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Category:Letter
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Ginna Nuclear Power Plant - Annual Commitment Change Notification RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator 2024-02-05
[Table view] Category:Operating Procedures
MONTHYEARML0536101822005-12-12012 December 2005 Revisions to Emergency Operating Procedures ML0532604132005-11-0404 November 2005 Rev. 5 to Emergency Operating Procedure AP-SG.1, Steam Generator Tube Leak. ML0531203082005-10-28028 October 2005 R. E. Ginna, Emergency Operating Procedures ML0529200482005-09-28028 September 2005 R. E. Ginna Emergency Operating Procedures, ATT-24.0, Rev 2 ML0522703522005-08-0303 August 2005 Submittal of Emergency Operating Procedures ML0520707062005-07-12012 July 2005 Emergency Operating Procedures ML0513702382005-04-28028 April 2005 Emergency Operating Procedures ML0513003412005-04-26026 April 2005 Revision 21 to Emergency Operating Procedure AP-CR.1, Control Room Inaccessibility. ML0510904052005-04-10010 April 2005 Letter Transmitting Ginna Station Emergency Operating Procedures ML0508903982005-03-18018 March 2005 Revisions to Emergency Operating Procedures ML0508303472005-03-11011 March 2005 R. E. Ginna, Emergency Operating Procedures ML0503304822005-01-21021 January 2005 Emergency Operating Procedures ML0434202032004-11-19019 November 2004 R. E. Ginna Nuclear Power Plant, Transmittal of Emergency Operating Procedures ML0435005402004-11-17017 November 2004 Transmittal of R.E. Ginna Nuclear Power Plant Emergency Operating Procedures ML0429405512004-10-0707 October 2004 R. E. Ginna Nuclear Power Plant, Emergency Operating Procedures ML0425305352004-09-0101 September 2004 Emergency Operating Procedures ML0421703052004-07-28028 July 2004 R. E. Ginna - Emergency Operating Procedures ML0419404762004-06-30030 June 2004 R. E. Ginna, Emergency Operating Procedures ML0418105602004-06-10010 June 2004 Emergency Operating Procedures ML0414001092004-04-29029 April 2004 R. E. Ginna - Emergency Operating Procedures ML0407106382004-03-0303 March 2004 R. E. Ginna Nuclear Power Plant, Emergency Operating Procedures ML0405707732004-02-17017 February 2004 Transmittal of Emergency Operating Procedures ML0404906722004-02-0404 February 2004 Emergency Operating Procedures ML0402201882004-01-0707 January 2004 Transmittal of Emergency Operating Procedures ML0400204162003-12-17017 December 2003 Revised Emergency Operating Procedures, Including Rev. 35 to E-0, Rev. 28 to E-1, Rev. 11 to E-2 & Rev. 35 to E-3 ML0334305112003-11-26026 November 2003 Emergency Operating Procedures ML0332400292003-11-0606 November 2003 Emergency Operating Procedures ML0329500832003-10-10010 October 2003 Emergency Operating Procedures ML0328804462003-10-0202 October 2003 Emergency Operating Procedures ML0327514252003-09-24024 September 2003 Emergency Operating Procedures ML0326612932003-08-26026 August 2003 Emergency Operating Procedures ML0320401662003-07-10010 July 2003 Emergency Operating Procedures Index and ECA-0.0, Rev. 026 ML0317503292003-05-30030 May 2003 Emergency Operating Procedures, Rev 2 of Att-2.4 Through Rev 26 of ECA-2.1 ML0317503282003-05-30030 May 2003 Emergency Operating Procedures ML0316204512003-05-30030 May 2003 Emergency Operating Procedures, Rev 26 of ECA-3.1 Through Rev 18 of FR-I.3 ML0314003192003-05-0808 May 2003 Emergency Operating Procedures, for R.E. Ginna Nuclear Power Plant ML0312802532003-04-30030 April 2003 Emergency Operating Procedures ML0310400122003-03-20020 March 2003 EOP Index & EOP-ATT-14.5, Rev. 3, Attachment RHR System. ML0306409142003-02-25025 February 2003 R. E. Ginna, Emergency Operating Procedures Including AP Index, AP-CR-1, Rev. 19, Control Room Inaccessibility; AP-ELEC.1, Rev. 24, Loss of 12A And/Or 12B Busses; AP-RCC.3, Rev. 6, Dropped Rod Recovery ML0224200802002-08-20020 August 2002 R. E. Ginna Emergency Operating Procedures ML0222400482002-07-30030 July 2002 R. E. Ginna Nuclear Power Plant Application for Renewed Operating License, Volume 3, Chapter 5, Page 5-1 - Attachments, List of Oversized Drawings ML0215703392002-05-21021 May 2002 Revision 11 to AP-RHR.2, Loss of RHR While Operating at RCS Reduced Inventory Conditions. ML0217902502002-03-0606 March 2002 Emergency Operating Procedures 2005-09-28
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Joseph A. Widay Ro Always at Your Servke Vice President and Plant Manager October 2, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, a G. i 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):
AT] Index ATT-17.0, Rev 15 An equal opportunity employer
-AC-10*
89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge .com An Energy East Company
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NPSP0200 Ginna Nuclear Power Plant Thu 10/2/2003 9:41:17 WRIGHTJ PROCEDURE INDEX Page 1 olf 2.
