ML091730136

05000321/366-2009-301 Final Administrative JPMs

ML091730136
Person / Time
Site:	Hatch
Issue date:	04/06/2009
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
50-321/09-301, 50-366/09-301, LR-JP-45.33A 50-321/09-301, 50-366/09-301
Download: ML091730136 (92)

Text

{{#Wiki_filter:FINAL 04/06/09 Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 1 ) N/R )

SOUTHERN NUCLEAR OPERATING COMPANY "nLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Pro~am/Course Code: OPERATIONS TRAINING Media Number: LR-JP-45.33A 00 03/17/09 I Initial FNF

LR-JP-45.33A Page 1 of5 UNIT 1 (X) UNIT 2 (X) VERIFY FUEL MOVEMENT SHEET LR-1P-45.33A Verify proper fuel movements. 045.033 045.033.0 PLANT HATCH JTA IMPORTANCE RATING: RO Not Available SRO Not Available KIA CATALOG NUMBER: G2.1.35 KIA CATALOG JTA IMPORTANCE RATING: RO 2.2 SRO 3.9 OPERATOR APPLICABILITY: Senior Reactor Operator APPROXIMATE COMPLETION TIME: 30 Minutes SIMULATOR SETUP: N/A

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.

LR-JP-45.33A Page 3 of5 For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. START TIME: _ _ __ 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, THEN tell the operator he is only responsible for in-core verifications.

1. Obtains the correct procedures. Obtains and reviews 42FH-ERP- SAT/UNSAT 014-0, "Fuel Movement" and 34FH-OPS-00I-0, "Fuel Movement Operation."

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 SAT/UNSAT
• JLV682 SAT I UNSAT
• JLK804 SAT I UNSAT
• JLK817 SAT I UNSAT I --

(** Indicates critical step)

LR-JP-45.33A Page 4 of5 Operator determines Control Cell 14-37 bundles are the correct bundles but in the INCORRECT orientation:

• JLV678 SAT/UNSAT
• JLV670 SAT IUNSAT NOTE: Bundles JLV678 and JLV670 are 1800 out.

4. I VerifY correct loading of Control Cell Operator determines Control Cell 14-37. 14-37 bundles are the correct bundles and in the correct orientation:

• JLK805 SAT I UNSAT
• JLK812 SAT IUNSAT Operator determines Control Cell 38-17 bundle is the INCORRECT bundle but in the correct orientation:
• JLV668 SAT IUNSAT NOTE: Wrong bundle loaded. The correct bundle is JLV698

6. I 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 SAT IUNSAT
• JLK807 SAT IUNSAT
• JLK820 SAT I UNSAT Operator determines Control Cell SAT IUNSAT 14-17 Double Blade Guide is in the INCORRECT orientation.

(*

• Indicates critical step)

LR-1P-45.33A Page 5 of5 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: That completes this JPM.

  )

(** Indicates critical step)

SOUTHERN NUCLEAR \ PLANT E.!. 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: --.2L 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. NIA Date NIA 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. gso6ert Jfilton 1 04/22/09 Date

                                                              *     (j)an wi[[iams         1    04/22/09 Date Prepared by:            (]Jan wi[[iams                                    1 04/22/09 Reactor Engineering                        Date Verified by:           ZaX Pa'1ua[                                       1 04/22/09 Reactor Engineering                        Date

• Verified by: 'Kennetfi Pair6ou/J.fi 1 04/22/09 Reactor Engineering Date

  ** Approved by:        gso6ert Jri[ton                                  1 04/22/09 Reactor Engineering Supervisor                     Date

• Additional verification IF required by the Reactor Engineering Supervisor for certain evolutions or marked NIA, 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: 'Kennetfi Pair6ou/J.fi 104/22/09 Date Verified By: gso6ert Jri[ton 104/22/09 Date ENG-0190 Rev. 7.1 G16.40 42FH-ERP-014-0S

SOUTHERN NUCLEAR Unit_2_ PLANT E. I. HATCH FORM TITLE: FUEL MOVEMENT SHEETS

                                 ~  Performs these moves in sequence DThese may be performed non-sequentially Approved Page 1 of 1 1(o6ert J{i(ton Date 04/22/09 Step             Move    From:                             Comments:                   Move   To:                   Double Verif.

1. Location Init OR Init Serial Number Location Init OR Init Init Date 1 23K11 JJ{ SW JJ{ JLV675 37-36 JJ{ SE JJ{ )I(j3 04/22/09 2 23K10 JJ{ SW JJ{ JLV682 39-38 JJ{ NW JJ{ )I(j3 04/22/09 3 37-38 I 39-36 JJ{ N/A JJ{ DBL BIG 17F11/17G10 JJ{ N/A JJ{ )I(j3 04/22/09 4 23H12 JJ{ SW JJ{ JLK804 37-38 JJ{ SW JJ{ )I(j3 04/22/09 5 23H11 JJ{ SW JJ{ JLK817 39-36 JJ{ NE JJ{ )I(j3 04/22/09 6 23H10 JJ{ SW JJ{ JLV678 13-36 JJ{ SE JJ{ )I(j3 04/22/09 7 23H09 JJ{ SW JJ{ JLV670 15-38 JJ{ NW JJ{ )I(j3 04/22/09 8 13-38 I 15-36 JJ{ N/A JJ{ DBL BIG 17F10 I 17G09 JJ{ N/A JJ{ )I(j3 04/22/09 9 23K09 JJ{ SW JJ{ JLK805 13-38 JJ{ SW JJ{ )I(j3 04/22109 10 23K08 JJ{ SW JJ{ JLK812 15-36 JJ{ NE JJ{ )I(j3 04/22/09 11 23G11 JJ{ SW JJ{ JLV698 37-16 JJ{ SE JJ{ )I(j3 04/22/09 12 23G10 JJ{ SW JJ{ JLV674 39-18 JJ{ NW JJ{ )I(j3 04/22/09 13 37-18/39-16 JJ{ N/A JJ{ DBL BIG 17F09 I 17G08 JJ{ N/A JJ{ )I(j3 04/22/09 14 23F10 JJ{ SW JJ{ JLK807 37-18 JJ{ SW JJ{ )I(j3 04/22/09 15 23F09 JJ{ SW JJ{ JLK820 39-16 JJ{ NE JJ{ )I(j3 04/22109 16 17J13/17J12 JJ{ --

N/A JJ{ DBL BIG 13-18/15-16 JJ{ N/A JJ{ )I(j3 04/22/09 ENG-0190 Rev. 7.1 G16.40 42FH-ERP-014-0S

SOUTHERN NUCLEAR PLANT E.!. HATCH I PAGE 2 OF FORM TITLE: FUEL MOVEMENT SHEETS Movements Performed/Verified By: John Hart ZJi / 04/22109 / / Print Init Date Print Init Date Alan Barnes 21/B / 04/22/09 / / Print Init Date Print Init Date

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1 Print Init Date Print Init Date / ENG-0190 Rev. 7.1 G16.40 42FH-ERP-0 14-0S

SNC PLANT E. I. HATCHl Pg 41 of 49 Version No: DOCUMENT TITLE: FUEL MOVEMENT OPERATION I DOCUMENT NUMBER: 34FH-OPS-00 1-0 21.21 ATTACH MENT l Att. Pg. TITLE: UNIT 2 CORE MAP 1 of 1 NORTH

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FINAL 04/06/09 Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 2 ) N/R ) Energy to Serve Your World SM

ISOUTHERN NUCLEAR OPERATING COMPANY ,rLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERA TIONS TRAINING Media Number: LR-1P-007.15-00 00 ~ J

UNIT 1 0 UNIT 2 (X) PERFORM A VALVE POSITION VERIFICATION OF THE SYSTEM LR-JP-007.15-00 The task shall be complete when the operator has closed the open valve and documented the as-found condition. H-OPR0007.015 H-OP007.015.A PLANT HATCH JTA IMPORTANCE RATING: RO 2.2 SRO 2.69 KIA CATALOG NUMBER: 2.1.29 KIA CATALOG JTA IMPORTANCE RATING: RO 4.1 SRO 4.0 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO) OPS-0050 Operator At 34SV-SUV-018-2 ECCS Status Check APPROXIMATE COMPLETION TIME: 30 Minutes SIMULATOR SETUP: Refer to simulator setup sheet on the following page

LR-1P-2521O-02 Page 2 of8 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to an IC 113, or other 100% power IC.

2. INSERT the following OVERRIDE:

diEII-F048B RHR B Ht Exch Bypass CLOSE N/A o

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

• Place RCIC Flow Controller setpoint to 200 gpm

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

6. ESTIMATED Simulator SETUP TIME: 10 Minutes

 )

2

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

1. Unit 2 is at 100% power and 1 hour into the shift you have assumed the OATC duties.

2. As per "Operator At The Controls Relief Checklist", the "ECCS Status Check" had been started and is only partially complete.

INITIATING CUES: The Shift Supervisor directs you to:

• Complete 34SV-SUV-018-2, "ECCS Status Checks" sections:
• 7.2.3.3 for RHR B
• 7.2.5 for RCIC

For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. NOTE: Hand the operator a partially completed "Operator At The Controls Relief Checklist" (filled in up to the ECCS Status Check) and "ECCS Status Check" procedure. (everything filled in except leave blank Table 5, Table 7 and no initials on section: 7.2.3.3, 7.2.5.1, 7.2.5.2) START TIME: _ _ __

1. The operator reviews the checklist. Operator reviews the ECCS SAT IUNSAT Status Check list.

2. Verify CLOSED 2E11-F075B,

• Operator observes control SAT/UNSAT RHRSWVlv switch green light on.
• Places checkmark in Table 5.

3. Verify OPEN 2E11-F065B,

• Operator observes control SAT I UNSAT Torus Suction Vlv switch red light on.

    )

• Places checkmark in Table 5.

4. Verify OPEN 2E11-F065D,

• Operator observes control SAT IUNSAT Torus Suction Vlv switch red light on.
• Places checkmark in Table 5.

5. Verify OPEN 2E1l-F060B,

• Operator observes control SAT/UNSAT RHR Injection Vlv switch red light on.
• Places checkmark in Table 5.

6. Verify OPEN 2Ell-F017B,

• Operator observes control SAT IUNSAT RHR Outbd Inj Vlv switch red light on.
• Places checkmark in Table 5.

7. Verify CLOSED2El1-F015B,

• Operator observes control SAT IUNSAT RHR Inbd lnj Vlv switch green light on.
• Places checkmark in Table 5.

8. Verify OPEN 2El1-FOO7B,

• Operator observes control SAT/UNSAT MinFlowVlv switch red light on.
• Places checkmark in Table 5.

9. Verify CLOSED 2Ell-F021B,

• Operator observes control SAT I UNSAT Cnrnt Spray Inbd Vlv switch green light on.
• Places checkmark in Table 5.

10. Verify CLOSED 2Ell-F016B,

• Operator observes control SAT IUNSAT Cnrnt Spray Outbd Vlv switch green light on ..

I

• Places checkmark in Table 5.

(** Indicates critical step)

11. I Verify OPEN 2Ell-F047B,

• Operator observes control SAT I UNSAT Hx Inlet Vlv switch red light on.
• Places checkmark in Table 5.

12. I Verify OPEN 2EI1-F003B,

• Operator observes control SAT/UNSAT Hx Outlet Vlv switch red light on.
• Places checkmark in Table 5.

13. I Verify OPEN 2Ell-F048B,

• Operator observes control SAT I UNSAT Hx Bypass Vlv switch green light on

14. I Document as found conditions

• Operator documents on Table 5 that the valve was closed and circles the notation
• Operator informs Shift SAT/UNSAT Supervisor that 2E11-F048B was closed.

PROMPT: WHEN informed that 2EI1-F048B is closed, THEN repeat back the message. IF asked for guidance, THEN inform the candidate that for this component, he is to provide the guidance as the Shift Supervisor. I 16. Attempts to open 2EII-F048B. Operator attempts to open 2E 11-F048B. SAT I UNSAT

     \

17. Notify Shift Supervisor of failure of Operator notifies Shift Supervisor SAT/UNSAT r 2E 11-F048B to open of failure of2E11-F048B to open NOTE: The candidate may not infonn the Shift Supervisor if the previous prompt (that he is also the Shift Supervisor) is remembered.

