NL-13-1257, FNP-2-ESP-0.3, Revision 12 - Farley Nuclear Plant Event Specific Procedure FNP-2-ESP-0.3 Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (with Rvlis), Enclosure 3 to NL-13-1257

FNP-2-ESP-0.3, Revision 12 - Farley Nuclear Plant Event Specific Procedure FNP-2-ESP-0.3 Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (with Rvlis), Enclosure 3 to NL-13-1257

ML13198A460
Person / Time
Site:	Farley
Issue date:	06/14/2013
From:	Reed D Southern Co, Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
NL-13-1257 FNP-2-ESP-0.3, Rev 12
Download: ML13198A460 (24)

Text

UNIT 2 Enclosure 3 to NL-13-1257 611412013 12:26 FNP-2-ESP-0.3 5-19-2010 Revision 12 FARLEY NUCLEAR PLANT EVENT SPECIFIC PROCEDURE FNP-2-ESP-0.3 NATURAL CIRCULATION COOLDOWN WITH ALLOWANCE FOR REACTOR VESSEL HEAD STEAM VOIDING (WITH RVLIS)

S A

F PROCEDURE USAGE REQUIREMENTS-per FNP-0-AP-6 SECTIONS E T

Continuous Use ALL Y Reference Use R E

Information Use L A

T E

D Approved:

David L . Reed(for)

Operations Manager Date Issued: 01 / 11 / 11

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611412013 12:26 NATURAL CIRCULATION ! OOLDOWN W~H ALLOWANCE FOR FNP-2-ESP-O.3 Revision 12 REACTOR VESSEL HEAD STEAM VOIDING (WITH RVLIS)

TABLE OF CONTENTS Procedure Contains Number of Pages Body .................................. 16 Figure 1 ............................... 1 Figure 2 ............................... 1 Figure 3 ............................... 1 Attachment 1 ........................... 1 Attachment 2 ........................... 1 Foldout Page ........................... 1 Page 1 of 1

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6/14/2013 12:26 NATURAL CIRCULATION !OOLDO~N wITH ALLOWANCE FOR FNP-2-ESP-O.3 Revision 12 REACTOR VESSEL HEAD STEAM VOIDING (WITH RVLIS)

A. Purpose This procedure provides actions to continue plant cooldown and depressurization to cold shutdown, with no accident in progress, under conditions that allow for the potential formation of a void in the upper head region with a vessel level system available to monitor void growth.

B. Symptoms or Entry Conditions I. This procedure is entered after completing the first ten steps of FNP-2-ESP-O.2 when the limits of FNP-2-ESP-O.2 must be exceeded; from the following:

a. FNP-2-ESP-O.2, NATURAL CIRCULATION COOLDOWN TO PREVENT REACTOR VESSEL HEAD STEAM VOIDING, step 11

b. FNP-2-ESP-O.2, NATURAL CIRCULATION COOLDOWN TO PREVENT REACTOR VESSEL HEAD STEAM VOIDING, step 14 Page 1 of 16

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6/14/2013 12:26 NATURAL CIRCULATION !OOLDO~N wITH ALLOWANCE FOR FNP-2-ESP-O.3 Revision 12 REACTOR VESSEL HEAD STEAM VOIDING (WITH RVLIS)

Step Action/Expected Response Response NOT Obtained II CAUTION: [CA] To ensure proper plant response. FNP-2-EEP-O. REACTOR TRIP OR SAFETY INJECTION. must be entered upon any SI actuation.

CAUTION: The first ten steps of FNP-2-ESP-O.2. NATURAL CIRCULATION COOLDOWN TO PREVENT REACTOR VESSEL HEAD STEAM VOIDING. must be performed before continuing with this procedure.

CAUTION: If RCP seal cooling had previously been lost. the affected RCP should not be started prior to a status evaluation.

NOTE:

• FOLDOUT PAGE should be monitored continuously.

• To ensure adequate pressurizer spray. the priority for establishing RCP support conditions is 2B. 2A and then 2C.

