Text

Initial Exam 2009-301 Draft Simulator Scenarios
	ML100620144
Person / Time
Site:	Saint Lucie
Issue date:	02/09/2010
From:	; NRC/RGN-II
To:	;
References
	Download: ML100620144 (196)
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Appendix D Scenario Outline Form ES-D-1 Facility St. Lucie Scenario No.: 3 Op Test No.: HLC-19 NRC Examiners: Operators: SRO:

RO:

BOP:

Initial Conditions: 2-3 % power, BOC. 2C Charging pump OOS for repack.

Turnover: 2-3% power. BOC, 1622 PPM boron, MTC approximately '0'. 2C Charging pump OOS for repack. MFW and SBCS are in service. Vacuum has been drawn in the Condenser.

Raise power and place the Turbine on line.

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Tasks Critical Tasks:

Start 2B HPSI pump

Block MSIS

Close 2B MSIV

Isolate 2B SG Event Malf. Event Event No. No. Type* Description 1 R/RO Raise Reactor power to 10-12%,

10-12%.

2 1 C/RO CEA # 8 slips 20 inches from current position T.S.I SRO 3 2 1/ RO H IC 1100 Spray Controller fails high HIC 4 3 C/BOP CEDM Fan HVE-21A trips 1 -'--

f-~--

5A 4 T.S. SRO SGTL (10 gpm) 2B SG 5B 58 M I All SGTR (200 gpm) 2B SG 6 5 C/BOP B side SIAS does not actuate 2B HPSI does not start with manual SIAS 7 6 C/BOP 2A HPSI Pump becomes air bound 8 7 C/BOP 2B MSIV does not close from the Control Room during Appendix R 9 BOP Isolate 2B SG I--------.-~

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1

Scenario Event Description NRC Scenario 3 st. Lucie The Unit is at 2-3 % power. MFW and S8CS SBCS is in service. The secondary is pressurized with main steam and a vacuum has been drawn. The crew will be instructed to increase power to 10-12% in preparation to place the Turbine on line.

During the power increase a CEA #8 will slip approximately 20 inches. The CEA can be manually retrieved The SRO will refer to T.S. associated with the slipped CEA.

retrieved.

HIC H IC 1100 Spray controller fails high requiring manual control. Pressurizer pressure will continue to lower until the crew takes manual control of spray valves.

CEDM Fan HVE-21 HVE-21A A will trip. The crew will start the standby CEDM fan after a wait time of 10 minutes as per the ~NP.

When the crew reaches 10-12% power a 10 gpm SGTL on the 28 2B SG will develop. The SRO will refer to T.S. to determine appropriate actions. The leak will get progressively worse and the crew should manually trip the unit. The leak will reach approximately 200 gpm.

As the unit depressurizes SIAS 8 B side does not actuate. Manual actuation will be successful but the 28 2B HPSI pump does not start. It can be manually started. The 2A HPSI pump becomes air bound and will require venting to become operable.

When the 28 2B SG is being isolated lAW EOP-99 Appendix R, the 28 2B MSIV does not close from the control room. Local closure lAW EOP-99 Appendix I will be successful.

The scenario may be terminated when 2-EOP-04 Steam Generator Tube Rupture is implemented, the 2B SG is isolated and the RCS is being cooled down.

Procedures Used

2-GOP-201, Reactor Plant Startup Mode 2 to Mode 1

2-NOP-09.01, Main Feedwater System Operation

2-0110030, CEA Off-Normal Operation and Realignment

2-0120035, Pressurizer Pressure and Level

2-0NP-25.01, Loss of RCB Cooling Fans

2-0830030, Steam Generator Tube Leak

2-EOP-01, Standard Post Trip Actions

2-EOP-04, Steam Generator Tube Rupture

2-EOP-99, Appendix R

2-EOP-99, Appendix I Technical Specifications Entered

3.1 3.1 CEA Position 3.1.3.1

3.4.6.2 Operational Leakage 2

Appendix 0 D Operator Action ES-D-2 Form ES-O-2 I:P T"tNo Op Test No.: 1 Scenario # 3 Event # ~_

_ ____ _ Page Page 33 of 19 I Event

Description:

Description Raise power to 10-12% in preparation to roll the Turbine I!

i~~~~r=~~~=r~~~~----~~~~~~~~~~~~--~~~I Time Position A licant's Actions or Behavior I Booth Operator Instructions:

! ** Initiate IC #78 and ensure 2C Charging Pump out of service

- Sign off applicable steps in 2-GOP-201 up to step 6.10 I

I Hand out 2*GOP-2012-GOP-201 signed off up to step 6.10.

IL-------------------------------------------~

I Indications Available:

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Direct power increase to 10-12% lAW 2-GOP-201 step 6.10 in SRO preparation to roll the Turbine. (attached page_4_)

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! 2-GOP-201 step 6.11, When Reactor is in Mode 1, direct i; maximize SG blowdown

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, lAW 2-NOP-23.02 Steam Generator i

! Blowdown Slowdown System Operations, (attached page_6_l page_6_)

I t-=--~-

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[ ______ j - - - - - + - - - - - - - - - - - - - - - - - - - -_ _ _- 1 RO Ii If directed commence Dilution for power increase lAW 2 -NOP 2-NOP- -

i 02.24 step 6.5.12,13,14 6.5.12, 13, 14 (attached page_7_)

f-.

I I !

I Withdraw CEAs in 'Manual Sequential' as directed to control Rx I power.

I

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I I NOTE: Power should be raised initially by CEA's. CEA's should be withdrawn to at least

!, 1 0 2" 102" p rior to 20% power prior p ower to meet LTSSIL

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--_.. ---~-----____+---------------------------___i I BOP SOP Monitor SSCS SBCS for proper operation during power iincrease.

ncrease.

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[

When directed call Unit 1 to determine SG blowdown flow rate.

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REVISION NO.: PROCEDURE TITLE TITLE: PAGE:

1_ _~6..;;..060 _ _~REACTOR REACTOR PLANT STARTUP - MODE 2 TO MODE 1 1---...;;",;;,.------4 PROCEDURE NO.:

25 of 69 2-GOP-201 ST. LUCIE UNIT 2 6.8 (continued) INITIAL

2. P. ((continued) continued)

6. Using the Single Down Arrow, CONTINUOUSLY and FULLY CLOSE LCV-9006, 2B 15% BYPASS Valve while VERIFYING FCV-9021, SG 2B FEED REG Valve OPENING and SG level being maintained at setpoint.

3. RESTORE the AFW system to its normal standby lineup in accordance with 2-NOP-09.02, Auxiliary Feedwater System Operation.

NOTE If the SBCS is already in service or Turbine startup on ADVs is desired, the next step is NOT required to be performed.

6.9 !f if desired PLACE SBCS in service as follows:

( 1. ENSURE the Steam Bypass Permissive switch is in the AUTO position.

2. ENSURE all five SBCS controllers are in AUTOMATIC.

3. NAVIGATE to the SBCS OVERVIEW screen and if the INFO TAG "COND VAC RESET REQUIRED" is on the SBCS OVERVIEW screen, Then PERFORM the following:

A. SELECT the [COND VAC RESET] Button to bring up the COND VAC RESET Button Overlay.

B. SELECT the [COND VAC RESET] Button and VERIFY this Button momentarily flashes from Gray to White.

C. VERIFY the INFO TAG "COND VAC RESET REQUIRED" disappears from the screen.

4. Slowly CLOSE the ADVs and ENSURE the SBCS valves begin to open and control RCS temperature at approximately 532°F.

6.10 When the Main Feedwater Control System and SBCS are in service, raise reactor power between 10% to 12%.

4

REVISION NO.: PROCEDURE TITLE: PAGE:

60 REACTOR PLANT STARTUP - MODE 2 TO MODE 1 I --------i I--------------~ 26 of 69 PROCEDURE NONO.:..

2-GOP-201 ST. LUCIE UNIT 2 INITIAL 6.11 When Reactor is in Mode 1, Then MAXIMIZE Steam Generator Blowdown Slowdown per Chemistry direction. REFER to 2-NOP-23.02, Steam Generator Blowdown Slowdown System Operations.

NOTE Steps 6.12 through 6.20 may be performed concurrently and/or andlor in any order.

6.12 ENSURE Step 6.3, of this procedure is COMPLETE.

SRO Date 1/ Time _ _ _ _ _...:../:. ./_ _ _ __

6.13 ENSURE the Reactor is critical and the RCS is at approximately 532°F and 2250 PSIA.

SRO 6.14 ENSURE that Steam Generators are being maintained between 60%

( and 70% narrow range level.

SRO 6.15 ENSURE the DEH System is in service in accordance with 2-NOP-22.03, DEH System Operation.

SRO 6.16 ENSURE the status of the Main Generator disconnects are as follows:

1. ENSURE 8G50, Unit 2 Generator Disconnect, is CLOSED and clear of switching clearance tags.

Switchman

2. ENSURE 8G518G51,, Unit 2 Generator Disconnect, is CLOSED and clear of switching clearance tags.

Switchman

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REVISION NO NO.:.. PROCEDURE TITLE: PAGE PAGE:

13C STEAM GENERATOR BLOWDOWN SYSTEM 19 1 9 of 39 PROCEDURE NO.:NO. OPERATION 2-NOP-23.02 ST. LUCIE UNIT 2 6.5 Adjusting Steam Generator Blowdown Flow CHECK NOTE

If the respective Steam Generator Pressure Control Valve is Bypassed or in Manual, monitor and adjust as required.

High total Steam Generator Blowdown flows (in excess of 200 gpm total) may require use of two Closed Blowdown Cooling pumps to maintain Closed Blowdown outlet temperature less than 140 degrees F.

Refer to 2-NOP-34.02, Blowdown Cooling System - Closed, to start the second Closed Blowdown Cooling Pump.

1. PERFORM the following to adjust 2A Steam Generator Blowdown Flow.

A. If PCV-23-2 is in SERVICE, STATION an OPERATOR at PCV-23-2 to ensure pressure is maintained approximately 300 psig as indicated on PIC-23-2.

B. If PCV-23-2 is BYPASSED, STATION an OPERATOR at V23252, PCV-23-2 Bypass, to adjust pressure to maintain approximately 300 psig as indicated on PIC-23-2.

C. If FCV-23-12 is in AUTO, SLOWLY Adjust the setpoint on FIC-23-12 to desired flow.

D. If FCV-23-12 is in MANUAL, SLOWLY depress the raise /I lower pushbuttons on FIC-23-12 to obtain the desired flow.

E. If FCV-23-12 is bypassed, Then THROTTLE V23124, FCV-23-12 Bypass, as necessary to adjust flow.

2. PERFORM the following to adjust 2B Steam Generator Blowdown Flow.

A. If PCV-23-3 is in SERVICE, STATION an OPERATOR at PCV-23-3 to ensure pressure is maintained approximately 300 psig as indicated on PIC-23-3.

B. If PCV-23-3 is BYPASSED, STATION an OPERATOR at V23255, PCV-23-3 Bypass, to adjust pressure to maintain approximately 300 psig as indicated on PIC-23-3.

C. If FCV-23-14 is in AUTO, SLOWLY Adjust the setpoint on FIC-23-14 to desired flow.

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REVISION NO,:

NO.: PROCEDURE TITLETITLE: PAGE:

24A BORON CONCENTRATION CONTROL 20 of 75 PROCEDURE NO,:

NO:

2-NOP-02.24 ST. LUCIE UNIT 2 6.5 Aligning for MANUAL Dilution (continued)

CAUTION To preclude lifting the VCT relief valve while using V-2525, do NOT allow PMW flowrate to exceed the running Charging pump(s) capacity.

12. DODD 0 DOD ADJUST FIC-2210X PMW Flow in AUTO or MANUAL to desired flowrate (and if using V-2525 do NOT exceed the flowrate for the number of running Charging Pumps).

13. 0 0 0 0 MAINTAIN VCT pressure less than or equal to 30 psig by DOD opening and closing V2513, VCT Vent, as needed.

14. 0 0 0 0 !f if necessary to maintain the desired VCT level, Then DIVERT the letdown flow to the Waste Management System by placing V2500, VCT Divert Valve, in the WMS position:

A. 0 0 0 0 ENSURE V2500 VCT Divert Valve indicates OPEN.

B. 0 0 DO 0 0 When the desired VCT level is reached, PLACE V2500 in AUTO.

C. 0 0 0 0 ENSURE V2500 indicates CLOSED.

15. 0 0 0 0 When the desired amount of primary water has been added, Then CLOSE FCV-221 OX, Primary Makeup Water.

16. 0 0 0 0 !f if V-2512 Reactor Makeup Water Stop Vlv was opened, Then PLACE V-2512 in CLOSE and ENSURE it indicates CLOSED.

17. 0 0 0 0 If V-2525 if V -2525 Boron Load Control Valve was opened, Then PLACE V-2525 in CLOSE and ENSURE it indicates CLOSED.

18. DO 0 0 0DO 0 ENSURE FIC-2210X, PMW Flow controller is in MANUAL and RECUCE output to MINIMUM.

19. 0 0DOD 0 0 MONITOR for any abnormal change in Tave.

20. 0 0 0 0 §1 RECORD on Data Sheet 1, Boration I/ Dilution Log, the number of gallons of Primary Makeup Water added as indicated on FQI-2210X, PMW Flow Totalizer.

21. 0 0 0 0 !fif additional dilutions are desired, or if the expected changes to Tave or Boron concentration are NOT achieved, Then REPEAT Steps 6.5.1 through 6.5.20.

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REVISION NO.: PROCEDURE TITLE: PAGE PAGE:

60 REACTOR PLANT STARTUP - MODE 2 TO MODE 1 28 of 69 PROCEDURE NO.:

2-GOP-201 ST. LUCIE UNIT 2 "INITIAL INITIAL 6.21 ENSURE the MSR tube side vents are aligned to the condenser to purge non-condensible gases as follows:

COMPONENT DESCRIPTION POSITION INITIAL V11508 2B Cndsr Vent From 2A MSR Isol OPEN V11446 2A MSR To Extr Stm Isol CLOSED V11507 2B Cndsr Vent From 2B MSR Isol 1501 OPEN V11451 2B MSR To Extr Stm Isol CLOSED V11520 2B Cndsr Vent From 2C MSR Isol OPEN V11117 2C MSR To Extr Stm Isol CLOSED V11227 2A Cndsr From 20 MSR Tube OPEN Bundle Vent Isol V11122 20 MSR To Extr Stm Isol1501 CLOSED

1. DEPRESS the Reset pushbutton on the Reheat Control Valve Panel.

2. VERIFY locally the MSR TCVs are positioned as follows:

(

COMPONENT DESCRIPTION POSITION INITIAL TCV-08-1 MS to 2A MSR CLOSED TCV-08-7 MS to 2A MSR CLOSED TCV-08-3 MS to 2B MSR CLOSED TCV-08-9 MS to 2B MSR CLOSED TCV-08-4 MS to 2C MSR CLOSED TCV-08-10 MS to 2C MSR CLOSED TCV-08-2 MS to 20 MSR CLOSED TCV-08-8 MS to 20 MSR CLOSED

3. ENSURE the manual isolation valves for the MSR TCVs are positioned as follows:

COMPONENT DESCRIPTION POSITION INITIAL V08381 TCV-08-7Isol OPEN V08370 TCV-08-7Isol TCV-08-7 Isol OPEN V08378 TCV-08-8 Dwnstm 1501Isol OPEN V08382 TCV-08-8 Upstrm Isol OPEN V08383 TCV-08-9 Isol OPEN V08372 TCV-08-9 Isol TCV-08-9Isol OPEN V08375 TCV-08-10 Isol TCV-08-10Isol OPEN V08384 TCV-08-10 Isol OPEN 8

Appendix D 0 Operator Action Form ES-D-2 I;

I! Op Test No.:

-1 Scenario # 3 Event Event## _ _ _ _ _ _ Page 4 of 19

~~I Event

Description:

Raise power to 10-12% in preparation to roll the Turbine Time II Position II Applicant's A licant's Actions or Behavior

[B I Booth I

ooth Operator Instructions:

I If NPO asked to ensure MSR tube side vents aligned to condenser (step 6.21 2*

Ilf

GOP*201)

G OP*201) state this step has been verified i If Chemistry asked for SG Blowdown Slowdown flow rate, state 100 gpm per SG.

IlfIf asked from SNPO state PCV*23*2 and PCV*23*3 SG blowdown PCV's are in auto. auto .

. If Unit 1 asked for SG blowdown flow rate state 40 gpm per SG.

I i I I

I Adjust SG blowdown to no more than 100 gpm per SG. lAW

!I 2-NOP-23.02 Steam Generator Blowdown System Operations

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BOP I! step 6.5.1.C (2A SG). Step 6.5.2.C 6.S.2.C (2B(28 SG) (attached I page_6_)

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I If directed depress RESET pushbutton on Reheat Control I

I I Panel. Step 6.21.1. Notify NPO to verify locally TCV's closed.

I

! II i (attached page_9_) I I

( :-- .

,I

When Reactor power reaches 5%, make plant announcement BOP

'Reactor is in Mode l'

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1---------+-----+-------------------------1 I

iL_. ______ ~ ____ ~ ___________________________ ~

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Appendix D 0 Operator Action Form ES-O-2 ES-D-2

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i Ii Op Test No. No.: 1 Scenario # 3 Event # 2 Page 5 of ~19'--"'1 19

~~I t.Event Event

Description:

CEA #8 slips 20 inches from current position

. Time II Position III Applicant's Actions or Behavior I* NOTE TO EXAMINER: Ensure power is >5% prior to initiating CEA failure.

i Booth Operator Instructions:

k When directed by Examiner initiate CEA #8 slip.

(CEA slips to 65")

I: Indications Available: Control Room Indications Available: ADS indicates CEA i slipped

!I Annuncaitors K-11 CEA Motion Inhibit

~~~~. K-30 CEA Position Deviation Motion Block (ADS) l!,...-----

__ .._ I SRO Recognize CEA # 8 slipped> 15" (not dropped) r I

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-D-ir-e-c-t-R*-O-t-o-p-I-ac-e-C-E-D-M-C-S-c-o-n-trol i~~ff~*---*---1 panel in !

t----i i

I i

Direct RO to place CEDMCS control panel

. Direct RO to secure dilution if initiated.

off.

! I

i Implement 2-0110030, "CEA Off-Normal Off*Normal and Realignment", in l

I the following order: Appendix D, Appendix A, and Appendix H I

( (attached page_12-15_)

~, ...

T.S. SRO Consult Tech Spec 3.1.3.1 for CEA misalignment T.S. Action D I

! __ I TS_SRO l--

Contact Reactor Engineering I II i

I i Notify SM of CEA misalignment !

I Determines F/ Fe' from Physics curve C.3 to be 1.624

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Ii II !

I I I Consult COLR Figure 3.1-1 3.1*1 a and determines 63 minutes time i iI I to retrieve I!

I 1=

[

..- ---- [-._ ..

1--'

Direct RO to determine operability lAW Appendix A 2-0110030.

I NOTE: step 1 of Appendix A is only step applicable, applicable.

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I, II I Direct RO to realign lAW Appendix H 2-0110030 1-------- i I1--******t~-I~ --

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Appendix D Operator Action Form ES-D-2

~

1 I Op Test No No.: 1 Scenario # 3 Event # 2 Page 6 of 19

--~I I Event

Description:

Description CEA #8 slips 20 inches from current position

,c ____ _

I Time j II Position II Applicant's A licant's Actions or Behavior I'f * * - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - j I Booth Operator Instructions:

i Indications, Available:

When CEA realigned, direct BOP to reset DCS CEA position

1 SRO

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I I

lAW 2-NOP-102.01 DCS Operations. (attached page_16_)

I I RO Recognize CEA #8 slipped to 65" I

i Periorms Immediate Operator actions of 2-0110030, Performs 2~011 0030, "CEA Off-Off~

, Normal and Realignment"

Step 7.1.1 Place CEDMCS panel to OFF !

- Step 7.1.2 Not applicable i

- Step 7.1.3 Not applicable I

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perio~m When directed perform Appendix D (attached page_12_)

i which directs implementation of Appendix A.

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Determine operability lAW Appendix A (attached page_13_)

I I,

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I Recover CEA lAW Appendix H (attached page_14,15_) page_14, 15_)

i I I!. :------~f---

Resume power ascension when directed f

r- -- --

i

,- - - - y - -

I -

Monitors SBCS to ensure operation commensurate with plant i--+-I I

II BOP I

conditions.

,, I When directed, reset CEA #8 on DCS. 2-NOP-102.012-NOP-1 02.01 'DCS I i I l -..

Operations step 6.2.1' A-F. (attached page_16_)

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REVISION NO_:

NO .. PROCEDURE TITLE: PAGE:

57A CEA OFF-NORMAL OPERATION AND 16 of 33 PROCEDURE NO.:NO: REALIGNMENT 2-0110030 ST. LUCIE UNIT 2 APPENDIX D D ; { :.. >::.

ONE CEA MISALIGNED BY GREATER THAN 15 INCHES BUT NOT A DRO'Ppl~DCEA DROPPED CEA (Page 1 of 3)

NOTE Refer to T.S. 3.1.3.1.d RefertoT.S.3.1.3.1.d

1. Ensure the following:

A. CEDMCS panel in OFF.

B. Turbine power adjusted to equal reactor power.

C. CEA motion inhibit.

NOTE If in the previous 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months a dropped or slipped CEA has been successfully retrieved, upper plant management will make the decision to retrieve the CEA and continue operation.

2. Maintain reactor power at or below, but NOT to exceed the power level which resulted from the CEA insertion.

3. Determine from symptoms and CEA position indications, the operability of the CEA in accordance with Appendix A.

4. During determination of the cause of the misaligned CEA, maintain reactor power at or below, but NOT to exceed the power level which resulted from the CEA insertion.

5. If CEA determined to be inoperable for any reason, refer to Appendix B.

NOTE If difficulty is experienced in CEA realignment, a power reduction to less than or equal to 70% rated thermal power should be initiated.

6. If in Mode 3, realign the CEA in accordance with Appendix H and proceed to Step 7.

7. If J.f in Modes 1 and 2, Then refer to plant curve book and obtain the most recent F\ FT R value. This value, when interpreted on the technical specification Fig. 3.1-1a, 3.1-1 a, will indicate the amount of time to restore the CEA within 7 inches of all other CEAs in its group.

A. Within the time allowed by Technical Specification COLR Fig. 3.1-1a, restore the CEA (per Appendix H) to within 7 inches of all other CEAs in its group.

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REVISION NO.

NO.: PROCEDURE TITLE: PAGE:

57A CEA OFF-NORMAL OPERATION AND 9 of 33 PROCEDURE NO NO.:.. REALIGNMENT 2-0110030 ST. LUCIE UNIT 2 APPENDIX A CEA INVESTIGATION FOR OPERABILITY (Page 1 of 3)

CAUTION

Reactor Power shall NOT be increased above the stable power level established following the CEA(s) misalignment.

Criticality shall be anticipated any time CEAs are being withdrawn.

1. For the affected CEA(s), perform the following to determine operability:

A. Place the mode select switch in the manual individual mode.

B. Select the affected CEA on the individual CEA selection switches.

C. Select the group of the affected CEA on the group select switch.

D. 11 CEA motion

!f inhibit is present, Then:

1. Depress and hold the CEA motion inhibit bypass pushbutton.

(

2. Depress then release the bypass enable pushbutton.

E. 11 the CEA was dropped,

!f Then first withdraw the affected CEA until core mimic CEA bottom light and lower electrical limit lights both deenergize.

CAUTION Do NOT exceed +/- 10 inches of the original position without permission from the US.

F. Insert and withdraw the affected CEA and check for smooth operation and normal indications.

G. If CEA is determined to be operable proceed to the applicable appendix for CEA realignment.

13

REVISION NO.: PROCEDURE TITLE: PAGE:

57A CEA OFF-NORMAL OPERATION AND "24 24 of 33 PROCEDURE NO.: NO .. REALIGNMENT 2-0110030 ST. LUCIE UNIT 2 APPENDIX H CEA REALIGNMENT (MODES 1! 1: 2 AND 3)

(Page 1 of 2)

1. While realigning CEAs, observe the following:

A. Regulating CEAs shall be withdrawn in sequence and overlap between groups shall NOT exceed 54 inches.

B. Do NOT exceed a sustained SUR of 1.4 DPM (alarm 1.3 DPM).

C. Criticality shall be anticipated any time CEAs are being withdrawn.

D. If deviation between CEAs in any group approaches 3 inches, stop group withdrawal and realign CEAs.

E. While CEA is misaligned, individual CEA positions within the group shall be determined at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months except when the CEA position deviation circuit is out of service, then verify CEA positions at least once every four hours.

2. Misaligned CEA(s) while in Modes 2 and 3 (subcritical).

A. Place the mode select switch in the manual individual mode.

B. Select the misaligned CEA on the individual CEA selection switches.

C. Select the group of the misaligned CEA on the group select switch.

D. !f CEA motion inhibit is present then:

If

1. Depress and hold the CEA motion inhibit bypass pushbutton.

2. Depress then release the bypass enable pushbutton.

E. REALIGN the CEA by performing ONE of the following:

INSERT the remainder of the group to the misaligned CEA and then withdraw the group to the pre-misaligned position.

ALIGN the misaligned CEA to the remainder of the group.

F. Check the position of all CEAs in the group for proper alignment (CEDMCS and DCS).

14

PROCEDURE TITLE: PAGE: ... .

REVISION NO.: , .

57A CEA OFF-NORMAL OPERATION AND 25 of 33 PROCEDURE NONO.:.. REALIGNMENT 2-0110030 ST. LUCIE UNIT 2 APPENDIX H CEA REALIGNMENT (MODES 1! 1, 2 AND 3)

(Page 2 of 2)

3. Misaligned CEA(s) while in Modes 1 and 2 (critical).

CAUTION Reactor Power shall NOT be increased above the stable power level established following the CEA(s) misalignment.

A. Prior to realigning of CEA, contact Reactor Engineering and supply them with the following information.

1. Power level at which recovery is to be made.

2. Rate of CEA movement during recovery.

3,

3. Movement of other CEAs to support recovery.

B. Place the mode select switch in the manual individual mode.

( C. Select the misaligned CEA on the individual CEA selection switches.

D. Select the group of the misaligned CEA on the group select switch.

E. IfJl CEA motion inhibit is present, Then:

1. Depress and hold the CEA motion inhibit bypass pushbutton.

2. Depress then release the bypass enable pushbutton.

F. Realign CEA to the group position while borating as necessary to maintain Reactor Power at or below the power level which resulted from the CEA insertion.

G. Check the position of all CEAs in the group for proper alignment (CEDMCS and DCS).

H. Using manual group mode, readjust the group positions for proper automatic sequencing as necessary.

END OF APPENDIX H

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15

REVISION NO.: PROCEDURE TITLE TITLE: PAGE:

8A DISTRIBUTED CONTROL SYSTEM (DCS) -

8 of 81 NO ..

PROCEDURE NO.: OPERATIONS 2-NOP-102.01 ST. LUCIE UNIT 2 6.2 Changing CEA Positions

1. Changing Individual CEA Positions A. From the Main Menu, SELECT the CEA Group that contains the individual CEA to be changed.

B. SELECT the Realign button located at the bottom of the screen.

C. SELECT the input box located just right of the current CEA position value.

D. ENTER the new CEA position in the input box and press the enter key.

E. SELECT the Adjust button and verify that the CEA Position value has changed to the new value.

F. SELECT Close to return to the CEA group screen

2. Changing all CEA positions in a single group

(

A. From the Main Menu, SELECT the CEA Group to be changed.

B. SELECT the Realign button located at the bottom of the screen.

C. SELECT the input box located at the bottom of the screen.

D. ENTER the new CEA position in the input box and PRESS the Enter key.

E. SELECT the Adjust All This Group button.

F. VERIFY that the all of the CEA Position values have changed to the new value.

G. SELECT Close to return to the CEA group screen.

END OF SECTION 6.2

(

16

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

Appendix D 0 Operator Action Form ES-D-2 ES-O-2

i ----------

. Op Test No No... 1 Scenario # 3 Event # -.;...3

--,-3_ _ _ _ _ Page 7 of 19 II Event

Description:

DesCription: HIC 1100 Spray Controller fails high L__Time 1-Tlrrle II Position II Applicant's Actions or Behavior

Booth Operator Instructions: When directed by examiner initiate Hie 1100 Fails High.

r---~-------- ---------------------------------j i Indications Available: Pressurizer pressure lowering, both spray valves indicate I

full open.

,I I Recognizes pressurizer pressure trending down I/ main spray SRO c-----

I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----!

I. valves fully open ir----... - - - - - I I I Directs RO to take manual control of HIC-11 00 I I,--- ---. I I

, ! I r-I I

i I

Refers to 2-0120035, "Pressurizer Pressure and Level" step 7.2.1. A.3 (attached page_18, 19_) Direct spray controller operated in manual.

II I\--_.

_._--- I

-+--- I i

May direct hold on power increase (if still in progress) i L_

-ti I i

Ii I Directs RO to control RCS pressure by energizing additional I I I

I heaters, if available and manual control of spray valves.

~----~-----+I-N-o-ti-fi-es-S-M-a-n-d-I&--C-O-f-e-v-e-n-t---------------------~

f--

~--

Notifies SM and I&C of event f------+

~ I- ~~~__+I~~~~-----------------~~----i I f-I,i I

rI!

Refers to Tech Spec 3.2.5 (DNB) if pressure <2225 psia.

Restore within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

,I

"-TRO

-- i I RO Recognizes pressurizer pressure trending down I/ main spray valves fully open

+-

r--

I

! !i Secures dilution if directed by SRO (if still in progress)

I

!i I i I t-----*

I

,I r----.... . ---.-

I Places HIC 1100 in manual as per step 7.2.1.A.3

~--- --

, ----------~

i I

t-

[

17

REVISION NO:

NO . PROCEDURE TITLE TITLE: PAGE: .

PAGE:,

26 PRESSURIZER PRESSURE AND LEVEL

~55 of 15 PROCEDURE NO.:

2-0120035 ST. LUCIE UNIT 2 7.0 OPERATOR ACTIONS 7.1 Immediate Operator Actions

1. None 7.2 Subsequent Operator Actions INSTRUCTIONS CONTINGENCY ACTIONS NOTE

Technical Specifications 3.3.3.5, Remote Shutdown System Instrumentation, and 3.3.3.6, Accident Monitoring Instrumentation, are applicable for Pressurizer Level and Pressure Instrumentation ma Ifu nctions.

malfunctions.

If SIAS has actuated, SIAS must be RESET before Pressurizer Heaters can be energized.

1. ABNORMAL PRESSURIZER 1.

( PRESSURE CONDITION NOTE Appendix "A" contains a listing of pressurizer pressures which are associated with automatic actions.

A. Verify pressurizer spray, proportional A. !f11 system is NOT operating and back-up heaters are operating properly in automatic, Then properly in automatic. Refer to perform the following as Appendix "A" "AI! for expected automatic necessary:

responses.

1. !f 11 selected pressure channel has failed, Then shift to the operable pressure channel.

2. !f 11 selected pressure channel has failed high (greater than 2340 psia),

Then after selecting the operable channel, reset heater control switches on RTGB 203.

18

REVISION NO.

NO.: PROCEDURE TITLE: PAGE:

26 PRESSURIZER PRESSURE AND LEVEL

. 6 of 15 PROCEDURE NO.:

NO ..

2-0120035 ST. LUCIE UNIT 2 7.2 Subsequent Operator Actions (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

1. A. (continued) 1. A. (continued)

3. !f If both pressure channels are failed or automatic pressure control does NOT operate properly, Then operate spray controller in manual and energize or deenergize heaters as necessary.

NOTE Divergence of Spray Line Temperatures between 281 2B1 and 2B2 282 Spray lines may indicate a stuck open spray valve. The stuck open spray valve would have the spray line with the higher temperature approaching cold leg temperature.

(

B. Verify PCV 11 OOE, Spray Valve 2B2, B. !f!! either spray valve is OPEN, and PCV 11 OOF, Spray Valve 2B1,281, Then perform the following:

CLOSED by observing BOTH of the following:

1. CLOSED valve position 1. !! PCV 11 OOE, Spray Valve

!f indication. 2B2, 282, is OPEN, Then PLACE the spray valve selector switch in PCV 1100F.

11 OOF.

2. TIA-1103, Spray Line 2B1 281 2. !! PCV 11 OOF, Spray Valve

!f Temperature, and TIA-11 04, 2B1, 281, is OPEN, Then Spray Line 2B2 282 Temperature, PLACE the spray valve approximately equal. selector switch in PCV 1100E.

19

- - - -- - -- - - - ------ ---------------~ ------------------

Appendix D Operator Action Form ES-D-2

~op Op T",

Test No.:No 11 Scenario # 3 Event # -.;..4 4 _ _ _ _ _ Page 8 of 19

~~I I, Event Description

Description:

CEDM fan HVE-21A trips Ii II Time IIL Position II Applicant's Ap licant's Actions or Behavior I

i NOTE TO EXAMINER: Consider initiating SGTL, event SA, 5A, at this time.

I Booth Operator Instructions: When directed by examiner initiate CEDM fan HVE-21A trip I!;

When directed by examiner initiate SGTL (10 gpm)

When asked the status of Brk. 2-20205 state the breaker is tripped, overcurrent I,..-flag dropped.

! Indications Available: Annunciators:

- X-2 CEDM Cooling air temp high

- X-8 CEDM Cooling HVE-21A flow low I Ovrld I Trip

Am Ampp meter for HVE 21A 21 A indicate '0' f--

I I Recognize CEDM fan HVE-21A tripped. Implement 2-0NP-SRO

, SRO 25_01 'Loss Of RCB Cooling Fans'. (attached page_21-23_)

25.01 1 ~ . ----------+-----+------------------------------1 t--_*

r----

I I

,i

{ L-.------

iI i ------- J I

-+--------

I I

I After approximately 10 minutes from time of trip directs HVE-21B started. Step 6.1.1 6_1.1 (attached page_21_)

page_21_l

!-1------ Ii* .. ..

I I Verify operability of tripped CEDM cooling fan. Perform I

, Appendix A (attached page_24_l-page_24_). Directs Brk. 2-20205 status I , determined.

..._-t-1

~-,..

I

[

II I

Notifies Shift Manager I

~-

iI ! BOP Recognize CEDM fan HVE-21A has tripped.

-- - ~

Starts standby CEDM fan HVE-21 HVE-21B B when directed. i 1-----------

I iI

, Notifies SNPO to investigate status of Brk 2-20205IAW==j I 2-20205 lAW t-------

I t-=-~--!-

Appendix A (attached page_24_)

I Appendix A (attached page_24_1 II I

~

~I-----+-----------------------~

i~' _ _

_ _ _---'--_ _ _ _- - - ' -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .1I 20

REVISION NO.:

NO .. PROCEDURE TITLE: PAGE:

3 LOSS OF RCB COOLING FANS 6 of 19 PROCEDURE NO.NO.:

2-0NP-25.01 ST. LUCIE UNIT 2 6.0 OPERATOR ACTIONS 6.1 Loss of CEDM Cooling Fan INSTRUCTIONS CONTINGENCY ACTIONS CAUTION

§1,2 At least one CEDM Cooling Fan (HVE-21A or HVE-21 B) must be in operation to maintain the reactor vessel support structure within design basis. Operator action is required within 45 minutes, to restore a CEDM Cooling Fan to operation or initiate reactor trip and cooldown to at least Hot Shutdown. The total time from the loss of CEDM Cooling Fan to Hot Shutdown is 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

hours .

To ensure motor is not started while rotating in reverse, a time delay of approximately 10 minutes shall be observed before starting a CEDM Cooling Fan.

1. After approximately 10 minutes 11 the standby fan does NOT

1. If

( from time of trip, START the start, Then PERFORM the standby CEDM Cooling Fan. following:

A. PERFORM Appendix A, CEDM Cooling Fan Local Breaker Operations.

B. ATTEMPT one start of any available CEDM Cooling Fan.

C. INITIATE a rapid shutdown using 2-0NP-22.01, Rapid Downpower.

21

REVISION NO.: PROCEDURE TITLE: PAGE: ....*:* '.:" .

3 LOSS OF RCB COOLING FANS 7 of 19, 19 PROCEDURE NO.:

NO 2-0NP-25.01 ST. LUCIE UNIT 2 6.1 Loss of CEDM Cooling Fan (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

1. (continued) 1. (continued)

D. !f11 at least one fan does NOT start, Then NOTIFY the following:

Maintenance Supervisor

EM E. §1,2

§1,2 11 at least one CEDM

!f Cooling Fan is NOT operating within 45 minutes of fan trip, Then PERFORM the following:

1. TRIP the reactor.

2. TRIP the turbine.

3. IMPLEMENT 2-EOP-01, Standard Post Trip Actions.

4. COOL DOWN to at least Hot Shutdown within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months from the loss of the fan in accordance with 2-GOP-305, Reactor Plant Cooldown - Hot Standby to Cold Shutdown.

(

22

REVISION NO NO.:.. PROCEDURE TITLE TITLE: PAGE:

3 LOSS OF RCB COOLING FANS

>8

'8 of 19 . .

PROCEDURE NO NO.:..

2-0NP-25.01 ST. LUCIE UNIT 2 6.1 Loss of CEDM Cooling Fan (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

2. VERIFY operability of the tripped CEDM Cooling Fan as follows:

A. PERFORM Appendix A, CEDM Cooling Fan Local Breaker Operations.

B. DETERMINE operability of the tripped fan.

C. !f11 the fan is inoperable, Then NOTIFY the SM/US.

(

END OF SECTION 6.1 23

REVISION NO NO.:.. PROCEDURE TITLE:

TITLE PAGE:

3 LOSS OF RCB COOLING FANS 16 of 19 PROCEDURE NO,:NO ..

2-0NP-25,01 2-0NP-25.01 ST. LUCIE UNIT 2 APPENDIX A CEDM COOLING FAN LOCAL BREAKER OPERATIONS (Page 1 of 1)

INITIAL

1. VERIFY electrical alignment of BOTH fans, as follows:

A. Bkr 2-20205, CEDM Cooling Fan HVE-21 A, on 4.16 KV Swgr 2A3:

RACKED IN

Relay targets indicate normal status B. Bkr 2-20408, CEDM Cooling Fan HVE-21 B, on 4.16 KV Swgr 2B3:

RACKED IN

Relay targets indicate normal status

( 2. ENSURE fuses are checked and replaced as necessary.

3. NOTIFY the Control Room of breaker status.

4. !f any breaker is TRIPPED, Then IMPLEMENT OP 1250020, Valve, If Breaker, Motor and Instrument Instructions.

( END OF APPENDIX A

\

24

AppendIx Appendix D Operator Action Form ES-D-2 r- ---~.

Scenario # 3 Event # 5A Page 9 of II Op Test No.:

rO;Test Ii,I

i No

-SA ---- 19

.i Even.t Event

Description:

Description SGTL 10 gpm.

l~*~*~~~=~~_ _ _ _=~=~~~~=

IC'Gme Time . Position PCl.sition A plicant's Actions or Behavior

____=---II i Sooth Operator Instructions: If not previously initiated and when directed by l Indications Available: Charging and letdown mismatch.

examiner initiate SGTL (10 gpm)

I

PC*11 PC-11 SJAE trending up and eventual alarm i

! PC*11PC-11 Slowdown trending up (10*15 minutes after SJAE)

..... _ - _ . _ . I I

I

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

.. 1 i

SRO I.

Recognize Steam generator tube leak occurring on

. - -.......- j - - - - - - - f - - - - - - - - - - - - - - - - - - . - - - -..----j SJAE alarm on PC-11 2B SG Blowdown radiation trending up 0~~~~

2B SG ___1 I

i

Mismatch Chg / Letdown

May refer to 2-0120031 Excessive RCS Leakage if I Charging and Letdown mismatch identified prior to L

L--...

___ +- i

.-+-_ _ _ _+-_ _ _SJAE radiation alarm. _ _ _ _ _ _ _ _ _ _ _----j S_J_A_E_ra_d_ia_t_io_n_a.la._rm_.

f-----

r-~----- ---.-----+-----.-----~------------------------_i

, I Implement 2-0830030, "Steam Generator Tube Leak"

(

Implement Appendix A (attached page_27-39) and refer: refer

. to Figure 2 (attached page page_ 40 )

40_) I II ** Directs or Brief if leak becomes >capacity of charging pumps we will manually trip reactor

- Estimate primary to secondary leakage using daily chemistry report.

,

Contact HP and inform of present plant conditions, conduct secondary surveys T.S. SRO

, ** Direct Chemistry to implement COP-06.05 High activity i in a SG i

! ** Step 11, Consider isolating U-1 Vacuum drag

- Step 12 Verify SGBD not aligned to Discharge Canal i

Direct field operators to perform step 13, 17, 18, 19 and

! 20 of Appendix A (attached page_36-38_).

i !

Determine T.S. 3.4.6.2. c (Action a) HSB within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months i i

Contact Chemistry for secondary sampling t-i 1--. Ii I

i

\

25

Appendix D Operator Action Form ES-O-2 ES-D-2

~-

i Op Test No.: No .. 1 Scenario #

Scenano 3 Event # 5A _ _ _ _

...;;;5A~ Page 10 of 1199 II Event

Description:

Description SGTL 10 gpm.

I: -'4F~~~~~~~~~~~~~~~~~~~~=---~~~~-~1 il__ Time Position II Applicant's Ap licant's Actions or Behavior

.i Sooth Operator Instructions: Notify Control Room Appendix A steps 13, 17, 18, 19 i* and 20 are complete approximately 10 minutes after request.

f* ____ **_*_** .. __

i Indications Available: Charging and letdown mismatch.

i PC-11 SJAE trending up and eventual alarm I

!I PC-11 Slowdown trending up (10-15 minutes after SJAE) r---*----*

I-'~-----"

u

..... _ . _ - , . I ii-- i BOP/RO I Recognize Steam generator tube leak occurring I ** SJAE radiation alarms

- Blowdown radiation trending up

- Mismatch Chg. I Letdown I

I ,

r----.-.

f - - - - _._- ..._---- --. I ._-'I i

Determines approximate leak rate of 10 gpm based on ii I RO Charging /I Letdown mismatch mismatch..

Communicate with NPO I SNPO to perform Appendix A steps BOP 13, 17, 18, 19 and 20 of Appendix A when directed by SRO.

i I

!I

,I

, I

+----r

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

I,

~------~-.-i -'-- ._".-

i i --_ ....

ii

[------_.

r-----------.-_.- ----

I It..

t L

I I r---

f----~.---. -------- --.-.-----.--... --.-~. j---.

r-._--+- _.- ---_..-+----_.._-

I i,

--i-------_._---- l t

,,I---_ ... _... -

"",, - --_. - .. ---~ ...---- t-..

j-- - -....

l!

l 10 -

26

REVISION NO' NO.: PROCEDURE TITLE: PAGE:

36B STEAM GENERATOR TUBE LEAK

.,' '9 9 of 35 PROCEDURE NO. NO.:

2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 1 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS

1. 1fIf at any time RCS leakage exceeds the capacity of the charging pumps and pressurizer level cannot be maintained, Then:

A. 1fIf in Modes 1 and 2, Then trip the reactor and turbine and implement 2-EOP-01, Standard Post Trip Actions.

B. If 1f in Mode 3 (SIAS NOT Blocked),

Then implement 2-EOP-04, Steam Generator Tube Rupture.

NOTE

~1 Quick diagnosis of a tube leak and subsequent rapid isolation of the

( effected S/G will minimize secondary contamination and radiation exposure. Observation of S/G Blowdown Radiation Monitors may assist in validating SJAE Radiation Monitor indications, and may become the primary measured indication if the SJAE Radiation Monitor is out-of-service. Even before confirmation of a tube leak has been established, planning and preparation for unit shutdown and mitigating the affects should commence, by performing notifications, procedure reviews, crew briefings, and ensuring resources are available to tend to the unit conditions.

2. Ensure sufficient charging pumps are 2. 1f pressurizer level is NOT being If operating and maintaining pressurizer maintained, Then isolate letdown to level. assist in maintaining pressurizer level.

3. If 1f the steam generator blowdown rad 3. Manually close the S/G blowdown monitor is in High Alarm, Then ensure and sample valves from the affected steam generator blowdown and sample steam generator.

valves from the affected steam generator have closed on high radiation.

4. Notify Health Physics of present plant conditions and to conduct secondary area radiation surveys.

27

REVISION NO.: NO. PROCEDURE TITLE: PAGE:

36S STEAM GENERATOR TUSE LEAK 10 of 35 ..

PROCEDURE NO.:

2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 2 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS NOTE

A time delay may exist between an increase in SJAE monitor reading and Steam Generator Slowdown monitor readings.

Steam Generator Slowdown sample isolates on Steam Generator Slowdown process monitor high radiation signal.

CAUTION IF conditions of Steam Generator Tube Leakage Change, THEN REDIAGNOSIS of shutdown conditions is REQUIRED to ensure compliance with EPRI guidelines and Technical Specifications.

5. CHECK Air Ejector and! and / or Steam !f Steam Generator sample flow is

5. .!.f

( Generator Slowdown monitor reading. isolated due to CIAS or high radiation, Then perform the

Log radiation monitor readings every following, to regain sample flow only:

15 minutes. (Data Sheet 2)

PLACE control switch for FCV-23-7/9 to CLOSE!

FCV-23-7!9 CLOSE /

OVERRIDE position

OPEN FCV-23-7/9 FCV-23-7!9

6. If and I or Steam Generator

.!.f Air Ejector and!

Slowdown monitor shows step rise or continuous rise, Then perform the following:

A. DIRECT Chemistry to implement COP-06.05, High Activity in a Steam Generator.

B. ESTIMATE primary to secondary B.. !f B .!.f it is not possible to estimate leakage by comparing Air Ejector primary to secondary leakage or and!I or Steam monitor (preferred) and the radiation monitors are out-of-Generator Slowdown monitor reading service, Then determine leak rate with Daily Chemistry Report. by Chemistry sample.

28

REVISION NO.:

NO. PROCEDURE TITLE:

TITLE PAGE:.

PAGE: ' ..

36B 368 STEAM GENERATOR TUBE LEAK ,',

'11 11 of 35 PROCEDURE NO.:NO.

2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 3 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS

6. (continued) 6. (continued)

CAUTION Downpower load rate should be consistent with allowed time. Use of most of the time allowed for the downpower will minimize possible plant perturbations.

NOTE

The following step is used to estimate an increase in the rate of change of the leak.

Example: Initially estimated leak rate is 80 gpd. 30 minutes later

= 15 gpd estimated leak rate is 95 gpd. 95 gpd - 80 gpd :::

increase in 30 minutes, which is an increase of 30 gpd I hr.

Data Sheet 1 is available to facilitate monitoring leakage.

c.

C. 11 BOTH the following conditions exist, If C. Go TO Step 6.0 of Appendix A.

§3, 4 Estimated primary to secondary leakage is ?: ~ 75 gpd.

Estimated rate of change in primary to secondary leakage is

?:~ 30 gpd I hr (as measured by an of ~ 15 gpd in 30 minutes) increase of?:

Then PERFORM the following:

1. REDUCE power at a rate of 10 mw/min to $~ 50% in 1 hr and be in Mode 3 in the next 2 hrs, in accordance with 2-0NP-22.01, Rapid Downpower.

2. Go to Step 16 of Appendix A.

29

REVISION NO NO.:. PROCEDURE TITLE: PAGE: .

36B STEAM GENERATOR TUBE LEAK PROCEDURE NO.:

NO :

J2 12 of 35 2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 4 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS

6. (continued) 6. (continued)

NOTE II =

150 gpd = 0.1 gpm II D. 11 RCS

!f inventory balance or plant D. Go TO Step 6.E of Appendix A.

indications confirm primary to secondary leakage exceeds Tech Spec limits.

OR Valid SJAE and I/ or S/G Blowdown Radiation Monitor indicates S/G tube

( leakage is ~ 150 gpd, Then PERFORM the following:

1. COMMENCE a plant shutdown at a rate of 3 mw/min, be in Mode 3 in s;; 6 hrs, in accordance with ONE of

s; the following:

2-GOP-123, Turbine Shutdown

- Full Load to Zero Load

2-0NP-22.01, Rapid Downpower

2. GO TO Step 16 of Appendix A.

0

~----------------------------------------------------------~ :to>~

~------------------------------------------------------------~

30

REVISION NO NO.: PROCEDURE TITLE: PAGE:

36B STEAM GENERATOR TUBE LEAK 13 of 35-

.13 35 PROCEDURE NO.:

NO:

2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 5 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS

6. (continued) 6. (continued)

CAUTION Downpower load rate should be consistent with allowed time. Use of most of the time allowed for the downpower down power will minimize possible plant perturbation.

E. If!f BOTH the following conditions exist, E. Go TO Step 6.F of Appendix A.

§3,4 Estimated primary to secondary leakage is ;:::;: : 75 gpd.

There is no operable SJAE or affected S/G Blowdown radiation

( monitor, Then PERFORM the following:

1. REDUCE power at a rate of 3 mw/min and be in Mode 3 in the next 6 hrs, in accordance with 2-0NP-22,01, 2-0NP-22.01, Rapid Downpower.

2. Go to Step 16 of Appendix A.

31

-------------------------------~

REVISION NO.: NO .. PROCEDURE TITLE: PAGE:

PAGE,:_,_ .>

(

PROCEDURE NO.

36B NO.:

STEAM GENERATOR TUBE LEAK

-l40f 14 of 35:35 2-0830030 ST, ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 6 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS 6,

6. (continued) 6. (continued)

CAUTION Downpower load rate should be consistent with allowed time. Use of most of the time allowed for the downpower will minimize possible plant perturbation, pertu rbation.

F. II1f either of the following condition F. Go TO Step 6.G of Appendix A.

exists:

- §3,4 The estimated primary to

§3.4 secondary leakage is greater than or equal to 75 gpd and is sustained for greater than or equal to one hour.

hour_

0 OR w en

§2 Primary to secondary leak rate is unstable or increasing AND both SJAE and S/G Blowdown radiation monitors become ;0 inoperable. w en Then PERFORM the following:

1. COMMENCE a plant shutdown at a rate of 3 mw/min and be in Mode 3 in less than or equal to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , in accordance with one of the following:

2-GOP-123, Turbine Shutdown Full Load to Zero Load

2-0NP-22.01, Rapid Downpower

2. Go to Step 16 of Appendix A.

32 .,.. r " ..

REVISION NO NO.:.. PROCEDURE TITLE: PAGE:

36B 36S STEAM GENERATOR TUBE TUSE LEAK

~5 j5 of 35...

PROCEDURE NO.:NO 2-0830030 ST. LUCIE UNIT 2 .;:~?~li');)**

APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 7 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS

6. (continued) 6. (continued)

NOTE A stabilized leak rate is when the rate of change is less than or equal to 10% of the last determined leak rate.

G. If

.If estimated primary to secondary G. GO TO Step 6.H of Appendix A A..

leakage is less than 75 gpd but greater than or equal to 30 gpd, Then PERFORM the following:

1. DETERMINE the affected Steam Generator.

( 2. ESTIMATE primary to secondary leakage by comparing Air Ejector and SIGS/G Blowdown Slowdown rad monitor readings with the daily Chemistry report using the following schedule schedule..

a. If

.If the primary to secondary leak rate is not stable, Then PERFORM the monitoring comparison every 15 minutes minutes..

b. If

.If the leak rate has been stable for more than one hour, Then PERFORM the monitoring comparison every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months hours..

c. .IfIf the leak rate has been stable for more than one 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , Then CONTINUE monitoring in accordance with Chemistry requirements.

3. CONSULT with Chemistry on the contaminated water plan for operational requirements.

33

REVISION NO.: PROCEDURE TITLE:

36B STEAM GENERATOR TUBE LEAK 6 of 35 PROCEDURE NO,:

NO.:

2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 8 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS

6. G. (continued) 6. G. (continued)

4. With concurrence from Chemistry, CONTACT I&C to adjust process monitor alarm setpoints.

5. GO TO Step 7 of Appendix A.

H. If if estimated primary to secondary H. GO TO Step 7 of Appendix A.

leakage is less than 30 gpd but greater than or equal to 5 gpd, Then PERFORM the following:

1. DETERMINE the affected Steam Generator

2. QUANTIFY Steam Generator leakage

3. RETURN out-of-service radiation monitoring instrumentation to service.

service,

4. INCREASE monitoring frequency of radiation monitors to hourly.

5. With concurrence from Chemistry, CONTACT CONT ACT I&C to adjust process monitor alarm setpoints.

34

REVISION NO.

NO.: PROCEDURE TITLE TITLE: PAGE:

36B STEAM GENERATOR TUBE LEAK 17 of 35 PROCEDURE NO.:

2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 9 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS NOTE A full isotopic analysis of steam generator water activity could take up to an hour. If an expeditious indication of gross activity is required, a frisk in the Secondary Lab or a quick count gamma analysis in the Hot Lab, will yield the necessary information to determine the gross magnitude and source of the leak.

7. Notify Chemistry of present plant conditions and to sample both steam activity . .if generators for activity. If a CIAS or high radiation signal has closed the steam generator sample valves, Then they may be opened to permit sampling as follows:

A. Place control switch for FCV-23-7/9 to CLOSE / OVERRIDE position and then take switch to OPEN position.

NOTE A prompt determination of the leak rate takes precedence over fulfilling the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months time requirement of Data Sheet 1.

8. Determine the primary to secondary leak rate, per 2-0SP-01.03, Reactor Coolant System Inventory Balance.

NOTE

§1 If total tube leakage is greater than .1 GPM, Then the reactor must

§1!f be in Hot Standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and Cold Shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Reference Daily Chemistry Report for projected ;0 W

Condenser Air Ejector Reading (CPM) with a .1 GPM Primary / Gl OJ Secondary Leak.

A prompt expeditious shutdown is desired, however a controlled shutdown with minimal pressure transients takes precedence over a short duration to shutdown.

9. NOTIFY Plant Management of potential plant shutdown.

35

NO.:

REVISION NO" PROCEDURE TITLE: PAGE: ,'', .

PAGE:

( 36B STEAM GENERATOR TUBE LEAK

~;::< ::~.~

,018 of 35 PROCEDURE NO,:NO, 2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 10 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS

10. REVIEW procedures and CONDUCT shift briefs as needed for plant shutdown, shutdown.

11. CONSIDER isolating blowdown and vac drag on Unit 1, 1.

12. VERIFY steam generator blowdown is not aligned to the discharge canal.

13. DIRECT a field operator to the SGBTF to perform ALL of the following:

A. ENSURE SGBTF Truck Bay (roll-up) door is CLOSED.

( B. ENSURE SGBTF ventilation systems are in operation:

Supply Fans HVS-10A or HVS-10B

Exhaust Fans HVE-41A or HVE-41B HVE-41 B

SGBTF Ventilation Process Monitor

14. VERIFY RCS water inventory balance 14. RETURN TO Step 6.B of and /I or Chemistry samples indicate Appendix A.

A, primary to secondary leak rate is less than or equal to 30 gpd.

15. !f11 RCS Inventory balance and /I or 15. RETURN to Step 6.B of Chemistry samples indicate primary to Appendix A.

secondary leak rate is less than 5 gpd, Then EXIT this procedure and continue with the normal monitoring program.

36

REVISION NO.: PROCEDURE TITLE: PAGE:

36B STEAM GENERATOR TUBE LEAK

.e O *

PROCEDURE NO.:

NO,:

19 of 35 2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 11 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Downpower load rate should be consistent with allowed time. Use of most of the time allowed for the downpower will minimize possible plant perturbation.

pertu rbation.

16. PERFORM ALL of the following:

11 necessary, Then INITIATE the Emergency Plan.

CONTINUE to monitor process monitors for changing conditions due to Steam Generator tube leakage every

( 15 minutes.

CONSULT CONSUL T with Chemistry to implement Contaminated Water Plan.

17. DIRECT a field operator to the SGBTF to perform ALL of the following:

A. ENSURE SGBTF Truck Bay (roll-up) door is CLOSED.

B. ENSURE SGBTF ventilation systems are in operation:

Supply Fans HVS-10A or HVS-10B

Exhaust Fans HVE-41A or HVE-41B

SGBTF Ventilation Process Monitor 37

REVISION NO,:

NO.: PROCEDURE TITLE: PAGE:

PAGE.--

i1~ig~f3~.'****

36B STEAM GENERATOR TUBE LEAK

'20 of 35 PROCEDURE NO.:

2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 12 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS CAUTION To reduce the release of potentially radioactive steam from turbine auxiliary feedwater pump exhaust, motor driven auxiliary feedwater feed water or main feedwater pumps should be used. If the motor driven auxiliary feedwater pumps are not available, steam from the unfaulted or least affected steam generator should be used to drive the turbine driven auxiliary feedwater pump.

18. Capture the CTCS sponge ball in accordance with 2-NOP-21.01, Condenser Tube Cleaning System Operation.

19. Ensure condenser air ejector is aligned to the plant vent.

(

20. Locally isolate auxiliary steam to auxiliary priming ejectors by closing V08245.

V08245, V~When the turbine is tripped and the reactor v~When 21. !f If the reactor is shutdown, Then go

~7 is NOT shutdown, Then shutdown the

~J to Step 22 of Appendix A.

reactor as follows:

A. REFER TO 2-GOP-203, Reactor Shutdown.

B. Verify that shutdown margin is within the limits specified in COLR in accordance with 2-NOP-1 00,04, 2-NOP-100.04, Surveillance Requirements for Shutdown Margin Modes 2, 3, 4 & 5 Subcritical.

38

REVISION NO.: PROCEDURE TITLE: PAGE: ,

36B STEAM GENERATOR TUBE LEAK PROCEDURE NO.:

-21 21 of 35 2-0830030 ST. LUCIE UNIT 2 APPENDIX A ACTIONS IN MODE 1 THROUGH MODE 3 (SIAS NOT BLOCKED)

(Page 13 of 13)

INSTRUCTIONS CONTINGENCY ACTIONS

22. When the reactor is shutdown, Then 22.

PERFORM BOTH of the following:

A. COMMENCE an RCS cooldown until A. !f the SBCS is If NOT available, hot leg temperature is less than 510°F 51 oaF Then PERFORM both of the using the SBCS. following:

1. Steam to the atmosphere using the atmospheric steam dump valves.

2. Reevaluate the E-Plan classification.

B. DEPRESSURIZE the RCS and

( maintain 20°F to 50°F subcooling per Figure 1, RCS Pressure /

Temperature.

23. If

!f RCS pressure and level are being controlled, Then when RCS pressure reaches 1836 psia and annunciator R-8, SIAS Channel Block Permissive alarms, perform the following:

A. Block channels A A and B8 of SIAS by turning the SIAS block key switches (99 & 100) on RTGB RTG8 206 to the block position.

B. Ensure annunciators R-9 and R-10 SIAS Actuation Channel A (B)(8) Blocked have annunciated.

24. GO TO Step 3 of main procedure.

END OF APPENDIX A 39

NO ..

REVISION NO.: PROCEDURE TITLE: PAGE:

36B STEAM GENERATOR TUBE LEAK NO.

32 of 35 PROCEDURE NO.:

2-0830030 ST. LUCIE UNIT 2 FIGURE 2 MODE 1 THROUGH 3 (SIAS NOT BLOCKED)

(Page 1 of 1) 1)

The rate of change

)--_Y_ES_~I YES

_* 8e le~ lhan Be less than 5O%Pomr 50% Pomr in In one ho'"

holS IS grea!er then

- ee8e In Mode 3 v.ithin

'Mthm tho two hou" neXl \VI<)

the next hours lY equal to 30 gpdIhr NO SJEAor affected SGSD NO Red MOniter operable NO YES r------------J 8e In rnode 3 YJlthin SIX hours

(

Greeter than YES or Of Equal 10to 108 gpd t:!Qlli f:!QIi A

A Stabilized Stablli2:ed leakrale leakrate IS \\!len Wlen the rate rale of NO , tho IS less change 1$10 than or equal to 10%01

.. than" the last determined leakrata 10% of Jeakra!e Greater than Of Equal to 75 gpd YES for Greater than or Se Be inIn Mode 3 v.ittlin vAthin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Equal 10 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months NO

.* Detennine affecte<l

.Nectod SIG Estimele PriiSec

- Es1imata ltlakrste every 15 Min Pri/Sec l.akrsie Grealer Greater than YES leakrate stable for

-* If le.krsta Ie;( great",

greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or Equal 10 >--------------1

>-------------~I monitor every 2 hou" then monitorevOfy hours

-IIIf leakrale LeBkrate stable lor for gr ** t", than 24 greater 30 gpO gpd hours then montier t>ours Ihen p&r Chemiolry mOOlil)l per Chemistry requ,emenls requremenls NO YES -. Determine tha the affected SIG

+-.j

.---.----.~ leakrale

QlUlntify S/G leokrat.

-Quantify

-I.\onltor

-Momtor Hourly 40

Appendix D Operator Action Form ES-D-2 Ii! Op Test No.: 1 Scenario # 3 Event # _5;,.;8_____

5B Page 11 of 19

-.;..;~----

'I I! Event DescriPtion:- Description SGTR 200 gpm.

Ii!.

Time Position A licant's Actions or Behavior

":I Booth Operator Instructions' .----------------------------------------------,

Instructions: When directed by examiner initiate SGTR (200

! gpm)

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

I Indications Available: Pressurizer level and pressure rapidly lowering !

I 1------'

i Direct RO to isolate Letdown (Close V2515, V2516, V2522) V2522l as SRO I leak increases.

~------

I i Notifies SM of SGTL and power reduction

' - - -- _.. .. -~-.- ,-

I 1--- --

Direct power reduction to Mode 3 lAW step 6.F.1 then goes to step 16 of Appendix A. (attached page_32_) page_32_l i I

I I Directs Reactor tripped when notified Pressurizer level cannot be maintained.

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

o-_n I

BOP I Monitors and maintainS maintains SG levels 60*70% 60-70%

~

I Communicate with HP and Chemistry as directed by SRO r---' -----

I Makes plant announcement of Unit shutdown

~

~---

I Trips the Reactor when directed by SRO I r---'

r---'

iI

.. __._-". .- I I

1---_*-

> - - - - - _..- .--- i

,!I II,.... ....

RO Isolate letdown when directed as leak increases I iI r---- I I

Recognize Pressuirzer level lowering with letdown isolated and II I both Charging pumps running.

I I If .... .-----

['

, Inserts CEA's in Manual Sequential when directed, to place the

, plant in Mode 3 I;

I Trips the Reactor when directed by SRO

- 11 .-

41

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

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # .1...-

3 Event # .....;;.;5B;...._ _ _ _ Page

-5B- - - - -

12 of 19 Event Description

Description:

SGTR 200 gpm.

I Time I Position I A plicant's Actions or Behavior Applicant's I Booth Operator Instructions:

!. Indications Available: Available' I Examiners note: SIAS SIA~ will not actuate until the crew enters 2*EOP*04 2*EOp*Q4 SGTR and cooldown, starts a cooldown.

~--~--.

Directs implementation of 2-EOP-01 2-EOP-01,, "Standard Post Trip Actions" as follows:

SRO

RO: Reactivity control, Inventory Control, Pressure control, Core Heat Removal

BOP: Vital Auxiliaries, RCS heat removal, Containment Conditions.

iI

,i Periorms EOP-01 Safety Functions as directed for Reactivity Performs RO Control, Inventory Control, Pressure Control, Core Heat

removal

( ~-

~---

I Reactivity Control i

, *~ Verify Reactor power is lowering

Verify startup rate is negative.

II

Verify a maximum of one CEA is not fully inserted.

~ -_. --_..

Inventory Control

Verify pressurizer level is between 10 and 68%

I

Pressurizer level is trending to 30 - 35% (take manual

! control of chg pumps and isolate letdown if not already I isoalted)

I

(

42

Appendix D Operator Action Form ES-D-2 ES*D*2 Op Test No.:

No. 1 Scenario # 3 Event # 5B Page 13 of 19

~~------ ~~I Event

Description:

SGTR 200 gpm.

Time III Position IlII Aj)Qlicant's Applicant's Actions or Behavior Booth Operator Instructions:

Indications Available:

I

~------'I- - - - - - , - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1

! Pressure Control

e Verify RCS pressure is between 1800-2300 psia (at 1736 psia verify SIAS and stop RCP in each loop)

I ,

i II RO *e Verify RCS pressure is trending 2225-2275 psia psi a (control manually)

_,,_I+-___

Verify RCS subcooling is >20 0 F

~

I r-II I

e e __V_e_ri_fy_R Core Heat Removal

__C_S_S_U_b_CO_o_li_n_g_is_>_2_0_0_F________________

Verify at least one RCO running with CCW ( if> 10 if >10 Ii I minutes with no CCW must secure)

II I

( ~---.

I

e Verify loop delta T is <10 F f-------------+---~--+----------------------j

~

1"-i f----

1---

I BOP Performs EOP-01 Safety functions as directed for: Vital Auxiliaries, RCS Heat Removal, Containment Conditions II

~---.----

i------

I, I

l------*1 I

Maintenance of Vital Auxiliaries

,i ' I *e Verifies turbine governor and throttle valves closed I

i

e Verify GEN Brk open (East breaker, Mid Breaker and II Exciter Breaker)

e Verify all vital and non vital AC Buses energized. energized, (2A 1, 2A2, 2A3 2AB, 2B1, 2B2 and 2B3 6,9 6.9 and 4,16kv 4.16kv buses)

I L-~ ___ ~ ____ ~

All vital and non vital DC Buses energized. energized,

_ _ _e_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~

43

Appendix D Operator Action Form ES-D-2 ES-O-2 illl Op Test Op Test No.: No. 1 Scenario # 3 Event Event## 5B Page 14 of 19 SGTR 200 gpm.

I Event

Description:

I i~ime_ Time JlII Position III Applicant's Actions or Behavior

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

Booth Operator Instructions:

_._. __ .. _--_. _. -_. .. - ..---.---------~-----------------------"

Indications Available:

---~

~--------.-- .- --~-----*-___rl--------------------------

RCS Heat Removal I

Verify at least one SG has feedwater available (AFW or I MFW)

BOP i ! ** Verify RCS Tavg is between 525 and 535 F I

Verify SG pressure is between 835 and 915 psig.

III

~.---!

i I ** Ensure MSR Block valves and warmup valves closed f--------.. --

I Containment Conditions I i, I I

I Ii iiI

Verify containment pressure <2 psig

Verify NO containment radiation monitors in alarm.

BOP

(

Verify containment temperature is less than 120 F

Verify NO secondary plant radiation alarms (SG Blowdown may be in alarm

~-.-

I Upon unit trip, notify NPO to perform App.X sect. sect.11 of EOP-99. ;

Ii -------i I

I

~

1-* i I I I,j

~-------

t~=~*~-=-~r---*-

~-----~-

r---~.ii i

I, ,

! I i :

I I

I II I

i-------

r-.----~-

I I!

f...-- _ _ _ _ .* _ _ _ _ _ _ _ _ _ ,_ - -

>----~--. .-~- .. -~.-

I

(

44

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

Appendix D 0 Operator Action Form ES-D-2 p--

I. Op Test No.: No .. Scenario # 3 Event #

Event# ~6'.;..7':..;8;..:.'

~6'.;...7,~8~,.;.,9 ,,;.9_

_____ Page ~

_15_ of _19_..,1

_1_9--"1 I

i: Event Description.

Description:

2-EOP-04 Steam Generator Tube Rupture. SIAS B 8 side does not actuate. 2B 28 j: HPSI pump does not start. 2A HPSI pump becomes air bound. 2B 28 MSIV does not close from the control room. Isolate the 28 2B SG.

I:

1~~_~:="Ti-m-e-_=iF[~ Time I __-:£'::"'-f2.=s.-:ltl~~.0~_

Position . _~~~=~===~A-::-ilc-a-nt:':'"'s=A':'"'c-:ti-on-s-o-r-::8:-e-:-ha-v'":"'io~r====~===\1 I Applicant's Actions or Behavior

