ML20091J844

Rev 1 to Emergency Operating Procedure E-0, Reactor Trip or Safety Injection

ML20091J844
Person / Time
Site:	Point Beach
Issue date:	09/01/1983
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20091J821	List: ML20091J818 ML20091J828 ML20091J837 ML20091J844 ML20091J849 ML20091J856 ML20091J858
References
E, E-0, TAC-56311, TAC-56312, TAC-56602, TAC-56603, NUDOCS 8406060220
Download: ML20091J844 (12)

Text

'

, ATTACHMENT 1.3 i

. 'n n m .. ja.,a o. ,

' #'"'" I E.0 REACTOR TRIP OR SAFETY INJECTION

, 1 Sept.1983 A. PURPOSE This guideline provides actions to verify proper response of the automatic protection systems

~

following manual or automatic actuation of a reactor trip or safety injection, to sssess plant conditions, and to identify the appropriate recovery guideline.

B. 5YMPTOMS OR ENTRY CONDITIONS

1) The following are symptoms that require a reactor trip, if one has not occurred:

[ Enter plant specific setpoints and requirements).

2) The following are symptoms of a reactor trip: ,

c. Any reactor trip annunciator lit,

b. Rapid decrease in neutron level indicated by nuclear instrumentation.

c. All shutdown and control ror's are fully inserted. Rod bottom lights are lit.

3) The following are symptoms that require a reactor trip and safety injection, if one hos not occurred:

[ Enter plant specific setpoints and requirements). 1

4) The following are symptoms of a reactor trip and safety injection:

a. Any Si annunciator lit.

b. Si pumps running.

c. [ Enter plant specific list].

t e

~

8406060220 840601 PDR ADOCK 05000266 F PDR

• • N8 Gew.tenwe, m :

s LP Rev. I E0 REACTOR TRIP OR SAFETY INJECTION 1 Sept.1983 J

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -

NOTE

• Steps 1 through 14 are IMMEDIA TE ACTION steps.

~

• Foldout page should be open. ,

i 1 Verify Reector Trip: Manually trip reactor. E reactor will NOT ,

i trip, THEN go to FR-5.1, RESPONSE TO

• Rod bottom lights - LIT NUCLEAR POWER GENERATION / ATWS,

• Reactor trip and bypass breakers -

OPEN St'P I-

• Rod position indicators - AT ZERO

• Neutron flux - DECREASING 2 Verify Turbine Trip:

a. All turbine stop volves - CLOSED o. Manually trip turbine.

3 Verify Power To AC Emergency Busses:

a. AC emergency busses - AT LEAST o. Try to restore power to at least one ONE ENERGl2ED oc emergency bus.E power con NOT be restored to at least one ac emergency bus, THEN go to ECA-0.0, LOSS OF ALL AC POWER, Step 1.

b. AC emergency busses - ALL b. Try to restore power to deenergized ENERGlZED oc emergency busses.

4 Check if Si is Actuated: Check if 51 is required. 2 51 is required.

THEN manually actuate. 2 Si is NOT

[ Enter plant specific means]

required, THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step 1.

t 2 of 13

- rm., i. n . ,w, LP Rev. 1 E0 REACTOR TRIP OR SAFETY INJECTION

. 1 Sept.1983 I

STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -

5 Verify FW isolation: Manually close valves as necessary.

• Flow control valves - CLOSED

-

• Flow control bypass valves - CLOSED

• FW isolation volves - CLOSED

• SG blowdown isolation valves -

CLOSED

+ SG sample isolation volves - CLOSED 6 Verify Containment Isolation Phase A:

a. Phase A - ACTUATED a. Manually actuate Phase A.

b. Phase A valves - CLOSED b. Manually close valves.

7 Verify AFW Pumps Running:

a. MD pumps - RUNNING a. Manually start pumps.

b. Turbine-driven pump - RUNNING IF b. Manually open steam supply valves NECESSARY 8 Verify $l Pseps Running: Manually start pumps.

• High-head 51 pumps - RUNNING

• Low-head Si pumps - RUNNING 9 Verify CCW Pumps - RUNNING Manually start pumps.

3 ef 13 i.

I _. _.. .. _ . _ .

iMonsters TH6es lRev. leave /Deses l

E0 LP-Rev.1 REACTOR TRIP OR SAFETY INJECTION 1 Sept.1983 STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -

10 Verify Service Water Pumps - RUNNING Manually start pumps.

11 Verify Containment Fon Coolers - Manually start fan coolers in emergency

_ RUNNING IN EMERGENCY MODE mode.

12 Verify Containment Ventikion Isolation:

a. Dampers - CLOSED o. Manually close dampers.

(Appropriate steps for verification of other essential equipment as required by the specific plant design should be p! aced after Step 12.]

