ML093430150

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Initial Exam 2009-302 Final SIM/In-Plant JPMs
ML093430150
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 12/07/2009
From:
NRC/RGN-II/DRS/OLB
To:
Southern Nuclear Operating Co
References
05-321/09-302, 05-366/09-302
Download: ML093430150 (167)
v • d • e


Text

FACIt.lITY NAME:

HATCH

--~~~----------------------

Section 11 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 FINAL 8IM/IN-PLANT JPM8 CONTENTS:

o Final SIM/ln-Plant JPMs o 'As given' with changes made during administration annotated Location of Electronic Files:

O:\\Hatch Examinations\\lnitial Exam 2009-302 Submitted By:

Bruno Caballero FACILITY NAME: _.....:.H.:.:.,A..:..,:T'-=C:..:.H-=---_________

Section 11 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 FINAL SIM/IN-PLANT JPMS CONTENTS:

D Final SIM/ln-Plant JPMs o 'As given' with changes made during administration annotated Location of Electronic Files:

O:\\Hatch Examinations\\lnitial Exam 2009-302 Submitted By:

Bruno Caballero Verified By: 1M JJ. ~

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FINAL Southern E. I.

atch uclear uclear lant Operations Training JPM Simulator 1 - ALL C.M.EDMUND 10111/2009 TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 1 - ALL

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START A RECIRC MG SET / Adjustable Speed Drive (ASD) FROM THE CONTROL ROOM AUTHOR MEDIA NUMBER TIME F. FAGAN 2009-302 Sim 1 15.0 Minutes RECOMMENDED BY APPROVED BY DATE N/R C.M.EDMUND 10/1112009

c SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009*302 SOO 1 16 02/22/02 Include initial Operator statement RAB RAB 17 05103/02 Revise Simulator Setup DNM DHG 18 03/01105 Deleted "S" from procedure numbers, changed Revision and Rev.

BEB DHG numbers to "Current Version," changed "Reactor Operator" to "Nuclear Plant Operator," changed IC 121 to IC 127 for Simulator Setup, added new prompts, changed location of some steps and 19 05/27/05 Revised Initial License statement for successful completion RAB RAB 20 03/30106 Remove Response Cues RAB RAB 21 01/06/09 This revision is meant for initial training prior to DNM RAB implementation of ASDs on U2 during the 2009 U2 CEB outage. It is the intent of Training & Operations to perform the best training possible gathering feedback from Operators during the process & feeding this information back to Operations prior to implementation to improve procedures prior to final implementation. (Note: originally a new JPM 04.20 was written, however this JPM was revised to modify the task and TO for the equipment and JPM 04.20 not retained). Section for Unit One will be "simulate" in Main Control Room due to modification on simulator to reflect to Unit 2.

10/11/09 Revised for use on 2009-302 Exam FNF CME

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SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERA TIONS TRAINING Media Number:

2009-302 Sim 1 Rev.

Date Reason for Revision Author's Supv's No.

Initials Initials 16 02/22/02 Include initial Operator statement RAB RAE 17 05103/02 Revise Simulator Setup DNM DHG 18 03/01/05 Deleted "S" from procedure numbers, changed Revision and Rev.

BEB DHG numbers to "Current Version," changed "Reactor Operator" to "Nuclear Plant Operator," changed IC 121 to IC 127 for Simulator Setup, added new prompts, changed location of some steps and prompts.

19 05/27/05 Revised Initial License statement for successful completion RAE RAE 20 03/30106 Remove Response Cues RAE RAE 21 01/06109 This revision is meant for initial training prior to DNM RAB implementation of ASDs on U2 during the 2009 U2 CEB outage. It is the intent of Training & Operations to perform the best training possible gathering feedback from Operators during the process & feeding this information back to Operations prior to implementation to improve procedures prior to final implementation. (Note: originally a new JPM 04.20 was written, however this JPM was revised to modify the task and TO for the equipment and JPM 04.20 not retained). Section for Unit One will be "simulate" in Main Control Room due to modification on simulator to reflect changes to Unit 2.

10/11/09 Revised for use on 2009-302 Exam FNF CME

2009*302 Sim 1 Page 1 of6 UNITl 0

UNIT 2 (X)

START A RECIRC MG SET I Adjustable Speed Drive (ASD) FROM THE CONTROL ROOM LR-JP-04.02-21 The task shall be completed when the Adjustable Speed Drive (ASD) has been started and then secured.

004.002 004.002.A, 004.002.E PLANT HATCH JTA IMPORTANCE RATING:

RO 3.50 SRO 3.22 KIA CATALOG NUMBER: 202001K6.02 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.1 SRO 3.2 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

APPROXIMATE COMPLETION TIME:

38.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

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2009-302 Sim 1 Page 1 of 6 UNIT 1 0

UNIT 2 (X)

TASK TITLE:

START A RECIRC MG SET / Adjustable Speed Drive (ASD) FROM THE CONTROL ROOM JPMNUMBER:

LR-JP-04.02-21 TASK STANDARD:

The task shall be completed when the Adjustable Speed Drive (ASD) has been started and then secured.

TASK NUMBER:

004.002 OBJECTIVE NUMBER: 004.002.A, 004.002.E PLANT HATCH JTA IMPORTANCE RATING:

RO 3.50 SRO 3.22 KIA CATALOG NUMBER: 202001K6.02 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.1 SRO 3.2 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

I GENERAL

REFERENCES:

Unit 2 34S0-B31-001-2 (current version) 34AB-B31-001-2 (current version)

I REQUIRED MATERIALS:

Unit 2 34S0-B31-001-2 (current version) marked up to step 7.1.3.1.11 APPROXIMATE COMPLETION TIME:

38.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #102 and leave in FREEZE.

2.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Secure both Recirc Pumps and Close their Discharge valves B.

Raise RWL to >47 inches as indicated on GEMAC.

C.

Use rfB31_29 and open Seal purge valve B31-F016A.

D.

Open Reactor Recirc Pump Suction Valves, 2B31-F023A and 2B31-F023B.

E.

Start up the "2A" Recirc ASD up to step 7.1.3.1.11, with the breaker closed for the ASD, the ASD START pushbutton lit, and RWL > 32".

F.

Have a Marked up copy of 34S0-B31-00 1-2, Recirc system, marked up to step 7.1.3.1.11, G.

Tum OFF the SPDS screens.

H.

Acknowledge/Reset annunciators

3.

INSERT the following Event Trigger:

B31*1 Inserts the following alarms when F031A is fully open (Green light goes out):

  • ASD A - Cooling Normal (White Light Off)

Event Trigger Contents:

(ET portion of ET)

Activate ET B31-1 when 2A Recirc pump discharge valve is full open (green light out) loB31-F031AG1.algToPanel =0
THEN (SCN Portion of ET) lOR loB31-DS42A W 1 f
O d:O; ASD A - Cooling Normal (White Light Off)

IMF mf60211169 f: 1 d:O; ASD A Cooling Trouble (Annunciator On)

+2IMF mf60211170 f: 1 d:O; ASD A Cooling Fault (Annunciator On)

+ lOIMF mf60211146 f: 1 d:O; ASD A Fatal Fault (Annunciator On)

4.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5.

ESTIMATED Simulator SETUP TIME:

15 Minutes

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SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #102 and leave in FREEZE.

2.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Secure both Recirc Pumps and Close their Discharge valves B.

Raise RWL to >47 inches as indicated on GEMAC.

C.

Use rfB31_29 and open Seal purge valve B31-FOI6A.

D.

Open Reactor Recirc Pump Suction Valves, 2B31-F023A and 2B31-F023B.

E.

Start up the "2A" Recirc ASD up to step 7.1.3.1.11, with the breaker closed for the ASD, the ASD START pushbutton lit, and RWL > 32".

F.

Have a Marked up copy of 34S0-B31-001-2, Recirc system, marked up to step 7.1.3.1.11, G.

Tum OFF the SPDS screens.

H.

Acknowledge/Reset annunciators

3.

INSERT the following Event Trigger:

ET#

Description B31-1 Inserts the following alarms when F031A is fully open (Green light goes out):

  • ASD A - Cooling Normal (White Light Off)

Event Trigger Contents:

(ET portion of ET)

Activate ET B31-1 when 2A Recirc pump discharge valve is full open (green light out) loB31-F031AG1.algToPanel =0
THEN (SCN Portion of ET) lOR loB31-DS42A WI f
O d:O; ASD A - Cooling Normal (White Light Off)

IMF mf60211169 f: 1 d:O; ASD A Cooling Trouble (Annunciator On)

+2IMF mf60211170 f:l d:O; ASD A Cooling Fault (Annunciator On)

+lOIMF mf60211146 f:l d:O; ASD A Fatal Fault (Annunciator On)

4.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5.

ESTIMATED Simulator SETUP TIME:

15 Minutes

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

Unit 2 is in cold shutdown

2.

SPDS is Out of Service and being worked.

3.

"A" Recirc Pump is required for forced circulation.

4.

CRD seal purge is in service with 1.9 gpm flow to the "A" seals.

5.

Maintenance has performed all applicable sections for venting/purging of the "A" Recirc Pump seals IA W 52CM-B31-003-0.

6.

34S0-B31-001-2, Recirc system, is complete up to step 7.1.3.1.11,

7.

34S0-B31-001-2 Attachment 5 "Recirc Pump Startup Prerequisites" was just completed and is SAT for a start of the "A" Recirc Pump.

INITIATING CUES:

Start 2A Recirc Pump IA W, 34S0-B31-001-2 "Reactor Recirculation System" Section 7.1.3., starting at step 7.1.3.1.11,

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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

Unit 2 is in cold shutdown

2.

SPDS is Out of Service and being worked.

3.

"A" Recirc Pump is required for forced circulation.

4.

CRD seal purge is in service with 1.9 gpm flow to the "A" seals.

5.

Maintenance has performed all applicable sections for venting/purging of the "A" Recirc Pump seals IA W 52CM-B31-003-0.

6.

34S0-B31-001-2, Recirc system, is complete up to step 7.1.3.1.11,

7.

34S0-B31-001-2 Attachment 5 "Recirc Pump Startup Prerequisites" was just completed and is SAT for a start of the "A" Recirc Pump.

INITIATING CUES:

Start 2A Recirc Pump IA W, 34S0-B31-001-2 "Reactor Recirculation System" Section 7.1.3., starting at step 7.1.3.1.11,

NOTE: Unless otherwise indicated, all actions are carried out at paneI2H11-P601.

2009-302 Sim 1 Page 4 of6

~4.1fltJNS~T (C()l\\1MENTS START TIME: ___ _

PROMPT:

Once the applicant has identified the correct procedure, Provide the applicant with a copy of 34S0-B31-001-2, Recirc system, marked up to step 7.1.3.1.11,

1. Operator obtains procedure and Operator has obtained 34S0-B31-SAT/UNSAT reviews the procedure's precautions 001-2 and reviewed the and limitations.

precautions and limitations.

NOTE: RWL indication on 2H11-P603 is not corrected. The operator must subtract 15 inches from the indicated RWL. Therefore RWL is required to be above 47 inches (32 + 15 = 47).

2. Confirm RWL is greater than +32 At paneI2H11-P603, the SAT/UNSAT inches.

Operator VERIFIES that RWL is greater than +32 inches actual level (> 47 inches indicated).

PROMPT:

IF addressed by the Operator, INFORM the Operator that Attachment 5 was complete and acceptable within the last 15 minutes.

3. Confirm/Close Reactor Recirc Pump Operator confirms PUMP DISCH SAT/UNSAT Discharge Valve, 2B31-F031A.

VLV 2B31-F031A is CLOSED, green light illuminated.

4. Confirm ASD A START pushbutton Operator confirms ASD A SAT/UNSAT indicating lamp is illuminated.

START pushbutton indicating lamp is illuminated

5. Visually Confirm the ASD "A" Operator confirms the ASD "A" SAT/UNSAT startup temperature limits are still startup temperature limits are still acceptable.

acceptable by observing temperatures on 2B31-R601 at Pane12H11-P614.

Note:

The above step may not be performed, since the Initiating Cue states that Attachment 5 (checking startup temperatures) has just been performed and all temperatures are acceptable.

PROMPT:

Once the applicant has identified the 2B31-R601 recorder, INFORM the applicant that all temperatures are acceptable.

(** Indicates critical step)

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PERFORMANCE STEP STANDARD NOTE: Unless otherwise indicated, all actions are carried out at pane12Hll-P601.

2009-302 Sirn 1 Page 4 of 6 SATIUNSAT (COMMENTS START TIME: ___ _

PROMPT:

Once the applicant has identified the correct procedure, Provide the applicant with a copy of 34S0-B31-001-2, Recirc system, marked up to step 7.1.3.1.11,

1. Operator obtains procedure and Operator has obtained 34S0-B31-SAT/UNSAT reviews the procedure's precautions 001-2 and reviewed the and limitations.

precautions and limitations.

NOTE: RWL indication on 2HII-P603 is not corrected. The operator must subtract 15 inches from the indicated RWL. Therefore RWL is required to be above 47 inches (32 + 15 = 47).

2. Confirm RWL is greater than +32 At pane12Hll-P603, the SAT/UNSAT inches.

Operator VERIFIES that RWL is greater than +32 inches actual level (> 47 inches indicated).

PROMPT:

IF addressed by the Operator, INFORM the Operator that Attachment 5 was complete and acceptable within the last 15 minutes.

3. Confirm/Close Reactor Recirc Pump Operator confirms PUMP DISCH SAT/UNSAT Discharge Valve, 2B31-F031A.

VLV 2B31-F031A is CLOSED, green light illuminated.

4.

Confirm ASD A START pushbutton Operator confirms ASD A SAT/UNSAT indicating lamp is illuminated.

START pushbutton indicating lamp is illuminated

5. Visually Confirm the ASD "A" Operator confirms the ASD "A" SAT/UNSAT startup temperature limits are still startup temperature limits are still acceptable.

acceptable by observing temperatures on 2B31-R601 at Pane12HII-P614.

Note:

The above step may not be performed, smce the Imtlating Cue states that Attachment 5 (checking startup temperatures) has just been performed and all temperatures are acceptable.

PROMPT:

Once the applicant has identified the 2B31-R601 recorder, INFORM the applicant that all temperatures are acceptable.

(** Indicates critical step)

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7. Confirm the following:
  • The ASD A STARTING light illuminates
  • The ASD A START light extinguishes.
  • 2B31-F031A, Recirc Pump A Disch Vlv, starts to JOG OPEN 2 seconds after the ASD A STARTING light illuminates.
  • The ASD A speed increases to

-370 RPM on 2B31-R660A and -22% on 2B31-R661A in

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about 4 seconds.

  • The ASD A RUNNING light illuminates.
  • The ASD A STARTING light extinguishes.

<96 seconds after the Recirc ASD A STARTING light illuminates.

  • Recirc A Flow, indicates 11,000 - 13,000 GPM on 2B31-R617.
  • Acknowledge expected alarms

(** Indicates critical step)

Operator depresses ASD A START PUSH BUTTON.

Operator confirms the following:

  • The ASD A STARTING light illuminates.
  • The ASD A START light extinguishes.
  • 2B31-F031A, Recirc Pump A Disch Vlv, starts to JOG OPEN 2 seconds after the ASD A STARTING light illuminates.

on 2B31-R661A in about 4 seconds.

  • The ASD A RUNNING light illuminates.
  • The ASD A STARTING light extinguishes.
  • 2B31-F031A, Recirc Pump A Disch Vlv, is FULL OPEN <96 seconds after the Recirc ASD A STARTING light illuminates.
  • Recirc A Flow, indicates 11,000 - 13,000 GPM on 2B31-R617.
  • Acknowledges expected alarm 602-227, "Recirc Loop B Out Of Service" 2009-302 Sim 1 Page 5 of6 SATlUNSAT* *

.. (C~MJ1ENTS SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT PERFORMANCE STEP

    • 6. DEPRESS the ASD A START pushbutton.
7. Confirm the following:
  • The ASD A STARTING light illuminates
  • The ASD A START light extinguishes.
  • 2B31-F031 A, Recirc Pump A Disch Vlv, starts to JOG OPEN 2 seconds after the ASD A STARTING light illuminates.
  • The ASD A speed increases to

~370 RPM on 2B31-R660A and ~22% on 2B31-R661A in

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about 4 seconds.

  • The ASD A RUNNING light illuminates.
  • The ASD A STARTING light extinguishes.

<96 seconds after the Recirc ASD A STARTING light illuminates.

  • Recirc A Flow, indicates 11,000 - 13,000 GPM on 2B31-R617.
  • Acknowledge expected alarms

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(** Indicates critical step)

STANDARD Operator depresses ASD A START PUSH BUTTON.

Operator confirms the following:

  • The ASD A STARTING light illuminates.
  • The ASD A START light extinguishes.
  • 2B31-F03IA, Recirc Pump A Disch Vlv, starts to JOG OPEN 2 seconds after the ASD A STARTING light illuminates.

on 2B31-R661A in about 4 seconds.

  • The ASD A RUNNING light illuminates.
  • The ASD A STARTING light extinguishes.
  • 2B31-F031A, Recirc Pump A Disch Vlv, is FULL OPEN <96 seconds after the Recirc ASD A STARTING light illuminates.
  • Recirc A Flow, indicates 11,000 - 13,000 GPM on 2B31-R617.
  • Acknowledges expected alarm 602-227, "Recirc Loop B Out Of Service" 2009-302 Sim 1 Page 5 of 6 SATIUNSAT (COM.MENTS SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT

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2009-302 Sim 1 Page 6 of6

.*.**.* S.t\\.'I'/UN$i\\l.'.*

(COMMENTS' PROMPT:

WHEN the operator addresses Attachment 5, INFORM the operator that another operator will complete Attachment 5.

NOTE: This step may not be done due to the cooling and fault alarms coming in on the ASD.)

8. Complete remainder of Attachment 5.

Operator has verified Attachment SAT/UNSAT 5 will be completed.

Simulator Operator confirm ET B31-1 is triggered when the green light extinguishes on F031A.

NOTE: The following cooling fault automatically occurs based on 2B31-F031A being full open.

Operator places the ASD A control switch to the STOP position OR DEPRESSES the ASD A Shutdown pushbutton within 5 minutes of receiving the

-alarm&:- M '! ~

1'2--0'2.'Oq NOTE:

The terminating cue shall be given to the Operator when:

With no reasonable progress, the Operator exceeds double the allotted time.

Operator has tripped or shutdown ASD A.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

SAT/UNSAT END TIME: ___ _

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PERFORMANCE STEP STANDARD 2009-302 Sim 1 Page 6 of 6 SATIUNSAT (COMMENTS PROMPT:

WHEN the operator addresses Attachment 5, INFORM the operator that another operator will complete Attachment 5.

NOTE: This step may not be done due to the cooling and fault alarms coming in on the ASD.)

8. Complete remainder of Attachment 5.

Operator has verified Attachment SAT/UNSAT 5 will be completed.

Simulator Operator confirm ET B31-1 is triggered when the green light extinguishes on F031A.

NOTE: The following cooling fault automatically occurs based on 2B31-F031A being full open.

Operator places the ASD A

  • 602-125 "ASD A Cooling control switch to the STOP position OR DEPRESSES the Trouble" ASD A Shutdown pushbutton
  • 602-126 "ASD A Cooling Fault"

~l.. ithif!: ;5 miHYt@s Gt: f~G~il.lillg the

  • 602-102 ASD A FATAL

-alarm&:- M '! ~

1'2-- o '2..' oq FAULT NOTE: The terminating cue shall be given to the Operator when:

With no reasonable progress, the Operator exceeds double the allotted time.

Operator has tripped or shutdown ASD A.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

SAT/UNSAT END TIME: ___

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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

Unit 2 is in cold shutdown

2.

SPDS is Out of Service and being worked.

3.

"A" Recirc Pump is required for forced circulation.

4.

CRD seal purge is in service with 1.9 gpm flow to the "A" seals.

5.

Maintenance has performed all applicable sections for venting/purging of the "A" Recirc Pump seals IA W 52CM-B31-003-0.

6.

34S0-B31-001-2, Recirc system, is complete up to step 7.1.3.1.11,

7.

34S0-B31-00 1-2 Attachment 5 "Recirc Pump Startup Prerequisites" was just completed and is SAT for a start of the "A" Recirc Pump.

INITIATING CUES:

Start 2A Recirc Pump IA W, 34S0-B31-001-2 "Reactor Recirculation System" Section 7.1.3., starting at step 7.1.3.1.11,

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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

Unit 2 is in cold shutdown

2.

SPDS is Out of Service and being worked.

3.

"A" Recirc Pump is required for forced circulation.

4.

CRD seal purge is in service with 1.9 gpm flow to the "A" seals.

5.

Maintenance has performed all applicable sections for venting/purging of the "A" Recirc Pump seals lAW 52CM-B31-003-0.

6.

34S0-B31-001-2, Recirc system, is complete up to step 7.1.3.1.11,

7.

34S0-B31-001-2 Attachment 5 "Recirc Pump Startup Prerequisites" was just completed and is SAT for a start of the "A" Recirc Pump.

INITIATING CUES:

Start 2A Recirc Pump lAW, 34S0-B31-001-2 "Reactor Recirculation System" Section 7.1.3., starting at step 7.1.3.1.11,

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N/R

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FI Southern E. I. Hatch AL uclear uclear Plant Operations Training JPM Simulator 2 - ALL C.M.EDMUND 10/11/2009

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TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 2 - ALL RESTORE Reactor Water Level USING RHRSW AUTHOR MEDIA NUMBER F. Fagan 2009-302 Sim 2 RECOMMENDED BY APPROVED BY N/R C.M.EDMUND TIME 12.0 Minutes DATE 10/1112009

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SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET 2009-302 Sim 2 Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Sim 2

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' c Initials Initials

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    • *****.*;.* ** *************.****.* *. *.*.ii...........

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. **.*..i 06 11102/00 Include objective number RAE DHG 07 03112120 Include initial Operator statement RAE RAE 08 06114/05 Revised Initial License statement for successful completion RAE RAB 09 04121106 Remove Response Cues RAB RAE 10 05119/07 Remove E11-F003 and F048 to match the procedure.

DHG RAB 11 09/18/08 For Unit 1, added critical steps to open F068AIB to JWP RAB reflect plant procedure.

10/11/09 Revised for use on 2009-302 exam FNF CME SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH

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FORM TITLE: TRAINING MATERIAL REVISION SHEET 2009-302 Sim 2 Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Sim 2 Rev...

Date Reason for Revision Author's Supv's Initials Initials No.

06 11102/00 Include objective number RAE DHG 07 03/12120 Include initial Operator statement RAE RAE 08 06/14/05 Revised Initial License statement for successful completion RAB RAB 09 04121106 Remove Response Cues RAB RAE 10 05/19/07 Remove E11-F003 and F048 to match the procedure.

DHG RAB 11 09/18/08 For Unit 1, added critical steps to open F068AJB to JWP RAB reflect plant procedure.

10/11/09 Revised for use on 2009-302 exam FNF CME

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    • T:ASI{~iTLE; jpM)~ER:

UNIT 1 (X)

RESTORE Reactor Water Level USING RHRSW LR-JP-34.12-11 2009-302 Sim 2 Page 1 of7 UNIT 2 (X)

The task shall be completed when the Operator has successfully started one loop of RHRSW with RHRSW injecting into the Reactor per 31EO-EOP-ll O.

034.012

{)B.JEctI'VENUMnER: 034.012.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.86 SRO Not Available KIA CATALOG NUMBER:

295031EA108

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KIA CATALOG JTA IMPORTANCE RATING:

RO 3.80 SRO 3.90 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

(current versions)

APPROXIMATE COMPLETION TIME:

12.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE TASK TITLE:

JPMNUMBER:

UNIT 1 (X)

RESTORE Reactor Water Level USING RHRSW LR-JP-34.12-11 2009-302 Sim 2 Page 1 of7 UNIT 2 (X)

TASK STANDARD:

The task shall be completed when the Operator has successfully started one loop of RHRSW with RHRSW injecting into the Reactor per 31EO-EOP-ll O.

TASK NUMBER:

034.012 OBJECTIVE NUMBER: 034.012.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.86 SRO Not Available KIA CATALOG NUMBER:

295031EA108

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KIA CATALOG JTA IMPORTANCE RATING:

RO 3.80 SRO 3.90 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

I GENERAL

REFERENCES:

Unit 1 Unit 2 31EO-EOP-llO-l 31EO-EOP-II0-2 31EO-EOP-015-1 31EO-EOP-015-2 (current versions)

(current versions)

I REQUIRED MATERIALS:

Unitt Unit 2 31EO-EOP-11O-1 31EO-EOP-IlO-2 (current version)

(current version)

Key for RHRSW Manual Key for RHRSW Manual Override Override APPROXIMATE COMPLETION TIME:

12.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

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SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #113 and leave in FREEZE.

2009-302 Sim 2 Page2of7

2.

Make sure RECORDER POWER is TURNED ON. Roll Chart Recorders and Process Computer Typers forward. Ensure any information printed on the Process Computer Typer from previous ICs is removed.

3. INSERT the following MALFUNCTIONS:

mfB21_48A Steam Line A Break (After Restrictor) (Var) 100 100 00000 mfG31_242 RWCU Non-Isol Leak (0-10000 gpm) 7 100 00000 mtE4L107 HPCI Failure to Start (FOOl Stuck) 00000 rntE51_11O RCIC Turbine Trip 00000 mfS11_227B SUT 2D Failure 00000 mtE1Ll15A RHR Pump A Trip 00000 mtE1Ll15B RHR Pump B Trip 00000 mtE11_115C RHR Pump C Trip 00000 rntE11_115D RHR Pump D Trip 00000 rntE21_102A Core Spray Pump A Trip 00000 rntE21_102B Core Spray Pump B Trip 00000 mfC11_30A Control Rod Drive Pump A Trip 00000 mfC11_30B Control Rod Drive Pump B Trip 00000

4.

INSERT the following REMOTE FUNCTIONS:

rfE11167 2E11-FO 17 A&B Override 5 Min Timer ORIDE rtP64-332 Drywell Chillers B006A Lockout Reset RESET rfp64-333 Drywell Chillers B006B Lockout Reset RESET

(** Indicates critical step)

(

(

PERFORMANCE STEP STANDARD SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #113 and leave in FREEZE.

2009-302 Sim 2 Page 2 of7 SATIUNSAT (COMMENTS

2.

Make sure RECORDER POWER is TURNED ON. Roll Chart Recorders and Process Computer Typers forward. Ensure any information printed on the Process Computer Typer from previous ICs is removed.

3.

INSERT the following MALFUNCTIONS:

MALF#

TITLE FINAL RAMP ACT.

VALUE RATE TIME mfB21_48A Steam Line A Break (After Restrictor) (Var) 100 100 00000 mfG3l_242 RWCU Non-Isol Leak (0-10000 gpm) 7 100 00000 mfE4l_107 HPCI Failure to Start (FOOl Stuck) 00000 mfE5l_110 RCIC Turbine Trip 00000 mfSll_227B SUT 2D Failure 00000 mtEll_115A RHR Pump A Trip 00000 mtElLl15B RHR Pump B Trip 00000 mtEll_115C RHR Pump C Trip 00000 mfEll_115D RHR Pump D Trip 00000 mtE2l_l02A Core Spray Pump A Trip 00000 mtE21_l02B Core Spray Pump B Trip 00000 mfCll_30A Control Rod Drive Pump A Trip 00000 mfClL30B Control Rod Drive Pump B Trip 00000

4.

INSERT the following REMOTE FUNCTIONS:

REM #

DESCRIPTION STATUS rtEll167 2Ell-F017A&B Override 5 Min Timer ORIDE rfP64-332 Drywell Chillers B006A Lockout Reset RESET rfp64-333 Drywell Chillers B006B Lockout Reset RESET

(** Indicates critical step)

(

2009-302 Sim 2 Page 3 of7

5.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A.

Take the simulator out of FREEZE and allow simulator to run until RWL is at the Top of Active Fuel.

B.

Restart the DryweU Chillers and Coolers.

C.

Reopen the 316s.

D.

Place Rx Mode Switch to Shutdown E.

Open 7 ADS Valves F.

Override 2P52-F565 switch to Open G.

At -70" RWL, delete steam line break H.

Close 2Ell-F017A

6.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

7.

ESTIMATED Simulator SETUP TIME:

20 Minutes

(** Indicates critical steD)

(

(

PERFORMANCE STEP STANDARD 2009-302 Sim 2 Page 3 of7 SATIUNSAT (COM.MENTS

5.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A.

Take the simulator out of FREEZE and allow simulator to run until RWL is at the Top of Active Fuel.

B.

Restart the Drywell Chillers and Coolers.

C.

Reopen the 316s.

D.

Place Rx Mode Switch to Shutdown E.

Open 7 ADS Valves F.

Override 2P52-F565 switch to Open G.

At -70" RWL, delete steam line break H.

Close 2EII-F017A

6.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

7.

ESTIMATED Simulator SETUP TIME:

20 Minutes

(** Indicates critical steo)

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has had a LOCA.
2. RWL is below the Top of Active Fuel and decreasing.
3. HPCI and RCIC have isolated on low steam supply pressure.
4. SUT "2D" is de-energized.
5. RHR pumps" A, B, C, & D" have tripped.
6. Core Spray pumps "A" and B" have tripped.
7. The EOP jumpers to override the 5 minute timer have been installed for 2EII-F017A & B.

INITIATING CUES:

IA W 31EO-EOP-IlO-2, "Alternate RPV Water Level Control" maximize injection of RHRSW into the reactor using the "A" loop.

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has had a LOCA.
2. RWL is below the Top of Active Fuel and decreasing.
3. HPCl and RClC have isolated on low steam supply pressure.
4. SUT "2D" is de-energized.
5. RHR pumps" A, B, C, & D" have tripped.
6. Core Spray pumps "A" and B" have tripped.
7. The EOP jumpers to override the 5 minute timer have been installed for 2Ell-F017A & B.

INITIATING CUES:

lAW 31EO-EOP-IlO-2, "Alternate RPV Water Level Control" maximize injection of RHRSW into the reactor using the "A" loop.

1. Operator locates the correct Operator locates 31EO-EOP-11O-procedure.

2, "Alternate RPV Water Level Control" NOTE: All steps are at pane12H11-P601 unless noted differently.

2. Confirm that RHR Loop A is not The Operator has VERIFIED that operating in the LPCI mode.

RHR Loop A is not operating in the LPCI mode.

3. Confirm or stop RHR Pumps RHR PUMPs 2E11-C002A and C 2E11-COO2A and C.

are STOPPED, green lights illuminated.

4. Confirm or close the following valves:

The following valves are 2Ell-F01O CWSED, green light illuminated:

2Ell-F016A RHR CROSSTIE VLV, 2Ell-F028A 2Ell-F01O 2Ell-F017A CNMT SPRAY OUTBD VLV, 2E11-F068A 2E11-F016A TORUS SPRAY OR TESTVLV, 2E11-F028A RHR OUTBD INJ VLV, 2E11-F017A HXDISCHVLV, 2E11-F068A 2009-302 Sim 2 Page 5 of7 START TIME: ___ _

SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT/UNSAT PROMPT:

2E 11-FO lOis normally de-energized in the closed position. If the Operator indicates that this is the condition of the valve, that portion of Step 4 is acceptable.

(** Indicates critical step)

IF the Operator requests the SO to verify the valve position, as SO, INFORM the Operator that valve 2E11-F01O has been verified closed locally.

IF the Operator wants the valve energized, the simulator Operator should TOGGLE REMOTE FUNCTION rfE11135, "E11-F01O Breaker Rackout," to ON.

(

(

(

PERFO~NCESTEP STANDARD

1. Operator locates the correct Operator locates 31EO-EOP-llO-procedure.

2, "Alternate RPV Water Level Control" NOTE: All steps are at pane12HII-P60l unless noted differently.

2. Confirm that RHR Loop A is not The Operator has VERIFIED that operating in the LPCI mode.

RHR Loop A is not operating in the LPCI mode.

3. Confirm or stop RHR Pumps RHR PUMPs 2EII-C002A and C 2E ll-C002A and C.

are STOPPED, green lights illuminated.

4. Confirm or close the following valves:

The following valves are 2Ell-FOlO CLOSED, green light illuminated:

2Ell-F016A RHR CROSSTIE VLV, 2EII-F028A 2EII-FOlO 2Ell-F0l7A CNMT SPRAY OUTBD VLV, 2EI]-F068A 2EII-FOI6A TORUS SPRAY OR TESTVLV, 2Ell-F028A RHR OUTBD IN] VLV, 2Ell-F0l7A HX DISCH VLV, 2EII-F068A 2009-302 Sim 2 Page 5 of7 SATIUNSAT (COMMENTS START TIME: ___ _

SAT/UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT PROMPT:

2EII-FOIO is normally de-energized in the closed position. If the Operator indicates that this is the condition of the valve, that portion of Step 4 is acceptable.

(** Indicates critical step)

IF the Operator requests the SO to verify the valve position, as SO, INFORM the Operator that valve 2EII-FOlO has been verified closed locally.

IF the Operator wants the valve energized, the simulator Operator should TOGGLE REMOTE FUNCTION rfEl1135, "EII-FOlO Breaker Rackout," to ON.

5. Open the following valves:

2Ell-FOI5A

6. Prelube RHRSW Pumps 2Ell-COOIA and C.

STANDARD The operator:

Verifies RHR INBD INJ VLV, 2EI1-FOI5A is open, red light illuminated.

Places RHRSW CROSSTIE VLV, 2EI1-F073A, key lock switch to open, red light illuminated.

Places RHRSW VL V, 2E 11-F075A, key lock switch to open, red light illuminated.

The RHR SERVICE WATER LUBE V ALVES push-button has been DEPRESSED for RHRSW Loop A pumps.

2009-302 Sim 2 Page 6 of7 S1\\..Tf(JNSAT ** *

. {CPMl\\,IENTSJ SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT NOTE: 2EII-F068B does not require being opened to crosstie the RHRSW divisions, but if it is opened it does not decrease any available flow to the reactor.

7. Place Interlock Override Vlv 2El1-The operator PLACES Interlock SAT I UNSAT F068A keylock switch in OVERRIDE Override Vlv 2EII-F068A
8. Position 2EI1-F068A to 45% open
  • .Place~~
  • . *Seffice~a,tel'P~ll1p

(:~pn~01s'Vit5~i~1\\1ANUAI./.*

QVERIn) position:

11. Open Service Water Crosstie Valves 2Ell-F1l9A and B, if required.

keylock switch in the OVERRIDE position.

The operator POSITIONS 2El1-F068A to 45% open as indicated on 2Ell-R600A.

The operator places the Division I SERVICE WATER PUMP CONTROL switch, 2El1-S19A, in MANUAL OVERRD.

The operator places SERVICE WATER PUMP 2EI1-COOlA and C control switch to START, red light illuminated.

The Operator has identified that SERV WTR CROSSTIE VLV 2EII-FI19A(B) does not need to be opened.

SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT/UNSAT NOTE: RHRSW System has no inoperable components and is capable of injecting to the vessel without the crosstie valve being opened. Only the A loop of RHRSW is needed.

(** Indicates critical step)

5.
6.
7.

S.

    • 9.
    • 10.
11.

PERFORMANCE STEP STANDARD Open the following valves:

The operator:

2Ell-F015A Verifies RHR INBD IN} VL V, 2Ell-F015A is open, red light illuminated.

2EII-F073A Places RHRSW CROSSTIE VLV, 2Ell-F073A, key lock switch to open, red light illuminated.

2EII-F075A Places RHRSW VLV, 2Ell-F075A, key lock switch to open, red light illuminated.

Prelube RHRSW Pumps TheRHR SERVICE WATER 2EII-COOIA and C.

LUBE VALVES push-button has been DEPRESSED for RHRSW Loop A pumps.

2009-302 Sim 2 Page 6 of 7 SATIUNSAT COMMENTS*

SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT NOTE: 2EII-F068B does not require being opened to crosstie the RHRSW divisions, but if it is opened it does not decrease any available flow to the reactor.

Place Interlock Override Vlv 2El1-The operator PLACES Interlock SAT/UNSAT F068A keylock switch in OVERRIDE Override Vlv 2EII-F068A keylock switch in the OVERRIDE position.

Position 2EII-F068A to 45% open The operator POSITIONS 2Ell-SAT/UNSAT F068A to 45% open as indicated on 2EII-R600A.

Place RHR* Service Water Pump The operator places the Division I SAT/UNSAT Control switch in MANUAL SERVICE WATER PUMP OVERRD position.

CONTROL switch, 2Ell-S19A, in MANUAL OVERRD.

Start RHRSW Pumps The operator places SERVICE SAT/UNSAT 2EII-COOIA and C.

WATER PUMP 2EII-COOIA and C control switch to START, red light illuminated.

Open Service Water Crosstie Valves The Operator has identified that SAT/UNSAT 2Ell-F1l9A and B, ifrequired.

SERV WTR CROSSTIE VLV 2Ell-F1l9A(B) does not need to be opened.

NOTE: RHRSW System has no inoperable components and is capable of injecting to the vessel without the crosstie valve being opened. Only the A loop of RHRSW is needed.

(** Indicates critical step)

(

2009-302 Sim 2 Page 7 of7 N01E: In the next step, flow will exceed 7600 gpm when 2Ell-FOI7A is opened.

The intent is that flow be reduced and stabilized at or below 7600 gpm prior to the operator finishing the task unless SS approval is granted to exceed 7600 gpm.

RHR OUTBD INJ VLV, 2Ell-FOI7A is THR01TLED OPEN, to maintain injection flow at less than or equal to 7600 gpm flow on RHR FLOW indicator, 2EII-R602A, with reactor water level increasing.

