ML031400319

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Emergency Operating Procedures, for R.E. Ginna Nuclear Power Plant
ML031400319
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/08/2003
From: Widay J
Rochester Gas & Electric Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML031400319 (149)


Text

Ri~ 1i~'

A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND ELECTRIC CORPORAION 89 EASTAVENUE, ROCHESTER, N.Y. 14649-0001

  • 716-771-3250 JOSEPH A. WIDAY VICE PRESIDENT & PLANT MANAGER GINNA STATION May 8, 2003 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):

AP Index AP-CCW.2, Rev 18 AP-ELEC.1, Rev 25 AP-ELEC.14/16, Rev 5 AP-ELEC.17/18, Rev 5 AP-FW.1, Rev 15 AP-PRZR. 1, Rev 14 AP-RCP.1, Rev 15 AP-SW.1, Rev 18 AP-SW.2, Rev 3 AP-TURB.1, Rev 12 www rge.com

-ADO-

C Ginna Nuclear Power Plant PROCEDURE INDEX I, -

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V INPUT PARAMETERS: TYPE:

PRAR, PRAP, PRER STATUS VALUE(S):

EF, QU 5 YEARS ONLY:

PRAP ABNORMAL PROCEDURE

\\

PROCEDURE NUMBER PROCEDURE TITLE LEAKAGE INTO THE COMPONENT COOLING LOOP LOSS OF CCW DURING POWER OPERATION LOSS OF CCW - PLANT SHUTDOWN CONTROL ROOM INACCESSIBILITY CVCS LEAK LOSS OF ALL CHARGING FLOW LOSS OF A CIRC WATER PUMP LOSS OF 12A AND/OR 12B BUSSES SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F)

LOSS OF SAFEGUARDS BUS 14/16 LOSS OF SAFEGUARDS BUS 17/18 ABNORMAL MAIN FEEDWATER FLOW LOSS OF INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD WITHDRAWAULNSERTION RCCIRPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OF REACTOR COOLANT FLOW HIGH REACTOR COOLANT ACTIVITY SHUTDOWN LOCA LOSS OF RHR LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS STEAM GENERATOR TUBE LEAK SERVICE WATER LEAK LOSS OF SERVICE WATER TURBINE TRIP WITHOUT RX TRIP REQUIRED TURBINE LOAD REJECTION

EFFECT, LAST REV DATE REVIEW 015 06/26/2002 06/26/2002 018 05/08/2003 06/26/2002 015 11/19/2002 06/26/2002 019 02/25/2003 06/26/2002 013 06/26/2002 06/03/2002 003 06/2612002 02/26/1999 011 06/26/2002 04/16/2003 025 05/08/2003 06/26/2002 010 06/26/2002 06/26/2002 011 06/26/2002 06/26/2002 005 05/08/2003 06/26/2002 005 05/08/2003 06/26/2002 015 05/08/2003 06/26/2002 018 06/26/2002 04/16/2003 014 05/08/2003 06/26/2002 008 06/26/2002 04/16/2003 010 06/26/2002 01/22/2002 006 02/25/2003 02/25/2003 015 05/08/2003 04/24/2003 016 06/26/2002 04/16/2003 011 06/26/2002 04/16/2003 010 06/26/2002 04/01/2002 014 04/30/2003 04/30/2003 019 04/30/2003 04/30/2003 013 04/30/2003 04/30/2003 003 11/21/2002 06/26/2002 018 05/08/2003 04/21/2003 003 05/08/2003 10/31/2001 012 05/08/2003 06/26/2002 018 06/26/2002 06/26/2002

(-

NPSP0200 WRIGHTJ AP-CCW.1 AP-CCW.2 AP-CCW.3 AP-CR.1 AP-CVCS.1 AP-CVCS.3 AP-CW.1 AP-ELEC.1 AP-ELEC.2 AP-ELEC.3 AP-ELEC.14/16 AP-ELEC.17/18 AP-FW.1 AP-IA.1 AP-PRZR.1 AP-RCC.1 AP-RCC.2 AP-RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS.2 AP-RCS.3 AP-RCS.4 AP-RH~R.1 AP-RHR.2 AP-SG.1 AP-SW.1 AP-SW.2 AP-TURB.1 AP-TURB.2 NEXT REVIEW 06/26/2007 06/26/2007 06/26/2007 06/26/2007 06/03/2007 02/26/2004 04/16/2008 06/26/2007' 06/26/2007 06/26/2007 06/26/2007 06/26/2007 06/26/2007 04/16/2008 06/26/2007 04/16/2008 01/22/2007 02/25/2008 04/24/2008 04/16/2008 04/16/2008 01/22/2007 04/30/2008 04/30/2008 04/30/2008 06/26/2007 04/21/2008 10/31/2006 06/26/2007 06/26/2007 ST EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF Ef EF EF EF EF EF EF

Ginna Nuclear Power Plant PROCEDURE INDEX r.~~~~~~

C' Thu 5/8/2003 7:59:05 am Page 2 of 40 INPUT PARAMETERS: TYPE:

PRAR, PRAP, PRER STATUS VALUE(S):

EF, QU 5 YEARS ONLY:

PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.3 TURBINE VIBRATION 011 06/26/2002 06/26/2002 06/26/2007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 017 04/30/2003 04/30/2003 04/30/2008 EF AP-TURB.5 RAPID LOAD REDUCTION 006 06/26/2002 06/26/2002 06/26/2007 EF PRAP TOTAL:

33

(.

NPSP0200 WRIGHTJ

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBL AGER F5--CTIV oAT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

PURPOSE -

This procedure provides the steps necessary to respond to a loss of CCW while the plant is at power.

ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS -

This procedure is entered from:

a. AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING SYSTEM, when CCW surge tank level decrease indicated at power.
2.

SYMPTOMS -

The symptoms of LOSS OF CCW DURING POWER OPERATION are;

a. Annunciator A-13, CCW SURGE TANK LO LEVEL 41.2%,

lit, or

b. Annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, lit, or
c. Annunciator A-17, MOTOR OFF RCP CCWP, lit, or
d. Annunciator A-9, RHR PUMP COOLING WATER OUTLET LO FLOW 15 GPM, lit or
e. Annunciator A-6, CONT SPRAY PUMP COOLING WATER OUT LOW FLOW 15 GPM, lit or
f. Annunciator A-14, SAFETY INJ PUMPS COOLING WATER OUT LO FLOW 25 GPM, lit or
g. Annunciator A-7 (A-15), RCP A (B) CCW RETURN HI TEMP OR LO FLOW 165 GPM 1250F, lit or
h. Annunciator A-24 (A-32), RCP A (B) OIL LEVEL + 1.25, lit or,
i. Annunciator A-12, NON-REGEN HX LETDOWN OUT HI TEMP 145°F lit or,
j.

Annunciator A-18, VCT HI TEMP 1450.

A.

B.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED CAUTION o IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 2000F. THEN TRIP THE AFFECTED RCP.

o IF CCW IS LOST, THEN SEAL INJECTION SHOULD BE MAINTAINED TO THE RCP(S)

UNTIL RCS TEMPERATURE IS LESS THAN 1500F. OR UNTIL CCW IS RESTORED.

1 Check CCW Pump Status:

o Both CCW pump breaker white lights - EXTINGUISHED o Annunciator A-17, MOTOR OFF RCP CCWP - EXTINGUISHED Perform the following:

a. Ensure standby CCW pump running.

IF no CCW pump can be operated.

THEN perform the following:

1) Trip the reactor.
2) WHEN all E-O Immediate Actions done, THEN trip BOTH RCPs.
3) Close letdown isol, AOV-427.
4) Close excess letdown. HCV-123.
5) Go to E-0. REACTOR TRIP OR SAFETY INJECTION.
b. IF annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, lit.

THEN check closed CCW to RHR HXs (MOV-738A and MOV-738B).

EOP:

TITLE:

REV: 18 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 3 of 10 I

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED NOTE:

MCB CCW surge tank level indication should be verified locally in the AUX BLDG. if possible.

  • 2 Monitor CCW Surge Tank Level Perform the following:

APPROXIMATELY 50% AND STABLE

a. Open RMW to CCW surge tank.

MOV-823.

b. Start RMW pump(s).
c. IF surge tank level stable or increasing, THEN control level at approximately 50% while continuing with Step 3.

IF CCW surge tank level can NOT be maintained greater than 10%.

THEN perform the following:

1) Close letdown isol. AOV-427.
2) Close excess letdown. HCV-123.
3) Trip the reactor.
4) WHEN all E-0 Immediate Actions done, THEN trip BOTH RCPs.
5) Place both CCW pumps in pull stop.
6) Go to E-O. REACTOR TRIP OR SAFETY INJECTION.

EOP:

TITLE:

REV: 18 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 4 of 10

ACTION/EXPECTED RESPONSE 3 Check CCW To Both RCPs:

o Annunciator A-7 (A-15). RCP A (1B) CCW return Hi temp or low flow 165 gpm 125°F alarm -

EXTINGUISHED o RCP motor bearings temperature (PPCS Group Display-RCPS OR RCP temperature monitor RK-30A recorder) -

200°F IF CCW lost to RCP(s). THEN perform the following:

a. Trip the reactor.
b. WHEN all E-0 Immediate Actions done. THEN trip affected RCP(s).
c. Go to E-0. REACTOR TRIP OR SAFETY INJECTION.
  • 4 Monitor If Letdown Should Be Isolated:
a. Check annunciator A-12.

Non-Regen Hx Letdown Out Hi Temp 1450

- EXTINGUISHED

a. Isolate Normal Letdown:
1) Close letdown isolation, AOV-427.
2) Close letdown orifice valves (AOV-200A. AOV-200B, and AOV-202).
3) Close letdown isolation, AOV-371.
4) Close charging flow control valve. HCV-142 WHILE adjusting charging pump speed to maintain:

. RCP labyrinth seal D/P between 15 inches and 80 inches

. PRZR level at program

b. Check excess letdown temperature

- LESS THAN 195°F

b. Isolate Excess Letdown:
1) Close excess letdown flow control valve. HCV-123.
2) Close excess letdbwn isolation valve. AOV-310.

EOP:

TITLE:

REV: 18 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 5 of 10 1=~IRSOSENTOTIE

5 Check CCW Valve Alignment -

NORMAL

a. Check MCB CCW valves (Refer to ATT-1.0. ATTACHMENT AT POWER CCW ALIGNMENT)
a. Align CCW valves as necessary.
b. Direct AO to check local flow indications per ATT-1.1.

ATTACHMENT NORMAL CCW FLOW NOTE:

o IF Seal Water Hx will be bypassed. THEN an increase in VCT temperature is expected.

o IF Seal Water Hx will be isolated. THEN seal return and excess letdown (if in service) will be to the PRT through RV-314.

6 Check Seal Water Hx For Tube Leak:

o Locally check Seal Water Hx CCW outlet flow - NORMAL (FI-605, refer to AO log) o Locally check Seal Water Hx CCW outlet temperature - NORMAL (TI-604. refer to AO log) o VCT level - NO UNEXPLAINED INCREASE IF a tube leak is indicated. THEN bypass and isolate Seal Water Hx and, if desired, isolate Seal Return.

a. To bypass and isolate Hx perform the following:
1) Open seal bypass V-394
2) Close seal inlet V-265
3) Close seal outlet V-321
4) Close CCW inlet V-763
5) Close CCW outlet V-767
b. IF desired to isolate seal return line, THEN close MOV-313.
c. Notify RP to sample RCS for chromates.

EOP:

TITLE:

REV: 18 AP-CCW.2 LOSS OF CCW DURING POWER OERATION PAGE 6 of 10

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

Operation may continue with the reactor this occurs, notify higher supervision.

7 Check For CCW Leakage In CNMT:

a. Check CNMT sump A level:

o Level - STABLE o Sump A pumps - OFF

b. RCP oil levels -

STABLE support coolers isolated.

If

a. IF abnormal increase in CNMT sump level. THEN perform the following:
1) Direct RP Tech to sample sump A for chromates.
2) Prepare to make CNMT entry to check for CCW leak.
b. IF any RCP oil level increasing uncontrollably. THEN perform the following:
1) Trip the reactor.
2) WHEN all E-0 Immediate Actions done. THEN trip affected RCP(s).
3) Close CCW supply and return for affected RCP(s).
  • RCP A. MOV-749A and MOV-759A
  • RCP B. MOV-749B and MOV-759B
4) Go to E-0. REACTOR TRIP OR SAFETY INJECTION.

EOP:

TITLE:

REV: 18 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 7 of 10

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check for CCW Leakage In AUX BLDG:

Dispatch AO to investigate AUX BLDG for CCW leakage.

o Start frequency of AUX BLDG sump pump(s) - NORMAL (Refer to RCS daily leakage log) o Waste holdup tank level - STABLE OR INCREASING AS EXPECTED 9 Verify CCW System Leak -

IDENTIFIED

a. Leak identified
a. Perform the following:
1) Direct RP Tech to sample CCW HX SW outlet for chromates.
2) Return to Step 2.
b. Isolate leak if possible
c. Refer to IP-ENV-3. RESPONSE TO A SPILL OF HAZARDOUS MATERIAL/WASTE 10 Check Normal Or Excess Letdown -

IN SERVICE IF normal letdown desired. THEN establish normal letdown (refer to ATT-9.0, ATTACHMENT LETDOWN).

IF normal letdown NOT available.

THEN establish excess letdown if desired.

(Refer to ATT-9.1.

ATTACHMENT EXCESS L/D)

ACTION/EXPECTED RESPONSERS E O B I 11 Check CCW System Leak Isolated

a. Surge tank level - APPROXIMATELY 50%
b. Surge tank level - STABLE 12 Direct RP To Sample CCW System For Chromates 13 Evaluate MCB Annunciator Status (Refer to AR Procedures) 14 Evaluate Plant Conditions:
a. CCW system malfunction -

IDENTIFIED AND CORRECTED

b. CCW system status adequate for power operation (Refer to ITS Section 3.7.7).
a. IF level less than 50%. THEN continue filling.

IF 2-50%, THEN perform the following:

1) Stop RMW pump(s).
2) Close MOV-823.
b. Return to Step 2.
a. Return to Step 1.
b. IF shutdown required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.

EOP:

TITLE:

REV: 18 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 9 of 10

EOP:

TITLE:

REV: 18 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 10 of 10

EOP:

TITLE:

REV: 18 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 1 of 1 AP-CCW.2 APPENDIX LIST TITLE

1)

ATTACHMENT AT POWER CCW ALIGNMENT

2)

ATTACHMENT EXCESS L/D

3)

ATTACHMENT NORMAL CCW FLOW

4)

ATTACHMENT LETDOWN (ATT-1.0)

(ATT-9.1)

(ATT-1.1)

(ATT-9.0)

1EOP:

TITLE:

AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES REV: 25 PAGE 1 of 33 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE aANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP:

TITLE:

REV: 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 2 of 33 A.

PURPOSE -

This procedure provides actions to respond to a loss of 12A and/or 12B Busses from HSD or at power conditions.

B.

ENTRY CONDITIONS/SYMPTOMS

2.

SYMPTOMS -

The symptoms of loss of #12A or 12B SS Transformer are:

a. Annunciator L-20, 12A XFMR OR 12A BUS TROUBLE, lit, or
b. Annunciator L-28, 12B XFMR OR 12B BUS TROUBLE, lit.

STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINED CAUTION o IF ANY RADIOACTIVE RELEASE IN PROGRESS. THEN IT SHOULD BE TERMINATED UNTIL SUPPORT CONDITIONS ARE EVALUATED.

o OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR, 2250 KW FOR 2 HOURS.

AND 1950 KW FOR CONTINUOUS SERVICE.

  • a * * * * * * * *
  • NOTE:

Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Check RCS Temperature -

GREATER THAN 350OF Go to AP-ELEC.3, LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 3500F).

  • 2 Monitor Tavg
a. Place Rods in MANUAL
b. Manually move control rods to control Tavg 3 Verify RCPs -

BOTH RUNNING IF reactor trip breakers closed.

THEN manually trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

4 Verify Emergency D/G Associated With Deenergized Bus(es) -

RUNNING Manually start D/G(s) with affected bus.

associated o Bus 12A - D/G A o Bus 12B - D/G B iEOP:

TITLE:I I

~~~~~~~~~~~~~REV:

25 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES

.I PAGE 3 of 33

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 5 Verify Both Trains Of AC IF both trains deenergized. THEN go Emergency Busses Energized To to ECA-O.O.

LOSS OF ALL AC POWER.

At Least 420 VOLTS:

Step 1.

o Bus 14 and bus 18 IF one train deenergized. THEN perform the following:

o Bus 16 and bus 17

a. Ensure D/G aligned for unit operation o Mode switch in UNIT o Voltage control selector in AUTO
b. Check D/G running.

IF NOT. THEN perform the following:

1) Depress D/G FIELD RESET pushbutton
2) Depress D/G RESET pushbutton
3) Start D/G
4) IF D/G will NOT start. THEN dispatch AO to locally start D/G.

(Refer to ER/D/G.1.

RESTORING D/Gs)

c. Adjust D/G voltage to approximately 480V
d. Adjust D/G frequency to approximately 60 Hz.

IF only ONE safeguards bus is deenergized. THEN refer to AP-ELEC.14/16, LOSS OF SAFEGUARDS BUS 14/16 or AP-ELEC.17/1, LOSS OF.

SAFEGUARDS BUS 17/18.-

[IEOP:

TITLE:

I~~~~~~~~~111 I

REV: 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B hBUSSES PAGE 4 of 33

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 6 Verify Service Water System Operation:

a. Check at least one SW pump running in each loop

. A or B Pump in Loop A

. C or D Pump in Loop B

a. Perform the following:
1) Manually start pumps as necessary (257 kw each).
2) IF adequate cooling can NOT be supplied to a running D/G, THEN perform the following:

a) Trip affected D/G(s) b) Immediately depress voltage shutdown pushbutton

3) IF no SW pumps can be operated, THEN perform the following:

a) Trip the reactor b) WHEN all E-O Immediate Actions done, THEN trip BOTH RCPs c) Close letdown isol, AOV-427 d) Close excess letdown, HCV-123 e) Go to E-O. REACTOR TRIP OR SAFETY INJECTION

4) IF only one SW pump can be operated. THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
b. SW header pressure - GREATER THAN 40 PSIG IN EACH LOOP
b. Refer to AP-SW.1. SERVICE WATER LEAK.

EOP:

TITLE:

I

~~~~~~~~REV:

2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 5 of 33

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 7 Check CCW Pump Status:

a. At least one CCW pump - RUNNING
b. Annunciator A-22. CCW PUMP DISCHARGE LO PRESS 60 PSIG -

EXTINGUISHED

a. Start one CCW pump (122 kw).

IF neither CCW pump can be.

started, THEN perform the following:

o IF reactor trip breakers closed. THEN:

1) Trip the reactor
2) WHEN all E-0 Immediate Actions done, THEN trip both RCPs
3) Close letdown isol, AOV-427
4) Close excess letdown, HCV-123
5) Pull stop BOTH CCW pumps
6) Go to E-0. REACTOR TRIP OR SAFETY INJECTION.

o IF reactor trip breakers open. THEN:

1) Trip both RCPs
2) Close letdown isol. AOV-427
3) Close excess letdown.

HCV-123

4) Pull stop BOTH CCW pumps
5) Go to step 8
b. Start second CCW pump (122 kw).

EOP:

TITLE:

REV: 25 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

PAGE 6 of 33

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Verify charging pump status AT LEAST ONE RUNNING Isolate letdown flowpaths:

a. Close letdown isol. AOV-427
b. Close excess letdown. HCV-123
c. Close Loop A cold leg to excess letdown Hx. AOV-310 9 Verify Annunciator H-16, INSTRUMENT AIR COMP -

EXTINGUISHED Dispatch AO to locally reset and start adequate air compressors.

IF electric air compressor(s) can NOT be restored. THEN start diesel air compressor.

(Refer to ATT-11.2.

ATTACHMENT DIESEL AIR COMPRESSOR).

IF IA can NOT be established. THEN refer to AP-IA.1, LOSS OF INSTRUMENT AIR.

10 Verify Bus 11A And 11B Normal Feed Breakers -

CLOSED Go to Step 22.

11 Check MFW RESTORING AUTO Regulating Valves -

S/G LEVEL TO 52% IN Perform the following:

a. Place affected S/Gs MFW regulating valves in MANUAL
b. Restore S/G level to 52%

IF S/G level can NOT be controlled manually. THEN refer to AP-FW.l.

ABNORMAL MAIN FEEDWATER FLOW.

EOP:

TITLE:

REV: 25 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

PAGE 7 of 33

EOP:

TITLE:

1 -

~

~

~

~

k I

~REV: 2 5 P -ELEC.1 LOSS OF 12A AND/OR 12B BUSSES KlPAGE 8 of 33 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl NOTE:

IF VCT level decreases to 5%. charging pump suction will swap to the RWST.

This may require a load reduction.

12 Check VCT Makeup System:

a. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
b. Check VCT level:
b. Check letdown divert valve, LCV-112A. aligned to VCT.

o Level GREATER THAN 20%

Manually increase VCT makeup

-OR-flow as follows:

o Level - STABLE OR INCREASING

1) Ensure BA transfer pumps and RMW pumps running.
2) Adjust RMW flow control valve, HCV-lll, to increase RMW flow.
3) Increase boric acid flow as necessary to maintain required concentration.

IF VCT level can NOT be maintained, THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION, if necessary..

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Check Charging Pump Suction Aligned to VCT:

a. VCT level - GREATER THAN 20%
a. IF VCT level can NOT be maintained greater than 5%. THEN perform the following:
1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed
2) Continue with Step 14.

WHEN VCT level greater than 20%.

THEN do Step 13b.

b. Align charging pumps to VCT o LCV-112C open o LCV-112B closed EOP:

TITLE:

REV: 25 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

PAGE 9 of 33

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl NOTE:

When restarting equipment for recovery, it is preferable to start equipment on busses being supplied from offsite power.

14 Check CVCS Operation:

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

RUNNING

1) IF all seal cooling has been lost to any RCP. THEN close seal injection to affected RCP(s)

. RCP A, V-300A

. RCP B, V-300B

2) Start one charging pump (75 kw).
3) IF no charging pumps can be operated, THEN refer to AP-CVCS.3. LOSS OF ALL CHARGING FLOW.

This Step continued on the next page.

EOP:

TITLE:

REV: 25 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

PAGE 10 of 33

STEP ACTION/EXPECTED RESPONSE RESPONSE-NOT OBTAINED (Step 14 continued from previous page)

b. Check letdown indications:

o Check PRZR level - GREATER THAN 13%

b. Perform the following:
1) Close letdown isolation.

AOV-427.

o Letdown flow -

40 gpm (60 gpm OPEN)

APPROXIMATELY if AOV-202

2) Close letdown orifice valves (AOV-200A, AOV-200B. and AOV-202) o Letdown flow - STABLE
3) Close letdown isolation, AOV-371
4) IF seal injection in service, THEN close charging flow control valve, HCV-142 WHILE adjusting charging pump speed to maintain:

. RCP labyrinth seal D/P between 15 inches and 80 inches

. PRZR level at program

5) IF PRZR level greater than 13%. THEN go to Step 15.

IF NOT, THEN continue with Step 17.

WHEN PRZR level greater than 13%. THEN do Steps 15 and 16.

c. Adjust charging pump speed and HCV-142 to restore PRZR level and labyrinth seal D/P
d. Go to Step 16 EOP:

TITLE:

AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

PAGE 11 of 33

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 15 Establish Normal Letdown:

(Refer to ATT-9.0, ATTACHMENT LETDOWN) 16 Verify PRZR Heaters Restored:

o PRZR proportional heater breaker

- CLOSED o PRZR backup heater breaker -

RESET/IN AUTO IF normal letdown can NOT be established, THEN establish excess letdown.

(Refer to ATT-9.1.

ATTACHMENT EXCESS L/D)

IF adequate D/G capacity available for PRZR heaters (400 kw each bank), THEN perform the following:

a. Reset and close PRZR proportional heater breaker if necessary.
b. Reset PRZR backup heater breaker and return to AUTO if necessary.

IF adequate D/G capacity NOT available. THEN refer to ER-PRZR.l.

RESTORATION OF PRZR HEATERS DURING BLACKOUT.

.EOP:

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I~

REV: 25 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 12 of 33

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Verify Normal Rod Control Restored:

a. Annunciator C-5. PPCS ROD SEQUENCE OR ROD DEVIATION -

EXTINGUISHED

a. IF alarm is due to a loss of power to MRPI. THEN maintain rods in manual AND minimize rod motion.

IF alarm is due to actual rod misalignment, THEN refer to AP-RCC.2. RCC/RPI MALFUNCTION.

while continuing with this procedure.

b. Annunciator E-28, POWER RANGE ROD DROP ROD STOP - EXTINGUISHED
b. Perform the following:
1) Place rods in MANUAL.
2) Reset NIS rod drop rod stop signals (at NIS racks) as necessary.
c. Annunciator F-15. RCS TAVG DEV 4°F - EXTINGUISHED
c. Go to step 18.
d. Place rods in AUTO if desired

. EOP:

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~~~~~~~~~~~~~~~~REV 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 13 of 33

NOTE:

With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode.

(Refer to TR 3.4.3).

18 Establish Stable Plant Conditions:

a. Check Tavg - TRENDING TO TREF
a. IF Tavg restore more of greater than Tref. THEN Tavg to Tref by one or the following:

. RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:

. Withdraw control rods

. Reduce turbine load

  • Dilution of RCS
b. Check PRZR pressure - TRENDING TO 2235 PSIG IN AUTO
b. Control PRZR pressure by one of the following:
  • 431K in MANUAL

. Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually, THEN refer to AP-PRZR.l. ABNORMAL PRESSURIZER PRESSURE.

c. Check PRZR level - TRENDING TO PROGRAM IN AUTO CONTROL
c. Perform the following:
1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually, THEN refer to AP-RCS.1. REACTOR COOLANT.

LEAK.

EOP:

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AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES

.I PAGE 14 of 33

ACTION/EXPECTED

~

~

~

~

NO OBTAINNSE CAUTION ANYTIME EMERGENCY DGS ARE THE ONLY SOURCE OF AC POWER TO THE PLANT, PERSONNEL SHOULD BE ASSIGNED TO MAINTAIN SURVEILLANCE OF THE D/GS.

19 Restore Normal Electric System Alignment:

a. Verify circuit 767 and/or 751 -

AVAILABLE

a. Continue with Step 20.

WHEN offsite power available, THEN do Steps 19b. c and d.

b. Restore power to non-faulted Buses 12A and/or 12B (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER)
c. Verify all AC bus normal feed breakers - CLOSED

. Bus 13

. Bus 14

. Bus 15

. Bus 16

. Bus 17

. Bus 18

c. Restore all AC busses and MCCs to normal power supply (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER)
d. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4. DIESEL GENERATOR OPERATION)

.EOP:

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AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES REV: 25 PAGE 15 of 33

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 20 Check CNMT Recirc Fans -

AT LEAST 2 RUNNING Establish 2 CNMT recirc fans running EOP:

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I

~~REV: 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B USSES PAGE 16 of 33

STEP _ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Establish Control Systems In Auto:

a. Verify 431K in AUTO
b. Verify PRZR spray valves in AUTO
c. Verify PRZR heaters restored:

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO

d. Verify charging pumps o 2 charging pumps running o One charging pump in AUTO
e. Verify MFW regulating valves in AUTO
f. Restore EH controls
1) Place in OP PAN. IMP OUT
2) Select load rate to 10%/hour
3) Match setter and reference
g. Verify annunciator G-15, STEAM DUMP ARMED - EXTINGUISHED
h. Verify Rods in AUTO
i. Go to Step 38
a. Place 431K in AUTO. if desired.
b. Place PRZR spray valves in AUTO.

if desired.

c. Restore PRZR heaters, if desired.
d. Perform the following:
1) IF all seal cooling has been lost. THEN ensure seal injection isolated to affected RCPs

. RCP B, V-300B

2) Establish 2 charging pumps running (75 kw each).
3) Place one charging pump in AUTO, if desired.
e. Place MFW regulating valves in AUTO, if desired.
g. WHEN Tavg within 5F of Tref.

THEN perform the following:

1) Ensure steam dump valves closed.
2) Reset steam dump.
h. Place Rods in AUTO, if desired.

LOP:

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EOP:

IlEE:

REV: 25 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

PAGE 17 of 33

STEP _ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

o Temperatures in the loop with the stopped RCP will not be indicative of true Tavg and AT values.

o Attempts to restore offsite power should continue (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER.)

22 Check Secondary Heat Sink Status:

a. Any main feed pump - RUNNING
a. Perform the following:
1) Verify MDAFW pumps running as necessary.
2) Verify TDAFW pump running if necessary.
3) Adjust AFW pump flow to restore S/G level to 52%.
4) Go to Step 23.
b. Verify MFW regulating valves -

RESTORING S/G LEVEL TO 52%

b. Perform the following:
1) Place affected SG(s) MFW regulating valve in MANUAL.
2) Restore SIG level to 52%.

IF S/G level can NOT controlled manually.

to AP-FW.1, ABNORMAL FEEDWATER FLOW.

be THEN refer MAIN EOP:

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REV: 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 18 of 33

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check TDAFW Pump Status:

a. TDAFW pump - RUNNING
b. Check S/G status o At least one S/G level -

GREATER THAN 17%

a. Go to Step 24.
b. Go to Step 24.

-OR-o Both MDAFW pumps - OPERABLE

c. Pull stop TDAFW pump steam supply valves
  • MOV-3504A

. MOV-3505A NOTE:

Use of ARV associated with the running RCP is preferred.

24 Establish RCS Temperature Control:

a. Verify condenser available:

o Any MSIV - OPEN o Annunciator G-15. STEAM DUMP ARMED - LIT

b. Adjust condenser steam dump controller HC-484 to stabilize RCS temperature
c. Place steam dump mode selector switch to MANUAL
a. Perform the following:
1) Adjust S/G ARV controllers to stabilize RCS temperature.
2) Go to Step 25.

