ML040570773

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Transmittal of Emergency Operating Procedures
ML040570773
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/17/2004
From: Widay J
Rochester Gas & Electric Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML040570773 (71)
v • d • e


Text

R 1s A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND ELECTRIC CORPORATION E 89 EASTAVENUE, ROCHESTER, N.Y. 146490001 d 716.771.3250 JOSEPH A. WIDAY VICE PRESIDENT

& PLANT MANAGER GINNA STATION February 17, 2004 www.rge.orn U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, JAW/jdw xc:

U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):

ANIT Index E Index ATI-3.0, Rev 7 ATT-3. 1, Rev 5 ATT-14.7, Rev 0 E-0, Rev 36 E-1, Rev 29 A,

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PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ATT-1.0 ATTACHMENT AT POWER CCW ALIGNMENT 003 02/12/2003 0211212003 02/1212008 EF ATT-1.1 ATT-2.1 ATT-2.2 ATT-2.3 ATT-2.4 ATT-2.5 ATT-3.0 ATT-3.1 ATT-4.0 ATT-5.0 ATT-5.1 ATT-5.2 ATT-6.0 ATT-7.0 ATT-8.0 ATT-8.1 ATT-8.2 ATT-8.3 ATT-8.4 ATT-8.5 ATT-9.0 ATT-9.1 ATT-10.0 ATT-1 1.0 ATT-1 1.1 ATT-1 1.2 ATT-12.0.

ATT.13.0 ATT.14.0 ATTACHMENT NORMAL CCW FLOW ATTACHMENT MIN SW ATTACHMENT SW ISOLATION ATTACHMENT SW LOADS IN CNMT ATTACHMENT NO SW PUMPS ATTACHMENT SPLIT SW HEADERS ATTACHMENT C/CVI ATTACHMENT CNMT CLOSURE ATTACHMENT CNMT RECIRC FANS ATTACHMENT COND TO SIG ATTACHMENT SAFW ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP ATTACHMENT COND VACUUM ATTACHMENT CR EVAC ATTACHMENT DC LOADS ATTACHMENT DIG STOP ATTACHMENT GEN DEGAS ATTACHMENT NONVITAL ATTACHMENT SI/UV ATTACHMENT LOSS OF OFFSITE POWER ATTACHMENT LETDOWN ATTACHMENT EXCESS LA)

ATTACHMENT FAULTED SIG ATTACHMENT [A CONCERNS ATTACHMENT IA SUPPLY ATTACHMENT DIESEL AIR COMPRESSOR ATTACHMENT N2 PORVS ATTACHMENT NC ATTACHMENT NORMAL RHR COOLING 000 05/18/2000 05/18/2000 005 02101/2001 02103/2003 008 03/06/2002 03127/2003 004 03/0612002 12131/1999 002 05/30/2003 10/31/2001 000 06/26/2002 06/26/2002 007 02117/2004 02117/2004 005 02117/2004 02117/2004 003 07/26/1994 03/27/2003 006 10/10/2003 12/31/1999 008 05/30/2002 12/31/1999 003 01/14/1999 01/28/2004 003 12/18/1996 02/03/2003 006 03106/2002 02/03/2003 007 02104/2004 02/04/2004 005 03/06/2002 02103/2003 008 06/20/2002 08/17/1999 004 03/06/2002 02103/2003 005 03/06/2002 02103/2003 001 08/26/2003 05102/2002 009 01107/2004 03/06/2002 005 03/06/2002 10/31/2001 006 03/06/2002 03/27/2003 003 06/26/2003 03/27/2003 003 03/06/2002 03/27/2003 004 11/18/2002 03/10/2003 005 02/1212003 02/1212003 003 02/122003 0211212003 003 03/06/2002 09/23/1999 05/18/2005 02/03/2008 03/27/2008 12/31/2004 10/31/2006 06/26/2007 02/17/2009 02/17/2009 03127/2008 12/31/2004 12131/2004 01/28/2009 02/03/2008 02103/2008 02/04/2009 02103/2008 08/17/2004 02/03/2008 02/03/2008 05/0212007 03/06/2007 10/31/2006 03/27/2008 03/27/2008 03/27/2008 03/10/2008 02/1212008 02/12/2008 09/23/2004 EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF Er EF EF EF EF EF EF EF EF EF

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S PROCEDURE NUMBER ATT 14.1 ATT 14.2 ATT-14.3 ATT 14.5 ATT-14.6 ATT-14.7 ATT-15.0 ATT-15.1 ATT-15.2 ATT-16.0 ATT-16.1 ATT-16.2 ATT-17.0 ATT-17.1 ATT-18.0 ATT-20.0 ATT-21.0 ATT-22.0 ATT-23.0 ATT-24.0 ATT-26.0 PROCEDURE TITLE ATTACHMENT RHR COOL ATTACHMENT RHR ISOL ATTACHMENT RHR NPSH ATTACHMENT RHR SYSTEM ATTACHMENT RHR PRESS REDUCTION ATTACHMENT ADJUST RHR FLOW ATTACHMENT RCP START ATTACHMENT RCP DIAGNOSTICS ATTACHMENT SEAL COOLING ATTACHMENT RUPTURED SIG ATTACHMENT SGTL ATTACHMENT RCS BORON FOR SGTL ATTACHMENT SD-i ATTACHMENT SD-2 ATTACHMENT SFP - RWST ATTACHMENT VENT TIME ATTACHMENT RCS ISOLATION ATTACHMENT RESTORING FEED FLOW ATTACHMENT TRANSFER 4160V LOADS ATTACHMENT TRANSFER BATTERY TO TSC ATTACHMENT RETURN TO NORMAL OPERATIONS EFFECT LAST 006 04/30/2003 01/08/2002 003 02112/2003 02/12/2003 003 03/06/2002 01/28/2004 003 03/20/2003 02/03/2003 002 03/06/2002 01/28/2004 000 02/17/2004 02/17/2004 009 03/06/2002 03/17/2000 003 04/24/1997 02/03/2003 005 03/06/2002 02/03/2003 011 07/18/2001 01/11/2000 002 03/06/2002 09/08/2000 003 11/26/2003 09/08/2000 016 10/10/2003 02/29/2000 006 03/06/2002 01/30/2001 005 03/06/2002 02/03/2003 003 07/26/1994 02/03/2003 002 03/06/2002 02/03/2003 003 05/02/2002 01/22/2002 000 02/26/1999 01/28/2004 000 09/08/2000 09/08/2000 000 10/31/2001 10/31/2001 NEXT REVIEW 01/08/2007 02/12/2008 01/28/2009 02/03/2008 01/28/2009 02/17/2009 03/17/2005 02/03/2008 02/03/2008 01/11/2005 09/08/2005 09108/2005 02/28/2005 01/30/2006 02/03/2008 02/03/2008 02/03/2008 01/22/2007 01/28/2009 09/08/2005 10/31/2006 ST E:

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PRE STATUS VALUE(S):

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PRE EMERGENCY PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST E-0 REACTOR TRIP OR SAFElY INJECTION 036 02/17/2004 03/24/2003 03/2412008 EF E-1 LOSS OF REACTOR OR SECONDARY COOLANT 029 02/1712004 03/24/2003 03/24/2008 EF E-2 FAULTED STEAM GENERATOR ISOLATION 011 05/30/2003 03/24/2003 03/24/2008 EF E-3 STEAM GENERATORTUBE RUPTURE 036 01/07/2004 03/24/2003 03/24/2008 EF PRE TOTAL 4

GRAND TOTAL:

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7 ATT-3.0 ATTACHMENT CI/CVI PAGE 1 of 4 K'QuavQJ\\"U Responsible Manager NOTE:

Locked valve Date a___-__

key may be r uired for local operations.

1.

For each of the following AUTO ISOL VALVES that will not close, take the action directed in the ALTERNATE ISOLATION column.