SAT/UNSAT PROMPT:

IF the Operator addresses RWL band, as the Shift Supervisor, INFORM the Operator that another Operator has been directed to control flowlRWL.

PROMPT:

IF the Operator addresses system restoration, as the Shift Supervisor, INFORM the Operator that it is not desired at this time.

PROMPT:

IF the Operator requests permission to exceed RHRSW flow limitations, as the Shift Supervisor, INFORM the Operator that the limitations may be exceeded until RWL is above TAF.

13.
14.

Throttles closed 2Ell-F068A, Hx The operator throttles 2Ell-Discharge Valve.

F068A, Hx Discharge Valve, control switch to CLOSE.

Place Interlock Override Vlv 2Ell-The operator PLACES Interlock F068A keylock switch in NORMAL Override Vlv 2EII-F068A keylock switch in the NORMAL position.

NOTE: The terminating cue shall be given to the Operator when:

With no reasonable progress, the Operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

SAT/UNSAT SAT/UNSAT END TIME: ___ _

(

(

    • 12.

PERFORMANCE STEP STANDARD 2009-302 Sim 2 Page 7 of 7 SATIUNSAT (COMMENTS NOTE: In the next step, flow will exceed 7600 gpm when 2Ell-FOI7A is opened.

The intent is that flow be reduced and stabilized at or below 7600 gpm prior to the operator finishing the task unless SS approval is granted to exceed 7600 gpm.

Throttle RHR Outbd Injection Valve, RHR OUTBD IN] VLV, SAT/UNSAT 2EII-FOI7 A, to control injection 2EII-FOI7A is THROTTLED OPEN, to maintain injection flow at less than or equal to 7600 gpm flow on RHR FLOW indicator, 2EII-R602A, with reactor water level increasing.

PROMPT:

IF the Operator addresses RWL band, as the Shift Supervisor, INFORM the Operator that another Operator has been directed to control flowlRWL.

PROMPT:

IF the Operator addresses system restoration, as the Shift Supervisor, INFORM the Operator that it is not desired at this time.

PROMPT:

IF the Operator requests permission to exceed RHRSW flow limitations, as the Shift Supervisor, INFORM the Operator that the limitations may be exceeded until RWL is above TAP.

13.
14.

Throttles closed 2Ell-F068A, Hx The operator throttles 2Ell-Discharge Valve.

F068A, Hx Discharge Valve, control switch to CLOSE.

Place Interlock Override Vlv 2Ell-The operator PLACES Interlock F068A keylock switch in NORMAL Override Vlv 2EII-F068A keylock switch in the NORMAL position.

NOTE: The terminating cue shall be given to the Operator when:

With no reasonable progress, the Operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

SAT/UNSAT SAT/UNSAT END TIME: ___ _

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has had a LOCA.
2. RWL is below the Top of Active Fuel and decreasing.
3. HPCI and RCIChave isolated on low steam supply pressure.
4. SUT "2D" is de-energized.
5. RHR pumps" A, B, C, & D" have tripped.
6. Core Spray pumps "A" and B" have tripped.
7. The EOP jumpers to override the 5 minute timer have been installed for 2EI1-F017A & B.

INITIATING CUES:

IA W 31EO-EOP-II0-2, "Alternate RPV Water Level Control" maximize injection ofRHRSW into the reactor using the "A" loop.

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has had a LOCA.
2. RWL is below the Top of Active Fuel and decreasing.
3. BPCI and RCIC have isolated on low steam supply pressure.
4. SUT "2D" is de-energized.
5. RHR pumps" A, B, C, & D" have tripped.
6. Core Spray pumps "A" and B" have tripped.
7. The EOP jumpers to override the 5 minute timer have been installed for 2EU-F017A & B.

INITIATING CUES:

IA W 3IEO-EOP-Il 0-2, "Alternate RPV Water Level Control" maximize injection ofRHRSW into the reactor using the "A" loop.

(

(

N/R FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 3 - ALL C.M.EDMUND 1010912009 SOUTHERN.\\

COMPANY Energy to Serve Your World SM

(

TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 3 - ALL EMERGENCY DEPRESS THE REACTOR USING THE HEAD VENTSIDRYWELL COOLERS AUTHOR MEDIA NUMBER F. Pagan 2009-302 Sirn 3 RECOMMENDED BY APPROVED BY N/R C.M.EDMUND 10 Minutes DATE 1010912009 Energy to Serve Your World sM

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Sim 3

.#~V;~9r.** Ii i<

...*....*............. ii\\'D.~f~ci.*.x....... *c;Lf-.L<.....**.....

.........*..**..* Author~s.*.**..* Sllpy~s;**

lii.i.{..*........-'..'~~~X.. *.*..*.............

..........i.. ii~.-;...c.~\\I;l)-:'\\..

....*... c....*..

..**.**...* <i.........;.

initials..

Initials; 00 08/05/96 Initial development RAB DHG 01 03/05/99 Revised due to new simulator computer.

SCB DHG 02 03/13/00 Format modification, change time allowance based on RAB DHG running, modify title 03 11106/00 Include objective number RAB DHG 04 03/19/02 Include initial operator statement RAB RAB 05 06/21105 Revised Initial License statement for successful RAB RAB completion 06 05/08/06 Remove Response Cues RAB RAB 10/09/09 Revised for use on 2009-302 Exam FNF CME

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Sim 3 Rev. No.

Date Reason for Revision Author's Supv's Initials Initials 00 08/05/96 Initial development RAB DHG 01 03/05/99 Revised due to new simulator comj)uter.

SCB DHG 02 03113/00 Format modification, change time allowance based on RAB DHG running, modify title 03 11106/00 Include objective number RAB DHG 04 03119/02 Include initial operator statement RAB RAB 05 06/21105 Revised Initial License statement for successful RAB RAB completion 06 05/08/06 Remove Response Cues RAB RAB 10/09/09 Revised for use on 2009-302 Exam FNF CME

2009-302 Sim 3 Page lof6 UNIT 1 ()

UNIT 2 (X)

EMERGENCY DEPRESS THE REACTOR USING THE HEAD VENTSIDRYWELL COOLERS LR-JP-20198-06 The task shall be complete when the operator has initiated the emergency depress process with the Head VentslDrywell Coolers, per 31EO-EOP-108-2.

201.098 OBJECllVENlJMBER:* 201.098.A PLANT HATCH JTA IMPORTANCE RATING:

RO 4.57 SRO 3.66 KIA CATALOG NUMBER: 295025A1.01 KIA CATALOG JTA IMPORTANCE RATING:

RO 2.9 SRO 3.0 OPERA TOR APPLICABILITY:

Nuclear Plant Operator (NPO)

APPROXIMATE COMPLETION TIME:

10 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE 2009-302 Sim 3 Page 1 of 6 UNIT 1 ()

UNIT 2 (X)

TASK TITLE:

JPMNUMBER:

TASK STANDARD:

TASK NUMBER:

EMERGENCY DEPRESS THE REACTOR USING THE HEAD VENTSIDRYWELL COOLERS LR-JP-20198-06 The task shall be complete when the operator has initiated the emergency depress process with the Head VentsIDrywell Coolers, per 31EO-EOP-108-2.

201.098 OBJECTIVE NUMBER: 201.098.A PLANT HATCH JTA IMPORTANCE RATING:

RO 4.57 SRO 3.66

(

KIA CATALOG NUMBER: 295025A1.01 KIA CATALOG JTA IMPORTANCE RATING:

RO 2.9 SRO 3.0 OPERA TOR APPLICABILITY:

Nuclear Plant Operator (NPO)

I GENERAL

REFERENCES:

Unit 2 31EO-EOP-108-2 34S0-T47-001-2 34S0-T48-002-2 I REQUIRED MATERIALS:

Unit 2 31EO-EOP-108-2 34S0-T47-001-2 34S0-T48-002-2 APPROXIMATE COMPLETION TIME:

10 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #113 and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS:

IMA~F~:};

Ii.***.......

... **TI'fPE;*......

I

.'.**....*...... '.. '..i<...........* :......:.... '..

..~........... '............>>.

mfB21 129B Main Steam Relief Valve B Fails Stuck mfB21 129C Main Steam Relief Valve C Fails Stuck mfB21 129D Main Steam Relief Valve D Fails Stuck mfB21 129E Main Steam Relief Valve E Fails Stuck mfB21 129F Main Steam Relief Valve F Fails Stuck mfB21 129G Main Steam Relief Valve G Fails Stuck mfB21 129H Main Steam Relief Valve H Fails Stuck mfB21 129K Main Steam Relief Valve K Fails Stuck mfB21 129L Main Steam Relief Valve L Fails Stuck mfB21 129M Main Steam Relief Valve M Fails Stuck

3.

INSERT the following OVERRIDES (SVO) & (10):

DESCRIPTION svoT48140 Water Level in Torus diB21-F013A Auto Relief SRV A

4.

INSERT the following REMOTE FUNCTIONS:

REM.#*

. DESCRIPTION

>/:F1NA.L l>$LA~

VALUE 11'IME' 2009-302 Sim 3 Page 2 of6

.***.*.**ACT~

TIME 00000 00000 00000 00000 00000 00000 00000 00000 00000 00000 FINAL RAMP ACT.

  • VALUER-A.TE TIME 115 100 00000 AUTO DryweU Chillers B006A & B LOCAILOSP Trip Links BYPASS Drywell Chillers B006B LOCAILOSP Trip Links BYPASS SIMULATOR SETUP

(

Simulator Initial Conditions:

1.

RESET the Simulator to IC #113 and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS:

MALF#

TITLE FINAL VALUE mfB21_129B Main Steam Relief Valve B Fails Stuck mfB21_129C Main Steam Relief Valve C Fails Stuck mfB2L129D Main Steam Relief Valve D Fails Stuck mfB21_129E Main Steam Relief Valve E Fails Stuck mfB2L129F Main Steam Relief Valve F Fails Stuck mfB21_129G Main Steam Relief Valve G Fails Stuck mfB21_129H Main Steam Relief Valve H Fails Stuck mfB2L129K Main Steam Relief Valve K Fails Stuck

(

mfB21_129L Main Steam Relief Valve L Fails Stuck mfB2L129M Main Steam Relief Valve M Fails Stuck

3.

INSERT the following OVERRIDES (SVO) & (10):

SVO#

DESCRIPTION FINAL VALUE svoT48140 Water Level in Torus 115 diB21-F013A Auto Relief SRV A AUTO

4.

INSERT the following REMOTE FUNCTIONS:

REM #

DESCRIPTION rfP64_330 Drywell Chillers B006A & B LOCAILOSP Trip Links rfP64_331 Drywell Chillers B006B LOCAILOSP Trip Links DELAY TIME RAMP RATE 100 2009-302 Sim 3 Page 2 of6 ACT.

TIME 00000 00000 00000 00000 00000 00000 00000 00000 00000 00000 ACT.

TIME 00000 STATUS BYPASS BYPASS

2009-302 Sim 3 Page 3 of6 S.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A.

On 2HII-P700 place the key switch for the Drywell Chillers to Override B.

On 2HII-P654 and P657, place keyswitchs for Drywell Fans to Override C.

Perform RC-I, RC-2, and TC-I and RWL to the normal band.

D.

Reset the Group 2 isolation.

E.

Prevent a further Group 2 by starting RCIC to maintain level >3" (SRV A will be cycling)

F.

Close the MSIVs G.

Place ALL SRV switches to OPEN H.

Place HPCI in service in Auto, injecting at 750 gpm.

I.

Acknowledge annunciators.

6.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

7.

ESTIMATED Simulator SETUP TIME:

20 Minutes 2009-302 Sim 3 Page 3 of6

(

5.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

(

(

A.

On 2HII-P700 place the key switch for the Drywell Chillers to Override B.

On 2HII-P654 and P657, place keyswitchs for Drywell Fans to Override C.

Perform RC-I, RC-2, and TC-I and RWL to the normal band.

D.

Reset the Group 2 isolation.

E.

Prevent a further Group 2 by starting RCIC to maintain level >3" (SRV A will be cycling)

F.

Close the MSIV s G.

Place ALL SRV switches to OPEN H.

Place HPCI in service in Auto, injecting at 750 gpm.

I.

Acknowledge annunciators.

6.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

7.

ESTIMATED Simulator SETUP TIME:

20 Minutes

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

A seismic event has caused a small steam leak in the drywell and an unisolable leak in the Torus.

2.

Attempts to raise Torus water level have been unsuccessfuL

3.

3 1 EO-EOP-O 1 2-2 (PC-I) is in progress.

4.

The Reactor has been shutdown

5.

The Shift Supervisor has determined that the plant cannot be maintained in the SAFE Region of the Heat Capacity Temperature Limit and decided to Emergency Depress the Reactor.

6.

3IEO-EOP-015-2 (CP-l) is in progress.

7.

An attempt was made to Emergency Depress with the SRVs, but they have failed to open.

8.

Other methods of Alternate Emergency Depress have been unsuccessfuL

9.

Drywell Chillers and Fans have been placed in service per 34S0-P64-001-2 with the LOCA trips overridden.

10.

The Group 2 isolation has been reset.

11.

Standby Gas Treatment System is running with suction from the Reactor Building per 34S0-T46-00l-2.

INITIATING CUES:

Depressurize the Reactor using the Head VentslDrywell Coolers per 3IEO-EOP-108-2.

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11.

A seismic event has caused a small steam leak: in the drywell and an unisolable leak: in the Torus.

Attempts to raise Torus water level have been unsuccessful.

3 1 EO-EOP-O 1 2-2 (PC-I) is in progress.

The Reactor has been shutdown The Shift Supervisor has determined that the plant cannot be maintained in the SAFE Region of the Heat Capacity Temperature Limit and decided to Emergency Depress the Reactor.

3IEO-EOP-015-2 (CP-l) is in progress.

An attempt was made to Emergency Depress with the SRVs, but they have failed to open.

Other methods of Alternate Emergency Depress have been unsuccessful.

Drywell Chillers and Fans have been placed in service per 34S0-P64-00l-2 with the LOCA trips overridden.

The Group 2 isolation has been reset.

Standby Gas Treatment System is running with suction from the Reactor Building per 34S0-T46-001-2.

INITIATING CUES:

Depressurize the Reactor using the Head VentslDrywell Coolers per 3IEO-EOP-I08-2.

1. Obtain the procedure needed to perform the task.
2. Place all available DW Chillers and Fans in service
3. Obtain the procedure needed to perform the task.

Operator obtains 3IEO-EOP-108-

2.

Recognizes that all DW Chillers and Fans in service from initial conditions or by observing red lights illuminated on 2HII-P654 and 2HII-P657.

Operator obtains 34S0-T48-002-2 or placard to vent the drywell.

2009-302 Sim 3 Page 5 of6

$kTlQNSAT

"(COMMENTS"..

START TIME: ___ _

SAT I UNSAT SAT I UNSAT SAT/UNSAT NOTE: Only one loop is critical and needs to be vented. Steps 5-7 are for the "A" side and steps 8-10 are for the "B" side.

(** Indicates critical step)

At 2HII-P657, the operator SAT I UNSAT INA places the control switch for 2T48-F334A, Drywell Vent Isol Vlv to OPEN.

At 2Hll-P657, the operator SAT I UNSAT I NA places the control switch for 2T48-F335A, Drywell Vent Isol Vlv to OPEN.

At 2HII-P657, the operator SAT I UNSAT INA increases the controller output on 2T48-R615A, Drywell Flow Controller for F336A with demand greater than zero.

At 2HII-P654, the operator places the control switch for 2T48-F334B, Drywell Vent Isol Vlv to OPEN.

At 2HII-P654, the operator places the control switch for 2T48-F335B, Drywell Vent Isol Vlv to OPEN.

SAT/UNSAT/NA SAT/UNSAT/NA

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(

PERFO~CESTEP

1. Obtain the procedure needed to perform the task.
2. Place all available DW Chillers and Fans in service
3. Obtain the procedure needed to perform the task.

STANDARD Operator obtains 31EO-EOP-108-

2.

Recognizes that all DW Chillers and Fans in service from initial conditions or by observing red lights illuminated on 2HII-P654 and 2HII-P657.

Operator obtains 34S0-T48-002-2 or placard to vent the drywell.

2009-302 Sim 3 Page 5 of6 SATIUNSAT (COMMENTS START TIME: ___ _

SAT/UNSAT SAT/UNSAT SAT/UNSAT NOTE: Only one loop is critical and needs to be vented. Steps 5-7 are for the "A" side and steps 8-10 are for the "B" side.

places the control switch for 2T48-F334A, Drywell Vent Isol Vlv to OPEN.

places the control switch for 2T48-F335A, Drywell Vent Isol Vlv to OPEN.

increases the controller output on 2T48-R615A, Drywell Flow Controller for F336A with demand greater than zero.

places the control switch for 2T48-F334B, Drywell Vent Isol Vlv to OPEN.

places the control switch for 2T48-F335B, Drywell Vent Isol Vlv to OPEN.

(** Indicates critical step)

2009-302 Sim 3 Page 6 of6 At 2HII-P654, the operator SAT I UNSAT INA

10. At 2HII-P602, Place the following pump control switches to PULL TO LOCK:
  • DIW Floor Drain Pump 2GII-COOlB increases the controller output on 2T48-R615B, Drywell Flow Controller for F336B with demand greater than zero.

At 2HII-P602, DRYWELL SUMP CONTROLS, the operator places the following pump control switches are in PULL TO LOCK:

At 2HII-P602, RX HEAD VENTS, VENT VLV, 2B21-F003 is OPEN, red light illuminated.

SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT PROMPT:

IF system restoration is addressed by the operator, as the Shift Supervisor, INFORM the operator that system restoration is not desired at this time.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

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(

(

PERFORMANCE STEP

10. At 2HII-P602, Place the following pump control switches to PULL TO LOCK:

STANDARD At 2HII-P654, the operator increases the controller output on 2T48-R615B, Drywell Flow Controller for F336B with demand greater than zero.

At 2HII-P602, DRYWELL SUMP CONTROLS, the operator places the following pump control switches are in PULL TO LOCK:

At 2HII-P602, RX HEAD VENTS, VENTVLV, 2B21-F003 is OPEN, red light illuminated.

2009-302 Sim 3 Page 6 of6 SATIUNSAT (COMMENTS SAT/UNSAT/NA SAT I UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT I UNSAT PROMPT:

IF system restoration is addressed by the operator, as the Shift Supervisor, INFORM the operator that system restoration is not desired at this time.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11.

A seismic event has caused a small steam leak in the drywell and an unisolable leak in the Torus.

Attempts to raise Torus water level have been unsuccessful.

3 I EO-EOP-O 12-2 (PC-I) is in progress.

The Reactor has been shutdown The Shift Supervisor has determined that the plant cannot be maintained in the SAFE Region of the Heat Capacity Temperature Limit and decided to Emergency Depress the Reactor.

31EO-EOP-01S-2 (CP-l) is in progress.

An attempt was made to Emergency Depress with the SRV s, but they have failed to open.

Other methods of Alternate Emergency Depress have been unsuccessful.

Drywell Chillers and Fans have been placed in service per 34S0-P64-001-2 with the LOCA trips overridden.

The Group 2 isolation has been reset.

Standby Gas Treatment System is running with suction from the Reactor Building per 34S0-T46-001-2.

INITIATING CUES:

Depressurize the Reactor using the Head Vents/Drywell Coolers per 31 EO-EOP-108-2.

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11.

A seismic event has caused a small steam leak in the drywell and an unisolable leak in the Torus.

Attempts to raise Torus water level have been unsuccessful.

3 I EO-EOP-OI2-2 (PC-I) is in progress.

The Reactor has been shutdown The Shift Supervisor has determined that the plant cannot be maintained in the SAFE Region of the Heat Capacity Temperature Limit and decided to Emergency Depress the Reactor.

3IEO-EOP-OIS-2 (CP-I) is in progress.

An attempt was made to Emergency Depress with the SRVs, but they have failed to open.

Other methods of Alternate Emergency Depress have been unsuccessful.

Drywell Chillers and Fans have been placed in service per 34S0-P64-001-2 with the LOCA trips overridden.

The Group 2 isolation has been reset.

Standby Gas Treatment System is running with suction from the Reactor Building per 34S0-T46-00I-2.

INITIATING CUES:

Depressurize the Reactor using the Head Vents/Drywell Coolers per 3 I EO-EOP-108-2.

(

NIR

(

FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 4 - All C. M. EDMUND 10/1112009 SOUTHERN..

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COMPANY Energy to Serve Your World SM

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TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 4 - All ROLL THE MAIN TURBINE FROM 800 TO 1800 RPM AUTHOR MEDIA NUMBER F.FAGAN 2009-302 Sim 4 RECOMMENDED BY APPROVED BY N/R C.M.EDMUND TIME 20.0 Minutes DATE 1011112009 Energy to Serve Your WOrld sM

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SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Sim 4

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              • .. *Initi3l.s 00 07/05/96 Initial development RAB SMC 01 03/05/99 Revised due to new simulator computer.

SCB DHG 02 02/07/00 Format modification RAB DHG 03 11/02100 Include objective number, TLB comment, changed RAB DHG required oil temperature for Step 33 04 01/03/02 Procedure changes RLS DHG 05 03111/02 Include initial operator statement RAB RAB 06 03/08/05 Changed RO to NPO, added statement ensuring the ELJ RAB procedure is the current version, changed procedure designations from -2S to -2, changed setup from IC 106 to IC 108.

07 06113105 Revised Initial License statement for successful RAB RAB completion 08 04118/06 Remove Response Cues RAB RAB 10111/09 Revised for use on 2009-302 Exam FNF CME

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Sim 4 Rev. No.

Date Reason for Revision Author's Supv's Initials Initials 00 07/05/96 Initial development RAB SMC 01 03/05/99 Revised due to new simulator computer.

SCB DHG 02 02/07/00 Format modification RAB DHG 03 11/02/00 Include objective number, TLB comment, changed RAB DHG required oil temperature for Step 33 04 01/03/02 Procedure changes RLS DHG 05 03/11/02 Include initial operator statement RAB RAB 06 03/08/05 Changed RO to NPO, added statement ensuring the ELI RAB procedure is the current version, changed procedure designations from -2S to -2, changed setup from IC 106 to IC 108.

07 06/13/05 Revised Initial License statement for successful RAB RAB completion 08 04/18/06 Remove Response Cues RAB RAB 10/11/09 Revised for use on 2009-302 Exam FNF CME

2009-302 Sim 4 Page 1 of7 UNITt

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UNIT 2 (X)

. ROLL THE MAIN TURBINE FROM 800 TO 1800 RPM LR-JP-17.15-08 The task shall be completed when the Main Turbine has been rolled from 800 to 1800 rpm per 34S0-N30-001-2.

017.015 017.015.A PLANT HATCH JTA IMPORTANCE RATING:

NPO 2.25 SRO 2.83 KIA CATALOG NUMBER: 245000A4.06 KIA CATALOG JTA IMPORTANCE RATING:

NPO 2.7 SRO 2.6 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

APPROXIMATE COMPLETION TIME:

20.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

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2009-302 Sim 4 Page 1 of7 UNIT 1

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UNIT 2 (X)

TASK TITLE:

JPMNUMBER:

TASK STANDARD:

TASK NUMBER:

ROLL THE MAIN TURBINE FROM 800 TO 1800 RPM LR-JP-17.15-08 The task shall be completed when the Main Turbine has been rolled from 800 to 1800 rpm per 34S0-N30-001-2.

017.015 OBJECTIVE NUMBER: 017.015.A PLANT HATCH JTA IMPORTANCE RATING:

NPO 2.25 SRO 2.83 KIA CATALOG NUMBER: 245000A4.06

(

KIA CATALOG JTA IMPORTANCE RATING:

(

NPO 2.7 SRO 2.6 OPERA TOR APPLICABILITY: Nuclear Plant Operator (NPO)

I GENERAL

REFERENCES:

Unit 2 34GO-OPS-001-2 (current version) 34S0-N30-001-2 (current version)

I REQUIRED MATERIALS:

Unit 2 34S0-N30-001-2 (current version)

APPROXIMATE COMPLETION TIME:

20.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

2009-302 Sim 4 Page 2 of7 SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #10S and place in RUN.

2.

INSERT the following OVERRIDES:

loN34-COO3G 1 MOTOR SUCT PMP ON 1

loN34-COO3R2 MOTOR SUCT PMP OFF 1

diN34-C005G 1 TURN GEAR OIL PMP ON 1

diN34-C005R2 TURN GEAR OIL PMP OFF 1

3.

INSERT the following MALFUNCTION:

RAMP DELAY *KE¥ mfN34_140 Main Turbine Quill Shaft Oil Pump Fail 9999 mfN34_153 Loss of Turbine Bearing Oil Pres (Var) 100 10,000 9999

4.

Create the following EVENT TRIGGERS with the following information:

(NOTE: Use Windows "Notepad" to create blank *.scn and *.et files with the indicated names below. Copy the "ET INFORMATION" and "SCN INFORMATION" into the appropriate files.

Copy the 4 files into the simulators "HatchlInstrIET" directory).

N34-01.scn N34-0l.et

TG Oil Pump to RUN Deletes MF and OR DMF mtN34_153; N34-02.scn N34-02.et diN34-C005.aivToPanel=2
Motor Suction Pump to RUN Deletes MF and OR diN34-C003.aivToPanel=2
5. ACTIV ATE event triggers N34-01 and N34-02.
6. INCREASE Turbine Oil setpoint to 115 deg F.
7. START Motor Suction Pump.

DOR loN34-C005G 1; DOR loN34-C005R2; DMF mtN34_153; DOR loN34-C003G 1; DOR loN34-C003R2; NOTE: The Turbine will trip at 1300 RPMs if the Motor Suction Pump is NOT running.

S. SELECT a Turbine Speed of SOO RPMs, Acceleration FAST.

2 2

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2009-302 Sim 4 Page 2 of7 SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #10S and place in RUN.

2.

INSERT the following OVERRIDES:

OR#

DESCRIPTION FINAL KEY loN34-COO3G 1 MOTOR SUCT PMP ON 1

loN34-COO3R2 MOTOR SUCT PMP OFF 1

diN34-C005G 1 TURN GEAR OIL PMP ON 1

diN34-C005R2 TURN GEAR OIL PMP OFF 1

3.

INSERT the following MALFUNCTION:

MALF#

DESCRIPTION FINAL RAMP DELAY KEY mfN34_140 Main Turbine Quill Shaft Oil Pump Fail 9999 mfN34_153 Loss of Turbine Bearing Oil Pres (Var) 100 10,000 9999

4.

Create the following EVENT TRIGGERS with the following information:

(NOTE: Use Windows "Notepad" to create blank *.scn and *.et files with the indicated names below. Copy the "ET INFORMATION" and "SCN INFORMATION" into the appropriate files.

Copy the 4 files into the simulators "HatchlInstrIET" directory).

SCNIET ET INFORMATION SCN INFORMATION NAME N34-01.scn

TG Oil Pump to RUN Deletes MF and OR DMF mfN34_153; N34-01.et diN34-C005. ai vToPanel=2 DOR loN34-C005G 1; DOR loN34-C005R2; N34-02.scn
Motor Suction Pump to RUN Deletes MF DMF mfN34_153; N34-02.et and OR DOR loN34-C003G1; diN34-C003. ai vToPanel=2 DOR loN34-C003R2;
5.

ACTIVATE event triggers N34-01 and N34-02.

6.

INCREASE Turbine Oil setpoint to 115 deg F.

7.

START Motor Suction Pump.

NOTE: The Turbine will trip at 1300 RPMs if the Motor Suction Pump is NOT running.

S.

SELECT a Turbine Speed of SOO RPMs, Acceleration FAST.

2 2

9.

AFTER Turbine is at 800 RPMS select Acceleration MED.

2009-302 Sim 4 Page 3 of7

(

10.

SELECT the EX2100 screen and place "Regulator Control" in "Auto".

(

11. SELECT the "Control" "Speed" screen (the normal Turbine Speed/Acceleration Screen).
12. WITH the Turbine at 800 RPMS, PLACE the Simulator in FREEZE until the INmATING CUE is given.
13.

Markup 34S0-N30-001-2 up to, but not including, step 7.1.5.41. Ensure proper marking techniques are used for completed steps.

13. ESTIMATED Simulator SETUP TIME:

15 Minutes

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(

9. AFTER Turbine is at 800 RPMS select Acceleration MED.
10.

SELECT the EX2100 screen and place "Regulator Control" in "Auto".

2009-302 Sim 4 Page 3 of7

11. SELECT the "Control" "Speed" screen (the normal Turbine Speed/Acceleration Screen).
12. WITH the Turbine at 800 RPMS, PLACE the Simulator in FREEZE until the INmATING CUE is given.
13.

Markup 34S0-N30-001-2 up to, but not including, step 7.1.5.41. Ensure proper marking techniques are used for completed steps.

13. ESTIMATED Simulator SETUP TIME:

15 Minutes

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

A plant startup is in progress.

2.

The Turbine Vibration Trip Bypass switch is in NORMAL

3.

The Main Turbine is rolling at 800 rpms to increase lube oil temperatures.

4.

Lube Oil temperatures have increased sufficiently.

5.

34S0-N30-00l-2, "Main Turbine Operations," is complete up to Step 7.1.5.40

6.

It is not desired to perform any checks of the turbine at 1500 rpm.

INITIATING CUES:

Increase the Main Turbine speed to 1800 RPM and continue turbine startup lAW 34S0-N30-001-2, starting at Step 7.1.5.41

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

A plant startup is in progress.

2.

The Turbine Vibration Trip Bypass switch is in NORMAL

3.

The Main Turbine is rolling at 800 rpms to increase lube oil temperatures.

4.

Lube Oil temperatures have increased sufficiently.

5.

34S0-N30-001-2, "Main Turbine Operations," is complete up to Step 7.1.5.40

6.

It is not desired to perform any checks of the turbine at 1500 rpm.

INITIATING CUES:

Increase the Main Turbine speed to 1800 RPM and continue turbine startup lAW 34S0-N30-001-2, starting at Step 7.1.5.41

(

NOTE: All manipulations are performed at 2HII-P650 unless otherwise indicated.

1. Operator obtains the procedure needed Operator has obtained to perform the task 34S0-N30-001-2 and refers to section 7.1.5.40 and then to 7.1.5.41.

2009-302 Sim 4 Page 5 of7

$.A.ctru:N$A.W (COMMENTS START TIME: ___ _

SAT/UNSAT PROMPT: IF the operator asks about selection of an acceleration rate, THEN inform him to select MED.

SELECT Speed Cmd RPM SAT/UNSAT

    • Rated (1800)**
3. Once 900 rpm is reached STOP the Operator, at 900 rpms, stops the SAT/UNSAT Shaft Lift Pumps.

Shaft Lift Pumps by placing the control switch in OFF PULL TO LOCK.

Operator selects **Manual** for SAT/UNSAT Regulator Control on the EX2100 screen.

5. At 1000 rpm, select Acceleration Operator, at 1000 rpms, selects SAT/UNSAT RPM/min Fast (180)

Speed Control, Acceleration RPM/min Fast (180)

6. At 1200 rpm, SELECT Speed Control, Operator leaves Speed Control, SAT I UNSAT Acceleration rpm/min desired rate:

Acceleration RPM/min selected Med (90) OR Fast (180).

to Fast (180).

PROMPT: IF Operator inquires as to desired acceleration rate at 1200 rpms, THEN inform the operator that FAST (180) is the correct rate.

7. OBSERVE Turbine Speed increase Operator observes Turbine Speed SAT/UNSAT and levels at approximately 1800 rpm increase and stabilize at approximately 1800 rpm on the DEHC screen.

(** Indicates critical step)

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PERFORMANCE STEP STANDARD NOTE: All manipulations are performed at 2H11-P650 unless otherwise indicated.

1. Operator obtains the procedure needed Operator has obtained to perform the task 34S0-N30-001-2 and refers to section 7.1.5.40 and then to 7.1.5.41.

2009-302 Sim 4 Page 5 of7 SATIUNSAT (COMMENTS*

START TIME: ___ _

SAT/UNSAT PROMPT: IF the operator asks about selection of an acceleration rate, THEN inform him to select MED.

    • 2. SELECT Speed of 1800 RPM.

SELECT Speed Cmd RPM SAT/UNSAT

    • Rated (1800)**
3. Once 900 rpm is reached STOP the Operator, at 900 rpms, stops the SAT/UNSAT Shaft Lift Pumps.

Shaft Lift Pumps by placing the control switch in OFF PULL TO LOCK.

    • 4. SELECT **Manual** for Regulator Operator selects **Manua1** for SAT/UNSAT Control on the EX2100 screen.

Regulator Control on the EX21 00 screen.

5. At 1000 rpm, select Acceleration Operator, at 1000 rpms, selects SAT/UNSAT RPM/min Fast (180)

Speed Control, Acceleration RPM/min Fast (180)

6. At 1200 rpm, SELECT Speed Control, Operator leaves Speed Control, SAT/UNSAT Acceleration rpm/min desired rate:

Acceleration RPM/min selected Med (90) OR Fast (180).

to Fast (180).

PROMPT: IF Operator inquires as to desired acceleration rate at 1200 rpms, THEN inform the operator that FAST (180) is the correct rate.

7. OBSERVE Turbine Speed increase Operator observes Turbine Speed SAT/UNSAT and levels at approximately 1800 rpm increase and stabilize at approximately 1800 rpm on the DEHC screen.

(** Indicates critical step)

(

8. CONFIRM annunciator 650-150, TURB SUPV TRIP BYPASS TURB vrn TRIP BYPASS, is clear.
9. CONFIRM Main Shaft Pump Discharge pressure is between 210 and 250 PSIG
10. PERFORM the following:
12. PERFORM the following:
13. CONFIRM 2N39-COOl, Turbine Turning Gear Motor control switch, is in the AUTO PULL position.
14. PLACE the Shaft Lift Pumps control switch in the AUTO START Position.
15. CONFIRM 2P41-R61O, Main Turbine Lube Oil Temp, is between 110°F and 120°F

(** Indicates critical step)

Operator confirms annunciator 650-150, TURB SUPV TRIP BYPASS TURB vrn TRIP BYPASS, is clear.

Operator confirms Main Shaft Pump Discharge pressure is between 210 and 250 PSIG on the

    • Monitor** ~ **lube oil**

screen.

  • Operator stops 2N34-C003, Motor Suction Pump by placing its control switch to OFF.
  • Operator places control switch for 2N34-C003 in the AUTO START position
  • Operator places control switch for 2N34-C005 in the AUTO START position.

Operator confirms the control switch for 2N39-COOl, Turbine Turning Gear Motor control switch, is in the AUTO PULL position.

Operator places the Shaft Lift Pumps control switch in the AUTO START Position.

Operator confirms on 2P41-R61O, that Main Turbine Lube Oil Temp, is between 110°F and 120°F 2009-302 Sim 4 Page 6 of7 SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT PERFORMANCE STEP

8. CONFIRM annunciator 650-150, TURB SUPV TRIP BYPASS TURB VIB TRIP BYPASS, is clear.
9. CONFIRM Main Shaft Pump Discharge pressure is between 210 and 250 PSIG
10. PERFORM the following:

(

12. PERFORM the following:
13. CONFIRM 2N39-COOl, Turbine Turning Gear Motor control switch, is in the AUTO PULL position.
14. PLACE the Shaft Lift Pumps control switch in the AUTO START Position.
15. CONFIRM 2P41-R61O, Main Turbine Lube Oil Temp, is between 110°F and 120°F

(** Indicates critical step)

STANDARD Operator confirms annunciator 650-150, TURB SUPV TRIP BYPASS TURB VIB TRIP BYPASS, is clear.

Operator confirms Main Shaft Pump Discharge pressure is between 210 and 250 PSIG on the

  • *Monitor* * -+ **lube oil **

screen.

  • Operator stops 2N34-C003, Motor Suction Pump by placing its control switch to OFF.
  • Operator places control switch for 2N34-C003 in the AUTO START position
  • Operator places control switch for 2N34-C005 in the AUTO START position.

Operator confirms the control switch for 2N39-COOl, Turbine Turning Gear Motor control switch, is in the AUTO PULL position.

Operator places the Shaft Lift Pumps control switch in the AUTO START Position.

Operator confirms on 2P41-R610, that Main Turbine Lube Oil Temp, is between 110°F and 120°F 2009-302 Sim 4 Page 6 of7 SATIUNSAT (COMMENTS SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT

Simulator Instructor Note:

2009-302 Sim 4 Page 7 of7 First: Ensure oil pumps have been manually turned off by the operator, INCLUDING the lift pumps being OFF and Placed in AUTO, then ACTIVATE overrides (Key 1)/event triggers for the lube oil pumps are already activated.

Second: ACTIV ATE Quill Shaft Failure malfunction (Key 2)

17. Respond to Quill Shaft Failure annunciator.
18. Confirm Turbine 200 psig oil pressure is below 60 psig.

Operator refers to annunciator procedure 650-152 for Quill Shaft Failure.

Operator observes that Turbine 200 psig oil pressure is below 60 psig as indicated by 2N34-R601C.

Operator starts the TGOP by placing it's control switch to RUN.

SAT/UNSAT SAT/UNSAT SAT I UNSAT NOTE: The TGOP is required for lift pump operation. IA W 34S0-N30-001-2 precaution 5.2.8, "No more than two shaft lift pumps may be OFF WHEN turbine speed is < 900 RPMs.

20. Confirm running or start MSP.

Operator starts the MSP by SAT/UNSAT placing it's control switch to RUN

21. If Turbine Trips, enter 34S0-N30-Operator refers to 34S0-N30-SAT/UNSAT 001-2.

001-2.

