ML041260403
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) | |
Text
Joseph A. Widay Vice President Always at Your Service 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 A,c) 0 2-,
tel (585) 546-2700 www.rge.com An Energy East Company
( (I NPSP0200 Ginna Nuclear Power Plant Tue 4/20/2004 1:03:29 pm WRIGHTJ PROCEDURE INDEX Page 1 of I 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 Ginna Nuclear Power Plant Tue 4/20/2004 1:03:48 pm WRIGHTJ PROCEDURE INDEX Page 1 of I INPUT PARAMETERS: TYPE: PRFR STATUS VALUE(S): EF, OU 5 YEARS ONLY:
PRFR FUNCTIONAL RESTORATION GUIDELINE PROC PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST FR-C.1 RESPONSE TO INADEGUATE CORE COOLING 020 05/30/2003 03/24/2003 03/24/2008 EF FR-C.2 RESPONSE TO DEGRADED CORE COOLING 018 04/20/2004 03124/2003 03/24/2008 EF FR-C.3 RESPONSE TO SATURATED CORE COOLING 009 05/30/2003 03/24/2003 03/24/2008 EF FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK 030 10/10/2003 03/24/2003 03/24/2008 EF FR-H.2 RESPONSE TO STEAM GENERATOR OVERPRESSURE 006 10/10/2003 03/2412003 03/24/2008 EF FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL 007 10/10/2003 03/24/2003 03/24/2008 EF FR-H.4 RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILIES 005 05/30/2003 03/24/2003 03/24/2008 EF FR-H.5 RESPONSE TO STEAM GENERATOR LOW LEVEL 009 05/30/2003 03/24/2003 03/24/2008 EF FR-1.1 RESPONSE TO HIGH PRESSURIZER LEVEL 017 01/07/2004 03124/2003 03/24/2008 EF FR-1.2 RESPONSE TO LOW PRESSURIZER LEVEL 011 05/30/2003 0312412003 03/24/2008 EF FR-1.3 RESPONSE TO VOIDS INREACTOR VESSEL 019 01/07/2004 03/24/2003 03/24/2008 EF FR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDMON 028 01/07/2004 03/24/2003 03/24/2008 EF FR-P.2 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDmON 008 05/30/2003 03/24/2003 03/24/2008 EF FR-S.1 RESPONSE TO REACTOR RESTART/ATWS 016 10/10/2003 03/24/2003 03/24/2008 EF-FR-S.2 RESPONSE TO LOSS OF CORE SHI¶JDOWN 009 05/30/2003 03/2412003 03124/2008 EF' FR-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE 008 10/10/2003 03/24/2003 03/24/2008 EF FR-Z.2 RESPONSE TO CONTAINMENT FLOODING 005 05/30/2003 03/24/2003 03/24/2008 EF FR-Z.3 RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL 005 05/30/2003 03/24/2003 03/24/2008 EF PRFR TOTAL 18 GRAND TOTAL: 18
EOP: 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 CORE EXIT TC's Lo -=I & FR-C.2 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 GO TO FIGURE MIN SUBCOOLING * *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
_CREMlENcerlTS 10 PSI l
.'TIIG
-t jl IIl
! IIT2II
!!II ii II II I IIl T I!I II 2200- itLltIt U o s _ , zTI ii IIT liy_ Ii
.I II I TIIIT 2100 21000- TTTTITrTT TT, TTTII1Ie-TIT I I11IT§1TTT II1 2000 - T I II TT II I I! TTTI i III iI! 1 1i 1 soo0 - 1 ITtl it!! !T lSi11 I I ll!lllll1 / Ill!
1700 - 'l lI~ T T 1 l;ili 1600! lI 11 11 1 II $ I I IT 1 1 ,1 a 1700 -'Iltl l1 ill llii!li/sfFTI, 1400 - I , _ 'I ! ! I / E '!' .
i 111111 H I H 11+++ ~=+~~il~~UBCOOLEDEIF{ t! 1! i!!
1300 - I iI T= = REGION IiiI lii- I , 'L 120 -n ;
1100 , 61 e* F ^ t , ;7,I
. , ,[I1 lll&:NX!Sl]lIiU I1xz.
-. T-rr TTrT Trrr00 TZ ,i 800 ,I1 1 rI1 T ll ] ]: x ]I Xl t x x I x t l . INADEOUATE ]
17n00 T TT T t suvv i i j, i Ii ii l 6 @ I i i i l l i SUBCOOL i i Ni iiGl I .
70 - TMP~ iTl 1 ~ T1 ITT ; y- NDo AERA TUTR T 100 INCREMENTS 101140FI -]nntl uu - AVRECM iiII3KUU 200 25 300 35 40 I0 I5 450 7 i.. 60 _ .- 65 70+IIi0 CORE EXIT SATURATION TEMPERATURE (OF)
EOP: TITLE:
REV: I8 FR-C.2 RESPONSE TO DEGRADED CORE COOLING
.. ~~ I .... PAGE 1 of 14 I I ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 43 RESPONSIBLE? ANAGER
-F2ECIV- DATE EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
.~ I !
