ML091730123
| ML091730123 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/22/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML091730123 (100) | |
Text
DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training Admin 1, RO, SRO-I
)
N/R Energy to Serve Your World SM
IsOUTHERN NUCLEAR OPERATING COMPANY
"'\PLANT E. I. HATCH Page 1 of 1
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FORM TITLE: TRAINING MATERIAL REVISION SHEET Prol[,amlCourse Code: OPERATIONS TRAINING Media Number: LR-JP-I0025
UNIT 1 () UNIT 2 (X)
ELECTRICAL SAFETY REQUIREMENTS LR-JP-10025-00 The task shall be completed when the candidate has determined the additional Personal Protective Equipment (PPE) to be worn and boundaries established IAW NMP-SH-003.
N/A N/A PLANT HATCH JTA IMPORTANCE RATING:
RO N/A SRO N/A KIA CATALOG NUMBER: G 2.1.26 KIA CATALOG JTA IMPORTANCE RATING:
RO 3.4 SRO 3.6 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)
H-13370 NMP-SH-003. Electrical Work Practices H-133 NMP-SH-003. Electrical Work Practices APPROXIMATE COMPLETION TIME: 20 Minutes
) SIMULATOR SETUP: NA
UNIT 1 READ AND GIVE A COpy TO THE OPERATOR INITIAL CONDITIONS:
- 1. Maintenance is to work on MCC-IB, lR24-S022 fcVtJ
- 2. The feeder breaker for this MCC will need to be racked out.
~cl~;-b;~~~;'i~i~~~t~d~~'1R2~:~2!20 -
- 4. The bus is shown on single line diagram H-13370 which is available as a reference.
S. The following is required for all workers in the area:
- HardHat
- Safety Glasses
- Hearing Protection
- Natural Fiber Clothing INITIATING CUES: 0
- Determine the additional Personal Protective Equipment (PPE) to be worn AND the minimum boundaries required to be established IAWNMP-SH-003. L r>~/*.l" YJdlli b! ~.{).(Nl
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
NOTE: Provide the operator with H-13370 and NMP-SH-003. START TIME: _ _ __
- 1. I Candidate obtains the procedure Operator has obtained procedure SAT I UNSAT needed to perform the task. NMP-SH-003 and Single line H-13370.
- 2. I Selects the appropriate matrix from Selects "Station Battery SAT/UNSAT attachment 1 ofNMP-SH-003. Maintenance and Breaker Operation 50 to 300 VDC" matrix from attachment 1 ofNMP-SH-003.
Determines leather or gauntlet SAT I UNSAT gloves are required.
Determines the answer is "Yes." SAT/UNSAT
)
Determines the answer is "Yes." SAT IUNSAT Reviews Prohibited Approach I Determines the answer is "No." SAT IUNSAT Boundary to see if requirements apply.
~eyle~s~estr1:Stg(l~~~r&~C~}<.*. * ; *.**.****. . ****.*1 Det~rmines the answer is "Yes." SAT IUNSAT a(J{J.l1d~rytose~Jfreqtgrewe:t)t§apply. AVOId Contact.
Determines the answer is "Yes." SAT IUNSAT The distance is 3 feet 6 inches.
Determines the answer is "Yes." SAT IUNSAT The distance is 10 feet.
END TIME:- - - -
NOTE: The terminating cue shall be given to the Applicant when:
- With no reasonable progress, the Applicant exceeds double the allotted time.
- Applicant states the task is complete.
TERMINATING CUE: That completes this JPM.
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Southern Nuclear Operating Company Nuclear NMP-SH-003 SOUTHERN COMPANY A Management Electrical Work Practices Version 8.0
£lftrD'"Snw J&#l'"lWI,J.f~ Procedure Page 37 of 41 Reference Use Attachment 2 - Approach Boundaries - Page 1 of 2 Prohibited Approach I
Restricted Approach (RAB)
Qualified Employees ONLY Limited Approach (LAB)
UnqualWied employees may cross this boundary if escorted by a qualified employee Flash Protection (FPB)
No entry without flash proIeclicn TABLE 1
. -_. --- - -_ .......... _ . '_**--*-1" .... _ . -_ . --_ .. --_ . _-- -_. _-
APPROACH BOUNDARIES FOR ALL HAZARD LEVELS (Need not be physically identified)
VOLTAGE PROHIBITED RESTRIC.TED LIMITED APPROACH APPROACH APPROACH BOUNDARY BOUNDARY BOUNDARY Less Than 50 N/A N/A N/A I 50-276 AVOID CONTACT AVOID CONTACT 3 FEET 6 INCHES 277 -750 o FEET 1 INCH 1 FOOT 3 FEET 6 INCHES I 751 -15 kV o FEET 7 INCH 2 FEET 2 INCHES 5 FEET TABLE 2 FLASH PROTECTION BOUNDARIES FOR WORK ON OR NEAR EXPOSED ENERGIZED PARTS FLASH PROTECTION BOUNDARIES
(*To be physically identified when ~ 480 VAC or racking breakers)
VOLTAGE TASK DISTANCE 125-250 VDC ANY 10 FEET
< 276 VAC ANY 3 FEET 6 INCHES 277-600VAC ANY *10 FEET Greater than 600 VAC ANY *20 FEET NOTES: 1. Flash protection boundaries encompass restricted and limited approach boundaries as depicted.
- 2. Specified distances are minimum distances.
- 3. Flash protection boundaries may be less than specified if work is to performed adjacent to a physical barrier such as a wall.
- 4. In instances where any boundary can not be established as specified due to equipment location/close proximity, alternate methods for providing boundaries shall be determined and established via Attachment 3, Electrical Safety Checklist.
Southern Nuclear r 'fating Company Nuclear NMp* )3 SOUTHERN COMPANY A Management Electric'Bntif ork Practices Version--cS.a Ene-rgy IfJ Sert~ fit,,: r \l%rld~ Procedure Page 31 of 41 Sheet 7 of 11
[ - Reference Use Attachment 1 - Electrical PPE Job Safety Matrix NOTE: Task assumes equipment is ENERGIZED and work is performed within the Flash Protection Boundary.
STATIONBATTERYMAINTENANC~ANDBREAKEROPERATION50.to 300VDC Voltage Arc*Resistant 20 Cal Arc Prohibited Approach Restricted Approach Limited Approach Flash Protection Definitions Rated Face Shield gear Boundary Boundary Boundary Boundary X = Required Gloves Battery Maintenance (Chemical protection and face shield required Note A when handling electrolyte NOTE B NOTE B NOTE B Racking 125 VDC and 250 VDC switchgear breakers. NoteC X X Attachment 2 Attachment 2 Attachment 2 Table 1 Table 1 Table 2 Breaker operation with covers on Note A Attachment 2 Attachment 2 Table 1 Table 1 NOTES A. When working on exposed ENERGIZED parts (>> 50 VACNDC and <<) 277 VAC/160 VDC, voltage rated gloves and/or insulated tools are required. However, voltage rated gloves shall be worn when working on exposed ENERGIZED parts at a voltage (>> 277 VAC/160 VDC.
B. The approach distance shall not apply to work performed by a qualified employee in the battery working zone.
C. As a minimum leather gloves or gauntlet gloves are required to be worn, however, voltage rated gloves are not required.
DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 2, RO, SRO-I TITLE ECCSSTATUSCHECK AU'tHQR. MEj)IANlJM~ER F.N.FAGAN LR-JP-007 .15-00 iR.JtG()MME~EI> * *.*BY NfR Energy to Serve Your World sM
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Pro~am/Course Code: OPERATIONS TRAINING Media Number: LR-JP-007.15-00
. R~as(,l)to.. ~evisi()Il** **\1. AllthC)*~.s ~~llY'S
- .Initials Initials 00 I Initial development FNF
UNIT 1 () UNIT 2 (X)
PERFORM A VALVE POSITION VERIFICATION OF THE SYSTEM LR-JP-007.l5-00 The task shall be complete when the operator has closed the open valve and documented the as-found condition.
H-OPR0007.015 H-OP007.015.A PLANT HATCH JTA IMPORTANCE RATING:
RO 2.2 SRO 2.69 KIA CATALOG NUMBER: 2.1.29
) KIA CATALOG JTA IMPORTANCE RATING:
RO 4.1 SRO 4.0 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)
OPS-0050 Operator At The 34SV-SUV-018-2 ECCS Status Check APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: Any 100% power IC. Throttle open 2EII-F040 until red light comes on and hold/throttle open for 3 seconds.
)
UNIT 2 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 is at 100% power and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> into the shift you have assumed the OA TC duties.
- 2. As per "Operator At The Controls Relief Checklist", the "ECCS Status Check" had been started and is only partially complete.
INITIATING CUES:
The Shift Supervisor directs you to complete the ECCS Status check per 34SV-SUV-018-2.
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
NOTE: Hand the operator a partially completed "Operator At The Controls Relief Checklist" (filled in up to the ECCS Status Check) and "ECCS Status Check" procedure (filled in up to 2El1-FOIIB on Table 5).
START TIME: _ _ __
- 1. The operator reviews the checklist. Operator reviews the ECCS SAT/UNSAT Status Check list.
- 2. Verify closed 2EII-FOIIB, RHR Hx
- Operator observes control SAT IUNSAT to Torus Valve switch green light on.
- Places checkmark in Table 5.
- 3. Verify closed 2EII-F073B, RHRSW
- Operator observes control SAT I UNSAT Crosstie Valve switch green light on.
)
- Places checkmark in Table 5.
- 4. Verify closed 2EII-F122B, Check
- Operator observes control SAT/UNSAT Valve F050B Bypass Valve switch green light on.
- Places checkmark in Table 5.
- 5. Verify open 2El1-F004B, Torus
- Operator observes control SAT I UNSAT Suction Valve switch red light on.
- Places checkmark in Table 5.
- 6. Verify closed 2El1-F006B, Shutdown
- Operator observes control SAT I UNSAT Cooling Valve switch green light on.
- Places checkmark in Table 5.
- 7. Verify open 2EII-F004D, Torus
- Operator observes control SAT/UNSAT Suction Valve switch red light on.
- Places checkmark in Table 5.
- 8. Verify closed 2El1-F006D, Shutdown
- Operator observes control SAT/UNSAT Cooling Valve switch green light on.
- Places checkmark in Table 5.
- 9. Verify closed 2EII-FI03B, Hx Vent
- Operator observes control SAT IUNSAT Valve switch green light on.
- Places checkmark in Table 5.
- 10. Verify closed 2EII-FI04B, Hx Vent
- Operator observes control SAT IUNSAT Valve switch green light on ..
)
- Places checkmark in Table 5.
- 11. Verify closed 2El1-Fl19B, Serv
- Operator observes control SAT/UNSAT Water Crosstie Valve switch green light on.
-~-~ ----- -----
- Places checkmark in Table 5.
(** Indicates critical step)
- 12. Verify closed 2E11-F053B, Hx Outlet
- Operator observes control SAT I UNSAT Press Reducing Valve switch green light on.
- Places checkmark in Table 5.
PROMPT: IF the operator asks for a relief to go to the back panels, THEN inform the operator that he has been properly relieved of the OA TC duties and may continue.
- 13. Verify open 2E11-F041B, Drywell
- Operator observes control SAT IUNSAT Press Switches Inst Line Isolation switch red light on.
- Places checkmark in Table 5.
- 14. Verify open 2E11-F041D, Drywell
- Operator observes control SAT IUNSAT Press Switches Inst Line Isolation switch red light on.
- Places checkmark in Table 5.
- Operator observes both SAT IUNSAT Radwaste Valve control switch green light on I and red light on.
16 Document as found valve position Operator documents on Table 5 SAT IUNSAT that the valve was opened and then circles the notation.
~()tifie~Ss,c)fdV~ljh~icatio~,()# .** .' .*****i< Operator informs SS of dual
.r?~iI SAT IUNSAT
.*.** < / .
- 2Ell.'".FQ40:.**L******* .*.**.**.*. ___.;L'*****.****...,~. _ . . indication on 2E11-F040 . ------- -----
PROMPT: WHEN notified of dual indication, THEN direct the operator to attempt to close 2E11-F040 valve.
NOTE: 2E 11-F040 valve is a throttle valve and must be held in the CLOSED position to fully stroke closed.
Operator places control switch for SAT IUNSAT 2E 11-F040 to the CLOSED END TIME:
NOTE: The terminating cue shall be given to the Applicant when:
- With no reasonable progress, the Applicant exceeds double the allotted time.
- 2E11-F040 is closed and documented TERMINATING CUE: That completes this JPM.
(** Indicates critical step)
SOUTHERN NUCLEAR DOCUMENT TYPE: TRAINING USE ONLY PAGE PLANT E. I. HATCH SURVEILLANCE PROCEDURE 1 OF 18
\?OCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
/ ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 EXPIRATION APPROVALS: EFFECTIVE DATE: DEPARTMENT MGR C. R. Dedrickson DATE 08/27/97 DATE:
N/A NPGM/POAGM/PSAGM OS/26/04 N/A DATE N/A 1.0 OBJECTIVE This procedure provides instructions for use when demonstrating Emergency Core Cooling System's operability as required by Unit 2 TS SR 3.5.1.2 and 3.5.2.4.