AUTO ISOL VALVE AOV-200A(L/D)

ALTERNATE ISOL Close the following valves:

(MCB)

  • AOV-371
  • HCV-133 AOV-200B(L/D)

Close the following valves:

(MCB)

  • AOV-371
  • HCV-133 AOV-202(L/D)

Close the following valves: (MCB)

  • AOV-371
  • HCV-133 AOV-5392 (IA)

Close the following valves: (IB BASEMENT CLEAN SIDE)

  • V-5397
  • V-5410 AOV-371(L/D)

Close the following valves: (NRHX ROOM)

V-204A V-820 MOV-313(RCP Seal)

Close the following valves:

(SWRF ROOM

[reach rods])

V-315A

  • V-315C AOV-9227(Fire Sys)

(Normally closed, and does NOT receive CI signal)

Close V-9225 (IB BASEMENT CLEAN SIDE)

AOV-508 (RMW)

Close the following valves:

(MCB)

  • AOV-548
  • AOV-550A
  • AOV-550B

EOP:

TITLE:

REV: 7 ATT-3.0 ATTACHMENT CI/CVI PAGE 2 of 4 AUTO ISOL VALVE ALTERNATE ISOL AOV-5738(S/G B/D)

AOV-5737(S/G B/D)

AOV-5735(S/G Saml AOV-5736(S/G Samr SOV-921(H2 Mon)

SOV-922(H2 Mon)

SOV-923(H2 Mon)

SOV-924(H2 Mon)

AOV-539(PRT gas)

AOV-1789(RCDT to Close V-5701 Close V-5702 Close V-5733 Close V-5734 Close V-928A Close V-928B Close V-929A Close V-929B Close V-546 gas anal)

Close V-1655 (IB BASEMENT CLEAN SIDE)

(IB BASEMENT CLEAN SIDE)

(SAMPLE HOOD)

(SAMPLE HOOD)

(INSIDE A H2 MON PNL, AFW PUMP AREA, key 59 required)

(INSIDE A H2 MON PNL, AFW PUMP AREA, key 59 required)

(INSIDE B H2 MON PNL, AFW PUMP AREA, key 59 required)

(INSIDE B H2 MON PNL, AFW PUMP AREA, key 59 required)

(BY SFP HX A)

(BY SFP HX A)

AOV-1786(RCDT/VH)

AOV-1787(RCDT/VH)

AOV-1721(RCDT Pumps)

Close AOV-1787 (MCB)

Close AOV-1786 (MCB)

Close the following valves:

  • AOV-1003A (WASTE PANEL)
  • AOV-1003B (WASTE PANEL)
  • V-1722 (AB SUB-BASEMENT, NORMALLY LOCKED CLOSED)

AOV-1003A(RCDT Pump AOV-1003B(RCDT Pump AOV-1597(CNMT rad)

AOV-1598 (CNMT rad)

AOV-1599(CNMT rad)

A)

B)

Close AOV-1721 (WASTE PANEL)

Close AOV-1721 (WASTE PANEL)

Close V-1596 (IB BASEMENT CLEAN SIDE)

Close AOV-1599 (MCB)

Close AOV-1598 (MCB)

EOP:

TITLE:

REV: 7 ATT-3.0 ATTACHMENT CI/CVI PAGE 3 of 4 AUTO ISOL VALVE ALTERNATE ISOL MOV-813(CCW)

Perform the following:

1) Direct AO with locked valve key to unlock and close breaker for MOV-817 (MCC D POS 10C)
2)

Stop both RCPs

3) Manually close MOV-817 (MCB).

IF MOV-817 will not close, THEN direct AO to locally close MOV-817 (AB INT LEVEL).

MOV-814(CCW)

Close V-815A (AB INT LEVEL)

AOV-1723(CNMT sump)

Perform the following:

1) Place BOTH CNMT Sump Pumps in PULL-STOP (MCB REAR)
2)

Close AOV-1728 (WASTE PANEL)

AOV-1728(CNMT sump)

Perform the following:

1) Place BOTH CNMT Sump Pumps in PULL-STOP (MCB REAR)
2)

Close AOV-1723 (WASTE PANEL)

AOV-951(PRZR STM samp)

Close AOV-966A (MCB)

AOV-953(PRZR Liq samp)

Close AOV-966B (MCB)

AOV-955(Hot Leg samp)

Close AOV-966C (MCB)

AOV-959(RHR samp)

(fuses normally pulled)

Close V-957 (PRIMARY SAMPLE ROOM, normally closed)

AOV-966A(PRZR STM samp) Close V-956F (SAMPLE.HOOD)

AOV-966B(PRZR Liq samp) Close V-956E (SAMPLE HOOD)

AOV-966C(Hot Leg samp)

Close V-956D (SAMPLE HOOD)

AOV-846(Accum N2)

Close the following valves:

(BY SFP HX A)

  • V-8629
  • V-944A

EOP:

TITLE:

REV: 7 ATT-3.0 ATTACHMENT CI/CVI PAGE 4 of 4 AUTO ISOL VALVE AOV-8418(DI Water)

ALTERNATE ISOL Close V-5021 (IB BASEMENT CLEAN SIDE)

AOV-7971(Mini-purge)

AOV-7970(Mini-purge)

AOV-7445(Mini-purge)

AOV-7478(Mini-purge)

Close AOV-7970 Close AOV-7971 Close AOV-7478 Close AOV-7445 (MCB REAR)

(MCB REAR)

(MCB REAR)

(MCB REAR)

AOV-5879(CNMT purge)

AOV-5869(CNMT purge)

N/A FLANGED N/A FLANGED SOV-1B (10214S1)

Close V-1080A (H2 recomb)

(normally de-energized)

SOV-2B (10214S)

Close V-1080A (H2 recomb)

(normally de-energized)

(SAMPLE HOOD, NORMALLY LOCKED CLOSED)

(SAMPLE HOOD, NORMALLY LOCKED CLOSED)

SOV-3B (10211S1)

(H2 recomb)

Close V-1076B (SAMPLE HOOD, NORMALLY LOCKED CLOSED)

(normally de-energized)

SOV-5B (10213S1)

Close V-1084B (H2 recomb)

(normally de-energized)

SOV-1A (10215S1)

Close V-1080A (H2 recomb)

(normally de-energized)

SOV-2A (10215S)

Close V-1080A (H2 recomb)

(normally de-energized)

(SAMPLE HOOD, NORMALLY LOCKED CLOSED)

(SAMPLE HOOD, NORMALLY LOCKED CLOSED)

(SAMPLE HOOD, NORMALLY LOCKED CLOSED)

SOV-3A (10205S1)

(H2 recomb)

Close V-1076A (IB BASEMENT CLEAN SIDE, NORMALLY LOCKED CLOSED)

(normally de-energized)

SOV-5A (10209S1)

(H2 recomb)

Close V-1084A (IB BASEMENT CLEAN SIDE, NORMALLY LOCKED CLOSED)

(normally de-energized)

EOP:

TITLE:

ATT-3.1 k3 REV: 5 PAGE 1 of 3 ATTACHMENT CNMT CLOSURE I D-Responsible Manager Date 0 -/7)

A) Ensure at least one door closed in EACH CNMT airlock:

o Equipment airlock o Personnel airlock B) Verify valves in column I closed.

IF any valve NOT closed, THEN evaluate penetration and isolate if penetration has direct access to outside atmosphere (Refer to column 2).

NOTE:

Locked valve key may be required for local operation.