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~~REV: 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

PAGE 19 of 33

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REV: 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PE 20

~~~~~~~~~~~~~~PAGE 20 of 33.

STEP _

ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED 25 Restore Non-Safeguards Busses As Follows:

a. Verify Bus 13 and 15 - ENERGIZED
a. IF offsite power available, THEN attempt to restore offsite power and normal feed to Bus 13/15 (Refer to ER-ELEC.1. RESTORATION-OF OFFSITE POWER).

IF offsite power is NOT available. THEN perform the following:

o Close Bus 13 to Bus 14 tie breaker o Close Bus 15 to Bus 16 tie breaker

b. Verify MCC A - ENERGIZED
b. Perform the following:
1) Ensure the following pumps in PULL STOP:
  • EH pump
  • Turning

. HP seal A

gear oil pump oil backup pump

2) Close MCC A supply breaker from bus 13.
3) Start HP seal oil backup pump.
c. Verify MCC B - ENERGIZED
d. Verify annunciator J-8. 480V MCC SUPPLY BREAKER TRIP -

EXTINGUISHED

c. Perform the following:
1) Ensure EH pump B in PULL STOP.
2) Close MCC B supply breaker from bus 15.
d. Restore power to other MCCs as D/G loading permits.
e. Reset control room lighting
f. Reset MAIN XFMR AUX PWR SUPPLY breakers

. Bus 13

  • Bus 15

STEP ACTION/EXPECTED RESPONSE rRESPONSE NOT OBTAINED NOTE: When restarting equipment for recovery, it is preferable to start equipment on busses being supplied from offsite power, if possible.

26 Verify Instrument Bus D -

ENERGIZED Energize MCC B. IF MCC B NOT available. THEN refer to ER-INST.3.

INSTRUMENT BUS POWER RESTORATION.

27 Check VCT Makeup System:

a. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
b. Check VCT level:

o Level GREATER THAN 20%

-OR-o Level -

STABLE OR INCREASING

b. Check letdown divert valve, LCV-112A, aligned to VCT.

Manually increase VCT makeup flow as follows:

1) Ensure BA transfer pumps and RMW pumps running.
2) Adjust RMW flow control valve, HCV-111. to increase RMW flow.
3) Adjust boric acid flow to maintain required concentration.

IF VCT level can NOT be maintained. THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION, if necessary.

EOP:

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L,

~REV: 2 5 AP-ELEC.1 tOSS OF 12A AND/OR 12B BUSSES PAGE 21 of 33

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDl 28 Check Charging Pump Suction Aligned to VCT:

a. VCT level - GREATER THAN 20%
a. IF VCT level can NOT be maintained greater than 5%, THEN perform the following:
1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed
2) Continue with Step 29.

WHEN VCT level greater than 20%.

THEN do Step 28b.

b. Align charging pumps to VCT o LCV-112C open o LCV-112B closed

[

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~~~~~~~~~~~~~~~~REV 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES J.1 PAGE 22 of 33

29 Check CVCS Operation:

a. Charging pumps - AT LEAST ONE RUNNING
b. Check letdown indications:

o Check PRZR level - GREATER THAN 13%

a. Perform the following:
1) Close letdown isolation, AOV-427.
2) Start one charging pump (75 kw).
3) Establish greater than 20 gpm charging line flow.
b. Perform the following:
1) Close letdown isolation, AOV-427.

o Letdown flow -

40 GPM (60 GPM OPEN)

APPROXIMATELY IF AOV-202 o Letdown flow - STABLE

2) Close letdown orifice valves (AOV-200A. AOV-200B. and AOV-202)
3) Close letdown isolation, AOV-371
4) IF seal injection in service, THEN close charging flow control valve. HCV-142 WHILE adjusting charging pump speed to maintain:

. RCP labyrinth seal D/P between 15 inches and 80 inches

. PRZR level at program

5) IF PRZR level greater than 13%, THEN go to Step 30.

IF NOT, THEN continue with Step 32.

WHEN PRZR level greater than 13%. THEN do Steps 30 and 31.

c. Adjust charging pump speed and HCV-142 to restore PRZR level and labyrinth seal D/P
d. Go to Step 31 EOP:

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AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

R PAGE 23 of 33

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 30 Establish Normal Letdown (Refer to ATT-9.0, ATTACHMENT LETDOWN) 31 Verify PRZR Heaters Restored:

o PRZR proportional heater breaker

- CLOSED o PRZR backup heater breaker -

RESET/IN AUTO IF normal letdown can NOT be established. THEN establish excess letdown.

(Refer to ATT-9.1, ATTACHMENT EXCESS L/D)

IF adequate D/G capacity available for PRZR heaters (400 kw each bank), THEN perform the following:

a. Reset and close PRZR proportional heater breaker if necessary.
b. Reset PRZR backup heater breaker and return to AUTO if necessary.

IF adequate D/G capacity NOT available, THEN refer to ER-PRZR.1.

RESTORATION OF PRZR HEATERS DURING BLACKOUT.

.EDP:

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~~~REV: 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 24 of 33

32 Verify TDAFW Pump Aligned For Auto Start:

a. Any MDAFW pump - AVAILABLE
b. Verify AMSAC TRIPPED status light - EXTINGUISHED
c. Verify both S/G levels THAN 17%

- GREATER

d. Verify Bus 11A and Bus lB - AT LEAST ONE ENERGIZED
a. Verify TDAFW pump operating to maintain required S/G level and go to Step 34.
b. Reset AMSAC.
c. Continue with Step 34.

WHEN S/G level greater than 17%. THEN do Steps 32d. e and 33.

d. Perform the following:
1) IF TDAFW pump NOT required to maintain S/G level. THEN pull stop TDAFW pump steam supply valves:

. MOV-3504A

  • MOV-3505A
2) Go to Step 33.
e. Verify the following:
1) TDAFW pump - OFF
2) TDAFW pump steam switches in AUTO supply valve
1) IF TDAFW pump NOT required to maintain S/G level. THEN stop pump if desired.
2) Place TDAFW pump steam supply valve switches in AUTO.

EOP:

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AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES REV: 25 PAGE 25 of 33

STEP ACTION/EXPECTED RESPONSE tRESPONSE NOT OBTAINED 33 Establish Normal AFW Pump Shutdown Alignment:

a. Verify the following:

o Both S/G levels - GREATER THAN 17% AND STABLE OR INCREASING o Total AFW flow - LESS THAN 200 GPM

b. Close MDAFW pump discharge valves

. MOV-4007

. MOV-4008

c. Place AFW bypass switches to DEF
d. Stop all but one MDAFW pump
e. Open AFW discharge crossover valves
  • MOV-4000A

. MOV-4000B

f. Adjust AFW bypass valves to control S/G levels at 52%
  • AOV-4480

. AOV-4481

a. Continue with Step 34.

WHEN conditions met, THEN do Steps 33b through f.

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-~REV:

2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

PAGE 26 of 33

NOTE:

With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode.

(Refer to TR 3.4.3) 34 Establish Stable Plant Conditions:

a. Check PRZR pressure - TRENDING TO 2235 PSIG IN AUTO
a. Control PRZR pressure at the desired value by one of the following:

. 431K in MANUAL

  • Manual control and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
b. Verify charging pumps o 2 charging pumps running o One charging pump in AUTO
c. Check PRZR level - TRENDING TO PROGRAM IN AUTO CONTROL
d. Check RCS Tavg - STABLE
b. Perform the following:
1) IF all seal cooling has been lost to any RCP. THEN isolate seal injection to affected RCP(s).

. RCP A. V-300A

. RCP B. V-300B

2) Establish 2 charging pumps running (75 kw each).
3) Place one charging pump in AUTO. if desired.
c. Perform the following:
1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.
d. Control dumping steam to stabilize RCS Tavg.

EOP:

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REV: 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES K

PAGE 27 of 33 of PRZR heaters

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION ANYTIME EMERGENCY D/GS ARE THE ONLY SOURCE OF AC POWER TO THE PLANT.

PERSONNEL SHOULD BE ASSIGNED TO MAINTAIN SURVEILLANCE OF THE D/GS.

35 Restore Normal Electric System Alignment:

a. Verify circuit 767 and/or 751 -

AVAILABLE

a. Continue with Step 36.

WHEN offsite power available, THEN do Steps 35b. c and d.

b. Restore power to non-faulted Buses 12A and/or 12B if necessary (Refer to ER-ELEC.1.

RESTORATION OF OFFSITE POWER)

c. Verify all AC bus normal feed breakers - CLOSED

. Bus 13

. Bus 14

. Bus 15

  • Bus 16

. Bus 17

. Bus 18

c. Restore all AC busses and MCCs to normal power supply (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER)
d. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4. DIESEL GENERATOR OPERATION)

.IEOP:

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~~~~~~~~~~~~~~~~REV 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B USSES

.I PAGE 28 of 33

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 36 Check CNMT Recirc Fans -

AT LEAST 2 RUNNING NOTE: Evaluate conditions to determine turning gear.

37 Verify Turning Gear Oil Pump RUNNING 38 Check Status Of DC System Loads:

a. Verify TURB emergency DC lube oil pump - OFF
b. Verify TDAFW pump DC oil pump -

OFF IN AUTO

c. Verify both MFW pump DC oil pumps - OFF Establish 2 CNMT recirc fans running if turbine should be placed on Perform the following:
a. Manually start turning gear oil pump (42 kw).
b. Break vacuum to accelerate turbine coastdown.
c. Continue with Step 38.

WHEN shaft stops, THEN dispatch AO to place turbine on turning gear (36 KW).

a. Manually stop emergency DC lube oil pump.
b. Perform the following:
1) Direct AO to locally check TDAFW AC oil pump running.

IF not running, THEN start pump from MCB.

2) Stop T-DAFW pump DC oil pump.
c. Perform the following:
1) Ensure associated MFW pump AC oil pump running.
2) Stop MFW pump DC oil pump and place-in AUTO EOP:

TITLE:

REV: 25 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES

.I PAGE 29 of 33

STEP _

ACTION/EXPECTED RESPONSE tRESPONSE NOT OBTAINED NOTE:

Inst Bus C provides power to all MCB manual controllers.

39 Check Status of Battery Chargers:

a. Battery Chargers 1A OR lAl -

ENERGIZED (Annunciator J-15.

BATTERY CHRGR FAILURE OR PA INVERTER TROUBLE. EXTINGUISHED)

b. Battery chargers 1B OR lB ENERGIZED (Annunciator J-15.

BATTERY CHRGR FAILURE OR PA INVERTER TROUBLE. EXTINGUISHED)

a. IF BOTH battery chargers are deenergized, THEN direct the Electricians to crosstie TSC battery charger to main battery A

(Refer to ATT-24.0.

ATTACHMENT TRANSFER BATTERY TO TSC).

b.

IF BOTH battery chargers are deenergized, THEN direct the Electricians to crosstie TSC battery charger to main battery B

(Refer to ATT-24.0.

ATTACHMENT TRANSFER BATTERY TO TSC)

EOP:

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~~~~~~~~~~~~~~~REV:

2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B OSSES l PAGE 30 of 33

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 40 Restore Equipment Alignment:

a. Check CCW pumps - ONLY ONE RUNNING
b. Check radiation monitoring systems:

o CNMT vent sample pump -

RUNNING o Plant vent sample pump -

RUNNING o All area and process monitors operating as required

c. Dispatch AO to verify proper operation of seal oil system
d. Verify motor fire pump breaker -

CLOSED

e. Verify annunciator L-1. AUX BLDG VENT SYSTEM CONTROL PANEL -

EXTINGUISHED

f. Verify MCC G - ENERGIZED
g. Verify control board valve alignment - NORMAL (Refer to 0-6.13, DAILY SURVEILLANCE LOG)
h. Verify adequate Rx head cooling:
1) Verify at least one control rod shroud fan - RUNNING
2) Verify one Rx compartment cooling fan - RUNNING
i. Dispatch AO to ensure one waste gas compressor in service This Step continued on the next page.
a. IF two CCW pumps running, THEN manually stop one pump.
b. Restore sample pumps and radiation monitors.
d. Close motor fire pump breaker.
e. IF bus 11A or 11B energized, THEN dispatch AO to restore AUX BLDG ventilation (Refer to T-35A. AUX AND INTERMEDIATE BUILDING VENTILATION STARTUP AND SHUTDOWN)
f. Manually close breaker.
g. Manually align valves as necessary.
1) Manually start one fan as power supply permits (45 kw).
2) Manually start one fan as power supply permits (23 kw).

EOP:

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STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl (Step 40 continued from previous page)

j.

Dispatch AO to restore SFP cooling

k. Verify adequate electric driven air compressors - RUNNING
1. IF diesel air compressor supplying instrument air, THEN secure diesel air compressors.

(Refer to T-2F. BACKUP AIR SUPPLY) 41 Reset UV Relay Targets On Undervoltage Cabinets

. Bus 14

. Bus 16

. Bus 17

. Bus 18 42 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE:

Refer to 0-9.3. NRC IMMEDIATE requirements.

k. Go to Step 41.

NOTIFICATION, for reporting 43 Notify Higher Supervision EOP:

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REV: 2 5 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 32 of 33 l~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.

, s.,.

STEP

~ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 44 Return To Procedure Or Guidance In Effect

-END-EOP:

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hP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES REV: 25 PAGE 1 of 1 AP-ELEC. 1 APPENDIX LIST TITLE

1) ATTACHMENT NC (ATT-13.0)
2) ATTACHMENT D/G STOP (ATT-8.1)
3) ATTACHMENT TRANSFER BATTERY TO TSC (ATT-24.0)
4) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
5) ATTACHMENT EXCESS L/D (ATT-9.1)
6) ATTACHMENT LETDOWN (ATT-9.0)

I_

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TITLE:

AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 REV: 5 PAGE 1 of 21 I

I ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER

Ž RESPONSIBLE eAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

I

EOP:

TITLE:

REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 2 of 21 A.

PURPOSE -

This procedure provides actions to respond to a loss of AC Emergency Bus 14 or Bus 16.

B.

ENTRY CONDITIONS/SYMPTOMS

2.

SYMPTOMS -

The symptoms of a LOSS OF SAFEGUARDS BUS 14/16 are;

a. Annunciator J-7, 480V MAIN OR TIE BREAKER TRIP, lit, or
b. Annunciator J-29, 480V TRANSFORMER BREAKER TRIP, lit.

STEP _

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o IF A LOSS OF BUS 12A OR 12B HAS OCCURRED. THEN AP-ELEC.1. LOSS OF 12A AND/OR 12B BUSSES. SHOULD BE PERFORMED.

o OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR. 2250 KW FOR 2 HOURS.

AND 1950 KW FOR CONTINUOUS SERVICE.

NOTE:

Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.O. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

  • 1 Monitor Tavg
a. Place Rods in MANUAL
b. Manually move control rods to control Tavg 2 Verify Emergency D/G Associated With Affected Bus RUNNING Manually start D/G(s) associated with affected bus.

(Refer to ER-D/G.1, RESTORING D/Gs) o Bus 14 - D/G A o Bus 16 - D/G B

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REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 4 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS:

o Bus 14 and Bus 18 o Bus 16 and Bus 17 IF both trains deenergized, THEN go to ECA-O.O, LOSS OF ALL AC POWER.

IF one train deenergized. THEN perform the following:

a. Ensure D/G aligned for unit operation o Mode switch in UNIT o Voltage control selector in AUTO
b. Check D/G running.

IF NOT. THEN perform the following:

1) Depress D/G FIELD RESET pushbutton
2) Depress D/G RESET pushbutton
3) Start D/G
4) IF D/G will NOT start, THEN dispatch AO to locally start D/G.

(Refer to ER-D/G.1.

RESTORING DIGs)

c. Adjust D/G voltage to approximately 480V.
d. Adjust D/G frequency to approximately 60 Hz.

EOP:

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REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 5 of 21 ACTION/EXPEC~~~~~~NTE OBTAINE _IEW CAUTION IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 2000F. THEN TRIP THE AFFECTED RCP.

i 4 Verify CCW Pump Status

a. At least ne CCW Pump - RUNNING
b. Annunciator A-22. CCW PUMP DISCHARGE LO PRESS 60 PSIG -

EXTINGUISHED

a. Start one CCW pump (122 kw)

IF neither CCW pump can be started. THEN perform the following:

o IF reactor trip breakers closed, THEN:

1) Trip the reactor.
2) WHEN all E-0 Immediate Actions done, THEN trip BOTH RCP's.
3) Close letdown isolation, AOV-427.
4) Close excess letdown.

HCV-123.

5) Pull stop BOTH CCW pumps.
6) Go to E-0, REACTOR TRIP OR SAFETY INJECTION.

o IF reactor trip breakers open, THEN:

1) Trip both RCPs.
2) Close letdown isolation, AOV-427.
3) Close excess letdown.

HCV-123.

4) Pull stop BOTH CCW pumps.
5) Go to Step 5.
b. Start second CCW pump (122 kw).

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REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 6 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify Charging Pump Status-AT LEAST ONE RUNNING Isolate letdown flowpaths

a. Close letdown isolation. AOV-427.
b. Close EXCESS LETDOWN HCV-123.
c. Close loop A cold leg to EXCESS LETDOWN Hx, AOV-310.

6 Check MFW Regulating Valves -

RESTORING S/G LEVEL TO 52 IN AUTO Perform the following:

a. Place affected S/G MFW regulating valve in MANUAL.
b. Restore S/G level to 52%.

IF S/G level can NOT be controlled manually. THEN refer to AP-FW.1.

ABNORMAL MAIN FEEDWATER FLOW.

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REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 7 of 21 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 7 Verify Bus 14 -

ENERGIZED TO Perform the following:

AT LEAST 420 VOLTS

a. Close letdown isolation, AOV-427.
b. IF steam dump is armed. THEN place STEAM DUMP MODE SELECTOR Switch to MANUAL.
c. Ensure only one charging pump operating (75 kw).
d. Transfer Inst Bus B to maintenance supply.
e. Return steam dump to AUTO, if desired.
f. Ensure the following equipment operating as necessary:

. CCW Pump B

  • PRZR Backup Heaters

. CNMT Recirc Fans B and C

. Boric Acid Pump B

  • RMW Pump B

. Reactor Compartment Cooling Fan B

. Penetration Cooling Fan B

. SFP cooling

g. IF Bus 14 can NOT be energized.

THEN:

o Provide alternate room cooling for D/G A.

o Cross-connect D/G B fuel oil transfer pump to D/G A (Refer to ER-D/G.1. RESTORING D/Gs).

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REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 8 of 21 ACTION/EXPECTED RESPONSE 8 Verify Bus 16 -

ENERGIZED TO AT LEAST 420 VOLTS I=RESPONSE NO BAINED Perform the following:

a. Ensure the following equipment operating as necessary:

. CCW Pump A

. Charging Pump A

. PRZR Proportional Heaters

. CNMT Recirc Fans A and D

  • RMW Pump A
  • Reactor Compartment Cooling Fan A

. Penetration Cooling Fan A

. SFP cooling

b. IF Bus 16 can NOT be energized, THEN:

o Provide alternate room cooling for D/G B.

O Cross-connect DIG A fuel oil transfer pump to D/G B (Refer to ER-D/G.1. RESTORING D/Gs).

.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

EOP:

TITLE:

REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 9 of 21 NOTE:

IF VCT level decreases to 5%. charging pump suction will swap to the RWST.

This may required a load reduction.

9 Check VCT Makeup System:

a. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
b. Check VCT level:

o Level GREATER THAN 20%

-OR-o Level -

STABLE OR INCREASING

b. Check letdown divert valve.

LCV-112A. aligned to VCT.

Manually increase VCT makeup flow as follows:

1) Ensure BA transfer pumps and RMW pumps running.
2) Adjust RMW flow control valve, HCV-l11. to increase RMW flow.
3) Adjust boric acid flow to maintain required concentration.

IF VCT level can NOT be maintained, THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION, if necessary..

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REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 10 of 21 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 10 Check Charging Pump Suction Aligned To VCT:

a. VCT level - GREATER THAN 20%
a. IF VCT level can NOT be maintained greater than 5%. THEN perform the following:
1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed
2) Continue with Step 11.

WHEN VCT level greater than 20%,

THEN do Step lOb.

b. Align charging pumps to VCT o LCV-112C open o LCV-112B closed

EOP:

TITLE:

REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 11 of 21 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED NOTE:

When restarting equipment for recovery. it is preferable to start equipment on busses being supplied from offsite power.

11 Check CVCS Operation:

a. Charging pumps - AT LEAST ONE RUNNING
a. IF charging pump(s) available.

THEN perform the following:

1) IF all seal cooling has been lost to any RCP. THEN isolate.

seal injection to affected RCP

. RCP B. V-300B

2) Start one charging pump (75 kw).
3) Establish greater than 20 gpm charging line flow.

IF NO charging pumps available, THEN go to step 13

b. Charging line flow - GREATER THAN 20 GPM
b. Establish charging line flow to REGEN Hx - GREATER THAN 20 GPM This Step continued on the next page.

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TITLE:

REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 12 of 21 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED (Step 11 continued from previous page)

c. Check letdown indications:

o Check PRZR level - GREATER THAN 13%

c. Perform the following:
1) Close letdown isolation.

AOV-427.

o Letdown flow -

40 GPM (60 GPM OPEN)

APPROXIMATELY IF AOV-202

2) Close letdown orifice valves (AOV-200A. AOV-200B. and AOV-202) o Letdown flow - STABLE
3) Close letdown isolation.

AOV-371.

4) IF seal injection in service, THEN close charging flow control valve HCV-142 WHILE adjusting charging pump speed to maintain:

o RCP labyrinth seal D/P between 15 inches and 80 inches o PRZR level at program

5) IF PRZR level greater than 13%. THEN go to Step 12.

IF NOT, THEN continue with Step 14.

WHEN PRZR level greater than 13%. THEN do Steps 12 and 13.

d. Adjust charging pump speed and HCV-142 to restore PRZR level and labyrinth seal D/P
e. Go to Step 13

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REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 13 of 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAI 12 Establish Normal Letdown (Refer to ATT-9.0, ATTACHMENT LETDOWN) 13 Verify PRZR Heaters Restored:

o PRZR proportional heater breaker CLOSED o PRZR backup heater breaker -

RESET, IN AUTO IF normal letdown can NOT be established. THEN establish excess letdown.

(Refer to ATT-9.1.

ATTACHMENT EXCESS L/D)

IF adequate D/G capacity available for PRZR heaters (400 kw each bank), THEN perform the following:

a. Reset and close PRZR proportional heater breaker if necessary.
b. Reset PRZR backup heater breaker and return to AUTO if necessary.

IF adequate D/G capacity NOT available. THEN refer to ER-PRZR.1, RESTORATION OF PRZR HEATERS DURING BLACKOUT.

LOP:

TITLE:

AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 REV: 5 PAGE 14 of 21 ACTION/EXPECTED RESPONSE j

I ~~RE SP ONSE N OBA IN ED BAIE 14 Verify Normal Rod Control Restored:

a. Annunciator C-5. PPCS ROD SEQUENCE OR ROD DEVIATION -

EXTINGUISHED

a. IF alarm is due to a loss of power to MRPI. THEN maintain rods in manual AND minimize rod motion.

IF alarm is due to actual rod misalignment, THEN refer to AP-RCC.2. RCC/RPI MALFUNCTION, while continuing with this procedure.

b. Annunciator E-28, POWER RANGE ROD DROP ROD STOP - EXTINGUISHED
b. Perform the following:
1) Place rods in MANUAL.
2) Reset NIS rod drop rod stop signals (at NIS racks) as necessary.
c. Annunciator F-15, RCS TAVG DEV 4°F - EXTINGUISHED
c. Go to step
d. Place rods in AUTO, if desired 15

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REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 15 of 21 STEP _

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode.

(Refer to TR 3.4.3) 15 Establish Stable Plant Conditions:

a. Check Tavg - TRENDING TO TREF
a. IF Tavg restore more of greater than Tref, THEN Tavg to Tref by one or the following:
  • Insert control rods RCS boration IF Tavg restore more of less than Tref. THEN Tavg to Tref by one or the following:
  • Reduce turbine load

. Dilution of RCS

b. Check PRZR pressure - TRENDING TO 2235 PSIG IN AUTO
b. Control PRZR pressure by one of the following:

a 431K in MANUAL

. Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.

c. Check PRZR level - TRENDING TO PROGRAM IN AUTO CONTROL
c. Perform the following:
1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1, REACTOR COOLANRT LEAK.

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Restore Normal Electric System Alignment:

a. Verify all AC bus normal feed
a. Perform the following:

breakers - CLOSED

1) Refer to AR-L-5 to reset a

. Bus 13 safeguards bus over current

. Bus 14 condition.

. Bus 15

. Bus 16

2) Restore non-faulted AC busses

. Bus 17 and MCCs to normal power

. Bus 18 supply (Refer to ER-ELEC.1.

RESTORATION OF OFFSITE POWER)

3) IF normal power is restored to all AC emergency buses.

THEN return to step 7. IF NOT, THEN go to step 17.

b. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4. DIESEL GENERATOR OPERATION)

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TITLE:

REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 17 of 21 STEP ACTION/EXPECTED RESPONSE REPNENTOTIE 17 Establish Normal Plant Conditions:

a. Verify 2 charging pumps - RUNNING
a. Perform the following:
1) Manually start charging pumps as necessary.
2) Place one charging pump in AUTO, if desired.
b. Verify at least 2 CNMT recirc fans - RUNNING
b. Establish 2 CNMT recirc fans running.
c. Check CCW pumps RUNNING
d. Check radiation systems:

- ONLY ONE monitoring o CNMT vent sample pump -

RUNNING

c. Locally verify two CCW pumps running. THEN manually stop one pump.
d. Restore sample pumps and radiation monitors as necessary.

(Refer to the ODCM).

o Plant vent sample pump -

RUNNING o All area and process monitors operating as required 18 Check Status Of DC System Loads:

a. Verify TDAFW pump DC oil pump -

OFF IN AUTO

a. Perform the following:
1) Direct AO to locally check TDAFW AC oil pump running.

IF not running. THEN start pump from MCB.

2) Stop TDAFW pump DC oil pump.

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

Inst Bus C provides power to all MCB manual controllers.

19 Check Status of Battery Chargers:

a. Battery Chargers 1A OR lAl -

ENERGIZED (Annunciator J-15.

BATTERY CHRGR FAILURE OR PA INVERTER TROUBLE, EXTINGUISHED)

b. Battery Chargers 1B OR lBl -

ENERGIZED (Annunciator J-15, BATTERY CHRGR FAILURE OR PA INVERTER TROUBLE. EXTINGUISHED)

a. IF BOTH battery chargers are deenergized. THEN direct the Electricians to crosstie TSC battery charger to main battery A

(Refer to ATT-24.0.

ATTACHMENT TRANSFER BATTERY TO TSC).

b. IF BOTH battery chargers are deenergized, THEN direct the Electricians to crosstie TSC battery charger to main battery B

(Refer to ATT-24.0.

ATTACHMENT TRANSFER BATTERY TO TSC).

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TITLE:

REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16