In addition, instructions are provided for use WHEN demonstrating Reactor Core Isolation Cooling System AND Suppression Pool Cooling and Spray Modes of the Residual Heat Removal System operability as required by Unit 2 TS SR 3.5.3.2, 3.6.2.3.1, 3.6.2.4.1, and partially covers 3.7.1.1.
TABLE OF CONTENTS Section Page 2.0 APPLiCABILITy .................................................................................................................. 1
)
3.0 REFERENCES
................................................................................................................... 2 4.0 REQUIREMENTS ............................................................................................................... 3 5.0 PRECAUTIONS/LIMITATIONS ........................................................................................... 4 6.0 PREREQUISITES ............................................................................................................... 4 7.0 PROCEDURE ..................................................................................................................... 5 7.1 PRETEST ..................................................................................................................... 5 7.2 ECCS STATUS CHECK ................................................................................................ 5 7.3 TEST RESULTS ......................................................................................................... 17 7.4 TEST REViEW ............................................................................................................ 18 2.0 APPLICABILITY This procedure is applicable to the valves in the flow paths of the following ECCS AND safe shutdown systems: High Pressure Coolant Injection System, Reactor Core Isolation Cooling System, LPCI AND Suppression Pool Cooling and Spray Modes of the Residual Heat Removal System AND the Core Spray System. It is performed WITHIN two hours of every shift change AND is required to be performed once every 31 days by Tech Specs. This procedure is also applicable to the ECCS and RCIC Room Coolers and valves as an administrative control over system alignment.
MGR-0002 Ver. 8
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 2 OF 18 nOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
/ ECCS STATUS CHECKS 34SV-SUV-018-2 6.4
3.0 REFERENCES
3.1 90AC-OAM-001-0, Test and Surveillance Control 3.2 Unit 2, TS SR 3.5.1.2, 3.5.2.4, 3.5.3.2, 3.6.2.3.1, 3.6.2.4.1, and 3.7.1.1 3.3 USNRC Inspection Report 50-366/79-21 3.4 H-26014 and H-26015, RHR System P&ID, Sheets 1 and 2 3.5 H-26018, Core Spray System P&ID 3.6 H-26020 and H-26021, HPCI System P&ID, Sheets 1 and 2 3.7 H-26023 and H-26024, RCIC System P&ID, Sheets 1 and 2 G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 30F 18
") DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
, ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS The number and qualification level of Operations personnel performing this procedure will be determined by Shift Supervisor.
4.2 MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure 4.3 SPECIAL REQUIREMENTS 4.3.1 IF valves OR switches are NOT in pOSition specified, i.e., NOT in Standby Lineup, the Shift Supervisor will determine from other plant conditions IF the system/loop is operable.
4.3.2 For any valves found out of the Normal Position, perform the following:
4.3.2.1 Record AND circle the valve position in the appropriate table AND inform the Shift Supervisor.
4.3.2.2 Provide an explanation of the position as follows:
4.3.2.2.1 IF the misposition causes the ECCS OR Safe Shutdown system to be inoperable, record explanation in Unsatisfactory Conditions.
4.3.2.2.2 IF the position does NOT cause the system to be inoperable, record the explanation under Comments/Corrective Actions section.
4.3.2.3 The Shift Supervisor will initiate corrective action as necessary to return the valve OR switch to its correct position.
G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 40F 18
"'oOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
J ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS Observe safety rules outlined in the Southern Nuclear Safety and Health Manual.
5.2 LIMITATIONS These checks may be performed in any order necessary.
6.0 PREREQUISITES N/A - Not applicable to this procedure G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 50F 18
,?OCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
. ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.0 PROCEDURE 7.1 PRETEST 7.1.1 Obtain Unit 2 Shift Supervisor's permission to perform this test.
~
7.1.2 Record the Plant Condition (1, 2, 3, 4, 5 or *): 1
~
7.2 ECCS STATUS CHECK CONTINUOUS I 7.2.1 IF Core Spray Loop A is required to be operable, confirm that Core Spray Loop A valves in the flow path are in the correct position by completing Table 1.
~
Table 1 OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (..J) POSITION (O/C)
POSITION Core Spray Loop A Valves 2E21-FOO1A OPEN Torus Suction Vlv -V 2E21-F019A OPEN Torus Suction Vlv -V 2E21-FOO4A OPEN Outbd Discharge Vlv -V 2E21-FOO5A CLOSED Inbd Discharge Vlv -V 2E21-F015A CLOSED Test Vlv -V 2E21-F031A OPEN Min FlowVlv -V 2E21-FOO7A OPEN Manual Injection Vlv -V
)2E21-F037A I _-
CLOSED (Testable Check) Bypass Vlv -V G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 6 OF 18 POCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
/ ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.2 IF Core Spray Loop B is required to be operable, confirm that Core Spray Loop B valves in the flow path are in the correct position by completing Table 2.
~
Table 2 Core Spray Loop B Valves 2E21-FOO1B OPEN Torus Suction Vlv -V 2E21-F019B OPEN Torus Suction Vlv -V 2E21-FOO4B OPEN Outbd Discharge Vlv -V 2E21-FOOSB CLOSED Inbd Discharge Vlv -V 2E21-F01SB CLOSED Test Vlv -V 2E21-F031B OPEN Min FlowVlv -V
)2E21-FOO7B OPEN Manual Injection Vlv -V 2E21-F037B CLOSED (Testable Check) Bypass Vlv -V 2GS1-F017 CLOSED Torus Water Makeup Outbd Isol -V l2H11-P70m 2GS1-F013 CLOSED Torus Water Makeup Inbd Isol -V L. l2H11-P70m G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 7 OF 18
'P0CUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
J ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 NOTE Valves 2E11-F008 and F009 positions are confirmed whenever any loop of RHR is required to be operable ..
7.2.3 Confirm that the RHR System valves in the LPCI AND Suppression Pool Cooling modes are in the correct position as follows:
7.2.3.1 IF the LPCI OR Suppression Pool Cooling mode OR Suppression Pool Spray Mode of RHR Loop A is required to be operable, confirm that RHR Loop A valves in the LPCI AND/OR Suppression Pool Cooling AND/OR Suppression Pool Spray Flow Path are in the correct position by completing Tables 3 and 4.
~
7.2.3.2 IF RHR Loop A is in a mode of operation other than Standby for LPCI and Suppression Pool Cooling AND/OR Suppression Pool Spray Modes of operation, confirm that Loop A is operable AND record that mode of operation below:
Mode of Loop A operation: N/A N/A Table 3 OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (..J) POSITION (O/C)
POSITION 2E11-F009 CLOSED SDC Suction Vlv (2H11-P602) -V 2E11-F008 CLOSED SDC Suction Vlv -V Table 4 OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (..J) POSITION (O/C)
POSITION RHR Loop A Valves 2E11-F075A CLOSED RHRSWVlv -V 2E11-F065A OPEN Torus Suction Vlv -V
\ 2E11-F065C OPEN Torus Suction Vlv -V
'!2E11-F060A OPEN RHR Injection Vlv -V G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 80F 18
""'DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
) ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 4 (continued)
OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (..J) POSITION (O/C)
POSITION 2E11-F017A OPEN RHR Outbd Inj Vlv 2E11-F015A CLOSED RHR Inbd Inj Vlv ""
2E11-FOO7A OPEN Min FlowVlv 2E11-F021A CLOSED Cnmt Spray Inbd Vlv 2E11-F016A CLOSED Cnmt Spray Outbd Vlv 2E11-F047A OPEN Hx InletVlv ""
2E11-FOO3A OPEN Hx Outlet Vlv 2E11-F048A OPEN Hx Bypass Vlv ""
\2E11-F027A CLOSED Torus Spray Vlv
'2E11-F024A CLOSED Full Flow Test Line Vlv 2E11-F028A CLOSED Torus Spray or Test Vlv 2E11-F011A CLOSED RHR Hx To Torus Vlv ""
2E11-F073A CLOSED RHRSW Crosstie Vlv ""
2E11-F122A CLOSED Testable Check F050A Bypass Vlv 2E11-FOO4A OPEN Torus Suction Vlv ""
2E11-FOO4C OPEN Torus Suction Vlv 2E11-FOO6A CLOSED Shutdown Cooling Vlv 2E11-FOO6C CLOSED Shutdown Cooling Vlv 2E11-F103A CLOSED HxVentVlv 2E11-F104A CLOSED HxVentVlv 2E11-F119A CLOSED Serv Water Crosstie Vlv G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 9 OF 18
'pOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
, ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 4 (continued)
OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (..J) POSITION (O/C)
POSITION 2E11-F053A** CLOSED Hx. Outlet Press Reducing Vlv -I 2E11-F041A OPEN DIW Press Sw Inst Line Isol f2H11-P657)
-I 2E11-F041C OPEN DIW Press Sw Inst Line Isol
_ __(2j--L1J ..f>657~
-I
~"- -,-" --,
- Confirm that power is off to this valve by confirming the F053A solenoid control switch is in closed (valve fails closed on loss of power).
G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 10 OF 18
\DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
) ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.3.3 IF the LPCI OR Suppression Pool Cooling mode OR Suppression Pool Spray Mode of RHR Loop B is required to be operable, confirm that RHR Loop B valves in the LPCI AND/OR Suppression Pool Cooling AND/OR Suppression Pool Spray Flow Path are in the correct position by completing Tables 3 and 5.
7.2.3.4 IF RHR Loop B is in a mode of operation other than Standby for LPCI and Suppression Pool Cooling AND/OR Suppression Pool Spray Modes of operation, confirm that Loop B is operable AND record that mode of operation below:
Mode of Loop B operation: N/A N/A Table 5 OPERABLE VALVE CONFIRMED OFF-NORMAL I (NORMAL) VALVE DESCRIPTION NUMBER (~) POSITION (O/C) I POSITION RHR Loop B Valves i J2E11-F075B CLOSED RHRSWVlv 2E11-F065B OPEN Torus Suction Vlv 2E11-F065D OPEN Torus Suction Vlv 2E11-F060B OPEN RHR Injection Vlv 2E11-F017B OPEN RHR Outbd Inj Vlv ""
2E11-F015B CLOSED RHR Inbd Inj Vlv ""
2E11-F007B OPEN Min FlowVlv ""
2E11-F021B CLOSED CnmtSpray Inbd Vlv ""
2E11-F016B CLOSED Cnmt Spray Outbd Vlv 2E11-F047B OPEN Hx Inlet Vlv ""
2E11-F003B OPEN Hx Outlet Vlv ""
2E11-F048B OPEN Hx Bypass Vlv ""
2E11-F027B CLOSED Torus Spray Vlv ""
G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 11 OF 18
\ DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
) ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 5 (continued)
OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (..J) POSITION (O/C)
POSITION 2E11-F024B CLOSED Full Flow Test Line Vlv -V 2E11-F028B CLOSED Torus Spray or Test Vlv -V 2E11-F011B CLOSED RHR Hx To Torus Vlv 2E11-F073B CLOSED RHRSW Crosstie Vlv 2E11-F122B CLOSED Testable Check F050B Bypass Vlv 2E11-FOO4B OPEN Torus Suction Vlv 2E11-FOO6B CLOSED Shutdown Cooling Vlv I
2E11-FOO4D OPEN Torus Suction Vlv i I
2E11-FOO6D CLOSED Shutdown Cooling Vlv
) 2E11-F103B CLOSED Hx Vent Vlv i
i 2E11-F104B CLOSED Hx Vent Vlv 2E11-F119B CLOSED Serv Wtr Crosstie Vlv 2E11-F053B** CLOSED Hx. Outlet Press Reducing Vlv 2E11-F041B Drywell Press Switches Inst Line OPEN Isolation l2H11-P654) 2E11-F041 D Drywell Press Switches Inst Line OPEN Isolation l2H11-P654) 2E11-F040 CLOSED RHR to Radwaste Vlv (2H11-P602) 2E11-F049 CLOSED RHR to Radwaste Vlv
- Confirm that power is off to this valve by confirming the F053B solenoid control switch is in closed (valve fails closed on loss of power).
)
G16.30 MGR-0001 Ver. 3
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ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.3.5 Confirm that the following valves are de-energized in the CLOSED position.
7.2.3.5.1 2E 11-F022, Rx Head Spray Vlv 7.2.3.5.2 2E11-F023, Rx Head Spray Vlv 7.2.4 IF HPCI System is required to be operable, perform the following:
7.2.4.1 Confirm that the HPCI Flow Controller is in AUTO (green light ILLUMINATED) AND set at 4250 GPM with demand meter indicating> 100%.