PROMPT: WHEN informed that 2E11-F048B fails to open, THEN inform the operator that you will contact maintenance.

18. Verify CLOSED 2E11-F027B

• Operator observes control SAT/UNSAT Torus Spray Vlv switch green light on.
• Places checkmark in Table 5.

19. Verify CLOSED 2E 11-F024B

• Operator observes control SAT/UNSAT Full Flow Test Line Vlv switch green light on.
• Places checkmark in Table 5.

20. Verify CLOSED 2EII-F028B

• Operator observes control SAT I UNSAT Torus Spray or Test Vlv switch green light on.
• Places checkmark in Table 5.

21. Verify CLOSED 2E11-F011B

• Operator observes control SAT/UNSAT RHR Hx To Torus Vlv switch green light on.

    )

• Places checkmark in Table 5.

22. Verify CLOSED 2E11-F073B

• Operator observes control SAT I UNSAT RHRSW Crosstie Vlv switch green light on.
• Places checkmark in Table 5.

(** Indicates critical step)

Verify CLOSED 2E 11-F 122B Testable Check F050B Bypass Vlv I- Operator observes control switch green light on. SAT I UNSAT

24. I Verify OPEN 2E11-FOO4B

                                               -

I-Places checkmark in Table 5. Operator observes control SAT/UNSAT Torus Suction Vlv switch red light on.

                                               -      Places checkmark in Table 5.

25. I Verify CLOSED 2E 11-FOO6B Shutdown Cooling Vlv I- Operator observes control switch green light on.

SAT/UNSAT

26. I Verify OPEN 2E11-FOO4D -- Places checkmark in Table 5.

Operator observes control SAT/UNSAT Torus Suction Vlv switch red light on.

                                                -     Places checkmark in Table 5.

27. I Verify CLOSED 2EII-FOO6D Shutdown Cooling Vlv I- Operator observes control switch green light on.

SAT I UNSAT

                                                -      Places checkmark in Table 5.

28. I Verify CLOSED 2Ell-F103B Hx VentVlv I- Operator observes control switch green light on.

SAT/UNSAT

29. I Verify CLOSED 2E11-F104B -- Places checkmark in Table 5.

Operator observes control SAT I UNSAT Hx VentVlv switch green light on.

30. I Verify CLOSED 2Ell-F1l9B I-

                                                 -     Places checkmark in Table 5.

Operator observes control SAT I UNSAT Serv Wtr Crosstie Vlv switch green light on.

                                                 -     Places checkmark in Table 5.

31. I Verify CLOSED 2Ell-F053B**

Hx. Outlet Press Reducing Vlv I- Operator observes control switch is in the closed position. SAT I UNSAT

32. I Verify OPEN 2E11-F041B

                                                 --    Places checkmark in Table 5.

Operator observes control SAT/UNSAT Drywell Press Switches Inst Line switch red light on. Isolation (2HII-P654)

33. I Verify OPEN 2Ell-F041D -- Places checkmark in Table 5.

Operator observes control SAT/UNSAT Drywell Press Switches Inst Line switch red light on. Isolation (2H11-P654)

34. I Verify CLOSED 2Ell-F040 -- Places checkmark in Table 5.

Operator observes control SAT/UNSAT RHR to Radwaste Vlv (2H11-P602) switch green light on.

                                                    -  Places checkmark in Table 5.

35. I Verify CLOSED 2Ell-F049 RHR to Radwaste Vlv I- Operator observes control switch green light on.

SAT/UNSAT

36. I Confirm that the RCIC Turbine Flow - Places checkmark in Table 5.

Operator observes RCIC Flow SAT/UNSAT Controller is in AUTO (green Controller is set at 200 gpm. light ILLUMINATED) AND set at 400 GPM with demand meter

                      > 100%.

(** Indicates critical step)

     ! 37 I Inform Shift Supervisor                   Operator informs Shift Supervisor     SAT /UNSAT that RCIC Flow Controller is set at 200 !rom ..

NOTE: The candidate may NOT inform the Shift Supervisor if the previous prompt (that he is also the Shift Supervisor) is remembered. PROMPT: IF informed that RCIC Flow Controller demand meter is 200 gpm, THEN repeat back the message. IF asked for guidance, THEN inform the candidate that for this component, he is he is to provide the guidance as the Shift Supervisor. Operator adjusts RCIC Flow SAT/UNSAT Controller to 400 gpm.

39. I Verify OPEN/STOP 2E51-F007 .. Operator observes control SAT/UNSAT Steam Supply Iso1 VIv switch red light on.

• Places checkmark in Table 7.

40. I Verify OPEN/STOP 2E51-F008

• Operator observes control SAT /UNSAT Steam Supply Line Is01 VIv switch red light on.
• Places checkmark in Table 7.

    )41. Verify CLOSED 2E51-F045 Steam to Turbine VIv

• Operator observes control switch green light on.

SAT/UNSAT

• Places checkmark in Table 7.

42. Verify CLOSED 2E51-FO 19 4lI Operator observes control SAT/UNSAT MinFlowVlv switch green light 011.

• Places checkmark in Table 7.

43. I Verify CLOSED 2E51-F022

• Operator observes control SAT /lJNSAT Test Line To CST switch green light on.
• Places checkmark in Table 7.

44. I Verify CLOSED 2E51-FO 13

• Operator observes control SAT/UNSAT Pump Discharge Vlv switch green light on.
• Places checkmark in Table 7.

45. I Verify OPEN 2E51-F012

• Operator observes control SAT/UNSAT Pump Discharge Viv switch red light on.
• Places checkil1ark in Table 7.

46. I Verify OPEN 2E51-F003 liD Operator observes control SAT /UNSAT Torus Suction Vlv switch red light on.

                                                      ~    Places checkmark in Table 7.

47. I Verify CLOSED 2E51-F031

• Operator observes control SAT/UNSAT Torus Inbd Suction Viv switch green light on.

e Places checkmark in Table 7.

    )48'1 Verify O~EN I-FOIO                               Operator observes control        SAT/UNSAT I* CST SuctIon VIv fjI switch red light on.

e Places checkmark in Table 7. (** Indicates critical step)

Verify CLOSED 2E51-F029 Torus Outbd Suction Vlv I* Operator observes control switch green light on. SAT IUNSAT

• Places checkmark in Table 7.

50. I Verify CLOSED 2E51-F046

• Operator observes control SAT/UNSAT Turb Clg Water Vlv switch green light on.
• Places checkmark in Table 7.

51. I Verify CLOSED 2E51-F054

• Operator observes control SAT I UNSAT Stearn Line Drain Vlv switch green light on.
• Places checkmark in Table 7.

52. I Verify CLOSED 2E51-F004

• Operator observes control SAT/UNSAT Barom Cndsr Disch To CRW switch green light on.
• Places checkmark in Table 7.

53. I Verify OPEN 2E51-F005

• Operator observes control SAT IUNSAT Barom Cndsr Disch To CRW (2Hll- switch red light on.

P601)

• Places checkmark in Table 7.

54. Verify OPEN 2E51-F025

• Operator observes control SAT IUNSAT Steam Line Drain Vlv switch red light on.
• Places checkmark in Table 7.

55. Verify OPEN 2E51-F026

• Operator observes control SAT I UNSAT Stearn Line Drain Vlv (2HII-P601) switch red light on.

     )

• Places checkmark in Table 7.

56. Verify OPEN 2E51-F 104

• Operator observes control SAT I UNSAT Exh Vacuum Brkr Vlv switch red light on.
• Places checkmark in Table 7.

57. I Verify OPEN 2E51-F105

• Operator observes control SAT I UNSAT Exh Vacuum Brkr Vlv (2Hl1-P601) switch red light on.
• Places checkmark in Table 7.

58. Verify OPEN 2E51-F523

• Operator observes control SAT I UNSAT Governor Vlv (open indication) switch red light on.
• Places checkmark in Table 7.

59. I Verify OPEN 2E51-F524

• Operator observes control SAT/UNSAT Trip & Throttle Vlv switch red light on.
• Places checkmark in Table 7.

END TIME: _ _ __ NOTE: The terminating cue shall be given to the Applicant when:

                           -   With no reasonable progress, the Applicant exceeds double the allotted time.
                           -   Operator has completed the ECCS Status Check Surveillance.

TERMINATING CUE: That completes this lPM. (** Indicates critical step)

SOUTHERN NUCLEAR PLANT E. I. HATCH FORM TITLE: I PAGE 1 of 1 Part IV To be completed by on duty OATC just prior to end of shift. On coming OATC will place his initials in the box when reviewed in PART IV. OPERATOR AT THE CONTROLS RELIEF CHECKLIST General Information (Le., Demins to be BIW & PC, etc). _ _ _ _ _ _ _ _ _ _ _ _ _0600_to_1800_ _ 04_1_22J_09_ UNIT 2 OATC ON DUTY SHIFT DATE (mm/dd/yy) Part I To be reviewed prior to OATC assuming shift.

• Control Board Walkdown (front & back panel) r2J
• Oncoming OATC reviewed OATC Log from the previous 12-hour shift r2J
• Ensure radio available. r2J OFF Standard Conditions Part II To be completed as early in shift as possible. Check each box as completed
• Review Reactivity Briefing Sheet (OPS-1625 for U2) OR (OPS-1689 for U1) r2J
• Review of Active Operating Orders. r2J
• Review procedure 34SV-SUV-018-1/2, ECCS Status Check D
• Review condensate and RWCU demin status. D
• OATC has informed other NPOs on duty of work to be done on this shift. D
• Review Compensatory Actions for this shift. D Procedures In progress Procedures Step Awaiting
• Review RAS Log. D
• Review Night Order Book. D
• Confirm logged on to GENCOM. D Part III To be completed prior to leaving shift.
• Mid Shift control room panel walk down completed. D
• Review 34SV-SUV-019-1/2 for completeness. D
• Review 34GO-OPS-030-1 12 for completeness. D _ _--'I I_ _
• Review 34GO-OPS-031-1 for completeness. D OFF GOING OATC SIGNATURE DATE (mm/dd/yy)
• Review/sign procedures completed on shift. D
• Operating Orders required this shift completed. D
• Compensatory Actions for this shift completed. D _ _--'I I_ _
• OATC GMA Key Inventory. D REVIEWED BY (SS) DATE (mm/dd/yy)
• Once per shift validation of ELDS entry per 34GO-OPS-018-1/2. D OPS-0050 Ver 20.0 TRAINING USE 31 GO-OPS-OO?-O

SOUTHERN NUCLEAR DOCUMENT TYPE: TRAINING USE ONL Y PAGE PLANT E. I. HATCH SURVEILLANCE PROCEDURE 1 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 EXPIRATION APPROVALS: EFFECTIVE DATE: DEPARTMENT MGR C. R. Dedrickson DATE 08/27/97 DATE: N/A NPGM/POAGM/PSAGM OS/26/04 __ L- ___________________ N/A DATE N/A 1.0 OBJECTIVE This procedure provides instructions for use when demonstrating Emergency Core Cooling System's operability as required by Unit 2 TS SR 3.5.1.2 and 3.5.2.4. In addition, instructions are provided for use WHEN demonstrating Reactor Core Isolation Cooling System AND Suppression Pool Cooling and Spray Modes of the Residual Heat Removal System operability as required by Unit 2 TS SR 3.5.3.2, 3.6.2.3.1, 3.6.2.4.1, and partially covers 3.7.1.1. TABLE OF CONTENTS Section Page 2.0 APPLiCABILITy .................................................................................................................. 1

3.0 REFERENCES

................................................................................................................... 2 4.0 REQUIREMENTS ............................................................................................................... 3 5.0 PRECAUTIONS/LIMITATIONS ........................................................................................... 4 6.0 PREREQUISITES ............................................................................................................... 4 7.0 PROCEDURE ..................................................................................................................... 5 7.1 PRETEST ..................................................................................................................... 5 7.2 ECCS STATUS CHECK................................................................................................ 5 7.3 TEST RESULTS ......................................................................................................... 17 7.4 TEST REViEW ............................................................................................................ 18 2.0     APPLICABILITY This procedure is applicable to the valves in the flow paths of the following ECCS AND safe shutdown systems: High Pressure Coolant Injection System, Reactor Core Isolation Cooling System, LPCI AND Suppression Pool Cooling and Spray Modes of the Residual Heat Removal System AND the Core Spray System. It is performed WITHIN two hours of every shift change AND is required to be performed once every 31 days by Tech Specs. This procedure is also applicable to the ECCS and RCIC Room Coolers and valves as an administrative control over system alignment.

