ML12304A011

Initial Exam 2012-301 Draft Sim in-Plant JPMs

ML12304A011
Person / Time
Site:	Surry
Issue date:	10/26/2012
From:	NRC/RGN-II
To:	Virginia Electric & Power Co (VEPCO)
References
50-280/12-301, 50-281/12-301
Download: ML12304A011 (108)

Text

_____

Surry 2012-301 Locally Isolate Secondary, 1-E-3 Aft. I U.S. Nuclear Regulatory Commission Surry Power Station SR12301 Simulator Job Performance Measure 038EA1 .32 (4.6/4.7)

Applicant_

Examiner Date Title Locally Isolate the Secondary System (1-E-3, KIA: 038EA1 .32 Ability to operate and a of a ruptured SIG Applicability Actual Time ROISRO(I) Minutes Conditions

• TaskistobeSlMULA

• A simulated SGTR MSTV and NRV will not close. The A and C SG MSTVs Standards

• Uniti 1, Step 6 completed.

el.

• 1-E-3, SGTR, 6 completed.

Procedures

• 1-E-3, Steam Generator Tube Rupture, Rev 43.

Tools and Equipment Safety Considerations

. None

• Standard Personal Safety Equipment Page 1 of 7

Su rry 2012-301 Locally Isolate Secondary, 1-E-3 Aft 1 Initiating Cues

• B Steam Generator Tube Rupture with the failure of B SG isolation from the Control Room.

Directions to the Applicant

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• I am the Nuclear Shift Manager. There has been a SGTR identified in Unit 1s SG. We have attempted to isolate the B Steam Generator but its MSTV and NRV will not close. The oSTVs have been closed and now we have to isolate the secondary system.

• Heres 1-E-3, Attachment 1. I need you to locally isolate Unit I lAW I-E-3, Attachment 1, Steps 4 though 6 Notes

• This task is to be SIMULATED. Do NOT allow the switches or reposition valves.

Page 2 of 7

Su rry 2012-301 Locally Isolate Secondary, 1-E-3 Aft 1 PERFORMANCE CHECKLIST Notes to the Evaluator

. Task critical elements are bolded and denoted by an asterisk (*).

• An additional instructor may be needed to silence and acknowledge alarms

• START TIME:

Auxiliary and Gland Steam Isolation (Step 4)

STANDARD:

a) Locally open auxiliary steam crosstie: 1 -AS-8.

b) Locally close auxiliary steam isolation: 1-AS-i.

C) Locally verify gland steam supply from main steam EVALUATORS NOTE:

a) 1-AS-8 located on right side of stairs, When SIMULATING Opening: Valve Counter clockwise, and stem thç appear al turns, handwheel motion shoi turn clockwise to ensure valve b) 1-AS-i located west of 1-AS-PCV-100, six feet above floor. valve freely moves and stem threads di turns of the handwheel, valve motion stops, ai 1-MS-i5 of i-MS-PCV-104, six feet l turnea wise, valve freely moves and stem heel. After several turns of the handwheel, valve ing above handwheel.

Page 3 of 7

Surry 2012-301 Locally Isolate Secondary, 1-E-3 Att. 1 SAT Turbine Building Steam Trap Isolation, Main steam line and Turbine trap isolation valves:

(Step 5a) UNSAT STANDARD:

a) Reviews to Note prior to Step 5: NOTE: Steps 5 and 6 may be order.

b) 1-MS-46 (mezz level north face of south stanchion under HP tui c) 1-MS-50 (mezz level north face of south stanchion under HP tui d) 1-MS-30 (mezz level south face of north stanchion under HP e) 1-MS-35 (mezz level south face of north stanchion under f) 1-MS-55 (mezz level west of grating over HP drain pp).

EVALUATORS NOTE:

When valve handwheel turned Clockwise, valve handwheel, valve motion stops.

COMMENTS:

SAT UNSAT STANDARD:

a) 1-SD-367 below VP tank).

moves freely. After several turns of the Page 4 of 7

Surry 2012-301 Locally Isolate Secondary, 1-E-3 Att. 1 U.S. Nuclear Regulatory Commission Surry Power Station SR12301 Simulator Job Performance Measure 038EA1 .32 (4.6 /4.7)

Applicant________________________________ Start Time___________________

Examiner________________________________

Date Stop Time___________________

Title Locally Isolate the Secondary System (1-E-3, Attachment 1)

KJA: 038EA1 .32 Ability to operate and monitor the following as they apply to a SGTR: Isolation of a ruptured SIG Applicability Estimated Time Actual Time ROISRO(l) 10 Minutes Minutes Conditions

• Task is to be SIMULATED in the Plant.

• A simulated SGTR has occurred on the Unit 1 B SG and the B MSTV and NRV will not close. The A and C SG MSTVs have been closed.

Standards

• Unit lseondary system isolated lAW 1-E-3, Attachment 1, Step 6 completed.

Initiating Cues

• Shift Manager Direction.

• 1-E-3, SGTR, (RNO column) Step 3.e RNO el.

Terminating Cues

• 1-E-3, SGTR, Attachment 1, Step 6 completed.

Procedures

• 1-E-3, Steam Generator Tube Rupture, Rev 43.

Tools and Equipment Safety Considerations

• None

• Standard Personal Safety Equipment Page lof7

Surry 2012-301 Locally Isolate Secondary, 1-E-3 Att. I Initiating Cues

• B Steam Generator Tube Rupture with the failure of B SG isolation from the Control Room.

Directions to the Applicant

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• I am the Nuclear Shift Manager. There has been a SGTR identified in Unit ls.B SG. We have attempted to isolate the B Steam Generator but its MSTV and NRV will not close. The other MSTVs have been closed and now we have to isolate the secondary system.

• Heres 1-E-3, Attachment 1. I need you to locally isolate Unit I secondary system lAW 1-E-3, Attachment 1, Steps 4 though 6.

Notes

• This task is to be SIMULATED. Do NOT allow the Candidate to manipulate controls, operate switches or reposition valves.

Page 2 of 7

Surry 2012-301 Locally Isolate Secondary, 1-E-3 Att. 1 PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded and denoted by an asterisk (*).

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME:

STEP 1:

SAT Auxiliary and Gland Steam Isolation (Step 4)

UNSAT STANDARD:

a) Locally open auxiliary steam crosstie: 1 -AS-8. (Step 4a) b) Locally close auxiliary steam isolation: 1-AS-i. (Step 4b) c) Locally verify gland steam supply from main steam closed: 1-MS-15 (Step 4c)

EVALUATORS NOTE:

a) 1 -AS-8 located on right side of stairs, near Unit I side of Fire Door #28.

When SIMULATING Opening: Valve freely moves when handwheel turned Counter clockwise, and stem threads appear above handwheel. After several turns, handwheel motion stops. Candidate should move handwheel one half turn clockwise to ensure valve does not jam on backseat.

b) i-AS-I located on Turbine Building Mezzanine level, west of 1-AS-PCV-iOO, six feet above floor. When valve handwheel turned Clockwise, valve freely moves and stem threads disappear into valve handwheel. After several turns of the handwheel, valve motion stops, and two threads showing above handwheel.

c) I-MS-15 located on Turbine Building Mezzanine, west of i-MS-PCV-i04, six feet above floor. When valve handwheel turned Clockwise, valve freely moves and stem threads disappear into valve handwheel. After several turns of the handwheel, valve motion stops, and two threads showing above handwheel.

COMMENTS:

Page 3 of 7

Surry 2012-301 Locally Isolate Secondary, 1-E-3 Att. 1 STEP 2:

Turbine Building Steam Trap Isolation, Main steam line and Turbine trap isolation valves:

(Step 5a) UNSAT STANDARD:

a) Reviews to Note prior to Step 5: NOTE: Steps 5 and 6 may be performed in any order.

b) 1-MS-46 (mezz level north face of south stanchion under HP turb).

c) 1-MS-50 (mezz level north face of south stanchion under HP turb).

d) 1-MS-30 (mezz level south face of north stanchion under HP türb).

e) 1-MS-35 (mezz level south face of north stanchion under HP turb) f) 1-MS-55 (mezz level west of grating over HP drain pp).

EVALUATORS NOTE:

When valve handwheel turned Clockwise, valve moves freely. After several turns of the handwheel, valve motion stops.

COMMENTS:

STEP 3:

Turbine Building Steam Trap Isolation, Reheat steam line trap isolation valves: (Step 5b)

UNSAT STANDARD:

a) 1-SD-367 (mezz level; NW corner of condenser; between 2nd & 3rd point ES piping).

b) 1-SD-382 (mezz level; SW corner of condenser).

c) 1-SD-415 (mezz level; SE corner of condenser; left of stairs to H 2 area; 2 feet below grating level) d) 1-SD-420 (mezz level; NE corner of condenser; behind VP tank).

EVALUATORS NOTE:

When valve handwheel turned Clockwise, valve moves freely. After several turns of the handwheel, valve motion stops.

COMMENTS:

Page 4 of 7

Surry 2012-301 Locally Isolate Secondary, 1-E-3 Att. 1 STEP 4:

SAT Turbine Building Steam Trap Isolation, Steam Dumps. (Step 5c)

UNSAT STANDARD:

a) 1-SD-425 (Locally at the steam dumps on mezz level).

b) 1-SD-430 (Locally at the steam dumps on mezz level).

c) 1-SD-372 (north side of mezz level handrails at access platforms).

d) I -SD-377 (north side of mezz level handrails at access platforms).

• e) 1-SD-432 (TB bsmt; East end of condenser; left under TCV-MS-105B).

f) 1-SD-436 (TB bsmt; East end of condenser; left under TCV-MS-106B).

g) 1-SD-401 (TB bsmt; West end of condenser; right under TCV-MS-106A).

h) 1-SD-405 (TB bsmt; West end of condenser; right under TCV-MS-105A).

EVALUATORS NOTE:

When valve handwheel turned Clockwise, valve moves freely. After several turns of the handwheel, valve motion stops.

COMMENTS:

STEP 5:

SAT Sample Line Isolation, on Sample Panel 1-SS-PNL-101. (Step 6)

UNSAT STANDARD:

a) 1-SS-711, A steam line sample isolation.

b) 1-SS-626, A steam line sample isolation.

c) 1-SS-710, B steam line sample isolation.

d) 1-SS-627, B steam line sample isolation.

e) 1-SS7O9, C steam line sample isolation.

f) 1-SS-628, C steam line sample isolation.

EVALUATORS NOTE:

When valve handwheel turned Clockwise, valve moves freely. After several turns of the handwheel, valve motion stops.

COMMENTS:

Page 5 of 7

Surry 2012-301 Locally Isolate Secondary, 1-E-3 Att. 1 STEP 7:

SAT REPORT TO SHIFT MANAGER (EVALUATOR).

UNSAT STANDARD:

Verbal status report made that E-3, Attachment 1 Steps 4 though 6 complete.

COMMENTS:

STOP TIME:

Page 6 of 7

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be SIMULATED in the Plant.

• Locally isolate Unit 1 secondary system lAW 1 -E-3, Attachment 1, Steps 4 though 6.

Directions The evaluator will explain the initial conditions of the task to be performed and wiLlprovide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• A simulated SGTR has occurred on the Unit I B SG and the B MSTV and NRV will not close. The A and C SG MSTVs have been closed.

Initiating Cues

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves

• I am the Nuclear Shift Manager. A simulated SGTR has occurred on the Unit 1 B SG and the B MSTV and NRV will not close. The A and C SG MSTVs have been closed.

• Heres 1-E3, Attachment 1. I need you to locally isolate Unit I secondary system lAW 1-E-3, Attachment 1, Steps 4 though 6.

• When you finish the actions necessary to accomplish this Task, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

• A simulated SGTR has occurred on the Unit 1 B SG and the B MSTV and NRV will not close. The A and C SG MST\Is have been closed.

Initiating Cues

• This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves

• I am the Nuclear Shift Manager. A simulated SGTR has occurred onthe Unit I B SG and the B MSTV and NRV will not close. The A and C SG MSTVs have been closed.

• Heres 1-E-3, Attachment 1. I need you to locally isolateUnit1 secondary system lAW 1-E-3, Attachment 1, Steps 4 though 6.

• When you finish the actions necessary to accomplish this Task, please inform me.

NUMBER ATTACHM ENT TITLE ATTACHMENT 1-E-3 1 SECONDARY SYSTEM ISOLATION REVISION PAGE 43 lof2 Steam Dump Isolation D a. Put the STM DUMP CONTR switch in OFF and verify the steam dumps close.

b. IF steam dump valves do NOT close, THEN locally close the following valves:

1-MS-21 1-MS-61

2. Reheat Steam Isolation

a. Verify reheat FCVs closed.

b. Close MSR STM SUP valves:

1-MS-MOV-100A 1-MS-MOV-100B 1-MS-MOV-100C 1-MS-MOV-100D

3. Safeguards Steam Trap Isolation

a. Verify steam trap trip valves closed:

1-MS-TV-109 1-MS-TV-lb

b. IF trip valves will NOT close, THEN locally close the following steam trap header isolation valve:

1 -MS-3

4. Auxiliary and Gland Steam Isolation

a. Locally open auxiliary steam crosstie:

1-AS-8

b. Locally close auxiliary steam isolation:

1-AS-i

c. Locally verify gland steam supply from main steam closed:

1 -MS-b 5

NUMBER ATTACHMENT TITLE ATTACHMENT 1-E-3 1 SECONDARY SYSTEM ISOLATION REVISION PAGE 43 2of2 NOTE: Steps 5 and 6 may be performed in any order.

5. Turbine Building Steam Trap Isolation

a. Locally close Main steam line and Turbine trap isolation valves:

1 -MS-55 1 -MS-30 1 -MS-46 1-MS-35 1-MS-50

b. Locally close Reheat steam line trap isolation valves:

1 -SD-382 1 -SD-420 1-SD-415 1-SD-367

c. IF steam dumps were NOT locally isolated, THEN locally close the following isolation valves:

1 -SD-425 1 -SD-372 1 -SD-401 1 -SD-432 1 -SD-430 1 -SD-377 1 -SD-405 1 -SD-436

6. Sample Line Isolation Locally close the following sample line isolation valves at west end of Sample Panel 1-SS-PNL-1O1.

