ML091730177

05000321/366-2009-301 Draft Simulator/In-Plant JPMs

ML091730177
Person / Time
Site:	Hatch
Issue date:	06/22/2009
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
50-321/09-301, 50-366/09-301 50-321/09-301, 50-366/09-301
Download: ML091730177 (127)

Text

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH

\\

I IFORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

LR-JP-25038 A.utll(ii-'s.. $"l1v~s Irtitmls' Inltj;d~

00 01118/00 Initial development RAB DHG 01 11/06/00 Include objective number RAB DHG 02 12/27/01 Corrected IRM scale ranging values to match BKW DHG procedure.

03 03/25/02 Include initial operator statement RAB RAB 04 06/27/05 Revised Initial License statement for successful RAB RAB completion 05 07/25/06 Remove Response Cues RAB RAB

)

UNITl( )

LR-JP-25038-05 Page 1 of7 UNIT 2 (X)

VERIFY THE CORRECT OVERLAP BETWEEN IRM RANGES 6 AND 7 (STOP POWER ASCENSION)

.reMNUMBER:***

T~SK.NlJMBEii:*********

LR-JP-25038-05 This task will be complete when the operator has successfully verified IRM overlap between Ranges 6 and 7 and has determined that overlap for two IRMs is unacceptable, per 34GO-OPS-00 1-2, "Plant Startup," and power ascension must discontinue.

012.010 Q}JJEC1:1YENI.JMBER: 012.010.B PLANT HATCH JTA IMPORTANCE RATING:

RO 3.40 SRO 3.07 KIA CATALOG NUMBER:

215003A407 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.60 SRO 3.60 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

. GENERAL

REFERENCES:

• mt~P1R~D>~'I'Ef{JA.LS:*

APPROXIMATE COMPLETION TIME:

14.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

LR-JP-25038-05 Page 2 of7 SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #103 or other startup IC and leave in FREEZE.

2.

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

3.

INSERT the following MALFUNCTIONS:

mfC51 8F I IRM F Failure (Downscale) mfC51 155C I IRM C Range 7 Fails High By a Factor of2 mfC51 155B I IRM B Range 7 Fails High By a Factor of 2 00000 00000 00000

4.

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

A.

Bypass IRM "F."

B.

Pull control rods until all IRMs are on Ranges 5 or 6, with a Reactor period of about 150 seconds.

B.

While pulling control rods, don't forget to increase Dump Flow, withdraw SRMs, and close Head Vents, if required.

C.

Place simulator in freeze and take a snapshot when IRMs are on Range 5 and/or

6.

5.

Complete a markup of 34GO-OPS-001-2 thru step 7.2.23. Have Attachment 9 available (other attachments are not required).

6.

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

7.

ESTIMATED Simulator SETUP TIME:

30 Minutes NOTE: While the operator is performing this JPM, it will be necessary to withdraw more control rods to maintain a positive period. This should be done until all IRMs are on Range 7 or above.

')

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

1. Unit 2 is in Startup, with 34GO-OPS-001-2 (Plant Startup) in progress.

2. All plant equipment is in normal line-up for this condition. IRM "F" failed downscale last shift. It has been bypassed and I & C is investigating.

3. Each Intermediate Range Monitor (IRM) is on Range 5 or Range 6.

4. 34GO-OPS-001-2, Plant Startup, has been completed thru Step 7.2.23.

5. All Source Range Monitors (SRMs) have been fully withdrawn.

6. Reactor Period is approximately 150 seconds, with the CBO performing required rod movement per 34GO-OPS-065-0.

7. A second operator is monitoring the remainder of the Control Room Panels, including Feedwater Control.

INITIATING CUES:

Range IRMs as power is increased and perform Steps 7.2.24 and 7.2.25 of 34GO-OPS-001-2, Plant Startup, to verify IRM overlap.

)

/

)

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.

LR-JP-25038-05 Page 4 of7 START TIME: ___ _

PROMPT:

AS the Shift Supervisor, INFORM the operator that another operator is monitoring the remainder of the Control Room Panels, including F eedwater Control.

NOTE: The Simulator operator, as the CBO, may be required to withdraw Control Rods to maintain Reactor Period, due to the negative reactivity addition encountered at the Point of Adding Heat, such that all IRMs will go to Range 7 or above.

PROMPT:

INFORM the operator that the CBO will perform any required rod movement to maintain the Reactor critical.

1. Operator OBTAINS the correct Operator has OBTAINED a copy SAT/UNSAT procedure and LOCATES the correct of34GO-OPS-001-2 and has step.

LOCATED Step 7.2.24.

PROMPT:

WHEN operator addresses 34GO-OPS-001-2, PROVIDE the operator with the previously markup version of 34GO-OPS-001-2 and a blank.

NOTE: The critical part of Step 2 will be satisfied if the operator ranges the IRMs in such a manner that no half-scrams or full scrams are received.

Operator has RANGED IRMs to maintain IRM indications between 10 and 80 on the recorder 0 - 125 scale (black scale).

PROMPT:

IF addressed, INDICATE to the operator that all the SRMs are fully withdrawn.

SAT IUNSAT

(** Indicates critical step)

.operator has RANGED each IRM from Range 6 to Range 7 and has L.oGGED Range 6 and Range 7 readings in Column 3 and Column 4, respectively, of of 34G.o-.oPS-OO 1-

2.

LR-JP-25038-05 Page 5 of7 SAT I UNSAT PR.oMPT:

As the SS, N.oTIFY the operator that another operator will monitor the IRMs while Attachment 9 is completed.

N.oTE:

Instructor is to range the IRMs as necessary to prevent a scram.

p~~r1lt()~9:I\\lII5p~R.~g,~f(~oluJl1n ZJ;~a4jp.gsby*.19**.*atld~~*'I'ItRS.. ~11~**.

• l}§SI.llJ~ScjllH()1~l11n4():t;.............................................

Attac1fn1cl1t 90f34GO~OPS.. o.Ol*-2.**

.operator has DIVIDED Range 6 (Column 2) readings by 10 and has ENTERED the RESULTS in Column 4 of Attachment 9 of 34G.o-.oPS-OOl-2.

SAT IUNSAT PR.oMPT:

IF addressed, as a second operator, PERFORM verification of Column 5 of.

.operator checks that Column 3 equals Column 4 +/-2 (on the red scale, Column 3) and has DETERMINED:

that IRM "B" N.oT ACCEPTABLE (> +/-2).

• that IRM "C" N.oT ACCEPTABLE (> +/-2).

SAT IUNSAT SAT I UNSAT PR.oMPT:

IF addressed, as a second operator, PERFORM calculation verification.

N.oTE: The operator may have the Shift Supervisor notifY the I & C Shop.

(** Indicates critical step)

'f~~~>

6. I Operator RECORDS the unacceptable overlap for IRM "B" and "C" in the Operator's log and notifies the Shift Supervisor of the unacceptable overlap for IRM "B" and "C".

0~l5r~t()r*(Jtiij~s;the:s~ithatB~rtIl... *.**.*.........

~(')!rPf1\\tt~ehnle~t *. 9,B()~er***;ii**;**.

Cls~e~s.i8H.~aty1()1 ** ~ontin~e'3Ti~

• .* less

't

..... *.h

....... an

.*......*........... t

.. hr.'

• .......... e. e.!.*I.R

.....*..*. M

• ..** ***......** *. channelsID<ea;clt RPS tripi~yst~Jll;....*...... '.;

Operator has RECORDED the unacceptable overlap for IRM "B" and "C" in the Operator's log and notifies the Shift Supervisor of the unacceptable overlap for IRM "B" and "C."

Operator NOTIFIES the SS that per the Note of Attachment 9, power accession cannot continue with less than three IRM channels in each RPS trip system.

LR-JP-25038-05 Page 6 of7

~1\\.l'fIJ~~Al'

(]Ol\\fl\\fl!jNTS SAT I UNSAT SAT I UNSAT PROMPT:

AS the Shift Supervisor, INFORM the operator that another operator will maintain current power while the condition of the IRMs is being evaluated.

NOTE:

The terminating cue shall be given to the operator when:

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

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(*

• Indicates critical step)

END TIME: ___ _

ATTACHMENT 1 (EXCERPT FROM 34GO-OPS-001 ATTACHMENT 9)

TITLE:

IRM OVERLAP CHECK 1.0 Confirm that there is overlap between IRM ranges 6 and 7 is acceptable as follows:

1.1 Record readings from range 6 for each IRM channel.

1.2 Record readings from range 7 for each IRM channel.

1.3 Divide Range 6 readings (COLUMN 2) by 10 and enter in Column 4.

COLUMN 1 COLUMN 2 COLUMN 3 COLUMN 4 COLUMN 5 IRM RANGE 6 RANGE 7 (COLUMN 2)/

SIGN-OFF CHANNEL READING READING 10 (Black (Red INITIALS VERIFIED Scale)

Scale)

A B

C D

E F

G H

-- ~------.---.--.-.. -... -----

1.4 Confirm that Column 3 = Column 4 +/- 2 (on the red scale).

1.5 Initial and verify the calculations.

NOTE Acceptable overlap must be obtained on three IRM channels in each RPS Trip System to continue power ascension (LIC OPER)

INITIALS VERIFY Page 70f7

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 17 OF 74 DOCUMENT TITLE:

PLANT STARTUP DOCUMENT NUMBER:

34GO-OPS-001-2 VERSION NO:

38.16 7.2 APPROACH TO CRITICALITY 7.2.1 CONTINUOUS I

Announce on the Public Address system that reactor startup is about to commence and that Primary and Secondary Containment are in effect.

7.2.2 Obtain Shift Supervisor's and Shift Manager's signatures confirming that all prerequisites necessary to put the Reactor Mode switch in START & HOT STBY for the purpose of plant startup have been met.

IU1c. Itme.5 4/20/09 0900 Shift Supervisor Date 5Mn,. 5mitft 4/20109 Shift Manager Date 7.2.3 PLACE the Reactor Mode Switch in START & HOT STBY.

4/20109 0900 Date Time 7.2.4 Confirm that the "MODE SWITCH SHUTDOWN TRIP BYPASS" annunciator on 2H11-P603 clears.

Time 0900 Time 7.2.5 Confirm the Scram Group A AND Scram Group B indicating lights (eight white lights) are ILLUMINATED (there is power to the RPS Trip System and all trips are reset), paneI2H11-P603.

At certain times in core life, it may be necessary to establish a minimum moderator NOTE: I temperature limit for rod withdrawal in order to prevent startup with a positive moderator coefficient.

7.2.6 Contact Rx. Engineering to determine if a minimum moderator temperature limit for rod withdrawal is required.

Record limit here and on Attachment 8, or record NIA if no limit is required per Rx. Engineering.

NIA of G16.030 MGR-0001 Rev. 4.0 de, M

~

A-e, A-e,

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

PLANT STARTUP DOCUMENT NUMBER:

34GO-OPS-001-2 PAGE 18 OF 74 VERSION NO:

38.16

• With the RWM inoperable BEFORE the first 12 control rods are withdrawn during a startup, provided that these circumstances (RWM inoperable prior to withdrawing the first 12 rods) have not occurred within the previous 12 months, control rod movement is permitted provided that a Peer Checker (licensed Operator or technical staff member) is also present at the reactor control console, NOTES: I with no concurrent duties, and doubly verifies compliance with the prescribed control rod sequence.

)

)

7.2.7 7.2.8 7.2.9 NOTE:

• With the RWM inoperable BEFORE the first 12 control rods are withdrawn during a startup, and these circumstances (RWM inoperable prior to withdrawing the first 12 rods) have occurred within the previous 12 months, control rod movement must be suspended immediately except by scram.

CONFIRM no startup in past calendar year has taken place with RWM inoperable, by checking for Required Action Sheets on the RWM.

CONFIRM Rod Worth Minimizer (RWM) is operable per Attachment 5 PRIOR to withdrawal of control rods for the purpose of making the reactor A-&

critical.

A-&

IF the RWM is inoperable during the withdrawal of the first 12 rods, a Required Action Sheet has been generated ensuring that no further start-ups with the RWM inoperable prior to withdrawal of the first 12 rods shall be initiated UNTIL one calendar year from the RAS's date.

SS Sig.

N/A The following steps are used to confirm that Reactor Coolant System Temperature and Reactor Vessel Pressure are to the right of the curve in figure 3.4.9-3 and the maximum heatup is :s. 100'F in anyone hour period every 30 minutes as required by TS 3.4.9.1.

7.2.10 During heatup and pressurization, perform Attachment 8 at least once every 15 minutes.

~

G16.030 MGR-0001 Rev. 4.0

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 19 OF 74 DOCUMENT TITLE:

PLANT STARTUP DOCUMENT NUMBER:

34GO-OPS-001-2 VERSION NO:

38.16 NOTE:

Reactor water level must be monitored during heatup and additional water rejected to the hotwell (preferred) OR radwaste per 34S0-G31-003-2, Reactor Water Cleanup System Operating Procedure.

7.2.11 WITHIN 15 minutes PRIOR to the withdrawal of control rods to bring the reactor critical, start performing Attachment 8.

Record the time that Attachment 8 is complete for rod pull below and in the Control Room Operator's log.

Time of completion 0930

..!..,4=~,,-_

• Control rod withdrawal must be performed in a manner that will avoid steady periods of ~ 50 seconds on the SRM period meters.

~OTES:I. WHE~ reposi~ionin~ control rods, the need for conservative action and for strict compliance with wntten procedures must be adhered to.

• The Operator at the 2H11-P603 panel may place the SRMIIRM/APRM recorder(s) in the high speed mode at his discretion anytime during the start up process.

7.2.12 7.2.13 7.2.14 7.2.15 7.2.16 Notify the ST A to initiate 11m plots.

Commence control rod withdrawal in accordance with the sequence specified by the Shift Technical Advisor/RX Eng and 34GO-OPS-065-0, Control Rod Movement.

Perform Rod Drift Alarm Test while withdrawing a Group 1 control rod, per Attachment 6.

Record time and number of the first control rod withdrawn below:

First control rod withdrawn 30 - 03 Time first control rod withdrawn 0935 I DATE 4/20109 Monitor SRM channels as control rods are being withdrawn and confirm SRM count rates are increasing.

G16.030 MGR-0001 Rev. 4.0 A-~

A-6 A-6 A-6 A-6

II SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 20 OF 74

, DOCUMENT TITLE:

j PLANT STARTUP DOCUMENT NUMBER:

34GO-OPS-001-2 VERSION NO:

38.16 NOTE:

As criticality is approached, an increasingly longer time interval is required for subcritical multiplication to increase the neutron population to a higher level as indicated on the SRMs. Periodic pauses during rod withdrawal are to be utilized to allow stabilization of the neutron level and collection of data for estimating the proximity to criticality using 11m plots. As it becomes apparent that criticality is impending based upon increased subcritical multiplication, a notch and wait control rod withdrawal scheme must be adopted.

7.2.17 Confirm the green RETRACT PERMIT light ILLUMINATES for each SRM detector WHEN the SRM level exceeds 200 CPS.

SRMA SRMB SRMC SRMD

)

I The following are indications of criticality:

NOTE: I. SRM period meters indicate a stable, positive period and SRM levels are increasing WITHOUT requiring additional control rod withdrawal.

CAUTION:

EXTENDED OPERATION JUST BELOW OR JUST ABOVE THE POINT OF CRITICALITY IS UNDESIRABLE. THE DECISION TO CONTINUE OPERATION IN THIS CONDITION WILL REQUIRE THE APPROVAL OF THE MANAGER OPERATIONS. IF ROD MOVEMENT IS TO BE SUSPENDED FORAN EXTENDED PERIOD OF TIME, THE CONTROL RODS WILL NORMALLY BE INSERTED TO AN ALL RODS IN CONDITION TO ENSURE SUBCRITICALITY.

G16.030 MGR-0001 Rev. 4.0 A-6 A-6 A-6 A-6

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 21 OF 74 DOCUMENT TITLE:

PLANT STARTUP DOCUMENT NUMBER:

34GO-OPS-001-2 VERSION NO:

38.16 7.2.18 WHEN criticality is achieved, perform the following:

7.2.18.1 Record the following information in the Operator's log:

a. Time

b. Rod Sequence

c. Rod Group

d. Control Rod

e. Notch Position

f.

Period (1.44 x Doubling Time)

g. Reactor pressure

h. Recirculation loop A temperature

i.

Recirculation loop B temperature

j.

Operator pulling critical Arthur Clark 7.2.18.2 IF first startup after fuel movement within the RPV or control rod replacement, notify Reactor Engineering that 42CC-ERP-01 0-0 (Shutdown Margin Demonstration) must be performed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of criticality per TS SR 3.1.1.1.

7.2.18.3 Announce the reactor critical over the plant public address system.

7.2.18.4 Notify the on shift Lab Foreman of reactor criticality.

G16.030 MGR-0001 Rev. 4.0 A-e-M A-e-A-e-

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 22 OF 74 DOCUMENT TITLE:

PLANT STARTUP DOCUMENT NUMBER:

34GO-OPS-001-2 VERSION NO:

38.16 NOTE:

Today's core loadings require that SRMs be associated to IRMs by proximity.

SRM IRM A

B C

o Aand C Band 0 E and G F and H Correct SRM/IRM overlap is demonstrated when both of the IRMs associated with an SRM indicate?: 5/125 of full scale before the SRM reaches 105 CPS, while still fully inserted.

Reference TS SR 3.3.1.1.6 & B 3.3.1.1 CAUTION:

IF CORRECT SRM/IRM OVERLAP IS NOT CONFIRMED, THE STARTUP WILL BE HALTED AND REACTOR POWER MAINTAINED AT ITS PRESENT LEVEL UNTIL AN EVALUATION CAN BE MADE BY THE REACTOR ENGINEER AND THE SHIFT MANAGER.

7.2.19 Confirm correct overlap between SRM and IRM channels.

7.2.20 Continue to pull rods to establish a heatup rate < 100'F/hr.

With IRM channels below range 3, the SRM channels will initiate a rod withdrawal block WHEN EITHER of the following conditions exist:

NOTE:

1. An SRM channel indicates less than 5 CPS

2. An SRM channel indicates less than 200 CPS with its detector NOT full-in.

7.2.21 WHEN SRMIIRM overlap has been confirmed, withdraw SRM detectors as required to maintain an indicated level between 200 and 7 x 104 CPS.

G16.030 MGR-0001 Rev. 4.0 A-e..

A-e..

A-e..

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 23 OF 74

.. ) DOCUMENT TITLE:

PLANT STARTUP DOCUMENT NUMBER:

34GO-OPS-00 1-2 VERSION NO:

38.16 WHEN POSITIONING THE IRM RANGE SWITCHES, CARE MUST BE CAUTION: I EXERCISED TO PREVENT A REACTOR SCRAM FROM OCCURRING.

7.2.22 7.2.23 7.2.24 7.2.25 IF POSSIBLE, RANGE IRMS IN ONLY ONE RPS CHANNEL AT A TIME.

As reactor power increases, range up the IRM Range Switches to maintain IRM indication on recorders between 10 and 80 on the 0-125 scale.