EOP: TITLE:
REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 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 Perform the following:
THAN 28%
- 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:
- OPEN suction valve from RWST open
- MOV-825A
- MOV-825A
- MOV-825B
- MOV-825B
[EOP: 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 a. Ensure at least one valve open.
deluge - OPEN
- MOV-852A
- MOV-852B
- b. Verify SI pump C - RUNNING b. Manually start pump on available bus.
- c. Verify SI pump A - RUNNING 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. Verify SI pump B - RUNNING 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. Verify both SI pump C discharge e. Manually open valves as valves - OPEN necessary.
- MOV-871A
- MOV-871B
EOP: TITLE:
REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 5 of 14 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINEDl 4 Verify SI Flow In Both Trains:
- a. SI line loop A and B flow a. Perform the following:
indicators - CHECK FOR FLOW
- 1) Manually start SI pumps and align valves as necessary.
- 2) Establish maximum charging flow.
- b. RCS pressure - LESS THAN b. Go to Step 5.
250 psig [465 psig adverse CNMT]
I>
.EOP: TITLE:
FR-C.2 RESPONSE TO DEGRADED CORE COOLING
. PAGE 6 of 14 ACTION/EXPECTED RESPONSE llRESPONSE STP 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 a a a a a a a a a a a a a a a a a a a a 5 Check RCS Vent Paths:
- a. Power to PRZR PORV block valves a. Restore power to block valves
- AVAILABLE unless block valve was closed to isolate an open PORV:
- MOV-515. MCC D position 6C
- MOV-516. MCC C position 6C
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 vent valves - d. Manually close valves.
CLOSED
- SOV-590
- SOV-591
- SOV-592
- SOV-593
EOP: 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 a. Go to Step 9.
- b. Support conditions for the b. Try to establish support operating RCP(s) available conditions for the operating RCP.
(Refer to ATT-15.0. ATTACHMENT RCP START) 7 Check RVLIS Fluid Fraction
- a. Fluid fraction (any RCP on) - a. IF increasing. THEN return to GREATER THAN 66% 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 a. Go to Step 10.
- b. Stop one RCP
- c. Go to Step 10 9 Check Core Cooling:
- a. RVLIS level (no RCPs) - GREATER a. IF increasing. THEN return to THAN 52% [55% adverse CNMT] Step 1. IF NOT. THEN go to Step 10.
- b. Core exit T/Cs - LESS THAN 7000 F b. IF decreasing. THEN return to Step 1. IF NOT. THEN go to Step 10.
- c. Return to procedure and step in effect
EOP: 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 Discharge IF SI ACCUM discharge valves closed Valves - OPEN after ACCUM discharge. THEN go to Step 11. IF NOT, THEN perform the
- MOV-841 following:
- MOV-865
- 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 a. Increase total feed flow to THAN 5% [25% adverse CNMT] 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%
EOP: 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: a. Place intact S/G ARV controller in MANUAL and go to Step 13.
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
EOP: 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 *
- 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 4 4 . . . 4 4 . 4 4 . . ,
- 4 . . .
- 4 4 . 4 4 4 4
- 4 . . 4 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 pressures - LESS THAN c. Return to Step 11.
200 PSIG
- d. Check RCS hot leg temperatures - d. Return to Step 11.
BOTH LESS THAN 400 0 F
- e. Stop S/G depressurization
EOP: TITLE: REV 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING
. PAGE 11 of 14 STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- *, *
- 4 * * * . X * * * * * * * * . * * * * * * * * * .
14
- Check
- * *
- RUN NI * * * *
- Mna 44
- tart
- pumps a s n * * * *
- 14 Check RHR Pumps - RUNNING Manually start pumps as necessary.
EOP: TITLE:
REV: 18 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 12 of 14 RESPONSE NOT OBTAINED e SP 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 C position 12F
- MOV-865. MCC D position 12C
- b. Reset SI
- c. Close SI ACCUM discharge valves c. Perform the following to vent an unisolated accumulator:
- MOV-841
- MOV-865 1) Reset CI
- 2) Ensure adequate air compressor(s) running
- 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 * * * * . a
- a a
- a a a a . * *
- a * , . . a a 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 a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a 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
EOP: TITLE:
REV: 18 i FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 14 of 14 ACTION/EXPECTED RESPONSE SP lRESPONSE NOT OBTAINED I 18 Verify SI Flow: Perform the following:
o SI line loop A and B flow a. Continue efforts to establish SI indicators - CHECK FOR FLOW or RHR flow.
-OR- b. Try to establish maximum charging flow.
o RHR loop flow indicator - CHECK FOR 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
- 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
EOP: 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.
- 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.