~~~~-&=========--===-U~~~~~~~~~=========-__~

Booth Operator Instructions: I Indications Available:

III SRO Evaluate diagnostic flow chart of 2-EOP-01 Determines SGTR.

J I Directs entry to 2-EOP-04, "Steam Generator Tube Rupture" RuPture~

f~---------

_~ _ _ _ _ _ _ _ _ _ _ 0_ _ _ _

I II--I I I

BOP/ST A to perform SFSC's of EOP-04 Direct BOP/STA iI

~

I f--

I f----

II I

Implements place keeper (attached page_46-48_)

--.----~------;--~----

.-~---~.

Notifies shift manager to classify the event r----

f---"~------- .

i i i---

f-----

! i i

Direct performance of EOP-99 Appendix A, sampling SG's

---1 Ii !:, (attached page_49,50_)

! I r--

!I I

~

1------- I ----- -- -1 I, Direct BOP to verify Si flow per Figure 2 (attached page_51_)

I I

Ensure all available charging pumps are operating I

I I~-

i Direct one RCP/LOOP stopped when SIAS received on low I

I!I , Pressurizer pressure. i Ii I .---- !

!r I i f---- - _ +-----

f---- ..... ....** -. ~-

I II I Direct RO to monitor RCP Operating Limits per Table 13 II II I, II IfIf------.-----;------------- i (attached page_52_) iI

_+_ -----

,i I i

I I II Direct EOP-99 Appendix J, CCW restoration to RCP's after ,I II SIAS (attached page_53,54_)

r -J I

i r

I Directs RO to perform controlled cooldown to <510°F T hot using II SBCS in manual, not to exceed 100°F in anyone hour period I,

I!

.~-.--- ---"-

45

REVISION NO.

NO PROCEDURE TITLE: PAGE:

24 STEAM GENERATOR TUBE RUPTURE 44 of 46 PROCEDURE NO NO.:..

2-EOP-04 ST. LUCIE UNIT 2 ATTACHMENT 2 PLACEKEEPER PLACE KEEPER FOR SGTR (Page 1 of 3)

TIME: EOP ENTRY DATE:

STEP INSTRUCTIONS STATUS START DONE 4

4. Sample Steam Generators D 0 D 0

5. Ensure Safety Injection Actuation D 0 D 0

6. Maximize SI Flow D 0 D 0

7. RCP Trip Strategy D 0 D 0

8. Ensure RCP Seal Cooling D 0 D 0

A. Time of CCW loss D 0 D 0

(

B. Time plus 10 D 0 D 0

C. Time plus 30 D 0 D 0

9. Verify RCP Operating Limits D 0 D 0

10. RCS Cooldown 51 oaF Cool down to less than 510 aF D 0 0D

11. Depressurize the RCS D 0 0D

12. Block MSIS and SIAS D 0 D 0

13. Protect Main Condenser D 0 D 0

14. Restore Instrument Air D 0 0

15. Determine the MOST Affected S/G 0 0

16. Isolate the MOST Affected S/G D 0 D 0

17. Maintain ISOLATED S/G Below 915 psig (930 psia) D 0 D 0

18. Verify Correct S/G was Isolated D 0 D 0

19. HPSI Throttling Criteria D 0 D 0

- Continuously Applicable or Non-Sequential Step 46

REVISION NO.:

NO. PROCEDURE TITLE PAGE:

24 STEAM GENERATOR TUBE RUPTURE 45 of 46 PROCEDURE NO NO...

2-EOP-04 ST. LUCIE UNIT 2 ATTACHMENT 2 ATIACHMENT2 PLACEKEEPER FOR SGTR (Page 2 of 3)

STEP INSTRUCTIONS STATUS START DONE

20. HPSI Pump Restart Criteria 0 0

21. LPSI Pump Stop Criteria 0 0

22. LPSI Pump Restart Criteria 0 0

23. Maintain RCS within Figure 1A limits 0 0

24. Maintain the UNISOLA TED S/G Level 60 to 70% NR UNISOLATED 0 0

25. Evaluate Condensate Inventory 0 0

26. Borate the RCS for SDM 0 0

( 27. RCS Cooldown (to SDC)

SOC) 0 0

28. Sample RCS for Dilution 0 0

29. Disable RCPs in the ISOLATED S/G loop 0 0

30. Maintain ISOLATED S/G Level less than 90% NR 0 0

31. Restore Letdown 0 0

32. Verify RCS is NOT Water Solid 0 0

33. Establish a Pzr Bubble 0 0

34. Maintain Pzr Level 30 to 68% 0 0

35. Restore Offsite Power 0 0

36. RCP Restart 0 0

37. Verify Single Phase Natural Circulation 0 0

38. Ensure Two Phase Natural Circulation 0 0

39. Sample for Secondary Activity 0 0

- Continuously Applicable or Non-Sequential Step 47

NO.

REVISION NO.: PROCEDURE TITLE: PAGE:

24 STEAM GENERATOR TUBE RUPTURE 46 of 46 NO.

PROCEDURE NO.:

2-EOP-04 ST. LUCIE UNIT 2 ATTACHMENT 2 PLACEKEEPER FOR SGTR (Page 3 of 3)

STEP INSTRUCTIONS STATUS START DONE

40. Monitor Spread of Contamination 0 0

41. RCS Void Elimination 0 0

42. Cool and Depressurize the Isolated S/G 0 0

43. SIT Venting/lsolation Ventingllsolation 0 0

44. LTOP Initiation 0 0

45. Reset Safety Systems 0 0

46. SOC Operation Exit to SDC 0

(

- Continuously Applicable or Non-Sequential Step END OF ATTACHMENT 2 48

REVISION NO.:

NO. PROCEDURE TITLE: PAGE:

36A APPENDICES APPENDICES!I FIGURES TABLES / DATA FIGURES!I TABLES!

33 of 156 PROCEDURE NO. NO.: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 .... ' .

APPENDIX A SAMPLING STEAM GENERATORS (Page 1 of 2)

(..J)

A Train (-J) B Train (..J) CY) o 1. !f a LOOP has occurred, Then PERFORM BOTH of the following:

o A. ENSURE 2AB 480V Load Center is aligned to an energized bus.

o B. DISPATCH an operator to restore Instrument Air.

REFER TO Appendix H, Operation of the 2A and 2B Instrument Air Compressors.

CAUTION Under SIAS conditions the CCW 'N' header should only be aligned to ONE essential header. This will maintain train separation while safeguards signals are still present.

NOTE

- HCV-14-9 (HCV-14-10) will open 5 seconds after HCV-14-8A (HCV-14-8B) starts to open

It When SIAS is present, placing the control switches in CLOSE and then OVERRIDE will open the CCW 'N' header valves, until SIAS is reset o 2. !f SIAS has closed the 'N' Header valves, Then RESTORE flow from EITHER 'A' or 'B' CCW Header by PLACING the control switches for the desired train to CLOSE and then to OVERRIDE:

HCV-14-8A

HCV-14-9 OR

HCV-14-8B HCV-14-S8

HCV-14-10 49

REVISION NO.: PROCEDURE TITLE: PAGE:.',"

PAGE:

36A APPENDICES I/ FIGURES I/ TABLES I/ DATA 44 of 156 PROCEDURE NONO.:. SHEETS 2-EOP-99 ST_ LUCIE UNIT 2 ST.

APPENDIX A . .

SAMPLING STEAM GENERA TORS GENERATORS (Page 2 of 2) o 11 CIAS or high radiation has closed the SGBD Sample Valves,

3. if Then OPEN FCV-23-7 and FCV-23-9 by PLACING the control switch to CLOSE I/ OVERRIDE and then to OPEN.

0 4. DIRECT Chemistry to perform S/G samples for activity and boron.

0 5. 11 if S/Gs cannot be sampled, Then DIRECT Health Physics to conduct secondary plant local area radiation surveys.

END OF APPENDIX A

(

50

~---------------------~

REVISION NO.:

NO_ PROCEDURE TITLE: PAGE:

PAGE:,

36A APPENDICES I/ FIGURES I/ TABLES I/ DATA

1:21 121 of 15'6 156 PROCEDURE NO.:NO_: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 FIGURE 2 SAFETY INJECTION FLOW VS. RCS PRESSURE (Page 1 of 1 1))

1300 1300 ----~I I I I I I T-'-J I

1200 +--+---f--_+_--i----__t I This curve represents 1200 - NOTE expected II minimum expected This curve represents minimum 1100 ~

t\\

SI Flow. If measured flow is less than this pP 1100 --- ---- figure, Then SI System lineup should be 1 -

R verified.

E S

sS 1000 - \

1000 \

U R 900 - -

900* ._'" -t--tT----------~ ~- 1----- -----------+----i----4----- ---- -----f----i I

Z 8 800 0 0 - - - -I -r---+-~_+__--- ~---+_--+_--+_-+_----1 E

R 700 I - --\-

\- ~-_+_~+____i-___i_~+___+__~\___+__---+___;I

(

RR p

E 600 600 r----

\ 1 Full Train sS

\

f--- \

" 1 Full Train S 500 500 -- In OPTtion

< in Operation + - - - j - - - I - - - - I - - - - + - - - + - - - + - - - - - 1

+----+t~ ~\\V .~ . . ~2}~!T-r~+~:-~~-+--+---f---+----t:---+----1 U /

R E 400 \ 2 Full Trains

in Operation 300 '. ~l----* .----+-----+-----+~+---+----+-- -----

p

~ --------

s i 200 200- I\,\

I-I------~::::jr----...=---t---+----Lr--_

a 1 r---. - --r--r--

100 100-o0:~

1 o0

,--+

1000 I

2000

~~

I '

~

3000

--+--+-1'----=---+---+---+--+--+--+--+---;--+----..:---+---1 4000 5000 6000 TOTAL SAFETY INJECTION FLOW (gpm) (P/OPS/2-EOP-99/Flg2fRevOltlf)

(P/OPSI2* EOP*99/Fig2lRev O/tif) 51

REVISION NO.:

NO, TITLE PROCEDURE TITLE: PAGE PAGE:-

36A APPENDICES / FIGURES I/ TABLES I/ DATA OAT A J:55 155 of 156 PROCEDURE NO_:

NO,' SHEETS 2-EOP-99 ST. LUCIE UNIT 2 TABLE 13 RCP OPERATING LIMITS (Page 1 of 1)

ACCEPTABLE RANGE OF ACTIONS WHEN CONDITIONS ARE OPERATION OUTSIDE ACCEPTABLE RANGE TCOLD must be greater than 500°F for 4 1fIf T COLD is approaching or is less than 500°F, RUNNING, RCPs to be RUNNING. Then ENSURE at least ONE RCP is STOPPED.

RCS Pressure Temperature is above MONITOR RCP instrumentation for and to the left of the RCP NPSH cavitation or seal failure requirement curve of Figure 1A or 1 B, If cavitation or multiple seal failure is RCS Pressure Temperature.

indicated, Then STOP the affected RCPs Guide bearing temperatures are less STOP the affected RCPs.

185°F, than 185°F.

Thrust bearing temperatures are less STOP the affected RCPs.

200°F, than 200°F.

( CCW flow greater than 200 gpm. If CCW flow is lost and can NOT be re-established within 10 minutes Then STOP the affected RCPs.

Oil Reservoir Levels +2 to -2 inches. If valid, rapidly changing or full scale high or low indicated level in either the upper or lower oil reservoir Then STOP the affected RCPs.

Controlled Bleedoff and Lower Cavity If Controlled Bleedoff or Lower Seal Cavity Seal temperature is less than 250°F.

250°F, temperature is greater than or equal to 250°F, Then STOP the affected RCPs. RCPs, END OF TABLE 13 52

NO

REVISION NO: PROCEDURE TITLE:

TITLE PAGE:

PAGE. .;

36A APPENDICES I FIGURES I TABLES I DATA 62 of 156 PROCEDURE NONO.:.* SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX J RESTORATION OF CCW AND CSO CBO TO THE RCPs (Page 1 of 2) o 1. ENSURE Instrument Air to Containment is available by PLACING HCV-18-1HCV-1S-1 to CLOSE I OVERRIDE and then to OPEN.

CAUTION Under SIAS conditions the CCW 'N' header should only be aligned to ONE essential header. This will maintain train separation while safeguards signals are still present.

NOTE

HCV-14-9 (HCV-14-1 (HCV-14-10) 0) will open 5 seconds after HCV-14-8A HCV-14-SA (HCV-14-8B)

(HCV-14-SB) starts to open.

When SIAS is present, placing the control switches in CLOSE and then OVERRIDE will open the CCW 'N' header valves, until SIAS is reset.

( o 2. 11 SIAS has closed

!f the 'N' Header valves, Then RESTORE flow from EITHER 'A' or 'B' CCW Header by PLACING the control switches for the desired train to CLOSE and then to OVERRIDE:

HCV-14-8A 'N' Hdr Isol Discharge HCV-14-SA

HCV-14-9 'N' Hdr Isol Suction OR

HCV-14-88 'N' Hdr Isol Discharge HCV-14-SB

HCV-14-10 'N' Hdr Isol Suction o 3. ALIGN CCW to I from the RCPs by OPENING ALL of the following valves:

o HCV-14-1, CCWTo RC PUMP o HCV-14-2, CCW From RC PUMP o HCV-14-7, CCW To RC PUMP o HCV-14-6, CCW From RC PUMP o 4. If

!f CIAS has isolated controlled bleedoff flow to the VCT, Then OPEN V2507, RCP Bleedoff Relief Stop Vlv.

53

REVISION NO.

NO.: PROCEDURE TITLE: PAGE:

36A APPENDICES /I FIGURES /I TABLES I/ DATA

'63 63 of 156 PROCEDURE NO.

NO,: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX J RESTORATION OF CCW AND CSO TO THE RCPs (Page 2 of 2)

CAUTION RCP Seal Cooler isolation valves automatically close on high Seal Cooler outlet temperature of 200°F. Maintaining the control switch in the OPEN position will override this function. CCW radiation monitors should be closely monitored for indication of RCS to CCW leakage should conditions warrant the valve(s) to be maintained in the open position. Consideration should be given to returning the control switch(

switch(es) es) to the AUTO position once the valves have been opened.

o D 5. ENSURE ALL RCP Seal Cooler Isolation valves are OPEN:

o D HCV-14-11-A HCV 11-A 1, CCW From 2A 1 RCP Seal Cooler o

D HCV-14-11-A2, CCW From 2A2 RCP Seal Cooler o

D HCV-14-11-B1, CCW From 2B1 RCP Seal Cooler oD HCV-14-11-B2, CCW From 2B2 RCP Seal Cooler o

D 6. VERIFY RCP CCW related alarms are CLEAR or have been evaluated and dispositioned.

END OF APPENDIX J

(

54

Appendix D Operator Action Form ES-D-2 I'

II I i Op Test No.

IIOPTestNo.: 1 Scenario #

Scenario # 3 3 Event #

Event # _6~,~7'...;;8.:..;'

6,7,8,9 9;..-._ _ Page 12-16 of ~9

_1;.;;..9__1 II Event

Description:

2-EOP-04 Steam Generator Tube Rupture. SIAS B side does not actuate. 2B I,

II:i HPSI pump does not start.start 2A HPSI pump becomes air bound. 2B MSIV does

,i not close from the control room. Isolate the 2B SG.

III:

I,~

Time Position plicant's A plica nt's Actions or Behavior

!r--B-~oth Booth Operator Instructions: If SNPO called to investigate 2A HPSI pump, state the pump appears OK.

Trigger vent 2A HPSI pump when asked to vent the 2A HPSI pump. Wait 5 minutes and report back the 2A HPSI has been vented and a large I volume of air was vented.

II~dications

\----

Indications Available: 2A HPSI pump Amps oscillating.

i 1--

I I

I II Direct RO to depressurize RCS lAW step 11 EOP-04 I

1 I I i .* Within-Figure 1A (attached -

page 56 )

page_56_)

I SRO I * <930 psia i

I i

i !

Above RCP minimum pressure i

Approx. Equal to 2A SG pressure (within 50 psia)

C-_ _ _ _ _ .ji __

I J - - - - .. -- .--.--~- ---~--

Recognize SIAS B 8 side did not actuate at setpoint of 1736 psia.

It------- Directs manual actuation of B side SIAS I

r-- ---

t-_**

I ----:-

iI i !

Critical I Recognize 2B 28 HPSI pump failed to start upon B side SIAS

! Task actuation. Directs manual start of 2B HPSI pump.

I:-

I I I -~

,,!I I

Recognize 2A HPSI pump low amps. Direct stopping 2A HPSI I

pump. Direct BOP to notify SNPO to investigate 2A HPSI I,i pump.

Ij ,

I

,~......

. - i I i Direct venting 2A HPSI pump

~ - _. _... --- --. ii I

f---~

I I

~-~--_j__i- - - - - - - - - - - - - - - - - - - - - - - - - - - - i i r--'~

i I Direct starting the 2A HPSI pump when venting complete complet~~

I Critical I

~ _______ ~

Critical I __ !ask Task 1 I Direct MSIS blocked when block permissive received at 685

_ psia.(must be done before MSIS occurs at 600 psia)

___ ._.___________.____l ..___.._______ ~. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _---'

i 55

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

REVISION NO.: PROCEDURE TITLE: PAGE:

36A APPENDICES I FIGURES I TABLES I DATA 119 of 156 PROCEDURE NO. SHEETS 2-EOP-99 ST. LUCIE UNIT 2 FIGURE 1A RCS PRESSURE TEMPERATURE (Page 1 of 1) 1)

(Containment Temperature Less Than or Equal to 200°F)

CAUTION The RCP NPSH curve assumes one pump is operating in each loop. RCP instrumentation should be monitored for seal and pump performance in accordance with 2-EOP-99, Table 13.

"00 I[O_*I'"--'*~:"::*=~=-~

OII"""*" ..*~:..:':-==-~f -:J~---

.... IAny I,*,,*t$l£ln k>

10 1/"0'$ t.(l1:;tK)n ot it1r$ t,.(j1:tt>n ~ tn~

t:n~ DfCC.ol'OI.Io ~h41l y\l7>'1'r ylll>tr thothe 1-001-'< INly rc'l'lW,lon pt'CCiH!UO )h41l VIII!dty VIII!d:tyol01 tre

~ OPl'"lolYr OPl'"IIlror A,d and 11 cfl~nQrC~

C/1<l'noo 'M~I" J)OCI;!s:>ary.

r.c.;;u~ry, MI:#y noUy!he the EOPC'..QOI"OlI"\i()tOl)

EOPf'"QOI"(lll"\(ltOlJ 2200 Acceplable Acceptable 2000 " "'00- ".~. .