..!..~-,-,6:::....-_

WHEN all operable IRM channels are above range 3 and PRIOR to reaching range 7, fully withdraw all operable SRM detectors.

A-6 Confirm there is overlap between IRM ranges 6 and 7, by completing Attachment 9.

Record any unacceptable IRM overlaps in the Operator's log book and notify I&C Shop to adjust IRM preamplifiers.

Shift Supervisor approval is required to continue power ascension with any inoperable IRMs.

G16.030 MGR-0001 Rev. 4.0

TITLE AUTilOR DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training ALTERNATEPATHJPM SIM 2, RO, SRO-I SHUT DOWN COOLING ISOLATION D. H. GIDDENS M)1:11IANuMnER* *.

LR-JP-13.047-00

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A~~li(}&~D.BY***

NIR Energy to Serve Your Wor/d SM

r SOUTHERN NUCLEAR OPERATING COMPANY "PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Prol£am/Course Code:

OPERATIONS TRAINING Media Number:

LR-1P-13.047-00

...... ~~~lt9t'S'~ul>V'S

... Initials Initials.

-Wl\\fNlJMUER:

T1t$KNUMSERr UNIT 1 ()

UNIT 2 (X)

SHUT DOWN COOLING ISOLATION LR-JP-13.047-00 The task shall be completed when "B" loop of RHR valves 2EII-F008, F009, and F015B are closed.

013.047 i:iBJEctWE:Nl1Malr,R:. 013.047 A ALTERNATE PATH PLANT HATCH JTA IMPORTANCE RATING:

RO 3.76 SRO N/A KIA CATALOG NUMBER: 223002 K1.08 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.4 SRO 3.5 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

• • • • • (;;J;NERtL}REifE~N(;InS:

• • • lltQuIR1tnl\\ij.r[~IlIAts:

34S0-E11-007-2, RHR System Operating Procedure 34AB-C71-001-2, SCRAM PROCEDURE NMP-OS-007, CONDUCT OF OPERATIONS 34AB-C71-001-2, SCRAM PROCEDURE APPROXIMATE COMPLETION TIME:

15 Minutes

)

SIMULATOR SETUP:

Refer to simulator setup sheet on the following page Page 1 of5

Page 2 of5 SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to an IC 101, or other IC with "B" SDC in service, and leave in FREEZE.

mf

2.

INSERT the following MALFUNCTIONS:

~qr*i.

• • • • • • • • • tIME**.. *******

NONE

3.

INSERT the following SIMULATOR VALUE OVERRIDES (SVO):

l>ES(JIHPl'I.()N

~I.~~iJr?~~f.**. ~()'l'~ *.

. ********lvA~p:EI*~Tl!J.*1 **.TIME svoB21 009 LT-N080A RPS LEVEL 3 SCRAM 37 1000 STO SvoB21010 LT-N080B RPS LEVEL 3 SCRAM 37 1000 STO SvoB21011 LT-N080C RPS LEVEL 3 SCRAM 37 1000 STO SvoB31012 LT-N080D RPS LEVEL 3 SCRAM 37 1000 STO

4.

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

Lower RWL to 1-3" by securing CRD and increasing dump flow to the surge tame ( do not cause a high drywell pressure signal).

5.

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

6.

ESTIMATED Simulator SETUP TIME:

10 Minutes

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

1.

The Unit is being shutdown to cold shutdown.

"B" loop ofRHR is in Shutdown Cooling with the "B" heat exchanger inlet partially open and the heat exchanger bypass valve fully open.

3.

Unit 2 RWL has decreased below +3".

3.

The CBO will handle RC-l, RC-2, and RC-3.

INITIATING CUES:

For "B" loop ofRHR, VERIFY Group 2 and Group 6 Isolations per 34AB-C71-001-2

Page 4 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.

NOTE: Action to close isolation valves is required per NMP-OS-007, "Conduct of Operations", step 5.9.3.3 and 5.10.3.3 "Initiate Engineered Safety Systems actuation if indications exceed automatic actuation setpoints and an actuation has not occurred".

1. I Operator obtains the procedure needed I Operator has obtained procedure to perform the task.

34AB-C71-001-2,

1.

2 I Verifies 2EII-F015B has closed lAW Group 2 Isolation requirements attachment 1.

4. I Verifies 2EII-FOI5B closed.

5. I Verifies 2EII-F008 has closed IA Vv' Group 6 Isolation requirements of attachment 1.

On pane12HII-P601, Observes 2EII-FOI has a red (open) light illuminated.

On pane12EII-H601, places I-FOI control switch to close and allows it to spring return to mid position.

On pane12HII-P601, Observes the green light is illuminated and the red light is extinguished for 2EI-FOI5B.

On pane12HI1-P601, Observes 2EII-F008 has a red (open) illuminated.

On panel2Ell-H601, places 2El1-FOOS control switch to close and allows it to spring return to mid position.

2HII-P601, Observes the green light is illuminated and the red light is extinguished for 2EI-FOOS.

START TIME: ___

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

8. I Verifies 2Ell-F009 has closed IA W Group 6 Isolation requirements of attachment 1.

10. I Verifies 2EI1-F009 closed.

On pane12H11-P602, Observes 2Ell-F008 has a red (open) light illuminated.

On panel 2E 11-H602, places 2E11-F009 control switch to close and allows it to spring return to mid position.

On panel2H11-P602, Observes the green light is illuminated and the red light is extinguished for 2E1-F009.

NOTE:

The terminating cue shall be given to the operator when:

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

Operator states the task is complete.

J TERMINATING CUE: That completes this lPM.

Page 5 of5 SAT IUNSAT SAT IUNSAT SAT I UNSAT END TIME: ----

SOUTHERN NUCLEAR 1

PAGE 11 OF 28 PLANT E.I. HATCH DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

1 SCRAM PROCEDURE 34AB-C71-001-2 9.26 J

ATTACHMENT J.

ATTACHMENT PAGE:

TITLE:

PRIMARY CONTAINMENT ISOLATION CONFIRMATION 2 OF 9 2.0 NOTE:

2.1 2.2

~OTES:

GROUP 2 ISOLATION EITHER of these conditions can be indicative of a pipe break in the Reactor Building.

Refer to 34AB-T22-001-2 as applicable.

EITHER of the following conditions cause isolation:

Reactor Water Level Low (Level 3) (+3")

Drywell Pressure High (1.85 PSIG)

Confirm the following valves have closed:

Position indication can also be found on SPDS diagnostic and on pane12H11-P601 vertical display except as noted.

The Reactor Operator can quickly identify all Control Room Panel Group 2 Isolation Valves by a blue circular tag with white letters (G2) placed in the proximity of each Group 2 Valve control switch on panels 2H11-P601, 2H11-P602, 2H11-P607, 2H11-P654, 2H11-P657, and 2H11-P700.

The tags will appear as the illustration below:

2H11-P602 2G11-F003 2G11-F019 2E11-F040 2T48-F118B 2T48-F309 2T48-F307 2T48-F341 2T48-F339 2T48-F118A 2T48-F318 2T48-F319 Floor Drain Vlv Equip Drain Vlv (0

RHR to Radwaste Vlv N2 Makeup to Torus Vlv Torus Air Purge Vlv Drywell Air Purge Vlv Drwl Vent & Relief Vlv Torus Vent & Relief Vlv N2 Makeup To Drwl Vlv Torus Vent Vlv Drywell Vent Vlv MGR-0009 Rev. 5.0

SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:

I PAGE 12 OF 28

)

SCRAM PROCEDURE ATTACHMENT.1 1 DOCUMENT NUMBER:

34AB-C71-001-2 VERSION NO:

9.26 ATTACHMENT PAGE:

30F9 TITLE:

PRIMARY CONTAINMENT ISOLATION CONFIRMATION 2H11-P601 2G11-F004 2G11-F020 2E11-F049 2T48-F324 2T48-F308 2T48-F340 2T48-F338 2T48-F104 2T48-F103 2T48-F326 2T48-F320 (b) 2E11-F01SB*

(b) 2E11-F122B (b) 2E11-F01SA*

(b) 2E11-F122A 2H11-P700 2D11-FOS1 2D11-FOSO (b) 2E41-F122 (b) 2B21-F111 (b) 2P70-F002 2P33-F002 2P33-F007 2P33-F004 2P33-F003 2P33-FOOS (a)(b) 2D11-F071 2P33-F006 (b) 2GS1-F011 (b) 2GS1-F017 2D11-FOS2 2D11-FOS3 (b) 2B21-F112 (b) 2E41-F121 Floor Drain Vlv Equip Drain Vlv RHR To Radwaste Vlv Torus Air Purge Vlv Drywell Air Purge Vlv Drwl Vent & Relief Vlv Torus Vent & Relief Vlv Nitrogen Makeup Vlv Nitrogen Purge Vlv Torus Vent Vlv Drywell Vent Vlv RHR Inbd Inj Vlv Check FOSOB Bypass Vlv RHR Inbd Inj Vlv Check FOSOA Bypass Vlv Pri Cnmt Fis Prod Man Inbd Isol Pri Cnmt Fis Prod Man Inbd Isol Post Acc Rx Cool/Cnmt Atmos Smplg Inbd Isol Post Acc Rx Cool/Cnmt Atmos Smplg Inbd Isol Drwl Pneu Inbd Suction Isol Pri Cnmt Atmos H202 Anly Inbd Isol Ch B Pri Cnmt Atmos H202 Anly Inbd Isol Ch A Pri Cnmt Atmos H202 Anly Ch A Rtn Line Inbd Isol Pri Cnmt Atmos H202 Anly Inbd Isol Ch A Pri Cnmt Atmos H202 Anly Inbd Isol Ch B Return Line Pri Cnmt Atmos Fis Prod Man Sample Line Isol Pri Cnmt Atmos H202 Anly Inbd Isol Ch B Torus Water Cleanup Inbd Isol Torus Water Makeup Outbd Isol Pri Cnmt Fis Prod Man Outbd Isol Pri Cnmt Fis Prod Man Outbd Isol Post Acc Rx Cool/Cnmt Atmos Smplg Outbd Isol Post Acc Rx Cool/Cnmt Atmos Smplg Outbd Isol (a)

(b)

No indication on SPDS diagnostic No indication on 2H11-P601 vertical display Will close on Group 2 only IF a RHR loop is in Shutdown Cooling Mode MGR-0009 Rev. S.O

SOUTHERN NUCLEAR PLANT E.I. HATCH I

PAGE 13 OF 28

)

DOCUMENT TITLE:

SCRAM PROCEDURE I DOCUMENT NUMBER:

34AB-C71-00 1-2 VERSION NO:

9.26 ATTACHMENT..1 TITLE:

PRIMARY CONTAINMENT ISOLATION CONFIRMATION ATTACHMENT PAGE:

40F9 2H11*P700 (CONTINUED) 2P33-F015 2P33-F010 (b) 2P70-F003 2P33-F013 2P33-F011 2P33-F012 (a)(b) 2P33-F605 (a)(b) 2D11-F072 2P33-F014 (b) 2G51-F013 (b) 2G51-F012 2H11*P607 (a) 2C51-J004A-D 2H11*P657 (b) 2T48-F334A (b) 2T48-F335A (b) 2T48-F332A (b) 2T48-F333A (a) 2T48-F209 (a) 2T48-F211 2H11*P654 (b) 2T48-F334B (b) 2T48-F335B (b) 2T48-F332B (b) 2T48-F333B (a) 2T48-F210 (a) 2T48-F212 2H21*P018 2E11-F079A 2E11-F080A 2H21*P021 2E11-F079B 2E11-F080B Pri Cnmt Atmos H202 Anly Outbd 1501 Ch A Pri Cnmt Atmos H202 Anly Outbd 1501 Ch B Drwl Pneu Outbd Suction 1501 Pri Cnmt Atmos H202 Anly Outbd 1501 Ch B Return Line Pri Cnmt Atmos H202 Anly Outbd 1501 Ch A Pri Cnmt Atmos H202 Anly Ch A Rtn Ln Outbd 1501 O2 Analyzer 1501 Valve Pri Cnmt Fis Prod Mon Rtn Ln 1501 Pri Cnmt Atmos H202 Anly Outbd 1501 Ch B Torus Drn/Purif Torus Water Makeup Inbd 1501 Torus Drn/Purif Torus Water Cleanup Outbd 1501 Tip Ball Vlvs (See Step 2.3)

Cad A Drywell Vent 1501 Vlv Cad A Drywell Vent 1501 Vlv Cad A Torus Vent 1501 Vlv Cad A Torus Vent 1501 Vlv Drwl To Torus Dp Sys Inbd 1501 Drwl To Torus Dp Sys Inbd 1501 Cad B Drywell Vent 1501 Vlv Cad B Drywell Vent 1501 Vlv Cad B Torus Vent 1501 Vlv Cad B Torus Vent 1501 Vlv Drwl To Torus Dp Sys Outbd 1501 Drwl To Torus Dp Sys Outbd 1501 (87RLR14)

RHR Sample Vlv RHR Sample Vlv (87RLR24)

RHR Sample Vlv RHR Sample Vlv (a)

No indication on SPDS diagnostic (b)

No indication on 2H11-P601 vertical display MGR-0009 Rev. 5.0

SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:

I SCRAM PROCEDURE ATTACHMENT -1 I DOCUMENT NUMBER:

34AB-C71-001-2 TITLE:

PRIMARY CONTAINMENT ISOLATION CONFIRMATION PAGE 14 OF 28 VERSION NO:

9.26 ATTACHMENT PAGE:

5 OF 9 2.3 IF any Tip Ball Vlv fails to close and there is indication that a radioactive release from Primary Containment is occurring via this pathway, THEN perform the following:

2.3.1 At paneI2H11-P607, place the Shear Vlv keylock switch for the failed Tip Ball valve to the FIRE position.

2.3.2 Confirm the SHEAR VLV MONITOR and SQUIB MONITOR lights ILLUMINATE for the appropriate Tip.

MGR-0009 Rev. 5.0

SOUTHERN NUCLEAR PLANT E.1. HATCH DOCUMENT TITLE:

l SCRAM PROCEDURE ATTACHMENT -1 I* DOCUMENT NUMBER:

34AB-C71-001-2 TITLE:

PRIMARY CONTAINMENT ISOLATION CONFIRMATION 6.0 GROUP 6 ISOLATION PAGE 18 OF 28 VERSION NO:

9.26 ATTACHMENT PAGE:

90F9 NOTE:

Some of the following conditions can be indicative of a RHR pipe break in the Reactor Building. Refer to 34AB-T22-001-2 as applicable.

6.1 6.2 NOTE:

EITHER of the following conditions cause isolation:

Reactor Water Level Low (level 3) (+3")

Reactor Pressure High (138 PSIG)

Confirm the following valves have closed:

Position indication can also be found on SPDS diagnostic and on panel 2H11-P601 vertical display except as noted.

2H11-P602 2E11-F009 SDC Suction Vlv 2H11-P601 2E11-F008 SDC Suction Vlv MGR-0009 Rev. 5.0

NIR DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM SIM 3, RO, SRO-I

SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH

(~ORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:

OPERATIONS TRAINING Media Number:

01 11106/00 Include objective number Changed referenced procedure used for manual start from the Control 02 12/27/01 Room, from the "Monthly" surveillance to the "Semi-Annual" surveillance. Deleted reference to annunciator "Governor Not At Sync Speed Setting," alarm has been deleted.

03 03125102 Include initial Operator statement 04 06/27/05 Revised Initial License statement for successful completion 05 06/30106 Remove Response Cues 06 10/14/08 Removed step 39 to conform to procedure.

Page 1 of 1 LR-JP-25034

~~t~~t's.

. niitials.

$,~.Pv"s

• lnitials RAB DHG RAB DHG BKW DHG RAB RAB RAB RAB RAB RAB JWP RAB

LR-JP-25034-06 Page 1 of8 UNIT 1 ()

UNIT 2 (X)

~MNtTIVl:a-ER:

• • TA.S.KNJJMBI1R:***

PERFORM A DIESEL GENERATOR MANUAL START SURVEILLANCE (TRIP FAILURE)

LR-JP-25034-06 The task shall be completed when the Operator has tied the "2A" Diesel Generator to the "2E" 4160 VAC Bus per 34SV-R43-004-2. Then following a failure to auto trip, shutdown the Diesel Generator.

028.016 OBJECl'I'VENUMBER: 028.016.0 PLANT HATCH JTA IMPORTANCE RATING:

RO 3.22 SRO 2.93 KIA CATALOG NUMBER: 264000A404 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.70 SRO 3.70 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

GENltRALlt-ElfElt-ENCES: IUQif2*

~QQlJ:{itl);~'FEIU~ts;.....

34SV-R43-004-2 (current version) 34AR-652-111-2 (current version) 34AR-652-129-2 (current version) 34SV-R43-004-2 (current version) 34AR-652-111-2 (current version) 34AR-652-129-2 (current version)

Stopwatch APPROXIMATE COMPLETION TIME:

20 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #113, or other full power IC.

2.

INSERT the following MALFUNCTIONS:

mf652 1 1665 mf652II683 Spur Ann - LUBE OIL PRESS LOW Spur Ann - EMERGENCY ENGINE SHUTDOWN

3.

INSERT the following REMOTE FUNCTIONS:

rtR43294 DG 2A Engine Remote Speed Droop (0 -100)

'&~~'J'~~

4. PLACE the Diesel Gen 2A Mode Select switch in the TEST position.

5. PLACE the simulator in FREEZE.

6.

ESTIMATED Simulator SETUP TIME:

10 Minutes NOTE To monitor Diesel Generator "A" engine speed, governor setting, frequency, perform the following steps at the instructor station.

1. Click on any screen, off of any list.

2. Type ALT-P.

3. Select OPEN TABLE

4. Select DG SPEED VOLT REG SP.TBI

5. Select OPEN LR-JP-25034-06 Page 2 of8

\\<21

.>

T1M:E 99999 99999 STATUS*.*....

o

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

1. Diesel Generator "2A" is ready to be run for its semi-annual manual start per 34SV-R43-004-2. The procedure is complete up to and including step 7.2.2.7.

2. No other testing or maintenance is in progress.

3. A SO is standing by at the Diesel Generator.

INITIATING CUES:

Starting at step 7.2.2.8, perform the Diesel Generator 2A Semi-Annual Test per 34SV-R43-004-2. 1ST is not being performed.

For INITIAL Operator Programs:

LR-JP-25034-06 Page 4 of8 For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

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

PROMPT:

WHEN the Operator is ready to begin, give him a stopwatch and a copy of 34SV-R43-004-2 which is completed up to and including step 7.2.2.7.

NOTE: The prelube pump may be started from the Main Control Room.

However, standard practice is to contact the SO at the Diesel and have that Operator prelube the Diesel.

1. I Operator reviews the procedure.

3. I Select Diesel Generator 2A Voltmeter for monitoring phase voltage during the startup.

Operator reviews precautions, limitations and completed steps.

Contacting the SO at the Diesel Generator 2A Room, the Operator CONFIRMS that the Diesel 2A PRELUBE PUMP to ON, red light illuminated.

At panel 2HII-P652, the Operator SELECTS Diesel Generator 2A Voltmeter, 2R43-R904, using the voltmeter select switch.

