Text

R. E. Ginna - Transmittal of Emergency Operating Procedures
	ML041260403
Person / Time
Site:	Ginna
Issue date:	04/20/2004
From:	Widay J; Rochester Gas & Electric Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	F-0.2, Rev 5, FR-C.2, Rev 18
	Download: ML041260403 (22)
	v • d • e

Always at Your Service Joseph A. Widay Vice President and Plant Manager April 20, 2004 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, seph A. Widay 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):

F Index FR Index F-0.2, Rev 5 FR-C.2, Rev 18 An equal opportunity employer 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com A, c) 0 2-,

An Energy East Company

NPSP0200 WRIGHTJ

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(I Tue 4/20/2004 1:03:29 pm Page 1 of I Ginna Nuclear Power Plant PROCEDURE INDEX INPUT PARAMETERS: TYPE:

PRF STATUS VALUE(S):

EF, QU 5 YEARS ONLY:

=.

PRF CRITICAL SAFETY FUNCTION STATUS PROC PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST F-0.1 SUBCRITICALITY CSFST 001 07/21/1989 02/25/2004 02/25/2009 EF F-0.2 CORE COOUNG CSFST 005 04/20/2004 04/20/2004 04/20/2009 EF F-0.3 HEAT SINK CSFST 003 06103/1996 02/25/2004 02/25/2009 EF F-0.4 INTEGRITY CSFST 002 03/31/2000 02/25/2004 02/25/2009 EF F-0.5 CONTAINMENTCSFST 002 01/12/1990 02/25/2004 02/25/2009 EF F-0.6 INVENTORYCSFST 004 05/01/1998 03/27/2003 03/27/2008 EF PRF TOTAL' 6

GRAND TOTAL' 6

(7 NPSP0200 WRIGHTJ

(

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Tue 4/20/2004 1:03:48 pm Page 1 of I Ginna Nuclear Power Plant PROCEDURE INDEX INPUT PARAMETERS: TYPE:

PRFR STATUS VALUE(S):

EF, OU 5 YEARS ONLY:

PRFR FUNCTIONAL RESTORATION GUIDELINE PROC PROCEDURE NUMBER FR-C.1 FR-C.2 FR-C.3 FR-H.1 FR-H.2 FR-H.3 FR-H.4 FR-H.5 FR-1.1 FR-1.2 FR-1.3 FR-P.1 FR-P.2 FR-S.1 FR-S.2 FR-Z.1 FR-Z.2 FR-Z.3 PROCEDURE TITLE RESPONSE TO INADEGUATE CORE COOLING RESPONSE TO DEGRADED CORE COOLING RESPONSE TO SATURATED CORE COOLING RESPONSE TO LOSS OF SECONDARY HEAT SINK RESPONSE TO STEAM GENERATOR OVERPRESSURE RESPONSE TO STEAM GENERATOR HIGH LEVEL RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILIES RESPONSE TO STEAM GENERATOR LOW LEVEL RESPONSE TO HIGH PRESSURIZER LEVEL RESPONSE TO LOW PRESSURIZER LEVEL RESPONSE TO VOIDS IN REACTOR VESSEL RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDMON RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDmON RESPONSE TO REACTOR RESTART/ATWS RESPONSE TO LOSS OF CORE SHI¶JDOWN RESPONSE TO HIGH CONTAINMENT PRESSURE RESPONSE TO CONTAINMENT FLOODING RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL EFFECT LAST REV DATE REVIEW 020 05/30/2003 03/24/2003 018 04/20/2004 03124/2003 009 05/30/2003 03/24/2003 030 10/10/2003 03/24/2003 006 10/10/2003 03/2412003 007 10/10/2003 03/24/2003 005 05/30/2003 03/24/2003 009 05/30/2003 03/24/2003 017 01/07/2004 03124/2003 011 05/30/2003 0312412003 019 01/07/2004 03/24/2003 028 01/07/2004 03/24/2003 008 05/30/2003 03/24/2003 016 10/10/2003 03/24/2003 009 05/30/2003 03/2412003 008 10/10/2003 03/24/2003 005 05/30/2003 03/24/2003 005 05/30/2003 03/24/2003 NEXT REVIEW 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03124/2008 03/24/2008 03/24/2008 03/24/2008 ST EF EF EF EF EF EF EF EF EF EF EF EF EF EF-EF' EF EF EF PRFR TOTAL 18 GRAND TOTAL:

18

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TITLE:

REV: 5 F-0.2 CORE COOLING PAGE 1 of 2 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER IoXtn RESPONSIBL j4ANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

GO TO FR-C.1 RVLIS LEVEL GREATER THAN 520/1

[55% adverse CNMT]

E (i)

GGO TO Lo

-=I &

FR-C.2 CORE EXIT TC's LESS THAN 700'F O

GOTO r

FR-C.2 CORE EXIT TC's LESS THAN 1200@F RVLIS LEVEL GREATER THAN 520

[55% adverse CNMT]

0 GO TO a Boost FR-C.3

?

GOTO IfFR-C.2 RCS SUBCOOLING BASED ON CORE EXIT TC'S NO GREATER THAN REQUIREMENTS OF YES FIGURE MIN SUBCOOLING GO TO

*Coe l FR-C.3

FIGURE MIN SUBCOOLING NOTE:

Subcooling Margin =Saturation Temperature From Figure Below []Core Exit T/C Indication RCS PRESSURE (PSIG) 2300 -

RCS PRESSURE l

-t jl IIl !!II II ii II I IIl T I!I II

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CORE EXIT SATURATION TEMPERATURE (OF)

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TITLE:

FR-C.2 RESPONSE TO DEGRADED CORE COOLING

~~

I REV:

I 8 PAGE 1 of 14 I

I ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 4 3 RESPONSIBLE? ANAGER

-F2ECIV-DATE EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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TITLE:

FR-C.2

.~

I RESPONSE TO DEGRADED CORE COOLING REV: 18 PAGE 2 of 14 I.

A. PURPOSE -

This procedure provides actions to restore adequate core cooling.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS -

This procedure is entered from:

a. F-0.2, CORE COOLING Critical Safety Function Status Tree, on any ORANGE condition.

I EOP:

TITLE:

REV: 1 8 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 3 of 14

_ SEP _

.ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

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

o Normal conditions for running RCPs are desired. but RCPs should NOT be tripped if normal conditions cannot be established or maintained.

o Foldout Page should be open and monitored periodically.

1 Monitor RWST Level -

GREATER THAN 28%

Perform the following:

a. Ensure SI system aligned for cold leg recirculation using Steps 1 through 13 of ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

b. Go to Step 4.

2 Verify SI Pump Suction Aligned To RWST:

a. SI pump suction valves from RWST

- OPEN

a. Ensure at least one SI pump suction valve from RWST open

MOV-825A

MOV-825B

MOV-825A

MOV-825B

[

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TITLE:

.REV:

18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 4 of 14 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 3 Verify SI Pump And RHR Pump Emergency Alignment:

a. RHR pump discharge to Rx vessel deluge - OPEN

MOV-852A

MOV-852B

b. Verify SI pump C - RUNNING

c. Verify SI pump A - RUNNING

d. Verify SI pump B - RUNNING

e. Verify both SI pump C discharge valves - OPEN

MOV-871A

MOV-871B

a. Ensure at least one valve open.

b. Manually start pump on available bus.

c. Perform the following:

1) Ensure SI pumps B and C running.

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

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

3) Go to Step 4.

d. Perform the following:

1) Ensure SI pumps A and C running.

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

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

3) Go to Step 4.

e. Manually open valves as necessary.

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REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 5 of 14 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 4 Verify SI Flow In Both Trains:

a. SI line loop A and B flow indicators - CHECK FOR FLOW

a. Perform the following:

1) Manually start SI pumps and align valves as necessary.

2) Establish maximum charging flow.

b. RCS pressure - LESS THAN 250 psig [465 psig adverse CNMT]

b. Go to Step 5.

c. RHR loop flow FOR FLOW indicator - CHECK

c. Manually start RHR pumps and align valves.