7.2.4.2 Confirm that the valves are in the correct position by completing Table 6.
Table 6 OPERABLE VALVE CONFIRMED OFF-NORMAL I (NORMAL) VALVE DESCRIPTION NUMBER (--I) POSITION (O/C)
POSITION I 2E41-F002 OPEN/STOP Inbd Steam Isol Vlv 2E41-F003 OPEN/STOP Outbd Steam Isol Vlv 2E41-F001 CLOSED Turb Steam Supply Vlv 2E41-F011 CLOSED Test To CST Vlv 2E41-F012 CLOSED Min FlowVlv 2E41-F051 OPEN Torus Suction Vlv 2E41-F042 CLOSED Torus Inbd Suct Vlv 2E41-F008 CLOSED Test To CST Vlv 2E41-F059 CLOSED Lube Oil Clg Wtr Vlv 2E41-F054 CLOSED Drain Pot Trap Byp Vlv 2E41-F041 CLOSED Torus Outbd Suct Vlv 2E41-F007 OPEN Pump Discharge Vlv 2E41-F053 AUTO Drain Pot Drain Vlv
)
G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 13 OF 18 POCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
) ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 6 (continued)
I OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (--J) POSITION (O/C)
POSITION 2E41-F004 OPEN CST Suction Vlv 2E41-F006 CLOSED Pump Discharge Vlv 2E41-F104 Exh Vacuum Brkr Vlv OPEN (2H11-602) 2E41-F111 OPEN Exh Vacuum Brkr Vlv 2E41-F025 OPEN Barom Cndsr Disch To CRW (2H 11-P602) 2E41-F026** CLOSED Barom Cndsr Disch To CRW 2E41-F028 OPEN Steam Line Drain Vlv (2H11-P602) 2E41-F029 OPEN Steam Line Drain Vlv
\2E41-F3052 CLOSED H PCI Control Vlv r2E41-F3053 .. _ CLOSED HPCI Stop Vlv
- Valve cycles automatically on barometric condenser level.
G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 14 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.5 IF RCIC System is required to be operable, perform the following:
7.2.5.1 Confirm that the RCIC Turbine Flow Controller is in AUTO (green light ILLUMINATED) AND set at 400 GPM with demand meter indicating> 100%.
7.2.5.2 Confirm that the valves are in the correct position by completing Table 7.
Table 7 OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (-V) POSITION (O/C)
POSITION 2E51-F007 OPEN/STOP Steam Supply Isol Vlv 2E51-F008 OPEN/STOP Steam Supply Line Isol Vlv 2E51-F045 CLOSED Steam to Turbine Vlv 2E51-F019 CLOSED Min FlowVlv
) 2E51-F022 CLOSED Test Line To CST 2E51-F013 CLOSED Pump Discharge Vlv 2E51-F012 OPEN Pump Discharge Vlv 2E51-F003 OPEN Torus Suction Vlv 2E51-F031 CLOSED Torus Inbd Suction Vlv 2E51-F010 OPEN CST Suction Vlv 2E51-F029 CLOSED Torus Outbd Suction Vlv 2E51-F046 CLOSED Turb Clg Water Vlv 2E51-F054 CLOSED Steam Line Drain Vlv 2E51-F004** CLOSED Barom Cndsr Disch To CRW Barom Cndsr Disch To CRW 2E51-F005 OPEN (2H11-P601 )
- Valve cycles automatically on barometric condenser level.
)
G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 15 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 7 (continued)
OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (..J) POSITION (O/C)
POSITION 2E51-F025 OPEN Steam Line Drain Vlv 2E51-F026 OPEN Steam Line Drain Vlv (2H11-P601) 2E51-F104 OPEN Exh Vacuum Brkr Vlv 2E51-F105 OPEN Exh Vacuum Brkr Vlv (2H11-P601) 2E51-F523 OPEN Governor Vlv (open indication) 2E51-F524 OPEN Trip & Throttle Vlv 7.2.6 Confirm that the Control Room Ventilation System is correctly aligned for the existing plant condition per 34S0-Z41-001-1, Control Room Ventilation System.
G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 16 OF 18
DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
) ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.7 Confirm that the ECCS AND RCIC ROOM COOLER System is correctly aligned for the existing plant condition per Table 8.
Table 8 Panel 2H 11-P657 OPERABLE COOLER CONFIRMED OFF-NORMAL POSITION COOLER DESCRIPTION NUMBER (..J) POSITION CIRCLE 2T41-BOO1A AUTO/RUN CRD PUMP ROOM COOLER (Note 1) 2T41-BOO2A AUTO CS/RHR S-E DIAGONAL PUMP (Note 2) ROOM COOLER 2T41-BOO3A AUTO CS/RHR N-E DIAGONAL PUMP (Note 2) ROOM COOLER 2T41-BOO4A AUTO/RUN RCIC PUMP RM COOLER (Note 3) 2T41-BOO5A AUTO/RUN HPCI PUMP RM COOLER (Note 4)
) Panel 2H 11-P654 2T41-BOO1B AUTO/RUN CRD PUMP ROOM COOLER (Note 1) 2T41-BOO2B AUTO CS/RHR S-E DIAGONAL PUMP (Note 2) ROOM COOLER 2T41-BOO3B AUTO CS/RHR N-E DIAGONAL PUMP (Note 2) ROOM COOLER 2T41-BOO4B AUTO/RUN RCIC PUMP RM COOLER (Note 3) 2T41-BOO5B AUTO/RUN HPCI PUMP RM COOLER (Note 4)
Note 1. One CRD cooler in RUN, one in AUTO Note 2. Both CS/RHR coolers in each diagonal in AUTO Note 3. One RCIC cooler in RUN or AUTO, one in AUTO Note 4. One HPCI cooler in RUN, one in AUTO G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 17 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.3 TEST RESULTS 7.3.1 Reason for test: ( ) Normal surveillance ( ) Other _ _ _ _ _ _ _ _ _ __
7.3.2 Acceptance Criteria 7.3.2.1 WHEN a Loop of RHR is required to be operable, each Residual Heat Removal System Valve in the LPCI or Suppression Pool Cooling or Suppression Pool Spray flow path, that is NOT locked, sealed OR otherwise secured in position, is in the correct position listed in Tables 3 and 4(5) OR the Shift Supervisor had determined from other plant requirements, e.g., Shutdown Cooling required, that the Loop is operable.
7.3.2.2 WHEN a Core Spray Loop is required to be operable, each Core Spray System Valve in the flow path, that is NOT locked, sealed OR otherwise secured in position, is in the correct position listed in Table 1(2).
7.3.2.3 WHEN HPCI is required to be operable, each HPCI System Valve in the flow path, that is NOT locked, sealed OR otherwise secured in position, is in the correct position listed in Table 6, unless the Shift Supervisor had determined from other plant requirements, HPCI aligned to Torus, that HPCI is operable.
) 7.3.2.4 WHEN RCIC is required to be operable, each RCIC System Valve in the flow path that, is NOT locked, sealed OR otherwise secured in position, is in the correct position listed in Table 7, unless the Shift Supervisor has determined from other plant requirements e.g., Surveillance Procedure in progress, that RCIC is operable.
7.3.3 Test Result:
( ) Satisfactory
( ) Unsatisfactory 7.3.4 Unsatisfactory Conditions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
7.3.5 Comments/Corrective Actions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
)
G16.30 MGR-0001 Ver. 3
SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 18 OF 18
\ DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:
/ ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.3.6 Test completed and/or verified by:
/ /
Print Name / Initial / Date
/ /
Print Name / Initial / Date
/ /
Print Name / Initial / Date
/ /
Print Name / Initial / Date
/ /
Print Name / Initial / Date 7.4 TEST REVIEW 7.4.1 The Shift Supervisor will review the procedure data for completeness and indicate concurrence with the test satisfactory/unsatisfactory determination by signing below.
)
Results reviewed by: SS Date 7.4.2 The Shift Supervisor will forward this procedure, with all sign-offs complete, to Document Control for retention in accordance with 20AC-ADM-002-0, Quality Assurance Records Administration.
G16.30 MGR-0001 Ver. 3
SOUTHERN NOCLEAR '-'
Part IV To be completed by on duty OATC just prior to end-of shift. On PLANT E. I. HATCH , PAGE 1 of 1 coming OATC will place his initials in the box when reviewed in FORM TITLE: PART IV.
OPERATOR AT THE CONTROLS RELIEF CHECKLIST General Information (Le., Demins to be BIW & PC, etc).
to _ _1_ _1 _ -
UNIT 2 OATCON DUTY SHIFT DATE (mm/dd/yy)
Part I To be reviewed prior to OATC assuming shift.
- Control Board Walkdown (front & back panel) [ZJ
- Oncoming OATC reviewed OATC Log from the previous 12-hour shift [ZJ
- Ensure radio available. [ZJ OFF Standard Conditions Part II To be completed as early in shift as possible. Check each box as completed
- Review Reactivity Briefing Sheet (OPS-1625 for U2) OR (OPS-1689 for U1) [ZJ
- Review of Active Operating Orders. [ZJ
- Review procedure 34SV-SUV-018-1/2, ECCS Status Check 0
- Review condensate and RWCU demin status. 0
- OATC has informed other NPOs on duty of work to be done on this shift. 0
- Review Compensatory Actions for this shift. 0 Procedures In progress Procedures Step Awaiting
- Review RAS Log. 0
- Review Night Order Book. 0
- Confirm logged on to GENCOM. 0 Part III To be completed prior to leaving shift.
- Mid Shift control room panel walk down completed. 0
- Review 34SV-SUV-019-1/2 for completeness. 0
- Review 34GO-OPS-030-1/2 for completeness. 0 / /
- Review 34GO-OPS-031-1 for completeness. 0 OFF GOING OATC SIGNATURE DATE (mm/dd/yy)
- Review/sign procedures completed on shift. 0
- Operating Orders required this shift completed. 0
- Compensatory Actions for this shift completed. 0 1
- OATC GMA Key Inventory. 0 REVIEWED BY (SS)
/
DATE (mm/dd/yy)
- Once per shift validation of ELDS entry per 34GO-OPS-018-1/2. 0 OPS-0050 Ver 20.0 TRAINING USE ONLY 31 GO-OPS-OO?-O
DRAFT
)
Southern Nuclear E. I. Hatch Nuclear Plant Operations Training Admin 3, SRO-I MCRECRAS MEDIA.1N'UMBER D. H. GIDDENS LR-JP-I0027-00 REcdMMtNDEDBY/ **Al'PRdvEJ)*B¥ N/R Energy to Serve Your World sM
SOUTHERN NUCLEAR OPERATING COMPANY
- ,PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: LR-JP-I0027
- A~tlt~~'S ~~I1Y
- '~
Initials Initials
UNIT 1 ( X) UNIT 2 0 MCRECRAS LR-JP-I0027-00 The task shall be completed the candidate has completed sections 1 and 2 of Required Action Sheet, form 1349.
OPSR300.027 H-OP300.027A PLANT HATCH JTA IMPORTANCE RATING:
RO N/A SRO N/A KIA CATALOG NUMBER: G 2.2.23 KIA CATALOG JTA IMPORTANCE RATING:
RO NA SRO 4.6 OPERATOR APPLICABILITY: Senior Reactor Operator Completion Times OPS-1349 TECH SPECS UNIT 1
) APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: N/A
UNIT 1 READ AND GIVE A COpy TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 1 is in Mode 5 with fuel movement within the core in progress. Fuel movements are expected to last for 15 days.
- 2. Unit 2 is at 100% power.
- 3. During a routine monthly surveillance lZ41-CO 12A, Main Control Room filter train fan, tripped 10 minutes after being started and will not restart.
- 4. The fan tripped at 0600 on 4122/09.
- 5. The remaining filter train fan and the three air handling units and associated fans are operable.
INITIATING CUES:
Complete sections 1 and 2 of a Required Action Sheet, form OPS-1349, for Unit 1 for lZ41-COI2A, Main Control Room filter train fan.
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
START TIME: _ _ __
- 1. Operator obtains the procedure needed Operator has obtained procedure SAT/UNSAT to perform the task.
Unit 1 tech spec NOTE: Provide the candidate with a blank RAS form, OPS 1349.
PROMPT: WHEN the operator indicates he would look in the Required Action Tracking Log for a RAS number, INFORM him that the number is 1-09-027.
- 2. I Assign a RAS number from the Writes in 1-09-027 as the SAT /UNSAT Required Action Tracking Log. Required Action Sheet Number.
- 3. I Locates the appropriate tech spec Addresses Unit 1 tech spec SAT/UNSAT section. section 3.7.4 Action A.
Writes lZ41-COI2A, In the MPL SAT/UNSAT block.
Writes MCREC fan or a similar SAT/UNSAT name In the Description block.
Writes 0600 for the time and SAT /UNSAT 4/22/09 for the date in the Inoperable time/date block.
- 7. I Reviews the RAS section 1 "Return to Writes nothing in the Return To SAT/UNSAT Oper" time/date block. OPER Time/Date block.
S. I Reviews the RAS section 1 "Init" Writes nothing in the INIT block. SAT/UNSAT block I
Writes time of 0600 and date of SAT /UNSAT 4/22/09 in the Initiation TimelDate block of section 2.