_l-SS-711 MSlineA 1-55-626 MS line A 1-SS-710 MS line B 1-SS-627 MS line B 1-SS-709 MS line C 1-S S-628 MS line C

Surry 2012-301 Isolate Flooding to #5 MER U.S. Nuclear Regulatory Commission Surry Power Station SRi 2301 In Plant Job Performance Measure 076A2.01 (3.5 I 3.7)

[Alternate Path]

Applicant Start Examiner Date Title Isolate Service Water to #5 MER During Flooding KIA: 076A2.O1 Ability to (a) predict the impacts of the foi SWS; and (b) based on those predictions, use procedures to consequences of those malfunctions or operations: Loss of SWS.

Applicability Actual Time RO/SRO(l)/SRO(U) Minutes Conditions

• TaskistobeSiMUl

• Major Service Standards

• 0-AP-t Step 22.

• 0-AP-1 3.00, MER 3 Flooding, Step 22, complete.

Procedures

• 0-AP-1 3.00, Turbine Building or MER 3 Flooding, Rev 25

• Probabilistic Risk Assessment, SPS Units 1&2 IPE, FDS-1ME2

• SA-AA-104, Confined Space Entry Page 1 of 8

Surry 2012-301 Isolate Flooding to #5 MER Tools and Equipment Safety Considerations

. None . Standard Personal Safety Equipment Page 2 of 8

Su rry 2012-301 Isolate Flooding to #5 MER Initiating Cues Report of a major Service Water leak in #5 MER Directions to the Candidate

• This task is to be SIMULATED. Do NOT allow the Candidate to manipul controls, operate switches or reposition valves

• I am the Nuclear Shift Manager. There is a major Service Water leak in:

• Here is a copy of 0-AP-1 3.00, Turbine Building or #3 MER Flooding: Service Water to #5 MER in accordance with Step 22.

The SW header from Unit 1 D Waterbox is in service.

. The #5 MER chillers have been secured.

. When you finish the actions necessary to accomplish this T Notes

• This task is to be SIMULATED. Do ilate controls, operate switches or reposition valves Page 3 of 8

Surry 2012-301 Isolate Flooding to #5 MER PERFORMANCE CHECKLIST Notes to the Evaluator

. Task critical elements are bolded and denoted by an asterisk (*)*

. START TIME:

Page 4 of 8

Surry 2012-301 Isolate Flooding to #5 MER CLOSE OR CHECK CLOSED 2-SW-535 TO ISOLATE SW TO MER 5. (Step 22a)

STANDARD: U NSAT a) Locates 2-SW-535 in MER 5 on back waIl 10 feet from the west wall, waist high.

b) Closes 2-SW-535 by rotating the valve handle clockwise until the valve stem is fully inserted.

c) Observes no flow indicated on 1-SW-Fl-I 32D.

EVALUATORS NOTE:

If asked: Flooding continues from dike area next to electrical area.

COMMENTS:

CLOSE OR CHECK CLOSED 2-SW-536 TO ISOLATE SW STANDARD: UNSAT a) Locates 2-SW-536 in MER 5 on back b) Closes 2-SW-536 by rotating the vai is fully inserted.

c) Observes no flow indicategp 1-SW-Fl-I:

EVALUATORS NOTE:

If asked: Floodii into chiller area.

COMMENTS:

SAT UNSAT EVALUATORS If asked: Water still pouring over top of dike.

COMMENTS:

Page 5 of 8

Surry 2012-301 Isolate Flooding to #5 MER STEP 6:

SAT Check or place in service SW Header 1 D lAW 0-OP-SW-49.3, SWAPPING CONTROL ROOM CHILLER AND CHARGING PUMP SW SUPPLY HEADERS. UNSAT (Step 22 b, RNO 1))

STANDARD:

a) Recalls from initial briefing that the 1 D SW header is in service. (or) b) Simulates Gai-Tronics use to contact SRO for the status of the I D c) Checks 1-SW-495, in the Unit 1 CC HX SW MOV Pit, open and sui header.

EVALUATORS NOTE:

e If asked: 1 D SW header is in service.

If asked: Evaluated Space requirements are atmospheric hazards

. If asked: Should Candidate go to Unit 1 CC HX position, after Candidate points out valve location, position arrow is pointing towards the OPEN position.

Safety Concern: Candidate does not hvel down ii identify which valve label they are looking luator 1-SW-495 if the correct label is identified.

valve manipulation from above.

Safety Concern: The allow the Candidate valve pits are Security by gated enclosures. If the enclosure is to be t. It is permissible for the Candidate to si gated enclosures.

Page 6 of 8

Su rry 2012-301 Isolate Flooding to #5 MER STEP 7:

Close 2-SW-474, located in Unit 2 BC HX SW MOV pit. (Step 22b, RNO 2))

U N SAT STANDARD:

a) Locates 2-SW-474 in Unit 2 BC HX SW MOV Pit and pulls pin from 2-SW-474 valve operator.

b) Closes 2-SW-474 by rotating the handwheel in the clockwise EVALUATORS NOTE:

When Candidate locates 2-SW-474 in Unit 2 BC HX MOV pit above, use flashlight to indicate 2-SW-474 position mdi CLOSE position; valve motion stops when CLOSED If asked: All confined space requirements have operator is standing by the valve pits acting as a Safety Concern: Candidate does not have to travel identify which valve label they are lookina .ai. and the 1-SW-495 if the correct label is ee can valve manipulation from above.

Safety Concern: The valve pits have allow the Candidate to enter the valve pits.

valve pits are Evaluated Security Concern: by gated enclosures, If the enclosure is to first. It is permissible for the Candidate to gated enclosures.

Page 7 of 8

Su rry 2012-301 Isolate Flooding to #5 MER 8:

CHECK THAT FLOODING HAS STOPPED. (Step 22b, RNO 3))

UNSAT STANDARD:

a) Candidate returns to #5 MER to determine status of #5 MER flooding.

b) Locates 2-SW-I I in Unit 2 RS HX SW MOV (SW-MOV-203C/D) Pit.

c) Pull pin from 2-SW-I I valve positioner.

d) Closes 2-SW-Il by rotating the handwheel in the clockwise e) Returns to MER #5 and verifies flooding stopped.

EVALUATORS NOTE:

a) above: Inform Candidate that water is still flowing water level in #5 MER now 5 and rising.

d) above: When Candidate locates 2-SW-il in Unit action in d) above, use flashlight to indical from OPEN to CLOSE position; valve mc reached.

e) above: When Candidate returns to #5R to status of*

water has stopped flowing ovAe, and water decreasing.

Safety Concern: Candidate does not have identify which valve label they are looking at, 1-SW-495 if the correct valve manipulation from Safety Concern: as Evaluated Spaces. Do not allow the Candith should mention that the valve pits are Evak pits are no .ct by gated enclosures. If the must be cond first. It is permissible for the required to open the gated enclosures.

Page 8 of 8

Surry 2012-301 Isolate Flooding to #5 MER STEP 9:

SAT REPORTS TO SHIFT MANAGER (EVALUATOR).

UNSAT STANDARD:

Verbal report that 0-AP-13.00, Step 22 is complete.

COMMENTS:

STOP TIME:

A Page 9 of 8

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in the Plant.

• Perform 0-AP-1 3.00, Turbine Building or MER 3 Flooding, Step 22.

Directions The evaluator will explain the initial conditions of the task to be performed the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions

• Report of a major Service Water leak in #5 MER.

• The SW header from Unit ID Waterbox is in service.

Initiating Cues This task is to be SIMULATED. Do NOT

. I am the Nuclear Shift Manager. There Here is a copy of 0-AP-13.00, Turbine 22. I need you to isolate Service Water to #5 MER in accordance with Step

• The #5 MER chillers have been secured.

• When you finish the actions necessary to

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Report of a major Service Water leak in #5 MER.

• The SW header from Unit 1 D Waterbox is in service.

Initiating Cues

• This task is to be SIMULATED. Do NOT turn switches, manipul valves.

• I am the Nuclear Shift Manager. There is a major Service Water 0 Here is a copy of 0-AP-1 3.00, Turbine Building or #3 MER you to isolate Service Water to #5 MER in accordance with Step 22.

• The #5 MER chillers have been secured.

• The SW header from Unit 1 D Waterbox is in service.

• When you finish the actions necessary to accomplish me..

NUMBER PROCEDURE TITLE REVISION 25 0-AP-1 3.00 TURBINE BUILDING OR MER 3 FLOODING PAGE 6 of 18 STEP_F__I ACTION? EXPECTED RESPONSE RESPONSE NOT OBTAINED

21. SECURE MER 5 CHILLERS:

D

• 1-VS-E-4D D

• 1-VS-E-4E

22. ISOLATE SW TO MER 5:

a) Close or check closed the following isolation valves:

D

• 2-SW-530 (NW corner of MER 5)

D

• 2-SW-532 (NW corner of MER 5)

D

• 2-SW-535 (South wall, West side of MER 5)

D

• 2-SW-536 (South wall, East side of MER 5)

C b) Check flooding STOPPED

- b) Do the following:

C 1) Check or place in service SW Header 1 D lAW O-OP-SW-49.3, SWAPPING CONTROL ROOM CHILLER AND CHARGING PUMP SW SUPPLY HEADERS.

C 2) Close 2-SW-474, located in Unit 2 BC HX SW MOV pit.

C 3) IF flooding NOT stopped, THEN close 2-SW-i 1, located in Unit 2 RX HX SW MOV pit.

23. CHECK CONTROL ROOM CHILLERS ONE - C Start Control Room Chiller lAW Shift RUNNING Supervision direction using O-OP-VS-006, CONTROL ROOM RELAY ROOM VENTILATION SYSTEM.

24. GO TO STEP 49

Surry 2012-301 Perform AP-3.00 Emergency Borate U.S. Nuclear Regulatory Commission Surry Power Station SRi 2301 Simulator Job Performance Measure 024AK3.02 (4.2 / 4.4)

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner________________________________

Date Stop Time___________________

Title Perform AP-3.OO Emergency Boration of the RCS.

KIA: 024AK3.02 Knowledge of the reasons for the following responses as they apply to Emergency Boration: Actions contained in EOP for emergency boration.

Applicability Estimated Time Actual Time ROISRO(l) 10 Minutes Minutes Conditions

• Task is to be PERFORMED inihe simulator.

• A BOL startup was in progress lAW 1-OP-RX-006, Withdrawal of the Control Banks to Critical Conditions, Step 5.2.6.h.3, withdrawing control bank rods in overlap from B bank at 15 steps to C bank at 15 steps to verify proper overlap, when doubling occurred at 35 steps on B control bank. Attachment I Plot of l-OP-RX-006 has shows that the 1/M = 0.5 point is below the MIL Line.

• Rod withdrawal has been stopped, Reactor Trip breakers have been opened, 1-OP-RX-004 reevaluated, and current RCS boron resampled with the result that RCS boron is 150 ppm less than required critical boron concentration.

• The STA has performed a calculation of the amount of Boric Acid to be added to ensure an adequate Shutdown Margin while a new ECC is prepared and verified.

Standards

• Verify STA Calculation of amount of Boric Acid to be added lAW 1-DRP-003, Unit 1 Curve Book.

• Borate the requirédnumber of gallons lAW AP-3.00.

Initiating Cues

• Verify STA calculation of amount of Boric Acid necessary to achieve minimum critical boron concentration in the RCS.

• Emergency Borate the required amount lAW AP-3.00.

Page 1 of 9

Surry 2012-301 Perform AP-3.00 Emergency Borate Terminating Cues

• AP-3.00, Emergency Boration, Step 11 complete.

Procedures

• 1-AP-3.00, Emergency Boration, Rev 5.

Tools and Equipment Safety Considerations

• None

• None Page 2 of 9

Surry 2012-301 Perform AP-3.00 Emergency Borate Simulator Setup

• Call up BOL, 10 -8 amps IC and initialize. Place simulator in RUN. Open reactor trip breakers. Using Remote function, RC, BORON_INIT_ALL set boron concentration 100 ppm less than current over 180 sec ramp.

• Set Auto trigger 1; Event Action: CHMOV35O_OPEN.

• Trigger 1: MDV Control, CH, CHMOV35O_Rackin, Rackout.

• Trigger 3: MDV Control, CH, CHMOV35O, Remote Value 100, 30 Sec Ramp

• Place the Reactivity Summary Sheet in the Simulator Control Booth.

Initiating Cues

• A BOL startup was in progress lAW 1-OP-RX-006, Withdrawal of the Control Banks to Critical Conditions, Step 5.2.6.h.3, withdrawing control bank rods in overlap from B bank ati5 steps to C bank at 15 steps to verify proper overlap, when doubling occurred at 35 steps on B control bank. Attachment I Plot of 1-OP-RX-006 has shows that the 1/M = 0.5 point is below the MIL Line.

• Rod withdrawal has been stopped, Reactor Trip breakers have been opened, 1-OP-RX-004.reevaluated, and current RCS boron resampled with the result that RCS boron is 150. ppm less than required critical boron concentration.

• The STA has performed a calculation of the amount of Boric Acid to be added to ensure an adequate Shutdown Margin while a new ECC is prepared and verified.

Directions to the Applicant

• I am the Nuclear Shift Manager. You are the Unit I BOB. Here is a copy of the STAs calculation of the amount of Boric Acid to add for minimum shutdown margin.

• You are to verify the STAs Calculation of the amount of Boric Acid to add to meet minimum shutdown margin for Hot Shutdown, and borate that amount lAW 1-AP-3.00, Emergency Boration.

• When you finish the actions necessary to accomplish these tasks, please inform me.

Notes Page 3 of 9

Surry 2012-301 Perform AP-3.00 Emergency Borate PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME:

STEP 1:

Verification of amount of Boric Acid Addition.

