ML17309A519

From kanterella
Jump to navigation Jump to search
Forwards Ginna Nuclear Power Plant Eop,Including Rev 7 to AP-TURB.1, Turbine Trip W/O Rx Trip Required & Rev 8 to FR-C.2, Response to Degraded Core Cooling.
ML17309A519
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/24/1993
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Andrea Johnson
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML17263A305 List:
References
NUDOCS 9306040043
Download: ML17309A519 (18)
v • d • e


Text

A.CCEI ERAT 0 DOCUVIENT DIST UTION SYSTEM REGULAT INFORMATION DISTRIBUTIO SYSTEM (RIDS)

ACCESSION NBR:9306040043 DOC.DATE: 93/05/24 NOTARIZED: NO DOCKET N FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION /u 5'P JOHNSON,A. Project Directorate Z-3 ++4~+~

SUBJECT:

Forwards Ginna Nuclear Power Plant EOP,including Rev 7 to AP-TURB.l, "Turbine Trip W/o RX Trip Required" a Rev 8 to FR-C.2, "Response to Degraded Core Cooling." D DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR TITLE: OR/Licensing Submittal: Suppl 1 A ENCL SIZE:

to NUREC-0737(Generic Ltr 82-33)

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 2 2 INTERNAL: NRR DRCH/HHFB11 1 1 OC/LFMB 1 0 REG E Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D

D D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAI NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9

IIIII/i7llll IIIIIIIIII!II

////// /// Ill/IIIII l IIIIII/ /IIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY TELEPHONE trice Prerldent ArtEA cooE Tie 546-2700 Cinna Nudear Production May 24, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Allen Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Emergency Operating Procedures R. E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, Robert C. Mecredy Enclosures c: Mr. Lee Bettenhausen, USNRC, Region 1 Resident Inspector, Ginna Station oaoe06 pO~

I I 930b040043 'Tt30524 PDR ADDCK 05000244 P PDR

t 1

l k

~ ~

I/

l V

ii

AP-TURB.1 Turbine Trip Without RX Trip Required FR-C.2 Response To Degraded Core Cooling

TITLE:

REV:

AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAG 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORAT ON GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT UPERINTENDENT EFF I E DATE CATEGORY 1.0 REVIEWED BY

T1TLE:

REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 2 of 10 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.l, LOSS OF A CIRC WATER PUMP, or,
b. AP-ELEC.1, LOSS OF 12A AND/OR 12B TRANSFORMER, or,
c. AP-FW.l, PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER, or
d. AP-TURB.2, AUTOMATIC TURBINE RUNBACK, or,
e. AP-TURB.3, TURBINE VIBRATIONS, 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-10, TURBINE MANUAL TRIP, lit, or
d. Annunciator K-17, TURBINE LOW VACUUM TRIP 20" Hg, lit, or
e. Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit, or
f. Annunciator K-26, GENERATOR LOCKOUT RELAY, lit, or
g. Annunciator K-25, TURBINE OVERSPEED ALERT 1980 RPM, lit, or
h. Annunciator F-21, COND HI PRESS 20" HG OR LOSS OF BOTH CIRC WTR PMPS, lit, or
i. Annunciator K-3, AMSAC ACTUATED, lit.

TITLE REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.

1 Verify Turbine Stop Valves- Manually trip turbine.

CLOSED IF turbine stop valves can NOT be closed, THEN close both MSIVs.

IF reactor power greater than 8%

with both MSIVs closed, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

CAUTION PRZR PRESSURE LOW PRESSURE TRIP IS RATE SENSITIVE, THEREFORE, MONITOR PRESSURE WHEN REDUCING RCS TEMPERATURE.

NOTE: Automatic rod control is desired, if available.

2 Check Reactor Power:

F-

a. NIS intermediate ranges a. Go to Step 8.

GREATER THAN 2.5x10 ~ AMPS

b. Verify control rods driving in b. Ensure rod control bank selector to reduce reactor power in AUTO switch in manual and drive rods in as necessary to reduce reactor power.
c. Borate as necessary to maintain control rods above rod insertion limits

E TlTLE REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Establish Shutdown S/G Level Control

a. Place MFW regulating valve controllers in MANUAL
b. Control MFW flow as necessary to restore S/G level
c. S/G level - TRENDING TO PROGRAM c. Operate MFW bypass valves in MANUAL to restore. S/G level.

IF S/G level can NOT be restored, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

4 Verify Proper Operation Of Steam Dump:

,a. Verify annunciator G-15, STEAN a. Place steam dump mode selector DUMP ARMED - LIT switch to MANUAL.

b. Condenser steam dump~operating b. IF steam dump NOT available, in AUTO THEN perform the following:
1) Adjust S/G ARV setpoints to 1005 psig and verify proper operation.
2) IF power is greater than 8%,

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

c. Tavg - TRENDING TO 547'F c. IF Tavg,can NOT be controlled, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

EOP: TITLE:

REV 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check PRZR Pressure IF PRZR pressure can NOT be TRENDING TO 2235 PSIG controlled, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.