1800 Maximum

( ..g'"

/: I Suixooled' .,.

Su!)cooled' ',.

1600

~

1400

~

l' 1!

CL (l.

vl;':J CL

~~

l' 1!

(l.

1Z00 I

I if

.1 I

I I

f \

\

\\

II

'!; 1I

~ 1000 I \

I MInimum E

I Subcooled' I

I 800 600 I RCP NPSH I

Reqwremenl" "-

ReqUlremenl' ""'- I I

600 ~,

~'- , ~.

I*

I

", ~/...

I 400 :---------_

!n~tT1Jmen1 Unctirt<unhes

~Includes lm,tnJmen1 UncertaH,j~'S 200 Shutdown Envelop.;- EnveloPl' ~

a0

-/

-:/

a0 100 lOa 200 300 400 500 600 700 600 800 Indicaled RCS Temperalure Indicated Tempe, ature (F) I-V-'~'J I<

1-'"<;<-'I'v'J :}~'.~I.~

".>~q.;':1 Mk"" :-".

--3 1l~,Jf"" :.~",

RCS Pressure Range Required QSPDS Subcooled Margin Reading (Rep CET) 2250 psi a to 1000 psia 40 to 180°F 1000 psia to 500 psia psi a 50 to 170°F Less than 500 psia 80 to 160°F 56

Appendix D Operator Action Form ES-D-2 Op Test No.' No.: 1 Scenario # 3 Event # _6""'.;.07'.;.08;.....:. '

_6_."-'7.'-8 _9___ Page 1Z-

_17_ of _1_9_.."

_1_9_-i1 Event

Description:

2-EOP-04 Steam Generator Tube Rupture. SIAS B side does not actuate. 2B HPSI pump does not start. 2A HPSI pump becomes air bound. 2B MSIV does not close from the control room. Isolate the 2B SG.

Time JII Position II~ Applicant's Actions or Behavior I Booth Operator Instructions:

I Ii Indications Available:

SRO

! Directs BOP to isolate 28 2B Steam Generator when Thot is Critical oF lAW 2-EOP~99,

<510

<510°F 2-EOP-99, Appendix R (attached page_58-60_) page_58~60_)

Task Critical 2~EOP-99 Appendix I, MSIV local

. Direct performance of 2-EOP-99 Ii Task !. closure, to close HCV~08-1 HCV-08-1 B, 8, 2B 28 MSIV (attached page_62_)

. i

,I I

I i

i!I

( I I:I I

I

~-.-~- - _--- 1---_

----- -__.- ..._----- 1---_...

i .._---_.

1-- -_.--- -----

i I

I r-'

I ,

I I

i I i I

I I

I i; I I

I II !

I 57

REVISION NO.: PROCEDURE TITLE: PAGE:

36A APPENDICES I/ FIGURES I/ TABLES I/ DATA 93 of 156 PROCEDURE NO.: NO .. SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX R STEAM GENERATOR ISOLATION (Page 4 of 6)

Section 2: 2B Steam Generator Isolation CAUTION If S/G isolation is due to a SGTR the secondary plant may have higher than normal radiation levels. Contact Health Physics for area accessibility instructions.

oD 1. ENSURE ENSU RE HCV-08-1 B, Main Steam Header 'B' Isolation Valve (MSIV), is CLOSED.

oD 2. !f if HCV-08-1 B did not close remotely, Then PERFORM local closure.

REFER TO Appendix I, MSIV Local Closure.

oD 3. ENSURE MV-08-1 B, MSIV Header 'B' Bypass Valve, is CLOSED.

( NOTE Instrument air must be available to close MFIVs using RTGB control switch.

If instrument air is NOT available when MFIV closure is required, then manual initiation of MSIS should be considered.

o D 4. ENSURE HCV-09-2A, Main Feedwater Header 'B' Isolation Valve, is CLOSED.

oD 5. ENSURE HCV-09-2B, Main Feedwater Header 'B' Isolation Valve, is CLOSED.

oD 6. !f BOTH HCV-09-2A and HCV-09-2B, Main Feedwater Isolation Valves to S/G if 2B, are NOT CLOSED or suspected of leaking, Then PERFORM ANY of the following AS NECESSARY:

oD A. ENSURE ALL of the following valves are CLOSED:

o MV-09-6, Stm Gen 2B Reg Block Valve D

oD LCV-9006, 2B 15% Bypass o

D MV-09-4, 2B 100% Bypass o

D B. STOP BOTH Main Feedwater Pumps.

oD 7. ENSURE FCV-23-5, 2B SG Blowdown, is CLOSED.

58

REVISION NO NO.: PROCEDURE TITLE: PAGE: - .'

( 36A APPENDICES I FIGURES I TABLES I DATA

,94 of 156 PROCEDURE NO.: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX R STEAM GENERATOR ISOLATION (Page 5 of 6)

Section 2: 2B Steam Generator Isolation (continued) o 8. ENSURE FCV-23-6, 2B SG Blowdown, is CLOSED.

o MV-08-19B, 2B S/G Atmos Dump Vlv, is CLOSED.

9. ENSURE MV-OB-19B, o 10.CLOSE MV-08-17, 2B S/G ADV Isol.

o 11. PLACE the control switch for auxiliary feed, Pump 2B, in STOP.

o 12.ENSURE

12. ENSURE MV-09-10, Pump 2B Disch to SG 2B Valve, is CLOSED.

o 13.ENSURE MV-09-12, Pump 2C to SG 2B, is CLOSED.

o 14.PLACE

14. PLACE MV-08-12, SG 2B Stm to AFW PP 2C, in CLOSE.

{ o MV-08-18B, 2B S/G Atmos Dump Vlv, is CLOSED.

15. ENSURE MV-OB-1BB, 1S.ENSURE o 16.CLOSE MV-08-16, 2B S/G ADV Isol.

o 17. PERFORM the following LOCAL operations:

o A. UNLOCK and CLOSE V09158, V0915B, 2C AFW Pump to 2B S/G Isolation.

o B. UNLOCK and CLOSE V09136, 2B AFW Pump to 2B S/G Isolation.

o C. CLOSE SE-08-1, Main Steam to 2C AFW Pump Warm-up Valve Solenoid.

o D. If SE-08-1,

!f Main Steam to 2C AFW Pump Warm-up Valve Solenoid is NOT CLOSED or suspected of leaking, Then CLOSE V08883, SE-08-1 Inlet Isolation.

(continued on next page) 59

REVISION NO.:

NO .. PROCEDURE TITLE: PAGE:

PAGE 36A APPENDICES I/ FIGURES I/ TABLES I/ DATA 95 of 156 PROCEDURE NO.:NO .. SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX R STEAM GENERATOR ISOLATION (Page 6 of 6)

Section 2: 28 Steam Generator Isolation (continued) 17 17.. (continued) o E. !f MV-08-12, S/G 2B Steam to AFW Pump 2C, is NOT CLOSED or suspected of leaking, Then PERFORM ANY of the following AS NECESSARY:

o 1. Locally CLOSE MV-08-12 using the handwheel.

D o 2. ISOLATE steam to 2C AFW Pump as follows:

D o a. CLOSE MV-08-3, 2C Pump.

D o b. Locally CLOSE the following valves:

o V08622, CB #67 Drain

( o V08618, Drain off MV-08-3 Isol o V08619, Drain off MV-08-3 Isol Iso!

End of Section 2 END OF APPENDIX R

(

60

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

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # ~6.:.:...7:..;.

6,7,8, 8;;.:.,. ..;;,9 9_ _ _ Page 1L

_19_ of _1..;.,9

_19_-1 __ 1 1

Event

Description:

2-EOP-04 Steam Generator Tube Rupture. SIAS 8 B side does not actuate. 28 2B HPSI pump does not start. 2A HPSI pump becomes air bound. 28 2B MSIV does il not close from the control room. Isolate the 28 2B SG.

Ii

!F, =-=Ti-m~e=-~II~~p~o~si~tio-n--~i--=----=-=---=~A~ppll~ic=an~t'~s~A-ct~io-n~s-or~8~e~h-av~io-r----==--==--==91 Time J Position Applicant's Actions or Behavior

. Booth Operator Instructions:

- .--.-~-

Indications Available:

RO Stop one RCP in each Loop when directed

~----~ ._---- .-~ .. ---~.

Monitor RCP's for operating limits lAW Table 13 (attached page_52_)

page_ 52-)

~--*~-t --+--

I

I 1

Cooldown the RCS to <510°F T hol hot using S8CS, SBCS, in manual, not I

to exceed 100°F in anyone hour period. I i -----,

I

'-'-'---'--~

I I When directed, depressurize the RCS lAW step 11 EOP-04.

i

( 1 Examiners Note: Use of Main or Auxiliary spray is acceptable.

Within Figure 1A 1A (attached page_56_)

i I I * <930 psia psi a

- Above RCP minimum pressure

- Approx. Equal to 2A SG pressure (within 50 psia) I I I 1f-*--"

.... ----- '------+-------------------- Suggested termination pOint: point: 1 I

- 28 2B HPSI is started and 2A HPSI is vented and running I

- 2B SG is isolated lAW Appendix R i

I I ** 28 MSIV is closed 2B j I

I j ** ..'._-. - ------------------------------~

i

~-------~--------------------------------

i I

(

61

REVISION NO.: PROCEDURE TITLE: PAGE:

36A APPENDICES / FIGURES / TABLES I/ DATA 61 of 156 PROCEDURE NO.: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX I MSIV LOCAL CLOSURE of 1)

(Page 1 of1) o 1. To locally CLOSE HCV-08-1A, 2A S/G MSIV, PERFORM the following:

o A. CLOSE V181197, Inst Air to 2A MSIV - Air Accum & & HCV-08-1A Isol.

(Inside Steam Trestle just North of 2A MSIV) o B. CLOSE local instrument valve for PS-08-12A.

(Inside Steam Trestle just North of 2A MSIV) o C. REMOVE T-Handle swaglockswag lock cap from PS-08-12A test connection.

(Inside Steam Trestle just North of 2A MSIV)

CAUTION Loud noise and air blowing when venting; stay clear of vent path. I o D. OPEN PS-08-12A local instrument valve to bleed air from system through the connection, test connection.

(

o 2. To locally CLOSE HCV-08-1 B, 2B S/G MSIV, PERFORM the following:

o A. CLOSE V181195, Inst Air to 2B MSIV - Air Accum & HCV-08-1 B Isol.

(Inside West of Steam Trestle door entrance) o B. CLOSE V08423, PS-08-12B Isol.

(Inside West of Steam Trestle door entrance) o C. REMOVE T-handle swaglock T -handle swag lock cap from PS-08-12B test connection.

(Inside Steam Trestle just South of 2B MSIV) o D. OPEN V08423, PS-08-12B Isol to bleed air from system through the test connection, connection.

END OF APPENDIX I

~

0 w

~----------------------------------------------------------~ ~~

OJ

~------------------------------------------------------------~

62

Appendix D Scenario Outline Form ES-D-1 Facility: St. Lucie Scenario No.: 5 Op Test No.: HLC-19 NRC Examiners: Operators: SRO:

RO:

BOP:

Initial Conditions: IC-14, 30% power, MOL. 6 gpm dilution to compensate for Xenon. 2B Main Feedwater pump is out of service to replace the oil cooler. 2C Charging pump is out of service for repack.

Turnover: Crew is to perform an up power to 45% power. 2B Main Feedwater pump is out of service to replace the oil cooler. Not expected back this shift. 2C Charging pump is out of service for repack. Chemistry limits have been cleared to perform an up power within the capacity of the operating Main Feedwater pump.

Critical Tasks:

Close 2A Diesel output breaker

Crosstie 2A AFW pump to feed 2B SG ,

Event Malf. Event Event No. No. Type* Description 1 R/RO Power increase to approximately 45%.

N/BOP

(

2 1 C/RO Loss of 2B Component Cooling Water Pump T.S, SRO T.S.

3 2 II RO Selected Pressurizer Level Channel LT 111 OX fails high 1----.

~-

4 3 1.S, T.S. SRO PORV 1474 Acoustic Monitor fails f- ---- ---

5 4 C/BOP Loss of Sups Vital AC Bus Inverter. Stabilize the plant after C/RO alternate source has energized the Vital AC bus.

6 5 M I All LOOP I Loss of Feedwater 7 6 C/BOP 2B Diesel does not start, start. 2A Diesel output breaker does not close 8 7 CI BOP C/BOP 2C AFW pump trips and MV-09-9 2A AFW pump to 2A SG fails to open 9 8 C/BOP Crosstie 2A AFW pump to feed 2B Steam Generator

~,

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1

Scenario Event Description NRC Scenario 5 st. Lucie The unit will be turned over to the crew at 30% power. The 2B Main Feedwater Pump is out of service to replace the oil cooler. The crew will increase power to approximately 45%.

A loss of the 2B Component Cooling water pump will require the crew to swap the AB electrical to the B T.S. credit for the 2C Component Cooling water pump, side to take T,S. pump.

Selected Pressurizer Level LT 1110X 111 OX fails high requiring the RO to swap level channels.

channels, Acoustic monitor for PORV 1474 will annunciate and fail high. The crew will determine this failure is only instrument failure and not a leaking PORV,PORV. The SRO is to evaluate T.S,T.S. for accident monitoring, monitoring.

A loss of the 2A Sups Vital bus inverter will occur during the up power. Numerous secondary alarms and loss of instrumentation will occur. The alternate dump valves on the heaters will open in addition to loss of DEH turbine control. The Vital bus can be re-energized from the alternate source. Plant stabilization will be required due to secondary perturbation.

perturbation, A LOOP combined with a loss of feedwater will occur. The 2B Diesel will not start and the 2A Diesel output breaker will not close. The output breaker can be closed from the RTGB, RTGB. The 2C AFW pump will trip on AFAS or manual start and cannot be restarted. The 2A AFW pump MV-09-9, 2A AFW pump to 2A will not open. The crew is expected to crosstie the 2A AFW pump to feed the 2B SG.

SG, Will The Crew will probably enter 2-EOP-09. LOOP, LOFC prior to entering 2-EOP-06 due to AFAS-2 actuating approximately 15 minutes after the trip and AFAS-1 actuating approximately 20 minutes after trip, the trip.

(

2-EOP-06 Total Loss of Feedwater will be entered, entered. The scenario can be terminated when the crew has closed the 2A Diesel output breaker and the 2B SG is being fed by the 2A AFW pump, pump.

Procedures Used

2-GOP-201, Reactor Plant Startup - Mode 2 to Mode 1

2-GOP-1 01, Reactor Operating Guidelines During Steady State and Scheduled Load Changes

2-GOP-502, Data Sheets Required for Heatup

2-0NP-49,01,, SUPS - NON - Safety Vital AC ISFSI Security or Fire and Security Inverter 2-0NP-4901 Malfunction

2-0310030, Component Cooling Water - Off- Normal Operation

2-NOP-52,02 Alignment Of 2AB Buses And Components 2-NOP-52.02

2-0120035, Pressurizer Pressure and Level

2-EOP-01, Standard Post Trip Actions

2-EOP-06, Total Loss of Feedwater

2-0NP-09,02, 2-0NP-09.02, Auxiliary Feedwater Technical Specifications Entered

3.7.3 Component Cooling Water System 3.7,3

3.3.3.6 3,3,3,6 Accident Monitoring 2

Appendix D Operator Action Form ES-D-2 Op Test No No.: 1 Scenario # 5 Event #

Page 3 of 19 Event

Description:

Description' Power increase to approximately 45%.

Time II Position II Applicant's Actions or Behavior I Booth Operator Instructions: Initiate Ie #14 30% power. Xenon building in, 6 gpm dilution rate. MOL. 2C Charging Pump OOS for i repack. 28 MFW Pump OOS to repair oil cooler.

I Indications NOTE: Inform the crew 2-GOP-201 step 6.1.26 has been signed off by

_ NOTE: Inform l Indications the crew 2*GOP*201 step 6.1.26 has been signed off by RE and power ascension is approved.

ii Direct power increase lAW 2-GOP-201 step 6.128 (attached SRO II I page_4_)

I

!i Directs Placing MSRs in service - 300 MW per 2-GOP-S02, 2-GOP-502, Data Sheets Required For Heatup, Appendix - AA (attached page _ S-8 _) as directed.

page_S-8_)

I

!, I I

C" l I I

f----

I!

Directs Control of Rx power and ASI lAW 2-GOP-101 Operating Guidelines step 6.1 (attached, page_9_)

2-GOP-1 01 Rx I

i Commences dilution for power increase lAW 2-NOP-02.24 step

( I RO 6.S (attached page_11-13_)

I Ii

!I Withdraws CEA's to control Rx power and ASI ASIIAW 2-GOP-101 lAW 2-GOP-1 01

Rx Operating Guidelines step 6.1 (attached, page_9_ )

I Ii iI

CEA Withdrawal, select MS on the CEDMCS Control Switch II II:

Move the IN/HOLD/OUT Switch to the OUT I

direction I

Programs DEH for power increase at a rate lAW 2-GOP-101 step 6.1.2.D 6.1.2.0 Category 4. (attached page_9_)

I

Set reference by ensuring REF selected and then I BOP depress desired MW endpoint, select ENTER I

Depress LOAD RATE type in desired load rate and I select ENTER

~

iI

Depress GO pushbutton I I

, >-- - - - - - - - - - - - - - j - - - - - - - - - - - - - - - - - - - - - - - - - - - - j Places MSRs in service - 300 MW per 2-GOP-S02, Data I

Sheets Required For Heatup, Appendix - AA as directed.

I (attached page_S-8_)

page_S-B_)

i I

(

3

REVISION NO PROCEDURE TITLE PAGE:

PAGE 60 REACTOR PLANT STARTUP - MODE 2 TO MODE 1 f - - - -........- - - - I f---......;;..~---t 51 of 69 PROCEDURE NO .

2-GOP-201 ST. LUCIE UNIT 2 6.125 (continued) INITIAL

6. if Exhaust Hood temperatures are less than 150°F (TR-22-6B points 3,7,8 and 10), Then:

A. CLOSE V12396, 2A LP Turb Spray Hdr TCV-22-61A Bypass.

B. CLOSE V12403, 2B LP Turb Spray Hdr TCV-22-61 B Bypass.

6.126 When Turbine load is approximately 250 MW, Then VERIFY that secondary chemistry values are less than the minor inleakage limits of ONOP 2-0610030, Secondary Chemistry - Off Normal.

CHEM NOTE Based on JPN Engineering Evaluation, the RE Supervisor, may recommend to Operations that any or all of the 30% Reactor Power level surveillance may be performed at 45% following a power ascension that was NOT as a result of a refueling refuelin9. outage.

(

6.127 ~'O

~'0 if required, Then prior to Reactor Power reaching 30% as indicated on the highest reading instrument, PERFORM the following:

1. STOP the power ascension.

2. NOTIFY SCE or I&C to perform DCS Steam Generator 2-NOP-102.01.

Feedwater Discharge Coefficients Verification per 2-NOP-1 02.01. _ __

SCE II&C

3. 2-0SP-69.01,, Nuclear I Delta T Power Calibration.

PERFORM 2-0SP-6901

4. ENSURE scheduled incore surveillance have been performed.

5. ENSURE the Incore Detection System is OPERABLE in accordance with OSP-64.01.

OSP-6401 , Reactor Engineering Periodic Tests, Checks and Calibrations.

NOTE The power ascension may continue while the MSRs are being placed in service.

6.128 6,128 When Turbine load is approximately 300 MW, Then PERFORM Appendix AA of 2-GOP-502, Placing MSRs In Service.

4

(

4

REVISION NO PROCEDURE TITLE PAGE 51A DATA SHEETS REQUIRED FOR HEATUP 1240f127 PROCEDURE NO 2-GOP*502 ST. LUCIE UNIT 2 APPENDIX AA PLACING MSRs IN SERVICE (Page 1 of 4)

INITIAL Date __1/__1 -

- - - -/- -

1. DEPRESS the Reset pushbutton on the Reheater Control System

2. follows VERIFY locally the MSR TCVs are positioned as follows:

COMPONENT DESCRIPTION POSITION INITIAL TCV-OS-1 TCV-08-i MS to 2A MSR CLOSED TCV-OS*7 TCV-08*7 MS to 2A MSR CLOSED TCV-08*3 TCV*08-3 MS to 2B MSR CLOSED TCV*OS*9 TCV*08*9 MS to 2B MSR CLOSED TCV*OB-4 TCV*08-4 MS to 2C MSR CLOSED TCV*OS-10 TCV-08-i0 MS to 2C MSR CLOSED TCV-OS-2 TCV-08-2 MS to 20 MSR CLOSED TCV*OS*S TCV-08-8 MS to 20 MSR CLOSED

(

NOTE A large steam demand may occur while opening the MSR Block Valves.

The MSR Block Valves should be opened one at a time. allowing time for the RCS to stabilize.

3. POSITION the MSR Block Valves as follows COMPONENT DESCRIPTION POSITION INITIAL MV-OB-4 MV-08-4 2A Block TCV OPEN MV-08-6 20 Block TCV OPEN MV-OS-8 MV-08-8 2B Block TCV OPEN MV-08-10 MV-08*10 2C Block TCV OPEN 5

5

REVISION NO PROCEDURE TITLE PAGE 51A DATA SHEETS REQUIRED FOR HEATUP 1250f127 PROCEDURE NO 2-GOP-502 ST.

ST LUCIE UNIT 2 APPENDIX AA PLACING MSRs IN SERVICE (Page 2 of 4)

INITIAL NOTE t!Q.I£ Quench water to the MSRs will be supplied immediately upon opening the MSR Block Valves.

4, When the MSR Block Valves are open, Then THROTILE OPEN the following components to adjust MSR subcooling flow to app 5 to 7 gpm on applicable indicator:

COMPONENT DESCRIPTION INDICATOR INITIAL V09322 SE-09-1A 2A, MSR Subcooling Subcoolmg =

FI-09-4A = 5 Dwnstrm Isol 1501 to 7 gpm V09319 SE-09-1 SE*09*1 B 282B MSR, Subcooling FI*09-48 = 5 FI-09-4B::

Dwnstrm Isol to 7 gpm V09328 V0932B SE-09*1C 2C MSR, Subcooling SE-09-1C =

FI-09-4C :: 5 Dwnstrm Isol 1501 to 7 gpm V09325 SE-09-1 D 20 SE-09-1D 2D MSR, Subcooling FI-09-4D :::

=5 Dwnstrm Isol 1501 to 7 gpm NOTE

When the MSR TCVs have started the warm up period by either automatic or manual control, the Turbine startup should continue.

If the wrong pushbutton is depressed, the controller can be reset by depressing the Reset pushbutton.

Ramp starts a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months timed opening of TCV-08-7, 8, 9 and 10 (small TCVs). This IS TCVs) is followed by a 30 minute time delay and then a 10 minute timed opening of TCV-08-1, TCV-OB-1, 2, 3 and 4 (large TCVs). Total time is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 40 minutes until TCV-08*1, TCV-OB-1, 2, 3 and 4 indicate open.

open 5, if11 automatic startup ISis desired, Then DEPRESS the Ramp pushbutton.

pushbutton 6

6

- - - - - - - - - - --------_._-_.-._-----~------ ---

REVISION NO REVISION NO PROCEDURE PROCEDURE TITLE TiTLE PAGE:

PAGE 51A DATA SHEETS REQUIRED FOR HEATUP 126 of 127 1260f127 PROCEDURE NO 2-GOP~502 2-GOP-502 S1. LUCIE UNIT 2 ST.

APPENDIX AA PLACING MSRs IN SERVICE (Page 3 of 4)

INITIAL CAUTION If the manual valve positioner is NOT on zero before pushing the Manual Valve Position pushbutton, the TCVs will OPEN to a position relative to the manual valve positioner setpoint and possibly damage the MSRs from the resultant thermal stresses.

6. lf manual startup is desired, Then PERFORM the following:

A. ENSURE the manual valve positioner posItioner IS on zero.

zero B. DEPRESS the Manual Valve Position pushbutton.

pushbutton C. Slowly OPEN the TCVs by rotating the manual valve positioner. positioner Manual opening of the MSR TCVs should take approximately hours 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . -

( - -- -

7. After the MSR TCVs are OPEN, Then PERFORM the following: following' A. POSITION the small TCV Isolation isolation valves as follows follows:

COMPONENT DESCRIPTION POSITION INITIAL V08381 TCV~08~7 Isol TCV*08-7 CLOSED V08370 TCV~08-7 Isol TCV-08-7Isol CLOSED V08378 TCV-08~8 Dwnstm Isol TCV-08-8 CLOSED V08382 TCV~08-8 TCV-08-8 Upstrm Isol 1501 CLOSED V08383 TCV~08-9 TCV-08-S Isol1501 CLOSED V08372 TCV-08-9 TCV-08-S Isol1501 CLOSED V08375 TCV-08-10 Isol CLOSED V08384 TCV-08-10 Isol 1501 CLOSED B. ALIGN the MSR vents to the 5A and 58 Feedwater Heaters as follows COMPONENT DESCRIPTION POSITION INITIAL V11446 2A MSR to Extr Stm Isol OPEN V11451 2B MSR To Extr Stm Iso 28 1501I OPEN V11117 2C MSR To Extr Stm Isol 1501 OPEN V11122 20 2D MSR To Extr Stm Isol OPEN 7

7

REVISION NO REVISION NO PROCEDURE TITLE PROCEOURE TITLE PAGE PAGE 51A DATA SHEETS REQUIRED FOR HEATUP NO 1270f127 PROCEDURE NO.

2-GOP-502 2*GOP-502 ST. LUCIE UNIT 2 APPENDIX AA PLACING MSRs IN SERVICE (Page 4 of 4)

7. (continued) INITIAL C. ALIGN the MSR vents to the Condenser as follows:

follows COMPONENT DESCRIPTION POSITION INITIAL V11508 28 Cndsr Vent From 2A MSR Isol CLOSED V11507 28 Cndsr Vent From 28 MSR Isol CLOSED V11520 2B Cndsr Vent From 2C MSR Isol CLOSED V11227 2A Cndsr From 20 MSR Tube CLOSED Bundle Vent Isol D. ALIGN the MSR Warm Up Valves as follows COMPONENT DESCRIPTION POSITION INITIAL MV-08-5 MV-08*5 Warmup 2A MSR CLOSED MV-08-7 MV*08*7 Warmup 20 2D MSR CLOSED MV*08-9 Warmup 2B MSR CLOSED MV-08-11 MV-08*11 Warmup 2C MSR CLOSED Reviewed by Date __

_1 1__1 1-SRO END OF APPENDIX AA 8

(

8

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

REVISION NO PROCEDURE TITLE TITLE PAGE 9B REACTOR OPERATING GUIDELINES DURING STEADY 6 of 15 PROCEDURE NO STATE AND SCHEDULED LOAD CHANGES 2-GOP-101 S1. LUCIE UNIT 2 ST.

6.0 INSTRUCTIONS 6.1 Power Level Escalations NOTE CEAs should be above the Long-term Steady State Insertion Limit (102 inches withdrawn on Group 5) before reaching 20% core power and at a position to begin controlling ASI at the ESI between 20% and 50% power. power Refer to NOP-1 00.02, Axial Shape Index Control, for further guidance.

guidance,

1. As Main Generator loading commences, MAINTAIN T-avg at T-ref by by:

A. CEA withdrawal in Manual Sequential.

ANDfOR B. Boron concentration changes in accordance with 2-NOP-02.24, Boron Concentration Control.

2. At or above 50% power

( A_

A. All planned reactivity additions should be made by boration or dilution 2-NOP-02.24, Boron Concentration Control In accordance with 2-NOP-02.24. Control.

B. USE CEAs for ASI control, CONSIDER the reactivity effect of CEAs when adjusting AS!.

C. REFER to NOP-1 00.02, 00,02, Axial Shape Index Control, for specific instructions regarding ASI control during power escalations_

escalations.

D. ,-j,

~, When raising Reactor power, all power escalation rates should be within the following fuel preconditioning guidelines:

Max Equivalent Turbine Category Max Core Power Escalation Rate 1-------

1----------

Generator Load Rate 1 3%IHR at or above 15% Power 3%/HR MWIMIN

.42 MW/MIN I

e 2 3%IHR above 50% Power 3%/HR .42 MWfMIN ii

[ 3 20%fHR 20%/HR above 50% Power MWIMIN 280 MW/MIN I 4 30%/HR above 50% Power MWIMIN 4.2 MW/MIN 9

9

~~----------- -._-------_._----- ._--

REVISION NO PROCEDURE TITLE TITLE: PAGE 98 REACTOR OPERATING GUIDELINES DURING STEADY I-P-RO-C-E-OU-R"';'E"';"NO~---I i-P-RO-C-E-D-UR-E-N-O---; STATE AND SCHEDULED LOAD CHANGES 7 of 15 2-GOP-101 ST. LUCIE UNIT 2 6.1 Power Level Escalations (continued)

2. D. (continued)

NOTE To determine the correct category for a power escalation, Appendix B, 8, Fuel Preconditioning Guidelines Worksheet, may be used. Contact Reactor Engineering if further assistance is required.

Category Definitions:

1. Category 1:

a. INCREASE in power to a level which has not been previously sustained in this core cycle for at least 72 continuous hours.

2. Category 2:

a. INCREASE in power following 30 continuous days or more at a power level less than 70% of rated thermal power_

power.

( OR

b. INCREASE in power to a level which has not been maintained for more than 3 continuous hours during the past 60 days.

3. Category 3: 3

a. INCREASE in power to a level which has not been maintained for 3 continuous hours or more during the past 8 days.

4. Category 4: 4

a. INCREASE in power to a level which has been maintained for 3 continuous hours or more during the past 8 days.

3. If11 available, Then ENSURE two Charging Pumps are operating.

If necessary, START an additional Charging Pump in accordance with 2-NOP-02.02, Charging and Letdown.

2-NOP-0202,

4. PLACE the Pressurizer on recirculation in accordance with Appendix A, Pressurizer Recirculation Guidelines.

5. CONTINUE to load the Main Generator in accordance with 2-GOP-201, Reactor Plant Startup, Mode 2 to Mode 1.

END OF SECTION 6.1 10

(

10

REVISION NO TITLE.

PROCEDURE TITLE: PAGE.

PAGE:

24A BORON CONCENTRATION CONTROL 19 of 75 PROCEDURE NO 2-NOP-0224 ST. LUCIE UNIT 2 6.5 Aligning for MANUAL Dilution NOTE

An Operator Aid has been placed at RTGB-205 PNL "N". Any revision to this section of the procedure shall verify the validity of the Operator Aid and, if changes are necessary, a Label Request shall be initiated to Incorporate these changes on a new Operator Aid placard.

The Operations Supervisor SHALL be notified and a CR submitted of any unexplained or unplanned Reactivity change in accordance with OPS Policy 534 (i.e.,

(ie., >.5

> 5 deg Tcold change or >.5%

>5% power change).

If a Reactivity management issue occurs, refer to procedure ADM-09.11, Reactivity Management.

If constant dilution is desired then ensure flow on FIC-2210X is observable.

observable

Engineering Assessment of FIC-2210X PMW Flow, shows that there could be an error up to -+/- 0 0.55 gpm, and the recommended minimum flow rate is 2 gpm

1. o 0 0 0 ENSURE Section 3.0, Prerequisites is completed at least once 0000

( per shift.

2. 0000 0 0 0 0 ENSURE Section 4.0, 40, Precautions / Limitations, has been reviewed at least once per shift shift.

3. 0000 0 0 0 0 ~2 ENSURE calorimetric power is less than 100.00% prior to any dilutions by obtaining a DCS calorimetric power.

power

4. 0000 0 0 0 0 DETERMINE the desired volume of primary water to be added. added

5. 0000 0 000 PLACE the Makeup Mode Selector switch in MANUAl. MANUAL.

6. 0000 ENSURE FIC-2210X, PMW Flow, is in MANUAL and REDUCE the controller output to ZERO ZERO.

7. 0000 ENSURE FIC-2210Y, Boric Acid Flow is in MANUAL and REDUCE the controller output to ZERO.

8. 0000 ENSURE either Primary Makeup Water Pump is running.

9. 0000 PLACE FCV-2210X, FCV-221 OX, Primary Makeup Water Control Switch in Auto.

10. 0000 11 Lf diluting to the VCT, Then OPEN V-2512, Reactor Makeup Water Stop Vlv.

0 33 N

tv

>>p

11. 0000 11 Lf diluting to the Charging Pump suction, Then OPEN V-2525, ::0 Boron Load Control Valve.

Valve N

33

...N

>>P 11

(

REVISION NO PROCEDURE TITLE PAGE:

PAGE 24A BORON CONCENTRATION CONTROL 20 of 75 PROCEDURE NO 2-NOP-02.24 ST. LUCIE UNIT 2 6.5 Aligning for MANUAL Dilution (continued)

CAUTION To preclude lifting the VCT relief valve while using V-2525, do NOT allow PMW flowrate to exceed the running Charging pump(s) capacity. capacity

12. DODD ADJUST FIC-2210X PMW Flow in AUTO or MANUAL to desired flowrate (and if using V-2525 do NOT exceed the flowrate for the number of running Charging Pumps). Pumps)

13. DODD MAINTAIN VCT pressure less than or equal to 30 psig by opening and closing V2513, VCT Vent, as needed.

14.

14, 0DODD 0 0 0 if11 necessary to maintain the desired VCT level, Then DIVERT the letdown flow to the Waste Management System by placing V2500, VCT Divert Valve, in the WMS position position:

A. DODD DO 0 0 ENSURE V2500 VCT Divert Valve indicates OPEN.

B.

8, 0DODD 0 0 0 When the desired VCT level is reached, PLACE V2500 in AUTO.

(

C. 0DODD 0 0 0 ENSURE V2500 indicates CLOSED.

15. 0DODD 0 0 0 When the desired amount of primary water has been added. added, Then CLOSE FCV-221 OX, Primary Makeup Water.

16. 0 0 0 if 0DODD 11 V-2512 Reactor Makeup Water Stop Vlv was opened, Then PLACE V*2512 V-2512 in CLOSE and ENSURE it indicates CLOSED.

17. 0DODD 0 0 0 if11 V-2525 V*2525 Boron Load Control Valve was opened, Then PLACE V-2525 in CLOSE and ENSURE it indicates CLOSED.

18. 0DODD 0 0 0 ENSURE FIC-2210X, PMW Flow controller is in MANUAL and RECUCE output to MINIMUM.

MINIMUM

19. 0DODD 0 0 0 MONITOR for any abnormal change in Tave Tav8 20,

20. 0DODD 0 0 0 §1 §, RECORD on Data Sheet 1, Boration I/ Dilution Log, the number of gallons of Primary Makeup Water added as indicated on FQI-2210X, PMW Flow Totalizer.

21. 0DODD 0 0 0 if11 additional dilutions are desired, or if the expected changes to Tave Tav8 or Boron concentration are NOT achieved, Then REPEAT Steps 6.5 6.5.11 through 6.5 6.5.20.

20.

\

/

0 N

l>

12

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

REVISION NO PROCEDURE TITLE PAGE:

PAGE 24A BORON CONCENTRATION CONTROL 210f75 21 of 75 PROCEDURE NO 2-NOP-02.24 2-NOP-0224 ST. LUCIE UNIT 2 6.5 Aligning for MANUAL Dilution (continued)

22. 0 0 0 0 11 it is desired to restore the Boron Concentration Control system to the Automatic Mode of Operation, Then REFER to Section 6.1, Aligning for Automatic VCT Makeup.

23. After review by the Unit Supervisor is complete, this document may be discarded.

END OF SECTION 6.5

(

13

Appendix D Operator Action Form ES-D-2 Op Test No.: No. 1 Scenario # 5 Event # _22_ _ _ _ _ Page

.L-4 of _119 9~1

-~-II Event

Description:

Description Loss of 28 Component Cooling Water Pump Time III Position II Applicant's Actions or Behavior Booth Operator Instructions: When directed by examiner, trigger Loss of 2B CCW pump.

Trigger AB Battery Charger when requested by Control Room.

1------

)-- ,~----

Indications Available: Increasing amps on 2B CCW pump.

II Alarms: S-2: 2B CCW Hdr Flow High/Low

S-32

2B CCW PUMP OVRLD/ TRIP, alarms and will clear after pump trip.

Ii S-26: 2C CCW PUMP HDR VALVES/AB BUS MISALIGNMENT, while I

iI alignin~ 2C pump.

i

!i iI SRO/ROI Recognize loss of 2B 28 CCW pump.

I i BOP ii I

~

I I

~ Enters T.S. 3.7.3. (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action to restore 2 CCW pumps, 2 I iI TS I I hours to ensure valve lineup commensurate with electrical II , SRO I I~ lineup) i i I

~- --_._-_._-_ ... _ - - - - i '---------------------------j

( NOTE SRO May elect to hold power increase.

r---'-- -- ".--'

~'--------- -

, II Enters 2-0310030 and directs lineup of 2C CCW pump to I I replace 2B CCW pump per step 6.2.3.B 1 & 2 (attached I i page_

page_15_)15-)

!i ii I i Directs swapping of 2AB bus to the B side per step 6.2.3.B.4 i thru 2-NOP-52.02, Alignment Of 2AB Buses And Components, I

!! step 4.1.4 A thru C (attached page_17 _for 4.16KV bus only) I

, i I

~.-.----~

!,i

,i Directs starting the 2C CCW pump per step 6.2.3.B.5 (attached II

~--

1,i page_ 16-)

page_16_) Ii o-----~ _ _ . ____ .. _ _ _ _ _ Ii i

I! Directs placing 2B CCW pump to Pull To Lock positions per step Ii i

iI 6.2.3.8,7 6.2.3.8.7 (attached page_16_)

~--- -

14

REVISION NO REVISION NO PROCEDURE PROCEDURE TITLE TITLE PAGE:

PAGE.

37 COMPONENT COOLING WATER* WATER -

7 of 23 PROCEDURE NO OFF*NORMAL OFF-NORMAL OPERATION 2-0310030 ST. LUCIE UNIT 2 6.2 Subsequent Action (continued)

3. A. (conti nued)

(continued)

CAUTION If 2AB AC and DC Busses are not all completely powered from the A side, Then do NOT take Technical Specification Credit for the 2C CCW pump until alignment has been completed.

6. VERIFY the pressures and nows return to normal. normal

7. PLACE the 2A CCW pump control switch to the PULL TO LOCK position.

8. !!l.f the 480V Load Center 2AB and DC bus 2AB are NOT completely aligned to the A side, Then REALIGN the 480V Load Center 2AB and DC bus 2AB to the A side per 2-NOP-52.02, Alignment of 2AB Busses and Components. Components B.

S. Loss of the 2B CCW Pump.

( 1. ENSURE Closed. Closed:

MV-14-1, 2C CCW Pump Discharge to A Header AND

MV-14-3, 2C CCW Pump Suction from A Header

2. ENSURE Open: Open

MV-14-2, 2C CCW Pump Discharge to B Header AND

MV 4, 2C CCW Pump Suction from B Header MV-14-4,

3. 11!f SOC is in service and CCW is completely lost to an SOC Heat Exchanger, Then SOC flow must be terminated to the affected heat exchanger prior to restoring CCW noW. now. REFER to ONOP 2-0440030, Shutdown Cooling Off-Normal.

4. ~2 11If the 2C CCW Pump is NOT NOT electrically aligned to the B Electrical Bus AND the Unit is in Modes 1-4, Then REALIGN the 2AB 4.16KV Bus to the B Side per p;--

2-NOP-52.02 PRIOR to starting the 2C CCW Pump on the 28 26 CCW Header.

12 15

REVISION NO PROCEDURE PROCEOURE TITLE PAGE:

PAGE 37 COMPONENT COOLING WATER WATER--

8 of 23 PROCEDURE NO OFF-NORMAL OPERATION 2-0310030 ST, LUCIE UNIT 2 6.2 6,2 Subsequent Action (continued)

3. B. ((continued) continued)

5. START ST ART the 2C CCW Pump.

CAUTION Ifif 2AB AC and DC Busses are not all completely powered from the B side, Then do NOT take Technical Specification Credit for the 2C CCW pump until alignment has been complete.

6. VERIFY the pressures and flows return to normal.

7. PLACE the 2B CCW pump control switch in the PULL TO LOCK position.

8. ~2

,-]2 Ifif the 480V Load Center 2AB and DC bus 2AB are NOT completely aligned to the B side, Then REALIGN the 480V Load Center 2AB and DC bus 2AB to the B side per 2-NOP-52.02, 2-NOP-52 02, Alignment of 2AB Busses and Components, Components.

(

C. Loss of two (2) CCW Pumps CAUTION

REFER to off-normal operating procedure 2-0NP-2501 2-0NP-25,01,, Loss of RCB Cooling Fans, for appropriate direction.

direction

§,

§122 Sufficient Containment Fan Coolers (HVS-1 (HVS-1A, A, HVS-1 HVS-1B,B, HVS-1 HVS-1C Cor or HVS-1D)

HVS-1 D) are required to be in operation to maintain Containment air temperature less than or equal to 120°F. This is necessary to maintain the reactor vessel support structure within design basis.

Operator action is required within 45 minutes, to restore air temperature to less than or equal to 120°F or initiate reactor trip cooldown to at least Hot Shutdown.

1. ~3!f

~3 if the health and safety of the public is in jeopardy, Then ATTEMPT ONLY ONE restart.

16

~~- _---

~-

_ ..----~-------

REVISION NO REVISION NO PROCEDURE TITLE PROCEDURE TITLE PAGE' PAGE' 12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 12 of 37 PROCEDURE NO 2-NOP-5202 2-NOP*5202 ST LUCIE UNIT 2 4.1 Transfer of 2AB Buses and Components from A Side to B Side (continued)

NOTE While performing Section 4.1 Step 4, the following annunciators will be received

B-48,4 16KV SWGR 480V LC/MCC 2AB UV (RTGB 201)

B-48, 4.16KV

S-26, 2C CCW PUMP HDR VALVES/AB BUS MISALIGNMENT (RTGB 206)

4. ALIGN 4160V Bus 2AB to B side, as follows A.

A_ At RTGB 201, VERIFY the following tie breakers are OPEN. OPEN

Bkr 1-20501, 1AB 416 KV BUS SBO TIE Bkr1-20501,1AB416KVBUSSBOTIE

Bkr 2-20501, 2AB 416 KV BUS SBO TIE

( B. VERIFY the following pump control sWitches are in PULL-TO-LOCK PULl-TO-LOCK

Component Cooling Water Pump 2C (RTGB 206)

Intake Cooling Water Pump 2C (RTGB 202)

C. At RTGB 201, PERFORM the following (1) OPEN Bkr 2-20505.

2-20505, 4.16KV BUS TIE 2AB/2A3 (2) OPEN Bkr 2-20208, 4.16KV BUS TIE 2A3/2AB.

(3) 2-20409, 416KV CLOSE Bkr 2-20409,4 16KV BUS TIE 2B3/2AB 2B3/2AB.

