ML030560547
| ML030560547 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/12/2003 |
| From: | Widay J Rochester Gas & Electric Corp |
| To: | Clark R Document Control Desk, NRC/NRR/DLPM/LPD1 |
| References | |
| Download: ML030560547 (9) | |
Text
R .Lf A Subsidiary of RGS Energy Group, Inc ROCHESTER GAS AND ELECTRIC CORPORATION
- 89 EASTAVENUE, ROCHESTER, N Y 14649-0001 - 716-771-3250 wwwrge corn JOSEPH A WIDAY VICEPRESIDENT & PLANT MANAGER GINNA STATION February 12, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Robert Clark Project Directorate I Washington, D.C. 20555
Subject:
Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Clark:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, s 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 ATT-1.0, Rev 3 ATT-12.0, Rev 5 ATT-13.0, Rev 3 ATT-14.2, Rev 3 4V14
"REPORT NO. 01 GINNA NUCLEAR POWER PLANT
( 02/12/03 PAGE: 30
(
REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRATT EOP ATTACHMENTS PARAMETERS: DOC TYPESS - PRATT PRAR PRER ST.ATUS EF OU 5 YEARS ONLY PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ATT-I 0 ATTACHMENT AT POWER CCW ALIGNMENT 003 02/12/03 02/12/03 02/12/08 EF ATT-1.1 ATTACHMENT NORMAL C-W FLOW 000 05/18/00 05/18/00 05/18/05 EF ATT-2.1 ATTACHMENT MIN SW 005 02/01/01 02/03/03 02/03/08 EF ATT-2.2 ATTACHMENT SW ISOLATION 008 03/06/02 08/11/98 08/11/03 EF ATT-2.3 ATTACHMENT SW LOADS IN CNMT 004 03/06/02 12/31/99 12/31/04 EF ATT-2.4 ATTACHMENT NO SW PUMPS 001 01/08/02 10/31/01 10/31/06 EF ATT-2.5 ATTACHMENT SPLIT SW HEADERS 000 06/26/02 06/26/02 06/26/07 EF ATT-3.0 ATTACHMENT CI/CVI 006 03/06/02 01/06/99 01/06/04 EF ATT-3.1 ATTACH4ENT CNMT CLOSURE 004 03/06/02 01/25/99 01/25/04 EF ATT-4.0 ATTACIDENT CNMT RECtRC FANS 003 07/26/94 05/13/98 05/13/03 EF ATT-5.0 ATTACHMENT COND TO S/G 005 03/06/02 12/31/99 12/31/04 EF ATT-5.1 ATTACHMENT SAFW 008 05/30/02 12/31/99 12/31/04 EF ATT-5.2 ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP 003 01/14/99 01/14/99 01/14/04 EF ATT-6.0 ATTACHMENT COND VACUUM 003 12/18/96 02/03/03 02/03/08 EF ATT-7.0 ATTACHMENT CR EVAC 006 03/06/02 02/03/03 02/03/08 EF ATT-8.0 ATTACHMENT DC LOADS 006 03/22/99 01/14/99 01/14/04 EF ATT-8.1 ATTACHMENT D/G STOP 005 03/06/02 02/03/03 02/03/08 EF ATT-8.2 ATTACHMENT GEN DEGAS 008 06/20/02 08/17/99 08/17/04 EF ATT-8.3 ATTACHMENT NONVITAL 004 03/06/02 02/03/03 02/03/08 EF ATT-8.4 ATTACHMENT SI/UV 005 03/06/02 02/03/03 02/03/08 EF ATT-8.5 ATTACHMENT LOSS OF OFFSITE POWER 000 05/02/02 05/02/02 05/02/07 EF ATT- 9.0 ATTACHMENT LETDOWN 008 03/06/02 03/06/02 03/06/07 EF ATT-9.1 ATTACHMENT EXCESS L/D 005 03/06/02 10/31/01 10/31/06 EF ATT-10 0 ATTACHMENT FAULTED S/G 006 03/06/02 05/13/98 05/13/03 EF
REPORT NO 01( GINNA NUCLEAR POWER PLANT C 02/12/03 PAGE: 31 C
REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRATT EOP ATTACHMENTS PARAMETERS: DOC TYPES - PRATT PRAR PRER ST* ATUS. EF QU 5 Y'EARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ATT-11.0 ATTACHMENT IA CONCERNS 002 04/07/97 08/11/98 08/11/03 EF ATT-11.1 ATTACHMENT IA SUPPLY 003 03/06/02 08/11/98 08/11/03 EF ATT-11.2 ATTACHMENT DIESEL AIR COMPRESSOR 004 11/18/02 04/03/98 04/03/03 EF ATT- 12.0 ATTACHMENT N2 PORVS 005 02/12/03 02/12/03 02/12/08 EF ATT-13.0 ATTACHMENT NC 003 02/12/03 02/12/03 02/12/08 EF ATT-14.0 ATTACHMENT NORMAL RHR COOLING 003 03/06/02 09/23/99 09/23/04 EF ATT-14.1 ATTACHMENT RHR COOL 005 01/08/02 01/08/02 01/08/07 EF ATT-14.2 ATTACIHMENT RHR ISOL 003 02/12/03 02/12/03 02/12/08 EF ATT-14.3 ATTACHMENT RUR NPSH 003 03/06/02 01/06/99 01/06/04 EF ATT-14.5 ATTACHMENT RHR SYSTEM 002 07/26/94 02/03/03 02/03/08 EF ATT-14.6 ATTACHMENT RI{R PRESS REDUCTION 002 03/06/02 01/14/99 01/14/04 EF ATT-15.0 ATTACHMENT RCP START 009 03/06/02 03/17/00 03/17/05 EF ATT-15.1 ATTACHMENT RCP DIAGNOSTICS 003 04/24/97 02/03/03 02/03/08 EF ATT-15 2 ATTACHMENT SEAL COOLING 005 03/06/02 02/03/03 02/03/08 EF ATT-16.0 ATTACHMENT RUPTURED S/G 011 01/18/01 01/11/00 01/11/05 EF ATT-16.1 ATTACHMENT SGTL 002 03/06/02 09/08/00 09/08/05 EF ATT-16.2 ATTACHMENT RCS BORON FOR SGTL 002 04/09/02 09/08/00 09/08/05 EF ATT- 17. 0 ATTACHMENT SD-I 014 06/20/02 02/29/00 02/28/05 EF ATT-17.1 ATTACHMENT SD-2 006 03/06/02 01/30/01 01/30/06 EF ATT-18.0 ATTACHMENT SFP - RWST 005 03/06/02 02/03/03 02/03/08 EF ATT-20 .0 ATTACHMENT VENT TIME 003 07/26/94 02/03/03 02/03/08 EF ATT- 21 .0 ATTACHMENT RCS ISOLATION 002 03/06/02 02/03/03 02/03/08 EF ATT-22. 0 ATTACHMENT RESTORING FEED FLOW 003 05/02/02 01/22/02 01/22/07 EF ATT-23.0 ATTACHMENT TRANSFER 4160V LOADS 000 02/26/99 02/26/99 02/26/04 EF
REPORT NO 01 REPORT NPSP0200 GINNA NUCLEAR POWER PLANT PROCEDURES INDEX
( 02/12/03 PAGE- 32 f
DOC TYPE PRATT EOP ATTACHMENTS PARAMETERS, DOC TYPES - PRATT PRAR PRER STATUS- EF QU S YEARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURI E TITLE REV DATE REVIEW REVIEW ST ATT-24 .0 ATTACIME! NT TRANSFER BATTERY TO TSC 000 09/08/00 09/08/00 09/08/05 EF ATT-26 0 ATTACHME? NT RETURN TO NORMAL OPERATIONS 000 10/31/01 10/31/01 10/31/06 EF TOTAL FOR PRATT so
EDP. TITLE:
REV: 3 ATT-l.O ATTACHMENT AT POWER CCW ALIGNMENT PAGE 1 of 1 Responsible Manager Date 2-/c- 2o(
This attachment provides the normal at power valve alignment for control board operated valves:
NOTE: IF any valve position differs from that indicated below, THEN the reason should be determined and the valve restored to normal if desired.
o CCW to RHR Hx A MOV-738A Closed o CCW to RHR Hx B MOV-738B Closed o CCW from RCP 1A Thermal Barrier AOV-754A Open o CCW from RCP 1B Thermal Barrier AOV-754B Open o CCW from Ex Ltdn Hx Isol Vlv AOV-745 Open o CCW Surge Tk Vent RCV-017 Open o CCW to CNMT Isol Vlv MOV-817 Open o CCW to Rx Supp Clrs Isol Vlv MOV-813 Open o CCW from Rx Supp Clrs Isol Vlv MOV-814 Open o CCW to RCP 1A Isol Vlv MOV-749A Open o CCW to RCP lB Isol Vlv MOV-749B Open o CCW from RCP lA Isol Vlv MOV-759A Open o CCW from RCP 1B Isol Vlv MOV-759B Open o NRHX Ltdn Outlet Iemp (Controller) TCV-130 In Auto at approximately 1000 F
EOP:" TITLE:
REV: 5 ATT-12.0 ATTACHMENT N2 PORVS PAGE 1 of 2 Responsible Manager U4" Date 2/P-6c5 6
WHEN IA to CNMT NOT available, THEN perform the following to operate one (or both) PRZR PORV(s) in accordance with guidance provided by the procedure step:
NOTE: o If RCS overpressurization accumulator pressure decreases to less than 200 psig, then recharge accumulators using S-29.2, CHARGING THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM ACCUMULATORS WITH N2.