PROMPT: WHEN operator refers to 34S0-N30-001-2, THEN inform the operator that another operator will carry out the actions for a Turbine Trip.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator has started lube oil pumps and has entered 34S0-N30-001-2 for a Turbine Trip.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

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PERFORMANCE STEP STANDARD Simulator Instructor Note:

2009-302 Sim 4 Page 7 of7 SATIUNSAT (COMMENTS First: Ensure oil pumps have been manually turned off by the operator, INCLUDING the lift pumps being OFF and Placed in AUTO, then ACTIVATE overrides (Key l)/event triggers for the lube oil pumps are already activated.

Second: ACTIV ATE Quill Shaft Failure malfunction (Key 2)

17. Respond to Quill Shaft Failure Operator refers to annunciator SAT I UNSAT annunciator.

procedure 650-152 for Quill Shaft Failure.

18. Confirm Turbine 200 psig oil pressure Operator observes that Turbine SAT I UNSAT is below 60 psig.

200 psig oil pressure is below 60 psig as indicated by 2N34-R601C.

    • 19. Confirm running or start TGOP.

Operator starts the TGOP by SAT I UNSAT placing it's control switch to RUN.

NOTE: The TGOP is required for lift pump operation. IA W 34S0-N30-001-2 precaution 5.2.8, "No more than two shaft lift pumps may be OFF WHEN turbine speed is < 900 RPMs.

20. Confirm running or start MSP.

Operator starts the MSP by SAT/UNSAT placing it's control switch to RUN

21. If Turbine Trips, enter 34S0-N30-Operator refers to 34S0-N30-SAT I UNSAT 001-2.

001-2.

PROMPT: WHEN operator refers to 34S0-N30-001-2, THEN inform the operator that another operator will carry out the actions for a Turbine Trip.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator has started lube oil pumps and has entered 34S0-N30-001-2 for a Turbine Trip.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

(

C

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.
2.
3.
4.
5.
6.

A plant startup is in progress.

The Turbine Vibration Trip Bypass switch is in NORMAL The Main Turbine is rolling at 800 rpms to increase lube oil temperatures.

Lube Oil temperatures have increased sufficiently.

34S0-N30-00l-2, "Main Turbine Operations," is complete up to Step 7.1.5.40 It is not desired to perform any checks of the turbine at 1500 rpm.

INITIATING CUES:

Increase the Main Turbine speed to 1800 RPM and continue turbine startup IA W 34S0-N30-001-2, starting at Step 7.1.5.41

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

A plant startup is in progress.

2.

The Turbine Vibration Trip Bypass switch is in NORMAL

3.

The Main Turbine is rolling at 800 rpms to increase lube oil temperatures.

4.

Lube Oil temperatures have increased sufficiently.

5.

34S0-N30-001-2, "Main Turbine Operations," is complete up to Step 7.1.5.40

6.

It is not desired to perform any checks of the turbine at 1500 rpm.

INITIATING CUES:

Increase the Main Turbine speed to 1800 RPM and continue turbine startup IA W 34S0-N30-00 1-2, starting at Step 7.1.5.41

(

NIR FINAL Southern E. I. Hatch uclear uclear Plant Operations Training JPM Simulator 5 - All C.M.EDMUND 1011112009 Energy to Serve Your World SM

(

TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 5 - All LOWER TORUS WATER LEVEL AUTHOR MEDIA NUMBER F.N.FAGAN 2009-302 Sim 5 RECOMMENDED BY APPROVED BY NIR C. M. EDMUND TIME 20 Minutes DATE 10/11/2009 Energy to Serve Your World sM

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:

OPERATIONS TRAINING 00 10/11/09 Initial development Page 1 of 1 Media Number:

2009-302 Sim 5

........................ *******.******.. **i\\titI1ol7's

.... Supv~s

........*.. Jwti~lsIJnitiaIs*.**

FNF CME

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:

OPERATIONS TRAINING Rev. No.

Date Reason for Revision 00 10111/09 Initial development Page 1 of 1 Media Number:

2009-302 Sirn 5 Author's Supv's Initials Initials FNF CME

UNIT 1 0

Lower Torus Water Level Jl:'MNlJIVIBER.:> LR-JP-HLT5-S5 2009-302 Sim 5 Page 1 of 6 UNIT 2 (X)

TASKSTANJ)ARD:

The task shall be complete when the operator has lowered torus water level to 148".

OBJECTlVENUMBER( E11-RHR-LP-00701,013.004.A PLANT HATCH JTA IMPORTANCE RATING:

RO SRO KIA CATALOG NUMBER: 223001A2.11 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.6 SRO 3.8 OPERATOR APPLICABILITY:

Reactor Operator (RO) 34S0-E11-010-2 L-________________________________ ~

APPROXIMATE COMPLETION TIME:

20 Minutes SIMULATOR SETUP:

See next page.

(

(

TASK TITLE:

Lower Torus Water Level JPMNUMBER:

LR-JP-HLTS-SS UNIT 1 0

2009-302 Sim S Page I of 6 UNIT 2 (X)

TASK STANDARD:

The task shall be complete when the operator has lowered torus water level to 148".

TASK NUMBER:

OBJECTIVE NUMBER:

EII-RHR-LP-00701,013.004.A PLANT HATCH JTA IMPORTANCE RATING:

RO SRO KIA CATALOG NUMBER: 223001A2.11 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.6 SRO 3.8 OPERATOR APPLICABILITY:

Reactor Operator (RO)

I GENERAL

REFERENCES:

I Unitt &2 I REQUIRED MATERIALS:

Unit 1 & 2 34S0-Ell-01O-2, Section 7.4.5 APPROXIMA TE COMPLETION TIME:

20 Minutes SIMULATOR SETUP:

See next page.

(

(

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to an IC 113 and leave in place in FREEZE.

2.

INSERT the following REMOTE FUNCTIONS:

E21-FOO2A Suction From CST to CS Pump A OPEN E21-FOO2B Suction From CST to CS Pump B OPEN

3.

INSERT the following OVERRIDES:

loEII-F003AR2 RHR A HT EXCH OUTLET OFF loEll-F047AR2 RHR A HTEXCH INLET OFF

4. Place the simulator in RUN.

1 2

2009-302 Sim 5 Page 2 of6

5.

Allow Torus Level to increase to 149.5", insure annunciator "Torus Water Level High/Low" in alarm, THEN return rfE21_214 and rfE21~15 to NORM.

6.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

7.

ESTIMATED Simulator SETUP TIME:

5 Minutes 2

(

(

(

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to an IC 113 and leave in place in FREEZE.

2.

INSERT the following REMOTE FUNCTIONS:

RF#

TITLE FINAL VALUE rfE21_214 E21-FOO2A Suction From CST to CS Pump A OPEN rfE21_215 E21-FOO2B Suction From CST to CS Pump B OPEN

3.

INSERT the following OVERRIDES:

OR#

TITLE FINAL VALUE loEII-F003AR2 RHR A HT EXCH OUTLET OFF loEII-F047AR2 RHR A HT EXCH INLET OFF

4. Place the simulator in RUN.

RAMP RATE RAMP RATE 2009-302 Sim 5 Page 2 of6 Key KEY 1

2

5.

Allow Torus Level to increase to 149.5", insure annunciator "Torus Water Level HighlLow" in alarm, THEN return rfE21_214 and rfE21_215 to NORM.

6.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

7.

ESTIMATED Simulator SETUP TIME:

5 Minutes 2

(

UNIT 2 READ AND GIVE A COPY TO THE OPERA TOR INITIAL CONDITIONS:

1. Unit 2 is at normal full power operations.
2. Annunciator 602-235 "Torus Water Level HighlLow" is in alarm
3. Known and documented Torus in-leakage has caused torus level to increase to 149.5"
4. Both loops of RHR have been filled and vented lAW 34SV-SUV-017-2, "Core Spray and RHR Keepfill and RHR Cross Header Valve Check".

INITIATING CUES:

The Shift Supervisor directs that Torus Water Level be lowered to 148.5" IA W 34S0-E 11-0 1 0-2, Residual Heat Removal System, Section 7.4.5.

(

UNIT 2 READ AND GIVE A COPY TO THE OPERA TOR INITIAL CONDITIONS:

1. Unit 2 is at normal full power operations.
2. Annunciator 602-235 "Torus Water Level HighJLow" is in alarm
3. Known and documented Torus in-leakage has caused torus level to increase to 149.5"
4. Both loops of RHR have been filled and vented lAW 34SV-SUV-017-2, "Core Spray and RHR Keepfill and RHR Cross Header Valve Check".

INITIATING CUES:

The Shift Supervisor directs that Torus Water Level be lowered to 148.5" IA W 34S0-Ell-01O-2, Residual Heat Removal System, Section 7.4.5.

NOTE: Unless otherwise indicated, all manipulations are on 2HII-P601.

1. The operator obtains the correct Operator obtains 34S0-EII-010-procedure.

2 and refers to section 7.4.5.2

2. CONFIRM Radwaste is capable of Operator calls Radwaste to ask if receiving the amount of water to be it is capable of receiving water.

transferred.

Page 4 of6

  • SAtroN~A.T.

COl\\1MEN1S START TIME: ___ _

SAT/UNSAT SAT/UNSAT PROMPT: WHEN operator calls Radwaste, THEN ask the operator how many gallons of water should be expected.

Operator informs Radwaste that 5,770 gallons are expected (accept 2850 - 8550 gallons, this equates to + or - 0.5 inches on the torus level recorder).

SAT/UNSAT PROMPT: WHEN informed of the number of gallons to expect, THEN tell the operator that Radwaste is capable and ready to receive the water.

Operator OPENS 2EII-F049, RHR To Radwaste Vlv by placing its control switch to OPEN at 2HII-P602, red light illuminated.

5. CLOSE 2EII-F003B, Hx Outlet Vlv Operator CLOSES 2EI1-F003B, Hx Outlet Vlv by placing its control switch to CLOSE, green light illuminated.

SAT/UNSAT SAT I UNSAT NOTEIPROMPT: Stroke time for F003B is approximately 80 seconds. IF desired, notify Simulator Instructor to activate Key 1 and THEN tell the applicant, that using time compression, the valve is closed.

6. CLOSE 2EII-F047B, Hx Inlet Vlv.

Operator CLOSES 2EII-F047B, SAT/UNSAT Hx Inlet Vlv by placing its control switch to CLOSE, green light illuminated.

NOTEIPROMPT: Stroke time for F047B is approximately 80 seconds. IF desired, notify Simulator Instructor to activate Key 2 and THEN tell the applicant, that using time compression, the valve is closed.

(** Indicates critical step)

PERFO~CESTEP STANDARD

~VV7--'V~ \\Jllil.J Page 4 of6 SATIUNSAT COMMENTS

(

NOTE: Unless otherwise indicated, all manipulations are on 2Hll-P60l.

(

START TIME: ___ _

1. The operator obtains the correct Operator obtains 34S0-Ell-01O-SAT I UNSAT procedure.

2 and refers to section 7.4.5.2

2. CONFIRM Radwaste is capable of Operator calls Radwaste to ask if SAT/UNSAT receiving the amount of water to be it is capable of receiving water.

transferred.

PROMPT: WHEN operator calls Radwaste, TIffiN ask the operator how many gallons of water should be expected.

    • 3. Informs Radwaste of the number of Operator informs Radwaste that SAT/UNSAT gallons expected.

5,770 gallons are expected (accept 2850 - 8550 gallons, this equates to + or - 0.5 inches on the torus level recorder).

PROMPT: WHEN informed of the number of gallons to expect, TIffiN tell the operator that Radwaste is capable and ready to receive the water.

RHR To Radwaste Vlv by placing its control switch to OPEN at 2Hll-P602, red light illuminated.

5. CLOSE 2Ell-F003B, Hx Outlet Vlv Operator CLOSES 2Ell-F003B, SAT/UNSAT Hx Outlet Vlv by placing its control switch to CLOSE, green light illuminated.

NOTEIPROMPT: Stroke time for F003B is approximately 80 seconds. IF desired, notify Simulator Instructor to activate Key 1 and THEN tell the applicant, that using time compression, the valve is closed.

6. CLOSE 2Ell-F047B, Hx Inlet Vlv.

Operator CLOSES 2Ell-F047B, SAT/UNSAT Hx Inlet Vlv by placing its control switch to CLOSE, green light illuminated.

NOTEIPROMPT: Stroke time for F047B is approximately 80 seconds. IF desired, notify Simulator Instructor to activate Key 2 and THEN tell the applicant, that using time compression, the valve is closed.

(** Indicates critical step)

7. CONFIRM OPEN/OPEN 2E11-Operator CONFIRMS F048B, Hx Bypass Vlv.

OPEN/OPEN 2E11-F048B, Hx Bypass Vlv by observing red light illuminated.

8. Monitor Suppression Pool level.

Monitor Suppression Pool level on 2T48-R607A at 2Hll-P602 OR on 2T48-R607B at 2H11-P654.

$rr\\.R'I1;R!IRJ,,(}Oplr~ur1lp Operator STARTS RHR Pump B OR D by placing its control

. switch to START, red light illuminated.

10. Acknowledge expected annunciators.

Acknoledges the following annuciators:

11. Dispatch an operator to locally check the RHR pump for seal leakage.

602-312 Auto Blowdown CS or RHR Press Permissive 650-234 SEC System Auto Initiation Signal Present 601-222 RHR Flow Low Operator dispatches an operator to locally check the RHR pump for seal leakage.

Page 5 of6

  • <SA.TlO~$A'f COMMENTS*

SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT Simulator Instructor PROMPT:

After approximately 5 minutes, report back to the operator that there is no seal leakage.

12. CONFIRM RHR discharge water temperature is < 200°F.

$lQWlyTFl~0'1'l'PlE()P:ENfEl.*l",

F040,RHRToRadwas.te \\fly"

14. Acknowledge cleared annunciators

(** Indicates critical step)

Operator CONFIRMS RHR discharge water temperature is <

200°F, as read on 2T47-R627, point 3 at panel 2H11-P650.

Operator slowly THROTTLES OPEN 2Ell-F040, RHR To Radwaste Vlv by placing its control switch to OPEN, red light illuminated.

Acknowledges the following cleared annunciators:

601-222 RHR Flow Low 602-235 Torus Water Level High/Low SAT/UNSAT SAT/UNSAT SAT/UNSAT

(

PERFORMANCE STEP

7. CONFIRM OPEN/OPEN 2E11-F048B, Hx Bypass Vlv.
8. Monitor Suppression Pool level.
    • 9. START a RHR Loop B Pump
10. Acknowledge expected annunciators.
11. Dispatch an operator to locally check the RHR pump for seal leakage.

STANDARD Operator CONFIRMS OPEN/OPEN 2E11-F048B, Hx Bypass Vlv by observing red light illuminated.

Monitor Suppression Pool level on 2T48-R607A at 2H11-P602 OR on 2T48-R607B at 2H11-P654.

Operator STARTS RHR Pump B OR D by placing its control switch to START, red light illuminated.

Acknoledges the following annuciators:

  • 602-312 Auto Blowdown CS or RHR Press Permissive
  • 650-234 SEC System Auto Initiation Signal Present
  • 601-222 RHR Flow Low Operator dispatches an operator to locally check the RHR pump for seal leakage.

Page 5 of6 SATIUNSAT COMMENTS SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT Simulator Instructor PROMPT:

After approximately 5 minutes, report back to the operator that there is no seal leakage.

12. CONFIRM RHR discharge water Operator CONFIRMS RHR SAT /UNSAT temperature is < 200°F.

discharge water temperature is <

200°F, as read on 2T47-R627, point 3 at paneI2H11-P650.

    • 13. Slowly THROTTLE OPEN 2E11-Operator slowly THROTTLES SAT/UNSAT F040, RHR To Radwaste Vlv.

OPEN 2E11-F040, RHR To Radwaste Vlv by placing its control switch to OPEN, red light illuminated.

14. Acknowledge cleared annunciators Acknowledges the following SAT/UNSAT cleared annunciators:
  • 601-222 RHR Flow Low
  • 602-235 Torus Water Level High/Low

(** Indicates critical step)

Page 6 of6 Sl\\1'f(Jl'l§A.T COMJ\\iENTS NOTE:

Only ONE of the following three critical steps (closing F049, F040 or stopping the pump) is critical.

WHEN the Suppression Pool level is lowered to 148.5" (+ or -

.5"), Operator CLOSES 2Ell-F040, RHR To Radwaste Vlv by placing its control switch to CLOSE, reen light illuminated.

WHEN the Suppression Pool level is lowered to 148.5" (+ or-

.5"), Operator STOPS the Loop B operating RHR Pump by placing its control switch to STOP, green light illuminated.

WHEN the Suppression Pool level is lowered to 148.5" (+ or-

.5"), Operator CLOSES 2E 11-F049, RHR To Radwaste Vlv at 2HI1-P602 by placing its control switch to CLOSE, green light illuminated.

SAT I UNSAT SAT/UNSAT SAT/UNSAT PROMPT: WHEN the Operator starts to open 2EII-F003B, THEN inform the operator that another operator will complete this section and place RHR in Standby.

NOTE: The terminating cue shall be given to the Operator when:

With no reasonable progress, the Operator exceeds double the allotted time.

Operator starts to open 2E I1-F003B.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

(

(

(

PERFORMANCE STEP STANDARD kVVY-..JVk \\Jllll..J Page 6 of6 SATIUNSAT COMMENTS NOTE:

Only ONE of the following three critical steps (closing F049, F040 or stopping the pump) is critical.

    • 15. WHEN the Suppression Pool has WHEN the Suppression Pool SAT I UNSAT been pumped down to the desired level is lowered to 148.5" (+ or -

level CLOSE 2E 11-F040, RHR To

.5"), Operator CLOSES 2Ell-Radwaste Vlv.

F040, RHR To Radwaste Vlv by placing its control switch to CLOSE, green light illuminated.

    • 16. STOP the Loop B operating RHR WHEN the Suppression Pool SAT/UNSAT Pump.

level is lowered to 148.5" (+ or-

.5"), Operator STOPS the Loop B operating RHR Pump by placing its control switch to STOP, green light illuminated.

    • 17. CLOSE 2E11-F049, RHR To WHEN the Suppression Pool SAT I UNSAT Radwaste Vlv.

level is lowered to 148.5" (+ or -

.5"), Operator CLOSES 2E11-F049, RHR To Radwaste Vlv at 2H11-P602 by placing its control switch to CLOSE, green light illuminated.

PROMPT: WHEN the Operator starts to open 2E1l-F003B, THEN inform the operator that another operator will complete this section and place RHR in Standby.

NOTE: The terminating cue shall be given to the Operator when:

With no reasonable progress, the Operator exceeds double the allotted time.

Operator starts to open 2E1l-F003B.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

(

UNIT 2 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is at nonnal full power operations.
2. Annunciator 602-235 "Torus Water Level High/Low" is in alann
3. Known and documented Torus in-leakage has caused torus level to increase to 149.5"
4. Both loops ofRHR have been filled and vented lAW 34SV-SUV-017-2, "Core Spray and RHR Keepfill and RHR Cross Header Valve Check".

INITIATING CUES:

The Shift Supervisor directs that Torus Water Level be lowered to 148.5" lAW 34S0-E11-010-2, Residual Heat Removal System, Section 7.4.5.

(

(

UNIT 2 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is at normal full power operations.
2. Annunciator 602-235 "Torus Water Level High/Low" is in alarm
3. Known and documented Torus in-leakage has caused torus level to increase to 149.5"
4. Both loops ofRHR have been filled and vented lAW 34SV-SUV-017-2, "Core Spray and RHR Keepfill and RHR Cross Header Valve Check".

INITIATING CUES:

The Shift Supervisor directs that Torus Water Level be lowered to 148.5" lAW 34S0-EII-0I0-2, Residual Heat Removal System, Section 7.4.5.

(

N/R FI AL Southern uclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 6 - All C.M.EDMUND 10109/2009

(

TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 6 - All RE-ENERGIZE BUS WITH DIESEL GENERATOR AUTHOR MEDIA NUMBER F. FAGAN 2009-302 Sim 6 RECOMMENDED BY APPROVED BY N/R C.M.EDMUND TIME 10 Minutes DATE 1010912009

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Sim 6 Rev.*

<.N6:***

00 01 02 Date

.1

.... i/~e~s()llf()rf{evisi()]lJ

.... *****<A\\lth()~'~

S~}lv's

.....1**** **.....

...............*....*......*..*............*.........(........*..*** *L_.*............. ****...iIniti(llslnitials...

06/01/07 Initial development DHG BKW 6/26/07 Modify The Malfunction Numbers 10/23/08 Removed critical step requirement from step to lower voltage to 57 Hz; Clarified action required to complete critical task to match procedure step.

10/09/09 Modified to use for 2009-302 DHG ADY FNF RAB RSG CME

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Sim 6 Rev.

Date Reason for Revision Author's Supv's No.

Initials Initials 00 06/01/07 Initial development DHG BKW 01 6126/07 Modify The Malfunction Numbers DHG RAB 02 10123/08 Removed critical step requirement from step to lower ADY RSG voltage to 57 Hz; Clarified action required to complete critical task to match procedure step.

10/09/09 Modified to use for 2009-302 FNF CME

(

(

2009-302 Sim 6 Page 1 of 5 UNIT 1 0

UNIT 2 (X)

TASk NUMBER:

  • 't, POWER A DEENERGIZED BUS FROM A DIESEL GENERATOR, ALTERNATE PATH LR-IP-28.06A-02 The task shall be completed when the Operator has powered the 4160 VAC Emergency Bus "2E" successfully from the 2A Emergency Diesel per 34AB-R43-001-2.

028.006 AND 028.023 OBJECTrvENmwE:R: 028.006.C PLANT HATCH JTA IMPORTANCE RATING:

RO 4.14 SRO 3.30 KIA CATALOG NUMBER: 295003A1.02 KIA CATALOG JTA IMPORTANCE RATING:

RO 4.2 SRO 4.3 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO) 34AR-652-102-2 34S0-R43-001-2 34AB-R43-001-2 (current versions)

APPROXIMATE COMPLETION TIME:

7.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE 2009-302 Sim 6 Page 1 of 5 UNIT 1 0

UNIT 2 (X)

TASK TITLE:

JPMNUMBER:

TASK STANDARD:

TASK NUMBER:

POWER A DEENERGIZED BUS FROM A DIESEL GENERATOR, ALTERNATE PATH LR-JP-28.06A-02 The task shall be completed when the Operator has powered the 4160 VAC Emergency Bus "2E" successfully from the 2A Emergency Diesel per 34AB-R43-001-2.

028.006 AND 028.023 OBJECTIVE NUMBER: 028.006.C PLANT HATCH JTA IMPORTANCE RATING:

RO 4.14 SRO 3.30

(

KIA CATALOG NUMBER: 295003A1.02 KIA CATALOG JTA IMPORTANCE RATING:

RO 4.2 SRO 4.3 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

I ::;ENERAL REFERENCES Unit 2 34AR-652-102-2 34S0-R43-00l-2 34AB-R43-001-2 (current versions)

I REQUIRED MATERIALS:

Unit 2 34AB-R43-001-2 (current version)

APPROXIMATE COMPLETION TIME:

7.0 Minutes

(

SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

(

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to 100% Power and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS:

4KV Bus 2E Fault DIESEL GEN FAILURE TO Auto START 2A mtR43_239A DG A Output Brk One Shot Fail to Auto Tie

2.

INSERT the following OVERRIDES:

.. **MALF#

loR43-S251 Diesel 2A Mode Sel SW

-f1N;\\'l)

VALUE OFF

3.

Create the following EVENT TRIGGERS with the following information:

2009-302 Sim 6 Page 2 of 5 KEY UFjLJi\\X TllVlE 1

99999 0000 (NOTE: Use Windows "Notepad" to create blank *.scn and *.et files with the indicated names below. Copy the "ET INFORMATION" and "SCN INFORMATION" into the appropriate files.

Copy the 2 files into the simulators "HatchlInstrIET" directory).

S~l'JIJf!

. NAME R43-01.scn R43-01.et

DIESEL 2A SHUTDOWN RELAY ACTIVATES SYS OP LIGHT diR43-S57.aivToPanel= 1
4. ACTIVATE event triggers R43-01.

SCNINFORMATION DOR loR43-S251;

5.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A.

Activate malfunction mtR22_182 with Key 1.

B.

Hold the "A" EDG speed switch to slower for approximately 5 seconds.

C.

Remove malfunction mtR22_182.

4.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5.

ESTIMATED Simulator SETUP TIME:

10 Minutes

(

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to 100% Power and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS:

MALF#

TITLE FINAL VALUE mtR22_182 4KV Bus 2E Fault mtR43_62A DIESEL GEN FAILURE TO Auto START 2A mtR43_239A DG A Output Brk One Shot Fail to Auto Tie

2.

INSERT the following OVERRIDES:

MALF#

TITLE FINAL VALUE loR43-S251 Diesel 2A Mode Sel SW OFF (note: this is the System Operative Light)

3.

Create the following EVENT TRIGGERS with the following information:

KEY 1

KEY 2009-302 Sim 6 Page 2 of 5 DELAY TIME 99999 0000 ACT.

TIME (NOTE: Use Windows "Notepad" to create blank *.scn and *.et files with the indicated names below. Copy the "ET INFORMATION" and "SCN INFORMATION" into the appropriate files.

Copy the 2 files into the simulators "HatchlInstrIET" directory).

SCNIET ETINFORMATION SCN INFORMATION NAME R43-01.scn

DIESEL 2A SHUTDOWN RELAY DOR loR43-S251; R43-01.et ACTIV A TES SYS OP LIGHT diR43-S57.aivToPanel=1
4. ACTIVATE event triggers R43-01.
5.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Activate malfunction mtR22_182 with Key 1.

B.

Hold the "A" EDG speed switch to slower for approximately 5 seconds.

C.

Remove malfunction mtR22_182.

4.

PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5.

ESTIMATED Simulator SETUP TIME:

10 Minutes

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The 4160 VAC 2E Bus is de-energized.

2.

The 2A Emergency Diesel Generator has failed to start.

3.

Normal AC power is available to all other electrical distribution switchgear.

4.

34AR-652-102, LOSS OF OFFSITE POWER, is in progress.

INITIATING CUES:

Start the 2A Emergency Diesel Generator and Energize the 2E 4160 V AC Bus, per 34AB-R43-00l-2.

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The 4160 VAC 2E Bus is de-energized.

2.

The 2A Emergency Diesel Generator has failed to start.

3.

Normal AC power is available to all other electrical distribution switchgear.

4.

34AR-652-102, LOSS OF OFFSITE POWER, is in progress.

INITIATING CUES:

Start the 2A Emergency Diesel Generator and Energize the 2E 4160 VAC Bus, per 34AB-R43-00l-2.

STANI)'A.:RU 2009-302 Sim 6 Page 4 of 5

$A.TIUNSAT COMMENTS****

Note: The JPM uses the steps from 34AB-R43-001-2, PLACARD, manual Startup and Tying of Emergency diesel generator." The student may select to use the procedure steps from the body of the procedure which is allowable.

NOTE: All actions are performed on panel 2HII-P652.

1. Confirms EDG 2A is NOT running.
2. Verify the Auto Start System Operative Light is lit.

The operator the student verifies CLEAR Diesel Auto Start Sys Operative light is illuminated and the Red Diesel Start light is extinguished.

The operator determines the Auto Start System Operative Light is NOT lit.

!~*3~J)epresstheBieselShtltdo\\Vn~elay> The operator depresses the Diesel

.........pu$hburt9n Shutdown Relay pushbutton.

START TIME: ___ _

SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT: WHEN the Diesel Shutdown Relay pushbutton is depressed, THEN inform operator of time compression, 110 seconds have passed.

p'Iace***tlieEDGsiARf/STOp*switch toSTART.*

The operator momentarily places the 2A EDG START/STOP switch to start.

NOTE: This begins the Alternate path portion of this JPM.

5. Verify the EDG has started.

The operator verifies the "CLEAR Diesel Auto Start Sys Operative" light extinguishes and the "Red Diesel Start" light illuminates.

6. Verify the "E" 4160 V AC bus is The operator observes voltage on energized.

the "E" 4160 V AC bus equals "0" V AC and answers procedure step with "NO".

(** Indicates critical step)

SAT/UNSAT SAT/UNSAT SAT I UNSAT

(

(

PERFORMANCE STEP STANDARD 2009-302 Sim 6 Page 4 of 5 SATIUNSAT COMMENTS Note: The JPM uses the steps from 34AB-R43-001-2, PLACARD, manual Startup and Tying of Emergency diesel generator." The student may select to use the procedure steps from the body of the procedure which is allowable.

START TIME: ___ _

NOTE: All actions are performed on paneI2H11-P652.

1. Confirms EDG 2A is NOT running.

The operator the student verifies SAT/UNSAT CLEAR Diesel Auto Start Sys Operative light is illuminated and the Red Diesel Start light is extinguished.

2. Verify the Auto Start System The operator determines the Auto SAT/UNSAT Operative Light is lit.

Start System Operative Light is NOT lit.

    • 3. Depress the Diesel Shutdown Relay The operator depresses the Diesel SAT/UNSAT pushbutton Shutdown Relay pushbutton.

PROMPT: WHEN the Diesel Shutdown Relay pushbutton is depressed, THEN inform operator of time compression, 110 seconds have passed.

    • 4. Place the EDG START/STOP switch The operator momentarily places SAT/UNSAT to START.

the 2A EDG START/STOP switch to start.

NOTE: This begins the Alternate path portion of this JPM.

5. Verify the EDG has started.

The operator verifies the SAT/UNSAT "CLEAR Diesel Auto Start Sys Operative" light extinguishes and the "Red Diesel Start" light illuminates.

6. Verify the "E" 4160 VAC bus is The operator observes voltage on SAT/UNSAT energized.

the "E" 4160 V AC bus equals "0" V AC and answers procedure step with "NO".

(** Indicates critical step)

9. Verify the "E" bus is energized.

At panel 2HII-P652, the Diesel Gen 2A SPEED ADJUST switch has been taken to LOWER until frequency is 57 Hz (+ or - 1 hz).

At paneI2HII-P652, the Diesel Gen 2A SPEED ADJUST switch has been taken to RAISE until frequency is 60 Hz (+ or - 1 hz).

(Critical action is EDG output breaker closing)

The operator observes voltage on the "E" 4160 V AC bus equals "4160" VAC and answers procedure step with "Yes".

2009-302 Sim 6 Page 5 of5 Sj\\TWNSAT COMMENTS SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:

IF the opeator used the placard for energizing 2E Bus, when the operator goes to get to 34AB-R43-00l-2, INFORM the operator that another operator will verify actions IA W 34AB-R43-00l-2.

NOTE: The terminating cue shall be given to the Operator when:

With no reasonable progress, the Operator exceeds double the allotted time.

4160 Bus 2E is energized with frequency at 59 - 61 Hz.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

(

PERFORMANCE STEP

    • 7. Using Diesel Gen 2A(e) Speed Adjust, lower frequency to*57 Hz.
    • 8. Using Diesel Gen 2A(C) Speed Adjust, raise frequency to 60 Hz.
9. Verify the "E" bus is energized.

STANDARD At pane12HI1-P652, the Diesel Gen 2A SPEED ADJUST switch has been taken to LOWER until frequency is 57 Hz (+ or - 1 hz).

At pane12Hll-P652, the Diesel Gen 2A SPEED ADJUST switch has been taken to RAISE until frequency is 60 Hz (+ or - 1 hz).

(Critical action is EDG output breaker closing)

The operator observes voltage on the "E" 4160 VAC bus equals "4160" VAC and answers procedure step with "Yes".

2009-302 Sim 6 Page 5 of 5 SATIUNSAT COMMENTS SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:

IF the opeator used the placard for energizing 2E Bus, when the operator goes to get to 34AB-R43-00l-2, INFORM the operator that another operator will verify actions IA W 34AB-R43-00l-2.

NOTE:

The terminating cue shall be given to the Operator when:

With no reasonable progress, the Operator exceeds double the allotted time.

4160 Bus 2E is energized with frequency at 59 - 61 Hz.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The 4160 V AC 2E Bus is de-energized.

2.

The 2A Emergency Diesel Generator has failed to start.

3.

Normal AC power is available to all other electrical distribution switchgear.

4.

34AR-652-102, LOSS OF OFF SITE POWER, is in progress.

INITIATING CUES:

Start the 2A Emergency Diesel Generator and Energize the 2E 4160 VAC Bus, per 34AB-R43-001-2.

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The 4160 V AC 2E Bus is de-energized.

2.

The 2A Emergency Diesel Generator has failed to start.

3.

Normal AC power is available to all other electrical distribution switchgear.

4.

34AR-652-102, LOSS OF OFF SITE POWER, is in progress.

INITIATING CUES:

Start the 2A Emergency Diesel Generator and Energize the 2E 4160 V AC Bus, per 34AB-R43-001-2.

(

F.FAGAN FI Southern E. I. Hatch AL uclear uclear Plant Operations Training JPM Simulator 7 - RO ONLY 2009-302 Sim 7

,:--~:

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BECQ~NDEDBV;**

  • ARPR.OVEtfJiv.

C.M.EDMUND N/R 1010912009 Energy to Serve Your World sM

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(

TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 7 - RO ONLY CONDUCT A ROD WORTH MINIMIZER (RWM) FUNCTIONAL TEST (FAILURE)

AUTHOR MEDIA NUMBER TIME F.FAGAN 2009-302 Sim 7 10.0 Minutes RECOMMENDED BY APPROVED BY DATE N/R C.M.EDMUND 10109/2009 Energy to Serve Your World sM

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERA TIONS TRAINING Media Number:

2009-302 Sim 7 00 11/15/99 Initial development RAB DHG 01 11106/00 Include objective number RAB DHG 02 03 04 05 03/19/02 Include initial operator statement 03/17/05 Deleted "S" from procedure numbers, changed Revision and Rev. numbers to "Current Version".

Changed to Nuclear Plant Operator. Updated Simulator IC# and added "Prompt" for sequence control mode.

06127/05 Revised Initial License statement for successful completion 06/30/05 Remove Response Cues 10/09/09 Revised for use on 2009-302 RAB RAB ARB DHG RAB RAB RAB RAB FNF CME

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Sim 7 Rev. No.

Date Reason for Revision Author's Supv's Initials Initials 00 11115/99 Initial development RAB DHG 01 11/06/00 Include objective number RAB DHG 02 03119/02 Include initial operator statement RAB RAB 03 03117/05 Deleted "s" from procedure numbers, changed ARB DHG Revision and Rev. numbers to "Current Version".

Changed to Nuclear Plant Operator. Updated Simulator IC# and added "Prompt" for sequence control mode.

04 06/27/05 Revised Initial License statement for successful RAB RAB completion 05 06/30/05 Remove Response Cues RAB RAB 10/09/09 Revised for use on 2009-302 FNF CME

2009-302 Sim 7 Page 1 of7 UNIT 1 0

UNIT 2 (X)

TASKN1Jl\\113ER!

CONDUCT A ROD WORTH MINIMIZER (RWM)

FUNCTIONAL TEST (FAILURE)

LR-JP-25032-05 The task shall be completed when the operator has successfully conducted the Rod Worth Minimizer Functional Test per 34GO-OPS-OO 1.

001.014

()BJ~¢TrV~.l~lJ~ER: 001.014.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.40 SRO 2.85 KIA CATALOG NUMBER: 201006A302 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.5 SRO 3.4 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

GENERAL*

REFERENCES:

(current version)

Control Rod Movement Se uence APPROXIMATE COMPLETION TIME:

10.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE UNIT 1 0

2009-302 Sim 7 Page 1 of7 UNIT 2 (X)

TASK TITLE:

CONDUCT A ROD WORTH MINIMIZER (RWM)

FUNCTIONAL TEST (FAILURE)

JPMNUMBER:

LR-JP-25032-05 TASK STANDARD:

The task shall be completed when the operator has successfully conducted the Rod Worth Minimizer Functional Test per 34GO-OPS-001.

TASK NUMBER:

001.014 OBJECTIVE NUMBER: 001.014.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.40 SRO 2.85 KIA CATALOG NUMBER: 201006A302

(

KIA CATALOG JTA IMPORTANCE RATING:

RO 3.5 SRO 3.4 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

I GENERAL

REFERENCES:

Unit 1 Unit 2 34GO-OPS-00l-1 34GO-OPS-00 1-2 34GO-OPS-065-0 34GO-OPS-065-0 34AB-C 11-004-1 34AB-C11-004-2 Control Rod Movement Control Rod Movement Sequence Sequence (current versions)

(current versions)

I REQUIRED MATERIALS:

Unit 1 Unit 2 34GO-OPS-00l-1 Att 5 34GO-OPS-00l-2 Att 5 (current version)

(current version)

Control Rod Movement Control Rod Movement Sequence Sequence APPROXIMA TE COMPLETION TIME:

10.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #102 and leave in FREEZE.

2.

INSERT the following ORS OVERRIDES:

RWM Mode Switch

3. INSERT the following MALFUNCTIONS:

BYPASS 2009-302 Sim 7 Page 2 of7 SA'fIIJNSA.T (COMMENTS)..

1 l[INA.L RAMP VAtUE** RATE rnfC12 24 50-31 Control Rod 50-31Drift Out

4.

Create the following EVENT TRIGGERS with the following information:

(NOTE: Use Windows "Notepad" to create blank *.scn and *.et files with the indicated names below. Copy the "ET INFORMATION" and "SCN INFORMATION" into the appropriate files.

Copy the 2 files into the simulators "HatchlInstrIET" directory).

C91-01.scn C91-01.et

Selected Rod Bypasses RWM loC51-RS-50-31Bl.al ToPanel=1
5. ACTIVATE Event Trigger C91-01.

lOR diC91-JOOl f:2

6.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A.

Reset all annunciators.

B.

