13

-P870: Section 3C P53-F001 (After 30 sec T.D.)

Section 9C P53-F007 (After 30 sec T.D.)

2) IF all Drywell temperatures are less than 200F (CRD cavity temperature excluded) AND Drywell Chillers are available, THEN RESTORE Drywell Chilled Water as follows:
a. IF required, RE-ENERGIZE MCC's 15B42 AND 16B42 on 1H13-P864. b. AFTER a 30 second time delay, OPEN the following valves on 1H13

-P870: Section 3C P72-F121 P72-F122 P72-F125 Section 9C P72-F123 P72-F126 P72-F124 c. ENSURE at least one Drywell Chilled Water pump is running. d. ENSURE Drywell Coolers are in operation.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 21 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP 3) IF Drywell Chilled Water is NOT restored per previous step, THEN STOP DW CHLD WTR PMP A AND B, IF running. 4) The following valves Will NOT close due to being gagged open. As time permits, give these valves an OPEN signal to lift actuator off of gag.

Section 3C P53-F026A Section 9C P53-F026B 5) REFER to Att. IV for Auxiliary Building restoration of Plant Service Water and Plant Chill Water isolations as required.

6) REFER to system SOI's when time permits to ensure complete system restoration.

If Diesel Generators received a start signal then verify proper operation and cooling water being supplied.

o Ensure Diesel running indication o Ensure SSW A/B/C are aligned to provide cooling water to running diesel generators.

SSW pump running A/B/C SSW Discharge Valves are open P41

-F001A/B SSW Supply to Diesel Generators Valves are open P41

-F018A/B SSW Return Valves to Basin are open P41

-F005A/B, P41

-F011.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 22 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior CRS Directs installation of Attachment 8 Directs reactor water level to be lowered by terminate and prevent all RPV injection except for Boron, CRD and RCIC

. Directs a level band of

-70" to -130" wide range.

Directs installation of Attachments 12 Booth When asked to install EP attachments:

Select Remotes on Director Select EP ATT folder at bottom of page.

Select desired attachment Select Install. When Attachment is complete notify CRS ATC Terminates feedwater injection by performing the following per 02

-S-01-43, Transient Mitigation Strategy:

IF time does NOT permit closing of valves, THEN TRIP reactor feed pump(s) AND/OR condensate/condensate booster pump(s) to prevent injection.

IF time permits closing of valves:

(1) IF S/U level control in service, THEN CLOSE the S/U level control valve AND/OR N21-F040 IF necessary.

(2) IF S/U level control is NOT in service, THEN ALIGN Feedwater for S/U level control with S/U level control valve closed.

Per step L

-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches

-70" wide range Controls Reactor water level using Feedwater Startup Level Control Valve within given band of

-70" to -130" wide range.

CRITICAL TASK IN BOLD

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 23 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Terminates Low pressure ECCS systems by performing the following per 02

-S-01-43, Transient Mitigation Strategy.

(1) ARM AND DEPRESS the manual system initiation push

-button for selected division.

(2) AFTER indication of pump(s) start, THEN TRIP the pump(s).

(3) CLOSE the associated injection valve(s).

(4) ENSURE the associated pump(s) and valve(s) override alarms are sealed in.

(5) REPEAT these steps for the other division.

For Division 1 ECCS:

Low Pressure Core Spray system RHR 'A' LPCI system For Division 2 ECCS RHR 'B' LPCI system RHR 'C' LPCI system Per step L

-7 terminate and prevent all RPV injection except for Boron injection, CRD and RCIC until level reaches

-70" wide range CRS Directs for pressure control to be maintained by Main Steam Bypass valves with a pressure band of 800 psig to 1060 psig.

Directs for Main Turbine Pressure control to lower pressure setpoint on the Main Turbine to 900 psig.

BOP Lowers Main Turbine Pressure Reference setpoint to 900 psig and maintains pressure band of 800 psig to 1060 psig.

Depresses the PRESS REF LOWER pushbutton on P680

-9C. Monitors N32

-R610 TURB STM PRESS DEMAND indication on P680

-9B When 900 psig is indicated releases PRESS REF LOWER pushbutton.

CRITICAL TASK IN BOLD

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 24 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior CRS Directs CRD system to be aligned for MAX Flow.

Directs installation of Attachments 18, 19, and 20 (performed by I&C)

Booth When asked to install EP attachments:

Select Remotes on Director Select EP ATT folder at bottom of page.

Select desired attachment Select Install. When Attachment is complete notify CRS

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 25 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 201 5 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Maximizes CR D system for flow by performing the following per 04 01-C11-1, Control Rod Drive SOI, Attachment VIII:

IF no CRD pumps are initially running, THEN a CRD pump Must be started per ONEP 05-1-02-IV-1 prior to performing the following steps.

All controls are located on panel 1H13

-P601-22B OR 22C. Per ONEP 05-1-02-IV-1 to restart 1 st pump: IF running CRD pump trips, THEN START standby CRD pump as follows: a. IF required, RE-ENERGIZE MCC's 15B42 AND 16B42 on 1H13

-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.

d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54

-66 gpm after charging pressure is normal.

e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54

-66 gpm. Per 04-1-01-C11-1, Control Rod Drive SOI, Attachment VIII:

1. ENSURE oil pump is running on the non

-running CRD Pump A(B).

2. With one CRD pump already running, THEN START standby CRD PMP A(B). 3. PLACE CRD SYS FLO CONT C11

-R600 in MANUAL.

4. USING CRD SYS FLOW CONT C11

-R600, fully OPEN C11-F002A(B), CRD FLO CONT VLV.

5. IF maximizing CRD for flow, THEN FULLY OPEN C11-F003, CRD DRIVE WTR PRESS CONT VLV.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 26 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior CRS Directs for injection of Standby Liquid Control per Hard Card BOP Initiates Standby Liquid Control by performing the following per 04 01-C41-1 Section 5.3:

a. OBTAIN SLC Initiation keys from the Shift Manager's key cabinet, INSERT keys into SLC PMP A AND B key switches on 1H13

-P601 AND TURN each momentarily to the START position (spring return to normal).

b. CHECK that system initiation has occurred by OBSERVING the following:

(1) F001A AND F001B STORAGE TANK OUTLET valves OPEN as indicated on 1H13

-P601. (2) Squib Valves F004A AND F004B fire as indicated by the following on 1H13

-P601: (a) White SQUIB VALVE READY light is Off.

(b) Annunciator "SLC SYS A AND B OOSVC" Alarms.

(c) Amber status light SQUIB A AND B LOSCONT OR PWR LOSS is On.

(3) SLC Pumps A AND B start WHEN the associated storage tank outlet valves open as indicated by red pump running lights on 1H13

-P601. (4) The following RWCU valve(s) CLOSE: (a) SLC A initiated

- 1G33-F004 CLOSES (1H13-P680) (b) SLC B initiated

- 1G33-F001 (1H13

-P680) AND 1G33-F251 (1H13

-P870-9C) CLOSE c. CHECK that SLC injection to the reactor by OBSERVING the following:

(1) SLC pump discharge pressure exceeds reactor pressure as indicated by SLC PMP A/B DISCH PRESS indicator.

(2) SLC tank level is lowering as indicated on SLC STOR TK LVL indicator 1H13

-P601. (3) Nuclear instrumentation on 1H13

-P680 indicates reactor power level is lowering.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 27 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP d. Monitor Reactor Power AND INSERT SRMs AND IRMs prior to reactor power going downscale on APRMs.

e. WHEN directed by the EPs to secure SLC injection, TURN the running SLC pump key switch(es) to the STOP position.
f. As soon as possible, RETURN the SLC System to STANDBY in accordance with Section 4.1.

Recognizes and reports SLC is NOT injecting due to low discharge pressure

. CRS Directs installation of Attachment 28 (performed by Mechanical Maint.)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 28 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

7 Event

Description:

RCIC steam line break with failure to auto isolate TIME Position Applicant's Actions or Behavior BOP Recognize and report steam line break in the RCIC room by the following Alarms on the P601

-21A panel:

H2 - RCIC PIPE/EQUIP AMBIENT TEMP HI H3 - G3 - RCIC EQUIP AREA TEMP HI Recognize and report EP

-4 entry condition. (P601

-21A-G3) Recognize automatic actions did not occur by observing E51

-F063 and F064, Steam Supply Valves did not close.

Perform actions that should have occurred automatically but did not.

Place handswitch for E51

-F063 and F064 to the CLOSE position on P601 panel section 21C Report to the CRS that RCIC isolation has completed manually with F063 and F064 have closed.

Isolate all systems (RCIC) discharging outside the primary CTMT through a break, except systems needed for fire suppression or EP actions prior to any other area exceeding its Max safe value in table 10 of EP

-4 CRS Enter EP-4 Monitor EP

-4 Operating and Max safe values Direct a manual isolation of RCIC

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 29 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

8 Event

Description:

Feedwater Line 'B' rupture in the Drywell TIME Position Applicant's Actions or Behavior ATC Recognize symptoms of a FW Line B rupture in the Drywell.

As indicated by high feed flow to the reactor in B feed water line a nd near zero feed water flow in A feed water line. Also indicated by rising DW pressure and temperature and drywell floor drain sump level and temperature alarms on 1H13

-P680-8A1. Perform the following:

Report the Feed water leak to the CRS.

Trip all condensate pumps. (This is necessary to immediately stop the leak in the drywell.)

Isolate the 'B' FW line by closing the B21

-F065B to allow feedwater to feed the reactor through the 'B' feedwater line

. o Depresses the CLOSE pushbutton for the B21

-F065B on the P680 panel.

Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.

CRS Directs ATC to isolate the Feedwater break by closing B21

-F065B and restore level. (Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 30 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

8 (cont.) Event

Description:

Feedwater Line 'B' rupture in the Drywell (cont.) TIME Position Applicant's Actions or Behavior ATC After B21-F065B gets full closed perform the following:

Restart at least 2 Condensate pumps o Depress the START pushbutton for the desired pump Restart at least 2 Condensate Booster pumps o Depress the START pushbutton for the desired pump Restart 1 Reactor Feedwater pump by performing the following:

RESTORE one Reactor Feed Pump to operation as follows:

a. ENSUR E RFPT A(B) CONTROLS "MANUAL" pushbutton is backlit.
b. VERIFY an AC lube oil pump is running for RFPT to be restarted.
c. ENSURE Instrument Air is available.
d. OPEN RFP A(B) DISCH VLV N21

-F014A(B).

e. DEPRESS the RFPT A(B) TRIP RESET pushbutton.

(1) IF the reactor feed pump turbine W ill NOT reset, PERFORM the following Step Locally:

(a) WHEN the oil system is operating, GRAB AND HOLD the Local Reset Lever for approximately 1 minute (This fills the circuit).

f. To place RFP in service, PERFORM one of the following:

(1) IF Turbine is OFFLINE, THEN RAISE pump speed USING the RAISE pushbutton until governor position is approx. 60%

OR as required to obtain discharge pressure approx. 250 psig above reactor pressure.

(2) IF Turbine is ONLINE, THEN RAISE pump speed USING the RAISE pushbutton as required to obtain discharge pressure approx. 250 psig above reactor pressure.

(3) IF desired to establish Feedwater flow without Startup Level Controller in service, THEN CONTROL Feedwater flow with RAISE AND LOWER pushbuttons as required.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 31 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

8 (cont.) Event

Description:

Feedwater Line 'B' rupture in the Drywell (cont.)

TIME Position Applicant's Actions or Behavior ATC g. IF desired, THEN SELECT SPEED AUTO

h. IF transferring to Startup Level Control, THEN RETURN to Attachment VII.