MGR-0002 Ver. 8

. SOUTHERN NUCLEAR TRAINING USE ONLY PAGE ) PLANT E. I. HATCH 2 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4

3.0 REFERENCES

3.1 90AC-OAM-001-0, Test and Surveillance Control 3.2 Unit 2, TS SR 3.5.1.2,3.5.2.4, 3.5.3.2, 3.6.2.3.1, 3.6.2.4.1, and 3.7.1.1 3.3 USNRC Inspection Report 50-366/79-21 3.4 H-26014 and H-26015, RHR System P&ID, Sheets 1 and 2 3.5 H-26018, Core Spray System P&ID 3.6 H-26020 and H-26021, HPCI System P&ID, Sheets 1 and 2 3.7 H-26023 and H-26024, RCIC System P&ID, Sheets 1 and 2 G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 3 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS The number and qualification level of Operations personnel performing this procedure will be determined by Shift Supervisor .. 4.2 MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure 4.3 SPECIAL REQUIREMENTS 4.3.1 IF valves OR switches are NOT in position specified, i.e., NOT in Standby Lineup, the Shift Supervisor will determine from other plant conditions IF the system/loop is operable. 4.3.2 For any valves found out of the Normal Position, perform the following: 4.3.2.1 Record AND circle the valve position in the appropriate table AND inform the Shift Supervisor. 4.3.2.2 Provide an explanation of the position as follows: 4.3.2.2.1 !E the misposition causes the ECCS OR Safe Shutdown system to be inoperable, record explanation in Unsatisfactory Conditions. 4.3.2.2.2 IF the position does NOT cause the system to be inoperable, record the explanation under Comments/Corrective Actions section. 4.3.2.3 The Shift Supervisor will initiate corrective action as necessary to return the valve OR switch to its correct position. G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 4 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS Observe safety rules outlined in the Southern Nuclear Safety and Health Manual. 5.2 LIMITATIONS These checks may be performed in any order necessary. 6.0 PREREQUISITES N/A - Not applicable to this procedure G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 5 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.0 PROCEDURE 7.1 PRETEST 7.1.1 Obtain Unit 2 Shift Supervisor's permission to perform this test.

                                                                                                ~

7.1.2 Record the Plant Condition (1, 2, 3, 4, 5 or *): 1

                                                                                                ~

7.2 ECCS STATUS CHECK CONTINUOUS I 7.2.1 IF Core Spray Loop A is required to be operable, confirm that Core Spray Loop A valves in the flow path are in the correct position by completing Table 1.

                                                                                                -J:K-Table 1 OPERABLE VALVE                                                                           CONFIRMED     OFF-NORMAL (NORMAL)                VALVE DESCRIPTION NUMBER                                                                              (..J)    POSITION (O/C)

POSITION Core Spray Loop A Valves 2E21-FOO1A OPEN Torus Suction Vlv ..,; 2E21-F019A OPEN Torus Suction Vlv ..,; 2E21-FOO4A OPEN Outbd Discharge Vlv ..,; 2E21-FOO5A CLOSED Inbd Discharge Vlv ..,; 2E21-F015A CLOSED Test Vlv ..,; 2E21-F031A OPEN Min FlowVlv ..,; 2E21-FOO7A OPEN Manual Injection Vlv ..,; 2E21-F037A CLOSED (Testable Check) Bypass Vlv ..,; - - _.. - G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 6 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.2 !E Core Spray Loop B is required to be operable, confirm that Core Spray Loop B valves in the flow path are in the correct position by completing Table 2. J:K-Table 2 Core Spray Loop B Valves 2E21-F001B OPEN Torus Suction Vlv ...J 2E21-F019B OPEN Torus Suction Vlv ...J 2E21-F004B OPEN Outbd Discharge Vlv ...J 2E21-FOOSB CLOSED Inbd Discharge Vlv ...J 2E21-F015B CLOSED Test Vlv ...J 2E21-F031B OPEN Min FlowVlv ...J 2E21-F007B OPEN Manual Injection Vlv ...J 2E21-F037B CLOSED (Testable Check) Bypass Vlv ...J 2GS1-F017 CLOSED Torus Water Makeup Outbd Isol ...J (2H11-P70Q) 2GS1-F013 CLOSED Torus Water Makeup Inbd Isol ...J (2H11-P70Q) G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 7 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 NOTE Valves 2E11-F008 and F009 positions are confirmed whenever any loop of RHR is required to be operable. 7.2.3 Confirm that the RHR System valves in the LPCI AND Suppression Pool Cooling modes are in the correct position as follows: 7.2.3.1 IE the LPCI OR Suppression Pool Cooling mode OR Suppression Pool Spray Mode of RHR Loop A is required to be operable, confirm that RHR Loop A valves in the LPCI AND/OR Suppression Pool Cooling AND/OR Suppression Pool Spray Flow Path are in the correct position by completing Tables 3 and 4.

                                                                                              ~

7.2.3.2 IF RHR Loop A is in a mode of operation other than Standby for LPCI and Suppression Pool Cooling AND/OR Suppression Pool Spray Modes of operation, confirm that Loop A is operable AND record that mode of operation below: Mode of Loop A operation: NIA NIA Table 3 OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER ('~) POSITION (O/C) POSITION 2E11-F009 CLOSED SDC Suction Vlv (2H 11-P602) -V 2E11-F008 CLOSED SDC Suction Vlv -V Table 4 OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (..J) POSITION (O/C) POSITION RHR Loop A Valves 2E11-F075A CLOSED RHRSWVlv -V 2E11-F065A OPEN Torus Suction Vlv -V  ! 2E11-F065C OPEN Torus Suction Vlv -V 2E11-F060A OPEN RHR Injection Vlv -V G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 8 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 4 (continued) OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (--.j) POSITION (O/C) POSITION 2E11-F017A OPEN RHR Outbd Inj Vlv -I 2E11-F015A CLOSED RHR Inbd Inj Vlv -I 2E11-F007A OPEN Min FlowVlv -I 2E11-F021A CLOSED Cnmt Spray Inbd Vlv -I 2E11-F016A CLOSED Cnmt Spray Outbd Vlv -I 2E11-F047A OPEN Hx Inlet Vlv -I 2E11-F003A OPEN Hx Outlet Vlv -I 2E11-F048A OPEN Hx Bypass Vlv -I 2E11-F027A CLOSED Torus Spray Vlv -I ~ 2E11-F024A CLOSED Full Flow Test Line Vlv -I

                                                                                            -

2E11-F028A CLOSED Torus Spray or Test Vlv -I 2E11-F011A CLOSED RHR Hx To Torus Vlv -I 2E11-F073A CLOSED RHRSW Crosstie Vlv -I 2E11-F122A CLOSED Testable Check F050A Bypass Vlv -I 2E11-F004A OPEN Torus Suction Vlv -I 2E11-F004C OPEN Torus Suction Vlv -I 2E11-F006A CLOSED Shutdown Cooling Vlv -I 2E11-F006C CLOSED Shutdown Cooling Vlv -I 2E11-F103A CLOSED Hx Vent Vlv -I 2E11-F104A CLOSED Hx Vent Vlv -I 2E11-F119A CLOSED Serv Water Crosstie Vlv

                                -~
                                                                       -I G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 9 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 4 (continued) OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER ('~) POSITION (O/C) POSITION 2E 11-F053A** CLOSED Hx. Outlet Press Reducing Vlv -V 2E11-F041A OPEN D/W Press Sw Inst Line Isol -V (2H11-P657) 2E11-F041C OPEN D/W Press Sw Inst Line Isol -V (2H11-P657) -

• • Confirm that power is off to this valve by confirming the F053A solenoid control switch is in closed (valve fails closed on loss of power).

G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 10 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.3.3 IF the LPCI OR Suppression Pool Cooling mode OR Suppression Pool Spray Mode of RHR Loop B is required to be operable, confirm that RHR Loop B valves in the LPCI AND/OR Suppression Pool Cooling AND/OR Suppression Pool Spray Flow Path are in the correct position by completing Tables 3 and 5. 7.2.3.4 IF RHR Loop B is in a mode of operation other than Standby for LPCI and Suppression Pool Cooling AND/OR Suppression Pool Spray Modes of operation, confirm that Loop B is operable AND record that mode of operation below: Mode of Loop B operation: _ _ _ _ _----'-N:..:...A..!....-_ _ _ _ _ __ NA .

                 ....:.

Table 5 OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (~) POSITION (O/C) POSITION RHR Loop B Valves 2E11-F075B CLOSED RHRSW Vlv 2E11-F065B OPEN Torus Suction Vlv 2E11-F065D OPEN Torus Suction Vlv 2E11-F060B OPEN RHR Injection Vlv 2E11-F017B OPEN RHR Outbd Inj Vlv 2E11-F015B CLOSED RHR Inbd Inj Vlv 2E11-F007B OPEN Min FlowVlv 2E11-F021B CLOSED Cnmt Spray Inbd Vlv 2E11-F016B CLOSED Cnmt Spray Outbd Vlv 2E11-F047B OPEN Hx Inlet Vlv 2E11-F003B OPEN Hx Outlet Vlv 2E11-F048B OPEN Hx Bypass Vlv 2E11-F027B CLOSED Torus Spray Vlv G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 11 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 5 (continued) OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (-V) POSITION (O/C) POSITION 2E11-F024B CLOSED Full Flow Test Line Vlv 2E11-F028B CLOSED Torus Spray or Test Vlv 2E11-F011 B CLOSED RHR Hx To Torus Vlv 2E11-F073B CLOSED RHRSW Crosstie Vlv 2E11-F122B CLOSED Testable Check F050B Bypass Vlv 2E11-F004B OPEN Torus Suction Vlv 2E11-F006B CLOSED Shutdown Cooling Vlv 2E11-F004D OPEN Torus Suction Vlv 2E11-F006D CLOSED Shutdown Cooling Vlv 2E11-F103B CLOSED Hx Vent Vlv 2E11-F104B CLOSED Hx Vent Vlv 2E11-F119B CLOSED Serv Wtr Crosstie Vlv 2E11-F053B** CLOSED Hx. Outlet Press Reducing Vlv 2E11-F041B Drywell Press Switches Inst Line OPEN Isolation (2H 11-P654) 2E11-F041D OPEN Drywell Press Switches Inst Line Isolation (2H 11-P654) 2E11-F040 CLOSED RHR to Radwaste Vlv (2H11-P602) 2E11-F049 CLOSED RHR to Radwaste Vlv

                                                             ----    -----                               ----

• • Confirm that power is off to this valve by confirming the F053B solenoid control switch is in closed (valve fails closed on loss of power).

G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 12 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.3.5 Confirm that the following valves are de-energized in the CLOSED position. 7.2.3.5.1 2E11-F022, Rx Head Spray Vlv

                                                                                               ~

7.2.3.5.2 2E11-F023, Rx Head Spray Vlv

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7.2.4 IF HPCI System is required to be operable, perform the following: 7.2.4.1 Confirm that the HPCI Flow Controller is in AUTO (green light ILLUMINATED) AND set at 4250 GPM with demand meter indicating> 100%.