~~~~~~~~~~~~~~~PAGE 19 of 21.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 20 Restore Equipment Alignment:

a. Verify annunciator L-1, AUX BLDG VENT SYSTEM CONTROL PANEL -

EXTINGUISHED

a. Dispatch AO to restore AUX BLDG ventilation (Refer to T-35A.

AUX AND INTERMEDIATE BUILDING VENTILATION STARTUP AND SHUTDOWN)

b. Restore affected bus equipment as desired o SFP Cooling o

Penetration cooling fans o Reactor compartment cooling fans o Hydrogen panel o PA system inverter (Battery Room A) o Auxiliary Bldg lighting (normal supply MCC D. manual throwover to MCC C)(located at MCC C) o Fire system (Refer to SC-3.16.2.3)

c. Evaluate MCB annunciator status (Refer to AR Procedures)
d. Verify control board valve alignment - NORMAL (Refer to 0-6.13. DAILY SURVEILLANCE LOG)
d. Manually align valves as necessary.

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REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 20 of 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Establish Control System In Auto:

a. Verify 431K in AUTO
b. Verify PRZR spray valves in AUTO
c. Verify PRZR heaters restored:

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO

d. Verify one charging pump in AUTO
e. Verify,MFW regulating valves in AUTO
f. Restore EH controls
1) Place in OP PAN. IMP OUT
2) Place load rate thumbwheel to 10%/hr
3) Match setter and reference
g. Verify annunciator G-15, STEAM DUMP ARMED - EXTINGUISHED
h. Verify rods in AUTO
a. Place 431K in AUTO, if desired.
b. Place PRZR spray valves in AUTO, if desired.
c. Restore PRZR heaters, if desired.
d. Place one charging pump in AUTO.

if desired.

e. Place MFW regulating valves in AUTO, if desired.
g. WHEN Tavg within 5F of Tref.

THEN perform the following:

1) Ensure steam dump valves closed
2) Reset steam dump
h. Place rods in AUTO, if desired.

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TITLE:

REV: 5 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 21 of 21 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 22 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE:

Refer to 0-9.3. NRC IMMEDIATE requirements.

23 Verify emergency AC bus' normal feed breakers closed NOTIFICATION, for reporting Return to Step 6 o Bus 14 o Bus 16 24 Verify Inst Bus B on normal supply Place Inst Bus B on normal supply (Refer to ER-INST.3.INSTRUMENT BUS POWER RESTORATION).

25 Reset V relay targets on undervoltage cabinets o Bus 14 o Bus 16 26 Notify Higher Supervision 27 Return To Procedure Or Guidance In Effect

-END-

AP-ELEC.14/16 APPENDIX LIST TITLE

1)

ATTACHMENT TRANSFER BATTERY TO TSC (ATT-24.0)

2)

ATTACHMENT EXCESS L/D (ATT-9.1)

3)

ATTACHMENT LETDOWN (ATT-9.0)

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TITLE:

REV: 5 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 7/18 PAGE 1 of 7 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER X_

RESPONSIBLE ANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP:

TITLE:

REV: 5 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 2 of 7 A.

PURPOSE -

This procedure provides actions to respond to a loss of AC Emergency Bus 17 or Bus 18.

B.

ENTRY CONDITIONS/SYMPTOMS

2.

SYMPTOMS -

The symptoms of a LOSS OF SAFEGUARDS BUS 17/18 are;

a.

Annunciator J-7, 480V MAIN OR TIE BREAKER TRIP, lit, or

b.

Annunciator J-29, 480V TRANSFORMER BREAKER TRIP, lit.

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TITLE:

REV: 5 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 3 of 7 STP ACTION/EXPECTED RESPONSE l

RESPONSE NOT OBTAINEDl

  • * * * * * * * * * * * * * * * * * * * * * * * *
  • A * * *
  • CAUTION o IF A LOSS OF BUS 12A OR 12B HAS OCCURRED. THEN AP-ELEC.1, LOSS OF 12A AND/OR 12B BUSSES, SHOULD BE PERFORMED.

o OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR. 2250 KW FOR 2 HOURS.