Maintain reactor water level using Startup Level Control Valve with a band of

-70" to -1 91" wide range Isolate the Feedwater line break inside the drywell and restore feedwater prior to emergency depressurization.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 32 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior CRS Verifies installation of Attachments 18, 19 and 20 then directs to Scram and Drive Control rods.

Directs BOP to maximize CRD for pressure Following an ATWS, insert control rods by manual scram and/or normal rod insertion prior to exiting EP

-2A BOP Maximize CRD for pressure by performing the following per 04 01-C11-1, Attachment VIII:

IF no CRD pumps are initially running, THEN a CRD pump Must be started per ONEP 05-1-02-IV-1 prior to performing the following steps.

All controls are located on panel 1H13

-P601-22B OR 22C. Per ONEP 05-1-02-IV-1 to restart 1 st pump: IF running CRD pump trips, THEN START standby CRD pump as follows: a. IF required, RE-ENERGIZE MCC's 15B42 AND 16B42 on 1H13

-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.

d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54

-66 gpm after charging pressure is normal.

e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54

-66 gpm. (Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 33 of 35 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

1 Event No:

6 (cont.) Event

Description:

ATWS (cont.)

TIME Position Applicant's Actions or Behavior BOP Per 04-1-01-C11-1, Control Rod Drive SOI, Attachment VIII:

1. ENSURE oil pump is running on the non

-running CRD Pump A(B).

2. With one CRD pump already running, THEN START standby CRD PMP A(B). 3. PLACE CRD SYS FLO CONT C11

-R600 in MANUAL.

4. USING CRD SYS FLOW CONT C11

-R600, fully OPEN C11-F002A(B), CRD FLO CONT VLV.

5. IF maximizing CRD for pressure , THEN FULLY CLOSE C11-F003, CRD DRIVE WTR PRESS CONT VLV, to maximize drive water pressure. NOTE:If CRD system is already maximized for FLOW only step 5 above will be performed.

Inserts Control Rods by Scram and normal lnsert drive by:

Manual Scram:

Reset Scram signal (Division 1 only)

Allow Scram Discharge Volume to drain Arm and depress Manual Scram pushbuttons.

(Division 1 only)

Normal Drive Reset Scram signal (Division 1 only)

Select control rod Select gang drive mode depress IN TIMER SKIP pushbutton until control rods indicate 00 Following an ATWS, insert control rods by manual scram and/or norma l rod insertion prior to exiting EP

-2A (Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 34 of 35 Revision 0 9/21/2015 TERMINATION Once rod movement has occurred and reactor water level is being controlled in band or as directed by Lead Evaluator:

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 1 Page 35 of 35 Revision 0 9/21/2015

Attachment 1 06-OP-1R21-W-0001, ATTACHMENTS II & III

Revision 0 9/21/2015 36 of 46 GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II Page 1 of 4 Model WO#

50289936 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Plant AC and DC Electrical Power Distribution Weekly Lineup Technical Specifications: SR 3.8.1.1 1.0 IMPAC T STATEMENT 1.1 Performance of this procedure has no impact on plant operation.

2.0 PROCEDURE

2.1 Plant Mode is (circle one): 1 2 3 2.2 Test Start Time

/ /

Performer / Date Time

2.3 Radiation

Protection Revie w

RWP # 3.0 TES T RESULTS 3.1 Test Completion: (CHECK one in each category.)

Entire procedure completed [ ] Partial procedure completed [ ]

Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable [ ]

All other steps/data Acceptable [ ] Unacceptable [ ]

3.2 Inop Electrical Equipment (include LCO #)

3.3 Comments

3.4 Test performed by Date/Time

/

4.0 DEFICIENCIES

CR Issued # LCO Entered # WR Issued # 5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]

Shift Supervision Date CONCURRENCE Operations Management Date GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II Page 2 of 4 Page XRef Revision 0 9/21/2015 37 of 46 DATA SHEET I PLANT AC AND DC ELECTRICAL POWER DISTRIBUTION WEEKLY LINEUP SAFETY RELATED (Step 5.2.2) Div 1, 2 & 3 Offsite Feeders OFFSITE ENERGIZED VOLTAGE RECORDED FREQUENCY RECORDED INITIALS FEEDER INDICATOR VOLTAGE INDICATOR FREQUENCY

YES/NO (LOCATION)

(ACCEPTANCE (LOCATION)

(ACCEPTANCE

CRITERIA)

CRITERIA)

BAXTER

500 kV FREQ.

$ WILSON

  • JACKSON kV SR27-SR-R600 Hz DISPATCHER

(H13-P807)

$ FRANKLIN

  • (496-525kV)*** or Pine Bluff Dispatcher (58.5-61.8Hz)

x 27.64

152-1511 = kV

115kV LINE 152-1611 (120.75-

$ PORT GIBSON

  • 152-1704 112.13) kV
  • To determine status of offsite feeders, CONTACT load dispatcher. Ensure that the feeders are independently energized from the grid, such that the loss of one feeder would NOT result in the loss of another. ** To determine voltage of the Port Gibson 115kV line, record ESF 12 incoming voltage at Bus 15AA, 16AB OR 17AC placing the Sync switch for the designated breaker to ON. MULTIPLY this reading by 27.64 for equivalent feeder voltage. RETURN Sync switch to OFF after taking reading

. *** Allowable Value of minimum voltage is

>491 kV for operability of Offsite Feeders. This value is based on analysis of the Class 1E ESF buses AND includes an allowance for instrument uncertainty associated with the voltage measurement in the switchyard. Extended operation beyond the normal continuous operating limits Should be evaluated AND caution Should be taken when starting large loads under these conditions.

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II Page 4 of 4 Page XRef Revision 0 9/21/2015 38 of 46 DATA SHEET I (Continued)

PLANT AC AND DC ELECTRICAL POWER DISTRIBUTION WEEKLY LINEUP SAFETY RELATED

RECORDED

VOLTAGE REQUIRED ACTUAL INSTRUMENT ACCEPTANCE BREAKE R POSITION POSITION INITIALS COMMENTS (LOCATION)

CRITERIA Service Transformer 11

- Bus 11R to ESF 15AA, 16AB & 17AC

34.5kV Bus A-B = (1) $ 552-1105 Closed 11R Volts B-C = (1) 1R25-EI-R603 C-A =

(1) $ 552-1104 Closed (H13-P807-1B) (31.05-37.95kV)

Bkr 152-1514

  • Inc Voltage (3952-4576)

Bkr 152-1601 *

$ 152-1901 Closed Inc Voltage (3952-4576)

Bkr 152-1706 *

$ 152-1902 Closed Inc Voltage (3952-4576)

  • Note: For these breakers VERIFY voltage is available to the ESF Bus by placing the Sync switch on 1 H13-P864 OR 1H13-P601 for the designated breaker to ON AND RECORDING incoming voltage. RETURN Sync switch to OFF after taking reading.

(1) Voltage indication from 1R25

-EI-R603 is NOT required to meet Tech Spec acceptance criteria.

Voltage indication is met by acceptable incoming voltage for breakers 152

-1514, 152-1601, AND 152-1706. SELECT phase of bus to be monitored by use of the voltage select switch. INSURE voltage select switch is NOT left in OFF.

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II Page 4 of 4 Page XRef Revision 0 9/21/2015 39 of 46 DATA SHEET I (Continued)

PLANT AC AND DC ELECTRICAL POWER DISTRIBUTION WEEKLY LINEUP SAFETY RELATED (Step 5.2.2)

RECORDED

VOLTAGE REQUIRED ACTUAL INSTRUMENT ACCEPTANCE BREAKER POSITION POSITION INITIALS COMMENTS (LOCATION)

CRITERIA Service Transformer 21

- Bus 21R to ESF 15AA, 16AB & 17AC

34.5kV Bus A-B = (1) $ 552-2105 Closed

21R Volt B-C =

(1)

2R25-EI-R603 C-A =

(1) $ 552-2104 Closed

(H13-P807-4B) (31.05-37.95kV)

Bkr 152-1501

  • Inc Voltage (3952-4576)

Bkr 152-1614 *

$ 152-2901 Closed

Inc Voltage (3952-4576)

Bkr 152-1705 *

$ 152-2902 Closed

Inc Voltage (3952-4576) 115 kV Line to ESF 15AA, 16AB & 17AC

$ J3885 Closed

N/A N/A

Bkr 152-1511

  • Inc Voltage (3952-4576)

Bkr 152-1611 *

$ 152-1903 Closed

Inc Voltage (3952-4576)

Bkr 152-1704 *

$ 152-1904 Closed

Inc Voltage (3952-4576)

  • Note: For these breakers VERIFY voltage is available to the ESF Bus by placing the Sync switch on 1H13

- P864 OR 1H13-P601 for the designated breaker to ON AND RECORDING incoming voltage.

RETURN Sync switch to OFF after taking reading. (1) Voltage indication from 2R25

-EI-R603 for Bus 21R is not required to meet Tech Spec acceptance criteria. Voltage indication is met by acceptable incoming voltage for breakers 152

-1501, 152-1614, AND 152-1705. SELECT phase of bus to be monitored by use of the voltage select switch. INSURE voltage select switch is NOT left in OFF.

ACCEPTANCE CRITERIA REFERENCE TECHNICAL SPECIFICATION REQUIRED ACTION(S)

IF ACCEPTANCE CRITERIA NOT MET FOR: SR 3.8.1.1

- Mode 1, 2, 3

- LCO 3.8.1 - Condition A, C, D two of the above circuits between the offsite

transmission network AND the onsite Class 1E

distribution system are Operable; correct breaker

lineup AND power available.

Revision 0 9/21/2015 40 of 46 GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment III Page 1 of 6 PAGE XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Operability Checksheet Technical Specifications: LCO 3.8.1, Required Action B.2

1.0 IMPAC

T STATEMENT 1.1 Performance of this procedure has no impact on plant operation.

2.0 PROCEDURE

2.1 Plant Mode is (circle one): 1 2 3 2.2 Test Start Time

/ /

Performer / Date Time

2.3 Radiation

Protection Review

RWP # 3.0 TES T RESULTS 3.1 Test Completion: (CHECK one in each category.)

Entire procedure completed [ ] Partial procedure completed [ ]

Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable

[ ] All other steps/data Acceptable [ ] Unacceptable [ ]

3.2 Comments

3.3 Test performed by Date/Time

/

4.0 DEFICIENCIES

CR Issued #

LCO Entered # WR Issued #

5.0 APPROVAL

Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]

Shift Supervisor. Date Comments:

CONCURRENCE Operations Management Date

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II I Page 2 of 6 Page XRef Revision 0 9/21/2015 41 of 46 DATA SHEET I OPERABILITY CHECKSHEET SAFETY RELATED 5.3.2 WHEN Div 1 D/G is declared Inop THEN the following items Shall be verified Operable per LCO 3.8.1, Required Action B.2.