START TIME: ___ _

SAT I UNSAT SAT I UNSAT SAT I UNSAT NOTE: For the following step, starting the Diesel is the critical portion of this step.

(*

• Indicates critical step)

At paneI2HI1-P652, the Operator STARTS the stopwatch and TAKES the Diesel Gen 2A START switch to the START position.

When the Diesel Generator 2A reaches synchronous speed

(~3800 volts and (~59 hertz),

STOP the stopwatch.

SAT I UNSAT

5.

6.

7.

I

8.

9.

Record the time the diesel starts and comes up to synchronous speed and confirm that the time is less than or equal to 12 seconds.

Confirm that the average diesel generator output voltage is between 3740 V and 4240 V AND that diesel generator frequency is between 59 and 61 Hz.

Confirm that the Diesel Generator 2A Cooling Water Outlet AOV, 2P41-F339A is OPEN.

Confirm that the Diesel Gen 2A Auto Start Sys Operative clear light is EXTINGUISHED.

Confirm that the Diesel Gen 2A Start red light and Diesel Gen 2A Shutdown System Operative light are ILLUMINATED.

At paneI2H11-P652, the Operator RECORDS the time the diesel starts and comes up to synchronous speed and CONFIRMS that the time is less than or equal to 12 seconds.

At panel2H11-P652, the Operator CONFIRMS that the average diesel generator output voltage is between 3740 V and 4240 V AND that diesel generator frequency is between 59 and 61 Hz.

Contacting the SO at the Diesel Generator 2A Room, the Operator CONFIRMS that the Diesel Generator 2A COOLING WATER OUTLET AOV, 2P41-F339A, is OPEN.

At panel2H11-P652, the Operator CONFIRMS that the Diesel Gen 2A AUTO START SYS OPERATIVE clear light is EXTINGUISHED.

At panel2H11-P652, the Operator CONFIRMS that the Diesel Gen 2A Start red light and Diesel Gen 2A SHUTDOWN SYSTEM OPERATIVE light are ILLUMINATED.

LR-JP-25034-06 Page 5 of8 SNt7f:JN.S:~1'.

• {COMMENTS**

SAT IUNSAT SAT I UNSAT SAT IUNSAT SAT IUNSAT SAT I UNSAT NOTE: The simulator Operator, when contacted by the Operator, will TOGGLE REMOTE FUNCTION rfR43294, "DG 2A Engine Remote Speed Droop (0 to 100), to change the speed droop for the following step.

Contacting the SO at the Diesel Generator 2A Room, at the Diesel Generator 2A Woodward Governor Control, the Operator has the SPEED DROOP control knob PLACED to "50".

SAT IUNSAT

(** Indicates critical step)

12. I Confirm that the Diesel Gen 2A Voltage Reg Transfer Auto red light is EXTINGUISHED.

13. I Confirm that the Diesel Gen 2A Voltage Reg Transfer Manual green light is ILLUMINATED.

At panel 2HII-P652, the Operator PLACES the Diesel Gen 2A VOLTAGE REG TRANSFER switch in MANUAL, green light illuminated.

At panel 2HII-P652, the Operator CONFIRMS that the Diesel Gen 2A VOLTAGE REG TRANSFER AUTO red light is EXTINGUISHED.

At paneI2HII-P652, the Operator CONFIRMS that the Diesel Gen 2A VOLTAGE REG TRANSFER MANUAL green light is ILLUMINATED.

NOTE: The following step is critical only if an adjustment is required.

16. I Using Diesel Gen 2A Speed Adjust switch, adjust diesel speed to attain a slow synchroscope rotation in the clockwise (fast) direction.

(** Indicates critical step)

At paneI2HII-P652, the Operator ADJUSTS the Diesel Gen2A VOLTAGE ADJUST switch until diesel output voltage is equal to 4160 Bus 2E Voltage, as indicated on VOLTMETER, 2R43-R904.

At paneI2HI1-P652, the Operator PLACES Diesel Gen 2A Synchroscope switch (SSW) for ACB 135530 to ON, synchroscope starts rotating and the synchroscope lights cycle through dim to bright.

At pane12HI1-P652, the Operator uses the Diesel Gen 2A SPEED ADJUST, to adjust diesel speed to attain a slow synchroscope rotation in the clockwise (fast) direction.

LR-JP-25034-06 Page 6 of8 SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT

i

• P!ERFQRMA~p~S'li~***

17. I Observe the voltage on each phase of 4160V Bus 2E and record the highest voltage.

18. I Using Diesel Generator 2A Voltage Adjust switch, increase diesel output voltage to match the highest phase voltage on 4160V Bus 2E.

At panel 2HII-P652, the Operator OBSERVES the voltage on each phase of 4160V Bus 2E, as indicated on VOLTMETER, 2R43-R904, and RECORDS the highest voltage.

At panel 2HII-P652, the Operator uses Diesel Generator 2A VOLTAGE ADJUST switch, INCREASES diesel output voltage to match the highest phase voltage on 4160V Bus 2E.

At panel2H11-P652, the Operator, when the synchroscope indicates 2 minutes to 12 and when the synchroscope lights are at the dimmest point, CLOSES EMERGENCY SUPPLY ACB 135530, red light illuminated.

LR-JP-25034-06 Page 70f8

$1\\:UWN~.t\\T*C COMMENTS SAT IUNSAT SAT IUNSAT SAT/UNSAT NOTE: IF during the perfonnance of the following two steps, the Operator trips the diesel, these steps become critical and the JPM is failed.

20. Using the Diesel Gen 2A Speed At pane12H11-P652, the SAT/UNSAT Adjust switch, adjust the load on the Operator uses the Diesel Gen 2A diesel to 500 to 1000 kW.

SPEED ADJUST switch, ADJUSTS the load on the diesel to 500 to 1000 kW, as indicated on KILOWATT, 2R43-R615A.

21. Using the Diesel Gen 2A Voltage At paneI2H11-P652, the SAT IUNSAT Adjust switch, adjust the reactive load Operator uses the Diesel Gen 2A to between 500 and 1000 KV AR VOLTAGE ADJUST switch, adjusts reactive load to between 500 and 1000 KV AR.

22. Gradually increase load to between At paneI2H11-P652, the SAT IUNSAT 1750 and 2000 KW.

Operator uses the Diesel Gen 2A SPEED ADJUST switch, ADJUSTS the load on the diesel to 1750 and 2000 KW, as indicated on KILOWATT, 2R43-R615A.

(*

• Indicates critical step)

1'l'~~'

/..... #-./....

LR -JP-25034-06 Page 8 of8 NOTE: AS the Operator is increasing the diesel loading to 1750 kW, ACTIVATE MALFUNCTION mf65213665, "Spur Ann - LUBE OIL PRESS LOW."

5 -10 seconds later, ACTIVATE MALFUNCTION mf65213683, "Spur Ann - EMERGENCY ENGINE SHUTDOWN."

PROMPT:

PAGE the Operator as the SO in the Diesel Building and REPORT that an oil line has split and spewing hot oil. I cannot get to the diesel and it is beginning to smoke.

23. I Opens the Emergency Supply ACE.

At pane12HII-P652, the Operator, OPENS EMERGENCY SUPPLY ACB 135530, green light illuminated.

At pane12HII-P652, the Operator TAKES the Diesel Gen 2A START switch to the STOP position.

SAT/UNSAT SAT/UNSAT

)

PROMPT:

ONCE the Operator has stopped the diesel, INFORM the Operator that another Operator will complete the shutdown and contact Maintenance.

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.

Operator has stopped the 2A Diesel Generator.

TERMINATING CUE: We will stop here.

(*

• Indicates critical step)

END TIME: ___

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 80F 31 POCUMENT TITLE:

DOCUMENT NUMBER:

34SV-R43-004-2 VERSION NO:

15.23 i

DIESEL GENERATOR 2A SEMI-ANNUAL TEST

)

7.2 DIESEL GENERATOR 2A SEMI-ANNUAL MANUAL START CONTINUOUS I

7.2.1 At paneI2H11-P652, perform the following:

7.2.1.1 7.2.1.2 7.2.1.3 7.2.1.4 7.2.1.5 Confirm Diesel Gen 2A Mode Select switch is in NORM.

Confirm Diesel Gen 2A Shutdown System Operative red light is EXTINGUISHED.

Confirm Diesel Gen 2A Start red light is EXTINGUISHED.

At the Diesel Gen 2A Voltage Reg Transfer switch, confirm the following:

• Voltage Reg Transfer switch is in AUTO

• AUTO red light is ILLUMINATED

• MANUAL green light is EXTINGUISHED.

At Diesel Gen 2A Voltage Adjust switch, confirm the following:

• RAISE red light is EXTINGUISHED

• LOWER green light is EXTINGUISHED.

~

~

~

~

~

~

~

~

7.2.1.6 Confirm Diesel Gen 2A Auto Start Sys Operative clear light is ILLUMINATED. ~

7.2.1.7 IF Diesel Gen 2A Auto Start Sys Operative light is EXTINGUISHED, DEPRESS Diesel Gen 2A Shutdown Relay pushbutton.

~

7.2.1.8 Confirm ACB 135530, Diesel Gen 2A Emergency Supply, indicates OPEN.

~

IF DIESEL GEN 2A MODE SELECT SWITCH IS IN TEST AND SAT 2D IS LOST, ANY AUTO TRANSFER TIE TO DIESEL 2A OR SAT 2C WILL NOT OCCUR EVEN THOUGH THE ALTERNATE OR EMERGENCY POWER CAUTION: I SUPPLIES ARE AVAILABLE. THE DIESEL GEN 2A MODE SELECT SWITCH 7.2.1.9 MUST BE PLACED IN NORM. THIS SITUATION DOES NOT APPLY IN A LOCA CONDITION.

PLACE the Diesel Gen 2A Mode Select switch in the TEST position.

G16.030 MGR-0001 Ver. 3

~

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 90F 31

\\DOCUMENT TITLE:

)

DIESEL GENERATOR 2A SEMI-ANNUAL TEST DOCUMENT NUMBER:

34SV-R43-004-2 VERSION NO:

15.23 7.2.1.10 7.2.1.11 IF SAT 2C is de-energized, PLACE the Diesel Gen 2A Test SAT 2C Out Of Svc Interlock switch to TEST position.

Confirm annunciator DIESEL 2A IN TEST MODE (652-105) is in the ALARM condition.

7.2.2 In Diesel Generator 2A Room, perform the following:

~

~

7.2.2.1 7.2.2.2 Confirm the At Engine - Remote control switch is in the REMOTE position.

~

At Diesel Generator 2A Woodward Governor Control, confirm OR place the Speed Droop control knob to 0 (fully counter clockwise).

~

7.2.2.3 At Diesel Generator 2A Woodward Governor Control, confirm Load Limit control knob is set fully clockwise (approximately 1 0).

~

7.2.2.4 Confirm 2P41-F339A, Diesel Generator 2A Cooling Water Outlet AOV, is CLOSED by observing local position indication.

~

7.2.2.5 Confirm governor oil level is approximately halfway in the sight glass.

~

INOTE" I The mark on the bearing oil sightglass indicates correct oil level for non-operating

" generator. Oil level should be at OR above the painted mark, but not full.

7.2.2.6 7.2.2.7 Confirm the front and rear generator bearing oil levels are at OR above the painted mark on the sightglass, but not full.

Confirm the diesel lube oil level is within W' below the upper FULL mark on the dipstick.

NOTE:

Prelubing will be performed within 15 minutes of starting the diesel engine. Delays between prelubing and engine starting will negate the effects of prelubing due to system drain down. The Prelube Pump, WHEN started, will operate for approximately 3 minutes. Prelubing can be accomplished in the Control Room OR locally.

7.2.2.8 TAKE the Diesel2A Prelube Pump to ON.

G16.030 MGR-0001 Ver. 3

~

~I

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 10 OF 31

)DOCUMENT TITLE:

(

DIESEL GENERATOR 2A SEMI-ANNUAL TEST DOCUMENT NUMBER:

34SV-R43-004-2 VERSION NO:

15.23 7.2.3 At paneI2H11-P652, perform the following:

7.2.3.1 Using the voltmeter select switch, SELECT 2R43-R904, Diesel Generator 2A Voltmeter, for monitoring phase voltage during the diesel startup.

The liGEN FIELD GROUND" annunciator is expected to alarm during performance NOTES: I of the following steps.

The following two steps must be performed simultaneously.

7.2.3.2 7.2.3.3 7.2.3.4 7.2.3.5 7.2.3.6 7.2.3.7 7.2.3.8 7.2.3.9 7.2.3.10 MGR-0001 Ver. 3 START the stopwatches.

TAKE the Diesel Gen 2A Start switch to the START position.

WHEN Diesel Generator 2A reaches synchronous speed

e. 3800 volts and?: 59 hertz), STOP the stopwatches.

Record the time the diesel starts and comes to synchronous speed, and confirm the time is less than or equal to 12 seconds.

Start time:

seconds Confirm the average diesel generator output voltage is between 3740 V and 4240 V AND diesel generator frequency is between 59 and 61 Hz.

At Diesel Generator 2A Room, confirm 2P41-F339A, Diesel Generator 2A Cooling Water Outlet AOV, OPENS, by observing local position indication.

Confirm Diesel Gen 2A Auto Start Sys Operative clear light is EXTINGUISHED.

Confirm Diesel Gen 2A Start red light is ILLUMINATED.

(810 RPM or 21 PSIG oil pressure).

Confirm Diesel Gen 2A Shutdown System Operative light is ILLUMINATED.

(approximately 20 second time delay).

G16.030

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 11 OF 31

~"POCUMENT TITLE:

)

DIESEL GENERATOR 2A SEMI-ANNUAL TEST DOCUMENT NUMBER:

34SV-R43-004-2 VERSION NO:

15.23 NOTE'I With Speed Droop set to 50, direct local operator action would be required in an emergency to allow Control Room operation of the Diesel Generator.

CAUTION'I IF LOSP AND I OR LOCA OCCURS, THEN SPEED DROOP CONTROL KNOB

, MUST BE POSITIONED TO ZERO (FULLY COUNTERCLOCKWISE).

7.2.3.11 7.2.3.12 7.2.3.13 7.2.3.14 7.2.3.15 CAUTIONS:

7.2.3.16 7.2.3.17 7.2.3.18 7.2.3.19 When performing the following step, an Operator must remain in the direct vicinity of the DG skid AND must maintain the capability for conducting prompt communications with Control Room personnel.

At Diesel2A Woodward Governor Control, position Speed Droop control knob to 50.

PLACE the Diesel Gen 2A Voltage Reg Transfer switch in MANUAL.

Confirm Diesel Gen 2A Voltage Reg Transfer Auto red light is EXTINGUISHED.

Confirm Diesel Gen 2A Voltage Reg Transfer Manual green light is ILLUMINATED.

DO NOT EXCEED 4350 VOLTS ON ANY PHASE OF THE DIESEL GENERATOR.

ADJUST the Diesel Gen 2A Voltage Adjust switch UNTIL diesel output voltage is equal to 4160V Bus 2E voltage.

PLACE Diesel Gen 2A Synchroscope switch (SSW) for ACB 135530, inON.

Using Diesel Gen 2A Speed Adjust switch, adjust diesel speed to attain a slow synchroscope rotation in the clockwise (fast) direction (1 to 3 RPM).

Observe the voltage on each phase of 4160V Bus 2E and record the highest voltage. _________ volts G16.030 MGR-0001 Ver. 3

SOUTHERN NUCLEAR PLANT E. I. HATCH "DOCUMENT TITLE:

DOCUMENT NUMBER:

34SV-R43-004-2

)

DIESEL GENERATOR 2A SEMI-ANNUAL TEST 7.2.3.20 Critical 7.2.3.21 7.2.3.22 7.2.3.23 7.2.3.24 7.2.3.25 7.2.3.26 7.2.3.27 With Diesel Generator 2A Voltage Adjust switch, adjust diesel output voltage to match the highest phase voltage on 4160V Bus 2E.

WHEN the synchroscope indicates 2 minutes to 12 and WHEN the synchroscope lights are at the dimmest point, TAKE ACB 135530, Diesel Gen 2A Emergency Supply, to the CLOSE position.

Using the Diesel Gen 2A Speed Adjust switch, adjust the load on the diesel to between 500 and 1000 KW.

Using the Diesel Gen 2A Voltage Adjust switch, adjust the reactive load to between 500 and 1000 KV AR.

Gradually INCREASE load to between 1750 and 2000 KW.

Adjust the reactive load to between 200 and 1000 KV AR.

PLACE Diesel Gen 2A Synchroscope switch (SSW) for ACB 135530 in OFF position.

Subsection 7.4, Diesel Generator 2A Fuel Oil Transfer Test, PAGE 12 OF 31 VERSION NO:

15.23 can be performed anytime during the Diesel Generator loaded run time.

7.2.3.28 Subsection 7.5, Diesel Generator 2A Air Compressor Test, can be performed anytime during the Diesel Generator loaded run time.

7.2.3.29 After approximately 30 minutes, gradually increase load to between 2764 and 2825 KW, while maintaining reactive load between 200 and 1000 KV AR.

7.2.3.30 After the load has been increased to greater than 2764 KW, record the time.

Time ----------------------

7.2.3.30.1 Verify the local tachometer to be reading between 860 rpm and 940 rpm.

7.2.3.30.2 If the tachometer indication is not in this band, MGR-0001 Ver. 3 initiate a condition report and hang a repair tag on the local tachometer indication.

The Shift Manager will ensure a "prompt" work order is initiated to calibrate the tachometer prior to the next monthly Diesel Generator run.

G16.030

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 13 OF 31 "DOCUMENT TITLE:

)

DIESEL GENERATOR 2A SEMI-ANNUAL TEST DOCUMENT NUMBER:

34SV-R43-004-2 VERSION NO:

15.23 Operating the diesel generator for one hour at 2764 to 2825 KW satisfies the Unit 2 NOTE:

Technical Specification SR 3.8.1.2 requirement to operate the diesel generator between 1710 and 2000 KW for an hour.

7.2.3.31 Maintain Diesel Generator 2A load between 2764 and 2825 KW for a minimum of one (1) hour.

7.2.3.32 Confirm OR place Diesel Generator 2A Amp Select switch in phase 1, 2, OR 3 position.

7.2.4 After Diesel Generator 2A has operated for 30 minutes at between 2764 and 2825 KW, record the operating parameters on Table 1 AND Table 2 of Attachment 1, Diesel Generator 2A Operating Parameters.

7.2.5 Record the time upon completion of the one (1) hour run.

NOTE:

TIME _____

WHILE reducing the load on the diesel, the diesel amperage can be monitored to ensure that a reverse power trip will NOT occur.

CAUTION"j IF DIESEL GENERATOR 2A IS OPERATED AT A LOAD OF ZERO (0) KW,

" A DIESEL TRIP WILL OCCUR AS A RESULT OF REVERSE POWER.