Writes a time of 0600 and a date SAT /UNSAT of 4/29/09 in the REQ RESTORATION TimelDate block of section 2.
- 11. I Completes the RAS section 2 Writes N/A or similar wording in SAT /UNSAT "Modified Completion" Time/Date the Modified Completion TimelDate block of section 2.
- 12. Completes the RAS section 2 Writes NIA or similar wording in SAT IUNSAT "Extended Completion the Extended Completion TimelDatellnit" block. TimelDatellnit block in section 2.
- 13. Completes the RAS section 2 "SFDP Marks the NIA box ofthe SFDP SAT IUNSAT Entered" block. Entered block NOTE: If candidate asks to see the Status Indication, hand the candidate a picture of the status indicators.
- 14. I Completes the RAS section 2 "INOP Marks the yes box of the }NOP SAT I UNSAT Status Indication" block. Status Indication Block after directing personnel to switch the light on.
PROMPT: asked to tum on the status indication light, the operator the light is now on.
Writes Modes 1,2, and 3, During SAT/UNSAT movement of irradiated fuel assemblies in the secondary containment, During Core Alterations, During operations with a potential for draining the reactor vessel, (OPDRVs). In the Applicability block of section 2.
Writes, D.l Place OPERABLE SAT/UNSAY MCREC subsystem in pressurization mode Immediately OR D.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment Immediately AND D.2.2 Suspend CORE ALTERA nONS Immediately AND D.2.3 Initiate actions to suspend OPDRVs.
Immediately, in the Required Action if Comp time is exceeded block.
- 17. I Completes the RAS section 2 Writes tech spec 3.7.4 in the SAT I UNSAT "Reference Document" block. reference block of section 2.
- 18. I Completes RAS section 2 Writes 225 in the SAT IUNSAT "Revision/Amendment" block. RevisionlAmendment block.
- 19. I Completes fhe RAS section Writes "3.7.4.A.l" (or similar) in SAT IlJNSAT "Reference Document" block. the "Reference Document" block
- 20. Completes the RAS section 4, Writes "Restore MCREC SAT IUNSAT "Required Action" block. subsystem to Operable status" in the Required Action block.
- 21. Completes the RAS section 4, "Req Writes "7 days" in the Req Comp SAT I UNSAT Comp Time of Freq" block. Time ofFreq block.
END TIME:- - - -
NOTE: The terminating cue shall be given to the Applicant when:
- With no reasonable progress, the Applicant exceeds double the allotted time.
- Applicant states the task is complete.
TERMINATING CUE: That completes this JPM.
MCREC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Main Control Room Environmental Control (MCREC) System LCO 3.7.4 Two MCREC subsystems shall be OPERABLE.
NOTE-------------------------------------------------------------
The main control room boundary may be opened intermittently under administrative control.
APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MCREC subsystem A.1 Restore MCREC 7 days inoperable. subsystem to OPERABLE status.
B. Two MCREC subsystems B.1 Restore control room 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable due to boundary to inoperable control room OPERABLE status.
boundary in MODE 1, 2, or3.
C. Required Action and C.1 Bein MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3.
C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)
)
HATCH UNIT 1 3.7-8 Amendment No. 225
MCREC System 3.7.4 CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and ------------------NOTE------------------
associated Completion Time LCO 3.0.3 is not applicable.
of Condition A not met --------------------------------------------
during movement of irradiated fuel assemblies in D.1 Place OPERABLE Immediately the secondary containment, MCREC subsystem in during CORE pressurization mode.
AL TERATIONS, or during OPDRVs. OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.
AND D.2.2 Suspend CORE Immediately AL TERATIONS.
) AND D.2.3 Initiate action to Immediately suspend OPDRVs.
E. Two MCREC subsystems E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3 for reasons other than Condition B.
(continued)
HATCH UNIT 1 3.7-9 Amendment No. 225
SOUTHERN NUCLEAR For Examiner-Training Use Only PAGE 1 OF 3 PLANT E.I. HATCH FORM TITLE:
REQUIRED ACTION SHEET REQUIRED ACTION SHEET NUMBER SECTION 1 INITIATING CONDITIONS RETURN TO INOPERABLE MPL DESCRIPTION OPER INIT TIMEIDATE TIMEIDATE L--~
1Z41- MCRECfan 0600 4/22/09 C012A -- --- - ----
SECTION 2 REQUIRED ACTION SHEET ACTIVATION INITIATION TIME/DATE REO. RESTORATION TIME/DATE MODIFIED COMPLETION 0600 4/22/09 0600 4/22/09 TIMEIDATE N/A
) EXTENDED COMPLETION SFDP ENTERED INOP STATUS INDIC LIT TIME/DATEIINIT N/A DYES !ZIN/A !ZIYES DN/A APPLICABILITY Modes 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During Core Alterations, During operations with a potential for draining the reactor vessel, (OPDRVs).
REO. ACTION D.1 Place OPERABLE MCREC subsystem in pressurization mode Immediately IF COMP TIME OR EXCEEDED D.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment Immediately AND D.2.2 Suspend CORE ALTERATIONS Immediately AND D.2.3 Initiate actions to suspend OPDRVs. Immediately.
REFERENCE TS 3.7.4 REVISION/AMENDMENT DOCUMENT 225 SS SIGN / TSA ACTIVE SOS SIGN
---- I OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S
SOUTHERN NUCLEAR For Examiner-Training Use Only PAGE 2 OF 3 PLANT E.1. HATCH FORM TITLE:
REQUIRED ACTION SHEET SECTION 5 REQUIRED ACTION SHEET TERMINATION INDICATE COMPLETE(D) ACTIONS:
D PROCEDURES:
D OTHER:
MWOFT INOP STATUS INDIC OFF REQUIRED ACTION TERMINATED TIME/DATE COMPLETE DYES DN/A DYES DN/A SS SIGN / TSA TERMINATED SOSSIGN I i SECTION 3 < 1 HOUR ACTIONS REFERENCE REQUIRED ACTION REQ. COMP TIME PERFORMED INIT DOCUMENT TIME/DATE
/
/
/
/
/
~-- -
/
SECTION 4 > 1 HOUR ACTIONS REFERENCE REQUIRED ACTION REQ. COMP TIME OR SEQ. COMPLETE COMPo DOCUMENT FREQ. NO. TIME/DATE INITIAL Restore MCREC subsystem 3.7.4.A.1 7 days /
to Operable Status.
I I I I
/
fm I I I ~ m ~
/
<< "'~~
[l8:""/&""~ I I I m ~
/
"' I I I
/
I I J ~ ~
OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S
SOUTHERN NUCLEAR PAGE 1 OF2 PLANT E.I. HATCH FORM TITLE:
REQUIRED ACTION SHEET REQUIRED ACTION SHEET NUMBER SECTION 1 INITIATING CONDITIONS RETURN TO INOPERABLE MPL DESCRIPTION OPER INIT TIME/DATE TIME/DATE SECTION 2 REQUIRED ACTION SHEET ACTIVATION INITIATION TIME/DATE REQ. RESTORATION TIMEIDATE MODIFIED COMPLETION TIMEIDATE
\
EXTENDED COMPLETION SFDP ENTERED INOP STATUS INDIC LIT
! TIMEIDATE/INIT DYES DN/A DYES DN/A APPLICABILITY REQ.ACTION IFCOMPTIME EXCEEDED REFERENCE REVISION/AMENDMENT DOCUMENT SS SIGN / TSA ACTIVE SOS SIGN I
SECTION 5 REQUIRED ACTION SHEET TERMINATION INDICATE COMPLETE(D) ACTIONS:
D PROCEDURES:
D OTHER:
MWOFT INOP STATUS INDIC OFF REQUIRED ACTION TERMINATED TIMEIDATE COMPLETE
) DYES DN/A DYES DN/A SSSIGN/TSA TERMINATED OPS-1349 Rev 0 G16.30 L_ ----
SOSSIGN 31 GO-OPS-006-0S
SOUTHERN NUCLEAR PAGE 2 OF2 PLANT E.I. HATCH FORM TITLE:
REQUIRED ACTION SHEET SECTION 3 < 1 HOUR ACTIONS REFERENCE REQUIRED ACTION REQ. COMP TIME PERFORMED INIT DOCUMENT TIME/DATE
/
/
/
/
/
/
SECTION 4 > 1 HOUR ACTIONS REFERENCE DOCUMENT REQUIRED ACTION REQ. COMP TIME OR I SEQ. I COMPLETE I COMPo FREQ. NO. TIME/DATE INITIAL
/
/
OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S
(
DRAFT Southern -uclear E. I. Hatch uclear Plant Operations Training JPM Admin 4, SRO-I TITLE AutHOR MEIJIA*.NoMBER .
DAVID GIDDENS LR-1P-I0029-00
~~--.-
RJhdoMMIDNUlDlJBY* APPRovEnnt NIR Energy to Serve Your World sM
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Pro~am/Course Code: OPERATIONS TRAINING Media Number: LR-JP-I0029
.*~eYr~P'.<J**.* 'SUl>y,'~ .
Initials
UNIT 1 (X) UNIT 2 0 Declare A Tech Spec System Operabiellnoperable LR-JP-10029-00 The task shall be completed when the candidate has provided an answer for each item within the initiating cue.
H-OPSR300.006 H-OP300.006A SRO Administrative PLANT HATCH JTA IMPORTANCE RATING:
RO N/A SRO 3.00 KIA CATALOG NUMBER: G2.3.11 KIA CATALOG JTA IMPORTANCE RATING:
RO N/A SRO 4.3 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)
Specs Unit 1 TRM Unit 1 ODCM 34AR-650-350-1, HX lA PSWIRBCCW DIFF PRESS LOW Annunciator APPROXIMATE COMPLETION TIME: 10 Minutes
) SIMULATOR SETUP: NIA
UNIT 1 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:
/x tA,,( .
- 1. Maintenance reports scaffolding has fallen on a radiation m~or, IDll-K605, severing its electrical cable and causing other damage.
- 2. It is estimated it will be 2 months before a replacement can be delivered.
- 3. Unit 1 "B" RBCCW Heat Exchanger is out of service and under clearance.
- 4. Annunciator 650-350-1 ,"HX lA PSWIRBCCW DIFF PRESS LOW," 1 alarms
- 5. An SO reports the following local pressures:
!~ PSW pressure indicator P41-R577 ....................... 96 psig I ~A" Heat Exchanger PSW Inlet pressure)
I 1-?7 S.) ,e,
/
- 7. I PSW pressure indicator IP41-R578 ..................... 89 psig I I i ("A" Heat Exchanger PSW Outlet pressure) ;c--
f
- 8. i RBCCW pressure indicator IP42-R002A, ............. 92 psig
("A" Heat Exchanger RBCCW Inlet pressure)
I----;a;-
\y RBCCW pressure indicator IP42-R005A, ............. 87 psig
("A" Heat Exchanger RBCCW Outlet pressure)
INITIATING CUES:
Determine if the radiation monitor is fI'required 8nCM--mOIliter and any applicable actions and/or limitations.
]1
\; C~ IJ \' i/
WVV\ J (f if'
!II
\
\
For INITIAL Operator Programs:
)
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
START TIME: _ _ __
- 1. Operator obtains the procedure needed Operator has obtained the Unit 1 SAT/UNSAT references ODCM and other controlled documents.
~~-------.---------.- - -------- ~----~--~-------
Note: The candidate has several means to find the specification for this radiation monitor. One is to use the Master Equipment Cross Reference in the Unit 1 TRM, another is the Tech Spec/TRM/ODCM reference section ofthe ARP.
Operator determines the SAT/UNSAT instrument is a required ODCM monitor.
- 3. I Locate the administrative The candidate identifies that SAT/UNSAT requirements associated with this ODCM section 2.1 contains the
) radiation monitor. requirements for this radiation monitor being inop.
- 4. I Selects the applicable instrument on On table 2-1 determines the SAT IUNSAT table 2-1 of the Unit 1 ODCM. inoperative monitor is addressed in section 2 of the table, as this instrument does not provide any automatic isolation.
- 5. I Evaluates whether the minimum Recognizes the minimum number SAT I UNSAT number of channels OPERABLE is of channels is NOT met.
met from table 2.
- 6. I Evaluates the applicability of the Determines note (2) applies with SAT I UNSAT specification, whether the instrument respect to applicability which is required to be OPERABLE, under states "Whenever the Service the current plant conditions. Water System pressure is below the Closed Cooling Water System pressure, or ~p indication is not available."
Determines the lowest PSW SAT IUNSAT pressure of 89 psig IS lower than the most limiting RBCCW pressure of 92 psig, and concludes that action 101 of table 2-1 must be applied.
Detennines that once per shift SAT/UNSAT grab samples are collected and analyzed for a gross radioactivity at a MINIMUM DETECTABLE CONCENTRATION no higher than IxlO-hlCi/ml.
Identifies that if the instrument is SAT IUNSAT inoperative for over 30 days, "An explanation of the circumstances must be included in the next Radioactive Effluent Release Report."
