ML17311A070

Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.

ML17311A070
Person / Time
Site:	Ginna
Issue date:	04/14/1999
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17309A651	List: ML17309A650 ML17309A652 ML17311A070
References
AP-PRZR.1, NUDOCS 9904200389
Download: ML17311A070 (225)

Text

EOP:

REV: 10 P-PRZR.l ABNORMAL PRESSURIZER PRESSURE PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE NAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

9904200389 990414 PDR ADQCK 05000244 P PDR

EOP TITLE:

REV: 10 P.-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 2 of 10 A. PURPOSE This procedure provides the actions necessary to mitigate the consequences of abnormal PRZR pressure.

B. ENTRY CONDITIONS/SYMPTOMS

l. ENTRY CONDITIONS This procedure is 'entered from:

a. AP-CVCS.l, CVCS LEAK, or

b. AP-FW.l, PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER, or

c. AP-IA.1, LOSS OF INSTRUMENT AIR, or

d. AP-RCC.1, CONTINUOUS CONTROL ROD WITHDRAWAL OR INSERTION, or

e. AP-RCS.1, REACTOR COOLANT LEAK, or

f. AP-TURB.1, TURBINE TRIP WITHOUT RX TRIP REQUIRED, or

g. AP-TURB.2, TURBINE LOAD REJECTION, when PRZR pressure can NOT be controlled.

2. SYMPTOMS The symptoms of ABNORMAL PRZR PRESSURE are;

a. Annunciator F-19, or PRZR PORV OUTLET HI TEMP 145'F, lit,

b. Annunciator F 1 8 i PRZR SAFETY VLV OUTLET H I TEMP 1 4 5 Fi lit, or

c. Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION,

~

lit, or

d. Annunciator F-l, PRT LIQUID HI TEMP 220 F, lit, or

e. Annunciator F-'9, PRT HI PRESS 5 PSI, lit, or

f. Annunciator F-17, PRT LEVEL 60.8  % 84.5, lit, or

g. Annunciator F-2, PRESSURIZER HI'PRESS 2310 PSI, lit, or

h. Annunciator F-10, PRESSURIZER LO PRESS 2205 PSI, lit, or

i. Annunciator F-6, PRESSURIZER HEATER BREAKER TRIP, lit.

j. Annunciator F-26, 2377 PSX.

PRESSURIZER HI PRESS CHANNEL ALERT

EOP TITLE:

REV: 10 P-PRZR.1. ABNORMAL PRESSURIZER PRESSURE PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

~ ~ ~ ~ I ~ 4 ~ ~ ~ 1 ~ ~ ~ 4 ~ 1 0 0 1 4 1 ~ ~ 1 1 * ~ ~ 0 I 4 ~ ~ ~ t ~ 4 ~ ~ ~ ~

CAUTION IF, AT ANY TIME DURING THIS PROCEDURE. A REACTOR TRIP OR SI OCCURS. E-O.

REACTOR TRIP OR SAFETY. INJECTION. SHALL BE PERFORMED.

NOTE: o Actual PRZR pressure should be verified by more than 1 indicator.

o Refer to ITS section 3.4.1 for limiting conditions for operations.

1 Check PRZR Pressure: IF one pressure channel deviates significantly from the other 3.

o All 4 narrow range channels- THEN perform the following:

APPROXIMATELY EQUAL r

a. IF the controlling PRZR pressure o All 4 narrow range channels channel has failed. THEN place TRENDING TOGETHER controller. 431K. in MANUAL and adjust output to restore PRZR pressure.

b. Refer to ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE.

2 Check Reactor Power STABLE IF the abnormal PRZR pressure is a result of a power transient. THEN evaluate conditions and go to the appropriate plant procedure. "

EOP TITLE:

REV 10 P-PRZR.1 ~

ABNORMPJ PRESSURIZER PRESSURE PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check PRZR Pressure:

a. Pressure - LESS THAN 2235 PSIG a. Go to Step 12.

b. Pressure - GREATER THAN 2000 PSIG b. ~F pressure "decreasing uncontrollably. THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

~ P P ~ P ~ * 'P ~ P P * * ~ ~ ~ ~ ~ ~ ~ P P P P P P * ~ P ~ ~ ~ ~ P P ~ ~ ~ ~ ~ ~

~CAU ION OBSERVE D/G LOADING LIMITS OF 2300 KM FOR 1/2 HOUR, 2250 KM FOR 2 HOURS. AND 1950 KW FOR CONTINUOUS SERVICE.

~ P ~ ~ ~ P ~ ~ ~ P ~ P P ~ ~ P ~, ~ P P ~ ~ ~ ~ ~ P P ~ ~ ~ P ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

4 Check PRZR Heater Status:

a. PRZR heater control group- a. Place PRZR heater control group BREAKER CLOSED switch to TRIP to reset, then place switch to CLOSE and let return to AUTO.

b. PRZR heater backup group - ON b. IF PRZR pressure less than 2220 psig. THEN energize PRZR backup heaters.

IF PRZR backup heater breaker has tripped. THEN perform the following:

1) Place the breaker switch to OFF to reset breaker.

2) Place the breaker switch to ON to energize heaters.

3) Verify load increase on Bus 16'.

EOP: TlTLE:

REV 10 P-PRZR.l. ABNORMAL PRESSURIZER PRESSURE PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify Normal PRZR Spray ~ Place controllers in MANUAL at 0/

Valves CLOSED demand. IF valves can NOT be closed, THEN perform the following:

~ PCV-431A I

~ PCV-431B a. Trip the reactor.

I

b. Trip the associated RCP.

c. Go to E-O, REACTOR TRIP OR SAFETY INJECTION.

NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not be operable in the automatic mode.

6 Check PRZR Pressure Place 431K in MANUAL and decrease Controller, 431K, Demand output to energize PRZR heaters.

LESS THAN 50%

EOP TITLE:

REV: 10 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRZR PORVs:

a. PORVs - CLOSED a. Manually close PORVs.

IF any valve can NOT be closed, THEN manually close the associated block valve.

~ MOV-516 for PCV-430

~ MOV-515 for PCV-431C

b. Annunciator F-19. PRZR PORV b. IF PORV leakage is indicated.

OUTLET HI TEMP 145'F- THEN perform the following:

EXTINGUISHED

1) Close PORV block valves one at a time AND check pressure stabilizes.

if

~ MOV-515

~ MOV-516

2) IF a leaking PRZR PORV is identified. THEN restore any nonleaking PORV to operable AND go to Step 8.

c. Go to Step 9

EOP,:

REV: 10 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Attempt To Reseat Any Leaking PORV:

a. Verify affected PORV block valve a. Close the affected PORV block

- CLOSED valve.

b. Cycle the leaking PORV open then closed

c. Open affected PORV block valve

d. Verify leakage has stopped d. IF leakage continues. THEN perform the following:

1) Reclose leaking PORV block valve.

2) Refer to ITS section 3.4.11 for required actions.

e. Go to Step ll 9 Check PRZR Safety Valves: IF safety valve leakage indicated, THEN perform, the following:

o Position indicator - LESS THAN 0.1 INCH a. Verify leakage within limits of ITS section 3.4.13.

o Annunciator F-18. PRZR SAFETY VLV OUTLET HI TEMP 145 F- b. Go to Step 17.

EXTINGUISHED o Annunciator AA-13. PRESSURIZER SAFETY VALVE POSITION EXTINGUISHED

EOP: TITLE:

REV: 10 P-PRZR.1. ABNORMAL PRESSURIZER PRESSURE

~ ~

PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check AUX Spray Valve, Manually close valve. IF valve can AOV-296 CLOSED NOT be closed. THEN consider isolating letdown and closing charging flow control valve, HCV-142.

11 Check PRZR Pressure Control Restored:

a. Pressure - TRENDING TO 2235 PSIG a. IF pressure continues to decrease, THEN return to Step 1.

b. Go to Step 17 12 Check PRZR Backup Heaters- Verify PRZR backup heater switch in OFF AUTO. ~D ensure proper operation.

NOTE: With PRZR pressure controller 431K in manual, PORV-431C'ill not be operable in the automatic mode.

13 Check PRZR Pressure Place 431K in MANUAL at 50'/i demand.

Controller, 431K, Demand INCREASING NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray .valves.

o The aT between the REGEN Hx charging outlet and the PRZR shall NOT exceed 320'F.

14 Check RCPs ANY RUNNING IF letdown in service, THEN perform the following:

a..Open AUX spray valve, AOV-296, as necessary to control PRZR pressure.

b. Go to Step 16.

EOP:

REV: 10 P-PRZR.1. ABNORMAL PRESSURIZER PRESSURE PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If either RCP is off, then the associated PRZR spray valve controller should be closed by placing in MANUAL with demand at 0/.

15 Check PRZR Spray. Valve Place PRZR spray valve controllers Controllers Demand GREATER in MANUAL and open as required to THAN 0% control pressure.

~ PCV-431A

~ PCV-431B 16 Check PRZR Pressure IF PRZR pressure continues to TRENDING TO 2235 PSIG increase uncontrollably. THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION.

17 Check PRT Indications:

a. Level - BETWEEN 61/i AND 841i a. Drain PRT to RCDT using PRT drain valve, AOV-526.

b. Pressure - APPROXIMATELY b. Open PRT vent. AOV-527. IF PRT 1.5 PSIG AND STABLE- pressure will NOT decrease. THEN open PRT drain valve. AOV-526.

to reduce pressure.

c. Temperature - AT CNMT AMBIENT c. To feed'n'd bleed the PRT.

TEMPERATURE AND STABLE perform the following:

1) Start a RMW pump.

2) Verify RMW to CNMT isolation valve. AOV-508. open.

3) Feed and bleed the PRT using PRT fill valve AOV-548, and PRT from RMW.

drain valve, AOV-526.

EOP TITLE:

REV: 10 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

18 Notify Higher Supervision 19 Notify Reactor Engineer for Transient Monitoring Program

-END-

EOP.

REV: 10 P-PBZR. 1 . ABNORMAL PRESSURIZER PRESSURE PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPO TION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE NAGER EF CTIVE DATE CATEGORY 1.0 REVIEWED B 9904200389 05000244,'

q904ij.'DR ADQCK PDR

0 0 TITLE.

REV: 10 P-PRZR. 1 ~

ABNORMAL PRESSURIZER PRESSURE PAGE '2 of 10 A. PURPOSE This procedure provides the actions necessary to mitigate the consequences of abnormal PRZR pressure.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure is entered from:

a. AP-CVCS.1, CVCS LEAK, or

b. AP-FW.1, PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER, or

c. AP-IA.1, LOSS OF INSTRUMENT AIR, or

d. AP-RCC.1, CONTINUOUS CONTROL ROD WITHDRAWAL OR INSERTION, or e ~ AP-RCS.1, REACTOR COOLANT LEAK, or f AP TURB 1 TURB INE TRI P WITHOUT RX TRI P I REQU RED@ or

g. AP-TURB.2, TURBINE LOAD REJECTION, when PRZR pressure can NOT be controlled.

2. SYMPTOMS The symptoms of ABNORMAL PRZR PRESSURE are;

a. Annunciator F-19, or PRZR PORV OUTLET HI TEMP 145 F, lit,

b. Annunciator F 1 8 PRZR SAFETY VLV OUTLET H I TEMP 1 4 5 F~

lit, or g

c. Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION, 1 i't or

d. Annunciator F-l, PRT LIQUID HI TEMP 220', lit, or

e. Annunciator F-', PRT HI PRESS 5 PSI, lit, or

f. Annunciator F-17, PRT LEVEL 60.8 0 84.5, lit, or

g. Annunciator F-2, PRESSURIZER HI'PRESS 2310 PSI, lit, or

h. Annunciator F-10, PRESSURIZER LO PRESS 2205 PSI, lit, or

i. Annunciator F-6, PRESSURIZER HEATER BREAKER TRIP, lit.

j. Annunciator F-26, 2377 PSI.

PRESSURIZER HI PRESS CHANNEL ALERT

0 0

~< P ~ ~ . 'ta

EOP TITLE.

REV 10 P-PRZR. 1 ABNORMAL PRESSURIZER PRESSURE PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 1 1 ~ ~ 4 4 4 * ~ 0 1

• 1 1 ~ * ~ l 1 1 0 1 4 t ~ t 1 ~ t ~ I 0 I 1 0 4 4 4 1 ~

CAUTION IF, AT ANY TIME DURING THIS PROCEDURE. A REACTOR TRIP OR SI OCCURS. E-O, REACTOR TRIP OR SAFETY, INJECTION. SHALL BE PERFORMED.

NOTE: o Actual PRZR pressure should be verified by more'than 1 indicator.

o Refer to ITS section 3.4.1 for limiting conditions for operations.

1 Check PRZR Pressure: IF one pressure channel deviates significantly from the other 3, o All 4 narrow range channels THEN perform the following:

APPROXIMATELY EQUAL

a. IF the controlling PRZR pressure o All 4 narrow range channels channel has failed, THEN place TRENDING TOGETHER controller. 431K, in MANUAL and adjust output to restore PRZR pressure.

b. Refer to ER-INST.1, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE.

2 Check Reactor Power STABLE IF the abnormal PRZR pressure is a result of a power transient, THEN evaluate conditions and go to the appropriate plant procedure.

0

~ l A t P'

BOP TITLE.

REV 10 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check PRZR Pressure:

a. Pressure - LESS THAN 2235 PSIG a. Go to Step 12.

b. Pressure - GREATER THAN 2000 PSIG b. IF pressure decreasing uncontrollably, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

I I I I I I

• I I ~ I ~ ~ I I I

• I ~ * * * *

• I I I I I I I

• I I I I I I CAUTION OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR. 2250 KW FOR 2 HOURS, AND 1950 KW FOR CONTINUOUS SERVICE.

I

• I I I I I I I I ~ t I I I I I I

• I I I I 't ~ I ~ ~ I t I I I I I I I I I ~

• 4 Check PRZR Heater Status:

a. PRZR heater control group- a. Place PRZR heater, control group BREAKER CLOSED switch to TRIP to reset,, then place switch to CLOSE and let return to AUTO.

b. PRZR heater backup group - ON b. IF PRZR pressure less than 2220 psig. THEN energize PRZR backup heaters.

IF PRZR backup heater breaker has tripped, THEN perform the following:

1) Place the breaker switch to to reset breaker. 'FF

2) Place the breaker switch to ON to energize heaters.

3) Verify load increase on Bus 16.

Qi

'I ~

OP P-PRZR. l.

TITLE.

'I ABNORMAL PRESSURIZER \'EV:PRESSURE PAGE 5 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify Normal PRZR Spray ~

Place controllers in MANUAL at 0'5 Valves CLOSED demand. IF valves can NOT be closed. THEN perform the following:

~ PCV-431A

~ PCV-431B a. Trip the reactor.

b. Trip the associated RCP.

c. Go to E-0. REACTOR TRIP OR SAFETY INJECTION.

NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not be operable in the automatic mode.

6 Check PRZR Pressure Place 431K in MANUAL and decrease Controller, 431K, Demand output to energize PRZR heaters.

LESS THAN 50%

'1

\

1 1' ~ 4 1 1 ~ 4 4 4 ~

0

EOP.

REV: 10 P-PRZR. 1. ABNORMAL PRESSURIZER PRESSURE PAGE 6 of 10 STEP 'CTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRZR PORVs:

a. PORVs - CLOSED a. Manually close PORVs.

IF any valve can NOT be closed, THEN manually close the associated block valve.

~ MOV-516 for PCV-430

~ MOV-515 for PCV-431C

b. Annunciator F-19, PRZR PORV b. IF PORV leakage is indicated, OUTLET HI,TEMP 145'F- THEN perform the following:

EXTINGUISHED

1) Close PORV block valves one at a time AND check if pressure stabilizes.

~ MOV-515

~ MOV-516

2) IF a leaking PRZR PORV is identified. THEN restore any nonleaking PORV to operable AND go to Step 8.

c. Go to Step 9

l 0

EOP.: .TITLE:

REV: 10 AP-PRZR. l. ABNORMAL PRESSURIZER PRESSURE PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Attempt To Reseat Any Leaking PORV:

a. Verify affected PORV block valve a. Close the affected PORV block CLOSED valve.

b. Cycle the leaking PORV open then closed

c. Open affected PORV block valve

d. Verify leakage has stopped d. IF leakage continues, THEN perform the following:

1). Reclose leaking PORV block valve.

