ML17311A067
| ML17311A067 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/14/1999 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17265A517 | List: |
| References | |
| NUDOCS 9901220051 | |
| Download: ML17311A067 (33) | |
Text
CATEGORY 1 REGULA'RY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9901220051 DOC.DATE: 99/01/14 NOTARIZED: NO
DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME.
AUTHOR AFFILIATION WIDAY,J.A.
Rochester Gas S Electric Corp.
pm~
RECXP.NAME RECIPIENT AFFILIATION VISSING,G.S.
SUBJECT:
Forwards revised Emergency Operating Procedures for plant.
DISTRIBUTION CODE: A002D COPIES RECEIVED:LTR ENCL SXZE:
TITLE: OR Submittal:Inadequate Core Cooling (Item II.F.2)
GL 82-2 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) 05000244~
RECIPIENT ID CODE/NAME PD1-1 PD COPIES LTTR ENCL 1
1 RECIPIENT ID CODE/NAME VISSING,G.
COPIES LTTR ENCL 1
1 INTERNA LE CE T R 0
1 1
1 1
1 NRR/DSSA/SRXB RES/DET/EIB 1
1 1
1 EXTERNAL: NOAC NRC PDR 1
1 0
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 9
ENCL 9
8F:
ROCHESTERGASANDELECTRICCORPORATION o 89EASTAVENUE ROCHESTER, N.K 14649<001 JOSEPH A. WIDAY TELEPHONE Plant Managor AAEACODE 716 546.2700 Ghna Nucloar Plant January 14, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 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 oseph A. Wida 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-Index E Index ECA Index ES Index FR Index AP-SW.1, Rev 14 Zyoo82 ATT-5.2, Rev 3 ATT-8.0, Rev 5 ATT-14.6, Rev 1
E-1, Rev 17.
ECA-1.1, Rev 16 ES-1.3, Rev 26 FR-Z.2, Rev 4 9'F01220051 9'PQ1.14
,PDR ADOCK 05000244 F
~I Lt 4P If If ef'- f
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 12/14/98 PAGE:
1 P
ERS:
DOC TYPES -
PRAP PRE PRECA PRER PRES STATUS:
EF QU 5 YEARS ONLY:
PROCEDUR NUYBER AP-CCW.1 AP-CCW.2 AP-CCW.3 AP-CR.1 AP-CVCS.1 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.1 AP-RCC.1 AP-RCC.2 AP RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS.2 AP-RCS.3 AP-RCS.4 AP-RHR.1 AP-RHR.2 PROCEDURE TITLE
~E IÃIO THE COMPONENT COOLING LOOP SS OF CCW DURING POWER OPERATION LOSS 0 PLANT SHUTDOWN CONTROL ROOM CVCS LEAK SIBILITY LOSS OF A CIRC WATER PUMP LOSS OF 12A AND/OR 128 BUSSES SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FR UENCY LOSS OF 12A A%)/OR 12B TRANSFORMER (BELOW 350 F)
LOSS OF SAFEGUARDS BUS li/16 LOSS OF SAFEGUARDS BUS 11/18 PARTIAL OR COMPLETE LOSS OF PAIN FEEDWATER LOSS OF INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD WITHDRAWAL/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 LOSS OF RHR WHILE OPERATIN T RCS REDUCED INVENTORY CONDITIONS EFFECT DATE LAST REVIEW NEXT REVIEW ST 013 10/30/98 05/01/98 05/01/03 EF 012 02/24/96 08/30/94 08/30/99 EF 010 03/29/96 08/30/94 08/30/99 EF 015 01/26/98 11/17/94 11/17/99 EF 012 05/01/98 010 07/16/98 016 05/01/98 008 01/26/98 005 05/01/98 05/01/98 05/01/03+F 05/01/98 05/0 03 EF 05/01/98 5/01/03 EF 02/11/ci4 02/11/99 EF 05/