(4) 2*20504,4 16KV BUS TIE 2AB/2B3.

CLOSE Bkr 2-20504.4

5. ALIGN 480V Load Center 2AB to B side, as follows A. REFER TO Technical Specifications SpeCifications 3.3 3.1 for the Plant Vent Stack Radiation Monitor.

B.

B_ running, THEN ALIGN charging IF Charging Pump 2C is running.

2*NOP*0202, pumps per 2-NOP-02 02, Charging and Letdown, to prepare for the loss of Charging Pump 2C 2C.

17

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

Appendix D Operator Action Form ES-D-2

( i~ Op Test No.:Test No 1 1 Scenario # 5 Event #

Event# _2~ _ _ _ _ Page

....;2~_ L-5 19 of _1,.;;,,9---11

l Event Event

Description:

Description Loss of 2B 28 Component Cooling Water Pump Time II Position ~ Applicant's Actions or Behavior i! Booth Operator Instructions:

r;dications Available:

I I Examiners Note: Due to the time needed to swap the 2AB 480V and 2AB DC bus, Ii consider moving on with scenario and initiate Event 3. (Typical time for crews to I! perform the below is 30*40 30-40 minutes) r*r-------- -----

II If time permits directs realignment of 2AB 480VAC Load Center and DC bus 2AB to B side per 2-NOP-52.02, alignment of 2AB SRO ii I Ii Busses and Components, steps 4.1.1 thru 4.1.3, 4.1.5, 4.1.6 (attached page _ 19-29_)

page_19-29_)

i i~~. ,!

i

~------

r--~---~

i t T.S. 3.3.3.1, Radiation Monitoring Instrumentation, action 27 iI i I

T.S.

! I, I Plant Vent on 480 VAC Swgr swap loss of power.(72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months I

SRO action)

i

!~

l--

~ .- ..... ... __ . _---t-i i:

RO Monitors primary plant.

I!

( ,

I I BOP Goes to Hold on turbine if directed.

,l- i

,i !

i I

,----- ii i Lines up 2C CCW pump to replace 2B CCW pump as directed I

I per step 6.2.3.B 1 & 2 (attached page_15_)

.----+- Ii

i-~ I Swaps of 2AB bus to the B side as directed per step 6.2.3.B.4 I

thru 2-NOP-52.02, Alignment Of 2AB Buses And Components,

, I!

I----~-.--

I i

1 step 4.1.4 A thru C (attached page_17_)

I I

- 1 II Starts the 2C CCW pump as directed per step 6.2.3.B.5 I

i (attached page_16_)

i l Ii I!

I I Places 2B CCW pump to Pull To Lock position as directed per

~------l-I

~ ________ i II' step step 6.2.3.B.7 (attached page_16_)

6.2.3.B.7 (attached page_16_) i

.- '0 __ -

_-_._-----t-i! ------r.- - - - - - - - - - - - - - - - - - - - - - - - - - - - <

Ilf lf directed realign the 2AB 480VAC Load Center and DC bus II 2AB to B side as directed per 2-NOP-52.02, alignment of 2AB I I Busses and Components steps 4.1.1 thru 4.1.3,4.1.5,4.1.6 4.1.3, 4.1.5, 4.1.6

~.. ____

_~ _~ ~~~ _ _____'_(_a_tt_a_ch_e_d_p_a_g_e_-_19_-_2_9_)

-,-(_at_ta_c_h_e_d_p_ag_e___1_9_-2_9_)_ _ _ _ _ __ __ __ __ __ __ __ __ _ ..-I

.J 18

--- ~~--------------------

REVISION NO PROCEDURE TITLE PAGE PAGE 12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 7 of 37 PROCEDURE NO 2-NOP-5202 ST LUCIE UNIT 2 4.0 INSTRUCTIONS 4_1 4.1 Transfer of 2AB Buses and ComQonents Comgonents from A Side to B Side

1. REMOVE the Vital AC SUPS Rectifier from service by performing the following A. At 125V DC Bus 20. ENSURE Bkr 2-61303, PLANT VITAL AC SUPS, SUPS. is ON B. At 480V MCC 2AB, ENSURE Bkr 2-42434, CONST VOLTAGE VOL TAGE TRANSFORMER, IS ON.

C. At Vital AC SUPS Inverter, PERFORM the following (1 ) ENSURE the following breakers are ON

CB1, BATTERY INPUT

CB4, CB4. AL TERNATE SOURCE AC INPUT ALTERNATE

( ( 2)

(2) NOTIFY Control Room to expect the receipt of annunciator B-33, 120 VAC VITAUSECURITY/FIRE INVTR TROUBLE (RTGB 201), alarm.

(3) PLACE CB3.

CB3, AC INPUT, in OFF.

(4) VERIFY INVERTER SUPPLYING LOAD light remains ON.

(5) VERIFY the following lights are ON

INVERTER ON DC BATTERY POWER

480 VOL TS AC FAILURE

FAN FAILURE D. At 480V MCC 2AB,2AB. PLACE Bkr 2-42433.

2-42433, INVERTER RECTIFIER, In OFF E. NOTIFY Control Room the Vital AC SUPS rectifier is removed from service F. VERIFY annunciator B-33, 120 VAC VITAUSECURITY/FIRE INVTR TROUBLE (RTGB 201), alarm received 19

FlFV'SION NO REv'SION PROCEDURE TITLE PAGE:

PAGE 12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 8 of 37 PfiOCEDURE NO PROCEDURE 2-NOP-5202 2*NOP*52 02 S1. LUCIE UNIT 2 ST 4,1 Transfer of 2AB Buses and Components from A Side to B Side (continued) 2, REMOVE the Fire and Security SUPS Rectifier from service by performing the following:

following.

A. At 125VDC Bus 2D, 20, ENSURE Bkr 2-61305, SECURITY VITAL SUPS, is ON.

B, At 480V MCC 2C, ENSURE Bkr 2-42508, PS & FD INVERT, is IS ON.

ON C,

C. At Fire Detection & Station Security Vital A.C. SUPS Inverter, PERFORM the following:following (1 )

(1) ENSURE the following breakers are ON: ON.

- CB1, BATTERY INPUT

- CB4, ALTERNATE SOURCE AC INPUT

( (2) NOTIFY Control Room to expect the receipt of 8-33, B-33, 120 VAC VITAUSECURITY FIRE INVTR TROUBLE (RTGB 201), alarm_alarm (3) PLACE CB 403, 403. AC INPUT, in In OFF_

OFF (4) VERIFY INVERTER SUPPLYING LOAD light remains ON.

ON (5) VERIFY the following lights are ON: ON.

- FAN FAILURE

- AC POWER FAILURE

- BATTERY CURRENT D. At 480V MCC 2AB, PLACE Bkr 2-42415, INVERTER SEC SUPS RECT, in In OFF.

OFF E. NOTIFY Control Room the Fire and Security SUPS Rectifier is removed from service F. VERIFY annunciator B-33, 120 VAC VITAUSECURITY FIRE INVTR TROUBLE (RTGS 201). alarm received.

(RTGB 201),

20

~-.-

REV:SION NO REViSION NO PROCEDURE TITLE PROCEDURE TITLE PAGE:

PAGE:

12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 9 of 37 PROCEDURE NO 2-NOP-S2 02 2*NOP*52.02 ST.

S1. LUCIE UNIT 2 4.1 Transfer of 2AB Buses and Components from A Side to B Side (continued)

3. TRANSFER DC Bus 2AB to DC Bus 2B by performing the following A. VERIFY Battery Charger 2A and/or 2-M is supplying power to 125V DC Buses 2A and 2M. 2M B. VERIFY Battery Charger 2B and/or 2-BB is supplying power to 125V DC Buses 2B and 2BB.

C. At 480V MCC 2AB, ENSURE Bkr 2-42413, BATTERY CHARGER 2AB, is IS positioned to ON.

0, At Battery Charger 2AB, PERFORM the following (1) ENSURE the OFF/ON switch is positioned to ON (2) ENSURE 2AB BATTERY CHARGER AC INPUT BREAKER IS positioned to ON CAUTION If the AC Input breaker IS in OFF. then to ensure proper charger warm up, the AC input breaker should be positioned to ON at least 15 minutes prior to placing the DC output breaker to ON.

(3) ENSURE 2AB BATTERY CHARGER DC OUTPUT BREAKER is positioned to ON.

(4) VERIFY DC output voltage IS 132 to 137 VDC In the float mode.

mode (5) IF DC voltage IS outside the 132 to 137 VDC range, THEN PERFORM the following

a. PLACE 2AB BATTERY CHARGER DC OUTPUT BREAKER In OFF

b. PLACE 2AB BATTERY CHARGER AC INPUT BREAKER in OFF

c. NOTIFY the US/NWE (6) IF the DC output voltage is satisfactory, THEN PLACE Battery Charger 2AB in the equalize mode by turning the equalizer timer to HOLD.

(

21

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

REVISION NO ReVISION PROCEDURE TITLE PAGE' PAGE:

12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 10 of 37 PRl)CEJURE PROCEJURE NO 2 NOP-52 02 2*NOP-5202 ST LUCIE UNIT 2 4.1 Transfer of 2AB Buses and Components from A Side to B Side (continued)

3. (continued)

NOTE The following alarms on RTGB 201 may be received during the performance of Section 4.1 4 1 Step 3.E 3 E through Section 4.1 Step 3.J due to no charge conditions on the respective side

A20, 125V DC BATT 8ATT CHGR 2B/2BB28/28B TROUBLE

A50, 125V BAn BATT CHGR 2AB TROUBLE

B20, 125V DC BATT CHGR 2A12AA TROUBLE E. At 125V DC Bus 2AB, PLACE Bkr 2-60326, CKT #26 (Battery Charger 2AB), In in ON F.

F, IF DC amperage on Battery Charger 2AB does NOT increase

( as expected, THEN PERFORM the following following:

(1) Immediately PLACE Bkr 2-60326, CKT #26 (Battery Charger 2AB), in OFF. OFF (2) CONTACT CONT ACT USINWE US/NWE for further instructions.

G. NOTIFY Control Room that Battery Charger 2AB is powering 125V DC Bus 2A8.

ZAB.

NOTE When performing SectIOn Section 4.1 Step 3 3. H, the following annunciators will ALARM:

ALARM

S-16, EM ERG 125VDC/4.16KV/480V 125VDC/4 16KV/480V AB BUSES MISALIGNED (RTGB 206)

B-60, DC/4 16KV/480V AB BUSES MISALIGNED 8-60, EMERG 125V DCf4.16KV/480V (RTGB 201)

H. At RTGB 201, PERFORM the following: following (1) OPEN Bkr 2-60335, 2*60335, TIE 2AB/2A.

2A8/2A.

(2) 2-60143, TIE 2A12AB.

OPEN Bkr 2*60143, 22

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

R[VIS'O'J REYI$IO'J NO PROCEDURE TITLE PAGE:

PAGE.

12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 11 of 37 PROCEDURE NO 2*NOP*5202 2-NOP-52 02 ST. LUCIE UNIT 2 4.1 Transfer of 2AB Buses and Components from A Side to B Side (continued)

3. H. ((continued) continued)

(3) CLOSE Bkr 2-60243, TIE 2B/2AB.

(4) CLOSE Bkr 2-60333, TIE 2AB/2B 2AB/2B.

I. VERIFY the following annunCiators annunciators are in ALARM ALARM:

S-16, EMERG 125VDC/416KV/480V 125VDC/4.16KV/480V AB BUSES MISALIGNED (RTGB 206)

B-60, EMERG 125V DC/4.16KV/480V AB BUSES MISALIGNED (RTGB 201)

J. At Battery Charger 2AB, TURN the equalizer timer to zero (0).

(0)

K, VERIFY Battery Chargers 2B and/or 2-BB are carrying some load.

load

(

L. At 125V DC Bus 2AB, PLACE Bkr 2-60326, 2*60326, CKT #26 (Battery Charger 2AB), in OFF.

M. NOTIFY Control Room that Battery Charger 2AB is in hot standby.

standby N. ENSURE the following battery charger trouble alarms are CLEAR by resetting their associated reflash panels, if necessary necessa ry

B*20, B-20. 125V DC BATT CHGR 2A12AA 2N2AA TROUBLE (RTGB-201) .- Reflash Panel RA-RAB*11/B-20 RA-RAB-11/B-20 (RAB/49/RA2/RAJ) and Reflash Panel RA*RAB-26/B-20 RA-RAB-26/B-20 (RAB/48/N-RA4/E-RAK)

A-20, 125V DC BATT CHGR 2B/2BB TROUBLE A*20, (RTGB*201)

(RTGB-201) Reflash Panel RA*RAB*10/A*20 RA-RAB-10/A-20 (RAB/48/N-RA3/E-RAK) and Reflash Panel (RAB/48/N*RA3/E*RAK)

RA-RAB-271A-20 (RAB/48/S-RA3NV-RAK)

RA-RAB-27/A-20 (RAB/48/S-RA3/vv-RAK)

A-50, 125V DC BATT CHGR 2AB TROUBLE A*50, (RTGB-201) - Reflash Panel RA-RAB-12/A*50 (RTGB-201)* RA-RAB-12/A-50 (RAB/48/N-RA2/E-RAL)

(RAB/48/N*RA2/E*RAL) 23

REVISION NO PROCEDURE TITLE TiTLE PAGE' PAGE 12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 13 of 37 PROUDURE PROCEDURE NO 2 NOP*52 02 2*NOP*5202 ST. LUCIE UNIT 2 ST 4,1 4.1 Transfer of 2AB Buses and Components from A Side to B Side (continued) 5,

5. (continued)

C, C. IF Control Room AlC NC HVNACC-3C HVAlACC-3C is operating, THEN ALIGN Control Room air conditioning per 2-NOP-25 2*NOP*25,07, 07, Control Room Ventilation System, to prepare for the loss of HVNACC-3C.

HVAlACC-3C NOTE Refer to Attachment 2. 2, Expected Alarms When Transferring 480V Load Center 2AB Power Source, for alarms received when performing the following step, step.

D.

0, At RTGB 201, PERFORM the following:

following (1) OPEN Bkr 2*40702, 2-40702, 480V BUS TIE 2AB/2A2.

2AB/2A2, (2) OPEN Bkr 2*40220, 480V BUS TIE 2A2/2AB

(

(3) CLOSE Bkr 2-40504, 480V BUS TIE 2B2/2AB.

2B2/2AB, (4) CLOSE Bkr 2-40706, 480V BUS TIE 2AB/2B22AB/2B2, 6, VERIFY the following follOWing annunciators are CLEAR CLEAR

6*60, EM B-60. DC/4, 16KV/480V AB BUSES ERG 125V DC/4.16KV/480V EMERG MISALIGNED (RTGB 201)

S-16, EMERG 125VDC/4,16KV/480V 125VDC/4.16KV/480V AB BUSES MISALIGNED (RTGB 206)

NOTE 4 1, Steps 7 through 19, may be completed in any order, Section 4,1, order.

7. ENSURE N-45, WASTE MANAGEMENT LOCAL ALARM (RTGB-205) IS is CLEAR by locally acknowledging alarms on Waste Management Panel.Panel, if necessary, necessary.

8. annunciators listed in Attachment 2 are CLEAR VERIFY annunCiators CLEAR.

g, RESTORE charging pumps to the desired lineup per 2-NOP-02,02, 2-NOP*02,02, Charging and Letdown, Letdown 24

REVISION REVISION NO NO PROCEDURE TITLE PROCEDURE TITLE PAGE PAGE 12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 14 of 37 P"<OCEOURc P'<OCEIJURc NO 2*NOP*5202 2-NOP-5202 ST ST LUCIE UNIT 2 4.1 Transfer of 2AB Buses and Components from A Side to B Side INITlAL INITIAL (continued) 1 10.

Q, At RTGB-206, RTGB*206, ALIGN 2C CCW Pump to 2B CCW header as follows A. MV-14*1, PUMP 2C DISCH TO HEADER A CLOSE MV-14-1, A.

-IV-B. CLOSE MV-14-3, HEADER A TO PUMP 2C.

-IV-C. OPEN MV-14-4, MV-14-4. HEADER B TO PUMP 2C

-IV-D. OPEN MV-14-2, MV-14*2, PUMP 2C DISCH TO HEADER B

-IV-( E. VERIFY annunciator S*26, S-26, 2C CCW PUMP HDR VALVES/AB VALVES/AS BUS MISALIGNMENT, is CLEAR.

F. IF 2C CCW Pump is required to be running, THEN START 2C CCW Pump per 2*NOP*14 2-NOP-14 02, Component Cooling Water System Operation.

Operation 11 .

11. ALIGN 2C ICW Pump to 2B ICW header, as follows:

A. LOCK CLOSED SB21165, 2C ICW PUMP X-TIE DISCH To (INTK/9/N-4!W-C)

'A' TRAIN ISOL (INTKl9/N*41W*C)

-IV-IV B,

B. LOCK OPEN SB21211, 2C ICW PUMP X*TIE X-TIE DISCH To 'B'

'8' TRAIN ISOL (INTKl9/N*41W*C).

(INTK/9/N-4!W-C).

-IV-C. IF 2C ICW Pump IS required to be running, THEN START 2C ICW Pump per 2-NOP-21 03, Intake Cooling Water System Operation 25

~.--------

(

REVISION NO PROCEOURE TITLE PROCEDURE PAGE:

PAGE.

12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 15 of 37 PROCEDURE NO 2-NOP-52 02 2*NOP-5202 ST LUCIE UNIT 2 4.1 Transfer of 2AB Buses and Components from A Side to B Side INITIAL (continued)

12. HVNACC-3C, Control Room Area Supply Air Handling Unit.

ALIGN HVAlACC-3C, CCW supply and return headers to the 2B CCW header as follows:

A. LOCK CLOSED V14510. SUPPLY HDR A TO HVAlACC-3C HVNACC*3C CNTL ROOM AlC NC ISOL (RABf70/S-RA21W-RAI)

(RAB!70/S-RA2f\N-RAI)

IV B. LOCK CLOSED V14518, HVAlACC-3C HVNACC-3C CNTL ROOM AlC NC TO RETURN HDR A ISOL (RAB/70/S-RA2/E-RAJ).

(RAB/70/S-RA2/E-RAJ)

-IV-C. LOCK OPEN V14506, SUPPLY HDR B TO HVNACC-3C HVAlACC-3C CNTL ROOM AlC NC ISOL (RAB/70/N-RA2IW-RAI).

(RAB/70/N-RA2f\N-RAI)

-IV- -

IV

(

D. HVNACC-3C CNTL RM AlC LOCK OPEN V14514, HVAlACC-3C NC TO (RAB/70/S-RA2/E-RAJ)

RETURN HDR B ISOL (RAB/70/S-RA2/E-RAJ). --

-IV-

13. IF HVNACC*3C HVAlACC-3C is required for operation, THEN START HVNACC-3C per 2-NOP-25 07. Control Room Ventilation System. System

14. IF the Instrument Air Emergency Cooling System radiator fan and recirculation reCIrculation pump were In in service, service. THEN PERFORM the following A. ReCIrculation Pump (TGB/24/24/E-B)

Locally START Recirculation (TGB/24/24/E-B).

B. Locally START Radiator Fan (TGB/24/24/E-B)

(TGB/24/24/E-B).

26

(

REVISION NO PROCEDURE TITLE PAGE:

12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 16 of 37 PROCEDURE NO 2-NOP-5202 2*NOP*5202 ST. LUCIE UNIT 2 4.1 Transfer of 2AB Buses and Components from A Side to B Side (contin ued)

(continued) t:!Q.I£ NOTE

Verification of proper Plant Vent Stack Radiation Monitor operation Includes pump restart when power is restored.

Tech Spec 3 331 3.3.1 is applicable.

15. VERIFY proper operation of RC-26-90, RC*26*90, Pl PL T VENT STACK RAD MONITOR, by performing periorming the following following.

A. On Plant Auxiliary Control Board No.2, No 2, VERIFY OPER green LED is ON for the following:

following

LOW RANGE

EFF LEVEL

( B.

8. On PC-11 PC*11 Radiation Monitor, VERIFY the following parameters on Grid 4 are GREEN (normal):

AAL621 ML621

AAE624 ME624 C. If Indications indications are NOT normal, PRESS the FLOW pushbutton on RC-26-90, RC*26*90, PL T VENT STACK RAD MONITOR panel to start sample fiow flow D. If Indications indications are still NOT normal, CONTACT I&C.

16. IF HVE-37, HVE*37, PASS Room Fan. Fan, was running, THEN locally VERIFY restart of the fan

17. VERIFY annunciator N-45, N-45. WASTE MANAGEMENT LOCAL ALARM (RTGB 205).

205), IS is clear.

clear

18. RESTORE the Vital AC SUPS Rectifier to service by performingperiorming the following follOWing A. At 480V MCC 2AB, PLACE Bkr 2-42433. 2*42433, INVERTER RECTIFIER, RECTIFIER. In in ON, ON 27

(

REVISION REVISION NO NO PROCEDURE PROCEDURE TITLE TITLE PAGE:

PAGE:

12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 17 of 37 PROCEDURE PROCEDURE NONO 2*NOP*5202 ST. LUCiE LUCIE UNIT 2 4.1 Transfer of 2A6 2AB Buses and Components from A Side to B Side (continued)

18. ((continued) continued)

B. Inverter, PERFORM the following:

At Vital AC SUPS Inverter. following (1

(1)) VERIFY PRE-CHARGE light is ON.

(2) PLACE CB3, CB3. AC INPUT, in ON.

(3) VERIFY INVERTER SUPPLYING LOAD light remains ON ON.

(4) VERIFY the following indicating lights are OFF

- INVERTER ON DC BATTERY POWER

- 480 VOLTS VOL TS AC FAILURE

(

FAN FAILURE (5) MONITOR AC INPUT AC A.C AMPERES meter for an Increase increase Indicating the rectifier has picked up the load C. NOTIFY Control Room the Vital AC SUPS rectifier is returned to service

19. RESTORE the Fire and Security SUPS Rectifier to service by performing the following A. At 480V MCC 2AB, PLACE Bkr 2-42415, INVERTER SEC SUPS RECT, RECT. in ON.

B. At Fire and Security SUPS Inverter, Inverter. PERFORM the following following:

(1) ENSURE PRE-CHARGE light is ON IS ON.

(2) PLACE CB 403, 403. AC INPUT.

INPUT, breaker Inin ON (3) VERIFY INVERTER SUPPLYING LOAD is ON. ON

(

28

REVIS'ON NO PROCEDURE TITLE PROCEDURE TITLE PAGE:

PAGE 12 ALIGNMENT OF 2AB BUSES AND COMPONENTS 18 of 37 PROCEDURE NO 2-NOP-5202 2*NOP*5202 ST. LUCIE UNIT 2 4.1 4,1 Transfer of 2AB Buses and Components from A A Side to B Side (continued) 19,

19. B.

8. (continued)

(4) VERIFY the following indicating Indicating lights are off:

- AC POWER FAILURE

- BATTERY CURRENT

- FAN FAILURE (5) MONITOR AC INPUT AC AMPERES meter for an increase indicating the rectifier has picked up the load.

C. NOTIFY Control Room the Fire and Security SUPS Rectifier is returned to service.

20. VERIFY annunciator B-33, 120 VAC VITAL/SECURITY/FIRE VITAl/SECURITY/FIRE INVTR TROUBLE, alarm CLEAR (RTGB 201).

21. VERIFY Sewage Lift Station (located In in the NE corner of the Turbine Building)

BUilding) is operating properly, as evidenced eVidenced by the sound of the solenoids energizing and de-energizing.

29

Appendix D 0 Operator Action Form ES-D-2 ES-O-2

( II[I

'lOp

1 Op Test No. No 1 Scenario # 5 Event # 3 Page L- of 19 il Event DescriPtion:-- Description Selected Pressurizer Level Channel LT 111 OX fails high

~I

'~-=-=-==r~-=-=-=~---=-=======~~~~~----~~--=-----====---=91 L- Time L- Position A licant's Actions or Behavior IIsooth Booth Operator Instructions: When directed by examiner, trigger LT 111 OX fails Ii high.

i Indications Available: Alarms H-17 Pzr Channel X Level High/Low pzr Channel X Level High LA-S Pzr

~.-

Recognizes by numerous alarms that Selected Pressurizer Level 8RO/RO SRO / RO Channel LT 111 OX failed high high..

~- ..- - . '

Enters 2-0120035, Pressurizer Pressure And Level. (attached Ii 8RO SRO page_31-33_)

page_ 31-33 -)

r i-"~- ' .-- .-

ii I T8 TS II Enters T.8 T.S 3.3.3.6a Accident Monitoring Action A (7 day action) 8RO SRO

!i i

f- - -

f- -----1-I

( .--------t-- I I Directs verifying proper operation of the Letdown system I

~'- -- _. _._._-----,------I I! I Directs restoring Pressurizer Heaters per 2-0120035 step

--_._ .._._.- -.~ _._-_... _._.

7.2.2.G. (attached page_33_)

page_ 33-)

RO Verifies proper operation of the letdown system.

i--

1--

iI I

,,I Restores Pressurizer Heaters as directed per 2-0120035 step 7.2.2.G. (attached page_33_)

~ _----"-

BOP I Monitors balance of plant.

I

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

.... --.~

I

-~--

iI

--. ------1.

,,r- ..... _--_.

Ir-l-

~-

i I

30

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

~-~ --_._-

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

REVISION NO PROCEDURE TITLE PAGE 26 PRESSURIZER PRESSURE AND LEVEL 9 of 15 PROCEDURE PROCE CURE NO 2-0120035 ST. LUCIE UNIT 2 7.2 Subsequent Operator Actions (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

1. (continued)

G. ifLf (LOOP) Loss of Offsite Power has occurred with diesel generators supplying supplYing power and pressurizer level is greater than 27%, Then periorm the following to regain perform pressurizer heaters:

heaters

1. Manually close the breakers for pressurizer heater on 4160V buses Bkr 8kr 2-20204 on 2A3 bus Bkr 2-20403 on 2B3 283 bus.

2. Manually reset the backup heater breakers B1 81 and B484 only (200 kw each).

(

2. ABNORMAL PRESSURIZER LEVEL 2.

CONDITION NOTE Appendix AppendiX "8" "B" contains a listing of pressurizer levels which are associated with automatic actions.

A. Verify selected RRS channel is A. Ifif the selected RRS channel operating properly properly. has failed, Then shift to the operable channel.

1. NAVIGATE to the SBCS S8CS inputs screen on either FW FPD and reset the TAVE T AVE signal, if required B. Ensure backup charging pump starts B. if automatic actions have NOT and letdown flow is decreasing, decreaSing, or occurred, Then manually the backup charging pump stops and control charging and letdown letdown flow is Increasing, increasing, whichever flow as required is IS applicable. (Appendix "8""B" contains expected automatic responses.)

responses) 31

.,--.-."~ . '-

'<0 REVISION NO PROCEDURE TITLE PAGE 26 PRESSURIZER PRESSURE AND LEVEL 10 of 15 PROCEDURt NO PROCEDURE 2-0120035 ST.

ST LUCIE UNIT 2 7.2 Subsequent Operator Actions (continued)

INSTRUCTIONS CONTINGENCY ACTIONS 2, (continued) 2. (continued)

C. Verify level anomaly is NOT caused C. Slow the rate of change of T~avg.

by a large rate of change in T-avg. T~avg or stabilize until level T-avg anomaly is controlled, controlled.

D. Verify "Letdown Isol. Valves",

D, D. l!if letdown has isolated, Then V~2522 are V-2515, V-2516, and V-2522 secure charging and refer to open.

open 2~ONP~0203, Charging and 2-0NP-02,03, Letdown.

Letdown E. Verify selected pressurizer level E. l!if selected level control valve is IS control valve (LCV-2110P (LCV-211 OP /I NOT operating properly, Then LCV-21100)

LCV-211 00) is IS operating properly, properly take manual control of level control valve and refer to 2~ONP~0203, Charging and 2-0NP-02.03, Letdown, Letdown.

(

F.

F, Verify selected letdown pressure F. l! if selected pressure control control valve (PCV*2201 (PCV-2201 P PI/ valve is NOT operating PCV*22010)

PCV-220 10) is operating properly, properly properly, Then take manual control of pressure control valve and refer to 2~ONP~02.03, Charging and 2-0NP*02,03, Letdown.

32

- --~---------- ------------------ ------

REVISION NO PROCEDURE TITLE PAGE.

PAGE 26 PRESSURIZER PRESSURE AND LEVEL 11 of 15 PROCEDURE NO 2*0120035 2-0120035 ST.

ST_ LUCIE UNIT 2 7.2 7,2 Subsequent Operator Actions (continued)

INSTRUCTIONS CONTINGENCY ACTIONS 2.

2, (continued) 2. (continued)

NOTE With less than 27% level on Channel X, the "A" pressurizer heater transformer feeder breaker (2-20204) trips and the "B""8" side 480V power deenergize, With less than 27% level on Channel Y, the "B" supplies deenergize. "8" pressurizer heater transformer feeder breaker (2-20403) trips and the "A" side 480V power supplies deenergize.

deenergize, The backup interlock bypass keyswitch keyswltch selected to the level position, allows the 480V heater power supplies to be reset.

G. Verify pressurizer level indicating G. If!f pressurizer heaters are controllers (selected and non- deenergized or level indicating selected) are operating properly and controller( s) failed, Then controller(s) power is available to pressurizer perform the following:

heaters.

heaters,

(

J1 either level control

1. If channel has failed, Then shift to the operable channel and reset heaters as follows:

a. Place the backup interlock bypass keyswitch (RTGB-203) to the LEVEL position (This regains power to the proportional and backup heater banks controlled by the selected channel.)

channel)

b. Reset pressurizer pressuriZer heater banks as needed.

needed, OR 33

Appendix D AppelldIx Operator Action Actioll Form ES-D-2 II Op Test No.: 1 Scellario #

Scenario 5 Event Evellt## 4 Page 7 of 19

~-------- ~~I Event

Description:

PORV 1474 Acoustic Monitor fails ii I~

TIme Time ]III Position POSitIOIl II Applicant's Actions Applicallt's Actiolls or Behavior r--------------------------------------------------------------~

!; Booth Operator Instructions: When directed by examiner, trigger PORV 1474 Acoustic Monitor fails

--~~------

Indications Available: Alarms LC-1 PZR PORV/SAFETY OPEN Examiners Note: If Applicants realize that only the Acoustic Monitor has failed,

. they may elect to swap PORV Block valves. (Open V1477 and Close V1476 and

~~o~ o~n breaker) breaker This will allow T.S. 3.3.3.6 to be exited.

i SRO/ROI Recognize that PORV 1474 Acoustic Monitor is in alarm.

BOP

~.--- ..- - - - - - - - - J - - - - - - - J - - - - - - - - - - - - - - - - - - - - - - - - - - - l i , I!,

L------i------t-I

+- ,

1

! SRO I Enters 2-0120036, Pressurizer Reliefl Safety Valve (attached SRO i,

I page_35_)

page_ 35 -)

i I I

! I II Evaluates T.S. 3.3.3.6, Accident Monitoring Instrumentation (7 Ii TS day action and monitor alt indicators every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , may refer I

SRO to 2-0SP-1 00.17, Accident Monitoring Instrumentation Monthly i

(

._- l

- - - ..--------1----

_--.- --+-_. I i

I Channel Check, step 7.1.18 (attached page_36_) page ~ 36_)

Directs checking plant parameters to determine if PORV is open by 2-0120036, steps 7.2.1 by checking PORV 1474 Position indicating light, Discharge line temperature and i

I Quench Ouench Tank parameters and documenting using Data Sheet 30.

II Determines that only the PORV 1474 Acoustic Monitor has

! : failed.

--- .. -~-.--+--

---.~-->-

~-----

._+_ !

.... i ii Observes tailpipe temperatures, pressurizer pressure stable, i RO Ii ' an

.a nd de ter m Jnes PORV d determines POR V 147414 74 IS not open.

----------------+-*------+1

-_. _._-_.-- -------;--.. ------------------------------------------------i I

_-_______________+---_______________________________________

! ---1

. Checks as directed plant parameters to determine if PORV is open by 2-0120036, steps 7.2.1 by checking PORV1474 RO Position indicating light, Discharge line temperature and Quench Ouench Tank parameters. Documents using Data Sheet 30.

--.-------------!---------t------------------------------~_______l BOP I! Monitors balance of plant plant.

34

REVISION NO PROCEDURE TITLE PAGE.

PAGE:

14 PRESSURIZER RELIEF I/ SAFETY VALVE 5 of 8 PRUCE DURE NO PROCEDURE 2-0120036 ST. LUCIE UNIT 2 7.0 OPERATOR ACTIONS 7.1 Immediate Operator Actions

1. None 7.2 Subsequent Operator Actions INSTRUCTIONS CONTINGENCY ACTIONS

1. RELIEF VALVE FAILURE OR 1.

LEAKAGE:

A. Determine which PORV is open or A. J!

if it is NOT known which leaking by observing acoustic flow PORV is stuck open, Then monitors or PORV position indicating immediately close both block lights.

lights valves (V-1476 and V-1477).

S. 11 B. if a PORV has failed OPEN, Then B. !!11 the relief valve does NOT place the control switch to close anda nd pressurizer pressure c.

(

OVERRIDE position and verify valve closure by is less than 2300 psia, Then immediately close the applicable block valve (V-14 76 orV-1477) or V-1477).

1. Position indicating lights.

2. Acoustic flow monitoring.

3. Discharge line temperature.

4. Quench tank parameters.

35

~--------------------

REVISION NO PROCEDURE TITLE PAGE:

PAGE 4 ACCIDENT MONITORING INSTRUMENTATION 11 of 17 PROCEDURE NO MONTHLY CHANNEL CHECK 2-0SP-100.17 2-0SP-10017 ST. LUCIE UNIT 2 7.1 (continued) INITIAL

16. 'Verify PORV block valve position indicators are illuminated and indicate desired position (not required if the PORV block valves are closed and power is removed).

A. V1476 8.

B. V1477

17. 'Verify PORV Valve Position Indicators are illuminated and indicate desired position.

Indicate A. V1474 8.

B. V1475

18. 'Verify the following on the PORV and Safety Valve acoustic flow fiow monitor (FI-01-1, FI-01-2, FI*01-3, FI-01-3, FI*01-4 & FI-01-5):

FI-01-4 &

A. No flow indication Red LEDs LEOs is illuminated.

( 8.

B. Power available Red LEDsLEOs are illuminated.

7.2 ifli it has been evaluated that an accident monitoring instrument has failed the channel check, Then ensure that a plant work order is initiated and the instrument is entered In in the equipment out-of-service program.

Additionally, ensure those instruments determined to be satisfactory are removed from the equipment out-of-service program. Equipment out-of-service entries for CETs and HJTCs are documented on a form similar to Table 1 of this data sheet. A single generic EOOS entry is utilized, utilized.

Table 1 will be maintained in the EOOS notebook along with the green PWO tags associated with the individual plant work orders. A single yellow dot will be affixed to the QSPDS QSPOS monitor to identify that the system has pending work orders.

7.3 Ensure that Table 1 is placed in the review file at the beginning of each fuel cycle and a new Table 1 is Initiated initiated (transferring all existing EOOS entries to the new Table 1) 1).

7.4 113

~J 'The Accident Monitoring Instrumentation checked by this Data Sheet has been verified against and meets the requirements of Tech Spec 3.3.3.6, Table 33-10 3.3-10

(

36

Appendix D Operator Action Form ES-D-2 I

L-il Op Test No.:

Ii No..

-1 Scenario # 5 Event # _5;...-_

5 _ _ _ Page _8_ of _1;,;;.9 19 __(1

!I Event

Description:

Loss of Sups Vital AC Bus Inverter. Stabilize the plant after alternate I~

source has energized the Vital AC bus.

Time II Position II Applicant's A licant's Actions or Behavior I Booth Operator Instructions: When directed by examiner, trigger Loss Of SUPS Inverter.

When contacted by Control Room acknowledge communications and trigger Restore SUPS INV.

!i When contacted by Control Room: will perform steps 6.3.1 thru 6.3.5 to restore alternate source of power to Vital AC SUPS (attached) t-~------~--------~------------~----------------------------------~

,~ Indications Available:

,. Alarms B*33, 120V AC Vitali Vital/ Security/Fire Invtr Trouble

~

i SRO/ROI Recognize numerous alarms related to the Vital AC Bus

! I BOP Inverter failure.

I Enters 2-0NP-49.01, SUPS- Non Safety Vital AC, ISFSI SRO I Security Or Fire And Security Inverter Malfunction.

c. I I! Notifies SM I

~f--

I r

~

!: Directs SNPO to perform step 6.1.1A 6.1.1 A (attached page_38_)

page_38_l r**--

f-----..

\-- ~--.

!, Directs SNPO to perform step 6.3.1 thru 6.3.5 (attached

, I page_39_)

page __ 39_l to place the Inverter on alternate source.

r-i I:., I

, I I

I[

I r-![-

I I

!I I

L.

I

,-- ~----

37

(

REVISION NO TilLE PROCEDURE TITLE PAGE 4C SUPS - NON-SAFETY VITAL AC, ISFSI SECURITY OR i-P-RO-C-EO-U-R-E.;:;.NO-----I PROCEDURE NO FIRE FIRE AND AND SECURITY SECURITY INVERTER INVERTER MALFUNCTION MALFUNCTION 5 of 28 2-0NP-49.01 ST. LUCIE UNIT 2 6.0 OPERATOR ACTIONS 6.1 SUPS - Non-Safety Vital AC, ISFSI Security or Fire and Security Inverter INSTRUCTIONS CONTINGENCY ACTIONS 1,

1. Diagnostic Actions NOTE

SUPS Vital AC Inverter power sources are:

Main feed - Bkr 2-42433, Inverter Rectifier, MCC 2AB

Bypass feed feed*- Bkr 2-42434, Const. Voltage Transformer, MCC 2AB

DC feed - Bkr 2-61303, Plant Vital AC SUPS, 125VDC Bus 20

Fire and Security Inverter power sources are:

Main feed* feed - Bkr 2-42415, Inverter Sec SUPS SU PS Rect, MCC 2AB

Bypass feed - Bkr 2-42508, PS & & FD Invert, MCC 2C

DC feed - Bkr 2-61305, Security Vital SUPS, 125VDC Bus 2D 20

Vital AC and Fire and Security inverters automatically shift to the alternate source in the event of a degraded voltage situation if the

( alternate source is available (In Sync light LIT).

A. DIRECT an operator to CHECK Reflash Module RA-RAB-4 to determine which SUPS is in alarm and the cause (West wall of the Cable Spreading Room). Room)

NOTE Inability to gain access to the Cable Spreading Room would Indicate indicate the Fire and Security Inverter is aHected.

affected.

B. !f unable to gain entry to the Cable Spreading Room, Then:

1. CONTACT Security to man Control Room and Cable Spreading Room access.

2. GO TO Section 6.4.

~ ________________________________________________________________ ~ n::0,.

(

38

REVISION NO PROCEDURE PROCEOURE TITLE PAGE' PAGE:

4C SUPS - NON* SAFETY VITAL AC, ISFSI SECURITY OR NON*SAFETY 17 1? of 28 PROCEDURE NONO FIRE AND SECURITY INVERTER MALFUNCTION 2*0NP-49.01 2*0NP*4901 ST- LUCIE UNIT 2 ST 6.3 Loss of Vital AC SUPS Inverter INSTRUCTIONS CONTINGENCY ACTIONS 1.

1. ENSURE alternate source Bkr 2*42434, Const. Voltage Transformer, on MCC 2AB, is CLOSED.

2. ENSURE the following inverter breakers are positioned as indicated:

indicated COMPONENT ID COMPONENT NAME POSITION CB-4 Alternate Source AC Input ON CB*6 CB-6 2A Vital Instr. Bus ON CB*7 CB-? 2B Vital Instr. Bus ON CB*8 CB-8 Vital AC Bus 2A*1 & Vital AC Bus 2B-1 ON NOTE t!QIE

The Manual Bypass Switch may have to be taken past the Alternate Source to Load position to get it to snap into the Alternate Source to

( Load.

Load

The Manual Bypass Switch will NOT allow automatic transfer of the inverter Inverter when in Alternate Source to Load.

3. RESTORE power to the Vital AC SUPS bus by placing the Manual Bypass Switch SWitch to Alternate Source to Load.

Load

4. VERIFY the Alternate Source Supplying 4. !f11 the Alternate Source Supplying Load light is LIT. Load light is NOT LIT, Then NOTIFY the US.

S.

5. CHECK with the Control Room to verify power has been restored.

6. NOTIFY EM to investigate the malfunction and repair the inverter.

7, When the inverter has been repaired, Then RESTORE the inverter to service in accordance with 2-NOP-4901 2-NOP-49.01,, 120 V Vital AC Sups (Non-Class 1E) 1 E) Operation.

END OF SECTION 6.3 39

Appendix D Operator Action Form ES-D-2

( Op Test No 1 Scenario # 5 Event # ...;:.,5

_5::..-__ __

____ Page ~

_9_ _19_-11 of _1_9--11

,, Event

Description:

Loss of Sups Vital AC Bus Inverter. Stabilize the plant after alternate source has energized the Vital AC bus.

Time II Position II Applicant's Actions or Behavior Booth Operator Instructions:

Ip3'ooth i

Indications Available'

i Examiners Note: On the DeS, both channels for SG Wide Range level and Steam

~ Pressure will be in bypass as indicated by the Yellow overlay. When SUPS Inverter

,_ power restored, FW Reg. valves will have to be placed in manual to remove the Ii above from bypass, then, placed back to automatic.

1

,I When SUPS inverter placed on bypass, DeS SG Wide Range level and Steam Header pressure channels will require

! restoring from bypass. Directs transfer of MFW from AUTO to SRO i MANUAL, reset channels, then place MFW back to AUTO control per 2-NOP-102.01 DeS Operations per step 6.7.4 (attached page_ 41-43_) and step 6.9.4 (attached page_44_)

, Notifies EM per step 6.3.6

,~---t I

~-.

i l !. -- ! --------+--T-ra-n-s-fe-rs-M-F-W-v-a-Iv-e-s-f-ro-m-A-U-T-O-to-M-A-N-U-A-L-,-th-e-n-,-r-e-st-o-re-s------i Transfers MFW valves from AUTO to MANUAL, then, restores I Wide Range level from bypass. Places MFW back to AUTO I BOP control per 2-NOP-1 02.01, DeS Operations, per step 6.7.4 as 2-NOP-102.01, directed. (attached page_ 41-43_). Restores Steam Header

.1 pressure from bypass per step 6.9.4 (attached page_ 44_)

. - - - - - -I- - - - - - \ - - - - - - + - - - - - - - - - - - - - - - - - - - - - - - - - - - 1

.--.--~

II I

~----~----~------------------------~

~-----+------+--------------------------------------------~

~

~----~-----r------------------------------~

>--- .---------t-----t-------------------------l

~-

~-----+-------+---------------------------~

I,

'~------------+--------------------------~

)---~--

i

~---.---t-------t---------------------------I I

i, i

I 40

-~------~------

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

(

REVISION NO REVISION NO PROCEDURE TITLE PROCEDURE TITLE PAGE' PAGE:

8A DISTRIBUTED CONTROL SYSTEM (DCS) -

PROCEDURE NONO 20 of 81 PROCEOURE OPERATIONS 2-NOP-102.01 2-NOP-10201 ST. LUCIE UNIT 2 6.7 DCS Input Signal Removal I Restoration - FWCS (continued)

Removal/Restoration INITIAL

3. C. 5. (continued)

b. An Info Tag appears on the S/G FW INPUTS screen above theWR the WR level digital indicator that reads HOLDING LAST GOOD VALUE RESET REQUIRED.

c. The digital and graphical indicators Indicators for WR level on the S/G FW INPUTS and the S/G FW OVERVIEW screen indicate POOR (Black & Cyan)

d. The digital and graphical indicators for SG NR level Validated Output on the S/G FW INPUTS and S/G FW OVERVIEW screens indicate POOR (Black & Cyan).

