ML021050224

Emergency Operating Procedures

ML021050224
Person / Time
Site:	Ginna
Issue date:	04/01/2002
From:	Widay J Rochester Gas & Electric Corp
To:	Clark R Document Control Desk, NRC/NRR/DLPM/LPD1
References
Download: ML021050224 (16)

Text

SfA Subsidiary of RGS Energy Group, Inc.

www.rge.com ROCHESTER GAS AND ELECTRIC CORPORATION

• 89 EAST AVENUE, ROCHESTER, N.Y 14649-0001 a 716-771-3250 JOSEPH A. WIDAY VICEPRESIDENT & PLANTMANAGER GINNA STATION April 1, 2002 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Robert Clark Project Directorate I Washington, D.C. 20555

Subject:

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

Dear Mr. Clark:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, s 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):

AP Index AP-RCS.3, Rev 9 AP-SW.2, Rev 1 4'z,

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04/01/02 PAGE: 1 GINNA NUCLEAR POWER PLANT REPORT NO. 01 PROCEDURES INDEX REPORT: NPSP0200 ABNORMAL PROCEDURE DOC TYPE: PRAP PRAP STATUS: EF QU 5 YEARS ONLY:

PARAMETERS: DOC TYPES - PRAR EFFECT LAST NEXT PROCEDURE REV DATE REVIEW REVIEW ST NUMBER PROCEDURE TITLE 01/09/01 OS/01/98 05/01/03 EF 014 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 015 09/14/01 08/17/99 08/17/04 EF AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 013 09/14/01 08/17/99 08/17/04 EF AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN 017 05/11/01 01/11/010 01/11/05 EF AP-CR.1 CONTROL ROOM INACCESSIBILITY 012 05/01/98 05/01/98 05/01/03 EF AP-CVCS.1 CVCS LEAK 002 02/11/00 02/26/99 02/26/04 EF AP-CVCS.3 LOSS OF ALL CHARGING FLOW 010 07/16/98 05/01/98 05/01/03 EF AP-CW.1 LOSS OF A CIRC WATER PUMP 022 10/31/01 05/01/98 05/01/03 EF AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 009 03/22/99 03/22/99 03/22/04 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 010 10/31/01 05/01/98 05/01/03 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 003 03/15/01 01/22/02 01/22/07 SF AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 003 10/31/01 01/22/02 01/22/07 EF AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 012 02/11/00 02/27/98 02/27/03 EF AP-FW.1 PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER 12/02/99 05/01/98 05/01/03 EF 017 AP-IA.1 LOSS OF INSTRUMENT AIR 03/26/01 12/02/99 12/02/04 EF 012 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 007 05/22/01 05/14/98 05/14/03 EF AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION 09/14/01 01/22/02 01/22/07 EF 009 AP-RCC.2 RCC/RPI MALFUNCTION 004 11/16/98 02/27/98 02/27/03 EF AP-RCC.3 DROPPED ROD RECOVERY 013 06/09/00 05/01/98 05/01/03 EF AP-RCP.1 RCP SEAL MALFUNCTION 015 09/08/00 05/01/98 05/01/03 EF AP-RCS.1 REACTOR COOLANT LEAK 010 12/14/98 05/01/98 05/01/03 EF LOSS OF REACTOR COOLANT FLOW AP-RCS.2 009 04/01/02 01/22/02 01/22/07 EF AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 011 12/02/99 05/01/98 05/01/03 EF AP-RCS.4 SHUTDOWN LOCA 016 09/14/01 05/01/98 05/01/03 EF AP-RHR.1 LOSS OF RHR

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04/01/02 PAGE:

REPORT NO. 01 GINNA NUCLEAR POWER PLANT PROCEDURES INDEX REPORT: NPSP0200 ABNORMAL PROCEDURE DOC TYPE: PRAP

- PRAR PRAP STATUS: EF QU 5 YEARS ONLY:

PARAMETERS: DOC TYPES EFFECT LAST NEXT PROCEDURE REV DATE REVIEW REVIEW ST NUMBER PROCEDURE TITLE 010 09/14/01 03/31/00 03/31/05 EF AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 001 07/18/01 09/08/00 09/08/05 EF AP-SG.1 STEAM GENERATOR TUBE LEAK 016 10/31/01 06/03/98 06/03/03 EF AP-SW.1 SERVICE WATER LEAK 001 04/01/02 10/31/01 10/31/06 EF AP-SW.2 LOSS OF SfRVICE WATER 010 02/12/99 01/22/02 01/22/07 EF AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 017 02/11/00 05/13/98 05/13/03 EF AP-TURB.2 TURBINE LOAD REJECTION 010 02/11/00 02/10/98 02/10/03 EF AP-TURB.3 TURBINE VIBRATION 014 05/01/98 05/01/98 05/01/03 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 005 06/09/00 06/09/00 06/09/05 EF AP-TURB.5 RAPID LOAD REDUCTION TOTAL FOR PRAP 33

SEOP TITLE: REV: 9 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 1 of 4 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 3 RESPONSIBLOMANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE: REV 9 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 2 of 4 A. PURPOSE - This procedure provides guidance necessary to operate the plant with indication of high reactor coolant activity.

B. ENTRY CONDITIONS/SYMPTOMS

1. SYMPTOMS - The symptoms of HIGH REACTOR COOLANT ACTIVITY are;

a. Unexplained increase in letdown line monitor, R-9, or

b. Sampling indicates 1-131 equivalent GREATER THAN

.64 gCi/gm at 40 gpm letdown or GREATER THAN

.46 p.Ci/gm at 60 gpm letdown or

c. Sampling indicates gross degassed activity GREATER THAN 20 pCi/gm, or

d. Sampling indicates that total specific activity exceeds 100/E.