/98 05/01/03 EF 007 009 08/05/97 08/05/97 08/05/02 EF 05/01/98 05/01/98 05/01/03 EF 012 05/01/98 05/01/98 05/01/03 EF 007 05/15/97 03/21/95 03/21/00 EF 000 06/09/97 6/09/97 06/09/02 EF 001 02/27/
8 06/09/97 06/09/02 EP 011 02 7/98 02/27/98 02/27/03 EF 01 05/01/98 05/01/98 05/01/03 EF 09 0
3/96 09/29/94 09/29/99 EF 006 02/24/9 05/14/98 05/14/03 EF 008 11/16/98 02/0 97 02/06/02 EF 004 11/16/98 02/27/98
/27/03 EF 012 05/01/98 05/01/98 05/0 03 EF 013 05/01/98 05/01/98 05/01/03 010 12/14/98 05/01/98 05/01/03 EF
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 12/14/98 PAGE:
2 PARAMETERS:
DOC TYPES -
PRAP PRE PRECA PRER PRES STATUS:
EF QU 5 YEARS ONLY:
PROCEDURE NUMBER AP SW. 1 AP TURB.1 AP-TURB. 2 AP-TURB. 3 AP-TURB. 4 AP-TURB.5 PROCEDURE TITLE SERVICE WATER LEAK TURBINE TRIP WITWOlTT RX TRIP REQUIRED TURBINE LOAD REJECTION TURBINE VIBRATION LOSS OF CONDENSER VACUUM RAPID LOAD REDUCTION EFFECT DATE LAST REVIEW NEXT REVIEW ST 013 08/24/98 06/03/98 06/03/03 EF 009 10/10/97 10/10/97 10/10/02 EF 016 02/27/98 05/13/98 05/13/03 EF 008 12/04/96 02/10/98 02/10/03 EF 014 05/01/98 05/01/98 05/01/03 EF 003 02/27/98 07/10/95 07/10/00 EF TOTAL FOR PRAP 30
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRATT GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EOP ATTACHMENTS 10/30/98 PAGB:
1 PARAMETERS:
DOC TYPES - PRATT 5 YEARS ONLY:
PROCEDURE NUMBER ATT-1.0 ATT-2.0 ATT-2. 1 ATT-2.2 ATT-2.3 ATT-3.0 ATT-3. 1 ATT-4.0 ATT-5. 0 ATI'-5.1 ATT-5.2 ATT-6.0 ATT-7.0 ATT-8. 0 ATT-8.1 ATT-8.2 ATT-8.3 ATT-8.4 ATT-9.0 ATT-9.1 ATT-10.0 ATT-11.0 ATT-11. 1 ATT-11.2 PROCEDURE TITLB ATTACHMENT AT POWER CCW ALIGNMENT ATTACHMENT AUX BLDG SW ATI'ACHMENTMIN SW ATTACHMENT SW ISOLATION ATTACHMENT SW LOADS IN CNMT ATTACHMENT CI/CVI ATTACHMENT CNMT CLOSURE ATTACHMENT CNMT RECIRC PANS ATTACHMENT COND TO S/G ATTACHMENT SAFW ATTACHMENT PIRE WATER COOLING TO TDAFW PUMP ATTACHMENT COND VACUUM ATTACHMENT CR EVAC ATTACHMENT DC LOADS ATTACHMENT D/G STOP ATTACHMENT GEN DEGAS ATTACHMENT NONVITAL ATI'ACHMENT S I/UV ATTACI94ENT LETDOWN ATTACHMENT BXCESS L/D ATTACHMENT PAULTED S/G ATTACHMENT IA CONCERNS ATTACHMENT IA SUPPLY ATTACHMENT DIESEL AIR COMPRESSOR EFFBCI'ATE LAST REVIEW 004 06/26/98 02/10/98 02/10/03 BF 005 10/30/98 08/11/98 08/11/03 EP 003 01/25/95 01/25/95 01/25/00 EP 004 02/27/98 02/11/94 02/11/99 BP 002 07/26/94 02/ll/94 02/11/99 EP 003 07/26/94 05/13/98 05/13/03 EF 004 01/25/95 01/25/95 01/25/00 EP 006 07/07/98 11/08/94 11/08/99 EF 002 10/26/95 03/04/94 03/04/99 BF 003 12/18/96 02/10/98 02/10/03 EF 004 05/04/98 02/10/98 02/10/03 EF 004 06/03/98 01/26/94 01/26/99 EF 004 11/03/95 02/10/98 02/10/03 EF 005 07/26/94 02/11/94 02/11/99 EF 003 07/26/94 02/10/98 02/10/03 EF 004 04/24/97 02/10/98 02/10/03 EF 006 04/07/97 01/26/94 01/26/99 EF 002 07/26/94 02/10/98 02/10/03 EF 005 10/03/96 05/13/98 05/13/03 EF 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 001 07/26/94 02/10/98 02/10/03 EF 06/26/98