I r INPUT PARAMETERS: n fPE: PRATT STATUS VALUE(S): EF, aU 5 YEARS ONLY:
PRATT EOP ATTACHMENTS PROCEDURE EFFECT LAST NEXT __
NUMBER PROCEDURE TITLE RtEV DATE REVIEW REVIEW ST ATT-1.0 ATTACHMENT AT POWER CCW ALIGNMENT 003 0211212003 02/122003 02/12008 EF ATT-t.1 ATTACHMENT NORMAL CCW FLOW 000 051812000 051812000 05/1U2005 EF ATT-2.1 ATTACHMENT MIN SW 005 021012001 02/03/2003 02/03/2008 EF ATT-2.2 ATTACHMENT SW ISOLATION 008 03/1082002 03/27/2003 03127/2008 EF ATT-2.3 ATTACHMENT SW LOADS INCNMT 004 03/0612002 12/31/1999 12/31/2004 EF ATT-2.4 ATTACHMENT NO SW PUMPS 002 0513012003 10/31/2001 10/31120 EF ATT-2.5 ATTACHMENT SPLIT SW HEADERS 000 06/28/2002 086/2002 06/28/2007 EF ATT-3.0 ATTACHMENT CCV, 008 03/06/2002 01/08/1999 01/08/2004 EF ATT-3.1 ATTACHMENT CNMT CLOSURE 004 03108/2002 01125/1999 01/25/2004 EF ATT-4.0 ATTACHMENT CNMT RECIRC FANS 003 07126/1994 03/2712003 03/27/2008 EF ATT-5.0 ATTACHMENT COND TO S/G 005 031082002 12/31/1999 1231/2004 EF ATT-5.1 ATTACHMENT SAFW 008 05130/2002 12/31/1999 1231/2004 EF ATT-5.2 ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP 003 0111411999 0111411999 01/14/2004 EF ATT-4.0 ATTACHMENT COND VACUUM 003 12118/1998 020312003 02/03/2008 EF ATT-7.0 ATTACHMENT CR EVAC 008 03/0862002 02/03/2003 02/03/2008 EF ATT-8.0 ATTACHMENT DC LOADS 008 03/2211999 0111411999 01/14/2004 EF ATT-8.1 ATTACHMENT D/G STOP 005 03/0612002 0203/2003 02/03/2008 EF ATT-8.2 ATTACHMENT GEN DEGAS 008 06120/2002 08/17/1999 08/17/2004 EF ATT-8.3 ATTACHMENT NONVITAL 004 03/062002 02/03/2003 02/3/2008 EF ATT-8.4 ATTACHMENT SUN 005 03/0682002 02/03/2003 02/03/2008 EF ATT-8.5 ATTACHMENT LOSS OF OFFSITE POWER 001 08126/2003 05/02/2002 05/02/2007 EF ATT-9.0 ATTACHMENT LETDOWN 008 03/06/2002 03/08/2002 03/0612007 EF ATT-9.1 ATTACHMENT EXCESS LID 005 03/0862002 10/31/2001 10131/2006 EF ATT-10.0 ATTACHMENT FAULTED S/G 008 03/06/2002 03127/2003 03/27/2008 EF ATT-11.0 ATTACHMENT IA CONCERNS 003 06/28/2003 03/27/2003 03/27/2008 EF ATT-11.1 ATTACHMENT IA SUPPLY 003 03/0812002 03/2712003 03/27/2008 EF ATT-11.2 ATTACHMENT DIESEL AIR COMPRESSOR 004 11/16/2002 03/10/2003 03/10/2008 EF ATT-12.0 ATTACHMENT N2 PORVS 005 02112003 0211212003 02/122008 EF ATT-13.0 ATTACHMENT NC 003 02/12003 0211 22003 02/1212008 EF ATT-14.0 ATTACHMENT NORMAL RHR COOLING 003 03/06/2002 09/231999 09/23/2004 EF