COLUMN 1 COLUMN 2 AUTO ISOL VALVE ALTERNATE ISOL AOV-5392 (IA)

Close the following valves: (IB BSMT CLEAN SIDE)

  • V-5397
  • V-5410 AOV-371 (L/D)

MOV-313 (RCP Seal)

AOV-9227 (Fire Sys)

AOV-508 (RMW)

AOV-5738 (S/G BID)

AOV-5737 (S/G B/D)

AOV-5735 (S/G samp)

AOV-5736 (S/G samp)

AOV-539 (PRT gas)

AOV-1789 (RCDT to gas anal)

Close the following valves:

(NRHX ROOM)

  • V-204A
  • V-820 Close the following valves:

(SWRF ROOM

[reach rods])

  • V-315A
  • V-315C Close V-9225 (IB BSMT CLEAN SIDE)

Close the following valves:

(MCB)

  • AOV-548
  • AOV-550A
  • AOV-550B Close V-5701 (IB BSMT CLEAN SIDE)

Close V-5702 (IB BSMT CLEAN SIDE)

Close V-5733 (SAMPLE HOOD)

Close V-5734 (SAMPLE HOOD)

Close V-546 (BY SFP HX A)

Close V-1655 (BY SFP HX A)

EOP:

TITLE:

REV: 5 ATT-3.1 ATTACHMENT CNMT CLOSURE PAGE 2 of'3 COLUMN 1 COLUMN 2 AUTO ISOL VALVE ALTERNATE ISOL AOV-1786 (RCDT/VH)

Close the following valves:

  • AOV-1787 (MCB)

AOV-1721 (RCDT pumps)Close the following valves:

  • AOV-1003A (WASTE PANEL)
  • AOV-1003B (WASTE PANEL)
  • V-1722 (AB SUB-BASEMENT, NORMALLY LOCKED CLOSED)

AOV-1597 (CNMT rad)

Close V-1596 (IB BSMT CLEAN SIDE)

AOV-1598 (CNMT rad)

Close AOV-1599 (MCB)

MOV-813 (CCW)

Ensure CCW SYSTEM INTACT (AUX BLDG INT, MOV-814 (CCW)

BY RWST)

Ensure CCW SYSTEM INTACT (AUX BLDG INT, BY RWST)

AOV-1723(CNMT sump)

Perform the following:

1)

Place BOTH CNMT Sump Pumps in PULL-STOP (MCB REAR)

2) Close AOV-1728 (WASTE PANEL)

AOV-846 (ACCUM N2)

Close the following valves:

(BY SFP HX A)

V-8629

  • V-944A AOV-8418 (DI water)

Close V-5021 (IB BSMT CLEAN SIDE)

AOV-7970 (Mini purge)Close AOV-7971 (MCB REAR)

AOV-7445 (Mini purge)Close AOV-7478 (MCB REAR)

AOV-5879 (Purge)

Stop the Purge Exhaust Fan (MCB REAR)

AOV-5869 (Purge)

Stop the Purge Supply Fan (MCB REAR)

EOP:

TITLE:

REV: 5 ATT-3.1 ATTACHMENT CNMT CLOSURE PAGE 3 of 3 C) Verify both S/Gs intact in CNMT OR steam and feed headers isolated outside CNMT (Refer to 0-15.2, REQUIRED VALVE LINEUP FOR REACTOR HEAD REMOVAL, for specific guidance).

D) Evaluate and isolate any other known openings from CNMT to the outside atmosphere.

Contact Outage Scheduling or Maintenance Manager and refer to O-2.3.lA, CONTAINMENT CLOSURE CAPABILITY IN TWO HOURS DURING REDUCED RCS INVENTORY OPERATION, for add-itional guidance.

E) Verify fuel transfer flange installed or gate valve, V-650J, closed.

F) Contact Outage Scheduling to ensure that S/G maintenance penetration (Pen 2) is isolated (no openings to outside).

EOP:

TITLE:

REV: 0 ATT-14.7 ATTACHMENT ADJUST RHR FLOW PAGE 1 of 1 Responsible Manager _

Date

_1______

This attachment provides instructions for locally throttling HCV-624 and HCV-625 following a LOCA to ensure RHR pump NPSH requirements are met for sump recirculation.

NOTE:

Locked valve key required.

1. Perform the following to locally throttle HCV-624 handwheel:

a) Unlock and remove chain from HCV-624 handwheel.

b) Turn handwheel in the closed direction to take up handwheel play until resistance is felt (- 3/4 handwheel turn) and reference marks attached to the handwheel and air operator bonnet are aligned.

At this point, further handwheel actuation will initiate valve travel in the closed direction.

c) With reference marks attached to the handwheel and air operator bonnet aligned, rotate handwheel 17 complete turns in the closed direction.

d) Upon attaining 17 complete turns closed, turn handwheel in the open direction 2 complete turns.

e) Lock HCV-624 handwheel to maintain current throttled setting of HCV-624.

2. Perform the following to locally throttle HCV-625 handwheel:

a) Unlock and remove chain from HCV-625 handwheel.

b) Turn handwheel in the closed direction to take up handwheel play until resistance is felt (- 21/2 handwheel turns) and reference marks attached to the handwheel and air operator bonnet are aligned.

At this point, further handwheel actuation will initiate valve travel in the closed direction.

c) With reference marks attached to the handwheel and air operator bonnet aligned, rotate handwheel 18 complete turns in the closed direction.

d) Upon attaining 18 complete turns closed, turn handwheel in the open direction 1 complete turn.

e) Lock HCV-625 handwheel to maintain current throttled setting of HCV-625.

Eop:

TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 29 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER

__3 RESPONSIBLE tNAGER EF-ECI

-E DA0 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE -

This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection and to assess plant conditions, and identify the appropriate recovery procedure.

B. ENTRY CONDITIONS/SYMPTOMS

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

o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-1, REACTOR CONTROL AND PROTECTION SYSTEM.

o Operator discretion.

2. The following are symptoms of a reactor trip:

o Any First Out reactor trip annunciator lit.

o A rapid decrease in core neutron level as indicated by nuclear instrumentation.

o MRPI indicates all control and shutdown rods on bottom.

o Reactor trip breakers indicate open.

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

o Any plant parameter reaches the Safety Injection setpoint and logic listed in procedure P-i, REACTOR CONTROL AND PROTECTION SYSTEM.

o Operator discretion.

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

o Any SI annunciator lit.

o Safeguards sequencing started.

l EOP:rlTLE:REV

3 6 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 3 of 29 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 0

Verify Reactor Trip:

o At least one train of reactor trip breakers - OPEN o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manually trip reactor.

IF reactor trip breakers NOT open, THEN perform the following:

a. Open Bus 13 and Bus 15 normal feed breakers.
b. Verify rod drive MG sets tripped.
c. Close Bus 13 and Bus 15 normal feed breakers.
d. Reset lighting breakers.

IF the reactor will NOT trip OR IF power range NIS indicates greater than 5%. THEN go to FR-S.1.

RESPONSE TO REACTOR RESTART/ATWS.

Step 1 0

0 Verify Turbine Stop Valves -

CLOSED Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS:

  • Bus 14 and Bus 18
  • Bus 16 and Bus 17 Manually trip turbine.

IF turbine trip can NOT be verified. THEN close both MSIVs.

Attempt to start any failed emergency D/G to restore power to all AC emergency busses.

IF Bus 14 AND Bus 16 are deenergized. THEN go to ECA-O.O.

LOSS OF ALL AC POWER, Step 1.

EOP:

TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 4 of 29 SP ACTION/EXPECTED RESPONSE l

lRESPONSE NOT OBTAINEDl O

Check if SI is Actuated:

a. Any SI Annunciator - LIT
a. IF any of the following conditions are met. THEN manually actuate SI and CI:

o PRZR pressure 1750 psig less than

-OR-o Steamline pressure 514 psig less than

-OR-o CNMT pressure greater than 4 psig

-OR-o SI sequencing started

-OR-o Operator determines SI required IF SI is NOT required. THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step 1.

b. SI sequencing - BOTH TRAINS STARTED.
b. Manually actuate SI and CI.

EOP:

TITLE:

REV: 3 6 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 5 of 29 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl NOTE: o FOLDOUT page should be open and monitored periodically.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

5 Verify SI and RHR Pumps Running:

a. All SI pumps - RUNNING
a. Perform the following:
1) Ensure SI pump suction supply open from RWST.
2) Manually start pumps.
b. Both RHR pumps - RUNNING
b. Manually start pumps.

6 Verify CNMT RECIRC Fans Running:

a. All fans - RUNNING
b. Charcoal filter dampers green status lights - EXTINGUISHED
a. Manually start fans.
b. Dispatch personnel to relay room with relay rack key to locally open dampers by pushing in trip relay plungers.

. AUX RELAY RACK RA-2 for fan A

  • AUX RELAY RACK RA-3 for fan C

EOP:

TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 6 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 7 Verify CNMT Spray Not Required:

o Annunciator A-27. CNMT SPRAY -

EXTINGUISHED o CNMT pressure - LESS THAN 28 PSIG Verify CNMT spray initiated.

IF CNMT spray NOT initiated. THEN perform the following:

a. Depress manual CNMT spray pushbuttons (2 of 2).
b. Ensure CNMT spray pumps running.

IF no CNMT spray pump available.'