Place Rx Mode Switch to Startup.

C.

Select a control rod from Step 1 and initialize the RWM by pushing the ETC button on the operator display.

D. Verify that all RWM rod blocks are clear and the Rod Sequence Selector Switch is in A-2.

E. Use Remote Function rfC51_190, RWM Sequence Control, and place to ON.

7.

PLACE the Simulator in FREEZE until the crew assumes the shift.

8.

ESTIMATED Simulator SETUP TIME:

10 Minutes

9.

HAVE an extra person available to hold the Rod-in switch for the operator, if requested.

(** Indicates critical step) 2009-302 Sim 7 Page 2 of7 PERFO~CESTEP STANDARD SATIUNSAT (COMMENTS SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #102 and leave in FREEZE.

2.

INSERT the following ORS OVERRIDES:

TAG #

DESCRIPTION STATUS Key diC9LJOOl RWM Mode Switch BYPASS 1

3. INSERT the following MALFUNCTIONS:

MALF#

TITLE FINAL RAMP Key VALUE RATE mfC12 2450-31 Control Rod 50-31Drift Out

4.

Create the following EVENT TRIGGERS with the following information:

(NOTE: Use Windows "Notepad" to create blank *.scn and *.et files with the indicated names below. Copy the "ET INFORMATION" and "SCN INFORMATION" into the appropriate files.

Copy the 2 files into the simulators "HatchlInstrIET" directory).

SCNIET ET INFORMATION SCN INFORMATION NAME C91-01.scn

Selected Rod Bypasses RWM lOR diC91-JOOl f
2 C91-01.et loC51-RS-50-31B l.algToPanel=1
5. ACTIVATE Event Trigger C91-01.
6.

Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A.

Reset all annunciators.

B.

Place Rx Mode Switch to Startup.

C.

Select a control rod from Step 1 and initialize the RWM by pushing the ETC button on the operator display.

D. Verify that all RWM rod blocks are clear and the Rod Sequence Selector Switch is in A-2.

E. Use Remote Function rfC5L190, RWM Sequence Control, and place to ON.

7.

PLACE the Simulator in FREEZE until the crew assumes the shift.

8.

ESTIMATED Simulator SETUP TIME:

10 Minutes

9.

HAVE an extra person available to hold the Rod-in switch for the operator, if requested.

(** Indicates critical step)

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A Unit 2 plant startup is commencing and the Reactor Mode Switch is in START & HOT STBY.
2. All systems required for plant startup are in service. Permission for Reactor startup has been given.
3. 34GO-OPS-OOl-2, "Plant Startup," is in progress.
4. The Rod Worth Minimizer Functional Test is the next startup action to be completed INITIATING CUES:

Perform the Rod Worth Minimizer Functional Test using Attachment 5 of 34GO-OPS-OOl-2.

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A Unit 2 plant startup is commencing and the Reactor Mode Switch is in START & HOT STBY.
2. All systems required for plant startup are in service. Permission for Reactor startup has been given.
3. 34GO-OPS-OOI-2, "Plant Startup," is in progress.
4. The Rod Worth Minimizer Functional Test is the next startup action to be completed INITIATING CUES:

Perform the Rod Worth Minimizer Functional Test using Attachment 5 of 34GO-OPS-OOl-2.

(

1. Operator confirms that power is Operator has VERIFIED power is turned on to the Refueling Bridge.

turned on to the Refueling Bridge.

2009-302 Sim 7 Page 4 of7 START TIME: ___ _

SAT I UNSAT PROMPT:

WHEN the operator addresses confirming power on the Refueling Bridge, as the SO, INFORM the operator that the Refueling Bridge has power.

2. Confirm RMCSIRWM ROD BLOCK At paneI2H11-P603, the operator SAT/UNSAT OR SYS TROUBLE annunciator is VERIFIES that the annunciator clear.

603-239, RMCSIRWM ROD BLOCK OR SYS TROUBLE, is extinguished.

PROMPT:

WHEN the operator addresses Section 1.3, (STA Verifies that the correct rod sequence has been loaded into the RWM), INFORM the operator that the STA has completed all of Section 1.3.

3. Confirm RWM keylock switches are At paneI2H11-P603, the operator SAT/UNSAT in OPERATE.

confirms that the RWMs Operator Display keylock switch is in OPERATE. (Key is vertical.)

AND Request another Operator to confirm that the Instrument Console keylock switch at panel 2H11-P616 is in OPERATE.

PROMPT:

WHEN the operator addresses the Instrument Console keylock switch on paneI2H11-P616, INFORM the operator it is in the OPERATE position.

4. Confirm Step 01 is displayed on At paneI2H11-P603, the operator SAT/UNSAT RWM Operator's Display.

has VERIFIED that 01 is displayed on the RWM Operator's Display.

5. Confirm the Reactor Mode switch is At paneI2H11-P603, the operator SAT/UNSAT in START & HOT STBY.

CONFIRMS the Reactor Mode switch is in START & HOT STBY.

(** Indicates critical step)

(

(

PERFORMANCE STEP STANDARD

1. Operator confirms that power is Operator has VERIFIED power is turned on to the Refueling Bridge.

turned on to the Refueling Bridge.

2009-302 Sim 7 Page 4 of7 SATIUNSAT COMMENTS START TIME: ___ _

SAT I UNSAT PROMPT:

WHEN the operator addresses confirming power on the Refueling Bridge, as the SO, INFORM the operator that the Refueling Bridge has power.

2. Confirm RMCS/RWM ROD BLOCK At paneI2HII-P603, the operator SAT I UNSAT OR SYS TROUBLE annunciator is VERIFIES that the annunciator clear.

603-239, RMCS/RWM ROD BLOCK OR SYS TROUBLE, is extinguished.

PROMPT:

WHEN the operator addresses Section 1.3, (STA Verifies that the correct rod sequence has been loaded into the RWM), INFORM the operator that the STA has completed all of Section 1.3.

3. Confirm RWM keylock switches are At paneI2HII-P603, the operator SAT/UNSAT in OPERATE.

confirms that the RWMs Operator Display keylock switch is in OPERATE. (Key is vertical.)

AND Request another Operator to confirm that the Instrument Console keylock switch at panel 2HII-P616 is in OPERATE.

PROMPT:

WHEN the operator addresses the Instrument Console keylock switch on paneI2HII-P616, INFORM the operator it is in the OPERATE position.

4. Confirm Step 01 is displayed on At paneI2HII-P603, the operator SAT/UNSAT RWM Operator's Display.

has VERIFIED that 01 is displayed on the RWM Operator's Display.

5. Confirm the Reactor Mode switch is At paneI2HII-P603, the operator SAT/UNSAT in START & HOT STBY.

CONFIRMS the Reactor Mode switch is in START & HOT STBY.

(** Indicates critical step)

(

At paneI2H11-P603, using the CONTROL ROD SELECT matrix pushbuttons, rod 22-51 is selected AND At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:

-"SE" "WB"

-"BLOCK: WITHDRAW".

2009-302 Sim 7 PageS of7 SAT/UNSAT NOTE: If the operator selects any rod not in Step 1 of the RWM Sequence, he will still receive the same indications as a Step 2 rod.

At panel2H11-P603, the operator positions Rod Movement Control Switch to OUTNOTCH and VERIFIES no rod motion occurred.

SAT/UNSAT PROMPT: WHEN the operator asks the STA for RWM step that has a Group 3 rod in it, INFORM the operator to SELECT the FIRST ROD in Step 07.

(** Indicates critical step)

At panel2H11-P603, using the CONTROL ROD SELECT matrix pushbuttons, rod 02-23 is SELECTED from AND At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:

-"SE" "WB"

-"BLOCK: WITHDRAW".

At panel2H11-P603, the operator positions Rod Movement Control Switch to OUTNOTCH and VERIFIES no rod motion occurred.

SAT/UNSAT SAT I UNSAT

    • 6.
    • 7.

PERFORMANCE STEP Select* a rod from Step 2.ofthe Rod Worth Minimizer Sequence and verify system response.

STANDARD At pane12HII-P603, using the CONTROL ROD SELECT matrix pushbuttons, rod 22-51 is selected AND At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:

-"SE" "WB"

-"BLOCK: WITHDRA W".

2009-302 Sim 7 Page 5 of7 SATIUNSAT (COMMENTS SAT/UNSAT NOTE: If the operator selects any rod not in Step 1 of the RWM Sequence, he will still receive the same indications as a Step 2 rod.

Attempt to withdraw the selected Tod.

At paneI2HII-P603, the operator SAT/UNSAT positions Rod Movement Control Switch to OUTNOTCH and VERIFIES no rod motion occurred.

PROMPT: WHEN the operator asks the STA for RWM step that has a Group 3 rod in it, INFORM the operator to SELECT the FIRST ROD in Step 07.

    • 8. Select a rod from Group 3 of the Rod At paneI2HII-P603, using the SAT/UNSAT Worth Minimizer Sequence and verify CONTROL ROD SELECT system response.

matrix pushbuttons, rod 02-23 is SELECTED from AND At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:

-"SE" "WB"

-"BLOCK: WITHDRAW".

    • 9. Attempt to withdraw the selected rod.

At paneI2HII-P603, the operator SAT I UNSAT positions Rod Movement Control Switch to OUTNOTCH and VERIFIES no rod motion occurred.

(*

  • Indicates critical step)

(

NOTE: When the operator selects this next control rod, the event trigger will activate causing RWM to be bypassed so the rod will move.

2009-302 Sim 7 Page 6 of7 PROMPT: WHEN the operator asks the STA for RWM step that has a Group 4 rod in it, INFORM the operator to SELECT the FIRST ROD in Step 13.

PROMPT:

At pane12HII-P603, using the CONTROL ROD SELECT matrix pushbuttons, rod 50-31 is SELECTED AND At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:

-"SE" "WB"

-"BLOCK: WITHDRAW".

At paneI2HII-P603, the operator positions Rod Movement Control Switch to OUTNOTCH and recognizes rod motion HAS occurred.

IF addressed by the operator, INFORM the operator that the STA has confirmed the RWM Scram Buffers are clear and ready to accept data.

(** Indicates critical step)

SAT/UNSAT SAT I UNSAT

\\.

(

    • 10.
    • 11.

PERFORMANCE STEP STANDARD 2009-302 Sim 7 Page 6 of7 SATIUNSAT (COMMENTS NOTE: When the operator selects this next control rod, the event trigger will activate causing RWM to be bypassed so the rod will move.

PROMPT: WHEN the operator asks the STA for RWM step that has a Group 4 rod in it, INFORM the operator to SELECT the FIRST ROD in Step 13.

Select a rod from Group 4 of the Rod At pane12Hll-P603, using the SAT/UNSAT Worth Minimizer Sequence and verify CONTROL ROD SELECT system response matrix pushbuttons, rod 50-31 is SELECTED AND At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:

-"SE" "WB"

-"BLOCK: WITHDRA W".

Attempt to withdraw the selected rod.

At pane12Hll-P603, the operator SAT/UNSAT positions Rod Movement Control Switch to OUTNOTCH and recognizes rod motion HAS occurred.

PROMPT:

IF addressed by the operator, INFORM the operator that the STA has confirmed the RWM Scram Buffers are clear and ready to accept data.

(*

  • Indicates critical step)
12. Insert the control rod and inform the SS that the RWM test failed.

. *STANQARl)

At paneI2HI1-P603, the operator moves the Rod Movement Control Switch to IN to INSERT the control rod.

The operator informs the Shift Supervisor the control rod is drifting out.

2009-302 Sim 7 Page 7 of7 SATIJJNSAT.

(COMMENtS SAT I UNSAT SAT/UNSAT PROMPT: If the operator requests assistance from another oprator to hold the Rod-In switch, then hold or have a provided extra operator hold the switch. If requested to hand the applicant the abnormal procedure, Do NOT let the applicant get another operator get the procedure for correcting the drifting rod.

14. Obtain 34AB-CI1-004-2 "Mispositioned Control Rods.

Operator obtains 34AB-C 11-004-2 "Mispositioned Control Rods" and refers to section 4.4.

Operator inserts a manual reactor scram.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

SAT/UNSAT SAT/UNSAT END TIME: ___ _

PERFO~NCESTEP

12. Insert the control rod and inform the SS that the RWM test failed.
    • 13. Informs the Shift Supervisor the control rod is drifting out.

STANDARD At paneI2HII-P603, the operator moves the Rod Movement Control Switch to IN to INSERT the control rod.

The operator informs the Shift Supervisor the control rod is drifting out.

2009-302 Sim 7 Page 7 of7 SATIUNSAT (COMMENTS SAT I UNSAT SAT I UNSAT PROMPT: If the operator requests assistance from another oprator to hold the Rod-In switch, then hold or have a provided extra operator hold the switch. If requested to hand the applicant the abnormal procedure, Do NOT let the applicant get another operator get the procedure for correcting the drifting rod.

14.
    • 15.

Obtain 34AB-CII-004-2 Operator obtains 34AB-CII-004-

"Mispositioned Control Rods.

2 "Mispositioned Control Rods" and refers to section 4.4.

Insert a scram.

Operator inserts a manual reactor scram.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(*

  • Indicates critical step)

SAT/UNSAT SAT/UNSAT END TIME: ___ _

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A Unit 2 plant startup is commencing and the Reactor Mode Switch is in START & HOT STBY.
2. All systems required for plant startup are in service. Permission for Reactor startup has been given.
3. 34GO-OPS-OOl-2, "Plant Startup," is in progress.
4. The Rod Worth Minimizer Functional Test is the next startup action to be completed INITIATING CUES:

Perform the Rod Worth Minimizer Functional Test using Attachment 5 of 34GO-OPS-OOl-2.

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A Unit 2 plant startup is commencing and the Reactor Mode Switch is in START & HOT STBY.
2. All systems required for plant startup are in service. Permission for Reactor startup has been given.
3. 34GO-OPS-OOl-2, "Plant Startup," is in progress.
4. The Rod Worth Minimizer Functional Test is the next startup action to be completed INITIATING CUES:

Perform the Rod Worth Minimizer Functional Test using Attachment 5 of 34GO-OPS-OOl-2.

SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 59 OF 78 DOCUMENT TITLE:

PLANT STARTUP DOCUMENT NUMBER:

34GO-OPS-001-2 VERSION NO:

38.21 TITLE:

ATTACHMENT 2 RWM OPERABILITY CHECK ATTACHMENT PAGE:

1 OF 2 NOTE:

CONTINUOUS I

With the RWM inoperable, after the first 12 control rods have been fully withdrawn on a startup, operation may continue AND control rod movement is permitted provided that a Peer Checker (licensed operator OR other qualified member of the technical staff) is also present at the reactor control console, with no other concurrent duties, AND double verifies compliance with the prescribed BPWS control rod pattern (Unit 2 TS 3.3.2.1).

CAUTION:

Control Rod movement is NOT expected during the RWM operability check.

IF control rod movement is observed, the control rod must be immediately returned to the full in position AND the SS AND STA notified that the RMW has failed its operability check.

1.0 Confirm Rod Worth Minimizer (RWM) is operable as follows:

1.1 Confirm power is turned on to the Refueling Bridge to remove that as a source of a rod block.

1.2 Confirm annunciator 603-239, RMCS/RWM ROD BLOCK OR SYSTEM TROUBLE, is CLEAR.

1.3 Request the STA perform the following:

1.3.1 Confirm the currently selected sequence in the RWM is identical to the control rod movement sheets (refer to 34GO-OPS-065-0) AND conforms to BPWS.

1.3.2 Check the Rod Bypass Options on the RWM Operator's display AND confirm bypassed rods match the change log of the Control Rod Movement Sequence.

1.3.3 Initiate the RWM's Full Range Sequence Control mode per the RWM Full Range Sequence Control subsection of 34GO-OPS-065-0, Control Rod Movement.

1.4 Confirm RWM Operator's Display keylock switch AND the Instrument Console's keylock switch are both in the OPERATE position with the keys removed.

1.5 Confirm '01' is displayed as the step on the RWM Operator's Display.

OPS-1073 Ver. N/A G16.030 MGR-0009 Rev. 5.0

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(

SOUTHERN NUCLEAR PLANT E.!. HATCH PAGE 59 OF 78 DOCUMENT TITLE:

DOCUMENT NUMBER:

34GO-O PS-OO 1-2 VERSION NO:

38.21 TITLE:

NOTE:

PLANT STARTUP ATTACHMENT -2 RWM OPERABILITY CHECK CONTINUOUS I

ATTACHMENT PAGE:

1 OF 2 With the RWM inoperable, after the first 12 control rods have been fully withdrawn on a startup, operation may continue AND control rod movement is permitted provided that a Peer Checker (licensed operator OR other qualified member of the technical staff) is also present at the reactor control console, with no other concurrent duties, AND double verifies compliance with the prescribed BPWS control rod pattern (Unit 2 TS 3.3.2.1).

CAUTION:

Control Rod movement is NOT expected during the RWM operability check.

IF control rod movement is observed, the control rod must be immediately returned to the full in position AND the SS AND STA notified that the RMW has failed its operability check.

1.0 1.1 1.2 1.3 1.3.1 Confirm Rod Worth Minimizer (RWM) is operable as follows:

Confirm power is turned on to the Refueling Bridge to remove that as a source of a rod block.

Confirm annunciator 603-239, RMCS/RWM ROD BLOCK OR SYSTEM TROUBLE, is CLEAR.

Request the STA perform the following:

Confirm the currently selected sequence in the RWM is identical to the control rod movement sheets (refer to 34GO-OPS-065-0) AND conforms to BPWS.

1.3.2 Check the Rod Bypass Options on the RWM Operator's display AND confirm bypassed rods match the change log of the Control Rod Movement Sequence.

1.3.3 Initiate the RWM's Full Range Sequence Control mode per the RWM Full Range Sequence Control subsection of 34GO-OPS-065-0, Control Rod Movement.

1.4 Confirm RWM Operator's Display keylock switch AND the Instrument Console's keylock switch are both in the OPERATE position with the keys removed.

1.5 Confirm '01' is displayed as the step on the RWM Operator's Display.

OPS-1073 Ver. N/A G16.030 MGR-0009 Rev. 5.0

(

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 60 OF 78 DOCUMENT TITLE:

DOCUMENT NUMBER:

34GO-OPS-001-2 VERSION NO:

38.21 TITLE:

PLANT STARTUP ATTACHMENT..§ RWM OPERABILITY CHECK ATTACHMENT PAGE:

20F2 1.6 Place OR confirm the Reactor Mode switch in START & HOT STBY position.

1.7 Select a rod from step 2 of the RWM Sequence AND perform the following:

1.7.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.

1.7.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.

1.8 Have the STAIReactor Engineering determine a RWM step that contains a RWM Sequence Rod Group 3 Control Rod.

1.9 1.9.1 1.9.2 1.10 Step #: ____ _

Select a rod from the step number listed above of the RWM Sequence AND perform the following:

Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.

Attempt to withdraw the selected rod AND confirm no rod motion occurs.

Have the ST AlReactor Engineering determine a RWM step that contains a RWM Sequence Rod Group 4 Control Rod.

Step #: ____ _

1.11 Select a rod from the step number listed above of the RWM sequence AND perform the following:

1.11.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.

1.11.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.

2.0 Have the STA confirm the RWM scram buffers are clear AND ready to accept data.

OPS-1073 Ver. N/A G16.030 MGR-0009 Rev. 5.0

(

(

SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:

TITLE:

PLANT STARTUP ATTACHMENT..§ RWM OPERABILITY CHECK DOCUMENT NUMBER:

34GO-OPS-001-2 PAGE 60 OF 78 VERSION NO:

38.21 ATTACHMENT PAGE:

20F2 1.6 Place OR confirm the Reactor Mode switch in START & HOT STBY position.

1.7 Select a rod from step 2 of the RWM Sequence AND perform the following:

1.7.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.

1.7.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.

1.8 Have the ST AlReactor Engineering determine a RWM step that contains a RWM Sequence Rod Group 3 Control Rod.

Step #: ____ _

1.9 Select a rod from the step number listed above of the RWM Sequence AND perform the following:

1.9.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.

1.9.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.

1.10 Have the ST AlReactor Engineering determine a RWM step that contains a RWM Sequence Rod Group 4 Control Rod.

Step #: ____ _

1.11 Select a rod from the step number listed above of the RWM sequence AND perform the following:

1.11.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.

1.11.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.

2.0 Have the STA confirm the RWM scram buffers are clear AND ready to accept data.

OPS-1073 Ver. N/A G16.030 MGR-0009 Rev. 5.0

SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:

TITLE:

PLANT STARTUP ATTACHMENT..§ ROD DRIFT ALARM TEST DOCUMENT NUMBER:

34GO-OPS-001-2 CONTINUOUS I

PAGE 61 OF 78 VERSION NO:

38.21 ATTACHMENT PAGE:

1 OF 1 1.0 During withdrawal of a Group 1 control rod while the Rod Movement Control switch is in the OUT NOTCH position, perform the following:

1.1 Take Rod Drift Alarm Test Switch to TEST AND confirm the following:

1.1.1 Full Core Display red ROD DRIFT light for the control rod being tested ILLUMINATES.

1.1.2 Annunciator ROD DRIFT, ALARMS.

1.2 Take the Rod Drift Alarm Test switch to RESET AND confirm the following:

1.2.1 Full Core Display red ROD Drift light for the control rod being tested EXTINGUISHES.

1.2.2 Annunciator ROD DRIFT, CLEARS.

OPS-1074 Ver. N/A G16.030 MGR-0009 Rev. 5.0

(

(

SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:

TITLE:

PLANT STARTUP ATTACHMENT..§ ROD DRIFT ALARM TEST DOCUMENT NUMBER:

34GO-OPS-001-2 CONTINUOUS I

PAGE 61 OF 78 VERSION NO:

38.21 ATTACHMENT PAGE:

1 OF 1 1.0 During withdrawal of a Group 1 control rod while the Rod Movement Control switch is in the OUT NOTCH position, perform the following:

1.1 Take Rod Drift Alarm Test Switch to TEST AND confirm the following:

1.1.1 Full Core Display red ROD DRIFT light for the control rod being tested ILLUMINATES.

1.1.2 Annunciator ROD DRIFT, ALARMS.

1.2 Take the Rod Drift Alarm Test switch to RESET AND confirm the following:

1.2.1 Full Core Display red ROD Drift light for the control rod being tested EXTINGUISHES.

1.2.2 Annunciator ROD DRIFT, CLEARS.

OPS-1074 Ver. N/A G16.030 MGR-0009 Rev. 5.0

(

(

FI AL Southern uclear E. I. Hatch Nuclear lant Operations Training JPM Simulator 8 - All LOSS OF AIR ACTIONS FOR RX BLDG VENTILATION A.UTHOR**********

EN.FAGAN N/R C.M.EDMUND 10109/2009 Energy to Serve Your World sM

(

TITLE AUTHOR F.N.FAGAN FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 8 - All LOSS OF AIR ACTIONS FOR RX BLDG VENTILATION MEDIA NUMBER TIME 2009-302 Sim 8 20 Minutes RECOMMENDED BY APPROVED BY DATE N/R C.M.EDMUND 1010912009 Energy to Serve Your World sM

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:

OPERATIONS TRAINING Page 1 of 1 Media Number:

2009-302 Sim 8 00 05/18/09 Initial development FNF CME

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:

OPERATIONS TRAINING Rev. No.

Date Reason for Revision 00 05118/09 Initial development Page 1 of 1 Media Number:

2009-302 Sim 8 Author's Supv's Initials Initials FNF CME

(

UNIT 1 0

2009-302 Sim 8 Page 1 of9 UNIT2 (X)

Recognize and Respond to an Instrument and Service Air Failure LR-JP-NRC-SIM8 The task shall be complete when the operator has completed 34AB-P51-00l-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air.

H-OPR0200.025 200.025.C from SG50273 PLANT HATCH JTA IMPORTANCE RATING:

RO 3.93 SRO 3.61 KIA CATALOG NUMBER: 295019AK2.08 KIA CATALOG JTA IMPORTANCE RATING:

RO 2.8 SRO 2.9 OPERATOR APPLICABILITY:

RO APPROXIMATE COMPLETION TIME:

20 Minutes SIMULATOR SETUP:

See the next sheet.

2009-302 Sim 8 Page 1 of9 UNIT 1 0

UNIT 2 (X)

TASK TITLE:

Recognize and Respond to an Instrument and Service Air Failure JPM NUMBER:

LR-JP-NRC-SIM8 TASK STANDARD:

The task shall be complete when the operator has completed 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air.

TASK NUMBER:

H-OPR0200.025 OBJECTIVE NUMBER:

200.025.C from SG50273 PLANT HATCH JTA IMPORTANCE RATING:

RO 3.93 SRO 3.61 KIA CATALOG NUMBER: 295019AK2.08

(

KIA CATALOG JTA IMPORTANCE RATING:

RO 2.8 SRO 2.9 OPERA TOR APPLICABILITY:

RO I GENERAL

REFERENCES:

Unit 1 & 2 34AB-P51-00 1-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" I REQUIRED MATERIALS:

Unit 1 & 2 34AB-P51-001-2 "Loss Oflnstrument And Service Air System Or Water Intrusion Into The Service Air System" completed through step 4.13.

APPROXIMATE COMPLETION TIME:

20 Minutes

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SIMULATOR SETUP:

See the next sheet.

(

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #113 and place in RUN.

2. INSERT the following MALFUNCTIONS:

mtP51_222A Service Air Compressor 2A Trip mtP51_222B Service Air Compressor 2B Trip mtP51_222C Service Air Compressor 2C Trip mtP52_191 Instrument Air Leakage mfC71_59 Spurious Reactor Scram

3. INSERT the following OVERRIDES:

diT46-DOOIA-l SBGTS A Fan/Filter AUTO diT46-DOOIB-l SBGTS B FanlFilter AUTO diP52-F565 Rx Bldg Inst. N2 to Noninter. Ser. Vlv.

OPEN

4.

Create the following EVENT TRIGGERS with the following information:

2009-302 Sim 8 Page 2 of9 (NOTE: Use Windows "Notepad" to create blank *.scn and *.et files with the indicated names below. Copy the "ET INFORMATION" and "SCN INFORMATION" into the appropriate files.

Copy the 4 files into the simulators "HatchlInstrIET" directory).

T46-11.scn T46-11.et T46-12.scn T46-12.et

SBGT A in RUN doesn't work, B works diT46-DOOIA-l.iivPanel=3
SBGT B in RUN doesn't work, A works diT46-DOOIB-l.iivPanel=3
5. ACTIVATE event triggers T46-11 and T46-12.
6. Place Rx Mode Switch to Shutdown.

DOR diT46-DOOIB-l; CET T46-12; DOR diT46-DOOIA-l; CETT46-11'

(

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #113 and place in RUN.

2. INSERT the following MALFUNCTIONS:

MALF#

TITLE FINAL RAMP VALUE RATE mtP51_222A Service Air Compressor 2A Trip mtP51_222B Service Air Compressor 2B Trip mtP5L222C Service Air Compressor 2C Trip mtP52_191 Instrument Air Leakage mfC7L59 Spurious Reactor Scram

3. INSERT the following OVERRIDES:

OVERIDE#

TITLE FINAL VALUE diT46-DOOIA-l SBGTS A FaniFilter AUTO diT46-DOOIB-l SBGTS B FaniFilter AUTO diP52-F565 Rx Bldg Inst. N2 to Noninter. Ser. Vlv.

OPEN

4.

Create the following EVENT TRIGGERS with the following information:

2009-302 Sim 8 Page 2of9 ACT.

TIME (NOTE: Use Windows "Notepad" to create blank *.scn and *.et files with the indicated names below. Copy the "ET INFORMATION" and "SCN INFORMATION" into the appropriate files.

Copy the 4 files into the simulators "Hatch/lnstrIET" directory).

SCNIET ET INFORMATION NAME T46-11.scn

SBGT A in RUN doesn't work, B works T46-11.et diT46-DOOIA-l.iivPanel=3 T46-12.scn
SBGT B in RUN doesn't work, A works T46-12.et diT46-DOOIB-l.iivPanel=3
s.

ACTIVATE event triggers T46-11 and T46-12.

6.

Place Rx Mode Switch to Shutdown.

SCN INFORMATION DOR diT46-DOOIB-l; CET T46-12; DOR diT46-DOOIA-l; CETT46-11;

2009-302 Sim 8 Page 3 of9

7. Place RCIC in service, injecting into the vessel, with level slowly rising (this is to prevent the auto start of SBGT).
8.

Allow the simulator to run until the SBGT air operated valves (FOO1l2/3) fail open (-4 minutes)

9.

Mark up 34AB-P51-001-2 up to, but not including, step 4.14.

10. PLACE the Simulator in FREEZE until the INffiATING CUE is given.
11.

ESTIMATED Simulator SETUP TIME:

10 Minutes

(

2009-302 Sim 8 Page 3 of9

7.

Place RCIC in service, injecting into the vessel, with level slowly rising (this is to prevent the auto start of SBGT).

8.

Allow the simulator to run until the SBGT air operated valves (FOOI/2/3) fail open (-4 minutes)

9.

Mark up 34AB-P5I-00l-2 up to, but not including, step 4.14.

10. PLACE the Simulator in FREEZE until the INITIATING CUE is given.
11.

ESTIMA TED Simulator SETUP TIME:

10 Minutes

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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has lost all Service Air Compressors and they can not be restarted.
2. Electrical Maintenance and I&C are checking all air system electrical circuits.
3. The reactor has been scrammed and 34AB-C71-001-2, "Scram Procedure" is being carried out.
4. 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" has been partially completed.

INITIATING CUES:

Complete procedure 34AB-P51-00l-2 starting at step 4.14.

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has lost all Service Air Compressors and they can not be restarted.
2. Electrical Maintenance and I&C are checking all air system electrical circuits.
3. The reactor has been scrammed and 34AB-C71-001-2, "Scram Procedure" is being carried out.
4. 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" has been partially completed.

INITIATING CUES:

Complete procedure 34AB-P51-001-2 starting at step 4.14.

Page 5 of9 PROMPT:

Provide the operator with 34AB-P51-001-2 completed up to section 4.13.

START TIME: ___ _

1. The operator starts at the correct step.

Operator refers to 34AB-P51-SAT/UNSAT 001-2 and starts at step 4.14.

2. Determine if Control Air header On paneI2H11-P650, Control Air SAT/UNSAT Pressure is below 45 PSIG AND NOT Pressure, 2P52-R600, the increasing.

operator observes pressure is less then 45 psig and not increasing.

NOTES:

  • If the operator attempts to first start the "A" SBGT, complete steps 3-9 and skip steps 10-16
  • If the operator attempts to first start the "B" SBGT, complete steps 10-16 and skip steps 3-9.
  • SBGT air operated valves FOO1/2/3 fail in the OPEN position.
3. OPEN 2T46-F003A, FItr Inlet from The operator places the keylock SAT/UNSAT/NA Refuel FIr.

switch for 2T46-F003A, FItr Inlet from Refuel FIr, to OPEN.

AND/OR Open 2T46-F001A, FItr Inlet from Rx The operator places the keylock SAT/UNSAT/NA Bldg.

switch for 2T46-F001A, FItr Inlet from Rx Bldg, to OPEN.

4. PLACE SBGT A in RUN position The operator places the control SAT/UNSAT switch for SBGT A to RUN.

NOTE: The operator should note that SBGT "A" does not start and continue with SBGT "B" start.

The operator places the keylock SAT / UNSAT / NA switch for 2T46-F003B, Fltr Inlet from Refuel FIr, to OPEN.

The operator places the keylock SAT / UNSAT / NA switch for 2T46-F001B, FItr Inlet from Rx to OPEN.

The operator places the control SAT / UNSAT switch for SBGT B in RUN.

7. CONFIRM 2T46-F002B OPENS.

The operator observes 2T46-SAT/UNSAT F002B red ILLUMINATED.

8. CONFIRM SBGT B HTR Red Light The operator observes SBGT B SAT/UNSAT ILLUMINATES HTR Red ILLUMINATED.

(** Indicates critical step)

(

PERFO~CESTEP STANDARD Page 5 of9 SATIUNSAT (COMMENTS PROMPT:

Provide the operator with 34AB-P51-001-2 completed up to section 4.13.

START TIME: ___ _

1. The operator starts at the correct step.

Operator refers to 34AB-P51-SAT/UNSAT 001-2 and starts at step 4.14.

2. Determine if Control Air header On paneI2H11-P650, Control Air SAT/UNSAT Pressure is below 45 PSIG AND NOT Pressure, 2P52-R600, the increasing.

operator observes pressure is less then 45 psig and not increasing.

NOTES:

  • If the operator attempts to first start the "A" SBGT, complete steps 3-9 and skip steps 10-16
  • If the operator attempts to first start the "B" SBGT, complete steps 10-16 and skip steps 3-9.
  • SBGT air operated valves FOO1l2/3 fail in the OPEN position.
3. OPEN 2T46-F003A, Fltr Inlet from The operator places the keylock SAT/UNSAT/NA Refuel FIr.

switch for 2T46-F003A, FItr Inlet from Refuel FIr, to OPEN.

AND/OR Open 2T46-F001A, FItr Inlet from Rx The operator places the keylock SAT/UNSAT/NA Bldg.

switch for 2T46-F001A, FItr Inlet from Rx Bldg, to OPEN.

4. PLACE SBGT A in RUN position The operator places the control SAT I UNSAT switch for SBGT A to RUN.

NOTE: The operator should note that SBGT "A" does not start and continue with SBGT "B" start.

    • 5. OPEN 2T46-F003B, FItr Inlet from The operator places the keylock SAT/UNSAT/NA Refuel FIr.

switch for 2T46-F003B, FItr Inlet from Refuel FIr, to OPEN.

I.

AND/OR Open 2T46-FOO1B, Fltr Inlet from Rx The operator places the keylock SAT/UNSAT/NA Bldg.

switch for 2T46-F001B, FItr Inlet from Rx Bldg, to OPEN.

    • 6. PLACE SBGT B in RUN position The operator places the control SAT I UNSAT switch for SBGT B in RUN.
7. CONFIRM 2T46-F002B OPENS.

The operator observes 2T46-SAT/UNSAT F002B red light ILLUMINATED.

8. CONFIRM SBGT B HTR Red Light The operator observes SBGT B SAT I UNSAT ILLUMINATES HTR Red Light ILLUMINATED.

(** Indicates critical step)

Page 6 of9

9. CONFIRM SBGT Flow increases to The operator observes SBGT SAT/UNSAT 1500-4000 SCFM.

flow between 1500-4000 scfm on 2U41-R600.

NOTES:

  • If the operator attempts to first start the "A" SBGT, complete steps 3-9 and skip steps 10-16
  • If the operator attempts to first start the "B" SBGT, complete steps 10-16 and skip steps 3-9.
  • SBGT air operated valves FOO1l213 fail in the OPEN position.
10. OPEN 2T46-F003B, Fltr Inlet from The operator places the keylock SAT/UNSAT/NA Refuel Flr.

switch for 2T46-F003B, Fltr Inlet from Refuel Flr, to OPEN.

AND/OR Open 2T46-FOOIB, Fltr Inlet from Rx The operator places the keylock SAT/UNSAT/NA Bldg.

switch for 2T46-FOOlB, Fltr Inlet from Rx Bldg, to OPEN.

11. PLACE SBGT B in RUN position The operator places the control SAT/UNSAT switch for SBGT B in RUN.

(

NOTE: The operator should note that SBGT "B" does not start and continue with SBGT "A" start.

The operator places the keylock SAT I UNSAT I NA switch for 2T46-F003A, Fltr Inlet from Refuel Flr, to OPEN.

The operator places the keylock SAT/UNSAT/NA switch for 2T46-FOOIA, Fltr Inlet fromRx to OPEN.

The operator places the control SAT/UNSAT switch for SBGT A to RUN.

14. CONFIRM 2T46-F002A OPENS.

The operator observes 2T46-SAT/UNSAT F002Ared LLUMINATED.

15. CONFIRM SBGT A HTR Red Light The operator observes SBGT A SAT/UNSAT lLLUMINA TES HTRRed lLLUMINA TED.
16. CONFIRM SBGT Flow increases to The operator observes SBGT SAT I UNSAT 1500-4000 SCFM.

flow between 1500-4000 scfm on 2T41-R618.

(** Indicates critical step)

(

PERFO~CESTEP

9. CONFIRM SBGT Flow increases to 1500-4000 SCFM.

NOTES:

STANDARD The operator observes SBGT flow between 1500-4000 sefm on 2U41-R600.

Page 6 of9 SATIUNSAT COMMENTS SAT I UNSAT

  • If the operator attempts to first start the "A" SBGT, complete steps 3-9 and skip steps 10-16
  • If the operator attempts to first start the "B" SBGT, complete steps 10-16 and skip steps 3-9.
  • SBGT air operated valves FOO1l2/3 fail in the OPEN position.
10. OPEN 2T46-F003B, Fltr Inlet from The operator places the keylock SAT/UNSAT/NA Refuel FIr.

switch for 2T46-F003B, Fltr Inlet from Refuel Flr, to OPEN.

AND/OR Open 2T46-FOOlB, Fltr Inlet from Rx The operator places the keylock SAT/UNSAT/NA Bldg.

switch for 2T46-FOOlB, Fltr Inlet from Rx Bldg, to OPEN.

11. PLACE SBGT B in RUN position The operator places the control SAT IUNSAT switch for SBGT B in RUN.

NOTE: The operator should note that SBGT "B" does not start and continue with SBGT "A" start.

    • 12. OPEN 2T46-F003A, FltrInlet from The operator places the key lock SAT/UNSAT/NA Refuel Flr.

switch for 2T46-F003A, Fltr Inlet AND/OR from Refuel Flr, to OPEN.

