Text

Initial Exam 2009-302 Final Administrative JPMs - Section 12
	ML093430147
Person / Time
Site:	Hatch
Issue date:	12/07/2009
From:	; NRC/RGN-II/DRS/OLB
To:	; Southern Nuclear Operating Co
References
	05-321/09-302, 05-366/09-302
	Download: ML093430147 (109)
	v • d • e

FACILITY NAME: _....:..H.:.:..A..;..;;T~C;..;..H.:....-_________

Section 12 REPORT NUMBER: 05000321/2009302 AND 05000366/~009302 FINAL ADMINISTRATIVE JPMS CONTENTS:

D Final ADMIN JPMs o 'As given' with changes made during administration annotated Location of Electronic Files:

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

Bruno Caballero FACILITY NAME: _.....;.H..;.;,.A..;..,;T;..,.;;C;..;.,H.::.--_________ _

Section 12 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 FINAL ADMINISTRATIVE JPMS CONTENTS:

D Final ADMIN JPMs o 'As given' with changes made during administration annotated Location of Electronic Files:

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

Bruno Caballero

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NIR FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM ADMIN I-ALL C.M.EDMUND 10/16/09 SOUTHERN.\\'

COMPANY FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM ADMIN I-ALL

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TITLE C\\

Diesel Generator Fuel Oil Tank/Confined Space Entry Requirements AUTHOR MEDIA NUMBER Anthony Ball 2009-302 Admin 1 RECOMMENDED BY APPROVED BY NIR C.M.EDMUND TIME 20 Minutes DATE 10/16/09

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

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Initial development ARB CME

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

Rev.

Date No.

00 10/16/09 OPERATIONS TRAINING Reason for Revision Initial development Media 2009-302 Admin 1 Number:

Author's Supv's Initials Initials ARB CME

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2009*302 Admin 1 UNIT 1 (X)

UNIT 2 (X)

Diesel Generator Fuel Oil Tank/Confined Space Entry Requirements JPl.VI:N~$ll:;**********

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The task shall be complete when the operator has identified which tanks require access and the required actions for entering access based on atmosphere sample OB.JEC'I'I¥EN~ER.~ R43-EDG-LP-02801,028.011A PLANT HATCH JTA IMPORTANCE RATING:

RO SRO KIA CATALOG NUMBER: 2.1.26 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.4 SRO 3.6 OPERATOR APPLICABILITY:

Reactor Operator (RO)

APPROXIMATE COMPLETION TIME:

20 Minutes SIMULATOR SETUP:

NI A

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2009-302 Admin 1 UNIT 1 (X)

UNIT 2 (X)

TASK TITLE:

JPMNUMBER:

TASK STANDARD:

TASK NUMBER:

Diesel Generator Fuel Oil Tank/Confined Space Entry Requirements The task shall be complete when the operator has identified which tanks require access and the required actions for entering access based on atmosphere sample OBJECTIVE NUMBER: R43-EDG-LP-0280l,028.0l1A PLANT HATCH JTA IMPORTANCE RATING:

RO SRO KIA CATALOG NUMBER: 2.1.26 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.4 SRO 3.6 OPERA TOR APPLICABILITY:

Reactor Operator (RO)

I GENERAL

REFERENCES:

Unit 1 & 2 I REQIDRED MATERIALS:

34S0-R43-001-1, "Diesel Generator Standby AC System".

NMP-SH-005 "Confined Space Procedure" NMP-SH-005-GL.OI, "Confined Space Decision Making Flowchart" Unit 1 &2 34S0-R43-00l-1, "Diesel Generator Standby AC System", and Attachment 8.

NMP-SH-005 "Confined Space Procedure" NMP-SH-005-GL.0l, "Confined Space Decision Making Flowchart" APPROXIMATE COMPLETION TIME:

20 Minutes SIMULATOR SETUP:

N/A

UNITl&2 READ AND PROVIDE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1. The Main Fuel Oil Storage Tanks are classified as Confined Spaces IA W NMP-SH-005 "Confined Space Procedure".

2. Fuel Oil was transferred from the 1A Main Storage Tank to the 2A and 2C Main Storage Tanks lAW Section 7.3.1 of 34S0-R43-001-1,"

Diesel Generator Standby AC System" and is complete up to and including step 7.3.1.11.

3. Final Control Room indications (after the transfer) for all Main Storage Tank quantities are listed below:

1A Main Storage Tank 35,010 gallons 1B Main Storage Tank 37,700 gallons 1C Main Storage Tank 38,120 gallons 2A Main Storage Tank 38,180 gallons 2C Main Storage Tank 37,950 gallons

4. Chemistry has re-sampled the Fuel oil storage tank accesses to facilitate a fuel oil storage quantity check lAW step 7.3.1.12 of 34S0-R43-001-1. The following sampling results currently exist (following the transfer) for all storage tank accesses:

Oxygen-22%

Flammable reading - 11 % LFL Carbon Dioxide - 6000 (ppm)

INITIATING CUES:

lAW 34S0-R43-001-1, Determine the MINIMUM number of Main Fuel Oil Storage Tanks accesses that are required to be re-entered to determine the individual Main Fuel Oil Storage Tank level.

Based ONLY on the above concentrations, determine ALL required actions (if any) to be taken prior to re-entering the accesses to the Diesel Fuel Oil Storage Tanks lAW NMP-SH-005, "Confined Space Procedure" step 6.7.

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UNIT 1 &2 READ AND PROVIDE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1. The Main Fuel Oil Storage Tanks are classified as Confined Spaces IA W NMP-SH-005 "Confined Space Procedure".

2. Fuel Oil was transferred from the IA Main Storage Tank to the 2A and 2C Main Storage Tanks IA W Section 7.3.1 of 34S0-R43-001-1,"

Diesel Generator Standby AC System" and is complete up to and including step 7.3.1.11.

3. Final Control Room indications (after the transfer) for all Main Storage Tank quantities are listed below:

lA Main Storage Tank 35,010 gallons IB Main Storage Tank 37,700 gallons IC Main Storage Tank 38,120 gallons 2A Main Storage Tank 38,180 gallons 2C Main Storage Tank 37,950 gallons

4. Chemistry has re-sampled the Fuel oil storage tank accesses to facilitate a fuel oil storage quantity check IA W step 7.3.1.12 of 34S0-R43-00l-1. The following sampling results currently exist (following the transfer) for all storage tank accesses:

Oxygen-22%

Flammable reading - 11 % LFL Carbon Dioxide - 6000 (ppm)

INITIATING CUES:

IA W 34S0-R43-001-1, Determine the MINIMUM number of Main Fuel Oil Storage Tanks accesses that are required to be re-entered to determine the individual Main Fuel Oil Storage Tank level.

Based ONLY on the above concentrations, determine ALL required actions (if any) to be taken prior to re-entering the accesses to the Diesel Fuel Oil Storage Tanks IA W NMP-SH-005, "Confined Space Procedure" step 6.7.

1. Obtains the procedures.

2. Review the procedure's precautions and limitations.

3. Identifies the correct section.

Operator has obtained the procedure 34S0-R43-00l-1.

Operator reviews precautions and limitations.

Operator identifies Attachment 8 as the correct section to reference.

2009-302 Admin 1 Page 3 of6

.**SA'rIIWSA.T.

COMMENTS START TlME: ___ _

SAT I UNSAT SAT/UNSAT SAT I UNSAT NOTE: Precaution 5.1.8 allows Control Room indication for 2A to be used for level determination since it is NOT sensitive to the variations in specific gravity of the received fuel oiL Operator has determined that entry into access for 2A storage tank area IS NOT required to determine tank level.

SAT I UNSAT NOTE: Precaution 5.1.8 allows Control Room indication for 2C to be used for level determination since it is NOT sensitive to the variations in specific gravity of the received fuel oil.

Operator has determined that entry into access for 2C storage tank area IS NOT required to determine tank level.

SAT I UNSAT NOTE: A note on page 2 of Att. 8 states that Control Room indication can NOT be used for IA since the level is approaching the administrative limit of 35,000 gallons.

Operator has determined that entry into access for IA storage tank IS required to determine tank level.

SAT I UNSAT NOTE: A note on page 2 of Att. 8 states that Control Room indication can be used for IB and IC since no addition of fuel oil has occurred to this tank.

Operator has determined that entry into access for IB storage tank area IS NOT required to determine level.

SAT I UNSAT

(

PERFO~NCESTEP

1. Obtains the procedures.

2. Review the procedure's precautions and limitations.

3. Identifies the correct section.

STANDARD Operator has obtained the procedure 34S0-R43-001-1.

Operator reviews precautions and limitations.

Operator identifies Attachment 8 as the correct section to reference.

2009-302 Admin 1 Page 3 of6 SATIUNSAT (COMMENTS START TIME: ___ _

SAT I UNSAT SAT/UNSAT SAT I UNSAT NOTE: Precaution 5.1.8 allows Control Room indication for 2A to be used for level determination since it is NOT sensitive to the variations in specific gravity of the received fuel oil.

- 4. Reviews Attachment 8 for 2A storage Operator has determined that SAT/UNSAT tank level indicator status.

entry into access for 2A storage tank area IS NOT required to determine tank level.

NOTE: Precaution 5.1.8 allows Control Room indication for 2C to be used for level determination since it is NOT sensitive to the variations in specific gravity of the received fuel oiL

- 5. Reviews Attachment 8 for 2C storage Operator has determined that SAT/UNSAT tank level indicator status.

entry into access for 2C storage tank area IS NOT required to determine tank level.

NOTE: A note on page 2 of Att. 8 states that Control Room indication can NOT be used for 1A since the level is approaching the administrative limit of 35,000 gallons.

- 6. Reviews Attachment8 for 1A storage Operator has determined that SAT/UNSAT tank level indicator status.

entry into access for 1 A storage tank IS required to determine tank leveL NOTE: A note on page 2 of Att. 8 states that Control Room indication can be used for 1B and 1C since no addition of fuel oil has occurred to this tank.

- 7. Reviews Attachment 8 for IB storage Operator has determined that SAT/UNSAT tank level indicator status.

entry into access for 1B storage tank area IS NOT required to determine leveL

Review the procedure's precautions limitations.

11. Identifies the correct section.

12. Enters flowchart and answers questions to arrive at the step for Oxygen content.

Operator determined entry into access for 1 C storage tank IS NOT required to determine tank leveL Operator has obtained procedure I\\MP-SH-OOS.

2009*302 Admin 1 Page 4 of6 S1\\{l{JN~~T

<<(}QMMENTS)

SAT/UNSAT SAT/UNSAT Operator reviews !.liovvau limitations.

and SAT/UNSAT Operator identifies step 6.7 and reviews NMP-SH-005-GL.Ol, "Confined Space Decision Making Flowchart".

Operator answers questions and arrives at the step for Oxygen content.

SAT I UNSAT SAT/UNSAT NOTE: Oxygen content between 19.5% and 23.5% will yield a YES answer since content is 22%.

Operator answers YES SAT/UNSAT content proceeds to the "A" block.

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PERFO~NCESTEP

- 8. Reviews Attachment 8 for 1 C storage tank level indicator status.

9. Obtains the procedure for confined spaces.

10. Review the procedure's precautions and limitations.

11. Identifies the correct section.

12. Enters flowchart and answers questions to arrive at the step for Oxygen content.

STANDARD Operator has determined that entry into access for 1 C storage tank IS NOT required to determine tank level.

Operator has obtained procedure NMP-SH-005.

Operator reviews precautions and limitations.

Operator identifies step 6.7 and reviews NMP-SH-005-GL.01, "Confined Space Decision Making Flowchart".

Operator answers questions and arrives at the step for Oxygen content.

2009-302 Admin 1 Page 4 of6 SATIUNSAT (COMMENTS)

SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT NOTE: Oxygen content between 19.5% and 23.5% will yield a YES answer since content is 22%.

- 13. Reviews Oxygen concentration Operator answers YES for SAT/UNSAT content and proceeds to the "A" block.

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NOTE: Flammable gas content> 10% LFL will yield a YES answer.

2009-302 Admin 1 Page 5 of6 SA1'ItINSAT C9MMEN'I'S)

Operator answers YES SAT I UNSA T flammable gases> 1 0% of LFL.

the SAT IUNSAT Operator notifies SS that the SAT! UNSAT accesses for the Main Storage Tanks wiIl have to be ventilated Operator notifies SS that the I UNSAT accesses for the Main Storage Tanks have to re-tested for oxygen content Operator notifies SS that the SAT! UNSAT accesses for the Main Storage Tanks will have to be re-tested for oxygen and flammable gases I NOTE:

IF the student waits on a required action to be completed before proceeding down to the next flowchart action, inform the operator that the applicable action has been performed. This will allow the operator to progress down the flowchart to the next required action.

PROMPT:

IF the student asks if the Storage Tank Accesses have been re-tested, (after the purge with inert gas and ventilate space is completed) inform the operator that the samples have not been analyzed yet and another operator will address the re-tested values.

PROMPT:

IF the student asks about performing the above mentioned items, inform the operator that another operator will perform these items.

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.

(

c PERFO~NCESTEP STANDARD 2009-302 Admin 1 Page 5 of6 SATIUNSAT COMMENTS)

NOTE: Flammable gas content> 10% LFL will yield a YES answer.

14.

- 15.

- 16.

- 17.

- 18.

Enters "A" at step for testing of Operator answers YES for SAT/UNSAT flammable gases.

flammable gases> 10% of LFL.

Reviews step "Purge with inert gas" Operator notifies SS that the SAT I UNSAT accesses for the Main Storage Tanks will have to be purged with inert gas.

Reviews step "Ventilate space" Operator notifies SS that the SAT/UNSAT accesses for the Main Storage Tanks will have to be ventilated after purging.

Reviews steps for retesting Oxygen.

Operator notifies SS that the SAT/UNSAT accesses for the Main Storage Tanks will have to be re-tested for oxygen content.

Reviews steps for retesting Operator notifies SS that the SAT/UNSAT flammable gases I vapors.

accesses for the Main Storage Tanks will have to be re-tested for oxygen and flammable gases I vapors.

NOTE:

IF the student waits on a required action to be completed before proceeding down to the next flowchart action, inform the operator that the applicable action has been performed. This will allow the operator to progress down the flowchart to the next required action.

PROMPT:

IF the student asks if the Storage Tank Accesses have been re-tested, (after the purge with inert gas and ventilate space is completed) inform the operator that the samples have not been analyzed yet and another operator will address the re-tested values.

PROMPT:

IF the student asks about performing the above mentioned items, inform the operator that another operator will perform these items.

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.

2009-302 Admin 1 Page 6 of6

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PERFO~CESTEP TERMINATING CUE: We will stop here.

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STANDARD 2009-302 Admin 1 Page 6 of6 SATIUNSAT (COMMENTS

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F.N.FAGAN FI AL Southern uclear E. I.

atch Nuclear Plant Operations Training JPM Admin 2 - S 0 Only

!iliCOlVIMFJNDEDBY N/R C. M. EDMUND 1011312009 Energy to Serve Your World sM

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TITLE AUTHOR EN.FAGAN FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 2 - SRO Only DETERMINE MINIMUM CREW STAFFING MEDIA NUMBER 2009-302 Admin 2 RECOMMENDED BY APPROVED BY N/R C. M. EDMUND TIME 15 Minutes DATE 1011312009 Energy to Serve Your World sM

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

OPERATIONS TRAINING

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Rev: No.

00 10/13/09 Initial development Page 1 of 1 Media Number: 2009-302 Admin 2

....,.'.. ~... '..... ~.. A.lltllor's Supv~s

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FNF CME

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

OPERATIONS TRAINING Rev. No.

Date Reason for Revision 00 10/13/09 Initial development Page 1 of 1 Media Number: 2009-302 Admin 2 Author's Supv's Initials Initials FNF CME

JPMNUMBER:** *. *******

2009-302 Admin 2 Page 1 of3 UNIT 1 (X)

UNIT 2 (X)

IDENTIFY ADEQUATE/INADEQUATE SHIFT STAFFING LR-JP-300.1-00 The task shall be complete when the operator has determined that crew staffing is short an HP, SO and appropriate management notified.

H-OPSR300.001 OBJECTIVENtJM]JER;' H-OP300.001.A.01 PLANT HATCH JTA IMPORTANCE RATING:

RO N/A SRO 3.03 KIA CATALOG NUMBER: 2.1.5

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KIA CATALOG JTA IMPORTANCE RATING:

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RO N/A SRO 3.9 OPERATOR APPLICABILITY:

Senior Reactor Operator (SRO) 10 CPR 50.54(m)(2)(i) 30AC-OPS-003-0 "Plant Operations" DI-OPS-81-0501, "Minimum Planned Crew Staffing" Tech S ecs APPROXIMATE COMPLETION TIME:

15 Minutes SIMULATOR SETUP:

N/A

(

TASK TITLE:

JPMNUMBER:

TASK STANDARD:

TASK NUMBER:

2009-302 Admin 2 Page 1 of 3 UNIT 1 (X)

UNIT 2 (X)

IDENTIFY ADEQUATE/INADEQUATE SHIFT STAFFING LR-JP-300.1-00 The task shall be complete when the operator has determined that crew staffing is short an HP, SO and appropriate management notified.

H-OPSR300.001 OBJECTIVE NUMBER:

H-OP300.001.A.Ol PLANT HATCH JTA IMPORTANCE RATING:

RO N/A SRO 3.03 KIA CATALOG NUMBER: 2.1.5

(

KIA CATALOG JTA IMPORTANCE RATING:

(

RO N/A SRO 3.9 OPERATOR APPLICABILITY:

Senior Reactor Operator (SRO)

I GENERAL

REFERENCES:

Unit 1 &2 I REQIDRED MATERIALS:

10 CPR 50.54(m)(2)(i) 30AC-OPS-003-0 "Plant Operations" DI-OPS-81-050l, "Minimum Planned Crew Staffing" Tech Specs Unitl &2 30AC-OPS-003-0, "Plant Operations" 10 CPR 50.54(m)(2)(i)

(note: 10CFR requirements covered in 30AC-OPS-003-0)

DI-OPS-81-050l, "Minimum Planned Crew Staffing" Tech Specs APPROXIMATE COMPLETION TIME:

15 Minutes SIMULATOR SETUP:

N/A

UNITl&2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. It is 2 AM and both Units are at 100% power.

2. Current shift staffing includes the following:

1 - Shift Manager (SM) 2 - Shift Supervisors (SS) 1 - Shift Support Supervisor (SSS) 1 - Shift Techinical Advisor (STA) 4 - Nuclear Plant Operator (NPO) 5 - System Operator (SO) o - Health Physics Technican (HP)

INITIATING CUES:

Considering only the above positions, determine if the planned and required shift staffing is met IA W the following documents and determine required actions, if any.

Tech Specs Operations Procedures.

Controlled plant documents may be referenced.

Training material may NOT be referenced.

(

UNITl&2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. It is 2 AM and both Units are at 100% power.

2. Current shift staffing includes the following:

1 - Shift Manager (SM) 2 - Shift Supervisors (SS) 1 - Shift Support Supervisor (SSS) 1 - Shift Techinical Advisor (STA) 4 - Nuclear Plant Operator (NPO) 5 - System Operator (SO) o - Health Physics Technican (HP)

INITIATING CUES:

Considering only the above positions, determine if the planned and required shift staffing is met lAW the following documents and determine required actions, if any.

Tech Specs Operations Procedures.

Controlled plant documents may be referenced.

Training material may NOT be referenced.

NOTE:

.C",'

PERFO~NcES'fEP**.

2009-302 Admin 2 Page 3 of3 SATW,NSi\\.T (COMMENTS)

The use/research of procedures may occur in any order. If the Operator does not verbalize his findings in each procedure, the evaluator may ask if he found any "applicable actions/time limits".

If referenced, staffing is met lAW 30AC-OPS-003-0, "Plant Operations" Att. 1 START Step 1 is from Tech Specs Section 5.2.2.d

Operator determines an HP is required

Operator determines that:

- Immediate action required to replace HP

- Time limit of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months TIME: ___ _

SAT/UNSAT Step 2 is from DI-OPS-81-0501, "Minimum Planned Crew Staffing" Section 4.0.

For this step, an NPO can be used as a substitute for an SO.

Operator determines that the number of SOs does NOT meet the planned staffing per DI-OPS-81-0501, "Minimum Planned Crew Staffing"

Operator determines the following actions are required:

Write a condition report.

Notify the Hatch Duty Manager Notify the Duty Ops Supervisor.

SAT/UNSAT END TIME:

TERMINATING CUE: We will stop here.

(** Indicates critical step)

(

NOTE:

PERFO~NCESTEP STANDARD 2009-302 Admin 2 Page 3 of 3 SATIUNSAT (COMMENTS)

The use/research of procedures may occur in any order. If the Operator does not verbalize his findings in each procedure, the evaluator may ask if he found any "applicable actions/time limits".

If referenced, staffing is met lAW 30AC-OPS-003-0, "Plant Operations" Att. 1 START TIME: ___ _

Step 1 is from Tech Specs Section 5.2.2.d

- 1. Determine required staffing and

Operator determines an HP SAT/UNSAT required action/time limit.

is required

Operator determines that:

- Immediate action required to replace HP

- Time limit of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months NOTE:

Step 2 is from DI-OPS-81-0501, "Minimum Planned Crew Staffing" Section 4.0.

For this step, an NPO can be used as a substitute for an SO.

- 2. Determine required staffing and

Operator determines that the SAT/UNSAT required actions number of SOs does NOT meet the planned staffing per DI-OPS-81-0501, "Minimum Planned Crew Staffing"

Operator determines the following actions are required:

Write a condition report.

Notify the Hatch Duty Manager Notify the Duty Ops Supervisor.

END TIME:

TERMINATING CUE: We will stop here.

(** Indicates critical step)

(

\\

UNITl&2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. It is 2 AM and both Units are at 100% power..

2. Current shift staffing includes the following:

1 - Shift Manager (SM) 2 - Shift Supervisors (SS) 1 - Shift Support Supervisor (SSS) 1 - Shift Techinical Advisor (STA) 4 - Nuclear Plant Operator (NPO) 5 - System Operator (SO) o - Health Physics Technican (HP)

INITIATING CUES:

Considering only the above positions, determine if the planned and required shift staffing is met IA W the following documents and determine required actions, if any.

Tech Specs Operations Procedures.

Controlled plant documents may be referenced.

Training material may NOT be referenced.

(

UNITl&2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. It is 2 AM and both Units are at 100% power.

2. Current shift staffing includes the following:

1 - Shift Manager (SM) 2 - Shift Supervisors (SS) 1 - Shift Support Supervisor (SSS) 1 - Shift Techinical Advisor (STA) 4 - Nuclear Plant Operator (NPO) 5 - System Operator (SO) o - Health Physics Technican (HP)

INITIATING CUES:

Considering only the above positions, determine if the planned and required shift staffing is met IA W the following documents and determine required actions, if any.

Tech Specs Operations Procedures.

Controlled plant documents may be referenced.

Training material may NOT be referenced.

FINAL Southern E. I. Hatch uclear uclear Plant Operations Training JPM Admin 3 -

0 Only DETERMINE THE DRYWELL FLOOR DRAIN LEAKAGE RATE

"'.*......................... ----....*.......*..............*........ .'...........*................*.*..............*.........**.*.*..... \\.........*....*......**..........*...

........... MEI)IXNUMBER 2009-302 Admin 3 N/R C.M.EDMUND 1011412009

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TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 3 - RO Only DETERMINE THE DRYWELL FLOOR DRAIN LEAKAGE RATE AUTHOR F.N.FAGAN RECOMMENDED BY N/R MEDIA NUMBER 2009-302 Admin 3 APPROVED BY C.M.EDMUND TIME 13.0 Minutes DATE 1011412009

(

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

OPERATIONS TRAINING Media Number: 2009-302 Admin 3

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Iriithds Initials 00 12118/2002 Initial Development DNM DHG 01 0210412003 Correct VI Calculation DNM DHG 02 0611712005 Revised Initial License statement for successful completion RAE RAE 03 05/0512006 Remove Response Cues RAE RAE 04 09/30108 Modified attachments 1, 3, 4, and 6 to reflect the tables JWP RAB referenced more closely_

10/14/09 Revised for use on 2009-302 exam FNF CME

(

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

OPERATIONS TRAINING Media Number: 2009-302 Admin 3 Rev.

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

Initials Initials 00 1211812002 Initial Development DNM DHG 01 02/0412003 Correct VI Calculation DNM DHG 02 0611712005 Revised Initial License statement for successful completion RAB RAB 03 05/0512006 Remove Response Cues RAB RAB 04 09/30108 Modified attachments 1, 3, 4, and 6 to reflect the tables JWP RAB referenced more closely_

10114/09 Revised for use on 2009-302 exam FNF CME

Page 1 of8 2009-302 Admin 3 UNIT 1 (X)

UNIT 2 (X)

DETERMINE THE DRYWELL FLOOR DRAIN LEAKAGE RATE LR-JP-40.05-03 The task will be complete when the Drywell Leakage Rate has been determined and any procedural limit violations reported to the Shift Supervisor.

040.004 040.004. A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.07 SRO 2.81 KIA CATALOG NUMBER: 2.2.12 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.7 SRO 4.1 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

(current version)

Calculator APPROXIMATE COMPLETION TIME:

13.0 Minutes SIMULATOR SETUP:

N/A

(

Page 1 of 8 2009-302 Admin 3 UNIT 1 (X)

UNIT 2 (X)

TASK TITLE:

JPMNUMBER:

TASK STANDARD:

TASK NUMBER:

DETERMINE THE DRYWELL FLOOR DRAIN LEAKAGE RATE LR-JP-40.05-03 The task will be complete when the Drywell Leakage Rate has been detennined and any procedural limit violations reported to the Shift Supervisor.

040.004 OBJECTIVE NUMBER: 040.004.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.07 SRO 2.81 KIA CATALOG NUMBER: 2.2.12 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.7 SRO 4.1 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

I GENERAL

REFERENCES:

Unitl 34SV -SUV -019-1 (current version)

I REQUIRED MATERIALS:

Unit 1 34SV-SUV-019-1 (current version)

Calculator APPROXIMATE COMPLETION TIME:

13.0 Minutes SIMULATOR SETUP:

NI A

LR-JP-40.05-04 UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

Unit One is operating at 100% power.

2.

The time is 0800.

3.

The Drywell Floor Drain (DWFD) sumps have just been "pumped down."

4.

34SV-SUV-019-1, "Surveillance Checks," is in progress.

5.

Drywell Equipment Drain 24 Hour Leakage has been calculated to be 0.20 gpm.

INITIATING CUES:

Complete Drywell Floor Drain Leakage, section 7.25.2 of 34SV -SUV -019-1, "Surveillance Checks" Evaluate the results AND identify all applicable 34SV-SUV-019-1, NOTES to the Shift Supervisor (SS).

(

LR-JP-40.05-04 UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1.

Unit One is operating at 100% power.

2.

The time is 0800.

3.

The Drywell Floor Drain (DWFD) sumps have just been "pumped down."

4.

34SV-SUV-019-1, "Surveillance Checks," is in progress.

5.

Drywell Equipment Drain 24 Hour Leakage has been calculated to be 0.20 gpm.

INITIATING CUES:

Complete Drywell Floor Drain Leakage, section 7.25.2 of 34SV-SUV-019-1, "Surveillance Checks" Evaluate the results AND identify all applicable 34SV-SUV-019-1, NOTES to the Shift Supervisor (SS).

2009-302 Admin 3 Page 3 of 8 START TIME: ___ _

1. Operator identifies the procedure Operator has identified SAT I UNSAT needed to perfonn the task.

34SV-SUV-019-1 as the correct procedure.

PROMPT:

WHEN the Operator addresses getting procedure 34SV-SUV-019-1, Section 7.24, PROVIDE the Operator a copy of Attach 1 and Attach 2.

PROMPT:

IF addressed by the Operator, as the SS, INFORM the Operator that another Operator has already perfonned the DWED Leakage Rate check.

N01E: The initial conditions stated the sumps had just been pumped down.

Operator has selected DWFD leakage integrator 1 G 11-K60 1.

Operator has obtained DWFD reading of 4017.0 (allowable band 4016.4 - 4017.6).

4. Operator completes Attachment 1.

Operator has completed with the same results as Attachment 3.

PROMPT:

IF the Operator addresses verification of calculations, INFORM the operator that will be done after he has completed his analysis.

Operator records step 22 at 5.50 gpm (allowable band 5.40-5.51).

Operator records step 25 at 5.34 gpm (allowable band 5.24-5.35).

Operator has notified the SS that:

DWFD leakage rate exceeds 5 OR provides the calculated numbers.

DWFD leakage rate exceeds 2 gpm limits OR provides the calculated numbers.

SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT

(

I STEP

1.

PERFORMANCE STEP Operator identifies the procedure needed to perform the task.

STANDARD Operator has identified 34SV-SUV-019-1 as the correct procedure.

2009-302 Admin 3 Page 3 of 8 SATIUNSAT (COMMENTS START TIME: ___ _

SAT/UNSAT PROMPT:

WHEN the Operator addresses getting procedure 34SV-SUV-019-1, Section 7.24, PROVIDE the Operator a copy of Attach 1 and Attach 2.

PROMPT:

IF addressed by the Operator, as the SS, INFORM the Operator that another Operator has already performed the DWED Leakage Rate check.

NOTE: The initial conditions stated the sumps had just been pumped down.

- 2. Select the correct integrator.

Operator has selected DWFD leakage integrator 1 G 11-K60 1.

- 3. Operator reads the integrator.

Operator has obtained DWFD reading of 4017.0 (allowable band 4016.4 - 4017.6).