6 Check PRZR Level:

a. Level - GREATER THAN 13% a. Perform the following:
1) Place loop B cold leg isolation valve to REGEN Hx (AOV-427) switch to CLOSE.
2) Place letdown orifice valve switches to CLOSE (AOV-200A, AOV-200B, and AOV-202).
3) Verify excess letdown isolation valve (AOV-310) closed.
4) Ensure PRZR heaters off.
5) Control charging to restore PRZR level greater than 13%.
6) WHEN PRZR level greater than 13%, THEN restore letdown.
b. Level - TRENDING TO PROGRAM b. Increase charging flow as necessary to restore PRZR level to program.

EOP: TITLE:

REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX'TRIP REQUIRED PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Placing MFW regulating valve controllers in MANUAL will restore automatic control of MFW bypass valves if desired.

7 Check MFW System:

a. Verify MFW regulating valve a. Place MFW regulating valve bypass valves - OPERATING IN AUTO bypass valve controllers in AUTO and transfer to bypass control if desired.
b. MFW pumps - BOTH RUNNING b. Perform the following:
1) Verify one MFW pump running.

IF NOT, THEN verify both MDAFW pumps running.

2) Go to Step 8.
c. Close one MFW pump discharge valve
d. Stop selected MFW pump 8 Establish Stable Plant Conditions:
a. Place rod control bank selector in MANUAL
b. Check Rx power - LESS THAN b. Return to Step 2.

2.5x10 6 AMPS

c. PRZR pressure - BETWEEN c. Control PRZR heaters and spray 2220 PSIG AND 2260 PSIG as necessary.
d. PRZR level - between 20% and 30% d. Control charging as necessary.
e. S/G levels - TRENDING TO PROGRAM e. Control S/G feed flow as necessary.
f. RCS Tavg - GREATER THAN 540'F f. Control dumping steam as necessary. IF cooldown continues, THEN close both MSIVs.

I' TITLE:

REV: 5 AP- TURB. 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Maintain Reactor power less than 2%. This is within the capacity of MDAFW pumps.

9 Check S/G Feed Flow Status:

a. Manually start both MDAFW pumps
b. Verify total AFW flow - GREATER b. Perform the following; THAN 200 GPM
1) Establish MFW flow using MFW regulating valve bypass valves.

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

2) 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
f. Check S/G level - TRENDING TO 39% f. Adjust MDAFW pump flow as necessary to restore S/G level.

TITLE REV: 5 AP-TURB. 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION WHEN FEEDING BOTH S/GS USING ONE MDAFW PUMP, THEN THE SUM OF THE FLOWS TO BOTH S/GS MUST BE LESS THAN 230 GPM.

10 Establish Normal AFW Pump Shutdown Alignment:

a. Place AFW bypass switches to DEF
b. Verify AFW bypass valves b. Go to Step 11.

OPERABLE

~ AOV-4480

~ AOV-4481

c. Verify the following: c. Continue with Step 11. WHEN conditions met, THEN do Steps o Both S/G levels - STABLE OR 10d through g.

INCREASING o Total AFW flow - LESS THAN 200 GPM

d. Close MDAFW pump discharge valves

~ MOV-4007

~ MOV-4008

e. Stop all but one MDAFW pump
f. Open AFW discharge crossover valves

~ MOV-4000A

~ MOV-4000B

g. Open AFW bypass valves as necessary to control S/G levels

~ AOV-4480

~ AOV-4481

EOP:

I REV: 5 AP-TURB. 1 E TRIP WITHOUT Rx TR1P REQUIRED PAGE 9 of 1O STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.
b. Perform the following as necessary:

o Open generator disconnects

~ 1G13A71

~ 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cern to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump it

c. Verify Bus 11A and Bus 11B c. IF either bus NOT energized, energized - BOTH BUSSES GREATER THEN refer to 0-6.9.2, THAN 4 KV ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/

BUS 12B.

d. Dispatch AO to perform Attachment SD-1 NOTE: Refer to 0-9.3, NRC STATE AND COUNTIES IMMEDIATE NOTIFICATION, for reporting requirements.

12 Notify Higher Supervision

Ebs:

REV' AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 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 FROM HOT SHUTDOWN TO STEADY LOAD.
b. Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN

-END-

F.OP:

REV: 5 TURBINE TRIP WITHOUT Rg TRIP REQUIRED PAGE 1 of 1 APPENDIX LIST

1) Attachment SD-1
2) Attachment SD-2

r

Retrieved from "https://kanterella.com/w/index.php?title=ML17309A519&oldid=2428204"