END TIME:- - - -
NOTE: The tenninating cue shall be given to the Applicant when:
- With no reasonable progress, the Applicant exceeds double the allotted time.
- Applicant states the task is complete.
TERMINATING CUE: That completes this JPM.
1.0 IDENTIFICATION
ALARM PANEL 1H11-P650 HX1A PSW/RBCCW DIFF
~
DIFF PRESS LOW DEVICE: SETPOINT:
1P42-R200A 7 PSID
2.0 CONDITION
3.0 CLASSIFICATION
EQUIPMENT STATUS Plant Service Water to RBCCW differential pressure has
4.0 LOCATION
decreased to setpoint.
1H11-P650 Panel 3 5.0 OPERATOR ACTIONS:
5.1 At 112TCT07, confirm low differential pressure by observing 1P42-B001A, Heat Exchanger, RBCCW Inlet Pressure, on 2P42-PI-R002A to 1P41-PI-R578, Service Water Outlet Pressure.
5.2 Confirm that the Plant Service Water System is in operation per 34S0-P41-001-1, Plant Service Water System.
5.3 At 112TCT07, confirm OPEN 1P41-F399A, 1P42-B001 A, RBCCW Heat Exchanger Service Water Inlet Valve.
5.4 IF RBCCW loads are being isolated remove RBCCW pumps from service as required to maintain Service Water to RBCCW pressure above setpoint.
5.5 THROTTLE 1P41-F206A, RBCCW HX Serv Water Disch Vlv, to increase PSW pressure observing 1P41-PI-R578.
6.0 CAUSES
6.1 Plant Service Water pressure has decreased from the normal operating pressure.
6.2 RBCCW Heat Exchanger service water inlet valve throttled OR closed.
7.0 REFERENCES
8.0 TECH. SPECS.ITRM/ODCM/FHA:
7.1 57SV-CAL-001-1, PSW TO RBCCW dP Channel Cal Unit One, ODCM, 2.1 7.2 H-13613, Wiring Diag Ann Logic Cab 1A Bag D 7.3 H-14036, Wiring Diagram 600V Swgr Bus 1C Frame 7 R23-S003 7.4 H-11609, P&ID Service Water Piping 34AR-650-350-1 Ver.2.2 MGR-0048 Ver. 5.0 AG-MGR-75-1101
)
HNPODCM Table 2-1 Radioactive Liquid Effluent Monitoring Instrumentation OPERABILITY Requirements" Minimum Channels Instrument OPERABLE Applicabilityb ACTION
- 1. Gross Radioactivity Monitors Providing Automatic Termination of Release Liquid Radwaste Effluent Line 1 (1 ) 100
- 2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water System Effluent Line 1 (2) 101
- 3. Flowrate Measurement Devicesc
- a. Liquid Radwaste I
I Effluent Line 1 (1 ) 102
- b. Discharge Canal 1 (1), (2) 102
- 4. Differential Pressure Measurement Devices Service Water System to Closed Cooling Water System 1 At all times 103
- 15. Groundwater Outfall Instrumentation I
- a. Auto Sampler at Y22N008A 1 At all times 104 Y22N012B 1 At all times 104
- b. Flow Totalizer at Y22N008A 1 At all times 105
- c. Flow Meters{d) at Y22N003A 1 At all times 105 Y22N012B
- a. All requirements in this Table apply to each unit.
- b. Applicability of requirements is as follows:
(1)Whenever the radwaste discharge valves are not locked closed.
(2)Wheneverthe Service Water System pressure is below the Closed Cooling Water System pressure, or AP indication is not available.
- c. Pump curves may be used to estimate flow; in such cases, ACTION statement 102 is not required.
) d. With either Y22N003A or Y22N012B nonfunctional, the other functional flow meter will be used to estimate the release rate.
2-3 Version 21 11/07
HNPODCM Table 2-1 (contd) Notation for Table 2 ACTION Statements ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Section 2.1.2.3, and
- b. At least two technically qualified individuals independently verify the discharge line valving and verify the release rate calculations.
Otherwise, suspend release of radioactive effluents via this pathway. If the channel remains inoperable for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report.
ACTION 101 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that once per shift grab samples are collected and analyzed for gross radioactivity at a MINIMUM DETECTABLE CONCENTRATION no higher than 1 x 10-7 J,lCi/mL. If the channel remains inoperable for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report.
ACTION 102 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that the flowrate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. If the channel remains inoperable for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report.
ACTION 103 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, assure that the Service Water System effluent monitor is OPERABLE.
ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, obtain daily grab samples and composite for weekly tritium, monthly gamma, and quarterly gross beta analyses.
ACTION 105 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, estimate outfall flow rate daily. If the channel remains inoperable for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report.
)
2-4 Version 21 11/07
TABLE T10.1-1 (SHEET 8 OF 22)
MASTER EQUIPMENT CROSS REFERENCE - SORTED BY MPL LOSS OF FUNCTION MPLNUMBER~ SPECIFICATION DIAGRAMS 1D11-D042 ODCM 3-1 (3.c.) N/A lO11-DOS1 ODCM 3-1 (1.b.) N/A lO11-DOS1 ODCM 3-1 (1.c.) N/A 1D11-K002 ODCM 2-1 (1.) LFD-1-PRM-01 lO11-K003 ODCM 2-1 (2.) N/A 10 11-KSOOA, B ODCM 3-1 (3.a.) LFD-1-PRM-OS 1D11-KS01, KS02 ODCM 3-1 (4.a.) N/A lO11-KS03A,B,C,D TRM TLCO 3.3.11 LFD-1-MSLR-01 1D11-KS04 ODCM 2-1 (1.) LFD-1-PRM-01 lO11-KSOS ODCM 2-1 (2.) _ N/A lO11-KS09A,B,C,D TS 3.3.S.1-1 (2.d.) LFD-1-PCIS-10 1D11-KS09A,B,C,D TS 3.3.S.2-1 (3.) LFD-1-SCIS-03 1D11-KS11A,B,C,D TS 3.3.S.1-1 (2.e.) LFD-1-PCIS-11 lO11-KS11A,B,C,D TS 3.3.S.2-1 (4.) LFD-1-SCIS-04 1D11-KS1SA,B TRM T3.3.S-1 (1.) LFD-1-PRM-03 lO11-KS1SA,B TRM T3.3.S-1 (2.) LFD-1-PRM-04 lO11-KS19A,B ODCM 3-1 (1.a.) LFD-1-PRM-02 lO11-KS19A,B ODCM 3-1 (1.b.) N/A lO11-KS19A,B ODCM 3-1 (1.c.) N/A lO11-KS19A,B ODCM 3-1 (2.b.) N/A 1D11-KS21A,B TS 3.3.3.1-1 (S.) N/A 1D11-KS21A,B TS 3.3.6.1-1 (2.c.) LFD-1-PCIS-09 1D11-KS22A,B,C,D TRM T3.3.3-1 (4.) N/A 1D11-KS30 TS LCO 3.4.S.b. N/A lO11-K7S1A,B TRM T3.3.S-1 (2.) LFD-1-PRM-04 lO11-K7S2A,B, ODCM 3-1 (3.a.) LFD-1-PRM-OS lO11-N003A,B TS 3.3.3.1-1 (S.) N/A lO11-N003A,B TS 3.3.S.1-1 (2.c.) LFD-1-PCIS-09 lO11-NOOSA,B,C,D TRM TLCO 3.3.11 LFD-1-MSLR-01 1D11-N007 ODCM 2-1 (1.) LFD-1-PRM-01 1D11-NOOS ODCM 2-1 (2.) N/A HATCH UNIT 1 TRM Revision 52
DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 5, RO NIR Energy to Serve Your World SM
SOUTHERN NUCLEAR OPERATING COMPANY
',J PLANT E. I. HATCH Page 1 of1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Pro~am/Course Code: OPERATIONS TRAINING Media Number: LR-JP-I0030
LR-lP-l 0030-00 UNIT 1 ( X) UNIT 2 (.)
Comply with radiation work permit requirements during normal or abnormal conditions .
.JPMNtIMBitR: LR-1P-I0030-00 The task shall be completed when the operator has determined:
dress out requirements, time before dosimetry alarm occurs, actions if an alarm occurs and when a brief is required.
TASK NtrMBER: NIA
()1JJEC.'l'IV-E.*NUMl1ERl NIA TYPE N/A PLANT HATCH JTA IMPORTANCE RATING:
)
KIA CATALOG NUMBER: G2.3.7 KIA CATALOG JTA IMPORTANCE RATING:
RO 3.5 SRO 3.6 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)
- GE;NJ!j~t*REjEtiENCE8:
~QlJI~]!jDi\1ATE'I.ttLS:>; *1*.*Tl~;i**'1 APPROXIMATE COMPLETION TIME: 10 Minutes SIMULATOR SETUP: N/A
UNIT 1 READ AND GIVE A COpy TO THE OPERATOR INITIAL CONDITIONS:
1 Unit 1 is at 100% power with no significant problems.
- 2. R WP 09-0004 is one of Operations current R WPs.
- 3. Health Physics survey 45552 is the latest survey ofthe Unit 1 Condensate Demin Valve nest.
- 4. You need to enter the Unit 1 Condensate Demin Valve Nest to perfonn an OJT module and train a new System Operator (SO).
- 5. HP approval has been granted to use minimum requirements for entry.
- 6. Assume the survey map is current.
\
! INITIATING CUES:
Using RWP 09-004 and survey map 45552 detennine the following infonnation:
- What, if any, are the minimum dress requirements for entry
- Assuming the highest current General Area Dose Rate, calculate the maximum stay time before the DAD alanns on dose accumulated.
- Required actions if the DAD alanns on dose accumulated.
- Assuming plant conditions change, detennine the minimum General Area Dose Rate which would REQUIRE an HP brief prior to entry
LR-JP-10030-00
,)STEP'# **,PERF()RMANi1EStEP
. SAXt(JNSAT
/(JOMMENTS'* .
i For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
START TIME: _ _ __
Note: Provide the candidate with RWP 09-0004 and survey 45552.
Operator determines that lab coat, SAT IUNSAT booties, and gloves are required when entering this area
) t)eteWi~Yithe*11l,aXi11l¥I11Sf~Y~i1he' Operator determines the max stay SAT IUNSAT b9{0t:eJ~eDADalarnlS9p.QO~e . time is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
- 1*acc::tiI111111i~ed.
Operator determines that SAT IUNSAT immediate exit and HP notification is required .
.. "~~d ***I1)~f~tn'1i~~thel11i~irtttl~~e~~t~li{\r,?~***. Operator determines that> .1 SAT/UNSAT
.* t)()sy;~ate~hi~lI:~?lll<i~QIJIRE*.~*.** Rem/hr (100 mr/hr) requires a
'1-lJ=tbriyrpriwtQYutry . brief.
NOTE: Per RWP, a briefing is required prior to entry into a High Rad Area which is defined as > .1 Remlhr.
END TIME:- - - -
NOTE: The terminating cue shall be given to the Applicant when:
- With no reasonable progress, the Applicant exceeds double the allotted time.
- Applicant states the task is complete.
TERMINATING CUE: That completes this JPM.
r Plant Hatch
)R d' .
, alation Work Permit 09-0004 ACTIVE Job Operations Inspection, Surveillance and Fire Watch - This RWP not for entries into Locked High Rad or Very High Rad Description Areas J I Location GENERAL PLANT LOCATION j~~
f"~it Ii ';~
HP Coverage Authorization Briefing Start Date 111/2009 End Date 11112010 INTERMITTENT WORK GROUP CONDITIONAL Job Supv. SOS Ext. 5959 Tasks DAD Alanns JlI i
Description i Dose (mr) Rate (mrlh)
OPS Rounds, Clearances, Surveil. 25 500 OPS Control Room Activities 10 50 Supervision / Observation 20 100 Usage is Conditional per HP
~I Instructions
!~ IDAD's must be accessible for visual monitoring. Monitor DAD periodically while in the RCA.
~f:! Lab Coats, Booties & Gloves allowed for training, inspections, surveillances, Step Off Pad maintenance or Light Work (with HP
~fi approval)
~ilUnless otherwise specified by HP, full dress is required for contaminated area entry.
~ Iu se Cameras in lieu of entry, when possible, to reduce exposure.
Entries into Locked High Rad or Very High Rad areas are not permitted on this RWP.