4. Operator completes Attachment 1.

Operator has completed with the same results as Attachment 3.

PROMPT:

IF the Operator addresses verification of calculations, INFORM the operator that will be done after he has completed his analysis.

- 5. Operator determines DWFD 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Operator records step 22 at 5.50 leakage leakage.

gpm (allowable band 5.40-5.51).

- 6. Operator determines. Differential Floor Operator records step 25 at 5.34 Drain Leakage gpm (allowable band 5.24 -

5.35).

- 7. Operator notifies SS of DWFD Operator has notified the SS that:

leakage limits exceeded.

DWPD leakage rate exceeds 5 OR provides the calculated numbers.

DWFD leakage rate exceeds 2 gpm limits OR provides the calculated numbers.

SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT

I

- 8. Operator notifies SS of DWFD applicable note:

- STANDARD Operator notifies SS that note FF is applicable.

2009-302 Admin 3 Page 4 of 8

..... Si\\.TIUNSAT (C()MMENTS SAT/UNSAT NOTE: The FF, F.2 and F.3 notes require the following:

F.2 Use 34S0-Gll-013-1 to calculate leakage IF integrator drifting. Circle the results in red OR, IF using HHC, add note stating integrator drifting.

F.3 IF an abnormal increase in Drywell Floor Drain leakage has been noted AND Drywell average temperature is < lOO°F, request Engineering to evaluate the need to secure some drywell cooling fans. This is due to the possibility of excessive moisture condensation at the low drywell temperature.

FF IF DWFD leakage is >0.5 GPM, perform the following:

1. Notify Management (Operations Duty Management AND Plant Hatch Duty Manager)

AND include DWFD leakage on the Morning Report under Major Equipment Impacting Operational Focus.

2. Each Operating crew will review 34AB-T23-002-1 at the beginning of shift AND log the DWFD leakage rate each shift.

3. Initiate a Condition Report and make a Control Room Log entry.

4. Engineering Support will include a graph of U-l DWFD leakage in the Daily Status Report each Friday.

IF DWFD leakage is > 1.5 GPM, perform the following:

1. Notify Management to schedule a Unit 1 shutdown based on DWFD leakage trend.

2. Initiate a Condition Report and make a Control Room Log entry.

3. Every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , calculate DWFD leakage and make a Control Room Log entry of the leakage rate.

IF DWFD leakage is >2.5 GPM, perform the following:

PROMPT:

1. PerfOlID a controlled shutdown of Unit 1 to repair the leakage.

2. Initiate a Condition Report and make a Control Room Log entry.

IF addressed by the Operator, as the Shift Supervisor, INFORM the Operator that a second Drywell Floor Drain leakage rate check is not desired at this time.

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.

(

PERFO~NCESTEP

- 8. Operator notifies SS of DWFD applicable note.

STANDARD Operator notifies SS that note FF is applicable.

2009-302 Admin 3 Page 4 of8 SATIUNSAT (COMMENTS SAT/UNSAT NOTE: The FF, F.2 and F.3 notes require the following:

F.2 Use 34S0-Gll-013-1 to calculate leakage IF integrator drifting. Circle the results in red OR, IF using HHC, add note stating integrator drifting.

F.3 IF an abnormal increase in Drywell Floor Drain leakage has been noted AND Drywell average temperature is < lOO°F, request Engineering to evaluate the need to secure some drywell cooling fans. This is due to the possibility of excessive moisture condensation at the low drywell temperature.

FF IF DWFD leakage is >0.5 GPM, perform the following:

1. Notify Management (Operations Duty Management AND Plant Hatch Duty Manager)

AND include DWFD leakage on the Morning Report under Major Equipment Impacting Operational Focus.

2. Each Operating crew will review 34AB-T23-002-1 at the beginning of shift AND log the DWFD leakage rate each shift.

3. Initiate a Condition Report and make a Control Room Log entry.

4. Engineering Support will include a graph of U-l DWFD leakage in the Daily Status Report each Friday.

IF DWFD leakage is >1.5 GPM, perform the following:

1. Notify Management to schedule a Unit 1 shutdown based on DWFD leakage trend.

2. Initiate a Condition Report and make a Control Room Log entry.

3. Every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , calculate DWFD leakage and make a Control Room Log entry of the leakage rate.

IF DWFD leakage is >2.5 GPM, perform the following:

PROMPT:

1. Perform a controlled shutdown of Unit 1 to repair the leakage.

2. Initiate a Condition Report and make a Control Room Log entry.

IF addressed by the Operator, as the Shift Supervisor, INFORM the Operator that a second Drywell Floor Drain leakage rate check is not desired at this time.

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.

7.25 7.25.1 ATTACHMENT I (VI)

(Excerpt from 34SV-SVV-OI9-1)

REAC TIS -OPER PANEL - INSTRUMENT I TECH SPEC.

NOTE MODE LIMIT IHll-P613: -lGll-K603,EquipmentDrain Leakage Actual Time (1)

F.l Present Reading (2)

F.l Yesterday's Reading Time (3)

F.l Yesterday's Reading (4)

F.l 1,2,3 Difference (2) - (4)

(5)

F.l Difference Conversion (5) x 10 (6)

F.l 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes (7)

F.l 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (6)/(7)

(8)

F.2 Initials Time Calculations Verified ARB DRK 0000 0800 1600 0000 0800 1600 0000 0800 3956.3 3965.9 0000 0800 3923.3 3937.1 33.0 28.8 330 288 1440 1440

.23

.20 CME DRK 0003 0800 DATE

(

7.25 7.25.1 ATTACHMENT I (UI)

(Excerpt from 34SV-SUV-OI9-1)

REAC TIS -OPER PANEL - INSTRUMENT I TECH SPEC.

NOTE MODE L1MIT IHll-P613: -IGll-K603,EquipmentDrain Leakage Actual Time (1)

F.I Present Reading (2)

F.I Yesterday's Reading Time (3)

F.I Yesterday's Reading (4)

F.I 1,2,3 Difference (2) - (4)

(5)

F.I Difference Conversion (5) x 10 (6)

F.I 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes (7)

F.I 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (6)1(7)

(8)

F.2 Initials Time Calculations Verified ARB DRK 0000 0800 1600 0000 0800 1600 0000 0800 3956.3 3965.9 0000 0800 3923.3 3937.1 33.0 28.8 330 288 1440 1440

.23

.20 CME DRK 0003 0800 DATE

7.25 CONTD.

7.25.2 ATTACHMENT I (VI)

(Excerpt from 34SV-SVV-OI9-1)

PANEL - INSTRUMENT I TECH SPEC.

NOTE REAC TIS -OPER MODE LIMIT 1H11-P613: - 1G11-K601, Floor Drain Leakage Actual Time (9)

F.1 Present Reading (10)

F.l Yesterday's Reading Time (11)

F.l Yesterday's Reading (12)

F.l Difference (10) - (12)

(13)

F.1 Difference Conversion (13) X 10 (14)

F.1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes (15)

F.1 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (14) / (15)

(16)

FF,F.2,

5gpm F3 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading (17)

F.1 1,2,3 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading time (18)

F.1 8 Hour difference (10) - (17)

(19)

F.1 Difference conversion (19) X 10 (20)

F.l 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months elapsed minutes (21)

F.1 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage (20) / (21)

(22)

FF,F.2,

5gpm F3 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage from previous (23) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Total Leakage (8) + (16)

(24)

30 gpm Differential Floor Drain (25)

FF Leakage (22)-(23)

2gpmin (SR 3.4.4.1)

Mode 1 Initials Time ARB Calculations Verified 0000 0800 1600 0000 0800 1600 0000 3752.9 0000 0800 1600 3723.9 3732.9 3744.1 29.0 290 1440

.20 3744.1 3752.9 1600 0000 8.8 88 480

.18

.16

.18 1.55

.02 CME 0003 DATE

(

7.25 CONTD.

7.25.2 ATTACHMENT I (VI)

(Excerpt from 34SV-SVV-OI9-1)

PANEL - INSlRUMENT I TECH SPEC.

NOTE REAC TIS -OPER MODE LIMIT 1H11-P613: - 1G11-K601, Floor Drain Leakage Actual Time (9)

F.1 Present Reading (10)

F.1 Yesterday's Reading Time (11)

F.1 Yesterday's Reading (12)

F.1 Difference (10) - (12)

(13)

F.1 Difference Conversion (13) X 10 (14)

F.1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes (15)

F.1 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (14) / (15)

(16)

FF,F.2,

5 gpm F3 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading (17)

F.1 1,2,3 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading time (18)

F.1 8 Hour difference (10) - (17)

(19)

F.1 Difference conversion (19) X 10 (20)

F.1 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months elapsed minutes (21)

F.1 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage (20) / (21)

(22)

FF,F.2,

5gpm F3 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage from previous (23) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Total Leakage (8) + (16)

(24)

30 gpm Differential Floor Drain (25)

FF Leakage (22)-(23)

2 gpm in (SR 3.4.4.1)

Mode 1 Initials Time ARB Calculations Verified 0000 0800 1600 0000 0800 1600 0000 3752.9 0000 0800 1600 3723.9 3732.9 3744.1 29.0 290 1440

.20 3744.1 3752.9 1600 0000 8.8 88 480

.18

.16

.18 1.55

.02 CME 0003 DATE

ATTACHMENT 2 DRYWELL LEAKAGE INTEGRATORS IGII-K601, Floor Drain Leakage IGII-K603, Equipment Drain Leakage

(

ATTACHl\\1ENT 2 DRYWELLLEAKAGEINTEGRATORS IGII-K601, Floor Drain Leakage IGII-K603, Equipment Drain Leakage

Evaluator Use Only (not a handout)

REAC TIS OPER 7.25 P ANEL-INSTRUMENTITECH SPEC NOTE MODE LIMIT 0000 0800 1600 IHll-P613 - IG11-K601, Floor Drain Leakage Actual Time 9

F.l 0000 0800 Present Reading 10 F.1 3752.9 4017.0 Allowable Band 4016.4-4017.6 Yesterday's Reading Time 11 F.l 0000 0800 1600 Yesterday's Reading 12 F.l 3723.9 3732.9 3744.1 Difference (10) - (12) 13 F.l 29.0 284.1 Allowable Band 283.5-284.7 Difference Conversion (13) x 10 14 F.1 290 2841 Allowable Band 2835-2847 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes 15 F.l 1440 1440 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (14) I (15) 16 FF,F.2

5gpm

.20 1.97

,F3 Allowable Band 1.96-1.98 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading 17 F.l 3744.1 3752.9 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading time 18 F.l 1600 0000 8 Hour difference (10) - (17) 19 F.I 8.8 264.1 Allowable Band 263.5-264.7 7.25.2 Difference conversion (19) x 10 20 F.1 88 2641 Allowable Band 2635-2647 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months elapsed minutes 21 F.l 480 480 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage (20) I (21) 22 FF,F.2

5gpm

.18 5.50

,F3 Allowable Band 5.40-5.51 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage from previous 23 F.I 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months F.l

.16

.18 Total Leakage (8) + (16) 24 F.I

30 gpm 1.55 2.17 Allowable Band 2.16-2.18 Differential Floor Drain 25 FF

2gpm Leakage (22) - (23)

(SR 3.4.4.1)

.02 5.34 Allowable Band 5.24-5.35 PalYe g of R : Evaluator Use Only (not a handout)

REAC TIS OPER 7.25 P ANEL-INSTRUMENTITECH SPEC NOTE MODE LIMIT 0000 0800 1600 1Hll-P613 - 1G11-K601, Floor Drain Leakage Actual Time 9

F.1 0000 0800 Present Reading 10 F.1 3752.9 4017.0 Allowable Band 4016.4-4017.6 Yesterday's Reading Time 11 F.1 0000 0800 1600 Yesterday's Reading 12 F.1 3723.9 3732.9 3744.1 Difference (10) - (12) 13 F.1 29.0 284.1 Allowable Band 283.5-284.7 Difference Conversion (13) x 10 14 F.1 290 2841 Allowable Band 2835-2847 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes 15 F.l 1440 1440 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (14) I (15) 16 FF,F.2

5gpm

.20 1.97

,F3 Allowable Band 1.96-1.98

(

Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading 17 F.l 3744.1 3752.9 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading time 18 F.l 1600 0000 8 Hour difference (10) - (17) 19 F.l 8.8 264.1 Allowable Band 263.5-264.7 7.25.2 Difference conversion (19) x 10 20 F.l 88 2641 Allowable Band 2635-2647 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months elapsed minutes 21 F.l 480 480 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage (20) I (21) 22 FF,F.2

5gpm

.18 5.50

,F3 Allowable Band 5.40-5.51 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage from previous 23 F.1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months F.1

.16

.18 Total Leakage (8) + (16) 24 F.1

30 gpm 1.55 2.17 Allowable Band 2.16-2.18 Differential Floor Drain 25 FF

2gpm Leakage (22) - (23)

(SR 3.4.4.1)

(

.02 5.34 Allowable Band 5.24-5.35 Pa!Y~ R of R

SOUTHERN NUCLEAR DOCUMENT TYPE:

PAGE PLANT E. I. HATCH SURVEILLANCE PROCEDURE 1 OF 73 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

SURVEILLANCE CHECKS 34SV-SUV-019-1 33.33 EXPIRATION APPROVALS:

EFFECTIVE DATE:

DEPARTMENT MGR G. L. Johnson DATE 11/19/02 DATE:

N/A SSMI PM N/A DATE N/A 8-7-09 1.0 OBJECTIVE This procedure contains those surveillance requirements of Technical Requirements Manual (TRM) 1 Technical Specifications (TS) such as channel checks, level, pressure AND temperature records AND other checks performed by the Operators without the need for additional procedures.

This procedure satisfies, in part OR in total, the requirements of the TRM 1 TS listed below:

SR 3.3.1.1.1 for 3.3.1.1-1 (1.a.),(2.a.),(2.b.),(2.c.),(2.e),(2.f),(3.),(4.),(6.)

SR 3.3.1.2.1, SR 3.3.1.2.3, SR 3.3.1.2.4, and 3.3.1.2.5 for 3.3.1.2-1 (1.)

SR 3.3.3.1.1 for 3.3.3.1-1 (1.), (2.a.), (2.b.), (2.c.), (2.d), (3.a.), (3.b.), (4.a.), (4.b.), (4.c.),

(5.), (9), (10), (12)

SR 3.3.4.2.1 for 3.3.4.2(a.)(b.)

SR 3.3.5.1.1 for 3.3.5.1-1 (1.a.),(1.b.),(1.c.),(1.d.),(2.a.),(2.b.),(2.c.), (2.d.), (2.e.), (2.9.),

(3.a.), (3.b.), (3.c.), (3.e.), (3.f.), (4.a.), (4.b.), (4.d.), (4.e.), (4.f.), (5.a.), (5.b.), (5.d.),

(5.e.), (5.f.)

SR 3.3.5.2.1 for 3.3.5.2-1 (1.),(2.)

SR 3.3.6.1.1 for 3.3.6.1-1 (1.a.),(1.c.),(1.e.),(2.a.),(2.b.),(2.c.),(2.d.), (2.e.), (3.a.), (3.b.),

(3.c.), (3.d.), (3.e.), (3.f.), (3.h.), (3.i.), (4.a.), (4.b.), (4.c.), (4.d.), (4.e.), (4.9.), (4.h.),

(5.a.), (5.b.), (5.d.), (6.a.), (6.b.)

SR 3.3.6.2.1 for 3.3.6.2-1 (1.),(2),(3.),(4.)

SR 3.3.6.3.1 for 3.3.6.3-1 (1.),(2.)

SR 3.3.8.1.1 for 3.3.8.1-1 (3.a.)

SR3.1.3.1, 3.1.6.1, 3.1.7.3, 3.1.8.1, 3.3.7.1.1, 3.4.4.1, 3.4.5.1, 3.4.7.1,3.4.8.1,3.4.9.7, 3.4.10.1, 3.5.1.2, 3.5.2.1, 3.5.2.2.a., 3.5.2.2.b., 3.5.2.4, 3.5.3.2, 3.6.1.4.1, 3.6.1.5.1, 3.6.1.7.1, 3.6.2.2.1, 3.6.1.8.1, 3.6.2.1.1, 3.6.3.2.1, 3.6.4.3.2, Unit 2 SR 3.6.4.3.2,3.7.2.1, 3.7.4.2, Unit 2 SR 3.7.4.2, 3.8.1.3, 3.9.2.1, 3.9.4.1, 3.9.5.2, 3.9.7.1, 3.9.8.1, 3.10.2.1, 3.10.2.2,3.10.8.1 TS 5.5.8.a., 5.5.4.f., 5.5.7, Unit 2 TS 5.5.7 MGR-0002 Ver. 8.1

(

SOUTHERN NUCLEAR DOCUMENT TYPE:

PAGE PLANT E. I. HATCH SURVEILLANCE PROCEDURE 1 OF 73 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

SURVEILLANCE CHECKS 34SV-SUV-019-1 33.33 EXPIRATION APPROVALS:

EFFECTIVE DATE:

DEPARTMENT MGR G. L. Johnson DATE 11/19/02 DATE:

N/A SSM 1 PM N/A DATE N/A 8-7-09 1.0 OBJECTIVE This procedure contains those surveillance requirements of Technical Requirements Manual (TRM) 1 Technical Specifications (TS) such as channel checks, level, pressure AND temperature records AND other checks performed by the Operators without the need for additional procedures.

This procedure satisfies, in part OR in total, the requirements of the TRM 1 TS listed below:

SR 3.3.1.1.1 for 3.3.1.1-1 (1.a.),(2.a. ),(2.b. ),(2.c.),(2.e ),(2.f),(3. ),(4. ),(6.)

SR 3.3.1.2.1, SR 3.3.1.2.3, SR 3.3.1.2.4, and 3.3.1.2.5 for 3.3.1.2-1 (1.)

SR3.3.3.1.1 for 3.3.3.1-1 (1.), (2.a.), (2.b.), (2.c.), (2.d), (3.a.), (3.b.), (4.a.), (4.b.), (4.c.),

(5.), (9), (10), (12)

SR 3.3.4.2.1 for 3.3.4.2(a.)(b.)

SR 3.3.5.1.1 for 3.3.5.1-1 (1.a.),(1.b.),(1.c.),(1.d.),(2.a.),(2.b.),(2.c.), (2.d.), (2.e.), (2.9.),

(3.a.), (3.b.), (3.c.), (3.e.), (3.f.), (4.a.), (4.b.), (4.d.), (4.e.), (4.f.), (5.a.), (5.b.), (5.d.),

(5.e.), (5.f.)

SR 3.3.5.2.1 for 3.3.5.2-1 (1.),(2.)

SR 3.3.6.1.1 for 3.3.6.1-1 (1.a.),(1.c. ),( 1.e.),(2.a.),(2.b.),(2.c. ),(2.d.), (2.e.), (3.a.), (3.b.),

(3.c.), (3.d.), (3.e.), (3.f.), (3.h.), (3.i.), (4.a.), (4.b.), (4.c.), (4.d.), (4.e.), (4.9.), (4.h.),

(5.a.), (5.b.), (5.d.), (6.a.), (6.b.)

SR 3.3.6.2.1 for 3.3.6.2-1 (1.),(2),(3.),(4.)

SR 3.3.6.3.1 for 3.3.6.3-1 (1.),(2.)

SR 3.3.8.1.1 for 3.3.8.1-1 (3.a.)

SR3.1.3.1, 3.1.6.1, 3.1.7.3, 3.1.8.1, 3.3.7.1.1, 3.4.4.1, 3.4.5.1, 3.4.7.1, 3.4.8.1, 3.4.9.7, 3.4.10.1, 3.5.1.2, 3.5.2.1, 3.5.2.2.a., 3.5.2.2.b., 3.5.2.4, 3.5.3.2, 3.6.1.4.1, 3.6.1.5.1, 3.6.1.7.1, 3.6.2.2.1, 3.6.1.8.1, 3.6.2.1.1, 3.6.3.2.1, 3.6.4.3.2, Unit 2 SR 3.6.4.3.2, 3.7.2.1, 3.7.4.2, Unit 2 SR 3.7.4.2, 3.8.1.3, 3.9.2.1, 3.9.4.1, 3.9.5.2, 3.9.7.1, 3.9.8.1, 3.10.2.1, 3.10.2.2, 3.10.8.1 TS 5.5.8.a., 5.5.4.f., 5.5.7, Unit 2 TS 5.5.7 MGR-0002 Ver. 8.1

(

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS TSR 3.3.3.1 for T3.3.3-1 (2.),(3.),(4.),(5.),(8.),(9.)

DOCUMENT NUMBER:

34SV-SUV-019-1 TSR 3.3.5.1 for T3.3.5-1 (2.),(3.),(5.),(6.),(7.a.),(7.b.)

TSR 3.3.7.1 for T3.3.7-1 (1.),(2.),(3.),(4.),(5.)

TSR 3.3.8.1 for T3.3.8-1 (1.),(2.)

TSR 3.3.9.1 TSR 3.3.11.1, TSR 3.3.13, TSR 3.4.1.1 ODCM, Table 2-1 (2.), (4.)

ODCM, Table 3-1 (1.a.), (1.d.), (3.a.), (4.a.)

2.0 APPLICABILITY PAGE 20F73 VERSION NO:

33.33 This procedure applies to Unit 1 Control Room instrumentation and other plant instrumentation which is directly related to Control Room surveillance requirements. This procedure is performed daily.

3.0 REFERENCES

3.1 Technical Specifications, Unit 1 3.2 ODCM 3.3 Technical Requirements Manual, Unit 1 3.4 DI-OPS-55-0193, Computerized Rounds 3.5 A-16397, Instrument Setpoint Index Drawing, Unit 1 G16.030 MGR-0001 Ver. 4

(

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS TSR 3.3.3.1 for T3.3.3-1 (2.),(3.),(4.),(5.),(8.),(9.)

DOCUMENT NUMBER:

34SV-SUV-019-1 TSR 3.3.5.1 forT3.3.5-1(2.),(3.),(5.),(6.),(7.a.),(7.b.)

TSR 3.3.7.1 for T3.3. 7-1 (1.),(2.),(3.),(4.),(5.)

TSR 3.3.8.1 for T3.3.8-1 (1.),(2.)

TSR 3.3.9.1 TSR 3.3.11.1, TSR 3.3.13, TSR 3.4.1.1 ODCM, Table 2-1 (2.), (4.)

ODCM, Table 3-1 (1.a.), (1.d.), (3.a.), (4.a.)

2.0 APPLICABILITY PAGE 2 OF 73 VERSION NO:

33.33 This procedure applies to Unit 1 Control Room instrumentation and other plant instrumentation which is directly related to Control Room surveillance requirements. This procedure is performed daily.

3.0 REFERENCES

3.1 Technical Specifications, Unit 1 3.2 ODCM 3.3 Technical Requirements Manual, Unit 1 3.4 DI-OPS-55-0193, Computerized Rounds 3.5 A-16397, Instrument Setpoint Index Drawing, Unit 1 G16.030 MGR-0001 Ver. 4

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS DOCUMENT NUMBER:

34SV-SUV-019-1 PAGE 30F73 VERSION NO:

33.33 The number AND qualification level of Operations personnel performing this procedure will be determined by the Shift Supervisor.

4.2 MATERIAL AND EQUIPMENT NIA - Not applicable to this procedure 4.3 SPECIAL REQUIREMENTS 4.3.1 All readings identified as unsatisfactory OR NOT meeting the limit in the TSIOperating Limit column must be circled in red, initialed by a Licensed Operator, AND reported to the Shift Supervisor. IF readings were taken using a computer, readings identified as unsatisfactory OR NOT meeting the minimax limits in the computer will be reviewed by the Shift Supervisor.

4.3.2 The following notes apply as designated in the NOTES column:

A.

WHEN total time reaches 650 hours0.00752 days 0.181 hours 0.00107 weeks 2.47325e-4 months , the filter must be tested per 42SV-T46-003-1, Testing of SBGT Filter Trains OR 42SV-Z41-002-0, Testing of Control Room Habitability Trains.

B.

Check ( ~ ) OR enter "SAT" !E item satisfactory. Enter "UNSAT" AND circle in red !E item is unsatisfactory.

C.

NOT a TRM I TS instrument OR requirement.

D.

Check that the green status light is lit, !E installed; the gross failure light is OFF; AND the red tripped light is OFF UNLESS the instrument is tripped due to a valid plant condition (Le., low flow Core Spray pump AlB tripped indication red light ILLUMINATED WHEN Core Spray pump NOT operating). Circle in red !E item is unsatisfactory.

E.

Main power switch on Analyzers A & B (Panels 1 P33-P601A & B) must be placed in the ANALYZE position one hour before taking readings.

F.1 Enter "N/A" !E the integrator is OR was inoperable due to drifting OR is OR was NOT required to be operable. For actual time AND present reading, enter data WHEN integrator is restored to service OR required to be operable.

F.2 Use 34S0-G11-013-1 to calculate leakage!E integrator drifting. Circle the results in red OR, !E using HHC, add note stating integrator drifting.

F.3 IF an abnormal increase in Drywell Floor Drain leakage has been noted AND Drywell average temperature is < 100'F, request Engineering to evaluate the need to secure some drywell cooling fans. This is due to the possibility of excessive moisture condensation at the low drywell temperature.

G16.030 MGR-0001 Ver. 4

(

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS DOCUMENT NUMBER:

34SV-SUV-019-1 PAGE 3 OF 73 VERSION NO:

33.33 The number AND qualification level of Operations personnel performing this procedure will be determined by the Shift Supervisor.

4.2 MATERIAL AND EQUIPMENT NIA - Not applicable to this procedure 4.3 SPECIAL REQUIREMENTS 4.3.1 All readings identified as unsatisfactory OR NOT meeting the limit in the TSIOperating Limit column must be circled in red, initialed by a Licensed Operator, AND reported to the Shift Supervisor. IF readings were taken using a computer, readings identified as unsatisfactory OR NOT meeting the minimax limits in the computer will be reviewed by the Shift Supervisor.

4.3.2 The following notes apply as designated in the NOTES column:

A.

WHEN total time reaches 650 hours0.00752 days 0.181 hours 0.00107 weeks 2.47325e-4 months , the filter must be tested per 42SV-T46-003-1, Testing of SBGT Filter Trains OR 42SV-Z41-002-0, Testing of Control Room Habitability Trains.

B.

Check (~) OR enter "SAT" !E item satisfactory. Enter "UNSAT" AND circle in red!E item is unsatisfactory.

C.

NOT a TRM I TS instrument OR requirement.

D.

Check that the green status light is lit, !E installed; the gross failure light is OFF; AND the red tripped light is OFF UNLESS the instrument is tripped due to a valid plant condition (Le., low flow Core Spray pump AlB tripped indication red light ILLUMINATED WHEN Core Spray pump NOT operating). Circle in red IF item is unsatisfactory.

E.

Main power switch on Analyzers A & B (Panels 1 P33-P601A & B) must be placed in the ANALYZE position one hour before taking readings.

F.1 Enter "N/A" !E the integrator is OR was inoperable due to drifting OR is OR was NOT required to be operable. For actual time AND present reading, enter data WHEN integrator is restored to service OR required to be operable.

F.2 Use 34S0-G11-013-1 to calculate leakage!E integrator drifting. Circle the results in red OR, !E using HHC, add note stating integrator drifting.

F.3 IF an abnormal increase in Drywell Floor Drain leakage has been noted AND Drywell average temperature is < 100'F, request Engineering to evaluate the need to secure some drywell cooling fans. This is due to the possibility of excessive moisture condensation at the low drywell temperature.

G16.030 MGR-0001 Ver. 4

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 PAGE 40F73 VERSION NO:

33.33 G.

IF Process Computer is unavailable, use Attachment 1, otherwise, attach a Rod Pattern Log (OD 7) printout.

H.

Day shift will RECORD the run time of SBGT filter trains AND Control Room Filter trains from 1200 EASTERN Time one day to 1200 EASTERN Time the next day AND THEN calculate the Total Run Times.

I.

Operations Personnel initials required.

J.

Refer to Attachment 2 for Torus Temperature Monitoring.

K.

The Post-LOCA radiation monitors 1 D11-K622A AND 1 D11-K622B are to be used as a pre-planned alternate for 1D11-K621AAND 1D11-K621B, High Range Radiation Monitors IF the high range instruments are inoperable. See TS Table 3.3.3.1-1, Item 5.

L.

IF Drywell average temperature is > 135'F, confirm OR PLACE Drywell Cooling System in Additional Cooling Operating Mode per 34S0-T47-001-1.

IF Drywell average temperature is < 120'F, confirm OR PLACE Drywell Cooling System in Normal Operating Mode per 34S0-T47-001-1.

IF Drywell average temperature is < 100'F AND an abnormal increase in Drywell Floor Drain leakage has been noted, request Engineering to evaluate the need to secure some drywell cooling fans. This is due to the possibility of excessive moisture condensation at the low drywell temperature.

M.

For the following ranges of Reactor Coolant temp. with Rx. head installed, utilize the applicable formula to obtain level.

L = Actual level LI = Indicated level on 1B21-R605

< 200°F L =.74 LI + 9 2: 200'F to < 300'F L =.75 L 1+10 2: 300'F to < 400'F L =.80 L 1+9 2: 400'F to < 500'F L =.86 L 1+7 With Rx Coolant temp 2: 500'F, no correction is necessary for 1 B21-R605 re cord indicated level AND N/A corrected level. Obtain Reactor Coolant temp. from 1 B31-R650AlB, 1 E41-R605 pt 1 OR 2, OR equivalent.

Corrected Level = indicated level !E the temporary reference leg is connected.

