ML12342A152

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Initial Exam 2012-301 Final Administrative JPMs
ML12342A152
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 12/06/2012
From:
NRC/RGN-II
To:
Southern Co
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FINAL Southern Nuclear E. I, Hatch Nuclear Plant Operations Training JPM ADMIN 1 - SRO ONLY TITLE VERIFY FUEL MOVEMENT SHEET AUTHOR MEDIA NUMBER TIME Anthony Ball 2012-301 ADMIN-1 30 Minutes RECOMMENDED BY APPROVED BY DATE N/R C. M. EDMUND 06107/2012 SOU- TH ERIl COMPANY

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2012-301 ADMIN-1 -

Rev. Date Authors Supvs Reason for Revision No. Iials initials 00 03/17/09 Initial development FNF CME 01 06/07/12 Revision for use on 2012-301 NRC Exam. After NRC ARB CME Exam. Media Number will be changed to LR-JP-45.33A.

2012-301 ADMIN-1 Page 1 of 6 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: VERIFY FUEL MOVEMENT SHEET JPM NUMBER: 2012-301 ADMIN-1 TASK STANDARD: The task will be complete when the operator has identified all in-core placement errors of all components listed on Page 1 of the attached Fuel Movement Sheet.

TASK NUMBER: 045.033 OBJECTIVE NUMBER: 045.033.O PLANT HATCH JTA IMPORTANCE RATING:

RO Not Available SRO Not Available K/A CATALOG NUMBER: G2.1.35 K/A CATALOG JTA IMPORTANCE RATING:

RO 2.2 SRO 3.9 OPERATOR APPLICABILITY: Senior Reactor Operator GENERAL

REFERENCES:

Refuel Floor 34FH-OPS-OOl-0 (current version) 42FH-ERP-014-0 (current version)

REQUIRED MATERIALS: Refuel Floor Fuel Movement Sheets 34FH-OPS-001-0 (current version) 42FH-ERP-014-0 (current version)

APPROXIMATE COMPLETION TIME: 30 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in a refueling outage.
2. You are the oncoming Refuel Floor SRO.
3. The off-going Refuel Floor SRO asks you to verify Page 1 of the attached Fuel Movement Sheet.
4. The fuel movement sheet, Core Map and pictures of the core cells are available.

INITIATING CUES:

Verify the in-core placement of all components listed on Page 1 of the attached Fuel Movement Sheet.

2012-301 ADM1N-1 Page 3 of 6 I STEP PERFORMANCE STEP STANDARD I (COMMENTS) 1 For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Li Human performance tools, safety, PPE met (1), AND Li Mark the JPM as a PASS Li For initial trg all steps completed correctly OR PASS Li For continuing trg, critical steps (if used) completed correctly FAIL Li Above standards not met Li Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.

START TIME:________

PROMPT: Hand the operator the fuel movement sheet, Core Map and pictures of the core cells.

PROMPT: IF the operator has problems reading the bundle serial numbers, THEN provide the serial numbers to the operator.

PROMPT: IF the operator asks about Spent Fuel Pool verification, TITEN tell the operator he is only responsible for in-core verifications.

1. Obtains the correct procedures. Obtains and reviews 42FH-ERP-014-0, Fuel Movement and 34FH-OPS-00 1-0, Fuel Movement Operation.
  • Indicates critical step)

2012-301 ADMIN-1 Page 4 of 6 I STEP I I SAT/UNSAT PERFORMANCE STEP

  1. 1 STANDARD I (COMMENTS)
2. Verify correct loading of Control Cell Operator determines Control Cell 38-37. 38-37 bundles are the correct bundles and in the correct orientation:
  • JLV675
  • JLV682 o JLK8O4
  • JLK817
    • 3 Determine INCORRECT loading of Operator determines Control Cell Control Cell 14-37. 14-37 bundles are the correct bundles but in the INCORRECT orientation:

. JLV678 o JLV67O NOTE: Bundles JLV678 and JLV67O are 180° out.

4. Verify correct loading of Control Cell Operator determines Control Cell 14-37. 14-37 bundles are the correct bundles and in the correct orientation:
  • JLK8O5
  • JLK812
  • 5 Determine INCORRECT loading of Operator determines Control Cell Control Cell 38-17. 38-17 bundle is the INCORRECT bundle but in the correct orientation:
  • JLV668 NOTE: Wrong bundle loaded. The correct bundle is JLV698

(*

  • Indicates critical step)

2012-301 ADMIN-1 Page 5 of 6 STEP SAT/UNSAT PERFORMANCE STEP STANDARD I (COMMENTS)

6. Verify correct loading of Control Cell Operator determines Control Cell 38-17. 14-37 bundles are the correct bundles and in the correct orientation:

. JLV674

  • JLK8O7

. JLK82O

    • 7* Determine INCORRECT loading of Operator determines Control Cell Control Cell 14-17. 14-17 Double Blade Guide is in the INCORRECT orientation.

END TIME:________

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

After JPM step #7 is complete.

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

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR PICK UP the Initiating Cue sheet.

(** Indicates critical step)

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in a refueling outage.
2. You are the oncoming Refuel Floor SRO.
3. The off-going Refuel Floor SRO asks you to verify Page 1 of the attached Fuel Movement Sheet.
4. The fuel movement sheet, Core Map and pictures of the core cells are available.

INITIATING CUES:

Verify the in-core placement of all components listed on Page 1 of the attached Fuel Movement Sheet.

SNC PLANT E. I. HATCH j Pg 46 of 59 DOCUMENT TITLE: DOCUMENT NUMBER: Version No:

FUEL MOVEMENT OPERATION 34FH-OPS-001-0 24.0 ATTACHMENT I Att. Pg.

TITLE: UNIT 2 CORE MAP 1 of 1 NORTH 4 HATCH UNIT 2 Northeast Southeast Quadrant 24 Quadrant 53 -

51 45 r -

43.

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37 29 35 33 31 --z 29 27 25 23 21

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I I I I I I I I I I . . I i I (N) 02 04 06 01 10 12 14 16 18 20 22 26 26 30 32 34 36 38 40 32 44 46 48 50 52 24 Northwest LI IRM Southwest Quadrant 0 SRM Quadrant CENTER IS AT (24,29)

MGR-0009 Ver. 5

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H WEST CONTROL CELL 38-37

EAST N S 0 0 R U 1

T H H WEST CONTROL CELL 14-37

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EAST N S 0 0 R U T T H H WEST CONTROL CELL 14-17

SOUTHERN NUCLEAR PLANT E.l. HATCH PAGE 1 OF FORM TITLE:

FUEL MOVEMENT SHEETS TYPE OF FUEL MOVEMENT:

(check the type of fuel sheets)

Core Off-Load: Partial Offload:

Core Reload: x Upfront Shuffle:

Shuffle: Backend Shuffle:

General Moves: Other (Specify):

Special Activity:

Brief description of moves: Control Cells 38-37. 14-37 and 38-37 to be loaded with fuel and blade guides removed. Control Cell 14-17 to have blade guide installed for insertion of control rod.

Verify the following for all core reload move sheets:

The first 4 steps in the movement sequence will place bundles around the SRM which will first be in the fueled region.

N/A /

Date N/A /

Date Verify the following for all core shuffle move sheets:

At least 2 irradiated fuel assemblies will remain around each SRM unless approved by the Reactor Engineering Supervisor or designated alternate.

Samie-l 7o,yzo,n / 06718712 Date

/06/18712 Date Prepared by: $e+i, WWcn I 06/18712 Reactor Engineering Date Verified bv,. MWcttoi / 06/18712 Reactor Engineering Date Verified by: KeetJi-, FciM,cm, / 06718/12 Reactor Engineering Date Approved by:. wcUc+n, TefFer /06718/12 Reactor Engineering Supervisor Date Additional verification IF required by the Reactor Engineering Supervisor for certain evolutions or marked N/A, initialed and dated by the RE Supervisor.

The Approved space on the actual sheets is to be signed by the Reactor Engineering Supervisor or designated alternate.

Spent Fuel Pool Inventory Database Updated By: Ke4etFcCrovv I 06/18/12 Date Verified By: 1VW.ni TefIe-vt / 06/18712 Date ENG-0190 Rev. 7.1 G16.40 42FH-ERP-O1 4-OS

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SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 2 OF FORM TITLE:

FUEL MOVEMENT SHEETS Movements PerformedNerified By:

John Hart IT1-E /6/18/12 / /

Print nit Date Print Init Date Alan Carter I AC I 6/18/12 I I Print Init Date Print Init Date I / / /

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FINAL Southern Nuclear E. I. Hatch Nuclear Plan t Operations Training JPM ADMIN 2 ALL TITLE CORRECT RWL INDICATORS FOR HIGH DRY WELL TEMPERATURES AUTHOR MEDIA NUMBER ANTHONY BALL TIME 2012-301 ADMIN-2 11.0 Minutes RECOMMENDED BY APPROVED BY N/R DATE C. M. EDMUND 06/07/2012 SOUTH ERN COMPANY

SOUThERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2012-301 ADMIN-2 Rev. No. Date 1 i.