I
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRATT GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EOP ATTACHMENTS 10/30/98 PAGE:
2 PARAMETERS:
DOC TYPES - PRATT 5 YEARS ONLY:
PROCEDURE NUMBER ATT-12.0 ATT-13.0 ATT-14.0 ATT-14.1 ATT-14.2 ATT-14.3 ATT-14.4 ATT-14.5 ATT-14. 6 ATT-15.0 ATT-15.1 ATT-15.2 ATT-16' ATT-17.0 ATT-17. 1 ATT-18. 0 ATT-19.0 ATT-20.0 ATT-21.0 ATT-22.0 PROCEDURE TITLE ATTACHMENT N2 PORVS ATTACHMENT NC ATTACHMENT NORMAL RHR COOLING ATTACHMENT RHR COOL ATTACHMENT RHR ISOL ATTACHMENT RHR NPSH ATTACHMENT RHR SAMPLE ATTACHMENT RHR SYSTEM ATTACHMENT RHR PRESS REDUCTION ATI'ACHMENT RCP START ATI'ACHMENT RCP DIAGNOSTICS ATTACHMENT SEAL COOLING ATTACHMENT RUPTURED S/G ATTACHMENT SD-1 ATTACK48NT SD-2 ATTACHMENT SFP - RWST ATTACHMENT SI FLUSH ATTACHMENT VENT TIME ATTACHMENT RCS ISOLATION ATTACHMENT RESTORING FEED FLOW EFFECT DATE LAST REVIEW 003 03/24/97 02/10/98 02/10/03 EP 002 07/26/94 02/10/98 02/10/03 EF 002 04/07/97 10/19/94 10/19/99 EF 004 05/01/98 05/01/98 05/01/03 EP 001 07/26/94 02/10/98 02/10/03 EP 002 08/01/97 01/26/94 01/26/99 EF 001 07/26/94 01/26/94 01/26/99 EF 002 07/26/94 02/10/98 02/10/03 EF 000 04/07/94 04/07/94 04/07/99 EP 005 05/22/97 04/20/95 04/20/00 EF 003 04/24/97 02/10/98 02/10/03 EF 003 05/22/97 02/10/98 02/10/03 EP 008 03/17/98 11/08/94 11/08/99 EF 006 11/03/95 02/03/95 02/03/00 EP 005 09/26/96 01/26/94 01/26/99 EF 004 10/08/97 02/10/98 02/10/03 EF XX 01/25/95 DE 003 07/26/94 02/10/98 02/10/03 EP 001 07/26/94 02/10/98 02/10/03 EP 000 03/24/97 03/24/97 03/24/02 EF TOTAL FOR PRATT 44
> ~
0
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRE GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EMERGENCY PROCEDURE 12/14/98 PAGE:
3 PARAMEIERS:
DOC TYPES -
PRAP PRE PRECA PRER PRES STATUS: EF QU 5 YEARS ONLY:
PROCEDURE NUMBER E-O E-1 E 2 E-3 PROCEDURB TITLE REACIOR TRIP OR SAFETY INJECTION LOSS OF REACTOR OR SECONDARY COOLANT FAULTED STEAM GENERATOR ISOLATION STEAM GENERATOR TUBE RUPTURE EFFECT DATE LAST REVIEW NEXT REVIEW ST 024 05/01/98 05/01/98 05/01/03 EF 016 05/01/98 05/01/98 05/01/03 EF 008 05/01/98 05/01/98 05/01/03 EF 023 12/14/98 05/01/98 05/01/03 EF TOTAL FOR PRE
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRECA GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EMERGENCY CONTINGENCY ACTIONS PROC 12/14/98 PAGE:
4 PARAMETERS:
DOC TYPES -
PRAP PRE PRECA PRER PRES STATUS:
EF QU 5 YEARS ONLY:
PROCEDURE NUMBER ECA-0. 0 ECA-0. 1 ECA 0 '
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 REACfOR COOLANT-SUBCOOLED RECOVERY DESIRED SGTR
'WITH LOSS OF RFACfOR COOLANT.SATURATED RECOVERY DESIRED SGTR WITHOUT PRESSURIZER PRESSURF.
