ML17263A588
| ML17263A588 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/07/1994 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17263A585 | List:
|
| References | |
| ATT-14.6, NUDOCS 9404190107 | |
| Download: ML17263A588 (10) | |
Text
EOP:
ATT-14.6 TITLE:
ATTACHMENT RHR PRESS REDUCTION REV:
0 PAGE 1 of 1 Superintendent
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NOTE: Under certain configurations of check valve leakage, the associated pressure buildup in the RHR system could prohibit the opening of MOV-850A/B or MOV-857A/B/C due to high seat DP.
The following steps may be used to reduce this DP.
NOTE: Perform only the portions of this attachment relating to the valves being addressed by the procedure in effect.
Verify the appropriate breakers are reset by directing the AO to check the breaker closed (not tripped)
AND to press the reset button on the front of the cubicle.
MOV-850A, MOV-850B, MOV-857A, MOV-857B, MOV-857C, MCC 1C pos 6J MCC 1D pos 6J MCC 1C pos 7M MCC 1D pos 7M MCC 1C pos 15J IF letdown is in service, THEN perform the following:
1)
Place TCV-145 to the VCT position.
2)
Place PCV-135 in manual THEN reduce letdown line pressure to 225 PSIG as indicated on PI-135.
3)
Open the valves being directed by the procedure in effect o
MOV-850A and MOV-850B OR o
MOV-857A, MOV-857B and MOV-857C 4)
Return letdown system to the desired configuration IF letdown is NOT in service, THEN perform the following:
1)
Ensure AOV-200A, AOV-200B and AOV-202 are closed 2)
Place TCV-145 to the VCT position 3)
Reset SI, CNMT Isolation and XY Relays if necessary, THEN open AOV-371.
4)
Fully open PCV-135 in manual, THEN verify PI-135 indicates 225 PSIG 5)
Open the valves being directed by the procedure in effect o
MOV-850A and MOV-850B OR o
MOV-857A, MOV-857B and MOV-857C 9404190107 940414 PDR ADOt K 05000244 p
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRAP GIRJA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORNAL PROCEDURE 03/30/00 PAGE:
2 PARANETERS:
TY
~ PRAR PRATT PRAP PRER STATUS:
EF QU 5 YEARS ONLY:
PROCEDURE NUNSER AP-RHR.2 AP-SW. 1 AP-TURB. 1 AP-TURB. 2 AP-TURB. 3 AP-TURB. 4 AP-TURB. 5 PROCEDURE LOSS OF RHR WHILE OPERAT T RCS REDUCED INVENTORY CONDITIONS SERVICE WATER LEAK TURBINE TRIP WITHOUT RX TRIP REQUIRED TURBINE LOAD REJECTION TURBINE VIBRATION LOSS OF CONDENSER VACUP4 RAPID LOAD REDUCTION REV EFFECT DATE LAST REVIEW NEXT REVIEW ST 017 02/11/00 05/13/98 05/13/03 010 02/11/00 02/10/98 02/10 EF 4
05/01/98 05/01/98
/01/03 EF 004 02 00 07/
/95 07/10/00 EF 008 03/31/00 03/31/00 03/31/05 EF 015 10/18/99 06/03/98 06/03/03 EF 010 02/12/99 10/10/97 10/10/02 EF TOTAL FOR PRAP 31
t A
i'f t
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 05/18/00 PAGE:
1 PARAMETERS:
DOC TYPES - PRATT PRAP PRE PRECA STATUS:
QU EF 5 YEARS ONLY:
PROCEDURE NUMBER AP-CCW. 1 AP-CCW. 2 AP-CCW. 3 AP CR.1 AP-CVCS. 1 AP-CVCS. 3 AP-CW. 1 AP-ELEC.1 AP-ELEC.2 AP ELEC.3 AP-ELEC. 14/16 AP-ELEC.17/18 AP-FW. 1 AP-IA.1 AP-PRZR F 1 AP-RCC.1 AP-RCC.2 AP-RCC.3 AP RCP.l AP-RCS. 1 AP-RCS.2 AP-RCS.3 AP-RCS.4 AP-RHR.1 PROCEDURE TITLE LEAKAGE INTO THE COMPONENT COOLING LOOP LOSS Of CCM DURING POWER OPERATION LOSS OF CCM - PLANT SHUTDOWN CONTROL ROON INACCESSIBILITY CVCS LEAK LOSS OF ALL CHARGING FLOW LOSS OP A CIRC MATER PUMP LOSS Of 12A AND/OR 12B BUSSES SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY LOSS OP 12A AND/OR 12B TRANSFORMER tBELOW 350 F)