                                                                                               ~

7.2.4.2 Confirm that the valves are in the correct position by completing Table 6.

                                                                                               ~

Table 6 OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER ('v) POSITION (O/C) POSITION 2E41-F002 OPEN/STOP Inbd Steam Isol Vlv -V 2E41-F003 OPEN/STOP Outbd Steam Isol Vlv -V 2E41-F001 CLOSED Turb Steam Supply Vlv -V 2E41-F011 CLOSED Test To CST Vlv -V 2E41-F012 CLOSED Min FlowVlv -V 2E41-F051 OPEN Torus Suction Vlv -V 2E41-F042 CLOSED Torus Inbd Suct Vlv -V 2E41-F008 CLOSED Test To CST Vlv -V 2E41-F059 CLOSED Lube Oil Clg Wtr Vlv -V 2E41-F054 CLOSED Drain Pot Trap Byp Vlv -V 2E41-F041 CLOSED Torus Outbd Suct Vlv -V 2E41-F007 OPEN Pump Discharge Vlv -V 2E41-F053 AUTO Drain Pot Drain Vlv -V - ----_._---- - G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 13 OF 18 DOCUMENT TITLE: . DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 6 (continued) OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (.y) POSITION (O/C) POSITION 2E41-F004 OPEN CST Suction Vlv .y 2E41-F006 CLOSED Pump Discharge Vlv .y 2E41-F104 OPEN Exh Vacuum Brkr Vlv (2H11-602)

                                                                     .y 2E41-F111       OPEN           Exh Vacuum Brkr Vlv                    .y 2E41-F025       OPEN Barom Cndsr Disch To CRW (2H 11-P602)
                                                                      .y 2E41-F026**     CLOSED         Barom Cndsr Disch To CRW                .y 2E41-F028       OPEN Steam Line Drain Vlv (2H11-P602)
                                                                      .y 2E41-F029       OPEN           Steam Line Drain Vlv                    .y 2E41-F3052       CLOSED         HPCI Control Vlv                       .y 2E41-F3053       CLOSED         HPCI Stop Vlv                          .y

• • Valve cycles automatically on barometric condenser level.

G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 14 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.5 IF RCIC System is required to be operable, perform the following: 7.2.5.1 Confirm that the RCIC Turbine Flow Controller is in AUTO (green light ILLUMINATED) AND set at 400 GPM with demand meter indicating> 100%. 7.2.5.2 Confirm that the valves are in the correct position by completing Table 7. Table 7 OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER ('-J) POSITION (O/C) POSITION 12E51-F007 OPEN/STOP Steam Supply Isol Vlv 2E51-F008 OPEN/STOP Steam Supply Line Isol Vlv 2E51-F045 CLOSED Steam to Turbine Vlv 2E51-F019 CLOSED Min FlowVlv 2E51-F022 CLOSED Test Line To CST 2E51-F013 CLOSED Pump Discharge Vlv 2E51-F012 OPEN Pump Discharge Vlv 2E51-F003 OPEN Torus Suction Vlv 2E51-F031 CLOSED Torus Inbd Suction Vlv 2E51-F010 OPEN CST Suction Vlv 2E51-F029 CLOSED Torus Outbd Suction Vlv 2E51-F046 CLOSED Turb Clg Water Vlv 2E51-F054 CLOSED Steam Line Drain Vlv 2E51-F004** CLOSED Barom Cndsr Disch To CRW Barom Cndsr Disch To CRW 2E51-F005 OPEN

------

(2H11-P601 ) -- --- --------- , .

 ** Valve cycles automatically on barometric condenser level.

G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 15 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 Table 7 (continued) OPERABLE VALVE CONFIRMED OFF-NORMAL (NORMAL) VALVE DESCRIPTION NUMBER (..J) POSITION (O/C) POSITION 2E51-F025 OPEN Steam Line Drain Vlv 2E51-F026 OPEN Steam Line Drain Vlv (2H11-P601) 2E51-F104 OPEN Exh Vacuum Brkr Vlv 2E51-F105 OPEN Exh Vacuum Brkr Vlv (2H11-P601) 2E51-F523 OPEN Governor Vlv (open indication) 2E51-F524 OPEN Trip & Throttle Vlv

                                                             ------         -----------    --------   --

7.2.6 Confirm that the Control Room Ventilation System is correctly aligned for the existing plant condition per 34S0-Z41-00 1-1, Control Room Ventilation System.

                                                                                              ~

G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 16 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.2.7 Confirm that the ECCS AND RCIC ROOM COOLER System is correctly aligned for the existing plant condition per Table 8. Table 8

                                                                                      +&

Pane12H11-P657 OPERABLE COOLER CONFIRMED OFF-NORMAL POSITION COOLER DESCRIPTION NUMBER (~) POSITION CIRCLE AUTO/RUN 2T41-B001A (Note 1) CRD PUMP ROOM COOLER -V AUTO CS/RHR S-E DIAGONAL PUMP 2T41-B002A (Note 2) ROOM COOLER

                                                                             -V AUTO           CS/RHR N-E DIAGONAL PUMP 2T41-B003A (Note 2)                 ROOM COOLER
                                                                             -V AUTO/RUN 2T41-B004A (Note 3)

RCIC PUMP RM COOLER -V AUTO/RUN 2T41-B005A (Note 4) HPCI PUMP RM COOLER -V Pane12H11-P654 AUTO/RUN 2T41-B001B (Note 1) CRD PUMP ROOM COOLER -V AUTO CS/RHR S-E DIAGONAL PUMP 2T41-B002B (Note 2) ROOM COOLER

                                                                             -V AUTO            CS/RHR N-E DIAGONAL PUMP 2T41-B003B (Note 2)                 ROOM COOLER
                                                                             -V AUTO/RUN 2T41-B004B (Note 3)

RCIC PUMP RM COOLER -V AUTO/RUN 2T41-B005B (Note 4) HPCI PUMP RM COOLER -V Note 1. One CRD cooler in RUN, one in AUTO Note 2. Both CS/RHR coolers in each diagonal in AUTO Note 3. One RCIC cooler in RUN or AUTO, one in AUTO Note 4. One HPCI cooler in RUN, one in AUTO G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 17 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.3 TEST RESULTS 7.3.1 Reason for test: ( Normal surveillance ( X) Other _ _ _ _ _ _ _ _ _ __ 7.3.2 Acceptance Criteria 7.3.2.1 WHEN a Loop of RHR is required to be operable, each Residual Heat Removal System Valve in the LPCI or Suppression Pool Cooling or Suppression Pool Spray flow path, that is NOT locked, sealed OR otherwise secured in position, is in the correct position listed in Tables 3 and 4(5) OR the Shift Supervisor had determined from other plant requirements, e.g., Shutdown Cooling required, that the Loop is operable. 7.3.2.2 WHEN a Core Spray Loop is required to be operable, each Core Spray System Valve in the flow path, that is NOT locked, sealed OR otherwise secured in position, is in the correct position listed in Table 1(2). 7.3.2.3 WHEN HPCI is required to be operable, each HPCI System Valve in the flow path, that is NOT locked, sealed OR otherwise secured in position, is in the correct position listed in Table 6, unless the Shift Supervisor had determined from other plant requirements, HPCI aligned to Torus, that HPCI is operable. 7.3.2.4 WHEN RCIC is required to be operable, each RCIC System Valve in the flow path that, is NOT locked, sealed OR otherwise secured in position, is in the correct position listed in Table 7, unless the Shift Supervisor has determined from other plant requirements e.g., Surveillance Procedure in progress, that RCIC is operable. 7.3.3 Test Result: ( ) Satisfactory ( ) Unsatisfactory 7.3.4 Unsatisfactory Conditions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 7.3.5 Comments/Corrective Actions: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ G16.30 MGR-0001 Ver. 3

SOUTHERN NUCLEAR TRAINING USE ONLY PAGE PLANT E. I. HATCH 18 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: *1 VERSION NO: ECCS STATUS CHECKS 34SV-SUV-018-2 6.4 7.3.6 Test completed and/or verified by:

                                                               /                /

Print Name / Initial / Date

                                                               /                /

Print Name / Initial / Date

                                                                /                /

Print Name / Initial / Date

                                                                /              /

Print Name / Initial / Date

                                                                /              /

Print Name / Initial / Date 7.4 TEST REVIEW ) 7.4.1 The Shift Supervisor will review the procedure data for completeness and indicate concurrence with the test satisfactory/unsatisfactory determination by signing below. Results reviewed by: SS Date 7.4.2 The Shift Supervisor will forward this procedure, with all sign-offs complete, to Document Control for retention in accordance with 20AC-ADM-002-0, Quality Assurance Records Administration. G16.30 MGR-0001 Ver. 3

FINAL 04/06/09 Southern Nuclear E. I. Hatch Nuclear Plant Operations Training Admin 3 NIR SOUTHERN.\ COMPANY Energy to Serve Your World SM

i SOUTHERN NUCLEAR OPERATING COMPANY ,PLANT E. I. HATCH Page 1 of 1 } I FORM TITLE: TRAINING MATERIAL REVISION SHEET Prog,ram/Course Code: OPERATIONS TRAINING Media Number: LR-JP-I0027

UNIT 1 (X) UNIT 2 0 MCRECRAS LR-lP-l 0027 -00 The task shall be completed the candidate has completed sections 1 and 2 of Required Action Sheet, form 1349. OPSR300.027 H-OP300.027A PLANT HATCH JTA IMPORTANCE RATING: RO N/A SRO N/A KIA CATALOG NUMBER: G 2.2.23 KIA CATALOG JTA IMPORTANCE RATING: RO NA SRO 4.6 OPERATOR APPLICABILITY: Senior Reactor Operator Completion Times OPS-1349 TECH SPECS UNIT 1 APPROXIMATE COMPLETION TIME: 30 Minutes SIMULATOR SETUP: N/A

UNIT 1 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 1 is in Mode 5 with fuel movement within the core in progress. Fuel movements are expected to last for 15 days.

2. Unit 2 is at 100% power.

4/'2 0/oq ~

3. Today, during routine operator rounds, at 0600 on 4122109, an SO found the lZ41-COI2A, Main Control Room filter train fan breaker tripped and can not be reset.

) 4. The last surveillance for the fan was successfully completed on 03/25/09.

5. The remaining filter train fan and the three air handling units and associated fans are operable.

INITIATING CUES: Complete sections 1 and 2 of a Required Action Sheet, form OPS-1349, for Unit 1 for lZ41-COI2A, Main Control Room filter train fan.

For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. START TIME: _ _ __

1. Operator obtains the procedure needed Operator has obtained procedure SAT IUNSAT to perform the task. Unit 1 tech spec NOTE: Provide the candidate with a blank RAS form, OPS 1349. Have a spare RAS form available.

PROMPT: WHEN the operator indicates he would look in the Required Action Tracking Log for a RAS number, INFORM him that the number is 1-09-027.

2. I Assign a RAS number from the Writes in 1-09-027 as the SAT I UNSAT Required Action Tracking Log. Required Action Sheet Number.

3. I Locates the appropriate tech spec Addresses Unit 1 tech spec SAT/UNSAT section. section 3.7.4 Action A.

Writes lZ41-C012A, In the MPL SAT /(JNSAT block. Writes MCREC fan or a similar SAT /UNSAT name In the Description block.

                                             'I Writes 0600 for the time and        SAT IUNSAT 4/22/09 for the date in the Inoperable time/date block.

7. I Reviews the RAS section 1 "Return to \¥rites nothing in the Return To Sl\T IUNSAT Oper" time/date block. OPER Time/Date block.

8. I Reviews the RAS section 1 "lnit" Writes nothing in the !NIT block. SAT 1 UNSAT block Writes time of 0600 and date of SAT 1 UNSAT 4/22/09 in the Initiation Time/Date block of section 2.

Writes a time of 0600 and a date SAT/UNSAT of 4/29/09 in the REQ RES TORA TION TimelDate block of section 2.

11. I Completes the RAS section 2 Writes N/A or similar wording in SAT IUNSAT "Modified Completion" Time/Date the Modified Completion Time/Date block of section 2.

l , 1

12. Completes the RAS section 2 "Extended Completion TimelDate/Init" block.

Writes N/A or similar wording in the Extended Completion TimelDatelInit block in section 2. SAT/UNSAT

13. Completes the RAS section 2 "SFDP Marks the N/A box of the SFDP SAT/UNSAT Entered" block. Entered block NOTE: If candidate asks to see the Status Indication, hand the candidate a picture of the status indicators.

14. I Completes the RAS section 2 "INOP Marks the yes box of the INOP SAT/UNSAT Status Indication" block. Status Indication Block after directing personnel to switch the light on.