OPERABLE INITIALS (YES/NO) 1. LPCI mode of RHR B System

2. LPCI mode of RHR C System
3. CTMT Spray mode of RHR B System
4. Suppression Pool Cooling mode of RHR B System
5. Shutdown Cooling mode of RHR B System (required in mode 3 only)
6. Suppression Pool Makeup System, Div 2
7. CTMT AND Drywell Isolation valves (Tables TR3.6.1.3

-1 AND TR3.6.5.3-1, Section 1), Div 2 (does NOT include AOVs OR closed/deenergized MOVs)

8. Post LOCA vacuum breaker AND Drywell purge vacuum relief subsystem, Div 2
9. Secondary CTMT Isolation valves (Table TR3.6.4.2

-1), Div 2 (does NOT include AOVs OR closed/deenergized MOVs)

10. Standby Gas Treatment B System
11. Hydrogen Recombiner System, Div 2
12. CTMT AND Drywell Hydrogen Ignition System, Div 2
13. Control Room Emergency Filtration System, Div 2
14. MSIV Leakage Control System, Div 2
15. FW Leakage Control System, Div 2

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II I Page 3 of 6 Page XRef Revision 0 9/21/2015 42 of 46 DATA SHEET I (Continued)

OPERABILITY CHECKSHEET SAFETY RELATED OPERABLE INITIALS (YES/NO) 16. RHR B Room HVAC

17. RHR C Room HVAC
18. ESF SWGR Room HVAC, Div 2
19. Standby Liquid Control System, Div 2 20. Drywell Purge Compressor, Div 2
21. Battery Charger, Div 2 (either 1B4 or 1B5)
22. Safeguard Switchgear and Battery Room Ventilation, Div 2
23. HPCS System
24. Control Room Air Conditioning System, Div 2
25. Standby Service Water, Div 2 NOTE IF Safeguard Switchgear AND Battery Room Ventilation ,Div 2,is Inop, AFTER four hours ENTER Tech. Spec. LCO ACTION for TS 3.8.4, 3.8.5, 3.8.7 AND/OR 3.8.8 as applicable unless An engineering determination be made in accordance with Generic letter 91

-18 that the Degraded Z77 functi on Will maintain the power distribution system OPERABLE under the Current condition.

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II I Page 4 of 6 Page XRef Revision 0 9/21/2015 43 of 46 DATA SHEET II OPERABILITY CHECKSHEET SAFETY RELATED 5.3.2 WHEN Div 2 D/G is declared Inop THEN the following items Shall be verified Operable per LCO 3.8.1, Required Action B.2.

OPERABLE INITIALS (YES/NO) 1. LPCS System

2. LPCI mode of RHR A System
3. CTMT Spray mode of RHR A System
4. Suppression Pool Cooling mode of RHR A System
5. Shutdown Cooling mode of RHR A System (required in mode 3 only)
6. Suppression Pool Makeup System, Div 1
7. CTMT AND Drywell Isolation valves (Tables TR3.6.1.3

-1 AND TR3.6.5.3-1, Section 1), Div 1 (does NOT include AOVs OR closed/deenergized MOVs)

8. Post LOCA vacuum breaker AND Drywell purge vacuum relief subsystem, Div 1
9. Secondary CTMT Isolation valves (Table TR3.6.4.2

-1), Div 1 (does NOT include AOVs OR closed/deenergized MOVs)

10. Standby Gas Treatment A System
11. Hydrogen Recombiner System, Div 1
12. CTMT AND Drywell Hydrogen Ignition System, Div 1
13. Control Room Emergency Filtration System, Div 1
14. MSIV Leakage Control System, Div 1
15. FW Leakage Control System, Div 1

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II I Page 5 of 6 Page XRef Revision 0 9/21/2015 44 of 46 DATA SHEET II (Continued)

OPERABILITY CHECKSHEET SAFETY RELATED OPERABLE INITIALS (YES/NO) 16. LPCS Room HVAC

17. RHR A Room HVAC
18. ESF SWGR Room HVAC, Div 1
19. Standby Liquid Control System, Div 1
20. Drywell Purge Compressor, Div 1
21. Battery Charger, Div 1 (either 1A4 or 1A5)
22. Safeguard Switchgear and Battery Room Ventilation, Div 1
23. HPCS System
24. Control Room Air Conditioning System, Div 1
25. Standby Service Water, Div 1 NOTE IF Safeguard Switchgear AND Battery Room Ventilation ,Div 1,is Inop, AFTER four hours ENTER Tech. Spec. LCO ACTION for TS 3.8.4, 3.8.5, 3.8.7 AND/OR 3.8.8 as applicable unless An engineering determination Can be made in accordance with Generic letter 91

-18 that the Degraded Z77 function WILL maintain the power distribution system OPERABLE under the Current condition.

GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-OP-1R20-W-0001 Revision 109 Attachment II I Page 6 of 6 Page XRef Revision 0 9/21/2015 45 of 46 DATA SHEET III OPERABILITY CHECKSHEET SAFETY RELATED 5.3.2 WHEN Div 3 D/G is declared Inop THEN the following items Shall be verified Operable per LCO 3.8.1, Required Action B.2.

OPERABLE INITIALS (YES/NO) 1. LPCS System AND any two of the following:

LPCI mode of RHR A, B, C

2. Automatic Depressurization System (A OR B)

Give this page to the CRS

` Crew Turnover:

Turnover the following conditions:

Power 9 5% M OC EOOS GREEN The plant is currently in Power Ascension from 65% power for sequence exchange. Reactor Engineering is performing calculations and will notify you when to continue to raise power.

SSW A is operating per 04 03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.

Planned Evolutions this shift:

Rotate power on electrical bus 17AC from transformer ESF 12 to ESF 21.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 1 of 7 Revision 0 9/21/2015 Facility:

Grand Gulf Nuclear Station Scenario No.:

2 Op-Test No.: NRC LOT 201 5 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________

____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Start RHR A in Suppression Pool Cooling
2. Respond to a trip of RHR 'C' Jockey pump
3. Respond to a trip of CRD pump A

. 4. Respond to CRD Accumulator Faults. 5. Respond to a Suppression pool leak in RHR pump A suction piping while operating in Suppression Pool Cooling

. 6. Respond to both Heater Drain Pump Trip

. 7. Respond to Reactor Instrument Line Failure

8. Respond to Logic Power Failure to LPCS/RHR A
9. Division 2 ECCS High Drywell Pressure fail to Initiate
10. Respond to a Hotwell low level signal

. Initial Conditions:

Operating at 100% power.

Inoperable Equipment:

None Turnover:

The plant is at 100%. RCIC is tagged for maintenance. LCO 3.5.3 Condition A has been entered, HPCS is verified OPERABLE. Planned activities for this shift are:

Start RHR 'A' in Suppression Pool Cooling mode SSW A is operating in preparation for weekly chemical addition.

Scenario Notes:

This scenario is a NEW Scenario. Validation Time: 60 minutes

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 2 of 7 Revision 0 9/21/2015 Event No. Malf. No. Event Type f Event Description 1* N (BOP) TS (CRS) Start RHR 'A' in Suppression Pool Cooling (04 01-E12-1, Tech Spec 3.5.1 Condition A

) 2 DI_1E12M601C TS (CRS) RHR 'C' Jockey Pump Trip (Tech Spec 3.5.1 Condition C) 3* c11028a C (BOP) A (CREW) Respond to a Trip of CRD pump 'A' (CRD Malfunction ONEP, 05-1-02-I V-4) 4* z024_024_32_17 z024_024_36_21 C (ATC) A (CREW) Respond to two HCU Accumulator low pressure fault (SOI 04-1-01-C11-1; ARI 04-1-03-P680-4A2-D4) 5 ct218a C (BOP) TS (CRS) Respond to Suppression pool leak from RHR 'A' suction line

. (EP-3 & 4, EN-OP-115, Conduct of Operations, Tech Spec 3.6.2.2 Low suppression pool level Cond A) 6 fw231a & b C (ATC) A (CREW) R (ATC) Respond to both Heater Drain Pumps trip , (Loss of Feedwater Heating 05 02-V-5; Reduction in Recirculation System Flow Rate ONEP, 05 02-III-3) 7 rr062 M (CREW) Respond to Reactor Instrument Line Failure (EP-2) 8 r21219 r21220 I (CREW) Respond to Logic Power Failure to LPCS/RHR 'A' (Alarm Response Instruction, 04-1-03-P601-21A-H8, LPCS OOSVC) 9 rr040f rr041f I (CREW) Division 2 ECCS High Drywell Pressure fails to initiate , (EN-OP-120). 10 p680_2a_e_9 fw115a, b & c I (CREW) Respond to a false Hotwell low level signal (EP-2 , Alarm Response Instruction 04 03-P680-2A-E9, CNDSR HTWL LVL LO) f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

  • Repeated task from last 2 NRC exams.

Quantitative Attributes Table Normal Events 1 E O P Contingency Procedures Used 2 Total Malfunctions 7 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 Abnormal Events 4 Critical Tasks 3 Major Transients 1 Instrument/Component Failures 7 E O Ps Used (Requiring measurable action) 2 Reactivity Manipulations 1

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 3 of 7 Revision 0 9/21/2015 SCENARIO ACTIVITIES:

Start RHR 'A' in Suppression Pool Cooling A. After Crew has taken shift contact the CRS to place RHR 'A' in Suppression Pool Cooling beginning with step 5.2.2 a. (Event 1)

B. When Test Return to Supp Pool Valve E21-F024A is opened the CRS will determine that Tech Spec 3.5.1 Condition A applies.

RHR 'C' Jockey Pump Trip A. After Crew has placed suppression pool cooling in service, Tech Specs have been addressed and/or at the direction of the lead evaluator trigger Event 2 to cause RHR 'C' Jockey Pump breaker (52

-161135) to trip.

B. Crew will respond using Alarm Response Instructions.

C. If asked to investigate pump trip, wait 3 minutes and report breaker 52

-161135 is in the trip free condition.

D. CRS will declare RHR

'C' INOP and determine Tech Spec 3.5.1 Condition C applies.

E. Crew will rackout the breaker for RHR 'C' pump, 152-1609, to protect the piping.

Trip of CRD pump 'A'

A. After Tech Specs have been addressed and RHR 'C' pump breaker is racked out and/or at the direction of the lead evaluator trigger Event 3 to cause CRD pump 'A' to trip.

B. Crew will enter CRD Malfunction ONEP and perform immediate actions to start standby CRD Pump.

C. If asked to investigate pump trip:

1. Wait 3 minutes and respond as a Plant Operator and report "no apparent reason for pump trip and motor is hot to the touch
2. Wait 3 minutes and respond as Electrical Maintenance and report breaker 152

-

1505 has a 186 device tripped with Instantaneous flags on all three phases.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 4 of 7 Revision 0 9/21/2015 Two HCU Accumulator low pressure faults.

A. During the CRS pump trip of event 2 two HCU accumulators will indicate low pressure (Event 4) 1. One accumulator will clear when the standby pump is started.

2. If asked to provide local accumulator pressure, wait 5 minutes and report as plant operator that HCU 32

-17 is 1620 psig and HCU 36

-21 is 15 80 psig. B. The CRS will instruct to recharge HCU 36

-21 per ARI and SOI, 04 01-C11-1. C. No Tech Spec is required due to >1520 psig.

Suppression Pool Leak from RHR 'A' suction line.

A. After Immediate and Subsequent actions of CR D Malfunction ONEP and Tech Specs have been addressed and/or at the direction of the lead evaluator trigger Event 5 to cause a leak on the suction line of RHR 'A' system.

B. A leak will develop on the downstream side of the RHR MOV suction valve E12

-F004A. C. Crew should trip RHR 'A' pump and close suction valve E12

-F004A to isolate the leak. 1. After E12-F004A is closed the leak will stop.

D. The CRS should enter EP

-3 due to suppression pool water level below 18.34 FT.

E. The CRS should enter EP-4 due to Hi

-Hi RHR 'A' room sump and RHR 'A' room flooded. F. The CRS will determine that Tech Spec 3.6.2.2 Condition A applies due to low suppression pool level

. No other tech spec on 3.5.1 due to RHR 'A' was already INOP. Both Heater Drain Pumps Trip A. After EPs and Tech Specs have been addressed and/or at the direction of the lead evaluator trigger Event 6 to cause both Heater Drain Pumps to trip.