7.2.6 After at least one (1) hour of loaded run, perform the following:

7.2.6.1 REDUCE load to between 400 and 500 KW AND 7.2.6.2 ADJUST reactive load to between 200 and 500 KVAR.

7.2.7 TAKE ACB 135530, Diesel Gen 2A Emergency Supply, to OPEN.

7.2.8 Confirm ACB 135530, Diesel Gen 2A Emergency Supply, OPEN green light is ILLUMINATED.

G16.030 MGR-0001 Ver. 3

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 14 OF 31 "DOCUMENT TITLE:

r DIESEL GENERATOR 2A SEMI-ANNUAL TEST DOCUMENT NUMBER:

34SV-R43-004-2 VERSION NO:

15.23 7.2.9 At Diesel Generator 2A Woodward Governor, perform the following:

7.2.9.1 POSITION and verify the Speed Droop Control Knob to 0 (fully counter-clockwise).

IV 7.2.9.2 Confirm Load Limit Control Knob is fully clockwise (approximately 10).

7.2.10 At paneI2H11-P652, perform the following:

7.2.10.1 IF necessary, ADJUST frequency of the diesel generator to 60 hertz with Diesel Gen 2A Speed Adjust switch.

7.2.10.2 IF necessary, ADJUST diesel generator voltage to 4160 volts with Diesel Gen 2A Voltage Adjust switch.

7.2.10.3 PLACE and verify the Diesel Gen 2A Voltage Reg Transfer switch in AUTO position.

7.2.10.4 7.2.11 CAUTION:

7.2.12 7.2.12.1 7.2.12.2 IV Confirm:

Diesel Gen 2A Voltage Reg Transfer AUTO red light is ILLUMINATED AND the MAN green light is EXTINGUISHED.

IF necessary, ADJUST voltage to 4160 volts with Diesel Generator 2A Auto Voltage Adjust switch inside paneI2R43-P001A.

OPERATION OF THE DIESEL AT LOW LOADS FOR EXTENDED PERIODS OF TIME WILL RESULT IN OIL ACCUMULATION IN THE EXHAUST MANIFOLD DUE TO INSUFFICIENT GAS FLOWS AND TEMPERATURE TO VAPORIZE THE OIL.

At panel 2H 11-P652, perform the following:

After allowing the diesel to run for five (5) minutes unloaded (for even cooling)

PLACE the Diesel Gen 2A Start switch to STOP.

Confirm Diesel Gen 2A Start and Diesel Gen 2A Shutdown System Operative red lights are EXTINGUISHED.

G16.030 MGR-0001 Ver. 3

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 15 OF 31

'P0CUMENT TITLE:

DIESEL GENERATOR 2A SEMI-ANNUAL TEST DOCUMENT NUMBER:

34SV-R43-004-2 VERSION NO:

15.23 NOTES:

There is a 100 second time delay from the time the diesel is shutdown UNTIL Diesel Gen 2A Auto Start Sys Operative light is ILLUMINATED.

7.2.12.3 7.2.12.4 7.2.12.5 7.2.12.6

)

7.2.12.7 IF Diesel Gen 2A Auto Start Sys Operative light is EXTINGUISHED, DEPRESS Diesel Gen 2A Shutdown Relay pushbutton.

Confirm Diesel Gen 2A Auto Start Sys Operative light is ILLUMINATED.

PLACE and verify the Diesel Gen 2A Mode Select Switch in NORM.

IV IF Diesel Gen 2A Test SAT 2C Out Of Svc Interlock switch is in TEST, PLACE and verify switch in NORM.

IV Confirm annunciator DIESEL 2A IN TEST MODE (652-105) has RESET.

7.2.13 Confirm 2P41-F339A, Diesel Generator 2A Cooling Water Outlet AOV, has CLOSED by observing local position indication.

7.2.14 Proceed to the Diesel Generator Barring After Shutdown subsection of this procedure.

G16.030 MGR-0001 Ver. 3

)

rl'I'~E DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM SIM 4, RO, SRO-I PERFORM A MANUAL STARTUP OF HPCI, CONTROLLER FAILURE,

) I LOW, ALTERNATE PATH AIJr1IQ.R D. H. GIDDENS RECQNlMENI)),t])..*** BV NIR LR-JP-05.02A-OO

-'<:--~-.<--..... -:',,"

APPROVED*>>'£'

Energy to Serve Your World sM

SOUTHERN NUCLEAR OPERATING COMPANY

,PLANT E. I. HATCH

) FORM TITLE: TRAINING MATERIAL REVISION SHEET Pro~am/Course Code:

OPERATIONS TRAINING 00 05/19/07 I Initial

)

Page 1 of1 Media Number: LR-JP-05.02A-00 DHG RAB

LR-JP-05.02A-00 Page 1 of6 UNIT 1 ()

UNIT 2 (X)

PERFORM A MANUAL STARTUP OF HPCI, CONTROLLER FAILURE, LOW, ALTERNATE PATH

~

JPl\\1:iYUMBEll:

. TASK Nt1:M]iEI{:

LR-JP-05.02A-00 The task shall be completed when the HPCI System is injecting to the Reactor with turbine speed greater than 2000 rpm per 34S0-E41-001-2.

005.002 01lJETIVENUMBER.:**.**. 005.002.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.00 SRO 3.00 KIA CATALOG NUMBER: 295031 EAl.02 KIA CATALOG JTA IMPORTANCE RATING:

RO 4.5 SRO 4.5 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

GENEBALREEERENCES:

• ltltQJIIf{Jj:J);;~'l'~RIALS:

APPROXIMATE COMPLETION TIME:

5.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

LR-JP-05.02A-00 Page 2 of6 SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #113, or other full power IC, and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS:

~p

• • I***ACT *.,*.

iRATE

• TIME mtE51 109 mfR22 180 mfR22 181 mtE41 235A mtE41 235B mtE41 106 RCIC Failure to Auto Start 4KV Bus 2C Fault 4KV Bus 2D Fault HPCI Fails to Auto Start on Low Level HPCI Fails to Auto Start on Hi Drywell Pressure HPCI Flow Control Fails Low 00000 00000 00000 00000 00000 00000

3.

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

A. Perform RC-l and RC-2.

B. Allow simulator to run until RWL as indicated on 2B21-R623A and B is <-35 inches.

C. Ensure the flow Controller display show flow and NOT flow rate.

D. Acknowledge annunciators.

4.

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

5.

ESTIMATED Simulator SETUP TIME:

10 Minutes 2

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

1.

The HPCI System is in Standby.

2.

A loss of the normal Feedwater pumps has occurred.

3.

31 EO-EOP-O 1 0-2 (RC) is in progress.

4.

R WL is < -35 inches and decreasing.

5.

HPCI failed to autostart.

6.

HPCI is required to maintain R WL.

INITIATING CUES:

Start HPCI manually and inject into the Reactor.

)

/

PERFORMANCES13Ep*************

sr~ND~RfQ*******

For INITIAL Operator Programs:

LR-JP-OS.02A-OO Page 4 of6 SA'1YUNSAT*****

COMMENTS' 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:

IF the operator addresses HPCI suction transfer logic, as the Shift Supervisor, INFORM the operator that the HPCI high Torus level suction transfer logic has been overridden.

At paneI2HII-P601, LUBE OIL CLG WTR VLV, 2E41-FOS9 is OPEN, red light illuminated.

SAT IUNSAT

2. I Start HPCI Barometric Condenser Vacuum Pump, 2E41-C002-2.

At paneI2HII-P601, HPCI BAROM CNDSR VACUUM PUMP, 2E41-C002-2 is OPERA TING, red light illuminated.

SAT IUNSAT PROMPT:

IF the operator addresses posting High Radiation Areas, as the Shift Supervisor, INFORM the operator as Shift Supervisor that Health Physics is posting the areas.

At paneI2HII-P601, the TURB STEAM SUPPLY VL V, 2E41-FOO 1 control switch is in the OPEN position, red light illuminated.

SAT IUNSAT NOTE: Valve 2E41-FOOI is not required to be full open prior to proceeding to following steps.

(*

• Indicates critical step)

At pane12HII-P601, the AUX OIL PUMP, 2E41-C002-3, is OPERATING, red light illuminated.

SAT/UNSAT

6. I Confirm the following valves are open:

Turbine Control Valve Turbine Stop Valve

8. I Verify the Minimum Flow Valve, 2E41-FO 12, closes as flow increases into the reactor.

At paneI2HII-P601, PUMP DISCHARGE VL V, 2E41-F006 is OPEN, red light illuminated.

At paneI2HII-P601, the following valves are OPEN, red light illuminated:

TURBINE CONTROL VL V TURBINE STOP VL V At paneI2HII-P601, operator RECOGNIZES HPCI FLOW CONTROL, 2E41-R612 has failed low. The operator TRANSFERS the controller to manual and ADJUST until HPCI discharge pressure is greater than reactor pressure with level increasing.

At paneI2HII-P601, the operator VERIFIES MIN FLOW VL V, 2E41-F012 is CLOSED with green light illuminated.

LR-JP-05.02A-OO Page 5 of6 S1\\,TIIJNSA?r;*****.*****

SAT/UNSAT SAT/UNSAT SAT IUNSAT SAT/UNSAT NOTE: If HPCI is started PER THE PLACARD, the following steps may be omitted.

9. Confirm the following valves are At paneI2HII-P602, the operator SAT IUNSAT closed:

has CONFIRMED the following 2E41-F028 valves are CLOSED, green light illuminated:

2E41-F025 2E41-F028, STEAM LINE 2E41-F029 DRAINVLV 2E41-F026 2E41-F025, BAROM CNDSR DISCHTOCRW 2E41-F029, STEAM LINE DRAINVLV 2E41-F026, BAROM CNDSR DISCHTOCRW

(*

• Indicates critical step)

'~T)jjr.

/

/PFl:(tFORNtANCi(STEP>.

LR-JP-05.02A-00 Page 6 of6 Sf\\TIlJWS-Al' COMMENTS'

10. Confirm Barometric Condenser At panel 2H11-P60 1, the operator SAT / UNSAT Condensate Pump, 2E41-C002-1 has VERIFIED HPCI BAROM cycles automatically to maintain CNDSR LEVEL HIGH

'----_----< barom~~ic conden~!~ater

~evel. _

__, annunciat~~_~ 601-129) is CLEAR. '----______

---

.J

)

}

PROMPT:

IF the operator addresses shutting down HPCI, as Shift Supervisor, INFORM the operator that shutdown is not desired at this time.

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

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

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(*

• Indicates critical step)

END TIME: ----

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 16 OF 66 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM 34S0-E41-001-2 22.10 7.2.2 CONTROL ROOM MANUAL STARTUP CONTINUOUS I

PRIOR to a planned non-emergency HPCI system run, the Health Physics Supervisor OR Foreman will be notified to post the necessary locations as HIGH RADIATION AREAS.

These areas will be controlled during HPCI operations.

This subsection is to be performed with the HPCI System initially in the Standby mode.

NOTES: I-UNLESS indicated otherwise, the following steps will be performed at panels 2H11-P601 and 2H11-P602.

For a quick reference for starting HPCI, refer to the placard on 2H11-P601 AND in Attachment 5.

During HPCI operation, increases in iodine and noble gas readings and a decrease in drywell-to-torus dp will occur. Fission product monitoring system alarms may be received.

• ... 'CAUTION.IIF SUPPRESSION POOL TEMPERATURE REACHES 95'F DURING HPCIOPERATION, Ii

. ENTER 34AB-T23-003-2, TORUS TEMPERATURE ABOVE 95'F.

7.2.2.1 7.2.2.2 7.2.2.3 OPEN 2E41-F059, Lube Oil Clg WtrVlv.

START 2E41-C002-2, Barom Cndsr Vacuum Pump.

The following step is a CRITICAL step.

Confirm the necessary locations are posted as High Radiation areas, except in an emergency situation.

MGR-0001 Ver. 4 I

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 17 OF 66 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM 34S0-E41-00 1-2 22.10 NOTES:

• HPCI Operation at rated flow and pressure results in approx. 300 gpm water discharged to the Torus due to steam flow. This will raise Torus water level at a rate of approx. 3"/hr.

• Frequent checks are to be made as to system flow rates, discharge pressure, reactor vessel level and reactor pressure during manual operations.

CAUTIONS:

7.2.2.4 7.2.2.5 7.2.2.6 7.2.2.7

• PROLONGED OPERATION OF THE HPCI TURBINE BELOW 2000 RPM OR AT LOW LOADS IS TO BE AVOIDED TO PREVENT TURBINE EXHAUST CHECK VALVE CHATTER.

• PROLONGED OPERATION OF THE HPCI TURBINE BELOW 2000 RPM WITH THE AUXILIARY OIL PUMP TRIPPED IS TO BE AVOIDED TO ENSURE ADEQUATE OIL PRESSURE FOR PROPER TURBINE GOVERNOR OPERATION AND BEARING LUBRICATION.

OPEN 2E41-F001, Turb Steam Supply Vlv.

TAKE 2E41-C002-3, Aux Oil Pump, control switch to the START position.

OPEN 2E41-F006, Pump Discharge Vlv.

Confirm the following valves OPENED:

Turbine Control Vlv Turbine Stop Vlv 7.2.2.8 Confirm the turbine comes up to speed as directed by 2E41-R612, Flow Control.

7.2.2.9 WHEN flow increases to 790 GPM, confirm 2E41-F012, Min FlowVlv, CLOSED.

7.2.2.10 Confirm CLOSED/CLOSE the following valves:

2E41-F028, Steam Line Drain Vlv 2E41-F025, Barom Cndsr Disch To CRW 2E41-F029, Steam Line Drain Vlv 2E41-F026, Barom Cndsr Disch To CRW 7.2.2.11 Confirm 2E41-C002-1, Barom Cndsr Cond Pump, cycles automatically to maintain barometric condenser water level.

7.2.2.12 IF necessary, ADJUST 2E41-R612, HPCI Flow Control, to the desired injection rate.

MGR-0001 Ver. 4

SOUTHERN NUCLEAR PAGE PLANT E. I. HATCH 18 OF 66 DOCUMENT TITLE:

DOCUMENT NUMBER: VERSION NO:

HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM 34S0-E41-00 1-2 7.2.2.13 IF Condensate Storage Tank level decreases below 2 feet 10 inches OR Suppression Chamber level exceeds 152 inches, confirm the following:

• 2E41-F041 and 2E41-F042, Torus Outbd and Inbd Suct Valves, OPEN;

• 2E41-F004, CST Suction Valve, CLOSES 22.10 7.2.2.14 IF necessary to shift from level control to pressure control, perform the following:

NOTE: IIF 2E41-F008 and 2E41-F011 are OPEN at the same time, HPCI is considered inoperable AND the requirements of Technical Specification 3.5.1 must be met.

WHEN 2E41-F008 AND 2E41-F011, TEST TO CST VLVS, AND 2E41-F006, PUMP DISCHARGE VLV, ARE ALL OPEN SIMULTANEOUSLY, RPV AND CST LEVELS ARE TO I.ICAUTION:I BE MONITORED FOR LEAKAGE TO THE CST. RAPID CHANGES OF INJECTION FLOWS ARE ALSO POSSIBLE.

}

)

7.2.2.14.1 OPEN 2E41-F011, Testto CSTVlv.

7.2.2.14.2 Slowly THROTTLE OPEN 2E41-F008, Test To CSTVlv.

7.2.2.14.3 Notify Shift Supervisor to declare HPCI INOP AND place under an LCO.

7.2.2.14.4 WHEN HPCI pump discharge pressure is less than reactor pressure, CLOSE 2E41-F006, Pump Discharge Vlv.

7.2.2.14.5 Adjust 2E41-F008 and 2E41-R612, Flow Control for pressure AND flow control.

7.2.2.15 WHEN HPCI is system is no longer necessary for RPV water level OR pressure control, SHUT DOWN the system per Control Room Shutdown subsection of this procedure.

MGR-0001 Ver. 4

NIR DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM 81M 5, RO, SRO... I SOUTHERN.'

COMPANY Energy to Serve Your World SM

I SOUTHERN NUCLEAR OPERATING COMPANY

• ,PLANT E. I. HATCH

)'

FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:

OPERATIONS TRAINING Media Number:

LR-JP-20003A

.* iJl,~V.~f).;.

.... ********************~.i~soh ***~e~i;;l;.:ii*i<

• • • • • • • • • • • • • • • • • • Author's

.~uPV'~

1<f.):It~*******.**/

.... Initials....

..... ii'>/............./................

.*********i

• .*.*Illitials 00 01125102 Initial development TLB DHG 01 03119/02 Include initial operator statement RAB RAB 02 05/27/05 Revised Initial License statement for successful RAB RAB completion 03 06/07/05 Include instructor feedback RAB RAB 04 05105/06 Remove Response Cues RAB RAB J

)

LR-JP-20003-04 Page 1 of6 UNIT 1 0

UNIT 2 (X)

OVERRIDE AND REOPEN PLANT SERVICE WATER ISOLATION VALVES LR-JP-20003-040 The task shall be completed when the Plant Service Water Isolation valves isolation signal has been overridden and the header pressure is controlled greater than 80 psig.

200.013 200.013.A PLANT HATCH JTA IMPORTANCE RATING:

RO 4.0 SRO 4.0 KIA CATALOG NUMBER 295018 AA2.05 KIA CATALOG JTA IMPORTANCE RATING:

RO 2.9 SRO 2.9 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

APPROXIMATE COMPLETION TIME:

3.0 Minutes (current version) OR PSWPlacard Key for Plant Service Water valves Isolation Override.

SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

)

SIMULATOR SETUP Simulator Initial Conditions:

LR-JP-20003-040 Page 2 of6

1.

RESET the Simulator to IC #113, or other full power IC, and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS and OVERRIDES:

mfP64 193A I Drywell Chiller Compressor A Failure mfP64 193B I DryweU Chiller Compressor B Failure mfP41 264B I PSW Line Break (Div 2 Supply) mfP41-67D Service Water Pump D Trip i QYE.R,RIDE diP41-COOIC PSWPumpC 10P41-COOIC Gl I PSW Pump C 10P41-COOIC R2 I PSW Pump C

'\\:F'I~~

VALUE 10 RAMP*

RATE 100 TRIP OFF OFF

'A.C'j>

TIME.**

00000 00000 0000

3.

Take the simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS.

A. When the plant scrams on high Drywell pressure, perform RC-l and RC-2.

B. Stabilize Reactor water level at 10 to 50 inches.

4.

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

5.

ESTIMATED Simulator SETUP TIME:

25 minutes NOTE: It takes 10-11 minutes to get a LOCA signal from loss ofDW chillers.

(*

• Indicates critical step)

)

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

1. PSW Pump 2C is tagged out for maintenance.

2. PSW Pump 2D tripped. Maintenance is investigating.

3. An event has occurred that caused the Unit Two Turbine Building Plant Service Water Isolation valves to isolate.

4. There is no indication of a physical PSW line break.

INITIATING CUES:

Reopen the Turbine Building Service Water Isolation Valves per 34AB-P41-001-2.

1.

2.

I

rEItF(JRMA.NGESij:p.

For INITIAL Operator Programs:

LR-JP-20003-04 Page 4 of6

. Sl\\r.rKlJ~~AT COMMENTS 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: Either Division lOR II may be started first. The completion of either Division will complete the JPM (Step 1,3 & 13 are common. Div II starts at step 8)

START TIME: ___ _

Operator obtains the procedure.

Operator obtains a copy of 34AB-SAT IUNSAT P41-001-2.