PROMPT: WHEN asked to tum on the status indication light, the operator the light is now on. Writes Modes 1, and 3, During SAT/UNSAT movement of irradiated fuel assemblies in the secondary contaimnent, During Core Alterations, During operations with a potential for draining the reactor vessel, (OPDRVs). In the Applicability block of section 2. Writes, D.l Place OPERABLE SAT/UNSAT MCREC subsystem pressurization mode Immediately OR D.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment Immediately AND D.2.2 Suspend CORE ALTERATIONS Immediately AND D.2.3 Initiate actions to suspend OPDRVs. Immediately, in the Required Action if Comp time is exceeded block.

17. I Completes the RAS section 2 Writes tech spec 3.7.4 in the SAT I UNSAT "Reference Document" block. reference block of section 2.

18. I Completes the RAS section 2 rites 225 in the SAT /UNSAT "Revision!Amendment" block. Revision/Amendment block.

19. I Completes the RAS section 'Writes "3.7.4.A.l" (or similar) in SAT /UNSAT "Reference Document" block. the "Reference Document" block

20. Completes the RAS section 4, Writes "Restore MCREC SAT/UNSAT "Required Action" block. subsystem to Operable status" in the Required Action block.

21. Completes the RAS section 4, "Req Writes "7 days" in the Req Comp SAT I UNSAT Comp Time ofFreq" block. Time of Freq block.

END TIME:. _ - - - NOTE: The terminating cue shall be given to the Applicant when:

                 -  With no reasonable progress, the Applicant exceeds double the allotted time.
                 -  Applicant states the task is complete.

TERMINATING CUE: That completes this JPM.

SOUTHERN NUCLEAR For Examiner-Training Use Only PAGE 1 OF 3 PLANT E.I. HATCH FORM TITLE: REQUIRED ACTION SHEET REQUIRED ACTION SHEET NUMBER SECTION 1 INITIATING CONDITIONS RETURN TO INOPERABLE MPL DESCRIPTION OPER INIT TIME/DATE TIMEIDATE 1Z41-C012A MCREC fan 0600 J4/22/09 J SECTION 2 REQUIRED ACTION SHEET ACTIVATION INITIATION TIME/DATE REO. RESTORATION TIME/DATE MODIFIED COMPLETION 0600 4/22/09 0600 4/29/09 TIME/DATE N/A EXTENDED COMPLETION SFDP ENTERED INOP STATUS INDIC LIT TIME/DATE/INIT N/A DYES lZIN/A lZIYES DN/A APPLICABILITY Modes 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During Core Alterations, During operations with a potential for draining the reactor vessel, (OPDRVs). REO. ACTION 0.1 Place OPERABLE MCREC subsystem in pressurization mode Immediately IF COMPTIME OR EXCEEDED 0.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment Immediately AND 0.2.2 Suspend CORE ALTERATIONS Immediately AND 0.2.3 Initiate actions to suspend OPDRVs. Immediately. REFERENCE TS 3.7.4 REVISION/AMENDMENT DOCUMENT 225 SS SIGN / TSA ACTIVE SOS SIGN I OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S

SOUTHERN NUCLEAR For Examiner-Training Use Only PAGE 2 OF 3 PLANT E.I. HATCH FORM TITLE: REQUIRED ACTION SHEET SECTION 5 REQUIRED ACTION SHEET TERMINATION INDICATE COMPLETE(D) ACTIONS: D PROCEDURES: D OTHER: MWOFT INOP STATUS INDIC OFF REQUIRED ACTION TERMINATED TIME/DATE COMPLETE DYES DN/A DYES DN/A SS SIGN / TSA TERMINATED SOS SIGN

         -_ .. -  - - _ ....... -                                   I SECTION 3                                         < 1 HOUR ACTIONS REFERENCE                         REQUIRED ACTION          REQ. COMP TIME      PERFORMED        INIT DOCUMENT                                                                       TIME/DATE
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SECTION 4 > 1 HOUR ACTIONS REFERENCE REQUIRED ACTION REQ. COMP TIME OR I SEQ. I COMPLETE I COMPo DOCUMENT FREQ. NO. TIME/DATE INITIAL Restore MCREC subsystem 7 days / to Ooerable Status. OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S

SOUTHERN NUCLEAR For Examiner-Training Use Only PAGE 3 OF 3 PLANT E.!. HATCH FORM TITLE: REQUIRED ACTION SHEET

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OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S

SOUTHERN NUCLEAR PAGE 1 OF 2 PLANT E.!. HATCH FORM TITLE: REQUIRED ACTION SHEET REQUIRED ACTION SHEET NUMBER SECTION 1 INITIATING CONDITIONS RETURN TO INOPERABLE MPL DESCRIPTION OPER INIT TIME/DATE TIME/DATE SECTION 2 REQUIRED ACTION SHEET ACTIVATION INITIATION TIMEIDATE REQ. RESTORATION TIME/DATE MODIFIED COMPLETION TIMEIDATE EXTENDED COMPLETION SFDP ENTERED INOP STATUS INDIC LIT TIME/DATE/INIT DYES DN/A DYES DN/A APPLICABILITY REQ. ACTION IF COMP TIME EXCEEDED REFERENCE REVISION/AMENDMENT DOCUMENT SS SIGN / TSA ACTIVE SOS SIGN I SECTION 5 REQUIRED ACTION SHEET TERMINATION INDICATE COMPLETE(D) ACTIONS: D PROCEDURES: D OTHER: MWOFT INOP STATUS INDIC OFF REQUIRED ACTION TERMINATED TIMEIDATE COMPLETE DYES DN/A DYES DN/A SS SIGN / TSA TERMINATED SOS SIGN I OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S

SOUTHERN NUCLEAR PAGE 2 OF 2 PLANT E.1. HATCH FORM TITLE: REQUIRED ACTION SHEET SECTION 3 < 1 HOUR ACTIONS REFERENCE REQUIRED ACTION REQ. COMP TIME PERFORMED INIT DOCUMENT TIME/DATE

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SECTION 4 > 1 HOUR ACTIONS REFERENCE DOCUMENT REQUIRED ACTION I REQ. COMP TIME OR FREQ. I SEQ. NO. I COMPLETE I COMPo TIMEIDATE INITIAL

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OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S

SOUTHERN NUCLEAR PAGE 1 OF 2 PLANT E.I. HATCH FORM TITLE: REQUIRED ACTION SHEET REQUIRED ACTION SHEET NUMBER SECTION 1 INITIATING CONDITIONS RETURN TO INOPERABLE MPL DESCRIPTION OPER INIT TIMEIDATE TIMEIDATE SECTION 2 REQUIRED ACTION SHEET ACTIVATION INITIATION TIME/DATE REQ. RESTORATION TIME/DATE MODIFIED COMPLETION TIME/DATE EXTENDED COMPLETION SFDP ENTERED INOP STATUS INDIC LIT TIMEIDATE/INIT DYES DN/A DYES D N/A APPLICABILITY REQ. ACTION IFCOMPTIME EXCEEDED REFERENCE REVISION/AMENDMENT DOCUMENT SS SIGN / TSA ACTIVE SOS SIGN I SECTION 5 REQUIRED ACTION SHEET TERMINATION INDICATE COMPLETE(D) ACTIONS: D PROCEDURES: D OTHER: MWOFT INOP STATUS INDIC OFF REQUIRED ACTION TERMINATED TIME/DATE COMPLETE DYES DN/A DYES DN/A SS SIGN / TSA TERMINATED SOS SIGN I OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S

SOUTHERN NUCLEAR PAGE 2 OF 2 PLANT E.I. HATCH FORM TITLE: REQUIRED ACTION SHEET SECTION 3 < 1 HOUR ACTIONS REFERENCE REQUIRED ACTION REQ. COMP TIME PERFORMED INIT DOCUMENT TIMEIDATE

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SECTION 4 > 1 HOUR ACTIONS REFERENCE DOCUMENT REQUIRED ACTION I REQ. COMP TIME OR FREQ. I SEQ. NO. ICOMPLETE I COMPo TIMEIDATE INITIAL

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OPS-1349 Rev 0 G16.30 31 GO-OPS-006-0S

SOUTHERN NUCLEAR DOCUMENT TYPE: PAGE PLANT E. I. HATCH GENERAL OPERATING PROCEDURE 1 OF 15 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES 31 GO-OPS-006-0 5.6 EXPIRATION APPROVALS: EFFECTIVE DATE: DEPARTMENT MGR C. R. Dedrickson DATE 09-16-99 DATE: N/A NPGM/POAGM/PSAGM 1-24-08 N/A DATE N/A 1.0 OBJECTIVE This procedure provides guidance for documenting events which cause entry into CONDITIONS, thus causing REQUIRED ACTIONS to be performed within the specified COMPLETION TIMES. These items are specified by the Unit Technical Specifications (TS), Offsite Dose Calculation Manual (ODCM), Technical Requirements Manual (TRM), Holtec Technical Specifications (HTS), AND the Safety Function Determination Program. This procedure also provides administrative tracking of items required by other plant procedures (34GO-OPS-001-1/2). TABLE OF CONTENTS Section Page 2.0 APPLICABILITY .................................................................................................................. 2

3.0 REFERENCES

................................................................................................................... 3 4.0 REQUIREMENTS ............................................................................................................... 4 5.0 PRECAUTIONS/LIMITATIONS ........................................................................................... 6 6.0 PREREQUISITES ............................................................................................................... 6 7.0 PROCEDURE ..................................................................................................................... 7 7.1 INITIATION OF A REQUIRED ACTION SHEET ........................................................... 7 7.2 TERMINATING REQUIRED ACTION SHEETS .......................................................... 11 7.3 INITIATING REQUIRED ACTION SHEET ON SSCs NOT REQUIRED TO BE OPERABLE DUE TO EXISTING PLANT CONDITIONS ............................................. 12 7.4 WO STATUS SHEET .................................................................................................. 13 7.5 EXTENDED COMPLETION TIMES ............................................................................ 13 Attachments 1    RAS WO FUNCTIONAL TEST SHEET ............................................................................. 14 MGR-0002 Rev 8

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH DOCUMENT TITLE: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES I DOCUMENT NUMBER: 31 GO-OPS-006-0 2 OF 15 VERSION NO: 5.6 2.0 APPLICABILITY 2.1 DEFINITION OF TERMS

• COMPLETION TIME: That part of a REFERENCE DOCUMENT that specifies the time frame during which a specified action must be completed. For the TRM, HTS, and the TS, these are specified in a column clearly labeled COMPLETION TIME. For FHA Appendix B and the ODCM these are contained within the sections labeled ACTION.
• CONDITION: That part of a REFERENCE DOCUMENT that specifies a situation (e.g., one PSW pump inoperable) for which the specified action must be completed in a specified time. For the TRM, HTS, and the TS, these are specified in a column clearly labeled CONDITION. For the FHA Appendix B and the ODCM these are contained within the sections labeled ACTION.
• REFERENCE DOCUMENT: A term used in this procedure to mean anyone of the following: TS, ODCM, HTS, or TRM.
• REQUIRED ACTION: That part of a REFERENCE DOCUMENT that prescribes actions to be taken under designated CONDITIONS within specified COMPLETION TIMES. For the TRM, HTS, and the TS, these are specified in a column clearly labeled REQUIRED ACTION. For the FHA Appendix B and the ODCM these are contained within the sections labeled ACTION.