Reason for Revision Authors Initials Supvs Imtials 00 06/07/12 Modified from LR-JP-25 101 for use on 2012-301 ARB CME NRC Exam.

2012-301 ADMIN-2 Page 1 of 8 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: CORRECT RWL INDICATORS FOR HIGH DRYWELL TEMPERATURES JPM NUMBER: 2012-301 ADMIN-2 TASK STANDARD: The task shall be completed when the operator has determined the corrected RWL for the specified instrumentation per 34AB-B21 -002.

TASK NUMBER: 201.099 OBJECTIVE NUMBER: 201 .099.B PLANT HATCH JTA IMPORTANCE RATING:

RO 4.57 SRO 3.83 STA 4.00 K/A CATALOG NUMBER: G2.1.35 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.90 SRO 4.20 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

Shift Technical Advisor (STA)

GENERAL

REFERENCES:

Unit 1 Unit 2 34AB-B21 -002-1 34AB-B2 1-002-2 (current version) (current version)

REQUIRED MATERIALS: Unit 1 Unit 2 34AB-B2 1-002-1 34AB-B2 1-002-2 (current version) (current version)

APPROXIMATE COMPLETION TIME: 11.0 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The Reactor has scrammed and the board operator has reported the following UNCOMPENSATED Reactor Water Levels:

1B21-R604A and 1B21-R623A (Wide Range) is -132 inches.

1B21-R604B and 1B21-R623B (Wide Range) is -134 inches.

1B21-R623A (Fuel Zone) is -170 inches

2. NO erratic behavior for the specified instruments has been observed.

INITIATING CUES:

Determine which of these RWL indications are valid and report the corrected RWL for EACH valid RWL instrument.

2012-301 ADM1N-2 Page 3 of 8 STEP PERFORMANCE STEP STANDARD I (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND I Mark the JPM as a PASS I For initial trg all steps completed correctly OR PASS L For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met i Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.

START TIME:________

1. Operator identifies the procedure Operator has identified the correct needed to perform the task. procedure as 34AB-B21-002-1.

NOTE: If the operator (STA) indicates that SPDS would be checked, give the operator Supplement 1.

PROMPT: IF the operator addresses Drywell temperature indications, INDICATE for the operator that temperature is greater than 150°F (Use Supplement 1 if SPDS is addressed).

2. Determine if RWL corrections are Using SPDS (or Drywell temp required. indications) the operator DETERMINES:

Drywell temperature is greater than 150°F.

RWL corrections ARE required.

3. Review Caution 1 and Caution 2 on The operator has REVIEWED Attachment 1 of 34AB-B21-002-1. Caution 1 and Caution 2 on Attachment 1 of 34AB-B21-002-1.

(** Indicates critical step)

2012-301 ADMIN-2 Page 4 of 8 STEP PERFORMANCE STEP STANDARD I 1

4. Confirm there is no indication of The operator has VERIFIED, by erratic instrument behavior, observation or by addressing the panel operator, that the following RWL instruments show NO erratic instrument behavior:

1B21-R604A 1B21-R604B 1B21-R623A (Wide Range) 1B21-R623B (Wide Range) 1B21-R623A (Fuel Zone)

PROMPT: WhEN the operator indicates use of the Diagnostic screen of SPDS, GIVE the operator Supplement 2.

5. Determine highest temperature for At SPDS panel, the operator has RTD Group 1 and 2 (Maximum Run DETERMINED the following Temperature). Maximum Run Temperatures:

RTD Group 1 - 260°F RTD Group 2 257°F PROMPT: IF the operator addresses temperature indications on Panels P654 and P657; indications can be SIMULATED using the values from Supplement 2.

    • 6. Determine if the RWL instrument may The operator has DETERMINED be used by comparing the Minimum the following RWL instruments Indicated Level for the associated are VALID:

Maximum Run Temperature.

1B21-R623A (Fuel Zone)

7. Determine if the RWL instrument may The operator has DETERMINED be used by comparing the Minimum the following RWL instruments Indicated Level for the associated are INVALID:

Maximum Run Temperature.

1B21-R604A 1B21-R604B 1B21-R623A (Wide Range) 1B21-R623B (Wide Range)

(** Indicates critical step)

2012-301 ADMIN-2 Page 5 of 8 I STEP PERFORMANCE STEP STANDARD I SAT/UNSAT (COMMENTS)

    • 8. Determine corrected Fuel Zone Level Using Attachment 3 of (1 B21-R623A). 34AB-B2l -002-1, the operator has DETERMINED Corrected Level for 1B21-R623A (fuel zone) is -137 inches (accept +/-1 inch).

END TIME:________

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

After JPM step #8 is complete.

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

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR PICK UP the Initiating Cue sheet.

(** Indicates critical step)

Page 6 of 8 UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The Reactor has scrammed and the board operator has reported the following UNCOMPENSATED Reactor Water Levels:

1B21-R604A and 1B21-R623A (Wide Range) is -132 inches.

1B21-R604B and 1B21-R623B (Wide Range) is -134 inches.

1B21-R623A (Fuel Zone) is -170 inches

2. NO erratic behavior for the specified instruments has been observed.

INITIATING CUES:

Determine which of these RWL indications are valid and report the corrected RWL for EACH valid RWL instrument.

MODE: RUN VENT HNPiI I jiCi/cc POWER 125 I I HNP2 I I jiCilcc 100*  % STACK I I jtCilcc 75.

SRM ISOLATION 5O 25 I I 10UT1 IN PRIMARY 0* cPs 2A 2B 0i 2C2D2E r

N J!J_

SEC 180 SCRAM lol H2%

SECONDARY lol ADS 02% 163 HNP1I I PSIG 90 LLSL 270 iriEILi!iI1 0

i H2% IN HNP2I I OF SRV I1ll [oII1F1II PSIG 02%

133 °F 0

SUPPLEMENT 1

DRYWELL TEMPERATURE DIAGNOSTIC VOLUMETRIC AVG. TEMP 12201 DEG. F NOO1A NOO1K N002 N003 N004 N007 NOO1J NOO1B NOO1M NOO1L N008 N005 00 C

00 SUPPLEMENT 2

FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM ADMIN 3- RO ONLY TITLE Determine if plant conditions allow a Quick Restart of a Recirculation Pump.

AUTHOR MEDIA NUMBER TIME Anthony Ball 2012-301 ADM1N-3 15 Minutes RECOMMENDED BY APPROVED BY DATE NR C. M. EDMUND 06/07/2012 SOUTH ERN COMPANY

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2012-301 ADMIN-3 Rev. No. Date Reason for Revision Authors Supvs

.1 I. Initials Initials 00 06/07/12 Modified from LR-JP-25050 & will become new ARB CME LR-JP-25053 after NRC Exam.

2012-301 ADMIN-3 Page 2 of 10 UNIT1 (X) UNIT2 ()

TASK TITLE: Determine if plant conditions allow a Quick Restart of a Recirculation Pump.

JPM NUMBER: 2012-301 ADM1N-3 TASK STANDARD: The task shall be complete when it has been determined that the requirements of 34S0-B3 1-001-1, Reactor Recirculation System have been met to start a Reactor Recirculation pump.

TASK NUMBER: 004.002 OBJECTIVE NUMBER: 004.002.A K/A CATALOG NUMBER: Generic 2.1.20/Generic 2.1.32 K/A CATALOG JTA IMPORTANCE RATING:

RO 4.3/3.4 SRO 4.2/3.8 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)/Senior Reactor Operator (SRO)

GENERAL

REFERENCES:

Unit 1 34S0-B31-001-1 (Current Version)

REQUIRED MATERIALS: Unit 1 34S0-B31-001-1 (Current Version)

APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: N/A, Used for NRC Admin JPM (classroom setting)

2012-301 ADMIN-3 Page 3 of 10 EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 10 minutes ago, the Unit 1 reactor scrammed from 100% power.
2. Both Reactor Recirculation pumps tripped during the scram transient.
3. Reactor water level went as low as 10 inches and has been restored to

+37 inches using Reactor Feedwater Pumps.

4. HPCI and RCIC were not required during the transient and have remained in standby.
5. RWCU is in service.
6. The Shift Supervisor has given direction to perform a Quick Restart of the 1B Reactor Recirculation pump to prevent thermal stratification.
7. An operator has entered 34S0-B3 1-001-1, Reactor Recirculation System and completed steps 7.1.4.2.1 through 7.1.4.2.5 (Recirc Pump B Quick Re-start).
8. Data collection began 4 minutes ago and the operator has completed gathering plant data for use with step 7.1.4.2.6 of 34S0-B 31-001-1.