AND 1950 KW FOR CONTINUOUS SERVICE.

NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Verify Emergency D/G Associated With Affected Bus RUNNING o Bus 18 Manually start D/G(s) associated with affected Bus.

(Refer to ER-D/G.1. RESTORING D/Gs)

D/G A o Bus 17 - D/G B

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TITLE:

REV: 5 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 4 of 7 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS:

o Bus 14 and Bus 18 o Bus 16 and Bus 17 IF both trains deenergized, THEN go to ECA-0.0. LOSS OF ALL AC POWER.

IF one train deenergized. THEN perform the following:

a. Ensure D/G aligned for unit operation o Mode switch in UNIT o Voltage control selector in AUTO
b. Check D/G running.

IF NOT, THEN perform the following:

1) Depress D/G FIELD RESET pushbutton
2) Depress D/G RESET pushbutton
3) Start D/G
4) IF D/G will NOT start. THEN dispatch AO to locally start D/G.

(Refer to ER-D/G.1.

RESTORING D/Gs)

c. Adjust D/G voltage to approximately 480V.
d. Adjust D/G frequency to approximately 60 Hz.

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TITLE:

REV: 5 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 5 of 7 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED

  • * * * * * * * * *
  • a
  • * *
  • a CAUTION IF EITHER D/G RUNNING WITHOUT SW COOLING AVAILABLE, THEN STOP THE AFFECTED D/G TO PREVENT OVERHEATING.

3 Verify Service Water System Operation:

a. SW pumps - AT LEAST ONE RUNNING
a. Perform the following:

IN EACH LOOP

1) Manually start SW pumps as o A or B pump in Loop A necessary (257 kw each).

o C or D pump in Loop B

2) IF adequate cooling can NOT be supplied to a running 7G THEN perform the following:

a) Trip affected D/G.

b) Immediately depress voltage shutdown pushbutton.

c) Refer to ER-D/G.2, ALTERNATE COOLING FOR EMERGENCY D/Gs.

3) IF no SW pumps can be operated. THEN perform the following:

a) Trip the reactor b) WHEN all E-O Immediate Actions done. THEN trip BOTH RCPs c) Close letdown isol. AOV-427 d) Close excess letdown.

HCV-123.

e) Go to E-0. REACTOR TRIP OR SAFETY INJECTION

4) IF only one SW pump can be operated. THEN refer to AP-SW.2, LOSS OF SERVICE

- WATER.

b. SW header pressure - GREATER THAN 40 PSIG IN EACH LOOP
b. Refer to AP-SW.1. SERVICE WATER LEAK.

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TITLE:

REV: 5 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 6 of 7 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 4 Restore Normal Electric System Alignment:

a. Verify all AC bus normal feed breakers - CLOSED

. Bus 13

. Bus 14

  • Bus 15 '

. Bus 16

. Bus 17

  • Bus 18
a. Perform the following:
1) Refer to AR-L-5 to reset safeguards bus overcurrent condition.
2) Restore all non-faulted AC busses and MCCs to normal power supply (Refer to ER-ELEC.I. RESTORATION OF OFFSITE POWER)

IF normal emergency

restored, power to all AC buses can NOT be THEN go to step 5.
b. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4. DIESEL GENERATOR OPERATION) 5 Restore Equipment Alignment:
a. Check SW Pumps - AT LEAST ONE PUMP RUNNING IN EACH LOOP
a. Start SW Pumps as necessary.

o Pump A or B in Loop A o Pump C or D in Loop B

b. Restore affected bus equipment as desired o MCC G o Intake Heaters o House Heating Boiler o Motor Fire Pump o Canal Sample Pump

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TITLE:

REV: 5 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 7 of 7 6 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE:

Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION.

requirements.

7 Verify Emergency AC Bus Normal Feed Breakers Closed for reporting Return to Step 4

. Bus 17

. Bus 18 8 Reset UV relay targets on undervoltage cabinets

. Bus 17

. Bus 18 9 Notify Higher Supervision 10 Return To Procedure Or Guidance In Effect

-END-

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TITLE:

AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW REV: 15 PAGE 1 of 13 I

I ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER c 3 RESPONSIBLO MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

I

A.

PURPOSE -

This procedure provides the steps necessary to respond to a MFW system malfunction resulting in a decrease in or complete loss of main feedwater, or an uncontrolled increase in main feedwater.

B.

ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS -

Other APs if feedwater flow can not be controlled.

2.

SYMPTOMS -

The symptoms of ABNORMAL MAIN FEEDWATER FLOW are;

a. Annunciator G-3(5), S/G A(B) LEVEL DEVIATION +/- 7%, lit, or
b. Annunciator G-19(21), S/G A(B) FLOW MISMATCH, lit, or
c. Annunciator G-20, ADFCS SYSTEM SWITCH TO MANUAL, lit, or
d. Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit, or
e.

Low indicated MFW pump suction flow on 1 pump, or

f. MFW pump indicates tripped, or
g. MFW pump discharge valve indicates shut.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 1 Check MFW Flow -

LESS THAN Perform the following:

STEAM FLOW

a. Place affected S/G(s) MFW regulating valve and bypass valve in MANUAL.
b. Restore S/G level to 52%.

IF S/G level greater than 52% AND can NOT be controlled manually.

THEN perform the following:

a. Trip the reactor.
b. WHEN all E-O Immediate Actions done. THEN stop all running MFW pumps.
c. Close both MFW pump discharge valves.
d. Go to E-O. REACTOR TRIP OR SAFETY INJECTION.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl NOTE:

IF power reduction is required the thumb rule for initial boron addition is -2 gal/% load reduction.

2 Check MFW Requirements:

a. Power - GREATER THAN 50%
a. IF power less than 50%. THEN go to Step 3.
b. Both MFW pumps - RUNNING
b. IF power greater than 75%. THEN trip the reactor and go to E-O.

REACTOR TRIP OR SAFETY INJECTION.

IF only one MFW pump has tripped, THEN perform the following:

1) Start all 3 AFW pumps and verify flow.
2) Place turbine in manual.
3) Depress MANUAL CONTROL VALVE LOWER AND MANUAL CONTROL VALVE FAST pushbuttons.
4) Ensure control rods inserting to control Tavg at program.
5) IF S/G level drops to < 20%

AND feed flow less than steam flow, THEN trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

6) WHEN feed flow greater than steam flow. THEN stop load reduction.
7) IF a PORV opens during load reduction, THEN ensure PORV closes when PRZR pressure is below 2335 psig.
8) Go to Step 4.

IF both MFW pumps have tripped.

THEN ensure reactor trip and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

c. Go to Step EOP:

TITLE:

REV: 15 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 4 of 13

3 Verify At Least One MFW Pump RUNNING IF power greater than 35%. THEN trip the reactor and go to E-0.

REACTOR TRIP OR SAFETY INJECTION.

IF NOT, THEN perform the following:

a. Start all 3 AFW pumps and verify flow.
b. IF turbine previously latched, THEN ensure turbine trip and go to AP-TURB.1. TURBINE TRIP WITHOUT RX TRIP REQUIRED OR E-0.

REACTOR TRIP or SAFETY INJECTION.

IF turbine NOT previously latched, THEN perform the following:

1) Reduce reactor power to less than 2%.
2) Go to Step 11.

4 Verify MFW Pump Suction Pressure -

GREATER THAN 185 PSIG Perform the following:

a. Verify standby condensate pump running. if required.
b. Verify condensate bypass valve open.
c. Place Hotwell level controller in MANUAL-at 50%.
d. Place trim valve controller to manual and close trim valves.
e. If condensate booster pumps have tripped THEN reduce turbine load until MFW pump suction pressure greater than 200 psig AND stable.

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TITLE:

REV: 15 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 5 of 13

STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify Adequate MFW Flow:

o A MFW flow - GREATER THAN OR EQUAL TO A STEAM FLOW o B MFW flow - GREATER THAN OR EQUAL TO B STEAM FLOW Check MFW regulating valves controlling in AUTO.

IF NOT. THEN control MFW flow in MANUAL.

IF MFW flow can NOT be adjusted to greater than steam flow. THEN trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

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REV: 15 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 6 of 13

.S --~~

NOTE:

With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode.

(Refer to TR 3.4.3) 6 Establish Stable Plant Conditions:

a. Tavg - TRENDING TO TREF
a. IF Tavg restore more of greater than Tref, THEN Tavg to Tref by one or the following:

. Insert control rods

. RCS boration IF Tavg less than Tref, THEN restore Tavg to Tref by one or more of the following:

a Withdraw control rods

. Reduce turbine load

. Dilution of RCS

b. PRZR pressure - TRENDING TO 2235 PSIG IN AUTO
b. Control PRZR pressure by one of the following:

. 431K in manual

. Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.

c. PRZR level - TRENDING TO PROGRAM IN AUTO CONTROL
c. Perform the following:
1) Place affected charging pump(s) in MANUAL
2) Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1, REACTOR COOLANT LEAK.

This Step continued on the next page.

EOP:

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REV: 15 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 7 of 13

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl (Step 6 continued from previous page)

d. MFW regulating valves -

RESTORING S/G LEVEL TO 52% IN AUTO

d. Perform the following:
1) Place affected S/G(s) MFW regulating valve in MANUAL.
2) Restore SIG level to 52%.
e. Rod insertion limit alarms -

EXTINGUISHED

e. Borate and withdraw control rods to clear insertion limit alarms (refer to affected rod bank alarm response procedures if necessary).

7 Check Status Of MFW System:

a. Check MFW pump suction pressure:

o Pressure - GREATER THAN 200 PSIG o Pressure - STABLE

b. Automatic feedwater control -

AVAILABLE

c. Restore feedwater control to AUTO if desired
a. Return to Step 4.
b. Continue with Step 8. WHEN malfunction identified, THEN do Step 7c.

system

. EOP:

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REV: 15 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 8 of 13

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 8 Check Status Of Condensate System:

a. Check condensate bypass valve -

CLOSED, IN AUTO

a. Perform the following:
1) Close condensate bypass valve-AND place in AUTO.
2) Verify MFW pump suction pressure remains greater than 200 psig.

IF NOT, THEN manually open condensate bypass valve.

b. Verify hotwell level - AT SETPOINT
b. Slowly restore hotwell level to setpoint.
c. Place hotwell level controller in AUTO
d. Check condensate pump - ONLY 2 PUMPS RUNNING
e. Verify trim valves in AUTO
d. Stop one condensate pump.

(Refer to T-5F. STARTING OR STOPPING THE CONDENSATE PUMPS)

e. Adjust trim valve controller to 300 to 375 psig (PI-2043) and place controller in AUTO.

. EOP:

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REV: 15 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW I.

.PAGE 9 of 13

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REV: 15 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 10 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish Control Systems In Auto

a. Verify 431K in AUTO
b. Verify PRZR spray valves in AUTO
c. Verify PRZR Heaters restored:

o PRZR proportional heater breaker - CLOSED o PRZR backup heater breaker -

RESET/IN AUTO

d. Verify one charging pump in AUTO
e. Verify MFW regulating valves in AUTO
f. Restore EH controls
1) Place in OP PAN, IMP OUT
2) Place load rate thumbwheel to 10%/hr
3) Match setter and reference
g. Verify steam dump controller.

HC-484, in AUTO at 1005 psig

h. Verify annunciator G-15, STEAM DUMP ARMED - EXTINGUISHED
i. Verify Rods-in AUTO
a. Place 431K in AUTO. if desired.
b. Place PRZR spray valves in AUTO.

if desired.

c. Restore PRZR heater, if desired.
d. Place one charging pump in AUTO, if desired.
e. Place MFW regulating valves in AUTO, if desired.
h. WHEN Tavg within 5F of Tref, THEN perform the following:
1) Ensure steam dump valves closed.
2) Reset steam dump.
i. Place Rods in AUTO, if desired.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 10 Restore AFW System To Auto Standby:

a. Verify MFW regulating valves -
a. IF level low, THEN return to RESTORING S/G LEVEL TO 52% IN Step 5. WHEN S/G levels return AUTO to 52%. THEN do Steps 10b through g.
b. Close TDAFW pump steam supply valves

. MOV-3504A

. MOV-3505A

c. Direct AO to locally isolate S/G blowdowns.

(Refer to T-14N.

BLOWDOWN SYSTEM FLOW CHANGES)

d. WHEN AO has locally isolated S/G blowdowns. THEN stop MDAFW pumps and place switches in AUTO
e. Open AFW pump discharge valves

. MOV-4007

. MOV-4008

. MOV-3996

f. Open TDAFW pump flow control valves
  • AOV-4297

. AOV-4298

g. Direct AO to locally restore S/G blowdowns to desired flow rate.

(Refer to T-14N. BLOWDOWN SYSTEM FLOW CHANGES)

h. Go to Step 12 EOP:

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REV: 15 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW I.

PAGE 11 of 13

11 Establish Stable Plant Conditions:

a. Verify reactor power - LESS THAN 2%
b. Adjust MDAFW pumps flow to restore S/G level to 52%.
c. PRZR pressure - TRENDING TO 2235 PSIG IN AUTO
a. Adjust control rods to CONTROL reactor power BETWEEN 1% AND 2%.
c. Control PRZR pressure by one of the following:
  • 431K in manual

. Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually, THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.

d. PRZR level - TRENDING TO PROGRAM IN AUTO CONTROL
d. Perform the following:
1) Place affected charging pump(s) in MANUAL
2) Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually, THEN refer to AP-RCS.1, REACTOR COOLANT LEAK.

e. Rod insertion limit alarms -

EXTINGUISHED

f. Tavg - STABLE AT APPROXIMATELY 547°F
e. IF the reactor is to remain critical. THEN borate and withdraw control rods to clear insertion limit alarms (refer to affected rod bank alarm response procedures if necessary).
f. Verify proper operation of steam dump OR manually control steam dump as necessary.

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12 Evaluate MCB Annunciator Status (Refer to AR procedures) 13 Check If PRZR Boron Should Be Mixed

a. Boration performed for load
a. Go to Step 14.

reduction

b. Place PRZR backup heaters switch to ON NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

14 Notify Higher Supervision 15 Return To Procedure Or Guidance In Effect

-END-EOP:

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REV: 15 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 13 of 13

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE AGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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REV: 14 NP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 2 of 11 A.

PURPOSE -

This procedure provides the actions necessary to mitigate the consequences of abnormal PRZR pressure.

B.

ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS -

This procedure is entered from:

a. Any of several APs, when PRZR pressure can not be controlled.
2.

SYMPTOMS -

The symptoms of ABNORMAL PRZR PRESSURE are;

a. Annunciator F-19, PRZR PORV OUTLET HI TEMP 1450F, lit, or
b. Annunciator F-18, PRZR SAFETY VLV OUTLET HI TEMP 1450F, lit, or
c. Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION, lit, or
d. Annunciator F-1, PRT LIQUID HI TEMP 220 0F, lit, or
e. Annunciator F-9, PRT HI PRESS 5 PSI, lit, or
f. Annunciator F-17, PRT LEVEL 60.8 % 84.5, lit, or
g. Annunciator F-2, PRESSURIZER HI PRESS 2310 PSI, lit, or
h. Annunciator F-10, PRESSURIZER LO PRESS 2205 PSI, lit, or
i. Annunciator F-6, PRESSURIZER HEATER BREAKER TRIP, lit.
j.