G16.030 MGR-0001 Ver. 4

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 4 OF 73 DOCUMENT TITLE:

DOCUMENT NUMBER:

34SV-SUV-019-1 VERSION NO:

33.33 SURVEILLANCE CHECKS G.

IF Process Computer is unavailable, use Attachment 1, otherwise, attach a Rod Pattern Log (OD 7) printout.

H.

Day shift will RECORD the run time of SBGT filter trains AND Control Room Filter trains from 1200 EASTERN Time one day to 1200 EASTERN Time the next day AND THEN calculate the Total Run Times.

I.

Operations Personnel initials required.

J.

Refer to Attachment 2 for Torus Temperature Monitoring.

K.

The Post-LOCA radiation monitors 1 D11-K622A AND 1 D11-K622B are to be used as a pre-planned alternate for 1 D11-K621A AND 1 D11-K621 B, High Range Radiation Monitors IF the high range instruments are inoperable. See TS Table 3.3.3.1-1, Item 5.

L.

IF Drywell average temperature is > 135'F, confirm OR PLACE Drywell Cooling System in Additional Cooling Operating Mode per 34S0-T47-001-1.

IF Drywell average temperature is < 120'F, confirm OR PLACE Drywell Cooling System in Normal Operating Mode per 34S0-T47-001-1.

IF Drywell average temperature is < 100'F AND an abnormal increase in Drywell Floor Drain leakage has been noted, request Engineering to evaluate the need to secure some drywell cooling fans. This is due to the possibility of excessive moisture condensation at the low drywell temperature.

M.

For the following ranges of Reactor Coolant temp. with Rx. head installed, utilize the applicable formula to obtain level.

L = Actual level LI = Indicated level on 1 B21-R605

< 200°F L =.74 LI + 9 2: 200'F to < 300'F L =.75 L I + 10 2: 300'F to < 400'F L =.80 L 1+9 2: 400'F to < 500'F L =.86 L 1+7 With Rx Coolant temp 2: 500'F, no correction is necessary for 1 B21-R605 re cord indicated level AND N/A corrected level. Obtain Reactor Coolant temp. from 1 B31-R650AlB, 1 E41-R605 pt 1 OR 2, OR equivalent.

Corrected Level = indicated level !E the temporary reference leg is connected.

G16.030 MGR-0001 Ver. 4

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 PAGE 50F 73 VERSION NO:

33.33 N.

Corrected Level = indicated level-15!E the reactor is in COLD SHUTDOWN.

Corrected Level = indicated level IF > 212'F. N/A corrected level.

O.

If required, adjust RlF AND Rx Bldg. to outside air delta pressure using 34S0-T41-006-1 AND 34S0-T41-005-1.

P.

Check that no trips OR alarms are present. Check that Self-Test Status indicates OK.

Q.

Alternate the DIW sump pumps in the PTL position on Monday. Check C'I/) when completed.

R.

TRM I TS recorders are required to be advancing, the pen inking, AND the pen must be indicating the parameter value as indicated by a channel check BEFORE it can be considered operable. Acceptable instrument reading is WHEN pen is properly on-scale AND neither upscale OR downscale. Refer to the "Video Graphic Recorders" section of 31 GO-OPS-007-0, Shift Logs and Relief of Personnel, for additional information concerning proper operation of paperless recorders.

G16.030 MGR-0001 Ver. 4

/

\\

(

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 PAGE 50F 73 VERSION NO:

33.33 N.

Corrected Level = indicated level-15!E the reactor is in COLD SHUTDOWN.

Corrected Level = indicated level IF > 212'F. N/A corrected level.

O.

If required, adjust RlF AND Rx Bldg. to outside air delta pressure using 34S0-T 41-006-1 AN D 34S0-T 41-005-1.

P.

Check that no trips OR alarms are present. Check that Self-Test Status indicates OK.

Q.

Alternate the DIW sump pumps in the PTL position on Monday. Check (...J) when completed.

R.

TRM I TS recorders are required to be advancing, the pen inking, AND the pen must be indicating the parameter value as indicated by a channel check BEFORE it can be considered operable. Acceptable instrument reading is WHEN pen is properly on-scale AND neither upscale OR downscale. Refer to the "Video Graphic Recorders" section of 31 GO-OPS-007-0, Shift Logs and Relief of Personnel, for additional information concerning proper operation of paperless recorders.

G16.030 MGR-0001 Ver. 4

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

PAGE 60F73 SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 VERSION NO:

33.33 S.

IF recorders 1T47-R611 AND/OR 1T47-R612 AND/OR SPDS are INOP, THEN substitute subject reading from SPDS OR from I&C test equipment.

For Torus water temperature readings per following indicated Test Points use Voltage to Temperature Conversion Chart below to determine equivalent temperature. Add note/comment indicating that instrument is INOP, AND source of reading.

Sensor Alternate Reading Test Point-VDC (Instrument/Panel)

(see figure below) 1T4B-N301A 1T4B-K610/ 1 H11-P691 A

[3(+)&3(-)]

1T4B-N302A 1 T4B-K61 0/ 1 H11-P691 B

[4(+)&4(-)]

1T4B-N303A 1T4B-K611 /1H11-P691 A

[3(+)&3(-)]

1T4B-N304A 1 T4B-K611 / 1 H11-P691 B

[4(+)&4(-)]

1T4B-N305A 1 T4B-K612 / 1 H11-P691 A

[ 3 J +} & 31-)J 1T4B-N306A 1T4B-K612/ 1 H11-P691 B

[4J+) & 41-)J 1T4B-N307A 1 T4B-K613 / 1 H11-P691 A [3 (+) & 3 (-) 1 1T4B-N30BA 1T4B-K613/1H11-P691 B

[41+}& 41-)J 1T4B-N309A 1T4B-K614/ 1 H11-P691 A

[ 3 _(+J & 31-) 1 1T4B-N310A 1T4B-K614/ 1 H11-P691 B

[4(+)&4(-)]

1T4B-N311A 1T4B-K615/ 1 H11-P691 A

[3(+)&3(-)]

B A

' ___ I G16.030 MGR-0001 Ver. 4

(

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

PAGE 6 OF 73 SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 VERSION NO:

33.33 S.

IF recorders 1T47-R611 AND/OR 1T47-R612 AND/OR SPDS are INOP, THEN substitute subject reading from SPDS OR from I&C test equipment.

For Torus water temperature readings per following indicated Test Points use Voltage to Temperature Conversion Chart below to determine equivalent temperature. Add note/comment indicating that instrument is INOP, AND source of reading.

Sensor 1T48-N301A 1T48-N302A 1T48-N303A 1T48-N304A 1T48-N305A 1T48-N306A 1T48-N307A 1T48-N30SA 1T48-N309A 1T48-N310A 1T48-N311A MGR-0001 Ver. 4 Alternate Reading (InstrumenUPanel) 1 T 48-K61 0/ 1 H11-P691 1T48-K610/1H11-P691 1T48-K611 /1H11-P691 1 T48-K611 / 1 H11-P691 1 T48-K612 / 1 H11-P691 1 T48-K612 / 1 H11-P691 1 T48-K613 / 1 H11-P691 1 T48-K613 / 1 H11-P691 1 T48-K614 / 1 H11-P691 1T48-K614/ 1 H11-P691 1T48-K615/1H11-P691 A

G16.030 B

Test Point-VDC (see figure below)

A

[3(+)&3(-)]

B

[4(+)&4(-)]

A

[3(+)&3(-)]

B

[4(+)&4(-)]

A

[3(+)&3(-)]

B

[4(+)&4(-)]

A

[3(+)&3(-)]

B

[4(+)&4(-)]

A

[3(+)&3(-)]

B

[4(+)&4(-)]

A

[3(+)&3(-)]

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 7 OF 73 DOCUMENT TITLE:

SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 VERSION NO:

33.33 VOLTAGE TO TEMPERATURE CONVERSION CHART TEST EQUALS C,'

TEST EQUALS I)

TEST EQUALS ;:

TEST EQUALS

~2)

TEST EQUALS READING (VDC) 0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 0.40 0.45 0.50 0.55 0.60 0.65 0.70 0.75 0.80 0.85 0.90 0.95 1.00 1.05 1.10 1.15 1.20 1.25 1.30 1.35 1.40 1.45 1.50 1.55 1.60 1.65 1.70 1.75 1.80 1.85 1.90 1.95 READING READING READING READING (OF)

J~

(VDC)

(OF)

(VDC) eFt (VDq (OF)

(VDC) 50 i"

2.00 90 i"

4.00 130

.!;{

6.00 170 <

8.00 51 2.05 91 4.05 131 6.05 171 8.05 52

?'

2.10 92 I'>.

4.10 132 6.10 172

.i 8.10 53 2.15 93 Ii 4.15 133 6.15 173 8.15 54 2.20 94

f.

4.20 134 6.20 174 8.20 55 I,.;

2.25 95 F';

4.25 135

\\.

6.25 175 8.25 56 Iii 2.30 96 Ii 4.30 136 oe 6.30 176 8.30 57 I*,;;

2.35 97 I

4.35 137

'c*

6.35 177 8.35 58 2.40 98 4.40 138 6.40 178 8.40 59 F<\\

2.45 99 4.45 139 (i

6.45 179 0

8.45 60 I.'

2.50 100 It 4.50 140

{

6.50 180 8.50 61 tIl 2.55 101 4.55 141 6.55 181

.*c, 8.55 62 I{

2.60 102 fr 4.60 142 if 6.60 182 8.60 63 I;

2.65 103 I.

4.65 143 6.65 183

(.

8.65 64 Ii' 2.70 104 I:

4.70 144 C

6.70 184 i

8.70 65 2.75 105 liZ 4.75 145 6.75 185

./

8.75 66 i

2.80 106 I.*

4.80 146 6.80 186

.J 8.80 67 2.85 107 4.85 147 6.85 187 i

8.85 68 1<

2.90 108 i>

4.90 148 6.90 188 8.90 69 Ir;.

2.95 109

)

4.95 149 6.95 189

.l.

8.95 70 3.00 110 H:

5.00 150 7.00 190 9.00 71 I.;'>

3.05 111 5.05 151 I?:..

7.05 191 r

9.05 72 I';

3.10 112 5.10 152 iX" 7.10 192 i"

9.10 73 Ii.

3.15 113 r"

5.15 153 7.15 193 9.15 74 3.20 114

/.,

5.20 154

);

7.20 194 '.

9.20 75 3.25 115 5.25 155 7.25 195 C'

9.25 76 3.30 116 5.30 156 7.30 196

'i 9.30 77 Io'r; 3.35 117

X 5.35 157 7.35 197 If 9.35 78 Ui 3.40 118

f 5.40 158

.o' 7.40 198 I',

9.40 79 1'<

3.45 119 5.45 159 7.45 199 i*,*

9.45 80

/f' 3.50 120 5.50 160 I'.

7.50 200 Iii 9.50 81 3.55 121 5.55 161 I"

7.55 201 I"

9.55 82 3.60 122

<1 5.60 162 1.1:

7.60 202 I'

9.60 83 j

3.65 123 5.65 163 1/'

7.65 203 I::

9.65 84 C:.

3.70 124

X' 5.70 164 I;'.)

7.70 204 I',

9.70 85

'i.;.

3.75 125 5.75 165 I::

7.75 205 I.

9.75 86 3.80 126 5.80 166 IE 7.80 206 I

9.80 87

3.85 127

',.~

5.85 167 7.85 207 I;

9.85 88 "

3.90 128 5.90 168 1\\

7.90 208 I;

9.90 89 3.95 129 5.95 169 I....

7.95 209 1\\>

9.95 10.00 T.

!E 1T48-R635 Pt 1 OR 2 is INOP, THEN substitute value from SPDS by subtracting Torus pressure from Drywell pressure.

The numerical value of the instrument listed is to be recorded for those instruments NOT designated with note "B" UNLESS otherwise specified.

G16.030 MGR-0001 Ver. 4 (OFl 210 211 212 213 214 215 216 217 218 219 220 221 222 223 224 225 226 227 228 229 230 231 232 233 234 235 236 237 238 239 240 241 242 243 244 245 246 247 248 249 250

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 7 OF 73 DOCUMENT TITLE:

SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 VERSION NO:

33.33 VOL TAGE TO TEMPERATURE CONVERSION CHART TEST EQUALS TEST EQUALS TEST EQUALS TEST EQUALS TEST EQUALS READING (VDC) 0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 0.40 0.45 0.50 0.55 0.60 0.65 0.70 0.75 0.80 0.85 0.90 0.95 1.00 1.05 1.10 1.15 1.20 1.25 1.30 1.35 1.40 1.45 1.50 1.55 1.60 1.65 1.70 1.75 1.80 1.85 1.90 1.95 READING READING READING READING (OF)

(VDC)

(OF)

(VDC)

(OF)

(VDC)

(OF)

(VDC) 50 2.00 90 4.00 130 6.00 170 8.00 51 2.05 91 4.05 131 6.05 171 8.05 52 2.10 92 4.10 132 6.10 172 8.10 53 2.15 93 4.15 133 6.15 173 8.15 54 2.20 94 4.20 134 6.20 174 8.20 55 2.25 95 4.25 135 6.25 175 8.25 56 2.30 96 4.30 136 6.30 176 8.30 57 2.35 97 4.35 137 6.35 177 8.35 58 2.40 98 4.40 138 6.40 178 8.40 59 2.45 99 4.45 139 6.45 179 8.45 60 2.50 100 4.50 140 6.50 180 8.50 61 2.55 101 4.55 141 6.55 181 8.55 62 2.60 102 4.60 142 6.60 182 8.60 63 2.65 103 4.65 143 6.65 183 8.65 64 2.70 104 4.70 144 6.70 184 8.70 65 2.75 105 4.75 145 6.75 185 8.75 66 2.80 106 4.80 146 6.80 186 8.80 67 2.85 107 4.85 147 6.85 187 8.85 68 2.90 108 4.90 148 6.90 188 8.90 69 2.95 109 4.95 149 6.95 189 8.95 70 3.00 110 5.00 150 7.00 190 9.00 71 3.05 111 5.05 151 7.05 191 9.05 72 3.10 112 5.10 152 7.10 192 9.10 73 3.15 113 5.15 153 7.15 193 9.15 74 3.20 114 5.20 154 7.20 194 9.20 75 3.25 115 5.25 155 7.25 195 9.25 76 3.30 116 5.30 156 7.30 196 9.30 77 3.35 117 5.35 157 7.35 197 9.35 78 3.40 118 5.40 158 7.40 198 9.40 79 3.45 119 5.45 159 7.45 199 9.45 80 3.50 120 5.50 160 7.50 200 9.50 81 3.55 121 5.55 161 7.55 201 9.55 82 3.60 122 5.60 162 7.60 202 9.60 83 3.65 123 5.65 163 7.65 203 9.65 84 3.70 124 5.70 164 7.70 204 9.70 85 3.75 125 5.75 165 7.75 205 9.75 86 3.80 126 5.80 166 7.80 206 9.80 87 3.85 127 5.85 167 7.85 207 9.85 88 3.90 128 5.90 168 7.90 208 9.90 89 3.95 129 5.95 169 7.95 209 9.95 10.00 T.

!E 1T48-R635 Pt 1 OR 2 is INOP, THEN substitute value from SPDS by subtracting Torus pressure from Drywell pressure.

The numerical value of the instrument listed is to be recorded for those instruments NOT designated with note "B" UNLESS otherwise specified.

G16.030 MGR-0001 Ver. 4 (OF) 210 211 212 213 214 215 216 217 218 219 220 221 222 223 224 225 226 227 228 229 230 231 232 233 234 235 236 237 238 239 240 241 242 243 244 245 246 247 248 249 250

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 U.

Swap Suction Source to Torus, obtain O2 reading, WHEN stabilized, PAGE 80F73 VERSION NO:

33.33 THEN swap back to the Drywell per 34S0-P33-003-1, Drywell & Torus Atmosphere Oxygen Analyzer System.

V.

Min. and Max. limits may be added to the computerized round when not specified by procedure. This note will only appear in the computerized round when applicable. If reading is abnormal due to these added limits, a Condition Report (CR) is NOT required to change the limit. If changes to these limits are needed, notify (Le., email)

Software Support personnel so that the limits may be investigated and changed. The following notes are used to specify when either the Min or Max. limit has been added.

V.1 Minimum limit not specified by procedure.

V.2 Maximum limit not specified by procedure.

W.

IF the specified component OR reading is NOT available (Le., DCR work in progress),

THEN substitute values for the reading as follows:

Record value from 1 B21-R623A Fuel Zone Range (Uncompensated). IF 1 B21-R623A Fuel Zone Range is NOT available, THEN substitute value from 1B21-N685A (1 H11-P925 panel) AND initiate RAS for inoperable instruments.*

Record value from 1 B21-R623B Fuel Zone Range (Uncompensated). IF 1 B21-R623B Fuel Zone Range is NOT available, THEN substitute value from 1B21-N685B (1 H11-P926 panel) AND initiate RAS for inoperable instruments.*

IF 1 B21-R623A Fuel Zone Range (Compensated) is NOT available, THEN record - 317 (downscale).*

IF 1 B21-R623B Fuel Zone Range (Compensated) is NOT available, THEN record - 317 (downscale).*

IF 1 B21-R623A Wide Range (Uncompensated) is NOT available, THEN substitute value from 1 B21-R604A (1 H11-P603 panel) AND initiate RAS for inoperable instruments.*

IF 1 B21-R623B Wide Range (Uncompensated) is NOT available, THEN substitute value from 1 B21-R604B (1 H11-P603 panel) AND initiate RAS for inoperable instruments.*

IF 1 B21-R623A Wide Range (Compensated) is NOT available, THEN record - 150 (downscale).*

IF 1B21-R623B Wide Range (Compensated) is NOT available, THEN record -150 (downscale).*

IF 1 B21-R623A RPV pressure is NOT available, THEN record 1 B21-N690A (1 H11-P927 panel) value.*

IF 1 B21-R623B RPV pressure is NOT available, THEN record 1 B21-N690D (1 H11-P928 panel) value.*

Enter note I comment for substituted value(s) recorded.

IF the operating condition specified for a reading does NOT match the current plant operating mode, THEN place "N/A" as the value for the reading.

G16.030 MGR-0001 Ver. 4

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 8 OF 73 DOCUMENT TITLE:

DOCUMENT NUMBER:

34SV-SUV-019-1 VERSION NO:

33.33 SURVEILLANCE CHECKS U.

Swap Suction Source to Torus, obtain O2 reading, WHEN stabilized, THEN swap back to the Drywell per 34S0-P33-003-1, Drywell & Torus Atmosphere Oxygen Analyzer System.

V.

Min. and Max. limits may be added to the computerized round when not specified by procedure. This note will only appear in the computerized round when applicable. If reading is abnormal due to these added limits, a Condition Report (CR) is NOT required to change the limit. If changes to these limits are needed, notify (Le., email)

Software Support personnel so that the limits may be investigated and changed. The following notes are used to specify when either the Min or Max. limit has been added.

W.

V.1 Minimum limit not specified by procedure.

V.2 Maximum limit not specified by procedure.

IF the specified component OR reading is NOT available (Le., DCR work in progress),

THEN substitute values for the reading as follows:

Record value from 1 B21-R623A Fuel Zone Range (Uncompensated). IF 1 B21-R623A Fuel Zone Range is NOT available, THEN substitute value from 1B21-N685A (1 H11-P925 panel) AND initiate RAS for inoperable instruments.*

Record value from 1 B21-R623B Fuel Zone Range (Uncompensated). IF 1 B21-R623B Fuel Zone Range is NOT available, THEN substitute value from 1B21-N685B (1 H11-P926 panel) AND initiate RAS for inoperable instruments.*

IF 1 B21-R623A Fuel Zone Range (Compensated) is NOT available, THEN record - 317 (downscale).*

IF 1 B21-R623B Fuel Zone Range (Compensated) is NOT available, THEN record - 317 (downscale).*

IF 1 B21-R623A Wide Range (Uncompensated) is NOT available, THEN substitute value from 1 B21-R604A (1 H11-P603 panel) AND initiate RAS for inoperable instruments.*

IF 1 B21-R623B Wide Range (Uncompensated) is NOT available, THEN substitute value from 1 B21-R604B (1 H11-P603 panel) AND initiate RAS for inoperable instruments.*

IF 1 B21-R623A Wide Range (Compensated) is NOT available, THEN record - 150 (downscale).*

IF 1 B21-R623B Wide Range (Compensated) is NOT available, THEN record - 150 (downscale).*

IF 1 B21-R623A RPV pressure is NOT available, THEN record 1 B21-N690A (1 H11-P927 panel) value.*

IF 1 B21-R623B RPV pressure is NOT available, THEN record 1 B21-N690D (1 H11-P928 panel) value. *

Enter note / comment for substituted value(s) recorded.

IF the operating condition specified for a reading does NOT match the current plant operating mode, THEN place "N/A" as the value for the reading.

G16.030 MGR-0001 Ver. 4

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 PAGE 90F73 VERSION NO:

33.33 X.

For instruments in which an indication of "Upscale" OR "Downscale" is expected based on the value of the parameter measured under the current operating mode AND the scale of the instrument, enter the min or max value that may be read on the gauge PRIOR to the reading being Upscale or Downscale. For example, the new Fuel Zone RWL bargraph displays on 1B21-R623A & B normally indicate upscale at 100% power. The max value for this RWL instrument range is -17 and therefore a value of -17 will be entered if upscale.

Y.

IF 1P41-R603 is INOP OR INVALID, THEN substitute value from one of the following:

1.

1 P41-R567 IE Unit One RBCCW HX A is in service

2.

1 P41-R569 IE Unit One RBCCW Hx B is in service,

3.

2P41-R372A IF Unit Two RBCCW HX A is in service,

4.

2P41-R372B IF Unit Two RBCCW Hx B is in service, or

5.

I&C installed test equipment. IE alternate indication is used add Note/comment indicating source of reading.

Z.

The operator will enter the Self Test page to check for error messages.

A FAILURE detected by the APRM self-test feature will be classified as a "CRITICAL" error OR "NON-CRITICAL" error.

A "CRITICAL" failure affects the operability of the instrument, AND causes alarm 603-210, APRM/OPRM TRIP, to annunciate.

A "NON-CRITICAL" failure, (which will NOT cause the above annunciator), does NOT render the APRM inoperable, but requires a CR to be written for I&C to investigate.

AA IE any LED fails to illuminate, initiate a CR. Failure of an LED does NOT render the APRM Voter inoperable.

BB.

The value listed in the TS or Operating limit OR Min.! Max. limit column is the acceptable operating value that is more conservative than EITHER the TS / TRM allowable value, if applicable, OR its actual instrument setpoint for that associated plant parameter. IE an out of spec reading exists, initiate a CR AND notify (Le., email) Operations computer support personnel to see if there is justification for changing the value listed in the TS or Operating limit OR Min.! Max. limit column.

CC.

IF either 1Z41-C009 or 1Z41-C010, Cable Spreading Room Fan, is found not running, then secure the other fan, 1Z41-C010 or 1Z41-C009.

Initiate compensatory action to confirm twice per shift that the temperature in the cable spreading room is less than 105 degrees F. An Engineering Evaluation is required if the temperature reaches 105 degrees F.

G16.030 MGR-0001 Ver. 4

(

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 9 OF 73 DOCUMENT TITLE:

DOCUMENT NUMBER:

34SV-SUV-019-1 VERSION NO:

33.33 SURVEILLANCE CHECKS X.

For instruments in which an indication of "Upscale" OR "Downscale" is expected based on the value of the parameter measured under the current operating mode AND the scale of the instrument, enter the min or max value that may be read on the gauge PRIOR to the reading being Upscale or Downscale. For example, the new Fuel Zone RWL bargraph displays on 1 B21-R623A & B normally indicate upscale at 100% power. The max value for this RWL instrument range is -17 and therefore a value of -17 will be entered if upscale.

Y.

IF 1P41-R603 is INOP OR INVALID, THEN substitute value from one of the following:

Z.

1.

1 P41-RS67 IE Unit One RBCCW HX A is in service

2.

1 P41-RS69 IE Unit One RBCCW Hx B is in service,

3.

2P41-R372A IF Unit Two RBCCW HX A is in service,

4.

2P41-R372B IE Unit Two RBCCW Hx B is in service, or S.

I&C installed test equipment. IE alternate indication is used add Note/comment indicating source of reading.

The operator will enter the Self Test page to check for error messages.

A FAILURE detected by the APRM self-test feature will be classified as a "CRITICAL" error OR "NON-CRITICAL" error.

A "CRITICAL" failure affects the operability of the instrument, AND causes alarm 603-210, APRM/OPRM TRIP, to annunciate.

A "NON-CRITICAL" failure, (which will NOT cause the above annunciator), does NOT render the APRM inoperable, but requires a CR to be written for I&C to investigate.

AA IE any LED fails to illuminate, initiate a CR. Failure of an LED does NOT render the APRM Voter inoperable.

BB.

The value listed in the TS or Operating limit OR Min.! Max. limit column is the acceptable operating value that is more conservative than EITHER the TS / TRM allowable value, if applicable, OR its actual instrument setpoint for that associated plant parameter. IF an out of spec reading exists, initiate a CR AND notify (i.e., email) Operations computer support personnel to see if there is justification for changing the value listed in the TS or Operating limit OR Min.! Max. limit column.

CC.

IF either 1 Z41-C009 or 1 Z41-C01 0, Cable Spreading Room Fan, is found not running, then secure the other fan, 1Z41-C010 or 1Z41-C009.

Initiate compensatory action to confirm twice per shift that the temperature in the cable spreading room is less than 10S degrees F. An Engineering Evaluation is required if the temperature reaches 10S degrees F.

G16.030 MGR-0001 Ver.4

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

SURVEILLANCE CHECKS DOCUMENT NUMBER:

34SV-SUV-019-1 PAGE 10 OF 73 VERSION NO:

33.33 DO.

Reset Total Nitrogen Usage, 1T48-R602 Pt. 38 on 1 H11-P654, on Saturday Day Shift by performing the following:

1.

Press the right arrow to reach the "TOTALIZER" screen.

2.

Open the front access panel on the recorder.

3.

Press "STOP".

4.

Press "Mem + Math"

5.

Press "ENTER".

6.

Press "Func".

7.

Scroll to the next screen by pressing the top right most button.

8.

Press "MATH RESET".

9.

Press "START".

EE From "Control" screen, SELECT "pressure xmittr" CONFIRM the following:

1)

Throttle Transmitter #1, Throttle Transmitter #2, Throttle Transmitter #3 read "okay".