INITIATING CUES:

Determine if plant conditions meet the procedural requirements for Quick starting the 1B Reactor Recirculation pump per step 7.1.4.2.6 of 34S0-B3 1-001-1, Reactor Recirculation System.

2012-301 ADMIN-3 Page4of 10 I STEP f PERFORMANCE STEP STANDARD I (COMrvIENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Li Human performance tools, safety, PPE met(1), AND Li Mark the JPM as a PASS Li For initial trg all steps completed correctly OR PASS Li For continuing trg, critical steps (if used) completed correctly FAIL Li Above standards not met Li Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.

START TIME:________

NOTE: 34S0-B31-OO1-1, Attachment 6 serves as an answer key for this JPM. It is NOT to be provided to the student.

NOTE: At this time, provide the operator with Attachment 1 (Plant Data page) and a copy of 34S0-B31-001-l.

PROMPT: IF addressed by the operator, INFORM the operator that the ASD is NOT in local control.

1. Operator refers to step 7.1.4.2.6 and is Step 7.1.4.2.6 directed to Attachment 6 of 34SO-B3 1-001-1.
2. Operator selects B Recirc Pump. Places a check mark next to B Recirc. Att. 6 Step 1.0
3. The operator enters the current time. Records current time.

Att. 6 Step 2.0

    • 4 The operator determines RPV Tsat = 521° F (+/-2° F) saturation temperature. Att. 6 Step 2.0 (A)

(** Indicates critical step)

2012-301 ADMIN-3 Page 5 of 10 STEP PERFORMANCE STEP STANDARD I (1) 1 NOTE: Data is NOT required to be filled in for the 1A Recirc Pump in the following step.

5. The Operator enters suction Recirc 1A: 470° F temperature for Recirculation Pumps. Recirc 1 B: 4750 F (Att. 6 Step 2.0 (A) & (B))
6. The operator enters the bottom head Bottom head temperature: 365° F temperature. (Att. 6 Step 2.0 (D))
7. The operator calculates the At between At = (5210 F 475° F) = 46° F the 1B loop and the RPV. (+/-2° F) (Att. 6 Step 1.2.1)
    • 8 The operator determines the At At of 46° F (+/-2° F) is < 50° F between the 1B loop and the RPV (Att. 6 Step 3.1)

IS acceptable.

NOTE: The student should NOT use step 4.2 to perform the following confirmation of plant conditions due to the NOTE that precedes step 4.0 (RWCU is in service). If the operator does refer to step 4.2, the check will NOT be acceptable due to Feedwater temperature < 300° F.

    • 9* The operator calculates the At between At = (52 1° F - 379° F) = 142° F bottom head and steam dome. (+/-2° F) (Att. 6 Step 4.1)
    • 1O. The operator determines that the At At of 142° F (+/-2° F) is < 145° F between bottom head and steam dome (Att. 6 Step 4.1)

IS acceptable.

11. The operator reports to the Shift Plant conditions ARE acceptable Supervisor, for starting the lB Reactor Recirculation pump.

NOTE: Step 4.2 is NOT required to be performed (it is an alternate method). If the student chooses to perform step 4.2, the conditions will NOT allow the start of the Recirc Pump (FW temp <300 F). The following information is expected to be determined by the student (see Attachment for details):

(a) is met (>40% of rated flow prior to the RPT).

(b) is met (HPCI and RCIC have not injected since the RPT)

(c) is NOT met (FW temp is not >300 F since the RPT) is met (<30 minutes since trip) and start time (calculated time to start is required to be 30 minutes from the RPT time)

(** Indicates critical step)

2012-301 ADMIN-3 Page 6 of 10 I STEP PERFORMANCE STEP STANDARD I (COMMENTS) 1 PROMPT: IF addressed by the operator, as the STA, INFORM the operator that power/flow map conditions are acceptable for starting the Recirc Pump.

PROMPT: IF addressed by the operator, as the Shift Supervisor, INFORM the operator that another operator will verify his calculations.

END HME:________

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

After JPM step #11 is complete.

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

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR PICK UP the Initiating Cue sheet.

  • Indicates critical step)

31L- rLd-1 I L. I. I1IIL-II 103 Ui LUO DOCUMENT TITLE: DOCUMENT NUMBER: VERSION No:

REACTOR RECIRCULATION SYSTEM 34SO-B31-OO1-1 41.1 ATIACHMENT Attachment Page TITLE: RECIRC PUMP QUICK RE-START LIMIT CHECKS 2 of 4 FIOU9 NOTE: This attachment may be performed in Modes 1, 2, AND 3.

/

1 .0 Recirc Loop and RPV Limit Checks: EVALUATOR USE ONLY (KEY)

Pre-startup checks for (1): A recirc DO NOT give to candidate B recirc 2.0 Record the following data: Time CURRENT TIME APPLICANTS INITIALS Parameter Location Value SPDS MISC RPV Heatup/

(A) RPV Saturation Temp. (A)

Cooldown OR Steam Tables 521°F (+/-2°F) 1B31-R650 OR Equivalent, (B) A Recirc Suction Temp average of process computer (B) points B034, B035 470°F 1B31-R650 QR Equivalent, (C) B Recirc Suction Temp average of process computer (C) points B036, B037 475°F

  • Vessel Bottom Head Drain *1B21R606 Pt 3 OR (D) (D) 1G31-N601 Pt 5 *379°F The Bottom Head Drain temperature (D) may still be used even if RWCU is NOT in service.

(See Limitation 5.2.14). IF Bottom Head Drain temperature is NOT available, (i.e., inoperable),

THEN use the alternate method of confirming the Bottom Head to Coolant AT in step 4.0.

Critical 3.0 FOR the Recirc loop to be started, confirm the AT between the reactor coolant temperature in the ioop AND the RPV coolant temperature is 50°F by performing step3.1 Q 3.2 below:

3.1 if both recirc loops are idle; Loop A AT = 1(A) (B) I =

- (acceptable 50°F) NA OR Loop B AT = 1(A) (C) I =

- 46°F (+/-2°F) (acceptable 50°F) INITIALS

.c!i e......................c,.....................

3.2 IF only one recirc loop is idle, THEN loop AT = 1(B) (C) = - (acceptable 50°F) NA OPS-1321 Ver. N/A Gi 6.030

,rr,T)

SNC PLANT E. L HATCH I Pg 184 of 208 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION No:

REACTOR RECIRCULATION SYSTEM 34S0-B31-001-1 41.1 ATtACHMENT Attachment Page LE: RECIRC PUMP QUICK RE-START LIMIT CHECKS 4 of 4 jf a direct indication is NOT available for Vessel Bottom Head Drain temp (D),

NOTE: THEN within 30 minutes of an RPT, the bottom head to coolant AT ( 145°F) may be confirmed per the alternate method in step 4.2.

Critical 4.0 Confirm the AT between the bottom head coolant temperature AND the reactor pressure vessel (RPV) coolant temperature is 145°F by performing step 4.1 Q 4.2 below:

4.1 AT = (A) (D)

- = 142° F (+/-2°F) (acceptable S 145°F) INITIALS

                                                                        • *.,e..****..............,e,...................

4.2 Per Tech Spec BASES B.3.4.9, confirm ALL of the following:

(a) One OR more loop drive flows were > 40% (18,000 gpm) of rated flow prior to the RPT, AND NA TRUE (b) HPCI and RCIC Systems have NOT injected since the RPT, AND NA TRUE (c) Feedwater temperature has remained > 300°F since the RPT, AND NOT CORRECT (d) Time between the RPT AND restart is < 30 minutes.

These are calculated by the student, based on JPM start time. The time will vary.

Record Recirc RPT trip time: (Ti)

Recirc start is required prior to:

30 minutes EVALUATOR USE ONLY (Ti)

+ = INITIALS (KEY)

Critical DO NOT give to candidate 5.0 ]f only ONE Recirc pump is idle, -

THEN confirm the operating pump loop flow is < 22,500 gpm. NA Critical 6.0 Confirm the:

(1) Power/flow condition is acceptable for restart per the STA/Rx Engineering. INITIALS OR (2) IF the OPRM System is inoperable, the reactor is 10% below the 61% Load Line of Attachment 1, OPRM System INOP Power vs. Flow map in 34AB-C51 -001-i, in order to avoid inadvertent entry into the RPI. INITIALS OPS-1321 Ver. N/A G16.030 MGR-0009 Ver. 5

SNC PLANTE. LHATCHj Pg 185 of 208 DOCUMENT TIThE: DOCUMENT NUMBER: VERSION No:

REACTOR RECIRCULATION SYSTEM 34S0-B31-001-1 41.1 ATtACHMENT Attachment Page LE: RECIRC PUMP QUICK RE-START LJMIT CHECKS 4 of 4 7.0 Independently verify the data recorded above is ACCEPTABLE prior to proceeding with the recirc pump start. (VERIFIED) INITIALS Critical 8.0 Confirm the steps 1 .0 thru 7.0 above, was performed within the last 15 minutes. INITIALS 9.0 Record Recirc pump start time: INITIALS EVALUATOR USE ONLY (KEY)

DO NOT give to candidate OPS-1321 Ver. N/A G16.030 MGR-0009 Ver. 5

Page 10 of 11 UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 10 minutes ago, the Unit 1 reactor scrammed from 100% power.
2. Both Reactor Recirculation pumps tripped during the scram transient.
3. Reactor water level went as low as 10 inches and has been restored to

+37 inches using Reactor Feedwater Pumps.

