ML041260403

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R. E. Ginna - Transmittal of Emergency Operating Procedures
ML041260403
Person / Time
Site: Ginna Constellation icon.png
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


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:

a. SI pump suction valves from RWST a. Ensure at least one SI pump

- 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]

c. RHR loop flow indicator - CHECK c. Manually start RHR pumps and FOR FLOW align valves.

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

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
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 * * * * . 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

a. Check RWST level - GREATER THAN a. Go to ES-1.3. TRANSFER TO COLD 28% 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

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.

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.
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