Annunciator F-26, PRESSURIZER HI PRESS CHANNEL ALERT 2377 PSI.

NOTE:

o Actual PRZR pressure should be verified by more than 1 indicator.

o Refer to ITS section 3.4.1.

1 Check PRZR Pressure:

o All 4 narrow range channels -

APPROXIMATELY EQUAL o All 4 narrow range channels -

TRENDING TOGETHER 2 Check Reactor Power -

STABLE IF one pressure channel deviates significantly from the other 3.

THEN perform the following:

a. IF the controlling PRZR pressure channel has failed. THEN place controller. 431K. in MANUAL and adjust output to restore PRZR pressure.
b. Refer to ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE.

IF the abnormal PRZR pressure is a result of a power transient. THEN evaluate conditions and go to the appropriate plant procedure.

3 Check PRZR Pressure:

a. Pressure - LESS THAN 2235 PSIG
b. Pressure -

GREATER THAN 2000 PSIG

a. Go to Step 12.
b. IF pressure decreasing uncontrollably. THEN trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

i"EOP:

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REV: 14 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE b

PAGE 3 of 11

LOP:

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REV: 14 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE

-l.

~~~~~~~~~~PAGE 4 of SThe ACTION/EXPECTED RESPONSER 4 Check PRZR Heater Status:

a. PRZR proportional heater breaker

- CLOSED

b. PRZR heater backup group - ON 5 Verify Normal PRZR Spray Valves -

CLOSED a AOV-431A

. AOV-431B

a. Place PRZR proportional heaters switch to TRIP to reset, then place switch to CLOSE and let return to AUTO.
b. IF PRZR pressure less than 2220 psig, THEN energize PRZR backup heaters.

IF PRZR backup heater breaker has tripped. THEN perform the following:

1) Place the breaker switch to OFF to reset breaker.
2) Place the breaker switch to ON to energize heaters.
3) Verify load increase on Bus 16.

Place controllers in MANUAL at 0%

demand.

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

a. Trip the reactor.
b. WHEN all E-0 Immediate Actions done. THEN trip the associated RCP.

. AOV-431A, RCP A

. AOV-431B. RCP B

c. Go to E-0. REACTOR TRIP OR SAFETY INJECTION.

ACTION/EXPECTED

~

~

~

~

NO OBTAINNSE NOTE:

With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode (refer to TR 3.4.3).

6 Check PRZR Pressure Controller, 431K, Demand -

LESS THAN 50%

Place 431K in MANUAL and decrease output to restore PRZR pressure to 2235 psig.

7 Check PRZR PORVs:

a. PORVs - CLOSED
a. Manually close PORVs.

IF any valve can NOT be closed.

THEN manually close the associated block valve.

  • MOV-516 for PCV-430

. MOV-515 for PCV-431C

b. Annunciator F-19, PRZR PORV OUTLET HI TEMP 145°F -

EXTINGUISHED

b. IF PORV leakage is indicated, THEN perform the following:
1) Close PORV block valves one at a time AND check if pressure stabilizes.

a MOV-515 a MOV-516

2) IF a leaking PRZR PORV is identified, THEN open any nonleaking PORV block valve AND go to Step 8.
c. Go to Step 9

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REV: 14 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE

.~~~~~~~

PAGE 6 of 11 STEP _ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Attempt To Reseat Any Leaking PORV:

a. Verify affected PORV block valve

- CLOSED

a. Close the affected PORV block valve.
  • MOV-516 for PCV-430

. MOV-515 for PCV-431C

b. Cycle the leaking PORV open then closed
c. Open affected PORV block valve
d. Verify leakage has stopped
d. IF leakage continues. THEN perform the following:
1) Reclose leaking PORV block valve.
2) Refer to ITS section 3.4.11 and TR 3.4.3 for required actions.
e. Go to Step 11 9 Check PRZR Safety Valves:

o Position indicator - LESS THAN 0.1 INCH o Annunciator F-18, PRZR SAFETY VLV OUTLET HI TEMP 145°F -

EXTINGUISHED IF safety valve leakage indicated.

THEN perform the following:

a. Verify leakage within limits of ITS section 3.4.13.
b. Go to Step 16.

o Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION -

EXTINGUISHED

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REV: 14 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 7 of 11 ACTION/EXPECTED RESPONSE RESPONSE-NOT OBTAINED 10 Check AUX Spray Valve, AOV-296 -

CLOSED Manually close valve.

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

a. Close letdown isolation. AOV-427.
b. Close letdown orifice valves (AOV-200A. AOV-200B and AOV-202).
c. Close letdown isolation. AOV-371.
d. Close charging flow control valve. HCV-142, WHILE adjusting charging pump speed to maintain:

. RCP labyrinth 15 inches and

. PRZR level at seal D/P between 80 inches program

e. Close charging to loop B cold leg, AOV-294.
f. Establish excess letdown.

(Refer to ATT-9.1. ATTACHMENT EXCESS L/D) 11 Check PRZR Pressure Control Restored:

a. Pressure - TRENDING TO 2235 PSIG
a. IF pressure continues to decrease, THEN return to Step 1.
b. Go to Step 16

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RIEV: 14 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE P

8Eo 11

~~~~~~~~~~~~PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 12 Check PRZR Backup Heaters -

OFF Verify PRZR backup heater switch in AUTO, AND ensure proper operation.

NOTE:

With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode.

(Refer to TR 3.4.3) 13 Check PRZR Pressure Controller, 431K, Demand -

INCREASING Place 431K in MANUAL AND adjust output to reduce PRZR pressure to 2235 psig.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED NOTE:

The AT between the REGEN Hx charging outlet and the PRZR shall NOT exceed 320°F.

14 Establish PRZR Spray

a. Check RCPs - BOTH RUNNING
a. Perform the following:
1) Place PRZR spray valve associated with any non-running RCP in MANUAL with demand at 0%.
  • PCV-431A, RCP A
  • PCV-431B. RCP B
2) IF any RCP running, THEN go to Step 14b.
3) IF NO RCP running. AND letdown in service. THEN perform the following as necessary to restore PRZR pressure to 2235 psig:

a) Open AUX spray valve.

AOV-296.

b) Close normal charging valve, AOV-294.

c) Go to Step 15.

b. Check PRZR Spray Valves -
b. Place PRZR spray valve OPENING AS REQUIRED controllers in MANUAL and open as required to restore pressure
  • AOV-431A to 2235 psig.
  • AOV-431B IF PRZR spray valves will not open. AND letdown is in service.

THEN perform the following as necessary to restore PRZR pressure to 2235 psig:

1) Open Aux spray valve. AOV-296.
2) Close normal charging valve.

AOV-294.

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STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 15 Check PRZR Pressure -

TRENDING TO 2235 PSIG IF PRZR pressure continues to increase uncontrollably, THEN trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

16 Check PRT Indications:

a. Level - BETWEEN 61% AND 84%
b. Pressure - APPROXIMATELY 1.5 PSIG AND STABLE
c. Temperature - AT CNMT AMBIENT TEMPERATURE AND STABLE
a. Drain PRT to RCDT using PRT drain valve. AOV-526 until PRT level is between 61% AND 84%.
b. Open PRT vent. AOV-527 until PRT pressure is approximately 1.5 psig.

IF PRT pressure will NOT decrease. THEN open PRT drain valve. AOV-526. to reduce pressure until PRT pressure is approximately 1.5 psig.

c. To feed and bleed the PRT.

perform the following:

1) Start a RMW pump.
2) Verify RMW to CNMT isolation valve, AOV-508, open.
3) Feed and bleed the PRT using PRT fill valve from RMW.

AOV-548. and PRT drain valve.

AOV-526 to reduce PRT temperature to CNMT ambient temperature.

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~~~~~~~~~PAGE 10 of 11

EOP:

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REV: 14 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 11 of 11.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 17 Establish PRZR Pressure Control In Auto:

a. Verify 431K in AUTO
b. Verify PRZR spray valves in AUTO
c. Verify PRZR heaters restored:

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO 18 Evaluate MCB Annunciator Status (Refer to AR Procedures)

a. Place 431K in AUTO, if desired.
b. Place PRZR spray valve in AUTO, if desired.
c. Restore PRZR heaters, if desired.

NOTE:

Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

19 Notify Higher Supervision 20 Notify Reactor Engineer for Transient Monitoring Program

-END-

AP-PRZR.1 APPENDIX LIST TITLE

1)

ATTACHMENT EXCESS L/D (ATT-9. 1)

A.

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REV: 15 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 05 RESPONSIBL NAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A.

PURPOSE -

This procedure provides the instructions necessary to diagnose and to respond to a reactor coolant pump seal malfunction.

B.

ENTRY CONDITIONS/SYMPTOMS

1.

ENTRY CONDITIONS -

This procedure is entered from:

a.

E-3, STEAM GENERATOR TUBE RUPTURE, or

b.

ES-1.1, SI TERMINATION, or

c.

ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, or

d.

ECA-O.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, or

e. ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, or
f. ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, or
g.

ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED, or

h.

ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, or

i.

FR-I.1, RESPONSE TO HIGH PRESSURIZER LEVEL, when RCP seal malfunction is indicated.

2.

SYMPTOMS -

The symptoms of RCP SEAL MALFUNCTION are;

a. Annunciator B-17(18), RCP A(B) No.1 SEAL HI-LO FLOW 5.0 GPM 1.0, lit, or
b.

Annunciator B-9(10), RCP A(B) LABYR SEAL LO DIFF PRESS 15" H20, lit, or

c. Annunciator B-3(4), RCP A(B) STAND PIPE HI LEVEL + 1 FT, lit, or Continued on next page

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REV: 15 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 3 of 11

2. SYMPTOMS (cont)
d. Annunciator B-11(12), RCP A(B) STAND PIPE LO LEVEL -4 FT, lit, or
e. Annunciator B-25(26), RCP A(B) No. 1 SEAL LO DIFF PRESS 220 PSID, lit, or
f. Annunciator B-1(2), RCP A(B) No. 1 SEAL OUT HI TEMP 200°F, lit, or,
g.

Annunciator A-7(15), RCP A(B) CCW RETURN HIGH TEMP OR LOW FLOW, lit.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl CAUTION IF ANY RCP IS SECURED BECAUSE OF A SEAL MALFUNCTION. IT SHOULD NOT BE RESTARTED UNTIL THE CAUSE OF THE MALFUNCTION HAS BEEN DETERMINED AND CORRECTED.

NOTE:

o If a Reactor trip is initiated while performing Step 1. transition to E-0 should occur while completing subsequent actions of the step.

o #2 Seal leak rate is total RCDT leak rate minus any known in-leakage to RCDT from another source.

o Total #1 Seal Flow is defined for each RCP as the sum of indicated

  1. 1 Seal Leakoff Flow and #2 seal leak rate to RCDT (PPCS Point ID L1003, 3.2 gal/% in the normal operating range).

1 Check Total #1 Seal Flow -

IF a #1 Seal Failure is verified by LESS THAN 8.0 GPM FOR EACH RCP a decrease in Labyr Seal Diff Pressure OR increasing Seal Inlet/Outlet temps. THEN perform the following:

a. IF reactor trip breakers closed.

THEN trip the reactor.

b. WHEN all E-O Immediate Actions done, THEN trip the affected RCP(s).
c. Allow 4 minutes for pump coast down. THEN close affected RCP(s) seal disch valve.
  • RCP A. AOV-270A

. RCP B. AOV-270B

d. IF reactor trip was NOT required. THEN perform the following:
1) Initiate SDM verification per 0-3.1.
2)

Go to step 4.

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STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 2 Check RCP Seal Return Valve Alignment:

a. RCP seal return isolation valve, MOV-313 - OPEN
a. Perform the following:
1) Ensure CI reset.
2) Ensure both trains of XY relays for RCP seal return isolation valve. MOV-313.

reset.

3) Open RCP seal return isolation valve, MOV-313.

IF MOV-313 can NOT be opened.

THEN dispatch AO to AUX BLDG with RWST area key to check valve and breaker locally (breaker MCC C position 13J).

b. Verify OPEN RCP seal disch valves -

. RCP A. AOV-270A

. RCP B. AOV-270B

b. Manually open valves.

IF valves can NOT be opened. THEN verify IA aligned to CNMT and go to Step 3.

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REV: 15 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 5 of 11

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

o If a reactor trip is initiated while performing Step 3. transition to E-0 should occur while completing subsequent actions of the step.

o The lower limit of 0.8 GPM limit for total #1 seal flow applies when the RCS is at normal operating pressure.

Refer to FIG-4.0.

FIGURE RCP SEAL LEAKOFF and consult plant staff for guidance if the RCS is at reduced pressure.

3 Check RCP Seal Return Flow:

a. Total #1 Seal Flow - BETWEEN
a. IF #1 Seal Inlet and Outlet 0.8 GPM AND 6.0 GPM FOR EACH RCP temperatures are increasing in an uncontrolled manner, THEN perform the following:
1) IF reactor trip breakers closed, THEN trip the reactor.
2) WHEN all E-0 Immediate Actions done. THEN trip the affected RCP(s).
3) Allow 4 minutes for pump coast down, THEN close affected RCP(s) seal disch valve.

. RCP A. AOV-270A

. RCP B. AOV-270B

4) IF reactor trip was NOT required, THEN initiate SDM verification per 0-3.1.

IF #1 Seal Inlet and Outlet temperatures are NOT increasing in an uncontrolled manner, THEN go to Step 4.

b. Go to Step 5.

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STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 4 Determine RCP Shutdown Requirements:

a. Each RCP Total #1 seal flow -
a. Perform the following while 2 0.8 GPM continuing with this procedure:
1) IF Seal Inlet/Outlet temperatures begin to increase in an uncontrolled manner, THEN return to 1.
2) Prepare for orderly pump shutdown by placing the plant in Hot Shutdown using 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN.

3) IF Total #1 seal flow increases to 0.8 GPM. THEN pump shutdown is NOT required.

Stop the load reduction AND return to Step 1.

4) Secure the affected RCP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b. Each RGP Total # 1 seal flow -
b. Perform the following while 6.0 gpm continuing with this procedure:
1) IF total #1 Seal flow from any RCP greater than 6.0 gpm.

THEN maintain seal injection flow rate of 9.0 GPM or greater to the affected RCP.

2) IF total #1 Seal flow from any RCP exceeds 8.0 GPM OR Seal Inlet/Outlet temperatures begin to increase in an uncontrolled manner'. THEN return to Step 1.
3) Prepare for orderly pump shutdown by placing the plant in Hot Shutdown using 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN.

4) Secure the affected RCP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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NOTE:

ATT-15.1. ATTACHMENT RCP DIAGNOSTICS may be used to aid in diagnosis. I 5 Check RCP Cooling:

o Annunciator A-7, RCP A CCW RETURN HIGH TEMP OR LOW FLOW -

EXTINGUISHED o Annunciatbr A-15. RCP B CCW RETURN HIGH TEMP OR LOW FLOW -

EXTINGUISHED 6 Check RCP #2 Seal Indications:

o Annunciator B-3. RCP A STANDPIPE HI LEVEL +1 FT - EXTINGUISHED o Annunciator B-4. RCP B STANDPIPE HI LEVEL +1 FT - EXTINGUISHED Perform the following:

a. Verify RCP CCW supply and return valves open.