Cyan)

6. RETURN FPD(s) to the default screen of S/G FW OVERVIEW or as directed by the US/SM.

(

US/SM

4. Restoring WR level input signal from LOW POWER or HIGH POWER Mode:

Mode A. VERIFY from I&C or Engineering that the signal to be removed from BYPASS is GOOD, within its DEVIATION Band and ready to be placed in service.

service

--~

S, NAVIGATE to the S/G FW INPUTS screen on the affected FW Train and SELECT the [8YP] [8YPl Button on the WR level section of the screen.

screen C. On the Overlay, SELECT [BYPASS] for the WR level signal (L9012 or L9022).

D. VERIFY the [BYPASS] Button on the Overlay has changed from a White background to a Gray background.

E. CLOSE the Overlay and VERIFY the following:

following

1. The input signal Signal SELECTED in 6.7.4.C 6.7.4 C indicates it has been Removed from BYPASS by its [BYP]

Button changing from Black letters on a White background to Black letters on a Gray background and the letter (M) placed next to itIt removed.

removed

2. The digital and graphical indicators Indicators for WR level on the S/G FW INPUTS and the S/G FW OVERVIEW screen indicate GOOD (Green & White).White) 41

(

REVISION NO PROCEDURE TITLE PAGE 8A DISTRIBUTED CONTROL SYSTEM (DCS) .

21 of 81 PROCEDURE NO OPERATIONS 2*NOp*102.01 ST. LUCIE UNIT 2 6.7 DCS Input Signal Removal I Restoration - FWCS (continued) INITIAL

4. (continued)

NOTE An Info Tag 2A (2B) FW REG SYS IN MANUAL will appear with any FW MIA Station in Manual F. From either the T*800s or the DCS FPD. FPD, PERFORM the following

1. PLACE the LOW POWER MIA STATION ST ATION of the affected FW Train in Manual

2. ENSURE the HIGH POWER MIA STATION of the affected FW Train is in Manual Manual. -- -- -

G. From the SIG FW INPUTS screen, PERFORM the following following.

1. SELECT the [RESET] Button in the WR level

( section of the screen to bring up the RESET Overlay for the WR level input. - --

2. SELECT [RESET] for the WR level Input mput signal

3. VERIFY the HOLDING LAST GOOD VALUE RESET REQUIRED Info Tag is removed.

4. The digital and graphical Indicators for NR level Validated Output indicators on both the SIG FW INPUTS and SIG FW OVERVIEW screens indicate GOOD (Green & & White)

White).

H. CLOSE the RESET OverlayOverlay.

NOTE The Info Tag 2A (2B) FW REG SYS IN MANUAL will be removed after Both MIA Stations are returned to Auto.

I. From either the T*800s or the DCS FPD, PERFORM the following

1. PLACE the LOW POWER MIA Station of the affected FW Train Inm Automatic.

2. Ensure the HIGH POWER MIA Station of the affected FW Train IS in its ItS required mode of control for current plant conditions.

(

42

REVISION NO REVISION NO PROCEDURE TITLE:

PROCEDURE TITLE: PAGE:

PAGE SA 8A DISTRIBUTED CONTROL SYSTEM (DCS) -

22 of 81 220f81 PROCEDURE NO NO OPERATIONS 2-NOp-102.01 2-NOP-102.01 ST.

S1. LUCIE UNIT 2 6.7 DCS Input Signal Removal I Restoration - FWCS (continued) INITIAL

4. (continued)

J. VERIFY Automatic SG level control has been restored restored to the affected FW Train.

K. RETURN FPD(s) to the default screen of S/G FW OVERVIEW or as directed by the US/SM.

5. BYPASSING a FWCS Feedwater Flow input signal (A Side:

F9011, F90 11, F0903A2, F0903A3; B Side F9021, F0903B2, F0903B3): F0903B3).

CAUTION I The Feedwater Flow signals are Critical System Signals when in the High Power Mode of operation (see Appendix C).

I* If 2 or more of the 3 input signals have been determined to be

'unavailable' for any reason, the FWCS will revert to Single Element control from 3 Element control (if in the High Power Mode). This

( condition IS is confirmed by the Feedwater Flow Validated Output value indicating BAD (Blue &

Indicating & White) and a 'Reset Required' Info Tag appearing next to the Feedwater Flow signals on the INPUTS screen.

The High Power Mode Info Tag on the FW Overview screen will still Indicate High Power Mode because the Feedwater flow signal is holding Last-Good-Value a Last-Good*Value NOTE

Feedwater Flow Input input signals use a Median Select scheme in determining a single Validated Output. The DEVIATION Band limit among the redundant signals is 7.5% of full flow or -~ 445 klbm/hr.

Although a Median Select scheme can operate with no degradation with a single unavailable signal, ALL 3 inputs must be GOOD following 2 or more becoming unavailable before a [RESET] (and a return to 3-Element control) can occur.

BYPASSING a signal in the 3-slgnal 3-signal Feedwater Flow inputs would result in In either a color change In in the Validated Output to POOR if the other 2 input signals are GOOD, in service and within DEVIATION of each other Input or a swap to Single Element control if in High Power Mode and 1 signal has already been established as being 'unavailable' after BYPASSING one of the remaining 2 2.

A. NAVIGATE to the S/G FW INPUTS screen on the affected FPD and SELECT any [BYP] Button on the Feedwater Flow section section of thethe screen.

(

43

REVISION NO PROCEDURE TITLE PAGE:

PAGE 8A DISTRIBUTED CONTROL SYSTEM (DCS) -

59 of 81 PROCEDURE NO OPERATIONS 2-NOP-102.01 2-NOP-10201 ST. LUCIE UNIT 2 6.9 Removal/Restoration DCS Input SHARED Signal Removal I Restoration - SBCS + FWCS (continued) INITIAL

3. (continued)

H. RETURN FPD(s) to the default screens of FW OVERVIEW or as directed by the US/SM.

4. Restoring Main Steam Header Pressure (P0802) from FW 2A, 2B, or SBCS:

A. VERIFY from I&C or Engineering that the signal to be removed from BYPASS is GOOD and ready to be returned ope ration.

to operation.

B. NAVIGATE to the A or B FWCS S/G INPUTS or SBCS OVERVIEW screens and PERFORM the following:

1.

1, Select the [BYP] Button on P0802, Main Steam Header Pressure indication.

2. On the Overlay, SELECT [BYPASS] for P0802, c 3.

Main Steam Header Pressure.

VERIFY the [BYPASS] Button on the Overlay has changed from a White background to a Gray background.

backg round.

4. SELECT the [RESET] Button on the P0802 Overlay and VERIFY the Info Tag HOLDING LAST GOOD VALUE RESET REQUIRED is removed from Both FWCS S/G INPUTS and SBCS INPUTS screens.

5. CLOSE the Overlay and VERIFY the following:

following

a. P0802 indicates it has been Removed from BYPASS by its [BYP] Buttons changing from a White background to a Gray background on Both FW INPUTS and SBCS INPUTS screens and the letter (M) next to the [BYP]

Buttons are removed.

b. The digital and graphical indicators for P0802 on Both FWCS S/G INPUTS and SBCS INPUTS screens indicate GOOD (Green &

White).

6. RETURN FPD(s) to the default screens of FW OVERVIEW or as determined by the US/SM.US/SM END OF SECTION 6.9

(

44

Appendix D Operator Action Form ES-D-2

(

Op Test No.: No. 1 Scenario # 5 Event # _6~,

_6;;.;.*._7____

...;..7_ _ _ _ Page l2...-

_10_ of _1;..;.9~1

_1;..;;..9-----i1 I Event

Description:

LOOP /I Loss of Feedwater, 26 2B Diesel does not start start. 2A Diesel output I:,. breaker does not close.

il ..

l,! Tim~1I Time Position II Applicant's Actions or Behavior I Booth Operator Instructions: When directed by examiner, trigger LOOP! LOOP / Loss of I Feedwater, 2B EDG should not auto start and 2A

,i output breaker does not close.

~dications Available:

I

~dications I! When SNPO called by Control Room Local 2B EDG alarms in are:

iI 6-1: 2B EDG TRIP/LOCKOUT

6-2: START DC FAILURE/ SS ISOL

If asked, one minute later state, lockout unable to be reset.

~--. SRB06~OI I--~~~"--

SRO/ROI II Multiple alarms, recognize Reactor ITurbine trip I i I BOP I r~ ,

IL i I!

Directs implementation of 2-EOP-01 2-EOP-01,, "Standard Post Trip i Actions" as follows:

I,I I

,I ii SRO

RO: Reactivity control, Inventory Control, Pressure control, Core Heat Removal

(

,ii

BOP: Vital Auxiliaries, RCS heat removal, Containment Conditions.(2B Conditions. 2B EDG does not auto start start)

I~------+-----------I~~~~---------1

~

I i _ _ + ___

r------.

I i

Recognizes that the 2B EDG did not start and that 2B EDG has alarm A-26, _2_B_E_m_e_r_g_D_I_G_L_o_c_k_o_u_VS_S_I_so_I_.

+-a_la_r_m_A_-_2_6_, 2B Emerg DIG Lockout/SS Isol. - - - - - - - - - 1 I

i I

I Critical Task Recognizes that 2A EDG breaker did not close.

Task I, SRO Directs BOP to close the 2A EDG breaker.

I SRO

=~=-~---~~T---

1-.. _ _ .

I BOP

+i-I=R=e=c=0=g=n=iz=e=s=t-h-a=t=t=h=e=2=B==E=D=G==d-i-d=n=0=t=s=ta=rt==a=n=d=t=ha=t=2=B==E=D=G==h=a:s Recognizes that the 2B EDG did not start and that 2B EDG has i i alarm A-26, 2B Emerg DIG Lockout/SS LockouUSS Isol.

L I

r - - _ _ .~ _ _ _ .

Critical

, Recognizes that 2A EDG breaker did not close.

i Task Close the 2A EDG breaker when directed.

~

I I, BOP r---**------

~- - ~ -~---- _.. _---- Ii

!i i

_ _ _ _ _ _ _ "'-------1---

.~

45

Appendix D Operator Action Form ES-D-2 r Op Test No No. Scenario # 5 Event # 6,...;..7

_6;.:. 7 _ _ _ _ Page ~19~-l1

_11_ of ....;..;19~-I1 Event Event

Description:

Description lOOP I/ Loss of Feedwater, 2B LOOP 28 Diesel does not start. 2A Diesel output breaker does not close.

Time II Position I Applicant's A licant's Actions or Behavior LSooth Booth Operator Instructions:

Ii Indications Available:

~ I Performs EOP-01 Safety Functions as directed for Reactivity i RO I Control, Inventory Control, Pressure Control, Core Heat I I removal r-*- -.-_

-- .-----+---

t-r----. ~ -----

'~'----

Reactivity Control

Verify Reactor power is lowering. lowering,

Verify startup rate is negative.

I

Verify a maximum of one CEA is not fully inserted.

~

r Inventory Control I

(

Verify Pressurizer level is between 10 and 68%

II 1----- Ii

Pressurizer level is trending to 30 - 35%

I i

I I Pressure Control

Verify RCS pressure is between 1800-2300 psia psi a iI i

Verify RCS pressure is trending 2225-2275 psia I

II I

.

Verify RCS subcooling is >20 00 F r[-

Core Heat Removal i

Verify at least one RCP running with CCW. CCW, (LOOP, no RCP's running) i I- II

Verify loop delta T is <10°<10 0 F I! I, I- ..*...--------r Verifies turbine trip on reactor trip. Performs EOP-01 Safety functions as directed for: Vital Auxiliaries, RCS Heat Removal, Containment Conditions BOP L__ ~~~~~~~~ ________________________________________________~

46

Appendix D Operator Action Form ES-D-2 I 0, Op Test No.:

TeetNo Scenario # 5 Event # _6~'..;.7 6, 7_ _ _ _ Page 1L-

_12_ of ...;.,;19:-""'1

_19_-{1 i Event

Description:

LOOP I/ Loss of Feedwater, 2B Diesel does not start. 2A Diesel output I! breaker does not close.

il Time II Position II Applicant's A plicant's Actions or Behavior l~_ooth L~ooth Operator Instructions:

Indications Available:

i,lndications

~-.--.

Ensures MSR Warmup Valves are CLOSED. Calls NPO to

Ii BOP L-.

I I manually close due to loss of of power.

~

I Notifies NPO to perform Appendix X section 1 of EOP-99.

I

! I (outside CR actions) (attached page_ 48-51_)

~.

Maintenance of Vital Auxiliaries I

Verifies turbine governor and throttle valves closed i

Verify GEN Brk open (East breaker, Mid Breaker and I

I Exciter Breaker)

I I Ii

Verify all vital and non vital AC Buses energized.

I (closes 2A EDG output breaker)

(

All vital and non vital DC Buses energized.

I

~.

I

! RCS Heat Removal I

,

Verify at least one S/G has feedwater available.

I

,I

Verify RCS T-avg is between 525 and 535°F by:

I i

Places one ADV on 'A' side and one ADV on 'B' side in

! 'Auto' / 'Auto' i

,f- i

~,

,-i .. I Containment Conditions I

Verify Containment pressure <2 psig.

I i

Verify NO Containment radiation monitors in alarm.

I

~

Verify Containment temperature is less than 120°F.

l_

i

Verify NO secondary plant radiation alarms.

47

REVISION NO .. PROCEDURE TITLE:

TITLE PAGE:

36A APPENDICES I/ FIGURES I/ TABLES I/ DATA 111 of 156 PROCEDURE NO NO. SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 1 of 8)

NOTE This appendix contains two sections. Each section has instructions for stabilization of the secondary plant following a unit trip.

Section 1 provides the field instructions that are performed in the Turbine Generator Building during execution of 2-EOP-01

Section 2 provides the control room instructions that are performed after 2-EOP-01 has been exited Section 1: FIELD ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS o 1. CONFIRM Turbine trip with the Control Room.

( o 2. PERFORM ALL of the following from the Turbine Deck:

o A. VERIFY ALL Main Steam o A.1 !fIf ANY Main Steam Safety Valves Safety Valves are CLOSED. are OPEN, Then immediately NOTIFY the Control Room.

o B. VERIFY ALL of the following 0o B.1 !f If ANY Turbine Valves are NOT Turbine valves are CLOSED: fully CLOSED, locally TRIP the Turbine.

Then loca"y o Governor Valves o Throttle Valves o Intercept Valves o Reheat Valves 48

--~---- --~--- -

REVISION NO.NO.: PROCEDURE TITLE: PAGE:

36A APPENDICES /I FIGURES I/ TABLES I/ DATA 112 of 156 PROCEDURE NO.: NO. SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 2 of 8)

Section 1: FIELD ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS III NOTE II~

III The remainder of the steps in this section may be performed in any order. II o 3. PERFORM ALL of the following from the Ground Floor Level:

o A. ADJUST FCV-12-1, Condensate Hdr Recirc to Cndsr, as required to maintain Condensate flow of 8,000 gpm.

( o B. PERFORM BOTH of the following to ALIGN cooling water to the Heater Drain Pumps, until water is flowing out the packing gland:

o THROTTLE OPEN V38238, DMW to 2A Htr Drain Pump Gland Quench Seallsol.

o THROTTLE OPEN THROTILE V38239, DMW to 2B Htr Drain Pump Gland Quench Seallsol.

o C. CLOSE V31190, Processed Bldn (Vacuum Drag) to 2B Cndsr 1501.

Isol.

o D. OPEN SB13139, TCW Pumps Isol.

Disch Cross-Tie. 1501.

(

49

REVISION NO.:

NO. PROCEDURE TITLE: PAGE:

(

36A APPENDICES / FIGURES / TABLES / DATA 113 of 156 NO ..

PROCEDURE NO.: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 3 of 8)

Section 1: FIELD ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS o 4. PERFORM BOTH of the following from on top of the TLO Reservoir:

o A. VERIFY ONE of the following:

o 1. Bearing Oil Pump and Seal Oil Backup Pump RUNNING.

o 2. Emergency Oil Pump RUNNING.

o B. VERIFY Bearing Oil Lift Pump

( RUNNING.

o 5. PERFORM ALL of the following from the Mezzanine Deck:

o A. THROTTLE OPEN V09218, Filiisol, 15 to 20 turns.

S/G Fillisol, o B. THROTTLE OPEN BOTH of the following valves to establish EACH Hood Spray between 200 and 250 psig:

o V12396, 2A LP Turb Spray TCV-22-61 A Bypass Hdr TCV-22-61A o V12403, 2B LP Turb Spray Hdr TCV-22-61 B Bypass (continued on next page) 50

REVISION NO.:

NO .. PROCEDURE TITLE: PAGE:

/\

36A APPENDICES!

APPENDICES / FIGURES !/ TA8LESTABLES !/ DATA 114 of 156 PROCEDURE NO:NO . SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 4 of 8)

Section 1: FIELD ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

5. (continued)

C. VERIFY ALL of the following valves CLOSED:

0 SC-10-3A, 3A LP Htr Extr Stm Non Return 0 SC-10-38, SC-10-3B, 38 3B LP Htr Extr Stm Non Return 0 SC-10-4A, 4A LP Htr Extr Stm Non Return 0 SC-10-4B, 4B LP Htr Extr SC-10-48, 48 Stm Non Return SC-10-SA, 5A 0 SC-10-5A, SA H HPP Htr Extr Stm Non Return o SC-10-5B, 58 SC-10-58, 5B HP Htr Extr Stm Non Return o 6. From the Turbine Deck, VERIFY the Turning Gear is ready for operation.

o 7. When Section 1 Field Actions are COMPLETE, Then NOTIFY the Control Room.

End of Section 1 51

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 5 Event # _8;.:.,..;.9_

_8,;.:,..,;;9 __

___ _ Page .11.-

~ _1~9--11 of ...;.;19~""1 Event

Description:

2C AFW pump trips and MV-09-9 2A AFW pump to 2A SG fails to open, Crosstie 2A AFW pump to feed 2B Steam Generator Time II Position II Applicant's Actions or Behavior I Booth Operator Instructions: Trigger Restore Instrument Air when contacted by Control I

I Room I Indications Available:

" SRO Performs Diagnostic Flow Chart I

II Exits EOP-01 to EOP-09, LOOP i

I I

Directs STA SFSC's for EOP-09 performed every 15 minutes.

I Directs HP to perform secondary surveys i--

I~-* -

~

Directs RCS depressurized to 1800 to 1850 psi a using i

auxiliary sprays. (key 76 and 77 to operate SE-02-3 and

( !I SE-02-4)l SE-02-4 I~-

I I Directs Ensure EDG Loading i I I

I I

! Directs Appendix H, to restore Instrument Air, of EOP-99.

,!i i (attached page_53-56_l page_53-56_)

I

! i I

~ i

i i Directs, If Appendix H, 'Restore Instrument Air' not I completed within 30 minutes of loss of CCW, ensure CCW II

!I NOT restored to RCP's.

r if 0-

, Examiners Note: If Instrument air is restored after 30 minutes with RCP CCW valves in

.; auto, the CCW valves will re-open, which is in violation of above step.

Iir--

I Directs closing of MSIV's I I I

I-~- III Directs closing of S/G blowdown and sample valves I

L 52

(

REVISION NO REVISION NO PROCEDURE PROCEDURE TITLE:

TITLE PAGE' PAGE 36A APPENDICES I FIGURES FIGURES I TABLES I DATA 57 of 156 PROCEDURE NO PROCEDURE NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX H OPERA TION OF THE 2A AND 26 INSTRUMENT AIR COMPRESSORS OPERATION COMPRESSORS (Page 1 of 4)

Section 1: Placing 2A Instrument Air Compressor in Service o 1. ENSURE the following breakers are aligned as indicated.

Component 10 Component Name POSITION (,J) c,j)

Bkr 41331 (MCC 2A6) Instr Air Compr 2A ON Bkr 42414 (MCC 2AB) Instrument Air Compressor Cooler Fan ON Bkr 42416 (MCC 2AB) Cooling System Water PP ON o 2. 11if TCW is NOT available, Then PERFORM the following: following 0 A. ALIGN 2A Instrument Air Compressor for emergency cooling and operation Component ID 10 Component Name POSITION (,J)

(...J)

( VV13197 13197 I 2A Instr Air Comp Jacket Inlet 1501 Isol OPEN V13201 2A Instr Air Comp Jacket Outlet 1501 Isol OPEN V13383 Air Comprs Outlet Hdr 1501 Isol CLOSE -

f- V13380 Air Comprs Inlet Hdr 1501Isol CLOSE -

I V13417 Air Compr Coolers Inlet Hdr from Recire Recirc Pump 1501 Isol OPEN V13420 Air Compr Coolers to Fan Cooler 1501 Isol OPEN V13424 Recirc Pump from 1 2A Recire / to 2A Expan Tank Isol OPEN V13419 Air Compr Coolers to Fan Cooler Isol 1501 OPEN V13418 2A Recirc Pump DisehDisch 1501 Isol OPEN I

V18109 instr Air Rcvr Instr Revr Inlet from 2A Aftercooler Af\ercooler Isol 1501 OPEN

~~_8660_, V18660 2C 1/ 2D Instr Air Comps Disch Isol 1501 CLOSE 0 6. ENSURE the Instrument Air Compressor Head Tank level is at least 3/4 full.

o0 C. START the Emergency Cooling System Recirculation Pump. Pump o0 D. START the Emergency Cooling System Radiator Fan.

7 53

REVISION NO PROCEDURE TITLE PAGE PAGE' 36A APPENDICES / FIGURES / TABLES / DATA 58 of 156 PROCEouRE NO PROCEDURE SHEETS 2-EOP-99 ST. LUCIE UNIT 2 ST, APPENDIX H OPERATION OF THE 2A AND 28 INSTRUMENT AIR COMPRESSORS (Page 2 of 4)

Section 1: Placing 2A Instrument Air Compressor in Service (continued) o 3. !fIf TCW is IS available, Then ALIGN 2A Instrument Air Compressor for normal cooling and operation operation:

Component 10

!component ID Component Name POSITION (..J) ,

I V13197 2A Inslr Instr Air Comp Camp Jacket Inlet 1501 OPEN V13201 2A Instr Air Comp Camp Jacket Outlet 1501 OPEN I V18109 Inslr Instr Air Rcvr Inlel Inlet from 2A Aftercooler 1501 OPEN I V18660 Y18660 2C / 20 2D Inslr Instr Air Comps Camps Disch

_ _Isol

~

__ L -_

-L-_ CLOSE

___==__!

~ = = ~

o 4. NOTIFY Unit 2 Control Room to RESET the 2A Instrument Air Compressor on the plant auxiliaries panel.

o 5. Locally START the 2A Instrument Air Compressor, o 6, NOTIFY Unit 2 Control Room that 2A Instrument Air Compressor IS

6. is running, End of Section 1 54

REVISION NO PROCEOURE PROCEDURE TITLE PAGE PAGE:

36A APPENDICES 1 I FIGURES 1 I TABLES 1I DATA 59 of 156 PROCEDURE PROCE DURE NO SHEETS 2-EOP-99 ST, ST. LUCIE UNIT 2 APPENDIX H OPERA TlON OF THE 2A AND 26 OPERATION 2B INSTRUMENT AIR COMPRESSORS (Page 3 of 4)

Section 2: Placing 28 26 Instrument Air Compressor in Service o 1. ENSURE the following breakers are aligned as indicated:

Component 10 Component Name POSITION ("-J)

(..J)

Bkr 42192 (MCC 2B6) Instr Air Compr 2B ON Bkr42414 Bkr 42414 (MCC 2AB) Instrument Air Compressor Cooler Fan ON 6kr 42416 (MCC 2AB)

Bkr COOling Cooling System Water PP ON 0 2. If 11 TCW is NOT available, Then PERFORM the following:

following 0 A. ALIGN 2B Instrument Air Compressor for emergency cooling and operation: operation Component 10ID Component Name POSITION ('-J)(..J)

V13209 26 Instr Air Comp 2B Camp Jacket Inlet Isol OPEN -

L- V13213 2B Instr Air Comp Camp Jacket Outlet Isol OPEN V13383 V133B3 Air Comprs Outlet Hdr Isol1501 CLOSE I V133BO V13380 Air Comprs Inlet Hdr Isol 1501 CLOSE I V13417 Air Compr Inlet Hdr from Recirc Pump 1501 Isol OPEN V13420 Air Compr Coolers to Fan Cooler 1501 OPEN V13424 2A Recirc Pump from /I to 2A Expan Tank Isol OPEN V13419 Air Compr Coolers to F an Cooler Isol Fan OPEN I--~

1--

V13418 2A Recire Recirc Pump Disch Isol 1so1 OPEN V18118 ! Instr Air Revr Rcvr Inlet from 2B26 Aftercooler Aftereooler 1501 Isol OPEN J----

V18660 :I 2C I/ 20 Instr Air Camps D~~_:!:~:?I Comps Disch 1501 CLOSE I

-- .-.--~- --"--

0 8. 6. ENSURE the Instrument Air Compressor Head Tank level is at least 3/4 full. full, 0 C. START the Emergency Cooling System Recirculation Pump. Pump, 0 D. START the Emergency Cooling System Radiator Fan. Fan, 55

REVISION NO PROCEDURE TITLE PAGE-PAGE 36A APPENDICES I FIGURES I TABLES I/ DATA 60 of 156 PROCEDURE NO_ NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX H OPERATION OF THE 2A AND 28 INSTRUMENT AIR COMPRESSORS (Page 4 of 4)

Section 2: Placing 28 2B Instrument Air Compressor in Service (continued) o 3. if

!.f TCW is available, Then ALIGN 2B Instrument Air Compressor for normal cooling and operation:

Component 10 Component Name POSITION (..J)

V13209 2B Instr Air Comp Jacket Inlet 1501 OPEN -

V13213 28 Instr Air Comp Jacket Outlet 1501 2B OPEN V18118 Instr Air Rcvr Inlet from 28 2B Aftercooler Isol 1501 OPEN -

II V18660 2C I 2D Instr Air Comps Camps Disch Isol 1501 CLOSE o 4. NOTIFY Unit 2 Control Room to RESET the 2B Instrument Air Compressor on the plant auxiliaries panel.

o 5. Locally START the 2B Instrument Air CompressorCompressor.

o 6, NOTIFY Unit 2 Control Room that 28

6. 2B Instrument Air Compressor is running.

End of Section 2 END OF APPENDIX H 56

Appendix D Operator Action Form ES-D-2

( No.

Op Test No.: 1 Scenario # 5 Event # 8, 9_ _ _ _ Page

_8:;.:"..;;,9 ~

_14_ _1.....

9--.,1 of _19_-11 Event

Description:

2C AFW pump trips and MV-09-9 2A AFW pump to 2A SG fails to open, Crosstie 2A AFW pump to feed 26 2B Steam Generator Time II Position JLII Applicant's Actions or Behavior l

I Booth Operator Instructions: When contacted by Control Room perform 2-0NP-I1-_____ 09.02, Auxiliary Feedwater Appendix C steps 1A thru 1H as directed.

Indications Available: Alarm: G-46, 2C AFW PUMP TURBINE

,i I FAILURE/Trip/OVRLD/SS FAILURE/Trip/OVRLO/SS ISOL r---

!--~-

I SRO Directs Stabilize RCS Temperature.

[;

I Directs Ensure S/G Level 60 to 70%

Ii I I

iI I If AFAS NOT actuated, direct AFW restored by manual I I starting of pumps and opening of valves lAW 2-NOP-09.02 i I ii (attached page_ 5866- -

(attac he d page_58-66_)

,I f-

-~.

l c_ ~

RO RCS depressurized to 1800 to 1850 psia using auxiliary sprays as directed.

t ~

I I If Appendix H, 'Restore Instrument Air' not completed within 30 minutes of loss of CCW, ensures CCW is NOT restored to I

I RCP's. I II

,~ Stabilizes RCS Temperature as directed.

f------

I I--f---

I Ensures S/G Level 60 to 70% as directed I

I I I"--

Informs NPO to perform Appendix H, 2-EOP-99 restore

,, BOP Instrument Air, as directed (attached page_53-56_)

i L

I, I

II Ii I, I

!, Resets Instrument Air Compressors when notified by NPO I

f-----

Li Aligns and initiates AFW flow to 2A and 2B SG lAW 2-NOP-09.02 (attached page 58-66_)

Ii

(

57

REVISION NO PROCEDURE TITLE PAGE' 2A AUXILIARY FEEDWATER SYSTEM OPERATION 7 of 34 PROCEDURE NO 2-NOP-0902 ST.

ST, LUCIE UNIT 2 4,0 4.0 INSTRUCTIONS INITIAL 4.1 2A AFW PUMP to 2A SfG S/G

1. START PUMP 2A. 2A,

2. OPEN SE-09-2, 2A PUMP DISCH TO 2A S/G VLV, VLV. (KEY 83) 3,

3. THROTTLE MV-09-9, PUMP 2A DISCH TO SG 2A VALVE, as S/G, necessary to establish and maintain desired AFW flow to 2A S/G.

4,

4. WHEN desired level is achieved AND the 2A AFW PUMP is no longer needed, THEN PERFORM the following:

A. CLOSE MV-09-9, PUMP 2A DISCH TO SG 2A VALVE, VALVE.

B. PLACE key switch for SE-09-2, 2A PUMP DISCH TO 2A S/G VLV, to AUTO.

AUTO, IV

( C, C. VERIFY SE-09-2, 2A PUMP DISCH TO 2A S/G VLV, is CLOSED CLOSED, D,

D. STOP PUMP 2A. 2A, E. RETURN PUMP 2A switch to AUTO. AUTO, IV Performed By:

PrinUSign Initials Date Verified By:

PrinUSign PrinUSlgn Initials Date 58

( PROCEDURE TITLE PAGE' PAGE*

REVISION NO 2A AUXILIARY FEEDWATER SYSTEM OPERATION 8 of 34 PROCEDURE NO 2-NOP-09.02 2-NOP-0902 ST. LUCIE UNIT 22 4.2 28 AFW PUMP to 28 S/G INITIAL

1. START PUMP 2B, 28.

2. OPEN SE-09-3, 28 2B PUMP DISCH TO 2B 28 S/G VLV, VLV. (KEY 84)

3. THROITLE MV-09-10, PUMP 28 THROTILE 2B DISCH TO SG 2B 28 VALVE, as necessary to establish and maintain desired AFW flow to 2B 28 S/G, 8/G.

4,

4. WHEN desired level is achieved AND the 2B 28 AFW PUMP is no longer needed, THEN PERFORM the following:

A. CLOSE MV-09-10, PUMP 2B 28 DISCH TO SG 2B 28 VALVE, VALVE.

8. PLACE key switch for SE-09-3, 2B 28 PUMP DISCH TO 2B 28 S/G AUTO.

VLV, to AUTO, IV C. VERIFY SE-09-3, 2B 28 PUMP DISCH TO 2B 28 S/G VLV, is CLOSED.

CLOSED, D. STOP PUMP 2B 28 E. RETURN PUMP 2B 28 switch to AUTO AUTO.

IV Performed By: -.-~-.

~----.----,------~------

PrinUSlgn Initials Date Verified By:

--~----------------------

PrinUSign Initials Date

(

59

REVISION NO PROCEDURE TITLE PAGE:

2A AUXILIARY FEEDWATER SYSTEM OPERATION 9 of 34 PROCEDURE P"<OCEDURE NO 2*NOP-0902 ST LUCIE UNIT 2 ST.

4.3 2C AFW PUMP to 2A I/ 2B SIG S/G NOTE If the 2C AFW PUMP has tripped, 2-0NP-09.02, Auxiliary Feedwater, provides instructions for restarting.

CAUTION When steam is isolated from the 2C AFW PUMP turbine, water may accumulate in the steam supply lines. Starting the pump with accumulated water could result in an overspeed trip.

1. IF this pump start is for post-maintenance testing AND the steam was completely removed from the turbine, THEN PERFORM the following steps:

A. CLOSE MV-08-3, 2C PUMP, by placing the key switch on RTGB 202 in the CLOSE position. (KEY 78)

( B. OPEN MV-08-12, SG 2B STM TO AFW PP 2C.

C. OPEN MV-08-13, SG 2A STM TO AFW PP 2C.

D. AFTER 5 minutes, CLOSE MV-08-12, SG 2B STM TO AFW PP 2C.

E. CLOSE MV-08-13, SG 2A STM TO AFW PP 2C.

F. OPEN MV-08-3, 2C PUMP, by placing the key switch on RTGB-202 in the OPEN position.

position IV

2. IF the 2C AFW PUMP turbine is rotating, THEN PERFORM the following:

following.

A. UNLOCK AND CLOSE V08884, SE-08-2 INLET ISOL.

B. WHEN the 2C AFW PUMP stops rotating, THEN SLOWLY OPEN V08884, SE-08-2 INLET ISO.

C. IF the 2C AFW PUMP does NOT STOP rotating, THEN PERFORM Section 5.4.2.

(

60

(

REVISION NO ReVISION PROCEDURE TITLE PAGE:

2A AUXILIARY FEEDWATER SYSTEM OPERATION 10 of 34 PROCEDURE NO 2-NOP-09,02 2*NOP*09.02 ST, LUCIE UNIT 2 ST.

4.3 2C AFW PUMP to 2A I 2B S/G (continued)

2. (continued)

D. LOCK OPEN V08884, SE-08-2 INLET ISOL.

NOTE An operator will be required at the 2C AFW PUMP local station to verify speed.

CAUTION The 2C AFW PUMP turbine shall not be started if turbine bearing or governor oil temperature is less than 40°F.

3. IF outside air temperature is less than 70 a F, THEN CHECK (by 70°F, pyrometer) turbine bearing and governor oil temperature.

(

A. IF turbine bearing or governor oil temperature is less than 70°F, THEN provisions should be made to warm the oil by external source.

B. IF turbine bearing or governor oil temperature is less than 60°F, THEN 2C AFW PUMP shall be declared OOS.

4. ENSURE the governor oil level is visible between the level mark and top of sightglass.

61

REVISiON NO PROCEDURE TITLE PAGE:

2A AUXILIARY FEEDWATER SYSTEM OPERATION 11 of 34 PROCEDURE NO 2-NOP-09.02 2*NOP*0902 ST ST. LUCIE UNIT 2 4.3 2C AFW PUMP to 2A I 2B S/G (continued)

CAUTION If the oil in the 2C AFW PUMP turbine governor is not allowed to fully drain back to the reservoir, restarting may cause overspeed. This can be prevented by waiting 3 minutes after the pump stops rotating or taking the manual speed control knob on the side of the governor fully counter-clockwise then returning fully clockwise. (Section 7.1.3 Management Directive 3)

5. ENSURE the 2C AFW PUMP Turbine is NOT rotating.

A. VERIFY 3 minutes have passed since pump rotation stopped.

OR B. CYCLE the manual speed control knob on the side of the governor fully counter-clockwise, then fully clockwise.

( 6. START 2C AFW PUMP by performing the following:

following

OPEN MV-08-12, SG 28 2B STM TO AFW PP 2C.

AND/OR

OPEN MV-08-13, SG 2A STM TO AFW PP 2C.

7. VERIFY turbine speed is stable between 3700 and 3800 rpm AND the governor valve is NOT hunting / oscillating,

8. OPEN the solenoid valve(s) in the header(s) to the S/Gs requiring feed feed:

SE-09-4, 2C PUMP DISCH TO 2A S/G VLV (KEY 85)

SE-09-5, 2C PUMP DISCH TO 28 2B S/G VLV (KEY 86)

9. THROTTLE MV-09-11, PUMP 2C TO SG 2A, as necessary to establish and maintain desired flow to 2A S/G.

10. THROTILE MV-09-12, PUMP 2C TO SG 28, as necessary to establish and maintain desired flow to 282B S/G.

62

REVISION NO PROCEDURE TITLE PAGE:

2A AUXILIARY FEEDWATER SYSTEM OPERATION 12 of 34 PROUDURE PROCeDURE NO 2-NOP-09.02 ST. LUCIE UNIT 2 4.3 2C AFW PUMP to 2A I 26 S/G (continued)

11. WHEN the 2C AFW PUMP is no longer being used for feed and it is desired to secure, THEN PERFORM the following:

A. ENSURE MV-09-11, PUMP 2C TO SG 2A, is CLOSED.

6. ENSURE MV-09-12, PUMP 2C TO SG 2B, is CLOSED.

C. PLACE key switch for SE-09-4, 2C PUMP DISCH TO 2A S/G VLV, to AUTO.

IV D. VERIFY SE-09-4, 2C PUMP DISCH TO 2A S/G VLV, is CLOSED.

E. PLACE key switch for SE-09-5, 2C PUMP DISCH TO 2B S/G VLV, to AUTO.

IV F. VERIFY SE-09-5, 2C PUMP DISCH TO 2B S/G VLV, is CLOSED.

G. STOP the 2C AFW PUMP by performing any of the following:

CLOSE MV-08-3, 2C PUMP, with key switch #78 on RTGB-202.

DEPRESS the local TURBINE TRIP pushbutton located on the 2C AFW PUMP TURBINE CONTROL PANEL.

Locally STOP the 2C AFW PUMP by tripping the mechanical overspeed trip lever.

H. VERIFY 2C AFW PUMP turbine is slowing by observing reduction of speed on 2C AFW PUMP TURBINE CONTROL PANEL.

(

63

REVISION RE VISION NO PROCEDURE TITLE PAGE:

2A AUXILIARY FEEDWATER SYSTEM OPERATION 13 of 34 PROCEDURE NO 2-NOP-09.02 ST. LUCIE UNIT 2 4.3 2C AFW PUMP to 2A I{ 2B 28 S/G (continued)

11. (continued)

NOTE

An electrical overspeed trip results in closed indication for MV-08-3, and alarm and reset for annunciator G-46.

A mechanical overspeed trip results in closed indication for MV-08-3, and locked In in alarm for Annunciator G-46.

Closing MV-08-3 alone will result in closed indication for MV-08-3 with no alarm for Annunciator G-46.

I. IF applicable, THEN VERIFY annunciator G-46, 2C AFW PUMP TURBINE FAILURE I/ TRIP I/ OVRLD I/ SS ISOL, is in ALARM.

J. VERIFY the 2C AFW PUMP is NOT rotating.

(

K. ENSURE MV-08-3, 2C PUMP, is reset by placing the key switch on RTGB 202 in the CLOSE position.

NOTE Refer to ATTACHMENT 1 for correct mechanical overspeed mechanism latching.

latching L. IF the 2C AFW PUMP was tripped using the mechanical overs peed trip lever, THEN PERFORM the following:

overspeed (1) RESET the 2C AFW PUMP mechanical overspeed linkage.

(2) VERIFY top surface of trip tappet nut is inline with the line marked on the head lever to ensure full engagement.

IV M. ENSURE MV-08-12, SG 26 2B STM TO AFW PP 2C, is CLOSED.

(

64

(

REVISION NO PROCEDURE TITLE PAGE' PAGE:

2A AUXILIARY FEEDWATER SYSTEM OPERATION 14 of 34 PROCE DURE NO 2-NOP-09.02 2-NOP-0902 ST. LUCIE UNIT 2 4.3 2C AFW PUMP to 2A /28 / 28 S/G (continued)

11. (continued)

N. ENSURE MV-08-13, SO SG 2A STM TO AFW PP 2C, is CLOSED.

O. ENSURE the manual speed control knob on the side of governor is fully CLOCKWISE.

P. OPEN MV-08-3, 2C PUMP, by placing the key switch on RTG6-202 in the OPEN position.

RTGB-202 IV Q. IF the 2C AFW PUMP is rotating, THEN PERFORM the following (1)

(1 ) UNLOCK AND CLOSE V08884, SE-08-2 INLET ISOL.

(

(2) WHEN the 2C AFW PUMP stops rotating, THEN slowly OPEN V08884, SE-08-2 INLET ISOL.

(3) IF the 2C AFW PUMP does NOT stop rotating, THEN PERFORM Section 5.4.2.

(4) LOCK OPEN V08884, SE-08-2 INLET ISOL.

IV

12. ENSURE MV-08-12, SO SG 26 2B STM TO AFW PP 2C, switch is in AUTO position.

IV 65

REVISION NO PROCEDURE TITLE PAGE' 2A AUXILIARY FEEDWATER SYSTEM OPERATION 15 of 34 PROCEDURE NO 2-NOP-0902 2*NOP*0902 ST. LUCIE UNIT 2 4.3 2C AFW PUMP to 2A I 28 SIG (continued) INITIAL

13. ENSURE MV-OB-13, MV-08-13, SG 8G 2A STM 8TM TO AFW PP 2C, switch is in AUTO position.

IV Performed By:

PrinUSign Initials Date Verified By:

PnnUSlgn Initials Date 66

Appendix D 0 Operator Action Form ES-D-2 ES-O-2 I Op Test No.: No. 1 Scenario # 5 Event # _8...,;,_9

..,;8:;,:.,..;;.9____

_ _ _ _ Page 2.2..-

.l2.- 9--""1 of _19'---11

_1__

IE",o'D",,,p'<o" Event

Description:

2C AFW pump trips and MV-09-9 2A AFW pump to 2A SG fails to open, Crosstie 2A AFW pump to feed 2B Steam Generator Time II Position III Applicant's Actions or Behavior I Booth Operator Instructions:

i Indications Available:

I BOP Closes the MSIV's as directed.

~

~-

,,I I

I!

i I I

,i Closes the S/G blowdown and sample valves as directed.

iIr-*

Performs EOP-99 Appendix X section 2 (attached page 68 -

71 J as directed

~

Recognizes 2C AFW pump trips when started. 2B AFW pump

,,iI discharge valve solenoid fails to open.

r-i I I

(

I ,I i

I!

I--

I t

I Li-

"--'~~.

I II I

~

ii iII

~--

1---

iI I .

I I I

I

[

67

REVISION NO.

NO: PROCEDURE TITLE:

TITLE PAGE:

(

36A APPENDICES I FIGURES I TABLES I DATA 115 of 156 PROCEDURE NO.: NO. SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 5 of 8)

Section 2: CONTROL ROOM ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS o 1. ENSURE ONLY ONE MFW Pump is RUNNING, with the control switch in RECIRC.

o 2. ENSURE ONLY ONE Condensate Pump is RUNNING.

o 3. .!f.!1 AFAS has actuated, o 3.1 .!f.!1 AF AS AFAS has NOT actuated and use of Main Feedwater is and use of Main Feedwater is desired, desired, Then PERFORM ALL of the Then PERFORM ALL of the following: following:

( o A. ENSURE AFAS is RESET. o A. ENSURE BOTH S/G [Main FRV] Block valves CLOSED.

o B. ENSURE BOTH S/G [Main o B. For EACH MFW header to FRV] Block valves CLOSED. be placed in service, ENSURE the associated MFIVs are OPEN.