4. HPCI and RCIC were not required during the transient and have remained in standby.
5. RWCU is in service.
6. The Shift Supervisor has given direction to perform a Quick Restart of the 1B Reactor Recirculation pump to prevent thermal stratification.
7. An operator has entered 34S0-B31-001-1, Reactor Recirculation System and completed steps 7.1.4.2.1 through 7.1.4.2.5 (Recirc Pump B Quick Re-start).
8. Data collection began 4 minutes ago and the operator has completed gathering plant data for use with step 7.1.4.2.6 of 34S0-B31-001-1.

INITIATING CUES:

Determine if plant conditions meet the procedural requirements for starting the 1B Reactor Recirculation pump per step 7.1.4.2.6 of 34S0-B3 1-001-1, Reactor Recirculation System.

Page 11 of 11 PROVIDE TO APPLICANT 1

Plant Data

  • Reactor pressure: 805 psig
  • A Recirc Suction Temp (1B3 1-R650): 4700 F
  • Vessel Bottom Head Drain (1B21-R606 Pt 3): 3790 F

FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM ADMIN 4= ALL TITLE REVIEW OF HPCI PUMP OPERABILITY SURVEILLANCE AUTHOR MEDIA NUMBER TIME Anthony Ball 2012-301 ADMIN-4 15 Minutes RECOMMENDED BY APPROVED BY DATE N/A C. M. EDMUND 06/07/2012 SOUTHERN COMPANY A

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2012-301 ADMTN-4 Rev. No. Date 1

£ Reason for Revision Authors Initials Supvs Initials 00 06/07/12 Initial development. ARB CME

2012-301 ADMIN-4 Page 1 of 18 UNIT1( ) UNIT2(X)

TASK TITLE: REVIEW OF HPCI PUMP OPERABILITY SURVEILLANCE JPM NUMBER: 2012-301 ADMIN-4 TASK STANDARD: The task shall be complete when the operator reviews the completed surveillance procedure, 34SV-E41-002-2, makes any required calculations and determines HPCI surveillanc is unsat, one PSW valve is sat and the other is inoperable.

TASK NUMBER: 300.011 OBJECTIVE NUMBER: 300.011 .0 K/A CATALOG NUMBER: Generic 2.2.12 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.7 SRO 4.1 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO) / Senior Reactor Operator (SRO)

GENERAL

REFERENCES:

Unit 2 34SV-E41-002-2 (current version)

[iQUIRED MATERIALS: Unit 2 Completed surveillance package: 34SV-E41 -002-2.

APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is at 100% power.
2. A Normal HPCI Pump Quarterly Inservice Test (1ST) Data Test has just been completed for the HPCI pump lAW 34SV-E41-002-2, HPCI Pump Operability.
3. Unit 2 reactor pressure is 1043 psig.

INITIATING CUES:

Review Attachment 1 of 34SV-E41-002-2, HPCI Pump Operability.

Complete any calculations required by the surveillance data sheets.

Using Attachment 1 of 34SV-E41-002-2 data COMPLETE Section 7.8 TEST RESULTS, step 7.8.1 through step 7.8.6.

Page 2 of 18

2012-301 ADMIN-4 Page 3 of 18 I STEP PERFORMANCE STEP STANDARD I (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Li Human performance tools, safety, PPE met (1), AND Li Mark the JPM as a PASS Li For initial trg all steps completed correctly OR PASS Li For continuing trg, critical steps (if used) completed correctly FAIL Li Above standards not met Li Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.

START TIME:________

PROMPT: AT this time, GIVE the applicant a complete copy of 34S V-E41-002-2, HPCI Pump Operability.

PROMPT: AT this time, GIVE the applicant Attachment 2 of this JPM (Data has been filled in for this 1PM).

PROMPT: IF the applicant addresses the 1ST Book, INFORM the applicant that a supervisor has verified the reference data.

NOTE: 1PM Steps 1 - 8 can be performed in any order.

1. The applicant evaluates parameters on On Attach. 1 of 34SV-E41-002-2, Attachment 1 and finds Turbine Speed the applicant EVALUATES Nr is acceptable. Turbine Speed Nr data is SATISFACTORY. 3900 rpm (Acceptable Range:

3861 (0.99) to 3939 (1.01) rpm)

(*

  • Indicates critical step)

2012-301 ADMIN-4 Page 4 of 18 STEP f PERFORMANCE STEP STANDARD I (COMMENTS)

2. The applicant evaluates parameters on On Attach. 1 of 34SV-E41-002-2, Attachment 1 and finds Inlet Pressure the applicant EVALUATES Inlet (Stopped) (Pt) is acceptable. Pressure (Stopped) (P) data is 1

SATISFACTORY. 34 psig Acceptable Range: >7 psig.

3. The applicant evaluates parameters on On Attach. 1 of 34S V-E41-002-2, Attachment 1 and finds Inlet Pressure the applicant EVALUATES Inlet (Running) (P) is acceptable.

1 Pressure (Running) (P) data is 1

SATISFACTORY. 31 psig Acceptable Range: >7 psig.

4. The applicant evaluates parameters on At step 7.8.2.1.1 of 34S V-E41-Attachment 1 and finds Outlet 002-2, the applicant Pressure (Running) P 0 is NOT EVALUATES Outlet Pressure acceptable. data IS NOT SATISFACTORY.

1072 psig is NOT in the Acceptable Range of 1 135 psig.

NOTE: At this time, the applicant may elect to inform the Shift Supervisor that Outlet Pressure (Running) P 0 is NOT acceptable and HPCI has failed the surveillance. This action IS acceptable.

It IS also acceptable for the applicant to complete the review before bringing this to the supervisors attention.

PROMPT: IF the applicant addresses the out of spec. item(s), DIRECT the applicant to finish the data package review.

(*

  • Indicates critical step)

2012-301 ADMIN-4 Page 5 of 18 I STEP PERFORMANCE STEP STA1 I (COMMENTS)

5. The applicant calculates and then On Attach. 1 of 34SV-E41-002-2, evaluates on Attachment 1 and finds the applicant CALCULATES Differential Pressure (2) dPr is NOT AND EVALUATES Differential acceptable. Pressure (2) dPr data IS NOT SATISFACTORY. 0.88 dPr is NOT in the Acceptable Range of 0.90 to 1.10 dPr.

NOTE: Ratio Differential Pressure (2) dPr is equal to the Test Value dPr divided by the Reference Value dPr. 1041/1183 = 0.88.

At this time, the applicant may elect to inform the Shift Supervisor that Differential Pressure (2) dPr is NOT acceptable and HPCI must be declared inoperable. This action IS acceptable.

It IS also acceptable for the applicant to complete the review before bringing this to the supervisors attention.

PROMPT: IF the applicant addresses the out of spec. item(s), DIRECT the applicant to finish the data package review.

6. The applicant evaluates parameters on On Attach. 1 of 34SV-E41-002-2, Attachment 1 and finds Flowrate (4) the applicant EVALUATES (Qr) is acceptable. Flowrate (4) (Qr) data (4250 gpm) is SATISFACTORY.

Acceptable value is 4250 gpm.

(** Indicates critical step)

2012-301 ADMIN-4 Page 6 of 18 I STEP SATJUNSAT PERFORMANCE STEP STANDARD I (COMMENTS)

7. The applicant evaluates the stroke On Attach. 1 of 34SV-E41-002-2, time data for the cooling water valve the applicant evaluates the stroke 2P41-F035A. time data for 2P41-F035A and determines that the valve data is SATISFACTORY.

4.4 seconds is within the Calculated Allowable Time range of 1.5 to 4.5 seconds.

8. The applicant evaluates the stroke On Attach. 1 of 34SV-E41-002-2, time data for the cooling water valve the applicant evaluates the stroke 2P41-F035B. time data for 2P41-F035B and determines that the valve data is NOT SATISFACTORY.

5.2 seconds has exceeded the MAXIMUM Time Limit of 5.0 seconds.

NOTE: At this time, the applicant may elect to inform the Shift Supervisor that 2P41-F035B has exceeded the MAXIMUM Time Limit of 5.0 seconds and failed the surveillanc. This action IS acceptable.