UNSAT STANDARD:

a) Using 1-DRP-003, Unit 1 Curve Book, Page 46, Gallons of Boric Acid Needed to Increase RCS by 1 ppm at 2235 psig, 550°F, determine 4.2 gallons BA required at current RCS Cb of 1500 ppm and 8.Owl% in A BAST.

b) Calculate required boron: 50 ppm x 4.2 gals!ppm = 210 gals.

c) Identify value calculated matches STA calcUlation.

EVALUATORS NOTE:

If asked: A BAST concentration sampled 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago.

COMMENTS:

STEP 2:

Reviews NOTES prior to Step I of 1-AP-3:00. (Step 1)

UNSAT STANDARD:

Review NOTE 1: If a Reactor Trip occurs or is required, 1-E-0, REACTOR TRIP OR SAFETY INJECTION, should be implemented.

Review NOTE 2: When the Reactor is shutdown with the Shutdown Banks withdrawn, tripping the Shutdown Banks may eliminate the need for emergency boration.

COMMENTS:

Page 4 of 9

Surry 2012-301 Perform AP-3.00 Emergency Borate STEP 3:

VERIFY CHARGING FLOW GREATER THAN 75 GPM. (Step 1)

UNSAT STANDARD:

a) Verifies Charging flow> 75 gpm using 1-CH-FI-1 122.

COMMENTS:

STEP 4:

SAT START EMERGENCY BORATION. (Step 2)

UNSAT STANDARD:

a) Transfer the in-service BATP to FAST (Step 2a).

b) Verifies indicating lights above control switch change from Slow (RED) to Fast (RED).

c) Open 1-CH-MOV-1 350 by removing brass cap and placing control switch to OPEN position.

d) Identifies GREEN indication light immediately ges out and RED light remains out.

e) Contacts Service Building Operator and directs local checking of 1-CH-MOV-1350 power supply breaker 1H1-2S-7C.

f) Contacts Auxiliary Building Operator and directs local check of 1-CH-MOV-1350 for abnormal indication.

g) Contacts Auxiliary Building Operator to locally open I -CH-MOV-I 350.

h) When report of 1-CH-MOV-1350 full open, verifies flow on 1-CH-Fl-1 110.

i) Determines with Indicated flow rate, 1-CH-MOV-1350 should remain open approximately 2 minutes.

EVALUATORS NOTE:

If asked: When 1-CH-MOV-1350 indication lost Candidate should notify Shift Manager.

Evaluator should acknowledge report and direct Candidate to continue.

Booth Operator: Will report as SBO that breaker 1HI-2S-7C is tripped.

Will report as ABC that I -CH-MOV-1 350 Normal.

Initiates Trigger 3 when directed to open 1-CH-MOV-1 350.

COMMENTS:

Page 5 of 9

Surry 2012-301 Perform AP-3.00 Emergency Borate STEP 5:

STOP BORATION WHEN DESIRED. (Step 3)

UNSAT STANDARD:

a) Close 1-CH-MOV-1350 after 2 minutes of full flow indicated on 1-CH-FI-111O by directing Auxiliary Building Operator to close 1-CH-MOV-I 350.

b) Verifies flow on 1-CH-Fl-1 110 goes to zero (0) gpm.

c) Transfer the in-service BATP to AUTO.

d) Verifies 1-CH-P-2A shifts to slow, RED slow light lit, RED fast light out.

EVALUATORS NOTE:

Booth Operator: When directed to close 1-CH-MOV-1 350, double click on CHMOV35O, set final value at 0, ramp 30 Secs, Insert.

COMMENTS:

STEP 6:

TURN ALL PRZR HEATERS ON. (Step 4)

UNSAT STANDARD:

a) Checks GRP E PRZR heater on by observing RED light ON, GREEN and AMBER lights OFF, and RED Flagged.

b) Checks GRP B PRZR heater on by observing RED light ON, GREEN and AMBER lights OFF, and RED Flagged.

c) Checks GRP C PRZR heater on by observing RED light ON, GREEN and AMBER lights OFF, and RED Flagged.

d) Checks GRP D PRZR heater on by observing RED light ON, GREEN and AMBER lights OFF, and RED Flagged.

e) Checks GRP A PRZR heater on by observing RED light ON, GREEN and AMBER lights OFF, and RED Flagged.

f) Checks PRZR heater power using PCS Screen.

COMMENTS:

Page 6 of 9

Surry 2012-301 Perform AP-3.00 Emergency Borate STEP 7:

CHECK UNIT AT POWER. (Step 5)

UNSAT STANDARD:

a) Checks reactor power in Source Range using NI-131B (H I)and NI-1-32B (CH II).

b) Goes to Step 8.

COMMENTS:

STEP 8:

SAT CHECK CHARGING FLOW. (Step 8)

UNSAT STANDARD:

a) Review NOTE prior to Step 8: NOTE: Emergency boration has increased the boric acid concentration to the RCP seals.

b) Charging flow control IN AUTO (Step 8a).

C) Checks 1-CH-FCV-1122 and 1-CH-LC-459G in automatic.

d) Charging flow STABLE (Step 8b).

COMMENTS:

STEP 9:

SAT VERIFY CHG PUMP SUCTION ALIGNED TO THE VCT. (Step 9)

UNSAT STANDARD:

a) Checks 1-CH-MOV-1 11 5C and 11 5E OPEN, RED light LIT, GREEN light Out.

b) Checks 1-CH-MOV-1 11 5B and 111 5D CLOSED, GREEN light LIT, RED light Out.

COMMENTS:

Page 7 of 9

Surry 2012-301 Perform AP-3.00 Emergency Borate STEP 10:

CONSULT WITH CHEMISTRY AND SHIFT SUPERVISION AND DEENERGIZE PRZR HEATERS lAW 1-OP-RC-019, PRESSURIZER BACKUP HEATER OPERATION]. (Step 10) UNSAT STANDARD:

Report to Shift Manager (Evaluator) that Chemistry should be consulted concerning operation of PRZR heaters.

EVALUATORS NOTE:

Acknowledge need to consult with Chemistry.

COMMENTS: -

STEP 11:

- SAT NOTIFY THE FOLLOWING: (Step 11)

• STA UNSAT

• Chemistry

• OMoncall

• Reactor Engineer.

STANDARD:

Notify Shift Manager(Evaluator) that notil1cations are required.

EVALUATORS NOTE:

Acknowledge need to make Notifications.

COMMENTS:

Page 8 of 9

Surry 2012-301 Perform AP-3.00 Emergency Borate STEP 10: SAT NOTIFY NUCLEAR SHIFT MANAGER (EVALUATOR) STATUS OF TASK. UNSAT When Step 11 completed, Candidate should report completion of task.

COMMENTS:

STOP TIME:

Page 9 of 9

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in the simulator.

• Perform Steps 1 through 11 of 1-AP-3.00.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions

• A BOL startup was in progress lAW 1-OP-RX-006, Withdrawal of the Control Banks to Critical Conditions, Step 5.2.6.h.3, withdrawing control bank rods in overlap from B bank at 15 steps to C bank at 15 steps to verify proper overlap, when doubling occurred at 35 steps on B control bank. Attachment 1 Plot of 1-OP-RX-006 shows that the 1/M = 0.5 point is below the MIL Line.

• Rod withdrawal has been stopped, Reactor Trip breakers have been opened, 1-OP-RX-004 reevaluated, and current RCS boron resampled with the result that RCS boron is 150 ppm less than required critical boron concentration.

• The STA has performed a calculation of the amount of Boric Acid to be added to ensure an adequate Shutdown Margin while a new ECC is prepared and verified Initiating Cues

• I am the Nuclear Shift Manager.You are the Unit I BOP. You are to perform the following Tasks:

• Verify STA calculation of amount of Boric Acid necessary to achieve minimum critical boron concentration in the RCS.

• Emergency Borate the required amount lAW AP-3.00.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A BOL startup was in progress lAW 1-OPRX-006, Withdrawal of the Control Banks to Critical Conditions, Step 5.2.6.h.3, withdrawing control bank rods in overlap from B bank at 15 steps to C bank at 15 steps to verify proper overlap, when doubling occurred at 35 steps on B control bank. Attachment I Plot of 1-OP-RXO06 shows that the 1/M = 0.5 point is below the MIL Line.

• Rod withdrawal has been stopped, Reactor Trip breakers have been opened, 1-OP-RX-004 reevaluated, and current RCS boron resampled with the result that RCS boron is 150 ppm less than required critical boron concentration.

• The STA has performed a calculation of the amount of Boric Acid to be added to ensure an adequate Shutdown Margin while a new ECC is prepared and verified Initiating Cues

• I am the Nuclear Shift Manager. You are the Unit 1 BOP. You are to perform the following Tasks:

• Verify STA calculation of amount of Boric Acid necessary to achieve minimum critical boron concentration in the RCS.

• Emergency Borate the required amount lAW AP-3.00.

DOMINION 1 -OP-RX-008 Swry Power Station Revision 32 Page 22 of 31 (Page ¶ of 1)

Attachment I INVERSE COUNT RATE RATIO PLOT (CONTROL BANKS A, B, AND C) cAUTEOrc During rod withdrawal. if the second data point falls below the [,1LL Line, the rod withdrawal must be stopped. the Reactor Trip Breakers must be opened. and I -OP-RX-004 must be reevaluated, to prevent a violation of Tech. Specs.

- )=

0 (C eps (first data point CONT BANK A at 000 steps JF 2. 0

=

1 C

) 2x(C

= cps(seconddatapoint)(Ref.2.4.I1}

IV JF FN 1152 C

=

2 4x(&= cps(thirddalapoint(Ref.2.4.1I)

IV 1.0 1IM 0.5 0 0 50 100 0 50 70 08 0 23 50 100 150 230 A B B BC CCCDDD D D D Rod Position GrMr Kl4E INVERSE COUNT RATE RATIO PLOT Perlormed by:

Signature lniiaI Print Date Signature Initial Print Date

ec,uJredCi Jncrease 4

R 1° =

50 21 921S7= So w/%

Current C fn CS =1500 1 ,m 42Is/ppm 50 ppm X 42q/ppm = 210 to t 3h

Surry Establish Hot Leg Injection U.S. Nuclear Regulatory Commission Surry Power Station Alternate Path Simulator Job Performance Measure 006A2.11 (4.0 /4.4)

Applicant________________________________ Start Time___________________

Examiner________________________________

Date Stop Time___________________

Title Manually Align Alternate High Head Safety Injection Flowpath KIA: 006A2.11 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control,ór mitigate the consequences of those malfunctions or operations: Rupture of ECCS header Applicability Estimated Time Actual Time RO/SRO(l)/SRO(U) 5 Minutes Minutes Conditions

• Task is to be PERFORMED in the simulator.

• A Safety Injection has occurred from 100% power due to a SBLOCA. 1-E-0, attachment 1 has been performed up to Step 12.

Standards

• Completion of 1-E-0, Reactor Trip or Safety Injection, attachment 1, Step 12.

Initiating Cues

• The operating team has initiated SI due to a SBLOCA on Unit I and has completed 1-E-O, Attachment 1 up to Step 12.

Terminating Cues

• Completion of 1-E-0, Reactor Trip or Safety Injection, Step 12.

Procedures

• 1-E-0, Reactor Trip or Safety Injection, Attachment 1, Step 12, Revision 65.

Tools and Equipment Safety Considerations

• None

• None Page 1 of 9

Surry Establish Hot Leg Injection Simulator Setup

• Call up 100% power IC and initialize. Place simulator in RUN.

• Implement malfunction for SBLOCA at 240 gpm. (RCO4 at 20% deg)

• Implement malfunction for cold leg Si injection header break at 100% degradation (Sill)

• Implement meter overrides for SI cold leg individual loop flow indicators (SIFI961, 962, 963)

• Place following variables on a Trigger: SIMOV869A Rackin; SIMOV869B Rackin.

• Manually initiate SI. Perform l-E-0 immediate actions and attachment 1 up to Step 12.

• Throttle AFW to approximately 200 gpm per generator.

• Place simulator in freeze until JPM performance.

• Have keys ready for 1 869A1B (keys 46147)

Initiating Cues

• Shift Manager Direction.

• 1-E-0, Reactor Trip or Safety Injection, Step 12.

Directions to the Applicant

• I am the Nuclear Shift Manager. A Safety Injection has occurred from 100% power due to a SBLOCA. l-E-0 is being performed and the operating team is currently at step 12 of attachment I.

• Here is a copy of l-E-0, attachment 1, Step 12. I need you to perform Step 12 ofattachmentl.

• When you finish the actions necessary to accomplish this task, please inform me.

Notes

• Operator is given a copy of l-E-0, attachment 1, Step 12 during directions.

• Have keys ready for operation of 1 -SI-MOV-l 869A and 1869B (Keys 46/47).

Page 2 of 9

Surry Establish Hot Leg Injection PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME:

STEP 1:

ACKNOWLEDGES NOTES PRIOR TO STEP 12 OF ATTACHMENT I (Step 12)

UNSAT STANDARD:

a) Notes that CHG pumps should be run in the following order of priority: C, B, A.

b) Notes that subsequent SI signals may be reset by reperforming step 12 EVALUATORS NOTE:

COMMENTS:

STEP 2:

CHECK SI FLOW: (Step 12a)

UNSAT STANDARD:

a) HHSI to cold legs FLOW INDICATED.

• 1-Sl-F1-1961 (NQ)

• 1-SI-Fl-I 962 (NQ)

• 1-SI-Fl-I 963 (NQ) a I-SI-Fl-i 943 or I-SI-Fl-i 943A.

b) ldentifies 0 (zero) indicated flow on 1-SI-Fl-i 961/1 96211 963.

C) Identifies greater than normal flow on 1-Sl-Fl-1943/1943A than expected for current RCS pressure.

d) Identifies RCS pressure and subcooling decreasing.

e) Diagnoses SI flow not reaching the core, notifies SM (Evaluator), and goes to Step 12 RNO.