B. Crew will enter Loss of Feedwater Heating

, Feedwater System Malfunctions, and Reduction in Recirculation System Flow Rate ONEP s. C. Crew will reduce core flow to 70 Mlbm/hr per immediate operator actions.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 5 of 7 Revision 0 9/21/2015 Reactor Instrument Line Failure A. After all immediate and subsequent actions of ONEPS have been addressed and/or at the direction of the lead evaluator trigger Event 7 to cause Reactor Below Core Plate pressure instrument line break.

Drywell pressure will slowly rise causing the crew to take action to place the mode switch in SHUTDOWN.

B. Crew will enter EP

-2, EP-3, Turbine Trip and Reactor Scram ONEPs.

C. The leak propagate s into a Reactor Recirc line break that cause reactor level to reduce. LPCS / RHR 'A' Logic Power Failure A. The crew will recognize and respond to a fail to initiate on LPCS and RHR 'A' (Event 8) B. The crew will manually start the LPCS system (per ARI P601-21A-H8, LPCS SYS OOSVC, step 4.6) and manually (locally) open the injection valve

. Division 2 ECCS High Drywell Pressure fail to initiate A. One of the two drywell pressure transmitters for Division 2 ECCS to auto initiate fails low (Event 9), Div 2 ECCS will not auto initiate requiring the crew to manually initiate the Division 2 ECCS system. (RHR B only, RHR C is unavailable due to jockey pump loss)

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 6 of 7 Revision 0 9/21/2015 False Hotwell Level Low A. Two minutes after Mode Switch is taken to SHUTDOWN, a false Hotwell level low will occur (Event 10) causing a trip of all Condensate pump which will cause a trip of all Condensate Booster pumps and Feedwater pumps.

B. This failure will cause a loss of all high pressure feed systems.

C. Reactor water level will lower to <

-160" requiring an Emergency Depressurization.

D. Crew will restore reactor water level with LPCS (If manually started), RHR 'B' and HPCS (if injection valve is manually opened) Termination:

A. After Reactor water level is restored by LPCS, RHR 'B' and HPCS systems and is being controlled in band or as directed by Lead Evaluator Take the simulator to Freeze and turn horns off. Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow-up questions are asked.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 2 Page 7 of 7 Revision 0 9/21/2015 Critical Task Number Description Bas i s 1 Open at least 7 SRVs when RPV water level is between

-160" and -190". If an injection source is available but the decreasing RPV water level trend cannot be reversed before RPV water level drops to the Minimum Steam Cooling RPV Water Level (-191 in.), emergency RPV depressurization is required to permit injection from low head systems, maximize flow from available injection sources, and minimize the flow through any primary system break.

(per 02-S-01-40, EP Technical Bases) 2 After Emergency Depressurization, restore and maintain RPV level above -191" using available injection systems prior to exiting EP-2. The Minimum Steam Cooling RPV Water Level is the lowest RPV water level at which the covered portion of the reactor core will generate sufficient steam to preclude any clad temperature in the uncovered portion of the core from exceeding 1500°F.

(per 02-S-01-40, EP Technical Bases) 3 When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig. Take manual actions (in accordance with procedure direction, if available) when automatic actions do not occur.

(per EN-OP-120, Operator Fundamentals Program). 300 psig is bases on maximum discharge pressure for RHR LPCI systems B and C injection is 285 psig.

  • Critical Task (As defined in NUREG 1021 Appendix D)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 1 of 23 Revision 0 9/21/2015 Simulator Setup:

A. Initialization

1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
4. Set the Simulator to IC-10 2 and perform switch check (Using Quick Reset in Director).
5. Click on "Open" in the Schedule window and Open Schedule File "201 5 NRC Scenario 2.sch" (in the Schedule Directory)
6. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 2 of 23 Revision 0 9/21/2015 7. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)

8. Take the simulator out of freeze.
9. Log on to all simulator PDS and SPDS computers.
10. Verify or perform the following:

IC-10 2 APRM's are turned on (4,1,2,3)

Ensure the MOC rod movement sequence available at the P680.

Advance all chart recorders and ensure all pens inking properly.

Clear any graphs and trends off of SPDS.

Ensure SSW A is aligned properly per 04-1-03-P41-1, SSW A Chemical Addition Run

. Marked up copy up to step 7.7 of 04 03-P41-1, SSW A Chemical Addition Run, is placed on CRS desk.

Marked up copy up to step 5.2.2 a of 04-1-01-E12-1 , Residual Heat Removal System

. Ensure CRD pump 'A' is in operation.

Ensure suppression pool temperature is 85 degrees F with alarms P870

-

3A-E4 and 10A

-E4. Ensure RCIC is tagged out of service RCIC OOSVS switches in the OOSVC position.

11. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

12. Place the simulator in Freeze.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 3 of 23 Revision 0 9/21/2015 B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 4 of 23 Revision 0 9/21/2015 Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 5 of 23 Revision 0 9/21/2015 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 100% M OC EOOS 10.0 GREEN Suppression Pool Temperature is 85

°F RCIC is tagged for maintenance. LCO 3.5.3 Condition A has been entered, HPCS is verified OPERABLE.

SSW A is operating per 04 03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition.

C. Planned Evolutions this shift:

Place RHR 'A' in Suppression Pool Cooling. Operations Work Control and Duty Manager have been notified

. D. Allow the crew to perform pre

-shift brief and review procedures for planned evolutions.

E. Bring the crew into the Simulator, place the simulator is in RUN.

F. Allow the crew to walk down panels. G. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 6 of 23 Revision 0 9/21/2015 SCENARIO ACTIVITIES:

Start SBT report and any other required recording devices.

Emergency Classification:

Alert on FA1 (RC2). Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

1 Event

Description:

Start RHR 'A' in Suppression Pool Cooling TIME Position Applicant's Actions or Behavior CRS Directs BOP to start RHR 'A' system in Suppression Pool cooling mode.

BOP Using RHR SOI, 04 01-E12-1, section 5.2.2, performs the following on P601 panel: (1) START SSW A with flow through RHR A heat exchangers in accordance with SOI 04 01-P41-1, if not already in service.

(2) START RHR RM A FAN COIL UNIT on 1H13

-P870. (3) OPEN OR CHECK OPEN F003A, HX A OUTL VLV. NOTE Opening of F024A causes LPCI A Mode of RHR to be inoperable.

(4) START RHR A PMP.

(5) OPEN F024A, RHR A TEST RTN TO SUPP POOL.

(6) THROTTLE F048A, HX A BYP VLV as needed for suppression pool cooling.

IF needed to further reduce suppression pool cooling, THEN THROTTLE F003A, HX A OUTL VLV after F048A is full Open.

(7) CHECK F064A is still Closed, OR has Closed when RHR PMP A FLO exceeded 1000 gpm.

CRS Enters Tech Spec 3.5.1 condition A

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 7 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

2 Event

Description:

RHR 'C' Jockey Pump Trip TIME Position Applicant's Actions or Behavior BOP Recognizes and reports RHR 'C' Jockey pump trip by the following indications:

P601-17A alarms C4, RHR PMP C DISCH. PRESS ABNORMAL.

H3, RHR C SYS OOSVC JKY PMP OVERLD/PWRLOSS status light on 17B RHR 'C' Jockey Pump handswitch shows green and amber indication CRS Directs BOP to send operator to investigate.

BOP Directs operator and or electrical maintenance to investigate breaker 52

-161135. Booth If ask to investigate, wait 3 minutes and report as operator or electrical maintenance that breaker 52

-161135 is in the trip free position. Any other investigation will require a work order.

CRS Enters Tech Spec 3.5.1 Condition C Enters Tech Spec 3.3.6.4 Condition C Directs Plant operator to rack out RHR 'C' pump breaker, 152

-1609, to prevent any auto start due to no jockey pump running.

Booth If ask to rack out breaker 152

-1609, wait 5 minutes, trigger event 30 and report as operator that 152

-1609 breaker for RHR pump 'C' is racked out.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 8 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

3 Event

Description:

CRD pump 'A' trip TIME Position Applicant's Actions or Behavior BOP Recognize and notify crew loss of CRD pump 'A'

. Performs immediate operator actions from CRD Malfunctions ONEP and Starts standby pump by performing the following:

IF running CRD pump trips, THEN START standby CRD pump as follows: a. IF required, RE-ENERGIZE MCC's 15B42 AND 16B42 on 1H13

-P864. b. PLACE CRD SYS FLO CONT in MANUAL AND REDUCE output to zero. c. START standby CRD pump.

d. IF no scram signal is present, THEN SLOWLY ADJUST CRD SYS FLO CONT to 54

-66 gpm after charging pressure is normal.

e. RETURN CRD SYS FLO CONT to AUTO with tapeset at 54

-66 gpm. CRS Enters Control Rod/Drive Malfunctions ONEP, 05-1-02-IV-1 ATC Monitors for Accumulator Faults before standby pump start By monitoring for HCU TROUBLE (P680

-4A2-D4) alarm and/or HCU FAULT back lit pushbutton on RCIS control panel (P680

-6C) Monitors for Control Rod Drift after pump start.

By monitoring for CONT ROD DRIFT (P680

-4A2-E4) alarm and/or ROD DRIFT back lit pushbutton on RCIS control panel (P680

-6C) Booth If dispatched wait 3 minutes and report the following:

As Plant operator report 'A' CRD pump motor hot to the touch.

As Electrical Maintenance and report breaker 152

-1505 186 device is tripped with Instantaneously flags on all three phases

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 9 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

4 Event

Description:

HCU Accumulator Low Pressure Fault

TIME Position Applicant's Actions or Behavior ATC Receives HCU TROUBLE alarm on P680, Recognizes and reports Two HCU Accumulator Faults (32

-17 & 36-21) prior to standby pump starting, by depressing HCU FAULT pushbutton on P680.

After HCUs are identified the ATC should depress ACK N HCU FAULT per ARI P680-4A2-D4 to reset the HCU TROUBLE alarm and seal in the RCIS red indication .

Reports one Accumulator Fault (32-17) clears after standby pump starts.

Reports one Accumulator Fault (36

-21) is still sealed in.

BOP Dispatches Plant Operator to HCUs to investigate Fault alarms.

Booth If dispatched wait 4 minutes and report the following HCU pressures:

36-21 1610 psig 32-17 15 80 psig CRS Directs plant operator to recharge accumulator 32-17. Determines no Tech Specs apply due to pressure is above min of 1520 psig

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 10 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

5 Event

Description:

Suppression Pool Leak from RHR 'A' Suction Line TIME Position Applicant's Actions or Behavior BOP Recognizes Suppression Pool Leak from RHR 'A' by receiving RHR ROOM FLOODED alarm on P870

-2A-E1. Verifies with ATC that RHR RM 'A' Sump Level Hi

-Hi alarm is also in.

Reports to CRS/Crew entry into EP

-4. Trips RHR 'A' pump and closes E12

-F004A per 02

-S-01-43, Transient Mitigation Strategy.

Monitors and reports Suppression Pool level.

ATC Reports RHR RM 'A' Sump Level Hi

-Hi P680-8A1-A2 Reports to CRS/Crew entry into EP

-4. CRS Enters EP-4 when either alarm RHR ROOM FLOODED alarm on P870

-2A-E1 or RHR RM 'A' Sump Level Hi

-Hi P680-8A1-A2 is received.

Enters EP-3 when suppression pool level is <18.34 ft.

Directs the BOP to isolate the leak.