1 [CAl Establish RCP support conditions.

Step 1 continued on next page.

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Step Action/Expected Response Response NOT Obtained II CAUTION: To prevent heat exchanger damage. do not attempt restoration of RCP seal return flow unless the CCW miscellaneous header is aligned to an operating CCW loop.

1.1 Verify CCW cooling - 1.1 Proceed to step 1.3.

ESTABLISHED.

1.1.1 Verify miscellaneous header aligned.

CCW TO SECONDARY HXS

[] Q2P17MOV3047 open 1.1. 2 Verify flow indicated in the On-Service train.

HX 2A(2B.2C)

CCW FLOW

[] FI 3043AA

[] FI 3043BA

[] FI 3043CA 1.2 Verify seal return flow -

ESTABLISHED.

RCP SEAL WTR RTN ISO

[] Q2E21MOV8100 open

[] Q2E21MOV8112 open 1.3 Verify No.1 seal support conditions established.

1.3.1 Maintain seal injection flow - GREATER THAN 6 gpm.

1.3.2 Verify No.1 seal leakoff flow - WITHIN FIGURE 1 LIMITS.

1.3.3 Verify No.1 seal differential pressure -

GREATER THAN 200 psid.

Step 1 continued on next page.

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Step Action/Expected Response Response NOT Obtained II I I I l.4 Verify CCW aligned.

CCW FROM RCP THRM BARR

[] Q2P17HV3045 open

[] Q2P17HV3184 open l.5 Check RCP thermal barrier - 1.5 Verify CCW flow isolated.

INTACT.

CCW FROM RCP RCP THRM BARR THRM BARR [] Q2P17HV3045 closed CCW FLOW [] Q2P17HV3184 closed HI

[] Annunciator DD2 clear l.6 Verify at least one RCP bus - 1.6 Proceed to step 1.11.

ENERGIZED.

[] 2A 4160 V bus

[] 2B 4160 V bus

[] 2C 4160 V bus l.7 Check CCW to RCP oil coolers - 1.7 Perform the following.

SUFFICIENT.

1.7.1 Verify CCW - ALIGNED.

CCW FLOW FROM RCP CCW TO RCP CLRS OIL CLRS [] Q2P17MOV3052 open LO

[] Annunciator DD3 clear CCW FROM RCP OIL CLRS

[] Q2P17MOV3046 open

[] Q2P17MOV3182 open 1.7.2 I I annunciator DD3 clear.

THEN proceed to step 1.8.

IF NOT proceed to step 1.11.

Step 1 continued on next page.

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Step Action/Expected Response Response NOT Obtained II 1.8 Check at least one RCP oil 1.8 Proceed to step 1.11.

level - SUFFICIENT.

RCP 2A(2B.2C) BRG UPPER/LOWER OIL RES LO LVL

[] Annunciator HH1 clear

[] Annunciator HH2 clear

[] Annunciator HH3 clear 1.9 Check RCS pressure - GREATER 1.9 I I RCS within FIGURE 2 limits.

THAN 1800 psig. THEN proceed to step 1.10.

IF NOT proceed to step 1.11.

2C(2A) LOOP RCS WR PRESS

[] PI 402A

[] PI-403A Step 1 continued on next page.

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Step Action/Expected Response Response NOT Obtained II 1.10 Check REACTOR VESSEL LEVEL 1.10 Establish conditions to indication - 100% UPPER HEAD. accommodate void collapse upon RCP start.

1.10.1 Raise pressurizer level to greater than 67% using charging and letdown .

• Raise charging flow.

CHG FLOW

[] FK 122 adjusted

• Reduce letdown flow.

1.10.2 Raise SUB COOLED MARGIN MONITOR indication to greater than 40°F subcooled in CETC mode.

1.10.2.1 Dump steam at a faster rate.

1.10.3 Use PRZR heaters. as necessary to saturate the pressurizer water.

PRZR HTR GROUP VARIABLE

[] 2C PRZR HTR GROUP BACKUP

[] 2A

[] 2B

[] 2D

[] 2E Step 1 continued on next page.