It IS also acceptable for the applicant to complete the review before bringing this to the supervisors attention.

PROMPT: WHEN the applicant addresses the Out of Spec readings, INFORM the applicant to finish the data package review.

9. The applicant performs step 7.8.1 The applicant places a check Reason for test: mark for Norm. Surv. per the initial conditions.
10. The applicant performs step 7.8.2.1.1 The applicant has determined HPCI pump delivers at least 4250 gpm HPCI pump Outlet Pressure at a pump discharge pressure of (Running) P 0 <1135 psig has greater than OR equal to 1135 psig failed to meet the acceptance with reactor pressure of> 920 psig criteria of step 7.8.2.1.1.

AND < 1058 psig.

(*

  • Indicates critical step)

2012-301 ADMIN-4 Page 7 of 18 STEP PERFORMANCE STEP STANDARD I (COMMENTS) 1

11. The applicant performs step 7.8.2.1.2 The applicant has verified that HPCI pump discharge lines up stream HPCI pump discharge lines up of valves 2E41-F006 AND FOl 1 are stream of valves 2E41-F006 AND filled. FOl 1 are filled.

PROMPT: WHEN the applicant addresses the HPCI pump discharge lines upstream of valves 2E41-F006 AND FOl 1 are filled, INFORM the applicant that HPCI pump discharge lines up stream of valves 2E41-F006 AND FOl 1 are filled.

12. The applicant performs step 7.8.2.1.3 The applicant has verified that 2T41-BOO5A AND 2T41-BOO5B, 2T41-BOO5A AND 2T41-BOO5B, HPCT Pump Rm Cooling Fans, auto HPCT Pump Rm Cooling Fans, start, WHEN HPCI is started.

J auto start, WHEN HPCI started.

PROMPT: WHEN the applicant addresses the 2T41-BOO5A AND 2T41-BOO5B, HPCI Pump Rm Cooling Fans, INFORM the applicant that 2T41-BOO5A AND 2T41-BOO5B, HPCI Pump Rm Cooling Fans, auto started.

13. The applicant performs step 7.8.2.1.4 The applicant has verified that 2P41-F035A AND 2P41-F035B, 2P41-F035A AND 2P41-F035B, HPCI Pump Rm Cooler Valves, HPCI Pump Rm Cooler Valves, OPEN, WHEN cooler is running. OPEN, WHEN cooler is running.

PROMPT: WHEN the applicant addresses the 2P41-F035A AND 2P41-F035B, HPCI Pump Rm Cooler Valves, open when HPCI is running, INFORM the applicant that 2P41-F035A AND 2P41-F035B, HPCI Pump Rm Cooler Valves, auto opened.

14. The applicant performs step 7.8.2.1.5 The applicant has verified that Oil Oil level AND pressure is observed, level AND pressure is observed.

PROMPT: WhEN the applicant addresses the Oil level AND pressure is observed, INFORM the applicant that Oil level AND pressures were observed.

(*

  • Indicates critical step)

2012-301 ADMIN-4 Page 8 of 18 I STEP PERFORMANCE STEP STANDARD I (COMMENTS)

15. The applicant evaluates step 7.8.2.2.1 The applicant has determined that HPCI pump Outlet Pressure HPCI pump Outlet Pressure (Running) P 0 data. (Running) P 0 has FAILED to meet the acceptance criteria of step 7.8.2.2.1.

NOTE: At this time, the applicant may elect to inform the Shift Supervisor that Outlet Pressure (Running) P 0 is NOT acceptable and HPCI has failed the surveillance. This action IS acceptable.

It IS also acceptable for the applicant to complete the review before bringing this to the supervisors attention.

16. The applicant evaluates step 7.8.2.2.1 The applicant has determined that HPCI pump dPr data. Differential Pressure dPr has FAILED to meet the acceptance criteria of step 7.8.2.2.1.

NOTE: At this time, the applicant may elect to inform the Shift Supervisor that Differential Pressure (2) dPr is NOT acceptable. This action IS acceptable.

It IS also acceptable for the applicant to complete the review before bringing this to the supervisors attention.

17. The applicant evaluates step 7.8.2.2.1 The applicant has determined that Flowrate (4) (Q) data. Flowrate (Qr) data meets the acceptance criteria of step 7.8.2.2.1.
18. The applicant performs step 7.8.2.2.2 The applicant has verified that HPCI Pump Rm Cooler valve HPCI Pump Rm Cooler valve operability was performed. operability was performed.

PROMPT: WHEN the applicant addresses HPCI Pump Rm Cooler valve operability, INFORM the applicant that HPCI Pump Rm Cooler valve operability was performed.

(** Indicates critical step)

2012-301 ADMIN-4 Page 9 of 18 STEP f PERFORMANCE STEP STANDARD I (COMMENTS)

19. The applicant evaluates step 7.8.3 if The applicant evaluates if Response Time Test was performed. Response Time Test was performed.

PROMPT: WHEN the applicant addresses Response Time Test, INFORM the applicant that Response Time Test was NOT performed.

20. The applicant performs step 7.8.4.1 The applicant compares the stroke for 2P41-F035A, The stroke times for time and has determined that each valve are less than the HPCI 2P41-F035A stroke time IS MAXIMUM TIME LIMIT. less than the MAXIMUM TIME LIMIT.
21. The applicant performs step 7.8.4.1 The applicant compares the stroke for 2P41-F035B, The stroke times for time and has determined that each valve are less than the HPCI 2P41-F035B has FAILED MAXIMUM TIME LIMIT. to meet the acceptance criteria of step 7.8.4.1.

NOTE: At this time, the applicant may elect to inform the Shift Supervisor that 2P41-F035B has exceeded the MAXIMUM Time Limit of 5.0 seconds and failed the surveillance. This action IS acceptable.

It IS also acceptable for the applicant to complete the review before bringing this to the supervisors attention.

22. The applicant performs step 7.8.4.2 The applicant compares the stroke for 2P41-F035A, The stroke times for time and has determined that each valve are WITHIN the HPCI 2P41-F035A stroke time IS CALCULATED ALLOWABLE time within the CALCULATED range on Attachment 1. ALLOWABLE time range on Attachment 1.
23. The applicant performs step 7.8.4.2 The applicant compares the stroke for 2P41-F035B, The stroke times for time and has determined that each valve are WITHIN the HPCI 2P41-F035B stroke time IS CALCULATED ALLOWABLE time NOT within the CALCULATED range on Attachment 1. ALLOWABLE time range on Attachment 1.

(** Indicates critical step)

2012-301 ADM1N-4 Page 10 of 18 I PERFORMANCE STEP STANDARD I (COMMENTS) 1 NOTE: At this time, the applicant may elect to inform the Shift Supervisor that 2P41-F035B has exceeded the CALCULATED ALLOWABLE time range. This action IS acceptable.

It IS also acceptable for the applicant to complete the review before bringing this to the supervisors attention.

24. The applicant performs step 7.8.4.3 The applicant has verified that Valve stem travel> 80% open based Valve stem travel was> 80%

on local stem mounted position open based on local stem indicator, mounted position indicator.

PROMPT: WHEN the applicant addresses valve stem travel> 80% open based on local stem mounted position indicator, INFORM the applicant that valve stem travel WAS> 80% open based on local stem mounted position indicator.

  • *25. The applicant performs step 7.8.5 The applicant completes step Test Result. 7.8.5 and marks the step UNSAT.

NOTE: JPM Steps 26 28 can be performed in any order.

    • 26. The applicant performs step 7.8.6 for The applicant lists in step 7.8.6 HPCI pump Outlet Pressure that HPCI pump Outlet Pressure (Running) P 0 <1135 psig has failed to (Running) P 0 has FAILED to meet the acceptance criteria of step meet the acceptance criteria of 7.8.2.1.1. step 7.8.2.1.1 & 7.8.2.2.1

(<1135 psig).

    • 27. The applicant performs step 7.8.6 The applicant also lists in step HPCI Differential Pressure dPr. 7.8.6 that HPCI Differential Pressure dPr has FAILED to meet the acceptance criteria of step 7.8.2.2.1 (dPr< 0.90).

(** Indicates critical step)

2012-301 ADMIN-4 Page 11 of 18 I STEP I SAT/UNSAT

  1. 1 PERFORMANCE STEP STANDARD I (COMMENTS)
    • 28. The applicant performs step 7.8.6 for The applicant also lists in step HPCI 2P41-F035B. 7.8.6 that HPCI 2P41-F035B has FAILED to meet the acceptance criteria of step 7.8.4.1 (Exceeded Maximum Time Limit).

NOTE: If the applicant addresses writing a Condition Report (CR) based on this surveillance, inform the applicant that another operator will write the CR.

END TIME:________

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

After JPM step #28 is complete.