2) Refer to ITS section 3.4.11 for required actions.

e. Go to Step 11 9 Check PRZR Safety Valves: IF safety valve leakage indicated, THEN perform the following:

o Position indicator - LESS THAN 0.1 INCH a. Verify leakage within limits of ITS section 3.4.13.

o Annunciator F-18, PRZR SAFETY VLV OUTLET HI TEMP 145'F b. Go to Step 17.

EXTINGUISHED o Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION EXTINGUISHED

~ ~ 8 OP TITLE.

REV: 10 P-PRZR.1- ABNORMAL PRESSURIZER PRESSURE PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check AUX Spray Valve, Manually close valve. IF valve can AOV-296 CLOSED NOT be closed. THEN consider isolating letdown and" closing charging flow control valve, HCV-142.

11 Check PRZR Pressure Control Restored:

a. Pressure - TRENDING TO 2235 PSIG a. IF pressur'e continues to decrease. THEN return to Step l.

b. Go to Step 17 12 Check PRZR Backup Heaters Verify PRZR backup heater switch in OFF AUTO, AND ensure proper operation.

NOTE: With PRZR pressure controller 431K in manual, PORV-431C'ill not be operable in the automatic mode.

13 Check PRZR Pressure Place 431K in MANUAL at 50% demand.

Controller, 431K, Demand INCREASING NOTE: o If auxiliary spray is in use. spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

o The aT between the REGEN Hx charging outlet and the PRZR shall NOT exceed 320'F.

14 Check RCPs ANY RUNNING IF letdown in service, THEN perform the following:

a..Open AUX spray valve, AOV-296, as necessary to control PRZR pressure.

b. Go to Step 16.

0

~ ~ El i1 C

~ ~

<OP TITLE.

REV: 10 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If either RCP is off. then the associated PRZR spray valve, controller should be closed by placing in MANUAL with demand at 0%.

15 Check PRZR Spray. Valve Place PRZR spray valve controllers Controllers Demand GREATER in MANUAL and open as required to THAN 0% control pressure.

~ PCV-431A

~ PCV-431B 16 Check PRZR Pressure IF PRZR pressure continues to TRENDING TO 2235 PSIG increase uncontrollably, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION.

17 Check PRT Indications:

a. Level - BETWEEN 61% AND 84% a. Drain PRT to RCDT using PRT drain valve. AOV-526.

, b. Pressure - APPROXIMATELY b. Open PRT vent, AOV'-527. IF PRT 1.5 PSIG AND STABLE pressure will NOT decrease, THEN open PRT drain valve, AOV-526.

to reduce pressure.

c. Temperature - AT CNMT AMBIENT c. To feed and bleed the PRT.

TEM/ERATURE AND STABLE perform the following:

1) Start a RMW pump.

2) Verify RMW to CNMT isolation valve. AOV-508, open.

3) Feed and bleed the PRT using PRT fill valve AOV-548, and PRT from RMW ~

drain valve.

AOV-526.

I '

EOP P-PRZR.1'ITLE: REV: 10 ABNORMAJ PRESSURIZER PRESSURE PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION. for reporting requirements.

18 Notify Higher Supervision 19 Notify Reactor Engineer for Transient Monitoring Program

-END-

.0 y~-z>W gj/5/,

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Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 010860442:1

Subject:

Emergency Operating Procedures For R.E. Ginna Nuclear Power. Plant.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML010860442.

Page 1

~la>

A002 - OR Submittal:Inadequate Core Cooling (Item II.F.2) GL 82-28 Docket: 05000244 Page 2

I WIVO A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS ANO ELEClRIC CORPORATION ~ 89 FAST AVENUE, ROCHESTER, N Y. 186d 94001 ~ 716-771-3250 www.rge.corn JOSEPH A. WIDAY VICE PRESIDENT d, PLANT MANAGER GINNA STATION March 15, 2001 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I Washington, D.C. 20555

Subject:

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

Dear Mr. Vissing:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, a.d J s phA. 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-ELEC.14/16

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 02/08/01 PAGE: 1 RB RT: NPSP0200 PROCEDURES INDEX DOC PB: PRAP ABNORMAL PROCEDURE P~: DOC TYPES PRFIG PRER PRAR PRAP STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE DATE REVIEW REVIEW ST AP-CCW. 1 LEAKAGE INTO THE COMPONENT COOLING LOOP 014 01/09/01 05/01/98 05/01/03 EF AP-CCW. 2 LOS OF CCW DURING POWER OPERATION 014 05/18/00 08/17/99 08/17/04 AP-CCW. 3 LOSS OF - PLANT SHUTDOWN 012 05/18/00 08/17/99 08/17/ EF AP-CR. 1 CONTROL ROOM INA ESSI8 ILITY 01/11/00 01/11/00 016 /11/05 EF AP CVCS.1 CVCS LEAK 012 05/01/98 05/ 98 05/01/03 EF AP-CVCS.3 LOSS OF ALL CHARGING PLOW 002 02/11 02/26/99 02/26/04 EF AP-CW.1 LOSS OF A CIRC WATER PUMP 010 07/16/98 05/01/98 05/01/03 EP AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 020 09/08/00 05/01/98 05/01/03 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQ CY 009 03/22/99 03/22/99 03/22/04 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 008 09/08/00 05/01/98 05/01/03 EF AP-ELEC. 14/16 LOSS OP SAFEGUARDS BUS 14/16 002 02/08/01 06/09/97 06/09/02. EF AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 002 10/18/99 06/09/97 06/09/02 EF AP-FW. 1 PARTIAL OR COMPLETE LOSS OF MAIN FEEDWA 12 02/11/00 02/27/98 02/27/03 EF AP- IA. 1 LOSS OF INSTRUMENT AIR 017 2/02/99 05/01/98 05/01/03 EF AP PRZR.1 ABNORMAL PRESSURIZER PRESSUR 011 12/0 9 12/02/99 12/02/04 EF AP-RCC.1 CONTINUOUS CONTROL RO ITHDRAWAL/INSERTION 006 02/24/96 14/98 05/14/03 BF AP-RCC.2 RCC/RPI MAL ION 008 11/16/98 02/06/ 02/06/02 EF AP-RCC.3 DROPP OD RECOVERY 004 11/16/98 02/27/98 02/ 03 EF AP-RCP.1 CP SEAL MALFUNCTION 013 06/09/00 05/01/98 05/01/03 AP-RCS.1 REACTOR COOLANT LEAK 015 09/08/00 05/01/98 05/01/03 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 010 12/14/98 05/01/98 05/01/03 EF AP-RC .3 HIGH REACTOR COOLANT ACTIVITY 007 08/05/97 08/05/97 08/05/02 EF

-RCS.4 SHUTDOWN LOCA 011 12/02/99 05/01/98 05/01/03 EF AP-RHR.1 LOSS OF RHR 015 02/08/01 05/01/98 05/01/03 EF

l l~

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 02/08/01 PAGE: 2 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRFIG PRER PRAR PRAP STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE DATE REVIEW REVIEW ST AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 009 10/13/00 03/31/00 03/31/05 EF AP-SG.1 STEAM GENERATOR TUBE LEAK 000 09/08/00 09/08/00 09/08/05 EF AP-SW. 1 SERVICE WATER LEAK 015 10/18/99 06/03/98 06/03/03 EF AP-TURB. 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 02/12/99 10/10/97 010 10/10/02 EF AP- TURB. 2 TURBINE LOAD REJECTION 02/11/00 017 05/13/98 05/13/03 EF AP- TURB . 3 TURBINE VIBRATION 02/11/00 010 02/10/98 02/10/03 EF AP-TURB. 4 LOSS OF CONDENSER VACUUM 014 05/01/98 05/01/98 05/01/03 EF AP- TURB. 5 RAPID LOAD REDUCTION 06/09/00 005 06/09/00 06/09/05 EP TOTAL FOR PRAP 32

REV: 2 AP ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 1 of 17 ROCHESTER GAS AND ELECTRIC CORP TION GINNA STATION CONTROLLED COPY NUMBE RESP SIB MANAGER FECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 2 of 17 A. PURPOSE This procedure provides actions to respond to a loss of AC Emergency Bus 14 or Bus 16.

B. ENTRY CONDITIONS/SYMPTOMS

2. SYMPTOMS The symptoms of a LOSS OF SAFEGUARDS BUS 14/16 are;

a. Annunciator J-7, 480V MAIN OR TIE BREAKER TRIP, lit, or

b. Annunciator J-29, 480V TRANSFORMER BREAKER TRIP, lit.

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 3 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• 1 4 * * *

• 1 l 4 * * *

• 0

• 1 4

• t

• t f 1 t 1 1 4 1 1

• 4 4 0 i l i 4 4 1 ~

CAUTION o IF A LOSS OF BUS 12A OR 12B HAS OCCURRED, THEN NO OUTSIDE, SHOULD BE PERFORMED.

o IF A TURBINE RUNBACK HAS OCCURRED. THEN AP-TURB.2. TURBINE LOAD REJECTION.

SHOULD BE PERFORMED.

o OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR. 2250 KW FOR 2 HOURS, AND 1950 KW FOR CONTINUOUS SERVICE.

o DO NOT ATTEMPT TO ENERGIZE A BUS THAT IS POTENTIALLY FAULTED.

NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Establish Manual Rod Control

a. Place Rod Control Bank Selector Switch to MANUAL

b. Verify control rod motion stops b. Manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

c. Manually move control rods as necessary 2 Verify Emergency D/G Attempt to start and load emergency Associated With Affected Bus D/G(s) manually. (Refer to RUNNING AND LOADED ER-D/G.l. RESTORING D/Gs) o Bus 14 - D/G A o Bus 16 - D/G B

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 4 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify At Least One Train of Go to ECA-O.O. LOSS OF ALL AC POWER AC Emergency Busses Energized step 1.

to at Least 420 Volts:

o Bus 14 and Bus 18

-OR-o Bus 16 and Bus 17

~ *

• 1 * * * *

• 1 1 * *

• 1 * ~

• 1 1 *

• 1 * ~ 1 1 1 ~ 1

• 1 1 1 1 1 CAUTION IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 200'F, THEN TRIP THE AFFECTED RCP.

4 Verify CCW Pump Status

a. At least one CCW Pump - RUNNING a. Start one CCW pump (124 KW)

1) IF neither CCW pump can be started. THEN perform the following:

a) Trip the reactor.

b) Trip BOTH RCP's.

c) Go to E-O, REACTOR TRIP OR SAFETY INJECTION.

b. Annunciator A-22. CCW PUMP b. Start second CCW pump (124 KW).

DISCHARGE LO PRESS 60 PSIG EXTINGUISHED

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 5 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify Charging Pump Status- Secure letdown flowpaths AT LEAST ONE RUNNING o Close loop B cold leg to REGEN Hx. AOV-427.

o Ensure closed loop A cold leg to EXCESS LETDOWN Hx, AOV-310.

o Ensure closed EXCESS LETDOWN HCV-123.

6 Monitor S/G Level Control: Place MFW regulating valves in MANUAL and control feed flow as o S/G level - TRENDING TO 52% necessary."

o MFW regulating valves CONTROLLING IN AUTO

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 6 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Verify Bus 14 ENERGIZED TO Perform the following:

AT LEAST 420 VOLTS

a. Close loop B cold leg to REGEN Hx, AOV-427.

b. IF steam dump is armed, THEN place STEAM DUMP MODE SELECTOR Switch to MANUAL.

c. Ensure only one charging pump operating.

d. Transfer Inst Bus B to maintenance supply.

e. Return steam dump to desired.

AUTO, if

f. Ensure the following equipment operating as necessary:

~ CCM Pump B

~ PRZR Backup Heaters

~ CNMT Recirc Pans B and C

~ Boric Acid Pump B

~ RMW Pump B

~ Reactor Compartment Cooling Pan B

~ Penetration Cooling Fan B

g. IF Bus 14 can NOT be energized, THEN:

o Provide alternate room cooling for D/G A.

o Cross-connect D/G B fuel oil transfer pump to D/G A (Refer to ER-D/G.l).

0 EOP:

REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 7 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Verify Bus 16 ENERGIZED TO Perform the following:

AT LEAST 420 VOLTS

a. Ensure the following equipment operating as necessary:

~ CCW Pump A

~ Charging Pump A

~ PRZR Proportional Heaters

~ CNMT Recirc Fans A and D

~ Boric Acid Pump A

~ RMW Pump A

~ Reactor Compartment Cooling Fan A

~ Penetration Cooling Fan A

b. IF Bus 16 can NOT be energized, THEN:

o Provide alternate room cooling for D/G B.

o Cross-connect D/G A fuel oil transfer pump to D/G B (Refer to ER-D/G.l).

0 EOP:

REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 8 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF VCT level decreased to 5%, charging pump suction will swap to the RWST. This may required a load reduction.

9, Check VCT Makeup System:

a. Verify the following: a. Adjust controls as necessary.

1) RMW mode selector switch in AUTO

2) RMW control armed - RED LIGHT LIT

b. Check VCT level b. Check letdown divert valve, LCV-112A, aligned to VCT.

o Level GREATER THAN 20%

Manually increase VCT makeup

-OR- flow as follows:

o Level - STABLE OR INCREASING 1) Ensure BA transfer pumps and RMW pumps running.

2) Adjust RMW flow control valve, HCV-111, to increase RMW flow.

3) Increase boric acid flow as necessary to maintain required concentration.

IF VCT level can NOT be maintained. THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION.

necessary.

if

4 i

'l

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 9 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check Charging Pump Suction Aligned To VCT:

a. VCT level - GREATER THAN 20% a. IF VCT level can NOT be maintained greater than 5%, THEN perform the following:

1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed

2) Continue with Step 11. WHEN VCT level greater than 20%,

THEN do Step 10b.

b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.

o LCV-112C open o LCV-112B closed

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 10 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: When restarting equipment for recovery, it is preferable to start equipment on busses being supplied from offsite power. if possible.

ll Check CVCS Operation:

a. Charging pumps - AT LEAST ONE a. IF charging pump(s) available.

RUNNING THEN perform the following:

1) Start charging pumps as necessary.

2) Establish greater than 20 gpm charging line flow.,

IF NO charging pumps available, THEN go to step 13

b. Charging line flow - GREATER b. Establish charging line-flow to THAN 20 GPM REGEN Hx - GREATER THAN 20 GPM

c. Check letdown indications: c. Perform the following:

o Check PRZR level - GREATER 1) Close loop B cold leg to THAN 13% REGEN Hx, AOV-427.

o Letdown flow - APPROXIMATELY 2) Close letdown orifice valves 40 GPM (AOV-200A, AOV-200B, and AOV-202) o Letdown flow - STABLE

3) IF PRZR level greater than 13%, THEN go to Step 12. IF NOT, THEN continue with Step 14. WHEN PRZR level greater than 13%. THEN do Steps 12 and 13.

d. Adjust charging pump speed and HCV-142 as necessary to restore PRZR level and labyrinth seal D/P

e. Go to Step 13

/

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REV: 2 AP-ELEC.14/16 14/16 LOSS OF SAFEGUARDS BUS PAGE ll of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Steps 12 and 13 may be performed concurrently.

12 Establish Normal Letdown: Perform the following steps in sequence to establish excess

a. Establish charging line flow to REGEN Hx - GREATER THAN 20 GPM letdown. if desired:

o Place excess letdown divert

b. Place letdown controllers in valve, AOV-312, to NORMAL MANUAL at 40% open o Ensure CCW from excess letdown

~ TCV-130 open, AOV-745

~ PCV-135 o Ensure RCP seal return isolation

c. Open AOV-427 valve open, MOV-313

d. Open letdown orifice valves as o Open excess letdown isolation necessary valve, AOV-310

e. Place TCV-130 in AUTO at 105'F o Slowly open HCV-123 to maintain excess letdown temperature less

f. Place PCV-135 in AUTO at 250 psig than 195 F and pressure less than 100 psig

g. Adjust charging pump speed and HCV-142 as necessary 13 Verify PRZR Heaters Restored: IF adequate D/G capacity available for PRZR heaters (400 kw each o PRZR proportional heater breaker bank), THEN perform the following:

CLOSED

a. Reset and close PRZR o PRZR backup heater RESET/IN AUTO breaker- proportional heater breaker necessary.

if

b. Reset PRZR backup heater breaker and return to AUTO if necessary.