2)

Confirm the following alarms are not present:

P1_P33 <R> PROCESSOR OFFLINE P1_P34 ~~PROCESSOR OFFLINE P1_P35 <T> PROCESSOR OFFLINE S1 P264 <R> PROCESSOR OFFLINE S1 P265 ~~PROCESSOR OFFLINE S1 P266 <T> PROCESSOR OFFLINE FF IF DWFD leakage is >0.5 GPM, perform the following:~~~~

~~1. Notify Management (Operations Duty Management AND Plant Hatch Duty Manager)~~
~~AND include DWFD leakage on the Morning Report under Major Equipment Impacting Operational Focus.~~
~~2. Each Operating crew will review 34AB-T23-002-1 at the beginning of shift AND log the DWFD leakage rate each shift.~~
~~3. Initiate a Condition Report and make a Control Room Log entry.~~
~~4. Engineering Support will include a graph of U-1 DWFD leakage in the Daily Status Report each Friday.~~
~~IF DWFD leakage is >1.5 GPM, perform the following:~~
~~1. Notify Management to schedule a Unit 1 shutdown based on DWFD leakage trend.~~
~~2. Initiate a Condition Report and make a Control Room Log entry.~~
~~3. Every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , calculate DWFD leakage and make a Control Room Log entry of the leakage rate.~~
~~IF DWFD leakage is >2.5 GPM, perform the following:~~
~~1. Perform a controlled shutdown of Unit 1 to repair the leakage.~~
~~2. Initiate a Condition Report and make a Control Room Log entry.~~
G16.030 MGR-0001 Ver. 4
(
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
SURVEILLANCE CHECKS DOCUMENT NUMBER:
34SV-SUV-019-1 PAGE 10 OF 73 VERSION NO:
33.33 DO.
Reset Total Nitrogen Usage, 1T48-R602 Pt. 38 on 1 H11-P654, on Saturday Day Shift by performing the following:
1.
~~Press the right arrow to reach the "TOTALIZER" screen.~~
2.
~~Open the front access panel on the recorder.~~
3.
~~Press "STOP".~~
4.
~~Press "Mem + Math"~~
5.
~~Press "ENTER".~~
6.
~~Press "Func".~~
7.
~~Scroll to the next screen by pressing the top right most button.~~
8.
~~Press "MATH RESET".~~
9.
Press "START".
EE From "Control" screen, SELECT "pressure xmittr" CONFIRM the following:
1)
~~Throttle Transmitter #1, Throttle Transmitter #2, Throttle Transmitter #3 read "okay".~~
2)
Confirm the following alarms are not present:
P1_P33 <R> PROCESSOR OFFLINE P1 P34 ~~PROCESSOR OFFLINE P1 P35 <T> PROCESSOR OFFLINE S1 P264 <R> PROCESSOR OFFLINE S1_P265 ~~PROCESSOR OFFLINE S1 P266 <T> PROCESSOR OFFLINE FF IF DWFD leakage is >0.5 GPM, perform the following:~~~~
~~1. Notify Management (Operations Duty Management AND Plant Hatch Duty Manager)~~
~~AND include DWFD leakage on the Morning Report under Major Equipment Impacting Operational Focus.~~
~~2. Each Operating crew will review 34AB-T23-002-1 at the beginning of shift AND log the DWFD leakage rate each shift.~~
~~3. Initiate a Condition Report and make a Control Room Log entry.~~
~~4. Engineering Support will include a graph of U-1 DWFD leakage in the Daily Status Report each Friday.~~
~~IF DWFD leakage is >1.5 GPM, perform the following:~~
~~1. Notify Management to schedule a Unit 1 shutdown based on DWFD leakage trend.~~
~~2. Initiate a Condition Report and make a Control Room Log entry.~~
~~3. Every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , calculate DWFD leakage and make a Control Room Log entry of the leakage rate.~~
~~IF DWFD leakage is >2.5 GPM, perform the following:~~
~~1. Perform a controlled shutdown of Unit 1 to repair the leakage.~~
~~2. Initiate a Condition Report and make a Control Room Log entry.~~
G16.030 MGR-0001 Ver. 4
SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 11 OF 73 DOCUMENT TITLE:
SURVEILLANCE CHECKS DOCUMENT NUMBER:
34SV-SUV-019-1 VERSION NO:
33.33 GG If the alarm is inop, OR illuminated, the actual DP for the associated Core Spray loop must be confirmed to be more negative than the alarm setpoint once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or the associated loop must be declared inoperable.
HH If the Core Spray DP is greater than the limit (less negative), OR if 1 E21-N004A(B) is inoperable, declare the associated Core Spray loop inoperable AND initiate a CR for I&C and Engineering to investigate.
Prior to exceeding 10 degrees F difference, place RHR in torus mixing per 34S0-E11-010-1.
4.3.3 Readings are required to be obtained WHEN in the Reactor Mode listed as follows:
1.
~~RUN~~
2.
~~STARTUP & HOT STANDBY~~
3.
~~HOT SHUTDOWN~~
4.
~~COLD SHUTDOWN~~
5.
~~REFUEL~~
6.
~~At all times 4.3.4 Readings are required at the following frequencies as noted in the FREQ column~~
~~a. Once / shift~~
~~b. Once / 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ~~
~~c. Once / 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ~~
~~d. Once / 7 days (day will be designated)~~
~~e. Once every 31 days (day will be designated) 4.3.5 Surveillances required once / 12 hr shift must be taken between 1200 and 1500 EASTERN Time on Day Shift AND between 0000 and 0300 on Night Shift.~~
4.3.6 ECCS Status Check is to be performed WITHIN 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of shift change per 34SV-SUV-018-1.
4.3.7 Surveillances required once / 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months must be taken within the time constraints established in step 4.3.5 for the once / 12 hr surveillances.
4.3.8 DIW Sump reading AND Fission Product reading are taken at times 0000, 0800, & 1600.
Surveillances required once/8 hours must be taken WITHIN 1.0 hour0 days 0 hours 0 weeks 0 months of the designated time.
4.3.9 "N/A" will be entered for all surveillances NOT required by existing plant conditions.
4.3.10 Independent Verification, as described in 10AC-MGR-019-0, Procedure Use and Adherence, will be required on each shift by a licensed operator for portions of this procedure where a "Calculations Verified" sign-off is given.
Verification of calculations is NOT required IE data is taken using the handheld computer.
G16.030 MGR-0001 Ver. 4
(
SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 11 OF 73 DOCUMENT TITLE:
SURVEILLANCE CHECKS DOCUMENT NUMBER:
34SV-SUV-019-1 VERSION NO:
33.33 GG If the alarm is inop, OR illuminated, the actual DP for the associated Core Spray loop must be confirmed to be more negative than the alarm setpoint once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or the associated loop must be declared inoperable.
HH If the Core Spray DP is greater than the limit (less negative), OR if 1 E21-N004A(B) is inoperable, declare the associated Core Spray loop inoperable AND initiate a CR for I&C and Engineering to investigate.
Prior to exceeding 10 degrees F difference, place RHR in torus mixing per 34S0-E11-010-1.
4.3.3 Readings are required to be obtained WHEN in the Reactor Mode listed as follows:
1.
~~RUN~~
2.
~~STARTUP & HOT STANDBY~~
3.
~~HOT SHUTDOWN~~
4.
~~COLD SHUTDOWN~~
5.
~~REFUEL~~
6.
~~At all times 4.3.4 Readings are required at the following frequencies as noted in the FREQ column~~
~~a. Once / shift~~
~~b. Once / 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ~~
~~c. Once / 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ~~
~~d. Once / 7 days (day will be designated)~~
~~e. Once every 31 days (day will be designated) 4.3.5 Surveillances required once / 12 hr shift must be taken between 1200 and 1500 EASTERN Time on Day Shift AND between 0000 and 0300 on Night Shift.~~
4.3.6 ECCS Status Check is to be performed WITHIN 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of shift change per 34SV-SUV-018-1.
4.3.7 Surveillances required once / 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months must be taken within the time constraints established in step 4.3.5 for the once / 12 hr surveillances.
4.3.8 DIW Sump reading AND Fission Product reading are taken at times 0000,0800, & 1600.
Surveillances required once/8 hours must be taken WITHIN 1.0 hour0 days 0 hours 0 weeks 0 months of the designated time.
4.3.9 "N/A" will be entered for all surveillances NOT required by existing plant conditions.
4.3.10 Independent Verification, as described in 1 OAC-MGR-019-0, Procedure Use and Adherence, will be required on each shift by a licensed operator for portions of this procedure where a "Calculations Verified" sign-off is given.
Verification of calculations is NOT required IE data is taken using the handheld computer.
G16.030 MGR-0001 Ver. 4
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
SURVEILLANCE CHECKS DOCUMENT NUMBER:
34SV-SUV-019-1 PAGE 12 OF 73 VERSION NO:
33.33 4.3.11 IF an Operator fails to complete any signoff/initial spaces, an SS OR SOS may sign off/initial the space.
4.3.12 Night shift begins at 1900 EASTERN Time, i.e., where a reading is specified for Saturday night shift, it will be taken from 1900 EASTERN Time Friday to 0700 EASTERN Time Saturday.
4.3.13 IF using the paper copy of this procedure, Attachment 3 is NOT required.
NOTE:
IF a word such as "INOP" is entered into a station in place of a value, any calculation performed with that station will substitute a numeric value of zero for the word. IF the calculation is a channel check, appropriate action must be taken for the inoperable instrument AND to ensure adequate channel check of remaining operable instruments.
4.3.14
!E the procedure is to be performed using the computerized rounds software, the procedure beginning with 7.1 may be completed by completing the following:
NOTE:
8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months tour is NOT applicable in modes 4 AND 5. Performance AND printouts are NOT required.
4.3.14.1 Perform 8 and 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months tours for 34SV-SUV-019-1, in accordance with Attachment 5.
4.3.14.2 Complete Condition 5 Surveillance Checks sheet as required by plant conditions.
4.3.14.3 Complete Operating Orders sheet, as required by plant conditions.
4.3.14.4 Complete Safety Parameter Display System Status Checks sheets.
4.3.14.5 Complete Attachment 3, Computerized Surveillance Documentation.
4.3.15 IF more than one Operator collects data for a tour using the computer, one of the following actions will be taken:
4.3.15.1 Each Operator will log into the computer and will enter the data collected, OR 4.3.15.2 Information will be placed in the Notes section that identifies the other operator who collected the data. The note will include name and area of data, if applicable.
(i.e., Cooling tower data taken by Terry Doe).
G16.030 MGR-0001 Ver. 4
(
(
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
SURVEILLANCE CHECKS DOCUMENT NUMBER:
34SV-SUV-019-1 PAGE 12 OF 73 VERSION NO:
33.33 4.3.11
!E an Operator fails to complete any signoff/initial spaces, an SS OR SOS may sign off/initial the space.
4.3.12 Night shift begins at 1900 EASTERN Time, i.e., where a reading is specified for Saturday night shift, it will be taken from 1900 EASTERN Time Friday to 0700 EASTERN Time Saturday.
4.3.13
!E using the paper copy of this procedure, Attachment 3 is NOT required.
NOTE:
!E a word such as "INOP" is entered into a station in place of a value, any calculation performed with that station will substitute a numeric value of zero for the word. IF the calculation is a channel check, appropriate action must be taken for the inoperable instrument AND to ensure adequate channel check of remaining operable instruments.
4.3.14
!E the procedure is to be performed using the computerized rounds software, the procedure beginning with 7.1 may be completed by completing the following:
NOTE:
8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months tour is NOT applicable in modes 4 AND 5. Performance AND printouts are NOT required.
4.3.14.1 Perform 8 and 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months tours for 34SV-SUV-019-1, in accordance with Attachment 5.
4.3.14.2 Complete Condition 5 Surveillance Checks sheet as required by plant conditions.
4.3.14.3 Complete Operating Orders sheet, as required by plant conditions.
4.3.14.4 Complete Safety Parameter Display System Status Checks sheets.
4.3.14.5 Complete Attachment 3, Computerized Surveillance Documentation.
4.3.15 IF more than one Operator collects data for a tour using the computer, one of the following actions will be taken:
4.3.15.1 Each Operator will log into the computer and will enter the data collected, OR 4.3.15.2 Information will be placed in the Notes section that identifies the other operator who collected the data. The note will include name and area of data, if applicable.
(i.e., Cooling tower data taken by Terry Doe).
G16.030 MGR-0001 Ver. 4
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
SURVEILLANCE CHECKS 4.3.16 The paper copy of the procedure will be used:
DOCUMENT NUMBER:
34SV-SUV-019-1 IF the computer will NOT perform required calculations.
PAGE 13 OF 73 VERSION NO:
33.33 IF the output from the computer is obviously incorrect AND represents a serious degradation of the computer system operation.
IF the version number specified in the computerized round for the procedure is incorrect AND the Software Support Personnel can NOT resolve the problem.
AutoTour will NOT display all required outstanding surveillances for a Unit Mode change, therefore a paper copy of this procedure MUST be performed. (e.g., IF Unit is in Mode 4 AND NOTE:
Mode 2 is inputted into AutoTour, at that time the Mode 2 surveillances will be displayed on AutoTour but some Mode 4 surveillances will NOT be displayed. In addition, surveillances that shift, day of the week OR month will NOT be displayed.
IF a pre-planned Mode change for the Unit will take place during the shift that may require performance of outstanding surveillances.
4.3.17 IF the HHC fails in some manner, every effort is to be made to perform the surveillance using the paper copy. However,!E full completion of the surveillance is impossible, a CR is to be written documenting the incomplete performance of the surveillance. Notify Operations Support for assistance with trouble shooting.
4.3.18
!E the version number specified in the computerized round for the procedure is incorrect,
!E possible, contact the Software Support Personnel for assistance.
4.3.19 Any abnormal condition identified will be marked (Le., red circled) and documented/explained in the notes section of the computer.
5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS None applicable to this procedure.
5.2 LIMITATIONS IF items being compared to each other fail to meet the limits of a comparison check, AND it is NOT readily discernible which item has an operability concern, THEN a CR must be initiated to investigate the condition in order to assist in making the operability determination.
6.0 PREREQUISITES None applicable to this procedure.
G16.030 MGR-0001 Ver. 4
(
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
SURVEILLANCE CHECKS 4.3.16 The paper copy of the procedure will be used:
DOCUMENT NUMBER:
34SV-SUV-019-1 IF the computer will NOT perform required calculations.
PAGE 13 OF 73 VERSION NO:
33.33 IF the output from the computer is obviously incorrect AND represents a serious degradation of the computer system operation.
IF the version number specified in the computerized round for the procedure is incorrect AND the Software Support Personnel can NOT resolve the problem.
AutoTour will NOT display all required outstanding surveillances for a Unit Mode change, therefore a paper copy of this procedure MUST be performed. (e.g., IF Unit is in Mode 4 AND NOTE:
Mode 2 is inputted into AutoTour, at that time the Mode 2 surveillances will be displayed on AutoTour but some Mode 4 surveillances will NOT be displayed. In addition, surveillances that shift, day of the week OR month will NOT be displayed.
IF a pre-planned Mode change for the Unit will take place during the shift that may require performance of outstanding surveillances.
4.3.17 IF the HHC fails in some manner, every effort is to be made to perform the surveillance using the paper copy. However, IE full completion of the surveillance is impossible, a CR is to be written documenting the incomplete performance of the surveillance. Notify Operations Support for assistance with trouble shooting.
4.3.18 IE the version number specified in the computerized round for the procedure is incorrect, IE possible, contact the Software Support Personnel for assistance.
4.3.19 Any abnormal condition identified will be marked (Le., red circled) and documented/explained in the notes section of the computer.
5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS None applicable to this procedure.
5.2 LIMITATIONS IF items being compared to each other fail to meet the limits of a comparison check, AND it is NOT readily discernible which item has an operability concern, THEN a CR must be initiated to investigate the condition in order to assist in making the operability determination.
6.0 PREREQUISITES None applicable to this procedure.
G16.030 MGR-0001 Ver. 4
7.25 CONTD.
7.25.2 ATTACHMENT 1 (Ul)
(Excerpt from 34SV-SUV-019-1)
PANEL -lNSTRUMENT I TECH SPEC.
NOTE REAC TIS -OPER MODE LIMIT lH11-P613: - IGll-K601, Floor Drain Leakage Actual Time (9)
F.1 Present Reading (10)
F.1 Yesterday's Reading Time (11)
F.1 Yesterday's Reading (12)
F.1 Difference (10) - (12)
(13)
F.1 Difference Conversion (13) X 10 (14)
F.1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes (15)
F.1 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (14) / (15)
(16)
FF,F.2,
~5gpm F3 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading (17)
F.1 1,2,3 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading time (18)
F.1 8 Hour difference (10) - (17)
(19)
F.1 Difference conversion (19) X 10 (20)
F.1 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months elapsed minutes (21)
F.l 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage (20) / (21)
(22)
FF,F.2,
~5gpm F3 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage from previous (23) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Total Leakage (8) + (16)
(24)
~30 gpm Differential Floor Drain (25)
FF Leakage (22)-(23)
~2 gpmin (SR 3.4.4.1)
Model Initials Time ARB CalculatIOns Verified 0000 0800 1600 0000 0800 1600 0000 3752.9 0000 0800 1600 3723.9 3732.9 3744.1 29.0 290 1440
.20 3744.1 3752.9 1600 0000 8.8 88 480
.18
.16
.16
.18 1.55
.02 CME DATE
(
(
7.25 CONTD.
7.25.2 ATTACHMENT I (VI)
(Excerpt from 34SV-SVV-OI9-1)
PANEL - INSTRUMENT I TECH SPEC.
NOTE REAC TIS - OPER MODE LIMIT lH11-P613: - 1Gl1-K601, Floor Drain Leakage Actual Time (9)
F.1 Present Reading (10)
F.1 Yesterday's Reading Time (11)
F.1 Yesterday's Reading (12)
F.1 Difference (10) - (12)
(13)
F.1 Difference Conversion (13) X 10 (14)
F.1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes (15)
F.1 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (14) I (15)
(16)
FF,F.2,
.:::5 gpm F3 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading (17)
F.1 1,2,3 Previous 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months reading time (18)
F.1 8 Hour difference (10) - (17)
(19)
F.1 Difference conversion (19) X 10 (20)
F.1 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months elapsed minutes (21)
F.l 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage (20) I (21)
(22)
FF,F.2,
.:::5 gpm F3 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months leakage from previous (23) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Total Leakage (8) + (16)
(24)
.:::30 gpm Differential Floor Drain (25)
FF Leakage (22)-(23)
,:::2 gpmin (SR 3.4.4.1)
Mode 1 Initials Time ARB CalculatlOns Venfied 0000 0800 1600 0000 0800 1600 0000 3752.9 0000 0800 1600 3723.9 3732.9 3744.1 29.0 290 1440
.20 3744.1 3752.9 1600 0000 8.8 88 480
.18
.16
.16
.18 1.55
.02 CME DATE
(
7.25 7.25.1 ATTACHMENT 1 (VI)
(Excerpt from 34SV -SUV -019-1)
PANEL - INSTRUMENT I TECH SPEC.
NOTE REAC MODE TIS -OPER LIMIT IHII-P613: - IG11-K603, Equipment Drain Leakage Actual Time (1)
F.l Present Reading (2)
F.l Yesterday's Reading Time (3)
F.l Yesterday's Reading (4)
F.l 1,2,3 Difference (2) - (4)
(5)
F.l Difference Conversion (5) x 10 (6)
F.l 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes (7)
F.l 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (6)/(7)
(8)
F.2 Initials Time Calculations Verified ARB DRK 0000 0800 1600 0000 0800 1600 0000 0800 3956.3 3965.9 0000 0800 3923.3 3937.1 33.0 28.8 330 288 1440 1440
.23
.20 CME DRK 0003 0800 DATE
(
7.25 7.25.1 ATTACHMENT I (UI)
(Excerpt from 34SV-SUV-OI9-1)
REAC TIS - OPER PANEL - INSTRUMENT I TECH SPEC.
NOTE MODE LIMIT IHll-P613: - IGll-K603, Equipment Drain Leakage Actual Time (1)
F.l Present Reading (2)
F.l Yesterday's Reading Time (3)
F.l Yesterday's Reading (4)
F.l 1,2,3 Difference (2) - (4)
(5)
F.l Difference Conversion (5) x 10 (6)
F.l 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months elapsed minutes (7)
F.l 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage (6)/(7)
(8)
F.2 Initials Time Calculations Verified ARB DRK 0000 0800 1600 0000 0800 1600 0000 0800 3956.3 3965.9 0000 0800 3923.3 3937.1 33.0 28.8 330 288 1440 1440
.23
.20 CME DRK 0003 0800 DATE
ATTACHMENT 2 DRYWELLLEAKAGEINTEGRATORS IGII-K601, Floor Drain Leakage IGII-K603, Equipment Drain Leakage
(
ATTACHMENT 2 DRYWELLLEAKAGEINTEGRATORS IGII-K601, Floor Drain Leakage IGII-K603, Equipment Drain Leakage
(
N/R FINAL Southern E. I. Hatch uclear uclear Plant Operations Training JPM Admin 4 - SRO Only C. M.EDMUND 1011412009 Energy to Serve Your World SM TITLE
(
FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 4 - SRO Only 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:
OPERA TIONS TRAINING Media Number: 2009-302 Admin 4
"/
I.....;>'
~~Rev~N().~~
~~. Date~~
.**.. ****.*.. ***;:~;.:;~{):;);;>:"'!;>~:'>
.' -." (::;.;; ;;
I; I Dosimetry
~~If.~;~~
I. DIGITAL ALARMING DOSIMETER (DAD)
I! WHOLE BODY TLD
~ !
~;£}*1;'::8'~ f
,:,~'.' ':i.'
~'I "
Protective Clodling Requiremen1s I; ~:~;~ TO ~?RI(~~SPECIAL INSTRUCTIONS I !
~-{f:l;?["i ;;;i;;.,i;!"y,*:*-*
III Respirators I*
I;~-----------------'
Ii RESP II i Usage is Conditional per HP OPS Rounds, Clearances, Surveil.
25
- OPS Control Room Activities 10 Supervision / Observation 20
~r**-. '.. _
.*..._ '" -Instructions -" -.
I
~ IDAD's must be accessible for visual monitoring. Monitor DAD periodically while in the RCA.'
~ Lab Coats, Booties & Gloves allowed for training, inspections, surveillances, Step Off Pad maintenance or Light Work (with HP I approval)
Ilunless otherwise specified by HP, full dress is required for contaminated area entry.
iluse Cameras in lieu of entry, when possible, to reduce exposure.
I~~~*'**
~~[f; I Briefing required prior to entering a High Radiation Area I Prepared~~
(:.
Health Physics Staff Approved 12126/2008 08:25 by DPHOBBS Sl)spended Terminated 500 50 100
->}I
(
Radiation Work Permit Plant Hatch 09-0004 ACTIVE Page 4 of 4 Unit Rev o
Job Operations Inspection, Surveillance and Fire Watch - This RWP not for entries into Locked High Rad or Very High Rad
.. Description Areas I Location I GENERAL PLANT LOCATION Cc c:
HPCoverage Authorization Briefing INTERMITIENT WORK GROUP CONDITIONAL c
c cL...I _____
R_a_di_*_ol_O_gI_* c_a_I_C_o_n_d_i_ti_o_n_s ____ --'
Refer to current survey of work area.
Dosimetry DIGITAL ALARMING DOSIMETER (DAD)
WHOLE BODY TLD Start Date 11112009 Job Supv. SOS Tasks Description OPS Rounds, Clearances, Surveil.
OPS Control Room Activities Supervision / Observation JPMs /Training Activities End Date 11112010 Ext. 5959 DAD Alarms Dose (mr) 25 10 20 10 Rate (mr/h) 500 50 100 100 (L...I ___
Pr_o_t_ec_t_iv_e_C_lo_t_h_in_g_R_e_q_u_ir_e_m_e_n_ts ____ ~
(
REFER TO WORKER/SPECIAL INSTRUCTIONS Respirators Cc RESP Usage is Conditional per HP c I Instructions c IDAD's must be accessible for visual monitoring. Monitor DAD periodically while in the RCA.
Lab Coats, Booties & Gloves allowed for training, inspections, surveillances, Step Off Pad maintenance or Light Work (with HP approval)
IUnless otherwise specified by HP, full dress is required for contaminated area entry.
Iuse 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 Prepared Health Physics Staff Approved 1212612008 08 :25 by DPHOBBS Suspended Terminated
UNIT 2 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:
1 Unit 2 is at 100% power with no significant problems.
2.
~~34SV-Ell-001-2, Residual Heat Removal Pump Operability, is to be performed this shift on "B" Loop RHR pumps.~~
3.
~~The current OPS RWP is 09-0004.~~
4.
The RWP and HP Survey Maps are available.
INITIATING CUES:
You are assigned to locally perform the pre-start checks for 34SV -EI1-001-2, Residual Heat Removal Pump Operability, "B" loop RHR and are to:
Determine the correct survey map for "B" loop RHR.
Calculate the maximum stay time before the DAD alarms on dose accumulated, assuming you:
o remain near the RHR pumps and o are at the highest current General Area Dose Rate State your required actions if the DAD alarms on dose accumulated.
Page 2 of4
(
UNIT 2 READ AND GIVE A COpy TO THE OPERATOR INITIAL CONDITIONS:
1 Unit 2 is at 100% power with no significant problems.
2.
~~34SV-Ell-00l-2, Residual Heat Removal Pump Operability, is to be performed this shift on "B" Loop RHR pumps.~~
3.
~~The current OPS RWP is 09-0004.~~
4.
The RWP and HP Survey Maps are available.
INITIATING CUES:
You are assigned to locally perform the pre-start checks for 34SV-Ell-001-2, Residual Heat Removal Pump Operability, "B" loop RHR and are to:
Determine the correct survey map for "B" loop RHR.
Calculate the maximum stay time before the DAD alarms on dose accumulated, assuming you:
o remain near the RHR pumps and o