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

Applicant states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR PICK UP the Initiating Cue sheet.

(** Indicates critical step)

ATTACHMENT 1

    • KEY**

DO NOT give this to applicant SNC PLANT E. I. HATCH I Pg 43 of 67 DOCUMENT TITLE: I DOCUMENT NUMBER: Version No:

HPCI PUMP OPERABILITY ATTACHMENT j_

I 34SV-E41-002-2 31.0 Attachment Page TITLE: HPCI PUMP QUARTERLY 1ST DATA AND ACCEPTANCE CRITERIA 1 of 2 Reference Data Changes:

Is reference data being changed? ( ) Yes (V) No IF YES, list justification for so doing:

(2E41 -COOl)

DATE REF RE INSTRU MPL REFERENCE ACCEPT. ALERT RATIO PARAMETER VALUE TEST VALUE ACT NO. VALUE RANGE RANGE (3)

TAKEN RANGE (1 Turbine 0.99 to 2E41-R610 3900 01/18/2010 3900 N/A N/A N/A Speed (Nr) 1.01 RPM Inlet Pressure 2E41-R606 34 01/18/2010 34 7PSIG N/A <7PSIG N/A (Stopped) (Pt)

Inlet Pressure (Running) 2E41-R606 01/18/2010 7PSIG N/A <7PSIG N/A (Pt)

Outlet Pressure 2E41-R601 1215 01/18/2010 1072 N/A N/A N/A N/A (Running)

)

0 (P

Differential <0.90 dPr Pressure (2) N/A 1183 01/18/2010 0.90 to 1041 N/A or >1.10 0.88 (DPr) 1.lOdPr dPr Flowrate (4) 2E41-R612 4250 N/A 4250 N/A N/A N/A 1.0 (Qr)

(1) Pump declared inoperable according to 31G0-INS-O01-0.

(2) Differential pressure must be calculated as: dP Outlet Pressure (pump running) Inlet Pressure (Pump running)

(3) Ratio = Test Value divided by Reference Value (4) Test value must equal reference value. Ratio for flowrate must equal 1.0.

Page 12 of 18

ATTACHMENT 1

    • KEY**

DO NOT give this to applicant SNC PLANT E. I. HATCH I Pg 44 of 67 DOCUMENT TITLE:

HPCI PUMP OPERABILITY I DOCUMENT NUMBER:

34SV-E41-002-2 Version No:

I 31.0 ATTACHMENT 1 Attachment Page TITLE: HPCI PUMP QUARTERLY 1ST DATA AND ACCEPTANCE CRITERIA 2 of 2 NOTE: WHEN calculating QE recording valve stroke times, round off to the nearest tenth second.

COLUMN 2 COLUMN 4 COLUMN 5 COLUMN 3 CALCULATED REFERENCE OPERATING MAXIMUM TIME ALLOWABLE TIME COLUMN 1 TIME TIME LIMIT TIMED (SEC)

MPL (TYPE) (SEC) (SEC) BY:

OPEN CLOSE INIT OPEN CLOSE OPEN CLOSE OPEN CLOSE MINIMAX MINIMAX 2P41 -F035A 3.0 N/A 1.5 4.5 N/A N/A 4.4 N/A <5 N/A SMH AOV -

2P41-F035B 2.5 N/A 1.3 3.8 N/A N/A 5.2 NIA <5 N/A SMH AOV I.E operating time is less than 1 second, record 1 second as operating time.

VERIFY STROKE TIMES ACCEPTABLE: DATE:

Page 13 of 18

ATTACHMENT 1

    • KEY **

DO NOT give this to applicant SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 40 OF 67 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:

HPCI PUMP OPERABILITY 34SV-E41-002-2 31.0 78 TEST RESULTS 7.8.1 Reason for test: (V) Norm. Surv. ( ) WO #

( ) Other 7.8.2 Acceptance Criteria:

7.8.2.1 jf any test was performed:

7.8.2.1.1 HPCI pump delivers at least 4250 gpm at a pump discharge pressure of greater than OR equal to 1135 psig with reactor pressure of> 920 psig AND < 1058 psig.

7.8.2.1.2 HPCI pump discharge lines up stream of valves 2E41-F006 AND FOl 1 are filled.

7.8.2.1.3 2T41-BOO5A AND 2T41-BOO5B, HPCI Pump Rm Cooling Fans, auto start, WHEN HPCI is started.

7.8.2.1.4 2P41-F035A AND 2P41-F035B, HPCI Pump Rm Cooler Valves, OPEN, WHEN cooler is running.

7.8.2.1.5 Oil level AND pressure is observed.

7.8.2.2 (1ST) was performed:

7.8.2.2.1 HPCI pump data matches the reference data WITHIN the limits stated on appropriate Attachment 1, 7, OR 8.

7.8.2.2.2 HPCI Pump Rm Cooler valve operabilfty was performed.

7.8.3 jf Response Time Test was performed:

7.8.3.1 HPCI reaches rated flow AND pressure in 70 seconds.

7.8.4 HPCI Room Cooler Valve Operability was performed:

7.8.4.1 The stroke times for each valve are less than the MAXIMUM TIME LIMIT.

7.8.4.2 The stroke times for each valve are WITHIN the CALCULATED ALLOWABLE time range on Attachment 1 or Attachment 7.

7.8.4.3 Valve stem travel > 80% open based on local stem mounted position indicator.

Page 14 of 18

ATTACHMENT 1

    • KEY **

DO NOT give this to applicant SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 41 0F67 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:

HPCI PUMP OPERABILITY 34SV-E41-002-2 31.0 7.8.5 Test Result:

( ) Satisfactory (V) Unsatisfactory 7.8.6 Unsatisfactory Conditions: (1)HPCI pump Outlet Pressure (RunninQ) Po has FAILED to meet the acceptance criteria of step 7.8.2.1.1 & 7.8.2.2.1 (<1135 psic)

(2fl-IPCI Differential Pressure dPr has FAILED to meet the accentance criteria of sten 7.8.2.2.1 (dPr < 0.90).

(3IHPCI 2P41-F035B has FAILED to meet the acceotance criteria of step 7.8.4.1 (Exceeded Maximum Time Limit).

7.8.7 Comments/Corrective Actions:

7.8.8 Test completed and/or verified by:

/ I Print Name / Initial / Date I /

Print Name / Initial I Date

/ /

Print Name / Initial / Date

/

/

Print Name / Initial / Date Page 15 of 18

ATTACHMENT 2 PROVIDE TO APPLICANT SNC PLANT E. I. HATCH I Pg 43 of 67 DOCUMENT TITLE: I DOCUMENT NUMBER: Version No:

HPCI PUMP OPERABILITY 34SV-E41-002-2 31.0 ATTACHMENT j_ Attachment Page TITLE: HPCI PUMP QUARTERLY 1ST DATA AND ACCEPTANCE CRITERIA 1 of 2 Reference Data Changes:

Is reference data being changed? ( ) Yes ( v) No IF YES, list justification for so doing:

(2E41 -Cool)

DATE REF RE INSTRU MPL REFERENCE ACCEPT. ALERT RATIO PARAMETER VALUE TEST VALUE A CTION NO. VALUE RANGE RANGE (3)

TAKEN RANGE (1)

Turbine 0.99 to 2E41-R610 3900 01/18/2010 3900 N/A N/A N/A Speed (Nr) 1.01 RPM Inlet Pressure 2E41-R606 34 01/18/2010 34 7PSIG N/A <7PSIG N/A (Stopped) (Pt)

Inlet Pressure (Running) 2E41-R606 01/18/2010 7 PSIG N/A <7 PSIG N/A (Pt)

Outlet Pressure 2E41-R601 1215 01/18/2010 1072 N/A N/A N/A N/A (Running)

)

0 (P

Differential <0.90 dPr Pressure (2) N/A 1183 01/18/2010 0.90 to 1041 N/A or >1.10

1. 10 dPr (DPr) dPr Flowrate (4) 2E41-R612 4250 N/A 4250 N/A N/A N/A 1.0 (Qr)

(1) Pump declared inoperable according to 31G0-1NS-001-0.

(2) Differential pressure must be calculated as: dP = Outlet Pressure (pump running) Inlet Pressure (Pump running)

(3) Ratio = Test Value divided by Reference Value (4) Test value must equal reference value. Ratio for flowrate must equal 1.0.

Page 16 of 18

ATTACHMENT 2 PROVIDE TO APPLICANT SNC PLANT E. I. HATCH I Pci 44 of 67 DOCUMENT TITLE: DOCUMENT NUMBER: Version No:

HPCI PUMP OPERABILITY 34SV-E41-002-2 31.0 ATTACHMENT j_ Attachment Page TITLE: HPCI PUMP QUARTERLY 1ST DATA AND ACCEPTANCE CRITERIA 2 of 2 FNOTE. WHEN calculating OR recording valve stroke times, round off to the nearest tenth I second.