IF adequate D/G capacity NOT available, THEN refer to ER-PRZR.1.

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 12 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify Normal Rod Control Restored:

a. Annunciator C-5. PPCS ROD a. IF alarm is due to a loss of SEQUENCE OR ROD DEVIATION power to MRPI, THEN maintain EXTINGUISHED rods in manual AND minimize rod motion.

IF alarm is due to actual rod misalignment, THEN refer to AP-RCC.2, RCC/RPI MALFUNCTION.

while continuing with this procedure.

b. Annunciator E-28, POWER RANGE b. Perform the following:

ROD DROP ROD STOP - EXTINGUISHED

1) Place rod control bank selector switch in MANUAL.

2) Reset NIS rod drop rod stop signals (at NIS racks) as necessary.

c. Annunciator F-15, RCS TAVG DEV c. Go to step 15 O'F - EXTINGUISHED

d. Place rod control bank selector switch in AUTO if desired

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 13 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish Stable Plant Conditions:

a. Check Tavg - TRENDING TO TREF a. Insert control rods or, if necessary, decrease turbine load to match Tavg to Tref.

b. Check PRZR pressure - TRENDING b. Verify proper operation of PRZR TO 2235 P8XG heaters and spray or take manual control of PRZR pressure controller 431K.

c. Check PRZR level - TRENDING TO c. Verify proper operation of PROGRAM charging pump speed controllers or take manual control of speed controllers to control PRZR level.

16 Restore Normal Electric System Alignment:

a. Verify circuit 767 and/or 751 a. Continue with Step 17. WHEN AVAILABLE offsite power available, THEN do Steps 16b,and c.

b. Verify all emergency AC bus b. Perform the following:

normal feed breakers - CLOSED

1) Restore emergency AC busses

~ Bus 14 to normal power supply (Refer

~ Bus 16 to ER-ELEC.1, RESTORATION OF

~ Bus 17 OFFSITE POWER)

~ Bus 18

2) IF normal power is restored to all AC emergency buses.

THEN return to step 7. IF NOT, THEN go to step 17.

c. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4)

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 14 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Establish Normal Plant Conditions:

a. Verify 2 charging pumps - RUNNING a. Perform the following:

l) Manually start charging pumps as necessary.

2) Place selected charging pump speed desired.

controller in AUTO if

b. Verify at least 2 CNMT recirc b. Start CNMT recirc fans as fans - RUNNING necessary (240 kw each).

c. Check CCW pumps - ONLY ONE c. Locally verify two CCW pumps RUNNING running, THEN manually stop one pump.

d. Check radiation monitoring d. Restore sample pumps and systems: radiation monitors as necessary.

(Refer to CHA-RETS-ODCM).

o CNMT vent sample pump RUNNING o Plant vent sample pump RUNNING o All area and process monitors operating as required 18 Check Status Of DC System Loads:

a. Verify TDAFW pump DC oil pump a. Perform the following:

OFF IN AUTO

1) Direct AO to locally check TDAFW AC oil pump running.

IF not running, THEN start pump from MCB.

2) Stop TDAFW pump DC oil pump.

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 15 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Inst Bus C provides power to all MCB manual controllers.

19 Check Status of Battery Chargers:

a. Battery Chargers 1A OR lA1 a. IF BOTH battery chargers are ENERGIZED. deenergized, THEN direct the Electricians to crosstie TSC battery charger to main battery A (Refer to ATTACHMENT TRANSFER BATTERY TO TSC).

b. Battery Chargers 1B OR 1Bl b. IF BOTH battery chargers are ENERGIZED deenergized, THEN direct the Electricians to crosstie TSC battery charger to main battery B (Refer to ATTACHMENT TRANSFER BATTERY TO TSC).

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REV: 2 AP-ELEC.'14/16 L'OSS OF SAFEGUARDS BUS 14/16 PAGE 16 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Restore Equipment Alignment:

a. Verify annunciator L-1. AUX BLDG a. Dispatch AO to restore AUX BLDG VENT SYSTEM CONTROL PANEL ventilation (Refer to T-35A.

EXTINGUISHED AUX AND INTERMEDIATE BUILDING VENTILATION STARTUP AND SHUTDOWN)

b. Restore affected bus equipment as desired o SFP Cooling o Penetration cooling fans o Reactor compartment cooling fans o Hydrogen panel o PA system inverter (Battery Room A) o Auxiliary Bldg lighting (normal supply MCC D, manual throwover to MCC C)(located at MCC C) o Fire system (Refer to SC-3.16.2.3)

c. Check control board annunciator c. Perform alarm response panels - ALARM STATUS VALID FOR procedures for unexpected alarms.

PLANT CONDITIONS

d. Verify control board valve d. Manually align valves as alignment - NORMAL (Refer to necessary.

0-6.13. DAILY SURVEILLANCE LOG)

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REV: 2 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 17 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

21 Verify emergency AC bus Return to Step 7 normal feed breakers closed o Bus 14 o Bus 16 22 Verify Inst Bus B on normal Place Inst Bus B on normal supply supply (Refer to ER-INST.3,INSTRUMENT BUS POWER RESTORATION).

23 Reset UV relay targets on undervoltage cabinets o Bus 14 o Bus 16 24 Notify Higher Supervision 25 Return To Procedure Or Guidance In Effect

-END-

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REV: 2 A ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 1 of 1 AP-ELEC.14 16 APPENDIX LIST TITLE

1) ATTACHMENT TRANSFER BATTERY TO TSC (ATT-24.0)

Distri-1.txt Distribution Sheet Priority: Normal From: E-RIDS2 Action Recipients: Copies:

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Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 010750076:1

Subject:

Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML010750076.

A045- OR Submittal: Emergency Preparedness Plans, Implementing Procedures, Corre Page 1

.aW Distri-l.txt spondence Docket: 05000244 Page 2

C zznzzizy zszuz e t t

~

zxi zi zzzzzzz 8K.:: r ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TELEPHONE AREA cooK 7IE 546.2700 March 12, 2001 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Guy S. Vissing (Mail Stop 14D11)

Project Directorate I-1

Subject:

Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244

~ll'~' ~y >

Gentlemen:

In accordance with 10 CFR 50.4(b)(5), enclosed are revisions to Ginna Station Emergency Plan Implementing Procedures (EPIPs).

We have determined, per the requirements of 10 CFR 50.54(q), that these procedure changes do not decrease the effectiveness of our Nuclear Emergency Response Plan.

Ver trul yours, Peter S; Polfleit Corporate Nuclear mergency Planner Enclosures xc: USNRC Region 1 (2 copies of letter and 2 copies of each procedure)

Resident Inspector, Ginna Station (1 copy of letter and 1 copy of each procedure)

RGSE Nuclear Safety and Licensing (1 copy of letter)

Dr. Robert C. Mecredy (2 copies of letter only)

PSP/jtw

PROCEDURE REVISION NUMBER EPIP 1-6 12 EPIP 3-1 15 EPIP 3-2 EPIP 3-4 EPIP 5-2 24 EPIP 5-5 12 EPIP 5-7 31

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Total Copies:

Item: ADAMS Document Library: ML ADAMS"HQNTADOl ID: 010720392:1

Subject:

Emergency Operating Procedures for R.E. Ginna Nuclear Power Plant.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML010720392.

Page 1

h A002-Docket: 05000244 Page 2

AND A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND EIEClRIC CORPORATlON ~ 89 EAST AVENUE, ROCHESTER, N.Y. I4649400l ~ 716.771-3250 www.rge.corn JOSEPH A. WIDAY VICE PRESIDENT S PLANT MANAGER GINNA STATION February 28, 2001 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I Washington, D.C. 20555

Subject:

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

Dear Mr. Vissing:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, o ep 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):

E Index ECA Index FIG Index E-l, Rev 21 E-3, Rev 27 ECA-3.3, Rev 24 FIG-4.0, Rev 2

Distri-1.txt Distribution Sheet @gal Priority: Normal From: E-RIDS2 g/jg/~]

Action Recipients: Copies:

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Total Copies:

Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID'10530028:1

Subject:

R. E. Ginna - Emergency Operating Procedures Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients c'n RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML010530028.

A002- OR Submittal:Inadequate Core Cooling (Item II.F.2) GL 82-28 Page 1

f, J Docket: 05000244 Page 2

I II 'rvo

,~ A Subsidiory of RGS Energy Group, Inc.

ROCHESTER GAS AND E(ECIIC CORPORATfON ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649CN01 ~ 716.771.3250 www.rge.corn JOSEPH A. WIDAY VICE PRESIDENT E PLANT MANAGER GINNASTATION February 8, 2001 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I Washington, D.C. 20555

Subject:

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

Dear Mr. Vissing:

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):

AP Index FIG Index AP-ELEC.14/16, rev 2 AP-RHR.1, rev 15 FIG-3.1, rev 1

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 10/16/00 PAGE: 1 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRATI'RAP PRES PRFIG STATUS: EF QU 5 YEARS ONLY:

PROCEDURE LAST NEXT EFFECI'ATE NINBER ROCEDURE TITLE REV REVIEW REVIEW ST AP-CCW. 1 LEA GE INTO THE COMPONENT COOLING LOOP 013 10/30/98 05/01/98 05/01/03 EP AP CCW.2 LOSS OF DURING POWER OPERATION 014 05/18/00 08/17/99 08/17/04 EF AP-CCW. 3 LOSS OF CCW - P SHUTDOWN 012 05/18/00 08/17/99 08/17/04 E AP-CR. 1 CONTROL ROOM INACCESSIBIL 016 01/11/00 01/11/00 01/11/ EF AP-CVCS. 1 CVCS LEAK 012 05/01/98 05/01/98 /01/03 EF AP-CVCS. 3 LOSS OF ALL CHARGING FLOW 002 02/11/00 02/2 99 02/26/04 EF AP-CW. 1 LOSS OF A CIRC WATER PUMP 010 07/16/98 5/01/98 05/01/03 EF AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 020 09/0 00 05/01/98 05/01/03 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 009 /22/99 03/22/99 03/22/04 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 09/08/00 05/01/98 05/01/03 EF AP-ELEC.14/16 LOSS OF SAPEGUARDS BUS 14/16 09/08/00 06/09/97 06/09/02 EF AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 002 10 99 06/09/97 06/09/02 EF AP-FW.1 PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER 012 02/11/00 /27/98 02/27/03 EP AP-IA. 1 LOSS OF INSTRUMENT AIR 017 12/02/99 05/01 05/01/03 EP AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 011 12/02/99 12/02/99 12 2/04 EF AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWAL/INS TION 006 02/24/96 05/14/98 05/14/0 EF AP-RCC.2 RCCIRPI MALFUNCTION 008 11/16/98 02/06/97 02/06/02 EF AP-RCC.3 DROPPED ROD RECOVERY 004 11/16/98 02/27/98 02/27/03 EF AP-RCP.1 RCP SEAL MALFUNCTION 013 06/09/00 05/01/98 05/01/03 EF AP-RCS.1 REACTOR COOLANT L K 015 09/08/00 05/01/98 05/01/03 EF AP-RCS.2 LOSS OF REA R COOLANT FLOW 010 12/14/98 05/01/98 05/01/03 EF AP-RCS.3 HIGH REA R COOLANT ACTIVITY 007 08/05/97 08/05/97 08/05/02 EF AP-RCS.4 SHUTDOWN LOCA 011 12/02/99 05/01/98 05/01/03 EF AP-RHR. 1 LOSS OF RHR 014 10/13/00 05/01/98 05/01/03 EP

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 10/16/00 PAGE: 2 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRATT PRAP PRES PRFIG STATUS: EF QU 5 YEARS ONLY:

PROCEDURE LAST NEXT EFFEC1'ATE NUMBER PROCEDURE TITLE REV REVIEW REVIEW ST AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 009 10/13/00 03/31/00 03/31/05 EF AP-SG.1 STEAM GENERATOR TUBE LEAK 000 09/08/00 09/08/00 09/08/05 EF AP-SW.1 SERVICE WATER LEAK 015 10/18/99 06/03/98 06/03/03 EF AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 010 02/12/99 10/10/97 10/10/02 EF AP-TURB.2 TURBINE LOAD REJECTION 017 02/11/00 05/13/98 05/13/03 EF AP-TURB.3 TURBINE VIBRATION 010 02/11/00 02/10/98 02/10/03 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 014 05/01/98 05/01/98 05/01/03 EF AP-TURB.5 RAPID LOAD REDUCTION 005 06/09/00 06/09/00 <<06/09/05 EF TOTAL FOR PRAP 32

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 1 of 17 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE NAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 2 of 17 A. PURPOSE This procedure provides actions to respond to a loss of AC Emergency Bus 14 or Bus 16.

B. ENTRY CONDITIONS/SYMPTOMS

2. SYMPTOMS The symptoms of a LOSS OF SAFEGUARDS BUS 14/16 are;

a. Annunciator J-7, 480V MAIN OR TIE BREAKER TRIP, lit', or

b. Annunciator J-29, 480V TRANSFORMER BREAKER TRIP, lit.

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REV 1 AP-ELEC. 14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 3 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

~ 1 4 ~ 0 4 ~ 1 0 1 I I ~ 1 I I 1 ~

• I 0 1 1 1 1 0 ~ 4 1 1 ~ ~ 1

• 1 ~ 0 I CAUTION o IF A LOSS OF BUS 12A OR 12B HAS OCCURRED. THEN NO OUTSIDE. SHOULD BE PERFORMED.

o IF A TURBINE RUNBACK HAS OCCURRED, THEN AP-TURB.2, TURBINE LOAD REJECTIONS SHOULD BE PERFORMED.

o OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR, 2250 KW FOR 2 HOURS, AND 1950 KW FOR CONTINUOUS SERVICE.

o DO NOT ATTEMPT TO ENERGIZE A BUS THAT IS POTENTIALLY FAULTED.

NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Establish Manual Rod Control

a. Place Rod Control Bank Selector Switch to MANUAL

b. Verify control rod motion stops b. Manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

c. Manually move control rods as necessary 2 Verify Emergency D/G Attempt to start and load emergency Associated With Affected Bus D/G(s) manually. (Refer to RUNNING AND LOADED ER-D/G.l, RESTORING D/Gs) o Bus 14 - D/G A o Bus 16 - D/G B

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 4 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify At Least One Train of Go to ECA-O.O, LOSS OF ALL AC POWER AC Emergency Busses Energized step 1.

to at Least 420 Volts:

o Bus 14 and Bus 18

-OR-o Bus 16 and Bus 17 I I I ~ ~ I I t I

• I I I I I * *

• I I t I I t I I

• I I I I I I ~ I I ~ I I I ~

CAUTION IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 200'F, THEN TRIP THE AFFECTED RCP.

4 Verify CCW Pump Status

a. At least one CCW Pump - RUNNING a. Start one CCW pump (124 KW)

1) IF neither CCW pump can be started, THEN perform the following:

a) Trip the reactor.

b) Trip BOTH RCP's.

c) Go to E-0. REACTOR TRIP OR SAFETY INJECTION.

b. Annunciator A-22, CCW PUMP b. Start second CCW pump (124 KW).

DISCHARGE LO PRESS 60 PSIG-EXTINGUISHED

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 5. of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify Charging Pump Status- Secure letdown flowpaths AT LEAST ONE RUNNING o Close loop B cold leg to REGEN Hx, AOV-427.

o Ensure closed loop A cold leg to EXCESS LETDOWN Hx. AOV-310.

o Ensure closed EXCESS LETDOWN HCV-123.