Enters Tech Spec 3.6.2.2 on Low Suppression Pool level, Tech Spec 3.6.1.7, RHR Containment Spray Tech Spec 3.6.2.3, RHR Suppression Pool Cooling Directs to raise Suppression Pool water level using normal P11 SOI.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 11 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

6 Event

Description:

Both Heater Drain Pumps Trip TIME Position Applicant's Actions or Behavior ATC Recognizes and reports Both Heater Drain Pumps Trip by the following indications:

P680-1A alarms A7 - HTR DR PMP A TRIP A8 - HTR DR PMP B TRIP P680-1C indications HTR DR PMP A handswitch green indication HTR DR PMP B handswitch green indication Perform immediate actions of Loss of Feedwater Heating ONEP, 05 02-V-5: Reduce Core Flow to 70 Mlbm/hr using both Recirc LOOP A CONT and LOOP B CONT, B33

-K603A & B, move the slide switches to the full left (i.e. fast detent) and verify core flow is lowering using B33

-R613 indicator of TOT JP FLO.

Maintain loop flow mismatch in Recirc system within 5% (2230 gpm)

If / When 70 Mlbm/hr is reached release the slide switches B33

-K603A & B. Note: Due to the partial loss of suction to the Feedwater pumps, Feedwater pump suction pressure will lower causing a trip of 'A' Feedpump.)

After Feedpump A trips and reactor water level reduces to the low alarm setpoint a Reactor Recirc FCV Runback will occur.

Release the Recirc Loop flow controllers and verify the runback completes.

CRS Enters Loss of Feedwater Heating ONEP, 05 02-V-5 and Reduction in Recirculation System Flow Rate ONEP, 05 02-III-3 and Feedwater Malfunction ONEP, 05 02-V-7 ATC After plant is stable, plots on Power to Flow map per Reduction in Recirculation System Flow Rate ONEP, 05 02-III-3, to determine region of operation.

Determines operation in the OPRM Trip Enable region and assumes THI watch with no concurrent duties.

BOP Verifies ATC plot on power to flow map.

Determines operation in the OPRM Trip Enable region

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 12 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

6 (cont.) Event

Description:

Both Heater Drain Pumps Trip (cont.) TIME Position Applicant's Actions or Behavior CRS After feedwater temperature, reactor power and core flow is stable directs ATC to have concurrent duties.

Dispatch plant operator to reset hi vibration alarm on Feedpump 'B' Booth If requested, reset hi vibration alarm on 'A' RFPT.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 13 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

7 Event

Description:

Reactor Instrument Line Failure TIME Position Applicant's Actions or Behavior ATC Recognizes and reports rising Drywell Pressure by the following indications:

PDS Computer point trend up P870 alarms P680 alarms o 4A1-A6 o 4A1-A7 o 8A1-B7 o 8A1-D7 P680 indicator B33

-UR-R613 RX CORE dP full upscale CRS Directs ATC to manually scram the reactor prior to exceeding scram setpoint

. Enters Turbine and Generator Trip, 05 02-I-2, Reactor Scram, 05-1-02-I-1, ONEPs and EP

-2 ATC Performs immediate operator actions for Turbine and Generator Trip, 05 02-I-2, and Reactor Scram, 05 02-I-1, ONEPs Place the Mode SW to SHUTDOWN as directed.

Provides a scram report:

o Reactor Mode SW in SHUTDOWN. o All Rods are Inserted. o Reactor power is 0%. o Reactor water level and trend.

Ensure Main Turbine Stop and Control Valves are CLOSED Ensure Both Generator Output Breakers are OPEN CRS Enters EP-2 RPV Control and EP

-3 Containment Control Verifies Reactor Mode Switch is in SHUTDOWN Evacuates affected areas

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 14 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

7 (cont.) Event

Description:

Reactor Instrument Line Failure (cont.) TIME Position Applicant's Actions or Behavior ATC Assumes Reactor water level control duties.

Aligns Condensate/Feedwater to Startup level control valve per hard card, 04 01-N19-1. IF two RFPTs are in operation, THEN TRIP one by DEPRESSING TRIP pushbutton.

CLOSE the following valves:

a. N21-F009A, FW HTR 6A OUTL VLV
b. N21-F009B, FW HTR 6B OUTL VLV.

OPEN the following valves:

a. N21-F001, SU FCV OUTL ISOL VLV.
b. N21-F010A, HP FW HTR STRNG A SU OUTL VLV.
c. N21-F010B, HP FW HTR STRNG B SU OUTL VLV.

VERIFY CLOSED the following valves:

a. N21-F513, X WTR LVL SU CONTR Valve (per controller 1C34

-LK- R602) b. N21-F510, FW CU RECIRC VLV

c. N21-F040, FW SU BYP VLV IF one RFPT is in service, THEN SELECT OR ENSURE in SPEED AUTO with discharge pressure approximately 250 psid above reactor pressure.

OPEN / VERIFY OPEN RFP A(B) DISCH VLV N21

-F014A(B) for at least one pump.

ADJUST N21-F513, RX WTR LVL SU CONT valve, as necessary in MANUAL OR AUTO to maintain desired Reactor level. N21

-F040 AND/OR N21-F009A(B) May be OPEN/CLOSED as necessary to augment flo

w.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 15 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

7 (cont.) Event

Description:

Reactor Instrument Line Failure (cont.) TIME Position Applicant's Actions or Behavior CRS Directs the BOP to Initiate each of the following which should have initiated but did not: Isolations ECCS initiation Emergency Diesel Generator BOP Verifies the following:

ECCS initiation (All on P601) o HPCS pump running with injection valve E22

-F004 open o LPCS pump running with injection valve E21

-F005 closed o RHR 'B' pump running with injection valve E12

- F042B closed Reports ECCS status to CRS:

o HPCS pump running with E22

-F004 breaker tripped no indication on valve o LPCS pump not running, E21

-F005 is closed. Recognize and report Logic Power Failure.

o RHR 'B' pump running with injection valve closed.

o RHR 'A' and 'C' not available.

Auxiliary Building / Containment / Drywell isolations (All on P870)

Reports isolation has gone to completion using the isolation status board as a quick reference and verifying the following alarms o P870 -9A-A4 & B3 o P870 -3A-A4 & B3 Emergency Diesel Generator start with cooling water Ensure Diesel running indication Ensure SSW A/B/C is aligned to provide cooling water to running diesel generators.

o SSW pump running A/B/C o SSW Discharge Valves are open P41

-F001A/B o SSW Supply to Diesel Generators Valves are open P41

-F018A/B o SSW Return Valves to Basin are open P41

-F005A/B, P41

-F011. Reports to CRS Emergency Diesel Generators start with cooling water Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 16 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

7 (cont.) Event

Description:

Reactor Instrument Line Failure (cont.) TIME Position Applicant's Actions or Behavior CRS Directs ATC to maintain Reactor Water level with a band of +11.4" to +53.5" ATC Using Startup level control valve supplied by Condensate and Feedwater in manual maintains level within band of +11.4" to +53.5"

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 17 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

8 Event

Description:

Logic Power Failure to LPCS/RHR A Logic TIME Position Applicant's Actions or Behavior BOP Recognize and report LPCS/RHRA Logic power failure from the following indications:

P601-21A-H8, LPCS OOSVC alarm P601-21B LPCS status light, LPCSLOGIC PWR FAIL LPCP PUMP handswitch has Green and Amber lights energized (pump not running).

P601-21B, LPCS/RHR A INIT light not energized.

Refers to ARI for P601

-21A-H8 for directions with logic power failure:

IF LPCS Power Failure status light is illuminated, THEN the following manual start of LPCS are effected as follows:

4.6.1 RHR A Can be manually started from P601 AND RSP. 4.6.2 Manual opening of E12

-F042A is from RSP only.

4.6.3 RHR A May be placed in Suppression Pool Cooling from P601 AND RSP with manual alignment of SSW A.

4.6.4 INITIATE

RCIC with ARM AND DEPRESS pushbuttons (RCIC Will NOT Auto Start).

4.6.5 E21-F005 CANNOT be opened manually OR automatically from P601 (Must be opened locally).

4.6.6 Containment

spray CANNOT be initiated automatically OR locally. 4.6.7 NO DIV I LOCA signal is received by LSS, D/G 11, ADS A, CGCS A, SSW A, OR RCIC. 4.6.8 E12-F064A will NOT open OR close automatically.

CRS Directs BOP to perform the following:

Manually start LPCS pump and ensure min flow valve opens.

Dispatch operators to be on standby to manually open E21

-F005 injection valve. Do NOT open before 476 psig reactor pressure.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 18 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

8 (cont.) Event

Description:

Logic Power Failure to LPCS/RHR A Logic (cont.)

TIME Position Applicant's Actions or Behavior BOP When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig.

Manually starts LPCS pump using handswitch on P601 panel Dispatch operators to standby E21

-F005, LPCS injection valve, be prepared to open manually upon request.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 19 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

9 Event

Description:

Division 2 ECCS High Drywell Pressure Fail to Initiate TIME Position Applicant's Actions or Behavior BOP Recognizes and reports a Division 2 ECCS (RHR 'B' and 'C')

failure to initiate on High Drywell pressure.

Per EN-OP-120, BOP will arm and depress the LPCS/RHR A MAN INIT pushbutton on P601

-21B Verifies the following:

RHR B pump starts and runs on minimum flow.

Division 2 EDG starts with cooling water When ECCS fails to initiate, the crew manually initiates ECCS prior to reactor pressure going below 300 psig.

CRS Directs Division 2 ECCS to be manually initiated.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 20 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

10 Event

Description:

False Hotwell low level signal TIME Position Applicant's Actions or Behavior ATC Recognizes all Condensate Pumps trip.

(This will also cause all condensate booster pumps to trip and Feed pumps to trip)

Determines trip is from a false Low Condenser Level by observing P680-2A-E9, CNDSR HTWL LVL LO.

Uses ARI P680

-2A-E9 to determine that removal of relay N19 63X

-1/N105 will defeat the Hotwell low level trip on the Condensate system

o If desired by Shift Supervision, REMOVE relay N19 63X

-1/N105 will defeat the Hotwell low level trips. (1H13

-P849 Bay C, third row of relays from the top, sixth relay from the left).

Booth Do not defeat low Hotwell level trip until Emergency Depressurization has occurred. If requested to remove relay and after ED has occurred delete malfunctions with Event 8 CRS Enters Alternate Level Control leg of EP

-2 Directs to Inhibit ADS Verifies injection systems Calls for Table 2 systems to be lined up.

Directs ATC to monitor reactor water level as a critical parameter with frequent updates.

Directs for E22

-F004 to be manually opened BOP Inhibits ADS on P601 by taking ADS A MANUAL INHIBIT and ADS B MANUAL INHIBIT handswitches to the INHIBIT position and verifying the following indication:

P601-18A-H2, ADS/SRV A OOSVC alarm P601-19A-H2, ADS/SRV B OOSVC alarm White status light above each handswitch

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 21 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

10 (cont.) Event

Description:

False Hotwell low level signal (cont.) TIME Position Applicant's Actions or Behavior BOP Provides ECCS update and injection systems using ECCS status hard card.

Feedwater Currently unavailable HPCS pump running F004 Injection valve has no power LPCS Injection valve local manual operation only RHR A Unavailable due to leak RHR B pump running RHR C Unavailable due to loss of Jockey pump Dispatches operators to manually open E22

-F004, HPCS Injection valve locally. Booth If ask to manually open E22

-F004, wait 3 minutes and report attempting to open. ATC Monitors Reactor Water level, giving frequent updates Notifies CRS when

-160" Wide Range is met.

CRS At <-160" Wide range but before level reaches

-191" Fuel Zone an Emergency Depressurization is required.

Enters Emergency Depressurization leg of EP

-2 Verifies Suppression Pool level is above 10.5 ft.

Directs 8 ADS/SRVs opened.

Open at least 7 SRVs when RPV water level is between

-160" and -190".