COMMENTS:

Page 3 of 9

Surry Establish Hot Leg Injection STEP 3:

Reads Step 12, RNO a). (Step 12 a)

UNSAT STANDARD:

a) Manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flowpath while continuing with this procedure.

o Alternate SI to cold legs -

• Hot leg injection EVALUATORS NOTE:

If asked: Which flowpath of SI flow should be attempted Ask the Candidate which flowpath is recommended and concur with recommendation.

COMMENTS:

STEP 4:

Aligns Hot Leg SI Isolation Valves 1-SI-MOV-1869A and/or 1869B. (Step 12 RNO a)

UNSAT STANDARD:

(a) Consults with SM on establishing another path.

(b) Opens 1-Sl-MOV-1 842, identifies no HHSI flow, closes 1-SI-MOV-1 842.

(c) Directs shift clerk (or another operator) to obtain keys from the Annex and bring keys to the MCR.

(d) Directs an auxiliary operator to close breakers MCC IHI-1-3C and MCC IJI I -9A.

(e) After receiving report that breakers MCC 1HI-1-3C and MCC 1JI-1-9A are closed, verify red lights are off and green lights are on for I -Sl-MOV-1 869A and 1869B.

(f) Place the control switch(s) for I-SI-MOV-1869A andlor I-Sl-MOV-1869B in the open position.

(g) Verify 1-SI-MOV-1869A is open by observing red light on and green light off.

(h) Verify 1-Sl-MOV-1869B is open by observing red light on and green light off.

(i) Verifies hot leg flow indicated on I-SI-Fl-i 940 and I 940A.

(j) Verifies hot leg flow indicated on individual loop flow transmitters I-SI-FI-1933, 1960, and 1932 EVALUATORS NOTE:

If asked: Which flowpath of SI flow should be attempted, Ask the Candidate which flowpath is recommended and concur with recommendation.

Notes: Candidate may elect to go straight to Th injection and not attempt to establish SI flow with 1-SI-MOV-1842. Also, the candidate can perform step 5 first.

COMMENTS:

Page 4 of 9

Surry Establish Hot Leg Injection STEP 5:

SAT Closes Cold Leg Isolation Valves 1-SI-MOV-1867C and 1-Sl-MOV-1867D. (Step 12, RNO a)

UNSAT STANDARD:

(a) Verify or reset SI by pushing the SI reset pushbuttons.

(b) Place the control switch for I -SI-MOV-l 867C in the closed position.

(c) Verify l-SI-MOV-1867C is closed by observing red light off and green light on.

(d) Place the control switch for 1-SI-MOV-1867D in the closed position.

(e) Verify 1-SI-MOV-1867D is closed by observing red light off and green Ught on.

(f) Verify no flow indicated on 1-SI-FI-1943 and 1943A.

COMMENTS:

STEP 6:

SAT CHECKS CHARGING PUMPS THREE RUNNING. (Step 12 b)

U N SAT STANDARD:

a) Checks 1-CH-P-1A breaker indication red light on and amps indicated.

b) Checks 1-CH-P-1 B breaker indication red light on and amps indicated.

c) Checks 1-CH-P-1C breaker indication red light on and amps indicated COMMENTS:

STEP 7:

SAT Reset SI. (Step 12c)

UNSAT STANDARD; Checks reset or resets SI by observing Annunciators 1A-F3 and 1A-F4 Not Lit.

COMMENTS:

Page 5 of 9

Surry Establish Hot Leg Injection STEP 8:

SAT Stops One CHG Pump and Place in Auto. (Step 12 d)

UNSAT STANDARD:

a) Place the control switch for 1-CH-P-IA in the auto after stop position.

b) Verify 1-CH-P-1A not running by observing zero amps and green breaker status light on and red status light off, and 0 (zero) amps indicated.

COMMENTS: -

STEP 9:

Check RCS Pressure Greater than 185 PSIG. (Step 12 e).

UNSAT STANDARD:

a) Checks RCS pressure greater than 185 psig by observing pressure indicated on:

• P1-1-403, or

• 1-RC-Pl-1458, or

• ICCM Train A, or

• ICCM Train B.

COMMENTS:

STEP 10:

SAT Stops One LHSI Pump and Place in Auto. (Step 12 UNSAT STANDARD; (a) Verifies SI reset by observing annunciators 1A-F3 and IA-F4 not lit.

(b) - Stops either 1-SI-P-IA or lB by placing the control switch for 1-SI-P-IA or lB in the auto after stop position.

(c) Verifies 1-SI-P-lA or lB not running by observing zero amps and green breaker statusIight on and red status light off.

COMMENTS:

Page 6 of 9

Surry Establish Hot Leg Injection STEP 11:

REPORTS TO SHIFT MANAGER (EVALUATOR).

UNSAT Standards Verbal status report made of task completion.

STOP TIME:

Page 7 of 9

Surry Establish Hot Leg Injection Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in the simulator.

• Perform 1 -E-O, Attachment 1, Step 12.

Directions to the Applicant

• I am the Nuclear Shift Manager. A Safety Injection has occurred frorniOO% power due to a SBLOCA. 1-E-O is being performed and the operating team is currently at step 12 of attachment 1.

• Here is a copy of 1-E-O, attachment 1, Step 12. I need you to perform Step 12 of attachment 1.

• When you finish the actions necessary to accomplish this task, please inform me.

Notes

• Operator is given a copy of 1-E-O, attachment 1, Step 12 during directions.

• Have keys ready for operation of 1-SI-MOV-1869A and 1869B (Keys 46147).

Page 8 of 9

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A Small Break LOCA has occurred on Unit 1.

Initiating Cues

• I am the Nuclear Shift Manager. A Safety Injection has occurred from 100% power due to a SBLOCA. 1-E-0 is being performed and the operating team is currently at step 12 of attachment 1.

• Here is a copy of 1-E-0, attachment 1, Step 12. I need you to perform Step 12 of attachment 1.

• When you finish the actions necessary to accomplish this task, please inform me.

NUMBER ATTACHMENT TITLE ATTACHMENT I-E-O 1 SYSTEM ALIGNMENT VERIFICATION REVISION PAGE 65 6of7

-_STEP jj ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

• CHG pumps should be run in the following order of priority: C, B, A.

• Subsequent SI signals may be reset by reperforming Step 12.

12._ CHECK SI FLOW:

a) HHSI to cold legs FLOW INDICATED

- D a) Manually start pumps and align valves. IF flow NOT established, D

• 1-SI-FI-1961 (NQ)

THEN consult with Shift D

• 1-Sl-FI-1962 (NQ) Supervision to establish another D

• 1-Sl-FI-1963 (NQ) high pressure injection flowpath D

• 1-Sl-Fl-1943 or 1-SI-Fl-I 943A while continuing with this procedure.

C

• Alternate SI to cold legs C

• Hot leg injection D b) Check CHG pumps THREE RUNNING

- C b) GOTO Step 12e.

D c) Reset SI D d) Stop one CHG pump and put in AUTO D e) RCS pressure LESS THAN 185 PSIG

- e) IF two LHSI pumps are running, THEN do the following:

C 1) Check reset or reset SI.

C 2) Stop one LHSI pump and put in AUTO.

C 3) GOTO Step 13.

C IF one LHSI pump running, THEN GO TO Step 13.

D f) LHSI flow INDICATED

- C f) Manually start pumps and align valves.

Surry 2012-301 Respond to a Spurious SI <350°F U.S. Nuclear Regulatory Commission Surry Power Station SRi 2301 Simulator Job Performance Measure EO2EK1 .3 (3.5 I 3.8)

Applicant________________________________ Start Time___________________

Examiner________________________________

Date Stop Time___________________

Title Respond to a Spurious SI <350°F KJA: EO2EKI .3 Knowledge of the operational implications of the following concepts as they apply to the (SI Termination): Annunciators and conditions indicating signals, and remedial actions associated with the (SI Termination).

Applicability Estimated Time Actual Time ROISRO(I)ISRO(U) 10 Minutes Minutes Conditions

• Task is to be PERFORMED in the simulator.

• A spurious SI has occurred, with Unit operating <350°F, and the A RHR pump and heat exchanger in service.

Standards

• Completion of 1-AP-1020, Response to Spurious Safety Injection with RCS Temperature Less Than 350°F, Step 10.

Initiating Cues

• A spurious safety injection has occurred with Unit I operating less than 350°F.

• 1-RH-P-IA and 1-RH-E-IA are in service.

• I am the Nuclear Shift Manager. You are the Unit 1 BOP.

• You are to respond to a spurious SI by performing Steps 1 through 10 of 1-AP-10.20, Response to Spurious Safety Injection with RCS Temperature Less Than 350° F

• When you complete the actions necessary to accomplish this Task, please inform me.

Terminating Cues

• Completion of 1-AP-10.20, Response to Spurious Safety Injection with RCS Temperature Less Than 350°F, Step 10.

Procedures Page 1 of 9

Surry 2012-301 Respond to a Spurious SI <350°F

• 1-AP-10.20, Response to Spurious Safety Injection with RCS Temperature Less Than 350°F, Rev 9 Tools and Equipment Safety Considerations

• None

• None Page 2 of 9

Surry 2012-301 Respond to a Spurious SI <350°F Simulator Setup

• Call up IC with RHR in service and RCS temperature <350 degrees.

• Insert malfunction S11801 (Spurious Train A SI) and S11802 (Spurious Train B SI).

• Place red magnets on RH-MOV-1700/1701/1720A.

• Place green magnets on Sl-MOV-1865A1B/C.

• Check RCS pressure 320 psig on 1-RC-Pl-1403 and 1-RC-Pl-1458.

• Allow all components to align, then freeze the simulator.

Initiating Cues

• A spurious safety injection has occurred with Unit I operating less than350°F.

• 1-RH-P-IA and 1-RH-E-IA are in service.

Directions to the Applicant

• I am the Nuclear Shift Manager. You are the Unit 1 BOP.

• You are to respond to the spurious SI by performing Steps 1 through 10 of 1-AP-1 0.20, Response to Spurious Safety Injection with RCS Temperature Less Than 350°F

• When you complete the actions necessary to accomplish this Task, please inform me.

Notes Page 3 of 9

Surry 2012-30 1 Respond to a Spurious SI <350°F PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the ,examinee.

• START TIME:

STEP 1:

CHECK SAFETY INJECTION INITIATION (Step 1)

UNSAT STANDARD:

a) Checks HHSI to cold legs flow indicated by observing flow, on 1-SI-Fl-1961/1962/1963/194311 943A and/or PCS.

b) Checks #1 and #3 EDG running by observing EDG RPM indicated, on #1 and #3 EDG Panels.

COMMENTS:

STEP2:

PRESS BOTH SI RESET TRAIN A AND TRAIN B PUSHBUTTONS (60 SECOND TD).

(Step 2) UNSAT STANDARD:

Depresses both SI reset pushbuttons on benchboard 1-1.

EVALUATORS NOTE:

If asked: SI actuation occurred 2 minutes ago.

COMMENTS:

Page 4 of 9

Surry 2012-301 Respond to a Spurious SI <350°F STEP 3:

CHECKS BOTH ANNUNCIATORS NOT LIT. (Step 3)

U NSAT STANDARD:

a) 1A-F3, SI INITIATED TRAIN A.

b) 1A-F4, SI INITIATED TRAIN B.

COMMENTS:

STEP 4:

CHECK CLOSED OR CLOSE SI TO COLD LEG MOVS: (Step 4)

UNSAT STANDARD:

a) 1-SI-MOV-1867C by placing and holding control switch in close.

b) Checks 1-SI-MOV-1867C closed by observing GREEN Light Lit and RED Light OFF.

c) 1-SI-MOV-1867D by placing and holding control switch in close.

d) Checks 1-SI-MOV-1867D closed by observing GREEN Light Lit and RED Light OFF EVALUATORS NOTE:

Substeps a) and b) above may be performed Simultaneously.

COMMENTS:

Page 5 of 9

Surry 2012-301 Respond to a Spurious SI <350°F STEP 5:

SAT CHECK RHR REQUIRED. (Step 5)

UNSAT STANDARD:

a) Identifies RHR required based on initial brief or queries Shift Manager (Evaluator).

b) Identifies 1-RH-P-IA in operation by observing 1-RH-P-IA breaker position, RED Light On and GREEN Light Off, Amps indicated for 1-RH-P-IA, and/or RHR flow indicated on 1-RH-FI-1605.

EVALUATORS NOTE:

If asked: RHR is required.

COMMENTS:

STEP 6:

CHECK CC TO RHR FLOW PATH. (Step 6)

UNSAT STANDARD:

a) Check open or open the following Trip Valves:

1) 1-CC-TV-109A, RHR HX A CC RTN HDR TV

2) Identifies 1-CC-TV-i 09A closed and OPENS valve using OPEN pushbutton

3) Checks 1-CC-TV-109A OPEN by observing RED Light Lit and GREEN Light Off.

4) 1-CC-TV-109B, RHR HX A CC RTN HDR TV

5) Identifies 1-CC-TV-i 09B closed and OPENS valve using OPEN pushbutton

6) Checks1-CC-TV-109B OPEN by observing RED Light Lit and GREEN Light Off.

b) Check CC to in-service RHR HX NORMAL.

1) Observes flow on 1-CC-Fl-I bA, OUTLET HDR A FLOW.

2) Observes flow on I-CC-Fl-i lOB, OUTLET HDR B FLOW COMMENTS:

Page 6 of 9

Surry 2012-301 Respond to a Spurious SI <350°F STEP 7:

SAT CHECK RCPS ANY RUNNING. (Step 7)

UNSAT STANDARD:

Observes 1-RC-P-1C running using breaker position indicating lights, RED Light On and GREEN Light OFF; 1-RC-P-1C amps indicated.