2.2 OPERATIONS SUPERVISORY PERSONNEL Responsible for the determination of REFERENCE DOCUMENT applicability, documentation of entry into CONDITIONS, AND compliance with REQUIRED ACTIONS/COMPLETION TIMES. 2.3 LIMITING CONDITION FOR OPERATION Use of the term "LCO" and TRACKING ACTION SHEETS in other procedures is equivalent to use of REQUIRED ACTION. MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 3 OF 15 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES 31 GO-OPS-006-0 5.6

3.0 REFERENCES

3.1 30AC-OPS-003-0, Plant Operations 3.2 Technical Specifications Unit 1 3.3 Technical Specifications Unit 2 3.4 Unit 1 Technical Requirements Manual (Unit 1 TRM) 3.5 Unit 2 Technical Requirements Manual (Unit 2 TRM) 3.6 Off Site Dose Calculation Manual (ODCM) 3.7 Safety Function Determination Program 3.8 Holtec Technicat Specifications 3.9 FULL SIZE FORM (S)

• OPS-1349 Required Action Sheet
• OPS-1350 Required Action Tracking Sheet
• OPS-1351 WO Status Sheet
• OPS-1352 Required Action Tracking Log 3.10 NMP-AD-012 Operability Determination and Functionality Assessments for Resolution of 'I Degraded and Nonconfomring Conditions MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 4 OF 15 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES 31 GO-OPS-006-0 5.6 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS N/A Not applicable to this procedure 4.2 MATERIAL AND EQUIPMENT N/A Not Applicable to this procedure 4.3 SPECIAL REQUIREMENTS 4.3.1 A REQUIRED ACTION SHEET (RAS) (OPS-1349) SHALL be initiated for the following conditions: 4.3.1.1 A Loss of Safety Function is determined to exist WHEN evaluated per Attachment 1 of the TRM T 12.0, Safety Function Determination Program. The RAS is to be initiated on the Structures, Systems, or Components (SSCs) determined to have a loss of safety function as evaluated from the preceding. 4.3.1.2 Equipment is out of service OR INOPERABLE, AND its downtime OR time in a condition is limited by plant licensing documents such that this time requires tracking UNTIL the time is reset (e.g., RWM, RCS Chemistry). 4.3.1.3 WHEN Corrective Maintenance is to be performed on Tech. Spec. applicable SSCs. 4.3.2 A RAS SHALL be initiated whenever one of the following conditions exists AND will remain in existence at the end of the shift: 4.3.2.1 An INOPERABILITY of required systems, structures or components (SSCs) required by a REFERENCE DOCUMENT. IF the INOPERABLE SSC does NOT result in a Loss of Safety Function (refer to 4.3.1.1), the RAS will be initiated for ONLY the Support SSC. 4.3.2.2 Preventative maintenance is performed on a SSC required by a REFERENCE DOCUMENT. 4.3.2.3 WHEN selected Non-LCO support systems are INOPERABLE AND other plant procedures require the initiation of a RAS (e.g., 34GO-OPS-001-1/2 specifies Cold Reference Leg Keepfill System). 4.3.2.4 WHEN a surveillance OR ACTION is required to be performed (other than maintaining alternate systems OR components OPERABLE) in order to comply with RASs. MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 5 OF 15 DOCUMENT TITLE: I I DOCUMENT NUMBER: VERSION NO: _~ONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES 31 GO-OPS-006-0 5.6 4.3.2.5 For instrumentation, the TS and the TRM usually provide allowances when an instrument is out of service for required Surveillances (e.g., "when a channel is placed in an INOPERABLE status solely for performance of required Surveillances. Entry into associated CONDITIONS and REQUIRED ACTIONS may be delayed for up to 6 hours.") for these instruments. IF testing/maint. is being performed on these instruments that is NOT required Surveillance, entry into associated CONDITIONS can NOT be delayed. 4.3.2.6 WHEN a surveillance is performed which does NOT maintain channel ANDIOR function capability as required by a REFERENCE DOCUMENT. 4.3.2.7 WHEN a channel is placed in an INOPERABLE mode for the performance of a required surveillance for a time exceeding the REFERENCE DOCUMENT allowable surveillance time. 4.3.3 Conventions for Use when a RAS Is NOT Required. Corrective Maintenance must be tracked by a RAS. 4.3.3.1 A RAS DOES NOT have to be initiated for a REQUIRED ACTION (Except For Corrective Maintenance) that WILL NOT be in effect at the end of the shift; however, the SS will perform the following: 4.3.3.1.1 Notify the SM of the INOPERABILITY. 4.3.3.1.2 ENTER the time the REQUIRED ACTION is active, the CONDITION initiating the ACTION, and the applicable REQUIRED ACTION specification number (e.g., TS LCO 3.3.2.2, REQUIRED ACTION A.1) into the MCR Log. 4.3.3.1.3 ENTER any actions taken to comply with the CONDITION in the MCR Log. 4.3.3.1.4 WHEN the CONDITION is no longer applicable, ENTER the time and the action(s) that terminated the CONDITION in the MCR Log. 4.3.3.1.5 Notify the SM the CONDITION I REQUIRED ACTION was terminated. 4.3.3.2 WHEN Required Surveillances are performed, the equipment MPL and time will be logged in the MCR Log to track time out of service, UNLESS the procedure being performed has provisions for tracking the time out of service. 4.3.3.3 WHEN equipment is returned to service per TS 3.0.5, ENTER the time returned to service in the MCR Log. THEN comply with one of the following: 4.3.3.3.1 IF the equipment is NOT being restored to an OPERABLE status, indicate in the MCR Log that control of the equipment is being returned to the RAS. MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 6 OF 15 DOCUMENT TITLE: I DOCUMENT NUMBER: IVERSION NO: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES 31 GO-OPS-006-0 5.6 __ 4.3.3.3.2 IF the equipment is being restored to an OPERABLE status, close out the RAS, and so state in the MCR Log. 4.3.4 Conventions for Use WHEN a RAS IS required 4.3.4.1 IF separate entry CONDITIONS are allowed by a REFERENCE DOCUMENT, initiate separate REQUIRED ACTION TRACKING SHEETs. Exceptions to separate entries can be made for Conditional Tracking Actions WHEN the first entry was NOT one of the required functions OR channels (e.g., APRMs). 4.3.4.2 IF Separate entry conditions are NOT allowed by a REFERENCE DOCUMENT, . ENTER any subsequent INOPERABILITIES on the original REQUIRED ACTION TRACKING SHEET, including the time and date of the subsequent event. THE ORIGINAL TIME AND DATE OF CONDITION ENTRY WILL REMAIN THE SAME. 4.3.5 This procedure provides guidance for tracking REQUIRED ACTIONS. Under extenuating circumstances, policies for tracking REQUIRED ACTIONS may be altered by the Operations Manager OR his Designee, provided no REFERENCE DOCUMENT requirement is violated AND the intent of Section 1.0 of this procedure is met. 4.3.6 When the PLANT HATCH RAS/FAS LIST is updated, RA8's with Required Actions greater than one week (7 days), will have the COMPLETION DATE normally set at one half (1/2) the REQUIRED DATE. (e.g.: for a 30 day RAS, the COMPLETION DATE would be 15 days). Operations Management approval will be required to extend the COMPLETION DATE beyond one half of the REQUIRED DATE. 4.3.7 Blocks that are NOT required to be completed may be left blank without being NA'd.* 4.3.8 Any WO's requiring an ASME inspection will be added to a RAS. Even for non Tech Spec systems, a Tracking RAS will be initiated when operations is informed that the work order requires an ASME inspection. 5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS N/A - Not applicable to this procedure 5.2 LIMITATIONS N/A - Not applicable to this procedure 6.0 PREREQUISITES N/A - Not applicable to this procedure MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 7 OF 15 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES 31 GO-OPS-006-0 5.6 7.0 PROCEDURE 7.1 INITIATION OF A REQUIRED ACTION SHEET CONTINUOUS I 7.1.1 Initiate a REQUIRED ACTION SHEET (RAS) (Form OPS-1349) by performing the following: 7.1.1.1 Assign a RAS NUMBER from the REQUIRED ACTION TRACKING LOG (Form OPS-1352). RAS numbers may be pre-assigned as determined appropriate. 7.1.1.2 ENTER the MPL number in the MPL block and the description of the SSC in the DESCRIPTION block in Section 10f OPS-1349 of the REFERENCE DOCUMENT required component. 7.1.1.3 ENTER the time and date the SSC became INOPERABLE in the INOPERABLE TIMEIDATE block in Section 1 of OPS-1349. 7.1.1.4 WHEN separate entry conditions are NOT allowed, ENTER subsequent, INOPERABLE items on the same RAS (OPS-1349) MPL, DESCRIPTION, and INOPERABLE blocks. The time and date for subsequent equipment will be WHEN the subsequent INOPERABILlTYoccurs. This discussion refers to subsequent INOPERABILITY of items for the same CONDITION. 7.1.1.5 IF plant / equipment conditions are such that the equipment is NOT presently required to be OPERABLE, go to 7.3. 7.1.1.6 ENTER the INITIATION, TIME/DATE data in Section 2 of the RAS. This is the time the equipment is required to be OPERABLE OR becomes required to be OPERABLE by plant conditions. 7.1.1.7 ENTER the REQUIRED RESTORATION TIME/DATE in Section 2 of the RAS. This time is determined from the more restrictive of either the REQUIRED ACTION time OR the MODIFIED COMPLETION TIMEIDATE. MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 8 OF 15 DOCUMENT TITLE: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES 31 GO-OPS-006-0 I DOCUMENT NUMBER: VERSION NO: 5.6 7.1.1.8 IF applicable (e.g., TS LCO 3.1.7, TS LCO 3.8.1), ENTER the MODIFIED COMPLETION TIMEIDATE in Section 2. 7.1.1.8.1 This time is the maximum allowable time that is allowed for failing to meet a REFERENCE DOCUMENT CONDITION / REQUIRED ACTION (e.g., TS LCO 3.1.7, REQUIRED ACTION A.1 has a MODIFIED COMPLETION TIME/DATE of 10 days for SLC). 7.1.1.8.2 This time is the same for subsequent INOPERABLE equipment which occurs while related TS LCO INOPERABLE equipment exists (e.g., SBLC pump A is INOPERABLE on day 1 and, then, on day 2 the SLC Tank fails to meet a requirement. The MODIFIED COMPLETION TIME for the tank and any subsequent entries would be the same as for SBLC pump A OR 10 days from the day 1 entry into the TS LCO REQUIRED ACTIONS.). 7.1.1.9 Indicate the applicability of the Safety Function Determination Program in the SFDP ENTERED block of Section 2. 7.1.1.10 Check appropriate box in the INOP STATUS INDIC LIT block of Section 2 for the inoperable equipment status indicators. 7.1.1.11 ENTER CONDITIONS, plant modes AND/OR applicability of the equipment OR CONDITION in the APPLICABILITY block of Section 2. 7.1.1.12 RECORD the REFERENCE DOCUMENT in the block of the same name of Section 2. (e.g., Unit 1 TS 3.6.1). 7.1.1.13 RECORD the REFERENCE DOCUMENT revision or amendment number in the REVISION/AMENDMENT block of Section 2. 7.1.1.14 ENTER the REQUIRED ACTION in the REQ. ACTION IF COMP TIME IS EXCEEDED block of Section 2, using the following: 7.1.1.14.1 ENTER the REQUIRED ACTION Number as shown in the REFERENCE DOCUMENT block of Section 2 (e.g., TS LCO 3.6.1.1, REQUIRED ACTION D.1). THEN, fill in the REFERENCE DOCUMENT, REQUIRED ACTION, REQ. COMP TIME OR FREQ., AND SEQ NO. blocks of Section 4. AND/OR 7.1.1.14.2 ENTER the ACTION required (e.g., Be in Mode 3 in 12 hours and in Mode 4 in 36 hours.) 7.1.1.15 SS signs SS SIGNITSA ACTIVE block of Section 2 of the RAS, signifying the sheet is active. 7.1.1.16 SM reviews and signs SM SIGN block of Section 2, indicating concurrence with the RAS. MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 9 OF 15 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES 31 GO-OPS-006-0 5.6 7.1.1.17 As equipment is returned to OPERABLE status, ENTER the time/date in the RETURN TO OPER TIME/DATE block AND initial in the INIT block of Section 1. 7.1.2 PERFORM the following in the ~ 1 HOUR ACTIONS section (section 3) of the RAS: 7.1.2.1 ENTER the REFERENCE DOCUMENTand section number in the appropriate block (e.g., TS LCO 3.4.1). 7.1.2.2 ENTER the REQUIRED ACTION as specified above (e.g., REQUIRED ACTION C.1: ENTER 3.0.3) using separate lines for each ACTION containing multiple parts. IF the REFERENCE DOCUMENT allows a choice of REQUIRED ACTIONS, list only the one chosen. 7.1.2.3 ENTER the REQ COMP TIME block. 7.1.2.4 ENTER the Time and Date the ACTION is completed in the PERFORMED TIMEIDATE block and initial in the INIT block WHEN the ACTION is completed. 7.1.3 PERFORM the following in the> 1 HOUR ACTIONS section (section 4): 7.1.3.1 ENTER the REFERENCE DOCUMENT and section number in the REFERENCE DOCUMENT block (e.g., TS 3.1.7, REQUIRED ACTION A.1). 7.1.3.2 ENTER the REQUIRED ACTION specified above in the REQUIRED ACTION block using the following guidelines: 7.1.3.2.1 WHEN more than one ACTION is required, use separate lines for each ACTION. 7.1.3.2.2 IF an ACTION is required to be performed initially and at specified intervals thereafter, use separate lines to track each requirement, IF the time intervals are different (e.g., 1 hour versus 8 hours). 7.1.3.2.3 INITIATE a REQUIRED ACTION TRACKING SHEET (Form OPS-1350) for each REQUIRED ACTION recurring at routine / periodic intervals. 7.1.3.3 ENTER the required completion time OR the Frequency at which the ACTION is to be performed in the FREQUENCY block of OPS-1350. 7.1.3.4 IF an ACTION is required to be performed at recurring intervals, assign a sequential number (e.g., 1,2,3, etc.) in the SEQUENCE block of OPS-1350 for each action to be tracked. 7.1.3.5 ENTER the Logical Connector(s) in the appropriate spaces beneath the REQUIRED ACTION block in Section 4 of OPS-1349 containing multiple parts. IF no logical connector is entered, "LEVEL 1 AND" is implied. ENTER the Logical Connector at the appropriate level of indention. MGR-0001 Rev 4 .