are at the highest current General Area Dose Rate State your required actions if the DAD alarms on dose accumulated.
Page 2 of 4
(
Radiation Work Permit Plant Hatch 09-0004 ACTIVE Page 4 of 4 Unit Rev o
Job Operations Inspection, Surveillance and Fire Watch - This RWP not for entries into Locked High Rad or Very High Rad Description Areas I. Location I GENERAL PLANT LOCATION HPCoverage Authorization Briefing INTERMITTENT WORK GROUP CONDITIONAL Radiological Conditions Dosimetry DIGITAL ALARMING DOSIMETER (DAD)
RESP Usage is Conditional per HP Start Date 11112009 Job Supv. SOS Tasks Description OPS Rounds, Clearances, Surveil.
OPS Control Room Activities Supervision / Observation I
Instructions IDAD's must be accessible for visual monitoring. Monitor DAD periodically while in the RCA.
End Date 11112010 Ext. 5959 DAD Alanns Dose(mr) 25 10 20 Rate (mrlh) 500 50 100
~~Lab Coats, Booties & Gloves allowed for training, inspections, surveillances, Step Off Pad maintenance or Light Work (with HP~~
. approval)
IUnless otherwise specified by HP, full dress is required for contaminated area entry.
Iuse 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 Health Physics Staff Approved 12126/2008 08:25 by DPHOBBS Suspended Terminated I
I I.****
1\\
I Radiation Work Permit Plant Hatch 09-0004 ACTIVE Page 4 of 4 Unit Rev o
Job Operations Inspection, Surveillance and Fire Watch - This RWP not for entries into Locked High Rad or Very High Rad Description Areas Location I GENERAL PLANT LOCATION HP Coverage Authorization Briefing INTERMITTENT WORK GROUP CONDITIONAL Radiological Conditions Refer to current survey of work area.
Dosimetry DIGITAL ALARMING DOSIMETER (DAD)
WHOLE BODY TLD Start Date 11112009 Job Supv. SOS Tasks Description OPS Rounds, Clearances, Surveil.
OPS Control Room Activities Supervision / Observation JPMs /Training Activities End Date 11112010 Ext. 5959 DAD Alarms Dose <rnr) 25 10 20 10 Rate (rnr/h) 500 50 100 100
( I Protective Clothing Requirements i
\\
REFER TO WORKER/SPECIAL INSTRUCTIONS Respirators RESP Usage is Conditional per HP
~I======================================I=n=st=r=u=c=ti=o=n=s====================================~I IDAD's must be accessible for visual monitoring. Monitor DAD periodically while in the RCA.
I Lab Coats, Booties & Gloves allowed for training, inspections, surveillances, Step Off Pad maintenance or Light Work (with HP approval)
IUnless otherwise specified by HP, full dress is required for contaminated area entry.
Use 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 Prepared Health Physics Staff Approved 12/26/2008 08:25 by DPHOBBS Suspended Terminated
(
Plant Hatch Radiologieallnformation Survey # 5777310/2512009 16:45 U2 N.E. Diag. 87 (2RX87NE Diag)
Status:
Performed By:
Max Dose Rate:
MaxCntm:
Approved By:
~~Purpose:~~
Remarks:
Component:
Approved Hendrix, David Griffis, Don 6 mrem/hr
<MDA dpml100 cm2 Griffis, Don Routine Survey Di Rad 03-1087N o
ASR#s Instrument Description 2368 RO-2A 725 RM-25 Postlngs:
1# Type 1 1 Low Dose 2 Caution - Rad Sign I
N UNIT 2 N"E. DIAGONAL -87' Rx Reactor Power:
Reactor Mode:
H2 Injection Level:
Void Level:
System Running:
10/2512009 16:45 Survey Dose:
RWP#S 09-0001 Comment Description Dosimetry Required for Entry Radiation Area Page 1 100%
1 10 0
No 0
(
Plant Hatch Radiological Information Survey # 5777310/2512009 16:45 U2 N.E. Diag. 87 (2RX87NE Diag)
Status:
Performed By:
Max Dose Rate:
MaxCntm:
Approved By:
~~Purpose:~~
Remarks:
Component:
Approved Hendrix, David Griffis, Don 6 mrem/hr
<MDA dpm/100 cm2 Griffis, Don Routine Survey Di Rad 03-1087N o
ASR#s Instrument Description 2368 RO-2A 725 RM-25 Postings:
I # Type I 1 Low Dose 2 Caution - Rad Sign UNIT 2 N~E. DIAGONAL - 87' Rx Reactor Power:
Reactor Mode:
H2 Injection Level:
Void Level:
System Running:
1 012512009 16 :45 Survey Dose:
RWP#s 09-0001 Comment Description Dosimetry Required for Entry Radiation Area Page 1 100%
1 10 0
No 0
Plant Hatch Radiological Information Survey # 57773 1012512009 16:45 Page 2 Radiation Controlled Area RWP required for entry Point Data:
~~Point Type~~
~alue Units Level Comments 1
91 Dose Rate - Gamma G/A 3
mrem/hr Low Dose Rate - Gamma Contact 5
mrem/hr Low-Low 2
92 Dose Rate - Gamma G/A 5
mrem/hr Low Dose Rate - Gamma Contact 8
mrem/hr Low-Low 3
Flex Dose Rate - Gamma G/A
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpmf100 cm2 Low-Low 4
Flex Dose Rate -Gamma GfA 6
mrem/hr Low Flex Dose Rate - Gamma Contact 10 mremfhr Low-Low Flex Contamination - BIG
<1000 dpml100 cm2 Low-Low 5
Flex Dose Rate - Gamma G/A
~
mrem/hr Low Flex Dose Rate - Gamma Contact 5
mrem/hr Low-Low 6
Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 7
Flex Dose Rate - Gamma G/A
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 8
Flex Dose Rate - Gamma G/A
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpml100 cm2 Low-Low 9
Flex Dose Rate - Gamma G/A 3
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low
(
10 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 11 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 12 Flex Dose Rate - Gamma GfA 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 13 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpmf100 cm2 Low-Low 14 Flex Dose Rate - Gamma GfA
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpmf100 cm2 Low-Low 15 Flex Dose Rate - Gamma G/A
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 16 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 17 Flex Dose Rate - Gamma G/A 5
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 18 Flex Dose Rate - Gamma G/A 3
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 19 Flex Dose Rate - Gamma G/A
~
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 20 Flex Dose Rate - Gamma G/A 3
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 21 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low Plant Hatch Radiological Information Survey # 57773 1012512009 16:45 Page2 Radiation Controlled Area RWP required for entry Point Data:
~~Point !Type Value Units Level Comments 1~~
91 Dose Rate - Gamma G/A 3
mrem/hr Low Dose Rate - Gamma Contact 5
mrem/hr Low-Low 2
92 Dose Rate - Gamma G/A 5
mrem/hr Low Dose Rate - Gamma Contact 8
mrem/hr Low-Low 3
Flex Dose Rate - Gamma G/A
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 4
Flex Dose Rate -Gamma G/A 6
mrem/hr Low Flex Dose Rate - Gamma Contact 10 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 5
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Dose Rate - Gamma Contact 5
mremlhr Low-Low 6
Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 7
Flex Dose Rate - Gamma G/A
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 8
Flex Dose Rate - Gamma G/A
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 9
Flex Dose Rate - Gamma G/A 3
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low
(
10 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 11 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 12 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 13 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 14 Flex Dose Rate - Gamma G/A
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 15 Flex Dose Rate - Gamma G/A
<2 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 16 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 17 Flex Dose Rate - Gamma G/A 5
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 18 Flex Dose Rate - Gamma G/A 3
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 19 Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 20 Flex Dose Rate - Gamma G/A 3
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 21 Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low
J, Plant Hatch Radiological Information Survey # 577691012512009 16,:45
(
U2 S.E. Diag. 87 (2RX87SE Diag)
(
UNIT 2 S.E.. DIAGONAL
~~87' Status:~~
Performed By:
Max Dose Rate:
MaxCntm:
Approve,d By;
~~Purpose:~~
Remarks:
Component:
Approved Griffis, Don Aycock, Brett 20 mremlhr 232 dpml100 cm2 Griffis. Don Routine Survey Di Ras 03-1087N ASR#S Instrument Description 3487 RO-2A 42123-1 TENNELEC 1 Caution* Rad Sign 1012512009 16:45 RWP#S Cl9-0001 Page 1 Rx Reactor Power:
100%
Reactor Mode~
1 H21njection Level:
10 Void Level:
0 System Running:
No Survey Dose:
1 Comment
(
Plant Hatch Radiological Information Survey # 577691012512009 16:45 U2 S.E. Diag. 87 (2RX87SE Diag)
UNIT 2 S.E. DIAGONAL - 87' Status:
Performed By:
Max Dose Rate:
MaxCntm:
Approved By:
~~Purpose:~~
Remarks:
Component:
Approved Griffis, Don Aycock, Brett 20 mremfhr 232 dpmf1 00 cm2 Griffis, Don Routine Survey Di Ras 03-1087N ASR#s Instrument Description 3487 RO-2A 42123-1 TENNELEC 1 Caution - Rad Sign 1012512009 16:45 RWP#S 09-0001 Description Radiation Area Page 1 Rx Reactor Power:
100%
Reactor Mode:
1 H2 Injection Level:
10 Void Level:
0 System Running:
No Survey Dose:
1 Comment
Plant Hatch Radiological Information Survey # 57769 10/25/2009 16:45
'oint Data:
~~Point Irype~~
!Value Units 1
103 Dose Rate - Gamma G/A
~
mrem/hr Dose Rate - Gamma Contact 10 mrem/hr Contamination - Alpha
<20 dpm/100 cm2 Contamination - BIG
<MDA dpm/100 cm2 2
104 Dose Rate - Gamma G/A 20 mrem/hr Dose Rate - Gamma Contact 50 mremlhr Contamination - Alpha
<20 dpml100 cm2 Contamination - BIG
<MDA dpm/100 cm2 3
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 4
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 5
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 6
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 7
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 8
Flex Dose Rate - Gamma G/A 10 mrem/hr Flex Dose Rate - Gamma Contact 20 mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG 232 dpm/100 cm2 9
Flex Dose Rate - Gamma G/A 12 mrem/hr Flex Dose Rate - Gamma Contact 20 mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 Page 2 Level Comments Low Low-Low Low-Low Low-Low Low
,"""ow Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low
~ow-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low Low-Low Low-Low Low-Low Low Low-Low Low-Low Low-Low
(
Plant Hatch Radiological Information Survey # 57769 10/25/2009 16:45
'oint Data"
~~Point Type Value Units 1~~
103 Dose Rate - Gamma G/A 5
mrem/hr Dose Rate - Gamma Contact 10 mrem/hr Contamination - Alpha
<20 dpm/100 cm2 Contamination - BIG
<MDA dpm/100 cm2 2
104 Dose Rate - Gamma G/A 20 mrem/hr Dose Rate - Gamma Contact 50 mrernfhr Contamination - Alpha
<20 dpm/100 cm2 Contamination - BIG
<MDA dpm/100 cm2 3
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 4
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 5
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 6
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 7
Flex Dose Rate - Gamma Contact 2
mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 8
Flex Dose Rate - Gamma G/A 10 mrem/hr Flex Dose Rate - Gamma Contact 20 mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG 232 dpm/100 cm2 9
Flex Dose Rate - Gamma G/A 12 mrem/hr Flex Dose Rate - Gamma Contact 20 mrem/hr Flex Contamination - Alpha
<20 dpm/100 cm2 Flex Contamination - BIG
<MDA dpm/100 cm2 Page 2 Level Comments Low Low-Low Low-Low Low-Low Low
,-ow Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low-Low Low Low-Low Low-Low Low-Low Low Low-Low Low-Low Low-Low
(
(
c.
Plant Hatch Radiologicallnfonnation Survey '# 5~730 10/25/2009 16:45 U1 S.. E Diag. 87 (1RX87SE Diag)
.'f't....
UNIT *1S.E~ DIAGONAL-.8.7' Status:
Performed By:
Max Dose Rate:
MaxCntm:
Approved By:
~~Purpose:~~
Remarks:
Component:
Approved Marionneaux, Mark Hutto, Lauren 24 mremlhr 203 dpm/100 cm2 Marionneaux,.Mark Routine Survey DI-RAD nla ASR#s Instrument Description 2368 RO-2A 42123"1 trENNELEC Postings:
# trype 1 paution - RadSign 2 Gaution - Rad Sign 3 Caution - Rad Sign 101251200916:45 RWP#s 09-0001 Description Radiation Area Contaminated Area Contaminated Area Page 1 Rx Reactor Power:
40%
Reactor Mode:
1 A21njection Level:
10 Void Level:
0 System Running:
No Survey Dose:
2
!comment
(
(
Plant Hatch Radiological Information Survey # 5973010/25/2009 16:45 U1 S.E. Diag. 87 (1RX81SE Diag)
~1 IEllFU71 lEllFU6Si RCA Pnstings.: lY.j5 lE21F060 UNIT 1 S.E. DIAGONAL - 87 1
Status:
Performed By:
Max Dose Rate:
MaxCntm:
Approved By:
~~Purpose:~~
Remarks:
Component:
Approved Marionneaux, Mark Hutto, Lauren 24 mremfhr 203 dpmf100 cm2 Marionneaux, Mark Routine Survey DI-RAD nfa ASR#s Instrument Description 2368 RO-2A 42123-1 iTENNELEC Postlngs:
~~rtype 1 Caution - Rad Sign 2 lCaution - Rad Sign 3 !caution - Rad Sign 1012512009 16:45 RWP#s 09-0001 Description Radiation Area Contaminated Area Contaminated Area Page 1 Rx Reactor Power:~~
40%
Reactor Mode:
1 H21njection Level:
10 Void Level:
0 System Running:
No Survey Dose:
2 Comment
Plant Hatch Radiological Information Survey # 59730 10/2512009 16:45 Page 2 14 ICaution - Rad Sign Contaminated Area I 5 ICaution - Rad Sign Dosimetry Required for Entry Radioactive Material 1
Radiation Controlled Area 1
RWP required for entry Point Data:
~~Point Type Value Units Level Comments 1~~
84 Dose Rate - Gamma G/A 24 mrem/hr Low Dose Rate - Gamma Contact 40 mrem/hr Low-Low Contamination - BIG
<1000 dpm/100 cm2 Low-Low 2
Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 3
Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 4
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG
<1000 dpml100 cm2 Low-Low 5
Flex Dose Rate - Gamma G/A 6
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 6
Flex Dose Rate - Gamma G/A 6
mrem/hr Low Flex Contamination - BIG 203 dpm/100 cm2 Low-Low 7
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 8
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG 101 dpm/100 cm2 Low-Low 9
Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 10 Flex Dose Rate - Gamma G/A 6
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 11 Flex Dose Rate - Gamma G/A 15 mrem/hr Low Flex Dose Rate - Gamma Contact 20 mrem/hr Low-Low Flex Contamination - BIG.
<1000 dpml100 cm2 Low-Low 12 Flex Dose Rate - Gamma G/A 12 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 13 Flex Dose Rate - Gamma G/A 20 mrem/hr Low Flex Dose Rate - Gamma Contact 40 mrem/hr Low-Low 14 Flex Dose Rate - Gamma G/A 20 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 15 Flex Dose Rate - Gamma G/A 22 mrem/hr Low Flex Dose Rate - Gamma Contact 32 mrem/hr Low-Low Flex Contamination - BIG
<MDA dpm/100 cm2 Low-Low 16 Flex Dose Rate - Gamma G/A 22 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 17 Flex Dose Rate - Gamma G/A 6
mrem/hr Low Flex Contamination - BIG
<1000 dpml100 cm2 Low-Low 18 Flex Dose Rate - Gamma G/A 16 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 19 Flex Dose Rate - Gamma G/A 10 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 20 Flex Dose Rate - Gamma G/A 10 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low Plant Hatch Radiological Information Survey # 59730 10/2512009 16:45 Page 2 I 4 Caution - Rad Sign Contaminated Area I 5 Caution - Rad Sign Dosimetry Required for Entry
(
Radioactive Material I
Radiation Controlled Area I
RWP required for entry Point Data:
Point Type Value Units Level Comments 1
84 Dose Rate - Gamma G/A 24 mrem/hr Low Dose Rate - Gamma Contact 40 mrem/hr Low-Low Contamination - BIG
<1000 dpm/100 cm2 Low-Low 2
Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 3
Flex Dose Rate - Gamma G/A 2
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 4
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 5
Flex Dose Rate - Gamma G/A 6
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 6
Flex Dose Rate - Gamma G/A 6
mrem/hr Low Flex Contamination - BIG 203 dpm/100 cm2 Low-Low 7
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG
<1000 dpml100 cm2 Low-Low 8
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG 101 dpm/100 cm2 Low-Low 9
Flex Dose Rate - Gamma G/A 2
mrem/hr Low
(
Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 10 Flex Dose Rate - Gamma G/A 6
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 11 Flex Dose Rate - Gamma G/A 15 mrem/hr Low Flex Dose Rate - Gamma Contact 20 mrem/hr Low-Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 12 Flex Dose Rate - Gamma G/A 12 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 13 Flex Dose Rate - Gamma G/A 20 mrem/hr Low Flex Dose Rate - Gamma Contact 40 mrem/hr Low-Low 14 Flex Dose Rate - Gamma G/A 20 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 15 Flex Dose Rate - Gamma G/A 22 mrem/hr Low Flex Dose Rate - Gamma Contact 32 mrem/hr Low-Low Flex Contamination - BIG
<MDA dpm/100 cm2 Low-Low 16 Flex Dose Rate - Gamma G/A 22 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 17 Flex Dose Rate - Gamma G/A 6
mrem/hr Low Flex Contamination - BIG
<1000 dpml100 cm2 Low-Low 18 Flex Dose Rate - Gamma G/A 16 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low
(
19 Flex Dose Rate - Gamma G/A 10 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 20 Flex Dose Rate - Gamma G/A 10 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low
(
Plant Hatch Radiological Information Survey # 59752 10/25/2009 16:45 U1 N.E. Diag. 87 (1RX87NE Oiag) 1E21 1E21 UNIT 1N.E. DIAGONAL -87' Status:
Performed By:
Max Dose Rate:
Max Cntm:
Approved By:
~~Purpose:~~
Remarks:
Component:
Approved Marionneaux, Mark Hutto, Lauren 34 mrem/hr Marionneaux, Mark Routine Survey DI-RAD-03 Survey na ASR#s Instrument Description 3487 RO-2A 42123-1 IrENNELEC Postings:
~~ITYpe 1 Caution - Rad Sign 2 lCaution - Rad Sign Rx Reactor Power:~~
Reactor Mode:
H21njection Level:
Void Level:
System Running:
1012512009 16:45 Survey Dose:
RWP#s 09-0001 Comment Description Radiation Area Room Posted Prior To This Entrance Dosimetry Required for Entry Page 1 58%
1 5
0 No 3
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t.
Plant Hatch Radiological Information Survey # 597521012512009 16:45 U1 N.E. Diag. 87 (1RX87NE Diag) 1E21 1E21 UNIT 1 N.E. DIAGONAL ~ 87' Status:
Performed By:
Max Dose Rate:
MaxCntm:
Approved By:
~~Purpose:~~
Remarks:
Component:
Approved Marionneaux, Mark Hutto, Lauren 34 mrem/hr Marionneaux, Mark Routine Survey DI-RAD-03 Survey na ASR#s Instrument Description 3487 RO-2A 42123-1 TENNELEC Postings:
~~Type 1 Caution - Rad Sign 2 Caution - Rad Sign Rx Reactor Power:~~
Reactor Mode:
H21njection Level:
Void Level:
System Running:
1 012512009 16 :45 Survey Dose:
RWP#s 09-0001 Comment Description RadiaUon Area Room Posted Prior To This Entrance Dosimetry Required for Entry Page 1 58%
1 5
0 No 3
Plant Hatch Radiological Information Survey # 59752 10/25/2009 16:45 Page2 I
Radioactive Material I
Radiation Controlled Area
(
Room Posted Prior To This Entrance I
RWP required for entry Point Data:
Point Type Value Units Level Comments 1
71 Dose Rate - Gamma G/A 18 mrem/hr Low Dose Rate - Gamma Contact 22 mrem/hr Low-Low 2
72 Dose Rate - Gamma G/A 34 mrem/hr Low Dose Rate - Gamma Contact 46 mrem/hr Low-Low Contamination - BIG
<1000 dpm/100 cm2 Low-Low 3
Flex Dose Rate - Gamma G/A 4
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 6
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 5
Flex Dose Rate - Gamma G/A 6
mrem/hr Low on brown drain pipes Flex Dose Rate - Gamma Contact 15 mrem/hr Low-Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG 92 dpm/100 cm2 Low-Low 6
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG
<MDA dpm/100 cm2 Low-Low 7
Flex Dose Rate - Gamma G/A 3
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 8
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 9
Flex Dose Rate - Gamma G/A 8
mrem/hr Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG 68 dpm/100 cm2 Low-Low 10 Flex Dose Rate - Gamma G/A 10 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 11 Flex Dose Rate - Gamma G/A 5
mrem/hr Low Flex Dose Rate - Gamma Contact 20 mrem/hr Low-Low Roor Drain Line in overhead 12 Flex Dose Rate - Gamma G/A 14 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 13 Flex Dose Rate - Gamma G/A 30 mrem/hr Low on big elbow Flex Dose Rate - Gamma Contact 50 mrem/hr 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 20 mrem/hr Low Flex Dose Rate - Gamma Contact 40 mrem/hr Low-Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG
<MDA dpm/100 cm2 Low-Low 15 Flex Dose Rate - Gamma G/A 25 mrem/hr Low Flex Dose Rate - Gamma Contact 40 mrem/hr Low-Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG 291 dpm/100 cm2 Low-Low 16 Flex Dose Rate - Gamma G/A 20 mrem/hr Low 17 Flex Dose Rate - Gamma G/A 12 mrem/hr Low 18 Flex Dose Rate - Gamma G/A 4
mrem/hr Low Plant Hatch Radiological Information Survey # 59752 10/25/2009 16:45 Page2 I
Radioactive Material I
Radiation Controlled Area
(
Room Posted Prior To This Entrance I
RWP required for entry Point Data:
Point Type Value Units Level Comments 1
71 Dose Rate - Gamma G/A 18 mrem/hr Low Dose Rate - Gamma Contact 22 mrem/hr Low-Low 2
72 Dose Rate - Gamma G/A 34 mrem/hr Low Dose Rate - Gamma Contact 46 mrem/hr Low-Low Contamination - BIG
<1000 dpm/100 cm2 Low-Low 3
Flex Dose Rate - Gamma G/A 4
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 6
mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 5
Flex Dose Rate - Gamma G/A 6
mrem/hr Low on brown drain pipes Flex Dose Rate - Gamma Contact 15 mrem/hr Low-Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG 92 dpm/100 cm2 Low-Low 6
Flex Dose Rate - Gamma G/A 4
mrem/hr Low Flex Contamination - BIG
<MDA dpm/100 cm2 Low-Low 7
Flex Dose Rate - Gamma G/A 3
mrem/hr Low
(
Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 8
Flex Dose Rate - Gamma G/A 4
mremfhr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 9
Flex Dose Rate - Gamma G/A 8
mremfhr Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG 68 dpm/100 cm2 Low-Low 10 Flex Dose Rate - Gamma G/A 10 mrem/hr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 11 Flex Dose Rate - Gamma G/A 5
mrem/hr Low Flex Dose Rate - Gamma Contact 20 mrem/hr Low-Low Roar Drain Line in overhead 12 Flex Dose Rate - Gamma G/A 14 mremfhr Low Flex Contamination - BIG
<1000 dpm/100 cm2 Low-Low 13 Flex Dose Rate - Gamma G/A 30 mrem/hr Low on big elbow Flex Dose Rate - Gamma Contact 50 mrem/hr Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG
<MDA dpmf100 cm2 Low-Low 14 Flex Dose Rate - Gamma G/A 20 mrem/hr Low Flex Dose Rate - Gamma Contact 40 mremfhr Low-Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG
<MDA dpm/100 cm2 Low-Low 15 Flex Dose Rate - Gamma G/A 25 mrem/hr Low Flex Dose Rate - Gamma Contact 40 mremfhr Low-Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG 291 dpm/100 cm2 Low-Low 16 Flex Dose Rate - Gamma G/A 20 mremfhr Low 17 Flex Dose Rate - Gamma G/A 12 mremfhr Low 18 Flex Dose Rate - Gamma G/A 4
mrem/hr Low
Plant Hatch Radiological Information Survey # 59752 10/25/2009 16:45 Page 3 Flex Contamination - Alpha
<20 dpm/100cm2 Low-Low
(
Flex Contamination - BIG
<MDA dpm/100 cm2 Low-Low 19 Flex Dose Rate - Gamma G/A 10 mrem/hr Low Flex Dose Rate - Gamma Contact 20 mrem/hr Low-Low Flex Contamination - Alpha
<20 ppm/100 cm2 Low-Low Flex Contamination - BIG
<MDA mrem/hr/100 cm2 Low-Low 20 Flex Dose Rate - Gamma G/A 30 mremlhr Low Flex Dose Rate - Gamma Contact 50 mremlhr Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG
<MDA dpm/100 cm2 Low-Low
(
Plant Hatch Radiological Information Survey # 59752 10/25/2009 16:45 Page 3 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 10 mrem/hr Low Flex Dose Rate - Gamma Contact 20 mrem/hr Low-Low Flex Contamination - Alpha
<20 dpmf100 cm2 Low-Low Flex Contamination - BIG
<MDA mrem/hrl1 00 cm2 Low-Low 20 Flex Dose Rate - Gamma G/A 30 mrem/hr Low Flex Dose Rate - Gamma Contact 50 mremfhr Low Flex Contamination - Alpha
<20 dpm/100 cm2 Low-Low Flex Contamination - BIG
<MDA dpm/100 cm2 Low-Low
(
(
N/R FINAL Southern Nuclear E. I. Hatch uclear Plant Operations Training JPM Admin 6 - RO Only C.M.EDMUND 1011412009 Energy to Serve Your World SM
(
TITLE FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 6 - RO Only DURING AN EMERGENCY, PERFORM A PROMPT OFFSITE DOSE ASSESSMENT CALCULATION AUTHOR MEDIA NUMBER TIME EN.FAGAN 2009-302 Admin 6 30.0 Minutes RECOMMENDED BY APPROVED BY DATE N/R C.M.EDMUND 10/14/2009 Energy to Serve Your World sM
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number: 2009*302 Admin 6 l{ev.~~.< 1>J)ate 00 05/02/94 01 09/06/96 02 09/12/96 03 10/03/97 04 09/16/98 05 01121/99 06 03/21100 07 11106/00 08 03/25/02 09 3/22/05 10 8/04/05 10/14/09 I'
....*............*......*.**..**.** ******rij}-'-*,fll~ ll~~!d";n<' *******<<;\\tJ.tltor'sS~pv'Si I
...........><...,-}
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Initial development Format change, convert to use SPDS information Editorial, correct MIDAS result numbers for peak TEDE and site boundaries Revised based on 1997 annual exam comments.
Revised due to procedurelMIDAS program revision.
Revised per feedback from EP.
Format modification, change time allowance based on running average, change MIDAS for due to revision Include objective number Include initial operator statement Changed RO to NPO, added statement ensuring the procedure is the current version, changed SOS to SM, addressed the use of TRN-052 and TRN-0146 flowchart and deleted the "S" from the procedure numbers. Modified steps and results to incorporate the use of the new MIDAS Windows based software.
Corrected "Alarms lllurninated" information to match plant conditions given in attachments.
Revised Initial License statement for successful completion.