Operator verifies PSW Division I Operator VERIFIES Division I SAT/UNSAT Header Pressure is greater that 80 Plant Service Water Header psig.

Pressure as indicated by 2P41-R601A is greater that 80 psig.

NOTE: Override switches are arranged AID and B/C so both switches must be in "override" to open either Div I or Div II valves.

qper:~tor"pyt~;tl~~"WePlaflt

• • $.r:ryi(je:J'aterJl!rbi,~e.EJl!ildi~i ***.. *....*...*...

lsol;iti?n§i~aI

.** fo[JlieZ~41~g~l6f\\.**.

(3Jld,Q,>aJ1clfor:the2P4J... FJ16*BallxJ.

CE At paneI2HII-P652, tlie operator POSITIONS the Keylock override switcli for valves 2P41-F316AID and 2P41-F316B/C to tlie "OVERRIDE" position.

NOTE: The operator may elect to open the 2P41-F316C(D) valve before tlie 2P41-F316A(B) valve.

At pane12HII-P652, tlie operator POSITIONS Control Switcli for 2P41-F316A( C) to tlie "OPEN" position, red liglit illuminated, green liglit extinguislied.

SAT I UNSAT SAT I UNSAT

(*

• Indicates critical step)

6. I Operator detennines that PS\\V Division I Header Pressure is decreasing.

At pane12Hl1-P652, operator THROTTLES open valve 2P41-F316(C)A, red light illuminated, while periodically monitoring Division I Header Pressure.

Operator VERIFIES Division I Plant Service Water Header Pressure is decreasing as indicated by 2P41-R601A.

At panel 2HII-P652, the operator THROTTLES OR CLOSES 2P41-F316C(A) to maintain Division I Header Pressure greater than 80 psig.

LR-1P-20003-04 Page 5 of6

--$~froN$$:'1r

,eOMMEN1;S SAT IUNSAT SAT/UNSAT SAT IUNSAT NOTE: IF 2P41-F316 C(A) switch is placed to CLOSE, the valve will travel to the full closed position.

8. Operator verifies PSW Division II Operator VERIFIES Division II Header Pressure is greater that 80 Plant Service Water Header pSlg.

Pressure as indicated by 2P41-R601B Is greater that 80 psig.

NOTE: The operator may elect to open the 2P41-F316D valve before the 2P41-F316B valve.

At paneI2HII-P652, the operator POSITIONS Control Switch for 2P41-F316B(D) to the "OPEN" position, red light illuminated, green light extinguished.

At paneI2HI1-P652, the operator THROTTLES open valve 2P41-F316D(B), red light illuminated, while periodically monitoring Division II Header Pressure.

(*

• Indicates critical step)

SAT IUNSAT SAT IUNSAT SAT IUNSAT

)S~ltr;:

/.... f/:,.

11. I Operator detennines that PSW Division II Header Pressure is decreasing.

Operator VERIFIES Division II Plant Service Water Header Pressure is decreasing as indicated by 2P41-R60IB.

At paneI2HII-P652, the operator THROTTLES OR CLOSES 2P41-F316D(B) to maintain Division II Header Pressure greater than 80 psig.

LR-JP-20003-04 Page 6 of6

• • '***.St\\TI]TNs'll'f Co.MMENTS SAT/UNSAT SAT I UNSAT NOTE: IF 2P41-F316 D(B) switch is placed to CLOSE, the valve will travel to the full closed position.

13. Operator notifies Shift Supervisor.

Operator infonns the Shift Supervisor that a2P41-F316 (A-D) valve must remain throttled to maintain Division header pressure

---

,greater than 80 psig.

NOTE:

The tenninating 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.

Operator is maintaining Division I & II header pressures greater than 80 psig.

TERMINATING CUE: We will stop here.

(*

• Indicates critical step)

SAT IUNSAT END TIME: ___ _

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 10 OF 18 DOCUMENT NUMBER: I VERSION NO:

34AB-P41-001-2 9.10 DOCUMENT TITLE:

)

LOSS OF PLANT SERVICE WATER 4.18 Re-opening Turbine Bldg. Isolation Valves 4.18.1 IF 2P41-F316A, 2P41-F316B, 2P41-F316C, 2P41-F316D, PSW To Turb Bldg, are closed AND there is no physical indication of a PSW Line Break DOWNSTREAM of 2P41-F316A, 2P41-F316B, 2P41-F316C, 2P41-F316D, OR when directed by the EOPs to maintain 2P41-F316A, 2P41-F316B, 2P41-F316C, 2P41-F316D open with no physical indication of a PSW Line Break, THEN perform the following:

4.18.1.1 IF PSW Division 1 Header Pressure is above 80 PSIG, THEN:

4.18.1.1.1 PLACE the following keylock switches to OVERRIDE:

OVERRIDE FOR 2P41-F316A & 2P41-F316D OVERRIDE FOR 2P41-F316B & 2P41-F316C.

4.18.1.1.2 OPEN 2P41-F316Aor 2P41-F316 C.

Critical 4.18.1.1.3 THROTTLE OPEN 2P41-F316C or 2P41-F316A maintaining Division 1 Header Pressure above 80 PSIG.

4.18.1.2 IF PSW Division 2 Header Pressure is above 80 PSIG, THEN:

4.18.1.2.1 PLACE the following keylock switches to OVERRIDE:

OVERRIDE FOR 2P41-F316A & 2P41-F316D OVERRIDE FOR 2P41-F316B & 2P41-F316C.

4.18.1.2.2 OPEN 2P41-F316B or 2P41-F316D Critical 4.18.1.2.3 THROTTLE OPEN 2P41-F316D or 2P41-F316 B maintaining Division 2 Header Pressure above 80 PSIG.

4.18.1.3 IF 2P41-F316A, 2P41-F316B, 2P41-F316C, or 2P41-F316D must be left partially closed, THEN continue in this procedure.

4.18.1.4 IF all valves 2P41-F316A, 2P41-F316B, 2P41-F316C, 2P41-F316D can be fully opened AND PSW Division 1 AND 2 Header Pressures maintained above 80 PSIG, THEN exit this procedure.

POSTED at 2H11-P652 Ref. 34AB-P41-001-2 MGR-0001 Rev. 4.0

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 11 OF 18 DOCUMENT TITLE:

DOCUMENT NUMBER: I VERSION NO:

)

LOSS OF PLANT SERVICE WATER 34AB-P41-001-2 9.10 4.18.2 IF 2P41-F316A, 2P41-F316B, 2P41-F316C, 2P41-F316D, PSW To Turb Bldg, are OPEN AND there is no physical indication of a PSW Line Break DOWNSTREAM of 2P41-F316A, 2P41-F316B, 2P41-F316C, 2P41-F316D, and it is desired to maintain the valves OPEN, THEN perform the following:

4.18.2.1 IF PSW Division 1 Header Pressure is above 80 PSIG, THEN PLACE OVERRIDE FOR 2P41-F316A & 2P41-F316D keylock switch to OVERRIDE AND confirm 2P41-F316A & 2P41-F316D remain open.

4.18.2.2 IF PSW Division 2 Header Pressure is above 80 PSIG, THEN PLACE OVERRIDE FOR 2P41-F316B & 2P41-F316C to OVERRIDE AND confirm 2P41-F316B & 2P41-F316C remain open.

MGR-0001 Rev. 4.0

)

)

NIR DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM SIM 6, RO, SRO-I SOUTHERN..

COMPANY Energy to Serve Your World SM

lSOUTHERN NUCLEAR OPERATING COMPANY

., PLANT E. I. HATCH

[FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 ofl Pro.£!:.amlCourse Code:

OPERATIONS TRAINING Media Number:

LR-JP-25040 00 11108/01 Initial development.

RLS DHG 01 03/25/02 Include initial operator statement RAB RAB 02 06/27/05 Revised Initial License statement for successful RAB RAB completion 03 I 04126106 Change initial condition step reference from 4.3 to 4.5 ELl RAB due to orocedure chanQ:e. removed ResDonse Cues

')

LR-JP-25040-03 Page 1 of5 UNIT 1 0 UNIT 2 (X)

REACTOR PRESSURE CONTROL WITH SRVs LR-JP-25040-03 The task will be completed when the operator is controlling Reactor pressure in a band using SRVs per 34AB-N71-001-2.

200.034 200.034.C PLANT HATCH JTA IMPORTANCE RATING:

RO 3.76 SRO 3.55 KIA CATALOG NUMBER: 295025 EAl.03 KIA CATALOG JTA IMPORTANCE RATING:

RO 4.4 SRO 4.4 OPERA TOR APPLICABILITY: Nuclear Plant Operator (NPO)

APPROXIMATE COMPLETION TIME:

10 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

SIMULATOR SETUP Simulator Initial Conditions:

LR-JP-2S040-03 Page 2 ofS

1.

RESET the Simulator to IC #113, or other full power Ie, and leave in FREEZE.

2.

PLACE clearance tag on HPCI Aux Oil Pump PTL.

3.

INSERT the following MALFUNCTIONS & OVERRIDES:

miN71 68A I Circulation Pump A Trip miN71 68B I Circulation Pump B Trip mfB21 129M I Main Steam Relief Valve M Fails Stuck mfB21-226A I Low-Low-Set A Fails Inop mfB21-226B I Low-Low-Set B Fails Inop OYF,AAI]))t loE41A-S20G1 I HPCI Aux Oil Pump 10E41A-S20R2 I HPCI Aux Oil Pump

~~.A~T

!V\\TE"TIME

}(IN'AI.'

VALUE*

OFF OFF 00000 99999 00000 00000 00000

4.

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

A. Insert Malfunction miN71 68B.

B. Immediately close MISIVs(to maintain Rx Pressure)

C. Perform RC-l and RC-2 actions.

D. Ensure Rx Press (B02S) is in computer window on P603 E.

Let simulator run until SRVs cycle on the electric open signal.

5.

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

6.

ESTIMATED Simulator SETUP TIME:

15 minutes 2

)

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

1. HPCI is tagged out for maintenance.

2. A total loss of Circ water has occurred.

3. The Reactor has been scrammed.

4. The Main Condenser has been isolated from the Reactor.

5. Other operators are performing scram actions.

INITIATING CUES:

MAINTAIN Reactor pressure at 700 to 850 psig using SRV s, lAW 34AB-N71-001-2, Step 4.5.

• • lI.***

.. * *.*. T*.*.*.*

.* *.. '. It

..*........ p llf.*.** *.****

1.

For INITIAL Operator Programs:

LR-JP-25040-03 Page 4 of5 For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

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

Operator identifies the procedure Operator has IDENTIFIED the needed to perform the task.

correct procedure as 34AB-N71-001-2.

START TIME: ___

SAT/UNSAT PROMPT:

IF the operator addresses using other systems to control Reactor pressure, INFORM the operator to use SRVs.

2. Operator identifies applicable system Operator has IDENTIFIED the SAT I UNSAT operating procedures to perform the correct procedure as task.

34S0-B21-001-2.

)

)

PROMPT:

IF the operator addresses using the Placard sequence for opening the SR V s, DIRECT the operator to follow the procedure.

NOTE: The 2B21-F013M fails to open with the switch.

3. Attempts to OPEN SRV At Pane12HII-P602, the operator SAT/UNSAT 2B21-F013M.

attempts to OPEN 2B21-F013M.

4. The failure of the 2B21-F013M to At 2HII-P602 the operator SAT/UNSAT open is recognized.

RECOGNIZES the failure of the 2B31-F013M to open.

PROMPT:

IF the operator reports the failure of the 2B21-F013M to open, INFORM the operator that you will get Maintenance to investigate, and to continue control Reactor pressure in the band.

At Panel 2HII-P602, the operator OPENS 2B21-F013B.

SAT IUNSAT

(** Indicates critical step)

)

)

LR-JP-25040-03 Page 5 of5 PROMPT:

IF the operator addresses checking SRV tailpipe temperature on recorder 2B21-R614, at PaneI2HII-P614, INFORM the operator that another operator will check the recorder for proper SRV operation.

6. I Reactor pressure in band:

700 to 850 psig The operator CONTROLS pressure in band:

700 to 850 psig (+/-50 psig)

At pane12HII-P602 the operator CLOSES 2B21-F013B by taking the switch to the CLOSE position prior to Reactor pressure decreasing below its band (-50 psig).

SAT I UNSAT SAT I UNSAT NOTE: AFTER the operator has demonstrated proper control of Reactor pressure, INFORM the operator that another operator will continue maintaining Reactor pressure in band.

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.

Operator has controlled pressure between 700-800 psig.

TERMINATING CUE: We will stop here.

END TIME: ___

(** Indicates critical step)

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 19 OF 35 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

AUTOMATIC DEPRESSURIZATION (ADS) AND LOW-LOW SET (LLS) SYSTEMS 34S0-B21-001-2 13.10 7.4 INFREQUENT OPERATIONS 7.4.1 Manual Operation of Safety Relief Valves NOTES:

I CONTINUOUS I

• Unless otherwise noted, all steps will be performed at paneI2H11-P602.

• IF possible, operate the safety valves in the following sequence to control suppression pool heat distribution: M, B, G, F, D, L, K, C, A, E, H. (Posted @ 2H11-P602)

• The RED indicator light for SRV shows ONLY that the actuating solenoid is energized. It is NOT positive indication of valve position. The RED light will be illuminated only when the electrical signal is present to open the SRV.

• The YELLOW indicator light for SRV indicates the Tailpipe Pressure switch has reached its setpoint.

• The GREEN indicator light for SRV will extinguish with the Control Switch in OPEN.

• In the event of a reactor vessel flooding incident, the temperature/pressure associated with a water environment may not actuate the 85 psig pressure switches as normally expected with an SRV open demand present. Operator action for failure OR apparent failure of SRV's should be to enter 34AB-B21-003-2, Failure Of Safety/Relief Valves.

7.4.1.1 OPEN any safety relief valve by placing its control switch to the OPEN position.

7.4.1.2 Confirm the RED indicator light for SRV is ILLUMINATED.

o o

7.4.1.3 MGR-0001 Ver. 3 Confirm the SRV is OPEN by using the following methods:

RPV pressure decreasing as indicated on multiple indications 0

Annunciator SAFETY / BLOWDOWN VALVE PRESS HIGH (602-311) is ILLUMINATED.

However, annunciator may be EXTINGUISHED if low RPV pressure exists or the SRV is passing water.

0 YELLOW indicator light ILLUMINATED for applicable SRV.

However, light may be EXTINGUISHED if low RPV pressure exists or the SRV is passing water.

0 Temperature increasing on 2B21-R614 Auto Blowdown / Safety Valve Temps recorder at pane12H11-P614 for applicable SRV D

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 20 OF 35 IJOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

AUTOMATIC DEPRESSURIZATION (ADS) AND LOW-LOW SET (LLS) SYSTEMS 34S0-B21-001-2 13.10 NnTI=:

Safety relief valves 2B21-F013A, C, E, H, K, L, M are ADS Relief Valves.

7.4.1.4 IF an ADS valve has been manually opened AND the desired pressure reduction is achieved, perform the following:

7.4.1.4.1 7.4.1.4.2 7.4.1.4.3 CLOSE the ADS valve by placing its control switch to the AUTO position.

Confirm GREEN indicator light for SRV is ILLUMINATED.

Confirm RED indicator light for SRV is EXTINGUISHED.

NOTE:

Safety relief valves 2B21-F013B, D, F, G are LLS I Manual Relief Valves.

7.4.1.5 IF a LLS valve has been manually opened AND the desired reactor pressure reduction is achieved, perform the following:

7.4.1.5.1 7.4.1.5.2 7.4.1.5.3 7.4.1.6 7.4.1.7 7.4.1.8 CLOSE the LLS valve by placing its control switch to the CLOSE position.

Confirm GREEN indicator light for SRV is ILLUMINATED.

Confirm RED indicator light for SRV is EXTINGUISHED.

RESET the safety relief valve leak detection logic as follows:

PLACE Leak Detection Logic A Reset keylock switch (2B21-S5A) to RESET position and back to NORMAL position.

PLACE Leak Detection Logic B Reset keylock switch (2B21-S5B) to RESET position and back to NORMAL position.

Confirm YELLOW indicator light for SRV is EXTINGUISHED.

Confirm temperature decreasing on 2B21-R614 Auto Blowdown I Safety Valve Temps recorder at pane12H11-P614 for applicable SRV.

o o

o o

o o

o o

o o

7.4.1.9 Confirm the system is in STANDBY per the STANDBY subsection of this procedure. 0 MGR-0001 Ver. 3

NIR DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM SIM 7, RO, SRO-I SOUTHERN.\\

COMPANY Energy to Serve Your World SM

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

OPERATIONS TRAINING Page 1 of 1 Media Number:

LR-JP-13.63 00 06/22/95 Initial development RAB SMC 01 06/26/96 Format change, change time allowance RAB DHG 02 04110197 Revised based on feedback from the from 1996 SCB RSG Requal annual exam.

03 03/02/99 Revised due to new simulator computer.

SCB DHG 04 02/04/00 Format modification, change time allowance based on RAB DHG running average, adjust title 05 04/24/00 Based on student feedback, expanded the initiating RAB DHG cue to be more exact 06 05119100 Based on instructor feedback, correct simulator setup RAB DHG 07 11102/00 Include objective number, change time allowance RAB DHG based on running average 08 03111102 Include initial operator statement RAB RAB 09 06110105 Revised Initial License statement for successful RAB RAB completion 10 04/07/06 Remove Response Cues RAB RAB

LR-JP-13.63-10 Page 1 of6 UNIT 1 0

UNIT 2 (X)

USING THE OVERRIDE SWITCHES, VENT THE TORUS WITH THE CAD SYSTEM JPM'~UM~ETt::<.

.... LR-JP-13.63-10 The task shall be completed when the Torus is being vented via the CAD System, per 31EO-EOP-101.

'J1.A.$,K*NtJ1Vf'F:~f'

. 013.063 OfiJ)!jtiTI'\\IJjJNtiMjER;* 013.063.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.56 SRO 3.16 KIA CATALOG NUMBER: 295038 EKl.02 KIA CATALOG JTA IMPORTANCE RATING:

RO 4.2 SRO 4.4 OPERA TOR APPLICABILITY:

Nuclear Plant Operator (NPO)

APPROXIMATE COMPLETION TIME:

9.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

SIMULATOR SETUP Simulator Initial Conditions:

1.

RESET the Simulator to IC #113, or other full power IC, and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS & DIGITAL POINTS (SVO):

LR-JP-13.63-10 Page 2 of6

F'l~~t>,~~,*..*.i\\ff'j?*.**

VAI.;J.TE>RATE*.. *****:TIMR mfP64 193A DryweU Chiller Compressor A Failure mfP64 193B Drywell Chiller Compressor B Failure mfB21 123A Steam Line A Break (Before Restrictor) (Var)

MFdl1 282A Fuel Gas Gap Release

,}j(;)lNtS********

svoP33080 DW 02 02 Concentration in Drywell svoP33081 DW H2 H2 Concentration in Drywell svoP33082 SP 02 02 Concentration in Torus svoP33083 SP H2 H2 Concentration in Torus 25 1000

.05

.063 1000

.069 1000

.066 1000

.071 1000 00000 00000 00000 See Step 3.E t\\.(J'f ***..