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 22 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

10 (cont.) Event

Description:

False Hotwell low level signal (cont.) TIME Position Applicant's Actions or Behavior ATC/BOP Opens 8 ADS.SRVs on P601 by taking the following handswitches to the OPEN position:

B21-F041K B21-F047L B21-F041F B21-F047A B21-F051C B21-F051A B21-F041C B21-F051B Open at least 7 SRVs when RPV water level is between -160" and -190". Booth If requested to remove relay N19 63X

-1/N105 to bypass Lo Hotwell level trip on the condensate system, DELETE the malfunction in event 10 and report relay is removed.

If requested to manually open E22

-F004, HPCS Injection valve, report valve will not open manually CRS Directs to monitor for injection from Low ECCS systems If requested to remove relay N19 63X

-1/N105 to bypass Lo Hotwell level trip on the condensate system direct ATC to restart Condensate system and inject.

BOP Verify RHR 'B' injection valve E12-F04 2 B open s at 476 psig Reactor Pressure by the following P601 indication:

P601-17A-C3, LPCI B/C INJ VLV RPV PRESS LO alarm Red indication for valve E12

-F042B handswitch At approximately 300 psig reactor pressure, RHR PMP B DISCH FLO indication, E12

-R603B, is indicating injection flow.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 23 of 23 Revision 0 9/21/2015 Op-Test No: NRC LOT 2015 Scenario No:

2 Event No:

10 (cont.) Event

Description:

False Hotwell low level signal (cont.) TIME Position Applicant's Actions or Behavior Booth If requested to manually open E21

-F005, LPCS Injection valve, report valve will not open. ATC If requested to remove relay N19 63X

-1/N105 to bypass Lo Hotwell level trip on the condensate system, restart the condensate system.

Restart at least 2 Condensate pumps o Depress the START pushbutton for the desired pump Restart at least 2 Condensate Booster pumps o Depress the START pushbutton for the desired pump CRS Direct to control RPV water level within a band of

-30" to +50" Wide Range.

After Emergency Depressurization, restore and maintain RPV level above

-191" using available injection systems prior to exiting EP

-2. BOP/ATC After Emergency Depressurization, restore and maintain RPV level above

-191" using available injection systems prior to exiting EP

-2. Using RHR 'B' and if requested the following systems:

Condensate Maintain RPV water level within band

-30" to +50" Wide Range.

(Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 2 Page 24 of 23 Revision 0 9/21/2015 TERMINATION Once reactor water level is being controlled in band or as directed by Lead Evaluator:

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Revision 0 9/21/2015 Give this page to the CRS ` Crew Turnover:

Turnover the following conditions:

Power 100% M OC EOOS GREEN Suppression Pool Temperature is 85

°F RCIC is tagged for maintenance. LCO 3.5.3 Condition A has been entered, HPCS is verified OPERABLE.

SSW A is operating per 04 03-P41-1, which is complete up to step 7.7, in preparation for weekly chemical addition Planned Evolutions this shift:

Place RHR 'A' in Suppression Pool Cooling mode

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 1 of 7 Revision 0 9/22/2015 Facility:

Grand Gulf Nuclear Station Scenario No.: 3 Op-Test No.:

NRC LOT 201 5 Examiners: ____________________________ Operators:

_____________________________

____________________________

_____________________________

____________________________

_____________________________

Objectives:

To evaluate the candidates' ability to operate the facility in response to the following evolutions:

1. Component Cooling Water Pump 'A' trip with Failure of Standby pump to Auto Start

. 2. MCC 17B01 Trip, HPCS System INOP

3. IRM Channel 'A' fails upscale
4. Loss of Power to ESF 15AA, with Diesel Generator restoring Bus

. 5. IRM Channel 'E' fails downscale

6. Condensate Booster Pump 'A' Trip

. 7. Component Cooling Water Pump 'B' and 'C' trip 8. Mode Switch Failure to Scram

. 9. Loss of Offsite Power with 15AA lockout

10. Division 2 Diesel Generator Fails to Auto Energize 16AB

. Initial Conditions:

Reactor startup in progress.

Reactor pressure is 400 psig Reactor power is 4% Inoperable Equipment:

None Turnover: A reactor startup is in progress.

Step 8 3 of Control Rod Movement Sequence is complete SJAE 'B' is in warm up 04 N62-1 step 4.2.2r Step 3 2 of Attachment XV in 03 01-1 The Condensate system is lined up as follows:

CFFF is in service Precoat Filters are not in service 4 Deepbed demins are in service Preps are being made to start the first Reactor Feedwater Pump Severe Weather is in the area, Tornado Watch is in affect Scenario Notes:

This scenario is a modified version of the 201 4 NRC Exam Scenario 5 (spare scenario, not used). Validation Time (60-90 min): 70 min Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 2 of 7 Revision 0 9/22/2015 Event No. Malf. No. Event Type f Event Description 1 p42151a C (BOP) A (CREW) Component Cooling Water Pump 'A' Trip with Failure of Standby Pump to Auto Start (05-1-02-V-1, Loss of Component Cooling Water ONEP, EN

-OP-120, 02-S-01-43) 2 R21142DD TS (CRS) MCC 17B01 Trip, HPCS System INOP (Tech Specs 3.5.1, 3.8.1, Loss of AC Power ONEP, 05 02-I-4) 3* c51004a C(ATC) TS (CRS) IRM Channel 'A' fails upscale (ARI P680-5A-A8, Tech Specs 3.3.1.1 and 3.3.2.1 potential) 4 DI_1R21M606A C (BOP) A (CREW) Loss of Power to ESF Bus 15AA with Diesel Restoring Bus (Loss of AC Power, 05 02-I-4, Loss of Instrument Air, 05 02-V-9 and Automatic Isolations, 05 02-III-5 ONEPs) 5 c5100 5 e TS (CRS) IRM Channel 'E' fails downscale (Tech Specs 3.3.1.1 and 3.3.2.1) 6 fw118a C (ATC) A (CREW) Condensate Booster Pump Trip (05-1-02-V-7, Feedwater System Malfunctions ONEP) 7 p42151b p42151c M (CREW) Component Cooling Water pumps 'B' and 'C' trip (05-1-02-V-1, Loss of Component Cooling Water , 05-1-02-I-1, Reactor Scram; 05 02-I-2, Turbine and Generator Trips ONEP, EP-2) 8 DI_1C71M602 C (ATC) Mode Switch Failure (EN-OP-115) 9 r21135 r21139e M (CREW) Loss of Offsite Power with ESF bus 15AA lockout (Loss of AC Power ONEP, 05 02-I-4) 10 n41142b C (BOP) Division 2 EDG fails to auto energize ESF Bus 16AB (Loss of AC Power ONEP, 05 02-I-4) f (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec

  • Repeated task from last 2 NRC exams.

Quantitative Attributes Table Normal Events 0 E OP Contingency Procedures Used 1 Total Malfunctions 8 Simulator Run Time 60 Malfunctions After EOP Entry 2 EOP Run Time 30 Abnormal Events 6 Critical Tasks 2 Major Transients 2 Instrument/Component Failures 6 E O Ps Used (Requiring measurable action) 1 Reactivity Manipulations 0

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 3 of 7 Revision 0 9/22/2015 SCENARIO ACTIVITIES:

Component Cooling Water pump 'A' trip A. After turnover and/or at the direction of the lead evaluator, trigger Event 1 to cause CCW pump 'A' to Trip

. B. Standby CCW pump '

B' will fail to auto start

. C. The crew (BOP) will take the actions per EN-OP-120 and 05-1-02-V-1, Loss of Component Cooling Water ONEP and manually start the standby pump

. D. The CRS will enter 05-1-02-V-1, Loss of Component Cooling Water ONEP

. MCC 17B01 trip

A. After immediate, subsequent actions of all associated ONEPs have been addressed and at the direction of the lead evaluator, trigger Event 2 to cause a MCC 17B01 trip. B. The crew will recognize loss of 17B01 due to loss of power to HPCS MOVs and HPCS service water system.

C. The CRS will enter Loss of AC Power ONEP, and determine that TS 3.8.7Condition D1 and 3.5.1 Condition B applies. IRM Channel 'A' fails upscale A. After Tech Specs have been addressed and at the direction of the lead evaluator, trigger Event 3 to cause IRM channel 'A' to fail full upscale.

B. The crew will recognize a division 1 half scram and rod block.

C. The crew will perform action per ARI by bypassing the IRM channel and resetting the half scram condition.

D. The CRS will direct the bypassing of the IRM channel and the resetting of the half scram. E. The CRS will determine that NO Tech Specs are entered at this time but will refer to Tech Specs 3.3.1.1 and 3.3.2.1. Three channels are required.

CRS may enter a potential LCO.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 4 of 7 Revision 0 9/22/2015 Loss of Power to ESF bus 15AA with EDG Restoring Power:

A. When Tech Specs have been addressed and any briefs are complete, at the Lead Evaluator's discretion, trigger Event 4 to cause incoming feeder breaker 152

-15 14 to trip removing power to 15AA.

B. The crew will respond using 0 5-1-02-I-4, Loss of AC Power ONEP.

C. The BOP will verify EDG powers bus 15AA and restore Instrument Air to the Containment by opening P53

-F00 1 on P870 using 05 02-V-9, Loss of Instrument Air ONEP. (P53

-F00 1 fails closed on loss of power and must be manually re-opened) D. The CRS should also enter 05 02-III-5, Automatic Isolations ONEP and 05-1-02-III-1, Inadequate Decay Heat Removal ONEP (due to the loss of Fuel Pool Cooling and Cleanup)

. E. The CRS will determine that Tech Spec 6.4.1, Continuous conductivity monitoring applies. IRM Channel 'E' fails downscale A. After Tech Specs have been addressed, Immediate and subsequent actions of ONEPs and at the direction of the lead evaluator, trigger Event 5 to cause IRM channel 'E' to fail downscale. B. The crew will recognize 'E' IRM in the downscale indication with a control rod block

. C. The crew will perform action per ARI, but cannot bypass the IRM channel due to one is already bypassed in that division

. D. The CRS will determine that Tech Specs 3.3.1.1 and 3.3.2.1 apply. Condensate Booster Pump 'A' trip A. After all Tech Spec actions has been address and/or at the direction of the lead evaluator, trigger Event 6 to cause Condensate Booster Pump 'A' to trip.

B. The crew (ATC) will take action per 05 02-V-7, Feedwater System Malfunctions ONEP and manually start the 'B' or 'C' Condensate Booster Pump

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 5 of 7 Revision 0 9/22/2015 Loss of Component Cooling Water Pumps 'B' and 'C' A. After immediate, subsequent actions of all associated ONEPs have been addressed and at the direction of the lead evaluator, trigger Event 7 to cause CCW pumps 'B' and 'C' to trip.

B. The crew (ATC) will recognize the complete loss of CCW system, per 05 02-V-1, Loss of Component Cooling Water ONEP immediate action place the Mode switch to SHUT DOWN and trip Reactor Recirc Pumps

. Mode Switch Failure A. When the ATC places the Mode Switch to SHUTDOWN the mode switch will fail in STARTUP (Event 8), no scram signal will be present.

B. The ATC will manually scram the reactor by arming and depressing the 4 RPS Manual Scram Pushbuttons per EN-OP-115. C. The Crew will enter Scram and Turbine and Generator Trips ONEPs Loss of All Offsite Power with bus 15AA lockout

A. Two minutes after the mode switch is taken to shutdown all offsite power will be lost (Event 9).

B. The Crew will recognize bus 15AA will be locked out and remain de

-energized.

C. The CRS will enter EP

-2, and call for RCIC to be started to maintain level.