. RCP A. MOV-749A and MOV-759A

. RCP B. MOV-749B and MOV-759B

b. Ensure open CCW outlet valves from RCP thermal barriers.

. RCP A, AOV-754A

. RCP B, AOV-754B IF affected RCP #1 seal leakoff flow decreasing. THEN failure of #2 seal may be indicated.

Check RCP #2 seal leak rate to RCDT (PPCS Point ID L1003, 3.2 gal/% in the normal operating range).

a. IF RCP #2 seal leak rate to RCDT is 1.1 gpm. THEN continue plant operation while closely monitoring RCP seal indications.
b. IF RCP #2 seal leak rate to RCDT is greater than 1.1 gpm, THEN perform the following:
1) Prepare for orderly pump shutdown by placing the plant in Hot Shutdown using 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN.

2) Secure the affected RCP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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_STEP _ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDl a * * * *

  • a * * * * * * * * * * * *
  • a * *
  • CAUTION REDUCING CHARGING FLOW WILL RESULT IN INCREASING REGEN HX OUTLET TEMPERATURE.

a

  • a
  • a
  • a
  • a a
  • 7 Check RCP GREATER WATER Labyrinth Seal D/Ps THAN 15 INCHES OF Perform the following:
a. Ensure open CCW outlet valves from RCP thermal barriers.

. RCP A. AOV-754A

. RCP B. AOV-754B

b. Verify seal injection flow greater than 5 GPM for affected RCP.
c. Adjust HCV-142 to obtain at least 15 inches labyrinth seal

,&P.

d. Dispatch AO to check seal injection filter D/P.
e. Check CCW surge tank level stable.

IF level increasing.

THEN go to AP-CCW.1. LEAKAGE INTO THE COMPONENT COOLING LOOP.

8 Check RCP #3 Seal Indications:

o Annunciator B-li. RCP A STAND PIPE LO LEVEL -4FT - EXTINGUISHED o Annunciator B-12. RCP B STAND PIPE LO LEVEL -4FT - EXTINGUISHED Check CNMT radiation monitors normal.

  • R-11

. R-12 IF RCP standpipe level low and CNMT radiation increasing. THEN # 3 seal leakage increase is probable.

Continue plant operation while closely monitoring RCP seal indications.

EOP:

TITLE:

REV: 15 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 9 of 11

STP ACTION/EXPECTED RESPONSE l[RESPONSE NOT OBTAINEDl NOTE:

In the absence of other seal failure outlet temperature may indicate pump indications, an elevated #1 seal bearing damage.

  • 9 Monitor RCP Seal Conditions:
a. RCP total #1 seal flow for each RCP o Total #1 seal flow - LESS THAN 6.0 GPM o Total #1 seal flow - GREATER THAN 0.8 GPM
b. RCP #1 Seal Leakoff Flow -

WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0. FIGURE RCP SEAL LEAKOFF

c. RCP #1 seal outlet temperatures

- LESS THAN 2150 AND STABLE

d. RCS leakage - NORMAL (Refer to leakage surveillance sheet)
a. IF affected RCP running. THEN return to Step 1. IF NOT, THEN perform the following:
1) Monitor affected RCP (Refer to ATT-15.1, ATTACHMENT RCP DIAGNOSTICS).
2) Consult Plant Staff to determine if cooldown required.
b. Perform the following:

o Ensure seal injection flow exceeds #1 seal leakoff flow.

o Refer to S-2.1. Reactor Coolant Pump Operation.

o Consult plant staff for further instructions.

c. IF pump bearing damage is suspected. THEN notify plant staff and expedite shutdown of the affected RCP.

IF NOT, THEN return to Step 1.

d. Perform the following:
1) Calculate RCS leakrate.
2) Refer to ITS section 3.4.13.

E EOP:

TITLE:

REV: 15 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 10 of 11

STEP ACTION/EXPECTED RESPONSEREPNEOTBAID 10 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

11 Notify Higher Supervision

-END-EOP:

TITLE:

REV: 15 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 11 of 11

IEOP:

TITLE:

. AP-RCP.1 RCP SEAL MALFUNCTION REV: 15 PAGE 1 of 1 AP-RCP.1 APPENDIX LIST TITLE

1)

FIGURE RCP SEAL LEAKOFF

2) ATTACHMENT RCP DIAGNOSTICS (FIG-4.0)

(ATT-15.1)

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER C?3 RESPONSIBL AGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A.

PURPOSE -

This procedure provides the necessary instructions to respond to a service water system leak.

B.

ENTRY CONDITIONS/SYMPTOMS

1.

SYMPTOMS -

The symptoms of SERVICE WATER LEAK are:

a.

Service water header pressure low alarms on computer, or

b.

Sump pump activity increases in containment, the AUX BLDG, or INT BLDG, OR

c. Unexplained increase in the waste hold-up tank, or
d. Visual observation of a SW leak, or
e. Annunciator C-2, CONTAINMENT RECIRC CLRS WATER OUTLET HI TEMP 217°F, lit, or
f. Annunciator C-10, CONTAINMENT RECIRC CLRS WATER OUTLET LO FLOW 1050 GPM, lit, or
g. Annunciator E-31, CONTAINMENT RECIRC FAN CONDENSATE HI-HI LEVEL alarm, exhibits an unexplained increase in frequency, or
h. Annunciator H-6, CCW SERVICE WATER LO FLOW 1000 GPM, lit.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 1 Verify 480V AC Emergency Busses 17 and 18 -

ENERGIZED Ensure associated DIG(s) running and attempt to manually load busses 17 and/or 18 onto the D/G(s) if necessary.

IF neither bus 17 nor bus 18 can be energized. THEN go to ECA-0.0. LOSS OF ALL AC POWER.

IF either bus 17 OR bus 18 is deenergized. THEN refer to AP-ELEC.17/18. LOSS OF SAFEGUARDS BUS 17/18.

EOP:

TITLE:

REV: 18 AP-SW.1 SERVICE WATER LEAK PAGE 3 of 12

ACT ION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Verify At Least One SW Pump Running In Each Loop:

. A or B pump in loop A

  • C or D pump in loop B Perform the following:
a. Manually start SW pumps as necessary (257 kw each).
b. IF adequate cooling can NOT be supplied to a running D/G. THEN perform the following:
1) Trip affected D/G
2) Immediately depress voltage shutdown pushbutton
3) Refer to ER-D/G.2. ALTERNATE COOLING FOR EMERGENCY D/Gs
c. IF no SW pumps can be operated, THEN perform the following:
1) Trip the reactor
2) WHEN all E-O Immediate Actions done. THEN trip BOTH RCPs
3) Close letdown isol, AOV-427
4) Close excess letdown. HCV-123.
5) Go to E-O. REACTOR TRIP OR SAFETY INJECTION
d. IF only one SW pump can be operated..THEN refer to AP-SW.2.

LOSS OF SERVICE WATER.

EOP:

TITLE:

REV: 18 AP-SW.1 SERVICE WATER LEAK PAGE 4 of 12

NOTE:

Abnormally low pressure in either SW loop may indicate that the idle pump check valve is open.

This may be corrected by restarting or isolating the idle pump.

3 Check SW System Status:

a. Check SW loop header pressures:

o Pressure in both loops -

APPROXIMATELY EQUAL o PPCS SW low pressure alarm status - NOT LOW

. PPCS point ID P2160

. PPCS point ID P2161 o Pressure in both loops -

STABLE OR INCREASING

b. Check SW loop header pressures -

GREATER THAN 55 PSIG

a. IF three SW pumps operating and either loop pressure less than 40 psig. THEN trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

IF only two SW pumps operating and either loop pressure less than 45 psig. THEN start one additional SW pump (257 kw each pump).

b. IF either SW loop pressure is less than 55 PSIG with three SW pumps running AND cause can NOT be corrected, THEN initiate a controlled shutdown while continuing with this procedure (Refer to AP-TURB.5, RAPID LOAD REDUCTION).

EOP:

TITLE:

REV: 18 AP-SW.1 SERVICE WATER LEAK PAGE 5 of 12

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED NOTE:

o If SW is lost to any safeguards equipment, the affected component should be declared inoperable and appropriate actions taken as required by ITS. Section 3.

o CNMT sump A level of 10 feet is approximately 6 feet 6 inches below the bottom of the reactor vessel.

4 Check For SW Leakage In CNMT:

a. Check Sump A indication
a. IF the SW leak is NOT in the CNMT. THEN go to Step 6.

o Sump A level -

INCREASING

-OR-o Sump A pump start frequency -

INCREASING (Refer to RCS Daily Leakage Log)

b. Evaluate Sump A conditions:
b. Plant shutdown should be considered, consult plant staff.
1) Verify Leakage within capacity of one Sump A pump (50 gpm)
2) Check Sump A level - LESS THAN 10 FEET
c. Direct RP to establish conditions for CNMT entry

NOTE:

o One Reactor Compartment cooling fan should be running whenever RCS temperature is greater than 135°F.

o CNMT recirc fan condensate collector level indicators may be helpful in identifying a leaking fan cooler.

5 Check CNMT fan indications:

o CNMT recirc fan collector dump frequency - NORMAL (Refer to RCS Daily Leakage Log) o CNMT recirc fan SW flows -

APPROXIMATELY EQUAL (INTER BLDG basement by IBELIP)

Dispatch AO with locked valve key to perform ATT-2.3. ATTACHMENT SW LOADS IN CNMT to determine leak location. WHEN CNMT SW leak location identified. THEN go to Step 9.

o Reactor compartment cooler SW outlet pressures - APPROXIMATELY EQUAL (INTER BLDG SAMPLE HOOD AREA)

  • Cooler A -

PI 2232

  • Cooler B - PI 2141 EOP:

TITLE:

REV: 18 AP-SW.1 SERVICE WATER LEAK il, PAGE 7 of 12

6 Dispatch AO To Screenhouse To Perform The Following:

a. Verify idle SW pump check valve closed o

Idle pump shaft stopped o Idle pump discharge pressure

- ZERO (unisolate and check local pressure indicator)

b. Investigate for SW leak in Screenhouse - NO EXCESSIVE LEAKAGE INDICATED
a. Notify Control Room of any indication of check valve failure.
b. Perform the following:
1) Identify leak location.

IF increase in leakage from underground header indicated.

THEN isolation of header should be considered (Refer to ATT-2.2. ATTACHMENT SW ISOLATION)

2) Notify Control Room of leak location.

NOTE:

Refer to ATT-2.2. ATTACHMENT SW ISOLATION for a list of the major non-safeguards loads supplied by each service water header.

7 Check Indications For Leak Location:

Dispatch AO to the specific area to investigate for leakage.

o AUX BLDG sump pump start frequency - NORMAL (Refer to RCS Daily Leakage Log) o Annunciator L-9. AUX BLDG SUMP HI LEVEL - EXTINGUISHED o Annunciator L-17. INTER BLDG SUMP HI LEVEL - EXTINGUISHED EOP:

TITLE:

REV: 18 AP-SW.1 SERVICE WATER LEAK PAGE 8 of 12

8 Dispatch AO To Locally Investigate For SW Leakage And To Monitor Operating Equipment

. Turbine BLDG

  • SAFW pump room NOTE:

If SW is lost to either D/G, refer to ER-D/G.2, ALTERNATE COOLING FOR EMERGENCY D/Gs. if cooling is required.

9 Evaluate SW Leak Concerns

a. Check SW pump status - AT LEAST THREE PUMPS RUNNING
b. Check SW loop header pressure -

BOTH LOOPS GREATER THAN 45 PSIG

c. Verify leak location - IDENTIFIED
d. Verify plant operating at power
e. Leak isolation at power -

ACCEPTABLE

a. IF either SW header pressure less than 45 psig, THEN start third SW pump.
b. Perform the following:
1) Dispatch AO to split A and B SW headers (refer to ATT-2.5.

ATTACHMENT SPLIT SW HEADERS)

2) IF plant at power. THEN initiate a controlled shutdown (Refer to AP-TURB.5, RAPID LOAD REDUCTION).
3) Go to Step 10.
c. Return to Step 3.
d. Verify SW system conditions appropriate for plant mode (Refer to ITS Section 3.7.8) and go to Step 10.
e. IF plant shutdown required. THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN or AP-TURB.5, RAPID LOAD REDUCTION.

10 Dispatch AO(s) To Locally Isolate SW Leak As Necessary EOP:

TITLE:

REV: 18 AP-SW.1 SERVICE WATER LEAK PAGE 10 of 12

STEP ACTION/EXPECTED RESPONSE RESPONSE-NOT OBTAINED 11 Verify SW Leak Isolated

a. Monitor SW System Operation o SW loop header pressure -

RESTORED TO PRE-EVENT VALUE Archive PPCS point ID loop A P2160 OR loop B P2161)

a. IF SW leak can NOT be isolated within the affected loop. THEN stop SW pumps in the affected loop.

o Both SW loop header pressures

- STABLE

b. Verify At Least One SW Pump Running In Each Loop:

. A or B pump in loop A

. C or D pump in loop B

b. Perform the following:
1) Ensure two SW pumps running (257 kw each).
2) IF adequate cooling can NOT be supplied to a runningD7lc.

THEN perform the following:

a) Trip affected D/G b) Immediately depress voltage shutdown pushbutton c) Refer to ER-D/G.2, ALTERNATE COOLING FOR EMERGENCY D/Gs.

3) IF no SW pumps can be operated, THEN perform the following:

a) Trip the reactor b) WHEN all E-0 Immediate Actions done, THEN trip BOTH RCPs c) Close letdown isol. AOV-427 d) Go to E-0. REACTOR TRIP OR SAFETY INJECTION

4) IF only one SW pump can be operated, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
c. Restore to normal position all valves repositioned during leak investigation-EXCEPT leak isolation boundary.

EOP:

TITLE:

REV: 18 AP-SW.1 SERVICE WATER LEAK PAGE 11 of 12

ACTION/EXPECTED RESPONSEREPNEOTBAID 12 Evaluate MCB Annunciator Status (Refer to AR procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

13 Notify Higher Supervision

-END-I EOP:

TITLE:

REV: 18 AP-SW.1 SERVICE WATER LEAK PAGE 12 of 12

EOP:

TITLE:

REV: 1 8 AP-SW.1 SERVICE WATER LEAK PAGE 1 of 1 AP-SW.1 APPENDIX LIST TITLE

1)

ATTACHMENT SW ISOLATION

2)

ATTACHMENT SW LOADS IN CNMT

3)

ATTACHMENT SPLIT SW HEADERS (ATT-2.2)

(ATT-2.3)

(ATT-2.5)

EOP:

TITLE:

REV: 3 AP-SW.2 LOSS OF SERVICE WATER PAGE 1 of 8 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER O

RESPONSIBL MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP:

TITLE:

REV: 3 AP-SW.2 LOSS OF SERVICE WATER PAGE 2 of 8 A.

PURPOSE -

This procedure provides the necessary instructions to respond to a loss of service water pumps.

B.

ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS -

This procedure is entered from:

a. AP-ELEC.17/18, LOSS OF SAFEGUARDS BUS 17/18.
b. Any of several EOPs, when only one SW pump can be operated.
2.

SYMPTOMS -

The symptoms of LOSS OF SERVICE WATER PUMPS are:

a.