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Step Action/Expected Response Response NOT Obtained II CAUTION: Step 1.10 must be complete before starting any RCP.

NOTE: Changes in RCP configuration may affect pressurizer spray flow.

1.11 [CA] IT support conditions 1.11 Perform the following.

exist to start an RCP THEN start at least one RCP. a) Continue efforts to establish RCP support 1.11.1 Start bearing oil lift conditions.

pump.

b) WHEN support conditions RCP exist to start an RCP.

OIL LIFT PUMP THEN return to step 1.

[] 2B(2A.2C) c) Proceed to step 2.

1.11.2 Check oil lift pressure OBSERVE NOTE PRIOR TO indicating light - LIT. STEP 2.

1.11.3 Start RCP.

RCP

[] 2B(2A.2C) 1.11.4 WHEN RCP has operated for one minute.

THEN stop bearing oil lift pump.

RCP OIL LIFT PUMP

[] 2B(2A.2C) 1.12 [CA] IT at least one RCP started.

THEN go to FNP-2-UOP-2.1.

SHUTDOWN OF UNIT FROM MINIMUM LOAD TO HOT STANDBY.

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Step Action/Expected Response Response NOT Obtained II NOTE: To prevent excessive pressure variations. saturated conditions should be established in the pressurizer prior to lowering pressurizer level.

2 Establish pressurizer level to accommodate void growth.

2.1 Check pressurizer level - 2.1 Control charging and letdown 25%-35%. as necessary.

2.2 Place charging flow control in manual.

CHG FLOW

[] FK 122 3 [CAl Continue RCS cooldoWil.

3.1 [CAl Maintain RCS cold legs cooldown rate - LESS THAN 100°F IN ANY 60 MINUTE PERIOD.

RCS COLD LEG TEMP

[] TR 410 3.2 [CAl Maintain SUB COOLED MARGIN MONITOR indication -

GREATER THAN 36°F SUB COOLED IN CETC MODE.

3.3 [CAl Maintain RCS cold leg temperature and pressure -

WITHIN FIGURE 3 LIMITS.

RCS COLD LEG TEMP

[] TR 410 2C(2A) LOOP RCS WR PRESS

[] PI 402A

[] PI 403A Page 8 of 16

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Step Action/Expected Response Response NOT Obtained II NOTE: Reactor vessel steam voiding may occur during RCS pressure reduction.

This will cause a rapid rise in pressurizer level.

4 Begin RCS pressure reduction.

4.1 I I normal letdown in service. 4.1 Open only one PRZR PORV to THEN control auxiliary spray reduce RCS pressure.

to reduce RCS pressure.

4.2 Maintain RCS cold leg temperature and pressure -

WITHIN FIGURE 3 LIMITS.

RCS COLD LEG TEMP

[] TR 410 2C(2A) LOOP RCS WR PRESS

[] PI 402A

[] PI 403A 5 [CAl Maintain pressurizer level 25%-90%.

5.1 Check pressurizer level - 5.1 Raise pressurizer level using GREATER THAN 25%. one or both of the following.

• Raise charging flow.

CHG FLOW

[] FK 122 manually adjusted

• Reduce letdown flow.

Step 5 continued on next page.

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Step Action/Expected Response Response NOT Obtained II 5.2 Check pressurizer level - LESS 5.2 Perform the following.

THAN 90%.

NOTE: The intent of step 5.2.1 is to maintain the pressurizer liquid at saturation temperature.

5.2.1 Turn on additional pressurizer heaters.

PRZR HTR GROUP VARIABLE

[] 2C PRZR HTR GROUP BACKUP

[] 2A

[] 2B

[] 2D

[] 2E 5.2.2 Reduce pressurizer level to less than 90% by one of the following.

• Control charging and letdown flow as necessary.

Reduce charging flow CHG FLOW

[] FK 122 manually adjusted Raise letdown flow.