D. A small Recirc loop leak will occur.

Division 2 EDG fails to Auto Energize ESF Bus 16AB

. A. The BOP will recognize Failure of Division 2 EDG to auto energize bus 16AB (Event 1 0). B. The BOP will recognize Division 2 EDG is running and manually close the EDG feeder breaker to 16AB 152

-1608 from P864

. C. The BOP will verify the EDG powers the bus and recognize that Feeder breaker to 16BB3 is not closed by Green light on handswitch and alarm on P864

-2A-E3 D. The BOP will verify SSW B is supplying cooling water

. E. Dispatch operator and/or electrical to investigate loss of 16BB3.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 6 of 7 Revision 0 9/22/2015 F. 16BB3 feeds 16B31 MCC that supplies power to RHR 'B' valves required for injection.

G. Recognizes that RHR 'C' pump trip.

H. Dispatch operator and/or electrical to investigate RHR pump 'C' trip.

I. After 5 minutes or when water level reaches

-100 inches notify CRS that problem with 16BB3 has been found and waiting for control room to re

-energize also RHR 'C' pump problem has been corrected and ready for restart.

Termination:

A. Once RPV is restored within band or as directed by Lead Evaluator

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Appendix D Scenario Outline Form ES-D-1 NRC 2015 Scenario 3 Page 7 of 7 Revision 0 9/22/2015 Critical Task Number Description Bas i s 1 Restore Instrument Air to the Containment prior to two or more control rods drifting.

When control rods to drift this could cause uneven flux distribution throughout the core which in turn could have detrimental effects reducing the margin of reactor safety limits.

2 When Reactor Mode Switch fails, manually insert a scram by depressing the RPS MANUAL SCRAM PUSHBUTTONS or Manual initiate ATWS/ARI prior to installing Attachment 21, "De

-energize scram solenoids.

Ensuring a reactor scram prevents entry into EP-2A (ATWS) procedure that would cause the crew to take compensatory actions that would complicate the event mitigation strategy.

3 Restore RHR B and/or C injection prior to level reaching TAF.

Maintaining adequate core cooling.

  • Critical Task (As defined in NUREG 1021 Appendix D)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 1 of 20 Revision 0 9/22/2015 Simulator Setup:

A. Initialization

1. Log off all simulator PDS and SPDS computers (PDS and SPDS must come up after the simulator load for proper operation).
2. Startup the simulator using Simulator Instructor's Job Aid section 7.3.
3. Open Schedule.exe and Director.exe by clicking on the Icon in the Thunder Bar.
4. Set the Simulator to IC-10 3 and perform switch check (Using Quick Reset in Director).
5. Click on "Open" in the Schedule window and Open Schedule File "201 5 NRC Scenario 3.sch" (in the Schedule Directory)
6. In Schedule window, click on the "Stopped" red block. The red block will change to a green arrow and indicate the scenario is active ("Running"). Note: Prior to running the Schedule File, ensure no Event Files are Open.

If an existing Event File is Open prior to running the Schedule File, then any associated Event Files will not automatically load.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 2 of 20 Revision 0 9/22/2015 7. Click the Summary tab in the Director window. Verify the schedule files are loaded and opened per Section B below. (Note: Any actions in the schedule file without a specific time will not load into the director until triggered.)

8. Take the simulator out of freeze.
9. Log on to all simulator PDS and SPDS computers.
10. Verify or perform the following:

IC-10 3 APRM's are selected to IRM with NO digital readout.

Ensure the MOC rod movement sequence available at the P680.

Advance all chart recorders and ensure all pens inking properly.

Clear any graphs and trends off of SPDS.

Marked up copy of 03 01-1 Att. XV to step 30, Cold Shutdown to Generator Carrying Minimum Load Reactor Heatup and Pressurization, is placed on CRS desk.

Marked up copy of Control Rod Movement Sequence sheet completed through step 83.

11. Run through any alarms and ensure alarms are on. (Note: On T

-Rex, to verify alarms are ON, the indicator will indicate "Alarms On").

12. Place the simulator in Freeze.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 3 of 20 Revision 0 9/22/2015 B. File loaded verification:

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 4 of 20 Revision 0 9/22/2015 Crew Turnover:

A. Assign the candidates crew positions.

B. Turnover the following conditions:

Power 4% M OC EOOS GREEN Planned Evolutions this shift:

Continue with Plant Startup Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

C. Allow the crew to perform pre-shift brief and review procedures for planned evolutions.

D. Bring the crew into the Simulator, place the simulator is in RUN.

E. Allow the crew to walk down panels.

F. When the crew assumes the shift begin Scenario Activities.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 5 of 20 Revision 0 9/22/2015 SCENARIO ACTIVITIES:

Start SBT report and any other required recording devices.

Emergency Classification:

Site Area Emergency on SS6. Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

1 Event

Description:

Component Cooling Water Pump 'A' Trip with Failure of Standby Pump to Auto Start TIME Position Applicant's Actions or Behavior BOP Recognizes and reports trip of CCW pump 'A'.

P870-5A-B1, C1 & C2 P870-8A-E1, and B1 P870-2A-B1 Report failure of standby pump to start and manually starts standby pump '

B' per EN-OP-115 and EN

-OP-120 Verifies CCW header pressure returns to normal using P870 CCW Header pressure indicator P42-R600. ATC Recognizes and reports the following alarms:

P680-3A, A5, D5, A11, &

D11, CRS Enters Loss of CCW ONEP, 05 01-V-1 Directs the BOP to start standby pump

. Monitor CCW system parameters May enter Inadequate Decay Heat Removal ONEP for loss of cooling to Fuel Pool Cooling and Cleanup.

Booth If directed to investigate CCW pump 'A', wait 3 minutes and report locally motor is hot to the touch.

If directed to investigate pump breaker 52

-11506, wait 3 minutes and report overcurrent trip with lockout.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 6 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

1 (cont.) Event

Description:

Component Cooling Water Pump 'A' Trip with Failure of Standby Pump to Auto Start (cont.)

CRS Directs BOP to restore cooling water to Fuel Pool Cooling and Cleanup Heat exchangers.

BOP Performs the following to restore cooling to the Fuel Pool Cooling and Cleanup Heat Exchangers:

a. To place Both heat exchangers in service, PERFORM the following (Initial Condition: CCW Cooling to Both FPHXs is OOSVC):

(1) OPEN OR VERIFY OPEN F028A AND F032A, FPHX A Inlet AND Outlet valves, USING their respective handswitches CLG WTR INL TO FPHX A [2C] AND CLG WTR OUTL FM FPHX A [2C]. (2) OPEN F105 AND F205 by SIMULTANEOUSLY HOLDI NG Both of their respective handswitches, CCW SPLY TO FPHX A/B [2C] AND CCW RTN FM FP HX A/B [2C], to the OPEN position until alarm Clears (1H13

-P870 Section 2A Grid B

-1). (3) OPEN F203 USING CCW INBD INL TO FPHX B [2C] handswitch.

(4) OPEN F028B USING CCW OUTBD INL TO FPHX B [8C] handswitch.

(5) OPEN F032B USING CCW INBD INL FM FPHX B [8C] handswitch.

(6) OPEN F204 USING CCW OTBD OUTL FM FPHX B [2C] handswitch.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 7 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

2 Event

Description:

MCC 17B01 Trip TIME Position Applicant's Actions or Behavior BOP Recognizes and reports MCC 17B01 Trip by the following:

P601-16A-F1, G1, E4 alarms HPCS system indication P870-5A-E2, F1, F2, G1 alarms CRS Enters Loss of AC Power ONEP, 05 02-I-4 Recognizes HPCS system is INOP Directs Division 3 Diesel Generator to be placed in MAINTENANCE due to loss of cooling water pump.

Directs HPCS pump breaker 152

-1702 be racked out (down) due to loss of jockey pump.

Enters Tech Specs

3.8.7 Condition

D1

3.7.2 Condition

A1

3.5.1 Condition

B Booth If requested to investigate loss of 17B01, wait 3 minutes and report feeder breaker 152

-1703 is tripped with an 86 lockout device

. If requested to place Div 3 D/G in maintenance, wait 3 minutes and trigger event 30 , notify control room that Division 3 D/G is in Maintenance.

If requested to rackout HPCS pumps breaker 152-1702, wait 3 minutes and trigger event 28 , notify control room that the HPCS pump breaker 152

-1702 is racked out.

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 8 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

3 Event

Description:

IRM Channel 'A' Fails upscale TIME Position Applicant's Actions or Behavior ATC Recognize and report division 1 half scram and indication of IRM 'A' full scale.

Receives the following P680 alarms: RPS CH A IRM UPSC TRIP INOP (5A-A8) IRM UPSC ALM (7A-A9) CONT ROD WITHDRAWL BLOCK (4A2-C5) HCU TROUBLE (4A2

-D4) RX SCRAM TRIP (7A-A2) NEUTRON MON SYS TRIP (7A-B3) Recognizes and reports the following:

Division 1 half scram.

Control Rod Block IRM channel '

A' indicating full upscale.

CRS Directs ATC to bypass IRM 'A' and reset division 1 half scram per ARI P680

-5A-A8 Refers to Tech Specs 3.3.1.1 and 3.3.2.1 and determine NO Tech Specs are in affect at this time, however, a potential LCO could be used.

Contacts I&C for investigation on IRM 'A'.

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3 Event No:

3 (cont) Event

Description:

IRM Channel 'A' Fails upscale (cont.)

TIME Position Applicant's Actions or Behavior ATC Bypasses IRM 'A' using ARI P680

-5A-A8: 3.2 Observe the IRM recorders on 1H13

-P680. If IRM A or IRM E are not upscale, the alarm is due to inoperative equipment. Perform the following:

3.2.1 Bypass

the affected IRM channel until the cause of the inoperative condition is corrected.

3.2.2 Check

the module on 1H13

-P669 to help determine the cause of the INOP.

Reset the half scram using ARI P680

-5A-A8: 3.4 Reset the Half

-Scram by momentarily placing the RPS DIV 1 SCRAM RESET switch to the RESET position.

Verifies the following alarms are clear:

RPS CH A IRM UPSC TRIP INOP (5A

-A8) IRM UPSC ALM (7A

-A9) CONT ROD WITHDRAWL BLOCK (4A2

-C5) HCU TROUBLE (4A2

-D4) RX SCRAM TRIP (7A

-A2) NEUTRON MON SYS TRIP (7A

-B3) Booth If requested to investigate IRM 'A', wait 5 minutes and report unknown reason and work order is required for more investigation.

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3 Event No:

4 Event

Description:

Loss of ESF Bus 15AA with Diesel Generator Restoring power TIME Position Applicant's Actions or Behavior BOP Recognizes and reports loss of 15AA.

Loss of indication on all 15AA components Loss of lighting inside the control room Multiple alarms on P864

-1A Within 10 seconds recognizes and reports Division 1 EDG has started and is supplying power to the 15AA bus.

Component indication returns Control room lighting returns to norma l Breaker 152

-1508, Feeder breaker from EDG Division 1, is closed Verifies SSW 'A' is supplying cooling water to EDG Division 1 SSW Pump 'A' is running P41-F001A, pump discharge OPEN P41-F005A, SSW system return to basin, OPEN P41-F018A, SSW supply to EDG Division 1, OPEN Recognize and report Division 1 Containment / Drywell isolation.

Verifies P53

-F001 closed on loss of power Re-opens P53-F001 per 05-1-02-V-9, Immediate Operator Actions o Determine cause for loss of Instrument Air and Attempt to restore. Restore Instrument Air to the Containment prior to two or more control rods drifting.

CRS Directs the BOP to verify power is restored to 15AA.