6 Monitor S/G Level Control: Place MFW regulating valves in MANUAL and control feed flow as o S/G level - TRENDING TO 52% necessary.

o MPW regulating valves CONTROLLING IN AUTO

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 6 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Verify Bus 14 ENERGIZED TO Perform the following:

AT LEAST 420 VOLTS

a. Close loop B cold leg to REGEN Hx, AOV-427.

b. IF steam dump is armed, THEN place STEAM DUMP MODE SELECTOR Switch to MANUAL.

c. Ensure only one charging pump operating.

d. Transfer Inst Bus B to maintenance supply.

e. Return steam dump to AUTO, if desired.

f. Ensure the following equipment operating as necessary:

~ CCW Pump B

~ PRZR Backup Heaters

~ CNMT Recirc Fans B and C

~ Boric Acid Pump B

~ RMW Pump B

~ Reactor Compartment Cooling Fan B

~ Penetration Cooling Fan B

g. IF Bus 14 can NOT be energized, THEN:

o Provide alternate room cooling for D/G A.

o Cross-connect D/G B fuel oil transfer pump to D/G A (Refer to T-27.4 Attachment A).

0 EOP:

REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 7 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Verify Bus 16 ENERGIZED TO Perform the following:

AT LEAST 420 VOLTS

a. Ensure the following equipment operating as necessary:

~ CCM Pump A

~ Charging Pump A

~ PRZR Proportional Heaters

~ CNMT Recirc Fans A and D

~ Boric Acid Pump A

~ RMW Pump A

~ Reactor Compartment Cooling Fan A

~ Penetration Cooling Fan A

b. IF Bus 16 can NOT be energized, THEN:

o Provide alternate room cooling for D/G B.

o Cross-connect D/G A fuel oil transfer pump to D/G B (Refer to T-27.4 Attachment B).

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REV: 1 AP-ELEC. 14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 8 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF VCT level decreased to 5%, charging pump suction will 'swap to the RWST. This may required a load reduction.

9 Check VCT Makeup System:

a. Verify the following: a. Adjust controls as necessary.

1) RMW mode selector switch in AUTO

2) RMW control armed - RED LIGHT LIT

b. Check VCT level: b. Check letdown divert valve.

LCV-112A. aligned to VCT.

o Level GREATER THAN 20% I Manually increase VCT makeup

-OR- flow as follows:

o Level - STABLE OR INCREASING 1) Ensure BA transfer pumps and RMW pumps running.

2) Adjust RMW flow control valve, HCV-ill, to increase RMW flow.

3) Increase boric acid flow as necessary to maintain required concentration.

IF VCT level can NOT be maintained, THEN refer to ER-CVCS.l, REACTOR MAKEUP CONTROL MALFUNCTION, if necessary.

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 9 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check Charging Pump Suction Aligned To VCT:

a. VCT level - GREATER THAN 20% a. IF VCT level can NOT be maintained greater than 5%, THEN perform the following:

1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed

2) Continue with Step ll. WHEN VCT level greater than 20%.

THEN do Step 10b.

b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.

o LCV-112C open o LCV-112B closed

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 10 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: When restarting equipment for recovery, it is preferable to start if equipment on busses being supplied from offsite power. possible.

11 Check CVCS Operation:

a. Charging pumps - AT LEAST ONE a. IF charging pump(s) perform the following:

available'HEN RUNNING

1) Start charging pumps as necessary.

2) Establish greater than 20 gpm charging line flow.

IF NO charging pumps available, THEN go to step 13

b. Charging line flow - GREATER b. Establish charging line flow to THAN 20 GPM REGEN Hx - GREATER THAN 20 GPM

c. Check letdown indications: c. Perform the following:

o Check PRZR level - GREATER 1) Close loop B cold leg to THAN 13% REGEN Hx, AOV-427.

o Letdown flow - APPROXIMATELY 2) Close letdown orifice valves 40 GPM (AOV-200A, AOV-2008, and AOV-202) o Letdown flow - STABLE

3) IF PRZR level greater than 13'/, THEN go to Step 12. IF NOT, THEN continue with Step 14. WHEN PRZR level greater than 13%. THEN do Steps 12 and 13.

d. Adjust charging pump speed and HCV-142 as necessary to restore PRZR level and labyrinth seal D/P

e. Go to Step 13

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 11 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Steps 12 and 13 may be performed concurrently.

12 Establish Normal Letdown: Perform the following steps in sequence to establish excess

a. Establish charging line flow to letdown, if desired:

REGEN Hx - GREATER THAN 20 GPM o Place excess letdown divert

b. Place letdown controllers in valve. AOV-312, to NORMAL MANUAL at 40/ open o Ensure CCW from excess letdown

~ TCV-130 open, AOV-745

~ PCV-135 o Ensure RCP seal return isolation

c. Open AOV-427 valve open. MOV-313

d. Open letdown orifice valves as o Open excess letdown isolation necessary valve, AOV-310

e. Place TCV-130 in AUTO at 105'F o Slowly open HCV-123 to maintain excess letdown temperature less

f. Place PCV-135 in AUTO at 250 psig than 195'F and pressure less than 100 psig

g. Adjust charging pump speed and HCV-142 as necessary 13 Verify PRZR Heaters Restored: IF adequate D/G capacity available for PRZR heaters (400 kw each o PRZR proportional heater breaker bank), THEN perform the following:

CLOSED

a. Reset and close PRZR o PRZR backup heater breaker- proportional heater breaker if RESET/IN AUTO necessary.

b. Reset PRZR backup heater breaker and return to AUTO if necessary.

IF adequate D/G capacity NOT available, THEN refer to ER-PRZR.1.

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 12 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify Normal Rod Control Restored:

a. Annunciator C-5. PPCS ROD a. IF alarm is due to a loss of SEQUENCE OR ROD DEVIATION power to MRPI. THEN maintain EXTINGUISHED rods in manual AND minimize rod motion.

IF alarm is due to actual rod misalignment. THEN refer to AP-RCC.2, RCC/RPI MALFUNCTION, while continuing with this procedure.

b. Annunciator E-28, POWER RANGE b. Perform the following:

ROD DROP ROD STOP - EXTINGUISHED

1) Place rod control bank selector switch in MANUAL.

2) Reset NIS rod drop rod stop signals (at NIS racks) as necessary.

c. Annunciator F-15, RCS TAVG DEV c. Go to step 15 4'F - EXTINGUISHED

d. Place rod control bank selector switch in AUTO if desired

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 13 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish Stable Plant Conditions:

a. Check Tavg - TRENDING TO TREF a. Insert control rods or, if necessary, decrease turbine load to match Tavg to Tref.

b. Check PRZR pressure - TRENDING b. Verify proper operation of PRZR TO 2235 PSIG heaters and spray or take manual control, of PRZR pressure controller 431K.

c. Check PRZR level - TRENDING TO c. Verify proper operation of PROGRAM charging pump speed controllers or take manual control of speed controllers to control PRZR level.

16 Restore Normal Electric System Alignment:

a. Verify circuit 767 and/or 751 a. Continue with Step 17. WHEN AVAILABLE offsite power available, THEN do Steps 16b and c.

b. Verify all emergency AC bus

- CLOSED

b. Perform the following:

normal feed breakers

1) Restore emergency AC busses

~ Bus 14 to normal power supply (Refer

~ Bus 16 to ER-ELEC.1, RESTORATION OF

~ Bus 17 OFFSITE POWER)

~ Bus 18

2) IF normal power is restored to all AC emergency buses, THEN return to step 7. IF NOT, THEN go to step 17.

c. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4)

i l

I

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REV: 1 AP-ELEC. 14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 14 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Establish Normal Plant Conditions:

a. Verify 2 charging pumps - RUNNING a. Perform the following:

l) Manually start charging pumps as necessary.

2) Place selected charging pump speed controller in AUTO if desired.

b. Verify at least 2 CNMT recirc b. Start CNMT recirc fans as fans - RUNNING necessary (240 kw each).

c. Check CCW pumps - ONLY ONE c. Locally verify two CCW pumps RUNNING running, THEN manually stop one pump.

d. Check radiation monitoring d. Restore sample pumps and systems: radiation monitors as necessary.

(Refer to CHA-RETS-ODCM).

o CNMT vent sample pump RUNNING o Plant vent sample pump RUNNING o All area and process monitors operating as required 18 Check Status Of DC System Loads:

a. Verify TDAFW pump DC oil pump a. Perform the following:

OFF IN AUTO l) Direct AO to locally check TDAFW AC oil pump running.

IF not running, THEN start pump from MCB.

2) Stop TDAFW pump DC oil pump.

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REV' AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 15 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Inst Bus C provides power to all MCB manual controllers.

19 Check Status of Battery Chargers:

a. Battery Chargers 1A OR 1A1 a. IF BOTH battery chargers are ENERGIZED. deenergized. THEN direct the Electricians to crosstie TSC battery charger to main battery A (Refer to ATTACHMENT TRANSFER BATTERY TO TSC).

b. Battery Chargers 1B OR 1Bl b. IF BOTH battery chargers are ENERGIZED deenergized, THEN direct the Electricians to crosstie TSC battery charger to main battery B (Refer to ATTACHMENT TRANSFER BATTERY TO TSC).

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 16 of 17 STEP ACTION/EXPECTED RESPONSE 'RESPONSE NOT OBTAINED 20 Restore Equipment Alignment:

a. Verify annunciator L-l, AUX BLDG a. Dispatch AO to restore AUX BLDG VENT SYSTEM CONTROL PANEL ventilation (Refer to T-35A.

EXTINGUISHED AUX AND INTERMEDIATE BUILDING VENTILATION STARTUP AND SHUTDOWN)

b. Restore affected bus equipment as desired o SFP Cooling o Penetration cooling fans o Reactor compartment cooling fans o Hydrogen panel o PA system inverter (Battery Room A) o Auxiliary Bldg lighting (normal supply MCC D. manual throwover to MCC C)(located at MCC C) o Fire system (Refer to SC-3.16.2.3)

c. Check control board annunciator c. Perform alarm response panels - ALARM STATUS VALID FOR procedures for unexpected alarms.

PLANT CONDITIONS

d. Verify control board valve d. Manually align valves as alignment - NORMAL (Refer to necessary.

0-6.13, DAILY SURVEILLANCE LOG)

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REV: 1 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 17 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

21 Verify emergency AC bus Return to Step 7 normal feed breakers closed o Bus 14 o Bus 16 22 Verify Inst Bus B on normal Place Inst Bus B on normal supply supply (Refer to ER-INST.3,INSTRUMENT BUS POWER RESTORATION).

23 Reset UV relay targets on undervoltage cabinets o Bus 14 o Bus 16 24 Notify Higher Supervision 25 Return To Procedure Or Guidance In Effect

-END-

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REV: 1 A ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 1 of 1 AP-ELEC.14 16 APPENDIX LIST TITLE

1) ATTACHMENT TRANSFER BATTERY TO TSC (ATT-24.0) I

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REV 14 AP-RHR.1 LOSS OF RHR PAGE 1 of 13 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE'ANAGER lo iz ao-EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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REV: 14 AP-RHR.l LOSS OF RHR PAGE 2 of 13 A. PURPOSE This procedure provides guidance in the event of a loss of RHR cooling at or above normal loop levels.

(i.e. RCS loop levels of 64 inches or greater)

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure is entered from;

a. FR-C.3, RESPONSE TO SATURATED CORE COOLING, or

b. AP-ELEC.3, LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350'), when RHR flow can NOT be restored, or

c. AP-CCW.3, LOSS OF CCW PLANT SHUTDOWN when CCW is inadequate for RHR cooling

2. SYMPTOMS The following are symptoms of LOSS OF RHR;

a. No RHR pumps running, or

b. Annunciator A-20, RESIDUAL HEAT REMOVAL LOOP LO FLOW 2900 GPM (Set at 400 GPM per 0-2.2 in RHR Cooling mode), lit, or

c. Unexpected increase in temperature while on RHR cooling, or

d. Erratic or no flow on FI-626, RHR Loop Flow, or

e. Annunciator J-9, SAFEGUARD BREAKER TRIP, lit.

0 EOP TITLE:

REV: 14 AP-RHR.1 LOSS OF RHR PAGE 3 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

~ ~ ~ I ~ ~ ~ ~ ~ i 4 ~ ~ ~ ~ ~ ~ ~ ~ ~ I 1 ~ 1 ~ 1 1 1 4 I 0 1 1 1 ~

CAUTION DO NOT START ANOTHER RHR PUMP UNTIL THE CAUSE OF THE ABNORMAL RHR INDICATIONS HAS BEEN DETERMINED. IF A RUNNING PUMP HAS TRIPPED FOR REASONS OTHER THAN LOSS OF SUCTION FLOW. THEN REDUNDANT PUMP MAY BE STARTED.

NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Check PRZR Wide Range Level IF RCS loop level indicator in GREATER THAN 0 INCHES service and loop level less than 64 inches, THEN go to AP-RHR.2 ~

LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.

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REV 14 AP-RHR. 1 LOSS OF RHR PAGE 4 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check Be If RHR Stopped:

Pump(s) Should

a. RHR pump - ANY RUNNING a. Go to Step 3.

b. Check RHR pump flow - LESS THAN b. Decrease RHR flow as necessary.

1500 GPM PER PUMP IF RHR flow can NOT be controlled, THEN perform the following:

1) Stop running RHR pump.

2) Dispatch an AO with a locked valve key to locally throttle RHR Hx outlet valves to approximately half open.

~ A RHR Hx. HCV-625 handwheel

~ B RHR Hx, HCV-624 handwheel

3) Start an RHR pump.

4) Direct AO to locally adjust RHR flow to less than 1500 gpm.

c. RHR pumps cavitating: c. Go to Step 17.

o RHR pump flow - OSCILLATING

-OR-o RHR pump NPSH - APPROXIMATELY ZERO (PPCS group GD NPSH)

d. Stop RHR pumps

EOP. I LE.

REV: 14 AP-RHR.1 LOSS OF RHR PAGE 5 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o DO NOT INITIATE ANY ACTIONS WHICH MAY ADD POSITIVE REACTIVITY TO THE CORE.

o NOTIFY S/G OFFICE THAT CNMT BREATHING AIR MAY BE LOST.

o IF REFUELING IN PROGRESS. THEN STOP REFUELING OPERATIONS (NOTIFY REFUELING SRO) .

NOTE: Personnel remaining in CNMT to assist in event mitigation should consult Health Physics for changes in radiological concerns.

3 Initiate Actions To Protect Personnel In CNMT:

a. Evacuate non-essential personnel from CNMT

b. Verify all available CNMT RECIRC b. Manually start available CNMT fan(s) RUNNING RECIRC fans.

c. Initiate monitoring of CNMT area c. Refer to appropriate alarm and process radiation monitors response procedures for required actions.

d. Verify CNMT penetrations with d. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, close all CNMT direct access to outside penetrations to outside atmosphere - CLOSED (Refer to atmosphere.

Attachment CNMT CLOSURE)

~ l EOP:

REV 14 AP-RHR.1 LOSS OF RHR PAGE 6 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check RHR Cooling Valve Manually or locally align valves as Alignment NORMAL (Refer to necessary.

Attachment NORMAL RHR COOLING)

CAUTION THE RHR HX OUTLET VALVES (HCV-624 AND HCV-625) WILL FAIL OPEN ON LOSS OF INSTRUMENT AIR PRESSURE.

5 Check IA System:

a. Verify 2 IA compressors - RUNNING a. Manually start IA compressors as necessary (75 kw each). IF IA compressors can NOT be started manually. THEN dispatch AO to locally reset and start compressors (75 kw each).

b. Check IA supply b. IF IA pressure can NOT be restored. THEN perform the o Pressure - GREATER THAN following:

60 PSIG

1) Dispatch AO with a locked o Pressure - STABLE OR valve key to locally throttle INCREASING RHR Hx outlet valves to approximately half open.

~ A RHR Hx, HCV-625 handwheel

~ B RHR Hx, HCV-624 handwheel

2) WHEN conditions permits THEN refer to AP-IA.l, LOSS OF INSTRUMENT AIR, to restore IA.

0 0 F

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REV: 14 AP-RHR.1 LOSS OF RHR PAGE 7 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• 6 Monitor RCS Temperature Go to Step 8.