COMMENTS:

STEP 8:

SAT CHECK IF RCPs MUST BE STOPPED: (Step 8)

UNSAT STANDARD:

Check the following:

a) RCS pressure LESS THAN 240 PSIG b) Identify RCS pressure> 240 psig by observing 1-RC-PI-1403 and 1-RC-Pl-1 458.

c) Seal leakoff flow LESS THAN 0.2 gpm d) Identify seal leakoff >.2 gpm on 1 -CH-FR-1 190, Pen 3 COMMENTS:

Page 7 of 9

Surry 2012-301 Respond to a Spurious SI <350°F STEP 9:

CHECK IF RCP SEAL RETURN FLOW SHOULD BE ESTABLISHED: (Step 9)

UNSAT STANDARD:

a) Check RCP Seal Return REQUIRED FOR PLANT CONDITIONS.

b) Check the following parameters SATISFIED

1) CCpumpRUNNING

2) Identify i-CC-P-i A and 1-CC-P-i B running by observing breaker indicating lights, RED Light Lit and GREEN Light Out; And amps indicated for both motors.

3) RCP seal injection flow BETWEEN 6 GPM AND 10 GPM.

4) Identify Seal injection flow by observing 1 -CH-Fl-1 1 24A, c) Open RCP Seal Return Valve 1 -CH-MOV-1 381 and observe RED Light On and GREEN Light Off.

EVALUATORS NOTE:

If asked: For substep a) above; Yes Seal Return flow required.

COMMENTS:

STEP 10:

SAT STABILIZE RCS PRESSURE AS NECESSARY FOR PLANT CONDITIONS (Step 10)

UN SAT STANDARD:

a) Operate heaters and normal spray to maintain pressure stable b) Identifies all pressurizer heaters On.

c) Adjusts 1 -RC-PCV-i 455B to stabilize RCS pressure

/

COMMENTS:

STEP 11:

REPORTS TO SHIFT MANAGER (EVALUATOR).

UNSAT Verbal status that 1-AP-1 0.20, steps 1-10 are complete.

COMMENTS:

STOP TIME:

Page 8 of 9

Surry 2012-301 Respond to a Spurious SI <350°F Page 9 of 9

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in the simulator.

• Perform Steps 1 through 10 of 1-AP-1 0.20, Response to Spurious Safety Injection with RCS Temperature Less Than 350°F.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions

• A spurious safety injection has occurred with Unit 1 operating less than 350°F.

• 1-RH-P-lA and 1-RH-E-1A are in service.

Initiating Cues

• I am the Nuclear Shift Manager. You are the Unit I BOP.

• You are to respond to a spurious SI by performing Steps I through I0of 1-AP-10.20, Response to Spurious Safety Injection with RCS Temperature Less Than 350°F

. When you complete the actions necessary to accomplish this Task, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A spurious safety injection has occurred with Unit 1 operating less than 350°F.

• 1-RH-P-lA and l-RH-E-IA are in service.

Initiating Cues

• I am the Nuclear Shift Manager. You are the Unit 1 BOP.

• You are to respond to a spurious SI by performing Steps 1 through 10 of 1-AP-10.20, Response to Spurious Safety Injection with RCS Temperature Less Than 350°F

• When you complete the actions necessary to accomplish this Task please inform me.

Surry 2012-301 Respond to B SG High Level U.S. Nuclear Regulatory Commission Surry Power Station Simulator Job Performance Measure 039A4.04 (3.8 / 3.9)

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner________________________________

Date Stop Time___________________

Title Respond to B SG High Level lAW 1-FR-H.3 KIA: 039A4.04 Ability to manually operate andlor monitor in the control room: Emergency feedwater pump turbines.

Applicability Estimated Time Actual Time ROISRO(l) 10 Minutes Minutes Conditions

• Task is to be PERFORMED in the simulator.

• Unit I B SG level at 95% following reactor trip.

Standards

• Isolation of feed sources to B SG JAW 1-FR-H.3, Response to Steam Generator High Level.

Initiating Cues

• An automatic reactor trip has occurred on Unit 1.

• B SG level has reached 95% NR level.

• I am the Nuclear Shift Manager. You are to take action lAW 1-FR-H.3, Response to Steam Generator High Level, for the B steam generator.

• When you have completed the Task, please inform me.

Terminating Cues

• Completion of Step 10 of 1-FR-H.3, Response to Steam Generator High Level.

Procedures

• 1-FR-H.3, Response to Steam Generator High Level (Rev 13).

Tools and Equipment Safety Considerations

• None

• None Page 1 of 9

Surry 2012-301 Respond to B SG High Level Simulator Setup

• Call up 50% power IC and initialize. Place simulator in RUN.

• Enter the following Malfunctions:

RDI8, Failure of Auto Reactor Trip, ACTIVE FWO2O1, Main Feed Reg Valve FCV-1478 Fails Shut, Trigger 1,30 SecTD FW0203, Main Feed Reg Valve FCV-1 498 Fails Shut, Trigger 1, 30 Sec TD S114, Spurious Initiation of AMSAC Train A&B, Trigger 1 EL0403 RSS XFMR C Pilot Wire Relay Actuation, Trigger 1, 210 Sec TD

• Enter the following Switch Overrides FWSOV1 55A_RESET, Stm Gen Level Reset Train A PB, Active FWSOV155B_RESET, Stm Gen Level Reset Train B PB, Active

• Enter FWMOVI51(1) through (6) on monitor screen.

• Actuate Trigger I

• After C RSST lockout occurs, Place 1-RC-PCV-1455B in manual and close.

• When A or C SG NR level> 12%, throttle AFW = 0.2 using Monitor. (H Train AFW will re-open fully when H bus is lost and regained by #1 EDG AFW will require re-throttling.

• Ensure SG PORVs are returned to L and A after SVB re-energized.

• When B SG NR level reaches 90%, place the B FRV in manual and set demand at 10%.

• Adjust B SG PORVsetpointto 1005 psig.

• When B SG NR level reaches 93%, Freeze Simulator until JPM performance.

Initiating Cues

• Shift Manager Direction Directions to the Applicant

• I am the Nuclear Shift Manager and you are the Unit I BOP. Unit 1 was initially operating at 50% with a ramp to 100% power in progress. A lightning strike near the Station caused a spurious AMSAC initiation, and reactor trip. Upon transition to 1-ES-al, a second lightning strike caused a Pilot wire lockout on the C RSST.

• The Unit 1 RD and SRO are performing 1-AP-l007, Loss of Unit I Power.

• Reactor Trip breaker A and B are stuck closed, an Operator has been dispatched to locally open them.

• The STA has just noted that the B SG NR Level is above 85% level and increasing.

• Here is a áopy of 1-FR-R3, Response to Steam Generator High Level. You are to perform 1-FR-H.3.

• When you complete the actions necessary to accomplish this task, please inform me.

Notes Page 2 of 9

Surry 2012-301 Respond to B SG High Level PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME:

/

STEP 1:

SAT CAUTIONS and NOTES Prior to Step I UNSAT STANDARD:

a) Reviews CAUTION: If SG narrow range level has increased to greater than 93%

[82%], an evaluation should be made for SG overfill considerations. Steam should NOT be released from any SC with level greater than 93% [82%] before overfill evaluation.

b) Reviews NOTE: Throughout this procedure, AFFECTED refers to any SC in which narrow range level is greater than 75%.

EVALUATORS NOTE:

If asked: Shift Manager is conducting a SC overfill evaluation.

Candidate may check for Adverse CTMT conditions by observing CTMT pressure indication <20 psia on I-LM-Pl-100A/B/C/D, and CTMT Radiation < 1E5 R/hr on I-RM RR-127/128.

If asked: CTMT Pressure and CTMT Radiation are as found.

COMMENTS:

STEP 2:

SAT IDENTIFY AFFECTED SC(s). (Step I)

UNSAT STANDARD:

Identifies B SG is approximately 93% NR Level and increasing.

COMMENTS:

Page 3 of 9

Surry 2012-301 Respond to B SG High Level STEP 3:

SAT VERIFY MEW ISOLATION TO AFFECTED SG(s): (Step 2)

UNSAT STANDARD:

a) MFWPumps-STOPPED. (STEP2a))

1) Identifies 1-FW-P-1A running by observing breaker RED light Lit, GREEN Light NOT Lit and Amps indicated for both MEW Pump motors.

2) Secures 1-FW-P-IA by placing control switch for 1-FW-P-IAI and 1-FW-P-1A2 in STOPIPTL.

3) Checks 1-FW-P-1A secure by verifying No amps indicated.

4) Checks 1-FW-P-1B by observing breaker GREEN light LIT and RED light NOT Lit for Both MFP motors, and No amps indicated for Both MFP Motors.

b) Feed Pump discharge MOVs CLOSED. (Step 2 b))

1) Monitors 1-FW-MOV-150A until fully closed, GREEN light Lit and Red Light Out.

2) Checks 1-FW-MOV-150B closed, GREEN light Lit and RED light Out.

c) SG feed Reg valves CLOSED. (Step 2 c))

1) Identifies 1-FW-FCV-1488 (B FRV) in Manual with Demand indicated.

2) Reduces Demand on B FRV until Zero (0) Demand Indicated and GREEN Closed light Lit and RED open light Not Lit.

3) Identifies A and B FRV full closed using GREEN Closed Light Lit and RED Open Light Not Lit.

d) SG FW bypass flow valves CLOSED ([Step 2 d))

1) Checks A, B, and C feed bypass valves closed by tUrning pot counterclockwise with no rotation, and No demand indicated, COMMENTS:

STEP 4:

ISOLATE AFW FLOW TO AFFECTED SG(s). (Step 3)

UNSAT STANDARD:

a) IndentiflesAFWflowto B SG by observing 1-FW-MOV-151C and 1-FW-MOV-151D in intermediate position, RED and GREEN lights Lit; and AFW flow indicated on 1-FW-Fl-i OOB.

b) Throttles closed on 1-FW-MOV-151C and 1-FW-MOV-151D until No flow indicated on 1-FW-Fl-IOOB, and GREEN lights Lit and RED Lights Out on 1-FW-MOV-151C and 1-FW-MOV-151D.

COMMENTS:

Page 4 of 9

Surry 2012-301 Respond to B SG High Level STEP 5:

CHECK AFFECTED SG(s) NARROW RANGE LEVEL: (Step 4)

UNSAT STANDARD:

a) Level LESS THAN 93% [82%].

1) Identifies containment Not Adverse by observing CTMT pressure indication <20 psia on 1-LM-PI-100AIB/C/D, and CTMT Radiation < 1E5 R/hr on 1-RM-RR-127/128.

2) Identifies B SG NR Level> 93% and Goes to Step 5.

EVALUATORS NOTE:

If asked: CTMT pressure is as found.

If asked: CTMT Radiation is as found.

Adverse CTMT Conditions may have been verified during review of CAUTION prior to Step 1.

COMMENTS:

STEP 6:

ADJUST AFFECTED SG(s) PORV CONTROLLER SETPOINT TO 1035 PSlG(Step 5)

UNSAT STANDARD: -

a) Checks setpointon 1-MS-PC-biB and observes setpoint indicates 1005 psig.

b) Adjusts setpoint using A or V pushbuttons to an indication of 1035 p51g.

COMMENTS:

STEP7 Reviews CAUTIONPrior to Step 6. (Step 6)

UNSAT STANDARD:

Reviews CAUTION: If the TD AFW pump is the only available source of feed flow, steam supply to the TD AFW pump must be maintained from at least one SG.

COMMENTS:

Page 5 of 9

Surry 2012-301 Respond to B SG High Level STEP 8:

SAT LOCALLY CLOSE AFFECTED SG(s) STEAM SUPPLY VALVES TO TD AFW PUMP: (Step

6) UNSAT STANDARD:

Directs Operator to iocaily close 1-MS-120 for SG B.

EVALUATORS NOTE:

When Booth Operator Directed to close 1-MS-120, the Booth Operator will inform the Candidate that a time compression has occurred and 1-MS-120 is closed.

COMMENTS:

STEP 9:

SAT CLOSE AFFECTED SG(s) MSTVs. (Step 7)

UNSAT STANDARD a) Identifies 1-NS-RV-IO1B Open, by observing RED light On and GREENJJght Off.

b) Removes Brass Cap over control switch and places 1-MS-TV-bIB control switch to close.

C) Verifies 1 -MS-TV-i 01 B closed by observing GREEN Light Lit and RED Light Out.

d) Silences and Acknowledges alarm IH-A8, STM LINE ISOL TRIP VVs CLOSED.

EVALUATORS NOTE:

d) Action above may be performed by Booth Operator if Candidate requested Alarms to be Silenced and Acknowledged during JPM performance.

COMMENTS:

Page 6 of 9

Surry 2012-301 Respond to B SG High Level STEP 10:

CHECK AFFECTED SG(s) RADIA11ON - NORMAL. (Step 8)

UNSAT STANDARD a) Checks B MS line RM normal using PCS (MS Screen).

b) Checks SG Blowdown Normal using PCS or 1-RM-RMS-113 (BID RM for B/C SG).

c) Samples.

EVALUATORS NOTE:

If asked: PCS Indication as found.

If asked: 1 -RM-RMS-1 13 indication as found.

If asked: Sampling will be considered following Blowdown Restoration.

COMMENTS:

STEP 11:

ESTABLISH BLOWDOWN FROM AFFECTED SG(s) lAW 1-OP-BD-001, STEAM GENERATOR BLOWDOWN SYSTEM OPERATION. (Step 9) UNSAT STANDARD a) Identifies that Blowdown is isolated by observing 1-BD-1V-IOOC and 1-BD-TV-IOOD closed on VBI-1, and zero (0) blowdown flow indicated in FI-BD-103B/FI-BD-104B.

EVALUATORS NOTE:

After Candidate identifies indications for Blowdown flow, inform Candidate that another Operator is currently being briefed and will place blowdown in service lAW 1-OP-BD-001.

COMMENTS:

STEP 12:

RETURN TO PROCEDURE AND STEP IN EFFECT (Step 10)

UNSAT NOTIFY NUCLEAR SHIFT MANAGER (EVALUATOR) STATUS OF TASK.

When Step 10 reached, Candidate should report task complete.

STOP TIME:

Page 7 of 9

Surry 2012-301 Respond to B SG High Level Page 8 of 9

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in the simulator.