LOSS OF SAFEGUARDS BUS 14/16 LOSS OF SAFEGUARDS BUS 17/18 PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER LOSS OF INSTRUMENT AIR ABNORMAL PRESSURI2ER PRESSURE CONTINUOUS CONTROL ROD WITHDRAMAL/INSERTION RCC/RPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OF REACTOR COOLANT FLOW HIGH REACTOR COOLANT ACTIVITY SHUTDOWN LOCA LOSS OF RHR EFFECT REV DATE LAST REVIEW NEXT REVIEW ST 013 10/30/98 05/01/98 05/01/03 EF 014 05/18/00 08/17/99 08/17/04 EF 012 05/18/00 08/17/99 08/17/04 Ef 016'1/11/00 01/11/00 01/11/05 EF 012 05/01/98 05/01/98 05/01/03 Ef 002 02/11/00 02/26/99 02/26/04 EF 010 07/16/98 05/01/98 05/01/03 EF 019 12/02/99 05/01/98 05/01/03 EF 009 03/22/99 03/22/99 03/22/04 EP 007 12/02/99 05/01/98 05/01/03 EF 000 06/09/97 06/09/97 06/09/02 EF 002 10/18/99 06/09/97 06/09/02 EF 012 02/11/00 02/27/98 02/27/03 Ef 017 12/02/99 05/01/98 05/01/03 EF 011 12/02/99 12/02/99 12/02/04 EF 006 02/24/96 05/14/98 05/14/03 EF 008 11/16/98 02/06/97 02/06/02 EF 004 11/16/98 02/27/98 02/27/03 Ef 012 05/01/98 05/01/98 05/01/03 EF 014 04/14/99 05/01/98 05/01/03 EF 010 12/14/98 05/01/98 05/01/03 EF 007 08/05/97 08/05/97 08/05/02 EF 011 12/02/99 05/01/98 05/01/03 EF 013 01/25/99 05/01/98 05/01/03 EF
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRATT GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EOP ATTACHMENTS 04/06/00 PAGE:
30 PARAMETERS:
DOC TYPES PRAR STATUS:
QU EF 5 YEARS ONLY:
PROCEDURE NUMBER ATT-l.0 ATT-2. 1 ATT-2.2 ATI'-2.3 ATT 3.0 ATT 3.1 ATT-4.0 ATl'-5.0 ATT-5. 1 ATT-5.2 ATT-6.0 ATT-7.0 ATT-8.0 ATT-8.1 ATT 8.2 ATI'-8.3 ATT-8.4 ATT-9.0 ATT-9. 1 ATT-10.0 ATT-11.0 ATT-11.1 ATT-11.2 ATT-12.0 PROCEDURE TITLE ATTACHMENT AT POWER CCW ALIGNMENT ATTACHMENT MIN SW ATI'ACHMENT SW 1SOLATION ATTACHMENT SW LOADS IN CNMT ATTACHMENT CI/CVI ATTACHMENT CNMT CLOSURE ATTACHMENT CNMT RECIRC FANS ATTACHMENT COND TO S/G ATTACHMENT SAFW ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP ATI'ACHMENT COND VACUtR4 ATTACHMENT CR EVAC ATTACHMENT DC LOADS ATTACHMENT D/G STOP ATTACHMENT GEN DEGAS ATTACHMENT NONVITAL ATTACHMENT SI/UV ATTACHMENT LETDOWN ATTACHMENT EXCESS L/D ATI'ACHMENT FAULTED S/G ATI'ACHMENT IA CONCERNS ATTACHMENT IA SUPPLY ATTACHMENT DIESEL AIR COMPRESSOR ATTACHMENT N2 PORVS EFFECT REV DATE LAST REVIEW NEXT REVIEW ST 001 07/26/94 02/10/98 02/10/03 BF 004 06/26/98 02/10/98 02/10/03 EF 006 03/25/99 08/11/98 08/11/03 EF 003 01/25/95 12/31/99 12/31/04 EF 005 01/25/99 01/06/99 01/06/04 EF 003 01/25/99 01/25/99 01/25/04 BF 003 07/26/94 05/13/98 05/13/03 EP 004 01/25/95 12/31/99 12/31/04 EF 006 07/0'7/98 12/31/99 12/31/04 EP 003 01/14/99 01/14/99 01/14/04 EF 003 12/18/96 02/10/98 02/10/03 EF 005 02/11/00 02/10/98 02/10/03 EF 006 03/22/99 01/14/99 01/14/04 BF 004 11/03/95 02/10/98 02/10/03 EF 006 08/17/99 08/17/99 08/17/04 EF 003 07/26/94 02/10/98 02/10/03 EF 004 04/24/97 02/10/98 02/10/03 BF 006 04/07/97 01/06/99 01/06/04 EF 003 03/31/00 02/10/98 02/10/03 EF 005 10/03/96 05/13/98 05/13/03 EP 002 04/07/97 08/11/98 08/11/03 EF 002 04/07/97 08/11/98 08/11/03 EF 000 04/03/98 04/03/98 04/03/03 EF 003 03/24/97 02/10/98 02/10/03 EF
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REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRATT GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EOP ATTACHMENTS 04/06/00 PAGE:
31 PARAMETERS:
DOC TYPES -
PRAR STATUS:
QU EF 5 YEARS ONLY:
PROCEDURE NUMBER ATT 13.0 ATT-14.0 ATT-14.1 ATT-14.2 ATI'-14.3 A1T-14.4 ATT-14. 5 ATT-14.6 ATT-15.0 ATT-15.1 ATI'-15.2 ATT-16.0 ATT-11. 0 ATI'-17.1 ATT-18.0 ATT-20.0 ATI'-21. 0 ATT-22.0 ATT-23.0 PROCEDURE TITLE ATTACHMENT NC ATTACHMENT NORMAL RHR COOLING ATTACHMENT RHR COOL ATI'ACHMENT RHR ISOL ATTACHMENT RHR NPSH ATTACHMENT RHR SAMPLE ATTACHMENT RHR SYSTEM ATTACHMENT RHR PRESS REDUCTION ATTACHMENT RCP START ATTACHMENT RCP DIAGNOSTICS ATTACHMENT SEAL COOLING ATTACHMENT RUPTURED S/G ATTACHMENT SD-1 ATTACHMENT SD-2 ATTACHMENT SFP -
RWST VENT TIME RCS ISOLATION ATTACHMENT RESTORING FEED FLOW ATTACHMENT TRANSFER 4160V LOADS REV EFFECT DATE LAST NEXT REVIEW REVIEW ST 002 07/26/94 02/10/98 02/10/03 EF 002 04/07/97 09/23/99 09/23/04 EF 004 05/01/98 05/01/98 05/01/03 EF 001 07/26/94 02/10/98 02/10/03 EF 002 08/01/97 01/06/99 01/06/04 EF 001 07/26/94 01/06/99 01/06/04 EF 002 07/26/94 02/10/98 02/10/03 EF 001 01/14/99 01/14/99 01/14/04 EF 005 05/22/97 03/17/00 03/11/05 EF 003 04/24/97 02/10/98 02/10/03 EF 003 05/22/97 02/10/98 02/10/03 EF 009 01/11/00 01/11/00 01/11/05 EF 009 04/06/00, 02/29/00 02/28/05 EF 005 09/26/96 09/10/96 09/10/01 EF 004 10/08/97 02/10/98 02/10/03 EF 003 07/26/94 02/10/98 02/10/03 BF 001 07/26/94 02/10/98 02/10/03 EF 001 02/12/99 03/24/97 03/24/02 EF 000 02/26/99 02/26/99 02/26/04 EF TOTAL FOR PRATT 43
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRES PARAMETERS:
DOC TYPES PRE PRES GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EQUIPMENT SUB-PROCEDURE PRF PRFR STATUS:
EF QU 5 YEARS PRECA ONLY:
03/30/00 PAGE:
3 PROCEDURE NUMBER ES-O.O ES-0. 1 ES-0. 2 ES-0. 3 PROCEDURE TITLE REDIAGNOSIS REACTOR TRIP RESPONSE NATURAL CIRCULATION COOLDOWN NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL REV EFFECT DATE LAST REVIEW NEXT REVIEW ST 008 05/01/98 05/01/98 05/01/03 EF 010 05/01/98 05/01/98 05/01/03 EF 01'7 03/31/00 05/01/98 05/01/03 EF 012 05/01/98 05/01/98 05/01/03 EF ES-l. 1 ES-1. 2 ES-1. 3 ES-3.1 ES-3". 2 ES-3. 3 SI TERMINATION POST IDCA COOLDOWN AND DEPRESSURIZATION TRANSFER TO COLD LEG RECIRCULATION POST-SGTR COOLDOWN USING BACKFILL POST-SGTR COOLDOWN USING BLOWDOWN POST-SGTR COOLDOWN USING STEAM DUMP 018 03/31/00 05/01/98 05/01/03 EF 021 03/31/00 05/01/98 05/01/03 EF 028 10/18/99 05/01/98 05/01/03 EF 013 05/01/98 05/01/98 05/01/03 EF 014 05/01/98 05/01/98 05/01/03 EF 014 05/01/98 05/01/98 05/01/03 EF TOTAL FOR PRES 10
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRECA GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EMERGENCY CONTINGENCY ACTIONS PROC 03/30/00 PAGE 2
PARAMETERS:
DOC TYPES PRE PRES PRECA PRF PRFR STATUS:
EF QU 5 YEARS ONLY:
PROCEDURE NUMBER ECA-0.0 ECA-0.1 ECA-0.2 ECA-1. 1 ECA-1. 2 ECA-2. 1 ECA-3. 1 ECA-3.2 ECA-3.3 PROCEDURE TITLE LOSS OF ALL AC POWER LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED LOSS OF EMERGENCY COOLANT RECIRCULATION LOCA OUTSIDE CONTAINMENT UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED SGTR WITHOUT PRESSURIZER PRESSURE CONTROL REV EFFECT DATE LAST REVIEW NEXT REVIEW ST 021 017 07/01/99 12/02/99 05/01/98 05/01/03 EF 05/01/98 05/01/03 EF 012 10/18/99 05/01/98 05/01/03 EF 018 12/02/99 05/01/98 05/01/03 EF 005 05/01/98 05/01/98 05/01/03 EF 020 03/31/00 05/01/98 05/01/03 EF 019 03/31/00 05/01/98 05/01/03 EF 022 03/31/00 05/01/98 05/01/03 EF 023 02/02/00 05/01/98 05/01/03 EF TOTAL FOR PRECA