Service water header pressure low alarms on computer, or

b. Annunciator C-2, CONTAINMENT RECIRC CLRS WATER OUTLET HI TEMP 217 0F, lit, or
c. Annunciator C-10, CONTAINMENT RECIRC CLRS WATER OUTLET LO FLOW 1050 GPM, lit, or
d. Annunciator H-6, CCW SERVICE WATER LOW FLOW 1000 GPM, lit, or
e. Annunciator H-9, AUXILIARY FEED PUMP CLG WTR FLTR HI DIFF PRESS, lit, or
f. Annunciator I-10, CW PUMP SEAL WATER LO FLOW, lit, or
g. Annunciator J-4, GENERATOR ISOPHASE BUS COOLING SYSTEM, lit, or
h. Annunciator J-9, SAFEGUARD BREAKER TRIP, lit, or
i. Annunciator K-30, TURBINE PLANT SAMPLING RACK TROUBLE, lit.

STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINED 1 Verify 480V AC Emergency Busses 17 and 18 -

ENERGIZED Ensure associated DIG(s) running and attempt to manually load busses 17 and/or 18 onto their respective D/G(s).

IF neither bus 17 nor bus 18 can be-energized, THEN go to ECA-O.O, LOSS OF ALL AC POWER.

EOP:

TITLE:

I REV: 3 AP-SW.2 LOSS OF SERVICE WATER PAGE 3 of 8

STEP ACTION/EXPECTED RESPONSE RESPONSE-NOT OBTAINED

  • 2 Verify SW Pump Alignment:
a. Check at least one SW pump running in each loop

. A or B pump in loop A

. C or D pump in loop B

a. Perform the following:
1) Manually start SW pumps as necessary (257 kw each).
2) IF adequate cooling can NOT be supplied to a running D/G, THEN perform the following:

a) Trip affected D/G b) Immediately depress voltage shutdown pushbutton

3) IF no SW pumps can be operated, THEN perform the following:

a) Trip the reactor b) WHEN all E-O Immediate Actions done, THEN trip BOTH RCPs c) Close letdown isol, AOV-427 d) Close excess letdown.

HCV-123 e) Go to E-0. REACTOR TRIP OR SAFETY INJECTION

4) IF only one SW pump can be operated. THEN go to step 3.
5) IF at least two SW pumps can be operated. THEN go to step 8.
b. Return to procedure or guidance in effect EOP:

TITLE:

REV: 3 AP-SW.2 LOSS OF SERVICE WATER PAGE 4 of 8

STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 3 Align Alternate Cooling To One D/G (Refer to ER-D/G.2, ALTERNATE COOLING EMERGENCY D/Gs):

o IF A or C SW Pump is operating.

THEN align alternate cooling to D/G B

-OR-o IF B or D SW Pump is operating.

THEN align alternate cooling to D/G A 4 Isolate SW To Non-Essential Loads

a. Close screenhouse SW isolation valves
  • MOV-4609
  • MOV-4780
b. Close air conditioning SW isolation valves

. MOV-4663

. MOV-4733

c. Direct AO to perform Part C of ATT-2.2. ATTACHMENT SW ISOLATION

. EOP:

TITLE:

REV: 3 AP-SW.2 LOSS OF SERVICE WATER PAGE 5 of 8

STEP ACTION/EXPECTED RESPONSE RESPONSE_NOT OBTAINED 5 Monitor Plant Equipment Cooled By SW -

TEMPERATURES STABLE

. Exciter

. MFP oil coolers

. Instrument air compressors

. Bus duct coolers

. Seal Oil unit

. Turbine lube oil cooler

. CCW Hx

. SFP Hx

. AFPs

. Condensate Pumps

. Secondary sample coolers IF required. THEN reduce load as necessary to stabilize equipment temperatures (Refer to 0-5.1. LOAD REDUCTIONS, or AP-TURB.5. RAPID LOAD REDUCTION) 6 Notify Higher Supervision EOP:

TITLE:

REV:

3 AP-SW.2 LOSS OF SERVICE WATER PAGE 6 of 8

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check SW System Status:

a. Check SW loop header pressures:

o PPCS SW low pressure alarm status - NOT LOW

a. Locally isolate selected SW loads as desired (Refer to ATT-2.2. ATTACHMENT SW ISOLATION)

. PPCS point ID P2160

  • PPCS point ID P2161 o Pressure in both loops -

STABLE OR INCREASING o Check SW loop header pressures - GREATER THAN 40 PSIG

b. Check at least one SW pump running in each loop:

. A or B pump in loop A

. C or D pump in loop B

b. Perform the following:
1) Continue efforts to start at least one SW pump in each loop.
2) IF at least two SW pumps can be operated, THEN go to Step 8. IF NOT, THEN return to step 3.

8 Notify Higher Supervision 9 Select Operable SW Pumps For Auto Start Refer to ITS LCO 3.7.8 EOP:

TITLE:

REV: 3 AP-SW.2 LOSS OF SERVICE WATER PAGE 7 of 8

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 10 Evaluate MCB Annunciator Status (Refer to AR Procedures) 11 Return To Procedure or Guidance In Effect

-END-EOP:

TITLE:

REV: 3 AP-SW.2 LOSS OF SERVICE WATER

'Z,:.

PAGE 8 of 8

EOP:

TITLE:

REV: 3 AP-SW.2 LOSS OF SERVICE WATER PAGE 1 of 1 AP-SW.2 APPENDIX LIST TITLE

1)

ATTACHMENT SW ISOLATION (ATT-2.2)

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE AGER 5-g-,a 662 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A.

PURPOSE -

This procedure provides the necessary instructions to control the plant following a turbine trip without a reactor trip required.

B.

ENTRY CONDITIONS/SYMPTOMS

1.

ENTRY CONDITIONS -

This procedure is entered from:

a. AP-CW.1, LOSS OF A CIRC WATER PUMP, or,
b. AP-ELEC.1, LOSS OF 12A AND/OR 12B BUSSES, or,
c. AP-FW.1, ABNORMAL FEED FLOW, or,
d. AP-TURB.2, TURBINE LOAD REJECTION, or,
e. AP-TURB.3, TURBINE VIBRATION, or,
f. AP-TURB.4, LOSS OF CONDENSER VACUUM, when power is less than P-9 and the turbine trips without a Rx trip.
2.

SYMPTOMS -

The symptoms of TURBINE TRIP WITHOUT RX TRIP REQUIRED are:

a. Annunciator K-1, THRUST BEARING FAILURE, lit, or
b. Annunciator K-9, TURBINE BEARING OIL LO PRESS TRIP 6 psi, lit, or
c. Annunciator K-17, TURBINE LOW VACUUM TRIP 20" HG, lit, or
d. Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit, or
e. Annunciator K-26, GENERATOR LOCKOUT RELAY, lit, or
f. Annunciator K-25, TURBINE OVERSPEED ALERT 1980 RPM, lit, or
g. Annunciator F-21, COND HI PRESS 20" HG OR LOSS OF BOTH CIRC WTR PMPS, lit, or
h. Annunciator K-3, AMSAC ACTUATED, lit.
i. Annunciator K-10, TURBINE HIGH VIBRATION TRIP.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 1 Verify Turbine Stop Valves -

CLOSED Manually trip turbine.

IF turbine stop valves can NOT be closed. THEN perform the following:

a. Trip the reactor
b. WHEN all E-O Immediate Actions done, THEN ensure both MSIVs closed
c. Go to E-0. REACTOR TRIP OR SAFETY INJECTION NOTE: o Automatic rod control is desired, if available.

o Transition to E-0 is NOT required opened in the following step.

if the reactor trip breakers are 2 Check Reactor Power:

a. NIS power ranges - ABOVE 1%
a. Perform the following:
1) IF the reactor is subcritical, THEN shut down the reactor using manual trip pushbutton.
2) Go to Step 3.
b. Verify control rods driving in to reduce reactor power in AUTO
b. Perform the following:
1) Place rods in MANUAL
2) Adjust rods to control reactor power between 1% and 2%.
c. Borate to maintain control rods above rod insertion limits

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED

  • 3 Monitor MFW Regulating Valves RESTORING S/G LEVEL TO 52%

IN AUTO Perform the following:

a. Place affected S/G(s) MFW regulating valve in MANUAL
b. Restore S/G level to 52%

IF S/G level can NOT be controlled manually, THEN refer to AP-FW.1, ABNORMAL MAIN FEEDWATER FLOW.

4 Verify Proper Operation Of Steam Dump:

a. Verify annunciator G-15. STEAM DUMP ARMED - LIT
b. Condenser steam dump operating in AUTO
c. Check RCS Tavg:
  • Tavg - GREATER THAN 545°F

. Tavg - LESS THAN 566°f

a. Place steam dump mode selector switch to MANUAL.
b. IF steam dump NOT available, THEN perform the following:
1) Adjust S/G ARV setpoints to 1005 psig and verify ARV operating to control Tavg to approximately 5470F.
2) IF power is greater than 8%.

THEN ensure reactor trip and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

c. Verify control rods responding in AUTO.

IF NOT. THEN place rods to MANUAL and adjust control rods to restore Tavg within limits.

IF Tavg is outside limits and can NOT be controlled. THEN trip the reactor and go to E-0.

REACTOR TRIP OR SAFETY INJECTION.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED NOTE:

With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode.

(Refer to TR 3.4.3) 5 Check PRZR Pressure -

Control PRZR pressure by one of the TRENDING TO 2235 PSIG IN AUTO following:

  • 431K in MANUAL

. Manual control of heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.

STEP ACTION/EXPECTED RESPONSE 1

1 RESPONSE NOT OBTAINED 6 Check PRZR Level:

a. Level - GREATER THAN 13%
a. Perform the following:
1) Place letdown isolation.valve AOV-427 switch to CLOSE.
2) Place letdown orifice valve switches to CLOSE (AOV-200A, AOV-200B. and AOV-202).
3) Close excess letdown isolation valve. AOV-310.
4) Ensure PRZR heaters off.
5) Close letdown isolation AOV-371 WHILE adjusting charging pump speed to maintain:

o RCP labyrinth seal D/P between 15 inches and 80 inches o PRZR level at program

6) WHEN PRZR level greater than 13%. THEN restore letdown.

(Refer to ATT-9.0. ATTACHMENT LETDOWN)

b. Level - TRENDING TO PROGRAM IN AUTO CONTROL
b. Perform the following:
1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually, THEN refer to AP-RCS.1..REACTOR.COOLANT LEAK.

EOP:

TITLE:

REV: 12 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 6 of 12

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check MFW System:

a. MFW pumps - BOTH RUNNING
a. Perform the following:
1) Verify one MFW pump running.

IF NOT. THEN establish sufficient AFW flow to maintain S/G levels

. MDAFW pump(s)

. TDAFW pump

2) Go to Step 8.
b. Close one MFW pump discharge valve
c. Stop selected MFW pump

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED

  • * * * *
  • a
  • *
  • a * * * * *
  • CAUTION IF AT ANY TIME IT IS SUSPECTED THAT THE REACTOR IS SUBCRITICAL, THEN MANUALLY TRIP THE REACTOR.
  • a * * *
  • NOTE: o With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode.

(Refer to TR 3.4.3) o Transition to E-0 is NOT required if the reactor trip breakers are opened in the following step.

8 Establish Stable Plant Conditions:

a. NIS power ranges - LESS THAN 2%
a. Return to Step 2.
b. Place rods in MANUAL
c. Check reactor power -

GREATER THAN 1%

c. IF the reactor is subcritical.

THEN perform the following:

1) Shut down the reactor using manual trip pushbutton.
2) Go to Step 8e.
d. Maintain reactor power between 1% and 2%
e. PRZR pressure - BETWEEN 2220 PSIG AND 2260 PSIG
f. RCS Tavg - GREATER THAN 545°F
e. Control PRZR pressure between 2220 psig and 2260 psig by one of the following:

. 431K in AUTO

. 431K in MANUAL

  • Manual control of heaters and spray
f. Control dumping steam to control Tavg.

IF cooldown continues.

THEN close both MSIVs.

IF MSIVs closed AND Tavg still decreasing, THEN trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED CAUTION IF ANY S/G LEVEL ABOVE 52%. THEN AFW FLOW MAY BE THROTTLED IMMEDIATELY TO PREVENT S/G ISOLATION.

  • * * * * * *
  • a * * * * * * * * * * * * * *
  • NOTE: Maintaining reactor power less than 2% is within the capacity of MDAFW pumps.

9 Check S/G Feed Flow Status:

a. Manually start both MDAFW pumps
b. Verify AFW flow - SUFFICIENT
b. Perform the following:

FLOW TO MAINTAIN S/G LEVELS

1) Establish MFW flow using MFW regulating valve bypass valves.

IF MFW NOT available, THEN manually start TDAFW pump and establish flow.

2) Adjust feed flow to restore S/G level to 52%.
3) Go to Step 10.
c. Verify MFW flow control valves -
c. Place A and B MFW regulating and CLOSED bypass valve controllers in manual at 0% demand.

. MFW regulating valves

. MFW bypass valves

d. Close MFW pump discharge valves

. MOV-3977. A MFW pump

. MOV-3976, B MFW pump

e. Stop any running MFW pump and place in PULL STOP
f. Place A and B MFW regulating and bypass valve controllers in manual at 0% demand.
g. Adjust AFW pump flow to restore S/G level to 52%.

10 Establish Normal AFW Pump Shutdown Alignment:

a. Place AFW bypass switches to DEF
b. Verify the following:

o Both S/G levels - STABLE OR INCREASING

b. Continue with Step 11.

WHEN conditions met, THEN do Steps 10c through d.

o Total AFW flow - LESS THAN 200 GPM

c. Close MDAFW pump discharge valves

. MOV-4007 a MOV-4008

d. Adjust AFW bypass valves to control S/G levels at 52%

. AOV-4480

  • AOV-4481

STEP ACTION/EXPECTED RESPONSE

[RESPONSE NOT OBTAINEDl 11 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE
b. Perform the following:

o Open generator disconnects

. 1G13A71

. 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump (Refer to T-5F.

STARTING OR STOPPING THE CONDENSATE PUMPS)

c. Verify Bus 11A and Bus lB energized - BOTH BUSSES GREATER THAN 4 KV
a. Dispatch AO to perform ATT-17.1, ATTACHMENT SD-2.
c. IF either bus NOT energized.

THEN refer to 0-6.9.2.

ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/

BUS 12B.

d. Dispatch AO to perform ATT-17.0.

ATTACHMENT SD-1

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Establish Control Systems In Auto:

a. Verify 431K in AUTO
b. Verify PRZR spray valves in AUTO
c. Verify one charging pump in AUTO
d. Verify PRZR heaters restored:
a. Place 431K in AUTO, if desired.
b. Place PRZR spray valves in AUTO.

if desired.

c. Place one charging pump in AUTO.

if desired.

d. Restore PRZR heaters, if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET, IN AUTO 13 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE:

Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

14 Notify Higher Supervision 15 Establish Desired Plant Conditions:

a. Reactor shutdown - DESIRED
a. IF turbine is to be restored to service, THEN maintain reactor critical and refer to 0-1.2.

PLANT STARTUP FROM HOT SHUTDOWN TO FULL LOAD.

b. Refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN

-END-

AP-TURB.1 APPENDIX LIST TITLE

1) ATTACHMENT SD-1 (ATT-17.0)
2) ATTACHMENT SD-2 (ATT-17.1)
3) ATTACHMENT LETDOWN (ATT-9.0)