Directs the BOP to restore instrument air to the containment / Drywell.

Directs ATC to monitor for Control Rod Drifts Enters the following ONEPs:

Loss of AC Power, 05 02-I-4 Automatic Isolations, 05 02-III-5 Loss of Instrument Air, 05 02-V-9 Inadequate Decay Heat Removal, 05 02-III-1 Dispatch personnel to determine reason for loss of 15AA (Critical TASK in BOLD)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 11 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

4 (cont.) Event

Description:

Loss of ESF Bus 15AA with Diesel Generator Restoring power (cont.) TIME Position Applicant's Actions or Behavior Booth If requested to investigate loss of 15AA, wait 3 minutes and report breaker 152

-151 4 has tripped.

CRS Directs BOP to initiate SBGT per Loss of AC Power ONEP:

3.1.5 IF Aux building isolation dampers closed on loss of power THEN DEPRESS SGTS DIV 1(2) MAN INIT pushbuttons (A AND C for Division 1, B AND D for Division 2).

Directs BOP to restore systems from isolation per Automatic Isolations ONEP step 3.5.3, and Attachment II BOP Manually initiates SBGT by performing the following:

3.1.5 IF Aux building isolation dampers closed on loss of power THEN DEPRESS SGTS DIV 1(2) MAN INIT pushbuttons (A AND C for Division 1, B AND D for Division 2).

CRS Directs BOP to perform the following from the Loss of AC Power ONEP

Reset NSSSS isolation logic Open/check open P41

-F239 and F240 BOP Performs the following per loss of AC Power ONEP

3.1.8 On 1H13-P601 panel, RESET respective DIV 1 (2) NSSSS isolation logic IF possible. Depresses the NSSSS INBD ISOL RESET and NSSSS OTBD ISOL RESET pushbuttons.

Verifies alarm P601

-E4, MSIV DR VLV TRIP INIT, resets.

3.1.9 IF power was lost to Bus 15AA, THEN OPEN/CHECK OPEN the following valves on P870-1C: a. 1P41-F239 b. 1P41-F240 Booth If requested to reset RCIS, wait 3 minutes and trigger event 29, notify control room that RCIS is reset.

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3 Event No:

5 Event

Description:

IRM 'E' Fails Downscale TIME Position Applicant's Actions or Behavior ATC Recognizes and reports IRM 'E' fails downscale by the following P680 alarms and indication:

4A2-C5, CONT ROD WITHDRAWAL BLOCK 7A-B9, IRM DNSC IRM 'E' indicator full downscale 7C2, DOWNSCALE status light.

CRS Determines the following Tech Spec: 3.3.1.1 Condition A1 TRM 3.3.2.1 Directs I&C to investigate IRM 'E' Booth If requested to investigate IRM 'E', wait 3 minutes and report cannot determine problem will require a work order.

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3 Event No:

6 Event

Description:

Condensate Booster Pump 'A' Trip TIME Position Applicant's Actions or Behavior ATC Recognizes and reports Condensate Booster Pump

'A'[ Trip Starts available Condensate Booster pump per ONEP 05 02-V-7, Feedwater Malfunctions ONEP 2.2 IF Reactor water level is lowering OR a Condensate pump, Condensate Booster pump OR Heater Drain pump has tripped, THEN PERFORM the following as required to maintain Reactor water level : 2.2.1 REDUCE Reactor Core Flow to 70 Mlbm/hr with Reactor Recirculation flow, MAINTAINING within power to flow limitations.

2.2.2 INITIATE

RCIC. 2.2.3 START standby Condensate, Condensate Booster, AND Reactor Feed Pumps as needed.

Depresses START pushbutton for Condensate Booster Pump 'B' or 'C'.

Verifies Reactor water level rising and being maintained by Startup Level Control Valve.

CRS Enters 05-1-02-V-7, Feedwater System Malfunctions ONEP.

Directs ATC to start standby Condensate Booster Pump Booth If dispatched by control room, wait 3 minutes and report problem unknown, can't be repaired without work order.

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3 Event No:

7 & 8 Event

Description:

Component Cooling Water Pumps 'B' and 'C' trip

/ Mode Switch Failure BOP Recognizes and reports Total Loss of CCW. ATC Performs the following per Loss of CCW ONEP immediate Operator Actions:

2.1 If a complete loss of CCW occurs, Then perform the following:

2.1.1 Manually

SCRAM the reactor.

2.1.2 Manually

TRIP Reactor Recirc Pumps.

Places the Mode switch to SHUTDOWN Recognizes and reports MODE switch failure.

Arms and Depresses 4 RPS Manual Scram pushbuttons When Reactor Mode Switch fails, manually insert a scram by depressing the RPS MANUAL SCRAM PUSHBUTTONS or Manual initiate ATWS/ARI prior to installing Attachment 21, "De

-energize scram solenoids.

Trips the Reactor Recirc Pumps on the P680 by depressing CB2 TRIP pushbutton or depressing the STOP LOCK push button on CB5 CRS Enters Loss of CCW ONEP (Total Loss)

Directs ATC to manually scram the reactor and trip Reactor Recirc Pumps

. Enters Turbine and Generator Trip, 05 02-I-2, Reactor Scram, 05 02-I-1, ONEPs and EP

-2 ATC Performs immediate operator actions for Turbine and Generator Trip, 05 02-I-2, and Reactor Scram, 05 02-I-1, ONEPs Place / Verify the Mode SW to SHUTDOWN as directed.

Provides a scram report:

o Reactor Mode SW in SHUTDOWN.

o All Rods are Inserted. o Reactor power is 0%. o Reactor water level and trend.

(Critical TASK in BOLD)

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3 Event No:

7 & 8 (cont.)

Event

Description:

Component Cooling Water Pumps 'B' and 'C' trip / Mode Switch Failure (cont.) CRS Directs ATC to maintain level control with a level band of

+11.4" to +53.5" Narrow Range ATC Maintains reactor water level with startup level control and the Condensate system. (already on the startup level control valve)

Appendix D Required Operator Actions Form ES-D-2 NRC 2015 Scenario 3 Page 16 of 20 Revision 0 9/22/2015 Op-Test No: NRC LOT 2015 Scenario No:

3 Event No:

9/10 Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB CREW Recognize and report loss of offsite power.

CRS Enters Loss of AC Power ONEP, 05 02-I-4 BOP Recognize ESF buses 15AA and 16AB are not energized by their respective Diesel Generator.

Per Loss of AC Power ONEP, 05 02-I-4, immediate operator actions

2.1 ENERGIZE

affected bus through an alternate feeder breaker OR its respective diesel generator.

Attempts to close Diesel Generator feeder breaker to 15AA, 152

-1508. Recognize and reports 152-1508 did not close and ESF bus 15AA is lockout and will not energize Attempts to close Diesel Generator feeder breaker to 16AB, 152-1608. Recognize and reports 152

-1608 closes and 16AB is energized.

Recognizes and reports LCC 16BB3 did not re

-energize. CRS Directs plant operator and/or electrical to investigate loss of 16BB3.

Directs ATC to maintain reactor water level using RCIC at a band of 11.4" to 53.5" Booth If requested to investigate loss of 16BB3 LCC, wait 3 minutes and report as plant operator or electrical that feeder breaker 52

-16301 has tripped and are investigating the cause.

ATC Monitors Reactor water level and initiates RCIC when required to maintain reactor water level in band by performing the following:

1. ARM AND DEPRESS RCIC MAN INIT pushbuttons
2. VERIFY SSW A is running with adequate flow path.

(SSW A in unavailable due to loss of 15AA)

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3 Event No:

9/10 (cont.) Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.) ATC/BOP Recognizes and reports Drywell pressure rising and reactor water level lowering. When Drywell pressure reaches 1.39 psig, verifies and reports ECCS initiations.

(Division 2 ECCS is the only division available due to Div 1 and 3 has no power) Recognizes and reports the following:

RHR 'C' pump has tripped RHR 'B' pump is running, however multiple MOVs have no power due to loss of 16BB3.

CRS Re-enters EP-2 and enters EP-3 due to drywell pressure.

Directs to verify:

Initiations Isolations Emergency Diesel Generator start.

Request ECCS status report.

Directs plant operator and/or electrical to investigate RHR 'C' trip.

BOP Verifies the following:

ECCS initiation Auxiliary Building / Containment / Drywell isolations Emergency Diesel Generator start with cooling water Reports to CRS Booth If requested to investigate RHR 'C' pump trip, wait 3 minutes and report as plant operator and / or electrical that breaker 152-1609 has tripped and are investigating the cause.

ATC Recognizes and reports reactor water level lowering with RCIC injection.

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3 Event No:

9/10 (cont.)

Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.) CRS Enters Alternate Level Control leg of EP

-2 Directs to Inhibit ADS Calls for Table 2 systems to be lined up.

o Attachment 26 through any or all of the following:

LPCS, HPCS, and RHR 'A' Directs ATC to monitor reactor water level as a critical parameter with frequent updates.

ATC Reports lowering level trend

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3 Event No:

9/10 (cont.)

Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.) TIME Position Applicant's Actions or Behavior Booth If crew has requested electrical to investigate breaker 52

-16301, when reactor water level reaches -100" wide range, contact control room with the following information:

Delete malfunction for 16BB3 trip 52-16301 feeder breaker to 16BB3 has been repaired Ready for the control room to attempt to close the breaker.

Restore RHR B and/or C injection prior to level reaching TAF CRS Direct s BOP to close 52

-16301 breaker to energize LCC 16BB3.

BOP Closes breaker 52

-16301 on panel P864

-2C. Verifies breaker closes and components gain indication of power.

CRS Directs ATC to verify injection from RHR 'B'. ATC Verifies and reports E12

-F042B, RHR Injection valve, auto opens or manually open the valve.

Verifies and reports injection flow on P601

-17B using E12

-R603B Booth If crew has requested electrical to investigate RHR 'C' pump, contact control room with the following information:

Delete RHR 'C' pump trip Report that breaker 152

-1609 is repaired and ready for start attempt.

CRS Directs BOP start RHR 'C' pump (if needed for level control)

. (Critical TASK in BOLD)

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3 Event No:

9/10 (cont.)

Event

Description:

Loss of Offsite Power with ESF bus 15AA Lockout Division 2 Diesel Generator Fails to Auto Energize 16AB (cont.) BOP Starts RHR 'C' pump on P601 panel

. Places handswitch for RHR 'C' pump to STOP then to START.

Verifies and reports pump starts and E12

-F042C is Open.

Verifies and reports injection flow on P601

-17B using E12

-R603 C Restore RHR B and/or C injection prior to level reaching TAF CRS Directs ATC to maintain reactor water level with a band of

-30" to + 50" wide range using the following systems:

RHR 'B" RHR 'C' RCIC (Critical TASK in BOLD)

TERMINATION Once reactor water level is being controlled in band or as directed by Lead Evaluator:

Take the simulator to Freeze and turn horns off.

Stop and save the SBT report and any other recording devices.

Instruct the crew to not erase any markings or talk about the scenario until after follow

-up questions are asked.

Revision 0 9/22/2015 Give this page to the CRS ` Crew Turnover:

Turnover the following conditions:

Power 4% Mode 2 M OC EOOS GREEN A reactor startup is in progress.

Step 8 3 of Control Rod Movement Sequence is complete SJAE 'B' is in warm up 04 N62-1 step 4.2.2r The Condensate system is lined up as follows:

CFFF is in service Precoat Filters are not in service 4 Deepbed demins are in service

Planned Evolutions this shift:

Continue with plant startup per IOI

-1 Attachment XV step 30.

Note that an independent Reactivity Management SRO per Operations Philosophy 6.8.1 will not be provided for this scenario.

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