This will require reset of CI and XY relays for the N2 supply valve to CNMT, AOV-846.
o For FR-H.1 Bleed and Feed the PORV block valve is not required to be operable.
A) Select a PORV with an operable block valve, obtain a key for the RCS overpressurization system, and perform the appropriate step below:
o PCV-431C:
a) Verify block valve MOV-515 - OPEN AND OPERABLE b) Place ACCUM TO SURGE TK VLV SOV-8616B to OPEN o PCV-430:
a) Verify block valve MOV-516 - OPEN AND OPERABLE b) Place ACCUM TO SURGE TK VLV SOV-8616A to OPEN B) To depressurize the RCS in accordance with the guidance provided by the EOP step, perform the following:
o For PCV-431C, place overpressurization system arming switch, N2 ARMING VLV SOV-8619B, to ARM o For PCV-430, place overpressurization system arming switch, N2 ARMING VLV SOV-8619A, to ARM C) IF it is desired to maintain PORV(s) open below 410 psig, THEN place overpressure bistables to the trip position:
(IF NOT, THEN go to step D)
- 1. In R-2 Protection Channel 1 Rack "o 452B "o 452C
- 2. In W-2 Protection Channel 2 Rack o 451B o '451C
- 3. In B-2 Protection Channel 3 Rack o 450B o 450C
- EOP: -TITLE: "--- REV:
R V 5 ATT-12.0 ATTACHMENT N2 PORVS PAGE 2 of 2 D) WHEN depressurization complete, THEN close PORV(s) by performing the following:
"o For PCV-431C:
o Place N2 ARMING VLV SOV-8619B to BLOCK o Place ACCUM TO SURGE TK VLV SOV-8616B to CLOSE "o For PCV-430:
"o Place N2 ARMING VLV SOV-8619A to BLOCK "o Place ACCUM TO SURGE TK VLV SOV-8616A to CLOSE E) Ensure the overpressure protection bistables in the untripped position:
- 1. In R-2 Protection Channel 1 Rack o 452B o 452C
- 2. In W-2 Protection Channel 2 Rack "o 451B "o 451C
- 3. In B-2 Protection Channel 3 Rack o 450B o 450C
Responsible Manager Q S Date /' O6 NOTE: It may take several minutes following initial transient for natural circulation to develop.
The following conditions indicate natural circulation flow:
"o RCS subcooling based on core exit T/Cs - GREATER THAN REQUIREMENTS OF FIGURE MIN SUBCOOLING "o S/G pressures - STABLE OR DECREASING "o RCS hot leg temperatures - STABLE OR DECREASING "o Core exit T/Cs - STABLE OR DECREASING "o RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR S/G PRESSURE The following equipment should be operating to support natural circulation and cooling:
"o Control rod shroud fans "o PRZR heaters (IF D/G loading does NOT permit loading an entire bank of heaters, THEN refer to ER-PRZR.1, RESTORATION OF PRZR HEATERS DURING BLACKOUT)
"o One Reactor Compartment Cooling Fan
EOP: TITLE:
REV: 3 ATT-14.2 ATTACHMENT RHR ISOL PAGE 1 of 1 Responsible Manager ___ Date 2/ -5 NOTE: o An A-52.4 should be submitted for train being isolated.
o A locked valve key will be required for local operations.
o Consult RP tech prior to performing any work above the 8 foot level on any AUJX BLDG floor.
- 1) Place the selected RHR pump switch in PULL STOP.
- 2) Isolate the selected RHR pump as follows:
RHR pump A:
"o Close RHR pump A suction valves "o MOV-704A "o MOV-850A "o Close RHR Hx flow control valve, HCV-625 "o Close RHR Hx bypass valve, HCV-626 "o Verify discharge to SI pump suction, MOV-857A, closed "o Dispatch AO to locally perform the following:
"o Close recirculation line isolation valve, V-694A (south of RWST purification pump)
"o Ensure closed RHR pump A discharge crosstie valve, V-709C (RHR sub-basement above RHR pumps)
"o Close RHR Hx A manual isolation valve, V-717 (by HCV-625)
"o Close either R1IR lix bypass isolation valve, V-712A or V-712B (AUX BLDG basement outside RHR Hx room)
o Close RHR pump B suction valves o MOV-704B o MOV-850B o Close RHR Hx flow control valve, HCV-624 o Close RHR Hx bypass valve, HCV-626 o Verify discharge to SI pump suction, MOV-857B, closed o Dispatch AO to locally perform the following:
o Close recirculation line isolation valve, V-694B (south of RWST purification pump) o Ensure closed RIIR pump B discharge crosstie valve, V-709D (RHR sub-basement above RHR pumps) o Close RHR Hx B manual isolation valve, V-715 (by HCV-624) o Close either RHR Hx bypass isolation valve, V-712A or V-712B (AUX BLDG basement outside RHR Hx room)