GREATER THAN 200 F

~ I 1 1 4 1 4 P 4 ~ ~ l

• I ~ 1 4 0 4 I ~ ~ I ~ 1 I P ~ t P 4 4 1 I 4 4 4 0 ~ 4 ~

CAUTION o CHANGES IN RCS PRESSURE COULD RESULT IN INACCURACIES IN RCS LOOP LEVEL INDICATION o UNSTABLE OR FLUCTUATING LEVEL INSTRUMENTS SHOULD NOT BE RELIED ON FOR INDICATION OF RCS INVENTORY.

7 Verify RCS Intact: Perform the following:

o PRZR level - GREATER THAN 5% AND a. Verify charging line flow STABLE control valve, HCV-142. open as necessary.

o RCS pressure - STABLE

b. Ensure charging line valve to o RCS subcooling based on core loop B cold leg, AOV-294, open.

exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING c. Start charging pumps as necessary.

o RCS vent paths - CLOSED

d. Control charging pump speed and letdown flow as necessary to stabilize RCS conditions.

~ PRZR pressure

~ PRZR level

~ Loop level IF charging flow greater than 75 gpm with letdown isolated OR unable to verify RCS inventory, THEN go to AP-RCS.4. SHUTDOWN LOCA.

EOP TITLE.

REV: 14 AP-RHR.1 LOSS OF RHR PAGE 8 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Establish Conditions To Start RHR Pump:

a. RHR pump - AVAILABLE a. Perform the following:

1) Start trending core exit TCs.

2) IF RCS closed, THEN go to Step 10. IF RCS open to atmosphere, THEN go to Step 16.

b. Verify CCW cooling to RHR system b. Perform the following:

in service

1) Ensure at least one CCW pump o CCW pumps - AT LEAST ONE running.

RUNNING

2) Open MOV-738A and MOV-738B as o CCW to RHR Hxs. MOV-738A AND necessary.

MOV-738B - OPEN AS NECESSARY IF CCW can NOT be restored, THEN continue with Step 9 while attempting to restore CCW (Refer to AP-CCW.3, LOSS OF CCW - PLANT SHUTDOWN).

c. Close RHR pump flow control valves (controllers at 100%

demand)

~ HCV-624

~ HCV-625

d. Place RHR Hx bypass valve.

HCV-626. to MANUAL and close valve

EOP ITLE.

REV 14 AP-RHR. 1 LOSS OF RHR PAGE 9 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

~ I 4 4 ~ ~ I 0 1 ~ ~ 4 0 ~ ~ 0 ~ I 1 0 ~ I 4 1 I ~ I 4 I ~ l 0 ~ 1 P 0 0 0 ~

• CAUTION STARTING AN RHR PUMP MAY RESULT IN AN RCS LEVEL OR PRESSURE DECREASE DUE TO SHRINK OR VOID COLLAPSE.

9 Restore RHR Flow:

a. Start one RHR pump - RHR PUMP a. Go to Step 9e.

RUNNING

b. Check RHR flow - LESS THAN b. Manually adjust RHR flow as 1500 GPM PER PUMP necessary.

c. Adjust RHR Hx bypass flow control valve. HCV-626, to desired flowrate

d. Place RHR Hx bypass flow control valve. HCV-626 'ontroller in AUTO

e. RHR flow - RESTORED e. Perform the following:

1) Start trending core exit T/Cs.

2) IF RCS closed. THEN go to Step 10. IF RCS vented to atmosphere. THEN go to Step 16.

f. Open RHR Hx outlet valves as necessary to control RCS temperature

~ HCV-624

~ HCV-625

EOP:

REV: 14 AP-RHR.1 LOSS OF RHR PAGE 10 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Monitor RCS Temperature:

a. RCS temperature - STABLE OR a. IF RCS closed. THEN go to DECREASING Step ll. IF RCS open to atmosphere. THEN go to Step 16.

b. Go to Step 19 11 Check Any S/G Level GREATER Verify at least 200 gpm AFW flow THAN 17% available. IF NOT, THEN go to Step 17.

12 Check RCS Pressure GREATER Increase RCS pressure to greater THAN 300 PSIG than 300 psig. IF RCS pressure can NOT be increased, THEN go to Step 17.

13 Check RCP Status ANY RCP Perform the followig:

RUNNING

a. Establish conditions for starting an RCP.

o Verify bus llA or llB energized.

o Refer to Attachment RCP START.

b. Start one RCP.

IF an RCP can NOT be started, THEN verify natural circulation. (Refer to Attachment NC.)

IF natural circulation NOT verified. THEN increase dumping steam.

I ~ 4 I S EOP:

REV: 14 AP-RHR.1 LOSS OF RHR PAGE ll of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Establish Condenser Steam Dump Manual Control:

a. Verify condenser available: a. Perform the following:

o Any MSIV - OPEN 1) Place S/G ARV controller in MANUAL and open ARVs as o Annunciator G-15. STEAM DUMP necessary to stabilize RCS ARMED - LIT temperature.

2) Go to Step 15.

b. Place condenser steam dump controller HC-484 in MANUAL

c. Place steam dump mode selector switch to MANUAL

d. Open steam dump valves as necessary to stabilize RCS temperature 15 Monitor RCS Temperature:

a. RCS temperature - STABLE OR a. IF dumping steam does NOT DECREASING provide adequate cooling, THEN perform the following:

1) Initiate S/G blowdown from both S/Gs.

2) Maintain both S/G levels stable by controlling AFW flow.

3) Go to Step 17.

b. Go to Step 18

e EOP:

REV: 14 AP-RHR.1 LOSS OF RHR PAGE 12 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check RCS Conditions:

a. Rx vessel head - REMOVED a. Go to Step 17.

b. Stop refueling operations if in progress

c. Verify Refueling Cavity Level c. Increase refueling cavity level GREATER THAN 23 FEET ABOVE to greater than 23 feet (Refer VESSEL FLANGE to 0-15.3, FILLING REFUELING CANAL).

d. Verify refueling cavity sweep d. Locally start refueling cavity fans - RUNNING sweep fans if available.

17 Check CCW System Operation: To restore CCW cooling to RHR Hxs.

perform the following:

o CCW pumps - AT LEAST ONE RUNNING

a. Ensure the standby CCW pump is CCW to RHR Hxs, MOV-738A AND running.

MOV-738B - OPEN AS NECESSARY

b. Open MOV-738A and MOV-738B as o Annunciator A-21. COMP COOLING necessary.

HX OUT HI TEMP .- EXTINGUISHED IF CCW can NOT be restored, THEN o Annunciator A-22, CCW PUMP continue attempts to restore CCW DISCHARGE LO PRESS - EXTINGUISHED (Refer to AP-CCW.3, LOSS OF CCW-PLANT SHUTDOWN).

o Annunciator A-30, CCW PUMP INLET HEADER HI TEMP - EXTINGUISHED

• ' f I 6 b 'I

EOP: TITLE:

REV 14 AP-RHR. 1 LOSS OF RHR PAGE 13 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Consult with Plant Staff to determine alternatives for long term cooling.

18 Monitor RHR Cooling: Perform the following:

o RHR cooling - RESTORED a. Evaluate alternatives for long term cooling (Consult Plant o RCS temperature - STABLE OR Staff)

DECREASING

~ Consider establishing secondary heat sink

~ Refer to ER-RHR.l. RCDT PUMP OPERATION FOR CORE COOLING

~ Consider RCS feed and bleed

b. Continue attempts to restore RHR to operable.

c. Return to Step 3.

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

19 Notify Higher Supervision 20 Return to Procedure Or Guidance In Effect

-END-

EOP:

REV 14 AP-RHR. 1 LOSS OF RHR PAGE 1 of 1 AP-RHR.1 APPENDIX LIST TITLE

1) FIGURE MIN SUBCOOLING (FIG-1.0)

2) ATTACHMENT NORMAL RHR COOLING (ATT-14.0)

3) ATTACHMENT RCP START (ATT-15. 0)

4) ATTACHMENT NC (ATT-13.0)

5) ATTACHMENT CNMT CLOSURE (ATT-3.1)

7

~

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Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 010450039:1

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML010450039.

Page 1 a/(y

A002- OR Submittal:Inadequate Core Cooling (Item II.F.2) GL 82-28 Docket: 05000244 Page 2

p ass A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. Id6d9CXUI ~ 716 77I-3250 www.rge.corn JOSEPH A. WIDAY VICE PRESIDENT E PIANT MANAGER GINNA STATION February 1, 2001 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I Washington, D.C. 20555

Subject:

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

Dear Mr. Vissing:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, se 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):

ATT Index E Index ES Index ATT-2.1, rev 5 E-1, rev 20 ES-1.3, rev 30

P ir/or Distri68.txt P Yr$

Distribution Sheet

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Item: ADAMS Document Library: ML ADAMS"HQNTADOl ID: 010240314:1

Subject:

Revision to Emergency Plan Implementing Procedures.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

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A045 - OR Submittal: Emergency Preparedness Plans, Implementing Procedures, Corre Page 1

'a Distri68.txt spondence Docket: 05000244 Page 2

t zzziriz ANO // IIIII/II/

/

Lian Oela1 zzgyzf'nziIII

/ IIIIII////I iud(ZVZ ~C.jf I 'TATE ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TELEPHONE AREA coDE Tld 546.2700 V

January 17, 2001 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Guy S. Vissing (Mail Stop 14D11)

Project Directorate I-1

Subject:

Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:

In accordance with 10 CFR 50.4(b)(5), enclosed are revisions to Ginna Station Emergency Plan Implementing Procedures (fPIPs).

We have determined, per the requirements of 10 CFR 50.54(q), that these procedure changes do not decrease the effectiveness of our Nuclear Emergency Response Plan.

Ver truly yours, Peter S. Polfleit Corporate N cle r Emergency Planner Enclosures xc: USNRC Region 1 (2 copies of letter and 2 copies of each procedure)

Resident Inspector, Ginna Station (1 copy of letter and 1 copy of each procedure)

RG&E Nuclear Safety and Licensing (1 copy of letter)

Dr. Robert C. Mecredy (2 copies of letter only)

PSP/jtw

PROCEDURE REVISION NUMBER EPIP 1-0 26~

EPIP 2-1 EPIP 5-1 ~oy' EPIP 5-2

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Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 010220472:1

Subject:

Revision 26 to R.E. Ginna emergency action level technical bases for procedure EPIP-1.

0 Ginna Station event evaluation and classification.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML010220472.

Page 1

Distri-6.txt A045 - OR Submittal: Emergency Preparedness Plans, Implementing Procedures, Corre spondence Docket: 05000244 Page 2

II ROCHESTER GAS 6 ELECTRIC CORPORATION DOCUMENT CONTROL Document Transmittal Transmittal: 200101016 010 To: DOCUMENT CONTROL DESK Date: 01/17/2001 US NRC Holder: 1217 ATT: GUY VISSING PROJECT DOCTORATE 1-1 WASHINGTON DC 20555 LISTED BELOW ARE NEW OR REVISED CONTROLLED DOCUMENTS. REVIEW THE ATTACHED INSTRUCTION LETTER (IF APPLICABLE), AND UPDATE YOUR CONTROLLED DOCUMENT IN ACCORDANCE WITH EP-3-S-0901 Doc Id Doc Title Rev Rev Date Qty EAL-TECHBASES R.ED GINNA EMERGENCY ACTION LEVELS 026 01/17/2001 1 TECHNICAL BASES FOR PROCEDURE EPIP-1.0 GINNA STATION,EVENT EVALUATION AND CLASSIFICATION Receipt Acknowledgement and Action Taken:

Signature Date Return ENTIRE FORM to: Rochester Gas &. Electric Corporation Ginna Station - Records Management 1503 Lake Road Ontario, New York 14519

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Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003776378:1

Subject:

R. E. Ginna Revision to Emergency Plan Implementing Procedures Body.

ADAMS DISTRIBUTION NOTIFICATION.

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A045 OR Submittal: Emergency Preparedness Plans, Implementing Proced ures, Correspondence Docket: 05000244 Page 1

EE NSR zest// zzjjj/jj// ~4 ~ 0 I~ 8 AND NOES' SrZg /I @msgr i ulZi88'I//IIjjj/ 'SRSE ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.y. 14649-0001 T E S. E P H 0 N E

• REA coDE 7le 546-2700 December 4, 2000 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Guy S. Vissing (Mail Stop 14D11)

Project Directorate I-1

Subject:

Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:

In accordance with 10 CFR 50.4(b)(5), enclosed are revisions to Ginna Station Emergency Plan Implementing Procedures (EPIPs).

We have determined, per the requirements of 10 CFR 50.54(q), that these procedure changes do not decrease the effectiveness of our Nuclear Emergency Response Plan.

Ver yours, Peter S. Polfl Corporate le r Emergency Planner Enclosures xc: USNRC Region 1 (2 copies of letter and 2 copies of each procedure)

Resident Inspector, Ginna Station (1 copy of letter and 1 copy of each procedure)

RG&E Nuclear Safety and Licensing (1 copy of letter)

Dr. Robert C. Mecredy (2 copies of, letter only)

PSP/jtw

4 r '"

p l

PROCEDURE REVISION NUMBER EPIP 2-14 14 EPIP 5-1 19 EPIP 5-7 30

A" ~ i io/zyf~

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Ifern: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003764539:1

Subject:

Ginna Nuclear Power Plant Revised Emergency Plan Implementing Procedures Body:

ADAMS DISTRIBUTION NOTIFICATION.

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A045 - OR Submittal: Emergency Preparedness Plans, implementing Procedures, Corre Page 1

Disfri60.txt spondence Docket: 05000244 Page 2

g/%'v

$+ ~

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item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003762431:1

Subject:

Emergency Operating Procedures for R.E. Ginna Nuclear Power Plant Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003762431.

Page 1

Distri58.fxt A002 - OR Submittal:inadequate Core Cooling (Item II.F.2) GL 82-28 Docket: 05000244 Page 2

WHO A Subsidiory of RGS Energy Group, Inc.

ROCHESTER GAS AND EtECIIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. Id6d94001 ~ 716-771-3250 www.rge.corn JOSEPH A. WIDAY VICE PRESIDENT IL PLANT MANAGER GINNA STATION October 13, 2000 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I Washington, D.C. 20555

Subject:

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

Dear Mr. Vissing:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, ose 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):

AP Index AP-RHR.2, Rev. 9 ATT Index ES-1.3, Rev. 29 ES Index FIG-2.0, Rev. 2 FIG Index FIG-4.0, Rev. 1 ATT-15.0, Rev. 6 ATT-16.2, Rev. 1 ATT-17.0, Rev. 10 AP-RHR.1, Rev. 14

'l\'

C Distri-4.txt Distribution Sheet Priority: Normal From: E-RIDS3 Action Recipients: Copies:

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Total Copies:

Item: ADAMS Document Library: ML ADAMS"HQNTADOI ID: 003759925:1

Subject:

Revision to Emergency Plan Implementing Procedures.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003759925.

Page 1

i~

Distri-4.txt A045 - OR Submittal: Emergency Preparedness Plans, implementing Procedures, Corre spondence Docket: 05000244 Page 2

////////// //////////

//~~ Zi///'/// /UZI///

k //////// //////////////

ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 TELEPHONE AREA cooK 710 546.2700 October 6, 2000 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Guy S. Vissing (Mail Stop 14D11)

Project Directorate l-1

Subject:

Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:

In accordance with 10 CFR 50.4(b)(5), enclosed are revisions to Ginna Station Emergency Plan Implementing Procedures (EPIPs).

We have determined, per the requirements of 10 CFR 50.54(q), that these procedure changes do not decrease the effectiveness of our Nuclear Emergency Response Plan.

Very truly yours, Peter S. Polfl Corporate ucl ar Emergency Planner Enclosures xc: USNRC Region 1 (2 copies of letter and 2 copies of each procedure)

Resident Inspector, Ginna Station (1 copy of letter and 1 copy of each procedure)

RGSE Nuclear Safety and Licensing (1 copy of letter)

Dr. Robert C. Mecredy (2 copies of letter only)

PSP/jtw

PROCEDURE REVISION NUMBER EPIP 1-9 19 EPIP 2-18 12 EPIP 4-7 15 EPIP 5-1 18 EPIP 5-7 29

e yP~(

Distri42.txt Distribution Sheet vi.~

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Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003754664:1

Subject:

Revision 14 for Technical Requirements Manual for Ginna Station.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003754664.

pa~

Page 1

0 1 y

I t

Distri42.txt A001 - OR Submittal:.General Distribution for Power Reactor (10 CFR 50) Submittals Docket: 05000244 .