Open 2T46-FOOlA, Fltr Inlet from The operator places the keylock SAT/UNSAT/NA Rx Bldg.

switch for 2T46-F001A, Fltr Inlet from Rx Bldg, to OPEN.

    • 13. PLACE SBGT Ain RUN position The operator places the control SAT/UNSAT switch for SBGT A to RUN.
14. CONFIRM 2T46-F002A OPENS.

The operator observes 2T46-SAT/UNSAT F002A red light LLUMINATED.

15. CONFIRM SBGT A HTR Red Light The operator observes SBGT A SAT I UNSAT ILLUMINATES HTR Red Light ILLUMINATED.
16. CONFIRM SBGT Flow increases to The operator observes SBGT SAT I UNSAT 1500-4000 SCFM.

flow between 1500-4000 sefm on 2T41-R618.

(** Indicates critical step)

Page 7 of9 Note:The operator may not check the next step until after all are other steps of this JPM are complete.

17 Checks the Rx bldg and RF Floor On paneI2Hll-P700 the operator SAT/UNSAT Diff pressures are negative.

checks the RF Floor to Outside Air dp and the Rx Bldg to Outside Air dp on recorders 2T46-R604A and 2T46-R604B.

The dp will be approximately (negative) -0.25 inches.

NOTE: For the fans listed below, if a fan is NOT running and does NOT auto start, then the step is NOT critical. The step is to be marked SAT if, after the operator is done, the fan is NOT running (green light illuminated).

(** Indicates critical step)

On panel 2Hll-P654 the operator places control switch for 2U4l-COOlA, Turb Bldg Vent Supply Fan, to the OFF position, green illuminated.

On panel2Hll-P654 the operator places control switch for 2U4l-COOlB, Turb Bldg Vent Supply Fan, to the OFF position, green illuminated.

On panel2Hll-P654 the operator places control switch for 2U4l-C002A, Turb Bldg Vent Exhaust Fan, to the OFF position, green illuminated.

On panel2Hll-P654 the operator places control switch for 2U4l-C002B, Turb Bldg Vent Exhaust Fan, to the OFF position, green illuminated.

On panel2Hll-P657 the operator places control switch for 2T4l-COOlA, Rx Bldg Vent Supply Fan, to the OFF position, green illuminated.

On panel2Hll-P657 the operator places control switch for to the OFF position, green light illuminated.

SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT/UNSAT

(

PERFO~CESTEP STANDARD Page 7 of9 SATIUNSAT COMMENTS Note: The operator may not check the next step until after all are other steps of this JPM are complete.

17 Checks the Rx bldg and RF Floor On pane12H11-P700 the operator SAT/UNSAT Diff pressures are negative.

checks the RF Floor to Outside Air dp and the Rx Bldg to Outside Air dp on recorders 2T46-R604A and 2T46-R604B.

The dp will be approximately (negative) -0.25 inches.

NOTE: For the fans listed below, if a fan is NOT running and does NOT auto start, then the step is NOT critical. The step is to be marked SAT if, after the operator is done, the fan is NOT running (green light illuminated).

    • 18. TRIP 2U41-C001A, Turb Bldg Vent On pane12H11-P654 the operator SAT I UNSAT Supply Fan places control switch for 2U41-COOlA, Turb Bldg Vent Supply Fan, to the OFF position, green light illuminated.
    • 19. TRIP 2U41-C001B, Turb Bldg Vent On panel 2H 11-P654 the operator SAT I UNSAT Supply Fan places control switch for 2U41-COOlB, Turb Bldg Vent Supply Fan, to the OFF position, green light illuminated.
    • 20. TRIP 2U41-C002A, Turb Bldg Vent On pane12H11-P654 the operator SAT I UNSAT Exhaust Fan places control switch for 2U41-C002A, Turb Bldg Vent Exhaust Fan, to the OFF position, green light illuminated.
    • 21. TRIP 2U41-C002B, Turb Bldg Vent On pane12H11-P654 the operator SAT I UNSAT Exhaust Fan places control switch for 2U41-C002B, Turb Bldg Vent Exhaust Fan, to the OFF position, green light illuminated.
    • 22. TRIP 2T41-C001A, Rx Bldg Vent On pane12H11-P657 the operator SAT I UNSAT

.. Supply Pan places control switch for 2T41-COOlA, Rx Bldg Vent Supply Fan, to the OFF position, green light illuminated.

    • 23. TRIP 2T41-COOlB, Rx Bldg Vent On pane12H11-P657 the operator SAT/UNSAT Supply Fan places control switch for to the OFF position, green light illuminated.

(** Indicates critical step)

(** Indicates critical step)

On pane12HII-P657 the operator

places control switch for 2T41-COOIB, Rx Bldg Vent Supply
  • Fan, to the OFF position, green Ii ht illuminated.

On panel 2HII-P657 the operator places control switch for 2T4l-C007B, Rx Bldg Vent Exhaust Fan, to the OFF position, green light illuminated.

.. On pane12HII-P657 the operator places control switch for 2T4l-BO 17 Fan 1, Rx Bldg Recirc Fan, to the OFF position, green light illuminated.

On panel 2HII-P657 the operator places control switch for 2T4l-B017 Fan 2, Rx Bldg Recirc Fan,

  • to the OFF position, green light illuminated.

On panel 2HII-P657 the operator places control switch for 2T4l-C002A, Refuel FIr Vent Supply Fan, to the OFF position, green light illuminated.

On pane12HII-P657 the operator places control switch for 2T4l-C002B, Refuel FIr Vent Supply Fan, to the OFF position, green light illuminated.

On pane12HII-P657 the operator places control switch for 2T4l-C005A, Refuel FIr Vent Exh Fan, to the OFF position, green light illuminated.

On pane12HII-P657 the operator places control switch for 2T4l-C005B, Refuel FIr Vent Exh Fan, to the OFF position, green light

  • illuminated.

Page 8 of9 SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PERFO~CESTEP

(

.. Exhaust Fan.

.~-... --

(** Indicates critical step)

STANDARD On pane12HII-P657 the operator places control switch for 2T41-COOIB, Rx Bldg Vent Supply Fan, to the OFF position, green light illuminated.

On pane12HII-P657 the operator places control switch for 2T41-C007B, Rx Bldg Vent Exhaust Fan, to the OFF position, green light illuminated.

On pane12HII-P657 the operator places control switch for 2T41-B017 Fan 1, Rx Bldg Recirc Fan, to the OFF position, green light illuminated.

On pane12H11-P657 the operator places control switch for 2T41-B017 Fan 2, Rx Bldg Recirc Fan, to the OFF position, green light illuminated.

On pane12HII-P657 the operator places control switch for 2T41-C002A, Refuel FIr Vent Supply Fan, to the OFF position, green light illuminated.

On pane12H11-P657 the operator places control switch for 2T41-C002B, Refuel FIr Vent Supply Fan, to the OFF position, green light illuminated.

On pane12H11-P657 the operator places control switch for 2T41-C005A, Refuel FIr Vent Exh Fan, to the OFF position, green light illuminated.

On pane12H11-P657 the operator places control switch for 2T41-C005B, Refuel FIr Vent Exh Fan, to the OFF position, green light illuminated.

Page 8 of9 SATIUNSAT COMMENTS SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT

(

32. Confirm OPEN/OPEN 2N21-F014, Condensate Demineralizer Bypass Valve.
          • STANDA@*

The operator sends an SO to confirm OPEN/OPEN 2N21-FO 14, Condensate Demineralizer Bypass Valve, at panel 2N21-POOL Page 9 of9 SAa'f(.JNSAl' COMMENTS SAT/UNSAT PROMPT:

WHEN the operator sends an SO to confirm the valve is open, INFORM the operator that another operator will complete the remainder of 34AB-P51-001-2.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator is prompted that another operator will complete 34AB-P51-001-2.

Operator states the task is complete.

(** Indicates critical step)

END TIME:. ___ _

(

(

PERFORMANCE STEP

32. Confirm OPEN/OPEN 2N21-F0l4, Condensate Demineralizer Bypass Valve.

STANDARD The operator sends an SO to confirm OPEN/OPEN 2N21-F014, Condensate Demineralizer Bypass Valve, at panel2N21-POOL Page 9 of9 SATIUNSAT COMMENTS SAT/UNSAT PROMPT:

WHEN the operator sends an SO to confirm the valve is open, INFORM the operator that another operator will complete the remainder of 34AB-P51-00l-2.

NOTE:

The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator is prompted that another operator will complete 34AB-P51-00l-2.

Operator states the task is complete.

(** Indicates critical step)

END TIME: ___ _

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has lost all Service Air Compressors and they can not be restarted.
2. Electrical Maintenance and I&C are checking all air system electrical circuits.
3. The reactor has been scrammed and 34AB-C71-001-2, "Scram Procedure" is being carried out.
4. 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" has been partially completed.

INITIATING CUES:

Complete procedure 34AB-P51-001-2 starting at step 4.14.

(

(

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has lost all Service Air Compressors and they can not be restarted.
2. Electrical Maintenance and I&C are checking all air system electrical circuits.
3. The reactor has been scrammed and 34AB-C71-001-2, "Scram Procedure" is being carried out.
4. 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" has been partially completed.

INITIATING CUES:

Complete procedure 34AB-P51-001-2 starting at step 4.14.

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 3 OF 14 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

LOSS OF INSTRUMENT AND SERVICE AIR SYSTEM OR WATER INTRUSION INTO THE SERVICE AIR SYSTEM 4.0 SUBSEQUENT OPERATOR ACTIONS 34AB-P51-001-2 4.5

-e-Attempt to restart Air Compressors per 34S0-P51-002-2, Instrument And Service Air Systems.

IF Air Compressors are running, dispatch personnel to determine cause of low pressure.

(broken lines, air spargers, other high use systems).

-e-At the SS direction and with concurrence of the Unit One Shift Supervisor, crosstie Unit Two AND Unit One Service Air Systems per 34S0-P51-002-2, Instrument And Service Air Systems.

,@r IF SSAC CCW is lost, perform the following:

-e-

~

Attempt to restore SSAC CCW AND restart Air Compressors per 34S0-P51-002-2, Instrument And Service Air Systems.

Initiate actions to place 2P51-C001A and 2P51-C001 B on alternate cooling water IF necessary AND restart Air Compressors per 34S0-P51-002-2, Instrument And Service Air Systems.

~

Enter 34AB-C71-001-2, Scram Procedure, AND SCRAM the reactor IF any of the following conditions occur:

~

SCRAM VLV PILOT AIR HDR PRESS HIGH/LOW (603-131) COINCIDENT with CRD HYD TEMP HIGH (603-140).

Scram pilot valve air header pressure less than or equal to 50 PSIG as indicated locally on 2C11-R013.

NOTE A fire in the isolated areas may necessitate de-isolating the sprinkler systems to that area.

~

Isolate the Fire Protection Sprinklers listed on Attachment 1 IF NO

~

fire exists in their protection areas.

-- IF there is an indication of mispositioned OR drifting control rod(s),

refer to 34AB-C11-004-2, Mispositioned Control Rods.

~

IF unable to restore system air pressure, TRANSFER operation of Refueling Floor Fuel Pool Seals to nitrogen bottle pressure supply per 34S0-P51-002-2, Instrument And Service Air Systems.

~

Manually initiate any automatic actions which did NOT occur.

-e-Confirm CLOSED/CLOSE 2N21-F125, StU Level Control Isol valve, on panel 2H 11-P650.

MGR-0001 Ver. 3

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 3 OF 14 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

LOSS OF INSTRUMENT AND SERVICE AIR SYSTEM OR WATER INTRUSION INTO THE SERVICE AIR SYSTEM 4.0 SUBSEQUENT OPERATOR ACTIONS 34AB-P51-001-2 4.5

-e-Attempt to restart Air Compressors per 34S0-P51-002-2, Instrument And Service Air Systems.

IF Air Compressors are running, dispatch personnel to determine cause of low pressure.

(broken lines, air spargers, other high use systems).

-e-At the SS direction and with concurrence of the Unit One Shift Supervisor, crosstie Unit Two AND Unit One Service Air Systems per 34S0-P51-002-2, Instrument And Service Air Systems.

,@r IF SSAC CCW is lost, perform the following:

-er

~

Attempt to restore SSAC CCW AND restart Air Compressors per 34S0-P51-002-2, Instrument And Service Air Systems.

Initiate actions to place 2P51-C001A and 2P51-C001B on alternate cooling water IF necessary AND restart Air Compressors per 34S0-P51-002-2, Instrument And Service Air Systems.

-e-Enter 34AB-C71-001-2, Scram Procedure, AND SCRAM the reactor IF any of the following conditions occur:

~

SCRAM VLV PILOT AIR HDR PRESS HIGH/LOW (603-131) COINCIDENT with CRD HYD TEMP HIGH (603-140).

Scram pilot valve air header pressure less than or equal to 50 PSIG as indicated locally on 2C11-R013.

NOTE A fire in the isolated areas may necessitate de-isolating the sprinkler systems to that area.

~

Isolate the Fire Protection Sprinklers listed on Attachment 1 IF NO

~

fire exists in their protection areas.

-- IF there is an indication of mispositioned OR drifting control rod(s),

refer to 34AB-C11-004-2, Mispositioned Control Rods.

~

IF unable to restore system air pressure, TRANSFER operation of Refueling Floor Fuel Pool Seals to nitrogen bottle pressure supply per 34S0-P51-002-2, Instrument And Service Air Systems.

~

Manually initiate any automatic actions which did NOT occur.

-- Confirm CLOSED/CLOSE 2N21-F125, StU Level Controllsol valve, on paneI2H11-P650.

MGR-0001 Ver. 3

(

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 40F 14 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

LOSS OF INSTRUMENT AND SERVICE AIR SYSTEM OR WATER INTRUSION INTO THE SERVICE AIR SYSTEM 34AB-P51-001-2 4.5 tt.:!:1.- Maintain Reactor water level between 15 and 45 inches utilizing 2N21-F11 0, Stu Level Control

~

Bypass, AND/OR varying RFPT speed.

-e-Confirm CLOSED/CLOSE 2P51-F017, Service Air Isolation valve, on paneI2H11-P650, AND notify Health Physics.

~

Confirm CLOSED/CLOSE 2P52-F015, Turb Bldg Inst Air After Fltrs, D102A1B, to RW Bldg Isol valve, on paneI2H11-P700.

4.14 IF Control Air header Pressure is below 45 PSIG AND NOT increasing, THEN perform the following:

4.14.1 START one train of 2T46-D001A or B, SBGT, with suction from the Reactor Building AND Refuel Floor.

4.14.2 TRI P the following equipment:

2U41-C001A, B, Turb Bldg Vent Supply Fans 2U41-C002A, B, Turb Bldg Vent Exhaust Fans 2T41-C001 A, B, Rx Bldg Vent Supply Fans 2T41-C007A, B, Rx Bldg Vent Exhaust Fans 2T41-B017 Fans 1 and 2, Rx Bldg Recirc Fans 2T 41-C002A, B, Refuel Fir Vent Supply Fans 2T41-C005A, B, Refuel Fir Vent Exh Fans 4.14.3 Send Operator to confirm OPEN/OPEN 2N21-F014, Condensate Demineralizer Bypass Valve, at panel 2N21-P001.

4.14.4 Confirm OPEN/OPEN 2T48-F026, CAD B Nitrogen Makeup Outbd Isol valve, on pane12H11-P654 4.14.5 Confirm OPEN/OPEN 2T48-F027, CAD A Nitrogen Makeup Inbdlsol valve, on paneI2H11-P657.

MGR-0001 Ver. 3

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 4 OF 14 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

LOSS OF INSTRUMENT AND SERVICE AIR SYSTEM OR WATER INTRUSION INTO THE SERVICE AIR SYSTEM 34AB-P51-001-2 4.5 tt::Jj.- Maintain Reactor water level between 15 and 45 inches utilizing 2N21-F11 0, S/U Level Control

~

Bypass, AND/OR varying RFPT speed.

-e-Confirm CLOSED/CLOSE 2P51-F017, Service Air Isolation valve, on paneI2H11-P650, AND notify Health Physics.

-e-Confirm CLOSED/CLOSE 2P52-F015, Turb Bldg Inst Air After Fltrs, D102A1B, to RW Bldg Isol valve, on panel 2H11-P700.

4.14 IF Control Air header Pressure is below 45 PSIG AND NOT increasing, THEN perform the following:

4.14.1 START one train of 2T 46-0001 A or B, SBGT, with suction from the Reactor Building AND Refuel Floor.

4.14.2 TRIP the following equipment:

2U41-C001 A, B, Turb Bldg Vent Supply Fans 2U41-C002A, B, Turb Bldg Vent Exhaust Fans 2T41-C001A, B, Rx Bldg Vent Supply Fans 2T41-C007A, B, Rx Bldg Vent Exhaust Fans 2T41-B017 Fans 1 and 2, Rx Bldg Recirc Fans 2T41-C002A, B, Refuel Fir Vent Supply Fans 2T41-C005A, B, Refuel Fir Vent Exh Fans 4.14.3 Send Operator to confirm OPEN/OPEN 2N21-F014, Condensate Demineralizer Bypass Valve, at panel 2N21-P001.

4.14.4 Confirm OPEN/OPEN 2T 48-F026, CAD B Nitrogen Makeup Outbd Isol valve, on pane12H11-P654 4.14.5 Confirm OPEN/OPEN 2T48-F027, CAD A Nitrogen Makeup Inbd Isol valve, on paneI2H11-P657.

MGR-0001 Ver. 3

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 50F 14 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

LOSS OF INSTRUMENT AND St::RVICE AIR SYSTEM OR WATER INTRUSION INTO THE SERVICE AIR SYSTEM 34AB-P51-001-2 4.5 ALLOWING 2P52-F565 TO CONTINUOUSLY CYCLE FULL OPEN TO FULL CLOSED CAUTION COULD CAUSE EXCESSIVE DUTY ON THE VALVE MOTOR AND MAY CAUSE THE EVENTUAL FAILURE OF THE MOTOR.

4.14.6 Confirm OPEN/OPEN 2P52-F565, Rx Bldg Inst N2 To Non-Int Air EI185 Isol VI v, on paneI2H11-P700.

4.14.6.1 IF 2P52-F565 is continuously cycling, THEN OPEN 2P52-F565 AND turn OFF the supply breaker (MCC 2R24-S011, FR 22E, 130RB) to the valve.

4.15 IF a leak isconfirmed, ISOLATE the header by closing the main header valve OR individual branches as conditions dictate.

4.16 Confirm running OR START the Service Air Compressor(s) as necessary and proceed to step 4.18.

4.17 IF any of the Air Compressors do NOT start, attempt to restore Instrument and Service Air pressure as follows:

4.17.1 RESTORE power to the following circuits as necessary:

4.17.1.1 2R23-S003, Frame 5B, Air Compressor 2A 2P51-C001A 4.17.1.2 2R23-S004, Frame 6B, Air Compressor 2B 2P51-C001 B 4.17.1.3 2R23-S001, Frame 1AB, Air Compressor 2C 2P51-C001C 4.17.1.4 2R25-S001, Brkr 29, 600V Bus 2C Fdr BRKR CNTL Power for 2P51-C001A 4.17.1.5 2R25-S00?, Brkr 19, 600V Bus 2D Fdr BRKR Control Power for 2P51-C001 B 4.17.1.6 2R25-S003, Brkr 15, 600V Bus 2A Fdr BRKR Control Power for 2P51-C001 C 4.17.1.7 2R24-S011, Brkr 1C, Power: Supply for 2H21-P513, 2P51-C005A, 2H21-P519 and 2P51-B002 Fans 1A, 2A, 3A, & 4A.

4.17.1.8 2R24-S012, Brkr 15C, PowerSupplyfor2H21-P514, 2P51-C005B, 2H21-P520 and 2P51-B002 Fans 1B, 2B, 3B, & 4B.

4.17.1.9 2R25-S036, Brkr 5, 120 VAC Feed to sol. vlvs 2P51-F01 OA, B, C 4.17.2 START the Service Air Compressor(s) as necessary.

MGR-0001 Ver. 3

~

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 5 OF 14 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

LOSS OF INSTRUMENT AND SERVICE AIR SYSTEM OR WATER INTRUSION INTO THE SERVICE AIR SYSTEM 34AB-P51-001-2 4.5 ALLOWING 2P52-F565 TO CONTINUOUSLY CYCLE FULL OPEN TO FULL CLOSED CAUTION COULD CAUSE EXCESSIVE DUTY ON THE VALVE MOTOR AND MAY CAUSE THE EVENTUAL FAILURE OF THE MOTOR.

4.14.6 Confirm OPEN/OPEN 2P52-F565, Rx Bldg Inst N2 To Non-Int Air EI1851soi Vlv, on paneI2H11-P700.

4.14.6.1 IF 2P52-F565 is continuously cycling, THEN OPEN 2P52-F565 AND turn OFF the supply breaker (MCC 2R24-S011, FR 22E, 130RB) to the valve.

4.15 IF a leak isconfirmed, ISOLATE the header by closing the main header valve OR individual branches as conditions dictate.

4.16 Confirm running OR START the Service Air Compressor(s) as necessary and proceed to step 4.18.

4.17 IF any of the Air Compressors do NOT start, attempt to restore Instrument and Service Air pressure as follows:

4.17.1 4.17.1.1 4.17.1.2 4.17.1.3 4.17.1.4 4.17.1.5 4.17.1.6 4.17.1.7 4.17.1.8 4.17.1.9 4.17.2 RESTORE power to the following circuits as necessary:

2R23-S003, Frame 5B, Air Compressor 2A 2P51-C001A 2R23-S004, Frame 6B, Air Compressor 2B 2P51-C001 B 2R23-S001, Frame 1 AB, Air Compressor 2C 2P51-C001 C 2R25-S001, Brkr 29, 600V Bus 2C Fdr BRKR CNTL Power for 2P51-C001A 2R25-S002, Brkr 19, 600V Bus 2D Fdr BRKR Control Power for 2P51-C001 B 2R25-S003, Brkr 15, 600V Bus 2A Fdr BRKR Control Power for 2P51-C001C 2R24-S011, Brkr 1 C, Power Supply for 2H21-P513, 2P51-C005A, 2H21-P519 and 2P51-B002 Fans 1A, 2A, 3A, & 4A.

2R24-S012, Brkr 15C, Power Supply for 2H21-P514, 2P51-C005B, 2H21-P520 and 2P51-B002 Fans 1 B, 2B, 3B, & 4B.

2R25-S036, Brkr 5,120 VAC Feed to sol. vlvs 2P51-F010A, B, C START the Service Air Compressor(s) as necessary.

MGR-0001 Ver. 3

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 6 OF 14 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

LOSS OF INSTRUMENT AND SERVICE AIR SYSTEM OR WATER INTRUSION INTO THE SERVICE AIR SYSTEM 34AB-P51-001-2 4.5 4.18 IF CONTROL BLDG SERVICE AIR SHUTOFF (700-234) Annunciator is ALARMING, determine AND correct the problem with the Service Air Header THEN REOPEN 2P51-F017 from paneI2H11-P650.

4.19 IF INSTR AIR DRYER MALFUNCTION (700-205) Annunciator is alarming, go to 2P52-D1 01 and observe local alarms AND attempt to restore per the Annunciator Response Procedure.

4.19.1 Attempt to reset alarms by depressing the reset pushbutton.

4.20 WHEN Non-Interruptible Air Header pressures return to normal, confirm CLOSED/CLOSE 2P52-F565, Rx Bldg Inst N2 To Non-Int Air EL 185 Isol Vlv.

4.21 Notify Plant Management and System Load Dispatcher.

4.22 WHEN air system is restored to normal operation, return affected systems to service per the applicable System Operating Procedures.

MGR-0001 Ver. 3

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 6 OF 14 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

LOSS OF INSTRUMENT AND SERVICE AIR SYSTEM OR WATER INTRUSION INTO THE SERVICE AIR SYSTEM 34AB-P51-001-2 4.5 4.18 IF CONTROL BLDG SERVICE AIR SHUTOFF (700-234) Annunciator is ALARMING, determine AND correct the problem with the Service Air Header THEN REOPEN 2P51-F017 from paneI2H11-P650.

4.19 IF INSTR AIR DRYER MALFUNCTION (700-205) Annunciator is alarming, go to 2P52-D101 and observe local alarms AND attempt to restore per the Annunciator Response Procedure.

4.19.1 Attempt to reset alarms by depressing the reset pushbutton.

4.20 WHEN Non-Interruptible Air Header pressures return to normal, confirm CLOSED/CLOSE 2P52-F565, Rx Bldg Inst N2 To Non-Int Air EL 185 Isol Vlv.

4.21 Notify Plant Management and System Load Dispatcher.

4.22 WHEN air system is restored to normal operation, return affected systems to service per the applicable System Operating Procedures.

MGR-0001 Ver. 3

(

NR FI Southern E. I. Hatch AL uclear uclear Plant Operations Training JPM 1 1M C.M.EDMUND 10/09/2009 Energy to Serve Your World SM

(

TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM PLANT I-ALL VENT THE SCRAM AIR HEADER AUTHOR MEDIA NUMBER F. Fagan 2009-302 Plant 1 RECOMMENDED BY APPROVED BY NR C.M.EDMUND TIME 10 Minutes DATE 10109/2009 Energy to Serve Your World sM

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:

OPERATIONS TRAINING 10-15-09 Modified for NRC exam 2009-302 Page 1 of 1 Media Number:

2009-302 Plant 1 FNF CME

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:

OPERATIONS TRAINING Rev. No.

Date Reason for Revision 10-15-09 Modified for NRC exam 2009-302 Page 1 of 1 Media Number:

2009-302 Plant 1 Author's Supv's Initials Initials FNF CME

(

2009-302 Plant 1 Page 1 of3 UNIT 1 (X)

UNIT 2 0

VENT THE SCRAM AIR HEADER LR-JP-I0.15-14 The task shall be completed when the operator has successfully vented the scram air header per 31EO-EOP-103.

010.015 010.015.0 PLANT HATCH JTA IMPORTANCE RATING:

RO 4.50 SRO 3.65 KIA CATALOG NUMBER: 295015K2.11

(

KIA CATALOG JTA IMPORTANCE RATING:

RO 3.5 SRO 3.7 OPERATOR APPLICABILITY:

RO 31EO-EOP-103-(current revision)

APPROXIMATE COMPLETION TIME:

10 Minutes SIMULATOR SETUP:

N/A TASK TITLE:

JPMNUMBER:

TASK STANDARD:

TASK NUMBER:

2009-302 Plant I Page I of 3 UNIT 1 (X)

UNIT 2 0

VENT THE SCRAM AIR HEADER LR-JP-1O.15-14 The task shall be completed when the operator has successfully vented the scram air header per 3IEO-EOP-103.

010.015 OBJECTIVE NUMBER: 010.015.0 PLANT HATCH JTA IMPORTANCE RATING:

RO 4.50 SRO 3.65 KIA CATALOG NUMBER: 295015K2.11

(

KIA CATALOG JTA IMPORTANCE RATING:

(

RO 3.5 SRO 3.7 OPERATOR APPLICABILITY:

RO I GENERAL

REFERENCES:

Unit 1 31EO-EOP-103-1 (current version) 31EO-EOP-Oll-I (current version)

I REQUIRED MATERIALS:

Unit 1 3IEO-EOP-103-1 (current revision)

APPROXIMATE COMPLETION TIME:

10 Minutes SIMULATOR SETUP:

N/A

UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

A Reactor scram signal has been received and all the control rods did not insert to Position 02 and Reactor power is greater than 10%.

2.

ATWS with 31EO-EOP-103-1 being performed

3.

ARI initiated and has been reset

4.

OATC is driving rod per section, per 31EO-EOP-103-1 section 3.7 and 3.8.

5.

OATC reports panellHll-P603 indications are:

  • White RPS Scram Group Lights - NOT illuminated
  • Blue Scram Lights - NOT illuminated INITIATING CUES:

lAW 31EO-EOP-103-1, Section 3.0, determine and perform actions to insert control rods.

(

(

UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

A Reactor scram signal has been received and all the control rods did not insert to Position 02 and Reactor power is greater than 10%.

2.

ATWS with 3IEO-EOP-103-1 being performed

3.

ARI initiated and has been reset

4.

OATC is driving rod per section, per 31EO-EOP-103-1 section 3.7 and 3.8.

5.

OATC reports panellHll-P603 indications are:

  • White RPS Scram Group Lights - NOT illuminated
  • Blue Scram Lights - NOT illuminated INITIATING CUES:

lAW 31EO-EOP-103-1, Section 3.0, determine and perform actions to insert control rods.

(

PERFOR.MANCESl'EP

1. Obtain the procedure.

Operator obtains 3IEO-EOP-103-I and refers to Section 3.0.

Operator determines that "Vent Scram Air Header" will insert rods and refers to section 3.6 2009-302 Plant I Page 3 of 3

..' Sl\\TIUNSA'r (COMMENTS,**,

START TIME: ___ _

SAT/UNSAT SAT/UNSAT PROMPT: IF the operator picks an incorrect section, THEN inform the operator that the section is unsuccessful in inserting rods.

At location l30RAR03, ICII-F095, SCRAM AIR HEADER ISOLATION V ALVE is turned in the clockwise direction until CLOSED.

SAT/UNSAT PROMPT: When the Operator closes ICII-F095 valve, the handwheel will be turned in the clockwise direction until it will not turn any farther.

l{~iliov;etapjf.jnst~le(l.frbln'end"*()f pipjng;clowustrealllo,f

'lGII-R013-TVl.

5. Open or verify open ICll-ROl3-NI.
7. Verify decreasing air pressure.

At location l30RAR03, cap is REMOVED from end of piping downstream of ICII-ROI3-TVI.

At location l30RAR03, ICII-ROl3-NI, Pressure Instrumentation Isolation Valve is open.

At location l30RAR03, ICII-ROI3-TVI, PRESSURE INSTRUMENTATION VENT VALVE, is OPEN.

At location 130RAR03, Scram Air Header pressure is verified decreasing on ICll-PI-ROl3.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time or the Operator states the task is complete TERMINATING CUE: We will stop here.

SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT END TIME: ___ _

(

(

PERFORMANCE STEP

1. Obtain the procedure.
    • 2. Determine correct flowchart action.

STANDARD Operator obtains 3IEO-EOP-103-I and refers to Section 3.0.

Operator determines that "Vent Scram Air Header" will insert rods and refers to section 3.6 2009-302 Plant I Page 3 of3 SATIVNSAT (COMMENTS)

START TIME: ___ _

SAT/UNSAT SAT/UNSAT PROMPT: IF the operator picks an incorrect section, THEN inform the operator that the section is unsuccessful in inserting rods.

    • 3. Close I CII-F095.

At location 130RAR03, ICII-SAT/UNSAT F095, SCRAM AIR HEADER ISOLATION VALVE is turned in the clockwise direction until CLOSED.

PROMPT: When the Operator closes ICII-F095 valve, the handwheel will be turned in the clockwise direction until it will not turn any farther.

    • 4.
5.
    • 6.
7.

Remove cap if installed from end of At location 130RAR03, cap is piping downstream of REMOVED from end of piping ICII-R013-TVl.

downstream of ICII-R013-TVl.

Open or verify open ICII-R013-Nl.

At location 130RAR03, ICII-R013-NI, Pressure Instrumentation Isolation Valve is open.

Open ICII-R013-TVl.

At location 130RAR03, ICII-ROI3-TVI, PRESSURE INSTRUMENTA TION VENT VALVE, is OPEN.

Verify decreasing air pressure.

At location 130RAR03, Scram Air Header pressure is verified decreasing on ICII-PI-R013.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time or the Operator states the task is complete TERMINATING CUE: We will stop here.

SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT END TIME: ___ _

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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

A Reactor scram signal has been received and all the control rods did not insert to Position 02 and Reactor power is greater than 10%.

2.

ATWS with 31EO-EOP-I03-1 being performed

3.

ARI initiated and has been reset

4.

OATC is driving rod per section, per 31EO-EOP-I03-1 section 3.7 and 3.8.

5.

OATC reports panellHll-P603 indications are:

  • White RPS Scram Group Lights - NOT illuminated
  • Blue Scram Lights - NOT illuminated INITIATING CUES:

lAW 31EO-EOP-I03-1, Section 3.0, determine and perform actions to insert control rods.

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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

A Reactor scram signal has been received and all the control rods did not insert to Position 02 and Reactor power is greater than 10%.

2.

ATWS with 31EO-EOP-I03-1 being performed

3.

ARI initiated and has been reset

4.

OATC is driving rod per section, per 31EO-EOP-I03-1 section 3.7 and 3.8.

5.

OATC reports panellHll-P603 indications are:

  • White RPS Scram Group Lights - NOT illuminated
  • Blue Scram Lights - NOT illuminated INITIATING CUES:

IAW 31EO-EOP-I03-1, Section 3.0, determine and perform actions to insert control rods.

SOUTHERN NUCLEAR DOCUMENT TYPE:

PAGE 1 OF 22 PLANT E. I. HATCH EMERGENCY OPERATING PROCEDURE DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 EXPIRATION APPROVALS:

EFFECTIVE DATE:

DEPARTMENT MANAGER G. R. Brinson DATE 10-15-09 DATE:

N/A SSM/PM W. L. Bargeron DATE 10-15-09 10-16-09 1.0 OBJECTIVE This procedure provides alternate methods of inserting control rods I F they fail to insert automatically upon receipt of a scram signal.

2.0 ENTRY CONDITIONS This procedure is to be performed as directed by 31 EO-EOP-011-1, RCA RPV Control (ATWS).

TABLE OF CONTENTS Section 3.0 OPERATOR ACTIONS........................................................................................................ 2 3.1 ARI MANUAL INITIATION............................................................................................. 3 3.2 RESETTING ARI........................................................................................................... 4 3.3 REPEATING MANUAL SCRAM..................................................................................... 5 3.4 DE-ENERGIZING SCRAM SOLENOIDS....................................................................... 7 3.5 INDIVIDUALLY SCRAMMING RODS............................................................................ 8 3.6 VENTING SCRAM AIR HEADER................................................................................ 10 3.7 DRIVING CONTROL RODS........................................................................................ 11 3.8 INCREASING CRD COOLING WATER DP................................................................. 12 3.9 VENTING CRD WITHDRAW PORT............................................................................. 13

4.0 REFERENCES

.................................................................................................................. 14 Attachments 1

SYSTEM RESTORATION................................................................................................. 15 2

THAXTON PIPE STOPPER DIAGRAM............................................................................. 22 MGR-0002 Ver. 8.1 I (

SOUTHERN NUCLEAR DOCUMENT TYPE:

PAGE 1 OF 22 PLANT E. I. HATCH EMERGENCY OPERATING PROCEDURE DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 5.0 EXPIRATION APPROVALS:

EFFECTIVE DATE:

DEPARTMENT MANAGER G. R. Brinson DATE 10-15-09 DATE:

N/A SSM / PM W. L. Bargeron DATE 10-15-09 10-16-09 1.0 OBJECTIVE This procedure provides alternate methods of inserting control rods IF they fail to insert automatically upon receipt of a scram signal.

2.0 ENTRY CONDITIONS This procedure is to be performed as directed by 31 EO-EOP-011-1, RCA RPV Control (ATWS).

TABLE OF CONTENTS Section 3.0 OPERATOR ACTIONS........................................................................................................ 2 3.1 ARI MANUAL INITIATION............................................................................................. 3 3.2 RESETTING ARI........................................................................................................... 4 3.3 REPEATING MANUAL SCRAM..................................................................................... 5 3.4 DE-ENERGIZING SCRAM SOLENOIDS....................................................................... 7 3.5 INDIVIDUALLY SCRAMMING RODS............................................................................ 8 3.6 VENTING SCRAM AIR HEADER................................................................................ 10 3.7 DRIVING CONTROL RODS........................................................................................ 11 3.8 INCREASING CRD COOLING WATER DP................................................................. 12 3.9 VENTING CRD WITHDRAW PORT............................................................................. 13

4.0 REFERENCES

.................................................................................................................. 14 Attachments 1

SYSTEM RESTORATION................................................................................................. 15 2

THAXTON PIPE STOPPER DIAGRAM............................................................................. 22 MGR-0002 Ver. 8.1

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SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

CONTROL ROD INSERTION METHODS 3.0 OPERATOR ACTIONS YES De-energize Scram solenoids per subsection 3.4 MGR-0001 Rev 3 NO WAIT UNTIL ARI inward rod motion has ceased G16.30 DOCUMENT NUMBER:

31 EO-EOP-1 03-1 PAGE 2 OF 22 VERSION NO:

5.0 Increase CRD Cooling Water LI. p per subsection 3.8 WAIT UNTIL All other rod insertion methods have failed Vent CRD Withdraw port per subsection 3.9

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SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

CONTROL ROD INSERTION METHODS 3.0 OPERATOR ACTIONS YES De-energize Scram solenoids per subsection 3.4 MGR-0001 Rev 3 NO WAIT UNTIL ARI inward rod motion has ceased G16.30 DOCUMENT NUMBER:

31 EO-EOP-1 03-1 PAGE 2 OF 22 VERSION NO:

5.0 Increase CRD Cooling Water A p per subsection 3.8 WAIT UNTIL All other rod insertion methods have failed Vent CRD Withdraw port per subsection 3.9

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 3 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 NOTE:

3.0.1 3.0.2 3.0.3 3.004 3.1 3.1.1 3.1.2 3.1.3 Subsections 3.3 through 3.9 of this procedure each describe a different method of inserting control rods. The Shift Supervisor or the plant operator will determine which sections will be most effective and which may be performed concurrently based on current plant conditions. Not all subsections need to be performed, and some subsections may be performed more than once IF desired. Section 3.0 may be referred to for guidance.