THEN go to Step 8.

c. Ensure CNMT spray pump discharge valves open for operating pump(s).

o CNMT spray pump A:

  • MOV-860A
  • MOV-860B o CNMT spray pump B:
  • MOV-860C
  • MOV-860D
d. Verify NaOH flow (FI-930)

IF NaOH flow NOT indicated. THEN place switches for NaOH tank outlet valves to OPEN.

  • AOV-836A
  • AOV-836B

l EOP:

TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION

.PAGE 7 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check If Main Steamlines Should Be Isolated:

a. Any MSIV - OPEN
b. Check CNMT pressure - LESS THAN 18 PSIG
c. Check if ANY main steamlines should be isolated:
a. Go to Step 9.
b. Ensure BOTH MSIVs closed and go to Step 9.
c. Go to Step 9.

o Low Tavg (545oF) AND high steam flow (0.4x106 lb/hr) from either S/G

-OR-o High-High steam flow (3.6x106 lb/hr) from either S/G

d. Verify MSIV closed on the affected S/G(s)
d. Manually close valves.

9 Verify MFW Isolation:

a. MFW pumps - TRIPPED
a. Perform the following:.
1) Manually close MFW pump discharge valves and trip MFW pumps.
2) Continue with Step 9c.

WHEN both MEPs are tripped. THEN perform Step 9b.

b. Depress MANUAL pushbuttons for A and B S/G MFW regulating valve and bypass valve controllers AND adjust to 0% demand.
c. SIG blowdown and sample valves -

CLOSED

c. Place SIG blowdown and sample valve isolation switch to CLOSE.

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 8 of 29 SP ACTION/EXPECTED RESPONSEl RESPONSE NOT OBTAINED 10 Verify Both MDAFW Pumps Running Manually start both MDAFW pumps.

IF less than 2 MDAFW pumps are running. THEN manually open TDAFW pump steam supply valves.

  • MOV-3505A

. MOV-3504A 11 Verify At Least Two SW Pumps RUNNING Perform the following:

a. Ensure one SW pump running on each energized screenhouse AC emergency bus:
  • Bus 17
  • Bus 18
b. IF offsite power NOT available.

THEN ensure SW isolation.

c. IF NO SW pumps running. THEN perform the following:
1) Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

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TITLE:I REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 9 of 29 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 12 Verify CI And CVI:

a. CI and CVI annunciators - LIT
a. Depress manual CI pushbutton.

. Annunciator A-26, CNMT ISOLATION

b. Verify CI and CVI valve status lights - BRIGHT
b. Manually close affected CI and CVI valve(s).

I IF valve(s) can NOT be closed from the MCB. THEN dispatch AO to locally close affected valve(s)

IF valve(s) can NOT be locally closed. THEN close alternate isolation valve(s).

(Refer to ATT-3.0. ATTACHMENT CI/CVI).

c. CNMT RECIRC fan coolers SW outlet valve status lights -

BRIGHT

c. Dispatch AO to locally fail open valves.

. FCV-4561

. FCV-4562

d. Letdown orifice valves - CLOSED
  • AOV-200A
  • AOV-200B
  • AOV-202
d. Place affected valve switch to CLOSE.

IF valves can NOT be verified closed by MCB indication. THEN close alternate isolations.

(Refer to ATT-3.0.

ATTACHMENT CI/CVI)

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 10 of 29 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 4

4 4

4 4

4 4

4 4

CAUTION RCP TRIP CRITERIA LISTED ON FOLDOUT PAGE SHOULD BE MONITORED PERIODICALLY.

4 13 Check CCW System Status:

a. Verify CCW pump - AT LEAST ONE RUNNING
a. IF offsite power available. THEN manually start one CCW pump.
b. Place switch for excess letdown AOV-310 to CLOSE
c. Place switch for CCW from excess letdown. AOV-745 to CLOSE 14 Verify SI And RHR Pump Flow:
a. SI flow indicators - CHECK FOR FLOW
a. IF RCS pressure 1400 psig. THEN pumps and align THEN go to Step less than manually start valves.

IF NOT.

15.

b. RHR flow indicator - CHECK FOR FLOW 15 Verify AFW Valve Alignment:
b. IF RCS pressure less than 140 psig. THEN manually start pumps and align valves.

IF NOT.

THEN go to Step 15:

Manually align valves as necessary.

a. AFW flow -

INDICATED TO BOTH S/G(s)

b. AFW flow from each MDAFW pump -

LESS THAN 230 GPM

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TITLE:

~REV: 36l E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 11 of 29 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl

  • 16 Monitor Heat Sink:
a. Check S/G narrow range level -

GREATER THAN 5% [25% adverse CNMT] in any S/G

a. Perform the following:
1) Verify total AFW flow -

GREATER THAN 200 GPM IF total AFW is less than 200 gpm, THEN manually start pumps and align valves to establish greater than 200 gpm AFW flow.

IF AFW flow greater than 200 gpm can NOT be established, THEN go to FR-H.1. RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.

2) Go to Step 17.
b. Check S/G narrow range level -

BOTH S/G LESS THAN 50%

b. Secure AFW flow to any S/G with level above 50%.
c. Control feed flow to maintain S/G narrow range level between 5% [25% adverse CNMT] and 50%.

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TITLE:

REV: 3 6 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 12 of 29 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 17 Verify SI Pump And RHR Pump Emergency Alignment:

a. RHR pump discharge to Rx vessel deluge - OPEN
  • MOV-852A

. MOV-852B

b. Verify SI pump C - RUNNING
c. Verify SI pump A - RUNNING
d. Verify SI pump B - RUNNING
e. Verify SI pump C discharge valves - OPEN
  • MOV-871A
  • MOV-871B
a. Ensure at least one valve open.
b. Manually start pump on available bus.
c. Perform the following:
1) Ensure SI pumps B and C running.

IF either pump NOT.

running. THEN go to Step 17e.

2) Ensure SI pump C aligned to discharge line A:

o MOV-871A open o MOV-871B closed

3) Go to Step 18.
d. Perform the following:
1) Ensure SI pumps A and C running.

IF either pump NOT.

running, THEN go to Step 17e.

2) Ensure SI pump C aligned to discharge line B:

o MOV-871B open o MOV-871A closed

3) Go to Step 18.
e. Manually open valves as necessary.

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 13 of 29 STECACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET.

TO RESTART SAFEGUARDS EQUIPMENT.

(REFER OFFSITE POWER)

THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5, ATTACHMENT LOSS OF 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

18 Check CCW Flow to RCP Thermal Barriers:

o Annunciator A-7. RCP 1A CCW RETURN HI TEMP OR LO FLOW -

EXTINGUISHED IF CCW to a RCP is lost. THEN perform the following:

a. Stop affected RCPs.
b. Reset SI.

o Annunciator A-15.

RETURN HI TEMP OR EXTINGUISHED RCP 1B CCW LO FLOW -

c. Verify adequate power available to run one charging pump (75 kw).
d. Start one charging pump at minimum speed for seal injection.
e. Adjust HCV-142 to establish either of the following:

o Labyrinth seal D/P to each RCP greater than 15 inches of water.

-OR-o RCP seal injection flow to each RCP greater than 6 gpm.

f. IF large.imbalance in seal injection flow exists. THEN consider local adjustment of V-300A and V-300B.

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TITLE:

REV: 3 6 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 14 of 29 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 19 Check If TDAFW Pump Can Be Stopped:

a. Both MDAFW pumps - RUNNING
a. Go to Step 20.
b. PULL STOP TDAFW pump steam supply valves
  • MOV-3504A
  • MOV-3505A
  • 20 Monitor RCS Tavg -

STABLE AT IF temperature less than 5470F and OR TRENDING TO 547° F decreasing, THEN perform the following:

a. Stop dumping steam.
b. Ensure reheater steam supply valves are closed.
c. IF cooldown continues. THEN control total feed flow greater than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in at least one S/G.

d. WHEN S/G level greater than 5%

[25% adverse CNMT] in one S/G.

THEN limit feed flow to that required to maintain level in at least one S/G.

e. IF cooldown continues, THEN close both MSIVs.

IF temperature greater than 5471F and increasing. THEN dump steam to stabilize and slowly decrease temperature to 547 0F.

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TITLE:

REV: 3 6 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 15 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check PRZR PORVs Valves:

a. PORVs - CLOSED And Spray
a. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.