TIME

3.

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

A.

Place H2/02 analyzers in service.

B.

Start SBGT System "A" with a suction from the Reactor Building C.

Perform EO-EOP-114-2 to control RHR and CS injection flow rate.

D. Allow the simulator to run until the plant is in the UNSAFE Region of the DSIL Curve.

E.

When in the UNSAFE Region of the DSIL Curve, close the MSIVs and open the ADS valves.

F.

Maintain R WL around "0" inches with Condensate.

G. Activate Fuel Gap Release malfunction and wait for rad alarms to come in.

4.

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

5.

ESTIMA TED Simulator SETUP TIME:

10 Minutes

(

\\

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

1.

A steam line broke in the Drywell.

2.

Fuel failure exists based on Lab grab samples.

3.

Standby Gas Treatment is in operation.

4.

Normal AC Power is available.

5.

A Group II isolation has occurred.

INITIATING CUES:

Vent the Torus with the "A" loop CAD valves, per 3IEO-EOP-1D1-2, irrespective of offsite radiological release rate, defeating isolation interlocks.

For INITIAL Operator Programs:

LR-JP-13.63-10 Page 4 of6 For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

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

1. Operator obtains the procedure.

(*

• Indicates critical step)

Operator obtains 3IEO-EOP-lOI-

2.

At pane12HII-P657, the operator PLACES the keylock PCIS Override Switches to OVERRIDE for:

• High Drywell Press, 2T48-F332A

• High Drywell Press, 2T48-F333A At paneI2HII-P657, the operator PLACES the keylock PCIS Override Switches to OVERRIDE for:

• Low RPV Level, 2T48-F332A

• Low RPV Level, 2T48-F333A START TIME: ___ _

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

(** Indicates critical step)

At paneI2HII-P657, the operator PLACES the keylock PCIS Override Switches to OVERRIDE for:

• Rx Bldg High Radn, 2T48-F332A

• Rx Bldg High Radn, 2T48-F333A At paneI2HII-P657, the operator PLACES the keylock PCIS Override Switches to OVERRIDE for:

• Refuel FIr High Radn, 2T48-F332A

• Refuel FIr High Radn, 2T48-F333A At paneI2HII-P657: TORUS VENT ISOL VL V, 2T48-F332A is OPEN, red light illuminated.

At paneI2HII-P657: TORUS VENT ISOL VL V,2T48-F333A is OPEN, red light illuminated.

At paneI2HII-P657, the operator OPENS FLOW CNTL FOR F337A,2T48-R616A:

TORUS VENT FLOW CNTRL VLV, 2T48-F337A is OPEN, red light illuminated.

OR Flow indicated on recorder TORUS VENT EXH FLOW A, 2T48-R620.

LR-JP-13.63-10 Page 5 of6 SAT I UNSAT SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT

9. Monitor Torus Pressure indication on recorder 2T48-R608.

At paneI2HII-P657, recorder "MIDRANGE PRESS DRWLlTORUS," 2T48-R608, has been IDENTIFIED by operator.

LR-JP-13.63-10 Page 6 of6

$i\\.l'llJNScAT;**.*.***..

COMMENTS**

SAT IUNSAT PROMPT:

WHEN the operator addresses Torus pressure, INDICATE for the operator that Torus pressure is less than 56 psig and slowly decreasing.

NOTE:

The tenninating 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.

Operator has started venting and is monitoring pressure.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

END TIME: ----

SOUTHERN NUCLEAR PLANT E. I. HATCH I)OCUMENT TITLE:

EMERGENCY CONTAINMENT VENTING 3.0 OPERATOR ACTIONS 3.1 SUPPRESSION CHAMBER VENTING DOCUMENT NUMBER:

31 EO-EOP-101-2 3.1.1 Confirm STARTED/START Standby Gas Treatment taking suction from the Reactor Building per 34S0-T46-001-2.

EITHER OR both CAD vent trains may be used as required However:

PAGE 20F 12 VERSION NO:

4.1

-IF 2R25-S064, Instrument Bus 2A, is de-energized, only the 'B' Loop CAD valves can be used.

NOTE:

-IF 2R25-S065, Instrument Bus 2B, is de-energized, only the 'A' Loop CAD valves can be used.

-IF both 2R25-S064 AND 2R25-S065 are de-energized, Suppression Chamber Venting is NOT possible.

3.1.2 Place keylock PCIS Override Switches to OVERRIDE:

DESCRIPTION 2T 48-F332A(B), High Drywell Press 2T48-F333A(B), High Drywell Press 2T 48-F332A(B), Low RPV Level 2T 48-F333A(B), Low RPV Level 2T 48-F332A(B), Rx Bldg High Radn 2T48-F333A(B), Rx Bldg High Radn 2T48-F332A(B), Refuel Fir High Radn 2T48-F333A(B), Refuel Fir High Radn 3.1.3 OPEN:

VALVE 2T 48-F332A(B) 2T48-F333A(B)

DESCRIPTION Torus Vent Isol Vlv Torus Vent Isol Vlv LOCATION 2H11-P657(P654) 2H11-P657(P654) 2H11-P657(P654) 2H11-P657(P654) 2H11-P657(P654) 2H11-P657(P654) 2H11-P657(P654) 2H11-P657(P654)

LOCATION 2H11-P657(P654) 2H11-P657(P654) 3.1.4 Operate 2T48-R616A(B), Torus Vent Flow Cntl Vlv 2T48-F337A(B), as required to maintain Suppression Chamber pressure below 56 psig, at 2H11-P657(P654).

3.1.5 IF Suppression Chamber pressure can NOT be maintained below 56 psig, THEN perform 3.1.6.

G16.30 MGR-0001 Rev 3

NIR DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM SIM 8, RO Only SOUTHERN..

COMPANY

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

OPERATIONS TRAINING Media Number:

~¢~'t/ I/,fi"~f~c,c Cc)i"iCiiJt~~i~~~it-Xj.'It{*Ci,>i:>r;j}~i~c>>.?;~i

• • ~~k****

1*.* c*...... *.i~.;3"7\\}~.c**...}

.'.........i.i.;i...*.Ic",i'. "i"'>ii,"..*"(t,,~,::..x 07 11103/00 Include objective number 08 02/20/02 Change numbers referenced for rod pull due to change in simulator 09 03/19/02 Include initial Operator statement 10 06/22/05 Revised Initial License statement for successful completion 11 05/09/06 Remove Response Cues 12 11105108 Changed Rod Group to Steps and made to match current move sheets; Changed power to 60% RTP; modified critical step to match procedure; changed to enter malfunction after 1 st rod inserted.

Page 1 of 1 LR-JP-25012 AtrtltoPs Supy'~

Xnijitils "'i " I.. lti~l~.

RAB DHG DNM DHG RAB RAB RAB RAB RAB RAB ADY BKW

LR-1P-25012-12 Page 1 of8 UNIT 1 ()

UNIT 2 (X)

JTAS.isc.'tlT:Jj~:i'.

• • <JPMit:r~jR;~.

MOVE CONTROL RODS AFTER A CRD PUMP TRIP

., LR-1P-25012-12 The task shall be completed when two control rods in the specified step have been moved to the specified position per 34GO-OPS-065-0.

001.010 PLANT HATCH JTA IMPORTANCE RATING:

RO 3.57 SRO 3.52 KIA CATALOG NUMBER: 201001A201 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.20 SRO 3.30 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

APPROXIMATE COMPLETION TIME:

13.0 Minutes SIMULATOR SETUP:

REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

SIMULATOR SETUP Simulator Initial Conditions:

LR-1P-25012-12 Page 2 of8

1.

RESET the Simulator to IC 110, or other IC at approximately 60% RTP, and leave in FREEZE.

2.

INSERT the following MALFUNCTIONS:

mfCll 30A CRD Pump A Trip RAMP* ACT;

• • • • AATE"TIl\\fE 99999

3.

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

A.

Insert Control Rods in Step 50 to Position 18.

B.

Ensure that CRD Pump 2A is operating.

C.

Flag annunciators:

o 603-211 RBM DOWNSCALE o 603-238 ROD OUT BLOCK

4.

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

5.

ESTIMATED Simulator SETUP TIME:

15 Minutes

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

1.

A normal plant shutdown is in progress per 34GO-OPS-013-2.

2.

Rod insertion per the prescribed sequence is in progress.

3.

Rod insertion has begun in Step 50, with all control rods in the STEP presently at position "18".

4.

The STA has recommended inserting Rods in Step 50 to its insert limit at position "12."

5.

Rod Worth Minimizer is operable and has been loaded with the correct movement sequence, which has been approved by the Reactor Engineering Supervisor.

6.

Due to the rod movements, the following reoccurring annunciators have been flagged:

o 603-211 RBM DOWNSCALE o 603-238 ROD OUT BLOCK

7.

All Pre Job Brief evolutions have taken place.

INITIATING CUES:

Follow the STA's recommendation to insert Rods, in reverse order, at Step 50, to position "12."

f~p...

1.

2.

3.

For INITIAL Operator Programs:

LR-1P-25 0 12-12 Page 4 of8

• • • .&ATt'UNS.i\\'l'

• • • • 6MMENTS For 6JT/6JE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

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

Operator identifies the procedure Operator has identified the correct needed to perform the task.

procedure as 34GO-OPS-065-0.

Operator reviews the procedure's Operator has reviewed the precautions and limitations.

precautions and limitations.

Operator identifies correct procedure Operator refers to section 7.2.1, section.

Use of Rod Movement Sequences.

START TIME: ___ _

SAT IUNSAT SAT IUNSAT SAT/UNSAT PROMPT:

WHEN the Operator addresses an approved copy ofthe Control Rod Movement Sequence Sheet, GIVE the Operator Control Rod Movement Sequence Sheet for Step 50. (You may use the Simulator move sequence book premarked for intermediate position 18).

PROMPT:

IF the Operator asked if continuous rod movement is allowed, as SS

4.

INF6RM the Operator that continuous may be used.

NOTE: These steps are written for rods 34-27 and 18-27. Rods 26-35 and 26-19 are the other two rods in step 50. The Operator may select any control rod in Step 50, although the Operator should proceed in reverse consecutive order.

Select a control rod 34-27.

At paneI2H11-P603, push-button SAT IUNSAT is DEPRESSED on CONTROL ROD SELECT Matrix for control rod 34-27

(*

• Indicates critical step)

5. Continues rod insertion by notch to position 12 or Continues rod insertion "continuous" to position 14. (one step prior to insert limit)

7. ConfIrm the proper control rod movement.

8. Complete the line, for rod 34-27, on the Control Rod Movement Sequence sheet.

At paneI2HII-P603, ROD MOVEMENT CONTROL switch is momentarily PLACED to "IN" position and RELEASED.

or MOVEMENT CONTROL switch is PLACED to "IN" position and RELEASED one step prior to insert limit.

At paneI2HII-P603, ROD MOVEMENT CONTROL switch is momentarily PLACED to "IN" position and RELEASED.

At paneI2HII-P603, the Operator VERIFIES:

Rod position indicator indicates "12" for rod moved in previous step on Four-Rod Display and/or RWM.

APRMlLPRM readings decrease.

On the Control Rod Movement Sequence sheet, on the line for the selected rod (Inserted side of sheet), the Operator has:

Filled in INIT block.

Filled in DATE block.

LR-1P-25012-12 Page 5 ofS SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT NOTE: AFTER the fIrst control rod has been inserted to Position 12, ACTIVATE MALFUNCTION mfCll_30A, "CRD Pump A Trip."

9. The Operator acknowledges the alarm At paneI2HII-P603, the SAT/UNSAT and addresses procedure Operator:

34AR-603-12S-2.

ACKNOWLEDGESCRDPUNW A BREAKER TRIP annunciator.

OBTAINS procedure 34AR-603-12S-2.

(** Indicates critical step)

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i LR-1P-25012-12 Page 6 of8 S~l'ftfN8AT '.

COMMENTS*****..

PROMPT:

IF the Operator addresses sending personnel to investigate pump trip, as the Shift Supervisor, INFORM the Operator that personnel have been dispatched and to continue with the Annunciator Response Procedure.

10. Check the indications to determine At paneI2HII-P603, the SAT/UNSAT validity of the alarm.

following indications are VERIFIED by the Operator:

CRD PUMP, 2CII-COOlA, indicating light is extinguished.

CRD FLOW, 2CII-R606, indicates zero flow.

CLG WTR FLOW, 2C ll-R605, indicates zero flow.

CHG WTR PRESS, 2CI1-R601, is decreasing.

DR WTR dP, 2Cll-R602, is decreasing.

CLG WTR dP, 2CII-R603, is decreasing.

11. The Operator addresses The Operator SAT/UNSAT 34AB-CII-001-2.

OBTAINSIENTERS 34AB-CI1-001-2S.

12. Place CRD Flow Control in Manual At paneI2HI1-P603, CRD SAT/UNSAT and decrease the output to zero.

FLOW CONTROL controller 2CII-R600:

MANUAL (M) push-button is DEPRESSED, yellow push-button illuminated.

Close arrow push button is DEPRESSED until output indicates zero (accept 5% to off scale low).

At paneI2HI1-P603, place CRD SAT I UNSAT PUMP 2B control switch to START and verify pump is running with red light illuminated.

(*

• Indicates critical step)

(

j At panel I-P603, CRD FLO'V CONTROL 2CII-R600, Open arrow push-button is DEPRESSED until CRD FLO\\V 2CII-R606 increases to 50 gpm LR-JP-25012-12 Page 7 of8 SAT IUNSAT PROMPT:

IF the Operator asked position of the CRD return line isolation valve, as the Shift Supervisor, INFORM the Operator that the return line is isolated.

15. Adjust controller setpoint (SV) to the At paneI2H11-P603, CRD SAT/UNSAT established flow value (50 gpm).

FLOW CONTROL 2C11-R600:

Adjust controller setpoint (SV) to the established flow value (50 gpm).

AUTO (A) push-button is DEPRESSED, green push-button illuminated.

PROMPT:

IF the Operator addresses locally monitoring CRD temperatures, as the Shift Supervisor, INFORM the Operator that a Operator has been dispatched to monitor CRD temperatures on 2C11-R018.

PROMPT:

AT this time, as the Shift Supervisor, INFORM the Operator to continue inserting Rods in Step 50 to position 12.

16. Select control rod 18-27 At paneI2H11-P603, push-button SAT IUNSAT is DEPRESSED on CONTROL ROD SELECT Matrix for next control rod 18-27.

17. Continues rod insertion by notch to At paneI2H11-P603, ROD SAT I UNSAT position 12 MOVEMENT CONTROL switch or is momentarily PLACED to "IN" Continues rod insertion "continuous" to position 14. (one step prior to insert position and RELEASED.

or limit)

MOVEMENT CONTROL switch is PLACED to "IN" position and RELEASED one step prior to insert limit.

(*

• Indicates critical step)

19. Confirm the proper control rod movement.

20. Complete the line, for control rod 1 27, on the Control Rod Movement Sequence sheet.

At pane12HI1-P603, the Operator VERIFIES:

Rod position indicator indicates "12" for rod moved in previous step on Four-Rod Display and/or RWM.

Process Computer acknowledgment.

APRMILPRM readings decrease.

On the Control Rod Movement Sequence sheet, on the line for the selected rod (Inserted side of sheet), the Operator has:

Filled in INIT block.

Filled DATE block.

LR-JP-25012-12 Page 8 of8 SAT I IUNSAT SAT/UNSAT PROMPT:

INFORM the operator that another operator will continue inserting control rods.

END TIME: ___

NOTE:

The terminating cue shall be given to the Operator when:

Operator has correctly moved one rod after the CRD Pump Trip With no reasonable progress, the Operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

SOUTHERN NUCLEAR PLANT E.I. HATCH UNIT 2 FORM TITLE: CONTROL ROD Page 50 of 54

~OVEMENT SEQUENCE SEQUENCE A2 RWM Status OPER BYPASS INIT MAN AUTO STEP SO Withdrawal Insertion

• Use Single Notch Mode Intermediate Step Notch Limits Positions pos INIT INIT DATE LO HI 12 **

• • HI limit to be supplied by Reactor Engineer Step Rod Movements (Verification required if RWM INOP and CTP < = 30%)

NOTE:

For rod insertions, follow the movement sequence in reverse order WITHDRAWN INSERTED COUPLING ROD ID INIT INIT DATE INIT INIT DATE CHECK 26-35 26-19 18-27 34-27 ENG-0501 Rev. 8 G16.30 34GO-OPS-065-0S

I

1.0 IDENTIFICATION

ALARM PANEL 603-1 DEVICE:

SETPOINT:

2R22-S005 FRAME 8 N/A

2.0 CONDITION

This annunciator alarms when 2C11-C001A, CRD Pump breaker, opens and the Control Room hand switch is in the AUTO AFTER START position.

5.0 OPERATOR ACTIONS:

CRD PUMPA BREAKER TRIP

3.0 CLASSIFICATION

AUXILIARY

4.0 LOCATION

2H 11-P603 Panel 603-1 5.1 Check the following indications on 2H11-P603 to determine validity of the alarming condition.

5.1.1 Pump indicating lights.

5.1.2 2C11-R600, CRD Flow controller, indicates zero flow.

5.1.3 2C11-R605, Clg Wtr Flow indicator, indicates zero flow.

5.1.4 2C11-R601, Chg Wtr Press indicator, decreasing.

5.1.5 2C11-R602, Dr Wtr dp indicator, decreasing.

5.1.6 2C11-R603, Clg Wtr dp indicator, decreasing.

5.2 Enter 34AB-C11-001-2, Loss of CRD System.

6.0 CAUSES

6.1 Low pump suction pressure 12 in. Hg Vacuum 6.2 Reactor level one

-101 inches 6.3 Drywell high pressure 1.85 PSIG 6.4 Electrical fault 340 amps inst.l50 amps time 6.5 Load Shedding

7.0 REFERENCES

8.0 TECH. SPECS.ITRM/ODCM/FHA:

7.1 H-27516, CRD System Elem. Diag.

7.2 H-27517, Sheets 1 and 2 MGR-0048 Ver. 5.0 8.1 TS 3.1.3, Control Rod Operability 8.2 TS 3.1.5, Control Rod Scram Accumulators 34AR-603-128-2 VER. 4.2 AG-MGR-75-1101

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

LOSS OF CRD SYSTEM 4.0 SUBSEQUENT OPERATOR ACTIONS CRITICAL 4.1 IF both CRD pumps are tripped, DOCUMENT NUMBER:

34AB-C11-001-2 PLACE 2C11-R600, CRD Flow Control, in MANUAL and DECREASE the output to zero.

PAGE 20F3 VERSION NO:

3.4 4.2 IF CRD pump has tripped due to LOCA signal (-101" RWL or 1.85 PSIG DW pressure),

perform the following:

4.2.1 PLACE control switch for the previously running pump to trip position, on 2H11-P603 o

panel.

0 4.2.2 DEPRESS Pump A and Pump B LOCA Trip Reset pushbuttons, on 2H11-P603 panel.

0 4.3 Attempt to start either CRD pump.