Briefing required prior to entering a High Radiation Area Healtb Physics 12/26/2008 08:25 Approved Suspended Terminated Staff by DPHOBBS
Plant Hatch Radiological Information Survey # 45552 07/19/2008 11 :25 Page 1 U1 Condensate Demin Valve Nest (1TB112)
')
Status: Approved Rx Reactor Power: 100%
Performed By: Lindy Williams Reactor Mode: 1 Danny Sweat H2 Injection Level: 10 Max Dose Rate: 5 mrem/hr Void Level: 0 MaxCntm: <MDA dpm/1 00 cm2 System Running: Yes Approved By: Williams, Lindy 07/20/200803:50 Survey Dose: 1
Purpose:
Routine Survey Remarks: Di Rad 03-1087N Survey Component:
ASR#s RWP#s 08-0001 Instrument Description Comment 42123-1 TENNELEC 5680 -- ---
RO-20
)ngs:
if Type Description 1 Caution - Rad Sign Contaminated Area Radiation Area Radioactive Material
Plant Hatch Radiological Information Survey # 45552 07/19/2008 11 :25 Page 2 2 Catch Basin _J 3 Caution - Rad Sign Contaminated Area I Radiation Area
) Radioactive Material Point Data:
- Point Type Value Units Level Comments 1 Flex Dose Rate - Gamma G/A <2 mrem/hr Low-Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 2 Flex Dose Rate - Gamma G/A 3 mrem/hr Low Flex Dose Rate - Gamma Contact 5 mrem/hr Low-Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 3 Flex Dose Rate - Gamma G/A 2 mrem/hr Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 4 Flex Dose Rate - Gamma G/A 3 mrem/hr Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 5 Flex Dose Rate - Gamma G/A 4 mrernlhr Low Flex Dose Rate - Gamma Contact 8 mrem/hr Low-Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low r --~Iex Dose Rate - Gamma G/A 2 mrem/hr Low I-
}Iex Contamination - Alpha <20 dpm/100 cm2 Low-Low I--
Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 7 Flex Dose Rate - Gamma G/A 3 mrem/hr Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 8 Flex Dose Rate - Gamma G/A 4 mrem/hr Low Flex Dose Rate - Gamma Contact 8 mrem/hr Low-Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 9 Flex Dose Rate - Gamma G/A 2 mrem/hr Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 10 Flex Dose Rate - Gamma G/A <2 mrernlhr Low-Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 11 Flex Dose Rate - Gamma G/A 3 mrem/hr Low Flex Dose Rate - Gamma Contact 8 mrem/hr Low-Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 12 Flex Dose Rate - Gamma G/A 2 mrem/hr Low
,Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low f- _ j=lex Contamination - BIG <MDA dpm/100 cm2 Low-Low 13 - Flex Dose Rate - Gamma G/A 3 mrernlhr Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 14 Flex Dose Rate - Gamma G/A 5 mrem/hr Low
Plant Hatch Radiological Information Survey # 4555207/19/200811 :25 Page 3 Flex Dose Rate - Gamma Contact 10 mrem/hr Low-Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low
~Jex Contamination - BIG <MDA dpm/100 cm2 Low-Low r-1 Jex Dose Rate - Gamma G/A 2 mrem/hr Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 16 Flex Dose Rate - Gamma G/A 3 mrem/hr Low i Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 17 Flex Dose Rate - Gamma G/A 4 mrem/hr Low Flex Dose Rate - Gamma Contact 9 mrem/hr Low-Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 18 Flex Dose Rate - Gamma G/A 2 mrem/hr Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 19 Flex Dose Rate - Gamma G/A 4 mrem/hr Low Flex Dose Rate - Gamma Contact 9 mrem/hr Low-Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 20 Flex Dose Rate - Gamma G/A 2 mrem/hr Low Flex Contamination - Alpha <20 dpm/100 cm2 Low-Low Flex Contamination - BIG <MDA dpm/100 cm2 Low-Low 21 Flex Temperature 109 Deg F High-High r----
)ex Humidity 30 % Low-Low
DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 6, SRO Only N/R
) Energy to Serve Your World SM
SOUTHERN NUCLEAR OPERATING COMPANY "pLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number:
00 FNF
UNIT 1 (X) UNIT 2 0 Develop Duty Roster For Extended Emergency Activities LR-JP-200.108-00 The task shall be complete when the operator has completed review and/or approval of1RN-0115, "Authorization To Exceed 10 CFR 20 Limits".
H-OPSR200.108 PLANT HATCH JTA IMPORTANCE RATING:
RO N/A SRO 4.08 KIA CATALOG NUMBER: 02.4.38 KIA CATALOG JTA IMPORTANCE RATING:
RO N/A SRO 4.4 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)
APPROXIMATE COMPLETION TIME: 10 Minutes SIMULATOR SETUP: N/A
) UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. An A TWS has occurred with fuel damage.
- 2. A General Emergency has been declared.
- 3. You are the Emergency Director.
- 4. The OSC is manned and requests your review and approval for emergency radiation exposures.
l~ITIATING CUES:
Review and approve the forms for "Authorization To Exceed 10 CFR 20 Limits" per the guidelines of 73EP-EIP-017-0, "Emergency Exposure Control".
)
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
NOTE: Provide the operator with the attached TRN-0115 Forms.
START TIME: _ _ __
- 1. Obtains the correct procedure. Emergency Director obtains a SAT I UNSAT copy of 73EP-EIP-OI 7-0.
- 2. Reviews precautions and limitations. Emergency Director reviews SAT/UNSAT precautions and limitations.
- 3. Reviews procedural guidelines for Emergency Director reviews SAT I UNSAT dose. "Emergency Response Personnel Exposure Guides" table.
- 4. Reviews first form for "Authorization Emergency Director reviews form SAT/UNSAT To Exceed 10 CFR 20 Limits". TRN-0115 for Mary T. Jones.
- 5. Determine if operator meets the dose Emergency Director determines SAT I UNSAT guidelines of73EP-EIP-017-0. Mary T. Jones does NOT meet the guidelines.
NOTE: Limitation 5.2.3, limits declared pregnant females dose to normal operating procedures (60AC-HPX-00I-0: 50 mr/month, 450 mr total).
Emergency Director does NOT SAT I UNSAT sign form TRN-0115 for Mary T.
Jones.
- 7. I Reviews second form for Emergency Director reviews form SAT/UNSAT "Authorization To Exceed 10 CFR 20 TRN-0115 for Jack R. Smith.
Limits".
- 8. I Determine if operator meets the dose Emergency Director determines SAT I UNSAT guidelines of73EP-EIP-017-0. Jack R. Smith DOES meet the Emergency Director DOES sign SAT/UNSAT form TRN-0115 for Jack R.
END TIME:
NOTE: The terminating cue shall be given to the Applicant when:
- With no reasonable progress, the Applicant exceeds double the allotted time.
- Applicant states the task is complete.
TERMINATING CUE: We will stop here.
SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:
1 DOCUMENT NUMBER:
IPAGE 6 OF 13 REVISION NO:
EMERGENCY EXPOSURE CONTROL 73EP-EIP-017-0 3.0 7.4 EMERGENCY EXPOSURE GUIDELINES 7.4.1 The Emergency Director will establish the exposure limits for the emergency response personnel based on the following Emergency Response Personnel Exposure Guides:
NOTES: I* These guidelines do not establish a rigid upper limit of exposure. The Emergency Director may use his/her judgment in establishing the appropriate limit.
- No thyroid limit is specified for lifesaving action since the complete loss of the thyroid may be considered an acceptable risk for saving a life; however, thyroid exposure must be minimized through the use of respiratory protection and/or KI tablets.
EMERGENCY RESPONSE PERSONNEL EXPOSURE GUIDES Dose Limit* Activity Condition (REM) 5 all n/a 10 protecting valuable lower dose not practicable property 25 life saving or protection of large lower dose not practicable populations
>25 life saving or protection of large to only on a voluntary basis persons populations fully aware of the risks involved
- This limit is expressed as the sum of the effective dose equivalent (EDE) and the committed effective dose equivalent (CEDE). The lens of the eye will normally be limited to three (3) times the values AND doses to other organs (including skin and extremities) will normally be limited to ten (10) times the listed value.
7.4.2 Review the qualifications of the volunteer emergency response personnel to ascertain which volunteers would have the highest probability of completing the rescue while accumulating the least exposure.
7.4.3 Review the exposure history of the emergency response personnel for current accumulated exposure levels.
)
MGR-OOOl Rev. 1
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
1 DOCUMENT NUMBER:
PAGE 7 OF 13 REVISION NO:
EMERGENCY EXPOSURE CONTROL 73EP-EIP-017-0 3.0 NOTE: Authorizing signatures of emergency volunteers and the Emergency Director will normally be obtained prior to receiving emergency exposure; however, to expedite Search and Rescue operations, verbal authorization by all parties is sufficient until signatures can be obtained.
7.4.4 Complete Form TRN-0115, Authorization To Exceed 10CFR20 Exposure Limits, with the following information:
7.4.4.1 Emergency response personnel's name, TLD number and security badge number.
7.4.4.2 Emergency response personnel yearly accumulated exposure.
7.4.4.3 Authorized exposure limit, and if applicable, thyroid emergency exposure limit.
7.4.4.4 Date and time limitations associated with authorized emergency limits.
7.4.4.5 Signature of volunteer emergency response personnel indicating awareness of exposure limit extension AND risks associated with the exposure. A summary of risks associated with large doses of radiation may be found in Attachment 1.
7.4.4.6 Authorization of the Emergency Director.
MGR-OOOl Rev. 1
SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 1 OF 1 FORM TITLE: AUTHORIZATION TO EXCEED 10 CFR 20 LIMITS
)
MARY T. JONES 9872 3455 (FIRST) (M.I.) (LAST) TLD NUMBER SECURITY BADGE NO is authorized to receive an exposure of 7 REM and a thyroid exposure of 0 REM for the period of 04/20/09 to 04/21/09 Reason for requesting exposure in excess of 10CFR20 limits:
A fire in the HPCI Room requires manual actuation of the sprinkler system. The operator is the only volunteer to actuate the sprinkler system. Mary is a declared pregnant female, 32 years old, in good health and understands the risks associated with the exposure.
Current year exposure:
) Exposure determined by:
25 mr Barry Barns 4/20109 EXPOSURE IN EXCESS OF 10CRF20 LIMITS EXPOSURE ABOVE 25 REM I have been made aware of the extension of my I have been made aware of the risks involved exposure limits. with the exposures listed above and I accept that risk.
4/20/09 'Nlit Date nature 1 Date APPROVAL 1
Emergency Director Date TRN-0115 Rev. 2 G16.70 73EP-EIP-017-OS
SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 1 OF 1 FORM TITLE: AUTHORIZATION TO EXCEED 10 CFR 20 LIMITS JACK R. SMITH 1802 9458 (FIRST) (M.I.) (LAST) TLD NUMBER SECURITY BADGE NO is authorized to receive an exposure of 35 REM and a thyroid exposure of 0 REM for the period of 04/20109 to 04/21/09 Reason for requesting exposure in excess of 10CFR20 limits:
A man is injured and pinned in a high radiation area and is expected to receive a lethal dose in 60 minutes. The operator is the only volunteer to perform a rescue. Jack is a 49 year old man, in good health and understands the risks associated with the exposure.
Current year exposure:
Exposure determined by:
1200 mr Barry Barns 4/20109 EXPOSURE IN EXCESS OF 10CRF20 LIMITS EXPOSURE ABOVE 25 REM I have been made aware of the extension of my I have been made aware of the risks involved exposure limits. with the exposures listed above and I accept that risk.
TM"k. g. Smit6- 4/20109 1m 1<. Smith, 4/20109 Date Date APPROVAL 1
Emergency Director Date TRN-0115 Rev. 2 G16.70 73EP-EIP-017 -OS
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
1 DOCUMENT NUMBER:
IPAGE 3 OF 13 REVISION NO:
EMERGENCY EXPOSURE CONTROL 73EP-EIP-017-0 3.0 5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS 5.1.1 The risks of actual or potential radiation induced damage must carefully be weighed against the benefits to be gained when authorizing exposures in excess of 10CFR20 limits.
5.1.2 Every reasonable effort must be made to maintain personnel exposures, As Low As Reasonably Achievable (ALARA).
5.1.3 Personnel known to be allergic to KI must not be given KI tablets.
5.1.4 Personnel who experience potential allergic reactions after having taken KI must not be administered any additional KI AND must be given immediate medical attention. Possible reactions to KI include skin rashes, swelling of salivary glands, and "iodism" (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold, and sometimes stomach upset and diarrhea).
5.1.5 After consultation with HP supervision, the Emergency Director may determine that emergency response personnel who have to enter any area of airborne radioactivity prior to air sample analysis may be administered KI as a precautionary measure.
5.2 LIMITATIONS 5.2.1 Doses to workers performing emergency services will be treated as a once-in-a-lifetime exposure.
5.2.2 Radiation doses to all workers during emergencies will, to the extent practicable, be limited to 5 REM. Justification of exposures above 5 REM must include the presence of conditions that prevent the rotation of workers or other commonly used dose reduction methods.
5.2.3 To assure adequate protection of minors and the unborn during emergencies, declare~
pregnant individuals exposures will be controlled in accordance with normal operating procedures.
5.2.4 The effectiveness of Potassium Iodide (KI) as a blocking agent drops quickly as a function of time AND therefore must be taken as soon as possible after authorization by the Emergency Director. The following guide provides an approximation of the effectiveness:
5.2.4.1 KI tablet taken before or concurrently with exposure is 90% effective.
5.2.4.2 KI tablet taken 3 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after exposure is 50% effective.
5.2.4.3 KI tablet taken 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after exposure has only limited effect.
MGR-OOOl Rev. 1
PAGE 4 OF 13 SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
I DOCUMENT NUMBER: REVISION NO:
EMERGENCY EXPOSURE CONTROL 73EP-EIP-017-0 3.0 5.2.5 KI has a shelf life specified by the distributing pharmaceutical company AND must be replaced prior to expiration.