Revised to use on 2009-302 Exam RAB DHG RAB DHG RAB RSG SCB DHG SCB DHG SCB DHG RAB DHG RAB DHG RAB RAB EU/CRC DHG BKW DHG FNF CME SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number: 2009-302 Admin 6 Rev. No.
Date Reason for Revision Author's Supv's Initials Initials 00 05/02/94 Initial development RAB DHG 01 09/06/96 Format change, convert to use SPDS information RAB DHG 02 09/12/96 Editorial, correct MIDAS result numbers for peak RAB RSG TEDE and site boundaries 03 10/03/97 Revised based on 1997 annual exam comments.
SCB DHG 04 09116/98 Revised due to procedurelMIDAS program revision.
SCB DHG 05 01121199 Revised per feedback from EP.
SCB DHG 06 03121/00 Format modification, change time allowance based on RAB DHG running average, change MIDAS for due to revision 07 11/06/00 Include objective number RAB DHG 08 03125/02 Include initial operator statement RAB RAB 09 3122/05 Changed RO to NPO, added statement ensuring the EU/CRC DHG procedure is the current version, changed SOS to SM, addressed the use of TRN-052 and TRN-0146 flowchart and deleted the "S" from the procedure numbers. Modified steps and results to incorporate the use of the new MID AS Windows based software.
10 8/04/05 Corrected "Alarms illuminated" information to match BKW DHG plant conditions given in attachments.
Revised Initial License statement for successful completion.
10/14/09 Revised to use on 2009-302 Exam FNF CME
2009*302 Admin 6 Page 1 of 14 UNIT 1 (X)
UNIT 2 (X)
DURING AN EMERGENCY, PERFORM A PROMPT OFFSITE DOSE ASSESSMENT CALCULATION LR-JP-25306-10 The task shall be complete when the Total Offsite Dose Rate has been calculated per 73EP-EIP-018-0 and the SMIED has been informed of the correct radiological assessment.
200.060 PLANT HATCH JTA IMPORTANCE RATING:
NPO 4.57 SRO 3.92 KIA CATALOG NUMBER: 2.4.39 KIA CATALOG JTA IMPORTANCE RATING:
NPO 3.9 SRO 3.8 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
REQtJ~RltJ)IVIATERJALS;*
34AB-DII-00l-2 (current version) 73EP-EIP-018-0 (current version)
TRN-0052 (current version)
TRN-0146 current version) ro ram APPROXIMATE COMPLETION TIME:
30.0 Minutes SIMULATOR SETUP:
N/A 2009-302 Admin 6 Page 1 of 14 UNIT 1 (X)
UNIT 2 (X)
TASK TITLE:
JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
DURING AN EMERGENCY, PERFORM A PROMPT OFFSITE DOSE ASSESSMENT CALCULATION LR-IP-25306-10 The task shall be complete when the Total Offsite Dose Rate has been calculated per 73EP-EIP-018-0 and the SMIED has been informed of the correct radiological assessment.
200.060 OBJECTIVE NUMBER: 200.060.0 PLANT HATCH JTA IMPORTANCE RATING:
NPO 4.57 SRO 3.92 KIA CATALOG NUMBER: 2.4.39
(
KIA CATALOG JTA IMPORTANCE RATING:
NPO 3.9 SRO 3.8 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
I GENERAL
~~REFERENCES:~~
Unit 1 & 2 34AB-D11-00l-2 (current version) 73EP-EIP-018-0 (current version)
TRN-0052 (current version)
TRN-0146 (current version)
I REQUIRED MATERIALS:
Unit 1 & 2 73EP-EIP-0l8-0 (current version)
TRN-0052 (current version)
TRN-0146 (current version)
Computer with the MIDAS program APPROXIMATE COMPLETION TIME:
30.0 Minutes SIMULATOR SETUP:
NI A
UNITl&2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
~~A pipe break has occurred causing a Primary System discharge outside Primary Containment.~~
2.
~~OFFGAS VENT RADIATION HIGH-HIGH is alarming on Unit 1.~~
3.
~~34AB-D11-00l-2, "Radioactivity Release Control," is in progress.~~
4.
SPDS is available for use.
S.
The Shift Manager (SM) is acting in the Emergency Director's position.
6.
The reactor failed to scram (ATWS), all rods did not fully insert.
INITIATING CUES:
~~1. DETERMINE Total Offsite Dose Rate per 73EP-EIP-0l8-0, "Prompt Offsite Dose Assessment".~~
~~2. NOTIFY the SMIED if:~~
~~A release is in progress An emergency classification should be addressed~~
~~3. PROVIDE the Shift Manager with completed:~~
MIDAS Dose Projection "ENN Form" printout TRN-52 form "Meteorological and Radiological Data Entry" t (,
UNITl&2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
2.
3.
4.
5.
6.
A pipe break has occurred causing a Primary System discharge outside Primary Containment.
OFFGAS VENT RADIATION HIGH-HIGH is alarming on Unit 1.
34AB-DII-00l-2, "Radioactivity Release Control," is in progress.
SPDS is available for use.
The Shift Manager (SM) is acting in the Emergency Director's position.
The reactor failed to scram (A TWS), all rods did not fully insert.
INITIATING CUES:
~~1. DETERMINE Total Offsite Dose Rate per 73EP-EIP-018-0, "Prompt Offsite Dose Assessment".~~
~~2. NOTIFY the SMJED if:~~
~~A release is in progress An emergency classification should be addressed~~
~~3. PROVIDE the Shift Manager with completed:~~
MIDAS Dose Projection "ENN Form" printout TRN-52 form "Meteorological and Radiological Data Entry"
2009*302 Admin 6 Page 3 of 14 SATIUNS,A.'F
... CQMMENTS>
START TIME:~ __ _
PROMPT:
PROVIDE the attached: Annunciator Status sheet, MIDAS screen and Chart Recorder
1.
2.
. t ptC ures.
Operator locates the correct Operator has LOCATED SAT/UNSAT procedure.
73EP-EIP-018-0.
Operator reviews procedure's Operator has REVIEWED the SAT I UNSAT Precautions and Limitations.
Precautions and Limitations section of the procedure.
NOTE: 73EP-EIP-018-0 directs the operator to perform procedure steps or use the Job Aid in TRN-0146, "Prompt Offsite Dose Assessment Flowchart".
Either method is acceptable.
PROMPT:
IF addressed by the operator, as the Shift Supervisor, INFORM the operator that SPDS is available.
4.
NOTE: The operator may collect the required data from SPDS prior to starting the computer. Therefore, Step 5 may be completed prior to Step 3.
NOTE: The computer that may be used is in the plant simulator or those computers that may have been setup by the Emergency Preparedness group specifically for this JPM evaluation.
NOTE: The MIDAS software prints to the user profiles default printer location.
The user should change their printer default to the local printer or a nearby printer location supplied by the Evaluator.
Operator selects the correct MIDAS version and menu option to perform a prompt dose projection.
At a computer workstation, the operator logs in with their business LAN ID and selects the "MIDAS Accident Cales" icon.
The operator selects "Start New Run" and enters or verifies that the correct selections are made to perform a prompt dose projection
[Plant Hatch, Plant, Manual, &
Quick Dose Projection (Menu A)].
SAT/UNSAT SAT/UNSAT
(** Indicates critical step)
(
(
PERFO~NCESTEP STANDARD 2009-302 Admin 6 Page 3 of 14 SATIUNSAT (COMMENTS START TIME:~ __ _
PROMPT:
PROVIDE the attached: Annunciator Status sheet, MIDAS screen and Chart Recorder
1.
2.
plctures.
Operator locates the correct Operator has LOCATED SAT I UNSAT procedure.
73EP-EIP-018-0.
Operator reviews procedure's Operator has REVIEWED the SAT I UNSAT Precautions and Limitations.
Precautions and Limitations section of the procedure.
NOTE: 73EP-EIP-018-0 directs the operator to perform procedure steps or use the Job Aid in TRN-0146, "Prompt Offsite Dose Assessment Flowchart".
Either method is acceptable.
PROMPT:
IF addressed by the operator, as the Shift Supervisor, INFORM the operator that SPDS is available.
3.
4.
NOTE: The operator may collect the required data from SPDS prior to starting the computer. Therefore, Step 5 may be completed prior to Step 3.
NOTE: The computer that may be used is in the plant simulator or those computers that may have been setup by the Emergency Preparedness group specifically for this JPM evaluation.
NOTE: The MIDAS software prints to the user profiles default printer location.
The user should change their printer default to the local printer or a nearby printer location supplied by the Evaluator.
Operator logs onto a business LAN At a computer workstation, the SAT I UNSAT computer that has the MIDAS operator logs in with their software installed.
business LAN ID and selects the "MIDAS Accident Cales" icon.
Operator selects the correct MIDAS The operator selects "Start New SAT I UNSAT version and menu option to perform a Run" and enters or verifies that prompt dose projection.
the correct selections are made to perform a prompt dose projection
[Plant Hatch, Plant, Manual, &
Quick Dose Projection (Menu A)].
(** Indicates critical step)
~~5. Operator records the required information for the Dose Assessment.~~
Using TRN-0052, "MIDAS Data Input Acquisition" Form the operator GATHERSIRECORDS the appropriate information to perform the calculation.
Using the Midas Program, the Operator INPUTS the collected data and performs the dose projection.
2009-302 Admin 6 Page 4 of 14
... SAT/IJN$Arr CCOMMENT$*
SAT/UNSAT SAT I UNSAT PROMPT:
IF asked, INFORM the operator that a reactor trip HAS NOT occurred.
NOTE: Durations other than 15 minutes will vary the resulting projected doses.
NOTE: An evaluator copy of a completed TRN-0052 is attached. Do NOT hand to operator.
Select "Start Calc" on Menu A Sheet # 2 to perform the calculations. The TEDE Rate screen for a 0.25 hrs (15 minutes) projection will be displayed.
The operator READS the peak TEDE Dose Rate Value from the screen and DETERMINES that it is greater than 10 times higher than the daily average. The operator NOTIFIES the SMIED that a release is in progress.
SAT/UNSAT SAT/UNSAT PROMPT:
WHEN the operator addresses informing the SMlED, ACKNOWLEDGE the operator's report and INFORM the operator as the SMIED that you understand a release is in progress.
(** Indicates critical step)
(
PERFO~CESTEP
~~s. Operator records the required information for the Dose Assessment.~~
~~6. Operator determines the*Offsite Dose Rates and Dose Projections.~~
STANDARD Using TRN-0052, "MIDAS Data Input Acquisition" Form the operator GATHERSIRECORDS the appropriate information to perform the calculation.
U sing the Midas Program, the Operator INPUTS the collected data and performs the dose projection.
2009-302 Admin 6 Page 4 of 14 SATIUNSAT (COMMENTS SAT I UNSAT SAT/UNSAT PROMPT:
IF asked, INFORM the operator that a reactor trip HAS NOT occurred.
NOTE: Durations other than 15 minutes will vary the resulting projected doses.
NOTE: An evaluator copy of a completed TRN-0052 is attached. Do NOT hand to operator.
~~7. Operator determines the estimated Select "Start Calc" on Menu A duration of the release.~~
~~Sheet # 2 to perform the calculations. The TEDE Rate screen for a 0.25 hrs (15 minutes) projection will be displayed.~~
~~8. Operator determines thata release is The operator READS the peak in progress and notifiestheSMIED.~~
TEDE Dose Rate Value from the screen and DETERMINES that it is greater than 10 times higher than the daily average. The operator NOTIFIES the SMIED that a release is in progress.
SAT I UNSAT SAT/UNSAT PROMPT:
WHEN the operator addresses informing the SMlED, ACKNOWLEDGE the operator's report and INFORM the operator as the SMIED that you understand a release is in progress.
(** Indicates critical step)
(
The operator READS the peak TEDE Dose Rate Value from the screen and DETERMINES that it exceeds 0.057 mRlhr and occurs beyond the site boundary. The operator NOTIFIES the SMIED that the Emergency Classification Procedure should be addressed 2009-302 Admin 6 Page 5 of 14
... SA'.l'lUNSA1,'
(COMMENTS)
SAT/UNSAT NOTE: Peak TEDE dose rate should calculate to be approximately: 2.6 E-l mRlhr.
PROMPT:
PROMPT:
To successfully complete Step 9, the calculated values must agree, within the allowable band, with the attached:
~~ENN Form printout (+ or - 10%)~~
~~TRN-52 Form (+ or - one increment for the recorder; exact data for the MIDAS screen)~~
WHEN the operator addresses informing the SMlED, ACKNOWLEDGE the operator's report and INFORM the operator as the SMIED that you will declare the Emergency and determine the Protective Action Recommendations (PARs).
The operator provides the SMIED with a completed:
Midas ENN Form printout AND TRN-52 form Meteorological and Radiological Data Entry" SAT/UNSAT WHEN addressed by the operator, as the SM/ED, RECEIVE the printed ENN Form and TRN-52 Form.
WHEN addressed by the operator, as the SM, INFORM the operator that another operator will perform additional dose projections.
NOTE: Compare the student results with the TEDE Rate and ENN attachments in this JPM.
NOTE: The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
END TIME: ___ _
(
9.
PERFORMANCE STEP Operator determines that the peak TEDE Dose Rate is greater than O~057 mRlhr and notifies the SMIED.
STANDARD The operator READS the peak TEDE Dose Rate Value from the screen and DETERMINES that it exceeds 0.057 mRfhr and occurs beyond the site boundary. The operator NOTIFIES the SMIED that the Emergency Classification Procedure should be addressed for releases.
2009-302 Admin 6 Page 5 of 14 SATIUNSAT (COMMENTS SAT I UNSAT NOTE: Peak TEDE dose rate should calculate to be approximately: 2.6 E-l mRlhr.
To successfully complete Step 9, the calculated values must agree, within the allowable band, with the attached:
~~ENN Form printout (+ or - 10%)~~
~~TRN-52 Form (+ or - one increment for the recorder; exact data for the MIDAS screen)~~
PROMPT:
WHEN the operator addresses informing the SMlED, ACKNOWLEDGE the operator's report and INFORM the operator as the SMIED that you will declare the Emergency and determine the Protective Action Recommendations (PARs).
~~10. Operator provides the completed The operator provides the SMIED SAT/UNSAT forms to the SMIED.~~
with a completed:
Midas ENN Form printout AND TRN-52 form Meteorological and Radiological Data Entry" PROMPT:
WHEN addressed by the operator, as the SMlED, RECEIVE the printed ENN Form and TRN-52 Form.
PROMPT:
WHEN addressed by the operator, as the SM, INFORM the operator that another operator will perform additional dose projections.
NOTE: Compare the student results with the TEDE Rate and ENN attachments in this JPM.
NOTE: The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
END TIME: ___
(
(
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MIDAS INFORMATION METEOROLOGICAL 1 Of-ll VVII-.J D SPD lY33-R601 3.0 At\\J1BIENT TEMP (F) 1 O~'/l 54 RADI()LOGICAL f*JIAIN STA.CK lOOt*.jl VVIND SPD lY33-R603 5.0 DELTA T 60~ 10 1.1 1 Ofl~/J VIIIND DIR lY33*R601 60 DELTA T 1 OO~ 10 I'} 4 L,
Ul RX. BLDG. VENT NOR fv'li*\\L R,~.NGE KPit\\IlAN t~ORI*,.IlAL RANGE KA.!VIAt-J 1 Dll-K600A 1 Dll-R631 1 Dll-K600B STABI LIN CLASS E
1.30E~02 1 Dl1-K619fll 1 Dll-R631 4,QOE 01 1 Dll-K619B 3.90E 01 1 OO~il VIIIND DIR lY33~R603 65 RAI t\\J FALL 15 MIN. AVG
.000 U2 r:(x. BLDG. VENT NORMP1 R,l\\NGE KAt'JlAN 2Dll-R619,A.
2D11-R631 4.00E 01 2Dll-R619B 4.QOE 01 MIDAS INFORMATION METEOROLOGICAL 1 OM vVII-.J D SPD lY33-R601 3.0 10Ot'*j] V\\lIND SPD 1Y33-R603 5.0 10/,/1 VIIIND DIR 1Y33-R601 60 At'JlBIE[\\JT TEMP (F) 1 O~'/l 54 f<ADI()LOGICAL t'JlAI/'J S'lf\\CK DELta. T 60-10 1.1 NOR MA,L R.~,~\\lGE Kf\\lt'*,IIAN 1 D l1-K600A 1 01 1-R631 1.30E-02 1 D11-K600B STABILIlY CLASS E
DELTA T 100-10 2.4 U 1 RX. BLDG. VEr'~T NORt'"IIAL R,t1,NGE K~.,MAN 1 D 1 1 -K61 9/\\
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~JORrv1f\\\\L R.L\\NGE KAt**jJ.AN 2Dll~R619.A 2D11-R631 4,QOE 01 2011 ~R619B 4,QOE 01
ANNUNC~TORSTATUS Panel Number Annunciator Title Alarm Status IHII-P60l-4 OFFGAS VENT RAD~ TION HIGH-HIGH Illuminated IHII-P60l-4 OFFGAS VENT RADIATION HIGH Illuminated IHll-P60l-4 OFFGAS VENT RADIATION DNSCIINOP Not llluminated IHII-P601-4 OFFGAS VENT SAMPLE FLOW HIGHJLOW Not llluminated IHII-P60l-4 RX BLDG VENT SAMPLE FLOW HIGHJLOW Not llluminated IHII-P60l-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not llluminated IHII-P603-2 RX BLDG STACK RADN MON HIGH-HIGH Not llluminated IHII-P603-2 RX BLDG STACK RADN MON HIGH Not llluminated IHII-P650-2 MAIN STACK EFFLUENT ANY COLLECTOR Not llluminated RADN LEVEL MAXIMUM IHII-P650-2 MAIN STACK EFFLUENT ALL COLLECTORS Not llluminated RADN LEVEL MAXIMUM IHll-P650-2 RB VENT EFFL ANY COLLECTOR RADN LEVEL Not llluminated MAX IHII-P650-2 RB VENT EFFL ALL COLLECTORS RADN LEVEL Not llluminated MAX 2HII-P60l-2 RX BLDG VENT EXHAUST RAD~TION HI-HI Not llluminated
(
2HII-P601-2 RX BLDG VENT EXHAUST RAD~ TION HIGH Not llluminated 2HII-P60l-4 RX BLDG VT MON HIGH/LOW FLOW Not llluminated DOWNSCALE/INOP 2HII-P60l-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not llluminated 2Hll-P650-2 RB VENT EFFL ANY COLLECTOR RADN LEVEL Not llluminated MAX 2HII-P650-2 RB VENT EFFL ALL COLLECTORS RADN LEVEL Not llluminated MAX Page 11 of 14 ANNUNCIATOR STATUS Panel Number Annunciator Title Alarm Status IH11-P601-4 OFFGAS VENT RADIATION HIGH-HIGH Illuminated IH11-P601-4 OFFGAS VENT RADIATION HIGH Illuminated IH11-P601-4 OFFGAS VENT RADIATION DNSCIINOP Not llluminated IH11-P601-4 OFFGAS VENT SAMPLE FLOW HIGHJLOW Not llluminated IHll-P601-4 RX BLDG VENT SAMPLE FLOW HIGHJLOW Not llluminated IH11-P60 1-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not llluminated IH11-P603-2 RX BLDG STACK RADN MON HIGH-HIGH Not llluminated IH11-P603-2 RX BLDG STACK RADN MON HIGH Not llluminated 1Hll-P650-2 MAIN STACK EFFLUENT ANY COLLECTOR Not llluminated RADN LEVEL MAXIMUM 1Hll-P650-2 MAIN STACK EFFLUENT ALL COLLECTORS Not llluminated RADN LEVEL MAXIMUM 1Hll-P650-2 RB VENT EFFL ANY COLLECTOR RADN LEVEL Not llluminated MAX 1Hll-P650-2 RB VENT EFFL ALL COLLECTORS RADN LEVEL Not llluminated MAX 2Hll-P601-2 RX BLDG VENT EXHAUST RADIATION HI-HI Not llluminated
(
2H11-P60 1-2 RX BLDG VENT EXHAUST RADIATION HIGH Not llluminated 2H11-P601-4 RX BLDG VT MON HIGHJLOW FLOW Not llluminated DOWNSCALE/INOP 2Hll-P601-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not llluminated 2H11-P650-2 RB VENT EFFL ANY COLLECTOR RADN LEVEL Not llluminated MAX 2Hll-P650-2 RB VENT EFFL ALL COLLECTORS RADN LEVEL Not llluminated MAX Pa!!:e 11 of 14
EVALUATOR USE ONLY (not a handout)
Southern Nuclear Emergency Notification l.~DRILL 2.~lNITIAL
~ACTUALEVENT MESSAGE #
~FOLLOW-UP NOTIFICATION: TIME _____ DA1E __ J __
I ___ AUTIffiNTICATION#_N/A
~~3. SI1E: HATCHNUCLEARPLANT Confirmation Phone #~~
CR or TSC - (912) 366-2000 ext. ___ _
EOF -
205 992-6586
~~4. EMERGENCY~~
~ALERT 19 SI1E AREA EMERGENCY
§ GENERAL EMERGENCY
~
UNUSUAL EVENT CLASSIFICATION BASED ON EAL # _____ _
EAL DESCRIPTION: _______________________ _
~~5. PROTECTIVE ACTION RECOMMENDATIONS:~~
I2iINONE
~EVACUA1E----------------------------------
§S~L1ER ____________________________________ _
@ Ad vise Remainder of EPZ to monitor local radiolTV s1ationsfTone Alert Radio. for additional information and CONSIDER THE uSE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WlTH STATE PLANS AND POLICY.
~m~R--------------------------------------
~~6. EMERGENCY RELEASE:~~
~None
~Is Occurring 19 Has Occurred
~~7. RELEASE SIGNIFICANCE:~~
~~8. EVENT PROGNOSIS:~~
~~9. METEOROLOGICAL DATA:~~
~
Not appl:icable
~Witbin normal operating Jim:its
~Improving
~Stable Wind Direction from ~degrees (g Above normal operating limits 19 Degrading Wind Speed ~mph IQI Under evaluation Precipitation IO.@DECLARATION iTERMINATION No Rain Stability Class g Time ________ Date __
1 ___ 1 __
II. AFFEC1ED UNIT(S):
II] I[]
~
~~12. UNIT STATUS:~~
(Unaffected Urnt(s) St.ws Not Rloqolied for Initial Notifications) ltJ U j __ % Power Shutdown at Tirne _____ Date ---.1 __
1 __
I§I U2 __ % Power Shutdown at Tirne Date ---.1 __
1 __
13.REMARKS: _______________________________________ ___
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA_ NOT REQUIRED IF LINE 6 A IS SELECTED.
~~14. RELEASE CHARACTERIZATION:~~
TYPE:8Elevated ~MiXed 19 Ground UNITS:~Ci I§I Ci/sec19~Cilsec MAGNITUDE:
Noble Gases:
1.1E-01 lodines:
1.4E-03 Particulates:
O.OE+OO Other: _____ _
FORM : ~ Airborne
~Liquid
~~15. PROJECTION PARAMETERS:~~
Start Time _____ Date ___ 1 __
I __ Stop Time ____ Date _1 __
1 __
Start Time Date ___ 1 __
I __ Stop Time Date ___ 1 __
1 __
Projection period: ____,Hours Estimated Release Duration 4.0 Hours Projection performed:
Time _____ Date _.-J_---.l __
Accident Type: __
2 __
~~16. PROJECTED DOSE:~~
DISTANCE Site bou ndary 2 Miles 5 Miles 10 Miles TEDE (mrem) 1.0E+00 (band: 0.9-1.1) 8.5E-01 (band: 7.65 - 9.35) 4.2E-01 (band: 3.78 - 4.62) 1.3E-01 (band: 1.17 - 1.43)
Adult ThyrOid CDE (mrem) 5.4 E-02 (band: 4.86 - 5.94) 1.1 E+OO (band:.99 -1.21) 1.9 E+OO (band: 1.71 - 2.09) 8.4 E-01 (band: 7.56 - 9.24)
~~17. APPROVED BY:~~
____________ Title _________ _
NOTIFIED RECEIVED BY: ____________________ __
BY: _____________
Time _____ Date_.J_---.l __
(To be corn ieted by receiving organization)
Page 12 of 14
(
(
EVALUATOR USE ONLY (not a handout)
Southern Nuclear Emergency Notification
~ACTUALEVENT MESSAGE #
~FOLLOW-UP NOTIFICATION: TIME _____ DATE __ J __
I ___ AUTIffiNTICATION#_~_
~~3. SITE: HATCH NUCLEAR PLANT Confirmation Phone #~~
CR or TSC - (912) 366-2000 ext. ___ _
EOF -
205 992-6586
~~4. EMERGENCY CLASSIFICATION~~
~
UNUSUAL EVENT
~ALERT 19 SITE AREA EMERGENCY
§ GENERAL EMERGENCY BASED ON EAL # _____
EAL DESCRIPTION: _______________________
~~5. PROTECTIVE ACTION RECOMMENDATIONS:~~
I2iI NONE
~EVACUATE _____________________________________ _
~S~LTER------------------------------------
§ Ad vise Remainder of EPZ to monitor local radiofTV stationsITone Alert Radios for additional information and CONSIDER THE uSE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WlTH STATE PlANS AND POlJCY.
~m~R--------------------------------------
~~6. EMERGENCY RELEASE:~~
~None
~Is Occurring 19 Has Occurred
~~7. RELEASE SIGNIFICANCE:~~
~~8. EVENT PROGNOSIS:~~
~~9. METEOROLOGICAL DATA:~~
~Not applicable
~Witbin normal operating Jim:its
~Improving
~Stable Wind Direction from ~degrees lSI Above normal operating lirnits 19 Degrading Wind Speed ~mph IQI Under evaluation IO.@DECLARATION Precipitation
~ TERMINATION No Rain Stability Class g Time ________ Date __
1 ___ 1 __
[] I[]
1m I I. AFFECTED UNIT(S):
~~12. UNIT STATUS:~~
(Unaffected Unites) Sta"" Not R<oquued for Initial Notifications) 8 U j __ % Power Shuldown al Time _____ _ Dale ---.1 __
1 __
Dale ---.1 __
1 __
jgJ U2 __ % Power Shuldown al Time _____ _
13.REMARKS: _______________________________________ ___
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.
~~14. RELEASE CHARACTERIZATION:~~
TYPE:8Elevated ~Mixed 19 Ground UNITS:~Ci I§I Ci/sec19!LCiisec MAGNITUDE:
Noble Gases:
1.1E-01 lodines:
1.4E-03 Particulates:
O.OE+OO Other: _____ _
FORM: §I Airborne
~Liquid
~~15. PROJECTION PARAMETERS:~~
Start Time _____ Date __ I __
I __ Stop Time _____ Date __ 1 ___ 1 __
Start Time _____ Date __ I ___ I __ Stop Time Date __ 1 ___ 1 __
Projection period: ___ ---'Hours Estimated Release Duration 4.0 Hours Projection performed:
Time _____ Date __ 1_---.1 __
Accident Type: __ 2 __ _
~~16. PROJECTED DOSE:~~
DISTANCE Site boundary 2 Miles 5 Miles 10 Miles TEDE (mrem) 1.0E+OO (band:0.9-1.1) 8.5E-01 (band: 7.65 - 9.35) 4.2E-01 (band: 3.78 - 4.62) 1.3E-01 (band: 1.17 - 1.43)
Adult Thyroid CDE (mrem) 5.4 E-02 (band: 4.86 - 5.94) 1.1 E+OO (band:.99 -1.21) 1.9 E+OO (band: 1.71 - 2.09) 8.4 E-01 (band: 7.56 - 9.24)
~~17. APPROVED BY:~~
____________ Title ________ _
NOTIFIED BY: __________ ___
RECEIVED BY:
Time _____ Date_J_---.l __
(To be corn ieled by receiving organizalion)
Pag:e 12 of 14
EVALUATOR USE ONL V (NOT A HANDOUT)
METEOROLOGICAL DATA ENTRY MIDAS SCREEN 10M WIND 100M WIND 10M WIND 100M WIND AMBIENT TEMP 15 MIN AVG, 15 MIN AVG, I RAINFALL LABELS SPEED SPEED DIRECTION' DIRECTION' (OF) (10M)
DIFFERENTIAL DIFFERENTIAL (15 MIN, AVG,)
TEMPERATURE (AT)
TEMPERATURE (AT) 60M*10M 100M*10M MPL#
DAre I TIME r:~JJ1--:-'t~~ntni:
54 1,1 2.4 000 Readings may be taken from SPDS (Emergency Screens/MIDAS Reporting Info. or Miscellaneous Screens/Meteorological Data),
Panel 1 H11*P690 (Primary Tower), OR 1 H11*P689 (Backup Tower). In the Simulator Building, the Met MIDAS System can be use to obtain 15 min. average Meteorological Data for the Primary and Back*up Towers.
Stability Class (L1T), wind speed, wind direction and rainfall readings taken directly from the panel must be 15 minute averages.
IF the indicated instrument is unavailable use the following table (TRN*0052 page 2 of 3) to identi~ the appropriate alternate EVALUATOR USE ONLY (NOT A HANDOUT)
METEOROLOGICAL DATA ENTRY MIDAS SCREEN 10M WIND 100M WIND 10M WIND 100M WIND AMBIENT TEMP 15 MIN AVG.
15 MIN AVG.
RAINFALL LABELS SPEED SPEED DIRECTION' DIRECTION' (OF) (10M)
DIFFERENTIAL DIFFERENTIAL (15 MIN. AVG.)
TEMPERATURE (~T)
TEMPERATURE (~T) 60M*10M 100M*10M MPL#
1Y33*R601 1Y33*R603 1Y33*R601 1Y33*R603 1Y33*R607 1Y33*R606 1Y33*R606 1Y33*R606 DATE TIME 3.0 5.0 60 65 54 1.1 2.4 000 Readings may be taken from SPDS (Emergency Screens/MIDAS Reporting Info. or Miscellaneous Screens/Meteorological Data),
Panel 1 H11-P690 (Primary Tower), OR 1 H11-P689 (Backup Tower). In the Simulator Building, the Met MIDAS System can be use to obtain 15 min. average Meteorological Data for the Primary and Back-up Towers.
Stability Class (L1T), wind speed, wind direction and rainfall readings taken directly from the panel must be 15 minute averages.
IF the indicated instrument is unavailable use the following table (TRN-0052 page 2 of 3) to identify the appropriate alternate
SOUTHERN NUCLEAR PLANT E.I. HATCH FORM TITLE:
MIDAS INPUT DATA ACQUISITION PAGE 140F 3 EVALUATOR USE ONLY (not a handout)
RADIOLOGICAL DATA ENTRY NOTES: I
Effluent monitor readings may be taken from SPDS (Emergency ScreenslMlDAS Reporting Info. or Diagnostic Screens/Main Stack Effluent & Vent Effluent HNP 1 &2) OR the associated recorders listed below for each data point.
~~RELEASE PATH MIDAS SCREEN LABELS~~