• Perform 1-FR-H.3, Response to Steam Generator High Level Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions

• Unit 1 was initially operating at 50% with a ramp to 100% power in progress. A lightning strike near the Station caused a spurious AMSAC initiation, and reactor trip. Upon transition to 1-ES-0.1, a second lightning strike caused a Pilot wire lockout on the C RSST.

• The Unit I RO and SRO are performing 1-AP-I 0.07, Loss of Unit I Power.

• Reactor Trip breaker A and B are stuck closed, an Operator has been dispatched to locally open them

• The STA has just noted that the B SG NR Level is above 85% level and increasing.

Initiating Cues

• I am the Nuclear Shift Manager and you are the Unit 1 BOP.

• Here is a copy of 1-FR-H.3, Response to Steam Generator High Level. You are to perform 1-FR-H.3.

• When you complete the actions necessary to accomplish this task, please infprm me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Unit 1 was initially operating at 50% with a ramp to 100% power in progress. A lightning strike near the Station caused a spurious AMSAC initiation, and reactor trip. Upon transition to 1-ES-0.1, a second lightning strike caused a Pilot wire lockout on the C RSST.

• The Unit 1 RO and SRO are performing 1-AP-1 0.07, Loss of Unit I Power.

• Reactor Trip breaker A and B are stuck closed, an Operator has been dispatched to locally open them

• The STA has just noted that the B SG NR Level is above 85% level and increasing.

Initiating Cues

• I am the Nuclear Shift Manager and you are the Unit 1 BOP.

• Here is a copy of 1-FR-H.3, Response to Steam Generator High Level. You are to perform 1-FR-H.3.

• When you complete the actions necessary to accomplish this task, please inform me.

Surry 2012-301 Place CTMT H2 Analyzer in Service U.S. Nuclear Regulatory Commission Surry Power Station Simulator Job Performance Measure 028A4.03 (3.1 I 3.3)

Applicant_________________________________ Start Time____________________

Examiner_______________________________

Date Stop Time___________________

Title Place the Containment Hydrogen Analyzer in Service KIA: 028A4.03 Ability to predict andlor monitor changes in parameter (to prevent exceeding design limits) associated with operating the HRPS controls including: Location and operation of hydrogen sampling and analysis of containment atmosphere, including alarms and indications.

Aplicabilitv Estimated Time Actual Time ROISRO(l) 10 Minutes Minutes Conditions

• Task is to be PERFORMED inthe simulator.

• A LBLOCA has occurred from 100% power.

• A determination of Containment Hydrogen concentration is required.

Standards

• 1-E-1, Loss of Reactor or Secondary Coolant (Rev 37).

Initiating Cues

• 1-E-1, Loss of Reactor or Secondary Coolant, Step 26a

• Shift Mahager direction.

Terminating Cues

• 1-E-1, Attachment 3,Stepl.2.h Procedures

• I -E-1, Loss of Reactor or Secondary Coolant, Attachment 3, Rev 37 Tools and Equipment Safety Considerations

• None

• None Page 1 of 6

Surry 2012-301 Place CTMT H2 Analyzer in Service Simulator Setup

• Call up 100% power IC and initialize. Place simulator in RUN.

• Initiate LBLOCA malfunction. Perform E-0 and E-1 Actions up to Step 26.

• Allow CTMT pressure to increase and return to < 18 psia.

• Place selector switch for H2A-GW1O4 in the Unit 2 position.

• Verify selector switch for the H 2 ANALYZER (H2A-GW-104) HEAT TRACE PANEL 6, 1-HT-HTP-6, is in the AUTO position & reset SI. Check heat tracing de-energized.

• Freeze simulator until JPM performance.

Initiating Cues

• A LBLOCA has occurred on Unit 1.

• The Operating Team has reached Step 26 of 1-E-1, Loss of Reactor or Secondary Coolant Directions to the Applicant

• I am the Nuclear Shift Manager. You are the Unit 1 BOP.

• You are to place Hydrogen Analyzer H2A-GWIO4 in service on Unit 1 Containment lAW 1-E-1, Attachment 3, Part I.

• When you complete the actions necessary to accomplish this Task, please inform me.

Notes Page 2 of 6

Surry 2012-301 Place CTMT H2 Analyzer in Service PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms forthe examinee.

• START TIME:

STEP 1:

Review NOTES prior to Step 1 of Attachment 3: (Step 1)

U NSAT STANDARD:

a) Reviews NOTE 1: Containment pressure should be between 9 and 60 PSIA.

• Observes CTMT Pressure indication on 1-LM-Pl-IOOA/IOOB/100C and 100D.

b) Reviews NOTE 2: Containment temperature should be between 40°F and 290°F.

• Observes CTMT Temperature on 1 -LM-Tl-1 00-1 and 1 OO-2; EVALUATORS NOTE:

If asked: CTMT Pressure and Temperature Indications are as found.

COMMENTS:

STEP 2:

SAT Select Hydrogen Analyzer to be placed in service: (Step 1)

UNSAT STANDARD:

• Determines from previous instructions that H2A-GWIO4 is the analyzer to be used.

EVALUATORS NOTE:

If asked: H2A-GW-104 is to be used.

COMMENTS:

Page 3 of 6

Surry 2012-301 Place CTMT H2 Analyzer in Service STEP 3:

IF H2A-G Wi 04 is to be placed in service, THEN do the following: (Step 2a)

UNSAT STANDARD:

a) Put selector switch XFER CKT UNIT #1 TO UNIT #2 in the UNIT 1 position (Switch is located on Unit 1 Post Accident Monitoring Panel).

b) Checks that white analyzer indicating light for Unit 1 lit.

COMMENTS:

STEP 4:

SAT Put selector switch H2 ANALYZER (H2A-GW-1 04) HEAT TRACE PANEL 6, 1 -HT-HTP-6, in ON. (Step 2b) UNSAT STANDARD:

a) Places selector switch for H 2 ANALYZER (H2A-GW-104) HEAT TRACE PANEL 6, 1-HT-HTP-6, in the ON position.

b) Checks RED light illuminates after switch isin ON position.

c) Records the time Heat Tracing is energized COMMENTS:

Page 4 of 6

Surry 2012-301 Place CTMT H2 Analyzer in Service STEP 5:

SAT Align H2 Analyzer valves to Detector. (Step 2 c -

UNSAT STANDARD:

a) Open 1-GW-TV-100, H2 ANALYZER VLV.

b) Checks valve open by observing RED light lit and GREEN off.

c) Opens 1-GW-TV-1O1, H2 ANALYZER VLV.

d) Checks valve open by observing RED light lit and GREEN off.

e) Opens 1-GW-TV-103, H2 ANALYZER VLV.

f) Checks valve open by observing RED light lit and GREEN off.

g) Opens 1-GW-TV-102, H2 ANALYZER VLV. /

h) Checks valve open by observing RED light lit and GREEN off.

COMMENTS:

STEP 6:

SAT NOTE: Before the Hydrogen Analyzer is placed in service, the heat tracing circuit must be energized for 20 minutes. (Step 2, Note prior to 2g) UNSAT STANDARD:

• Reviews Note Prior to Step 2g: Before the Hydrogen Analyzer is, placed in service, the heat tracing circuit must be energized for 20 minutes COMMENTS:

Page 5 of 6

Surry 2012-301 Place CTMT H2 Analyzer in Service STEP 7:

Energizes H2 Analyzer. (Step 2 g, h)

UNSAT STANDARD:

a) Verify that 20 minutes have elapsed since the time recorded in Step 2b.

b) Put selector switch H2 ANALYZER H2A-GW1 04 in the ANALYZE position.

c) Checks RED light illuminates after switch is in ANALYZE position.

d) Observes 1OGW-H2A-104 TR A, CTMT H2 Analyzer, moves upscale to an indication of approximately 0.8%.

EVALUATORS NOTE:

After Candidate reviews Step 2g, inform Candidate that a time compression has occurred and the current time is 20 minutes later than the time recorded in Step 2b.

COMMENTS:

STEP 8: SAT NOTIFY NUCLEAR SHIFT MANAGER (EVALUATOR) STATUS OF TASK. UNSAT When Step 2 h) Completed, Candidate should report completion of task.

COMMENTS:

STOP TIME:

Page 6 of 6

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in the simulator.

• Place Hydrogen Analyzer H2A-GWIO4 in service on Unit I Containment lAW 1-E-1, Attachment 3, Part I.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions

• A LBLOCA has occurred on Unit 1. /

• The Operating Team has reached Step 26 of l-E-l, Loss of Reactor or Secondary Coolant.

Initiating Cues

• I am the Nuclear Shift Manager. You are the Unit I BOP.

• You are to place Hydrogen Analyzer H2A-GWIO4 in service on Unit I Containment lAW l-E-I, Attachment 3, Part I.

• When you complete the actions necessary to accomplish this Task, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A LBLOCA has occurred on Unit 1.

• The Operating Team has reached Step 26 of 1-E-1, Loss of Reactor or Secondary Coolant.

Initiating Cues

• I am the Nuclear Shift Manager. You are the Unit I BOP.

• You are to place Hydrogen Analyzer H2A-GW1O4 in service on Unit I Containment lAW 1-E-1, Attachment 3, Part I. S

• When you complete the actions necessary to accomplish this Task, please inform me.

Surry 2012-301 LoadAACDGon1JBus U.S. Nuclear Regulatory Commission Surry Power Station SR12301 Simulator Job Performance Measure 056AK3.02 (4.4 /4.7)

Applicant________________________________ Start Time___________________

Examiner_______________________________

Date Stop Time___________________

Title Load the AAC Diesel on the Unit One J Bus KIA:056 AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Actions contained in EOP for loss of offsite power.

Applicability Estimated Time Actual Time RO 10 Minutes Minutes Conditions

• Task is to be PERFORMED in the simulator.

• Unit I has sustained a loss of all AC power and Unit 2 has only the H Bus energized from #2 EDG.

• The Operating Team is performing ECA-0.0.

Standards

• 0-AP-17O6, AAC Diesel Generator Emergency Operations.

Initiating Cues

• This JPM is **TIME CRITICAL**.

• You are the Unit I BOP and I am the Nuclear Shift Manager.

• Unit 1 has sustained a loss of all AC power and Unit 2 has only the H Bus energized from #2 EDG.

• The Operating Team is performing ECA-0.0.

• Here is a copy of 0-AP-1 7.06, AAC Diesel Generator Emergency Operations.

• I need you to restore power to Unit 1 J Bus with the AAC Diesel Generator by performing steps 1-6 of 0-AP-1 7.06, AAC Diesel Generator Emergency Operations.

• When you finish the actions necessary to accomplish this, please inform me so I can have the Operating Team restore loads on the Unit 1 J Bus.

Terminating Cues

• Unit 1 J Bus re-energized.

• 0-AP-1 7.06, Step 6 complete.

Page 1 of 8

Surry 2012-301 Load AAC DG on IJ Bus Procedures

• 0-AP-1 7.06, AAC Diesel Generator Emergency Operations (Rev 24)

Tools and Equipment Safety Considerations

• None

• None Page 2 of 8

Surry 2012-301 Load AAC DG on IJ Bus Simulator Setup

• Call up 100% IC and initialize.

• Implement Failure of #1 and #3 EDGs to start (ED0201 and ED0203).

• Enter Loss of Offsite Power (ELO1) with a 1 second time delay.

• Open SA_223 to valve in Temporary Air Compressor.

• Trigger 3, FW3102, FW-P-3B Spurious Trip.

• Place the simulator in run, implement all malfunctions, and perform the ECA-0.0 to Step 5c.

• Freeze the simulator and save this condition.

Initiating Cues

• Shift Manager direction

• ECA-0.0, Loss of all AC Power, Step 5c.

Directions to the Applicant

• I am the Nuclear Shift Manager. You are the Unit 1 BOP.

• This JPM is **TIME CRITICAL**.

• Unit 1 has sustained a loss of all AC power and Unit 2 has only the H Bus energized from #2 EDG.

• The Operating Team is performing ECA-0.0.

• Here is a copy of 0-AP-1 7.06, AAC Diesel Generator Emergency Operations.

• I need you to restore power to Unit 1 J Bus with the AAC Diesel Generator by performing steps 1-6 of 0-AP-1 7.06, MC Diesel Generator Emergency Operations.

• When you finish the actions necessary to accomplish this, please inform me so I can have the Operating Team restore loads on the Unit 1 J Bus.

Notes Page 3 of 8

Surry 2012-301 LoadAACDGon1JBus PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are Bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME:

STEP 1:

REVIEWS NOTEs prior to Step I (Step 1)

UNSAT STANDARD:

a) Reviews NOTE 1: A one-line diagram showing the AAC ElectrióaIdistribution is provided in Attachment 1.

b) Reviews NOTE 2: The AAC Diesel Generator should automatically start when Transfer Buses D and F OR E and F are deenergized.

EVALUATORS NOTE:

JPM is TIME CRITICAL. 0-DRP-049, Time Critical Operator Actions, Eli, allows 10 minutes to Align the AAC Diesel to respective emergency bus, Time starts when Simulator placed in RUN; Time Stops when breaker 15J8 closed and IJ bus energized.

If asked: Unit 2 Transfer buses are de-energized, #2 EDG is supplying 2H emergency bus.

COMMENTS:

STEP 2:

CHECKS EMERGENCY BUSES 1J and 2H - EITHER OR BOTH DE-ENERGIZED. (Step 1)

UNSAT STANDARD a) Identifies 1J Bus is de-energized by observing zero (0) volts indicated on 1J bus.

b) Identifies from instructions or Unit 2 inquiry that 2H energized.

EVALUATORS NOTE:

If asked: 2H Bus is energized from the #2 EDG.

COMMENTS:

Page 4 of 8

Surry 2012-301 Load AAC DG on 1J Bus STEP 3:

GO TO APPROPRIATE STEP BASED ON DESIRED USE OF THE AAC DIESEL GENERATOR. (Step 2) UNSAT STANDARD:

a) Reviews CAUTION prior to Step 2: Loading of the AAC Diesel should consider availability of Instrument Air from 1-IA-C-i or the Temporary Diesel Air Compressor.

b) Identifies iJ to be re-energized from the AAC Diesel from initial task brIefing or Evaluator query.