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 10 OF 15 DOCUMENT TITLE: ~f\lDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES IDOCUMENT NUMBER: IVERSION NO: 31 GO-OPS-006-0 5.6 7.1.3.6 WHEN the subsequent action has been completed, THEN ENTER the time and date in the COMPLETE TIME/DATE block in Section 4 on OPS-1349. 7.1.3.7 SS initials the COMP INITIAL block in Section 4 of OPS-1349, signifying all subsequent ACTIONS for the line have been completed. 7.1.3.8 SS close out the item in the REQUIRED ACTION TRACKING LOG (Form OPS-1352.). MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH DOCUMENT TITLE: . CONDITIONS, REQUIRED ACTIONS, AND COMPL~IION TIMES I 11 OF 15 I DOCUMENT NUMBER: VERSION NO: 31 GO-O~S=Q96-0 . . 5.6 7.2 TERMINATING REQUIRED ACTION SHEETS CONTINUOUS I 7.2.1 PERFORM the following WHEN terminating RASs: 7.2.1.1 ENTER the time and date the CONDITION no longer exists in the RETURN TO OPER TIMEIDATE block in Section 1 of OPS-1349. 7.2.1.2 ENTER SS initials in the INIT block in Section 1 of OPS-1349, signifying the equipment has been returned to an OPERABLE status. 7.2.1.3 Complete INDICATE COMPLETE (D) ACTIONS block in Section 5 of OPS-1349 to document procedure(s) / other action that were satisfactorily completed to terminate the RAS. 7.2.1.4 Check appropriate check box in the WO FT COMPLETE block in Section 5 of OPS-1349 for all WO functional tests completed satisfactorily. Attachment 1 can be used to perform Functional Test on WO against a RAS. Once the FTs on Att 1 are complete and a check is made to ensure this list contains all associated FTs for the RAS then proceed with RAS Termination. 7.2.1.5 Check appropriate check box in the INOP STATUS INDIC OFF block in Section 5 of OPS-1349 for the inoperable status indicator. 7.2.1.6 ENTER the Time and Date the RAS is terminated in the REQUIRED ACTION TERMINATED TIME/DATE block in Section 5 of OPS-1349. 7.2.1.7 SS signs SS SIGN/TSA TERMINATED block AND SM signs SM SIGN block in Section 5 of OPS-1349 terminating the RAS. 7.2.1.8 IF Attachement 1 was used as a method to perform the WO FTs for the RAS then use this information to sign off the actual WOs listed on the attachment. MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 12 OF 15 DOCUMENT TITLE: I I DOCUMENT NUMBER: VERSION NO: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES 31 GO-OPS-006-0 5.6 7.3 INITIATING REQUIRED ACTION SHEET ON SSCs NOT REQUIRED TO BE OPERABLE DUE TO EXISTING PLANT CONDITIONS CONTINUOUS I 7.3.1 WHEN the equipment OR CONDITION does NOT apply due to current plant / equipment conditions (Conditional Tracking Actions), perform the following: 7.3.1.1 Check appropriate box in INOP STATUS IN DIC LIT block in Section 2 of OPS-1349 for the inoperable equipment status indicators. 7.3.1.2 ENTER CONDITIONS, plant modes AND/OR applicability of the equipment OR CONDITION in the APPLICABILITY block in Section 2 of OPS-1349. 7.3.1.3 RECORD the REFERENCE DOCUMENT in the REFERENCE DOCUMENT block in Section 2 of OPS-1349. (e.g., Unit 1 TS LCO 3.6.1, REQUIRED ACTION A.1) 7.3.1.4 RECORD the REFERENCE DOCUMENT revision or amendment number in REVISION/AMENDMENT block in Section 2 of OPS-1349. 7.3.1.5 SS INITIALS the SS SIGN/TSA ACTIVE block. The SS SIGNS this block WHEN the RAS becomes active. 7.3.1.6 SM INITIALS the SM SIGN block. The SM SIGNS this block WHEN the RAS becomes active. 7.3.1.7 Complete the remainder of the REQUIRED ACTION TRACKING SHEET (per steps 7.1.1.5 through 7.1.4) WHEN the equipment becomes required to be OPERABLE by plant / equipment conditions. The Initiation Time and Date is WHEN plant / equipment conditions are such that the equipment is required to be OPERABLE. MGR-0001 Rev 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 13 OF 15 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: CONDITIONS, REQUIRED ACTIONS, AND COMPLETION TIMES -~-----.- ------------------ 31 GO-OPS-006-0 5.6 7.4 WO STATUS SHEET CONTINUOUS I 7.4.1 WOs (can also be used for Deficiencies and procedures) are tracked using one of the following methods: 7.4.1.1 The RAS number is written on the WO, THEN the WO is updated in the Document Management System with the RAS number (preferred method), OR 7.4.1.2 The WO number is recorded on the WO Status Sheet (Form OPS-1351). 7.4.2 WHEN entering information on the WO Status Sheet, record the following: 7.4.2.1 The RAS number 7.4.2.2 The Equipment MPL number 7.4.2.3 The current date 7.4.2.4 The applicable WO, Condition Report number OR procedure number 7.4.2.5 The Description of the equipment OR problem 7.4.2.6 The completion date. This is to be entered WHEN work on WO OR procedure is complete AND all functional testing is completed satisfactorily. 7.4.2.7 SS initials the appropriate block signifying WO no longer holding equipment INOPERABLE. 7.5 EXTENDED COMPLETION TIMES CONTINUOUS I Completion Times for multiple entry conditions may be extended using the guidance in TS 1.3. WHEN using Extended Completion Times, determine the permissible Extended Completion Time per TS 1.3, AND enter it in EXTENDED COMPLETION TIMEIDATE/INIT block in Section 2 of OPS-1349. MGR-0001 Rev 4

SNC PLANT E. I. HATCH I Pg 14 of 15 DOCUMENT TITLE: DOCUMENT NUMBER: RevIVer No: CONDITIONS, REQUIRED ACTIONS, AND 31 GO-OPS-006-0S 5.6 COMPLETION TIMES ATTACHMENT _1 Attachment Page TITLE: RAS WO FUNCTIONAL TEST SHEET 1 of 2 RAS# _____________ This is a list of the actions required to terminate this RAS. Page 2 contains the list of components being tested. Procedure Number I Completion Section to perform Other actions Date: Initials: SRO Approval: Date: _ _ _ _ _ __ MGR-0009 Rev 5

SNC PLANT E. I. HATCH I 1=>9 15 of 15 ) DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No: CONDITIONS, REQUIRED ACTIONS, AND 31 GO-OPS-006-0S 5.6 COMPLETION TIMES ATTACHMENT -1. Attachment Page TITLE: RAS WO FUNCTIONAL TEST SHEET 2 of 2 Attach a copy of a RAS report listing the WO and FT to this page. Section of procedure Procedure Number OR I Work Order to be performed or COMP MPL NO. FT if not a procedure INIT. Number ALL or NA if no DATE (leak check, etc.)

       ---
                              -       -    ---- - - - - -- - _ . - ----

_pr()cedure ---- Prepared By (SRO): _ _ _ _ _ _ _ _ _ _ __ Date:

• Use additional sheets if more space is needed.
• This sheet does not become a permanent record in Documentum as a form.
• A copy of this package may be attached to the RAS being teminated as a record of FT performance.

MGR-0009 Rev 5

FINAL 04/06/09 Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 4 NIR SOUTHERN . . ' COMPANY Energy to Serve Your World SM

lSOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of1 !FORM TITLE: TRAINING MATERIAL REVISION SHEET Pro~amlCourse Code: OPERATIONS TRAINING Media Number: LR-JP-I0029

UNIT 1 (X) UNIT 2 0 Declare A Tech Spec System Operable/Inoperable LR-JP-I0029-00 The task shall be completed when the candidate has provided an answer for each item within the initiating cue. H-OPSR300.006 H-OP300.006A SRO Administrative PLANT HATCH JTA IMPORTANCE RATING: RO N/A SRO 3.00 KIA CATALOG NUMBER: G2.3.11 KIA CATALOG JTA IMPORTANCE RATING: RO N/A SRO 4.3 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO) Unit 1 TRM Unit 1 ODCM 34AR-650-350-1, HX IA PSWIRBCCWDIFF PRESS LOW Annunciator APPROXIMATE COMPLETION TIME: 20 Minutes SIMULATOR SETUP: N/A

UNIT 1 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 1 is in Mode 3 with the "B" RBCCW Heat Exchanger out of service and under clearance.

2. Maintenance reports scaffolding has fallen on a radiation detector, IDll-K605, severing its electrical cable and causing other damage.

3. It is estimated it will be 2 months before a replacement can be delivered.

4. While restoring the "B" RBCCW Heat Exchanger to service the following alarms occurs:

• Annunciator 650-350-1,"HX lA PSWIRBCCW DIFF PRESS LOW," alarms

5. An SO reports the following local pressures:

• PSW pressure indicator IP41-R577 ....................... 96 psig

("A" Heat Exchanger PSW Inlet pressure)

• PSW pressure indicator IP41-R578 ..................... 89 psig

("A" Heat Exchanger PSW Outlet pressure)

• RBCCW pressure indicator IP42-R002A, ............. 92 psig

("A" Heat Exchanger RBCCW Inlet pressure)

• RBCCW pressure indicator IP42-R005A, ............. 87 psig

("A" Heat Exchanger RBCCW Outlet pressure) INITIATING CUES: Determine if the radiation detector is)\required at this time and any other additional actions.

For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. NOTE: Provide candidate ARP 650-350-1 START TIME: _ _ __

1. Operator obtains the procedure needed Operator has obtained the Unit 1 SAT I UNSAT references ODCM and other controlled documents.

Note: The candidate has several means to find the specification for this radiation detector. One is to use the Master Equipment Cross Reference in the Unit 1 TRM, another is the Tech Spec/TRM/ODCM reference section of the ARP. Operator determines the SAT/UNSAT instrument is a required ODCM detector. The candidate identifies that SAT I UNSAT requirements associated with this ODCM section 2.1 contains the radiation detector. requirements for this radiation detector being inop.

4. I Selects the applicable instrument on On table 2-1 determines the SAT I UNSAT table 2-1 of the Unit 1 ODCM. inoperative detector is addressed in section 2 of the table, as this instrument does not provide any automatic isolation.

5. I Evaluates whether the minimum Recognizes the minimum number SAT/UNSAT number of channels OPERABLE is of channels is NOT met.

met from table 2.