( ( ( .S3 NPSP0200 Ginna Nudear Power Plant Thu 10/2/2003 9:41:17 am WRIGHTJ PROCEDURE INDEX Page 2 of 2 INPUT PARAMETERS: TYPE: PRATT STATUS VALUE(S): EF. OU 5 YEARS ONLY: .I PRATT EOP ATTACHMENTS PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REv DATE REW REVIEW ST ATT-14.1 ATTACHMENT RHR COOL 006 04/302003 0110812002 01/0812007 EF ATT-14.2 ATTACHMENT RHR ISOL 003 02122003 02122003 02/12/2008 EF ATT-14.3 ATTACHMENT RHR NPSH 003 0306/2002 01/08/1999 01/06/2004 EF ATT-14.5 ATTACHMENT RHR SYSTEM 003 03/20/2003 02/03/2003 02/03/2008 EF ATT-14.6 ATTACHMENT RHR PRESS REDUCTION 002 03/08/2002 01/1411999 01/14/2004 EF ATT-15.0 ATTACHMENT RCP START 009 03/06/2002 03/17/2000 03/17/2005 EF ATT-15.1 ATTACHMENT RCP DIAGNOSTICS 003 04/24/1997 02/03/2003 02/03200 EF ATT-15.2 ATTACHMENT SEAL COOLNG 005 03/2002 02/03/2003 02/0312008 EF ATT-16.0 ATTACHMENT RUPTURED SIG 011 07/1812001 01/11/2000 01/11/2005 EF ATT-16.1 ATTACHMENT SGTL 002 03/06/2002 09/08/2000 09/0812005 EF ATT-16.2 ATTACHMENT RCS BORON FOR SGTL 002 04/09/2002 09/08/2000 09/082005 EF ATT-17.0 ATTACHMENT SD-I 015 10/02/2003 02/29/2000 02/282005 EF ATT-17.1 ATTACHMENT SD-2 006 03/08/2002 01130/2001 01/30/2006 EF ATT-18.0 ATTACHMENT SFP - RWST 005 03/0682002 02/032003 02/0312008 EF ATT-20.0 ATTACHMENT VENTTIME 003 07/26/1994 02/03/2003 02/03/2008 EF ATT-21.0 ATTACHMENT RCS ISOLATION 002 03/06/2002 02/03/2003 02/032008 EF ATT-22.0 ATTACHMENT RESTORING FEED FLOW 003 05/2002 011222002 01/22/2007 EF ATT-23.0 ATTACHMENT TRANSFER 4160V LOADS 000 0226/1999 02/26/1999 02/26/2004 EF ATT-24.0 ATTACHMENT TRANSFER BATTERY TO TSC 000 09/08/2000 09/0812000 09/08/05 EF ATT-26.0 ATTACHMENT RETUN TO NORMAL OPERATIONS 000 10/31/2001 10131/2001 10/31/2006 EF PRATT TOTAL 50 GRAND TOTAL 50
Responsible Manager Date 10i0? -ae Perform the following local actions to complete normal secondary system shutdown:
o Close reheater 4th pass temperature control valves:
o V-2432 (SW corner A MSR) o V-2433 (SW corner B MSR) o V-2434 (SW corner 2A MSR) o V-2435 (SW corner 2B MSR) o Close reheater steam chain valves:
o V-3550 (SW of B MSR) o V-3551 (SW of B MSR) o V-3552 (NW of 1A MSR) o V-3553 (NW of 1A MSR) o Open Reheater steamline vents (SW corner of condenser, middle floor):
o V-8500 o V-8501 o V-8502 o V-8504 o V-8505 o Open Reheater steamline vents (SW corner of condenser, above walkway):
o V-8506 o V-8507 o V-8508 o V-8509 o Locally close flange heating isolation valves:
o MOV-3601A (TB Middle Lvl East of TURB Lube Oil Reservoir) o MOV-3602A NOTE: IF either S/G pressure is LESS THAN condensate header pressure, THEN manual isolation of the MFW regulating and bypass valves should be considered before aligning for cooldown recirculation.