STEP ACTION/EXPECTED RESPONSE] RESPONSE NOT OBTAINED NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

1 Verify RCS Activity:

a. Direct RP Tech to sample RCS for activity

b. RCS activity - GREATER THAN b. IF normal activity verified, NORMAL THEN return to procedure or guidance in effect.

2 Increase Letdown Flow To 60 GPM (Refer to S-3.2P, SWAPPING CVCS LETDOWN ORIFICE VALVES) 3 Check Letdown Line Monitor, Evaluate conditions to determine R LESS THAN 200 MR/HR whether local radiation emergency ABOVE BACKGROUND exists (Refer to EPIP 1-13, LOCAL RADIATION EMERGENCY).

CAUTION PLACING A NEW DI IN SERVICE MAY RESULT IN A POSITIVE OR NEGATIVE REACTIVITY ADDITION DUE TO A BORON CHANGE.

4 Direct RP Tech To Sample IF DI efficiency is NOT acceptable, Letdown DI Efficiency THEN place a new mixed bed in DECONTAMINATION FACTOR service (Refer to S-3.2B, PLACING A GREATER THAN 10 MIXED BED DEMINERALIZER IN SERVICE

- BORON CONCENTRATION DIFFERENT THAN RCS).

EOP: TITLE: REV: 9 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 4 of 4 STEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED 5 Evaluate AUX BLDG Radiation Levels:

a. Direct RP Tech to survey AUX BLDG

b. Check AUX BLDG radiation b. Perform the following:

monitors - NORMAL

1) Direct RP Tech to survey AUX

• R-4 BLDG areas as necessary.

• R-9

• R-10B 2) Evaluate conditions to

• R-13 determine whether local e R-14 radiation emergency exists (Refer to EPIP 1-13, LOCAL RADIATION EMERGENCY).

6 Check MCB Annunciator Panels Perform alarm response procedures

- ALARM STATUS VALID FOR for unexpected alarms.

PLANT CONDITIONS 7 Determine If Plant Operation IF plant shutdown is required, THEN Can Continue (Consult Plant refer to 0-2.1, NORMAL SHUTDOWN TO staff if necessary) HOT SHUTDOWN.

OPERATION CAN CONTINUE o RP Supervision o Chemistry Supervision o Reactor Engineer NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

8 Notify Higher Supervision

- END -

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

RESPONSIBLg MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE: REV: 1 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'F, 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 1-10, 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.

EOP: TITLE: REV: 1 AP-SW.2 LOSS OF SERVICE WATER PAGE 3 of 8 STEP ACTION/EXPECTED RESPONSEvRESPONSE NOT OBTAINED 1 Verify 480V AC Emergency Ensure associated D/G(s) running Busses 17 and 18 - ENERGIZED 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-0.0, LOSS OF ALL AC POWER.

EOP: TITLE:

REV: 1 AP-SW.2 LOSS OF SERVICE WATER PAGE 4 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• 2 Verify SW Pump Alignment:

a. Check at least one SW pump a. Perform the following:

running in each loop

1) Manually start SW pumps as

• A or B pump in loop A necessary (257 kw-each).

• C or D pump in loop B

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 pushbuttonI

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

a) Close letdown isol. AOV-427 b) Trip the reactor c) Trip BOTH RCPs d) 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: 1 AP-SW.2 LOSS OF SERVICE WATER PAGE 5 of 8 SACTION/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 e MOV-4780

b. Close air conditioning SW isolation valves

• MOV-4663 e MOV-4733

c. Direct AG to perform Part C of ATT-2.2, Attachment SW ISOLATION

EOP: TITLE:

REV: 1 AP-SW.2 LOSS OF SERVICE WATER PAGE 6 of 8 SACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 5 Monitor Plant Equipment IF required, THEN reduce load as Cooled By SW - TEMPERATURES necessary to stabilize equipment STABLE temperatures (Refer to 0-5.1, LOAD REDUCTIONS, or AP-TURB.5, RAPID

"*Exciter LOAD REDUCTION)

"*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 6 Notify Higher Supervision

EOP: TITLE:

REV: 1 AP-SW.2 LOSS OF SERVICE WATER PAGE 7 of 8 STEP ACTION/EXPECTED RESPONSE1 RESPONSE NOT OBTAINED 7 Check SW System Status:

a. Check SW loop header pressures: a. Locally isolate selected SW loads as desired (Refer to "o PPCS SW low pressure alarm ATT-2.2, ATTACHMENT SW ISOLATION) status - NOT LOW e PPCS point ID P2160 e 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 b. Perform the following:

running in each loop:

1) Continue efforts to start at

• A or B pump in loop A least one SW pump in each

• C or D pump in loop B 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 Refer to ITS LCO 3.7.8 Auto Start

EOP: TITLE:

REV: 1 AP-SW.2 LOSS OF SERVICE WATER PAGE 8 of 8 SE ACTIoN/xPECTED RESoNSE RESPoNS NoT OBTAINE 10 Check MCB Annunciator Panels Perform alarm response procedures

- ALARM STATUS VALID FOR for unexpected alarms.

PLANT CONDITIONS 11 Return To Procedure or Guidance In Effect

-END-

EOP: TITLE:

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

1) ATTACHMENT SW ISOLATION (ATT-2.2)