IF BLUE Scram Inlet and Outlet Valve lights are ILLUMINATED, THEN perform subsection 3.3.

IF WHITE RPS Scram Group A (B) lights are ILLUMINATED, THEN Perform subsection 304.

IF BLUE Scram Inlet and Outlet Valve lights are EXTINGUISHED, THEN perform subsection 3.6.

IF all other rod insertion methods have failed, THEN perform subsection 3.9.

ARI MANUAL INITIATION Arm both ARI Manual Initiation Ch A and Ch B pushbuttons by rotating the pushbutton collar to the ARMED position at panel 1 H11-P603.

Depress both ARI Manual Initiation Ch A and Ch B pushbuttons.

Check that the ARIINITIATED (603-304) annunciator has ALARMED.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 3 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 NOTE:

3.0.1 3.0.2 3.0.3 3.0.4 3.1 3.1.1 3.1.2 3.1.3 Subsections 3.3 through 3.9 of this procedure each describe a different method of inserting control rods. The Shift Supervisor or the plant operator will determine which sections will be most effective and which may be performed concurrently based on current plant conditions. Not all subsections need to be performed, and some subsections may be performed more than once IF desired. Section 3.0 may be referred to for guidance.

IF BLUE Scram Inlet and Outlet Valve lights are ILLUMINATED, THEN perform subsection 3.3.

IF WHITE RPS Scram Group A (B) lights are ILLUMINATED, THEN Perform subsection 3.4.

IF BLUE Scram Inlet and Outlet Valve lights are EXTINGUISHED, THEN perform subsection 3.6.

IE all other rod insertion methods have failed, THEN perform subsection 3.9.

ARI MANUAL INITIATION Arm both ARI Manual Initiation Ch A and Ch B pushbuttons by rotating the pushbutton collar to the ARMED position at panel 1 H11-P603.

Depress both ARI Manual Initiation Ch A and Ch B push buttons.

Check that the ARI INITIATED (603-304) annunciator has ALARMED.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE40F22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.2 RESETTING ARI 3.2.1 IF ARI initiation signals have cleared, THEN depress ARI Reset pushbutton on panel 1 H11-P603.

AND Check that the annunciator ARI INITIATED on panel 1 H11-P603 is CLEAR.

3.2.2 IF ARI initiation signals have not cleared, THEN place the ARI System Test switch, to TEST, on paneI1C11-P001, at 112TFT12.

Check green lights ILLUMINATED on paneI1C11-P001:

VALVE DESCRIPTION 1C11-F228 ARI Solenoid Valve Exhaust Port.

1C11-F229A ARI Solenoid Valve Exhaust Port.

1C11-F229B ARI Solenoid Valve Exhaust Port.

1C11-F230 ARI Solenoid Valve Exhaust Port.

3.2.3 Perform SYSTEM RESTORATION per Attachment 1 Section 1 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE40F22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.2 RESETTING ARI 3.2.1 IF ARI initiation signals have cleared, THEN depress ARI Reset pushbutton on panel 1 H11-P603.

AND Check that the annunciator ARI INITIATED on panel 1 H11-P603 is CLEAR.

3.2.2 IF ARI initiation signals have not cleared, THEN place the ARI System Test switch, to TEST, on panel 1 C11-P001, at 112TFT12.

Check green lights ILLUMINATED on panel 1 C11-P001:

VALVE DESCRIPTION 1 C11-F228 ARI Solenoid Valve Exhaust Port.

1 C11-F229A ARI Solenoid Valve Exhaust Port.

1 C11-F229B ARI Solenoid Valve Exhaust Port.

1 C11-F230 ARI Solenoid Valve Exhaust Port.

3.2.3 Perform SYSTEM RESTORATION per Attachment 1 Section 1 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 5 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.3 REPEATING MANUAL SCRAM 3.3.1 Bypass scram discharge volume high level trip at 1 H11-P603.

3.3.2 Confirm RPS Test Trip Logic switches are in NORMAL SWITCH DESCRIPTION LOCATION 1C71-S2A RPS Test A 1 Trip Logic 1H11-P609 1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 1C71-S2B RPS Test B1 Trip Logic 1H11-P611 1C71-S2D RPS Test B2 Trip Logic 1H11-P611 3.3.3 IF all other scram signals are clear, THEN go to step 3.3.5.

NOTE:

Pre-staged jumpers will be found in the EOP jumper book located behind the operator desk.

3.3.4 Install jumpers to override all automatic scram signals:

JUMPER PANEL 1C71-K10A Contact 2 to 1C71-K12E Contact 4 1H11-P609C 1 C71-K1 OC Contact 2 to 1 C71-K12G Contact 4 1H11-P609A 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1H11-P611C 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1H11-P611A 3.3.5 Place Disch Voilsol Test switch to NORM.

3.3.6 Reset ARI, IF necessary, per subsection 3.2.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 5 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.3 REPEATING MANUAL SCRAM 3.3.1 Bypass scram discharge volume high level trip at 1 H11-P603.

3.3.2 Confirm RPS Test Trip Logic switches are in NORMAL SWITCH DESCRIPTION LOCATION 1C71-S2A RPS Test A1 Trip Logic 1H11-P609 1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 1 C71-S2B RPS Test B1 Trip Logic 1H11-P611 1 C71-S2D RPS Test B2 Trip Logic 1 H 11-P611 3.3.3 lE all other scram signals are clear, THEN go to step 3.3.5.

NOTE:

Pre-staged jumpers will be found in the EOP jumper book located behind the operator desk.

3.3.4 Install jumpers to override all automatic scram signals:

JUMPER PANEL 1C71-K10A Contact 2 to 1C71-K12E Contact 4 1H11-P609C 1 C71-K1 OC Contact 2 to 1 C71-K12G Contact 4 1H11-P609A 1 C71-K1 OB Contact 2 to 1 C71-K12F Contact 4 1H11-P611C 1 C71-K1 OD Contact 2 to 1 C71-K12H Contact 4 1 H11-P611A 3.3.5 Place Disch Voilsol Test switch to NORM.

3.3.6 Reset ARI, lE necessary, per subsection 3.2.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 6 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.3.7 IF 1C11-F034, Charging Water Header Isolation Valve, has been CLOSED AND Reactor pressure is below 800 psig, THEN REOPEN 1C11-F034 at 130RAR03.

3.3.8 Reset scram.

3.3.9 Confirm all SDV Vent and Drain Valves are OPEN.

3.3.10 Drain SDV UNTIL SCRAM DISCH VOL HIGH LEVEL TRIP alarm OR SCRAM DISCH VOL NOT DRAINED alarm clears.

3.3.11 Insert manual scram.

3.3.12 Repeat steps 3.3.8 through 3.3.11 UNTIL additional inward rod motion is no longer observed.

3.3.13 3.3.14 IF rod motion is not observed, THEN perform subsection 3.5.

Perform SYSTEM RESTORATION per Attachment 1 section 2.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 6 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.3.7 IF 1 C11-F034, Charging Water Header Isolation Valve, has been CLOSED AND Reactor pressure is below BOO psig, THEN REOPEN 1 C11-F034 at 130RAR03.

3.3.B Reset scram.

3.3.9 Confirm all SDV Vent and Drain Valves are OPEN.

3.3.10 Drain SDV UNTIL SCRAM DISCH VOL HIGH LEVEL TRIP alarm OR SCRAM DISCH VOL NOT DRAINED alarm clears.

3.3.11 Insert manual scram.

3.3.12 Repeat steps 3.3.B through 3.3.11 3.3.13 3.3.14 UNTIL additional inward rod motion is no longer observed.

IE rod motion is not observed, THEN perform subsection 3.5.

Perform SYSTEM RESTORATION per Attachment 1 section 2.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE70F22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.4 DE-ENERGIZING SCRAM SOLENOIDS 3.4.1 Place keylock RPS Test Trip Logic switches to TRIP:

SWITCHES DESCRIPTION LOCATION 1C71-S2A RPS Test A1 Trip Logic 1H11-P609.

1C71-S2C RPS Test A2 Trip Logic 1H11-P609.

1C71-S2B RPS Test B1 Trip Logic 1H11-P611.

1C71-S2D RPS Test B2 Trip Logic 1 H11-P611.

NOTE:

Fuse pullers may be found in the Unit 1 and Unit 2 key cabinets located behind the STA desk.

3.4.2 IF scram solenoids are still energized, THEN remove fuses:

LOCATION FUSES Panel CC-F03 1C71-F18A 1 H11-P609B CC-F04 1C71-F18E 1H11-P609B CC-F05 1C71-F18C 1 H11-P609B CC-F06 1C71-F18G 1 H11-P609B CC-F03 1C71-F18B 1H11-P611B CC-F04 1C71-F18F 1H11-P611B CC-F05 1C71-F18D 1H11-P611B CC-F06 1C71-F18H 1H11-P611B 3.4.3 Perform SYSTEM RESTORATION per Attachment 1 Section 3.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 7 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.4 DE-ENERGIZING SCRAM SOLENOIDS 3.4.1 Place keylock RPS Test Trip Logic switches to TRIP:

SWITCHES DESCRIPTION LOCATION 1C71-S2A RPS Test A1 Trip Logic 1H11-P609.

1C71-S2C RPS Test A2 Trip Logic 1H11-P609.

1C71-S2B RPS Test B1 Trip Logic 1 H11-P611.

1C71-S2D RPS Test B2 Trip Logic 1 H11-P611.

NOTE:

Fuse pullers may be found in the Unit 1 and Unit 2 key cabinets located behind the STA desk.

3.4.2 IF scram solenoids are still energized, TH EN remove fuses:

LOCATION FUSES Panel CC-F03 1C71-F18A 1 H11-P609B CC-F04 1C71-F18E 1 H11-P609B CC-FOS 1C71-F18C 1 H11-P609B CC-F06 1C71-F18G 1 H11-P609B CC-F03 1C71-F18B 1H11-P611B CC-F04 1 C71-F18F 1 H11-P611 B CC-FOS 1C71-F18D 1 H11-P611 B CC-F06 1C71-F18H 1H11-P611B 3.4.3 Perform SYSTEM RESTORATION per Attachment 1 Section 3.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 8 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.5 3.5.1 3.5.2 3.5.3 NOTE:

3.5.4 INDIVIDUALLY SCRAMMING RODS Bypass scram discharge volume high level trip at 1 H11-P603.

Confirm RPS Test Trip Logic switches in NORMAL:

SWITCH DESCRIPTION LOCATION 1C71-S2A RPS Test A 1 Trip Logic 1 H11-P609.

1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 1C71-S2B RPS Test B1 Trip Logic 1 H11-P611 1C71-S2D RPS Test B2 Trip Logic 1 H11-P611 IF all other scram signals are clear, THEN go to step 3.5.5.

Pre-staged jumpers will be found in the EOP jumper book located behind the operator desk.

Override all automatic scram signals by installing the following jumpers:

JUMPER PANEL 1C71-K10A Contact 2 to 1C71-K12E Contact 4 1 H11-P609C 1 C71-K1 OC Contact 2 to 1 C71-K12G Contact 4 1 H11-P609A 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1 H11-P611C 1 C71-K1 OD Contact 2 to 1 C71-K12H Contact 4 1H11-P611A 3.5.5 Place Disch Vol Isol Test switch to NORM.

3.5.6 Reset ARI, IF necessary, per subsection 3.2.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 8 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.5 INDIVIDUALLY SCRAMMING RODS 3.5.1 Bypass scram discharge volume high level trip at 1H11-P603.

3.5.2 Confirm RPS Test Trip Logic switches in NORMAL:

SWITCH DESCRIPTION LOCATION 1C71-S2A RPS Test A1 Trip Logic 1H11-P609.

1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 1C71-S2B RPS Test B1 Trip Logic 1 H11-P611 1C71-S2D RPS Test B2 Trip Logic 1 H11-P611 3.5.3

!E all other scram signals are clear, THEN go to step 3.5.5.

NOTE:

Pre-staged jumpers will be found in the EOP jumper book located behind the operator desk.

3.5.4 Override all automatic scram signals by installing the following jumpers:

JUMPER PANEL 1 C71-K1 OA Contact 2 to 1 C71-K12E Contact 4 1 H11-P609C 1 C71-K1 OC Contact 2 to 1 C71-K12G Contact 4 1 H11-P609A 1 C71-K1 OB Contact 2 to 1 C71-K12F Contact 4 1 H11-P611 C 1 C71-K1 OD Contact 2 to 1 C71-K12H Contact 4 1H11-P611A 3.5.5 Place Disch Vol Isol Test switch to NORM.

3.5.6 Reset ARI, IF necessary, per subsection 3.2.

G16.30 MGR-0001 Rev 3

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 9 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.5.7 IF 1C11-F034, Charging Water Header Isolation Valve, has been CLOSED; 3.5.8 3.5.9 NOTE:

Reactor pressure is below 800 psig, THEN REOPEN 1C11-F034 at 130RAR03.

Reset scram.

Confirm all SDV Vent and Drain Valves are OPEN.

Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.

3.5.10 Obtain recommendations from the STA as to which rods have the highest worth.

3.5.11 Establish communications between panel 1 H 11-P61 0 and 1 H 11-P603.

3.5.12 Place the Reactor Mode switch to REFUEL, at panel 1 H11-P603.

3.5.13 Select a high worth rod and monitor it's position, at panel 1 H11-P603.

3.5.14 Place the Rod Scram Switch for the selected rod to the DOWN (scram) position, at panel 1 H11-P61 O.

3.5.15 WHEN rod motion has stopped, THEN place the Rod Scram Switch to the UP (normal) position.

3.5.16 Repeat steps 3.5.13 thru 3.5.15 to individually scram other rods as desired 3.5.17 IF rod motion is NOT observed, THEN perform subsection 3.7.

3.5.18 Perform SYSTEM RESTORATION, per Attachment 1 Section 4.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 9 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.5.7 IF 1 C11-F034, Charging Water Header Isolation Valve, has been CLOSED; Reactor pressure is below 800 psig, THEN REOPEN 1 C11-F034 at 130RAR03.

3.5.8 Reset scram.

3.5.9 Confirm all SDV Vent and Drain Valves are OPEN.

NOTE:

Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.

3.5.10 3.5.11 3.5.12 3.5.13 3.5.14 Obtain recommendations from the STA as to which rods have the highest worth.

Establish communications between panel 1 H 11-P61 0 and 1 H 11-P603.

Place the Reactor Mode switch to REFUEL, at panel 1 H11-P603.

Select a high worth rod and monitor it's position, at panel 1 H 11-P603.

Place the Rod Scram Switch for the selected rod to the DOWN (scram) position, at panel 1 H 11-P61 O.

3.5.15 WHEN rod motion has stopped, THEN place the Rod Scram Switch to the UP (normal) position.

3.5.16 Repeat steps 3.5.13 thru 3.5.15 to individually scram other rods as desired 3.5.17 IF rod motion is NOT observed, THEN perform subsection 3.7.

3.5.18 Perform SYSTEM RESTORATION, per Attachment 1 Section 4.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 10 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.6 3.6.1 NOTE:

3.6.2 VENTING SCRAM AIR HEADER CLOSE 1 C11-F095, Scram Air Header Isolation Valve, at location 130RAR03.

Pliers may be obtained from the EOP gang box on the 130' elevation to aid in the cap removal.

IF the line is capped, THEN remove cap down stream of 1C11-R013-TV1, Pressure Instrumentation Vent Valve.

3.6.3 Confirm OPEN/OPEN 1 C11-R013-IV1, Pressure Instrumentation Isolation Valve, at location 130RAR03.

3.6.4 OPEN 1 C11-R013-TV1, Pressure Instrumentation Vent Valve, at location 130RAR03.

3.6.5 Perform SYSTEM RESTORATION per Attachment 1 Section 5.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 10 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.6 3.6.1 NOTE:

3.6.2 VENTING SCRAM AIR HEADER CLOSE 1C11-F095, Scram Air Header Isolation Valve, at location 130RAR03.

Pliers may be obtained from the EOP gang box on the 130' elevation to aid in the cap removal.

IF the line is capped, THEN remove cap down stream of 1 C11-R013-TV1, Pressure Instrumentation Vent Valve.

3.6.3 Confirm OPEN/OPEN 1 C11-R013-IV1, Pressure Instrumentation Isolation Valve, at location 130RAR03.

3.6.4 OPEN 1 C11-R013-TV1, Pressure Instrumentation Vent Valve, at location 130RAR03.

3.6.5 Perform SYSTEM RESTORATION per Attachment 1 Section 5.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 11 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.7 DRIVING CONTROL RODS 3.7.1 Place Reactor Mode switch to REFUEL.

3.7.2 Place Rod Worth Minimizer bypass switch to BYPASS.

NOTE:

Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.

3.7.3 Obtain recommendations from STA as to which rods have the highest worth.

3.7.4 3.7.4.1 3.7.4.2 Establish adequate CRD drive water pressure for driving rods as follows:

IF scram is reset and a CRD pump is running, THEN adjust 1C11-F003, Drive Press Cntl VI v, as required.

IF two CRD pumps can be started, THEN place CRD Flow Control 1 C11-R600 in MANUAL and adjust as required.

3.7.4.3 IF scram is NOT reset AND only one CRD pump can be started, 3.7.4.3.1 THEN place 1C11-R600, CRD Flow Control, in AUTO OR Manual, as needed to achieve adequate Drive Water dp.

3.7.4.3.2 IF adequate drive water pressure CANNOT be attained, THEN CLOSE 1 C11-F034 at 130RAR03.

3.7.5 Drive selected rods to at least position 02 using the Emerg In Notch Override switch in the EMER ROD IN position OR Rod Movement Switch in the IN position.

3.7.6 IF rod motion is NOT observed, THEN perform subsection 3.8.

3.7.7 Perform SYSTEM RESTORATION per Attachment 1 Section 6.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3 SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 11 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.7 DRIVING CONTROL RODS 3.7.1 Place Reactor Mode switch to REFUEL.

3.7.2 Place Rod Worth Minimizer bypass switch to BYPASS.

NOTE:

Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.

3.7.3 3.7.4 3.7.4.1 3.7.4.2 3.7.4.3 Obtain recommendations from STA as to which rods have the highest worth.

Establish adequate CRD drive water pressure for driving rods as follows:

IF scram is reset and a CRD pump is running, THEN adjust 1C11-F003, Drive Press Cntl VI v, as required.

IF two CRD pumps can be started, THEN place CRD Flow Control 1 C11-R600 in MANUAL and adjust as required.

IF scram is NOT reset AND only one CRD pump can be started, 3.7.4.3.1 THEN place 1 C11-R600, CRD Flow Control, in AUTO OR Manual, as needed to achieve adequate Drive Water dp.

3.7.4.3.2 IF adequate drive water pressure CANNOT be attained, THEN CLOSE 1 C11-F034 at 130RAR03.

3.7.5 Drive selected rods to at least position 02 using the Emerg In Notch Override switch in the EMER ROD IN position OR Rod Movement Switch in the IN position.

3.7.6 IF rod motion is NOT observed, THEN perform subsection 3.8.

3.7.7 Perform SYSTEM RESTORATION per Attachment 1 Section 6.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 12 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 S.O 3.8 INCREASING CRD COOLING WATER DP CAUTION. INCREASING CRD COOLING WATER DP MAY RESULT IN CRD SEAL

=.:.=-::.:.,:.:.. :,'. DAMAGE.

3.8.1 IF the scram cannot be reset, THEN CLOSE 1 C11-F034, Charging Water Header Isolation Valve, at location 130RAR03.

3.8.2 PLACE 1C11-R607, Press Control Vlv F127 Controller, in MAN and run output to 100%, at 1 H 11-P603.

3.8.3 Confirm OPEN OR fully OPEN 1C11-F003 at 1 H11-P603.

3.8.4 PLACE 1 C11-R600, CRD Flow Control, in MANUAL and run output to 100% at 1 H 11-P603.

3.8.S CLOSE 1C11-FOOS, Return To Vessel Flow Control, atpaneI1H11-P603.

3.8.6 Perform SYSTEM RESTORATION per Attachment 1 Section 7.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

(

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 12 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.8 INCREASING CRD COOLING WATER DP CAUTION' INCREASING CRD COOLING WATER DP MAY RESULT IN CRD SEAL

=-.;;.;:;...::..:...;::;..;...:.' DAMAG E.

3.8.1 IF the scram cannot be reset, 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 THEN CLOSE 1 C11-F034, Charging Water Header Isolation Valve, at location 130RAR03.

PLACE 1 C11-R607, Press Control Vlv F127 Controller, in MAN and run output to 100%, at 1 H11-P603.

Confirm OPEN OR fully OPEN 1 C11-F003 at 1 H11-P603.

PLACE 1 C11-R600, CRD Flow Control, in MANUAL and run output to 100% at 1 H 11-P603.

CLOSE 1C11-F005, Return To Vessel Flow Control, at paneI1H11-P603.

Perform SYSTEM RESTORATION per Attachment 1 Section 7.0 WHEN directed by the Shift Supervisor.

G16.30 MGR-0001 Rev 3

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 13 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.9 NOTE:

VENTING CRD WITHDRAW PORT Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.

-HIGH PRESSURE STEAM AND WATER WILL EXIST IN HOSE ATTACHED TO WITHDRAW VENT VALVE. WHEN MIXTURE EXITS HOSE OR IF ANY CONNECTIONS LEAK IT WILL FLASH TO STEAM. HEALTH PHYSICS PERSONNEL MUST BE NOTIFIED.

CAUTIONS:

-EXIT VELOCITY OF STEAM AND WATER MIXTURE WILL CAUSE HOSE TO WHIP. HOSE MUST BE ANCHORED USING SAFETY GAG.

-IF NEEDLE IN WITHDRAW VENT VALVE IS OPENED TOO FAR IT COULD SHOOT OUT AND CAUSE INJURY.

3.9.1 Obtain recommendations from the STA as to which rods have the highest worth. __

NOTE:

The 1 C11-F1 02 is a block valve located approximately 10 to 15 feet above the HCU.

3.9.2 Confirm 1 C11-F1 02, Withdraw Riser Vent Valve is CLOSED.

NOTE:

A high temperature hose with a quick-connect assembly for connection to 1 C11-F1 02 is located in the EOP gang box on the 130' elevation of the Reactor Building.

3.9.3 For selected control rod, remove plug and attach designated high pressure high temperature hose to 1 C11-F1 02, Withdraw Riser Vent Valve. Obtain hose from the EOP gang box on the 130' elevation of the reactor building.

3.9.4 Route hose to closest equipment drain hub. Place safety gag over standpipe and secure by tightening bolts. (See attach 2) 3.9.5 Fully insert Thaxton Pipe Stopper into Equipment Drain standpipe. Tighten hex nut until grip segments are firmly seated against inside wall of stand pipe.

G16.30 MGR-0001 Rev 3

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 13 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 3.9 NOTE:

VENTING CRD WITHDRAW PORT Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.

-HIGH PRESSURE STEAM AND WATER WILL EXIST IN HOSE ATTACHED TO WITHDRAW VENT VALVE. WHEN MIXTURE EXITS HOSE OR IF ANY CONNECTIONS LEAK IT WILL FLASH TO STEAM. HEALTH PHYSICS PERSONNEL MUST BE NOTIFIED.

CAUTIONS:

-EXIT VELOCITY OF STEAM AND WATER MIXTURE WILL CAUSE HOSE TO WHIP. HOSE MUST BE ANCHORED USING SAFETY GAG.

3.9.1

-IF NEEDLE IN WITHDRAW VENT VALVE IS OPENED TOO FAR IT COULD SHOOT OUT AND CAUSE INJURY.

Obtain recommendations from the STA as to which rods have the highest worth. __

NOTE:

The 1 C11-F1 02 is a block valve located approximately 10 to 15 feet above the HCU.

3.9.2 NOTE:

3.9.3 3.9.4 3.9.5 Confirm 1 C11-F1 02, Withdraw Riser Vent Valve is CLOSED.

A high temperature hose with a quick-connect assembly for connection to 1 C11-F1 02 is located in the EOP gang box on the 130' elevation of the Reactor Building.

For selected control rod, remove plug and attach designated high pressure high temperature hose to 1 C11-F1 02, Withdraw Riser Vent Valve. Obtain hose from the EOP gang box on the 130' elevation of the reactor building.

Route hose to closest equipment drain hub. Place safety gag over standpipe and secure by tightening bolts. (See attach 2)

Fully insert Thaxton Pipe Stopper into Equipment Drain standpipe. Tighten hex nut until grip segments are firmly seated against inside wall of stand pipe.

G16.30 MGR-0001 Rev 3

(

SOUTHERN NUCLEAR PLANT E. I. HATCH I

PAGE 14 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 S.O 3.9.6 SLOWLY OPEN 1 C11-F1 02, Vent Valve, ONE HALF OF ONE TURN using the prestaged CRD Vent Valve Tool found in the EOP Gangbox located on the 130' Elev. of the Reactor Building.

3.9.7 WHEN any of the following conditions occur:

-control rod inserts past position 02.

-control rod inward motion stops.

THEN CLOSE 1 C11-F1 02, Vent Valve.

3.9.8 Repeat steps 3.9.6 and 3.9.7 UNTIL control rod is inserted past position 02 as directed by the Shift Supervisor.

3.9.9 Repeat steps 3.9.2 through 3.9.8 to insert all selected rods past position 02.

3.9.10 Perform SYSTEM RESTORATION per Attachment 1 section 8.0 WHEN directed by Shift Supervisor.

4.0 REFERENCES

4.1 H-17791 and H-17792, Reactor Protection System C71 Elementary Diagram.

4.2 H-16064 and H-1606S, Control Rod Drive System P & ID 4.3 H-S0412, ATWS-ARI System C11 Elementary Diagram.

G16.30 MGR-0001 Rev 3

(

(

\\.

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 140F22 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 S.O 3.9.6 SLOWLY OPEN 1 C11-F1 02, Vent Valve, ONE HALF OF ONE TURN using the prestaged CRD Vent Valve Tool found in the EOP Gangbox located on the 130' Elev. of the Reactor Building.

3.9.7 WHEN any of the following conditions occur:

-control rod inserts past position 02.

-control rod inward motion stops.

THEN CLOSE 1 C11-F1 02, Vent Valve.

3.9.8 Repeat steps 3.9.6 and 3.9.7 UNTIL control rod is inserted past position 02 as directed by the Shift Supervisor.

3.9.9 Repeat steps 3.9.2 through 3.9.8 to insert all selected rods past position 02.

3.9.10 Perform SYSTEM RESTORATION per Attachment 1 section 8.0 WHEN directed by Shift Supervisor.

4.0 REFERENCES

4.1 H-17791 and H-17792, Reactor Protection System C71 Elementary Diagram.

4.2 H-16064 and H-1606S, Control Rod Drive System P & 10 4.3 H-S0412, ATWS-ARI System C11 Elementary Diagram.

G16.30 MGR-0001 Rev 3

(

SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:

CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION PAGE 15 OF 22 DOCUMENT NUMBER:

VERSION NO:

31 EO-EOP-103-1 5.0 ATTACHMENT PAGE:

10F?

The Shift Supervisor will forward this document with all sign-offs complete to Document Control.

PERSON(S) PERFORMING OR VERIFYING LINEUP (PRINT NAME)

INITIALS LINEUP COMPLETED:

TIME ______

DATE _____

REVIEWED BY: SS ____________ TIME ____

/DATE. ___

COMMENTS: ____________________________________________________ __

OPS-09?3 Rev NI A G16.30 MGR-0009 Rev 4

(

SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:

CONTROL ROD INSERTION METHODS ATTACHMENT 1 TITLE: SYSTEM RESTORATION PAGE 15 OF 22 DOCUMENT NUMBER:

VERSION NO:

31 EO-EOP-103-1 5.0 ATTACHMENT PAGE:

1 OF 7 The Shift Supervisor will forward this document with all sign-ofts complete to Document Control.

PERSON(S) PERFORMING OR VERIFYING LINEUP (PRINT NAME)

INITIALS LINEUP COMPLETED:

TIME ______

DATE _____

REVIEWED BY: SS _____________ TIME ____

./DATE ___

COMMENTS: ______________________________________________________ __

OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4

(

SOUTHERN NUCLEAR PLANT EJ. HATCH PAGE 16 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS ATTACHMENT.1.

TITLE: SYSTEM RESTORATION 31 EO-EOP-103-1 5.0 ATTACHMENT PAGE:

20F7 NOTE:

Each section may be performed in whole OR in part.

1.0 ARI Place ARI System Test switch to NORMAL on panel 1 C11-P001.

Verify 2.0 MANUAL SCRAM 2.1 IF jumpers were installed in 3.3.4, THEN remove the following jumpers:

JUMPER PANEL 1C71-K10A Contact 2 to 1C71-K12E Contact 4 1 H11-P609C Verify 1C71-K10CContact2 to 1C71-K12GContact4 1H11-P609A Verify 1 C71-K1 OB Contact 2 to 1 C71-K12F Contact 4 1H11-P611C Verify 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1H11-P611A Verify OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4

(

(

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 16 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION 31 EO-EOP-1 03-1 5.0 ATTACHMENT PAGE:

20F7 NOTE:

Each section may be performed in whole OR in part.

1.0 ARI Place ARI System Test switch to NORMAL on panel 1 C11-P001.

Verify 2.0 MANUAL SCRAM 2.1 IE jumpers were installed in 3.3.4, THEN remove the following jumpers:

JUMPER PANEL 1 C71-K1 OA Contact 2 to 1 C71-K12E Contact 4 1 H11-P609C Verify 1C71-K10C Contact 2 to 1C71-K12G Contact 4 1 H11-P609A Verify 1 C71-K1 OB Contact 2 to 1 C71-K12F Contact 4 1 H11-P611C Verify 1 C71-K1 00 Contact 2 to 1 C71-K12H Contact 4 1 H11-P611A Verify OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4

SOUTHERN NUCLEAR PAGE 17 OF 22 PLANT E.I. HATCH DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 ATTACHMENT J.

ATTACHMENT PAGE:

TITLE: SYSTEM RESTORATION 30F7 3.0 SCRAM SOLENOIDS 3.1 Install RPS Scram Solenoid Fuses.

LOCATION FUSES PANEL CC-F03 1C71-F18A 1 H11-P609B Verify CC-F04 1C71-F18E 1 H11-P609B Verify CC-F05 1C71-F18C 1 H11-P609B Verify CC-F06 1C71-F18G 1 H11-P609B Verify CC-F03 1C71-F18B 1H11-P611B Verify CC-F04 1C71-F18F 1 H11-P611 B Verify CC-F05 1C71-F18D 1H11-P611B Verify CC-F06 1C71-F18H 1 H11-P611 B Verify OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4 SOUTHERN NUCLEAR PAGE 17 OF 22 PLANT E.I. HATCH DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 5.0 ATTACHMENT..1 ATTACHMENT PAGE:

TITLE: SYSTEM RESTORATION 30F7 3.0 SCRAM SOLENOIDS 3.1 Install RPS Scram Solenoid Fuses.

LOCATION FUSES PANEL CC-F03 1C71-F18A 1 H11-P609B Verify CC-F04 1C71-F18E 1 H11-P609B Verify CC-F05 1C71-F18C 1 H11-P609B Verify CC-F06 1C71-F18G 1 H11-P609B

(

Verify CC-F03 1C71-F18B 1H11-P611B Verify CC-F04 1C71-F18F 1 H11-P611 B Verify CC-F05 1C71-F18D 1 H11-P611 B Verify CC-F06 1C71-F18H 1 H11-P611 B Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4

SOUTHERN NUCLEAR PLANT E.1. HATCH DOCUMENT TITLE:

CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION PAGE 18 OF 22 DOCUMENT NUMBER:

VERSION NO:

31 EO-EOP-103-1 5.0 ATTACHMENT PAGE:

40F7 3.2 Confirm keylock RPS Test Trip Logic switches in NORMAL.

SWITCHES LOCATION 1C71-S2A RPS Test A1 Trip Logic 1H11-P609 Verify 1C71-S2C RPS Test A2 Trip Logic 1H11-P609 Verify 1C71-S2B RPS Test B1 Trip Logic 1 H11-P611 Verify 1C71-S2D RPS Test B2 Trip Logic 1 H11-P611 Verify OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4

(

(

SOUTHERN NUCLEAR PLANT E.1. HATCH DOCUMENT TITLE:

CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION PAGE 18 OF 22 DOCUMENT NUMBER:

VERSION NO:

31 EO-EOP-103-1 5.0 ATTACHMENT PAGE:

40F7 3.2 Confirm keylock RPS Test Trip Logic switches in NORMAL.

SWITCHES LOCATION 1 C71-S2A RPS Test A1 Trip Logic 1 H11-P609 Verify 1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 Verify 1C71-S2B RPS Test B1 Trip Logic 1 H11-P611 Verify 1 C71-S2D RPS Test B2 Trip Logic 1 H11-P611 Verify OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4

(

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 190F22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 ATTACHMENT.1.

TITLE: SYSTEM RESTORATION 4.0 INDIVIDUAL ROD SCRAM 4.1 IF jumpers were installed in 3.5.4, THEN remove following jumpers:

IF jumpers were installed in 3.3.4, THEN remove the following jumpers:

JUMPER PANEL 1 C71-K1 OA Contact 2 to 1 C71-K12E Contact 4 1 H11-P609C 1C71-K10C Contact 2 to 1C71-K12G Contact 4 1H11-P609A 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1H11-P611C 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1H11-P611A ATTACHMENT PAGE:

50F7 Verify Verify Verify Verify 4.2 Confirm all Rod Scram Switches are in the UP (normal) position at 1 H11-P610.

Verify OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4

(

(

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 19 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 5.0 ATTACHMENT..1 TITLE: SYSTEM RESTORATION 4.0 INDIVIDUAL ROD SCRAM 4.1 IF jumpers were installed in 3.5.4, THEN remove following jumpers:

IF jumpers were installed in 3.3.4, THEN remove the following jumpers:

JUMPER PANEL 1 C71-K1 OA Contact 2 to 1 C71-K12E Contact 4 1 H11-P609C 1 C71-K1 OC Contact 2 to 1 C71-K12G Contact 4 1 H11-P609A 1C71-K10BContact2 to 1C71-K12FContact4 1H11-P611C 1 C71-K1 00 Contact 2 to 1 C71-K12H Contact 4 1 H11-P611 A ATTACHMENT PAGE:

50F7 Verify Verify Verify Verify 4.2 Confirm all Rod Scram Switches are in the UP (normal) position at 1 H11-P61 O.

Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 20 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 ATTACHMENT..1 TITLE: SYSTEM RESTORATION ATTACHMENT PAGE:

60F7 5.0 SCRAM AIR HEADER 5.1 CLOSE 1C11-R013-TV1, Pressure Instrumentation Vent Valve, at 130RAR03 Verify 5.2 IF the line was capped, THEN install cap down stream of 1C11-R013-TV1, Pressure Instrumentation Vent Valve.

Verify 5.3 Open Scram Air Header Isolation Valve 1C11-F095, at location 130RAR03.

Verify 6.0 DRIVING CONTROL RODS 6.1 Stop a CRD pump.

Verify 6.2 Adjust 1 C11-R600, CRD Flow Control, as required and place in AUTO.

Verify 6.3 OPEN 1 C11-F005, Return To Vessel Flow Control.

Verify 6.4 Place Reactor Mode switch to SHUTDOWN.

Verify 6.5 Place Rod Worth Minimizer bypass switch to OPERATE Verify 6.6 OPEN 1 C11-F034, Charging Water Header Isolation Valve Verify OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4

(

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 20 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 5.0 ATTACHMENT 1 TITLE: SYSTEM RESTORATION 5.0 SCRAM AIR HEADER ATTACHMENT PAGE:

60F7 5.1 CLOSE 1 C11-R013-TV1, Pressure Instrumentation Vent Valve, at 130RAR03 5.2

!E the line was capped, THEN install cap down stream of 1C11-R013-TV1, Pressure Instrumentation Vent Valve.

Verify Verify 5.3 Open Scram Air Header Isolation Valve 1 C11-F095, at location 130RAR03.

Verify 6.0 DRIVING CONTROL RODS 6.1 Stop a CRD pump.

Verify 6.2 Adjust 1 C11-R600, CRD Flow Control, as required and place in AUTO.

Verify 6.3 OPEN 1 C11-F005, Return To Vessel Flow Control.

Verify 6.4 Place Reactor Mode switch to SHUTDOWN.

Verify 6.5 Place Rod Worth Minimizer bypass switch to OPERATE Verify 6.6 OPEN 1 C11-F034, Charging Water Header Isolation Valve Verify OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4

(

(

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 21 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 5.0 ATTACHMENT..1 TITLE: SYSTEM RESTORATION 7.0 CRD COOLING WATER 7.1 Adjust 1C11-R607, Press Control Vlv F127 controller, as required and PLACE in AUTO.

ATTACHMENT PAGE:

70F7 Verify 7.2 Adjust CRD Flow Contro11C11-R600 as required and PLACE in AUTO.

7.3 OPEN 1 C11-F005, Return To Vessel Flow Control.

7.4 Throttle 1 C11-F003 to obtain CRD Drive Water dp at 260 psig as indicated on 1 C11-R602.

8.0 VENTING WITHDRAW PORT 8.1 Close 1 C11-F1 02 for each control rod that was vented 8.2 Remove all hoses.

8.3 Install all plugs OPS-0973 Rev NI A G16.30 MGR-0009 Rev 4 Verify Verify Verify Verify Verify Verify SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 21 OF 22 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 5.0 ATTACHMENT..1 TITLE: SYSTEM RESTORATION 7.0 CRD COOLING WATER 7.1 Adjust 1 C11-R607, Press Control Vlv F127 controller, as required and PLACE in AUTO.