6. I Evaluates the applicability of the Determines note (2) applies: SAT/UNSAT specification, whether the instrument * "Whenever the Service is required to be OPERABLE, under Water System pressure is the current plant conditions. below the Closed Cooling Water System pressure, or

                                                    ~p indication is not available."

I '~'>"

7. Evaluates the system pressure between Determines the lowest PSW SAT/UNSAT PSW and RBCCW. pressure of 89 psig IS lower than the most limiting RBCCW pressure of 92 psig and DP must be re-established.

PROMPT: IF candidate indicates pressure needs to be adjusted per the ODCM or ARP, THEN inform him that that the cause of the low pressure is being investigated. Determines that once per shift SAT I UNSAT grab samples are collected and analyzed for a gross radioactivity. Identifies that if the instrument is SAT/UNSAT inoperative for over 30 days:

                                                        * "An explanation of the circumstances must be included in the next Radioactive Effluent Release Report."

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

                       -   With no reasonable progress, the Applicant exceeds double the allotted time.
                       -   Applicant states the task is complete.

TERMINATING CUE: That completes this JPM.

1.0 IDENTIFICATION

ALARM PANEL 1H11*P650 HX1A PSW/RBCCW DIFF

                                                        ~

DIFF PRESS LOW DEVICE: SETPOINT: 1P42-R200A 7 PSID

2.0 CONDITION

3.0 CLASSIFICATION

EQUIPMENT STATUS Plant Service Water to RBCCW differential pressure has

4.0 LOCATION

decreased to setpoint. 1H 11-P650 Panel 3 5.0 OPERATOR ACTIONS: 5.1 At 112TCT07, confirm low differential pressure by observing 1P42-B001A, Heat Exchanger, RBCCW Inlet Pressure, on 2P42-PI-R002A to 1P41-PI-R578, Service Water Outlet Pressure. 5.2 Confirm that the Plant Service Water System is in operation per 34S0-P41-001-1, Plant Service Water System. 5.3 At 112TCT07, confirm OPEN 1P41-F399A, 1P42-B001 A, RBCCW Heat Exchanger Service Water Inlet Valve. 5.4  !.E RBCCW loads are being isolated remove RBCCW pumps from service as required to maintain Service Water to RBCCW pressure above setpoint. 5.5 THROTTLE 1P41-F206A, RBCCW HX Serv Water Disch Vlv, to increase PSW pressure observing 1P41-PI-R578.

6.0 CAUSES

6.1 Plant Service Water pressure has decreased from the normal operating pressure. 6.2 RBCCW Heat Exchanger service water inlet valve throttled OR closed.

7.0 REFERENCES

8.0 TECH. SPECS.lTRM/ODCM/FHA: 7.1 57SV-CAL-001-1, PSW TO RBCCW dP Channel Cal Unit One, ODCM, 2.1 7.2 H-13613, Wiring Diag Ann Logic Cab 1A Bag D 7.3 H-14036, Wiring Diagram 600V Swgr Bus 1C Frame 7 R23-S003 7.4 H-11609, P&ID Service Water Piping 34AR-650-350-1 ~-------------- ------ Ver.2.2 MGR-0048 Ver. 5.0 AG-MGR-75-1101

FINAL 04/06/09 Southern Nuclear E. I. Hatch Nuclear Plant Operations Training J*PM Admin 5 ) N/R Energy to Serve Your World SM

ISOUTHERN NUCLEAR OPERATING COMPANY '\PLANT E. I. HATCH Page 1 of1

!FORM TITLE:     TRAINING MATERIAL REVISION SHEET Prol[am/Course Code:         OPERATIONS TRAINING Media Number:

00 I Initial development FNF

UNIT 1 (X) UNIT 2 0 Develop Duty Roster For Extended Emergency Activities LR-JP-200.108-00 The task shall be complete when the operator has completed review and/or approval ofTRN-0115, "Authorization To Exceed 10 CFR 20 Limits". H-OPSR200.108 PLANT HATCH JTA IMPORTANCE RATING: RO N/A SRO 4.08 KIA CATALOG NUMBER: G2.4.38 KIA CATALOG JTA IMPORTANCE RATING: RO N/A SRO 4.4 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO) 73EP-EIP-0 17-0 , Emergency Exposure APPROXIMATE COMPLETION TIME: 30 Minutes SIMULATOR SETUP: N/A

UNITl READ TO THE OPERATOR INITIAL CONDITIONS:

1. An ATWS has occurred with fuel damage.

2. A General Emergency has been declared.

3. You are the Emergency Director.

4. The OSC is manned and requests you to review and approve emergency radiation exposure for the following missions:

• Mission 1: 3 people have volunteered (Long, Smith, Harms) to rescue someone in the plant; however only 2 rescuers are Beetled: +0 ~ apf~. I~
• Mission 2: 1 volunteer (Jones) needs to vent the scram air header.

INITIATING CUES:

• Choose two volunteers to rescue someone in the plant
• Review and approve for TRN-Ol15, Authorization to Exceed 10CFR20 )

Limits for the sslsQtsQ individuals<Lofi2:. Smith. HanlIs ana Jencst- jl5'\A. $e.leot- $IL-

For INITIAL Operator Programs: For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance. For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance. NOTE: Provide the operator with the attached TRN-0115 Forms. START TIME: _ _ __

1. Obtains the correct procedure. Emergency Director obtains a SAT/UNSAT copy of73EP-EIP-017-0.

2. Reviews precautions and limitations. Emergency Director reviews SAT/UNSAT precautions and limitations.

3. Reviews procedural guidelines for Emergency Director reviews SAT/UNSAT dose. "Emergency Response Personnel Exposure Guides" table.  :

4. Reviews first form for "Authorization Emergency Director reviews form SAT I UNSAT To Exceed 10 CFR 20 Limits". TRN-0115 for Jack T. Jones.

5. Determine if operator meets the dose Emergency Director determines SAT I UNSAT guidelines of73EP-EIP-017-0. Jack T. Jones does NOT meet the guidelines.

rIsks involved with the exposure. NOTE: Per the exposure guide, personnel "must be fully aware of the risks involved". Emergency Director does NOT SAT I UNSAT sign form TRN-0115 for Jack T. Jones.

7. I Reviews second form for Emergency Director reviews form SAT/UNSAT "Authorization To Exceed 10 CFR 20 TRN-0115 for John R. Smith.

Limits".

8. I Determine if operator meets the dose Emergency Director determines SAT I UNSAT guidelines of 73EP-EIP-017-0. Jack R. Smith DOES meet the Emergency Director DOES sign SAT I UNSAT form TRN-0115 for John R.

Smith.

10. I Reviews third form for "Authorization To Exceed 10 CFR 20 Limits".

IEmergency Director reviews form TRN-0115 for Alex M. SAT IUNSAT

11. I Determine if operator meets the dose Emergency Director determines SAT/UNSAT guidelines of73EP-EIP-017-0. Alex M. Long does NOT meet the 12 I Determine if form "Authorization To Emergency Director does NOT SAT/UNSAT Exceed 10 CFR 20 Limits" will be sign form TRN-0115 for Alex M.

NOTE: Alex is not approved because he is under 45 of age and Mark S. Harms has volunteered.

13. I Reviews fourth fonn for Emergency Director reviews fonn SAT/UNSAT "Authorization To Exceed 10 CFR 20 TRN-OIIS for Mark S. Harms.

Limits".

14. I Detennine if operator meets the dose Emergency Director detennines SAT/UNSAT guidelines of 73EP-EIP-017-0. Mark S. Harms DOES meet the Emergency Director DOES sign SAT/UNSAT fonn TRN-OllS for Mark S.

END TIME: NOTE: The tenninating cue shall be given to the Applicant when:

                     -  With no reasonable progress, the Applicant exceeds double the allotted time.
                     -  Applicant states the task is complete.

TERMINATING CUE: We will stop here. )

SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 1 OF 1

 )  FORM TITLE: AUTHORIZATION TO EXCEED 10 CFR 20 LIMITS JACK             T.           JONES           9872                            3455 (FIRST)             (M.I.)      (LAST)             TLD NUMBER              SECURITY BADGE NO is authorized to receive an exposure of 30     REM and a thyroid exposure of        0     REM for the period of     04/20109        to    04/21/09 Reason for requesting exposure in excess of 10CFR20 limits:

Venting the scram air header is required to insert control rods and limit the current off-site release to the Qublic. Jack Jones is a 49 year old man and in good health. Current year exposure: ) Exposure determined by: 900 mr Barry Barns 4/20109 EXPOSURE IN EXCESS OF 10CRF20 LIMITS EXPOSURE ABOVE 25 REM I have been made aware of the extension of my I have been made aware of the risks involved exposure limits. with the exposures listed above and I accept that risk. IMk. r. Icrnt5 4/20109 Date Employee's Signature 1 Date APPROVAL 1 Emergency Director Date ) TRN-0115 Rev. 2 G16.70 73EP-EI P-017 -OS

SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 1 OF 1 FORM TITLE: AUTHORIZATION TO EXCEED 10 CFR 20 LIMITS JOHN R. SMITH 1802 9458 (FIRST) (M.I.) (LAST) TLD NUMBER SECURITY BADGE NO is authorized to receive an exposure of 35 REM and a thyroid exposure of 0 REM for the period of 04/20/09 to 04/21/09 Reason for requesting exposure in excess of 10CFR20 limits: A man is injured and pinned in a high radiation area and is expected to receive a lethal dose in 60 minutes. John Smith is a 46 year old man and in good health. Current year exposure: Exposure determined by: 1200 mr Barry Barns 4/20/09 EXPOSURE IN EXCESS OF 10CRF20 LIMITS EXPOSURE ABOVE 25 REM I*have been made aware of the extension of my I have been made aware of the risks involved exposure limits. with the exposures listed above and I accept that risk. [(7&11. R. Smith. 4/20/09  ? [(7h.n g. Smith. 4/20/09 Date Date APPROVAL 1 Emergency Director Date TRN-0115 Rev. 2 G16.70 73EP-EIP-017-0S

SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 1 OF 1 FORM TITLE: AUTHORIZATION TO EXCEED 10 CFR 20 LIMITS ALEX M LONG 2334 4255 (FIRST) (M.I.) (LAST) TLD NUMBER SECURITY BADGE NO is authorized to receive an exposure of 35 REM and a thyroid exposure of 0 REM for the period of 04/20109 to 04/21/09 Reason for requesting exposure in excess of 10CFR20 limits: A man is injured and pinned in a high radiation area and is expected to receive a lethal dose in60 minutes. Alex Long is a 38 year old man and in good health. Current year exposure: Exposure determined by: 300 mr Barry Barns 4/20109 EXPOSURE IN EXCESS OF 10CRF20 LIMITS EXPOSURE ABOVE 25 REM I have been made aware of the extension of my I have been made aware of the risks involved exposure limits. with the exposures listed above and I accept that risk. 4/20109 4/20109 Date Date APPROVAL 1 Emergency Director Date TRN-0115 Rev. 2 G16.70 73E P-E IP-O 17-OS

SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 1 OF 1 FORM TITLE: AUTHORIZATION TO EXCEED 10 CFR 20 LIMITS MARK S HARMS 5866 1421 (FIRST) (M.I.) (LAST) TLD NUMBER SECURITY BADGE NO is authorized to receive an exposure of 35 REM and a thyroid exposure of 0 REM for the period of 04/20109 to 04/21/09 Reason for requesting exposure in excess of 10CFR20 limits: A man is injured and pinned in a high radiation area and is expected to receive a lethal dose in 60 minutes. Mark Harms is a 50 year old man and in good health. Current year exposure: Exposure determined by: 1400 mr Barry Barns 4/20109 EXPOSURE IN EXCESS OF 10CRF20 LIMITS EXPOSURE ABOVE 25 REM I have been made aware of the extension of my I have been made aware of the risks involved exposure limits. with the exposures listed above and I accept that risk. MMk1f&rM5 4/20109 M&rk1f&rM5 4/20109 1 Date Date APPROVAL 1 Emergency Director Date TRN-0115 Rev. 2 G16.70 73EP-EIP-017 -OS}}