~~Only normal range data for the associated release path should be recorded !E KAMAN is NOT running. !E KAMAN is running, only KAMAN data for associated release path should be recorded.~~
~~Entering data for the KAMAN monitors when the KAMAN system is NOT operating will result in inaccurate offsite dose estimates.~~
~~TSC HP/Chem staff or on*shift HP Foreman should be contacted for assistance lEthe normal range instrumentation for any release path is offscale high and KAMAN is NOT operating properly.~~
~~Units for radiological data entries should be checked to ensure the values are the same as those required by MIDAS.~~
MAIN STACK Ul RXBLDG.
I U2 RX BLDG MNSTKNR MNSTKKAM STACK U1RXBGNR Ul RXBGKM Ul RXBG U2 RXBGNR U2 RXBGKM U2 RXBG RELEASE RELEASE FLOW RELEASE RELEASE FLOW RELEASE RELEASE FLOW (CPS)
(uCncc)
(CFM)
(CPM)
(uCi\\cc)
(CFM)
(CPM)
(uCncc)
(CFM) 1Dll*K600 AlB lDll*R631 1Dll*R625 1Dll*K619AlB 1Dll-R631 1T41*R621 2Dll*R619 AlB 2Dll-R631 2T41-R621 lHll*P604 lHll-P689 lHll*P645 2Hll*P645 1.3E*02 I 18.0E03 4.0EOI 2.0E05 4.0EOI 200E03 I Allowable Band Allowable Band Allowable Band 17.5 -18.5 (E03) 1.9-2.1 (E05) 195 - 205 (E03)
Note: Highest Note: Highest Note: Highest Note: Highest Note: Highest reading is used.
reading is used.
reading is used.
reading is used.
reading is used.
~\\
SOUTHERN NUCLEAR PLANT E.I. HATCH FORM TITLE:
MIDAS INPUT DATA ACQUISITION PAGE 14 OF 3 EVALUATOR USE ONLY (not a handout)
RADIOLOGICAL DATA ENTRY NOTES:
~~Effluent monitor readings may be taken from SPDS (Emergency Screens/MIDAS Reporting Info. or Diagnostic Screens/Main Stack Effluent & Vent Effluent HNP RELEASE PATH MIDAS SCREEN LABELS PANEL MPL#~~
~~DATE TIME 1 &2) OR the associated recorders listed below for each data point.~~
~~Only normal range data for the associated release path should be recorded !E KAMAN is NOT running. !E KAMAN is running, only KAMAN data for associated release path should be recorded.~~
~~Entering data for the KAMAN monitors when the KAMAN system is NOT operating will result in inaccurate offsite dose estimates.~~
~~TSC HP/Chem staff or on-shift HP Foreman should be contacted for assistance IE.. the normal range instrumentation for any release path is offscale high and KAMAN is NOT operating properly.~~
~~Units for radiological data entries should be checked to ensure the values are the same as those required by MI DAS.~~
MAIN STACK U1 RXBLDG.
U2 RXBLDG MNSTKNR MNSTKKAM STACK U1RXBGNR U1 RXBGKM U1 RXBG U2 RXBGNR U2 RXBGKM U2 RXBG RELEASE RELEASE FLOW RELEASE RELEASE FLOW RELEASE RELEASE FLOW (CPS)
(uCncc)
(CFM)
(CPM)
(uCi\\cc)
(CFM)
(CPM)
(uCncc)
(CFM) 1D11-K600 AlB 1D11*R631 1D11*R625 1D11*K619 AlB 1D11*R631 1T41*R621 2D11*R619 AlB 2D11*R631 2T41*R621 1H11*P604 1H11*P689 1H11*P645 1H11*P604 1H11*P689 1H11*P645 2H11*P645 2H11*P689 2H11*P645 1,3E-02 18,OE03 4,OE01 2,OE05 4,OE01 2DDED3 Allowable Band Allowable Band Allowable Band 17,5 -18.5 (E03) 1.9 - 2,1 (E05) 195 - 205 (E03)
Note: Highest Note: Highest Note: Highest Note: Highest Note: Highest reading is used.
reading is used.
reading is used.
reading is used.
reading is used.
(
(
UNIT 1 &2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
2.
3.
4.
5.
6.
A pipe break has occurred causing a Primary System discharge outside Primary Containment.
OFFGAS VENT RADIATION HIGH-HIGH is alarming on Unit 1.
34AB-D11-001-2, "Radioactivity Release Control," is in progress.
SPDS is available for use.
The Shift Manager (SM) is acting in the Emergency Director's position.
The reactor failed to scram (A TWS), all rods did not fully insert.
INITIATING CUES:
~~1. DETERMINE Total Offsite Dose Rate per 73EP-EIP-018-0, "Prompt Offsite Dose Assessment".~~
~~2. NOTIFY the SMIED if:~~
~~A release is in progress An emergency classification should be addressed~~
~~3. PROVIDE the Shift Manager with completed:~~
MIDAS Dose Projection "ENN Form" printout TRN-52 form "Meteorological and Radiological Data Entry"
(
(
UNIT 1 &2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
~~A pipe break has occurred causing a Primary System discharge outside Primary Containment.~~
2.
~~OFFGAS VENT RADIATION HIGH-HIGH is alarming on Unit 1.~~
3.
~~34AB-D 11-001-2, "Radioactivity Release Control," is in progress.~~
4.
~~SPDS is available for use.~~
5.
~~The Shift Manager (SM) is acting in the Emergency Director's position.~~
6.
The reactor failed to scram (A TWS), all rods did not fully insert.
INITIATING CUES:
~~1. DETERMINE Total Offsite Dose Rate per 73EP-EIP-018-0, "Prompt Offsite Dose Assessment".~~
~~2. NOTIFY the SMIED if:~~
~~A release is in progress An emergency classification should be addressed~~
~~3. PROVIDE the Shift Manager with completed:~~
MIDAS Dose Projection "ENN Form" printout TRN-52 form "Meteorological and Radiological Data Entry"
,~-"
SOUTHERN NUCLEAR PLANT E./. HATCH FORM TITLE:
MIDAS INPUT DATA ACQUISITION MIDAS SCREEN 10M WIND 100M WIND LABELS SPEED SPEED 10M WIND DIRECTION' PAGE 1 OF 3 METEOROLOGICAL DATA ENTRY 100M WIND AMBIENT TEMP 15 MIN AVG.
15 MIN AVG.
RAINFALL DIRECTION*
(OF) (10M)
DIFFERENTIAL DIFFERENTIAL (15 MIN. AVG.)
TEMPERATURE (I'.T)
TEMPERATURE (I'.T) 60M-10M 100M-10M MPL#
DATE TIME Readings may be taken from SPDS (Emergency Screens/MIDAS Reporting Info. or Miscellaneous Screens/Meteorological Data), Panel 1 H11-P690 (Primary Tower), OR 1 H11-P689 (Backup Tower). In the Simulator Building, the Met MIDAS System can be use to obtain 15 min. average Meteorological Data for the Primary and Back-up Towers.
Stability Class (Ll T), wind speed, wind direction and rainfall readings taken directly from the panel must be 15 minute averages.
I.E the indicated instrument is unavailable use the following table (TRN-0052 page 2 of 3) to identify the appropriate alternate instrument.
~~For wind direction greater than 360 degrees, subtract 360.~~
TRN-0052 Rev. 13.0 G16.70 73EP-EIP-015-0 73EP-EIP-018-0 SOUTHERN NUCLEAR PLANT E.!. HATCH FORM TITLE:
MIDAS INPUT DATA ACQUISITION MIDAS SCREEN 10M WIND 100M WIND LABELS SPEED SPEED 10M WIND DIRECTION' PAGE 1 OF 3 METEOROLOGICAL OAT A ENTRY 100M WIND AMBIENT TEMP 15 MIN AVG.
15 MIN AVG.
RAINFALL DIRECTION' (OF) (10M)
DIFFERENTIAL DIFFERENTIAL (15 MIN. AVG.)
TEMPERATURE (~T)
TEMPERATURE (~T) 60M-10M 100M-10M MPL#
1Y33-R601 1Y33-R603 1Y33-R601 1Y33-R603 1Y33-R607 1Y33-R606 1Y33-R606 1Y33-R606 DATE TIME Readings may be taken from SPDS (Emergency Screens/MIDAS Reporting Info. or Miscellaneous Screens/Meteorological Data), Panel 1 H11-P690 (Primary Tower), OR 1 H11-P689 (Backup Tower). In the Simulator Building, the Met MIDAS System can be use to obtain 15 min. average Meteorological Data for the Primary and Back-up Towers.
Stability Class (L'l. T), wind speed, wind direction and rainfall readings taken directly from the panel must be 15 minute averages.
!E the indicated instrument is unavailable use the following table (TRN-0052 page 2 of 3) to identify the appropriate alternate instrument.
~~For wind direction greater than 360 degrees, subtract 360.~~
TRN-0052 Rev. 13.0 G16.70 73EP-EIP-015-0 73EP-EIP-018-0
~
SOUTHERN NUCLEAR PLANT E.1. HATCH FORM TITLE:
MIDAS INPUT DATA ACQUISITION
/,....,.-.,
Alternate Meteorological Instrument Designation for Dose Assessment Use i<<,
...** <i.
'..,..***.* '.'..../ '.'...,
~~. '...... **.. *M~in$t~cl<.~I~v~ted~~le~~e*(!VIeteOtpI9gi~~IPCltCl~ntry.~omr"'1pOM ~C:lt~)~~
100M Wind Speed~
100M Wind Direction~
1 00M-1 OM Differential 10M Ambient Temperature 15 Min. Avg. MPH5 15 Min. Avg. ° From5 Temp. 15 Av. liT ° F5 15 Min. Avg. of Value MPL#
Value MPL#
Value MPL#
Value MPL#
Primary 100 M Y33-R603 100 M Y33-R603 100M -10M Y33-R606 10 M Y33-R606 1 St Alternate 60 M Y33-R602 60 M Y33-R602 60M -10M Y33-R606 10M Y33-R604 2na Alternate 45M Y33-R604 45M Y33-R604 45M-10M Y33-R604 Estimate" 3ra Alternate 10 M Y33-R601 10 M Y33-R601 cre4 Y33-R603 N/A 100M or 60M Y33-R602 PAGE 2 OF 3 Rainfall 15 Min. Avg.
Value MPL#
10 M Y33-R606 Estimate" N/A N/A
. **i*>>**.. >................. <..........* *** *.*.*** *'.. **.* *.~~c:U:,t()r:l3ujltffrigy~t1tc;rqufld~,"el.~~rea~~.(JYlet~oroIO~i~~'Oait~ti~nJ.ryForl'll~,1PiVId.C:lt~)...*..**.. *.i.. **.*.
~~<>...... ***...,/I*.*,**** *.. *'.*.*.*.**i*.. **.'~~
10M Wind Speed~
10M Wind Direction~
60M-10M Differential 10M Ambient Rainfall 15 Min. Avg. mph5 15 Min. Avg. ° From5 Temp. 15 Avg. liT ° F5 Temperature 15 Min. Avg.
15 Min. Avg. OF Value MPL#
Value MPL#
Value MPL#
Value MPL#
Value MPL#
Primary 10 M Y33-R601 10 M Y33-R601 60M-10M Y33-R606 10 M Y33-R606 10 M Y33-R606 1 S Alternate 45 M Y33-R604 45M Y33-R604 45M-10M Y33-R604 10 M' Y33-R604 Estimate~
2nu Alternate 60 M Y33-R602 60 M Y33-R602 100M-10M Y33-R606 Estimate" N/A 3ra Alternate 100 M Y33-R603 100 M Y33-R603 cre4 Y33-R601 N/A N/A 10M or45M Y33-R6041
~~1. These readings are obtained from the Back-Up Meteorological Tower..~~
2.
~~Since this value has minimal impact on the dispersion calculation an estimated ambient Temperature is acceptable.~~
3.
~~Input these letters as estimates for rainfall based on a visual observation, L for Light, M for Medium Rain, or H for Heavy Rain. IE no information is available use 0 in.l15 min. rainfall.~~
~~4. IE the temperature values are unavailable for the Delta T readings, use the Sigma Theta (cre) (variation in wind direction (in degrees)) for the Stability Class -~~
~~2: 22.5° = A, 22.4° - 17.5° = B, 17.4° - 12.5° = C, 12.4° - 7.5° = D, 7.4° - 3.8° = E, 3.r - 2.1° = F, > 2.1° = G. Input the Stability Class "Letter" into MIDAS.~~
5. IE all instruments in this data field are inoperable, call the National Weather Service (see Emergency Call List Section 1-Offsite Agencies Phone List) and ask for the information from the nearest available source.
TRN-0052 Rev. 13.0 G16.70 73EP-EIP-015-0 73EP-EIP-0 18-0 SOUTHERN NUCLEAR PLANT E.1. HATCH FORM TITLE:
MIDAS INPUT DATA ACQUISITION Alternate Meteorological Instrument Designation for Dose Assessment Use Main Stack Elevated Release (Meteorological Data Entry Form - 100 M data) 100M Wind Speed" 100M Wind Direction" 1 00M-1 OM Differential 10M Ambient Temperature 15 Min. Avg. MPH5 15 Min. Avg. ° From5 Temp. 15 Av.,iT ° F5 15 Min. Avg. OF Value MPL#
Value MPL#
Value MPL#
Value MPL#
Primary 100 M Y33-R603 100 M Y33-R603 100M -10M Y33-R606 10 M Y33-R606 1 S Alternate 60 M Y33-R602 60 M Y33-R602 60M -10M Y33-R606 10M Y33-R604 2na Alternate 45M i
Y33-R604 45M Y33-R604 45M-10M Y33-R604 Estimate L
3 ru Alternate 10 M Y33-R601 10 M Y33-R601 08 4
Y33-R603 N/A 100M or 60M Y33-R602 Reactor Building Vent Ground Level Release (Meteorological Data Entry Form *10 M data) 10M Wind Speed" 10M Wind Direction" 60M-10M Differential 10M Ambient 15 Min. Avg. mph5 15 Min. Avg. ° From5 Temp. 15 Avg.,iT ° F5 Temperature 15 Min. Avg. OF Value MPL#
Value MPL#
Value MPL#
Value MPL#
Primary 10 M Y33-R601 10 M Y33-R601 60M-10M Y33-R606 10 M Y33-R606 1 S Alternate 45 M Y33-R604 45M Y33-R604 45M-10M Y33-R604 10 M Y33-R604 2na Alternate 60 M Y33-R602 60 M Y33-R602 100M-10M Y33-R606 Estimate L
3ru Alternate 100 M Y33-R603 100 M Y33-R603 08 4
Y33-R601 N/A 10M or 45M Y33-R6041
1.
~~These readings are obtained from the Back-Up Meteorological Tower..~~
2.
Since this value has minimal impact on the dispersion calculation an estimated ambient Temperature is acceptable.
PAGE 2 OF 3 Rainfall 15 Min. Avg.
Value MPL#
10 M Y33-R606 Estimate" N/A N/A Rainfall 15 Min. Avg.
Value MPL#
10 M Y33-R606 Estimate" N/A N/A
3.
~~Input these letters as estimates for rainfall based on a visual observation, L for Light, M for Medium Rain, or H for Heavy Rain. lE. no information is available use 0 in.l15 min. rainfall.~~
~~4. lE. the temperature values are unavailable for the Delta T readings, use the Sigma Theta (08) (variation in wind direction (in degrees)) for the Stability Class -~~
~~2': 22.5° = A, 22.4° - 17.so = B, 17.4° - 12.5° = C, 12.4° - 7.5° = D, 7.4° - 3.8° = E, 3.7° - 2.1° = F, > 2.1° = G. Input the Stability Class "Letter" into MIDAS.~~
5. lE. all instruments in this data field are inoperable, call the National Weather Service (see Emergency Call List Section I - Offsite Agencies Phone List) and ask for the information from the nearest available source.
TRN-0052 Rev. 13.0 G16.70 73EP-EIP-015-0 73EP-EIP-0 18-0
SOUTHERN NUCLEAR PLANT E.!. HATCH FORM TITLE:
MIDAS INPUT DATA ACQUISITION r'\\
PAGE 3 OF3 RADIOLOGICAL DATA ENTRY NOTES:
Effluent monitor readings may be taken from SPDS (Emergency Screens/MIDAS Reporting Info. or Diagnostic Screens/Main Stack Effluent & Vent Effluent HNP 1 &2) OR the associated recorders listed below for each data point.
~~Only normal range data for the associated release path should be recorded IF KAMAN is NOT running. !E KAMAN is running, only KAMAN data for associated release path should be recorded.~~
~~Entering data for the KAMAN monitors when the KAMAN system is NOT operating will result in inaccurate offsite dose estimates.~~
~~TSC HP/Chem staff or on-shift HP Foreman should be contacted for assistance !E."the normal range instrumentation for any release path is offscale high and KAMAN is NOT operating properly.~~
~~Units for radiological data entries should be checked to ensure the values are the same as those required by MIDAS.~~
RELEASE (CPS) 1D11-K600 NB Default flow values are as follows:
Unit 1 Reactor Building Vent Unit 2 Reactor Building Vent Main Stack TRN-0052 Rev. 13.0 RELEASE (uCi\\cc) 1D11-R631 FLOW (CFM) 1D11-R625 UNISOLATED 288,905 CFM 198,840 CFM 20,000 CFM U1 RXBLDG.
RELEASE (CPM) 1D11-K619NB ISOLATED 193,870 CFM 162,340 CFM 20,000 CFM G16.70 RELEASE (uCi\\cc) 1D11-R631 FLOW (CFM) 1T41-R621 RELEASE (CPM) 2D11-R619NB RELEASE (uCi\\cc) 2D11-R631 RXBG FLOW (CFM) 2T41-R621 A release is underway IF effluent monitors exceed the values below:
Main Stack Normal Range ~500 cps Either Reactor Bldg. Stack Vent ~ 10,000 cpm or Sum of Unit 1 and 2 Reactor Bldg Stack Vent ~ 10,000 cpm.
73EP-EIP-015-0 73EP-EIP-018-0 SOUTHERN NUCLEAR PLANT E.I. HATCH FORM TITLE:
MIDAS INPUT DATA ACQUISITION PAGE 3 OF 3 RADIOLOGICAL DATA ENTRY
Effluent monitor readings may be taken from SPDS (Emergency Screens/MIDAS Reporting Info. or Diagnostic Screens/Main Stack Effluent & Vent Effluent HNP 1 &2) OR the associated recorders listed below for each data point.
~~Only normal range data for the associated release path should be recorded!E KAMAN is NOT running.!E KAMAN is running, only KAMAN data for associated release path should be recorded.~~
~~Entering data for the KAMAN monitors when the KAMAN system is NOT operating will result in inaccurate offsite dose estimates.~~
~~TSC HP/Chem staff or on-shift HP Foreman should be contacted for assistance lEJhe normal range instrumentation for any release path is offscale high and KAMAN is NOT operating properly.~~
~~Units for radiological data entries should be checked to ensure the values are the same as those required by MIDAS.~~
RELEASE PATH MNSTKNR MIDAS RELEASE SCREEN LABELS (CPS) 1 D11-K600 AlB PANEL MPL#
1 H11-P604 DATE TIME Default flow values are as follows:
Unit 1 Reactor Building Vent Unit 2 Reactor Building Vent Main Stack TRN-00S2 Rev. 13.0 MAIN STACK MNSTKKAM STACK RELEASE FLOW (uCi\\cc)
(CFM) 1D11-R631 1D11-R625 1H11-P689 1 H11-P645 UNISOLATED 288,90S CFM 198,840 CFM 20,000 CFM U1RXBGNR RELEASE (CPM) 1D11-K619 AlB 1H11-P604 ISOLATED 193,870 CFM 162,340 CFM 20,000 CFM U1 RXBLDG.
U2RX BLDG U1 RXBGKM U1 RXBG U2 RXBGNR U2 RXBGKM U2 RXBG RELEASE FLOW RELEASE RELEASE FLOW (uCi\\cc)
(CFM)
(CPM)
(uCi\\cc)
(CFM) 1D11-R631 1T41-R621 2D11-R619 AlB 2D11-R631 2T41-R621 1H11-P689 1 H11-P645 2H11-P645 2H11-P689 2H11-P645 A release is underway IF effluent monitors exceed the values below:
Main Stack Normal Range;:: 500 cps Either Reactor Bldg. Stack Vent;:: 10,000 cpm or Sum of Unit 1 and 2 Reactor Bldg Stack Vent;:: 10,000 cpm.
G16.70 73EP-EIP-01S-0 73EP-EIP-018-0
MAIN STACK FLOW 1 Dll-R625 INST BUS lA MAIN STACK FLOW RED-(CHANNEL B) 0-25 CFM X 1000 BLK-(CHANNEL A) 0-25 CFM X 1000 1 Dll-R625 6050K60-858 PaQ"e fi of 14
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MAIN STACK FLOW 1 Dll-R625 INST BUS 1A o
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5
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MAIN STACK FLOW RED-(CHANNEL B) 0-25 CFM X 1000 BLK-(CHANNEL A) 0-25 CFM X 1000
'"'c L.V 1 Dll-R625 6050K60-858 PaQ"e 6 of 14
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STACK VENT FLOW lT41-R621 INST BUS lA
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STACK VENT FLOW lT41-R621 INST BUS 1A I I I I I I I I I I I I I I I I I I I~I I I I I I I I I I I I I II Il~lliili iiJ
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lT41-R621 CTA6445200 Pa!!c 7 of 14
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STACK VENT fLOW 2T41-R621 INST BUS 2B RB STACK MONITOR RED-RB STACK fLOW (CH-B) 0-400,000 SCfM BLK-RB STACK fLOW (CH-A) 0-400,000 SCfM 2T41-R621 CTA6445100 Page R of 14
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STACK VENT FLOW 2T41-R621 INST BUS 2B RB STACK MONITOR RED-RB STACK FLOW (CH-B) 0-400,000 SCFM BLK-RB STACK FLOW (CH-A) 0-400,000 SCFM 2T41-R621 CTA6445100 Page R of 14
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MIDAS INFORMATION METEOROLOGICAL lot\\1l VVIND SPD lV33-R601 3.0 At'"IlBIE~JT TEMP (F) 1 O~11 54 RADIOLOGICAL MAII\\J STACK 100t'*/I WIND SPD lY33~R603 5.0 DELTA T 60~ 10 1.1 1 Otv] VII/ND DIR lY33*R601 60 DELTA T 100*' 0 2.4 U 1 RX. BLDG. VE NT NORW,L R,A.NGE KAMAN NORt'"I1AL RANGE KA MA,N 1 D ll-K600A 1 D 1 l-R631 1 Dl1-K600B STABI LIlY CLASS E
1.30E-02 1 D 1 1 "'K61 9 A 1 D 11 ~R631 4,QOE 01 1 Dll-K619B 3.90E 01 1 OOtv1 VIIIND DIR lY33~R603 65 RAINFALL 16 MIN. AVG
,000 U2 RX. BLDG. VENT NOR t\\/IAL R.~NGE KAMAN 2D 11 ~R619A 2D 11-1<631 4.00E 01 2D11 ~R619B 4,OOE 01 MIDAS INFORMATION METEOROLOGICAL 1 01\\11 vVII-JD SPD lV33-R601 3.0 1 DOM VVIND SPD 1Y33~R603 5.0 1 Ot\\.:J VvlND DIR 1Y33-R60l 60 At\\}1BIE~JT TEMP (F) 1 O~J1 54 RADI()LOGICAL MAII\\J STACK DELtA. T 60-10 1.1 NORW,L R.il,NGE KAt'*J1AN 1 D ll-K600<\\
1 Dll-R631 1.30E-02 1 D11-K600B STABI LIlY CLASS E
DELTA T 1 OO~ 10 2.4 U 1 RX, BLDG. VE NT NORt'*J1AL RANGE KA Mil.N 1 D11-K619A 1 Dll wR631 4.00E 01 1 Dll-K619B 3.90E 01 1 OOt\\iJ VvlND DIR 1V33-R603 65 RAI~*,JFALL 15 MIN. AVG
.000 U2 r~x. BLDG. VENT NORf\\*tAL Rj~NGE KAMAN 2D 11 -R61 9.~\\
2D 11*R631 4.00E 01 2011 ~R619B 4,QOE 01
ANNUNCIATOR STATUS
(
Panel Number Annunciator Title Alarm Status IHII-P601-4 OFFGAS VENT RADIATION HIGH-HIGH Illuminated IHll-P601-4 OFFGAS VENT RADIATION HIGH Illuminated IHII-P601-4 OFFGAS VENT RADIATION DNSC/INOP Not llluminated IHII-P601-4 OFFGAS VENT SAMPLE FLOW HIGHILOW Not llluminated IHII-P601-4 RX BLDG VENT SAMPLE FLOW HIGHILOW Not llluminated IHll-P601-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not llluminated IHll-P603-2 RX BLDG STACK RADN MON HIGH-HIGH Not llluminated IHll-P603-2 RX BLDG STACK RADN MON HIGH Not llluminated IHll-P650-2 MAIN STACK EFFLUENT ANY COLLECTOR Not llluminated RADN LEVEL MAXIMUM IHll-P650-2 MAIN STACK EFFLUENT ALL COLLECTORS Not llluminated RADNLEVELMAXIMUM IHII-P650-2 RB VENT EFFL ANY COLLECTOR RADN LEVEL Not llluminated MAX IHII-P650-2 RB VENT EFFL ALL COLLECTORS RADN LEVEL Not llluminated MAX 2Hll-P601-2 RX BLDG VENT EXHAUST RADIATION HI-HI Not llluminated
(
2Hll-P601-2 RX BLDG VENT EXHAUST RADIATION HIGH Not llluminated 2Hll-P601-4 RX BLDG VT MON HIGHILOW FLOW Not llluminated DOWNSCALE/INOP 2Hll-P601-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not llluminated 2HII-P650-2 RB VENT EFFL ANY COLLECTOR RADN LEVEL Not llluminated MAX 2Hll-P650-2 RB VENT EFFL ALL COLLECTORS RADN LEVEL Not llluminated MAX
(
Pl'lP"~ 11 of 14 ANNUNC~TORSTATUS Panel Number Annunciator Title Alarm Status IH11-P601-4 OFFGAS VENT RAD~TION HIGH-HIGH Illuminated IH11-P601-4 OFFGAS VENT RADIATION HIGH Illuminated IHll-P601-4 OFFGAS VENT RADIATION DNSC/INOP Not illuminated IH11-P601-4 OFFGAS VENT SAMPLE FLOW HIGHILOW Not illuminated IHll-P601-4 RX BLDG VENT SAMPLE FLOW HIGHILOW Not illuminated IH11-P601-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not illuminated IH11-P603-2 RX BLDG STACK RADN MON HIGH-HIGH Not illuminated IH11-P603-2 RX BLDG STACK RADN MON HIGH Not illuminated 1H11-P650-2 MAIN STACK EFFLUENT ANY COLLECTOR Not illuminated RADN LEVEL MAXIMUM 1H11-P650-2 MAIN STACK EFFLUENT ALL COLLECTORS Not illuminated RADN LEVEL MAXIMUM 1H11-P650-2 RB VENT EFFL ANY COLLECTOR RADN LEVEL Not illuminated MAX 1H11-P650-2 RB VENT EFFL ALL COLLECTORS RADN LEVEL Not illuminated MAX 2Hll-P601-2 RX BLDG VENT EXHAUST RAD~ TION HI-HI Not illuminated
(
2Hll-P601-2 RX BLDG VENT EXHAUST RAD~ TION HIGH Not illuminated 2H11-P601-4 RX BLDG VT MON HIGHILOW FLOW Not illuminated DOWNSCALE/INOP 2 Hll-P60 1-4 REFUELING FLOOR VENT EXHAUST RAD HI-HI Not illuminated 2H11-P650-2 RB VENT EFFL ANY COLLECTOR RADN LEVEL Not illuminated MAX 2H11-P650-2 RB VENT EFFL ALL COLLECTORS RADN LEVEL Not illuminated MAX
(
P:u'e 11 of 14
FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 7 - SRO Only C.M.EDMUND 1011412009 SOUTHERN..
\\
COMPANY FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 7 - SRO Only TITLE EV ALUATE THE NEED FORIRECOMMEND OFFSITE PROTECTIVE
(
ACTIONS AUTHOR MEDIA NUMBER TIME F.N.FAGAN 2009-302 Admin 7 13.0 Minutes RECOMMENDED BY APPROVED BY DATE C.M.EDMUND 10114/2009
(
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number: 2009*302 Admin 7 S<,,;'T... *,~aie~./
I***
. ****)*.R~:L~f'~t ~; ___ L!_:_.** ******(;</(ii..
.......... 4-1J.tliot'~....... S~pV~S i<~~D.[~v.**....*.*......*... *.*.* *
.*.**.... * *. i'**< I.*****.* ******* *. ><>>i...**. *
.. ***.>i;*.< **)I *** ** ** *.*............~~;..,7;('*.*._.*..* **.***.*.5.- *. *..... *
** *.*** <.i j_
> lnitblls
. Initials 01 09/24/92 General revision and format change WMM SMC 02 08/05/94 General revision, word processor change, incorporate RAB MMG change to MIDAS, adjust format 03 08/21/96 Format change RAB DHG 04 07/03/97 Revised initiating cue and added MIDAS screen.
SCB DHG 05 03/21/00 Format modification, change time allowance based on RAB DHG running average, change MIDAS form due to revision 06 11/06/00 Include objective number RAB DHG 07 03/25/02 Include initial operator statement RAB RAB 08 03117/04 Rev to 73EP-EIP-054-0 DNM DHG 09 06127/05 Revised Initial License statement for successful RAB RAB completion 10 03121/06 Updated to include latest Midas and ENN form, RAB RAB removed Response Cues 11 12/04/06 Updated for NMP-EP-109.
DHG DHG 10114/09 Revised for use on 2009-302 Exam FNF CME
(
(
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number: 2009-302 Admin 7 Rev. No.
Date Reason for Revision Author's Supv's Initials Initials 01 09124/92 General revision and format change WMM SMC 02 08/05/94 General revision, word processor change, incorporate RAB MMG change to MIDAS, adjust format 03 08121196 Format change RAB DHG 04 07/03/97 Revised initiating cue and added MIDAS screen.
SCB DHG 05 03121/00 Format modification, change time allowance based on RAB DHG running average, change MIDAS form due to revision 06 11106100 Include objective number RAB DHG 07 03125102 Include initial operator statement RAB RAB 08 03117/04 Rev to 73EP-EIP-054-0 DNM DHG 09 06127/05 Revised Initial License statement for successful RAB RAB completion 10 03121106 Updated to include latest Midas and ENN form, RAB RAB removed Response Cues 11 12/04/06 Updated for NMP-EP-l 09.
DHG DHG 10114/09 Revised for use on 2009-302 Exam FNF CME
(
2009*302 Admin 7 Page 1 of7 UNIT 1 (X)
UNIT 2 (X)
...'fASKNNltJl:-.........
EVALUATE THE NEED FOR/RECOMMEND OFFSITE PROTECTIVE ACTIONS Error! Reference source not found.
The task shall be completed when the Protective Action Recommendation has been made per NMP-EP-109.
201.105 (EP 001.088)
PLANT HATCH JTA IMPORTANCE RATING:
RO 3.00 SRO 3.00 KIA CATALOG NUMBER: 2.4.9 KIA CATALOG JTA IMPORTANCE RATING:
RO N/A SRO 4.00 OPERA TOR APPLICABILITY:
Senior Reactor Operator (SRO)
APPROXIMATE COMPLETION TIME:
13.0 Minutes SIMULATOR SETUP:
N/A
(
(
2009-302 Admin 7 Page 1 of7 UNIT 1 (X)
UNIT 2 (X)
TASK TITLE:
JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
EV ALUATE THE NEED FORIRECOMMEND OFFSITE PROTECTIVE ACTIONS Error! Reference source not found.
The task shall be completed when the Protective Action Recommendation has been made per NMP-EP-109.
201.105 (EP 001.088)
OBJECTIVE NUMBER: 200.105.A PLANT HATCH JTA IMPORTANCE RATING:
RO 3.00 SRO 3.00 KIA CATALOG NUMBER: 2.4.9 KIA CATALOG JTA IMPORTANCE RATING:
RO N/A SRO 4.00 OPERATOR APPLICABILITY:
Senior Reactor Operator (SRO)
I GENERAL
~~REFERENCES:~~
Unit 1 & 2 NMP-EP-109 (current version)
I REQUIRED MATERIALS:
Unit 1 & 2 NMP-EP-109 (current version)
APPROXIMATE COMPLETION TIME:
13.0 Minutes SIMULATOR SETUP:
N/A
(
UNITl&2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
~~The Prompt Offsite Dose Assessment has just been completed. The ENN form has been printed and is available. The MIDAS screen is available.~~
2.
~~The Dose Assessment Staff is not available yet.~~
3.
~~The Shift Manager has declared a General Emergency due to the release.~~
4.
~~The release started 30 minutes ago and is ongoing.~~
4.
~~The Shift Manager is performing the functions of the Emergency Director.~~
5.
~~SPDS is not available.~~
6.
~~No adverse weather conditions exist.~~
7.
~~No manmade threats, i.e. terrorist threats, exist.~~
8.
No known offsite conditions for evacuation exist.
INITIATING CUES:
Complete Section 5, "Protective Action Recommendations" of the ENN form for the EPZ only, IA W NMP-EP-l 09. This is Time Critical.
(
(