IF any valve can NOT be closed.

THEN manually close its block valve.

. MOV-516 for PCV-430

  • MOV-515 for PCV-431C IF block valve can NOT be closed. THEN go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT.

Step 1.

b. Auxiliary spray valve (AOV-296)

- CLOSED

b. Manually close auxiliary spray valve.

IF valve can NOT be closed. THEN perform the following:

1) Decrease charging pump flow to minimum.
2) Ensure charging valve to loop B cold leg open (AOV-294).
c. Check PRZR pressure -

2260 PSIG LESS THAN

c. Continue with Step pressure less than THEN do Step 21d.
22. WHEN 2260 psig.
d. Normal PRZR spray valves - CLOSED
  • PCV-431A
  • PCV-431B
d. Place controllers in MANUAL at 0% demand.

IF valves can NOT be closed., THEN stop associated RCP(s).

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 16 of 29 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 22 Monitor RCP Trip Criteria:

a. RCP status - ANY RCP RUNNING
b. SI pumps - AT LEAST TWO RUNNING
c. RCS pressure minus maximum SIG pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs 23 Check If S/G Secondary Side Is Intact:

o Pressure in both S/Gs -

STABLE OR INCREASING o Pressure in both S/Gs -

GREATER THAN 110 PSIG 24 Check If S/G Tubes Are Intact:

o Air ejector radiation monitors (R-15 or R-15A) - NORMAL o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors (R-31 and R-32) - NORMAL

a. Go to Step 23.
b. Go to Step 23.
c. Go to Step 23.

IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN go to E-2. FAULTED STEAM GENERATOR ISOLATION. Step 1.

Go to E-3. STEAM GENERATOR TUBE RUPTURE. Step 1.

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 17 of 29 25 Check If RCS Is Intact:

Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT. Step 1.

a. CNMT area radiation monitors -

NORMAL

  • R-2

. R-7

  • R-29
  • R-30
b. CNMT pressure - LESS THAN 0.5 PSIG
c. CNMT sump B level - LESS THAN 8 INCHES
d. CNMT sump A level o Level - STABLE o Annunciator C-19. CONTAINMENT SUMP A HI LEVEL - EXTINGUISHED

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TITLE:.

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 18 of 29 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 26 Check If SI Should Be Terminated:

a. RCS pressure:

o Pressure - GREATER THAN 1625 PSIG

a. Do NOT stop SI pumps.

Step 27.

Go to o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core exit T/Cs - GREATER THAN 0 0F USING FIG-1.0. FIGURE MIN SUBCOOLING
b. Do NOT stop Step 27.

SI pumps. Go to

c. Secondary heat sink:

o Total feed flow to S/Cs -

GREATER THAN 200 GPM

c. IF neither condition met. THEN do NOT stop SI pumps.

Go to Step 27.

-OR-o Narrow range level in at least one S/G - GREATER THAN 5%

d. PRZR level - GREATER THAN 5%
d. Do NOT stop SI pumps.

the following:

Perform

1) IF normal PRZR spray available. THEN try to stabilize RCS pressure.with PRZR spray.
2) Go to Step 27.
e. Go to ES-l.1, SI TERMINATION.

Step 1.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED NOTE:

o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o The Critical Safety Function Red Path Summary is available in APPENDIX 1.

27 Initiate Monitoring of Critical Safety Function Status Trees

  • 28 Monitor S/G Levels:
a. Narrow range level - GREATER THAN 5%
b. Control feed flow to maintain narrow range level between 17%

and 50%

29 Check Secondary Radiation Levels -

NORMAL

a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% in at least one S/G.
b. IF narrow range level in any S/G continues to increase in an uncontrolled manner. THEN go to E-3. STEAM GENERATOR TUBE RUPTURE. Step 1.

Go to E-3. STEAM GENERATOR TUBE RUPTURE. Step 1.

o Steamline radiation monitor (R-31 and R-32) o Dispatch AO to locally check steamline radiation o Request RP sample S/Gs for activity

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TITLE:I REV: 3 6 I E -O REACTOR TRIP OR SAFETY INJECTION

[

PAGE 20 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET.

TO RESTART SAFEGUARDS EQUIPMENT.

(REFER OFFSITE POWER)

THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5. ATTACHMENT LOSS OF 30 Reset SI 31 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26. CNMT ISOLATION -

EXTINGUISHED

b. Perform the following:
1) Reset SI.
2) Depress CI reset pushbutton.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 32 Verify Adequate SW Flow:

a. At least three SW pumps - RUNNING
a. Manually start SW pumps as power supply permits (257 kw each).

IF less than three pumps running. THEN ensure SW isolation.

IF NO SW pumps running. THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.

IF only one SW pump running.

THEN refer to AP-SW.2. LOSS OF SERVICE WATER.

b. Dispatch AO to establish normal shutdown alignment (Refer to ATT-17.0. ATTACHMENT SD-1)

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TITLE:

R V Ed:REV:

36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 22 of 29 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 33 Establish IA to CNMT:

a. Verify non-safeguards busses
a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR-

  • Bus 13 to Bus 14 tie

. Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED

2) Verify adequate emergency D/G capacity to run air compressor(s)

(75 kw each).

IF NOT, THEN perform the following:

o Start diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR

-OR-o Evaluate if CNMT RECIRC fans should be stopped.

(Refer to ATT-4.0.

ATTACHMENT CNMT RECIRC FANS

3) WHEN bus 15 is restored. THEN reset control room lighting.
b. Check SW Pumps -

AT LEAST TWO

b. Perform the following:

PUMPS RUNNING

1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)
2) Go to step 33d.

This Step continued on the next page.

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 23 of 29 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl (Step 33 continued from previous page)

c. Verify SW isolation valves to turbine building - OPEN
  • MOV-4613 and MOV-4670
  • MOV-4614 and MOV-4664
d. Verify adequate air compressor(s) - RUNNING
e. Check IA supply:

o Pressure - GREATER THAN 60 PSIG o Pressure - STABLE OR INCREASING

c. Perform the following:
1) Manually align valves.
2) Dispatch AO to locally reset compressors as necessary.
d. Manually start electric air compressor(s) as power supply permits (75 kw each).

IF electric air compressor can NOT be started. THEN start diesel air compressor.

(Refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)

e. Perform the following:
1) Continue attempts to restore IA (Refer to AP-IA.1. LOSS OF INSTRUMENT AIR).
2) Continue with Step 34. WHEN IA restored. THEN do Steps 33f and g.
f. Reset both trains of XY relays for IA to CNMT AOV-5392
g. Verify IA to CNMT AOV-5392 - OPEN

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 24 of 29 P

ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 34 Check Auxiliary Building Radiation -

NORMAL U

0 Plant vent iodine (R-1OB)

Plant vent particulate (R-13)

Plant vent gas (R-14)

CCW liquid monitor (R-17)

LTD line monitor (R-9)

CHG pump room (R-4)

Evaluate cause of abnormal conditions.

IF the cause is a loss of RCS inventory outside CNMT. THEN go to ECA-1.2. LOCA OUTSIDE CONTAINMENT, Step 1.

Evaluate the following flowpaths for cause of abnormal conditions:

. RCP seal return relief

. PRZR safeties

  • Letdown line relief IF excess letdown previously in service, THEN close AOV-310. excess letdown isolation valve from loop A cold.

35 Check PRT Conditions o PRT level (LI-442) - LESS THAN 84%

o PRT temperature (TI-439) - LESS THAN 120 0F o PRT pressure (PI-440A) - LESS THAN 3 PSIG

M EP:

TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 25 of 29 P

ACTION/EXPECTED RESPONSE l

RESPONSE NOT OBTAINEDl I*

4 4

4 4

4 4

4 4

4 CAUTION RCS PRESSURE SHOULD BE MONITORED.

IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG, THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

4 4

4 4

4 4

4 4

4

  • 36 Monitor If RHR Pumps Should Be Stopped:
a. Check RCS pressure:
1) Pressure - GREATER THAN 250 PSIG
2) Pressure -

STABLE OR INCREASING

1) Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT. Step 1.
2) Go to Step 37.
b. Stop both RHR pumps and place in AUTO 37 Check Normal Power To Charging Pumps:

Available o Bus 14 CLOSED o Bus 16 CLOSED normal feed breaker -

normal feed breaker -

Verify adequate emergency D/G capacity to run charging pumps (75 kw each).