I>

.EOP:

TITLE:

FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 6 of 14 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED

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

ah a c a a*S ae n t a a a

a a

a a a a

a 5 Check RCS Vent Paths:

a. Power to PRZR PORV block valves

- AVAILABLE

a. Restore power to block valves unless block valve was closed to isolate an open PORV:

MOV-515. MCC D position 6C

MOV-516. MCC C position 6C

b. PORVs - CLOSED

b. IF PRZR pressure less than 2335 psig. THEN manually close PORVs.

IF any PORV can NOT be closed.

THEN manually close its block valve.

c. Block valves - AT LEAST ONE OPEN

c. Open one block valve unless it was closed to isolate an open PORV.

d. Rx vessef head CLOSED vent valves -

d. Manually close valves.

SOV-590

SOV-591

SOV-592

SOV-593

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TITLE:.

l E

l TIE:

lREV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 7 of 14 ACTION/EXPECTED RESPONSENOT OB NE 6 Check RCP Status:

a. At least one RCP - RUNNING

b. Support conditions for the operating RCP(s) available (Refer to ATT-15.0. ATTACHMENT RCP START)

a. Go to Step 9.

b. Try to establish support conditions for the operating RCP.

7 Check RVLIS Fluid Fraction

a. Fluid fraction (any RCP on) -

GREATER THAN 66%

a. IF increasing. THEN return to I

Step 1.

IF NOT, then go to Step 8.

b. Return to procedure and step in effect.

8 Check If One RCP Should Be -

Stopped:

a. Both RCPs - RUNNING

b. Stop one RCP

c. Go to Step 10 9 Check Core Cooling:

a. Go to Step 10.

a. RVLIS level (no RCPs) - GREATER THAN 52% [55% adverse CNMT]

b. Core exit T/Cs - LESS THAN 7000 F

a. IF increasing. THEN return to Step 1. IF NOT. THEN go to Step 10.

b. IF decreasing. THEN return to Step 1. IF NOT. THEN go to Step 10.

c. Return to procedure and step in effect

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TITLE:

REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 8 of 14 STEP ACTION/EXPECTED RESPONSE HRESPONSE NOT OBTAINED 10 Check SI ACCUM Valves -

OPEN Discharge IF SI ACCUM discharge valves closed after ACCUM discharge. THEN go to Step 11.

IF NOT, THEN perform the following:

MOV-841

MOV-865

a. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves.

MOV-841. MCC C position 12F

MOV-865, MCC D position 12C

b. Open SI ACCUM discharge valves.

ACCUM A. MOV-841

ACCUM B. MOV-865 a

a

a

a

a

a

a a

a CAUTION o IF CST LEVEL DECREASES TO LESS THAN 5 FEET. THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

o A FAULTED OR RUPTURED S/G SHOULD NOT BE USED IN SUBSEQUENT STEPS UNLESS NO INTACT S/G IS AVAILABLE.

NOTE:

TDAFW pumip flow control AOVs may drift open on loss of IA.

11 Monitor Intact S/G Levels:

a. Narrow range level - GREATER THAN 5% [25% adverse CNMT]

a. Increase total feed flow to restore narrow range level greater than 5% [25% adverse CNMT] in at least one SIG.

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

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TITLE:

REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 9 of 14 ACTION/EXPECTED RESPONSEBTAI 12 Establish Condenser Steam Dump Manual Control

a. Verify condenser available:

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

b. Place steam dump mode selector switch in MANUAL

c. Place steam dump controller in MANUAL

a. Place intact S/G ARV controller in MANUAL and go to Step 13.

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TITLE:

REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 10 of 14 SP ACTION/EXPECTED RESPONSE l

lRESPONSE NOT OBTAINED 4

4 4

4 CAUTION THE FOLLOWING STEP WILL CAUSE SI ACCUMULATOR INJECTION WHICH MAY RESULT IN A RED PATH CONDITION IN F-0.4. INTEGRITY STATUS TREE.