• Continue RCS cooldown to shrink inventory.

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Step Action/Expected Response Response NOT Obtained II 6 [CAl Check REACTOR VESSEL LEVEL 6 Perform the following.

indication - GREATER THAN 44%

UPPER PLENUM. 6.1 Raise RCS pressure.

6.1.1 Turn on additional pressurizer heaters.

PRZR HTR GROUP VARIABLE

[] 2C PRZR HTR GROUP BACKUP

[] 2A

[] 2B

[] 2D

[] 2E 6.2 Return to step 3.

7 Check when to isolate SI accumulators.

7.1 Check power to discharge 7.1 Close accumulator discharge valves - AVAILABLE. valve disconnects using ATTACHMENT 1.

2A(2B.2C) ACCUM DISCH ISO

[] Q2E21MOV8808A

[] Q2E21MOV8808B

[] Q2E21MOV8808C 7.2 [CAl WHEN RCS pressure less 7.2 Vent any SI accumulator that than 1000 psig. cannot be isolated.

THEN close all SI accumulator discharge valves. ACCUM N2 VENT 2A(2B.2C) ACCUM [] HIK 936 open DISCH ISO

[] Q2E21MOV8808A

[] Q2E21MOV8808B SI ACCUM 2A 2B 2C

[] Q2E21MOV8808C 2A(2B.2C) ACCUM N2 SUPP/VT ISO Q2E21HV [] 8875A [] 8875B [] 8875C open open open Step 7 continued on next page.

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Step Action/Expected Response Response NOT Obtained II 7.3 [CAl WHEN SI accumulator discharge valves closed.

THEN open and lock accumulator discharge valve disconnects using ATTACHMENT 2.

8 [CAl Maintain letdown flow.

8.1 WHEN letdown flow less than required.

THEN open additional letdown orifice isolation valves.

LTDN ORIF ISO 45 GPM

[] Q2E21HV8149A LTDN ORIF ISO 60 GPM

[] Q2E21HV8149B

[] Q2E21HV8149C 8.2 WHEN letdown flow less than required.

THEN adjust low pressure letdown control valve.

LP LTDN PRESS

[] PK 145 9 [CAl Maintain seal injection flow to each RCP 13 gpm.

SEAL WTR INJECTION

[] HIK 186 adjusted Page 12 of 16

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Step Action/Expected Response Response NOT Obtained II

_10 Check if RHR system can be placed in service.

10.1 Check RCS hot leg temperatures 10.1 Return to step 3.

- LESS THAN 350°F.

RCS HOT LEG TEMP

[] TR 413 10.2 Check RCS narrow range 10.2 Return to step 3.

pressure - LESS THAN 350 psig.

2C(2A) LOOP RCS NR PRESS

[] PI 402B

[] PI 403B 10.3 Place RHR system in service using FNP-2-S0P-7.0. RESIDUAL HEAT REMOVAL SYSTEM.

11 [CAl Continue RCS cooldown to cold shutdown with RHR.

CAUTION: Reactor vessel steam voiding may occur if the RCS is depressurized before the entire RCS is cooled to less than 200°F.

12 [CAl Continue cooldown of inactive portion of RCS.

12.1 Maintain RCS pressure -

350-400 psig.

2C(2A) LOOP RCS NR PRESS

[] PI 402B

[] PI 403B 12.2 Verify both CRDM FANs -

STARTED.

12.3 Continue dumping steam from all SGs.

12.4 Check REACTOR VESSEL LEVEL 12.4 Return to step 11.

indication - 100% UPPER HEAD.

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Step Action/Expected Response Response NOT Obtained II

_13 Check if RCS depressurization is permitted.

NOTE: FNP-2-S0P-68.0. INADEQUATE CORE COOLING MONITORING SYSTEM provides detailed operating instructions for the core exit T/C monitor.

13.1 Check reactor vessel upper 13.1 Return to step 11.

head temperature - LESS THAN 200 F .