CONTROL EFFECI'EV DATE LAST REVIEW NEXT REVIEW ST 019 12/14/98 05/01/98 05/01/03 EF 015 06/26/98 05/01/98 05/01/03 EF 011 12/14/98 05/01/98 05/01/03 EF 015 05/01/98 05/01/98 05/01/03 EF 005 05/01/98 05/01/98 05/01/03 EF 011 06/26/98 05/01/98 05/01/03 EF 016 06/26/98 05/01/98 05/01/03 EF 020 06/26/98 05/01/98 05/01/03 EF 020 06/26/98 05/01/98 05/01/03 EF TOTAL FOR PRECA
'I II
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRES GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EQUIPMENT SUB-PROCEDURE
~
12/14/98 PAGE:
7 PARAMETERS:
DOC TYPES PRAP PRE PRECA PRER STATUS:
EF QU 5 YEARS ONLY:
PROCEDURE NUMBER ES-0.0 ES-0. 1 ES-0.2 ES 0.3 ES-1.1 ES-1.2 ES-1.3 ES-3. I ES-3.2 ES-3.3 PROCEDURE TITLE REDIAGNOSIS REACIOR TRIP RESPONSE NATURAL CIRCULATION COOLDOWN NATURAL CIRCUIATION COOLDOWN WITH STEAM VOID IN VESSEL SI TERMINATION POST LOCA COOLDOWN AND DEPRFSSUR IZATION TRANSFER TO COLD LEG RECIRCUIJLTION POST.SGTR COOLDOwN USING BACKFILL I
POST-54'%OO!I~
USIN> BI~MWN POST
~ SGTR COOIXKWN USIN'I STFW'4 O'WP REV EFFECI'ATE NEXT REVIEW ST 010 05/01/98 05/01/98 05/01/03 EF 015 12/14/98 05/01/98 05/01/03 EF 012 05/01/98 05/01/98 05/01/03 EF 008 05/01/98 05/01/98 05/01/03 EF 015 06/26/98 05/01/98 05/01/03 EF 018 06/26/98 05/01/98 05/01/03 EF 025 06/26/98 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:
PRFR GlNNA NUCLEAR POWER PLANT PROCEDURES INDEX FUNCI'IONAL RESTORATION GUIDELINE PROC 12/14/98 PAGE:
1 PARAMETERS:
DOC TYPES PRFR STATUS:
EF QU 5 YEARS ONLY:
PROCEDURE NUMBER FR-C.1 FR-C.2 PR-C.3 FR-H.1 FR-H.2 FR-H. 3 FR H.4 FR-H. 5 FR-I. 1 FR-I.2 FR-I.3 FR-P. 1 FR-P. 2 FR-S. 1 FR-S.2 FR-Z. 1 FR-Z. 2 FR-Z. 3 PROCEDURE TITLE
RESPONSE
TO INADEQUATE CORE COOLING
RESPONSE
TO DEGRADED CORE COOI ING
RESPONSE
TO SATURATED CORE COOI ING
RESPONSE
TO LOSS OF SECONDARY HEAT SINK
RESPONSE
TO STEAM GENERATOR OVERPRESSURE
RESPONSE
TO STEAM GENERATOR HIGH LEVEL
RESPONSE
TO LOSS OF NORMAL STEAM REI EASE CAPABIIITIES
RESPONSE
TO STEAM GENERATOR LOW LEVEL
RESPONSE
TO HIGH PRESSURIZER l,EVEi.
RESPONSE
TO LOW PRESSURIZER LEVEl.