COLUMN 2 COLUMN 4 COLUMN 5 COLUMN 3 CALCULATED REFERENCE OPERATING MAXIMUM TIME ALLOWABLE TIME COLUMN 1 TIME TIME LIMIT TIMED (SEC)

MPL (TYPE) (SEC (SEC) (SEC) BY:

OPEN CLOSE INIT OPEN CLOSE OPEN CLOSE OPEN CLOSE MIN/MAX MIN/MAX 2P41-F035A AOV 3.0 N/A 1.5 4.5 N/A N/A 4.4 N/A <5 N/A SMH 2P41-F035B AOV 2.5 N/A 1.3 3.8 N/A N/A 5.2 N/A <5 N/A SMH if operating time is less than 1 second, record 1 second as operating time.

VERIFY STROKE TIMES ACCEPTABLE: DATE:

Page 17 of 18

UNIT 2 READ TO TIlE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is at 100% power.
2. A Normal HPCI Pump Quarterly Inservice Test (1ST) Data Test has just been completed for the HPCI pump lAW 34SV-E41-002-2, HPCI Pump Operability.
3. Unit 2 reactor pressure is 1043 psig.

INITIATING CUES:

Review Attachment 1 of 345V-E41-002-2, HPCI Pump Operability.

Complete any calculations required by the surveillance data sheets.

Using Attachment 1 of 34SV-E41-002-2 data COMPLETE Section 7.8 TEST RESULTS, step 7.8.1 through step 7.8.6.

Page 18 of 18

FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 5 ALL TITLE RADIATION EXPOSURE CALCULATION AND REQUIRED AUTHORIZATION AUTHOR MEDIA NUMBER TIME Anthony Ball 2012-301 ADMIN-5 15 Minutes RECOMMENDED BY APPROVED BY DATE N/A C. M. EDMUND 06/07/2012 SOUTHERN COMPANY A

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2012-301 ADMIN-5 Rev. No. Date Reason for Revision Authors Supvs Imt,als Imtials 01 06/07/12 Revision for HLT-7 NRC Exam. After NRC Exam, ARB CME Media Number will be changed to LR-JP-10020-01.

2012-301 ADMIN-5 Page 1 of 6 UNIT1 ( ) UNIT2 (X)

TASK TITLE: Radiation Exposure Calculation and Required Authorization.

JPM NUMBER: 2012-301 ADMIN-5 TASK STANDARD: The task shall be complete when it has been determined the job cannot be performed without exceeding annual administrative radiation exposure limits, and determining the level of approval to exceed the annual administrative radiation exposure limit.

TASK NUMBER: N/A OBJECTIVE NUMBER: LT30008.01 K/A CATALOG NUMBER: Generic 2.3.4 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.2 SRO 3.7 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO) I Senior Reactor Operator (SRO)

GENERAL

REFERENCES:

Unit 2 6OAC-HPX-001-0 (current version)

REQUIRED MATERIALS: Unit 2 6OAC-HPX-001-0 (current version)

APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. You are a radiation worker at Hatch and have been assigned to perform a job in the Unit 2 Clean Up Phase Separator (CUPS) room.
2. Gamma radiation is the only type of radiation of concern for this particular job (no airborne, Beta or Alpha).
3. Your job inside the CUPS room, will take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
4. Your total exposure (ThDE) for the year so far has been confirmed to be 1400 mrem.
5. One of the radiation fields you will work in for 20 minutes is 4500 mremlhour (Gamma radiation).
6. The other radiation field that you will work in for 40 minutes is 1200 mremlhour (Gamma radiation).
7. The dose in the travel path to the CUPS room is 1800 mremlhr.
8. Travel time through the 1800 mremlhr field to the CUPS area is 6 minutes EACH WAY.

INITIATING CUES:

Calculate the Total exposure you will receive for the job.

Determine if any Administrative Radiation Exposure Limits will be exceeded.

Considering your current exposure (1400 mrem) and that which will be received from this job, determine the HIGHEST AUTHORIZATION who must authorize the exposure, if anyone, lAW 6OAC-HPX-001-0.

2012-301 ADMIN-5 Page 3 of 6 I STEP PERFORMANCE STEP STANDARD I (COMMENTS) 1 For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Li Human performance tools, safety, PPE met (1), AND Li Mark the JPM as a PASS Li For initial trg all steps completed correctly OR PASS Li For continuing trg, critical steps (if used) completed correctly FAIL Li Above standards not met Li Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.

START TIME:________

NOTE: If the applicant addresses 8.1.2.1 which states: Prior to an individuals first work assignment in which the individual is likely to receive in excess of 2% of the limits in 8.1.1, the individual MUST submit a signed statement indicating the amount of occupational radiation exposure received during the current calendar year from sources of radiation possessed by other licensees. INFORM the applicant that this form has been signed.

    • 1. The applicant calculates exposure in f4,500 fllreflVhr) X 20 mm =

the 4,500 mremlhour field. 60 mm 1500 mrem

( 1% to accomodate rounding)

    • 2. The applicant calculates exposure in (1200 imefli!hr) X 40 mm =

the 1200 mrem/hour field. 60 ITlin 800 mrem (j 1% to accomodate rounding)

2012-301 ADMIN-5 Page 4 of 6 I STEP I I SAT![JNSAT

  1. I PERFORMANCE STEP STANDARD I (COMMENTS) 1
    • 3 The applicant calculates the dose (1800 mremlhr) X 6 mm X 2 trips received from travel time. 60 mm

= 360 mrem

    • 4 The applicant calculates total exposure 1500 (+/- 1%)

for the job:

800(+/- 1%)

360 2660 mrem Total ( 1%)

NOTE: 2660 mrem (+/- 1%) is the Total Exposure for the job.

    • 5 The applicant calculates their total 1400 exposure performing the job:

1500 (+/- 1%)

800 (+/- 1%)

360 4060 mrem Total (- 1%)

    • 6. The applicant determines that the The Hatch Administrative limits Hatch Annual Administrative are 2,000 and 4000 mremlyear.

Radiation Exposure limit will be (6OAC-HPX-001-0 step 8.2.1) exceeded while performing the work.

NOTE: The applicant may address being on the Margin List when within 400 mrem of the administrative exposure limit. It is NOT necessary for the applicant to discuss the requirements of the margin list for this JPM.

PROMPT: IF the applicant addresses the margin list, STATE that the Health Physics department is taking appropriate actions for Margin List requirements based on expected exposures for this job.

2012-301 ADMIN-5 Page 5 of 6 STEP PERFORMANCE STEP SAT!UNSAT STANDA1U)

(COMMENTS)

    • 7 The applicant determines the With available exposure authorization requirements to exceed confirmed, the HIGHEST the Annual Administrative limits, authorization must be written approval from the Plant Manager.

(Step 8.2.2)

END TIME:________

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

After JPM step #7 is complete.

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

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR PICK UP the Initiating Cue sheet.

Page 6 of 6 UNIT 2 READ TO THE APPLICANT INITIAL CONDITIONS:

1. You are a radiation worker at Hatch and have been assigned to perform a job in the Unit 2 Clean Up Phase Separator (CUPS) room.
2. Gamma radiation is the only type of radiation of concern for this particular job (no airborne, beta or alpha).
3. Your job inside the CUPS room, will take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
4. Your total exposure (TEDE) for the year so far has been confirmed to be 1400 mrem.
5. One of the radiation fields you will work in for 20 minutes is 4500 mremlhour (gamma radiation).
6. The other radiation field that you will work in for 40 minutes is 1200 mremlhour (gamma radiation).
7. The dose in the travel path to the CUPS room is 1800 mremlhr.
8. Travel time through the 1800 mremlhr field to the CUPS area is 6 minutes EACH WAY.

INITIATING CUES:

Calculate the total exposure you will receive for the job.

Determine if any administrative radiation exposure limits will be exceeded.

Considering your current exposure (1400 mrem) and that which will be received from this job, determine the HIGHEST AUTHORIZATION who must authorize the exposure, if anyone, lAW 6OAC-HPX-001-0.

FINAL Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 6- SRO ONLY TITLE EMERGENCY CLASSIFICATION AND NOTIFICATION (NEW EALS)

AUTHOR MEDIA NUMBER TIME CRITICAL Anthony Ball 2012-301 ADMIN-6 15.0/15.0 Minutes RECOMMENDED BY APPROVED BY DATE N/R C. M. EDMUND 06/07/2012 SOUTHERN COMPANY

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2012-301 ADMIN-6 Rev. No. Date Reason for Revision Authors Initials

[ Supvs Initials 00 04/30/07 Initial development CME RAB 01 11104/10 Added Task and HU Pass/Fail criteria. Updated EU CME Southern Company logo.