1. MV-09-5

2. MV-09-6 o0 C. ENSURE BOTH Low Power o 0 C. ENSURE BOTH Low Power MIA Stations in MANUAL. MIA Stations in MANUAL.

o0 D. For EACH MFW header to be o0 D. DEPRESS BOTH placed in service, ENSURE push buttons to RESET the pushbuttons the associated MFIVs are Low Power Feedwater OPEN. Valves.

o E. DEPRESS BOTH push buttons o0 E. ADJUST the Low Power MIA to RESET the Low Power Stations AS NECESSARY to Feedwater Valves. control S/G levels.

68

REVISION NO NO.:.. PROCEDURE TITLE: PAGE:

36A APPENDICES I FIGURES I TABLES I DATA 116 of 156 PROCEDURE NO.:NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 6 of 8)

Section 2: CONTROL ROOM ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

3. (continued) oD F. ADJUST the Low Power MIA Stations AS NECESSARY to control S/G levels.

o D G. RESTORE AFW to the standby alignment.

o D 4. ENSURE BOTH Heater Drain Pumps are STOPPED.

o D 5. ENSURE BOTH of the following:

(

oD A. Bearing Oil Pump oD A.1 ENSURE Emergency Bearing Oil and Seal Oil Backup Pump Pump RUNNING.

RUNNING.

o D B. When the turbine reaches 600 rpm, Then Bearing Oil Lift Pump RUNNING.

o D 6. ENSURE the Turbine Drain Valves are OPEN.

o D 7. ENSURE ONLY ONE Turbine Cooling Water Pump is RUNNING.

o 8. VERIFY Turbine Generator Bearing D o D 8.1 DIRECT a field operator to adjust Oil temperature between 110 to TCW to the in-service TLO Cooler 120°F. to maintain outlet Oil temperature between 110 to 120°F.

69

REVISION NO . PROCEDURE TITLE:

TITLE PAGE:

36A APPENDICES /I FIGURES I/ TABLES /I DATA 117 of 156 PROCEDURE NO.

NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 7 of 8)

Section 2: CONTROL ROOM ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS o 9. When Turbine speed reaches ZERO 0 9.1 PERFORM ALL of the following:

rpm, Then VERIFY the turning gear automatically ENGAGES.

o A. PLACE Turning Gear in MANUAL.

MANUAl.

o B. VERIFY the Turning Gear Permissive Light is ON.

o C. Locally ENSURE the Turning Gear is ENGAGED.

(

o D. Locally START the Turning Gear.

o 10.11 10.!f Reactor power history is low, Then CONSIDER reducing steam generator blowdown flow to maintain RCS temperature.

o 11. Place Boron Dilution Alarm o 11.1 !f11 BOTH Boron Dilution Alarm System in Operation. System channels are NOT operating, When indicated Reactor power is Then PERFORM applicable 10-55%,

less than 10. actions of ONP-02.01, Boron Then PERFORM BOTH of the Concentration Control.

following:

o A. ENERGIZE BOTH channels of Startup Nuclear Instrumentation to place the Boron Dilution Alarm System in operation.

o B. VERIFY BOTH Boron Dilution Alarm System Channels are operating.

(

70

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

REVISION NO:

NO PROCEDURE TITLE:

TITLE PAGE:

(( 36A APPENDICES /I FIGURES I/ TABLES /I DATA 118 of 156 PROCEDURE NO.:

NO. SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 8 of 8)

Section 2: CONTROL ROOM ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS NOTE Excessive moisture can build up in CEDMC's room, and impact equipment reliability if 15 KW heaters are not enerqized energized after plant shutdown.

o 11. NOTIFY SNPO to energize 15 KW heater located in the CEDMC's room to minimize humidity build-up per 2-NOP-25.10, CEDMCS Air Conditioning System Operation.

o 12. CONSIDER contacting the Division Load Dispatcher for a switching order

( to OPEN the Main Generator disconnects.

END OF APPENDIX X 71

Appendix D Operator Action Form ES-D-2

~p Test No.:

~p~est I

No. Scenario # 5 Event # _8;;,.:.,..;;.,9 _ _ _ _ Page

_8;;.,:,...,;;9____ 1L

.:!.L ....;..19~-I1 of ~19;;...--11 I! Event

Description:

I 2C AFW pump trips and MV-09-9 2A AFW pump to 2A SG fails to open, Crosstie 2A AFW pump to feed 26 2B Steam Generator I.

I.

Position Ap licant's Actions or Behavior Booth B ooth Operator Instructions:

In dications Available: No AFW flow available r- Ii Ii i Re - diagnose using diagnostic flow chart and exit to EOP-06 I SRO

'Total Loss of Feedwater' Direct STA ST A perform SFSC's for EOP-06 performed every 15 minu minutes.

es.

--I I

I

-~4 Direct HP to perform secondary surveys if not already

,, performed, performed.

,- i ii I

Direct RCS depressurized to 1800 to 1850 psia using auxiliary I sprays if not already performed, performed.

"-- ---- I iI iI

(

I

- ~-.

iI Direct Appendix H, restore Instrument Air, of EOP-99 if not II I already performed, performed.

I

-.--~---

I i

If Appendix H, 'Restore Instrument Air' not completed within 30 minutes of loss of CCW, ensure CCW NOT restored to RCP's if

! not already performed, performed.

,~ .. . -_.

Ii NOTE:

, When en AB Bus is swapped in App-H AFW flow indication on RTGB will be restored, f-- -

I I

I' ---

i i

closing of S/G blowdown and sample valves If not Direct clOSing already a rforme d performed Irea d y pe Ij

---+--

Direct closing of MSIV's if not already performed, performed.

--- I I

r------,

, Direct EOP-99 Appendix X section 2 if not already performed, performed. I

---" I 72

Appendix D 0 Operator Action Form ES-D-2 ES-O-2 r~~~est Op Test No. No_: 1 Scenario # 5 Event # 8, .,;.9____

_8;;.:..' 9 Page lZ..-

_17_ of -.;.;19;"'-'-11

_1;..;.,9--11

,.i!

IIil Event

Description:

2C AFW pump trips and MV-09-9 2A AFW pump to 2A SG fails to open, Crosstie 2A AFW pump to feed 28 2B Steam Generator I

'L-~=====-=--~~~~-=Y--=======---=~~~~~~--~~~______ ===-==-=41

~L_Time Position A licant's Actions or Behavior i Booth Operator Instructions:

I- --

. Indications Available:

i

1

1 SRO

, i I I Critical Direct Replenishing S/G Inventory by using 2-0NP-09.02, I Auxiliary Feedwater Appendix C steps 1A thru 1H (attached I Task page _74-75 _) if not already periormed.

page_74-75_) performed. I I

~

I

~

I!I i-----

i r---------- I I

r--

I

~--

I-- --.--.

+-

I BOP Performs as directed SFSC's for EOP-06 every 15 minutes.

I ..

I RCS depressurized to 1800 to 1850 psia PSI a using uSing auxiliary sprays sp ra ys I Ii RO

~

i

-- --.---~--

---.~----

I SE-02-3 and SE-0204, as directed if not already performed performed.

I

( If Appendix H, 'Restore Instrument Air' not completed within 30 I I

minutes of loss of CCW, ensures CCW is NOT restored to Ii I

RCP's.

I I

1------ --~-~---- ..-

I Periorms Appendix H, restore Instrument Air, of EOP-99.as Performs BOP

~-- - _o-._--- I, f directed if not already performed.(attached) periormed.(attached) r- -----

I Contacts NPO to perform local steps in Appendix H, restore

~

iI I Instrument Air, of EOP-99 if not already performed.

.- ----- ------------+-

-~------ --.-.f-- -----

~---

iI Resets Instrument Air Compressors when notified by NPO if

!: I not already performed.

periormed.

i I, r-I I Closes the MSIV's as directed if not already performed.performed .

r--..._ - - - - - --- - I

! 1I

--~.-,---

.~-

I 73

(

REVISION NO PROCEDURE TITLE PAGE PAGE.

11 AUXILIARY FEEDWATER PI,OCEDURE NO PllOCEOURE 19 of 29 2-0NP-09,02 2-0NP-0902 ST, LUCIE UNIT 2 ST.

APPENDIX C CROSS-CONNECTING AFW (Page 1 of 4)

INITIAL NOTE If cross-tying AFW in Modes 1 - 3, Then the motor driven pump not being used to supply SGs must be declared out-of-service per the applicable Tech, Tech. Spec, Spec.

1,

1. !fif 2A AFW Pump is to feed 28 S/G, Then PERFORM the following:

A. ENSURE MV-09-10, Pump 28 Disch To S/G 28 Valve, is CLOSED, CLOSED B. START ST ART Auxiliary Feedwater Pump 2A.2A, C. OPEN SE-09-2, 2A Pump Disch To 2A S/G Vlv Key 83, 83. -- -- -

CAUTION Opening both MV-09-13 and MV-09-14 while In in Modes 1, 2, 3 could make

( two Independent independent AFW flow path inoperable.

NOTE Key-switches for MV-09-13 and MV-09-14 are located in 2A128 AFW Pump Room Two keys are required since the keys are removable in CLOSE only, only.

D. Locally OPEN MV-09-13, 2A To 28 AFW Hdr Cross-tie.

NPO E. Locally OPEN MV-09-14, 28 To 2A AFW Hdr Cross-tie.

Cross-tie, NPO CAUTION Ensure total pump flow does not exceed 425 QPm, qpm.

F, F. THROTILE MV-09-10, Pump 28 Disch To SG 28 Valve, to establish desired flow rate, rate.

NOTE While feeding both S/Gs indicated flow is pump flow to both S/Gs.

S/Gs, G. To feed the 2A S/G, THROTTLE MV-09-9, Pump 2A Disch To SG 2A Valve, to establish desired flow rate.

(

74

(

REV'SION NO PROCEDURE TITLE PAGE:

PAGE 11 AUXILIARY FEEDWATER 20 of 29 PROCEDURE NO 2-0NP-09.02 2-0NP-0902 ST. LUCIE UNIT 2 APPENDIX C CROSS*CONNECTING AFW (Page 2 of 4)

1. (continued) INITIAL H. When the system is to be returned to normal, Then PERFORM the following:

following

1. CLOSE MV-09-10, Pump 2B Disch To SG 28 2B Valve.

2. !! 2A S/G If is being fed, Then CLOSE MV-09-9, MV-09-9. Pump 2A Disch To SG 2A Valve.

3. STOP Auxiliary Feedwater Pump 2A.

4. CLOSE SE-09-2. 2A Pump Disch To 2A S/G Vlv Key 83.

S.

5. Locally CLOSE MV-09-13, 2A To 28 AFW Hdr Cross-tie.

NPO

6. Locally CLOSE MV-09-14, 28 2B To 2A AFW Hdr Cross-tie.

NPO

7. PERFORM Independent Verification of the following:

COMPONENT POSITION IV INITIAL MV-09-9, Pump 2A Disch To SG 2A Valve MV-09-9. CLOSED MV-09-10. Pump 26 MV-09-10, 28 Disch To SG 262B Valve CLOSED SE-09-2, 2A Pump Disch To 2A S/G Vlv Key 83 SE-09-2. CLOSED MV-09-13, 2A To 26 MV-09-13. 28 AFW Hdr Cross-tie CLOSED MV-09-14. 26 2B To 2A AFW Hdr Cross-tie CLOSED NOTE If cross-tying AFW in Modes 1 - 3, Then the motor driven pump not being used to supply SGs must be declared out-of-service out-of*service per the applicable Tech. Spec.

2. !!Lf 2B AFW Pump is to feed 2A S/G, Then PERFORM the following:

A. MV-09-9, Pump 2A Disch to 2A SIG ENSURE MV-09-g, S/G Valve, is CLOSED.

B. START ST ART Auxiliary Feedwater F eedwater Pump 2B.2B C. OPEN SE-09-3, 28 Pump Disch To 28 2B SIG S/G Vlv Key 84.

(

75

Appendix D Operator Action Form ES-D-2

(

,I:

r,....-"***-~----*---

\, I'I! Op Op TestTest No.:No 1 1 Scenario # 5 Event #

Event# _8;..:.,;..:.9

_8.;.,;,,,.,,9______ _ Page ~ of _1;..,..9--11

_19'---11 I

I D IiI Event Description escnptlon: 2C AFW pump trips and MV-09-9 2A AFW pump to 2A SG fails to open, il Crosstie 2A AFW pump to feed 2B Steam Generator

~

~~

~me II Position II Applicant's A licant's Actions or Behavior r-----------------------------------,

I Booth Operator Instructions:

Tndications Indications Available:

f-i-~---T I!I Closes the S/G blowdown and sample valves as directed if not

!I I

, I :I already performed.

i I

~

--- ------ ----t-~-+-=--~~--------,-,---,~~-,-----::-------------I Performs EOP-99 Appendix X section 2 as directed if not

!I i already performed.

. . , . - - - - - - - - - - - + - - - - " - - - - - ' - - - - - - - - - - - - - - - - - - - - - - - - - - - i;

- ,,---- ..-.----._t_-.-

-.--.----~'

i

-i-- -- --

-- ---'--I--

---t----- ---- --- -- -- --- ----

------- -- ---- 1 j I BOP I I Critical Critical Replenishes S/G Inventory by using 2-0NP-09.02, Auxiliary I Feedwater Appendix C steps 1A 1A thru 1H as directed.

directed, Contacts

~_ --+_T_a_s_k_---+-N_P_O_t_o_p_e_rf_o_rm_s_te_p_s_(_a_tta_c_h_e_d__a__e___7_4_-7_5_______

Task NPO to perform steps (attached page_74-75_) p g l

---1

( :

~----~------------------------~

.N NOTEOTE: When NPO locally opens MV-09-10 MV-09-1 0 this may cause an AFAS-1 lockout so 1-SE-09-2 will need to be opened opened..

. -----------------,-----------------------------1 I

------i:

--- - - - - - i- - - - + - - - - - - - - - + - - - - - - - - - - - - - - - - - - - - - - - - - - - - - i

' - ---_o-I

1--------------"1--------------------------------1

~--------+------t-------------------------------i i -- - - - - -!- : - - - - - - - \ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 j

L--

1--

L.

i I iI

- - t - - - - - - - - - + - - - - - - - - - - - - - - - - - - - - - - - - - - - - - i Suggested termination point:

- 2A Diesel output breaker has been closed and II

---~-~--

-.----~--

- 2B S/G is being fed by the 2A AFW pump.

'------------------------------' I 76

Scenario Event Description NRC Scenario 7 Facility: SL St. Lucie Scenario No.:No,: 7 Op Test No,:

No.: HLC-19 NRC Examiners: Operators: SRO:

RO:

BOP:

Initial Conditions: 40% power, IC-72, xenon building in approximately 3177 pcm, 6 gpm dilution to the suction of the Charging pumps, pumps. 2C Charging pump OOS for repack, repack. NOTE: Open FCV-12-3C 2C Cond, Condo PP recirc, recirc. and start the condensate transfer pump, pump.

f-----.

~--" .-.

-~-

Turnover: 40% power, 2C Charging pump OOS for repack, repack. Unit was down powered to remove 2B Condensate from service due to motor oil leak, leak. The 2C Condensate pump is ready to be started, started. Return to 100% power when 2C Condensate pump and 2B MFW pump are running, running.

Critical Tasks: Tasks

Stop all RCP's upon loss of all CCW I!

Event Malf.

MaiL Event I Event No, No. No, No. Type' Description 1 R I All Start 2C Condensate Pump, Pump. Unit up power to 100%

( N/BOP 2 1 1/ RO TIC-2223 Letdown Temperature Controller malfunction, malfunction. V2520 ion exchanger bypass, does not close, close.

e--------

e-'

3 2 T,S, T.S. SRO RWT LIS 07-2B fails low 4 3 IIII RO FCV 2210X, 221 OX, primary water controller output fails high, high.

1--- - - ' - " - !--...

1---- '"------ 1-----

5 4 C/BOP RIM 26-61 fails high, high. CROAI valve FCV-25-16 trips on overload.

overload, T,

T. S, S. SRO HVE-13A does not auto start, when HVE-13A manually started, fan trips.

trips,

--"--~-'

6 5 C/BOP 2A Intake Cooling Water pump sheared shaft shaft.

7 6 M I All pressure, Plant down power I Unit trip Loss of Instrument Air pressure.

8 7 C/RO Three CEA's do not fully insert, insert. Emergency Borate

--- .-~---

~-"-~--- , ----

9 8 C/RO Stop All RCP's due to CCW valve closure on loss of air f-,----

Natural Circulation Cooldown I Depressurizarion 1----- _._._-

--~

10 9 M M/AIII All 2B2 RCP seal failure resulting in a LOCA

.. -.---.~.

k (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

,----~-------------------~~--------------------,

Scenario Event Description NRC Scenario 7 st. Lucie Unit was down powered to 40% power. 2B 28 Condensate pump has been removed from service.

2C Condensate pump is ready to be started. 2C Condensate pump started, raise power to 100%.

TIC-2223 Letdown Temperature controller malfunctions requiring manual control. When high temperature is reached, Ion Exchanger bypass valve V2520 does not close. Manual closure will be required.

RWT level transmitter LIS 07-2B 07-28 fails low. SRO to evaluate T.S.

FCV 221 OX controller fails high resulting in maximum dilution to the suction of the Charging pumps. Manual control will be needed to stop dilution.

RIM 26-61 fails high. This will result in Control room recirc. on the A train, however FCV 25-16 trips on overload and HVE-13A will not start. When HVE-13A is manually started, it will also trip.

SRO will be required to evaluate T.S.

2A Intake Cooling water pump will experience a sheared shaft. The 2C Intake Cooling water pump will be started in its place.

A loss of Instrument air requires a plant shutdown. Eventually a total loss of Instrument air occurs resulting in a manual trip. Upon the plant trip three CEA's will not fully insert requiring emergency boration boration. Due to loss of air, CCW to the RCP's will close requiring all RCP's to be stopped.

2-EOP-09 LOOP / Loss of Forced Circulation will be entered. Cooldown and depressurization will be required. During the cooldown, 2B2282 RCP seals will fail resulting in a LOCA. The crew should exit 2-EOP-09 and enter 2-EOP-03 Loss of Coolant Accident.

The scenario may be terminated when the crew is implementing 2-EOP-03 and a controlled cooldown is being implemented.

Procedures Used

2-GOP-201, Reactor Plant Startup Mode 2 to Mode 1

2-GOP-1 01, Reactor Operating Guidelines During Steady State and Scheduled Load Changes

NOP-100.02, Axial Shape Index Control

2-NOP-12.03 Condensate System Operation

2-0NP-02.03, 2-0NP-0203, Charging and Letdown

2-0NP-0902, 2-0NP-09.02. Auxiliary Feedwater

2-0NP-25 02, Ventilation Systems 2-0NP-25.02.

2-0640030, Intake Cooling Water System

2-NOP-21.03C 2C Intake Cooling Water Pump Operation

2-1010030, Loss of Instrument Air

2-NOP-100.02, Rapid Downpower

2-EOP-01. Standard Post Trip Actions 2-EOP-01,

2-EOP-09, Loss of Offsite Power / Loss of Forced Circulation

2-EOP-03, Loss of Coolant Accident Technical Specifications Entered 2

~~~--'--------"-'-

Scenario Event Description NRC Scenario 7

3.7.7 Control Room Emergency Ventilation System

3.3.2 ESFAS table 3.3-3

(

3

Appendix D Operator Action Form ES*D*2 ES-D-2

.r--~-~~~~~~~--~--~~~~~=-~~~~~~~=-~~~~~~

IIil Op Test No.: No_ 1 Scenario # 7 Event # ...;..._ _ _ _ Page i--

_4_ ...;..20~"'1 of _2..;;.0---."

i:1 Event

Description:

Raise power to approximately 45% and start 2C Condensate pump. pump_ Perform up Ii power power t::T~I~m~e_db~p~O~S~iti~On~db_~

bnm' Position ____ =-==_~A~I~ic~a~nt~'s~A~C~tio~n~s~o~r~B~e~ha~v~io~r A licant's Actions or Behavior _ _ _ _ _ _ _d r

, Booth Operator Instructions: From NPO, inform the crew Appendix F of 2*NOP* 2-NOP-12.03 Condensate System Operation up to step 15 is complete. Also when the 2B 1_ Main Feedwater pump is to be started, state 4.5.13 is ready to be implemented implemented..

, Examiners Note: Crew may elect to start the 2C Condensate pump and 2B MFW iI pump prior to 45% power.

f-----,._-----

1-

, Direct power ascension lAW 2-GOP-201 Reactor Plant Startup SRO

- Mode 2 to Mode 1 (attached page_5-7_) page_5-7 _)-.

, .- --- --------------+-----------1

-_. - -------+--1I -------------i-----

! Direct RO to increase dilution rate to raise power lAW 2-NOP-I 02.24 Boron Concentration Control (attached page_B*1 page_8-1 0_). i

. . . -----+--**1

~-- i --------1

_--+

___j___

r'- ' '~-'

I 1 __ Direct-RO Direct RO to withdraw CEA's lAW 2-GOP-1 2.GOP.1 01 (attached I

~~-~----~--_I---

page_11,12_)

g

.. i

.- .. ~ .

_---+---1p_a_e_-_11_,1_2_-)_ _ _ _ _ _ _ _ _ _ _ _ _ _ j

( Implement 2-NOP-12.03 2-NOP-12,03 Condensate System Operation,

'- Appendix F, step 15 (attached page_14_). Start the 2C Condensate pump lAW 2-GOP-201 step 6.130.7 at I approximately 45% power. When 2C started, direct recirc FCV* FCV-

_.__.. -._~--~-1-2---3-C-C-lo-s-e-d-...- _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

12-3C closed.

~---- ...----i - - ..-- +- -- - -- -- --+ - ----

+ -- --- --- -- -- -- --- -- ----- - - - - - - - - - - - - ,

i ! When 2C Condensate pump has been started start the 2B I Main Feedwater pump lAW 2-NOP-09.01 Main Feedwater I System step 4.5.13 (attached page_15_). page 15 ).

1-----

f* ..- - - - - - i - - I* - - - - j - - - - - - - --- --- - - - - - - - -

+---

t-~---II,.------+-----------------I

,- ------------+----

When 2C Condensate and 2B Main Feedwater pump have

, been started, direct power increase toward 100%.

I ..---.....

,."~----~.-

1--_-+-~~

-.-_t-

-.........- - l - - - - - + - - _

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

~ ~

Raise dilution rate for power increase lAW 2-NOP-02,24 2-NOP-02.24 Boron RO

____ ~i _____ i* Concentration

- Control step 6.5.12 (attached page_B-10_) page_8-1 0_)

-~-----~-

- I

.. -t***---+-W-it-hd-r-a-w* - Withdraw- CEA's to control Rx power and ASI lAW 2-GOP-1 01 ~

Rx Operating Guidelines step 6.1 (attached page_11_) v I I i

CEA Withdrawal, select MS on the CEDMCS J

CEA Withdrawal, select MS on the CEDMCS I Control Switch

~_____

IN/HOLD/OUT Switch to the OUT direction

~-----~------~~

4

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

--~---------~------

REVISION NO REVISION NO PROCEDURE TITLE.

PROCEDURE TITLE PAGE:

PAGE 1-_.--;.6..;..0 1-_ _5;.,.;0_ __ _ -iREACTOR PLANT STARTUP - MODE 2 TO MODE 1

--iREACTOR 54 of 69 59 PROCEDURE NO 2*GOP-201 2*GOP*201 ST_

ST. LUCIE UNIT 2 6.129 (continued) INITIAL

7. (continued)

I NOTE NOTE The following step will transfer the DEHOEH System S.l'stem to automatic control.

II I. DEPRESS Oper Auto.

J. REMOVE Maintenance Test Key.

8. REMOVE the Impulse Pressure Feedback Loop from service as follows' follows A. DEPRESS Imp In/ImpInllmp Out.

B. VERIFY Imp Out light is LIT.

6.130 When Reactor Power is at approximately 45% as indicated on the highest reading instrument, Then PERFORM the following:

1. STOP the power ascension.

2. §,

§1 PERFORM a Nuclear I/ Delta T power calibration in accordance with 2-0SP-59.01, 2-0SP-69.01, Nuclear and Delta T Power Calibration.

3. if11 NOT performed at 30% Reactor Power, Then NOTIFY SCE or I&C to perform DCS Steam Generator Feedwater Discharge Coefficients Verification per 2-NOP-102.01.

/ IC SCE IIC

4. ]lNOT performed at 30% Reactor Power, Then ENSURE

!iNOT scheduled incore surveillance has been performed.

5. !f if NOT performed at 30% Reactor Power, Then ENSURE the Ineore Incore Detection System is OPERABLE in accordance with OSP-64.01, Reactor Engineering Periodic Tests, Checks and OSP*54.01, Calibrations.

6. 1111lhe the Condensate Polisher is in service, Then ENSURE enough Powdex vessels are in service to support the increase in flow.

condensate fiow.

7. START the second Condensate Pump in accordance with START 2-NOP-12 03, Condensate System Operation 2-NOP-12.03.

5

REVISION REVISION NO NO PROCEDURE PROCE DURE TITLE TITLE PAGE:

PAGE 60 REACTOR PLANT STARTUP - MODE 2 TO MODE 1 1---..;..;;.----1 f---"':;"';~---; 55 of 69 PROCEDURE NO NO 2-GOP-201 ST.

S1. LUCIE UNIT 2 6.130 (continued) INITIAL

8. ENSURE the second Main Feed Pump is ready to start in accordance with 2-NOP-09.01, 2-NOP-0901 , Main Feedwater System Operation.

9. WARMUP the Heater Drain Pumps in accordance with 2-NOP-11.02, Heater Drain and Vents System Operation

10. VERIFY proper operation of heater Drain and Vent system.

A. VERIFY proper heater levels.

B. VERIFY proper operation of normal and alt drain valves.

CAUTION The second Main Feed Pump should NOT be started until the second Condensate Pump is running and total feedwater reedwater flow is approximately 10,000 GPM.

GPM

11. IF Condensate Polisher System is in service, THEN ENSURE

( that four polisher vessels are in service or as recommended by Jj (Jl o

Chemistry.

12. START the second Main Feed Pump in accordance with 2-NOP-09.01.

2-NOP-09.01

13. When total feedwater flow is between 15,000 GPM and 20,000 GPM, Then:

Then A. PLACE the second Main Feed Pump control switch in AUTO RECIRC.

B. VERIFY the Recirc Valve CLOSES.

CAUTION The power ascension should be stopped Ifif Main Feed Pump suction pressure decreases to less than 400 psig. psiq.

6.131 VERIFY the Moderator Temperature Coefficient is within limits as specified in TS 3.1.1.4.

3.1 14.

RE Date 1I Time _ __ __ __ __ _ -'1'--1 6

REVISION NO REVISION NO PROCEDURE TITLE' PROCEDURE TITLE PAGE.

PAGE.

60 _ _-iREACTOR 1--_-..:::.6,:..0 REACTOR PLANT STARTUP - MODE 2 TO MODE 1 1----..;.;..----1 56 of 69 PROCEOURE NO PROCEDURE 2-GOP-201 ST. LUCIE UNIT 2 INITIAL 6.132 ~6

~6 When Reactor Power is at approximately 50% as indicated on the highest reading instrument.

instrument, Then PERFORM the following:

1. ENSURE PCV-08-808.

PCV-08-808, Gland Steam \0 to HP Seal Stm, is CLOSED.

CLOSED

2. CLOSE valve V0880?V08807, PCV-08-808 Bypass.

3. ENSURE both Turbine Cooling Water Pumps are in operation. operation A. CLOSE SB 13139, TCW Pumps Disc Crosstie Isol.

S813139, NOTE Margin improvements Improvements may be captured in a future reload PCMs. This will delete the requirement for a specific Nuclear Delt T Power Calibration at power.

50% Rower.

4. VERIFY the specific stop at 50% power is NOT required to perform 2-0SP-69.01, 2-0SP-69 01, Nuclear Delta T Power Calibration.

Calibration, in

( accordance with the current Reload PCM.

PCM _ __ __ __ _ __ ____ Date _ __ __ ____ __

RE NOTE If 2-0SP-69.01 IS is NOT required due to Reload PCM, then the following two substeps may be marked N/A.

5. STOP the power ascension.

6. §,

§1 PERFORM a NuciearlDelta Nuclear/Delta T Power Calibration in 2-0SP-69.01, accordance with 2-0SP-69 01, Nuclear and Delta T Power Calibration 6.133 When Reactor power is approximately 60%, 60%. as indicated by the higher of Calorimetric or NI Power, Then PERFORM the following:

1. VERIFY proper heater levels.

2. VERIFY proper operation of normal and alt drain valves.

6.134 When Turbine load is approximately 660 MW, Then PLACE the Heater Drain Pumps in service in accordance with 2-NOP-11.02, Heater Drain and Vents System Operation.

7

~----

REVIS'ON REVIS'O"l NO PROCEDURE TITLE PAGE 24A BORON CONCENTRATION CONTROL 190f75 19 of 75 PROCEDURE NO 2-NOP-0224 ST LUCIE UNIT 2 6.5 6,5 Aligning for MANUAL Dilution NOTE

An Operator Aid has been placed at RTGB-205RTG8-205 PNL "N". Any revision to this section of the procedure shall verify the validity of the Operator Aid and, if changes are necessary, a Label Request shall be initiated to incorporate these changes on a new Operator Aid placard.

Incorporate placard

The Operations Supervisor SHALL be notified and a CR submitted of any unexplained or unplanned Reactivity change in accordance with OPS Policy 534 (i.e,(i.e., >5

> 5 deg Tcold change or >5%>.5% power change).

change)

If a Reactivity management Issue issue occurs, refer to procedure ADM-09.11, ADM-0911, Reactivity Management.

If constant dilution ISis desired deSired then ensure fiow ftow on FIC-2210X FIC-221 OX is observable

Engineering Assessment of FIC*2210X FIC-2210X PMW Flow, shows that there could be an error up to -+/- 0.5 gpm, and the recommended minimum fiow rate is 2 gpm ftow gpm

1. DODD ENSURE Section 30, 3.0, Prerequisites is completed at least once

( per shift

2. DODD ENSURE SectIOn Section 40, Precautions I/ Limitations, has been reviewed at least once per shift.

3. DODD ~2 ENSURE calorimetric power is IS less than 10000%

100.00% prior to any dilutions by obtaining a DCS calorimetric power.

power

4. DODD DETERMINE the desired volume of primary water to be added.

5. DODD PLACE the Makeup Mode Selector switch in MANUAL

6. DODD ENSURE FIC-2210X, PMW Flow, IS is In in MANUAL and REDUCE the controller output to ZERO.

7. DODO DODD ENSURE FIC*2210Y, FIC-2210Y, Boric Acid Flow is in MANUAL and REDUCE the controller output to ZERO.

8,

8. DODD ENSURE either Primary Makeup Water Pump IS 0000 is running.

running 9,

9. DODD PLACE FCV*2210X, 0000 FCV-2210X, Primary Makeup Water Control Switch In in Auto.

DODD 11 diluting to the VCT. Then OPEN V*2512, ;0 35

10. 0000 V-2512, Reactor Makeup Water Stop Vlv '":P>>A A

11.

11 . DODO 11 diluting to the Charging Pump suction, Then OPEN V*2525, 0000 V-2525, ;0 Boron Load Control Valve.

Valve '":P>>A

'V A

(

8

......*----...... -.-.--------~

REVISION NO PROCEDURE TITLE:

TITLE PAGE:

PAGE 24A BORON CONCENTRATION CONTROL 20 of 75 PROCEDURE NO 2-NOP-02.24 2-NOP-0224 ST. LUCIE UNIT 2 6.5 6,5 Aligning for MANUAL Dilution (continued)

CAUTION To preclude lifting the VCT relief valve while using V-2525, V*2525, do NOT allow PMW flowrate to exceed the running Chargingpump(sJ Charging pump(s) caJJ.acity.

capacity.

12. DODD ADJUST FIC*2210X DODO FIC-2210X PMW Flow In in AUTO or MANUAL to desired flowrate (and If using V-2525 V*2525 do NOT exceed the flowrate for the number of running Charging Pumps). Pumps) 13.

13, DODD MAINTAIN VCT pressure less than or equal to 30 psig by 0000 opening and closing V2513, VCT Vent, as needed.

14.

14, DODD if11 necessary to maintain the desired VCT level, Then DIVERT 0000 the letdown flow to the Waste Management System by placing V2500, VCT Divert Valve, in the WMS position: position A.

A, 0DODD 0 0 0 ENSURE V2500 VCT Divert Valve indicates OPEN OPEN.

B.

B, 0000 0 0 0 0 When the desired deSifed VCT level is reached, PLACE

( V2500 In in AUTO.

AUTO C.

C, 0DODD 0 0 0 ENSURE V2500 indicates CLOSED CLOSED.

15.

15, 0DODD 0 0 0 When the desired amount of primary water has been added, Then CLOSE FCV*2210X, FCV-2210X, Primary Makeup Water 16, DODD if DODO 11 V*2512 V-2512 Reactor Makeup Water Stop Vlv was opened, Then PLACE V-2512V*2512 in CLOSE and ENSURE it indicates CLOSED. CLOSED 17,

17. DODD 00 0 0 if 11 V-2525 V*2525 Boron Load Control Valve was opened, Then PLACE V-2525 in CLOSE and ENSURE it Indicates indicates CLOSED.

18.

18, 0000 ENSURE FIC*2210X, FIC-2210X, PMW Flow controller is In in MANUAL and RECUCE output to MINIMUM 19,

19. DODD DODO MONITOR for any abnormal change in Tave 20.

20, 0DODD 0 0 0 §, §1 RECORD on Data Sheet 1, Boratlon Boration I/ Dilution Log, the number of gallons of Primary Makeup Water added as indicated on FQI*2210X, Indicated FQI-2210X, PMW Flow Totalizer.

Totalizer 21.

21, 0DODD 0 0 0 if11 additional dilutions are desired, or if the expected changes to Tave Toye or Boron concentration are NOT achieved, Then REPEAT Steps 65.16 5.1 through 6.5.20 --

u

ij

~--------------------------------------------------_ _ _ _ _ _ _ __ J ~;pPA

(

9

REVISION rlEv'SION NO PROCEDURE TITLE PAGE:

PAGE' 24A BORON CONCENTRATION CONTROL 21 of 75 PROCEDURE NO 2*NOp*0224 2-NOP-02.24 S1. LUCIE UNIT 2 ST.

6.5 Aligning for MANUAL Dilution (continued)

22. o0 0 0 00 Uit is desired to restore the Boron Concentration Control

)J system to the Automatic Mode of Operation, Operation. Then REFER to Section 6.1.

6.1, Aligning for Automatic VCT Makeup.

23. After review by the Unit Supervisor is complete, this document may be discarded.

discarded END OF SECTION 6.5

(

10

REVISION NO PROCEDURE TITLE PAGE 9B 1--_---.,;9;,.;B;."...-_--i REACTOR OPERATING GUIDELINES DURING STEADY STATE 6 of 15 i-P-RO-C-E-D-UR-E-N-O------1 PRocmURE NO STATE AND AND SCHEDULED LOAD CHANGES 2-GOP-101 ST. LUCIE UNIT 2 6.0 INSTRUCTIONS 6.1 Power Level Escalations NOTE CEAs should be above the Long-term Steady State Insertion Limit (102 inches withdrawn on Group 5) before reaching 20% core power and at a position to begin controlling ASI at the ESI between 20% and 50% power. power Refer to NOP-1 00.02, Axial Shape Index Control, for further guidance.

1. As Main Generator loading commences, MAINTAIN T-avg T -avg at T-ref T-ref by:

by A. CEA withdrawal in Manual Sequential.

AND/OR B. Boron concentration changes in accordance with 2-NOP-02.24, Boron Concentration Control.

2. At or above 50% power

( A. All planned reactivity additions should be made by boration or dilution in accordance with 2-NOP-02.24, Boron Concentration Control.

B. USE CEAs for ASI control, CONSIDER the reactivity effect of CEAs when adjusting AS!.

ASI.

C. REFER to NOP-1 00.02, Axial Shape Index Control, for specific instructions regarding ASI control during power escalations.

D. 111

~1 When raising Reactor power, all power escalation rates should be within the following fuel preconditioning guidelines:

Max Equivalent Turbine !

f/ category Max Core Power Escalation Rate Max G EqtUlvaLlendt TRurtbine I Generator enera or Load oa Rateae Ij r'- 1f-- -- 3%/HR at or above 15% Power 1*_--- .- .---

i

~---

.42 MW/MIN MW/M1N I

i-3--~--,=1;:1~~

, .. " . - -2'

~_.?

20%/HR aabb';;;' 55%~;,PpOo:e;c-1 above 50% Power i 2~O ~~~ ~N

"-3%iHR above 50% Power . --.-+-----'----'-'--'..:.:..:..:.-'-----1

.42 MW/MIN 2.80 MW/MIN I

~

,_ 4 I 30%/HR above 50% PowerP0'Ner i 4.2 MW/MIN i 11

REVISION NO PROCEOURE PROCEDURE TITLE PAGE 9B 9S REACTOR OPERATING GUIDELINES DURING STEADY I-P-RO-C-E-O-UR....:E:..;N;;..O-..- - - I I-P-R-OC-E-D-U-R.::..E;;:.NO----l STATE AND SCHEDULED LOAD CHANGES 7 of 15 2-GOP-101 ST. LUCIE UNIT 2 6.1 Power Level Escalations (continued)

2. D. (continued)

NOTE To determine the correct category for a power escalation, Appendix B, S, Fuel Preconditioning Guidelines Worksheet, may be used. Contact Reactor Engineering ifIf further assistance is required.

Category Definitions:

Definitions

1. Category 1 1:.

a. INCREASE in power to a level which has not been previously sustained in this core cycle for at least 72 continuous hours.

2. Category 2:2

a. INCREASE in power following 30 continuous days or more at a power level less than 70% of rated thermal power.

( OR

b. INCREASE in power to a level which has not been maintained for more than 3 continuous hours during the past 60 days.

3. Category 3:3

a. INCREASE in power to a level which has not been maintained for 3 continuous hours or more during the past 8 days.

4. Category 4:

a. INCREASE in power to a level which has been maintained for 3 continuous hours or more during the past 8 days.

3. !f11 available, Then ENSURE two Charging Pumps are operating.

If necessary, START an additional Charging Pump in accordance with 2-NOP-0202, Charging and Letdown.

4. PLACE the Pressurizer on recirculation in accordance with Appendix A, Pressurizer Recirculation GUidelines.

Guidelines.

5. CONTINUE to load the Main Generator in accordance with 2-GOP-201 2-GOP-201,,

Reactor Plant Startup, Mode 2 to Mode 1 1.

END OF SECTION 6.1 12

Appendix D Operator Action Form ES-D-2

( . Op Test No. 1 Scenario # 7 Event # _ _ _ _ _ Page _5_

_5 _ oof ~

f ...;2;.;.0--11 IiII Event Descnption:

Description Raise power to approximately 45% and start 2C Condensate pump. Perform up II

.,:i power I I';1 fl.I'~~====~~~~==y-==================-.-~~--~~~----~--==--~I

]I L

.~_-~~P~o~s~iti~on~~=====-____==~A~~lic~a~nt~'s~A~c~tio~n~s~o~r~Be~h~a~vi~o~r============~

Position A licant's Actions or Behavior II

Booth Operator Instructions:

Indications Available:

I ff------*--*-*-~----_,_-----------------------__j

.. -.---.- -~---,,------------------------

! Control Rx power and ASI ASIIAWlAW 2-GOP-1 01 Rx Operating RO I Guidelines i - - - - - - + - - - - - - - - - - - - -page_11-12_)

step 6.1 (attached page_11-12_l

,-...- - - - + ---------------1

!, .--. - .--+--------~--------.----------------__i

, Program DEH ffor increase at a rate IA or power Increase lAW -

W22-GOP-101 GOP -101 I step 6.1.2.D 6, 1.2.D Category 4. I I I II

Set reference by ensuring REF selected and then II BOP depress desired MW endpoint, select ENTER I

I

- Depress LOAD RATE type in desired load rate and I

select ENTER

- - -.. - - - - t - - - -

I I

- Depress GO pushbutton 0-lI, i I ,I

! I Communicate with NPO, make plant announcement, and and start 'I:

i 2C Condensate pump lAW 2-NOP-12.03 Condensate System I Operation, Appendix F (attached page_14_l* page_14_). When directed,

--i---I ___ ~_tify notify NOP to close FCV-12-3C 2C recirc, recirc. I

+ I I

I I Communicate with NPO and start the 2B Main Feedwater1 I pump lAW 2-NOP-09.01 (attached page_15_)

page_15_l Main Feedwater 1,

,_._._- !i I Feedwater System

--+:-----

---+-

. ----*----1----* I

--+-I-------------------------------.j

- --.----------i

. __ +~-I--i---

~

-+

}-- --

.--------- * *

l i

I

--~--

I ._ ...

.~-.

I

___ _-.-L___________ ----- --._ .._ - - - - - - - - - - - - - - -

REV!SION NO PROCEDURE TITLE PAGE 3 CONDENSATE SYSTEM OPERATION 39 of 85 PROCEDURE NO 2-NOP-1203 ST. LUCIE UNIT 2 APPENDIX F 2C CONDENSATE PUMP START WITH THE CONDENSATE HEADER PRESSURIZED (Page 4 of 4)

CHECK

14. OPEN FCV-12-3C, 2C Condensate Pump Recirc in preparation for pump start.

A.

A, PLACE the recirc recire handswitch handswiteh for FCV*12-3C, 2C Condensate Pump Recirc Recifc in the OPEN position.

position

8. VERIFY FCV-12-3C, 2C Condensate Pump Recifc Recirc is OPEN.

OPEN

15. AFTER the Recirc Valve has been opened for at least 10 minutes, START the 2C Condensate Pump locally or at RTGB-202.

16. VERIFY the flow on FIC-12-1, Condensate Recirc to Cndsr, controller remains approximately 10,000 GPM (50% of scale). ---

17,

17. CLOSE recirc valve for the 2C Condensate Condensate Pump.

( A. PLACE the handswitch for FCV-12*3C, FCV-12-3C, 2C Condensate Pump Recirc in the CLOSED position. ---

B. VERIFY FCV-12-3C, 2C Condensate Pump Recirc Recire is CLOSED.

CLOSED,

18. SECURE Condensate Transfer Pump, Pump. ---

1 g,

19. CLOSE V12494 - Condensate Transfer Pump Discharge Valve.

NOTE The Idle idle condensate pump seal water isolation valve should be opened to minimize potential air intrusion when vacuum is established in the main condenser.

condenser

20. THROTTLE OPEN the individual seal water supply valve to the idle condensate pump as per US I SM direction:

1-i----------------C-o-M~P-O-N-E-N-T----------------'Ii---P-O--SI-T-IO-N----.-C~H-E-C-K~

COMPONENT POSITION CHECK r! V12242, 2A Condensate Pump Seallsol V12242, 2A Condensate Pump Seallsol I THROTTLE OPEN ly~?245, lY.2.?~45. 28 2B Condensate Pump Seal Isol Pump_S_e_a_I_ls

__o_1____________________

- LT_H_R_O_T_~~~_O_P_E_~_'____________'i THROTTLE OPEN END OF APPENDIX F

(

14

. - ..---.~-.- .. ---.-~-- ... - - - -.. _--._.-. __

._--_ ... -~ .. ---

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

REVISION REV'SION NONO PROCEDURE PROCEDURE TITLE TITLE PAGE PAGE:

5 MAIN FEEDWATER SYSTEM OPERATION 18 of 31 PROCEDURE NO 2 NOP*09 01 2*NOP*09.01 ST.

ST LUCIE UNIT 2 4.5 Start 28 2B Main Feed Pump as the Second MFW Pump (continued) 13,

13. At RTG8-202, RTGB*202, ENSURE the following initial conditions exist: exist

MV-09-2, PUMP 28 DISCHARGE VALVE, CLOSED

FCV-09-1 B2, PUMP 2B DISCH RECIRC VALVE, CLOSED

Pump 2B Aux Oil Pump RUNNING

Two condensate pumps are IN SERVICE 14,

14. At RTGB-202, RTGB*202, START Feedwater Feedwa\er Pump 2B as follows:

A, A. PLACE the FEEDWATER PUMP 28 control switch in START and then to the RECIRC position.

position, B. VERIFY the following valves are OPEN: OPEN

MV-09-2, PUMP 2B DISCHARGE VALVE

(

FCV-09-182, PUMP 28 DISCH RECIRC VALVE C. VERIFY PUMP 28 AUX OIL PUMP is OFF OFF.

D, D. VERIFY all 2628 MFW pump related annunciator alarms on Annunciator Panel G (RTGB-202)

(RTG8-202) are CLEAR.

15,

15. 28 MFW Pump shows evidence IF the 26 eVidence of unusual vibration, heat, noise or other malfunctions, THEN STOP 2B 28 MFW Pump.

Pump, 15

Appendix D 0 Operator Action Form ES-D-2 f------~-~~~~~~~~~--~~~~~~~~~~~~~----~--~~~~~

, Op Test No. No_ 1 Scenario # 7 Event # _2_ _ _ _ _ Page 6

_6_ of 20 I

...;2~0--l1

, Event

Description:

TIC-2223 Letdown temperature controller malfunction. V2520 iO=hang:-l ion exchanger bypass does not close.

,1 II~

~------------

L __ Time T~~1ie- L Position Ap licant's Actions or Behavior

! Booth Operator Instructions: Trigger TIC-2223 malfunction when directed 1----...-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - j i,

II Indications Available: Annunciator M-10 CVCS Ion Exchanger Temp High Identifies increasing temperature on TIC-2224. When I temperature alarm annunciates identifies V2520, ion exchanger i RO

! bypass valve did not close. Manually places V2520 to the I I ! bypass reset POSition.

position . .

._--------+-------

!-~ --- ,.

I

-.----~---~---___1----'------

--- ~.---

I I

+ -

!! Observes FIS-14-6 'Letdown Hx Flow' increasing (CCW flow to LD heat exchanger)

I LD heatexchanger) d

!r-I

. :: Places TIC-2223 to manual. Controls letdown temperature in I

__ L L~ I manual

! manual toto less less than than alarm alarm setpoint.

setpoin!. _ .1 i

I Places V2520 to the AUTO position when directed.

l -._-_._-"

I I I

--T ----L - JI I ---;;;- Ii Implements 2-0NP-02.03 Charging and Letdown step 6.0.14

! SRO (attached page_17_)

_ _ _ _ _ _ 0* * -

+-----+ - --------------

I

+O~~~tsDirects V2520 ion exchanger bypass placed to the Bypass I Reset position. Step 6.0.14.A ______ J

---_._------;--"--+---------------------------1 r

I I

Directs TIC-2223 placed in manual. Step 6.0.14.B

,,-------.-- - - - - - - - f - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 I

,. _-------+-----+---------------------j

+-----+------------------------~

I Direct placing V2520 back to auto when temperature has been .

i lowered in manual control.

+-----+-------------------------1 i ,

I I -----rC~-ntact Contact SMSM andand IC---

IC I

+------j-------

, ---- ----- ----1-----+-. -----------------------1!

. I ----------~-~.

i i

-.. - . - - - - + - - - - - - t - - - - - - - - - - - - - - - - - .

~------------.-+----

i

*1~--------+-----

J

,6/6

~~~~-- ---"---~--."-------

RE VISION NO REVISION "10 PROCEDURE TITLE PROCEOURE TITLE PAGE.