IF NOT. THEN evaluate if CNMT RECIRC fans can be stopped (Refer to ATT-4.0. ATTACHMENT CNMT RECIRC FANS).

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TITLE:

REV: 3 6 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 26 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 Check If Charging Flow Has Been Established:

a. Charging pumps - ANY RUNNING
a. Perform the following:
1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high.

THEN dispatch AO to close seal injection needle valve(s) to affected RCP:

  • V-300A for RCP A
  • V-300B for RCP B
2) Ensure HCV-142 open. demand at 0%.
b. Charging pump suction aligned to
b. Manually align valves.

RWST:

IF LCV-112B can NOT be opened.

o LCV-112B - OPEN THEN dispatch AO to locally open V-358. manual charging pump o LCV-112C - CLOSED suction from RWST (charging pump room).

IF LCV-112C can NOT be closed.

THEN perform the following:

1) Direct AO to locally open V-358. manual charging pump suction from RWST (Charging Pump Room).
2) Verify charging pump A NOT running and place in PULL STOP.
3) WHEN V-358 open. THEN direct AO to close V-268 to isolate char ging pumps B and C from VCT (charging pump room).
c. Start charging pumps as necessary and adjust charging flow to restore PRZR level

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION

,j, -.1 PAGE 27 of 29 SP ACTION/EXPECTED RESPONSE l[RESPONSE NOT OBTAINED 39 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG o Reset PRZR heaters o Use normal PRZR spray

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TITLE:

REV: 3 6 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 28 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 40 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses energized by offsite power:

o Emergency D/G output breakers

- OPEN o AC emergency bus voltage -

GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers - CLOSED

a. Perform the following:
1) Verify non-safeguards bus tie breakers closed:

. Bus 13 to Bus 14 tie

. Bus 15 to Bus 16 tie

2) Place the following pumps in PULL STOP:
  • EH pumps

. Turning gear oil pump

. HP seal oil backup pump

3) Ensure condenser steam dump mode control in MANUAL.
4) Restore power to MCCs:

. A from Bus 13

  • B from Bus 15

. E from Bus 15

  • F from Bus 15
5) Start HP seal oil backup pump.
6) Ensure D/G load within limits.
7) Refer to ATT-8.4. ATTACHMENT SI/UV for other equipment lost with loss of offsite power.
8) Try to restore offsite power (Refer to ER-ELEC.1.

RESTORATION OF OFFSITE POWER).

b. Stop any unloaded emergency D/G and place in standby (Refer to ATT-8.1, ATTACHMENT D/G STOP)

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TITLE:

REV: 3 6 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 29 of 29 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 41 Return to Step 20

-END-

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 E-0 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2)

FIGURE MIN SUBCOOLING (FIG-1.0)

3)

ATTACHMENT CI/CVI (ATT-3.0)

4)

ATTACHMENT SD-1 (ATT-17.0)

5)

ATTACHMENT CNMT RECIRC FANS (ATT-4.0)

6)

ATTACHMENT D/G STOP (ATT-8.1)

7)

ATTACHMENT SI/UV (ATT-8.4j)

8)

ATTACHMENT NO SW PUMPS (ATT-2.4)

9)

ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)

10)

ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

11)

FOLDOUT

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TITLE:

REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 RED PATH

SUMMARY

a.

SUBCRITICALITY -

Nuclear power greater than 5%

b.

CORE COOLING -

Core exit T/Cs greater than 12000F

-OR-Core exit T/Cs greater than 700°F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c.

HEAT SINK -

Narrow range level in all S/Gs less than 5%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d.

INTEGRITY -

Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e.

CONTAINMENT -

CNMT pressure greater than 60 psig

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REV: 36 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 FOLDOUT PAGE

1.

RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:

a.

SI pumps -

AT LEAST TWO RUNNING

b.

RCS pressure minus maximum S/G pressure -

LESS THAN 175 PSIG

[400 psig adverse CNMT]

2.

LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:

a.

Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b.

Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

3.

AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

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TITLE:

REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 23 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER R

RESPONSIBL eANAGER EF

/FE -TIE0 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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TITLE:

REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 2 of 23 A. PURPOSE -

This procedure provides actions to recover from a loss of reactor or secondary coolant.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS -

This procedure is entered from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when a PRZR PORV is stuck open and its block valve can not be closed.
b. E-0, REACTOR TRIP OR SAFETY INJECTION, with any of the following symptoms:

high containment radiation, high containment pressure, or high containment recirculation sump level.

c. E-0, REACTOR TRIP OR SAFETY INJECTION, ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when RCS pressure is less than the shutoff head pressure of the RHR pumps or is decreasing.
d. ES-l.l, SI TERMINATION, and FR-I.2, RESPONSE TO LOW PRESSURIZER LEVEL, if SI has to be reinitiated.
e. E-2, FAULTED STEAM GENERATOR ISOLATION, after identification and isolation of a faulted S/G.
f. ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, after normal injection mode conditions are established.
g. ECA-1.2, LOCA OUTSIDE CONTAINMENT, when a LOCA outside containment is isolated.
h. FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, and FR-C.2, RESPONSE TO DEGRADED CORE COOLING, after core cooling has been reestablished.
i. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are closed.

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REV: 2 9 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 3 of 23 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 4

4 4

CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28%. THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3. TRANSFER TO COLD LEG RECIRCULATION. STEP 1.

4 4

NOTE:

o FOLDOUT page should be open AND monitored periodically.

o Critical Safety Function Status Trees should be monitored.

(Refer to Appendix 1 for Red Path Summary.)

o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

1 Monitor RCP Trip Criteria:

a. RCP status - ANY RCP RUNNING
a. Go to Step 2.
b. SI pumps - AT LEAST TWO RUNNING
b. Go to Step 2.
c. RCS pressure minus maximum S/G
c. Go to Step 2.

pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs

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R V l

Ed:REV:

29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 4 of 23 P

ACTION/EXPECTED RESPONSE l[RESPONSE NOT OBTAINEDl 2 Check If SIG Secondary Side Is Intact:

o Pressure in both S/Gs - STABLE OR INCREASING o Pressure in both S/Gs - GREATER THAN 110 PSIG IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized. THEN verify faulted S/G isolated unless needed for RCS cooldown:

  • Steamlines
  • Feedlines IF NOT. THEN go to E-2. FAULTED STEAM GENERATOR ISOLATION. Step 1.

NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

  • 3 Monitor Intact SIG Levels:
a. Narrow range level - GREATER THAN 5% [25% adverse CNMT]
b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

  • 4 Monitor If Secondary Radiation Levels Are Normal o Steamline radiation monitor (R-31 and R-32) o Request RP sample SIGs for activity
a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in at least one SIG.

b. IF narrow range level in any S/G continues to increase in an uncontrolled manner. THEN go to E-3. STEAM GENERATOR TUBE RUPTURE. Step 1.

IF steamline radiation monitors NOT available, THEN dispatch AO to locally check steamline radiation.

IF abnormal-radiation levels detected in any S/G. THEN go to E-3. STEAM GENERATOR TUBE. RUPTURE.

Step 1.

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REV: 2 9 E-1 LOSS OF REACTOR OR SECONDARY COOLANT S OPAGE 5 of 23 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 4

CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE. IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).

4 M o 4

4

  • 5 Monitor PRZR PORV Status:
a. Power to PORV block valves AVAILABLE
a. Restore power to block valves unless block valve was closed to isolate an open PORV:
  • MOV-515. MCC D position 6C
  • MOV-516. MCC C position 6C
b. PORVs - CLOSED
b. IF PRZR pressure less than 2335 psig. THEN manually close PORVs.

IF any PORV can NOT be closed.

THEN manually close its block valve.

IF block valve can NOT be closed. THEN dispatch AO to locally check breaker.

  • MOV-515. MCC D position 6C

. MOV-516. MCC C position 6C

c. Block valves - AT LEAST ONE OPEN
c. Open one block valve unless it was closed to isolate an open PORV.

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29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 6 of 23 SP ACTION/EXPECTED RESPONSE l

lRESPONSE NOT OBTAINED i

CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

(REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER) 6 Reset SI 7 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26. CNMT ISOLATION - EXTINGUISHED
b. Perform the following:
1) Reset SI.
2) Depress CI reset pushbutton.