UNITl&2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
2.
3.
4.
4.
s.
6.
7.
8.
The Prompt Offsite Dose Assessment has just been completed. The ENN form has been printed and is available. The MIDAS screen is available.
The Dose Assessment Staff is not available yet.
The Shift Manager has declared a General Emergency due to the release.
The release started 30 minutes ago and is ongoing.
The Shift Manager is performing the functions of the Emergency Director.
SPDS is not available.
No adverse weather conditions exist.
No manmade threats, i.e. terrorist threats, exist.
No known offsite conditions for evacuation exist.
INITIATING CUES:
Complete Section 5, "Protective Action Recommendations" of the ENN form for the EPZ only, IA W NMP-EP-I09. This is Time Critical.
2009-302 Admin 7 Page 3 of?
START TIME: ___ _
PROMPT:
AT this time, GIVE the operator the Emergency Notification Form, and the MIDAS Screen.
~~1. Identifies the procedure needed to perform the task.~~
~~2. Review the procedure's precautions and limitations.~~
~~3. Utilize Attachment 1.~~
~~4. Determine if a General Emergency has been declared.~~
Operator has identified the correct procedure as NMP-EP-109.
Operator has reviewed the precautions and limitations.
Operator has identified the as the correct procedure section.
The Operator determines a General Emergency has been declared and answers YES on the flowchart.
The Operator determines a PUFF release is not in progress or been terminated and answers NO on the flowchart.
SAT I UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT NOTE: The definition section of NMP-EP-109 defines a PUFF release as "less than an hour". The EN form has the estimated release at 4.0 hours0 days 0 hours 0 weeks 0 months .
The Operator determines from the initial conditions that evacuation is not dangerous and answers NO on the flowchart.
The Operator determines that site boundary doses will exceed the PAGs and answers YES on the flowchart.
The Operator refers to the HATCH specific Table 1.
SAT/UNSAT SAT I UNSAT SAT/UNSAT NOTE: Operator may use the optional Attachment 5, PAR Worksheet to record the information.
(** Indicates critical step)
(
PERFORMANCE STEP STANDARD 2009-302 Admin 7 Page 3 of7 SATIUNSAT (COMl\\1ENTS START TIME: ___ _
PROMPT:
AT this time, GIVE the operator the Emergency Notification Form, and the MIDAS Screen.
~~1. Identifies the procedure needed to Operator has identified the correct SAT/UNSAT perform the task.~~
~~procedure as NMP-EP-109.~~
~~2. Review the procedure's precautions Operator has reviewed the SAT/UNSAT and limitations.~~
~~precautions and limitations.~~
~~3. Utilize Attachment 1.~~
~~Operator has identified the SAT/UNSAT as the correct procedure section.~~
~~4. Determine if a General Emergency The Operator determines a SAT/UNSAT has been declared.~~
~~General Emergency has been declared and answers YES on the flowchart.~~
5. Determine if a PUFF release is in*
The Operator determines a PUFF SAT/UNSAT progress or been terminated.
release is not in progress or been terminated and answers NO on the flowchart.
NOTE: The definition section of NMP-EP-109 defines a PUFF release as "less than an hour". The EN form has the estimated release at 4.0 hours0 days 0 hours 0 weeks 0 months .
6. Determine if a known Site, Plant The Operator determines from the SAT/UNSAT Event or Offsite Condition is initial conditions that evacuation Underway making Evacuation is not dangerous and answers NO Dangerous.
~~on the flowchart.~~
~~7. Determine if doses at or beyond the The Operator determines that site SAT/UNSAT site boundary are projected to exceed boundary doses will exceed the PAGs.~~
~~PAGs and answers YES on the flowchart.~~
~~8 Refer to Attachment3, Table 1 The Operator refers to the SAT/UNSAT HATCH specific Table 1.~~
NOTE: Operator may use the optional Attachment 5, PAR Worksheet to record the information.
(** Indicates critical step)
The Operator determines that the wind direction is 2S degrees and selects Table 1 Row labeled "NNE, >11 - 34".
The Operator determines that, under the PAR 3 column, the affected zones to be evacuated are A, BS, CS, DS, ES, D1O, E1O, and F1O.
The Operator provides a completed Attachment S, or equivalent information, to the ED.
Completes Section S of ENN Form by performing the following:
Checks Box for 'S.B' Enters affected zones to'S.B' line; A, BS, CS, DS, ES, D1O, E1O, and F10 Checks Box for 'S.D' 2009-302 Admin 7 Page 4 of7 S~'fllJNsA'f..*
(CllMMEN'.I'S SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT I UNSAT PROMPT:
IF the student asks about supplemental PARs inform them that they are not desired at this time.
PROMPT:
IF the operator addresses notifications, as the Shift Manager, INFORM the operator that another operator will make the State and Local notifications.
This is Time Critical. END TIME - START TIME IS :s 15 MINUTES.
NOTE:
The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
END TIME:
(
(
PERFO~CESTEP
~~9 Determine the wind* direction.~~
~~10 Determine the affected zones; I~~
~~11 Provide the information to the ED.~~
~~12 Completes Section S of ENN Form STANDARD The Operator determines that the wind direction is 2S degrees and selects Table 1 Row labeled "NNE, >11 - 34".~~
The Operator determines that, under the PAR 3 column, the affected zones to be evacuated are A, BS, CS, DS, ES, DlO, ElO, and FlO.
The Operator provides a completed Attachment S, or equivalent information, to the ED.
Completes Section S of ENN Form by performing the following:
Checks Box for 'S.B' Enters affected zones to'S.B' line; A, BS, CS, DS, ES, DlO, ElO, and FlO Checks Box for 'S.D' 2009-302 Admin 7 Page 4 of7 SATIUNSAT (COMMENTS)
SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT PROMPT:
IF the student asks about supplemental PARs inform them that they are not desired at this time.
PROMPT:
IF the operator addresses notifications, as the Shift Manager, INFORM the operator that another operator will make the State and Local notifications.
This is Time Critical. END TIME - START TIME IS :s 15 MINUTES.
NOTE: The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
END TIME:
(
(
Examiner Answer Key (Not a Handout)
~~1. ~DRn..L 2.~INITIAL~~
~~~ ACTUAL EVENT~~
~~MESSAGE #~~
~~~FOLLOW-UP NOTIFICATION: TI:ME ______ DATE_-.1_---1 ___ AUTIlENTICATION #_~~~
~~3. SITE: HATCHNUCLEARPLANT~~
~~4. EMERGENCY CLASSIFICATION~~
~ UNUSUAL EVENT
~ALERT Confirmation Phone #
CR or TSC - (912) 366-2000 ext. ___ _
EOF - (205) 992-6586 19 SITE AREA E:MERGENCY IQI GENERAL E:MERGENCY BASED ON EAL # _____ _
EALDESCRIPTION: _________________________ _
S. PROTECTIVE ACTION RECOMMENDATIONS:
~ NONE
~EVACUATE A, 85, C5, 05, E5, 010, E10, F10
~SIDaTER----------------------------------------------
~ Ad vise Remainder of EPZ to monitor local radiofTV stationsfI' one Alert Radios for additional information and CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE"WlTIr STATE PlANS AND POllCY.
~m~R----------------------------------------------
~~6. EMERGENCY RELEASE:~~
~
None
~Is Occurring
§ Has Occurred
~~7. RELEASE SIGNIFICANCE:~~
~~8. EVENT PROGNOSIS:~~
~~9. METEOROLOGICAL DATA:~~
~
Not applicable
~W:itbin normal operating limits
~Improving
~Stable Wind Direction from ~degrees No Rain
§ Above normal operating limits
§Degrading Wind Speed ~mph Stability Class Q.
Precipitation
~~10. ~DECLARATION ~TERMINATION Time ________ Date_-.1 ___ I __~~
II. AFFECTED UNIT(S):
[] I[] !till IQI Under evaluation
~~12. UNIT STATUS:~~
(Unaffected Urrit(.) Status Not Required for lnilia]
Notifications)
~ U 1 __ % Power Shutdown at Time _____ Date ---1 __
1 __
I§] U2 __
% Power Shutdown at Time Date _1 ___ 1 __
13.REMARKS: _______________________________________ _
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA_ NOT REQUIRED IF LINE 6 A IS SELECTED_
~~14. RELEASE CHARACTERIZATION:~~
TYPE: ItJ Elevated ~Mixed 19 Ground UNITS: ~Ci I§I Ci/secl9~cilsec MAGNITUDE:
Noble Gases:
9.7E+01 lodines:
1.2E+00 Particulates:
O.OE+OO Other: _____ _
FORM: ~ Airborne
~Liquid Start Time ______ Date _1 __
I __ Stop Time ____ Date _1 __
1 __
Start Time Date _1 __
I __ Stop Time Date __ 1 __
1 __
~~15. PROJECTION PARAMETERS:~~
~~Projection period: ___ -'Hours Estimated Release Duration 4.0 Hours Projection performed:~~
~~16. PROJECTED DOSE:~~
Time _____ Date _-.1_---1 __
DISTANCE Site boundary 2 Miles 5 Miles 10 Miles TEDE (mrem) 1.1 E+03 1.0 E+03 3.9 E+02 8.6 E+01 Accident Type: __
2 __
Adult Thyroid CDE (mrem) 2.0 E+03 6.7 E+03 3.4 E+03 9.1 E+02
~~17. APPROVED BY:~~
___________ Title ________
NOTIFIED RECEIVED By __________ _
BY: __________
(** Indicates critical step)
Pal!e 5 of7
(
Examiner Answer Key (Not a Handout)
~~1. ~DRILL 2.~1NTTIAL~~
~ ACTIJAL EVENT MESSAGE #
~FOLLOW-UP NOTIFICA TION: TIME ______ DATE_~
_ __.l ___ AlTIHENTICATION #_~
~~3. SITE' HATCHNUCLEARPLANT~~
~~4. EMERGENCY CLASSIFICATION~~
~
UNUSUAL EVENT
~ALERT Confumation Phone #
CR or TIC - (912) 366-2000 ext. ___ _
EOF - (205) 992-6586
§ SITE AREA EMERGENCY
§ GENERAL EMERGENCY BASED ON EAL #. _____
EAL DESCRIPTION: ________________________ _
~~5. PROTECTIVE ACTION RECOMMENDATIONS:~~
~ NONE
~EVACUATE A, 85, C5, 05, E5, 010, E10, F10
~SmaTER----------------------------------------------
~
Ad vise Remainder of EPZ to monitor local radio!TV stationsfTone Alert Radios for additional information and CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POllCY.
~m~~---------------------------------------------
~~6. EMERGENCY RELEASE:~~
~None
~IsOccurring
§HasOccurred
~~7. RELEASE SIGNIFICANCE:~~
~~8. EVENT PROGNOSIS:~~
~~9. METEOROLOGICAL DATA:~~
~
Not applicable
~W:itbin normal operating limits
~Improving
~Stable Wind Direction from ~degrees Precipitation No Rain
§.Above normal operating limits
§Degrading Wind Speed ~mph Stability Class Q.
~~10. ~DECLARATION ~TERMINATION Time ________ Date_~ ___ ' __~~
~~11. AFFECTED UNIT(S):~~
III jg]
!till IQI Under evaluation
~~12. UNIT STATUS:~~
(Unaffected Urrit(>> Starns Not Required for Initial Notificadons)
~ U 1 __ % Power ShuTdown at Time _____ Date --.1 __
1 __
I§ U2 __
% Power ShuTdown aT Time DaTe --.1 __
1 __
13.REMARKS: _______________________________________ __
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA_ NOT REQUIRED IF LINE 6 A IS SELECTED_
~~14. RELEASE CHARACTERIZATION:~~
TYPE: It) Elevated ~Mixed 19 Ground UNITS: ~Ci I§ Cifsecl9~cilsec MAGNITUDE:
Noble Gases:
9.7E+01 lodines:
1.2E+00 Particulates:
O.OE+OO Other: _____ _
FORM: ~Airborne
~Liquid
~~15. PROJECTION PARAMETERS:~~
Start Time _____ Date _1 ____ I __ Stop Time ____ Date _1 ___ 1 __
Start Time Date _f ____ I __ Stop Time Date _1 ___ 1 __
Projection period: ___ -'Hours Estimated Release Duration 4.0 Hours Projection performed:
Time _____ Date __ ' _ __.1 __
Accident Type: ___
2 __ _
~~16. PROJECTED DOSE:~~
~~DISTANCE Site boundary 2 Miles 5 Miles 10 Miles TEDE (mrem) 1.1 E+03 1.0 E+03 3.9 E+02 8.6 E+01~~
~~17. APPROVED BY:~~
____________ Title ________ __
NOTIFIED RECEIVED BY __________ _
BY: __________ _
To be com leled b
(** Indicates critical step)
Adult Thyroid CDE (mrem) 2.0 E+03 6.7 E+03 3.4 E+03 9.1 E+02 Page 5 of7
Candidate Handout Southern Nuclear Emergency Notification
~ACWALEVENT
~~MESSAGE #~~
~~!mFOLLOW-UP NOI1FICATION: TIME ____ DA1E __ '_-.l ___ AUIHENTICATION#_N'A~~
~~3. SITE: HATCHNUCLEARPLANT~~
~~4. EMERGENCY CLASSIFICATION~~
~ UNUSUAL EVENT Confirmation Phone #
CR or TSC - (912) 366*2000 ext. __
EOF -
205 992-6596 19 SITE AREA EMERGENCY 121 GENERAL EMERGENCY BASED ON EAL# _____ _
EAL DESCRIPTION: _____________________ _
~~5. PROTECTIVE ACTION RECOMMENDATIONS:~~
~ NONE
~EVACUA1E I9SHEL1ER 121 Ad vise Remainder ofEPZ to monitor local radiafIV stationsITone Alert Radios for additional information and CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE pLANS AND POllCY.
I§OTHER
~~6. EMERGENCY RELEASE:~~
~None
~Is Occurring 19 Has Occurred
~~7. RELEASE SIGNIFICANCE:~~
~~Ie!] Not applicable 1m Within normal operating limits 19 Above normal operating linUts IQI Under evaluation~~
~~8. EVENT PROGNOSIS:~~
~Improving
~Stable 19 Degrading
~~9. METEOROLOGICAL DATA:~~
Wind Direction from ~
degrees Wind Speed 5.0 mph Precipitation No Rain Stability Class.Q lO.~DECLARATION !mTERMINATION Time
____ Date_-.l __
~~11. AFFEC1ED UNIT(S):~~
II] jg]
1m
~~12. UNIT STATUS:~~
(Unaffected Unites) Status Not Required for Initial Notifications)
~ U1 __ % Power Shutdown at Time _____ Date _, __,_
I§I U2 __ % Power Shutdown at Time Date _, __,_
13.REMARKS: ____________________________________ _
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCV RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.
~~14. RELEASE CHARACTERIZATION:~~
TypE:~Elevated iilMixed 19 Ground UNITS:~Ci I§I Ci/secl9l1cilsec MAGNITUDE:
Noble Gases:
9.7E+01 lodines:
1.2E+00 Partbulates:
O.OE+OO Other: ____ _
FORM: ~ Airborne Start Time Date _1 __
I __ Stop Time Date _1 __
1 __
~ Liquid Start Time Date _f __
I __ Stop Time Date _1 __
1 __
~~15. PROJECTION PARAMETERS:~~
~~Projection performed:~~
~~16. PROJECTED DOSE:~~
Projection period: __
---'Hours Time _____ Date _1 __
Estimated Release Duration Accident Type: ----6.--
4.0 Hours DISTANCE Site boundary 2 Miles 5 Miles 10 Miles TEDE (mrem) 1.1 E+03 1.0 E+03 3.9 E+02 8.6 E+01 Adult Thvroid CDE (mrem) 2.0 E+03 6.7 E+03 3.4 E+03 9.1 E+02
~~17. APPROVED BY:~~
___________ Title ________ _
Time _____ Da1e_-' __ ' __
NOTIFIED RECEIVED BY: _________
BY: ____________
Time _____ Date_-' ___ L_
(To be com ieted by receiving organization)
Page 6 of?
(
(
Candidate Handout Southern Nuclear Emergency Notification
~ ACTUAL EVENT
~~MESSAGE #~~
~~1. ~DRn.,L 2.~INTI1AL~~
~~~FOLLOW-UP NOTIFICATION: TI:ME ____ DA1E_J_~ __ AlITHENTICATION # -l::l1i--~~
~~3. SI1E: HATCHNUCLEARPLANT~~
~~4. EMERGENCY CLASSIFICATION~~
~
UNUSUAL EVENT ffi/ALERT Confirmation Phone #
CR or TSC - (912) 366-2000 ext. ___ _
EOF -
205 992-6586
\\9 SI1E AREA E:MERGENCY IQI GENERAL E:MERGENCY BASED ON EAL # _____ _
EAL DESCRIPTION: ______________________ _
~~5. PROTECTIVE ACTION RECO:MMENDATIONS:~~
~NONE
~EVACUA1E-----------------------------
§S~L1ER ________________________________________ _
IQI Ad vise Remainder ofEPZ to monitor local radiolTV stationsfTone Alert Radios for additional information and CONSIDER THE USE OF KI
(:POTASS1UM lODIDE) 1N ACCORDANCE Wllli STATE PLANS AND POUCY.
~ro~R--------------------------------
~~6. EMERGENCY RELEASE:~~
~None
~
Is Occurring 19 Has Occurred
~~7. RELEASE SIGNIFICANCE:~~
~
Not applicable
~Within normal operating limits 19 Above normal operating l:im.its IQ] Under evaluation
~~8. EVENT PROGNOSIS:~~
~
Improving
~ Stable 19 Degrading
~~9. METEOROLOGICAL DATA:~~
Wind Direction from ~
degrees Wind Speed 5.0 mph Precipitation No Rain Stability Class
.Q.
~~10. ~~~
~~DECLARATION I§I TERMINATION~~
~~11. AFFEC1ED UNIT(S):~~
II] I[]
~
~~12. UNIT STATUS:~~
(Unaffected Unites) Status Not Required for Initial Notifications)
Time ________ Date_~ ___ ' __
~ U 1 ___ % Power Shutdown a1 Time _____ Da1e _l ___ l __
IfJ U2 ___ % Power Shu1down a1 Time Da1e _1 ___ 1 __
13.REMARKS: ______________________________________ _
FOLLO\\V-UPINFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.
~~14. RELEASE CHARACTERIZATION:~~
TYPE: leI Elevated ~Mixed jg Ground UNITS:~Ci I§I Ci/secl9~Cilsec MAGNITUDE:
Noble Gases:
9.7E+01 lodines:
1.2E+00 PartK;ulates:
O.OE+OO Other: ____ _
FORM: ~ Airborne
~LqUid
~~15. PROJECTION PARAMETERS:~~
Start Time _____ Date _1 __
I __ Stop Time ____ Date _1 __
1 __
Start Time Date _1 __
I __
Stop Time Date _1 __
1 __
Projection period: ___ -'Hours Estimated Release Duration 4.0 Hours Projection performed:
Time _____ Date __, __
Accident Type: __
2 __
~~16. PROJECTED DOSE:~~
~~DISTANCE Site boundary 2 Miles SMiles 10 Miles TEDE (mrem) 1.1 E+03 1.0 E+03 3.9 E+02 8.6 E+01 Adult Thyroid CDE (mrem) 2.0 E+03 6.7 E+03 3.4 E+03 9.1 E+02~~
~~17. APPROVED BY:~~
____________ Title ________ _
Time _____ Date_J __ ' __
NOTIFIED RECEIVED BY: __________
BY: ____________
Time _____ Date_J __ ' __
(To be com le1ed by receiving organiza1ion)
Page 6of7
"J 1:/
P
-..l a,
-..l fU1LfttilAttH...
... Ul'Iit: NT lOTA,tEFFECTNE Dtl$E EQUIVAJ.[NT.lrEDEt RAn:
AtO.25HClillrProi8ct.io..
10126109 09:04
\\P #Ml!!tJ:iata~-__ *--c-~-*-***--c~~'
I ~rl;.MetWS(rr¢'il: *.
WO(homl: 25~Sl;D;
,~,""~~~~:~.",,,~,.,.... ~....,.~~,~<..,~._;.,,:_~,,~~ *.. :.:. ""~~_,,~~,.;. L..,,,~.~:.~~..,,,.,.::~_._"~:,,,~"~ 'N~' __ ~' """""..1 ErdD~eQf15MinJIeAal:e.*
Co"1pt1llafDrt 1 0(.26109 09: 08 SIa-Iol Ffei;iltS.8:
1 0126109 08: 53 ErddAelea:te:
1012610909:08 1.1E402:...
5.tE +or*1.lE+Q\\!
1.. 1'£+01. ~5.aE+(r'I 5;C£.+OO
~~toe:.;~~~
1, (£+O'J~5.0t..,ro t,dt,01.,1.(E+Qb 1.(E*02-1P~4J~.
tre*og*~1:0Em 1;(E*04~ tOE*ill 1.tE*fil~*hOE4J.
l.tE*\\lF ME.a6 HE:*07*~ 1.0£<06 1
Site:
Title.:
Til\\tf:!!:
PlANT HA. TCH Unit: HT TOTAl EFFECTIVE DOSE EQUIVALENT JTEDEI RATE At 0.25 Hour Proiection
[lose Moret PI~OC;ted PkJme 5 Egmefll Cwetll Time:
1 0/"26..09 09: 05 Run Trne:
1 0/"26..09 09: 04 Ma"Il,~!Ertr.f' d MetData DJrrert Met WS (rtllh):5;Q \\I~D (Iroml: 25> SI: D Erd D.:teaf 15 Minute R.:te CampJl<JliJrr Sierl of Re~i3$e:
E rd ti Relea~e:
1 0126..09 09: 08 1 0126..09 08: 53 1 Ol26..o9 09: 08
.. Ma'lual E rtr,t! ct Monitol data OJrrert Relea&e Rate lOlrec):
9.EE +01 TolalCr NG: Ri'E+04 I: 1.1E+03 P: O.CE+OO Peal-:. "'a~es' Peoll<; TE DE (lTfan-'llt Dil (tolSS'v..'
Dis!: (ni\\::4 Pe~ THY toE Imrem""'r}
Diltrol SSW Di:;:\\: r,nik:!t}:
IE D EJ'EDE at PeQk T EDE:.
."~ ** "~_~~,,.~~o
~~~.,_~~
De<reRaI;e (lTferr~ih'1 1[£+02+
5,(£+01 *1(£+02
~~1. [£... 01~~
~~5.0E+01 5.[£+00 *1.0£+01 1.[(+00*5.0£.. 00 1.0E-01 *1.IE+OCt 1.(£,02* t.O£-Ol 1,1E*aJ-1.0E{l2 HE*04. 1.0E-03 HE*IE. 1.0E-I]4-U,E*(6 *1.0£-05 U,E*07 -1.0E-08 2.~+O2 1.0~~
~~3.3::+02 1.1 HE+OO~~
~j
..,:.. :-.~~-,........-~c......i.,~_..-;.._-l-":":.'.:~":.1 C.onCifm.... ~.. ~l
(
(
UNIT 1 &2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
2.
3.
4.
4.
5.
6.
7.
8.
The Prompt Offsite Dose Assessment has just been completed. The ENN form has been printed and is available. The MIDAS screen is available.
The Dose Assessment Staff is not available yet.
The Shift Manager has declared a General Emergency due to the release.
The release started 30 minutes ago and is ongoing.
The Shift Manager is performing the functions of the Emergency Director.
SPDS is not available.
No adverse weather conditions exist.
No manmade threats, i.e. terrorist threats, exist.
No known offsite conditions for evacuation exist.
INITIATING CUES:
Complete Section 5, "Protective Action Recommendations" of the ENN form for the EPZ only, IA W NMP-EP-109. This is Time Critical.
(
UNIT 1 &2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
~~The Prompt Offsite Dose Assessment has just been completed. The ENN form has been printed and is available. The MIDAS screen is available.~~
2.
~~The Dose Assessment Staff is not available yet.~~
3.
~~The Shift Manager has declared a General Emergency due to the release.~~
4.
~~The release started 30 minutes ago and is ongoing.~~
4.
~~The Shift Manager is performing the functions of the Emergency Director.~~
5.
~~SPDS is not available.~~
6.
~~No adverse weather conditions exist.~~
7.
~~No manmade threats, i.e. terrorist threats, exist.~~
8.
No known offsite conditions for evacuation exist.
INITIATING CUES:
Complete Section 5, "Protective Action Recommendations" of the ENN form for the EPZ only, IA W NMP-EP-109. This is Time Critical.
(
c Candidate Handout Southern Nuclear Emergency Notification 1m ACTUAL EVEN!'
~~MESSAGE #~~
~~1. ~DRD.-L 2.~INlTIAL~~
~~~FOLLOW-UP NOTIFICATION: 1'Th1E _____ DATE_-'_--' ___ AimmNTICATION#_~_~~
~~3. SITE: HATCH NVCLEARPLANT~~
~~4. EMERGENCY CLASSIFICATION~~
~ UNUSUAL EVEN!'
~ALERT Confirmation Phone #-
CR or TSC - (912) 366-2000 ext. __
EOF -
205.992-6586 19 SITE AREA EMERGENCY
[§I GENERAL EMERGENCY BASED ON EAL # _____ _
EAL DESCRIPTION: _____________________ _
~~5. PROTECTIVE ACTION RECOMMENDATIONS:~~
~ NONE
~EVACUATE i9SHELTER
~ Ad vise Remainder ofEPZ to monitor local radio/IV stationsITone Alert Radios for additional information and CONSIDER TKE USE! OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POllCY.
l§arHER
~~6. EMERGENCY RELEASE:~~
~~~None Illi Is Occurring 19 Has Occurred~~
~~7. RELEASE SIGNIFICANCE:~~
~
Nat applicable
~
Within normal operating limits lSI Above normal operating limits
~
Under evaillation
~~8. EVENT PROGNOSIS:~~
~Improving
~Stable 19 Degrading
~~9. METEOROLOGICAL DATA:~~
~~Wind Direction from ~degrees Wind Speed 5.0 mph Precipitation No Rain Stability Class Q~~
~~10. ~DECLARATION imTERMINATION~~
~~11. AFFECTED UNIT(S):~~
IIJ ([I
~
~~12. UNIT STATUS:~~
(Unaffected Unites) StattJs Not Required for Initial Notifications)
Tune _______ Date_--' ___ ' __
~ U 1 __ % Power Shutdown at Time _____ Date _, __,_
~ U2 __ % Power Shutdown at Time Date _, __,_
13.REMARKS: ____________________________________ __
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.
~~14. RELEASE CHARACTERIZATION:~~
TVPE:!elElevated ~Mixed 19 Ground UNITS:~Ci I§I cilseclfl~cilsec MAGNITUDE:
Noble Gases:
9.7E+01 lodines:
1.2E+00 Partbulates:
O.OE+OO Other: ____ _
FORM: ~ Airborne Start Time Date __ 1 __
I __ Stop Time Date __ ' __
I __
iii Liquid Start Time Date __ ' __
' __ Stop Time Date __, __
~~15. PROJECTION PARAMETERS:~~
Projection period: ___ --'Hours 4.0 Hours Projection performed:
Time _____ Date _--'_---' __
Estimated Release Duration Accident Type: ----L--
~~16. PROJECTED DOSE:~~
~~DISTANCE Site boundary 2 Miles 5 Miles 10 Miles TEDE (mrem) 1.1 E+03 1.0 E+03 3.9 E+02 8.6 E+01 Adult Thvroid CDE (mrem) 2.0 E+03 6.7 E+03 3.4 E+03 9.1 E+02~~
~~17. APPROVED BY:~~
___________ Title ________ _
Time ___ Date_-' __ C_
NOTIFIED RECEIVED BY: _________
BY: ____________
Time _____ Date_-'_---' __
(To be com leled by receiving organization)
Pag:e 6 of7
(
Candidate Handout Southern Nuclear Emergency Notification
~~1. 31DRlLL~~
~~~ ACTUAL EVENT~~
~~MESSAGE #~~
~~2. ~lNITIAL~~
~~!mFOLLOW-UP NOTIFICATION: Tll¥ffi _____ DATE_-.l_-.! __ Aim-rnNTICATION#_~_~~
~~3. SITE: HATCHNUCLEARPLANT~~
~~4. EMERGENCY CLASSIFICATION 31 UNUSUAL EVENT I!!IALERT Confirmation Phone #~~
CR or TSC - (912) 366-2000 ext. ___ _
EOF -
205 992-6586 19 SITE AREA E:MERGENCY I£] GENERAL EIvffiRGENCY BASED ON EAL # _____
EALDESCRIPTION: __________________________________________ _
~~5. PROTECTIVE ACTION RECO:MMENDATIONS:~~
0 NONE
~EVACUATE ____
~S~LTER----------*-----------------------
IQI Ad vise Remainder of EPZ to monitor local radiofIV stationsfTone Alert Radios for additional information and CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND PODCY.
~m~R--------------------------------
~~6. EMERGENCY RELEASE:~~
~~31 None (illIs Occurring 19 Has Occurred~~
~~7. RELEASE SIGNIFICANCE:~~
~Not applicable
~Within normal operating limits 19 Above normal operating limits IQI Under evaluation
~~8. EVENT PROGNOSIS:~~
~ Improving
~ Stable 19 Degrading
~~9. r-JIETEOROLOGICAL DATA:~~
Wind Direction from ~degrees Wind Speed 5.0 mph Precipitation 10.l;JDECLARATION
!mTERMINATION
~~11. AFFECTED UNIT(S):~~
ill jg]
~
No Rain Stability Class
.Q.
Time ________ Date _-.! ___, __
~~12. UNIT STATUS:~~
(Unaffected Unites) Status Not Required for Initial Notifications)
@I U 1 ___ % Power Shutdown at Time _____ Date _1 ___ ' __
lfJ U2 ___ % Power Shutdown at Time _____ Date _1 ___ 1 __
13.REMARKS: ___________________________________________________________________________ _
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.
~~14. RELEASE CHARACTERIZATION:~~
TYPE: (eJ Elevated §Mixed 19 Ground UNITS: ~Ci I§I ci/secl9~cifsec MAGNITUDE:
Noble Gases:
9.7E+01 lodines:
1.2E+00 Partculates:
O.OE+OO Other: ____ __
FORM: ~ Airborne Start Time Date _1 __
' __ Stop Time Date _1 ___ ' __
~ Lquid Start Time Date _1 __
I __ Stop Time Date _' ___ 1 __
~~15. PROJECTION PARAMETERS:~~
~~Projection performed:~~
~~16. PROJECTED DOSE:~~
Projection period: ___ -'Hours Estimated Release Duration 4.0 Hours Time _____ Date __ 1 __
DISTANCE Site boundary 2 Miles SMiles 10 Miles TEDE (mrem) 1.1 E+03 1.0 E+03 3.9 E+02 8.6 E+01 AccidelIt Type: ___
2 __
Adult Thyroid CDE (mrem) 2.0 E+03 6.7 E+03 3.4 E+03 9.1 E+02
~~17. APPROVED BY:~~
____________ Title ________ _
NOTIFIED RECEIVED BY: ___________ _
BY: ____________
Time _____ Date_-.l __ I __
(To be com ieted by receiving organization)
PaQ:e 60f7
~
n i
-..l a,
-..l PlANT HA reH Unit: HT TOTAl EFFECTIVE DOSE EQUIVALENT tTEDEI RATE At 0.25 Hour Proiection Mero: A ose Proi;;lc!:lon Moclet PI~ected Pume S egmet'l!
Cl,ITetl! Time:
1 0126..09 09: 05 Run Trne:
1 0126JD9 09: 04 MalualErtrp cH1etDafa.........
D.mert Met I*...,IS (l1llh}:$.O \\,yD (hom!: 25" 51: D Erd D<teof15 Mirnl:e R.al:e 1 0126..09 09: 08 1 0126>D9 08: 53 1 0126..09 09: 08 MalualEmp d Morioo! data Qllrert Rejea~e Rate (a/sec):
9JE l-fJ1 TotalCr NG: B.i'E+D4 I: 11E+03 P: 0.0:+00 PecA<. yakJes:'
fled<. 1E D E (nre;m.'l..-l:
Dil (to} SSW Dis!: (Ries):
Pea., THY CDE jmreMlhr}
DilftaJ SSW Dis( [Ilies):
iE 0 EJEDE at Peak. T fOE:
Dose R.al:e
[mm~11-r1 1[f... 1l2~
5.CE+01 *1.[£... 02 1.[E-+01 *5.0E+01 Mal 5:(£+OJ *1.0E.. 01 r~"
1,(£,+00.. 5.0[+00 1.0E-01 -1.CE+OD 1.0E*02 -1.0E-fJl UE*(JJ -1.0E-02 r~ 1CE*(14 -1.0E{)3 1.(£-(6 -1.0£-1]4-1.CE.1)3 - l.OE-05 1.(£-07*1.IJE-06 2.Et+02 1.0 3.3::+02 1.1 10E+DO

ML093430147

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ML093430147

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3.0 REFERENCES

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