0 NOTE:

A control rod scram accumulator is to be considered INOPERABLE if it's accumulator pressure is <940 PSIG.

4.4 IF Reactor Pressure is ~ 900 PSIG and the following conditions exist:

Two or more WITHDRAWN control rod scram accumulators INOPERABLE Charging water header pressure <940 PSIG THEN: WITHIN 20 minutes restore charging water header pressure ~ 940 PSIG IF charging water header pressure CAN NOT be restored within 20 minutes, enter o

o o

34AB-C71-001-2, Scram Procedure, AND SCRAM the reactor.

0 4.5 IF Reactor Pressure is <900 PSIG with the following conditions:

One or more WITHDRAWN control rod scram accumulators INOPERABLE Charging water header pressure <940 PSIG THEN: Enter 34AB-C71-001-2, Scram Procedure, AND SCRAM the reactor.

MGR-0001 Rev. 4.0 o

o o

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

LOSS OF CRD SYSTEM DOCUMENT NUMBER:

34AB-C11-001-2 4.6 IF the CRD system cannot be restarted and Reactor coolant temp. is >212°F, PAGE 30F3 VERSION NO:

3.4 THEN review 34S0-G31-003-2, RWCU System, for RWCU pump requirements without CRD seal purge.

0 4.7 INCREASE system flow to 50 GPM (59 GPM IF return line is open).

0 4.8 IF CRD pump 2C11-C001A OR 2C11-C001B is operating AND the in-service flow control valve is NOT controlling flow properly, THEN shift flow control valves per 34S0-C11-005-2 CRD System AND continue this procedure at 4.10.

0 4.9 IF CRD pump 2C11-C001A OR 2C11-C001 B is operating AND the in-service flow control valve is controlling flow properly, THEN perform the following:

4.9.1

4.9.2 NOTES

Adjust controller setpoint (SV) to the established flow value.

Place 2C11-R600, CRD Flow Control, in AUTO.

By depressing the DISPLAY / ENTER key and then selecting OVERVIEW with the up / down arrow keys and then depressing the DISPLAY / ENTER key again on the CRD Temperature Recorder 2C11-R018, all 137 CRD temperatures will be displayed on the screen at the same time. If any CRD temperature is above its alarm setpoint then that CRD's indication will be red.

By depressing the DISPLAY / ENTER key and then selecting TREND with the up /

down arrow keys and then depressing the DISPLAY / ENTER key again on the CRD Temperature Recorder 2C11-R018, a historical trend of CRD temperatures can be observed.

o o

POSTED @ 2H21-P007 4.10 Dispatch an Operator to locally monitor CRD temperatures on CRD Temperature Recorder, 2C11-R018, at PaneI2H21-P007, located on Rx. Bldg. 130' elevation Southeast corner.

4.11 IF any CRD temperature exceeds 350'F, notify Engineering for analysis.

MGR-0001 Rev. 4.0 o

o

NIR DRAFT Southern Nuclear E. I.

atch uclear Plant Operations Training JPM Plant 1, RO, SRO-I Energy to Serve Your World SM

/

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

OPERATIONS TRAINING Media Number:

LR-JP-ll.12

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.... *.)ii...........J.>.. ~:lllnaiS I' 01 06113/89 General revision and fonnat change JEM SMC 02 08/09/89 Procedure revision & add LR lesson plans JEM DHG 03 09108/89 Revision of questions JEM SMC 04 03/01190 Procedure, fonnat, & question revision JEM DHG 05 03/26/91 Procedure revision JEM DHG 06 07/21192 General revision and fonnat change WMM DBO 07 08113/93 General revision, incorporate instmctor comments, RAB RSG word processor change 08 08/05/94 Adjust format, change time allowance RAB MMG 09 08117195 Format change, incorporate student comments, change SMC time allowance 10 06117/96 F omlat change RAB RSG 11 01118/00 Fom1at modification, change time allowance based on RAB DHG running average, incorporate new K/ A numbers and values, clarify initial conditions 12 10/30/00 Change operator applicability to Systems Operator, RAB DHG include objective number, change time allowance based on nmning average 13 02/27/02 Include initial operator statement RAB RAE 14 03117/05 Deleted "S" from procedure numbers, changed ARB DHG Revision and Rev. numbers to "Current Version".

15 06102/05 Revised Initial License statement for successful RAB RAB completion 16 04/06/06 Remove Response Cues RAB RAB

LR-1P-l1.12-16 Page 1 of5 UNIT 1 (X)

UNIT 2 0

FROM OUTSIDE THE CONTROL ROOM, INJECT BORON USING THE SBLC SYSTEM

. LR-1P-l1.12-16 The task shall be completed when one Standby Liquid Control Squib Valve has been fired and one System pump has been started locally and the Standby Liquid Control System is injecting to the Reactor, per 34S0-C41-003.

011.012 Q~iI!J¢j:;JjtE;~l3~E~:* 011.0 12.B PLANT HATCH JTA IMPORTANCE RATING:

RO 4.20 SRO 4.20 KIA CATALOG NUMBER: 295037 EA1.04 KIA CATALOG JTA IMPORTANCE RATING:

RO 4.5 SRO 4.5 OPERATOR APPLICABILITY:

System Operator (SO)

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34S0-C41-003-1 (current version)

Four (4) SBLC Squib Valve jumper wires, from EOP fIle next to Remote Shutdown Panel 1H21-P173 Flathead screwdriver APPROXIMATE COMPLETION TIME:

21.0 Minutes SIMULATOR SETUP:

NI A

UNITl READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1.

The Reactor has failed to Scram either manually or automatically, and the Torus temperature is approaching the BUT curve.

2.

31EO-EOP-Oll-l (RCA) is in progress.

3.

SBLC has failed to initiate from the Control Room.

4.

RWCU is isolated.

INITIATING CUES:

Manually initiate SBLC locally per 34S0-C41-003-1.

1TEP For INITIAL Operator Programs:

LR-1P-ll.12-16 Page 3 of5 i$.>\\.T1PNS:A'l'

.... CQ1\\fMENTS For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

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

1. Operator identifies the materials that are required.

2. Operator reviews the procedure's precautions and limitations.

Operator has identified the required materials and where to obtain them.

Operator has reviewed the precautions and At Panel IH21-POl1, the foHowingjumpers are INSTALLED for lC41-F004A:

Terminal point BB-l to Squib Valve, lC41-F004A, Junction Box tenninal C 1 (white wire) and tenninal C (green wire).

Terminal point BB-4 to Squib Valve, lC41-F004A, Junction Box terminal C2 (black wire) and terminal C3 (red wire).

At Panel IH21-POll, the following jumpers are INSTALLED for lC41-F004B:

Tenninal point BB-8 to Squib Valve, lC41-F004B, Junction Box terminal (white wire) and terminal C (green wire).

Terminal point BB-II to Squib Valve, lC41-F004B, Junction Box terminal C2 (black wire) and temlinal C3 (red wire).

START TIME: ___ _

SAT IUNSAT SAT IUNSAT SAT IUNSAT PROMPT:

WHEN all terminals for a Squib Valve are correctly installed, INDICATE an explosive noise from the vicinity of that Squib Valve.

NOTE: Detonation of one Squib Valve will satisfactorily meet the standard.

(*

• Indicates critical step)

(

LR-1P-ll.12-16 Page 4 of5

• • • • • • y.**.~A'EIJl~.s~a":>***.*

• COMMJENrtS..

NOTE: The jumpers used to fire the Squib Valves are a jumper with 3 connections to connect all three terminal points.

PROMPT:

IF the operator addresses isolation ofRWCU, as the Control Room operator REPORT that RWCU is isolated.

4. Start SBLC Pump lC41-COOlA.

At panellH21-POll, SBLC SATfUNSAT PUMP, lC41-COOlA, control switch is in RUN.

PROMPT:

WHEN the operator starts the pump, INFORM the operator that there is no change in noise levels.

NOTE:

Ifthe operator looks at other pump indications, report negative indications for a running pump.

At panellH21-POll, SBLC PUMP, lC41-COOlA, control switch is in STOP.

At panel IH21-POll, SBLC PUMP, lC41-COOlB, control switch is in RUN.

SAT/UNSAT SAT fUNSAl'

7. CONFIRM start of lC41-COOlB, SBLC Pump IB.

Operator listens for the sound of a running pump or looks at other pump indications.

SAT fUNSAl' PROMPT:

WHEN the operator starts the pump, INFORM the operator that there is the sound of a running pump.

8.

NOTE:

If the operator looks at other pump indications, report positive indications for a running pump.

Verify the SBLC solution is being At panellH21-POll, the operator SATfUNSAT injected into the Reactor.

has VERIFIED SBLC Tank level is DECREASING as indicated by SBLC STORAGE TANK LEVEL INDICATOR, lC41-ROOl.

(** Indicates critical step)

PROMPT:

WHEN the operator addresses SBLC tank level, INDICATE for the operator that level is decreasing slowly, but is greater than l300 gallons.

NOTE: It will take between 30 and 70 minutes to completely empty the SBLC Storage Tank.

END LR-JP-ll.12-16 Page 5 of5 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.

Operator has started the "B" pump and checked on tank level.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 10 OF 51

')OCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

STANDBY LIQUID CONTROL SYSTEM 34S0-C41-003-1 10.13 7.2.2 Manual Initiation - Local CONTINUOUS I

CAUTION:

THIS SUBSECTION IS PERFORMED ONLY AS DIRECTED BY PLANT HATCH REMOTE SHUTDOWN AND/OR EMERGENCY OPERATING PROCEDURES.

NOTES:

Equipment required for local SBLC operation is stored at 1 H21-P173, Remote Shutdown Panel OR in the EOP gang box on the 185' elevation working floor.

1C41-F004A, Squib Valve, will detonate when the last jumper connection is made, preferably at 1 H21-P011, terminal paint BB-4. IF jumper is connected to 1 H21-P011 terminal point FIRST, THEN the other end of the jumper is energized.

7.2.2.1 DETONATE 1 C41-F004A, Squib Valve, by INSTALLING the following jumpers:

7.2.2.1.1 1C41-F004A, Squib Valve Junction Box, terminal C1 (white wire) AND terminal C (green wire) to 1 H21-P011, Standby Liquid Control Rack, terminal point BB-1.

7.2.2.1.2 1C41-F004A, Squib Valve Junction Box, terminal C2 (black wire) AND terminal C3 (red wire) to 1 H21-P011, Standby Liquid Control Rack, terminal point BB-4.

1C41-F004B, Squib Valve, will detonate when the last jumper connection is made, preferably NOTE:

at 1 H21-P011, terminal point BB-11. IF jumper is connected to 1 H21-P011 terminal point FIRST, THEN the other end of the jumper is energized.

7.2.2.2 DETONATE 1C41-F004B, Squib Valve, by INSTALLING the following jumpers:

7.2.2.2.1 7.2.2.2.2 MGR-0001 Ver. 3 1C41-F004B, Squib Valve, Junction Box terminal C1 (white wire) AND terminal C (green wire) to 1 H21-P011, Standby Liquid Control Rack, terminal point BB-8.

1C41-F004B, Squib Valve, Junction Box terminal C2 (black wire) AND terminal C3 (red wire) to 1 H21-P011, Standby Liquid Control Rack, terminal point BB-11.

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 11 OF 51 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

STANDBY LIQUID CONTROL SYSTEM 34S0-C41-003-1 10.13 7.2.2.3 IF RWCU is NOT isolated, perform the following to close 1G31-F004, at 1 R24-S022, located 130 Reactor Building - North side:

7.2.2.3.1 OPEN breaker in Frame 10A.

7.2.2.3.2 OPEN the following links located in the top compartment of breaker frame 10:

o 10A4 o 10A6 The "internal" side of the link is the side that the possum tail is hung on.

7.2.2.3.3 INSTALL a jumper:

from the "internal" side of link 10A5 to the "internal" side of link 10A6.

7.2.2.3.4 CLOSE breaker in Frame 10A to close 1G31-F004 valve.

7.2.2.4 At 1 H21-P011, Standby Liquid Control Rack, perform the following:

7.2.2.4.1 Place 1C41-C001A, SBLC Pump 1A, control switch in RUN position.

7.2.2.4.2 IF 1C41-C001A, SBLC Pump 1A, does NOT start, THEN perform the following:

7.2.2.4.2.1 Place 1C41-C001A, SBLC Pump 1A, control switch in STOP position.

7.2.2.4.2.2 Place 1C41-C001B, SBLC Pump 1B, control switch in RUN position.

7.2.2.4.2.3 CONFIRM start of 1C41-C001B, SBLC Pump 1B.

It will take between 30 AND 70 minutes to completely empty the SBLC Storage Tank 7.2.2.4.3 MGR-0001 Ver. 3 CONFIRM SBLC solution is being injected into the RPV, as indicated by C41-R001, Level Indicator.

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 12 OF 51 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

STANDBY LIQUID CONTROL SYSTEM 34S0-C41-003-1 10.13 CAUTION:

FAILURE TO DEENERGIZE THE SBLC TANK HEATERS ON LOW SBLC TANK LEVEL MAY CAUSE HEATER DAMAGE.

7.2.2.5 CAUTION:

7.2.2.6 MGR-0001 Ver. 3 WHEN SBLC Storage Tank level decreases below 1300 gallons, OPEN the following breakers:

o Standby Liquid Cntl Tank Heater 1 C41-A001 B, 1 R24-S011, Frame 1 B o Standby Liquid Cntl Tank Heater 1C41-A001A, 1R24-S012, Frame 3A THE SBLC PUMPS WILL LOSE SUCTION WHEN INDICATED LEVEL IN THE SBLC STORAGE TANK IS 250 GALLONS (5%). FAILURE TO STOP THE SBLC PUMP WHEN THE SBLC STORAGE TANK INDICATION IS LESS THAN 250 GALLONS (5%)

MAY RESULT IN PUMP DAMAGE WHEN all of the solution has been injected, as indicated by a reading of less than 400 gallons on SBLC Tank Indicator, 1 C41-R001, OR as directed by the Plant Hatch Remote Shutdown OR Emergency Operating Procedures, SHUT DOWN the SBLC System per the Local Shutdown subsection of this procedure.

NIR DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Plant 2, RO, SRO-I SOUTHERN..

\\

COMPANY Energy to Serve Your World SM

I SOUTHERN NUCLEAR OPERATING COMPANY

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

OPERATIONS TRAINING Media Number:

LR-JP-07.20

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11 10/31100 Include objective number RAB DHG 12 02i26/02 Include initial operator statement RAB RAE 13 03/17/05 Deleted "s" fi:om procedure numbers, changed Revision and Rev.

BEB DHG numbers to "Current Version," changed "Reactor Operator" to "Nuclear Plant Operator," and changed IC #107 tor Simulator Setup.

14 05/31105 Revised Initial License statement for successful completion RAB R,AB 15 04/06/06 Remove Response Cues RAE RAE 16 08/07/08 Corrected to match procedure step for confirming open GHC BKW 2EI1-FOO3B.

LR-JP-07.20-16 UNIT 1 0

UNIT 2 (X)

FROM THE REMOTE SHUTDOWN PANEL, START RHR IN TORUS COOLING LR-JP-07.20-16 The task shall be completed when the operator has successfully placed the "B" loop ofRHR into Torus Cooling from the Remote Shutdown Panel per 3 1 RS-OPS-OO 1.

007.020 007.020.0 PLANT HATCH JTA IMPORTANCE RATING:

RO 3.40 SRO 3.80 KIA CATALOG NUMBER: 295013 AAl.Ol KIA CATALOG JTA IMPORTANCE RATING:

RO 3.9 SRO 3.9 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

(current version)

Key for Remote Shutdown Panel in APPROXIMATE COMPLETION TIME:

22.0 Minutes SIMULATOR SETUP:

N/A

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

1.

An event has occurred which required the control room to be evacuated.

2.

RHR is in Standby.

3.

Normal AC power is available.

4.

RHRSW Pump "2B" is running at 4400 gpm.

5.

31RS-OPS-001-2 is in progress.

6.

All RSDP transfer switches have been placed in the "EMERG" position.

INITIATING CUES:

Place RHR Loop "B," in Torus Cooling at the Remote Shutdown Panel per 31RS-OPS-001-2.

(

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/#x For INITIAL Operator Programs:

LR -JP-07.20-16

......., \\Si\\XlUNSA'r;

• • • t10lVlME~TS For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

1.

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

Operator obtains the procedure.

Operator obtains a copy of 31 RS-OPS-001-2.

START TIME: ----

SAT IUNSAT PROMPT:

WHEN the operator addresses transfer switch positions, INDICATE for the operator that ALL transfer switches are in the EMERG position.

PROMPT:

IF the operator addresses RHRSW operation, as the Shift Supervisor, INFORM the operator that RHRSW Pump "2B" is running with 4400 gpm flow.

PROMPT:

IF the operator addresses Torus temperature, INDICATE for the operator that Torus temperature is <100°F.

2. Close valve 2E11-F047B.

3. Confirm 2E11-F003B is open.

4. Confirm 2E11-F048B is open.

(** Indicates critical step)

At paneI2C82-P001, the following valve is CLOSED, green light illuminated:

HX INLET VLV, 2E11-F047B At paneI2C82-P001, the following valve is OPEN, red light illuminated:

HX OUTLET VL V, 2E 11-F003B At paneI2C82-P001, HX BYPASS VLV, 2Ell-F048B, is OPEN, red light illuminated.

At paneI2C82-P001, RHR TORUS SPRAY OR TEST VL V, 2E11-F028B, is OPEN, red light illuminated.

SAT IUNSAT SAT IUNSAT SAT IUNSAT SAT IUNSAT

(** Indicates critical step)

At paneI2C82-P001, MIN FLOW VL V, 2EII-F007B, is OPEN, red light illuminated.

At paneI2C82-P001, RHR PUMP, 2EII-C002B, is RUNNING, red light illuminated.

At paneI2C82-P001, the following has been performed:

FULL FLOW TEST LINE VL V, 2Ell-F024B, is THROTTLED OPEN, red and green lights illuminated.

RHR FLOW 2C82-R004, indicates less than or equal to 7700 gpm. (accept 6700-7700 gpm)

At panel2C82-P001, MIN FLOW VLV, 2EII-F007B, is CLOSED, green light illuminated.

At paneI2C82-P001, the following valves are OPEN, red light illuminated:

HX INLET VLV, 2EII-F047B At paneI2C82-P001, HX BYPASS VLV, 2EII-F048B, is CLOSED, green light illuminated.

LR -JP-07.20-16 SAT/UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT SAT I UNSAT SAT I UNSAT

PROMPT:

PROMPT:

PROMPT:

LR-JP-07.20-16 SATfUNcSAl'>..

eol\\iMEN:[S IF the operator addresses RHRSW to RHR dP, as a System Operator, INFORM the operator that RHRSW to RHR dP is >20 psid.

IF the operator addresses Torus Spray, as the Shift Supervisor, INFORM the operator that Torus Spray is not required at this time.

IF the operator addresses securing Torus Cooling, as the Shift Supervisor, INFORM the operator that this is not desired at this time.