EVALUATORS NOTE:

If asked: Temporary Air Compressor is in service.

If asked: Load the AAC on 1J Bus.

COMMENTS:

STEP 4:

SAT CHECKS AAC DIESEL GENERATOR AVAILABLE AND RUNNING. (Step 3).

UNSAT STANDARD:

a) Observes 0-WD-C2, AAC SYSTEM AVAILABLE BUS 1D, is lit.

b) Observes 0-WD-D1 AAC GENERATOR TRIP, is not lit.

COMMENTS:

STEP 5:

SAT REVIEWS CAUTION AND NOTE PRIOR TO STEP 4. (Step 4)

UNSAT STANDARD:

a) An overcurrent fault on 15D1 will prevent 0-AAC-BKR-05L3 from closing.

b) Annunciator 0-WD-C2, AAC SYSTEM AVAILABLE BUS ID, should go out when 0-AAC-BKR-05L3 closes.

COMMENTS:

Page 5 of 8

Surry 2012-301 Load AAC DG on 1J Bus STEP 6:

ENERGIZE TRANSFER BUS D BY CLOSING 0-AAC-BKR-05L3. (Step 4)

U N SAT STANDARD:

a) At Unit 1 EDG 3 Control Panel, place Transfer Switch NORMALJAAC, O-AAC 43-15J8, in AAC position.

b) Check Annunciator 1 K-D3, BUS 1 D UNDERVOLT NOT LIT. - -

c) Checks annunciator 0-WD-C2, AAC SYSTEM AVAILABLE BUS 1 D extinguished (from NOTE prior to step).

COMMENTS:

STEP 7:

SAT CHECK OR PLACE THE FOLLOWING LOADS IN PTL. (Step 5)

UNSAT STANDARD:

a) Places 1-VS-F-I B in PTL b) Places I-SI-P-lB in PTL c) Places I-RS-P-2B in PTL d) Places I-RS-P-IB in PTLVV e) Places 1-CS-P-lB in PTL f) Places A PZR heater group in LOCKOUT g) Places 1-CH-P-IB in PTL h) Identifies 1-CH-P-1C ALT in PTL.

i) Places 1-FW-P-3B in PTL j) Places 1-CC-P-lB in PTL k) Identifies 1-VS-F-58B is powered from its normal source and not required to be manipulated.

I) Identifies1 -CS-p-i B breaker open (RED light off, GREEN light off).

m) identifies 1 -RS-P-i B breaker open (RED light off, GREEN light off).

n) Identifies 1-FW-P-3B breaker closed (RED light on, GREEN light off).

o) Opens 1-FW-P-3B breaker by resetting AMSAC or dispatching an operator to locally open breaker 15J4.

(p) IdentIfies 1-FW-P-3B breaker opened (RED light off, GREEN light off).

EVALUATORS NOTE:

If 1-VS-F-58B placed in PTL in k) above this action warrants a follow-up question if not corrected prior to completion of task.

Booth Operator: If contacted to locally open 1-FW-P-3B breaker locally, actuate Trigger 3, inform Candidate that a time compression has occurred and 15J4 open.

COMMENTS:

V Page6of8

Surry 2012-301 Load AAC DG on 1J Bus STEP 8:

ENERGIZE EMERGENCY BUS IJ. (Step 6)

UNSAT STANDARD:

a) Reviews NOTE Prior to Step 6: The control switch for Breaker 1 5J8 must be held in Closed position for at least five seconds.

b) Locates the generator synch switch and places it in 1 5J8.

c) Rotates the synch switch for 15J8 in the clockwise direction to the ON position.

d) Verifies breaker 15J3 is open (green light on red light off).

e) Rotates 15J8 breaker control switch in the clockwise direction to the close position and holds for 5 seconds, releases switch and verifies rotation back to 12:00 position. (NOTE: 15J8 amber light will need to be reset before closing breaker)

NOTE: TIME CRITICAL ACTION COMPLETE; TIME f) Verifies 1 5J8 breaker closed (Red light on, green light off).

g) Verifies 1J Bus energized (frequency at approximately 60 HZ and voTtage approximately 4200V).

h) Rotates the synch switch for 15J8 in the cOunterclockwise direction to the OFF position.

EVALUATORS NOTE:

The operator should not attempt to use the synch switchón the Liquid Waste Panel.

Usage of this switch warrants a follow-up question.

COMMENTS:

STEP 9:

SAT REPORTSTO SHIFT MANAGER (EVALUATOR)

UNSAT Standards Verbal status report that IJ Bus is energized and AP-17.06 is completed up to Step7 STOP TIME:

COMM ENTS:

Page 7 of 8

Surry 2012-301 LoadAACDGonIJBus STOP TIME:

Page 8 of 8

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in the simulator.

• Load the AAC Diesel Generator on the 1J Bus lAW O-AP-17.06, Steps 1-6.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions

• Unit I has sustained a loss of all AC power and Unit 2 has only the H Bus energized from #2 EDG.

• The Operating Team is performing ECA-O.O.

Initiating Cues

• This JPM is **TIME CRITICAL**.

• I am the Nuclear Shift Manager. You are the Unit I BOP.

• Here is a copy of O-AP-17.06, MC Diesel Generator Emergency Operations.

• I need you to restore power to Unit 1 J Bus with the AAC Diesel Generator by performing steps 1-6 of O-AP-1 7.06, MC Diesel Generator Emergency Operations.

• When you finish the actions necessary to accomplish this, please inform me so can have the Operating Team restore loads on the Unit 1 J Bus.

• When you finish the actiofls necessary to accomplishthis, please informrne.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Unit I has sustained a loss of all AC power and Unit 2 has only the H Bus energized from #2 EDG.

• The Operating Team is performing ECA-0.0.

Initiating Cues

• This JPM is **TIME CRITICAL**.

• I am the Nuclear Shift Manager. You are the Unit I BOP.

• Here is a copy of 0-AP-1 7.06, AAC Diesel Generator Emergency Operations.

• I need you to restore power to Unit 1 J Bus with the AAC Diesel Generator by performing steps 1-6 of 0-AP-1 7.06, AAC Diesel Generator Emergency Operations -

• When you finish the actions necessary to accomplish this, please inform me so I can have the Operating Team restore loads on the Unit 1 J Bus.

• When you finish the actions necessary to accomplish this task, please inform me.

Surry 2012-301 Adjust PR Nis 1-OPT-RX-001 U.S. Nuclear Regulatory Commission Surry Power Station SRi 2301 Simulator Job Performance Measure 015K4.08 (3.4 / 3.7)

[Alternate Path]

Applicant________________________________ Start Time___________________

Examiner________________________________

Date Stop Time____________________

Title Adjust the PRNIs in accordance with 1-OPT-RX-OO1 KJA: 015K4.08 Knowledge of NIS design feature(s) andlor interlock(s) provide for the following: Automatic rod motion on demand signals.

Applicability Estimated Time Actual Time ROISRO(I) 10 Minutes Minutes Conditions

• Task is to be PERFORMED in the simulator.

• Unit I operating at 100% power. 1-OPT-RX-001 has been completed up to Section 6.2.

Standards

• Adjust N42 and N44 lAW 1-OPT-RX-001, Section 6.2 and Attachment 1.

Initiating Cues

• Unit I operating at 100% power.

• The Unit 1 RO has completed I-OPT-RX-001, Section 6.1.

• I am the Nuclear Shift Manager. You are the Unit 1 BOP. You are to perform 1-OPT-RX-001, Section 6.2.

• When you have completed the actions associated with this task, please inform me.

Terminating Cues

• Rods placed in Manual lAW AP-1 .00.

Procedures

• I-OPT-RX-001, Rev 46 Tools and Equipment Safety Considerations

• None

• None Page 1 of 7

Surry 2012-301 Adjust PR Nis 1-OPT-RX-00l Simulator Setup

• Call up 100% power IC and initialize. Place simulator in RUN.

• Adjust N41 and N44 to 100% indication using drawer gain control.

• Adjust N42 to an indication of 97% power using the drawer gain control.

• Adjust N44 to an indication of 98% power using the drawer gain control.

• Trigger 1, enter malfunction RDO2O1, Continuous Rod Insertion Auto.

Initiating Cues

• nit 1 is operating at 100%.

• 1-OPT-RX-001, Section 6.2 and Attachment 1.

Directions to the Applicant

• I am the Nuclear Shift Manager. You are the Unit I BOP. -

• The Unit 1 RO has completed 1-OPT-RX-001, Section 6.1.

• You are to perform Section 6.2 of 1-OPT-RX-001.

• When you finish the actions necessary to accomplish this task, please inform me.

Notes Page 2 of 7

Surry 2012-301 Adjust PR Nis 1-OPT-RX-001 PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME:

STEP 1:

SAT Reviews Purpose, Initial Conditions, and Precautions and Limitations of 1-OPT-RX-001.

UNSAT STANDARD:

a) Reviews Purpose 1.1, 1.2, and 1.3.

b) Reviews Initial Conditions 3.1 and 3.2.

c) Reviews Precautions and Limitations 4.1 through 4.22; noting 4.3, and 4.6.

COMMENTS:

STEP2:

SAT Adjusting NI Channels. (Section 6.Z Step 6.2.1)

U NSAT STANDARD:

a) Reads and Initials Step 6.2.1: Compare each NI channel percent power indication with the Calcalc Total Thermal Pwr (UFM, Venturi or Normalized Feedwater) or Calcalc 10-Mm Avg Pwr (Steam Flow), whichever is the standard. (Each NI should be within +

2% and 0% of the Calorimetric value if Reactor power is greater than or equal to 90%, OR within + 4% and 0% of the Calorimetric value if Reactor power is less than 90%.).

b) Refers to Step 6.1.12 to determine Calcalc Total Thermal Power: 99.94%.

c) Locates to PRNI drawers and observes N41 indicating 100%, N42 indicating 97%,

N43 indicating 100%, and N44 indicating 98%.

COMMENTS:

Page 3 of 7

Surry 2012-301 Adjust PR Nis 1-OPT-RX-001 STEP 3:

Adjusting NI Channels. (Section 6.2, Step 6.2.2)

UNSAT STANDARD:

a) Reviews Note prior to Step 6.2.2: Gain potentiometer adjustment can cause average flux deviation alarms as well as high flux rod stop alarms. This should be anticipated when adjusting gain potentiometers. (Reference 2.4.6) b) Enters N/A and Initials Step 6.2.2: IF the NI Channel is within tolerance but adjustment will better align it with the calorimetric, THEN obtain Shift Supervision concurrence AND adjust NI Channel lAW Attachment 1 to the value recorded in Step 6.1.12 or Step 6.1.13. Record initials on Attachment 1. IF no NI adjUstment is made, OR NI is NOT within tolerance, THEN enter N/A.

COMMENTS:

STEP 4:

SAT Adjusting NI Channels. (Section 6.2, Step 6.2.3)

UNSAT STANDARD:

a) Initials Step 6.2.3: IF NI channel is NOT within tolerance, THEN obtain Shift Supervision concurrence AND adjust the gain potentiometer on the front panel of each NI Channel lAW Attachment I to the value recorded in Step 6.1.12 or Step 6.1.13. Record initials on Attachment 1. IF all NI channels are within tolerance, THEN enter N/A.

b) Reports to Shift Manager (EvaIuator)that N42 and N44 require adjustment, and requests authorization to make these adjustments.

c) Initiates Attachment 1.

EVALUATORS NOTE:

When asked: Initial Step 6.2.3 to authorize adjustment of PRNIs.

COMMENTS:

Page 4 of 7

Surry 2012-301 Adjust PR Nis 1-OPT-RX-001 STEP 5:

SAT Attachment, 1-OPT-RX-001, NI Calibration. (Step 1)

UNSAT STANDARD:

a) Reviews CAUTION Prior to Step 1 ofAttachmentl: CAUTION: To prevent introducing non-conservative High Flux Trip and High Flux Rod Stop setpoints, setpoint changes required by the following step must be completed before any associated Gain Potentiometer adjustments are performed.

b) Enters N/A and Initials Step 1 of Attachment 1: IF Reactor power is less than 90%

AND the Gain Potentiometer on any NI will be decreased, THEN before adjusting NIs, have I & C lower the High Flux Trip and High Flux Rod Stop setpointson all Nis based on current Reactor power level. Otherwise, enter N/A. (Reference 2.4.5).

COMMENTS:

STEP 6:

SAT Attachment I Table, N41. (Attachment 1, Step 1)

UNSAT STANDARD:

a) Enters N/A in Item 3) block, N41 column of the Table.

b) Enters N/A in item 4) block, N41 Column of the Table.

C) Enters N/A in Item 5) block, N41 câlumn of the Table.

COMMENTS:

STEP 7:

SAT Attachment I Table, N42. (Attachment 1, Step 1)

UNSAT STANDARD:

a) Enters 97% in Item 3) block, N42 column of the Table.

b) Checks alternate indications of reactor Power (i.e., N41, N43, Turbine Impulse Pressure, Calorimetric power) prior to adjustment of N42 lAW P&L 4.6.

c) Adjusts gain control on N42 Drawer to 100% indication. (Band: 99.95102%)

d) Enters Initials in item 4) block, N42 Column of the Table.

e) Records 100% in Item 5) block, N42 column of the Table.

COMMENTS:

Page 5 of 7

Surry 2012-301 Adjust PR Nis 1-OPT-RX-001 STEP 8: Table, N43. (Attachment 1, Step 1)

UNSAT STANDARD:

a) Enters N/A in Item 3) block, N43 column of the Table.

b) Enters N/A in item 4) block, N43 Column of the Table.

c) Enters N/A in Item 5) block, N43 column of the Table.