02 01/12/11 Updated references to NMP-EP-1 10 and MCK DNM NMP-EP- 111 03 06/07/12 General revision for use on NRC Exam 2012-301. ARB CME After NRC Exam, Media Number will be changed to LR-JP- 25061-03.

2012-301 ADMIN-6 Page 1 of 7 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: Emergency Classification and Notification (NEW EALS)

JPM NUMBER: 2012-301 ADMIN-6 TASK STANDARD: The task shall be completed when the event has been classified per NMP-EP- 110, the EN form NMP-EP- 111 Figure 1 has been completed, and offsite notifications have been directed.

TASK NUMBER: 200.052 OBJECTIVE NUMBER: 200.052.A PLANT HATCH JTA IMPORTANCE RATING:

RO 4.67 SRO 4.04 K/A CATALOG NUMBER: Generic 2.4.41 K/A CATALOG JTA IMPORTANCE RATING:

RO 2.9 SRO 4.6 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)

GENERAL

REFERENCES:

Unit 1 & 2 NMP-EP-1 10 (current version)

NMP-EP- 111 (current version)

REQUIRED MATERIALS: Unit 1 & 2 NMP-EP-1 10 (current version)

NMP-EP- 111 FIGURE 1 (current version)

APPROXIMATE COMPLETION TIME: 15.0/15.0 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT1&2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in a LOSP due to a failure of the 2D and 2C SUTs.
2. The Reactor scrammed and All rods fully inserted on the scram signal.
3. For the last 15 minutes, Only Emergency Diesel 2A has been running and is supplying power to 2E 4160 VAC bus.
4. Emergency Diesel Generators lB and 2C start attempts have not been successful.
5. All other Unit 2 parameters are normal.
6. The following Unit 1 conditions exists:

100% power All parameters normal INITIATING CUES:

Determine the emergency classification that should be declared.

Complete the EN form NMP-EP- 111 Figure 1 for offsite notifications.

Direct the operator to make the proper offsite notifications.

Current time is:

THIS IS TIME CRITICAL

2012-301 ADMIN-6 Page 3 of 7 I STEP I SAT!UNSAT

  1. 1 PERFORMANCE STEP STANDARD I (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND tJ Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS I For continuing trg, critical steps (if used) completed correctly FAIL U Above standards not met U Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.

NOTE: For the completion of this JPM, there is TWO SEPARATE CLOCKS.

The CLASSIFICATION must be made within 15 minutes of the initial prompt.

When the classification is made, a second clock starts. The EN form and direction to make the NOTIFICATIONS MUST BE COMPLETED WITH 15 MINUTES of that clock start.

1st START TIME:

1. Operator identifies the procedure Operator has identified the correct needed to perform the task, procedure as NMP-EP-1 10.
    • 2. Operator classified event per Operator has CLASSIFIED the NMP-EP-1 10. event as an ALERT EMERGENCY.

NOTE: The expected classification is an ALERT based on IC# SA5, Single power source to the ESF busses and an additional failure will result in a station blackout. If follow-up questioning reveals that a classification was declared and based on another IC #, the classification should be evaluated for validity.

1st END TIME:

(** Indicates critical step)

2012-301 ADMIN-6 Page 4 of 7 I STEP PERFORMANCE STEP SAT/UNSAT

  1. STANDARD (COMMENTS)

NOTE: The classification IS MADE when the operator STATES OR WRITES the classification. This starts the second clock.

PROMPT: WhEN the operator enquires about Meteorological conditions, GIVE the operator the MIDAS Information Sheet.

211 START TIME:________

    • 3 Operator properly completes the EN Operator has properly form per NMP-EP- 111. COMPLETED NMP-EP- 111 FIGURE 1, Southern Nuclear Emergency Notification form.

NOTE: To successfully complete the EN form, ALL STEPS HIGHLIGHTED IN YELLOW must be properly completed.

To be properly completed, the EN form must have all the required steps completed with correct information. APPLICABLE HIGHLIGHTED steps must contain sufficient information to describe the event.

    • 4 Operator directs an operator to make Operator has DIRECTED the the EN notifications Nuclear Plant Operator to make L the required EN notifications.

2 END TIME:

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

After JPM step #4 is complete.

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

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet.

(** Indicates critical step)

ATTACHMENT 1 ** KEY ** DO NOT GIVE TO APPLICANT Southern Nuclear Operating Company Emergency NMP-EP-1 11 Implementing Emergency Notifications Version 7.1 Procedure Page 35 of 47 Figure 1 Emergency Notification Form (page 1 of 2) 1 DRILL ACTUAL EVENT MESSAGE #_____

2, INITIAL FOLLOW-UP NOTIFICATION: TIME DA1_J.J_ AUTHENTICATION #_____

3. SITE: Plant Hatch Confirmation Phone #________________

UNUSUAL EVENT ALERT SITE AREA EMERGENCY CLASSIFICATION: j GENERAL EMERGENCY BASED ON EAL# SA5 EAL DESCRIPTION: Single power source to the Emergency busses and an additional failure will result in a station blackout. (OR similar words describing SA5)

5. PROTECTIVE ACTION RECOMMENDATIONS: El NONE

[] EVACUATE SHELTER Advise Remainder of EPZ to Monitor Local Radio/TV Stations/Tone Alert Radios for Additional Information and Consider the use of KI (potassium iodide) in accordance with State plans and policy.

OTHER

6. EMERGENCY RELEASE: None Is Occurring Has Occurred
7. RELEASE SIGNIFICANCE: Not applicable Within normal operating Above normal operating Under limits limits evaluation
8. EVENT PROGNOSIS: j Improving Stable Degrading
9. METEOROLOGICAL DATA: Wind Direction from degrees* Wind Speed mphK

(*May not be available for Initial Precipitation Stability Class* [] J DECLARATION TERMINATION Time Within 15 Minutes of Current Time Date Todays Date

11. AFFECTED UNIT(S): [J **
12. UNIT STATUS: Ui 100% Power Shutdown at Time Date __/.j_._...

(Unaffected Unit(s) Status Not Required for Shutdown at Time 15 Minutes before Current Time Date Initial Notifications) U20% Power Todays Date

13. REMARKS: May or may NOT write NONE or may give comments, either is acceptable.
    • Step 11 is NOT critical if Unit 2 is identified in step 13. Remarks or another place on this form.

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: Elevated Mixed Ground UNITS: Ci Ci/sec I.LCi/sec MAGNITUDE: Noble Gases:__________ lodines:___________ Particulates:__________ Other:

FORM: II Airborne Start Time Date _/_ _L__Stop Time Date _J._J...._..

Liquid Start Time Date __/_ ._/............Stop Time Date _JJ__

15. PROJECTION PARAMETERS: Projection period: Estimated Release Duration Projection performed: Time Date /__/_....... Accident Type:

16, PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem)

Site boundary 2 Miles 5 Miles 10 Miles

17. APPROVED BY: A Ti+l ifr. (ED Time Within 15 Minutes Of Declaration Time Date Todays Date NOTIFIED RECEIVED BY: BY: Time (To be completed by receiving organization)

Page 5 of 7

MIDAS INFORMATION METEOROLOGICAL 1 OM WIND SPD 1 OOM WIND SPD 1 OM WIND DIR 1 OOM WIND DIR 1Y33-R601 1Y33-R603 1Y33-R601 1Y33-R603 5.0 5.0 130 130 AMBIENT TEMP DELTA T DELTA T RAINFALL (F) 1 OM 60-10 100-10 15 MIN. AVG 54 -1.6 -2.9 .000 RADIOLOGICAL MAIN STACK U 1 RX. BLDG. VENT U2 RX. BLDG. VENT NORMAL RANGE KAMAN NORMAL RANGE KAMAN NORMAL RANGE KAMAN 1 Dli -K600A 1 Dli -R631 1 Dl 1 -K61 9A 1 Dl 1 -R631 2D1 1 -K636A 2D1 1 -R631 2.OOEOl 5.04E01 4.OOEO1 lDil-K600B iDli-K619B 2D11-K636B 2.OOEOi 4.OOEO1 STABILITY CLASS D

UNIT1&2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in a LOSP due to a failure of the 2D and 2C SUTs.
2. The Reactor scrammed and All rods fully inserted on the scram signal.
3. For the last 15 minutes, Only Emergency Diesel 2A has been running and is supplying power to 2E 4160 VAC bus.
4. Emergency Diesel Generators lB and 2C start attempts have not been successful.
5. All other Unit 2 parameters are normal.
6. The following Unit 1 conditions exists:

100% power All parameters normal INITIATING CUES:

Determine the emergency classification that should be declared.

Complete the EN form NMP-EP-1 11 Figure 1 for offsite notifications.

Direct the operator to make the proper offsite notifications.

Current time is:

THIS IS TIME CRITICAL.

Page 7 of 7

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