0 CORE EXIT THERMOCOUPLE MONITOR

[] TRAIN A (Points 22.23)

[] TRAIN B (Points 16.20) 13.2 Check all atmospheric relief 13.2 Perform the following.

valves - OPEN.

13.2.1 Direct counting room to 2A(2B.2C) MS ATMOS perform FNP-0-CCP-64S. MAIN REL VLV STEAM ABNORMAL

[] PC 3371A ENVIRONMENTAL RELEASE.

[] PC 3371B

[] PC 3371C 13.2.2 Open all atmospheric relief valves.

2A(2B.2C) MS ATMOS REL VLV

[] PC 3371A

[] PC 3371B

[] PC 3371C 13.3 Locally check SGs - NOT 13.3 Return to step 11.

STEAMING.

13.4 Go to FNP-2-UOP-2.2. SHUTDOWN OF UNIT FROM HOT STANDBY TO COLD SHUTDOWN.

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START STEP CONTINUOUS ACTION o CAUTION [CA] To ensure proper plant response.

FNP-2-EEP-0. REACTOR TRIP OR SAFETY INJECTION. must be entered upon any SI actuation.

1 [CA] Establish RCP support conditions.

1.11 [CA] IF support conditions exist to start an RCP THEN start at least one RCP.

1.12 [CA] IF at least one RCP started. THEN go to FNP-2-UOP-2.1. SHUTDOWN OF UNIT FROM MINIMUM LOAD TO HOT STANDBY.

[CA] Continue RCS cooldown.

3.1 [CA] Maintain RCS cold legs cooldown rate - LESS THAN 100F IN ANY 60 MINUTE PERIOD.

3.2 [CA] Maintain SUB COOLED MARGIN MONITOR indication -

GREATER THAN 36F SUB COOLED IN CETC MODE.

3.3 [CA] Maintain RCS cold leg temperature and pressure -

WITHIN FIGURE 3 LIMITS.

[CA] Maintain pressurizer level 25%-90%.

[CA] Check REACTOR VESSEL LEVEL indication - GREATER THAN 44% UPPER PLENUM.

7.2 [CA] WHEN RCS pressure less than 1000 psig. THEN close all SI accumulator discharge valves.

7.3 [CA] WHEN SI accumulator discharge valves closed. THEN open and lock accumulator discharge valve disconnects using ATTACHMENT 2.

[CA] Maintain letdown flow.

[CA] Maintain seal injection flow to each RCP 13 gpm.

0 11 [CA] Continue RCS cooldown to cold shutdown with RHR.

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T _J_ "T "'" Enclosure 3 to NL 1257 611412013 12:26 NATURAL CIRCULATION t OOLDOf N W~H ALLOWANCE FOR FNP-2-ESP-O.3 Revision 12 REACTOR VESSEL HEAD STEAM VOIDING (WITH RVLIS)

START STEP CONTINUOUS ACTION D 12 [CA] Continue cooldown of inactive portion of RCS.

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6/14/2013 12:26

,--*- -----T *

."".~

. Enclosure 3 to NL-13-1257

---

r--------,

NATURAL CIRCULATION COOLDOWN WITH ALLOWANCE FOR FNP-2-ESP-O.3 Revision 12 REACTOR VESSEL HEAD STEAM VOIDING (WITH RVLIS)

FIGURE 1 NO. 1 SEAL NORMAL OPERATING RANGE 2400 2250 I

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

/

J iiUU

/

2000

/

1800 No rma 1 Operating Range 1600 f

/

/

No.1 Seal 1400 Differential Pressure

( PS I D. See

/

Note 1) 1200 V

1000

/

800 600 V

/

/

400 j

200 I

I I

I 0

o .2 1 234 5 6 No.1 Seal Leak Rate (GPM)

Note 1: For No.1 Seal Differential Pressures greater than 400 psid. use ReS pressure in psig.