ATTACHMENT PAGE:

70F7 Verify 7.2 Adjust CRD Flow Contro11C11-R600 as required and PLACE in AUTO.

7.3 OPEN 1C11-F005, Return To Vessel Flow Control.

7.4 Throttle 1 C11-F003 to obtain CRD Drive Water dp at 260 psig as indicated on 1 C11-R602.

Verify Verify Verify

(

8.0 VENTING WITHDRAW PORT 8.1 Close 1 C11-F1 02 for each control rod that was vented Verify 8.2 Remove all hoses.

Verify 8.3 Install all plugs Verify

(

\\

OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4

(

(

SOUTHERN NUCLEAR PLANT E.I. HATCH I

DOCUMENT TITLE:

I DOCUMENT NUMBER:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 ATTACHMENT g TITLE: THAXTON PIPE STOPPER DIAGRAM 10 IC\\l-Fl01 MGR-0009 Rev 4 PAGE 22 OF 22 VERSION NO:

5.0 ATTACHMENT PAGE:

1 OF 1

(

SOUTHERN NUCLEAR PLANT E.I. HATCH I

DOCUMENT TITLE:

I DOCUMENT NUMBER:

CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 ATTACHMENT.2.

TITLE: THAXTON PIPE STOPPER DIAGRAM 10 leu-FlO'-

_...,..... 1nCI BUI1ll N MGR-0009 Rev 4 PAGE 22 OF 22 VERSION NO:

5.0 ATTACHMENT PAGE:

1 OF 1

(,

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NR FI AL Southern E. I. Hatch uclear uclear Plant Operations Training JPM C. M. EDMUND 10/0912009 Energy to Serve Your World sM

(

(

TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM PLANT2-ALL Locally Start IB psw Pump Breaker Without Control Power AUTHOR MEDIA NUMBER F. FAGAN 2009-302 Plant 2 RECOMMENDED BY APPROVED BY NR C. M. EDMUND TIME 18.0 Minutes DATE 10/0912009 Energy to Serve Your World sM

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Plant 2 10109/09 Modified so operator attempts to start pump locally with the control switch. The pump fails to start due to loss of control power. The operator then uses of the procedure to manually close in the breaker.

FNF

~upv~s**

InitialS**.

CME

(

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

2009-302 Plant 2 Rev. No.

Date Reason for Revision Author's Supv's Initials Initials 10109/09 Modified so operator attempts to start pump locally FNF CME with the control switch. The pump fails to start due to loss of control power. The operator then uses of the procedure to manually close in the breaker.

(

2009-302 Plant 2 Page 1 of 8 UNIT 1 (X)

UNIT 2 0

Locally Start IB PSW Pump Breaker Without Control Power LR-JP-27.65-13 The task is complete when from outside the Control Room, during a Control Room evacuation, a PSW Pump has been started without control power.

027.065 O:sJEQTlYE,NUMBER: 027.065.B PLANT HATCH JTA IMPORTANCE RATING:

RO 3.86 SRO 3.86 KIA CATALOG NUMBER:

KIA CATALOG JTA IMPORTANCE RATING:

RO SRO OPERATOR APPLICABILITY:

MQUlREJ)1\\1Al'F}J{JALS;***

(current version)

Breaker CharginglMaintenance Handle APPROXIMATE COMPLETION TIME:

18.0 Minutes SIMULATOR SETUP:

N/A

(

2009-302 Plant 2 Page 1 of 8 UNIT 1 (X)

UNIT 2 0

TASK TITLE:

JPMNUMBER:

TASK STANDARD:

TASK NUMBER:

Locally Start IB PSW Pump Breaker Without Control Power LR-JP-27.65-13 The task is complete when from outside the Control Room, during a Control Room evacuation, a PSW Pump has been started without control power.

027.065 OBJECTIVE NUMBER: 027.065.B PLANT HATCH JTA IMPORTANCE RATING:

RO 3.86 SRO 3.86 KIA CATALOG NUMBER:

KIA CATALOG JTA IMPORTANCE RATING:

RO SRO OPERATOR APPLICABILITY:

I GENERAL

REFERENCES:

Unit 1 31RS-OPS-00l-l (current version)

I REQUIRED MATERIALS:

Unit 1 31RS-OPS-00l-l (current version)

Breaker CharginglMaintenance Handle APPROXIMATE COMPLETION TIME:

18.0 Minutes SIMULATOR SETUP:

NI A

UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The Control Room has been evacuated.

2.

A Plant Shutdown is in progress per 31RS-OPS-OOl-l

3.

Off-Site Power is supplying all plant busses.

4.

PSW Pumps "C" and "D" are inoperable.

INITIATING CUES:

Locally start one PSW pump per 3 lRS-OPS-OOl-l, Attachment 9.

UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The Control Room has been evacuated.

2.

A Plant Shutdown is in progress per 3IRS-OPS-OOI-I

3.

Off-Site Power is supplying all plant busses.

4.

PSW Pumps "C" and "D" are inoperable.

(

INITIATING CUES:

Locally start one PSW pump per 3IRS-OPS-OOI-I, Attachment 9.

(

1.
2.
3.
4.
5.

Operator obtains the procedure and Operator obtains 31RS-OPS-001-selects the proper Attachment.

1 and selects Attachment 9.

Start the 1P41-COOlB pump In 4160V switchgear room 1G, at panel1H21-P175, the operator places lC82-S2B, transfer switch, to the EMER position.

The operator places the IP41-C001B pump control switch to START.

2009-302 Plant 2 Page 3 of 8 S~TIUNSA.T (COMMENTS.* ********

START TIME: ___ _

SAT I UNSAT SAT/UNSAT SAT/UNSAT PROMPT:

WHEN the control switch is closed, THEN inform the operator that there was no sound heard of a breaker closing in.

PROMPT:

PROMPT:

IF the operator checks breaker light indication, THEN inform the operator that both the red and green lights are off.

IF the operator checks control power breaker, THEN inform the operator that control power breaker is tripped and can not be reset.

Identifies the requirement to perform Operator has determined SAT/UNSAT. is required to start a pump.

Selects one PSW pump to start.

Operator selects "A" PSW pump SAT/UNSAT at 1R22-S005 Fr. 3 OR "B" PSW pump at 1 R22-S007 Fr. 4 OPEN breaker cubicle door.

Operator opens the selected SAT/UNSAT pumps cubicle door.

PROMPT:

WHEN the operator indicates the door is to be opened, THEN give the operator the pictures and inform the operator it is a view with the cubicle door open.

6. TRIP the 30A control power breaker Inside the selected pumps cubicle, in the associated breaker cubicle.

the operator has opened/verified tripped the 30A control power breaker.

PROMPT:

IF addressed by the Operator, as the Shift Supervisor, INFORM the operator that Control Power is NOT A V AILABLE.

(** Indicates critical step)

SAT/UNSAT

(

(

1.
2.
3.
4.
5.

PERFORMANCE STEP STANDARD Operator obtains the procedure and Operator obtains 31RS-OPS-001-selects the proper Attachment.

1 and selects Attachment 9.

Start the 1P41-COOlB pump In 4160V switchgear room 10, at panel 1 H21-P 175, the operator places lC82-S2B, transfer switch, to the EMER position.

The operator places the 1P41-COOlB pump control switch to START.

2009-302 Plant 2 Page 3 of 8 SATIUNSAT (COMMENTS START TIME: ___ _

SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:

WHEN the control switch is closed, THEN inform the operator that there was no sound heard of a breaker closing in.

PROMPT:

PROMPT:

IF the operator checks breaker light indication, THEN inform the operator that both the red and green lights are off.

IF the operator checks control power breaker, THEN inform the operator that control power breaker is tripped and can not be reset.

Identifies the requirement to perform Operator has determined SAT/UNSAT. is required to start a pump.

Selects one PSW pump to start.

Operator selects "A" PSW pump SAT/UNSAT at 1R22-S005 Fr. 3 OR "B" PSW pump at 1R22-S007 Fr. 4 OPEN breaker cubicle door.

Operator opens the selected SAT I UNSAT pumps cubicle door.

PROMPT:

WHEN the operator indicates the door is to be opened, THEN give the operator the pictures and inform the operator it is a view with the cubicle door open.

6. TRIP the 30A control power breaker Inside the selected pumps cubicle, in the associated breaker cubicle.

the operator has opened/verified tripped the 30A control power breaker.

PROMPT:

IF addressed by the Operator, as the Shift Supervisor, INFORM the operator that Control Power is NOT A V AILABLE.

(** Indicates critical step)

SAT/UNSAT

PROMPT:

IF the asks about spring charge status, INFORM the operator that the springs are DISCHARGED.

p:laye.* $p~l1gCh~geiMain{enan2e**....

\\E-Il:tQdleintqth(3s1gtin.tlieIUanu~li.......

E~t~hetle"er{lo~~t(3g*.. totlj~left2ftlj(3 "LwrTOiTR.W~'..plqng(W)**.

At the selected pumps cubicle, the operator has PLACED the Spring Charge/Maintenance Handle in the slot in the manual ratchet lever located to the left of the "LIFT TO TRIP" plunger.

At the selected pumps cubicle, the operator pumps the handle several times. the breaker closing spring. The handle moves freely and a "click" is heard.

2009-302 Plant 2 Page 4 of8

$A'l'IUNSAT COMMENTS SAT/UNSAT SAT/UNSAT PROMPT:

WHEN the operator indicates charging of the breaker, INFORM the operator that a click is heard and the handle moves freely.

9. REMOVE the Spring At the selected pumps cubicle, the SAT I UNSAT Charge/Maintenance Handle.

operator has REMOVED the Spring Charge/Maintenance Handle.

NOTE:

Disabling the undervoltage trip is only necessary if the operator was at Bus IF, IR22-S006.

NOTE:

With the 30 amp control power breaker open, the breaker indicating lights and meter will not function.

11. RECLOSE the 30A control power breaker.

(** Indicates critical step)

At the selected pumps cubicle, the operator has PUSHED UP the plunger marked "LIFT TO CLOSE."

At the selected pumps cubicle, the operator has RECLOSED the 30A control power breaker.

SAT I UNSAT SAT/UNSAT l

PERFO~CESTEP STANDARD PROMPT:

IF the asks about spring charge status, INFORM the operator that the springs are DISCHARGED.

    • 7. Place Spring ChargelMaintenance At the selected pumps cubicle, the Handle into the slot in the manual operator has PLACED the Spring ratchet lever. (located to the left of the Charge/Maintenance Handle in "LIFf TO TRIP" plunger).

the slot in the manual ratchet lever located to the left of the "LIFf TO TRIP" plunger.

    • 8. CHARGE the breaker closing spring At the selected pumps cubicle, the until the handle moves freely and a operator pumps the handle several "click" is heard.

times. the breaker closing spring. The handle moves freely and a "click" is heard.

2009-302 Plant 2 Page 4 of 8 SATIUNSAT COMMENTS SAT I UNSAT SAT/UNSAT PROMPT:

WHEN the operator indicates charging of the breaker, INFORM the operator that a click is heard and the handle moves freely.

9. REMOVE the Spring At the selected pumps cubicle, the SAT/UNSAT Charge/Maintenance Handle.

operator has REMOVED the Spring Charge/Maintenance Handle.

NOTE:

Disabling the undervoltage trip is only necessary if the operator was at Bus IF, IR22-S006.

NOTE:

With the 30 amp control power breaker open, the breaker indicating lights and meter will not function.

    • 10. PUSH UP on the plunger marked At the selected pumps cubicle, the SAT/UNSAT "LIFf TO CLOSE."

operator has PUSHED UP the plunger marked "LIFf TO CLOSE."

11. RECLOSE the 30A control power At the selected pumps cubicle, the SAT/UNSAT breaker.

operator has RECLOSED the 30A control power breaker.

(** Indicates critical step)

12. CLOSE the breaker cubicle door.

At the selected pumps cubicle, the operator has CLOSED the breaker cubicle door.

13. Re-enter Attachment 9.

Operator returns to Attachment 9.

2009-302 Plant 2 Page 5 of 8 SAT,IUNSAT.............

(COMMENTS).

SAT/UNSAT SAT/UNSAT PROMPT:

WHEN the operator addresses throttling PSW flow, INFORM the operator that another operator has been assigned to throttle flow.

PROMPT:

IF the operator addresses system restoration, INFORM the operator that restoration is not required at this time.

NOTE: The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

(

(

PERFO~NCESTEP

12. CLOSE the breaker cubicle door.
13. Re-enter Attachment 9.

STANDARD At the selected pumps cubicle, the operator has CLOSED the breaker cubicle door.

Operator returns to Attachment 9.

2009-302 Plant 2 Page 5 of 8 SATIUNSAT (COMMENTS SAT I UNSAT SAT I UNSAT PROMPT:

WHEN the operator addresses throttling PSW flow, INFORM the operator that another operator has been assigned to throttle flow.

PROMPT:

IF the operator addresses system restoration, INFORM the operator that restoration is not required at this time.

NOTE:

The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ___ _

( - 4160 VAC Breaker Open Cabinet

(** Indicates critical step)

Page 6 of8

(

{

\\ - 4160 VAC Breaker Open Cabinet

(** Indicates critical step)

Page 6 of 8

( - 4160 VAC Breaker Close Up Views Page 7 of8

(

\\ - 4160 VAC Breaker Close Up Views Page 7 of 8

( - 4160 VAC Breaker Close Up Views Page 8 of 8

(

(

( - 4160 VAC Breaker Close Up Views Page 8 of 8

( - 4160 VAC Breaker Open Cabinet

. (** Indicates c~tical step)

Page 6 of8 - 4160 VAC Breaker Open Cabinet

(** Indicates critical step)

Page 6 of 8

( - 4160 VAC Breaker Close Up Views Page 7 of8 - 4160 VAC Breaker Close Up Views Page 7 of 8

(

( - 4160 VAC Breaker Close Up Views Page 8 of 8

( - 4160 VAC Breaker Close Up Views Page 8 of 8

UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The Control Room has been evacuated.

2.

A Plant Shutdown is in progress per 31RS-OPS-OO 1-1

3.

Off-Site Power is supplying all plant busses.

4.

PSW Pumps "c" and "D" are inoperable.

INITIATING CUES:

Locally start one PSW pump per 31RS-OPS-OOl-l, Attachment 9.

(

UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The Control Room has been evacuated.

2.

A Plant Shutdown is in progress per 3lRS-OPS-OO 1-1

3.

Off-Site Power is supplying all plant busses.

4.

PSW Pumps "C" and "D" are inoperable.

(

INITIATING CUES:

Locally start one PSW pump per 3lRS-OPS-OOl-l, Attachment 9.

(

(,,

SOUTHERN NUCLEAR DOCUMENT TYPE:

PAGE PLANT E. I. HATCH REMOTE SHUTDOWN PROCEDURE 1 OF 48 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-OO1-1 5.14 EXPIRATION APPROVALS:

EFFECTIVE DATE:

DEPARTMENT MGR G. L. Johnson DATE 06-05-98 DATE:

N/A SSM /PM N/A DATE N/A 4-27-09 1.0 CONDITIONS Under certain conditions the Control Room may be uninhabitable. This procedure describes actions necessary to bring the reactor to a shutdown condition from a steady state normal operating condition by manipulating plant controls outside of the Main Control Room.

TABLE OF CONTENTS Section 2.0 AUTOMATIC ACTIONS...................................................................................................... 1 3.0 IMMEDIATE OPERATOR ACTIONS................................................................................... 2 4.0 SUBSEQUENT OPERATOR ACTIONS.............................................................................. 3 Attachments 1

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER.............................. 11 2

RCIC CONTINUED OPERATION FROM THE REMOTE SHUTDOWN PANEL............... 18 3

RCIC OPERATION FROM REMOTE SHUTDOWN PANEL............................................. 21 4

RCIC SHUTDOWN FROM REMOTE SHUTDOWN PANEL............................................. 25 5

MAXIMIZING CRD SYSTEM FLOW................................................................................. 27 6

LPCI OPERATION FROM THE REMOTE SHUTDOWN PANEL...................................... 31 7

TORUS COOLING FROM THE REMOTE SHUTDOWN PANEL...................................... 35 8

SHUTDOWN COOLING FROM THE REMOTE SHUTDOWN PANEL.............................. 39 9

PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM...................................... 47 2.0 AUTOMATIC ACTIONS None MGR-0002 Ver. 8.1

(

SOUTHERN NUCLEAR DOCUMENT TYPE:

PAGE PLANT E. I. HATCH REMOTE SHUTDOWN PROCEDURE 1 OF 48 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 5.14 EXPIRATION APPROVALS:

EFFECTIVE DATE:

DEPARTMENT MGR G. L. Johnson DATE 06-05-98 DATE:

N/A SSM /PM N/A DATE N/A 4-27-09 1.0 CONDITIONS Under certain conditions the Control Room may be uninhabitable. This procedure describes actions necessary to bring the reactor to a shutdown condition from a steady state normal operating condition by manipulating plant controls outside of the Main Control Room.

TABLE OF CONTENTS Section 2.0 AUTOMATIC ACTIONS...................................................................................................... 1 3.0 IMMEDIATE OPERATOR ACTIONS................................................................................... 2 4.0 SUBSEQUENT OPERATOR ACTIONS.............................................................................. 3 Attachments BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER.............................. 11 2

RCIC CONTINUED OPERATION FROM THE REMOTE SHUTDOWN PANEL............... 18 3

RCIC OPERATION FROM REMOTE SHUTDOWN PANEL............................................. 21 4

RCIC SHUTDOWN FROM REMOTE SHUTDOWN PANEL............................................. 25 5

MAXIMIZING CRD SYSTEM FLOW................................................................................. 27 6

LPCI OPERATION FROM THE REMOTE SHUTDOWN PANEL...................................... 31 7

TORUS COOLING FROM THE REMOTE SHUTDOWN PANEL...................................... 35 8

SHUTDOWN COOLING FROM THE REMOTE SHUTDOWN PANEL.............................. 39 9

PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM...................................... 47 2.0 AUTOMATIC ACTIONS None MGR-0002 Ver. 8.1

(

l SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER NOTE The following provides guidance on manually closing various types of air and vacuum circuit breakers without the presence of control power.

Pg 11 of 48 Version No:

5.14 Att. Pg.

1 of 7 WHEN WORKING WITH ENERGIZED ELECTRICAL EQUIPMENT FOLLOW CAUTION THE ELECTRICAL SAFETY PROCEDURE OUTLINED IN SOUTHERN NUCLEAR SAFETY MANUAL.

1.0 I F the breaker is 4160 VAC, THEN take the following applicable action:

1.1 CLOSE a 4160 VAC breaker to energize the load, by performing the following steps:

1.1.1 OPEN Breaker Cubicle Door.

1.1.2 TRIP the 30A control breaker in the associated breaker cubicle AND CLOSE the breaker as follows:

NOTE IF it can be confirmed that the spring is charged, go directly to step 1.1.3.

1.1.2.1 1.1.2.2 1.1.2.3 Place the end of the Spring Charge/Maintenance Handle (stored adjacent to the switchgear) into the slot in the manual ratchet lever, located to the left of the "LIFT TO TRIP" plunger. For the new DHP-VR vacuum breakers this slot is located just to the right of the "Spring Charged/Discharged" indicator.

Charge the spring with several downward pumping movements of the handle UNTIL the handle suddenly moves freely AND a "click" is heard.

Remove the Spring Charge Maintenance handle AND return to storage position.

MGR-0009 Ver. 4 SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER NOTE The following provides guidance on manually closing various types of air and vacuum circuit breakers without the presence of control power.

Pg 11 of 48 Version No:

5.14 Att. Pg.

1 of 7 WHEN WORKING WITH ENERGIZED ELECTRICAL EQUIPMENT FOLLOW CAUTION THE ELECTRICAL SAFETY PROCEDURE OUTLINED IN SOUTHERN NUCLEAR SAFETY MANUAL.

1.0 I F the breaker is 4160 VAC, THEN take the following applicable action:

1.1 CLOSE a 4160 VAC breaker to energize the load, by performing the following steps:

1.1.1 OPEN Breaker Cubicle Door.

1.1.2 TRIP the 30A control breaker in the associated breaker cubicle AND CLOSE the breaker as follows:

NOTE IF it can be confirmed that the spring is charged, go directly to step 1.1.3.

1.1.2.1 1.1.2.2 1.1.2.3 Place the end of the Spring Charge/Maintenance Handle (stored adjacent to the switchgear) into the slot in the manual ratchet lever, located to the left of the "LIFT TO TRIP" plunger. For the new DHP-VR vacuum breakers this slot is located just to the right of the "Spring Charged/Discharged" indicator.

Charge the spring with several downward pumping movements of the handle UNTIL the handle suddenly moves freely AND a "click" is heard.

Remove the Spring Charge Maintenance handle AND return to storage position.

MGR-0009 Ver. 4

(

SNC PLANT E. I. HATCH I Pg 12 of 48 DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM J

31 RS-OPS-001-1 Version No:

5.14 ATTACHMENT -L TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER Att. Pg.

2 of 7 The following breakers in Bus 1F are equipped with control power undervoltage trip devices:

1.1.3 Frame 2 - Plant Service Water Pump 1 D Frame 3 - RHR Service Water Pump 1C Frame 4 - Plant Service Water Pump 1C Frame 8 - CRD Pump 1 B Frame 9 - RHR Pump 1 C These devices will trip their associated breaker upon loss of 125 VDC control power to the breaker. The trip will be mechanically maintained UNTIL control power is restored.

Step 1.1.3.1 MUST be performed before manually closing these breakers.

Steps 1.1.3.1 AND 1.1.3.2 only apply to the Bus 1 F breakers listed above.

Disabling of the undervoltage trip linkage on Frame 7 (RHR Pump 1 D) is NOT necessary due to its control power transfer scheme.

IF the 4160V breaker is one of bus 1 F breakers listed in the above note, THEN perform the following:

NOTE The top nut on this linkage is factory adjusted AND must NOT be disturbed WHEN removing the bottom nut.

1.1.3.1 MGR-0009 Ver. 4 For the old style Type DHP Air Circuit Breakers DISABLE the control power undervoltage trip device by removing the bottom nut and disengage the tripping linkage as shown on Figure 1.

OR For the new style Type VR Vacuum Breakers disable the control power undervoltage trip device by removing the front cover, removing the screw and nut and removing the linkage as shown on Figure 2.

(

SNC PLANT E. I. HATCH I Pg 12 of 48 DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:

5.14 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER 1.1.3 The following breakers in Bus 1 F are equipped with control power undervoltage trip devices:

Frame 2 - Plant Service Water Pump 1 D Frame 3 - RHR Service Water Pump 1 C Frame 4 - Plant Service Water Pump 1 C Frame 8 - CRD Pump 1 B Frame 9 - RHR Pump 1C These devices will trip their associated breaker upon loss of 125 VDC control power to the breaker. The trip will be mechanically maintained UNTIL control power is restored.

Step 1.1.3.1 MUST be performed before manually closing these breakers.

Steps 1.1.3.1 AND 1.1.3.2 only apply to the Bus 1 F breakers listed above.

Disabling of the undervoltage trip linkage on Frame 7 (RHR Pump 1 D) is NOT necessary due to its control power transfer scheme.

IF the 4160V breaker is one of bus 1 F breakers listed in the above note, THEN perform the following:

NOTE The top nut on this linkage is factory adjusted AND must NOT be disturbed WHEN removing the bottom nut.

1.1.3.1 MGR-0009 Ver. 4 For the old style Type DHP Air Circuit Breakers DISABLE the control power undervoltage trip device by removing the bottom nut and disengage the tripping linkage as shown on Figure 1.

OR For the new style Type VR Vacuum Breakers disable the control power undervoltage trip device by removing the front cover, removing the screw and nut and removing the linkage as shown on Figure 2.

Att. Pg.

2 of 7

SNC PLANT E.I. HATCH I Pg 13 of 48 DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:

5.14 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER Att. Pg.

3 of 7 DO NOT DISTURB POSITION OF TOP NUT MGR-0009 Ver. 4 FIGURE 1 REMOVE BOTTOM NUT TO DISABLE UNDERVOLTAGE TRIP DEVICE 4160V BREAKER CUBICLE LOSS OF DC BREAKER TRIP DEVICE

(

SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 Pg 13 of 48 Version No:

5.14 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER Att. Pg.

3 of 7 DO NOT DISTURB POSITION OF TOP NUT MGR-0009 Ver. 4 FIGURE 1 REMOVE BOTTOM NUT TO DISABLE UNDER VOLTAGE TRIP DEVICE 4160V BREAKER CUBICLE LOSS OF DC BREAKER TRIP DEVICE

SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER STEP 2 Slide link up & remove.

STEP 1 Remove screw & nut.

FIGURE 2 Pg 14 of 48 Version No:

5.14 Att. Pg.

4 of 7 LOSS OF DC BREAKER TRIP DEVICE FOR NEW VR VACUUM BREAKER MGR-0009 Ver. 4

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SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER STEP 2 Slide link up & remove.

STEP 1 Remove screw & nut.

FIGURE 2 Pg 14 of 48 Version No:

5.14 Att. Pg.

4 of 7 LOSS OF DC BREAKER TRIP DEVICE FOR NEW VR VACUUM BREAKER MGR-0009 Ver. 4

SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM L

31 RS-OPS-001-1 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER NOTE Due to the possibility of initiating a trip, the nuts must NOT be re-installed WHILE the breakers are supplying power to their respective loads.

1.1.3.2 Upon restoration of control power, AND IF plant conditions permit, Re-install the nut removed in step 1.1.3.1 OR Re-install the linkage, screw and nut removed in step 1.1.3.1 BEFORE STARTING 4160V LOADS ON THE DIESEL GENERATOR, DiESEL LOAD MUST BE BELOW THE MAXIMUM VALUE INDICATED.

MAX DIESEL CAUTION:

LOAD LOAD FOR STARTING 310 AMPS RHR SERVICE WATER PUMP CORE SPRAY PUMP RHR PUMP PSW PUMP 310 AMPS 340 AMPS 390 AMPS 1.1.4 Confirm Diesel Generator AMP reading is BELOW the maximum value in the above CAUTION, PRIOR to closing any listed 4160V breaker.

1.1.5 IF a standard DHP Air Circuit breaker is installed in this cubicle, Manually close the 4 KV pump breaker by pushing up on the plunger marked "LIFT TO CLOSE".

OR IF a new DHP-VR vacuum breaker is installed in this cubicle, DEPRESS the button marked "Push to Close".

1.1.6 RE-CLOSE the 30A control breaker in the associated cubicle.

1.1.6.1 Go to step 1.2, IF the 4160 VAC breaker opens.

1.1.7 CLOSE the breaker cubicle door.

MGR-0009 Ver. 4 Pg 15 of 48 Version No:

5.14 Att. Pg.

5 of 7

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SNC PLANT E. I. HATCHl DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER NOTE Due to the possibility of initiating a trip, the nuts must NOT be re-installed WHILE the breakers are supplying power to their respective loads.

1.1.3.2 Upon restoration of control power, AND IF plant conditions permit, Re-install the nut removed in step 1.1.3.1 OR Re-install the linkage, screw and nut removed in step 1.1.3.1 BEFORE STARTING 4160V LOADS ON THE DIESEL GENERATOR, DIESEL LOAD MUST BE BELOW THE MAXIMUM VALUE INDICATED.

MAX DIESEL CAUTION:

LOAD LOAD FOR STARTING 310 AMPS RHR SERVICE WATER PUMP CORE SPRAY PUMP RHR PUMP PSW PUMP 310 AMPS 340 AMPS 390 AMPS 1.1.4 Confirm Diesel Generator AMP reading is BELOW the maximum value in the above CAUTION, PRIOR to closing any listed 4160V breaker.

1.1.5 IF a standard DHP Air Circuit breaker is installed in this cubicle, Manually close the 4 KV pump breaker by pushing up on the plunger marked "LIFT TO CLOSE".

OR IF a new DHP-VR vacuum breaker is installed in this cubicle, DEPRESS the button marked "Push to Close".

1.1.6 RE-CLOSE the 30A control breaker in the associated cubicle.

1.1.6.1 Go to step 1.2, IF the 4160 VAC breaker opens.

1.1.7 CLOSE the breaker cubicle door.

MGR-0009 Ver. 4 Pg 15 of 48 Version No:

5.14 Att. Pg.

5 of 7

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I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER Pg 16 of 48 Version No:

5.14 Att. Pg.

6 of 7 STEP 1.2 BYPASSES ALL TRIPS AND PROTECTIVE FUNCTIONS OF THE CAUTION BREAKER BY ALLOWING THE CONTROL CIRCUIT TO REMAIN DE-ENERGIZED AFTER THE BREAKER IS CLOSED.

1.2 IF the breaker has tripped AND must be reclosed regardless of possible equipment damage, THEN close the 4160 VAC breaker using the sequence of steps 1.1.2 through 1.1.4.

1.3 Trip 4160 VAC breaker to de-energize a load as follows:

1.3.1 OPEN breaker cubicle door.

1.3.2 IF a standard DHP Air circuit breaker is installed in this cubicle, push up on plunger marked "LIFT TO TRIP".

OR IF a new DHP-VR Vacuum breaker is installed in this cubicle, DEPRESS the button marked "Push to Trip".

MGR-0009 Ver. 4

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SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER Pg 16 of 48 Version No:

5.14 Att. Pg.

6 of 7 STEP 1.2 BYPASSES ALL TRIPS AND PROTECTIVE FUNCTIONS OF THE CAUTION BREAKER BY ALLOWING THE CONTROL CIRCUIT TO REMAIN DE-ENERGIZED AFTER THE BREAKER IS CLOSED.

1.2 1.3 1.3.1 1.3.2 IF the breaker has tripped AND must be reclosed regardless of possible equipment damage, TH EN close the 4160 VAC breaker using the sequence of steps 1.1.2 through 1.1.4.

Trip 4160 VAC breaker to de-energize a load as follows:

OPEN breaker cubicle door.

IF a standard DHP Air circuit breaker is installed in this cubicle, push up on plunger marked "LIFT TO TRIP".

OR IF a new DHP-VR Vacuum breaker is installed in this cubicle, DEPRESS the button marked "Push to Trip".

MGR-0009 Ver. 4

(

SNC PLANT E. I. HATCH I Pg 17 of 48 DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:

5.14 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER 2.0 IF the breaker is a 600 VAC General Electric breaker, THEN take the following applicable action:

2.1 OPEN the front breaker cabinet door. Note the breaker type indicated on metal plate at left.

2.2 Energize a 600 VAC load by closing contacts in the breaker as follows:

2.2.1 For AK25 breakers (load breakers, no Spring Charge Indicator):

CAUTION 2.2.1.1 2.2.1.2 2.2.1.3 2.2.2 2.2.2.1 DUE TO PERSONNEL SAFETY CONSIDERATIONS, THE AK25 BREAKERS WILL BE CLOSED MANUALLY ONLY WHEN THE FOLLOWING CONDITIONS ARE MET:

(1) AN EXTREME EMERGENCY EXISTS.

(2) THE APPROVAL OF THE SOS HAS BEEN OBTAINED.

(3) IF TIME PERMITS, THE CIRCUIT DOWNSTREAM OF THE BREAKER HAS BEEN MEGGERED TO ENSURE NO FAULT EXISTS, OR IF TIME DOES NOT PERMIT MEGGERING, THERE IS NO REASON TO SUSPECT THAT A FAULT EXISTS.

(4) THE OPERATOR MUST MEET THE REQUIREMENTS OF NMP-SH-003, ELECTRICAL WORK PRACTICES..

Confirm the above conditions have been met.

Place the two small hooks of the maintenance handle into the two slots located in the lower portion of the front panel.

Push the long end of the handle downward, forcing the shorter end of the handle upward against the breaker closing solenoid, thus closing the breaker's contacts.

For AK50 breakers (main feeder breakers, with Spring Charge Indicator):

Place the ratchet type maintenance handle onto the shaft that protrudes from the gear reduction unit on the right side of the breaker.

Att. Pg.

7 of 7 2.2.2.2 Operate the handle UNTIL the Spring Charge Indicator reads "CHARGED". __ _

2.2.2.3 Continue to operate handle UNTIL the closing springs discharge AND close the breaker's contacts.

2.3 De-energize a 600 VAC load, by pushing the TRIP pushbutton on the front of the breaker cabinet.

MGR-0009 Ver. 4

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SNC PLANT E. I. HATCH I Pg 17 of 48 DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:

5.14 ATTACHMENT _1 TITLE:

BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER 2.0 IF the breaker is a 600 VAC General Electric breaker, THEN take the following applicable action:

2.1 OPEN the front breaker cabinet door. Note the breaker type indicated on metal plate at left.

2.2 Energize a 600 VAC load by closing contacts in the breaker as follows:

2.2.1 For AK25 breakers (load breakers, no Spring Charge Indicator):

CAUTION 2.2.1.1 2.2.1.2 2.2.1.3 2.2.2 2.2.2.1 DUE TO PERSONNEL SAFETY CONSIDERATIONS, THE AK25 BREAKERS WILL BE CLOSED MANUALLY ONLY WHEN THE FOLLOWING CONDITIONS ARE MET:

(1) AN EXTREME EMERGENCY EXISTS.

(2) THE APPROVAL OF THE SOS HAS BEEN OBTAINED.

(3) IF TIME PERMITS, THE CIRCUIT DOWNSTREAM OF THE BREAKER HAS BEEN MEGGERED TO ENSURE NO FAULT EXISTS, OR IF TIME DOES NOT PERMIT MEGGERING, THERE IS NO REASON TO SUSPECT THAT A FAULT EXISTS.

(4) THE OPERATOR MUST MEET THE REQUIREMENTS OF NMP-SH-003, ELECTRICAL WORK PRACTICES..

Confirm the above conditions have been met.

Place the two small hooks of the maintenance handle into the two slots located in the lower portion of the front panel.

Push the long end of the handle downward, forcing the shorter end of the handle upward against the breaker closing solenoid, thus closing the breaker's contacts.

For AK50 breakers (main feeder breakers, with Spring Charge Indicator):

Place the ratchet type maintenance handle onto the shaft that protrudes from the gear reduction unit on the right side of the breaker.

Att. Pg.

7 of 7 2.2.2.2 Operate the handle UNTIL the Spring Charge Indicator reads "CHARGED". __ _

2.2.2.3 Continue to operate handle UNTIL the closing springs discharge AND close the breaker's contacts.

2.3 De-energize a 600 VAC load, by pushing the TRIP pushbutton on the front of the breaker cabinet.

MGR-0009 Ver. 4

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SNC PLANT E. I. HATCH I Pg 47 of 48 DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:

5.6 ATTACHMENT J!..

TITLE:

PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM Placing the Remote Shutdown Panel Transfer Switches for PSW in Emergency has the following effects on PSW system operation:

1.

Auto start of the 1 B PSW pump on low system header pressure (85 PSIG) is

2.

defeated.

The subsequent auto start of the 1 B PSW pump after tripping on receipt of a LOSP OR LOCA signal is defeated.

3.

All PSW trips are still valid:

CAUTION 3.1 Overcurrentlground fault 3.2 LOSP Load Shed 3.3 LOCA Load Shed WHEN DG is carrying respective bus following a LOSP AND THEN a LOCA is received.

DIESEL GENERATOR LOADING MUST NOT EXCEED THE FOLLOWING RATINGS FOLLOWING A LOSS OF OFFSITE POWER TO AVOID DIESEL OVERLOAD. AMPERAGE INDICATIONS ARE LOCATED ON PANEL R43-P001 IN EACH DIESEL GENERATOR ROOM.

RATINGS {AMPERES}

DIESEL CONTINUOUS 7 DAY {168 HOUR}*

1A 430 490 18 430 490 1C 430 490 5.14 1 of 2

  • THE HIGHER 7 DAY RATING IS BASED UPON A YEARLY ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE CONTINUOUS RATING. A TOTAL OF 168 HOURS PER YEAR WITH A LOAD OF 430 TO 490 AMPERES IS ALLOWED.

MGR-0009 Ver. 4

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SNC PLANT E. I. HATCH I Pg 47 of 48 DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:

5.6 ATTACHMENT Ji.

TITLE:

PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM Placing the Remote Shutdown Panel Transfer Switches for PSW in Emergency has the following effects on PSW system operation:

1.

Auto start of the 1 B PSW pump on low system header pressure (85 PSIG) is

2.

defeated.

The subsequent auto start of the 1 B PSW pump after tripping on receipt of a LOSP OR LOCA signal is defeated.

3.

All PSW trips are still valid:

CAUTION 3.1 Overcurrentlground fault 3.2 LOSP Load Shed 3.3 LOCA Load Shed WHEN DG is carrying respective bus following a LOSP AND THEN a LOCA is received.

DIESEL GENERATOR LOADING MUST NOT EXCEED THE FOLLOWING RATINGS FOLLOWING A LOSS OF OFFSITE POWER TO AVOID DIESEL OVERLOAD. AMPERAGE INDICATIONS ARE LOCATED ON PANEL R43-P001 IN EACH DIESEL GENERATOR ROOM.

DIESEL 1A 1B 1C RATINGS (AMPERES)

CONTINUOUS 430 430 430 7 DAY (168 HOUR)*

490 490 490 5.14 1 of 2

  • THE HIGHER 7 DAY RATING IS BASED UPON A YEARLY ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE CONTINUOUS RATING. A TOTAL OF 168 HOURS PER YEAR WITH A LOAD OF 430 TO 490 AMPERES IS ALLOWED.

MGR-0009 Ver. 4

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SNC PLANT E. I. HATCH I Pg 48 of 48 DOCUMENT TITLE:

I DOCUMENT NUMBER:

Version No:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT JL TITLE:

PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM

  • BEFORE STARTING A PSW PUMP ON THE DIESEL GENERATOR, DIESEL LOAD MUST BE BELOW 390 AMPS. REFER TO 34S0-R43-001-1 TO REDUCE DIESEL LOADS IF REQUIRED.