o Open the following valves to align for condensate feed system cooldown RECIRC:
o V-3982B (at 5 heater outlet header) o V-3983B (at 5 heater outlet header) o V-4363 (at 5 heater outlet header) o V-4365 (by MFW regulating valves) o V-4361 (southwest corner of condenser, middle floor) o V-3976A MFP A discharge valve bypass valve o V-3977A MFP B discharge valve bypass valve o Secure all 5 secondary chemical addition pumps on TURB BLDG middle floor by 5 heaters.
o Secure all 3 ammonia pumps, TURB BLDG basement by MCC A.
o Secure the Ethanolamine (ETA) injection pump, TURB BLDG basement by turbine lube oil purifier.
o Open Turbine Extraction Line Drain AOV-3850 isolation valve V-3884 (Turb Bldg Basement west platform, north end) o Open Turbine Extraction Line Drain AOV-3845 isolation valve V-3883-(Turb Bldg Basement west platform, north end) o Isolate SW from the following coolers:
o MFW Pump Oil Coolers (MFW pump room) o V-4703 o V-4704 o Exciter Air Cooler:
o V-4679B (chain valve next to condensate transfer pump) o Bus Duct Air Cooler (TURB BLDG basement East of bus duct cooler) o V-4674 o V-4674C (mini bypass around V-4674) o Throttle SW as necessary from following coolers:
o Generator Seal Oil Unit Coolers (H2 side and air side):
o V-4676A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o V-4677A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o Main Lube Oil Coolers (SW corner of Turb Oil Reservoir) o V-4691 o V-4692 o IF HDT Pump A seal injection primary filter (FGSO1A) is in service, THEN perform the following to place the HDT Pump A seal injection bypass line (and filter FGS02A) in service and isolate the primary filter as follows (north side of HDT Pump A):
- 1. Ensure closed HDT Pump A bypass filter outlet valve, V-3709C.
- 2. Slowly open HDT Pump A bypass filter inlet isolation, V-3907F.
- 3. Slowly throttle open HDT Pump A bypass filter outlet valve, V-3709C WHILE concurrently closing HDT Pump A primary filter outlet valve, V-3709B to maintain approximately 5 - 8 gpm seal injection flow (FAL-3799A).
o IF HDT Pump B seal injection primary filter (FGSO1B) is in service, THEN perform the following to place the HDT Pump B seal injection bypass line (and filter FGS02B) in service and isolate the primary filter as follows (south side of HDT Pump B):
- 1. Ensure closed HDT Pump B bypass filter outlet valve, V-3710C.
- 2. Slowly open HDT Pump B bypass filter inlet isolation, V-3910F.
- 3. Slowly throttle open HDT Pump B bypass filter outlet valve, V-3710C WHILE concurrently closing HDT Pump B primary filter outlet valve, V-3710B to maintain approximately 5 - 8 gpm seal injection flow (FAL-3799B).
o WHEN the turbine shaft stops, THEN notify Control Room. Control Room personnel will determine if adequate power (36 KW) available to start turning gear.
o Transfer house heating steam to house heating boiler if necessary (refer to T-35H, NUCLEAR HOUSE HEATING STEAM TO BOILER STEAM SUPPLY CHANGE).
o Align S/G blowdowns as follows:
- 1. Secure blowdown to the condenser per T-14G, STEAM GENERATOR BLOWDOWN HEAT RECOVERY SYSTEM SHUTDOWN.
- 2. Verify S/G releases are in effect. IF NOT, THEN ensure releases are in effect before performing the next step.
- 3. Align Steam Generator Blowdown Flash Tank drains to the discharge canal per T-14F.1, SG BLOWDOWN ALIGNMENT TO DISCHARGE CANAL.
o Restore MAKEUP to CSTs as directed by Control Room.