P.age 2

l P

h

ROCHESTER GAS & ELECTRIC CORPORATION DOCUMENT CONTROL Document Transmittal Transmittal: 200009017 055 To: DOCUMENT CONTROL DESK Date: 09/19/2000 US NRC Holder: 1217 ATT: GUY VISSING PROJECT DOCTORATE 1-1 WASHINGTON DC 20555 LISTED BELOW ARE NEW OR REVISED CONTROLLED DOCUMENTS. REVIEW THE ATTACHED INSTRUCTION LETTER (IF APPLICABLE), AND UPDATE YOUR CONTROLLED DOCUMENT IN ACCORDANCE WITH EP-3-S-0901 Doc Id Doc Title Rev Rev Date Qty TECHNICAL REQUIREMENTS MANUAL FOR 014 09/20/2000 1 GINNA STATION Receipt Acknowledgement and Action Taken:

Signature Date Return ENTIRE FORM to: Rochester Gas 8 Electric Corporation Ginna Station - Records Management 1503 Lake Road Ontario, New York 14519

Rochester Gas and Electric Corporation SEp;;., <0<~~

Inter-Office Correspondence RECORDS If'~;AGE'.vfENT September 18, 2000

Subject:

Technical Requirements Manual (TRM) Revision 14 To: Distribution Attached are the revised pages for the Ginna Station Technical Requirements Manual (TRM). The changes included within Revision 14 are summarized as follows:

Section TR 3.9.1 has been revised to include requirements for the storage of recently offloaded spent fuel in region 1 of the spent fuel pool. A new Bases section is also included in this change.

2. The entire TRM is being reissued due to changes in sofbvare and formatting. The general formatting changes are summarized in the attachment to this correspondence.

Revision 14 of the TRM is considered effective September 20, 2000. Instructions for the necessary changes to your controlled copy of the ITS are as folows:

Volume Section Remove Insert TRM all pages new pages Please contact Tom Harding (extension 3384) ifyou h ve any questions.

Thorn . Harding

The following is a listing of the changes that are being generically applied to the TRM I) The solid line at the bottom or top of a page of continued text has been deleted.

2) The use of the words "(continued)" at the bottom or top of a page of continued text has been deleted. Within the Actions tables the page break is maintained only after a 1" level logic so that the continuation is implicit.

3) The sub-section title or topic is deleted from each additional page of the sub-section or topic.

4) .'ection 3.0 has been given a combined title due to the two subsections having the same numbering. "LIMITINGCONDITION FOR OPERATION (LCO)

AND SURVEILLANCE REQUIREMENT (SR) APPLICABILITY"

5) For all notes, the words "NOTE" or "NOTES" which currently appear in the middle of a dashed line are moved under the dashed line and the "-NOTE-" is generically used in all cases including plural.

6) The page numbers are restarted for each individual sub-section.

7) In all tables the footnotes now appear at the end of the table, not on every page of the table.

1 ci Distri95.txt Distribution Sheet Priority: Normal g~((x)~~

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Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003750962:1

Subject:

\

Ginna Station Emergency Operating Procedures.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003750962.

Page 1

Distri95.txt A002 - OR Submittal:Inadequate Core Cooling (Item II.F.2) GL 82-28 Docket: 05000244 Page 2

AND A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND EIECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649000l ~ 716.771-3250 www.rge.corn JOSEPH A. WIDAY VICE PRESIDENT*ILANTMANAGER GINNA STATION September 11, 2000 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I Washington, D.C. 20555

Subject:

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

Dear Mr. Vissing:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, a.J A. Widay

'eph 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 ATT-16.1, Rev 0 ATT Index ATT-16.2, Rev 0 ES Index ATT-24.0, Rev 0 AP-ELEC.1, Rev 20 ES-1.1, Rev 19 AP-ELEC.3, Rev 8 AP-ELEC.14/16, Rev 1 AP-RCS.1, Rev 15 AP-SG.1, Rev 0

gu-ZW'i q)yf~~

Distri51.txt Distribution Sheet EP)fPj ~

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0 OK I 0 Hagan 1 Paper Copy FILE CENTER 0 1 Paper Copy Dennis agan 0 OK External Recipients: .

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Item: ADAMS Document Library: ML ADAMS HQNTAD01 ID: 003755319:1

Subject:

Revision 42 to Emergency Plan Implementing Procedures for R.E. Ginna.

Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003755319.

A045- OR Submittal: Emergency Preparedness Plans, Implementing Procedures, Corre Page 1

I I Distri5l.txt spondehce Docket: 05000244 Page 2

J l IIIIIIIIII' IIIIII II li'llllEIIII IIIIIIIIII t L III0%I> ~

ROCHFSTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TELEPHONE ARE* coDE /la 546.2700 September 11, 2000 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Guy S. Vissing (Mail Stop 14D11)

Project Directorate I-1

Subject:

Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:

In accordance with 10 CFR 50.4(b)(5), enclosed is a revision to a Ginna Station Emergency Plan Implementing Procedure (EPIP).

We have determined, per the requirements of 10 CFR 50.54(q), that these procedure changes do not decrease the effectiveness of our Nuclear Emergency Response Plan.

Ver truly yours, Peter S. Polfle Corporate c ar Emergency Planner Enclosures xc: USNRC Region 1 (2 copies of letter and 2 copies of each procedure)

Resident Inspector, Ginna Station (1 copy of letter and 1 copy of each procedure)

RGSE Nuclear Safety and Licensing (1 copy of letter)

Dr. Robert C. Mecredy (2 copies of letter only)

PSP/jtw

l 1

~i

PROCEDURE REVISION NUMBER EPIP 1-5 42

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 07/25/00 PAGE:

REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PREPIP EMERGENCY PLAN IMPLEMENTING PROCEDURE PARAMETERS: DOC TYPES - PREPIP STATUS: BF 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST EPIP-I ~ 0 GINNA STATION EVENT EVALUA ION AND CLASSIFICATION 025 11/19/97 11/19/97 11/19/01 EF EPIP-1=1 UNUSUAL EVENT 002 12/09/96 12/09/96 12/09/01 E EPIP-1 2 ALERT 003 12/09/96 12/09/96 12/09/0 EF EPIP-1-3 SITE AREA EMERGENCY 005 12/09/96 01/23/98 01 0/02 BF EPIP-1-4 GENERAL EMERGENCY 004 12/09/96 12/09/9 12/09/01 'EF EPIP 1-5 NOTIFICATIONS 041 07/25/00 25/00 07/25/05 EF EPIP-1-6 SITE EVACUATION 011 07 /00 07/25/00 07/25/05 EF EPIP-1-7 ACCOUNTABILITY OF PERSONNEL 8 07/27/99 07/27/99 07/27/04 EF EPIP-1-8 SEARCH AND RESCUE OPERATION 00 05/16/00 05/16/00 05/16/05 EF EPIP-1-9 TECHNICAL SUPPORT CENTER ACTIVATION 018 0 21/00 06/21/00 06/21/05 EF EPIP I 10 OPERATIONAL SUPPORT CENTER (OSC) ACTIVATION 010 07/25 0 07/25/00 07/25/05 EF EPIP-I 11 SURVEY CENTER ACTIVATION 021 05/16/00 16/00 05/16/05 EF BPIP-1-12 REPAIR AND CORRECI'IVE ACTION GUIDELINES DURING EM GENCY SITUATIONS 007 06/21/00 06/21 06/21/05 EF EPIP-1-13 LOCAL RADIATION EMERGENCY 003 08/04/95 01/23/98 01 /02 EF EPIP-1-15 USE OF THB HEALTH PHYSICS NETWORK HPN 005 04/24/96 03/03/99 03/03/04 F EPIP-1-16 RADIOACTIVE LIQUID RELEASE TO LAKE ARID OR DEER CREEK 004 02/13/98 02/13/98 02/13/02 EF EPIP-I-I7 PLANNING FOR ADVERSE WEATHE 002 06/21/00 06/21/00 06/21/05 EF EPIP-2-1 PROTECTIVE ACTION RE ENDATIONS 017 08/20/99 08/20/99 08/20/04 EF EPIP-2-2 OBTAINING METEO IDGICAL DATA AND FORECASTS AND THEIR USE IN EMERGENCY 009 02/13/98 02/13/98 02/13/02 EF DOSE ASSESS EPIP-2-3 EMERGENCY ELEASE RATE DETERMINATION 012 02/04/00 02/04/00 02/04/05 EF EPIP-2-4 EMERG CY DOSE PROJECTIONS - MANUAL METHOD 012 06/21/00 06/21/00 06/21/05 BF EPIP-2-5 EMERGENCY DOSE PROJECTIONS PERSONAL COMPUTER METHOD 010 11/16/99 11/16/99 11/16/04 EF EPIP-2-6 EMERGENCY DOSE PROJECTIONS - MIDAS PROGRAM 011 06/21/00 06/21/00 06/21/05 EF EPIP-2-7 MANAGEMENT OF EMERGENCY SURVEY TEAMS 009 10/01/99 10/01/99 10/01/04 EF

0

REPORT NO. 01 GINNA NUCLEAR POWER PIPIT 07/25/00 PAGE: 2 REPORT: NISP0200 PROCEDURES INDEX DOC TYPE: PREPI P EMERGENCY PLAN IMPLEMENTING PROCEDURE PARAMETERS-. DOC TYPES PREPIP STA'IUS: EF 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST EPIP-2-8 VOLUNTARY ACCEPTANCE OF EMERGENCY RADIATION EXPOSURE 005 05/16/00 05/16/00 05/16/05 EF EPIP-2-9 ADMINISTRATION OF POTASSIUM IODIDE (KI) 003 12/05/97 12/05/97 12/05/01 EF EPIP-2-10 I NPLANT RADIATION SURVEYS 003 01/16/97 01/16/97 01/16/02 EF EPIP-2-11 ONSITE SURVEYS 013 07/27/99 07/27/99 07/27/04 EF EPI P 12 OFFSITE SURVEYS 016 07/27/99 07/27/99 07/27/04 EF EPIP-2-13 IODINE AklD PARTICULATE ACTIVITY DETERMINATION FROM AIR SAMPLES 008 07/27/99 07/27/99 07/27/04 EF EPIP-2-14 POST PLUME ENVIRONMENTAL SAMPLING 013 08/20/99 08/20/99 08/20/04 EF EPIP-2-15 POST PLUME EVALUATION OF OFFSITE DOSES DUB TO DEPOSITION 004 03/06/98 03/06/98 03/06/03 EF BPIP-2-16 CORE DAMAGE ESTIMATION 010 02/25/00 02/25/00 02/25/05 EF EPIP-2-17 HYPOTHETICAL (PRE-RELEASE) DOSE ESTIMATES 005 11/16/99 11/16/99 11/16/04 EF EPI P-2-18 CONTROL ROOM DOSE ASSESSMENT 011 05/16/00 05/16/00 05/16/05 EF EPIP-3-1 EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION AND OPERATIONS 014 02/11/00 02/11/00 02/11/05 EF EPIP-3-2 ENGINEERING SUPPORT CENTER (ESC) 008 02/25/00 02/25/00 02/25/05 EF EPIP-3-3 I)0(EDIATE ENTRY 007 06/21/00 06/21/00 06/21/05 EF EPIP-3-4 EMERGENCY TERMINATION AND RECOVERY 007 05/28/99 05/28/99 05/28/04 EF EPIP-3-7 SECURITY DURING EMERGENCIES 009 11/16/99 11/16/99 11/16/04 EF EPIP-4-1 PUBLIC INFORMATION RESPONSE 'TO AN UNUSUAL EVENT 006 02/13/98 02/13/98 02/13/02 EF EPIP-4-3 ACCIDENTAL ACI'IVATION OF GINNA EMERGENCY NOTIFICATION SYSTEM SIRENS 008 02/13/98 02/13/98 02/13/02 EF EPIP-4-6 JOINT EMERGENCY NEWS CENTER ACTIVATION 008 02/11/00 02/11/00 02/11/05 EF EPIP-4-7 PUBLIC INFORMATION ORGANIZATION STAFFING 014 07/25/00 07/25/00 07/25/05 EF EPIP-5-1 OFFSITE EMERGENCY RESPONSE FACILITIES AND EQUIPMENT PERIODIC INVENTORY 017 06/21/00 06/21/00 06/21/05 EF CHECKS AND TESTS EPIP-5-2 ONSITE EMERGENCY RESPONSE FACILITIBS AND EQUIPMENT PERIODIC INVENTORY 022 05/24/00 05/24/00 05/24/05 EF CHECKS AND TESTS EPIP-5-5 CONDUCI'F DRILLS AND EXERCISES 011 02/25/00 02/25/00 02/25/05 EF

REPORT NO. 01 GINNA NUCLEAR POWER PLAINT 07/25/00 PAGE:

REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PREPIP EMERGENCY PLAN IMPLEMENTING PROCEDURE PARAMETERS: DOC PYPES PREPIP STATUS: EF 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST EPIP-5-6 ANNVAL REVIEW OF NUCLEAR EMERGENCY RESPONSE PLAN (NERP) 004 05/28/99 05/28/99 05/28/04 EF EPIP-5-7 EMERGENCY ORGANIZATION 028 07/25/00 07/25/00 07/25/05 EF EPIP-5-9 TESTING THE OFF HOURS CALL-IN PROCEDVRE AND QUARTERLY TELEPHONE NUMBER 006 05/28/99 05/28/99 05/28/04 EF CHECK EPIP-5-10 EMERGENCY RESPONSE DATA SYSTEM (ERDS) 005 09/05/97 09/05/97 09/05/02 EF NERP ANIAJAL UPDATE OF NUCLEAR EMERGENCY RESPONSE PLAN 019 12/09/99 12/09/99 12/09/04 EF TOTAL FOR PREPIP 52

4 ~

ROCSTER GAS S ELECTRIC CORP(TION GINNA STATION Controlled Copy Number 2-~

Procedure Number EPIP 1-5 Revision Number 41 NOTIFICATIONS Responsible Man 07 25 E ective Date Category 1.0 This procedure contains 24 pages

EPIP 1-5:1 EPIP 1-6 NOTIFICATIONS 1.0 PURPOSE The purpose of this procedure is to specify the means by which notifications are made to station personnel for all emergency action levels, to expedite the notification of selected RG8 E personnel to augment the emergency response organization and notify offsite agencies.

2.0 RESPONSIBILITY 2.1 The Shift Supervisor, Emergency Coordinator or EOF/Recovery Manager is responsible for making the decision to notify offsite agencies.

2.2 Ginna Station Control Room personnel are responsible for implementing this procedure.

2.3 Community Alert Network (CAN) is responsible for activating the onsite/offsite responders.

2.4 The Corporate Nuclear Emergency Planner is responsible for maintaining the station call lists up to date on a quarterly basis.

3.0 REFERENCES

3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.2 Implementing References 3.2.1 EPIP 1-0, Ginna Station Event Evaluation and Classification 3.2.2 EPIP 2-1, Protective Action Recommendations (PARs) 3.2.3 0-9.3, NRC Immediate NotiTication 3.2.4 10 CF,R 26, Fitness for. Duty Programs 3.2.5 P-9, Radiation Monitoring System

EPIP 1-5:2 3.2.6 EPIP 2-2, Obtaining Meteorological Data and Forecasts and their use in Emergency Dose Assessment 3.2.7 EPIP 4-7, Public Information Organization Staffing 3.2.8 EPIP 5-7, Emergency Organization 4.0 PRECAUTIONS 4.1 New York State, Wayne and Monroe Counties must be notified of all Emergency Classifications within 15 minutes of a declaration.

4.2 The Licensee should notify the USNRC immediately after notification of the appropriate State and local agencies and not later than one hour after the time the licensee declares one of the Emergency Classes.

4.3 Attachment 4 is a specialized notification list of people and organizations who may not require immediate notification but may need to be contacted during an emergency.