CAUTIONS

  • THE AMPERE VALUES ARE BASED UPON AN ASSUMED TOTAL POWER FACTOR OF 0.91. LOADING OF THE DIESEL GENERATORS ABOVE 430 AMPERES ON THE LOCAL INDICATORS MUST BE ACCOMPANIED BY CLOSE MONITORING OF OTHER DIESEL PARAMETERS FOR SIGNS OF OVERLOADING.

1.0 Start one PSW pump in a division as follows:

1.1 To start the 1 P41-C001 B pump:

1.1.1 In 4160V switchgear room 1 G, at panel 1 H21-P17S, place 1 C82-S2B, transfer switch, to the EMER position.

1.1.2 START the pump by placing the 1P41-C001B control switch to START.

1.2 To start pump 1P41-C001A, 1P41-C001C, OR 1P41-C001D, manually close the applicable breaker per Attachment 1.

PSWPUMP 1 P41-C001A 1P41-C001C 1P41-C001D BREAKER LOCATION 1 R22-S005 Fr. 3 1 R22-S006 Fr. 4 1 R22-S006 Fr. 2 CAUTION IF RIVER LEVEL IS GREATER THAN 61.2 FEET, LIMIT EACH PSW PUMP FLOW TO 8S00 GPM.

IF RIVER LEVEL IS LESS THAN 61.2 FEET, EACH PSW PUMP FLOW MUST BE LESS THAN 7000 GPM.

2.0 THROITLE 1P41-F302B (1P41-F302A, 1P41-F302C, 1P41-F302D), PSW pump 1 B (1A, 1 C, 1 D) Discharge valve, to establish a flow greater than 3000 GPM as indicated on 1 P41-NS04 (NS03, NSOS, NS06). Discharge Flow Indicator, (intake structure valve pit).

3.0 Start additional PSW pumps as required and as Diesel Generator capacity permits.

MGR-0009 Ver. 4 S.6 S.14 20f2

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SNC PLANT E. I. HATCH I Pg 48 of 48 DOCUMENT TITLE:

I DOCUMENT NUMBER:

Version No:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT JL TITLE:

PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM

  • BEFORE STARTING A PSW PUMP ON THE DIESEL GENERATOR, DIESEL LOAD MUST BE BELOW 390 AMPS. REFER TO 34S0-R43-001-1 TO REDUCE DIESEL LOADS IF REQUIRED.

CAUTIONS

  • THE AMPERE VALUES ARE BASED UPON AN ASSUMED TOTAL POWER FACTOR OF 0.91. LOADING OF THE DIESEL GENERATORS ABOVE 430 AMPERES ON THE LOCAL INDICATORS MUST BE ACCOMPANIED BY CLOSE MONITORING OF OTHER DIESEL PARAMETERS FOR SIGNS OF OVERLOADING.

1.0 Start one PSW pump in a division as follows:

1.1 To start the 1 P41-C001 B pump:

1.1.1 In 4160V switchgear room 1 G, at panel 1 H21-P17S, place 1 C82-S2B, transfer switch, to the EMER position.

1.1.2 START the pump by placing the 1P41-C001B control switch to START.

1.2 To start pump 1P41-C001A, 1P41-C001C, OR 1P41-C001D, manually close the applicable breaker per Attachment 1.

PSWPUMP 1P41-C001A 1P41-C001C 1P41-C001 D BREAKER LOCATION 1 R22-S00S Fr. 3 1 R22-S006 Fr. 4 1 R22-S006 Fr. 2 CAUTION IF RIVER LEVEL IS GREATER THAN 61.2 FEET, LIMIT EACH PSW PUMP FLOW TO 8S00 GPM.

IF RIVER LEVEL IS LESS THAN 61.2 FEET, EACH PSW PUMP FLOW MUST BE LESS THAN 7000 GPM.

2.0 THROTTLE 1P41-F302B (1P41-F302A, 1P41-F302C, 1P41-F302D), PSW pump 1B (1A, 1C, 1D) Discharge valve, to establish a flow greater than 3000 GPM as indicated on 1 P41-NS04 (NS03, NSOS, NS06), Discharge Flow Indicator, (intake structure valve pit).

3.0 Start additional PSW pumps as required and as Diesel Generator capacity permits.

MGR-0009 Ver. 4 S.6 S.14 2 of 2

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F.N.FAGAN FI Southern E. I. Hatch AL uclear uclear Plant Operations Training JPM II

      • ,REcB~MMENnEJ:)By:i.;

NR C.M.EDMUND 1011212009 Energy to Serve Your World SM

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TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM PLANT 3 - All STARTUP THE REACTOR PROTECTION SYSTEM (RPS) 120 VAC SYSTEM AUTHOR MEDIA NUMBER TIME F.N.FAGAN 2009-302 Plant 3 l3.0 Minutes RECOMMENDED BY APPROVED BY DATE NR C.M.EDMUND 10/12/2009 Energy to Serve Your World sM

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SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:

OPERATIONS TRAINING 10/12/09 Revised for use on 2009-302 Exam Page 1 of 2 Media Number:

2009-302 Plant 3 FNF CME

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SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:

OPERATIONS TRAINING Rev. No.

Date Reason for Revision 10112/09 Revised for use on 2009-302 Exam Page 1 of 2 Media Number:

2009-302 Plant 3 Author's Supv's Initials Initials FNF CME

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2009-302 Plant 3 Page 1 of 11 UNIT 1 (X)

UNIT 2 0

STARTUP THE REACTOR PROTECTION SYSTEM (RPS) 120 V AC SYSTEM

~MNUMJ.J~!l:.**

LR-JP-lO.01-19 The task shall be completed when the Reactor Protection System 120 VAC System, RPS MG Set, has been started per 34S0-C71-00 1.

OlO.OOl

      • o8Jic'J71YJENl.JMjJ~R.!. 010.00 1.B PLANT HATCH JTA IMPORTANCE RATING:

RO 3.00 SRO 3.31 KIA CATALOG NUMBER: 212000A1.01 KIA CATALOG JTA IMPORTANCE RATING:

RO 2.8 SRO 2.9 OPERATOR APPLICABILITY:

RO (current version)

APPROXIMATE COMPLETION TIME:

13.0 Minutes SIMULATOR SETUP:

N/A

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2009-302 Plant 3 Page 1 of 11 UNIT 1 (X)

UNIT 2 0

TASK TITLE:

STARTUP THE REACTOR PROTECTION SYSTEM (RPS) 120 V AC SYSTEM JPMNUMBER:

TASK STANDARD:

TASK NUMBER:

LR-JP-lO.01-19 The task shall be completed when the Reactor Protection System 120 VAC System, RPS MG Set, has been started per 34S0-C71-001.

OlO.OOl OBJECTIVE NUMBER: OlO.OOl.B PLANT HATCH JTA IMPORTANCE RATING:

RO 3.00 SRO 3.31 KIA CATALOG NUMBER: 212000Al.01 KIA CATALOG JTA IMPORTANCE RATING:

RO 2.8 SRO 2.9 OPERATOR APPLICABILITY:

RO I GENERAL

REFERENCES:

Unit 1 34S0-C71-001-1 (current version)

I REQIDRED MATERIALS:

Unit 1 34S0-C71-001-1 (current version)

APPROXIMATE COMPLETION TIME:

13.0 Minutes SIMULATOR SETUP:

N/A

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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The Reactor Protection System Bus A is de-energized and no electrical faults currently exist.

2.

The power source select switch on panellHII-P61O is in the Normal position.

3.

34AB-C71-002-1 is in progress.

INITIATING CUES:

Energize the "IA" RPS Bus by starting the 120 V AC RPS MG Set "IA" per 34S0-C71-00l-1.

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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The Reactor Protection System Bus A is de-energized and no electrical faults currently exist.

2.

The power source select switch on panellHII-P61O is in the Normal position.

3.

34AB-C71-002-1 is in progress.

INITIATING CUES:

Energize the "IA" RPS Bus by starting the 120 VAC RPS MG Set "IA" per 34S0-C71-00 1-1.

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1. Operator obtains the procedure needed to perform task.
2. Confirm Open RPS Equipment Protection Circuit Breaker 52-3C.
3. Confirm Open RPS Equipment Protection Circuit Breaker 52-3A.
4. Confirm fuses are installed in panel 1C71-P003A Operator has obtains procedure 34S0-C71-00 1-1.

In the RPS MG Set Room, the operator VERIFIES 52-3C in panel lC71-P003C is in the OFF position.

In the RPS MG Set Room, the operator VERIFIES 52-3A in panellC71-P003A is in the OFF position.

In panellC71-P003A, the operator CONFIRMS fuses C71AF474, and C71AF475 are installed.

2009-302 Plant 3 Page 3 of 12

  • S~"I!IIJN$A,'J'*.**......

(CQMMEN'l'S START TIME: ___

SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT: When operator indicates he would check the fuses in PanellC71-P003A(C), provide the operator with the associated attached pictures of the panel.

5. Confirm the green Motor Off light is illuminated.

At local RPS MG Set lC71-S001A Control Panel, operator VERIFIES the green MOTOR OFF light is ll.-LUMINATED.

At local RPS MG Set lC71-S001A Control Panel, MOTOR ON pushbutton is DEPRESSED and HELD until generator output voltage is greater than 118 VAC.

SAT/UNSAT SAT/UNSAT PROMPT: IF operator does NOT indicate that he held the pushbutton and asks for voltage, then inform the operator voltage is zero.

PROMPT: IF operator DOES indicate that he held the pushbutton and asks for voltage, then inform the operator voltage is 120 VAC.

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PERFO~NCESTEP

1. Operator obtains the procedure needed to perform task.
2. Confirm Open RPS Equipment Protection Circuit Breaker 52-3C.
3. Confirm Open RPS Equipment Protection Circuit Breaker 52-3A.
4. Confirm fuses are installed in panel IC71-P003A STANDARD Operator has obtains procedure 34S0-C71-00 1-1.

In the RPS MG Set Room, the operator VERIFIES 52-3C in panellC71-P003C is in the OFF position.

In the RPS MG Set Room, the operator VERIFIES 52-3A in panel IC71-P003A is in the OFF position.

In panel1C71-P003A, the operator CONFIRMS fuses C71AF474, and C7lAF475 are installed.

2009-302 Plant 3 Page 3 of 12 SATIUNSAT (COMMENTS START TIME: ___ _

SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT: When operator indicates he would check the fuses in PanelIC71-P003A(C), provide the operator with the associated attached pictures of the panel.

5. Confirm the green Motor Off light is At local RPS MG Set SAT I UNSAT illuminated.

IC71-S001A Control Panel, operator VERIFIES the green MOTOR OFF light is ILLUMINATED.

    • 6. Depress and Hold the Motor On At local RPS MG Set SAT/UNSAT pushbutton until generator output 1 C71-S00 1 A Control Panel, voltage is greater than 118 VAC.

MOTOR ON pushbutton is DEPRESSED and HELD until generator output voltage is greater than 118 VAC.

PROMPT: IF operator does NOT indicate that he held the pushbutton and asks for voltage, then inform the operator voltage is zero.

PROMPT: IF operator DOES indicate that he held the pushbutton and asks for voltage, then inform the

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operator voltage is 120 VAC.

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2009-302 Plant 3 Page 4 of 12

'... ***.;PElfi'ij~~~S'fEP.

7. Confirm output voltage is between At local RPS MG Set SAT/UNSAT 118 and 122 VAC.

IC71-S001A Control Panel, PROMPT:

NOTE:

PROMPT:

PROMPT:

operator VERIFIES voltage is between 118 and 122 VAC.

WHEN the operator addresses output voltage, INDICATE for the operator that output voltage is 120 V AC.

At panel1C71-P003A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER 52-3A is in the ON position.

At panel1C71-P003C, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER 52-3C is in the ON position.

SAT/UNSAT SAT/UNSAT If the operator attempts to close breaker 52-3C prior to closing the protection circuit breaker 52-3A, then breaker 52-3C will not stay closed.

WHEN the operator addresses the GEN A white light on panel 1H11-P61O, as the Control Room operator, INFORM the operator that the light is illuminated.

IF the operator addresses Subsection 7.1.3 (7.3.3), as the Shift Supervisor, INFORM the operator that another operator is performing the appropriate subsection.

END TIME: ___ _

NOTE:

The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

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PERFO~CESTEP

7. Confirm output voltage is between 118 and 122 VAC.

STANDARD At local RPS MG Set 1C71-S001A Control Panel, operator VERIFIES voltage is between 118 and 122 VAC.

2009-302 Plant 3 Page 4 of 12 SATIUNSAT (COMMENTS SAT/UNSAT PROMPT:

WHEN the operator addresses output voltage, INDICATE for the operator that output voltage is 120 VAC.

    • 8. Close RPS Equipment Protection At panel1C71-P003A, RPS SAT/UNSAT Circuit Breaker 52-3A.

EQUIPMENT PROTECTION CIRCUIT BREAKER 52-3A is in the ON position.

    • 9. CloseRPS Equipment Protection At panel 1 C71-P003C, RPS SAT/UNSAT Circuit Breaker 52-3C.

EQUIPMENT PROTECTION CIRCUIT BREAKER 52-3C is in the ON position.

NOTE:

If the operator attempts to close breaker 52-3C prior to closing the protection circuit breaker 52-3A, then breaker 52-3C will not stay closed.

PROMPT:

PROMPT:

WHEN the operator addresses the GEN A white light on panel 1H11-P61O, as the Control Room operator, INFORM the operator that the light is illuminated.

IF the operator addresses Subsection 7.1.3 (7.3.3), as the Shift Supervisor, INFORM the operator that another operator is performing the appropriate subsection.

END TIME: ___ _

NOTE:

The terminating cue shall be given to the operator when:

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

PanellC71-P003A 1

PanellC71-P003A

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1

Panel 1 C71-P003C 2

Panel 1 C71-P003C

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2

Panel 1 C71-P003B 3

PanellC71-P003B

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3

PanellC71-P003D 4

PanellC71-P003D

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4

Pane12C71-P003A

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5 Pane12C71-P003A

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5

Panel 2C71-P003C

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6 Panel 2C71-P003C

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6

Pane12C71-P003B

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7 Pane12C71-P003B

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7

Pane12C71-P003D c

8 Pane12C71-P003D I.

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8

PanellC71-P003A

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1 PanellC71-P003A

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1

Panel 1 C71-P003C

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2 Panel 1 C71-P003C

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2

PanellC71-P003B

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3 PanellC71-P003B

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3

Panel 1 C71-P003D

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4 PanellC71-P003D

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4

Pane12C71-P003A

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Pane12C71-P003A

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Panel 2C71-P003C

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6 Panel 2C71-P003C

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6

Pane12C71-P003B

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7 Pane12C71-P003B

(

(

7

Pane12C71-P003D

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8 Pane12C71-P003D

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8

. (

UNITt READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The Reactor Protection System Bus A is de-energized and no electrical faults currently exist.

2.

The power source select switch on panellHII-P610 is in the Normal position.

3.

34AB-C7I-002-1 is in progress.

INITIATING CUES:

Energize the "IA" RPS Bus by starting the 120 VAC RPS MG Set "IA" per 34S0-C71-00 1-1.

(

UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

The Reactor Protection System Bus A is de-energized and no electrical faults currently exist.

2.

The power source select switch on panellHII-P610 is in the Normal position.

3.

34AB-C71-002-1 is in progress.

INITIATING CUES:

Energize the "IA" RPS Bus by starting the 120 VAC RPS MG Set "IA" per 34S0-C71-00 1-1.

SOUTHERN NUCLEAR DOCUMENT TYPE:

PAGE PLANT E. I. HATCH SYSTEM OPERATING PROCEDURE 1 OF 50 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

120 VAC RPS SUPPLY SYSTEM 34S0-C71-001-1 8.12 EXPIRATION APPROVALS:

EFFECTIVE DATE:

DEPARTMENT MGR G. L. Johnson DATE 07-13-98 DATE:

N/A SSM / PM N/A DATE N/A 5-4-09 1.0 OBJECTIVE This procedure provides the instructions for startup, shutdown and power source transfer of the 120 VAC RPS power supply system.

TABLE OF CONTENTS Section 2.0 APPLICABILITY.................................................................................................................. 2

3.0 REFERENCES

................................................................................................................... 2 4.0 REQUIREMENTS................................................................................................................ 4 5.0 PRECAUTIONS/LIMITATION............................................................................................. 4 6.0 PREREQUISITES............................................................................................................... 5 7.0 PROCEDURE..................................................................................................................... 6 7.1 SYSTEM STARTUP...................................................................................................... 6 7.1.1 MOTOR GENERATOR SET STARTUP................................................................ 6 7.1.1.1 Motor Generator Set 1 A Startup..................................................................... 6 7.1.1.2 Motor Generator Set 1 B Startup..................................................................... 8 7.1.2 ALTERNATE POWER SOURCE STARTUP........................................................ 10 7.1.3 SUPPLYING RPS BUS FROM MOTOR GENERATOR SET.............................. 11 7.1.3.1 Supplying RPS Bus A From Motor Generator Set 1 A.................................... 11 7.1.3.2 Supplying RPS Bus B From Motor Generator Set 1 B.................................... 13 7.2 SYSTEM SHUTDOWN............................................................................................... 15 7.2.1 MOTOR GENERATOR SET SHUTDOWN......................................................... 15 7.2.1.1 Motor Generator Set 1 A Sh utdown............................................................... 15 7.2.1.2 Motor Generator Set 1 B Shutdown............................................................... 16 7.3 INFREQUENT OPERATIONS..................................................................................... 17 7.3.1 SUPPLYING RPS BUS FROM ALTERNATE POWER SOURCE........................ 17 7.3.. 1.1 Supplying RPS Bus A From Alternate Power Source.................................... 17 7.3.1.2 Supplying RPS Bus B From Alternate Power Source.................................... 19 7.3.2 TRANSFER RPS BUS FROM MG SET TO ALTERNATE POWER..................... 21 7.3.2.1 Transfer RPS Bus A From MG Set 1A To Alternate Power........................... 21 7.3.2.2 Transfer RPS Bus B From MG Set 1 B To Alternate Power........................... 26 7.3.3 TRANSFER RPS BUS FROM ALTERNATE POWER TO MG SET..................... 31 7.3.3.1 Transfer RPS Bus A From Alternate Power To MG Set 1A.... :...................... 31 7.3.3.2 Transfer RPS Bus B From Alternate Power To MG Set 1 B........................... 36 7.3.4 SWAPPING RPS THROWOVER SWITCH 1R26-M021....................................... 40 MGR-0002 Ver. 8.1

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SOUTHERN NUCLEAR DOCUMENT TYPE:

PAGE PLANT E. I. HATCH SYSTEM OPERATING PROCEDURE 1 OF 50 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

120 VAC RPS SUPPLY SYSTEM 34S0-C71-001-1 8.12 EXPIRATION APPROVALS:

EFFECTIVE DATE:

DEPARTMENT MGR G. L. Johnson DATE 07-13-98 DATE:

N/A SSM / PM N/A DATE N/A 5-4-09 1.0 OBJECTIVE This procedure provides the instructions for startup, shutdown and power source transfer of the 120 VAC RPS power supply system.

TABLE OF CONTENTS Section 2.0 APPLICABILITY.................................................................................................................. 2

3.0 REFERENCES

................................................................................................................... 2 4.0 REQUIREMENTS............................................................................................................... 4 5.0 PRECAUTIONS/LIMITATION............................................................................................. 4 6.0 PREREQUISITES............................................................................................................... 5 7.0 PROCEDURE..................................................................................................................... 6 7.1 SYSTEM STARTUP...................................................................................................... 6 7.1.1 MOTOR GENERATOR SET STARTUP................................................................ 6 7.1.1.1 Motor Generator Set 1 A Startup..................................................................... 6 7.1.1.2 Motor Generator Set 1 B Startup..................................................................... 8 7.1.2 ALTERNATE POWER SOURCE STARTUP........................................................ 10 7.1.3 SUPPLYING RPS BUS FROM MOTOR GENERATOR SET.............................. 11 7.1.3.1 Supplying RPS Bus A From Motor Generator Set 1A.................................... 11 7.1.3.2 Supplying RPS Bus B From Motor Generator Set 1 B.................................... 13 7.2 SYSTEM SHUTDOWN............................................................................................... 15 7.2.1 MOTOR GENERATOR SET SHUTDOWN......................................................... 15 7.2.1.1 Motor Generator Set 1 A Sh utdown............................................................... 15 7.2.1.2 Motor Generator Set 1 B Sh utdown............................................................... 16 7.3 INFREQUENT OPERATIONS..................................................................................... 17 7.3.1 SUPPLYING RPS BUS FROM ALTERNATE POWER SOURCE........................ 17 7.3.. 1.1 Supplying RPS Bus A From Alternate Power Source.................................... 17 7.3.1.2 Supplying RPS Bus B From Alternate Power Source.................................... 19 7.3.2 TRANSFER RPS BUS FROM MG SET TO ALTERNATE POWER..................... 21 7.3.2.1 Transfer RPS Bus A From MG Set 1A To Alternate Power........................... 21 7.3.2.2 Transfer RPS Bus B From MG Set 1 B To Alternate Power........................... 26 7.3.3 TRANSFER RPS BUS FROM ALTERNATE POWER TO MG SET..................... 31 7.3.3.1 Transfer RPS Bus A From Alternate Power To MG Set 1A.... :...................... 31 7.3.3.2 Transfer RPS Bus B From Alternate Power To MG Set 1 B........................... 36 7.3.4 SWAPPING RPS THROWOVER SWITCH 1 R26-M021....................................... 40 MGR-0002 Ver. 8.1

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 2 OF 50 DOCUMENT TITLE:

DOCUMENT NUMBER:

34S0-C71-001-1 VERSION NO:

8.12 120 VAC RPS SUPPLY SYSTEM Attachments 1

RPS ELECTRICAL LINEUP.............................................................................................. 42 2

BREAKER REALIGNMENT.............................................................................................. 45 3

VALVE REALIGNMENT.................................................................................................... 48 4

RPS MG SET CONTROL PANEL BULB REPLACEMENT PLACARD.............................. 50 2.0 APPLICABILITY This procedure applies to 1C71-S001A & B, Unit 1 G.E. supplied high inertia motor-generator sets, AND the associated distribution equipment.

3.0 REFERENCES

3.1 GEK-30486, Motor Generator Package Set (Found in Inst. Component Manual X #S30697) 3.2 H-17155, Reactor Protection System MG Set Control Elementary H-17197 H-17499 3.3 H-17783, Reactor Protection System Elementary thru H-17798 3.4 H-13369, 120/208V Essential AC System Single Line Diagram 3.5 H-13361, 600V Bus 1 C & 1 D Single Line Diagram 3.6 H-17806, Nuclear Steam Supply Shutoff System Elementary thru H-17819 3.7 H-17801, Primary Containment Isolation System Elementary thru H-17805 3.8 H-17096, Nitrogen Inerting & Makeup System Elementary 3.9 H-16000, Nitrogen Inerting System P&ID 3.10 H-17076 thru H-17078, Off Gas System Elementary 3.11 H-11613, Off Gas System P&ID 3.12 H-13377, Turbine Auxiliary Equipment Elementary 3.13 H-17081 thru H-17083, Primary Containment Purge And Inerting System Elementary 3.14 H-16024, Primary Containment Purge and Inerting P&ID 3.15 H-17052 thru H-17056, Reactor Building Ventilation System Elementary 3.16 H-16005, Reactor Building Ventilation System P&ID MGR-0001 Ver. 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 2 OF 50 DOCUMENT TITLE:

DOCUMENT NUMBER:

34S0-C71-001-1 VERSION NO:

8.12 120 VAC RPS SUPPLY SYSTEM Attachments 1

RPS ELECTRICAL LINEUP.............................................................................................. 42 2

BREAKER REALIGNMENT.............................................................................................. 45 3

VALVE REALIGNMENT.................................................................................................... 48 4

RPS MG SET CONTROL PANEL BULB REPLACEMENT PLACARD.............................. 50 2.0 APPLICABILITY 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 3.10 3.11 3.12 3.13 3.14 3.15 This procedure applies to 1 C71-S001 A & B, Unit 1 G.E. supplied high inertia motor-generator sets, AND the associated distribution equipment.

REFERENCES GEK-30486, Motor Generator Package Set (Found in Inst. Component Manual X #S30697)

H-17155, Reactor Protection System MG Set Control Elementary H-17197 H-17499 H-17783, Reactor Protection System Elementary thru H-17798 H-13369, 120/208V Essential AC System Single Line Diagram H-13361, 600V Bus 1C & 1D Single Line Diagram H-17806, Nuclear Steam Supply Shutoff System Elementary thru H-17819 H-17801, Primary Containment Isolation System Elementary thru H-17805 H-17096, Nitrogen Inerting & Makeup System Elementary H-16000, Nitrogen Inerting System P&ID H-17076 thru H-17078, Off Gas System Elementary H-11613, Off Gas System P&I D H-13377, Turbine Auxiliary Equipment Elementary H-17081 thru H-17083, Primary Containment Purge And Inerting System Elementary H-16024, Primary Containment Purge and Inerting P&ID H-17052 thru H-17056, Reactor Building Ventilation System Elementary 3.16 H-16005, Reactor Building Ventilation System P&ID MGR-0001 Ver. 3

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SOUTHERN NUCLEAR PLANT E, I. HATCH DOCUMENT TITLE:

120 VAC RPS SUPPLY SYSTEM DOCUMENT NUMBER:

34S0-C71-001-1 3.17 H-17104 and H-17105, Standby Gas Treatment System Elementary 3.18 H-17068 thru H-17073, Control Building HVAC Elementary 3.19 H-16042, Control Building HVAC P&ID 3.20 H-16020, Standby Gas Treatment System Process Flow and P&ID 3.21 H-17138 thru H-17140, Oxygen, Hydrogen Analyzer System Elementary 3.22 H-16276 thru H-16280, Oxygen, Hydrogen Analyzer System P&ID 3.23 H-17176 and H-17177, Reactor Water Clean-up System Elementary 3.24 H-16188, Reactor Water Clean-up System P&ID 3.25 H-16062, Nuclear Boiler System P&ID 3.26 H-17756 thru H-17757 and H-17800, TIP Calibration System Elementary 3.27 H-17760 thru H-17782, RHR System Elementary 3.28 H-16329, RHR System P&ID H-16330 3.29 H-19501 thru H-19543, Radwaste System Elementary 3.30 H-16066 Reactor Recirc. System P&ID 3.31 H-19801 thru H-19835, ATTS Elementary 3.32 Unit 1 FSAR, Chapter 7, Section 7.2.3.2 PAGE 3 OF 50 VERSION NO:

8.12 3.33 H-19551 thru H-19566 and H-19578, H-19584, H-19596. Process Radiation Monitoring System Elementary 3.34 57CP-C71-001-1, RPS MG Set Monitors Calibration.

3.35 Letter LR-REG-008-0689 3.36 Letter HL-1030 MGR-0001 Ver. 3 SOUTHERN NUCLEAR PLANT E, I. HATCH DOCUMENT TITLE:

120 VAC RPS SUPPLY SYSTEM DOCUMENT NUMBER:

34S0-C71-001-1 3.17 H-17104 and H-171 05, Standby Gas Treatment System Elementary 3.18 H-17068 thru H-17073, Control Building HVAC Elementary 3.19 H-16042, Control Building HVAC P&ID 3.20 H-16020, Standby Gas Treatment System Process Flow and P&ID 3.21 H-17138 thru H-17140, Oxygen, Hydrogen Analyzer System Elementary 3.22 H-16276 thru H-16280, Oxygen, Hydrogen Analyzer System P&ID 3.23 H-17176 and H-17177, Reactor Water Clean-up System Elementary 3.24 H-16188, Reactor Water Clean-up System P&ID 3.25 H-16062, Nuclear Boiler System P&ID 3.26 H-17756 thru H-17757 and H-17800, TIP Calibration System Elementary 3.27 H-17760 thru H-17782, RHR System Elementary 3.28 H-16329, RHR System P&ID H-16330 3.29 H-19501 thru H-19543, Radwaste System Elementary 3.30 H-16066 Reactor Recirc. System P&ID 3.31 H-19801 thru H-19835, ATTS Elementary 3.32 Unit 1 FSAR, Chapter 7, Section 7.2.3.2 PAGE 3 OF 50 VERSION NO:

8.12 3.33 H-19551 thru H-19566 and H-19578, H-19584, H-19596. Process Radiation Monitoring System Elementary 3.34 57CP-C71-001-1, RPS MG Set Monitors Calibration.

3.35 Letter LR-REG-008-0689 3.36 Letter HL-1030 MGR-0001 Ver. 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 40F50 DOCUMENT TITLE:

DOCUMENT NUMBER:

34S0-C71-00 1-1 VERSION NO:

8.12 120 VAC RPS SUPPLY SYSTEM 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS The number and qualification level of personnel performing the sections in this procedure will be determined by the Shift Supervisor.

4.2 MATERIAL AND EQUIPMENT Fuse pullers 4.3 SPECIAL REQUIREMENTS Independent verification, as described in 10AC-MGR-019-0, Procedure Use and Adherence, will be required during performance of Attachments 1 and 2 of this procedure.

5.0 PRECAUTIONS/LIMITATION 5.1 5.1.1 5.1.2 5.2 5.2.1 5.2.2 5.2.3 PRECAUTIONS Observe safety rules outlined in Southern Nuclear Safety and Health Manual.

The Shift Supervisor must be notified PRIOR to beginning work on any section of this procedure.

LIMITATIONS Electrical interlocks prevent supplying both RPS buses from the alternate power source at the same time.

Electrical interlocks prevent supplying the RPS bus from both the MG set AND the alternate power source at the same time.

An overvoltage trip of the MG set must be manually reset at the local control panel by momentarily depressing the Motor On pushbutton.

5.2.4 Transferring RPS bus power is a dead bus transfer. The RPS bus will be deenergized momentarily during the transfer.

5.2.5 After restoring power it takes approximately 5 minutes for the Main Steam Line Radiation Monitors to charge up to operating voltage AND the HV-INOP Alarm to clear automatically.

5.2.6 Ensure steps are taken to monitor reactor water conductivity as required by Technical Requirements Manual 3.4.1.

MGR-0001 Ver. 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 40F50 DOCUMENT TITLE:

DOCUMENT NUMBER:

34S0-C71-001-1 VERSION NO:

8.12 120 VAC RPS SUPPLY SYSTEM 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS The number and qualification level of personnel performing the sections in this procedure will be determined by the Shift Supervisor.

4.2 MATERIAL AND EQUIPMENT Fuse pullers 4.3 SPECIAL REQUIREMENTS Independent verification, as described in 10AC-MGR-019-0, Procedure Use and Adherence, will be required during performance of Attachments 1 and 2 of this procedure.

5.0 PRECAUTIONS/LIMITATION 5.1 5.1.1 5.1.2 5.2 5.2.1 5.2.2 5.2.3 PRECAUTIONS Observe safety rules outlined in Southern Nuclear Safety and Health Manual.

The Shift Supervisor must be notified PRIOR to beginning work on any section of this procedure.

LIMITATIONS Electrical interlocks prevent supplying both RPS buses from the alternate power source at the same time.

Electrical interlocks prevent supplying the RPS bus from both the MG set AND the alternate power source at the same time.

An overvoltage trip of the MG set must be manually reset at the local control panel by momentarily depressing the Motor On pushbutton.

5.2.4 Transferring RPS bus power is a dead bus transfer. The RPS bus will be deenergized momentarily during the transfer.

5.2.5 After restoring power it takes approximately 5 minutes for the Main Steam Line Radiation Monitors to charge up to operating voltage AND the HV-INOP Alarm to clear automatically.

5.2.6 Ensure steps are taken to monitor reactor water conductivity as required by Technical Requirements Manual 3.4.1.

MGR-0001 Ver. 3

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

120 VAC RPS SUPPLY SYSTEM 6.0 PREREQUISITES DOCUMENT NUMBER:

34S0-C71-00 1-1 PAGE 5 OF 50 VERSION NO:

8.12 NOTE:

System electrical lineups provided on the Attachments are to be completed as required by 34GO-OPS-003-1, Startup System Status Checklist.

6.1 AC power is available.

6.2 RPS electrical lineup is complete per Attachment 1.

MGR-0001 Ver. 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

120 VAC RPS SUPPLY SYSTEM 6.0 PREREQUISITES DOCUMENT NUMBER:

34S0-C71-001-1 PAGE 5 OF 50 VERSION NO:

8.12 NOTE:

System electrical lineups provided on the Attachments are to be completed as required by 34GO-OPS-003-1, Startup System Status Checklist.

6.1 AC power is available.

6.2 RPS electrical lineup is complete per Attachment 1.

MGR-0001 Ver. 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 60F50 DOCUMENT TITLE:

120 VAC RPS SUPPLY SYSTEM DOCUMENT NUMBER:

34S0-C71-001-1 VERSION NO:

8.12 7.0 PROCEDURE 7.1 SYSTEM STARTUP 7.1.1 MOTOR GENERATOR SET STARTUP 7.1".1.1 Motor Generator Set 1A Startup 7.1.1.1.1 7.1.1.1.2 7.1.1.1.3 7.1.1.1.4 7.1.1.1.5 7.1.1.1.6 7.1.1.1.7 CONTINUOUS I

Confirm open OR open 52-3C, Reactor Protection System (RPS)

EQUIPMENT PROTECTION CIRCUIT BREAKER, in paneI1C71-P003C.

Confirm open OR open 52-3A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, in paneI1C71-P003A.

Ensure fuse C71AF474, in pane11C71-P003A is installed.

Ensure fuse C71AF475 in pane11C71-P003A is installed.

Confirm green Motor Off light on the local Motor Generator (MG) set control panel is ILLUMINATED.

Depress AND hold the Motor ON pushbutton at the local MG Set 1A control panel, UNTIL the indicated generator output voltage is > 118 VAC.

Confirm voltage is between 118 VAC and 122 VAC, after the generator output voltage stabilizes.

D D

D D

D D

D NOTE: trhe breaker is TRIPPED WHEN white line CANNOT be seen.

Posted 1 C71-P003A, B, C, 0, E, F 7.1.1.1.8 MGR-0001 Ver. 3 Close 52-3A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, paneI1C71-P003A.

D

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SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

120 VAC RPS SUPPLY SYSTEM 7.0 PROCEDURE 7.1 SYSTEM STARTUP 7.1.1 MOTOR GENERATOR SET STARTUP 7.1.1.1 Motor Generator Set 1 A Startup DOCUMENT NUMBER:

34S0-C71-001-1 CONTINUOUS I

PAGE 6 OF 50 VERSION NO:

8.12 7.1.1.1.1 Confirm open OR open 52-3C, Reactor Protection System (RPS)

EQUIPMENT PROTECTION CIRCUIT BREAKER, in paneI1C71-P003C.

0 7.1.1.1.2 7.1.1.1.3 7.1.1.1.4 7.1.1.1.5 7.1.1.1.6 7.1.1.1.7 Confirm open OR open 52-3A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, in panel 1 C71-P003A.

0 Ensure fuse C71AF474, in panel 1 C71-P003A is installed.

0 Ensure fuse C71AF475 in pane11C71-P003A is installed.

0 Confirm green Motor Off light on the local Motor Generator (MG) set control panel is ILLUMINATED.

0 Depress AND hold the Motor ON pushbutton at the local MG Set 1A control panel, UNTIL the indicated generator output voltage is > 118 VAC.

0 Confirm voltage is between 118 VAC and 122 VAC, after the generator output voltage stabilizes.

o The breaker is TRIPPED WHEN white line CANNOT be seen.

NOTE:

Posted 1 C71-P003A, B, C, D, E, F 7.1.1.1.8 MGR-0001 Ver. 3 Close 52-3A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, panel 1 C71-P003A.

o

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 7 OF 50 DOCUMENT TITLE:

120 VAC RPS SUPPLY SYSTEM DOCUMENT NUMBER:

34S0-C71-00 1-1 VERSION NO:

8.12

  • Due to the undervoltage AND underfrequency condition, Circuit Breaker 52-3C will NOT CLOSE UNLESS Circuit Breaker 52-3A is CLOSED.

NOTES:

  • The breaker is TRIPPED WHEN white line CANNOT be seen.

Posted 1C71-P003A, B, C, D, E, F.

7.1.1.1.9 Close 52-3C, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, paneI1C71-P003C.

0 7.1.1.1.10 Confirm GEN. A white light, located above the Power Source Select switch, paneI1H11-P610, is ILLUMINATED.

0 7.1.1.1.11 Supply power to the RPS bus per subsection 7.1.3 OR 7.3.3 of this procedure, IF desired.

0 MGR-0001 Ver. 3

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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 7 OF 50 DOCUMENT TITLE:

120 VAC RPS SUPPLY SYSTEM DOCUMENT NUMBER:

34S0-C71-00 1-1 VERSION NO:

8.12

  • Due to the undervoltage AND underfrequency condition, Circuit Breaker 52-3C will NOT CLOSE UNLESS Circuit Breaker 52-3A is CLOSED.

NOTES:

  • The breaker is TRIPPED WHEN white line CANNOT be seen.

Posted 1C71-P003A, B, C, D, E, F.

7.1.1.1.9 Close 52-3C, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, panel 1 C71-P003C.

0 7.1.1.1.10 Confirm GEN. A white light, located above the Power Source Select switch, paneI1H11-P610, is ILLUMINATED.

0 7.1.1.1.11 Supply power to the RPS bus per subsection 7.1.3 OR 7.3.3 of this procedure,

!E desired.

0 MGR-0001 Ver. 3

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