THIS PROCEDURE SHOULD BE COMPLETED BEFORE TRANSITION TO FR-P.l. RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK.

4 4

4 13 Depressurize All Intact S/Gs To 200 PSIG:

a. Maintain cooldown rate in RCS cold legs - LESS THAN 100OF/HR

b. Dump steam to condenser

b. Manually or locally dump steam from intact S/Gs:

o Use S/G ARVs.

-OR-o Open TDAFW pump steam suppl valve(s) for affected S/G(s):

S/G A. MOV-3505A

S/G B. MOV-3504A

-OR-o Locally perform the following:

o Open intact S/G MSIV bypass valve.

o Open priming air ejector steam isolation valves.

V-3580

V-3581

c. Check S/G 200 PSIG pressures - LESS THAN

c. Return to Step 11.

d. Check RCS hot leg temperatures -

BOTH LESS THAN 4000F

d. Return to Step 11.

e. Stop S/G depressurization

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TITLE:

REV 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 11 of 14 STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4

X e

CAUTION RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS.

14 Check R U N NI Mna 44

tart pumps a s n

14 Check RHR Pumps RUNNING Manually start pumps as necessary.

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REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 12 of 14 SP RESPONSE NOT OBTAINED e 15 Isolate Both SI ACCUMs

a. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves if necessary

MOV-841, MCC

MOV-865. MCC C position 12F D position 12C

b. Reset SI

c. Close SI ACCUM discharge valves

MOV-841

MOV-865

c. Perform the following to vent an unisolated accumulator:

1) Reset CI

2) Ensure adequate air compressor(s) running

3) Establish IA to CNMT

4) Open vent valves for unisolated SI ACCUMs.

ACCUM A. AOV-834A

ACCUM B. AOV-834B

5) Open HCV-945.

IF an accumulator can NOT be isolated or vented. THEN consult TSC to determine contingency actions.

d. Locally reopen breakers for MOV-841 and MOV-865

'1 EOP:

TITLE:

REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 13 of 14 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED a

a a

a CAUTION SYMPTOMS FOR FR-C.1. RESPONSE TO INADEQUATE CORE COOLING. SHOULD BE CLOSELY MONITORED DURING SUBSEQUENT STEPS.

a a

a 16 Stop All RCPs 17 Depressurize All Intact S/Gs To Atmospheric Pressure:

a. Maintain cooldown rate in RCS cold legs -

LESS THAN 1000F/HR

b. Dump steam to condenser

b. Manually or locally dump steam from intact S/Gs:-

1) Use S/G ARVs.

2) Open TDAFW pump steam supply valve(s) for affected S/G(s):

S/G A. MOV-3505A

S/G B. MOV-3504A

3) Locally perform the following:

o Open intact S/G MSIV bypass valve.

o Open priming air ejector steam isolation valves.

V-3580

V-3581

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TITLE:

REV: 18 i

FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 14 of 14 SP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED I 18 Verify SI Flow:

o SI line loop A and B flow indicators - CHECK FOR FLOW

-OR-o RHR loop flow indicator - CHECK FOR FLOW Perform the following:

a. Continue efforts to establish SI or RHR flow.

b. Try to establish maximum charging flow.

c. Return to Step 17.

19 Check Core Cooling:

Return to Step 17.

o RVLIS level (no RCPs) - GREATER THAN 77% [82% adverse CNMT]

o Both RCS hot leg temperatures -

LESS THAN 320 0F 20 Go to Appropriate Plant Procedure

a. Check RWST level - GREATER THAN 28%

a. Go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION. Step 1.

b. Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT. Step 17

-END-

Eop:

TITLE:RE

1 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 1 of 1 FR-C.2 APPENDIX LIST TITLE

1) ATTACHMENT RCP START (ATT-15.0)

2) ATTACHMENT NO SW PUMPS (ATT-2.4)

3)

FOLDOUT

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TITLE:

REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 1 of 1 FOLDOUT PAGE NOTE:

This Foldout Page applies to all FR-C series procedures.

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

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

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

ML041260403

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