5.2.6 Any rescue action that may involve substantial personnel risk must be performed by volunteers. Each of the emergency workers must be advised of the known estimated extent of such risk prior to participation. Healthy volunteers above the age 45 will receive first consideration.
6.0 PREREQUISITES 6.1 This procedure will be utilized for drills, exercises and actual emergencies.
REFERENCE I
7.0 PROCEDURE Emergency response personnel may receive exposure under a variety of circumstances in order to assure protection of others and of valuable property. These exposures will be justified if the risks permitted to the workers are acceptably low, AND the costs to others that are avoided by their actions outweigh the risks to which workers are subjected.
7.1 SAVING OF HUMAN LIFE Where the potential risk of radiation hazard following the nuclear incident is such that life would be in jeopardy, or that there would be severe effects on the public health or loss of property detrimental to the public safety, the following criteria for saving of human life shall apply:
7.1.1 In consultation with HP supervision, the Emergency Director will evaluate the risks involved versus the benefits to be gained by considering the following:
7.1.1.1 The reliability of the prediction of radiation injury. Consideration must be given to limits of error associated with specific instruments AND techniques used to estimate the dose rate. This is especially crucial when the estimated dose approximates 100 REM or more.
7.1.1.2 Assessment of the capability of reducing inherent risks from the hazard through the use of appropriate mechanisms such as protective equipment, remote manipulation equipment or similar means.
7.1.1.3 The probable effects of acute exposure that may be incurred AND numerical estimates of the delayed effects. These effects are listed in Attachment 1 Emergency Worker Risks and Delayed Health Effects Associated With Large Doses of Radiation.
7.1.1.4 The probability of success of the emergency action.
MGR-OOOl Rev. 1
SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:
1 DOCUMENT NUMBER:
PAGE 5 OF 13 REVISION NO:
EMERGENCY EXPOSURE CONTROL 73EP-EIP-017-0 3.0 7.1.2 Make exposure authorizations in accordance with subsection 7.4 Emergency Exposure Guidelines.
7.2 PROTECTION OF HEALTH AND PROPERTY 7.2.1 When the Emergency Director in consultation with HP supervision, deems it necessary to reduce a hazard OR potential hazard to acceptable levels to prevent a substantial loss of property, an exposure of up to, but not to exceed, 10 REM may be received by individuals participating in the operation.
7.2.2 The person in charge of emergency action at the incident scene may elect, under special circumstances (e.g., first aid, removal of injured personnel, etc.), to waive these limits AND permit volunteers to receive an exposure up to, but not to exceed, 25 REM.
7.2.3 Where the potential risk of radiation hazard following the nuclear incident is such that life would be in jeopardy, that there would be severe effects on the public health OR loss of property detrimental to the public safety, the criteria for saving of human life (subsection 7.1) shall apply.
7.2.4 Make exposure authorizations in accordance with subsection 7.4 Emergency Exposure Guidelines.
) 7.3 RECOVERY OF DECEASED VICTIMS 7.3.1 Since the element of time is not a critical factor, the recovery of deceased victims must be well planned. The amount of radiation exposure received by persons in recovery operations shall be controlled within existing occupational exposure guides.
7.3.2 In situations where bodies are located in areas which are inaccessible because of high radiation fields, where the recovery mission would result in exposure in excess of occupational exposure limits, the use of special remote recovery devices will be considered to retrieve the bodies.
7.3.3 In special circumstances where it is impossible to recover bodies without the entry of emergency response personnel into the area, the Emergency Director may determine it necessary to exceed the occupational exposure limits.
7.3.4 Exposures received under these circumstances will be controlled in accordance with subsection 7.4, Emergency Exposure Guidelines.
MGR-OOOl Rev. 1
DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 7, RO
)
NIR Energy to Serve Your World SM
I,PLANT SOUTHERN NUCLEAR OPERATING COMPANY E. I. HATCH Page 1 of 1 r
FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: LR-JP-25020 01 10/01192 General revision and format change WMM SMC General revision, word processor change, adjust 02 07114/94 RAB SMC format Updated to NMP-AD-003 "Equipment Clearance and Tagging" requirements, update to new JPM format, 03 07/05/05 BKW RAB Include initial operator statement for successful completion 04 05111106 Remove Response Cues BKW RAB Corrected "Supplement 1" based on procedure 05 10/24/06 BKW DHG requirement.
)
LR-JP-25020-05 UNITl () UNIT 2 (X)
PREPARE EQUIPMENT DANGER TAGOUT LR-JP-25020-05 The task shall be completed when the operator has generated a Danger Tagout for RBCCW Pump 2A per procedure NMP-AD-003 "Equipment Clearance and Tagging".
- T:~$Kt'NIiMBER: 300.016 OBJ"E~iIVE'NtJMlJlDR:" 300.016.0 PLANT HATCH JTA IMPORTANCE RATING:
RO 3.20 SRO 2.74 KIA CATALOG NUMBER: 2.2.13 KIA CATALOG JTA IMPORTANCE RATING:
RO 4.1 SRO 4.3 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)
NMP-AD-003 Equipment Clearance and Tagging (current version)
NMP-AD-003-FOI Tagout Cover Sheet (current version)
NMP-AD-003-F02 Tagout Tag Listing (current version)
NMP-AD-003-F08 Tagout Preparation And Approval Checklist (current version) 34S0-P42-001 Reactor Building Closed Cooling Water System (current version)
NMP-OS-002 Verification Policy (cun~ent version)
Plant Drawimr H-260S4 NMP-AD-003 Equipment Clearance and Tagging (current version)
NMP-AD-003-F01 Tagout Cover Sheet (current version)
NMP-AD-003-F02 Tagout Tag Listing (current version)
NMP-AD-003-F08 Tagout Preparation And Approval Checklist (current version) 34S0-P42-001-2 Reactor Building Closed Cooling Water System (current version)
NMP-OS-002 Verification Policy (current version)
Plant Drawing H-26054
)
APPROXIMATE COMPLETION TIME: 40 Minutes SIMULATOR SETUP: N/A
')
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. The RBCCW Pump 2A, 2P42-COOIA, has tripped.
- 3. The Maintenance Foreman believes that the pump impeller may be bound and is writing up the MWO to investigate the pump trip. Maintenance will require a Danger Tagout on RBCCW Pump 2A.
- 4. The eSOMs Software System is down and will not be restored for several days.
- 6. The last manual tagout number used was 2-DT-09-2T46-30002, per section 4.0 ofNMP-AD-003.
INITIATING CUES:
Prepare a Danger Tagout for RBCCW Pump 2A, per Section 6.5 of NMP-AD-003.
LR-JP-2S020-0S For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
NOTE: Steps of this JPM may be completed in any order.
START TIME: _ _ __
- 1. Operator identifies the procedure Operator has IDENTIFIED the SAT I UNSAT needed to perform the task. correct procedure as NMP-AD-003 .
- 2. Operator identifies the procedure Operator has IDENTIFIED the SAT IUNSAT
- manual forms needed to perform the correct procedure manual forms task. as FO 1 and F02.
- 3. Operator identifies the reference Operator has IDENTIFIED the SAT IUNSAT
) materials which are required. required reference materials and where to obtain them.
Possible Ref Material:
- NMP-AD-003
- H-260S4 i
- 4. Operator determines "A" RBBCW Operator has DETERMINED that SAT/UNSAT Pump control switch requires a tag. "A" RBCCW Pump Control switch requires a tag.
NOTE: The valves listed in this JPM are the minimum requirements for safe tagging. Components tagged in excess of this minimum will require a case-by-case determination by the evaluator.
(*
- Indicates critical step)
LR-JP-2S020-0S The operator has DETERMINED the following must be tagged:
2R23-S003 FR 2B, pump breaker SAT IUNSAT 2P42-F004A, pump suction vlv SAT 11JNSAT 2P42-F005A, pumlJ discharge vlv SAT/UNSAT 2P42-FD005, disch line drain vlv SAT I UNSAT 2P42-F044A, pump casing vent SAT IUNSAT valve
- 6. I Complete the following on the Tagout On the Tagout Cover Sheet Cover Sheet (Form 01): (F onn 01), the operator has COMPLETED the following:
<D ?~Q't~Q1'1I~A Number <D Clearance Number DT-09 I(j) SAT I UNSAT CV Tagout Number Q) Tagout Number -
Q) 2-DT-09-2P42-30003 IUNSAT Component Affected Component Affected -
RBCCW Pump 2P42-COOIA I SAT I UNSA T Description Description - Investigate I@ SAT I UNSAT problem with RBCCW pump Ops Instructions @ Ors Instructions - Notify Lab I@ SAT I UNSAT prior to draining to Radwaste
@ Holder Instructions Holder Instructions - None I SAT I lJNSAT
<V References <V References - H26054 I <V SAT I UNSA T PROMPT: IF the operator addresses the Tagout Number, PROVIDE copy of Training Reference "Form 06 - Clearance Tagout Log Sheet".
- 7. Tagout Attributes @ Tagout Attributes- SAT IUNSAT May be left blank
! 8. WorkDoc Holder List WorkDoc Holder List - SAT IUNSAT
/
May be left blank
(*
- Indicates critical step)
LR-JP-2S020-0S PROMPT: IF the operator addresses Tagout Attributes, INFORM the operator as the Shift Supervisor that no additional attributes are required for this tagout.
PROMPT: IF the operator addresses WorkDoc No., INFORM the operator as the Maintenance Foreman the MWO is not written yet and a number has not been generated.
- 9. I Complete the fonowing on the Tagout On the Tagout Tag Listing Tag Listing (Form 02): (Form 02), the operator has COMPLETED the following:
<D Clearance Number <D Clearance Number - 2-DT-09 I<D SAT I UNSAT Q) Tagout Number ~ Tagout Number-2-DT-09-2P42-30003 I @ SAT I (JNSAT On the Tagout Tag Listing (FornI 02), the operator has COMPLETED the following:
@( Tag " fype-- SAT/UNSAT
- Similar to supplement 1 Equipment ID and description I location- @SAT/UNSAT
- Similar to supplement 1 Placement configuration and sequence - SAT/UNSAT
- Similar to supplement 1 Verification requirement -
@SAT/UNSAT
- Similar to supplement 1 PROMPT: IF the operator addresses Tag serial numbers, INFORM the operator as the Shift Supervisor that the Tag numbers will be created when the Tagout is Authorized.
(*
- Indicates critical step)
LR-JP-2S020-0S
- 11. Complete the following on the Tagout On the Tagout Cover Sheet SAT IUNSAT Cover Sheet (Form 01): (F orm 01), the operator has COMPLETED the following:
Tagout Verification Tagout Verification Prepared Name & Date PreQared Name & Date -
Operator Signs & Dates Tagout as Preparer PROMPT: IF the operator addresses review or authorization of Tagout, INFORM the operator as the Shift Supervisor that another Shift Supervisor will review the Tagout and forward it to him for authorization.
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.
(*
- Indicates critical step)
Southern Nuclear Operating Company Nuclear NMP-AD-003-FOI SOUTHERN COMPANY A. Management Tagout Cover Sheet Version 1.0
',fnergy tQS/TIJ.t YMtT World~
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Procedure '----- --'--
Page 1 of 1
~
Clearance:
ragout:
\1)
Til Component Affected: '-../
7:\
\..Jj
Description:
T:\
'---'9 OPS Instructions:
r.:\
\:57 Holder Instructions:
/:\
-col
)
References:
n . _ --------8 Tallout Attributes:
Attribute Attribute Description Value T;)
~
W orkDoc Holder List*
Number / Equipment ID Description 1sl Verified 2nd Verified
~
\!J Ta!!out Verifi ----~--.
Status Description N~ Verification Date Prepared Prepared l14 J Reviewed Reviewed ""'--'"
Authorized Authorized Tags Verified Hung Tags Verified Hung Removal Prepared Removal Prepared Removal Reviewed Removal Reviewed Removal Authorized Removal Authorized Tags Verified Removed Tags Verified Removed I Records Forwarded Records Forwarded Pagel 01_
For Training Use Only - JPM Reference LR-JP-2S020-0S Page 7 of 10
souillDNA.