13 Check if Main Steomlines should Be Isolated:

a. [ Enter plant specific means or a. Go to Step 14.

setpoints]

b. Verify main steamline isciation and b. Manually close volves, bypass valves - CLOSED ,

14 Verify Containment Spray Not Required:

a. Containment pressure - HAS a. Perform the following:

REMAINED LESS THAN u) PSIG 1) Verify containment spray initiated.

jf NQ.T, THEN manually initiate.

2) Verify containment isolation Phase B volves closed g NJ, THEN manually close volves.

3) Stop all RCPs.

l 4 of 13

!~

• psewed art flese: Rev. leave /Deses E0

• REACTOR TRIP OR SAFETY INJECTION LPoRev.1 1 Sept.1983 i

l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -

15 Verify 51 Flow:

a. RCS pressure - LESS THAN (2) PSIG o. Ga to Step 16.

((J) PSIG FOR ADVERSE CONTAINMENT]

b. High-head 51 pump flaw indicators - b. Manually start pumps and align CHECK FOR FLOW valves.

c. RCS pressure - LESS THAN (4) PSIG c.' Go to Step 16.

[($) PSIG FOR ADVER5E CONTAINMENT]

d. Law-head 51 pump f!aw indicatars - d. Manually start pumps and align CHECK FOR FLOW volves.

16 Verify AFW Flow - GREATER THAN Manually start pumps and align valves as (6) GPM necessary. IF AFW flaw greater than (6/ gpm can NOT be established, THEN ga to FR H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.

17 Verify AFW Velve Alignment - PROPER Manually align volves as necessary.

EMERGENCY ALIGNMENT 18 Verify SI Velve Alignment - PROPER Manually align volves as necessary.

EMERGENCY ALIGNMENT l

l I

l 5 si13 i

i

Asv. leave @ eve:

[habert TMos LP Rev. 1

E0 REACTOR TRIP OR SAFETY INJECTION

• 1 Sept.1983 l

STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED CA UTION

• If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.

• If SIis reset before automatic transfer of high-head SIpump suction to RWST occurs, manual transfer on BA T low level is required.

19 Check RCP Seal Cooling:

a. CCW flow to RCP thermal barriers - c. E CCW to an RCP is lost, THEN:

NORMAL 1) Trip the RCP.

2) Reset 51.

3) Verify adequate power available to run one charging pump. If necessary, shed sufficient non-essential loads.

4) Start one charging pump at minimum speed for soci injection.

20 Check RCS Average Temperature - E temperature less than (7;*F ond STABLE AT OR TRENDING TO (7;*F decreasing, THEN:

a) Stop dumping steam.

b) { cooldown continues, THEN control total feed flow. Maintain total feed

> flow greater than (6i gpm until narrow range level grecter than /31%

(t91% for adverse containment) in at least one SG.

c) { cooldown' continues, THEN close main steamline isolation and bypass valves.

g temperature greater than (7)*F and increasing, THEN: ,

• Dump steam to condenser.

-OR-

• Dump steam using SG PORVs.

6 of 13

n*n m ,a . mm ,

~

E0 REACTOR TRIP OR SAFETY INJECTION LP Rev. 1 1 Sept.1983 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -

l 21 Check PRZR PORVs And Spray Volves:

o. PORVs - CLOSED o. E PRZR pressure le'ss than /101 psig, THEN manually close PORVs.E any volve con NOT be closed, THEN manually close its block valve. E block volve can NOT be closed, THEN go to E-1, LOSS OF REACTOR OR SECONDA#Y COOLANT, Step 1.

b. Normal FRZR spray valves - CLOSED b. IF /RZR preseare less then //11 psig, THEN manually lose valves. IFF valves can NOT be closed. THEN stop RCP(s).

supplying failed spray cive(s).

22 Check If RCPs should Be Stopped:

a. High-head 51 pumps - AT LEAST o. Go to Step 23.

ONE RUNNING

b. RCP Trip Parameter - LESS THAN //11 b. Go to Step 23.

[(1.7) FOR ADVERSE CONTAINMENT]

c. Stop oil RCPs i

l l

l l

7 of 13

mn m .. I a .i ,

REACTOR TRIP OR SAFETY INJECTION LPcRev.1 E0 1 Sept.1983 )

STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -

I 23 Check if SGs Are Not Fowlted:

a. Check pressures in all SGs - a. Go to E-2, FAULTED STEAM GENERATOR 150LAT40N, Step 1.

• NO SG PRESSURE DECREASING IN AN UNCONTROLLCD MANNER

• NO SG COMPLETELY DEPRESSURIZED 24 Check if SG Tubes Are Net Ruptured: Go to E-3, STEAM GENERATOR TUBE

• Condenser air ejector radiation - RUPTURE, Step 1.