PAGE 158 15B CHARGING AND LETDOWN 13 of 26 PROUDURE NO PROCEOURE 2-0NP-0203 ST.

ST LUCIE UNIT 2 6.0 6"0 OPERATOR ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS 14, VERIFY TIC-2223 is responding 14, 14.

expected, 11 Letdown as expected.

Temperature Control is malfunctioning, Then following PERFORM the following:

A, A. BYPASS Letdown Ion Exchanger( s) by placing Exchanger(s)

V2520 Ion Exchanger Bypass Valve to the BYPASS RESET position S,

8. PLACE TIC-2223 in MANUAL B.

S, Dispatch an Operator to and ADJUST letdown Bypass TCV-2223 by temperature to setpoint. following:

performing the following 1,

1. THROTTLE OPEN SB14254, TCV-2223 Bypass,

2. CLOSE SB14248, TCV-2223 Upstream Isol.

3. ADJUST S814254 as directed by the SM I/

US to Control Letdown Temperature.

Temperature C.

C" 11 Letdown Temperature is stable at the desired temperature, Then PLACE the letdown Ion Exchanger(s) in service by placing V2520 Ion Exchanger Bypass Valve to the AUTO position position.

END OF SECTION 6.0 17

Appendix 0 D Operator Action ES-D-2 Form ES-O-2 c I-I'II Iil Op Test No.'

1 No,: 1 Scenario # 7 Event # _33_ _ _ _ _ _ Page 7 Of~

of 20 III_~v_ent Event Description Oescri ption: RWT LIS 07-28 low, 07-2B fails low.

il

,---- Time !lm~Liii:3ltiSiiCJI Position Applicant's Actions or Behavior i Booth Operator Instructions: Trigger LIS 07-2B 07*2B fail low when directed Indications Available: Annunciator S-19 RWT Level RAS Channel Trip I

=_.------:===_R-_-O~~~:l_--1d~e~n~t-i_fi-e_-s -~

I RO Identifies channel B RWT level LIS 07-2B failed low, I

c-h_a=n=n_e_I_B_RWT level LIS 07-28 failed l o w . -

I SRO 2-0NP-99,01 Loss of Tech Spec Instrumentation Implements 2-0NP-99.01 iI SRO !

step 6,3,2,B,1, page_19_)

6.3.2.B.1. (attached page_19_l I

+- Implements T.S.T,S, 3,3,2 3.3.2 Action 19, 19. Within one (1) the (1 l hour places th8i i

ii T,S, T.S. SRO Ii failed channel In in bypass or tnpped condition. Restore within 48 i tripped condition, I

---.-- __1______ I I

~Q2.LJrs.

hours, i I

I 1------*_-

i-**

t

'--1'---

I I

BOP :, Bypassed ESFAS channel B for RAS per step 6,3,2,B, 6.3.2.B.11

,- BOP

---4 II I (page_19_)

(page_19_l

.. -..------~- I .-------

( C"

~_

.--~----+------------------------_l Review Review ARP ARP forfor annunciator S-1 9 a_n_n_un_c_i_at_o_r_S_-_19

,----- - , , - - - - + - - - - - - 1 ' - - - - - - - - - - - - - - - - - - - - - - - - - - 1 I I I

- -._" - -.., _ ,- -- !- --------- --++ --._- ------ !- - -- -- -- - - - - - - - - - - - - - - - - - - - - - - 1 ~

--+1---------*---

r---------+------+---------------------------4 I

~- ----.----t------~------------------- .. ------.j

--l I I

-------i r--------

1 - - - ------,-- l ----f---------------

I

f------+-------------------------+

i

- - - - . - - - - + --+1

. -~------.-_l_--- -_1

--_-_-_ +_-_ --- -- --- -- -- --- -- - --- --

-- - -- ----- -- ---- --- -_...4 1

i -

I ,

---.--- .. - --+--.. - - - . - - t - - - - - - - - - - - - - - - - - - - - - - - - - - - ;

I

(

.--~- ------

(

I,,, VISION NO PROCEDURE TITLE PROCEDURE TITLE PAGE_

PAGE 21 LOSS OF TECH SPEC INSTRUMENTATION P'lOCE OURE NO NO 14 of 37 PROCEDURE 2*0NP*99.01 2-0NP-99.01 ST. LUCIE UNIT 2 6.3 ESFAS Channel Malfunction (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

2. (continued) 2. (continued)

CAUTION The ESFAS keyswitch and bistable trip unit to which itIt applies do NOT, in some instances, Instances, directly line up.

up It is necessary to verify the labels of the bypass key, key switch, and actuation trip unit being placed in Bypass to ensure that the correct trip unit is bypassed.

NOTE

RWT level indications are covered by Tech Spec 3.3.2, Table 3.3.-3.

ESFAS cabinet door key, key 114, is required for bypassing ESFAS.

B. Refueling Water tank Level B.1 PERFORM ONE of the following:

following.

instrumentation indication

( LlS-07*2A /I B I/ C I/ D.

1. BYPASS the affected RAS channel using key 131.

2. PLACE the affected ESFAS trips units in TRIP in accordance with Appendix A, Placing Trip Units in Trip.

19

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 7 Event # 4 Page 8 of 20 Event

Description:

Description FCV-2210X controller output fails high.

Time Position Applicant's A licant's Actions or Behavior

Booth Operator Instructions: Trigger FCY FCV 221 2210X OX fail when directed

!i When IC called, state it will be a few minutes before we can investigate.

I~--------------------------------------I

!, Indications Available:

NOTE: no alarms with failure. Flow will initially rise to 150 gpm then stabilize at 93

gpm. (There is not procedure guidance for this failure)

.------*-L I

.---.------t-----t----------------------~___1 RO I Identifies maximum dilution due to controller failure f_a~ilu_r~e_._~

-=:--~ -~Io:es I I i

I Closes V2525 V2525 OR place FCV-2210X OR place FCV-221 OX 10 to close close when when direcled.

directed. I i - ~

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

+-------~.-" - - + - - - - - -

Monitors Reactor power [

- -----------J .----1 I

--+----------------11 I

I '

~--- ~~---~~~--=--

I I

+,

j

~ .. ....*

(

t--i 8RO , Direct V2525 closed or FCV-221 FCV-2210X close.

OX to close, 1,

,~~=~~~~=---- ascensio~

, I Directs Directs stopping stopping powerpower ascension ________________iI

+-_._-----

~:---=--J! _-_ __

---. - I

._-"." ------t--

Contacts I Co lie; t;;-

nla cIs IIC to inve investigate controller s lig ale co n lroll er failure I

.----" --_ ... --+i

, I i I

~.

!i ! Notifies 8M

~.~-~ --I~

- - - - - - - - - - - r - - - - --- -

---~Bop-~I-Places BOP Places turbine on hold as directed. i

.~-----------L --.

._-----+ I I

I!

1"'-- - _.._".

~----___t_----_+------------------------------

i

--+---

r----~---L--------___+-~---~---*------------*---~------I

~-

!I I

L.. -_.

t-------r-------------- I -------------------j

~ I ----'--------------___

I ~_~___________ ~ _____J

Appendix D Operator Action Form ES-O-2 ES-D-2 r-----.

it

Ii[ Op Test No 1 Scenario # 7 Event # _5=--_

_5_ __ __ _ _ Page _2.;;.;O~-11

_9_ of ...;2;.;;.0 __ 1 II Event Description

'I oescnptlo~ RIM 26-61 fails high. CROAI valve FCV-25-16 trips on overload. HVE-13A does not start. When HVE-13A IS is manually started, fan trips.

II

[--

~G -r:1.rT18"::=J Position A licant's Actions or Behavior Il ~_~th Booth Operator Instructions: Trigger RIM 26-61 fails high when directed directed._ _------i r-------

Indications Available: PC-11 alarm. OAI 501 and 503 indicate RED Annunciator V-22 CNTL Room Isol FCV-25-14/16 FCV-25-14116 OVRLD/OVRD OVRLDIOVRD ,i

,_ ... - - - -~-~~~.-~

I 1

, BOP BOP

. Responds to PC-11 alarm. Identifies OAI 501 and 503 in high, I' Ji :Ihi~_ high alarm.

. -***- .---j--'-' ---..-I~-+--I' - i

~ .....__.. _. -----..1 _ _ _ _ _L.- - - - - - - - - - - - - - - - - - - - - - - - - - 1

i NOTE: NOTE Because HVE-13A did not start, dampers D-17 D-17A A and D-18 did not open. They

. will momentarily open then close when HVE-13A is started then trips.

I -

--.--~---

i

,.----.. --i ----.;- ~- . -..'=-~l*--- -+I=--+-=::=====~~::::::~:::__

,~-l_S_RO ~I, l

1m-p---Cl-e-m-e-n-ts---C-2---C-O=-N:-:-=-P--2=-5c-.-=-02-:-C-V-e-n--Cti-:-1a-tiC-o-n---cS=-y-s-te-m-s-,(-at-ta-cc-h-e-dc----

SRO page 22-25 ). Directs Appendix B to check system alignment. [

i-------~-- j - I I

~---------i--~~---

I

Directs HVE-13A Directs HVE-13A started started per per step step 2. Determines one

2. Determines tra-;~f-~il one train of

CREACS has failed.

(

~.---- .-

I

---+----- - +--,-, - - --- - , - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 ------I

~T-S-~R-o-+l-I

.......- .......- - - t - - - -...- - + - - - - - - - - - - - - - - - - - - - - - - - - j I T.S. SRO ilmplement m-pl-e-m-e-n-t-T-.S-.-3-.7-.-7-(-C-R-E-A-C-S-)-A-c-t-io-n-B-.-R-e-s-to-r-e-w-i-th-in-2-4-l T.S. 3.7.7 (CREACS) Action B. Restore within 24

---~---.=l hours.

_ -Ii __::'l_-r,_h_o_u_rs_.

. _+ : i ~. ________.___ __._"'_'___ ~ ... _1,

]

I

, BOP BOP II Perform steps from 2-0NP-25 2-0NP-25.02, 02, "Ventilation Systems" when .

Ii directed. (attached page 22-25)

I~ - -- . _ - - _ ,_..

... . . - - . - - - - - - -- -- -- --- -- ---------____o

.. ~--------------'

,....... ------~'--------I---

Identifies Control room recirc. initiated on A train but HVE-13A I BOP did not auto start and FCV-25-16, north OAI isolation valve has I

tripped tripped..

-=--~---L----l---------------------I

...- - - - - - - - + - - - - - - - - - - - - - - - - - - - - - - - - - 1 I

~----.

.. _ ~LT__ . .___+_~_~p_t~_~_p_t_s_t_o_s_ta_rt_H_V_E_-_1 I' : Attempts to start HVE-13A when directed. Identifies HVE-13A

t_tr_iP_s_.__________________________ 3_A_W_h_e_n_d_i_re_c_t_ed_._I_d_e_n_tif_ie_s_H_V_E_-1_3_A_--1 ~

~ ___ ._ *. __ ._

~----.-----------'-----.

I I

REVISION NO REVISION NO PROCEDURE PROCEDURE TITLE TITLE PAGE:

PAGE:

21 VENTILATION SYSTEMS 12 of 33 PROCE DURE NO 2~ONP~25.02 2-0NP-25.02 ST LUCIE UNIT 2 ST, 6,2 6.2 Control Room Ventilation INSTRUCTIONS CONTINGENCY ACTIONS

1. if11 only one Control Room NC Unit is available, Then REFER TO Tech Spec 3.7.71, 37.7 1, Control Room Emergency Ventilation System.

2. if11 ANY of the following have occurred:

occurred

Control Room OAI Radiation Monitor alarm

Unit 1 CIAS

Unit 2 CIAS

~ GO TO Appendix B, CIAS and Then Control Room OAI High Radiation.

( 3, ~3 !! ANNUNCIATOR V-5,

'-b!! V*5, Cntl Cnt! Room 3.

To Outside t.P t>P Low, is ALARMED, Then GO TO Appendix C, Control Room Low pressure Restoration.

4, ~2 11If a freon leak from a Control Room 4.

HVA I/ ACC Unit has been verified, Then PERFORM the following:following A. EVACUATE all personnel from the H&V Room CAUTION Personnel entering the H&V Room with a freon leak should wear SCBA to avoid breathing a hostile environment.

B. CHECK H&V Room Oxygen B. !f11 Oxygen concentration is less concentration greater than 195% than 19.5%, Then PERFORM the following

1. ENSURE personnel wear SCBA in the H&V Room.

22

REVISION NO REVISION NO PROCEDURE TITLE PROCEDURE TITLE PAGE PAGE 21 VENTILATION SYSTEMS PROCE DURE NO 28 of 33 PROCEDURE 2-0NP-25.02 2-0NP-25_02 ST.

ST_ LUCIE UNIT 2 APPENDIX B CIAS AND CONTROL ROOM OAI HIGH RADIATION (Page 1 of 3)

INITIAL 1_

1. CHECK the following system alignment:

!I A B B

, REQUIRED HVAC PANEL TRjlN TRAIN TR?N STATUS L

~~~

I lone (1) HVE*13A HVE-13A Inlet Damper (0-17 (D-17A) A) OPEN N/A lOne lone (1) HVE-13A Inlet Damper (0*18)

Damper(D-18) OPEN I! N/A t---

FCV-25-24. kitchen Exhaust Isolation Valve

!IFCV-25-24, CLOSED N/A L-.

r-FCV-25.16,

, f'CV*25-16, North OAllsolation Valve CLOSED N/A

FCV-25-17, South OAI Isolation Valve _._. CLOSED N/A N/A-j

- .. ~--'

FCV*25-18, FCV-25-18, Toilet Exhaust Isolation Valve

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

CLOSED i ~ N/A ilOne One (1) Control Room Emergency Filter Fan (HVE*13A)

(HVE-13A) START l N/A r- ~

!lOne One (1) HVE*138 lOne (1) HVE*138 lone HVE-13B Inlet Damper (0*178)

(D-178)

HVE-13B Inlet Damper (D-19)

(0-19)

OPEN OPEN N/A N/A II i FCV-25-25.

FCV-25-25, kitchen Exhaust Isolation Valve CLOSED N/A I1 FCV-25*14.

FCV*25-14, North OAllsolation Valve CLOSED N/A

,I FCV-25.15, FCV*25*15, South OAllsolation Valve CLOSED N/A FCV*25*19.

FCV-25-19, Toilet Exhaust Isolation Valve CLOSED N/A

One (1) Control Room Emergency Filter Fan (HVE-138)

(HVE*13B) START N/A J

2_

2. Il11 a Control Room Emerg Filter Fan did NOT start, Then manually START the applicable fan

HVE-13A

HVE-13S_.

HVE-13B 3_

3. Il11 any damper failed to position properly, properly. Then manually POSITION the damper, as indicated in step 1 1.

4,

4. STOP HVE-14, Cntr Rm Toilet Exhaust Fan. Fan_

5.

5, STOP HVE-33, Kitchen Exhaust Fan Fan.

6_

6. Il11 both Control Room OAI Radiation Monitors on any intake are trloperable, Inoperable. Then REFER TO Tech Spec 33.3_1_ 33.3.1.

23

RC:VISION REVISION NO PROCEDURE TITLE PAGE 21 VENTILATION SYSTEMS PROCEDURE NO 29 of 33 2-0NP-25.02 2-0NP-2502 ST. LUCIE UNIT 2 APPENDIX B CIAS AND CONTROL ROOM OAI HIGH RADIATION (Page 2 of 3)

NOTE

~7 §, §,

§2 Due to changing environmental conditions during long term events, it may be necessary to repeat steps 7 & 8 to maintain the lowest possible dose.

7. DETERMINE which Control Room OAI has the least amount of radiation:

radiation

Norih OAI North

South OAI

8. When the OAI with the lowest amount of radiation has been determined, Then PERFORM the following:

following

(

A. OPEN the FCV on the lowest reading side: Side

FCV-25-14, North Norih OAI Isolation Valve

OAI Isolation Valve FCV-25-15, South OAllsolation B,

B. THROTTLE the FCV on the lowest reading side throttle:

throttle

FCV-25-16, North OAI Isolation Valve

FCV-25-17, South OAI Isolation Valve C. THROTTLE Control Room ventilation return air as necessary.

necessary

PLACE PDIC-25-23A1, Cont Room to Outside I".P 6P to Man and ADJUST as necessary.

PLACE PDIC-25-23B1, Cont Room to Outside 6P c.P to Man and ADJUST as necessary.

~------------------------------------------------------------~ ~

24 24

REVISION

'lEV'SION NO PROCEDURE TITLE PAGE PAGE:

21 VENTILATION SYSTEMS P",OCEJURE PROCEJURE NO 30 of 33 2-0NP-2502 2*0NP*2502 ST.

ST, LUCIE UNIT 2 APPENDIX B CIAS AND CONTROL ROOM OAI HIGH RADIATION (Page 3 of 3)

8. (continued) INITIAL D. MAINTAIN parameters:

II OAI OAI FCV ! CONTROL ROOM PRESS 'j FLOW FLOW INITIAL Ii______--,-__i MIN INDICATION RATE

NORTH FCV*25*16 0.125 In. H 2O ! FI*25*18A <;450scfm r[ SOUTH FCV*25*17 0.125 In H 2O ! FI*25*18B :> 450 sefm E. if11 Control Room pressure indication is erratic and the required pressure differential can't be verified, Then MAINTAIN outside air intake air flow rate between 440 to 450 SCFM. SCFM,

9. §,§2 Initiate a Data Sheet 30 to track wind direction on a (4) four hour

~7§,.§2

,-]7 ;i) 33 frequency, frequency. ~

( ifIJ wind directions changes 90 degrees or more, in (4) four hours,

10. ~7§'§2

,-]7§1 §z ;i) 33 RE-PERFORM steps 7 and 8 above.

Then, RE*PERFORM above, ---

-~-

11.

11, 'h 11, If desired, Then STOP ONE of the following Control Room Emerg Filter Fans: Fans

HVE*13A

HVE*136 HVE*13B 12.

12, V\ihen initiating signals are CLEARED, Then PERFORM ALL of the When following A. ENSURE both Control Room Emerg Filter Fans are secured and their control switches are in auto,auto.

HVE*13A

HVE-136 HVE*13B B.

B, RESTORE Normal Norma! System Alignment per 2-NOP*25.07 2-NOP*25.07.

END OF APPENDIX B 25 25

Appendix D D Operator Action Form ES-D-2 r- - -

i

i Op Test No.: No.. 1 Scenario # ...l.-

7 Event # 6 Page 10

_10_ 2£J of _2_0--11 Ii Event

Description:

2A Intake Cooling Water Pump has a sheared shaft.

I

!::-=-~~~I_~~n~~fC)~__----.J~--Tll~~~.

_Iime [_ """Po::S::lt::io::n:::::::::::::::::::::::::::::=::::A::p:lic::a::n:t'S::A:c::t::io::ns::~o.;..r=B:e::h::a::vi=or::::::::::::::::::::::::::::::

Position A plica nt's Actions or Behavior B~ot-h-O~-~rator !

-~----,

I Booth Operator Instructions: Trigger event 6 ICW sheared shaft when directed When called to throttle 2C ICW PP discharge valve trigger throttle 2C ICW

~W~_=~called When called to to open open 2C 2C ICW ICW PP discharge valve, PP discharge valve, triggertrigger open open 2C vaIV:~--------------li 2C valve.

r---- -----------

i Indications Available: Annunciator: E*30 E-30 ICW Headers pressure low i LB*4LB-4 3B1/3B2 3B1/382 Lube Wtr Supply Strn liP t.P High

E*16 E-16 Circ Wtr Pump Lube Wtr B/U in service !

I

.: Low amperage on RTGB 2A ICW Pump amp meter. I

: BOP I Responds to low flow~a-n-n-u-n-c-ia-t-o-r.-I-d-e-nt-if-ie-s-Io-w-a-m-p-e-ra-g-e-.----:----11

~ ____________ t_B_~P_---+I_R_e_s_p_o_n_d_s__to_IO_W_f_IO_w_a_nn_u_n_c_ia_t_o_r._I_d_e_n_t_ifi_e_s_lo_w_a_m_p_e_ra_g_e_'_-I

n-j~--~--=r - ----- -------~

- ~~~~_--~*~~~-_-----t--IS_t_o_p_s_~A

i Stops 2A ICW pump when directed ICW pump_w_h_en_d_ir_ec_t_e_d_ _ _ _ _ _ _ _ _- - i

--~-~~~--- ----~--- .------- ------ -------~I*

SRO II Directs stopping 2A ICW pump .~

----+

i --------------------~

Ii

,-- -----------+-

( I-------+-Im-pl-e-m-e-n-ts-2--0-6-4-00-3-0--ln-ta-k-e-C--oo-l-in-g-W-a-te-r-S-y-s-te-m--7-.2-.-1.-B--1 I Implements 2-0640030 Intake Cooling Water System 7.2.1.B

! . and C (attached page_28_).page~28~). and 2-NOP-21.03C 2C Intake 1 '

L-___

--..-L I

______---'!_C_o_o_l_in_g_W_at_e_r_P_u_m_p

__O_p_er_a_ti_o_n_(a_t_ta_c_h_e_d_page~29-31_)

. Cooling Water Pump Operation (attached p

_a_g_e_2_9_-_3_1-_)_ _-----i

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

_ NOTE:

NOTE. As per NOTE in 2-NOP-21.03C (attached) steps 4.2.5 through 4.2.10 may be

skipped as directed by the US for an off normal or emergency condition. The SRO should recognize this as applicable and direct the above steps skipped.

--~-----------T-----~- T-'--'-'- --------1

r-----

r-----t-Direct ! Direct steps steps 4214.2 1 through through 4 4 implemented implemented. (attached (attached I I

I a~ 29 page )l I

i I

!II Direct start of 2C Intake Cooling Water Pump as per step I

,~ -:=t---

,l- ---------

I:

1421 ~(_a_tt_a_ch_e_d_p_a_g_e_-_3_0-~-)-----------_______11.1 4.2.11 (attached page _3o_)

I After pump started direct steps 4.2.2.12 through 20 I

__ ------j-- implemented.

lim (attach ed~a_g_e_-_3_0_,

pi em ented. (attached page_30,31_) 3_1_-_)_ _ _ _ _ _ _ _ _------1'

~-J i-****---** __

r---------

i

- - -i - - + - - - - - - - + - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - 1

..,,---. ...;.------.--.-~---------

BOP :,Direct Direct Field Operator to perform steps 4.2 1 through 4 of 2-

'- -_ _ -_-_:=~____

______ ~ ___= - r Li P -21.D3C 2C

_N_O_P_-2_1.03C Intake Cooling 2C Intake Cooling Water Water Pump Pump Operation Operatror

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

Appendix D D Operator Action Form ES-D-2ES*D*2 10 i;'"~--'----------=--==============--=----==========O, "i; Op Test No Scenario Event Page 11 20

77 Event # 66 of il Op Test No . Scenario # # Page 11 of "I, II Event Description 2A Intake Cooling Water Pump has a sheared shaft.

t~~. .;.T,;.;,i~;.;;~~*~~::;::,;..P==O;:S;;:it~I~'

r~.;:;e-]I o~n::::::::::::::::::A::;p;;pZli;;;;c~a;::nZt's;:;.;A~c;:t;,;;i=o,;.;.n~s;:.;;;o~r2B;:;e;:h;a,;.;v~i.;;;o~r::::::::::::::=J l-.-------.---.---~~~~~""T~~-=-------~~~-=~-------~~~

Position Applicant's Actions or Behavior J

. Booth Operator Instructions: Notify control room steps complete in about 5

!I minut minutes es after called.

c* - . - - - - - - - - - - - - - - ------

Indications Indica tions Available:

- T. __

I i

I

.. i

! BOP Start 2C Intake Cooling Water pump as per step 4.2.11

r-----+-I-

.-- ~.-

i***"-~ -.----.---~-+------.--

!! ----+--------------------------------1 I

Direct Field Operator to perform steps 4.2.12 through 20 after BOP pump started. (attached page_30,31_)

--*---~+--_' -+--- :

___~-----_ _ _ -+------I - - - - - - - - - 1 I

i

.. _._--_.--+---_.-----+-----

- ---- ----+---- - - - . - T " - - - - - -

II .

.--;--~----+--- i

--+ -------'------------------------.----.---~----- ...----.----

_--------.--..-. --------i

--.-- "-I i

c_ '---T~ -----+1---------------

,-.-.---~---.----

1--"-- ......_ _ i

- -.--~~--;-~---.----.-~-----

n - - f - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - :,1

--~------~ ~

+------t-I-- i

"'.---------+------+--------------------------------------1 I: I _.--j

~

'---------...'1i' ....- - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - 1

I I

--...... ------1 -- L- I

. . - - - - l'

+ - - - - - - - - - - - - - - - - - - - - - - 1 -i

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

~

--+-1------+--------------------_*_-_. _*_*_----_ . . . . -1I . ____ I

+-----+------------------------.-----

~-----~:~~~~~I~~~~~~~~~~-!~

r~---*-* ..

+ii _____-+_______________________________----1

~------~-I

-----------*-l-------r r-----

i I

, .------~---T'-------------------------I i

; I

"_. __.. _. __ .. - - + - - - - - . , - - - - - - - - - - - - - ----------------~ ------------------------j I

. _-------+-----.

".---- --- --7

. . . . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1I

... _..............J1 _ _ _ _........1_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..JI

_. ----.~-~---.----.-- .---.---

(

REVISION NO PROCEDURE TITLE TITLE: PAGE 41A INTAKE COOLING WATER SYSTEM 6 of 67 PROCEDURE NO 2-0640030 ST. LUCIE UNIT 2 7.0 OPERATOR ACTIONS 7.1 7,1 Immediate Operator Actions 1, None 7.2 7,2 Subsequent Operations Actions INSTRUCTIONS CONTINGENCY ACTIONS CAUTION If affected ICW header Indicates indicates 0 pressure, the standby pump discharge valve must be throttled prior to startinq.

1. 11!1 an ICW pump Indicates indicates extremely high amps, OR an ICW pump trips triPS unexpectedly. Then Then.

A, A. U

!1 the health and safety of the public IS is in In Jeopardy, jeopardy, Then ATTEMPT ONLY ONE restart. restart B.8. Place the pump control switch to PULL TO LOCK position position.

C. Then align the standby pump to c, if an ICW pump cannot be the header, lAW 2-NOP- restored to a header.

header, Then:

Then 21 03A(B)(C), 2A(B)(C) Intake 2103A(B)(C).

Cooling Water System Operation, and start the standby pump.

pump 1, Reduce MVARS to minimum minimum.

2. Monitor Main Generator Gas 2,

Temperatures Refer to 2-0NP-53 01,

01. Main Generator.

3. Reduce turbine load as needed to within the heat removal capability of the TCW system system.

4. Isolate S/G blowdown, then 4,

place the Open Blowdown heat exchanger TCVs In in MANUAL and close.

close 28 28

~--- - -----

-- --_. --------~.---.- - -----

.-~.-------- ... - - - - - _ .. _.' .. - ------ - ..... _- ._-

"iv,S,ON NO PROCEDURE f1TLE flHE PAGE:

OA 2C INTAKE COOLING WATER PUMP OPERATION 8 of 20 PROCEDURE PROCE DUR I: NO 2-NOP-21.03C 2-NOP-2103C ST. LUCIE UNIT 2 4.2 Starting 2C ICW PumQPump on A Header with Header De[!ressurized Depressurized INITlAL NOTE

- If pump start is for an off-normal emergency condition, any or all steps of I I Section 424 2 Step 5 thru Section 42 4 2 Step 10 may be skipped as directed by US/SM.

US/SM I

II

Proper CLOSED alignment of crosstie valve requires the valve indicator arrow to line up with the "V" notch on the indicator plate.

plate (Attachment 1 )

Ii I'

1.

System Performance Group/OSE shall be notified if crosstie valve is not aligned properly, properly ENSURE 2A ICW Pump Control Switch in PULL TO LOCK position, position

2. ENSURE Locked Closed S821211. 2C ICW PUMP X-TIE DISCH TO

'8' TRAIN ISOL (INTKl9/N-4/W-C),

(INTKJ9/N-4/W-C).

3. ENSURE Locked Open S821165.S821165, 2C ICW PUMP X-TIE DISCH TO

( (INTKJ9/N-4/W-C).

'A' TRAIN ISOL (INTK/9/N-4/W-C), --~

4, THROTTLE THROTILE approximately 10 turns OPEN, S821206, 2C ICW PUMP DISCH ISOL (INTKl18/N-3/W-C).

(INTKJ18/N*3/W-C) 5,

5. CHECK SS-21-1A Bearing Cartridge Lubrication Reservoir level between the HI LEVEL and LOW LEVEL tags on reservoir sightglass.

6,

6. ADD lubricant to SS-21-1A Bearing Cartridge Lubrication Reservoir as necessary per 2-NOP-21.03A, 2-NOP-2103A, Intake Cooling Water System Train A Operation.

7. ENSURE 2C ICW Pump motor lube oil level approximately at STANDSTILL level mark.

8,

8. CLOSE SH21204, PI-21-5C ISOL (INTK/23/N-3/W-C).

g,

9. CLOSE the local instrument Isolation isolation for PT-21-8A, 2A ICW PUMP DISCH HDR PRESS (INTK/12/N-4/W-C).

(INTK/12/N-4/W-C),

29 29

~~~~ _. __ ..._----- -

---_.- ~-------- --.-------------- - ----_._----_._--

---_ .. ------.~~-

P['.IS'CN NO PROCEDURE TITLE PAGE' OA 2C INTAKE COOLING WATER PUMP OPERATION 9 of 20 1;Jf:\OC[ OuRf NO Pf:\OCT OuRF ST, LUCIE UNIT 2 4,2 Starting 2C lew ICW Pump on A Header with Header Depressurized (continued)

F===================--==========--=~====~----======~==~

F==================--==========-===~===--=--======~==~

NOTE Actual backwash FLOW does not occur until untillCW ICW Header is pressurized, 1O, Immediately prior to starting 2C ICW Pump, START a manual backwash of 2A Debris Filter System uSing MANUAL CONTROL FROM CONTROL PANEL in accordance with 2-NOP-21 ,03A, Intake Cooling Water System Train A Operation ---

11, ST ART 2C ICW Pump

12. IF closed in Section 4.2 Step 8, SLOWLY OPEN SH21204, PI*21-5C ISOL ---

13, IF closed in Section 4,2 Step 9, SLOWLY OPEN the local instrument Isolation for PT*21-8A, 2A ICW PUMP DISCH HDR PRESS.

( 14, As pressure begins to rise In A ICW Header, SLOWLY OPEN SB21206, 2C ICW PUMP DISCH ISOL, until valve IS fully OPEN.

15, LOCK OPEN SB21206, 2C ICW PUMP DISCH ISOl, ---

16, ENSURE OPEN SH21520, 'A' TRAIN ICW TO HYPO SEAWATER BSTR PUMPS ISOL, (INTK/7/N*4/W-C), ---

17, OPEN SH40079, 2C ICW HYPO HDR ACID RETURN ISOL (INTK/17/N-3/E-C) -~-

18, ENSURE Closed SH40077, 2A ICW HYPO HDR ACID RETURN ISOL (INTKJ17/N-3/E-C) 19, WHEN SB21206, 2C ICW PUMP DISCH ISOL has been FULLY OPEN for greater than 15 minutes, THEN ENSURE 2A Debris Filter System MANUAL BACKWASH IS secured using MANUAL CONTROL FROM CONTROL PANEL in accordance with 2-NOP-21 ,03A, Intake Cooling Water System Train A Operation

( 30 30

~--~- ~~~~~~~~~~~

---- ----- - - -~---

PROCEDURE TITLE PAGE PAGE OA 2C INTAKE COOLING WATER PUMP OPERATION 10 of 20

[)~CC~ JUHE NO 2 NOP21 OJC 2NOP21.0JC ST.

ST LUCIE UNIT 2 4.2 Starting 2C lew ICW Pump on A Header with Header Depressurized (continued)

(conti nued)

II 11 NOTE NOTE

\1 The following step will require a ladder at the CCW platform for access to HX II vent valves and a pipe wrench to remove vent caps.

20. VENT 2A ICWlew header by opening the following valves until a steady stream of water issues from vent, THEN CLOSE the valve:

A. SS-21-1A SH21332, SS-21-1 A VENT (CCW/28/S-AJW-4) ~-

B. SH212049, SS*21*1A SS-21-1A BACKWASH OUTLET VENT (CeW/31 /S*AJW-4)

(CCW/31 /S-AJW-4) ---

~--

C. SH21197, 2A CCW HX TUBE SIDE INLET HEAD VENT (CeW/34/N-B/W-4)

(CCW/34/N-B/W*4)

D. SH21198, 2A ecw CCW HX ICW OUTLET VENT (t (CeW/38/S-A/W-2)

(CCW/38/S-AlW*2)

E. SH21358, SS-21-4A VENT (TGB/26/S-20/W-G) ---

~--

F. SH21171. 2A TCW HX TUBE SIDE OUTLET HEAD VENT (TGB/26/N-21/E -K)

(TGB/26!N-21/E-K)

G. SH21172, 2A TCW HX TUBE SIDE INLET HEAD VENT (TGB/26/N-21/W-D)

(TGB/26!N-21/W-D)

~-

( 31 31

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

Appendix D Operator Action Form ES-D-2 r---' .

!i!I Op Test No No.:.. 1 Scenario # 7 Event # 7, ..;,.8:..,;.

_7;..;.' 8, 9;..-.__

9 Page .1l-

_12_ of _20_-11

_2_0---11 I, '1' Event

Description:

Loss of Instrument Air pressure. Plant down power, power. Unit trip. Three CEA's do not fully insert. Stop all RCP's due to CCW unrecoverable.

1 iL~..==JL Time II __ ~6:J Position II Applicant's Actions or Behavior Booth Operator Instructions: Trigger event 7 loss of Instrument air air.. i

. If directed trigger 7a for faster response of instrument air loss. ~

~.--'---"'-'- _.-

Ind~~tion;Available:

Indications Available: Annunciator F-15 F~15 Inst Air Pressure High/Low I

' Two minutes late annunciator F-30 F~30 Unit 1 / Unit 2 Inst Air Crosstie Open ,

,---- I SRO I' Implement Im-plement 2-1010030 Loss of Instrument Air step 7.2.2 verify Ii 1-._---=1=-

~==T*

I . 2C or 20 2D has started. (attached page_35_) page_35~)

!I i---- .-+-: ~---Ir--NotifiesINotifies SM SM

~-----*------t

_. _- -.----.-+-----~~-+-~~.-~-

i

~~~~~~~~-~~--~~~- ----~

I Ensure Servic~ air or construction -a-ir-i-s r---------i-, **-----il-E-ns-u-r-e-s-e-rv-ic-e--a-ir-o-r-c-o-n-s-tr-u-c-ti-o-n -in-se-r-v-ic-e-.

air is in service.

1

=I~==t=---- I Direct opening SH18718 Service air crosstie to Instrument air.

I I Step 7.2.3.B (attached page_35_)

I !

._~~~l-*__

( -t-- I _ _ _ _ _ _ _ _ _ _ _,

i If air pressure drops to less than 75 psig evaluate the need to

--J ._.______

I

-.J. -

1 shut_~he shut the unit down. Step 7.2.7 (attached page_37_)

page_37 _)

-.. -. - - - - - i I

~~-+i~~--~~-

___ ._____ ._~~'_____ ----LDirect Direct unit down power~~

do,":,n power in response to lowering air pressure. pre_~sure I c** - .. - - - - - - - _ - -

i --1

-- --------" .--t----- ., i Direct Charging pumps stopped if Letdown isolates due to I

! lowering air pressure

~.---

'---1

....._ - + - - - - - j - - - - - - - - - - - - - - - - - - - - - - - - - - - - I I

~~--+:-0-1-'re-c-t-s-u-n-i-t-tr-ip-w-h-e-n~in-s-tr--u-m-e-n-t-a-i-r-p-r-e-ss-u-r-e-I-o-w-e-r-s-t-o-I-e-ss~~--I

+_

.--- ---+-----

. Directs unit trip when instrument air pressure lowers to less I than 60 psig. Step 7.1 7.1.1 (attached

.1 (attach page_34_)

ed page _ 34_)

"----,---.-.-. -~--+I-- .------~~~--~~--~~--~~-~---------1 I

r***** .- - ------"'"1'. I . -_.

i RO

'Ii Monitors Primary for Letdown valves, CCW valves to RCP's i possible closure on lowering air pressure.

--- .... -------T

- _._-_.----------- .... ---_._-------- I

.-- - - - - - - - - -I - - ' - - - -

Identify lowering Instrument air pressure in response to BOP I i annunciator. Refers to ARP F-15 i - ' - ...

,I _ _ _ _ _ .___ Ii .c _ _ _ _ _ -'---~ _____ ~~ __

(

~~------------- - _... .-----------

--~~ --~~~-~-

Appendix 0 Operator Action Form ES-D-2 iI~;est N:~.-

!!I, op-;est N:.- Scenario # 7 Event # 7, 8, .,;..9

_7;...:,...;;8,.:,., 9___ Page 21...-

~ of _20_..."

_2_0_-11 IIi Description.

Event Description Loss of Instrument Air pressure, Plant down power, Unit trip. Three CEA's do not fully insert, Stop all RCP's due to CCW unrecoverable.

I'i

'I

~=~J_Position L_-Ene J~ Position Ap licant's Actions or Behavior

! Booth Operator Instructions: If NPO asked the status of the Instrument air I! compressors, state both C and 0 D are running running..