5.0 PRERE UISITES An Emergency has been declared in accordance with EPIP 1-0, Ginna Station Event Evaluation and Classification or offsite assistance has been requested by RG8 E personnel.

6.0 ACTIONS 6.1 Shift Su ervisor Emer enc Coordinator EOF/Recove Mana er 6.1.1 Ensure that notifications of all emergency declarations to New York State, Wayne and Monroe Counties are made within 15 minutes of declaring an emergency, in accordance with Attachment 3.

6.1.2 The licensee should notify the USNRC immediately after notification of the appropriate State or local agencies and not later than one hour after the time the licensee declares one of the Emergency Classes using procedure 0-9.3 "NRC Immediate Notification".

6.1.3 Upon notification often.Unusual. Event at Ginna.Station,.direct the control room personnel to implement section 6.2.1 of this procedure. If the event is an Alert or higher, implement section 6.2.2.

6.1.4 If additional assistance is required, refer to the NOG E-Plan phone list (in the RG&E telephone directory) in the Control Room and all Emergency Response Facilities, for phone numbers of station personnel.

6.2 Control Room Personnel 6.2.1 Unusual Event - Go to Attachment 1 6.2.2 Alert Classification or Higher - Go to Attachment 2 6.2.3 When offsite assistance has been requested - Go to Attachment 5 7.0 ATTACHMENTS Unusual Event Notifications

2. Alert or Higher Notifications

3. Instructions for New York State Radiological Emergency Data Forms 3a. New York State Radiological Emergency Data Form (Part 1) 3b. New York State Radiological Emergency Data Form (Part 2) 3c. Instructions for Event 1 and Event 2 Printouts and Plant Status Report 3d. Event 1 Supplemental Information Form 3e. Plant Status Report (PPCS not available)

4. Specialized Notification Call List

5. Notifications When Offsite Assistance has been requested

6. Emergency Planning Contingency Notification

7. Management Notification Roster (This attachment is controlled by Nuclear Emergency Preparedness. It is not included as part of the distributed procedure)

EPIP 1-5:4 Attachment 1, Rev. 41 Page 1 of 3 UNUSUAL EVENT NOTIFICATIONS

1. Report information to NEW YORK STATE, WAYNE and MONROE counties within 15 minutes of declaring the emergency via REGS Line using New York State Radiological Emergency Data Forms (Part 1) Attachment 3a. Fax the New York State Radiological Emergency Data Form (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center.

2. Notify USNRC immediately after the notification of the State and Counties, using procedure 0-9.3, NRC Immediate Notification

3. Activate the following positions by stating the following:

"We have an UNUSUAL EVENT at Ginna Station based Condition) on'Initiating Please report to the Technical Support Center. The event was declared at hrs. We need to remind you of the Fitness for Duty Requirements. Are you available to report for Duty at this time? If not, we are requesting that you standby so you can be notified for the next call in shift".

A .Plant Manager: Report to the TSC to support the Control Room with offsite communications.

Joe Widay Business 3250 Will Report (YES/NO)

Home 716-586-2679 Pager 716-528-3977 Cellular 716-748-4681 OR Dick Marchionda Business 3699 Will Report (YES/NO)

Home 315-926-0324 Pager 716-464-4403 Cellular 716-748-4682 OR Jack St. Martin Business 3641 Will Report (YES/NO)

Home 716-586-5676 "Pager ' 7T6-464'-5287 OR Tom Alexander Business 3898 Will Report (YES/NO)

Home 315-524-8084 Pager 716-783-7045 Cellular: 716-748-3233

EPIP 1-5:5 Attachment 1, Rev. 41 Page 2 of 3 UNUSUAL EVENT NOTIFICATIONS Technical Assessment Manager: Report to the TSC to support the Control Room with offsite communications.

Jeff Wayland Business 3317 Will Report (YES/NO)

Home 315-524-2899 Pager 716-464-5445 OR Ron Ploof Business 3673 Will Report (YES/NO)

Home 716-381-9379 Pager 716-921-1722 OR Brian Flynn Business 3734 Will Report (YES/NO)

Home 716-293-1 565 Pager 716<64-5134 C. Operations Assessment Manager: Report to the TSC to support the Control Room with offsite communications.

Terry White Business 3667 Will Report (YES/NO)

Home 716-226-9381 Pager 716-464-7382 Cellular 716-748-4683 OR Pete Sidelinger Business 3509 Will Report (YES/NO)

Home 716-671-3198 Pager 716-463-9830 OR Russ Lingl Business 3415 Will Report (YES/NO)

Home 716-392-5020 Pager 716-527-7841 Cellular 716-752-6692 D. Ho Nieh Business 3265 Home 315-986-7927

.Pager 1-800-944-2337 (then dial personal ID¹ 53133)

OR Chris Welch Business 3265 Home (716) 425-2613 Pager 1-800-944-2337 (then dial personal ID¹ 51578)

0 EPIP 1-5:6 Attachment 1, Rev. 41 Page 3 of 3 UNUSUAL EVENT NOTIFICATIONS Corporate Nuclear Emergency Planner: Inform government officials, public relations, PSC and financial department of the event.

Peter Polfleit Business 6772 Home 716-654-5325 Pager 716-527-2207 Cellular 716-733-2207 OR Frank Cordaro Business 3108 Home 315-524-2924 Pager 716-527-3650 Cellular 716-729-4613 OR Richard Watts Business 8706 Home 716-425-2644 Pager 716-527-3749 Cellular 716-747-9760 OR Jill Willoughby Business 4033 Home 716-787-3156 Pager 716-528-3295 Cellular 716-732-7189 If the Unusual Event lasts greater than one (1) hour, report information using the New York State Radiological Emergency Data Forms (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center each hour from the time the previous notification was made. Fax the New York State Radiological Emergency Data Form (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center after each report.

EPIP 1-5:7 Attachment 2, Rev. 41 Page1 of2 ALERT OR HIGHER NOTIFICATIONS

1. Contact Community Alert Network (CAN) at 9-1-800-552-4226 (or at their back-up number of 9-1-518-862-0411). Inform the CAN operator the following information to activate the system:

a. This is I am the Ginna Control Room Communicator with RG&E.

(your name)

b. My password is: Brookwood

c. My callback number is:

d. This is (circle one): an Actual Event a Drill

e. This Emergency Classification declared at:

(Time from REGS form),

f. Message to deliver (circle one):

Drill Alert Site Area Emergency General Emergency

g. My current time is: . Please start notifications now.

2. Report information to NEW YORK STATE, WAYNE and MONROE counties within 15 minutes of declaring the emergency via REGS Line using New York State Radiological Emergency Data Forms (Part 1) Attachment 3a. Fax the New York State Radiological Emergency Data Forms (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center.

3. Notify Nuclear Emergency Preparedness of the event. Emergency Preparedness will verify actuation of the emergency response organization notification. If notifications have not begun, Emergency Preparedness will refer to Attachment 6 for contingency notification of one hour responders.

Peter Polfleit Business 6772 Home 716-654-5325 Pager 716-527-2207 Cellular -"716-733-2207 OR Frank Cordaro Business 3108 Home 315-524-2924 Pager 716-527-3650 Cellular 716-729-4613

EPIP 1-5:8 Attachment 2, Rev. 41 Page 2 of 2 ALERT OR HIGHER NOTIFICATIONS (Continued)

OR Richard Watts Business 8706 Home 716-425-2644 Pager 716-527-3749 Cellular 716-747-9760 OR Jill Willoughby Business 4033 Home 716-787-3156 Pager 716-528-3295 Cellular 716-732-7189

4. Notify USNRC immediately after the notification of the State and Counties, using procedure 0-9.3, NRC Immediate Notification 5.. NRC Resident Inspector: Informational call only Ho Nieh Business 3265 Home 315-986-7927 Pager 1-800-944-2337 (then dial personal ID¹ 53133)

OR Chris Welch Business 3265 Home 716-425-2613 Pager 1-800-944-2337 (then dial personal ID¹ 51578)

If the Alert of higher lasts greater than 30 minutes report information using the New York State Radiological Emergency Data Forms (Part 1) Attachment 3a to New York State, Wayne County, Monroe County every 30 minutes from the time the previous notification was made. Fax the New York State Radiological Emergency Data Form (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center after each report.

Notify Energy Operations (8944) that Ginna has an emergency and to implement procedures to increase reliability of power to Ginna.

8.. If requested by the TSC or EOF, the Control Room will fax the Event 1 Supplemental Information Form, Attachment 3d to the TSC and EOF.

NOTE: Event'1 and Event'2yrintouts should not be'transmitted by the Control Room, but should be faxed by the TSC Administrative/Communications Staff when it is sufficiently manned to do so.

9. Refer to Attachment 3c for Event 1 and Event 2 instructions.

EPIP 1-5:9 Attachment 3, Rev. 41 f

Page1 of2 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICALEMERGENCY DATA FORMS

1. The New York State Radiological Emergency Data Form, (Part 1) Attachment 3a should be filled out with the assistance of the Emergency Coordinator or EOF/Recovery Manager and Radiation Protection personnel.

For training and drills/exercise, circle "B" - An Exercise. For actual events, circle "A" - NOT An Exercise.

3. The determiriation for item 6 is made by checking effluent monitor readings against the release rate limits given in procedure P-9.

4. For item 7 of the form, the Emergency Coordinator or EOF/Recovery Manager shall use EPIP 2-1, Protective Action Recommendations (PARs). PARs will only reflect RG8 E recommendations, not actions implemented by offsite officials.

For item 8 of the form, enter the Emergency Action Level (EAL) number from EPIP 1-0, Ginna Station Event Evaluation and Classification.

NOTE: THE WIND SPEED INDICATOR AT THE 33 FOOT LEVEL IS DESIGNED TO

. MEASURE ONLY TO 50 MILES PER HOUR.

Obtain weather information, items 11-13 of the form, using the plant process computer (PPCS)

OR If the PPCS is not available, use the Control Room weather indication on the RMS rack.

~ OR The Radiation Protection Shift Technician or Dose Assessment Manager will determine the weather and stability class in accordance with procedure EPIP 2-2.

The communicator will initial the "prepared by" line at the bottom of the form. The SS/EC (or designee) will approve the form at the bottom prior to transmission. The communicator will ensure all forms are sent to the Corporate Nuclear Emergency Planner (CNEP) at the conclusion of the event.

Report the information on the completed New York State Radiological Emergency Data Form (Part 1) Attachment 3a to New York State, Wayne and Monroe Counties within 15 minutes of declaring the emergency using the REGS Line.

a. Pick up the receiver and depress "A" then "*" for all call. Wait 10 seconds then depress the "Push to Talk" bar on the handset and state:

"This is Glnna Station, please standby for roll call" "New York State" (wait for response)

"Monroe County" (wait for response)

"Wayne County" (wait for response)

b. Report the information by reading the statement number and the statement including the designation letter.

(e.g. "Item four; Classification; "O'"Unusual Event)

c. Upon completion of transmitting information, reset system by depressing "A" then "¹".

d. Hang up receiver.

EPIP 1-5:10 Attachment 3, Rev. 41 Page2of2 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICALEMERGENCY DATA FORMS IF REGS LINE IS OUT OF ORDER, perform the following:

Call Wayne County 9-1-315-946-9711 (Wayne County Warning Point)

Inform Wayne County, "This is a Ginna Emergency, please hold while we connect Monroe County and New York State". Press the conference button on the telephone.

Call Monroe County 9-528-2222 (Monroe County Warning Point)

Inform Monroe County, "This is a Ginna Emergency". Press the conference button on the telephone.

Wayne and Monroe should now be connected.

Roll call Wayne County Monroe County "Please hold while we connect New York State". Press the conference button on the telephone.

Call New York State 9-1-518-457-2200 (New York State Warning Point)

Inform New York State, "This is a Ginna Emergency". Press conference button on the telephone.

Wayne County, Monroe County and New York State should all be connected.

10. Data in items 15 through 20 of the New York State Radiological Emergency Data Form (Part 2)

'ttachment 3b should be filled out by the TSC/EOF Dose Assessment and transmitted by fax as information becomes available from the TSC/EOF.

11. Fax all New York State Radiological Emergency Data Forms to the following using the instructions on the fax machine:

Wayne County 9-1 -315-946-9721 Monroe County 9-256-6355 New York State 9-1-518-457-9942 TSC 3927 EOF 9-262-5788 Survey Center 3612 OSC Satellite 3524 Engineering Support Center 3774 Joint Emergency News Center 6771

12. Blank copies of the New York State Radiological Emergency Data Form (Part 1 and Part 2) are available in the Control Room.

13. When a County or the State request to be notified only if conditions change or when the event is terminated, check with the State/County warning points to see if they agree. If they all agree, note this in section 8 of the next Part 1 Form notification. The facility with command and control will inform the other RG8 E response facilities of the status of notifications. Perform a notification when conditions change or the event is terminated.

14. The New York State Radiological Emergency Data Form (Part2); Attachment 3b, is filled out by the Dose Assessment Group. The form is transmitted via fax only. The form is transmitted after there has been a release above technical specifications (Part 1 form, Item 6). A release above Technical Specifications is defined as exceeding the "ODCM release rate" limits in P-9.

EPIP 1-5:11 NOTE: See Attachment 3 for instructions. Attachment 3a, Rev. 41 Page 1 of 1 NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM (PART I) if "This a a is Ginna Station. Please stand b for roll call." "New York State" a a e 0 "Monroe Count "0 "Wa ne Count "0

1. Message transmitted at: 2. This is:

Date Time Via: A. REGS B. Other A. NOT an exercise B. An exercise

3. Facility providing information:

C. Ginna

4. Classification:

A. UNUSUAL EVENT D. GENERAL EMERGENCY G. TRANSPORTATION INCIDENT B. ALERT E. EMERGENCY TERMINATED C. SITE AREA EMERGENCY F. RECOVERY

5. Classification Time:

This Emergency Classification declared at: Date Time

6. Release of Radioactive Materials: (Refer to P-9)

A. No Release above Technical Specifications C. Release to a Body of Water above Technical Specifications B. Release to the Atmosphere above Technical Specifications

7. Protective Action RECOMMENDATIONS: IRofer to EPIP 2.1)

A. No need for Protective Actions outside tho site boundary B. Evacuate the following ERPAs W1 W2 W3 W4 W5 W6 W7 M1 M2 M3 M4 M5 M6 M7 MB M9 C. Shelter all remaining ERPAs B. Brief Event

Description:

EAL ¹

9. Plant Status: 10. Reactor Shutdown: (subcritical)

A. Stable C. Degrading E. Cold Shutdown A. Not Applicablo B. Date Tlrn o B. Improving D. Hot Shutdown

11. Wind Speed: 12. Wind Direction:

A. Miles/hour at elevation feet From: degrees at elevation

13. Stability Class: DO NOT REPORT 14. Reported By:

Stability Class Work Sheet Unstable, Noutral, Stable Name Temperature at 250 feet 'F Temperature at 33 feet F Area'Code Number Temperature Difference 'F

-1.74 -0.65 Unstable Neutral Stable

-3 -2 -1 0 1 Temperature Difference "New York State copy?" 0 "Monroe County copy?" CI "Wayne County copy?" 0 FOR RGftrE USE ONLY:

Time Prepared: Time Approved: Completed form sent Prepared By: Approved By: to EP Ginna Training

EPIP 1-5:12 Attachment 3b, Rev. 41 Page 1 of 1 NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM (PART II)

Telefax this data form to:

15. Message transmitted at:

Q New York State CI Monroe County 0 Wayne County Date Time Location/Facility Transmitted From:

16. General Release Information

.A. Release > Tech Specs started: Date Time B. Release > Tech Specs expected to end: Date Time OR 0 Unknown C. Release > Tech Specs ended: Date Tlnle D. Reactor Shutdown: N/A OR Date Time E. Wind Speed: miles/hour at elevation feet F. Wind Direction from: degrees at elevation G. Stability Class: PASQUILL A B C D E F G OR Other

17. Atmospheric Release Information A. Release from: 0 Ground 0 Elevated D. Noble Gas Release Rate Ci/sec B. Iodine/Noble Gas Ratio E. Iodine Rolease Rate Ci/sec C. Total Release Rate Ci/sec F. Particulate Release Rate Ci/sec

18. Waterborne Release Information A. Volume of Release gal or liters C. Radionuclides in Release B. Total Concontration yci/ml D. Total Activity Released

19. Dose Calculations (based on a releaso duration of hours)

Calculation is based on (circle one) A. Inplant Measurements B. Field Measurements C. Assumed Source Term Table below applies to (circle ono) A. Atmosphere Release B. Waterborne Release Dose Distance Xu/Q TEDE (rem) CDE - Child Thyroid (rem)

Site Boundary 2 Miles 5 Miles 10 Miles Miles 20.Field Measurements of Dose Rates or Surface Contamination/Disposition Dose Rate OR Miles/Sector OR Location OR Sampling Point Time of Roading Contammatlon Miles/Degrees (Include Units)

FOR RG&E USE ONLY: Time Prepared: Time Approved:

By: By:

Completed form sent to CNEP - 49/2

EPIP 1-5:13 Attachment 3c, Rev. 41 Page 1 of1 INSTRUCTIONS FOR EVENT 1 AND EVENT 2 PRINTOUTS AND PLANT STATUS REPORT Assure the Plant Process Computer System (PPCS) is operational. If PPCS is not operational, go to step 5.