T _J__ Encosure I 3 t0 NL 1257 611 412013 12:26 NATURAL CIRCULATION t OOLDOWN W 11H ALLOWANCE FOR FNP-2-ESP-O. 3 Revi s ion 12 REACTOR VESSEL HEAD STEAM VOIDING (WITH RVLIS)

FIGURE 2 RCP PRESSURE-TEMPERATURE OPERATING LIMITS 1800 1700 J 1600 I 1500 I 1400 I 1300 1200 1100 /

ReS 1000 Acc eptabl e Rep /

Pressure (ps i g) 900 Opera ti on /

800 /

700 /

600 /

500 V

/

400 /

/

300 200 100 0

0 100 200 300 400 500 600 ReS Hot Leg Tempera t ure (O F)

T _J__ Encosure I 3 t0 NL 1257 611 412013 12:26 NATURAL CIRCULATION t OOLDOWN W 11H ALLOWANCE FOR FNP-2-ESP-O. 3 Revi s ion 12 REACTOR VESSEL HEAD STEAM VOIDING (WITH RVLIS)

FIGURE 3 UNIT 2 100°FiHR TECH. SPEC. LIMIT RCS COOLDOWN RCS Pressure 2500 (n .i ::J I

2250 I

2000 I I

I 1750 Unacc eptable I Opera ti on I 1500 I I

I I

Acc eptabl e 1250 I Opera ti on I

1000 I J

J 750 Cooldown Rat e /

100° F/ HR J 500 250 Min. RCS Bol t up Temp. =75° F 0 I I I 0 50 100 150 200 250 300 350 400 450 500 RCS Co l d Leg Tempera t ure (O F)

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Step Action/Expected Response Response NOT Obtained II ATTACHMENT 1 1 Close the following disconnects.

'B' Train Disconnects Disconnect Description Position Key Location TPNS No.

139' hall way-Q2R18B03S-B Disconnect FV-S2 MOV 8808B-B ON v-s outside elec.

penetration room

'A' Train Disconnects Disconnect Description Position Key Location TPNS No.

Q2R18B031-A Dis conne ct FU-Z3 MOV 8808C-A ON V-6 139' hall way -

~---------+---------------------------+--------r---~outside Q2R18B032-A Dis conne ct FU-Z2 MOV 8888A-A ON V-4 counting room 2 Verify accumulator discharge valves MCB indication - POWER AVAILABLE.

2A(2B.2C) ACCUM DISCH ISO

[] Q2E21MOV8808A

[] Q2E21MOV8808B

[] Q2E21MOV8808C 3 Notify control room of accumulator discharge valve disconnect status.

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Step Action/Expected Response Response NOT Obtained II ATTACHMENT 2 1 Open and lock the following disconnects.

'A' Train Disconnects Disconnect Description Position Key Location TPNS No.

139 ' hallway-Q2R18B031-A Disconnect FU-Z3 MOV 8808C-A LOCKED V-6 outside OPEN counting room Q2R18B032-A Disconnect FU-Z2 MOV 8808A-A LOCKED V-4 OPEN

'B' Train Disconnects Disconnect Description Position Key Location TPNS No.

139' hallway-Q2R18B035-B Disconnect FV-S2 MOV 8808B-B LOCKED V- 5 outside elec.

OPEN penetration room 2 Notify control room of accumulator discharge valve disconnect status.

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NATURAL CIRCULATIO~Ol B8E~o~GW1TH ALLOWANCE FOR 611412013 12:26 FNP-2-ESP-O.3 Revision 12 REACTOR VESSEL HEAD STEAM VOIDING (WITH RVLIS)

Step Action/Expected Response Response NOT Obtained II I I I 1 Monitor SI criteria.

1.1 Greater than 16°F subcooled in 1.1 Verify SI actuated AND go CETC mode and PRZR level above to FNP-2-EEP-O.

4%.

2 Monitor switchover criteria.

2.1 CST level greater than 5.3 ft. 2.1 Align AFW pumps suction to SW using FNP-2-S0P-22.0.