NORMAL

• SG blowdown radiation - NORMAL 25 Check if RCS is latect: Go to E 1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

• Containment radiction - NORMAL

• Containment pressure - NORMAL

• Containment recirculation sump level - NORMAL 8 of 13 l

w m. ja .i ,

REACTOR TRIP OR SAFETY INJECTION LP Rev. 1 E0 1 Sept.1983 d STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check If 51 Flow Should Be Terminated:

o. RCS subcooling based on core exit a. DO NOT STOP 51 PUMPS. Go to

~

TCs - GREATER THAN (14;*F Step 28.

b. Secondary heat sink: b. E neither condition satisfied, THEN DO NOT STOP 51 PUMPS. Go to

• Total feed flow to SGs - GREATER Step 28.

THAN (6) GPM

-OR-

• Narrow range level in at least one SG - GREATER THAN /3/%

c. RCS pressure: c. DO NOT STOP 51 PUMPS. Go to Step 28.

• Pressure - GREATER THAN (2) PSIG

• Pressure - STABLE OR INCREASING

d. PRZR level - GREATER THAN (15>% d. DO NOT STOP 51 PUMPS. Try to stabilize RCS pressure with normal PRIR spray. Return to Step 260.

27 Go To E51.1, $1 TERMINATION, Step 1 l

l l

9 of 13

Muh fl8088 Rev. lanes */ Deco:

LP Rev. 1 E0 REACTOR TRIP OR SAFITY INJECTION i

1 hpt.1983 STEP l ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -

28 laitiste Monitoring Of Critical Sofety Function Status Trees ,

CA UTION Alternate water sourcesfor AFWpumps will be necessary if CST level decreases to less than n6).

29 Geck SG Levels:

a. Narrow range level - GREATER THAN a. Maintain total feed flow greater than (81% (6) gpm until narrow range level greater than ts)% in at least one SG.

b. Control feed flow to maintain narrow b. IF narrow rsage level in any SG range level between ts>% and 50% continues to increase in an uncontrolled manner, THEN go to E 3, l

STEAM GENERATOR TUBE RUPTURE, Step 1.

30 Deck Secondary Rodietion - NORMAL Go to E 3, STEAM GENERATOR TUBE RUPTURE, Step 1.

[ Enter plant specific means]

31 Geck Auxiliory Building Redietion - Evaluate cause of abnormal conditions. LF .

NORMAL the cause is o loss of RCS inventory outside containment, THEN go to ECA 1.2, LOCA OUTSIDE CONTAINMENT, Step 1.

t 32 Geck PRT Conditions - NORMAL Evoluote cause of abnormal conditions.

en 10 of 13 y - ,, -- - - . , --- , - , , , , -------,.a , ,- , -- ,-- -

IW TMet Sov. leave / Dees LP Rev. I

> E.0 REACTOR TRIP OR SAFITY INJECTION 1 Sept.1983 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED I

CA UTION

• If offsite power is lost after SI reset, jnanua!

action may be required to restart safeguards equipment.

• If SIis reset before automatic transfer of high-head SIpump suction to RWST occurs, manual transfer on BA T low level is required.

33 Reset 51 34 Roset Containment Isolation Phase A And Phase B 35 Establish lastrument Air To Conteinment Start one air compressor and establish instrument air to containment.

CA UTION RCS pressure should be monitored. If RCS pressure decreases to less than u> psig the low-head SI

pumps must be manually restarted to supply water to the RCS.

36 Check If Lew.ifeed $1 Pumps Shevid Be Stopped:

a. Check RCS pressure:

1) Pressure - GREATER THAN 1) Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

(4) PSIG

2) Pressure - STABLE OR INCREASING 2) Go to Step 37.

b. Stop low head 51 pumps and place in stondby li d 13

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

Tmeen m es n .wm REACTOR TRIP OR SAFETY INJECTION 1.P.Rev.1 E0 1 Sept.1983 STEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTAINED -

37 Oeck Power Supply To Gorging Verify adequate diesel capacity to run Pomps - 0FFSITE POWER AVAILABLE charging pumps. If necessary, shed

~

sufficient non-essential loads.

38 Geck if Charging Flow Has Been Established:

a. Charging pumps - AT LEAST ONE o. Perform the following:

RUNNING 1) 1F CCW flow to RCP(s) thermal barrier is lost, THEN isolate seal injection to affected RCP(5) before starting charging pumps.

2) Start charging pumps as necessary.

b. Establish flow as 'necessary:

[ Enter plant specific means]

39 Geck if Diesel Generators 5hecid Be Stepped:

a. Verify oc emergency busses - c. Try to restore offsite power to oc ENERGlZED BY OFFSITE POWER emergency busses.2 offsite power con NOT be restored, THEN loo.1 the following equipment on ac emergency busses:

(Enter piant specific list).

b. Stop any unloaded diesel generator and place in standby 40 Return Te Step 20 .

- END -

l l 12 of 13

.. -.