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

-.~.----.----- ..- ..... I Indications Available: Air operated valves that fail closed, begin to show red I

~

1 green light indication as air pressure degrades.

r 80 P Notifi- e-s-N-P-O-t-o-i-n-v-es-t-i9-a-te-1 g-a-t-e-I-n otifi-e-s-N-P-O-t-o-i-n-ve-s-t-i s-t-ru-m-e-n-t-a-ir-s-y-s-te-m-for lea ks n-s-t-ru-m-e-n-t

--.---. - - - - - - - - t - - - - - - - - - - -

I 1

.. ------ ----- -----t------ -.- --j--

'BOP/RO80P/RO Initiates manual Reactor trip when directed,

___ ~-

1------------

. _I----!-----

.-;---~

'-r-~- -+--------

_ _ _ _ _ _ll

~ ..

e----~

e--- .---- --- .-~----- .. -~~.---I--I---~

+1----- ------------- ----l -~-l

~~------- I --+- - - - -

(

. ------_l___I

~--r--~-J

-_._._-_._._[

__ ~. ---*--t---

,,---- __.~_+.-~

i

--+----*~1!--~--~--------------j

~ _____

I-------------------------------~lI

_~_~+__---------------------

~~~*_~~~___JI 1

-I

___1_' . . I II I

I

_~--+'-----

Ii i

=-J----~

;~~"~----I--~ ---------------~ ~~

- --------+ 1 I

+------------- l--1 -- -- ---- -------------------.- -- ---- -- -- -- - - - ~'

c~- . -

,-- -~**--

-.----- -ri- - - -

-T-----I - - t - - - - ---~_______I

--4---------- - - - - - - -------~--------------I

~. ~-.~l-- ~~---+-----

+----- II

-".----~--- -- -- -- _..-_ -- -- -

---.---------i--------~ ~---~

'--1I

---.J- - - - + - - - - - - - - - - - - - - - - -

L ==1

JI

'~---.-=-:*~--+-----------------~JI

, - - - - - - I- - + - - - - _ . - - - - + - - - - - - - - - - - - - - - - - - - - - - - - - - - 1

-~~--

~--

. --.-~-----.--+-----------------l I

... - .. _ _ _ _ t _ _ - - ...

i I

1

__ ,~._",L_._ ... ~ _ _---'-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _----'

REVISION NO REviSION PROCEDURE TITLE:

TITLE PAGE:

PAGE 27 LOSS OF INSTRUMENT AIR 5 of 19 PROCEDURE NO 2-1010030 ST LUCIE UNIT 2 ST.

7.0 OPERATOR ACTIONS 7.1 Immediate Operator Actions INSTRUCTIONS CONTINGENCY ACTIONS

1. if the Instrument Air header pressure Indicates indicates less than 60 psig and is still lowering, Then PERFORM the following:

A. TRIP the Reactor and Turbine.

B. GO TO 2-EOP-01, Standard Post Trip Actions.

END OF SECTION 7.1

(

34

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

REVISION NO PROCEDURE TITLE PAGE 27 LOSS OF INSTRUMENT AIR PROCEDURE NO 7 of 19 2-1010030 ST. LUCIE UNIT 2 7.2 Subsequent Operator Actions (continued)

INSTRUCTIONS CONTINGENCY ACTIONS NOTE The automatic cross-tie feature of the Instrument Air System occurs at approximately 85 psig lowering on the affected unit. The cross-tie valve on Unit 1 will close if EITHER of the following conditions occur:

The Unit 1 Instrument Air header pressure lowers below 85 psig.

l.* The Unit 2 Instrument.Air Instrument Air header pressure rises above 95 psig. psig

2. ifLf Instrument Air header pressure is 2. if11 the standby instrument air lowering, Then VERIFY the standby compressor (2C or 20) has NOT instrument air compressor (2C or 20)

Instrument started, Then manually START has started the standby instrument air compressor (2C or 20). 20)

NOTE The time period that the Service Air header feeds the Instrument Air header

( through the cross-tie should be minimized to prevent oil intrusion into the tnrough Instrument Air header.

3.

3. IflJ the Instrument Air header pressure is still stili lowering, Then PERFORM the following:

following A. ENSURE the Service Air Compressor is running, or Service Air is being supplied by Construction Air.

Air B.

8. OPEN SH18718, Service Air Cross-tie to Instrument Air Isol Isol C. iflJ the Instrument Air header is fed C. 11lJ oil, water, or crud build-up is from the Service Air header for detected, detected. Then CONTACT greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Then BLOW Engineering to evaluate DOWN the Instrument Air receiver continued use of the Service tank at V18126 hourly to check for Air System.

System oil, oil. water and crud build-up.

build-up

/

35

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

(

Rf VISIO;; NO REVISIOt-; NO PROCEDURE TlTl.E*

PROCEDURE TITLE PAGE.

PAGE.

27 LOSS OF INSTRUMENT AIR 8 of 19 PROCEDURE NO.

PROCEOURE NO 2-1010030 2*1010030 ST. LUCIE UNIT 2 7.2 Subsequent Operator Actions (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

4. Check pressure drop across the in 4. Jl!! pressure drop is greater than or service air dryer and filters, to be less equal to 13 psig, Then open V18075, than 13 psig. air dryer and filter bypass.

5. Uinstrument air pressure can be stabilized, Then:

Then A. Investigate the instrument air system for leaks, failures, or malfunctions B.

B, Ensure dryers and filters are aligned properly and placed in service correctly.

6. Ensure power available to the 2C and 6. Jl power is NOT available, Then if 20 instrument air compressors. perform the following as required:

required.

(

A. "2C Air Compressor (MCC 2A1)", A. Determine that malfunction of the Bkr 2-40802.

2-40802 motor or breaker was NOT the reason for loss of power.

B. "20 Air Compressor (MCC 2B1)",2B1 )", B. Restore power to the appropriate Bkr.2-41608.

Bkr. 2-41608. MCC and start the instrument air compressor.

C. Start Instrument Air Compressor 2A per Appendix A.

OR D. Start Instrument Air Compressor 28 per Appendix B.

( /

36

REVISION NO PROCEDURE TiTLE PAGE 27 LOSS OF INSTRUMENT AIR 9 of 19 PROCEDURE NO PROCeDURE 2*1010030 2-1010030 ST. LUCIE UNIT 2 7.2 Subsequent Operator Actions (continued)

INSTRUCTIONS CONTINGENCY ACTIONS CAUTION The ability to maintain Steam Generator levels at full power conditions may be affected as instrument air pressure degrades below 75 PSIG. Air operated valves and instrumentation may lose full range operating capability. Appendix C contains a partial listing of air operated components and their mode of failure upon loss of air supply.

7. ifUinstrument air pressure decreases to less than 75 psig, Then evaluate the need to shut down the unit in accordance with 2-GOP-123, Turbine Shutdown Full Load to Zero Load, or 2-EOP-01, Standard Post Trip Actions.

8. !fUfeedwater regulating 15% bypass

( valves are being used to maintain S/G level, Then use of the Auxiliary Feedwater System will be required if air pressure continues to degrade.

degrade

9. !f11 SDC SOC is In in service, serVice, Then refer to ONOP 2*0440030, 2-0440030. Shutdown Cooling Off-Normal.

Off-Normal

10. U 11 BOTH of the following conditions exist:

Loss of CCW to the RCPs, due to loss of Instrument Air pressure

CCW can NOT be restored within 10 minutes Then PERFORM ALL of the following:

A. TRIP the Reactor.

Reactor B. TRIP the Turbine C. TRIP ALL the RCPs.

D. GO TO 2-EOP-01, Standard Post Trip Actions.

(

\

37

Appendix D Operator Action Form ES-D-2 dl IF--

ii

~

{

\

IiI! Op Test No. No_: Scenario # 7 Event # 7, 8, 9~ 9 _ _ Page

_7;.;.,..;;.8:..;, Page ~ of of

[i:1 Event

Description:

Description Loss of Instrument Air pressure. Plant down power, Unit trip. Three CEA's I Thre.e .CEA>

II

.*11 do not fully insert. Stop all a(( RCP's due to CCW unrecoverable. __

,C'_' -~~='""i'F=====~=~=-======:====:~=======c==-=====~~1 il_ Time Position A licant's Actions or Behavior

Boot Booth h Operator Instructions

f-.. - -..- . - -..---~ ....- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - j 1--

ations Available:

Indications Indic

-rr?irects Directs implementation of 2-EOP-012-EOP-01,, "Standard Post Trip

! Actions" as follows:

I Identifies three CEA's not fully inserted. Directs Emergency SRO I Boration.

80ration.

,.

RO: Reactivity control, Inventory Control, Pressure control, Core Heat Removal I i I

BOP: Vital Auxiliaries, RCS heat removal, Containment I Conditions. I

..- - - - - - - i - - + - - - - - - - - - - - - - - - - - - - - . . I[

i

, Critical Direct stopping RCP's within 10 minutes of loss of CCW I Task

1----

( ---1---' . BOP Notify NPO to perform Appendix X (NPO Actions) section 1 of I; EOP-99. (attached attached page_39-42_)

pa ge- 39-42_)

il-p-e-rf-o~r-ms I

Performs EOP-01 EOP-01 Safety functions as Safety functions as directed directed for for: Maint Maint of of I Vital Auxiliaries RCS Heat Removal, Containment Conditions I c-" -- - - - - - 1 " - - - - - - - - 1 , - - - - - - - - - - - - - - - - - - - - - - - - - - - --I

---~i------+--------------------------------------

i

-~---I Maintenance of Vital Auxiliaries I ** Verifies turbine governor and throttle valves closed

- Verify GEN Brk open (East breaker, Mid Breaker and I BOP Exciter Breaker)

- Verify all vital and non vital AC Buses energized. (2A (2A1, 1,

2A2, 2A3 2AB, 2B1, 2B2 282 and 2B3 283 6.9 and 4.16kv

.. _ ______________ L_

buses)

---~

I,EVISION REVISION NO PROCEDURE TITLE PAGE PAGE.

36A APPENDICES /I FIGURES I/ TABLES I/ DATA 111 of 156 PROCEDURE NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 1 of 8)

NOTE This appendix contains two sections_

sections. Each section has instructions for stabilization of the secondary plant following a unit trip.

trip_

Section 1 provides the field instructions that are performed in the Turbine Generator Building during execution of 2-EOP-01

Section 2 provides the control room instructions that are performed after 2-EOP-01 has been exited Section 1: FIELD ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS oD 1. CONFIRM Turbine trip with the Control Room.

Room_

( oD 2. PERFORM ALL of the following from the Turbine Deck:

oD A. VERIFY ALL Main Steam oD A.1 If11 ANY Main Steam Safety Valves Safety Valves are CLOSED.

CLOSED are OPEN, Then immediately NOTIFY the Control Room.

o B. VERIFY ALL of the following D 0D B.1 11 ANY Turbine Valves are NOT Turbine valves are CLOSED:

CLOSED fully CLOSED, Then locally TRIP the Turbine Turbine.

oD Governor Valves oD Throttle Valves o Intercept Valves D

oD Reheat Valves 39

REVISION NO PROCEDURE TITLE PAGE 36A APPENDICES I/ FIGURES /I TABLES I/ DATA 112 of 156 PROCEDURE NO . SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 2 of 8)

Section 1: FIELD ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS I NOTE II II The remainder of the steps in this section may beperformed be performed in any order.

order. III o 3. PERFORM ALL of the following from the Ground Floor Level:

o A. ADJUST FCV-12-1. FCV-12-1, Condensate Hdr Recirc to Cndsr. as required to maintain Condensate flow of 8.000 gpm. gpm

( o B. PERFORM BOTH of the following to ALIGN cooling water to the Heater Drain Pumps, until water is flowing Pumps.

out the packing gland: gland o THROTTLE OPEN V38238, DMW to 2A Htr Drain Pump Gland Quench Seallsol.

Seal Isol.

o THROTTLE OPEN V38239. DMW to 2B Htr Drain Pump Gland Quench Seal Isol Isol o C. CLOSE V31190, Processed Bldn (Vacuum Drag) to 2B Cndsr Isol. Isol o D. OPEN SB13139, TCW Pumps Iso1.

Cross-Tie Isol.

Disch Cross-Tie.

40

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

REVISION NO PROCEDURE TITLE PAGE:

PAGE 36A APPENDICES /I FIGURES I/ TABLES /I DATA 113 of 156 PRoceDURE PROCEDURE NO SHEETS 2-EOP-99 S1.

ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 3 of 8)

Section 1: FIELD ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS o 4. PERFORM BOTH of the following from on top of the TLO Reservoir:

o A. VERIFY ONE of the following o 1. Bearing Oil Pump and Seal Oil Backup Pump RUNNING.

o 2. Emergency Oil Pump RUNNING.

RUNNING, o B. VERIFY Bearing Oil Lift Pump

( RUNNING, RUNNING o 5. PERFORM ALL of the following from the Mezzanine Deck Deck:

o A. THROTTLE OPEN V09218, S/G Fill Isol, 15 to 20 turns.

o B. THROTTLE OPEN BOTH of the following valves to establish EACH Hood Spray between 200 and 250 psig:

o V12396, 2A LP Turb Spray TCV-22-61A Hdr TCV-22-61 A Bypass o V12403, 26 2B LP Turb Spray Hdr TCV-22-61 B Bypass (continued on next page) 41

REVISION NO PROCEDURE TITLE PAGE 36A APPENDICES I FIGURES I TABLES I DATA 114 of 156 PROCEDURE NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 S1.

APPENDIX X SECONDARY POST TRIP ACTIONS (Page 4 of 8)

Section 1: FIELD ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

5. (continued)

C. VERIFY ALL of the following valves CLOSED:

CLOSED 0 SC-10-3A, 3A LP Htr Extr Stm Non Return 0 SC-10-3B, SC-10-38, 3B LP Htr Extr Stm Non Return 0 SC-10-4A, 4A LP Htr Extr Stm Non Return

(

0 SC-10-48, 4B LP Htr Extr SC-10-4B, Stm Non Return 0 SC-10-5A, 5A HP Htr Extr Stm Non Return o0 SC-10-58, SC-1 0-5B, 5B HP Htr Extr Stm Non Return o 6. From the Turbine Deck, VERIFY the Turning Gear is ready for operation.

o 7. When Section 1 Field Actions are COMPLETE, Then NOTIFY the Control Room.

End of Section 1 42

Appendix D Operator Action Form ES-D-2 fi~---- .

il 11i I!;: Op Test No. No.: Scenario # 7 Event # -.;..:7'...;8~,

7, 8, .;.,9 9 _ _ _ Page ~

_15_ of ....;;.,;20;"-'-11 20 IiII Event

Description:

Description Loss of Instrument Air pressure. Plant down power, Unit trip. Three CEA's I

,. do not fully insert insert. Stop all RCP's due to CCW unrecoverable. I i~--~~me

.... _J Ir' Time Position J=::Eosition JI A plica nt's Actions or Behavior licant's

,~-Bo~-th Booth O~~rator I

, ______ . __...~.'~__'

. Indications Available:

Operator Instructions: Suggested: Trigger Event 10, LOCA when RCP's have been stopped. -I

_~

i

.------------ ----r---------,---------------------------1

. - --- Ti I RC~ RC~ H:a~r~::t~::lst H:a~r~::~::lst one one SGSG has has feedwater available (:~--

feedwater available (MFW -II I

pumps will trip on low flow due to recirc valves failing I.

Ii' BOP BOP closed on loss of air) 0

Verify RCS Tavg is between 525 and 535 0 F

Place ADV's in service due to loss of air to SBCS valves.

i--------i------------------------------I I I[ Containment Conditions I ** Verify containment pressure <2 psig

Verify NO containment radiation monitors in alarm I

-+- 1~._v_e_r_if_y_Containment 0

Verify containment temperaturetemperature is is less less than than 120 120 F 0

F

(

Verify NO secondary plant radiation alarms

-----------------+------1---------------------------1

~_ _ _ _ _ _ _.t-, + - . i_ _ _-+----_ _ _ _ _ _ _ _ _ _ _--1

~-+I~--~ -~~

I I Identifies three CEA's not fully inserted. Initiates emergency

, boration by: by

Place the Makeup Mode Selector switch in Manual RO

Ensure V2525, Boron Load Control valve closed

Start 2A or 2B BA Pump

Close V2650 Tank 2A Recirc Valve

Close V2651 Tank 2B Recirc Valve II------~----

Open V2514, Emergency Borate

-+-----+--------------------------\

i

~-~----*I 1-II I Performs EOP*01EOP-01 Safety Functions as directed for Reactivity I i: Control, Inventory Control, Pressure Control, Core Heat

, _________. II _ __

____ ___ ~-tI~r~e~m~o~v~a~1

-II_r_e_m_o_v_a_I~~_ __ __ _~ _ _ _ _ _ _~~_~~_

________ _ _ _ _ _ _._~~----<

_ _ _--i

- I !

I

- - -- ..- - - - - - - - - - - + - - - -....

_.. -- ~~~-+-~~~~-~~~- ----------------------1

-.~~~.~~~~- ~-------j Critical Start RCP oil lift pumps and stop all RCP's when directed.

... _.. _ .. _ ... _ _ ~~~

Task

_ _ _ L... _ _ _ _ _ ~_~~_~~~~~~ ___ ~~~~_---j NOTE: Trigger Event 10, LOCA, when all RCP's are stopped

~-~~~-

Appendix D 0 Operator Action Form ES-D-2 ES-0-2 i

Iiil Op Test No, No. 1 Scenario # 7 Event # 7, 8, 9

_7;..:"..;.8:...;,9;....-_ _ Page ~

,]L of _20_-11

_2_0--i1

'I

!II: Event

Description:

Description Loss of Instrument Air pressure. Plant down power, Unit trip. trip, Three CEA's Ii do not fully insert, insert. Stop all RCP's due to CCW unrecoverable. unrecoverable, L:i~~-_-=1~~p~0~s~llio~n~"""-=~==~~=~A=PI~ic~an~t~'s~A~C~tio~n=s~o~r~B~eh~a~v~io~r=~===~~~1 Position A licant's Actions or Behavior

Booth Operator Instructions:

~-.---.,

i Indications Available:

r---' --.------ .---------------,!----------------------------i

~----------------------------------------------~

i Reactivity Control

- Verify Reactor power is lowering, lowering.

I I ] .*

Verify startup rate is negative, negative.

_ . !------L. I

maxim~m Verify a maximum of one CEA is not fully inserted. inserted, 1 I Inventory Control I

Verify pressurizer level is between 10 and 68%

I____-+.__*.__Pressurizer I

!,,---T level is trending to 30 -

p_r_es_s_u_r_iz_e_r_le_vel 35%

.-,,--,,--,,-"'j.---------+---------------------------------------<

i

. - - t - - - I Pressure C a n t r a l l

- Pressure Control i

Verify RCS pressure is between 1800-2300 psia I

( I \ I ** Verify RCS pressure is trending 2225-2275 psia (control II

' I manually due to loss of air to spray valves)

! I ** Verify RCS subcooling is >20 >20° F 0 I

+------+----------------------1

. ,,--- ----'--", . -=--+-+-----~-.------ -

I Core Heat Removal j

Verify at least one RCO running with CCW (identifies CCW unable to be restored due to loss of air to valves) 1--- - ---------t--- _ _ _+--__._____

I

Verify loop delta T is <10° F

,i--"-""------+-------+---------------------------------------I e.~_

J

==-

~--_-~~ _-~~_ I SRo_~iI

~----'-"-+-----+-------.-------------~

1 ___ SRO Exits 2-EOP~01 2-ECJP_~_0_9_LO_O_P_/L_O_F_C 2-EOP-01 to 2-EOP-_O,_9_LO_O_P_/L_O_F_C_ _ _ _ _ _~ ___j-1 l---------.~

f---- I ---------------JII NOTE: If RCS leakage identified while in 2-EOP-01, 2-EOP-09 LOOP/LOFC will praba~~~T-_~-T-be probably NOT be entered entered and 2-~_O_P_-_03~OCA and 2-EOP-03 LOCA will will be entered from be entered from 2-EOP-01.

2-EOP-01. _

-- I .--...

Fu~~t-;on

~-

Oi,rect Safety Function Status Check's performed every 15 I Direct i

minutes

! minutes n.-_

i

[~~

r- l==~--n----j.-o-irect pag~-45,46) I I

Direct Appendix Appendix A A EOP-99 EOP-99 Sample Sample SG's SG's (attached (attached page 45,46)

REVISION NO PROCEDURE TITLE PAGE 36A APPENDICES I/ FIGURES I/ TABLES I/ DATA 3 of 156 PROCEDURE NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX A SAMPLING STEAM GENERATORS (Page 1 of 2) o 1,

1. 11if a LOOP has occurred, Then PERFORM BOTH of the following:

o A, ENSURE 2AB 480V Load Center is aligned to an A.

energized bus.

o B. DISPATCH an operator to restore Instrument Air.

8.

REFER TO Appendix H, Operation of the 2A and 2B Instrument Air Compressors.

Compressors CAUTION Under SIAS conditions the CCW 'N' header should only be aligned to ONE essential header. This will maintain train separation while safeguards slqnals are still present.

Signals

( NOTE

HCV-14-9 (HCV-14-10) will open 5 seconds after HCV-14-8A (HCV 8B) starts to open (HCV-14-8B)

When SIAS is present, placing the control switches in CLOSE and then heade~ valves, until SillS OyERRIDE will open the CCW 'N' header SIAS is reset o 2. !f SIAS has closed the 'N' Header valves, Then RESTORE flow from EITHER 'A' or 'B' CCW Header by PLACING the control switches for the deSired desired train to CLOSE and then to OVERRIDE:

OVERRIDE'

HCV-14-8A

HCV-14-9 OR

HCV-14-8B

HCV-14-10 39 45

--~----------------

(

REVISION NO PROCEDURE TITLE PAGE:

PAGE.

36A APPENDICES I/ FIGURES I/ TABLES I/ DATA 4 of 156 PROCEDURE NO. NO SHEETS 2*EOP-99 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX A SAMPLING STEAM GENERATORS (Page 2 of 2) o 3. If CIAS or high radiation has closed the SGBD Sample Valves, Then OPEN FCV-23-7 and FCV-23-9 by PLACING the control switch to CLOSE I/ OVERRIDE and then to OPEN. OPEN, o 4. DIRECT Chemistry to perform SIG 4, S/G samples for activity and boron.

o 5.

5, IJ!.f SIGs S/Gs cannot be sampled, Then DIRECT Health Physics to conduct secondary plant local area radiation surveys END OF APPENDIX A

(

40

(

46

Appendix D 0 Operator Action Form ES-O-2 ES-D-2 r--

~~~-"------"-"

i IiII Op Test No.:

1 No 1 Scenario # 7 Event # _7~'..;;.8,_9 7, 8, 9_ _ _ Page 2Z--

1L- ~.

of _20_..,1 IiII

! Event

Description:

Loss of Instrument Air pressure. Plant down power, Unit trip. trip Three CEA's do not fully insert. Stop all RCP's due to CCW unrecoverable.

II Time Position A plicant's Actions or Behavior

~--"--"--------------------------------,

i Booth Operator Instructions:

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

i

.; Indications Available:

I I Verify CCW to the RCP's. If CCW lost to the RCP's for greater than 30 minutes:

I i.

I

Ensure CCW will remain isolated by placing the FOUR SRO Containment CCW To/From RC Pump valves to CLOSE

"-. ~~"-+--------- t-I ** Ensure RCP controlled Bleedoff will remain isolated by placing the TWO RCP Bleedoff valves to close. ---I I

_=~=r:SRO I Stabilize the secondary plant. X 2 plant Direct Appendix X Section 2

~

II

--1-- -- - - - - - - - + _ _

.. _.._._ .. _. ___.__I_._. . ____,_Stabilize ! Stabilize RCS RCS temperature temperature to to <535°F

<535°F Tcold Teold using using ADV's ADV_'_S____--11I

---"-"""-*""-"---"-------r"""- ------'i

( ~-~+--~--I-I Direct

.-...------l-m~nually starting Direct m_~.nually starting AFW AFW pumps pump~ and feedi~g-S-G-'S----~

and feeding SG's

~ ... -.

=-C--'- i I

*-1 i-I* "-- +----~-------~ --------- ~

! I When directed, depressurize the RCS to between 1800 and 'I RO I 1850 psia using auxiliary spray SE*02-3 SE-02-3 and SE-02-4. .

~--.-------:----

I

~--- .. -

I iI I When--directed, When directed, stabilize RCS temperature to <535°F Tcold Teold using I I

! ADV's I

~-~ I ~

I I

- - - + -! - - - ! I d e n t i fy Cavity leakage increasing, RCS pressure and level Identify l~v~I-- ----l

--~--

---t*-**I

-" """-"~--"--+

I, dropping.

! =J !

"_"" _______~i I

, -- STA-

i When When directed directed perform perform Safety Function Status Safety Function Status Check's Check's i I STA

! I performed every 15minutes 15 minutes . I I

I

t---.---- -~!-------------------------~

I I

BOP I When directed start A and B AFW pumps, open discharge

.. ---"-.---~ ----.1--

II

~.-

I valves and throttle throttle AFW flow to A and B SG's. I i

~

When directed perform Appendix X Section 2 (attached I 1

page page_ _ 48-51_) - -__"_______JI

REVISION NO REVISION NO PROCEDURE TITLE PROCEDURE TITLE PAGE:

PAGE 36A APPENDICES I FIGURES I TABLES I DATA 115 of 156 PROCEDURE NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 5 of 8)

Section 2: CONTROL ROOM ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS o 1. ENSURE ONLY ONE MFW Pump is RUNNING, with the control switch in RECIRC o 2. ENSURE ONLY ONE Condensate Pump is RUNNING, RUNNING.

o 3. !f11 AFAS AF AS has actuated, o 3.1 !f11 AFAS has NOT actuated and use of Main Feedwater is and use of Main Feedwater is desired, desired, Thel}

TheQ PERFORM ALL of the Then PERFORM ALL of the fol/owing:

following' following:

( o A. ENSURE AFAS is RESET,RESET. o A. ENSURE BOTH S/G [Main FRV]

FRV) Block valves CLOSED, CLOSED o B. ENSURE BOTH S/G [Main o B. For EACH MFW header to FRVl Block valves CLOSED, CLOSED. be placed in service, ENSURE the associated MFIVs are OPEN, OPEN.

1. MV-09-5

2. MV-09-6 o C. ENSURE BOTH Low Power o C. ENSURE BOTH Low Power MIA Stations in MANUAL, MANUAL. MIA Stations in MANUAL, MANUAL.

o D. For EACH MFW header to be o D. DEPRESS BOTH placed in service, ENSURE pushbuttons to RESET the the associated MFIVs are Low Power Feedwater OPEN, OPEN. Valves, Valves.

o E. DEPRESS BOTH pushbuttons o E. ADJUST the Low Power MIA to RESET the Low Power Stations AS NECESSARY to Valves, Feedwater Valves. SIG levels.

control S/G levels,

(

48

.~ ~

(

REVISION NO . PROCEDURE TITLE' TITLE PAGE, PAGE 36A APPENDICES I FIGURES I TABLES I DATA 116 of 156 PROCEDURE NO SHEETS 2-EOP-99 ST, ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 6 of 8)

Section 2: CONTROL ROOM ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

3. (continued) o F. ADJUST the Low Power MIA Stations AS NECESSARY to control S/G levels, levels.

o G. RESTORE AFW to the standby alignment, alignment.

o 4. ENSURE BOTH Heater Drain Pumps are STOPPED.

o 5. ENSURE BOTH of the following:

following

( o A.1 o A. Bearing Oil Pump ENSURE Emergency Bearing Oil and Seal Oil Backup Pump Pump RUNNING, RUNNING.

RUNNING, RUNNING.

o B. When the turbine reaches 600 rpm, rpm.

Then Bearing Oil Lift Pump RUNNING.

o 6. ENSURE the Turbine Drain Valves are OPEN o 7. ENSURE ONLY ONE Turbine Cooling Water Pump is IS RUNNING, RUNNING.

o B.

8. VERIFY Turbine Generator Bearing o 8,1 8.1 DIRECT a field operator to adjust Oil temperature between 110 to TCW to the in-service TLO Cooler 120°F to maintain outlet Oil temperature between 110 to 120°F.

(,

49

(

REVISION NO PROCEDURE TITLE PAGE:

PAGE 36A APPENDICES /I FIGURES / TABLES I/ DATA 117 of 156 PROCEDURE NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 7 of 8)

Section 2: CONTROL ROOM ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS o 9. When Turbine speed reaches ZERO 09.1 PERFORM ALL of the following:

following rpm, Then VERIFY the turning gear automatically ENGAGES.

o A. PLACE Turning Gear in MANUAl.

MANUAL o B. VERIFY the Turning Gear Permissive Light is ON.

o C. locally Locally ENSURE the Turning Gear is ENGAGED.

(

o D. locally Locally START the Turning Gear.

o 10.11 Reactor power history is low, 10.lf Then CONSIDER reducing steam generator blowdown now flow to maintain RCS temperature.

o 11. Place Boron Dilution Alarm o 11.1 If11 BOTH Boron Dilution Alarm System in Operation. System channels are NOT operating, When indicated Reactor power is Then PERFORM applicable less than 10'10. 55 %, actions of ONP-02.01, Boron Then PERFORM BOTH of the Concentration Control.

following:

following o A. ENERGIZE BOTH channels of Startup Stanup Nuclear Instrumentation to place the Boron Dilution Alarm System in operation.

o B. VERIFY BOTH Boron Dilution Alarm System Channels are operating.

50

REVISION NO PROCEDURE TITLE PAGE.

PAGE; 36A APPENDICES /I FIGURES I/ TABLES I/ DATA 118 of 156 PROCEDURE NO SHEETS 2-EOP-99 ST, ST. LUCIE UNIT 2 APPENDIX X SECONDARY POST TRIP ACTIONS (Page 8 of 8)

Section 2: CONTROL ROOM ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS NOTE Excessive moisture can build up in CEDMC's room, and impact equipment reliability Ifif 15 KW heaters are not energized after plant shutdown, shutdown.

o 11. NOTIFY SNPO to energize 15 KW 11.NOTIFY heater located In in the CEDMC's room to minimize humidity build-up per 2-NOP-25, 10, CEDMCS Air 2-NOP-2510, Conditioning System Operation, Operation o 12. CONSIDER contacting the Division 12.CONSIDER DIvision Load Dispatcher for a switching order

( to OPEN the Main Generator disconnects END OF APPENDIX X

(

51

--------------~ ----_. _*..._............. -.

Appendix D Operator Action Form ES-D-2

(

II Op Test No No. Scenario # 7 Event # 7,8,9 7, 8, 9 Page Page _18_

_18_ of ~I of ...;:;.;20'--~1 Ii Event

Description:

Description' Loss of Instrument Air pressure. Plant down power, Unit trip. Three CEA's I do not fully insert. Stop all RCP's due to CCW unrecoverable. I Time _:_'JII Position II Ap licant's Actions or Behavior Applicant's ilBO_~!~_

Booth Operator <?~_~rator Instructions:

Indications Available:

I

.----,----~--

When directed perform Appendix A EOP-99 Sample SG's BOP

, (attached page_ 45,46_)

- - --**-+1-------+---------------------------1

---~--

When directed:

Ensure CCW will remain isolated by placing the FOUR Containment CCW To/From RC Pump valves to fl..

BOP BOP

, CLOSE I

Ensure RCP controlled Bleedoff will remain isolated by

-. _______ ._.----r--~______ - . ~.~_.___ . placing the TWO RCP Bleedoff valves to close. close, ~

i

.- - - - - - *I - - + - - - - - - - - - - - ----.~---.-----.-

-- --1-------- _____ . ________________ ..-.----.-.---_1 u m _ _ _ _* ___________ -i

---+-

ii I

[- 1

-+---------------------------

( .......

~!

~-. *-=E-+------

J

, ... __.. _-+_. Il ----+-_*_----------_*_---------_*-----1

--..-.----.--1i ........- . - - - - - - - - - - - - - - - - - - - - - - - - - - 1.J

_ ..._--+".

I i i

._----+----+-----_. -----------------------------------------.;

'-.----.~---r ----

f----~-------+------------------------__j f-.-.-.------ - - - - - - r L___ ... _____---'___________________--'

__ ~ _ _ _ _ _ _ _ _ _- L ._ __

--------~-------------------

Appendix D Operator Action Form ES-D-2 ES*D-2 Op Test No No.:.. Scenario # 7 Event # 10 Page 19 of 20 i,

i

,: Event

Description:

2B2 RCP seal failure results in SBLOCA.

i t___Jirn~ Position A licant's Actions or Behavior

, Booth Operator Instructions: When directed, trigger RCP seal failure. This will result in a 185 gpm LOCA ramping in over 10 minutes.

r- - -------------------------------------~

,f--

Indications Available: Annunciator N-46 Reactivity Cavity leakage high.

i Pressurizer pressure and level lowering.

--~~-----

H---~- ___ J,I__~~~~__l!mplement 2-EOP-03, "Loss of Coolant Accident': _ _ _ _ _

SRO

~--------+--------+----------------------------,

Implement 2-EOP*03, "Loss of Coolant Accident" ----j

."-~_____T_

i

_ - -~--__+I--- -+----+----------------------- --------,--- II

.- _**,1 __ ..- - - - - - - . - _ " -

Directs BOP Directs BOP or or ST ST A to perform A to perform SFSC's SFSC's I

.~

i

~--------;----

, --~~ .. -----------+------ - - - - + I ----------------------------1 I

~_~~

Contact SM to classify the event

1

. .___"+I_ _c_o_n_t_ac_t_S_M_t_o_c,_I_as_S_i_fy_t_h_e_e_v_e_n_t_ _.________---11 I I Direct implementation of Appendix A A EOP-99 Sampling I SG's, if not performed in 2-EOP-09 (attached page 45,46)

~_~-~-,~~ .:'-:I:I: : ~:;-e_s-s_~:ru-e_r:;:.I-A~_*S:f:IO:W: :a:_d-e:q~U-a.-t_e:-p:e:r :R-C- - ~- ~- -j.

(

Ensure SIAS flow adequate per Figure g 2 SI flow Vs. RCS

- ***--_-'_- pressure. *F***.-i:u:r-e:_2:-S:1:f_I:OW::V:S-..

r------------+-~-+-----~---------l I

,- ----------t-I-----------+---D-ir-e-c-ts-B-O-P-t-o-p-I-a-ce-H-yd~r-o-g-e-n-A-n-a-Iy-z-e-r Directs BOP to place Hydrogen Analyzer -in-s-e-r-v-ic-e-p-e-r-----------1, in service per :

I

. __~I______\--_A.ppendix Appendix L L (attached page_54,55_) II

~ --- ---+.----1.: Direct RO to pertorm ReS cooldown not to exceed 50'F in anyone hour using ADV's.

j

-- ~--- -- I I

I Ensures containment spray actuates if pressure reaches reach~~

---1----

i 5.4 psig

+-,Ii - -5.4-psig i

t------ I --------------------1

~- . ,-,----'~----f__--------------.-----------.

I' BOP or STA I Perform Safety Functions for 2-EOP-03, "LOCA" when directed.

~--- -----+-------t------~-----------------------i

~----- ..

__ ~

L~------~-- ___ +i

,~.-----+-----

Ii

\------ -- ---- --- -- -- -- --- -- -- -- --- -- -- -- --- -1 -j

[.---------.--------+----------------------------1

'--~-- - ---~--..- -----'- .----------------------------~--------'

~~-~~---~-------~----

REVISION NO PROCEDURE TITLE PAGE 36A APPENDICES I FIGURES I TABLES I DATA 65 of 156 PROCEDURE NO SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX L PLACING HYDROGEN ANALYZER IN SERVICE (Page 1 of 2)

1. SELECT ONE sample point by PLACING the sample valve selector switch in the desired position position. FSE-27-8_

FSE-27-8 FSE-27*12 (Upper Cntmt. Dome) (Lwr Cntmt)

Cntmt.)

FSE-27-9_ FSE-27-13_

(pzr Area) (262 (282 RCP)

FSE-27-1 0 _ FSE-27-14_

FSE*27-1 (2A1 (2A 1 RCP) (261 (2B1 RCP)

FSE-27-11_

FSE-27-11 (2A2 RCP)

2. OPEN the Containment Isolation Valves. FSE-27-15 FSE-27.15_ FSE-27-17_

FSE-27-17 (Sample in to H2 Analyzer)

( AND FSE-27-16 FSE-27-16_ FSE-27 -18 FSE-27-18_

(Sample out of H2 Analyzer)

3. ENSURE the function selector switch is in the SAMPLE position.

4. PLACE the OFF I STANDBY I/ ANALYZE switch to ANALYZE.

NOTE If power is Interrupted and then restored to an in-service Hydrogen Analyzer (such as after an ESFAS or Undervoltage Relay actuation) the remote control selector pushbutton must be depressed to allow for continued operation of the analyzer from the Control Room.

5. DEPRESS the remote control selector pushbutton.

pushbutton

6. VERIFY the red sample light energizes.

54

REVISION NO PROCE DURE TITLE PROCEDURE PAGE 36A APPENDICES I/ FIGURES I/ TABLES I/ DATA 66 of 156 PROCEDURE NO SHEETS 2-EOP*99 2-EOP-99 ST.

ST_ LUCIE UNIT 2 APPENDIX L PLACING HYDROGEN ANALYZER IN SERVICE (Page 2 of 2)

A Train (Y)(0) B Train C-/)

(-:)

7, START the Hydrogen Analyzer Recorder.Recorder_ (switch located inside inSide recorder)

-- -~

8, Allow five to ten minutes for the Hydrogen Analyzer to 8.

stabilize as indicated by the (%) indication leveling off.

off_

END OF APPENDIX L

(

55

Appendix D Operator Action Form ES-D-2 r---

~=.~

III Op Op TestTest No.: No Scenario # 7 Event # 10 Page 20 of 20 i!, Event

Description:

Description 2B2 RCP seal failure results in SBLOCA SBLOCA.

i:~~=Ti~~~;_-='-b __P~o~s~itl_on__-b______ - =_______ A~I~ic~a_nt~'s_A_c_ti~on=s_o=r_B=e_ha=v=io=r===-

Applicant's Actions or Behavior __- = = - - = - = d

, Booth Operator Instructions:

Indications Available:

I RO ------rPerform RO Perform ,cooldown cooldown using ADV's not to exceed 50°F in anyone i I hour period. 1

--=-~-T -

~- .-'

I I Monitor Monitor subcooling subcooling per per Figure Figure 1A 1A ReSRCS pressure Temperature pressure Temperature I I

_____ ...... ______.. _1_._.""

I I (attached (attached page_57_)

page_57 - ) I

-~

~-~---.

-<I

_~." - .-.-_O...__---..

t-""_ --------...----r-.-- ---------------------- i BOP j Places the hydrogen analyzer in service per Appendix L of 2-

_._~_ . _._.+

I BOP I'

~. _._-_ ..-- .. ,-"

EOP-99 EOP-99 (attached page_54,55_)

(attached page_54,55_) __ ~~~~_ _ _----j.

i

____ -+ ____

-_.- - -_.__ .--1---- ~ ....---------

-.----.-.. - - - i i i - - - - - - - - - - - - - - - - - - - - - - -

I Compares SI flow to RCS pressure, Figure 2. (attached

,~

!I

! : _pa_ g_e_-_58_-_)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _--1!

page_58_)

II l

--+--I

( --=-j-.-I L.---------i----- -----+-t,- --

~-------_t_I .~I ---j-.

1- I

"'-~---r i I,

f----+------I

. --+---------l------

Suggested termination point:

Controlled cooldown of :S50°F :::50°F in anyone hour period.

i

SI fIflow venTIe d to meet F' ow verified Igure 2 Figure

. ___--_-._. . =:===-._-~-A-F-W-f-IO-w-c-o-nt_ro_I_le_d_t_o_b_o_t_h_S_G_'_s_t_o_r_eg_a_i_n_S_G_le_v_e_1s-*----i1 I

I

AFW flow controlled to both SG's to regain SG levels.

t--

I

. _. ._____--_-_-.. .i-_.-_-_-

I

---.. -~

i--

i

....- - - ---- -_.--+---------- .... _ - - - - - - - -

j I

.- ----- .~

II

--'._".- ----1-------.-.--..........,---------- -------.--------- I I

-"._. ..... - --~----\--------------------

I i

. _---_._- ---+--_ I . .._..........,-----------------_.._ - -

(

REVISION NO PROCEDURE TITLE PAGE*

PAGE 36A APPENDICES /I FIGURES /I TABLES /I DATA 119 of 156 PROCEDURE NO SHEETS 2-EOP-99 2*EOP*99 ST. LUCIE UNIT 2 FIGURE F!GURE 1A RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Less Than or Equal to 200°F)

CAUTION The RCP NPSH curve assumes one pump is operating in each loop. loop_ RCP instrumentation should be monitored for seal and pump performance in Instrumentation accordance with 2-EOP-99, 2*EOP*99, Table 13. 13 2<00 1:."""~"~'_~''''w<'''''''''''.1 an;. 1"""."._t.o~~!qf'fIItMpt~~\~'''''V'>f VlIJOtv 01,.. QprllliQ" J..,Q EOPC<I9'II .... ~1 1"<1 ~ CNlVI'\"" "K * .w,.,. ro<00 I I \ I I I \ '000 \ / I 1" ' I M.rllnll,Jrn I I SvPCoQIfH" I ""~'" 600 Reqlllremerw ~ wo ",,-" , '00 ... - ...... /~-- '\nc1udn InlllV~l'lt Shu,do_ LIn('tnllf\l,., 100 E.'/~ I 0 0 100 '00 200 300 '00 500 1O0 600 700 800 600 IndICa Ie<) Res Temperalure (.t") "'-"'V/" ...... ,,, .....'1.01 * ....... ...... 1 '~"' ',r. I! , ReS RCS Pressure Range ___ Required QSPDS Subcooled SUbCO?l!~ Margin Reading (Rep CeT) CET) I I 2250 psia pSla to\0 1000 psia pSI a 40 to 180'F I L____ 1000 1000 psia psi a to 500 psis pSla 50 50 to 170'F to 170°F -lIt 1--- Less than 500 pSla pSI a 80 to 160'F _ 57 -~~----~-- REVISION NONO, PROCEDURE TITLE PAGE 36A APPENDICES I/ FIGURES I/ TABLES I DATA 121 of 156 PROCEDURE NO SHEETS 2*EOP*99 ST. LUCIE UNIT 2 FIGURE 2 SAFETY INJECTION FLOW VS. VS, RCS ReS PRESSURE (Page 1 of 1) 1300 r * - - -r-~-~-l-~~' ~--~-~~---r--In- I 1200 ~-- I - 1--+-~-llf~-~iS curve repres~~sT~inimum expected' -j" r-l- ! SI Flow. If measured flow is less than this p R P 1100 ....... --;- *-11 figure, Then SI System lineup should be , : yenned. ' I. c-. 1 E _.t--+_.: I l ,. T~I S s S 1000 ' I !-_._-,- I ---- -.~, -- i - u U R 900 .:. , I -lI~tl~+___ Z E 800 R --I I i _ --,. 1-+ 1 700 ~ ~_:r-11-F~lt~ -1-;-1 p P I t R ( E 600 ~ _-++--+-+-1 s S sS u U 500 L.~- I in Operation I : ~ . I i r-*r .*iT _._.j 1 I I' 1I1T;;';i--I-*-~--i -.~:--I R E 400'-- -- I -*-1 300 ~-. -- --_. ' _. I __ ~;on - +--f- ._~ ~ +_ ~__ ~ ._+__~. __~ __ \ 1 ____ __ I ~- I I I ! I p .-,,. s I 200 .' ---- -+-_J __ acI 100 _. - -j ~---- --t- .-----"l'--=--_+_ : I I 1 ~""1-_~= o :**----+--..**1~+- .-. o 1000 2000 3000 4000 TOTAL SAFETY INJECTION FLOW (gpm) (PloPsrzEOPS9IF~2t~e,OM) IP'oPsrzEOP99IF~2JR',0I1'l \. 58

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