COMMENTS:

STEP 9:

Attachment I Table, N44. (Attachment 1, Step 1)

U N SAT STANDARD:

a) Places Rod control in manual, and initials item 2) block, N44 column of the Table.

a) Enters 98% in Item 3) block, N44 column of the Table.

b) Checks alternate indications of reactor Power (Le., N41, N43, Turbine Impulse Pressure, Calorimetric power) prior to adjustment of N44 JAW P&L 4.6.

c) Adjusts gain control on N44 Drawer to 100% indication,. (Band: 99.95 102%)

d) Enters Initials in item 4) block, N44 Column of the TabIe.

e) Records 100% in Item 5) block, N44 column of the Table.

f) Allows at least one (1) minute to pass before placing rod control in automatic following gain control manipulation.

g) Places Rod control in Automatic.

h) Identifies Rod Inward rod motion with no TavelTref deviation.

I) Returns rod control to manual j) Check Rod Motion stopped.

k) Reports completion of Immediate Action Steps of AP-1 .00.

EVALUATORS NOTE:

Booth Operator: When rod control placed in manual for item a) above, actuate Trigger 1.

COMMENTS:

Page 6 of 7

Surry 2012-301 Adjust PR Nis 1-OPT-RX-001 STEP 10: SAT NOTIFY NUCLEAR SHIFT MANAGER (EVALUATOR) S1ATUS OF TASK. UNSAT When report of completion of AP-1 .00 Immediate Actions made, Candidate should report completion of task.

COMMENTS: -

STOP TIME:

Page 7 of 7

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in the simulator.

• Perform Steps perform Section 6.2 of 1-OPT-RX-0O1.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions

• Unit 1 is operating at 100%.

• The Unit I RO has completed 1-OPT-RX-001, Section 6.1.

Initiating Cues

• I am the Nuclear Shift Manager. You are the Unit 1 BOP.

• The Unit 1 RO has completed 1 -OPT-RX-O01, Section 6.1 and recorded CALCALC Total Thermal Power on Step 6.1.12.

• You are to perform Section 6.2 of 1-OPT-RX-001.

• When you finish the actions necessary to accomplish this task, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• Unit 1 is operating at 100%.

• The Unit 1 RO has completed 1-OPT-RX-001 Section 6.1.

Initiating Cues

• I am the Nuclear Shift Manager. You are the Unit I BOP.

• The Unit 1 RO has completed 1-OPT-RX-001, Section 6.1 and recorded CALCALC Total Thermal Power on Step 6.1.12.

• You are to perform Section 6.2 of 1-OPT-RX-001.

• When you finish the actions necessary to accomplish this task, please inform me.

Surry 2012-301 Isolate Leaking RSHXD U.S. Nuclear Regulatory Commission Surry Power Station SR12301 Simulator Job Performance Measure 059AK3.O1 (3.5 I 3.9)

Applicant________________________________ Start Time___________________

Examiner________________________________

Date Stop Time___________________

Title Isolate Leaking RSHX (D)

KIA: 059AK3.O1 Knowledge of the reasons for the following responses as they apply to the Accidental Liquid Radwaste Release: Termination of a release of radioactive liquid Applicability Estimated Time Actual Time RO/SRO(l)ISRO(U) 10 Minutes Minutes Conditions

• Task is to be PERFORMED in the simulator.

• A LBLOCA has occurred on Unit 1. Following completion of 1-E-0, Attachment 1, Step 9d (Check OSRS pumps NOT CAVITATiNG), Annunciator RM-C8, RS/SW HX D ALERT/FAILURE was received followed by Annunciator RM-D8, 1-SW-RI-I 17 High.

Standards

• Completionof Annunciator Response Procedure 1-RM-D8, I-SW-Rl-117 HIGH, Step 12.

Initiating Cues

• A LBLOCA has occurred on Unit 1. Unit 2 is operating at stable power level of 100%.

• The Operating Team is currently performing 1 -E-1, Loss of Reactor or Secondary Coolant.

• 1-E-0, Attachment 1, Step 9d, Check OSRS pump NOT CAVITATING has just been completed.

• Annunciator I-RM-C8, RS/SW HX D ALERT/FAILURE, and I-RM-D8. 1-SW-Rl-117 HIGH have just been received.

• I am the Nuclear Shift Manager. You are the Unit 1 BOP. You are to perform Annunciator Response Procedure 1-RM-D8, l-SW-RI-117 HIGH.

• When you have completed the actions to accomplish this Task, please inform me.

Terminating Cues

• Report of completion of Annunciator Response Procedure 1-RM-D8, 1-SW-Rl-117 HIGH, Step 12.

Page 1 of 9

Surry 2012-301 Isolate Leaking RSHXD Procedures

• 1-RM-D8, 1-SW-RI-117 HIGH (Rev 3)

Tools and Equipment Safety Considerations

• None

• None Page 2 of 9

Surry 2012-301 Isolate Leaking RSHXD Simulator Setup

• Call up 100% power IC and initialize. Place simulator in RUN.

• Enter Malfunctions:

• RCOI0I, RCS Cold Leg A Pipe Rupture

• RS0504, MaIf Leak Flow from RS-E-1 D to SW System

• Place Simulator in Run. Perform Actions of E-0 until ORS Pumps start

• Ensure RM-D8, 1-SW-RI-117 HI goes into alarm.

• Reset CLS signal when Containment decreases to < 14.2 psia. -

• Place Simulator in Freeze until JPM performance.

Initiating Cues

• A LBLOCA has occurred on Unit 1. Unit 2 is operating at stable power level of 100%.

• The Operating Team is currently performing 1-E-1, Loss of Reactor or Secondary Coolant.

• 1-E-0, Attachment 1, Step 9d, Check OSRS pump NOT CAVITATING has just been completed.

• Annunciator 1-RM-C8, RS/SW HX D ALERT/FAILURE, and 1-RM-D8. 1-SW-Rl-117 HIGH have just been received.

• I am the Nuclear Shift Manager. You are the Unit 1 BOP. You are to perform Annunciator Response Procedure 1-RM-D8, 1-SW-RI-117 HIGH.

• When you have completed the actions to accomplish this Task, please inform me.

Directions to the Applicant

• I am the Nuclear Shift Manager. You are the Unit 1 BOP. You are to perform--Annunciator Response Procedure 1-RM-D8, 1-SW-Rl-117 HIGH.

• When you have completed the-actions to accomplish this Task, please inform me.

Notes Page 3 of 9

Surry 2012-301 Isolate Leaking RSHXD PERFORMANCE CHECKLIST Notes to the Evaluator

• Task critical elements are bolded.

• An additional instructor may be needed to silence and acknowledge alarms for the examinee.

• START TIME:

STEP 1:

VERIFY ALARM READINGS ON MONITOR OR CHART RECORDER GREATER THAN OREQUALTOHIGHSETPOINT(Stepl) UNSAT STANDARD:

a) Reviews CAUTION prior to Step 1: Operation of theRSHX SW radiation monitors is not required to directly support RS functional requirements. -

b) Verifies 1-SW-RI-il 7 greater than the High alarm setpoint by pressing the drawer High pushbutton and observing indication less than current reading.

c) Verifies i-RM-RR-i5OA, Pen 4 is trending with drawer indication.

COMMENTS:

STEP2:

CHECK UNIT 2- OPERATIONS NORMAL. (Step 2)

- UNSAT STANDARD:

Asks Unit 2 if Unit 2 Operation Normal or remembers Unit 2 status from initial briefing.

EVALUATORS NOTE:

If asked: Unit 2 is stable at 100% power.

COMMENTS:

Page 4 of 9

Surry 2012-301 Isolate Leaking RSHX STEP 3:

CHECK AFFECTED HX IN SERVICE. (Step 3)

UNSAT STANDARD:

a) Checks SW Flow to 1-RS-E-1D by observing 1-SW-MOV-103A through 103 D OPEN, GREEN lights Lit, RED Lights Out.

b) Check SW flow to RS-E-ID by observing 1-SW-MOV-104D and 1-SW-MOV-105D OPEN, GREEN Lights Lit, RED Lights Out.

c) Check SW flow by observing SW flow through 1-SW-Fl-I 06D, RS HX D SW OUTLET FLOW.

d) Checks 1-RS-P-2B running by observing breaker closed indications, RED Light Lit and GREEN Light Out.

e) Check amps indicated for 1-RS-P-2B and discharge pressure indication on 1-RS-PI-156B, DISCH PRESS PUMP B.

COMMENTS:

STEP 4:

PLACE ADDITIONAL RS HX(s) IN SERVICE AS REQUIRED. (Step 4)

UNSAT STANDARD:

a) Identifies RS-E-IA, RS-E-IB, and 1-RS-E-1C in service by observing SW valves Open, SW Flow through the HXs, and 1RS-P-1NIB/2A running.

b) Determines sufficient HXs in service to maintain heat sink for Reactor Core following shift to RMT.

COMMENTS:

Page 5 of 9

Surry 2012-301 Isolate Leaking RSHX STEP 5:

CONSULT WITH SHIFT SUPERVISION AND OMOC TO DETERMINE IF THE AFFECTED RSHX SHOULD BE REMOVED FROM SERVICE. (Step 5) UNSAT STANDARD:

a) Reviews CAUTION prior to Step 5: CAUTION: An operating RS train should NOT be secured unless sufficient redundant trains are available for containment heat removal.

b) Consults with Shift Manager (Evaluator) to determine if affected RSHX should be removed from service.

EVALUATORS NOTE:

When asked: State that the OMOC has been consulted and will concur with Candidates decision.

COMMENTS:

STEP 6:

CHECK AFFECTED RSHX TO BE REMOVED FROM SERVICE. (Step 6)

UNSAT STANDARD:

Identifies I -RS-E-1 D to be removed from service.

COMMENTS:

STEP 7:

SAT STOP ASSOCIATED RS PUMP AND PLACE iN PTL: (Step 7)

UNSAT STANDARD:

a) Places control switch for 1-RS-P-2B in PTL.

b) Checks 1-RS-P-2B secured by observing zero (0) amps indicated, GREEN Light Lit and RED Light Out on breaker control switch, and pump discharge pressure on 1-RS-P1-I 56B, DISCH PRESS PUMP B.

c) Acknowledges Annunciator IA-H8, RS PP 2B LOCKOUT OR OL TRIP.

COMMENTS:

Page 6 of 9

Surry 2012-301 Isolate Leaking RSHX STEP 8:

STOP ASSOCIATED RSHX SW PUMP: (Step 8)

UNSAT STANDARD:

a) Places 1-SW-P-5D control switch to Stop.

b) Verifies 1-SW-P-5D stopped by observing GREEN Light On, RED Light Qff.

COMMENTS:

STEP 9:

SAT ISOLATE SW TO 1-RS-E-ID BY CLOSING THE ASSOCIATED MOVS: (Step 9)

UNSAT STANDARD:

a) Reviews NOTE prior to Step 9: NOTE: If an undervoltage condition occurs before CLS reset, the SW MOVs will reopen when voltage is returned to normal.

b) Closes 1-SW-MOV-104D by placing control switch in close position.

c) Verifies 1-SW-MOV-104D closed by observing GREEN Light Lit, and RED Light Off.

d) Closes 1-SW-MOV-105D by placing control switch in close position.

e) Verifies 1-SW-MOV-105D closed by observing GREEN Light Lit, and RED Light Off.

COMMENTS:

STEP 10:

SAT INCREASE SURVEILLANCE ON INSERVICE MONITORS. (Step 10)

UNSAT STANDARD:

a) Locates to RM Panel and observes videographic recorder 1-RM-RR-150A,. and 1-SW-RI-i 14, 1-SW-RI-115, and 1-SW-RI-116.

b) Observes trend stable on 1-RM-RR-150A, pen 1 through 3.

c) Observes trend stable on i-RM-RI-1 14, 115, and 116.

COMMENTS:

Page 7 of 9

Surry 2012-301 Isolate Leaking RSHX STEP 11:

INITIATEACONDITION REPORT. (Step 11)

UNSAT STANDARD:

Candidate states need to initiate a Condition Report (CR) to Shift Manager (Evaluator).

EVALUATORS NOTE:

Inform Candidate that the STA will initiate the CR.

COMMENTS:

STEP 12:

PROVIDE NOTIFICATIONS AS NECESSARY. (Step 12)

UNSAT STANDARD:

Candidate notifies Shift Manager (Evaluator) that the following Notifications are required:

• Shift Supervision

• OMOC

• STA

• Health Physics -

• Instrumentation Department EVALUATORS NOTE:

Acknowledge Notifications are required.

COMMENTS:

STEP 13:

NOTIFY NUCLEAR SHIFT MANAGER (EVALUATOR) STATUS OF TASK. SAT Candidate should report completion of task. UNSAT COMMENTS:

STOP TIME:

Page 8 of 9

Surry 2012-301 Isolate Leaking RSHXD Page 9 of 9

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in the simulator.

• Perform Steps 1RM-D8, 1-SW-Rl-117 HIGH, Step 12.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions

• A LBLOCA has occurred on Unit 1. Unit 2 is operating at stable power level of 100%.

• The Operating Team is currently performing I -E-1, Loss of Reactor or Secondary Coolant.

• 1-E-0, Attachment 1, Step 9d, Check OSRS pump NOT CAVITATING has just been completed.

• Annunciator 1-RM-C8, RS/SW HX D ALERT/FAILURE, and 1-RM-D8.I-SW-Rl-117 HIGH have just been received.

Initiating Cues

• I am the Nuclear Shift Manager. You are the Unit I BOP. You are to perform Annunciator Response Procedure 1-RM.-D8, 1-SW-RI-117 HIGH.

• When you have completed the actions to accomplish this Task, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A LBLOCA has occurred on Unit 1. Unit 2 is operating at stable power level of 100%.

• The Operating Team is currently performing 1 -E-1, Loss of Reactor or Secondary Coolant.

• 1-E-0, Attachment 1, Step 9d, Check OSRS pump NOT CAVITATING has just been completed.

• Annunciator 1-RM-C8, RS/SW HX D ALERT/FAILURE, and 1-RM-D8. 1-SW-Rl-117 HIGH have just been received.

Initiating Cues

• I am the Nuclear Shift Manager. You are the Unit 1 BOP. You are to perform Annunciator Response Procedure 1-RM-D8, 1-SW-RI-117 HIGH.

• When you have completed the actions to accomplish this Task, please inform me.