Nuclear Management
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Tagout Tag Listing NMP-AD-003-Fl Version 1.0
_/
---1I COMPANY I I
Energy to s~ Your WorlJ~
Procedure Page 1 of 1 Tagout Tag List I Clearance: # :
Tagout: #:
~
\, I 2 (2)i-Tag Egui12ment Placement Restoration Num Type Egui12ment ID Verif Seq Configuration 1st 2nd Verif Description/Location Notes -. Verif Verif
@ 1: ..,
~ I@ @ 71')
."'-7 For Training Use Only - JPM Reference LR-JP-25020-05 Page 8 ofl0
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Nuclear NMP-AD-003-P ~
so~~A COMPANY Management
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Clearance Tagout Log Sheet Version 1.0 Energy toS~ ~u,. W&rkl" Procedure Pa e 1 of 1 UNIT 2 Clearance Tagout Installed Released Type Number Number Component Affected Reason for Tagout Date Initials Date Initials DT 2-DT-09 2P33-30000 2P33-F003 Repair air leak 1/24/09 BKW 1/26/09 BKW DT 2-DT-09 2El1-30001 2Ell-F007A Quarterly PM 2/05/09 ARB 2/06/09 MMG ,
DT 2-DT-09 2T46-30002 2T46-DOOIB DOPTest 3/15/09 CME 3/16/09 ARB For Training Use Only - JPM Reference LR-JP-2S020-0S Page 9 of 10
Nuclear Southern Nuclear r
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'-ating Company NMP-AD-003-Fl,~
sou~iiRNA. Management Tagout Tag Listing Version 1.0 COMPANY En~'V toSn-ue lbur world" Procedure Page 1 of 1 JPM 25020 Supplement 1 Tagout Tag List Clearance: # : 2-DT-09 Ta!2:out:
- 2-DT-09-2P42-30003 I I I "Verir' Tag Equipment Placement requirements estoration may be "SV, Num Type Equipment ID Verif Seq C~ "CV" or "IV" erif Seq Configyration 1st 2no
~ ~
Danger Description/Location 2P42COOIA CS RBCCW Pmp 2A, 2Hlll'u.;)u r~ - 1 OFFIPTL
~LLL r
~'LL
./
CS Tagging is "
Notes Verif Verif 2R23S003 FR 2B RA Cl\..\.Il.
- normal but not !
Danger RBCCW Pmp 2A, 130 U2 CV 2 a "Critical C/B Task". I I
2P42F004A HW CLOSED "I Danger CV 3 RBCCW Pump 2A Suet Vlv 2P42FOOSA HW CLOSED Danger CV 4 RBCCW Pump 2A Disch Vlv 2P42FDOOS HW OPEN Danger CV S RBCCW Pmp 2A Dis Line drn 2P42F044A HW OPEN Danger CV 6 RBCCW Pmp 2A casing vent ~- . . . .
For Training Use Only - JPM Reference LR-JP-2S020-0S Page 10 of 10
Southern Nuclear Operating Company Nuclear NMP-AD-003 SOUIHERN'\ Management Equipment Clearance and Tagging Version 11.0 COMPANY b'tl-tr[Ol /tI$rMJt YtutrWoYld~ Procedure Page 7 of 34 4.20 Supplemental Worker Supervisor - An individual or a "Plant Position" identified as a Tagout Holder. Typically, this will be the job supervisor. This individual shall sign on to a Tagout electronically as a Work Document Holder and shall maintain the Supplemental Worker List for the associated work document. This individual shall be responsible for briefing the Supplemental Workers and keeping them informed of Tagout boundaries and protections provide by the Tagout. This individual may not sign off the Tagout as Work Doc Holder until all supplemental workers have signed off the Supplemental Worker List.
4.21 Tagger - A qualified person, who repositions equipment per a Tagout and hangs, removes or verifies tags.
4.22 Tagging Official- The Tagging Desk Operator (TDO), Unit Shift Supervisor C&T (USS C&T), Shift Support Supervisor (SSS), Shift Technical Advisor (STA) or Shift Supervisor that may perform all Clearance and Tagging functions outlined in this procedure. The Tagging Official can serve as designee for the Shift Supervisor, provided that person is cognizant of the plant's status/configuration and the Shift Supervisor is made aware of all resultant changes to the plant configuration.
4.23 Tagout - A tool used to uniquely identify and authorize a collection of data to remove equipment from service, track component changes, track activities associated with the entity and return the equipment to service. A Tagout is a unique document that is used once and only once and is then stored as a completed document.
4.24 Tagout Holder - An individual or a "Plant Position" identified on a Tagout Holder List. This individual is usually the "lead" person responsible for the overall direction of a crew performing maintenance or an individual requiring administrative hold on a Tagout. It can also be the "Authorized Employee" or "lead" person responsible for performing a test or maintenance under an Operating Permit Tagout.
4.25 Tagout Lockout - A Tool used on Tagouts to Preclude Sign-on of Tagout Holders and Work Document Holders.
4.26 Tagout Number - A unique control number assigned to a Tagout document. The Tagout Number will be a 6-part alpha numeric designator using the unit number, Clearance Tagout Type, year or outage identifier, system number, consecutive or assigned number and the revision number. Example: 1-DT-04-1208(E11)-00014(002) would be the second revision of the fourteenth Danger Tagout document issued in 2004. The unit 1 designator will be used for unit one and common equipment. Computer generated Tagouts will be assigned the next sequential number available. Manual or hand written Tagouts will be numbered sequentially starting with the number 30,000 proceeded by the unit, Tagout type, system number and year. An index will be maintained to prevent duplication of manually generated Tagout numbers and can be discarded at the end of the calendar year.
4.27 Tagout Point - Any device, valve, breaker, switch, etc. that is positioned by a step on a Tagout.
Southern Nuclear Operating Company Nuclear NMP-AD-003 SOUTHERN COMPANY A Management Equipment Clearance and Tagging Version 11.0 EnnvttlStrNJ&.,.Wo"ur Procedure Page 80f34 4.28 Tag Numbers - The number placed on each Tag. The Tag Number will be a 4-part alpha numeric designator using the unit number, Clearance Tagout Type, year issued, and the consecutive number. Example: 1-DT-04-00014 would be the fourteenth Danger Tag issued in 2004. Outage Tags will be identified by the Outage number replacing the year issued field.
Example 1-DT-R14-00014 the R14 would identify the Outage code. Manual or hand written tags will be numbered sequentially starting with the number 30,000 proceeded by the unit, Clearance Tagout type, and year. An index will be maintained to prevent duplication of manually generated tag numbers and can be discarded at the end of the calendar year.
4.29 Tags - See NMP-AD-003-001, "Tag Standards" for Tag definitions.
4.30 Temporary Lift (Temp Lift) - The act of releasing one or more Tagout points with the possibility or intent to reinstall the Tagout points at a later time. This is performed after the component or subsystem has been placed in a configuration that assures personnel safety and the safe operation of plant equipment. Temporary Lift tags are similar to that shown on Figure 4 of NMP-AD-003-GL01.
4.31 Verification - The "second check" of a component's condition/position. Performed by an individual other than the one who performed the initial check/positioning. Requirements for verification can be found in procedure NMP-OS-002, "Verification Policy".
4.31.1 NV - No Verification used for position of steps such as NO TAG steps that will only be used for configuration control or as specified by Operations Management 4.31.2 SC - Single Check is normally used for placing and restoring components such as NON Safety related items that do not meet the Purpose or Applicability of Verification Policy per NMP-OS-002 4.31.3 CV - Concurrent Verification to be used per NMP-OS-002, "Verification Policy" 4.31.4 IV - Independent Verification to be used per NMP-OS-002, "Verification Policy" 4.32 Work Document Holder - An individual, who Signs-On a Tagout to identify that they are working under the protection of the Tagout. The individuals who Sign-on to the Tagout will do so by entry of the work document, user name, and date/time on to the Work Document/Holder List. This must be done by all workers who are afforded protection from energy sources or other hazards by the Tagout. Workers who are Work Document Holder qualified in the electronic system shall use the electronic system. Others who do not have electronic system access are called Supplemental Workers per this procedure and should sign on using the Supplemental Worker List, NMP-AD-003-F07.
5.0 Responsibilities 5.1 Plant Manager Nuclear Plant Ensuring that plant personnel are informed of their individual responsibilities regarding the Equipment Clearance and Tagging Procedure 5.2 Department Managers (all Departments)
- Ensures all department personnel (including contractors) working for their department are trained on and comply with this procedure
Southern Nuclear Operating Company Nuclear NMP-AD-003 SOUIHERNA Management Equipment Clearance and Tagging Version 11.0 COMPANY EtJ.I!Tgy to Snw Your Worllr Procedure Page 19 of 34
- No pressure such as Nitrogen over pressure exists in the main steam system
- The main steam header has been drained as necessary to ensure no adverse water flow will occur when the MSIV's are opened 6.4.3.2 With Shift Supervisor concurrence and satisfactory completion of the above prerequisites, tags may be placed on appropriate components which will prevent heat input into the main steam system from the reactor. Consideration should be given to the following when selecting appropriate components to tag.
- Nitrogen supply to the main steam lines.
- Auxiliary steam heat from opposite Unit.
- Pressurizer heater input to the RCS.
6.4.3.3 Tagging of components associated with RCS Pump and Pressurizer Heater heat input to the RCS is not required if the following conditions are met:
- Administrative controls are verified in place to ensure the Reactor Vessel level is maintained below the MSLs at Plant Hatch.
- Administrative controls are verified in place to ensure the RCS is maintained less than 200 'F (FarleyNogtle) or 150 0 F (Hatch).
- Administrative controls are in place to ensure MSIVs are re-tagged prior to
) RCS Temperature exceeding 200 'F (FarleyNogtle) or 150'F (Hatch), if a MSIV boundary is required.
6.5 Tagout Placement Preparation NOTE: Action shall be initiated to correct any database error found such as equipment name or location, etc. during preparation, review, approval and hanging of a Tagout by the individual discovering the error 6.5.1 A Preparer will use the guidance provided in NMP-AD-003-F08, Tagout Preparation and Approval Checklist" (or equivalent) and prepare the Tagout as follows:
6.5.1.1 Review the scope of work to ensure a thorough understanding of the protection needed for personnel and equipment.
6.5.1.2 Using approved documents, determine hazardous energy sources and isolations necessary to provide a safe work boundary for each work activity.
6.5.1.3 Identify and assess all potential hazards, automatic actions and/or effects on the plant which may result due to execution of the Tagout. These hazards should be identified in the Tagout Instructions when possible. Guidance should be provided as appropriate to inform and/or prevent any unwanted occurrences.
6.5.1.4 If approved documents do not exist for equipment to be tagged, then a physical walk down may be performed.
6.5.1.5 Enter the required information on the Tagout.
Southern Nuclear Operating Company Nuclear NMP-AD-003 SOUTHERN..\. Management Equipment Clearance and Tagging Version 11.0 COMPANY EtJnot~Snw JipIU'Wau Procedure Page 20 of 34 6.5.1.6 Components that are removed from the system or having maintenance performed on them should be identified with a "No-tag" tag type to ensure that it is positioned properly upon placement and removal. Do not hang any other type of tag on that component.
6.5.1.7 For components that are positioned but not tagged, mark the tag as a "No-tag" tag type.
6.5.1.8 For Tagout points that are to be used for Information only an "INFO Step" may be used.
6.5.1.9 Utilizing the Tagout points, prepare the Tagout:
- Indicate type of tag
- Indicate component number and name
- List the required position and sequence
- Indicate verification requirements
- If special instructions are applicable, annotate in appropriate section 6.5.1.10 Sign the Tagout as Preparer.
6.5.1.11 Sign the Work Documents listed on the Tagout as 1st Verified.
6.6 Tagout Placement Review 6.6.1 A Reviewer will perform an independent review of the Tagout.
6.6.2 Verify the Tagout pOints and boundary isolations selected provide adequate plant and personnel safety for work activities listed.
6.6.3 Verify and assess all potential automatic actions and/or effects on the plant which may result due to execution of the Tagout. Ensure these items are identified and are properly documented on the Tagout when possible.
6.6.4 Review the Tagout points for the correct:
- Tag type used
- Component number and name
- Position and sequence
- Placement verifications required 6.6.5 Review impact on equipment (including Tech Specs).
6.6.6 Review or add any special instructions that apply to the Tagout.
6.6.7 Sign the Tagout as Reviewer.
6.6.8 Sign the Work Documents listed on the Tagout as 2nd Verified.
Southern Nuclear Operating Company Nuclear NMP-AD-003-F08 SOUTHERN..\. Management Tagout Preparation and Approval Checklist Version 2.0 COMPANY Entt'X.1m~*,II1'~rl.rl~ Fol'l'I'!_~~~_ ----_ .. _ - - - _ .. _ -
Page 1 of 1
Southern Nuclear Operating Company Nuclear NMP-AD-003-F01 SOUTHERN~COMPANY Management Tagout Cover Sheet Version 1.0 ENergy tO$ffH }(Iur World' Form Page 1 of 1 Clearance: i Tagout: I Component Affected:
==
Description:==
OPS Instructions:
Holder Instructions:
References:
out Attributes:
Attribute Attribute Descri tion Value WorkDoc Holder List-Number I Equipment ID Description 1$ Verified Status Description Name Verification Date Prepared Prepared Reviewed Reviewed Authorized Authorized Tags Verified Hung Tags Verified Hung Removal Prepared Removal Prepared Removal Reviewed Removal Reviewed Removal Authorized Removal Authorized Tags Verified Removed Tags Verified Removed Records Forwarded Records Forwarded Page 1 of_
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