NOTE: OBTAIN EVENT1 AND EVENT2 PRINTOUTS FROM THE COMPUTER ANALYSTIF THAT POSITION IS STAFFED, OTHERWISE PERFORM THE FOLLOWING STEP.

Obtain Event 1 and Event 2 printouts by entering:

GASR <return>

Computer response - Enter Group Name EVENT1 <return>

Computer response - Select Printer Location Press F1 for Control Room, F2 for EOF, F3 for TSC GASR <return>

Computer response - Enter Group Name EVENT2 <return>

Computer Response - Select Printer Location Press F1 for Control Room, F2 for EOF, F3 for TSC Place printout in the Event 1 8 2 group trend log book NOTE: EVENT 1 AND EVENT 2 GROUP TREND (GTLOG) SHOULD BE PRINTED EVERY 15 MINUTES.

3. Initiate Event 1 8 2 group trend log (GT LOG) by entering:

GTLOG <return>

Computer response - Enter Name of Group to Log EVENT1 <return>

Computer response - Enter Update Rate (30-1800 seconds) 60 <return>

Computer response - Enter Print Interval (1-30 minutes) 15 <return>

Computer Response - Select Printer Location (F1-F4)

Press F1 for F3 for TSC Initiate Event 1 and Event 2 Group Trend Log in EOF by repeating step 3 and enter F2 when selecting printer location.

Place printouts in Emergency Coordinator or EOF/Recovery Manager notebook Verify with the TSC computer analyst that the PPCX (plant computer data) is being transmitted to New York State, Wayne County and Monroe County via computer modem. If the PPCX (plant computer data) to offsite agencies is unavailable, perform step 2 and fax the printout to New York State, Wayne County and Monroe County.

If the PPCS is unavailable, the Plant Status Report (Attachment 3e) must be completed by the Control Room and faxed to'the TSC for distribution to New York State, Wayne County, Monroe County and EOF.

When completing Attachment 3e, if the parameter is measurable (e.g. pressurizer level) use the numerical value. When the parameter is not measurable, the condition of any deviation from normal should be noted (e.g. core circulation - forced or natural).

EPIP 1-5:14 Attachment 3d, Rev. 41 Page 1 of1 EVENT 1 SUPPLEMENTAL INFORMATION FORM 61 Aux Feedwater System Inservice Standby OOS 62 Safety Injection System Inservice Standby OOS 63 Diesel Generators Inservice Standby OOS 64 Containment Fan Cooler lnservice Standby OOS System 65 Service Water System In service Standby OOS 66 Post Accident Charcoal In service Standby OOS Filters 67 Containment Spray Pumps Inservice Standby OOS 68 Component Cooling System Inservice Standby OOS 69 DC System A B Y 70 NaOH Tank Level Time Completed:

Completed By:

0 Attachment 3e, Rev. 41 PLANT STATUS REPORT PPCS NOT AVAILABLE Pa e1of1 Plant Parameters Plant Parameters Radiation Monitoring Auxiliary Feedwater Inservice R-1 Control Room Reactor Shutdown YES/NO TIME System Standby mRem/hr OOS Inservice R-2 Containment RCS Pressure PSIG Safety Injection Standby mRem/hr OOS Inservice R-9 Letdown PRZR Level Diesel Generators Standby . mRem/hr lnservice R-10 "A" Containment Iodine Core Circulation Forced/Natural Service Water System Standby CPM OOS

'F Cnmt Fan Coolers System Inservice R-11 Containment Particulate Subcooled Standby CPM "A" S/G Level Post Acc. Charcoal Filter Damper Damper R-12 Containment Gas CPM Open / Closed "8" S/G Level Cnmt. Spray Inservice R-10 "8" Plant Vent Iodine Standby CPM Cnmt. Spray Pumps Standby Comp. Cooling System Inservice R-13 Plant Vent Particulate "A" S/G Pressure PSIG Standby CPM 8" S/G Pressure PSIG D.C. System R-14 Plant Vent Gas Volts CPM Safeguard Train 8 (16/17) NaOH Tank Level R-29 Containment High Range EDG/Turbine/Offsite Offsite Power Available/Unavailable RWST Level R-30 Containment High Range R/hr Cnmt Pressure PSIG BA. Tank Level R-15 Air Ejector Gas CPM Sump "A" Level Wind Speed R-12A SPING Containment Gas MPH pCi/cc Sump "8" Level IN Wind Direction (From) 'R14A SPING Plant Vent Gas Degrees pCi/cc RCS Temp oF Temperature 33 FT 'F 'R-15A SPING Air Ejector Gas pCi/cc RVLIS Temperature 250 FT 'F R-31 Steam Line "A" mRem/hr CET oF R-32 Steam Line "8" mRem/hr R/hr = Roentgen/Hour *SPING Unit readings may be deleted if Date IiCI/cc =Microcuries/Cubic Centimeter radiation monitors R-12 and R-14 onTime Completed mRem/hr = millirem/Hour scale. Completed By

EPIP 1-5:16 Attachment 4, Rev. 41 Page1 of5 SPECIALIZED NOTIFICATION LIST Medical

1. Ontario Volunteer Emergency Squad 769-911 (Ginna Control Room Only)

(To request ambulance) 9-1-315-524-5751 (Business number)

2. Wayne County Emergency Dispatcher 9-1-315-946-5304 3, Rochester General Hospital, 9-338-2300 Emergency Department Triage Nurse

4. Rochester General Hospital Main Switchboard 9-338-4000

5. RG8 E Medical Services Office 8600 Alternate Office 4616 Answering Service 9-226-3800 Dr. Robert W. George Dr. T. K. Oates Dr. Alexander Kurchin

6. Newark-Wayne Community Hospital 9-1-315-332-2267 Police

1. New York State Police Warning Point 9-1-518-457-2200 9-1-315-457-6811

2. Canandaigua State Police 9-398-3200

3. Williamson State Police 9-1-800-962-0810

4. Wayne County Sheriff 9-1-315-946-9711

5. Monroe County Sheriff 9-428-5511 Fire Ontario Volunteer Fire Department 769-911 (Ginna Control Room Only)

(To report fire) 9-1-315-524-2661 (Business number)

EPIP 1-5:17 Attachment 4, Rev. 41 Page 2 of 5 SPECIALIZED NOTIFICATION LIST Westin house Emer enc Res onseOr anization Notify one Westinghouse contact using list in order shown. Provide available facts to individual and provide updates.

1. Hank Sepp 9-1-412-374-5282 Director ESBU Emergency Response Home 9-1-412-856-4036 Hotline 9-1-412-856-6121

2. Dan Lipman 9-1-412-374-6920 ESBU Service Response Manager Home 9-1-412-744-3244

3. Rose Cotton 9-1-412-374-6805 ESBU Emergency News Home 9-1-412-963-6129 Communications ENC Manager

4. Mike Young 9-1-412-374-5081 ESBU Emergency Response Home 9-1-412-243-7996 Technical Support Manager

5. Tom Hart 9-1-412-374-6980 ESBU Emergency Response Home 9-1-412-837-9486 Logistic Manager Hotline 9-1-412-837-1737 Pager 9-1-412-765-8886 Other Ontario Town Supervisor, Office 9-1-315-524-7105 Roy Hermann Home 9-1-315-524-8087

2. Ontario Water Department 9-1-315-524-2941

3. Plant Protection Department 9-722-2122 Kodak Park

4. Wayne County Emergency 9-1-315-946-5663 Operations Center

5. Director Wayne. County -

Home 9-1-315-597-6291 Office of Disaster Preparedness-Thelma Wideman

6. Monroe County Office of Daytime 9-473-0710 Emergency Preparedness Offhours 9-528-2222 (Nights, Weekends, Holidays)

EPIP 1-5:18 Attachment 4, Rev. 41 Page 3 of 5 SPECIALIZED NOTIFICATION LIST (Cont'd.)

7. Administrator, Monroe County Home 9-624-3194 Office of Emergency Preparedness- Pager 9-428-5141 Mary Louise Meisenzahl University of Rochester Advance Home 9-275-3788 RAP Team - David Maillie 9-334-2428

9. National Weather Service (Buffalo) 9-1-800-462-7751

10. Radiation Management Consultants Office 9-1-215-824-1300 Emergency 9-1-215-243-2990 Fax 9-1-215-824-1371

11. Helgeson Nuclear Services Inc 9-1-415-846-3453

12. James C. Hutton (NSARB) 9-1-716-381-8473

13. Institute of Nuclear Power Operations 9-1-800-321-0614

14. American Nuclear Insurers 9-1-203-677-7305

15. Emergency Preparedness Canada Phone 9-1-613-991-7000 Fax 9-1-613-996-0995

16. NYPA Environmental Laboratory Daytime 9-1-315-593-5740 Fulton, New York 9-1-315-593-5735 Lab 9-1-800-436-2732 Manager ¹ enter pager 713-6710 pager then your number Mgr Home ¹ 9-1-315-342-0015 RES on call 9-1-800-436-2732 pager ¹ enter pager 713-6726 then your number

EPIP 1-5:19 Attachment 4, Rev. 41 Page 4 of 5 SPECIALIZED NOTIFICATION LIST (Cont'd.)

Com an Personnel Thomson, Bill Business 3219 Manager, Radiation Protection Home 315-342-5082 and Chemistry Pager 716-528-8561 Richards, Thomas Business 8299 Chief Executive Officer Home (716) 288-9186 Lappan, George Business 8812 Manager of Corporate Home 716-377-6858 Communications Mecredy, Robert Business 3494 Vice President Home 716-381-6430 Nuclear Operations Pager 716-783-4900 Wilkens, Paul Business 8076 Sr. Vice President Home 716-248-2385 Generation Pager: 716-529-6426 Cellular 716<51-9761

6. Watts, Richard Business 8706 Manager, Nuclear Training Home 716-425-2644 Pager 716-527-3749 Cellular 716-747-9760 Nuclear Re ulato Commission Nuclear Regulatory Commission 610-337-5000 Region 1 - King of Prussia, PA Radiation Assistance Program 516-282-2200 Dept of Energy Brookhaven National Lab Commercial telephone system to 301-951-0550 NRC Operations Center (via Bethesda.Central.Office)

Commercial telephone system to 301-427-4056 NRC Communications Center (via Silver Spring Central Office)

Commercial telephone system to 301-492-8893 NRC Operator (via Bethesda Central Office)

EPIP 1-5:20 Attachment 4, Rev. 41 Page 5 of 5 SPECIALIZED NOTIFICATION LIST (Cont'd.)

New York State

1. James Baranski, 518-457-8909 State Emergency Management Office (SEMO)

2. SEMO Lake District 315-331-4880

3. NYS Department of Health 716-262-2010 Rochester Office

4. New York State Emergency 518-454-3337 Operations Center (EOC) Albany

5. EOC Albany - Dose Assessment 518-454-3321 518-454-2176 Federal Emergency Management Agency (FEMA)

1. Emergency Information Coordination 202-634-7800 Center 202-646-2400

EPIP 1-5:21 Attachment 5, Rev. 41 Page 1 of 3 NOTIFICATIONS WHEN OFFSITE ASSISTANCE HAS BEEN REQUESTED When offsite assistance has been requested activate:

Security Nuclear Management Emergency Planning Examples of initiating events that could require offsite assistance are:

Fire Medical Emergency Security Event HAZMATIncident Natural Events (such as flooding, earthquakes or severe weather)

2. Security Contact Security at 3210, so that they can make preparations for the arrival of the emergency vehicles and personnel.

Nuclear Management Notify the following individuals:

"This is the Ginna Control Room. We have requested offsite assistance from . Can you be the Nuclear Management contact for this event?

Your duties are (a) act as the RG&E lead for this event and (b) act as the liaison between the Control Room and the corporation."

Nuclear Mana ement (One person required to respond)

Joe Widay Business 3250 Available (YES/NO)

Home 716-586-2679 Pager 716-528-3977 Cellular 716-748-4681 OR Dick Marchionda Business 3699 Available (YES/NO)

Home 315-926-0324

- -Pager. .7"1 6-464%403 Cellular '16-748<682 OR Bob Mecredy Business 8069 Available (YES/NO)

Home 716-381-6430 Pager 716-783<900 The nuclear management representative may call other nuclear managers or members of the Ginna leadership team.

EPIP 1-5:22 Attachment 5, Rev. 41 Page 2 of 3 NOTIFICATIONS WHEN OFFSITE ASSISTANCE HAS BEEN RE VESTED Emergency Planning Notify the following individuals:

"This is the Ginna Control Room. We have requested offsite assistance from . Can you be the Emergency Planning contact for this event?

Your duties are (a) activate Public Relations and (b) act as the liaison between the Control Room and government agencies.

is acting as the Nuclear Management lead for this event. He can be reached at Nuclear Emer enc Pre aredness (One person required to respond)

Peter Polfleit Business 6772 Home 716-654-5325 Pager 716-527-2207 Cellular 716-733-2207 OR Frank Cordaro Business 3108 Home 315-524-2924 Pager 716-527-3650 Cellular 716-729-4613 OR Richard Watts Business 8706 Home 716-425-2644 Pager 716-527-3749 Cellular 716-747-9760 OR Jill Willoughby Business 4033 Home 716-787-3156 Pager 716-528-3295 Cellular 716-732-7189 The Emergency Planning representative. will call the duty. public information officer (PIO) via the ECC at 771-2233, and inform them of the event. The duty PIO will determine if a media announcement is warranted. The Emergency Planning representative will also contact Wayne County, Monroe County and New York State officials to brief them on offsite resources being Used

EPIP 1-5:23 Attachment 5, Rev. 41 Page 3 of 3 NOTIFICATIONS WHEN OFFSITE ASSISTANCE HAS BEEN REQUESTED

5. Contact the NRC resident inspector Ho Nieh Business 3265 Home 315-986-7927

.Pager 1-800-944-2337 (then dial personal ID¹ 53133)

OR Chris Welch Business 3265 Home 716-425-2613 Pager 1-800-944-2337 (then dial personal ID¹ 51578

0 1

Attachment 6, Rev. 41 Page 1 of1 EMERGENCY PLANNING CONTINGENCY NOTIFICATION

67. Upon verification that the Community Alert Network System or Group Page for one hour response positions does not activate or function properly, begin manual notification process.

68. Notify other Nuclear Emergency Preparedness staff members to assist with contingency notifications.

69. The following one hour response positions should be filled by contacting a minimum of one responder for each position by individual page or by home, office or cellular phone number. Refer to EPIP 4-7, Public Information Organization Staffing, and EPIP 5-7, Emergency Organization.

TSC Emergency Coordinator Operations Assessment Manager Technical Assessment Manager Communicator TSC Dose Assessment Manager RP/Chemistry Manager Maintenance Assessment Manager Survey Center Manager EOF Recovery Manager Nuclear Operations Manager Engineering Manager EOF Dose Assessment Manager

~ News Center Manager Inform the responder of the current emergency classification and instruct them to report to their emergency duty location immediately. Inform them of the fitness for duty requirements.