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 7 of 23

_STEP _ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Verify Adequate SW Flow:

a. Check at least two SW pumps -
a. Manually start SW pumps as power RUNNING supply permits (257 kw each).

IF less than two SW pumps running, THEN perform the following:

1) Ensure SW isolation.
2) IF NO SW pumps running. THEN perform the following:

a) Pull stop any D/G that is NOT supplied by alternate cooling. AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

3) IF only one SW pump running.

THEN refer to AP-SW.2. LOSS OF SERVICE WATER.

b. Dispatch AO to establish normal shutdown alignment (Refer to ATT-17.0. ATTACHMENT SD-1)

STP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDl 9 Establish IA to CNMT:

a. Verify non-safeguards busses
a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR-

  • Bus 13 to Bus 14 tie
  • Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED
2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).

IF NOT. THEN perform the following:

o Start diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR

-OR-o Evaluate if CNMT RECIRC fans should be stopped (Refer to ATT-4.0, ATTACHMENT CNMT RECIRC FANS).

3) WHEN bus 15 restored, THEN reset control room lighting.
b. Check SW pumps - AT LEAST TWO
b. Perform the following:

PUMPS RUNNING

1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)
2) Go to step 9d.

This Step continued on the next page.

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TITLE:I REV: 2 9 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 9 of 23 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl (Step 9 continued from previous page)

c. Verify turbine building SW isolation valves - OPEN
  • MOV-4613 and MOV-4670
  • MOV-4614 and MOV-4664
d. Verify adequate air compressors

- RUNNING

e. Check IA supply:

o Pressure - GREATER THAN 60 PSIG o Pressure -

STABLE OR INCREASING

c. Perform the following:
1) Manually align valves.
2) Dispatch AO to locally reset compressors as necessary.
d. Manually start electric air compressors as power supply permits (75 kw each).

IF electric air compressors can NOT be started. THEN start diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR).

e. Perform the following:
1) Continue attempts to restore IA (Refer to AP-IA.1. LOSS OF INSTRUMENT AIR).
2) Continue with Step 10.

WHEN IA restored. THEN do Steps 9f and g.

f. Reset both trains of XY relays for IA to CNMT AOV-5392
g. Verify IA to CNMT AOV-5392 -

OPEN

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29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 10 of 23 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 10 Check Normal Power Available To Charging Pumps:

o Bus 14 normal feed breaker -

CLOSED o Bus 16 normal feed breaker -

CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).

IF NOT. THEN evaluate if CNMT RECIRC fans can be stopped (Refer to ATT-4.O. ATTACHMENT CNMT RECIRC FANS).

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29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 11 of 23 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 11 Check If Charging Flow Has Been Established:

a. Charging pumps - ANY RUNNING
a. Perform the following:
1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high.

THEN dispatch AO to close seal injection needle valve(s) to affected RCP:

  • V-300A for RCP A
  • V-300B for RCP B
2) Ensure HCV-142 open. demand at 0%.
b. Charging pump RWST:

suction aligned to

b. Manually align valves as necessary.

o LCV-112B -

o LCV-112C -

OPEN CLOSED IF LCV-112B can NOT be opened.

THEN dispatch AO to locally open V-358. manual charging pump suction from RWST (charging pump room).

IF LCV-112C can NOT be closed.

THEN perform the following:

1) Direct AO to locally open V-358. manual charging pump suction from RWST (charging pump room).
2) Verify charging pump A NOT running and place in PULL STOP.
3) WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (charging pump room).
c. Start charging pumps as necessary and adjust charging flow to restore PRZR level

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TITLE:

REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 12 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If SI Should Be Terminated:

a. RCS pressure:

o Pressure - GREATER THAN 1625 psig [1825 psig adverse CNMT]

a. Do NOT stop SI pumps.

Step 13.

Go to o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core exit T/Cs - GREATER THAN 0 0F USING FIG-1.0. FIGURE MIN SUBCOOLING
c. Secondary heat sink:

o Total feed flow to intact S/Gs - GREATER THAN 200 GPM

b. Do NOT stop SI pumps.

Step 13.

Go to

c. IF neither condition satisfied.

THEN do NOT stop SI pumps.

Go to Step 13.

-OR-o Narrow range level in at least one intact S/G -

GREATER THAN 5% [25% adverse CNMT]

d. PRZR level - GREATER THAN 5%

[30% adverse CNMT]

d. Do NOT stop SI pumps.

the following:

Perform

1) IF normal PRZR spray available. THEN try to stabilize RCS pressure with PRZR spray.
2) Go to Step 13.
e. Go to ES-1.1. SI TERMINATION.

Step 1.

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 13 of 23 STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINEDl

  • 13 Monitor If CNMT Spray Should Be Stopped:
a. CNMT spray pumps - RUNNING
b. Check the following:

o CNMT pressure - LESS THAN 4 PSIG o Sodium hydroxide tank level -

LESS THAN 55%

c. Reset CNMT spray
d. Check NaOH flow (FI-930) - NO FLOW
a. Go to Step 14.
b. Continue with Step 14.

WHEN BOTH conditions satisfied, THEN do Steps 13c through f.

d. Place NaOH tank outlet valve switches to CLOSE.
  • AOV-836A
  • AOV-836B
e. Stop CNMT spray pumps and place in AUTO
f. Close CNMT spray pump discharge valves
  • MOV-860A
  • MOV-860B

. MOV-860C

. MOV-860D

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REV: 2 9 E-1 LOSS OF REACTOR OR SECONDARY COOLANT SC Y.

PAGE 14 of 23 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 4

4 4

S 4

CAUTION o IF OFFSITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

(REFER TO ATT-8.5. ATTACHMENT LOSS OF OFFSITE POWER) o RCS PRESSURE SHOULD BE MONITORED.

IF RCS PRESSURE DECREASES IN AN.

UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT]. THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

A 4

  • 14 Monitor If RHR Pumps Should Be Stopped:
a. RHR pumps - ANY RUNNING IN INJECTION MODE
b. Check RCS pressure:
a. Go to Step 15.
1) Pressure - GREATER THAN 250 psig [465 psig adverse CNMT]
2) RCS pressure -

STABLE OR INCREASING

1) Go to Step 16.
2) Go to Step 15.
c. Stop RHR pumps and place in AUTO 15 Check RCS And S/G Pressures
a. Check pressures in both S/Gs -

STABLE OR INCREASING

b. Check pressures in both S/Gs -

GREATER THAN 110 PSIG

c. Check RCS pressure -

STABLE OR DECREASING

a. Return to Step 1.
b. Monitor RCS pressure.

IF RCS pressure does NOT increase after faulted S/G dryout, THEN go to Step 16.

c. Return to Step 1.

[

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REV: 2 9 E-1 LOSS OF REACTOR OR SECONDARY COOLANT 1

.PAGE 15 of 23 SP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses energized by offsite power:

o Emergency D/G output breakers

- OPEN o AC emergency bus voltage -

GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers - CLOSED

a. Perform the following:
1) Close non-safeguards bus tie breakers as necessary:
  • Bus 13 to Bus 14 tie

. Bus 15 to Bus 16 tie

2) Place the following pumps in PULL STOP:
  • EH pumps

. Turning gear oil pump

  • HP seal oil backup pump
3) Ensure condenser steam dump mode control in MANUAL.
4) Restore power to MCCs:
  • A from Bus 13
  • B from Bus 15
  • E from Bus 15
  • F from Bus 15
5) Start HP seal oil backup pump.
6) Ensure D/G load within limits.
7) WHEN bus 15 restored, THEN reset control room lighting breaker.
8) Refer to ATT-8.4. ATTACHMENT SI/UV for other equipment lost with loss of offsite power.
9) Try t6 restore offsite power (Refer to ER-ELEC.1.

RESTORATION OF OFFSITE POWER).

b. Stop any unloaded emergency D/G and place in standby (Refer to ATT-8.1. ATTACHMENT D/G STOP)

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 16 of 23 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 17 Check If RHR Should Be Throttled:

a. Check RWST level - LESS THAN 70%
b. Perform ATT-14.7. ATTACHMENT ADJUST RHR FLOW to locally adjust HCV-624 and HCV-625.
a. Continue with Step 18.