END TIME: ___ _

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

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

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

SNC PLANT E. I. HATCH I Pg 31 of 46 DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-2 Version No:

6.11 ATTACHMENT ~

TITLE:

TORUS COOLING FROM THE REMOTE SHUTDOWN PANEL Attachment Page 1 of 5 CAUTION CAUTIONS:

DIESEL GENERATOR LOADING MUST NOT EXCEED THE FOLLOWING RATINGS FOLLOWING A LOSS OF OFFSITE POWER TO AVOID DIESEL OVERLOAD. AMPERAGE INDICATIONS ARE LOCATED ON PANEL 2R43-P001 IN EACH DIESEL GENERATOR ROOM.

RATINGS {AMPERES}

DIESEL 1000 HOUR 7 DAY {168 HOUR}*

1B 430 490 CONTINUOUS 12.5 DAY {300 HOUR}**

2A 440 500 2C 440 500

• THE HIGHER 7 DAY RATING IS BASED UPON A YEARLY ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE CONTINUOUS RATING. A TOTAL OF 168 HOURS PER YEAR WITH A LOAD OF 430 TO 490 AMPERES IS ALLOWED.

• • THE HIGHER 12.5 DAY RATING is BASED UPON A YEARLY ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE CONTINUOUS RATING. A TOTAL OF 300 HOURS PER YEAR WITH A LOAD OF 440 TO 500 AMPERES IS ALLOWED.

• BEFORE STARTING AN RHR PUMP ON THE DIESEL GENERATOR, DIESEL LOAD MUST BE BELOW 360 AMPS (2A AND 2B RHR PUMPS) 340 AMPS (2C AND 2D RHR PUMPS). REFER TO 34S0-R43-001-2 TO REDUCE DIESEL LOADS IF REQUIRED.

• BEFORE STARTING AN RHRSW PUMP ON THE DIESEL GENERATOR, DIESEL LOAD MUST BE BELOW 330 AMPS (2A, 2B, 2D RHRSW PUMPS), OR 320 AMPS (2C RHRSW PUMP). REFER TO 34S0-R43-001-2 TO REDUCE DIESEL LOADS, IF REQUIRED.

• THE AMPERE VALUES ARE BASED UPON AN ASSUMED TOTAL POWER FACTOR OF 0.91 (1 B DG) AND 0.9 (2A AND 2C DG). LOADING OF THE DIESEL GENERATORS ABOVE 430 AMPERES (1B DG) AND 440 AMPERES (2A AND 2C DG) ON THE LOCAL INDICATORS MUST BE ACCOMPANIED BY CLOSE MONITORING OF OTHER DIESEL PARAMETERS FOR SIGNS OF OVERLOADING.

G16.030 MGR-0009 Rev. 5.0

SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM l

31 RS-OPS-001-2 ATTACHMENT ~

TITLE:

TORUS COOLING FROM THE REMOTE SHUTDOWN PANEL Placing the Remote Shutdown Panel Transfer for RHR in Emergency has the following effects on RHR system operation:

Pg 32 of 46 Version No:

6.11 Attachment Page 20f5

1.

The A, C, and D RHR pumps will automatically initiate in the LPCI mode on the following signals:

1.1 Reactor level greater than or equal to -113 inches (actual setpoint = -101 inches) 1.2 High Drywell pressure less than or equal to 1.92 PSIG (actual setpoint =

1.85 PSIG). With transfer switch 2C82-S9 in the EMERG position, the 'B' RHR pump will NOT auto start on any of the above signals

2.

Load shed AND overcurrent are still valid trip signals.

3.

2E11-F006A, 2E11-F006B, 2E11-F006C, 2E11-F006D, Pump suction valves, are still interlocked with their respective 2E11-F004 valve.

4.

2E11-F004B, Pump suction from the Torus, AND 2E11-F024B, Torus cooling, must be closed to open 2E11-F006B, SDC suction.

However, once 2E11-F006B is open, 2E11-F024B may be reopened.

5.

The loss of suction valve alignment trip is defeated for the 2B RHR pump.

6.

2E11-F008 AND 2E11-F009, SDC Isol Vlvs, closure on high RX pressure NOTE (138 PSIG) AND low rx level (+3") is defeated.

7.

2E11-F007B, Min Flow Vlv, operates automatically.

8.

2E11-F048B, 3 minute LOCA interlock is defeated.

9.

The LOCA interlock for closing the following valves is defeated:

2E11-F011B, 2E11-F016B, 2E11-F028B, 2E11-F027B.

10. Interlock to prevent opening both 2E11-F015B AND 2E11-F017B, Inbd AND Outbd Inj Vlvs, with rx. pressure ~ 425 PSIG is defeated.

11. Interlock to automatically open 2E11-F015B AND 2E11-F017B, Inbd AND Outbd Inj Vlvs, on a LOCA signal (-101 RWL AND 1.85 PSIG drywell pressure) with rx.

pressure::;; 425 PSIG is defeated.

12. Interlock to automatically close 2E11-F015B, Inbd Inj VI v, IF in Shutdown Cooling AND receive a PCIS Group II signal (+3 RWL OR 1.85 PSIG Drywell pressure)

OR Rx pressure ~ 138 PSIG is defeated.

13. Interlock to automatically trip 2E11-C001 B AND 2E11-C001 D, RHRSW pumps, on a LOCA signal is defeated.

14. LOSP and breaker trips for 2E11-C001 B AND 2E11-C001 D, RHRSW pumps, are still in effect.

15. 2E11-F017B, RHR Outbd Inj Vlv, 5 minute LOCA interlock is defeated.

G16.030 MGR-0009 Rev. 5.0

SNC PLANT E. I. HATCH I Pll33 of 46 DOCUMENT TITLE:

I DOCUMENT NUMBER:

Version No:

6.11 SHUTDOWN FROM OUTSIDE CONTROL ROOM L

31 RS-OPS-001-2 ATTACHMENT ~

TITLE:

TORUS COOLING FROM THE REMOTE SHUTDOWN PANEL Attachment Page 3 of 5 NOTE 1.0 An RHR pump discharge pressure of greater than or equal to 112 PSIG (127 PSIG, actual setpoint) OR a Core Spray pump discharge pressure of greater than or equal to 137 PSIG (152 PSIG, actual setpoint) is the final permissive for an automatic depressurization initiation IF the ADS two minute delay has elapsed.

At panel 2C82-P001, PLACE the following transfer switches in the EMERG position:

2C82-S18, 2C82-S8, 2C82-S53, 2C82-S52, 2C82-S80, 2C82-S9, 2C82-S13, 2C82-S10, 2C82-S1, 2C82-S12, 2C82-S17, 2C82-S14, 2C82-S11, Nuc Blr Instrumentation RHR & RCIC Indications 2E51-F007, Steam Supply Inbd Isol Vlv.

2E11-F009, SDC Suction Vlv.

2E11-F006C, SID Clg Vlv.

2E11-F006A, SID Clg Vlv.

2E11-F007B, Min FlowVlv.

2E11-C002B, RHR Pump 2E11-F017B, Outbd Inj Vlv.

2E11-C001B, ServWtr Pump 2E11-F015B, Inbd Inj Vlv.

2E11-F004B, Torus Suction Vlv.

2E11-F006B, Shutdown Clg Vlv.

2E11-F006D, Shutdown Clg Vlv.

2E11-F008, SDC Suction Vlv.

2E11-F023, Rx Head Spray Isol Vlv.

2E11-F003B, Hx Outlet Vlv.

2E11-F027B, Torus SprayVlv.

2E11-F048B, Hx Bypass Vlv.

2E11-F047B, Hx Inlet Vlv.

2E11-F028B, RHR Torus Spray Or Test Vlv.

2E11-F073B, Serv Wtr crosstie Vlv.

2E11-C001 D, Serv Wtr Pump 2E11-F024B, Full Flow Test Line 2E11-F011B, Hxto Torus Vlv.

2E11-F016B, Cnmt Spray Outbd Vlv.

G16.030 MGR-0009 Rev. 5.0

SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-2 ATTACHMENT..§..

TITLE:

TORUS COOLING FROM THE REMOTE SHUTDOWN PANEL 2.0 PLACE RHR Service Water in operation by performing the following steps:

2.1 At 600/20BV MCC 2B ESS Div 2 2R24-S012, Frame 11 C, OPEN the breaker for 2E 11-F06BB, RHRSW Control Valve.

Pg 34 of 46 Version No:

6.11 Attachment Page 4 of 5 2.2 At 106RJR24, manually OPEN 2E11-F06BB to approximately 40% OPEN.

2.3 At paneI2CB2-P001, START 2E11-C001B OR 2E11-C001 D, RHR Serv Wtr Pump.

2.4 At 106RJR24 WHILE in communication with an operator at paneI2H21-P173, ADJUST 2E11-F06BB, RHRSW Control Valve, to obtain a flow rate of 4400 GPM as indicated on 2E 11-R071, RHR Heat Exchanger Service Water Flow.

NOTES:

• The RHR Hx is initially isolated to prevent damage to the Hx from the hydraulic shock created by starting the RHR Pump.

IF THE ONLY OPERATING PUMP IN AN RHR LOOP IN SUPPRESSION POOL CAUTION COOLING WATER TRIPS, iT IS POSSIBLE THAT THE LPCIINJECTION LINE AND THE DRYWELL SPRAY LINE MAY DRAIN TO THE TORUS.

3.0 At panel 2CB2-P001, Perform the following:

IF Suppression Pool temperature is < 100°F, Confirm CLOSED/CLOSE 2E11-F047B, Hx Inlet Vlv.

Confirm OPEN/OPEN 2E11-F003B, Hx Outlet Vlv.

4.0 At panel 2CB2-P001, confirm 2E11-F04BB, Hx Bypass Vlv, is OPEN.

5.0 At panel 2CB2-P001, OPEN 2E11-F02BB, RHR Torus Spray or Test Vlv.

6.0 Confirm 2E11-F007B, Min FlowVlv, is OPEN.

7.0 At paneI2CB2-P001, START 2E11-C002B, RHR Pump 2B.

B.O At paneI2CB2-P001, THROTTLE OPEN 2E11-F024B, Full Flow Test Line, to obtain a flow rate of less than or equal to 7700 GPM as indicated on 2C82-R004, RHR Flow, on panel 2CB2-P001.

8.1 Confirm 2E11-F007B, Min Flow Vlv, CLOSES.

G16.030 MGR-0009 Rev. 5.0

(

SNC PLANT E. I. HATCH I DOCUMENT TITLE:

I DOCUMENT NUMBER:

SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-2 ATTACHMENT ~

TITLE:

TORUS COOLING FROM THE REMOTE SHUTDOWN PANEL Pg 35 of 46 Version No:

6.11 Attachment Page 50f5 RHR Service Water flow must be maintained at less than 4400 GPM with one RHR NOTE: Service Water Pump operating, OR less than 8800 GPM with two RHR Service Water Pumps operating in a single RHR Service Water Loop.

9.0 At panel 2C82-P001, Confirm OPEN/OPEN the following valves:

2E11-F047B, Hx Inlet Vlv.

2E11-F003B, Hx Outlet Vlv.

10.0 At paneI2C82-P001, CLOSE 2E11-F048B, Hx Bypass Vlv.

11.0 At 1 06RJR24, ADJUST 2E11-F068B, RHRSW Control Valve, to maintain greater then or equal to 20 PSID as indicated on 2E11-DPIS-N003B, at 87RLR24, on panel 2H21-P021.

12.0 13.0 13.1 13.2 13.3 13.4 13.5 I F Torus Spray is desired, THEN at paneI2C82-P001, OPEN 2E11-F027B, Torus Spray Vlv.

WHEN Suppression Pool Cooling is no longer required, SHUT DOWN RHR from Suppression Pool Cooling by performing the following steps:

At paneI2C82-P001, CLOSE 2E11-F027B, Torus Spray Vlv.

At paneI2C82-P001, CLOSE 2E11-F024B Full Flow Test Line.

At paneI2C82-P001, SHUT DOWN 2E11-C002B, RHR Pump 2B.

At paneI2C82-P001, CLOSE 2E11-F028B, RHR Torus Spray or Test Vlv.

At paneI2C82-P001, OPEN 2E11-F048B, Hx Bypass Vlv.

NOTE:

RHR Service Water may be left in operation to support Shutdown Cooling.

G16.030 MGR-0009 Rev. 5.0

NIR DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Plant 3, RO, SRO-I SOUTHERN..

\\

COMPANY Energy to Serve Your World SM

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

OPERATIONS TRAINING Media Number:

00 10128/99 Initial development 01 04/24/00 Made Step 4 tor both units non-critical, correct operator title (SO) 02 11/02/00 Include objective number, change time allowance based on running average 03 03111102 Include initial operator statement 04 03/08/05 Documentum revision 05 OS/27/05 Revised Initial License statement for successful completion 06 04/18/06 Remove Response Cues I

Page 1 of 1 LR-JP-27.18 RAB DHG RAE DHO RAB DHG RAE RAE DNlVI Rt\\B RAB Rf\\t,B RAB RAB

LR-JP-27.18-06 Page 1 of 4 UNIT 1 (X)

UNIT 2 0

TRANSFER 600 V AC ESSENTIAL (LPCI BUS) FROM NORMAL TO ALTERNATE LR-JP-27.18-06 The task shall be completed when the operator has transferred a LPCI Bus (1R24-S018A) from its Normal to Alternate source per 34S0-R24-003-1.

027.018

,Qll.fEf3fl¥)frNt1M\\l'El~:* 027.018.0 PLANT HATCH JTA IMPORTANCE RATING:

RO 3.43 SRO 3.53 KIA CATALOG NUMBER: 203000K1.08 KIA CATALOG JTA IMPORTANCE RATING:

RO 3.5 SRO 3.5 OPERATOR APPLICABILITY:

Nuclear Plant Operator (NPO)

APPROXIMA TE COMPLETION TIME:

23.0 Minutes SIMULATOR SETUP:

N/A

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

1.

Unit 1 and Unit 2 are operating at 95% power.

2.

The Normal Supply Breaker for the lA LPCI Bus, lR24-S01SA, must be replaced by maintenance.

3.

Electrical power distribution for both units is aligned in a normal full power lineup.

4.

lR24-S04S is energized

5.

lR24-S01S AlB Alt. Supply Breaker is closed INITIATING CUES:

Transfer lR24-S01SA from its Normal to its Alternate supply per 34S0-R24-003-1.

v

~t~~;)***

For INITIAL Operator Programs:

LR-JP-27.18-06 Page 3 of 4 For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

1

2.

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

Operator obtains the procedure.

Operator obtains a copy of 34S0-R24-003-1.

Operator reviews the procedure's Operator has reviewed the precautions and limitations.

precautions and limitations.

START TIME: ___ _

SAT IUNSAT SAT IUNSAT PROMPT:

IF the operator asks if lR24-S018A has been de-energized, INFORM the operator that lR24-S01SA has NOT been de-energized.

The operator CALLS the Control Room and REQUESTS that a Control Room Operator OPEN the lR24-S018A normal supply breaker on 1 H 11-P60 1.

SAT/UNSAT PROMPT:

AS the Control Room Operator, INFORM the operator that lR24-S018A normal supply breaker is open.

4 Confirm OFFIPIace to OFF lR26-MlOS Disconnect switch.

Ii A

IIi, i

(*

• Indicates critical step)

In the 600V 1 CD Transformer Room, the operator CONFIRMS the lR26-M108 disconnect switch is in the OFF position.

In the 600 V AC 2C Bus Room, the operator PLACES the lR26-M077 disconnect switch to the OFF position.

SAT IUNSAT SAT IUNSAT

SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:

1 R24-S01BAlB 600 VOLT MCC OPERATION 7.2 SHUTDOWN 7.2.1 De-energizing 1R24-S01BA 600 VAC MCC I CONTINUOUS I PAGE B OF 11 DOCUMENT NUMBER:

VERSION NO:

34S0-R24-003-1 5.9 7.2.1.1 On 1H11-P601, CONFIRM OPEN OR OPEN 1R24-S01BA Norm Supply Bkr.

7.2.1.2 Locally, CONFIRM OFF/PLACE to OFF 1R26-M10B Manual Disconnect Switch (1 R24-S01BA Alt supp). (600V 1CD Transformer room) 7.2.1.3 CONFIRM OFF/PLACE to OFF 1 R26-M077 Manual Disconnect Switch (1 R24-S01BA Normal Supp). (600 VAC 2C Bus room)

/A Z 7.2.2 De-energizing 1R24-S01BB 600 VAC MCC 7.2.2.1 7.2.2.2 7.2.2.3 MGR-0001 Ver. 3 I CONTINUOUS I On 1H11-P601, CONFIRM OPEN/OPEN 1R24-S01BB Norm Supply Bkr.

Locally, CONFIRM OFF/place to OFF 1 R26-M109, Manual Disconnect Switch (1 R24-S01BB Alt Supp). (600V 1 CD Transformer room)

CONFIRM OFF/PLACE to OFF 1R26-M07B, Manual Disconnect Switch (1R24-S01BB Normal Supply). (600 VAC 2D Bus room)

SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 5 OF 11 DOCUMENT TITLE:

DOCUMENT NUMBER:

VERSION NO:

1 R24-S018A1B 600 VOLT MCC OPERATION 34S0-R24-003-1 5.9 7.1.2 Energizing 1R24-S018A From Alternate Source (1R24-S048)

I CONTINUOUS I NOTE 1 R24-S018A 600 VAC MCC MUST NOT be powered simultaneously from its Normal AND Alternate sources.

7.1.2.1 7.1.2.2 DE-ENERGIZE 1 R24-S018A per the De-energizing 1 R24-S018A 600 VAC MCC subsection (7.2.1) of this procedure.

CONFIRM 1R24-S048 is energized via the 1R22-S006 1F 4160 VAC Bus.

NOTE Breaker position can be determined EITHER at 1H11-P601 panel OR locally at breaker.

However, breaker must be positioned locally.

7.1.2.3 CONFIRM CLOSED/CLOSE 1R24-S018A1B Alt Supply Bkr. (1R24-S048 Fr 1A).

iNOTE 1 R24-S048 MCC can NOT power 1 R24-S018A AND 1 R24-S018B simultaneously.

CAUTION THE HANDLE WEIGHT OF 1R26-M107 TRANSFER SWITCH WILL TAKE SWITCH TO 1 R24-S018B POSITION.

7.1.2.4 7.1.2.5 MGR-0001 Ver. 3 In 600V 1 CD Transformer room, perform the following:

• CONFIRM OFF 1 R26-M108, Manual Disconnect Switch (1R24-S018A Alt Supp)

• CONFIRM OFF 1 R26-M109, Manual Disconnect Switch (1 R24-S018B Alt supp)

• At 1R26-M107, Transfer Switch (1R24-S018A1BAltSupp), CONFIRM 1 R24-S048 "POWER AVAILABLE" light ILLUMINATED

• PLACE 1 R26-M107 Transfer Switch to 1 R24-S018A position

• SECURE 1 R26-M1 07 Transfer Switch in the 1 R24-S018A position

• PLACE to ON 1R26-M108 Manual Disconnect Switch CONFIRM 1R24-S018A is energized by observing an ILLUMINATED position indication lights (red or green) for 1 E11-F015A AND/OR 1 E11-F007A.

I I