WHEN RWST level less than 70%. THEN perform step 17b.

b. Manually adjust RHR Hx outlet valves equally to reduce flow to less than 1500 gpm per operating pump
  • RHR Hx A. HCV-625
  • RHR Hx B. HCV-624

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REV: 2 9 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 17 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDl 18 Verify CNMT Sump Recirculation Capability:

a. Check RHR and CCW systems:
1) At least one recirculation flowpath, including required power supplies, from Sump B and back to RCS available per ATT-14.5, ATTACHMENT RHR SYSTEM
a. IF at least one flowpath of cold leg recirculation capability can NOT be verified, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION. Step 1.
2) At least one CCW pump available.
3) At least one CCW Hx available.
b. Check SW pumps -

PUMPS AVAILABLE AT LEAST 2

b. Attempt to restore at least 2 SW pumps to operable.

IF only 1 SW pump available, THEN refer to ATT-2.1.

ATTACHMENT MIN SW for additional guidance.

IF no SW pumps are available.

THEN perform the following:

1) Pull stop any DIG that is NOT supplied by alternate cooling. AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.
3) Go to ECA-l.l. LOSS OF EMERGENCY COOLANT RECIRCULATION.
c. Dispatch AO to check AUX BLDG sub-basement for RHR system leakage (AUX BLDG sub-basement key may be required)
c. IF any RHR pump seal leakage indicated. THEN leakage should be evaluated and isolated if necessary.

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REV: 2 9 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 18 of 23

=

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 19 Evaluate Plant Status:

a. Check auxiliary building radiation - NORMAL 0

0 0

Plant vent iodine (R-1OB)

Plant vent particulate (R-13)

Plant vent gas (R-14)

CCW liquid monitor (R-17)

LTDN line monitor (R-9)

CHG pump room (R-4)

a. Notify RP and refer to appropriate AR-RMS procedure.

IF the cause is a loss of RCS inventory outside CNMT. THEN go to ECA-1.2. LOCA OUTSIDE CONTAINMENT. Step 1.

b. Direct RP to obtain following samples:

. RCS boron

. RCS activity

. CNMT sump boron

c. Verify adequate Rx head cooling:
1) Verify at least one control rod shroud fan - RUNNING
2) Verify one Rx compartment cooling fan - RUNNING
1) Manually start one fan as power supply permits (45 kw)
2) Perform the following:

o Dispatch AO to reset UV relays at MCC C and MCC D.

o Manually start one fan as power supply permits (23 kw)

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 19 of 23 1

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check If RCS Cooldown And Depressurization Is Required:

a. RCS pressure - GREATER THAN 250 psig [465 psig adverse CNMT]
a. IF RHR pump flow greater than 475 gpm. THEN go to Step 21.
b. Go to ES-1.2. POST LOCA COOLDOWN AND DEPRESSURIZATION. Step 1

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 20 of 23 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED NOTE:

IF D/Gs supplying emergency AC busses. THEN non-essential loads may be shed as necessary to allow start of additional SW pumps.

21 Establish Adequate SW Flow:

a. Verify at least two SW pumps -

RUNNING

a. Start additional SW pumps as power supply permits (257 kw each).

IF only 1 SW pump operable. THEN perform the following:

1) Ensure ATT-2.1. ATTACHMENT MIN SW is in progress.
2) Go to Step 22.

IF no SW pumps are available.

THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling. AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.
3) Go to ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION.
b. Verify AUX BLDG SW isolation valves - OPEN
b. Manually align valves.
  • MOV-4615 and MOV-4734
  • MOV-4616 and MOV-4735
c. Dispatch AO to check BOTH CCW Hx IN SERVICE
c. Locally place BOTH CCW Hxs in service This Step continued on the next page.

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 21 of 23 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED (Step 21 continued from previous page)

d. Determine required SW flow to CCW HXs per table:

SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2

Total of 5000 - 6000 gpm equally divided to both HXs Normal 1

5000 -

6000 gpm to in-service HX Alternate 2

30-33" d/p across each RX Alternate 1

95-100" d/p across in-service HX

e. Direct AO to adjust SW flow to required value o IF on normal SW discharge:

. V-4619. CCW HX A

-OR-o IF on alternate SW discharge:

e. IF the required SW flow can NOT be obtained. THEN perform the following:
1) Isolate SW to screenhouse and air conditioning headers.
  • MOV-4609/MOV-4780 - AT LEAST ONE CLOSED
  • MOV-4663/MOV-4733 - AT LEAST ONE CLOSED a V-4619C. CCW HX A

. V-4620B. CCW HX B

2) Direct AO to locally adjust SW flow to required value.
3) Direct AO to locally isolate SW return from SFP Hxs:
  • SFP Hx A (V-4622) (for alternate SW discharge use V-4622A)
  • SFP Hx B (V-8689)
4) Verify SW portions of ATT-17.0. ATTACHMENT SD-1 are complete.

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT '

I.

PAGE 22 of 23 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 22 Establish CCW flow to RHR Hxs:

a. Check both CCW pumps - RUNNING
b. Manually open CCW valves to RHR Hxs
  • MOV-738A
  • MOV-738B
a. Perform the following:

l) -Start CCW pumps as power supply permits (122 kw each)

2) IF both CCW pumps are running. THEN go to step 22b.
3) IF only one CCW pump is running. THEN perform the following:

a) Direct AO to isolate CCW to boric acid evaporator o Close V-760A b) Manually open CCW MOV to only one operable RHR Loop o Open MOV-738A

-OR-o Open MOV-738B c) Go to step 23.

b. Dispatch AO to locally open valves.

K>

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REV: 2 9 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 23 of 23 STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINEDl 23 Check If Transfer To Cold Leg Recirculation Is Required:

a. RWST level - LESS THAN 28%
b. Go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION. Step 1
a. Return to Step 17.

-END-

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 E-1 APPENDIX LIST TITLE

1)

RED PATH

SUMMARY

2) 3)

4) 5)

6) 7 )

8) 9)

10)

' 11) 12) 13)

FIGURE MIN ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT FOLDOUT SUBCOOLING (FIG-1.0)

CNMT RECIRC FANS (ATT-4.0)

D/G STOP (ATT-8.1)

SD-i (ATT-17.0)

SI/UV (ATT-8.4)

MIN SW (ATT-2.1)

NO SW PUMPS (ATT-2.4)

LOSS OF OFFSITE POWER (AnT-8.5)

DIESEL AIR COMPRESSOR (ATT-11.2)

RHR SYSTEM (ATn-14.5)

ADJUST RHR FLOW (ATT-14.7)

I

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 RED PATH

SUMMARY

a.

SUBCRITICALITY -

Nuclear power greater than 5%

b. CORE COOLING -

Core exit T/Cs greater than 12000F

-OR-Core exit T/Cs greater than 700°F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK -

Narrow range level in all S/Gs less than 5%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d.

INTEGRITY -

Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT -

CNMT pressure greater than 60 psig

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 2 FOLDOUT PAGE

1. RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:
a. SI pumps - AT LEAST TWO RUNNING
b. RCS pressure minus maximum SIG pressure - LESS THAN 175 PSIG [400 psig adverse CNMTJ
2. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
3. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary:

o RCS subcooling based on core exit T/Cs - LESS THAN 0' F USING FIGURE MIN SUBCOOLING

-OR-o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT]

4. SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1:
a. RCS subcooling based on core exit T/Cs - GREATER THAN a' F USING FIGURE MIN SUBCOOLING
b. Total feed flow to intact S/Gs - GREATER THAN 200 GPM

-OR-Narrow range level in at least one intact S/G - GREATER THAN 5% [25% adverse CNMT]

c. RCS pressure:

o GREATER THAN 1625 PSIG [1825 psig adverse CNMT]

o STABLE OR INCREASING

d. PRZR level - GREATER THAN 5% [30% adverse CNMT]
5. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurizedAND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
6. E-3 TRANSITION CRITERIA IF any S/G level increased in an uncontrolled manner or any S/G has abnormal radiation,THEN manually start SI pumps as necessaryAND go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

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REV: 29 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 2 of 2

7. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
8. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet,THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
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