RESPONSE
TO VOIDS IN REACTOR VESSEl
RESPONSE
TO IMM!NENI'RESSURIZED THERMAI, SHOCK CONDITION
RESPONSE
TO ANTICIPATED PRESSUR!ZED THERMAL Sl(OCK CONDITION
RESPONSE
TO REACTOR RESTART/ATWS
RESPONSE
TO ASS OF CORE SHUIDOWN
RESPONSE
TO HIGH CONTAINMENI'RESSURE
RESPONSE
TO CONTAINMENT FIDODING
RESPONSE
TO HIGH CONTAINMENT RADIATION LEVEL REV EFFECT DATE LAST REVIEW NEXT REVIEW ST 016 12/14/98 05/01/98 05/01/03 EF 014 05/01/98 05/01/98 05/01/03 EF 008 05/01/98 05/01/98 05/01/03 EF 020 06/26/98 05/01/98 05/01/03 EF 004 05/01/98 05/01/98 05/01/03 EF 005 05/01/98 05/01/98 05/01/03 EF 004 05/01/98 05/01/98 05/01/03 EF 004 05/01/98 05/01/98 05/01/03 EF 009 06/26/98 05/01/98 05/01/03 EF 006 11/16/98 05/01/98 05/01/0)
EF 011 06/26/98 05/01/98 05/01/03 EF 019 12/14/98 05/01/98 05/OI/OI EF 007 05/01/98 05/OI/98 05/01/OI EF 013 12/14/98 05/OI/98 05/01/03 EF 008 05/01/98 05/01/98 05/01/03 EF 005 12/14/98 05/01/98 05/01/03 EF 003 05/01/98 05/01/98 05/01/03 EF 004 05/01/98 05/01/98 05/01/03 EF TOTAL FOR PRFR 18
EOP AP-SW.1 TITLE:
SERVICE WATER LEAK REV:
13 PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER kL~
RESPONSIBLE NAGER F-EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
EOP AP-SW.1 TITLE:
SERVICE WATER LEAK REV:
13 PAGE 2 of 10 A.
PURPOSE This procedure provides the necessary instructions to respond to a service water system leak.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
SYMPTOMS The symptoms of SERVICE WATER LEAK are:
a.
Service water header pressure low alarms on comput: er, or b.
Sump pump activity increases in containment, the AUX BLDG, or INT BLDG, OR c.
Unexplained increase in the waste hold-up tank, or d.
Visual observation of a SW leak, or e.
Annunciator C-2, CONTAINMENT RECIRC CLRS WATER OUTLET HI TEMP 217', lit, or f.
Annunciator C-10, CONTAINMENT RECIRC CLRS WATER OUTLET LO FLOW 920 GPM, lit, or g.
Annunciator E-31, CONTAINMENT RECIRC FAN CONDENSATE HI-HI LEVEL alarm, exhibits an unexplained increase in frequency, or h.
Annunciator H-G, CCW SERVICE WATER LO FLOW 1000
- GPM, lit.
fOP:
AP-SW.1 TITLE:
SERVICE WATER LEAK REV:
13 PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 4
1 0
4 1
1
~
1 t 1
1 I 4
~ t 4
~
~
4 1
4 1
1 t 4
4 t 1 I CAUTION o
IF.
AT ANY TIME DURING THIS PROCEDURE.
A REACTOR TRIP OR SI OCCURS.
E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
o IF EITHER D/G RUNNING WITHOUT SW COOLING AVAILABLE, THEN STOP THE AFFECTED D/G TO PREVENT OVERHEATING.
1 Verify 480V AC Emergency Busses 17 and 18 ENERGIZED Ensure associated D/G(s) running and attempt to manually load busses 17 and/or 18 onto the D/G(s) if necessary.
2 Verify At, Least One SW Pump Running In Each Loop:
~
A or B pump in loop A
~
C or D pump in loop B
IF a SW pump has tripped.
THEN ensure other pump in the affected loop is running.
EOP:
AP-SW. 1 TITLE:
SERVICE WATER LEAK REV 13 PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Abnormally low pressure in either SW loop may indicate that the idle pump check valve is open.
This may be corrected by restarting or isolating the idle pump.
3 Check SW System Status:
a.
Check SW loop header pressures:
o Pressure in both loops APPROXIMATELY EQUAL o
PPCS SW low pressure alarm status NOT LOW o
Pressure in both loops-STABLE OR INCREASING b.
Check SW loop header pressures GREATER THAN 55 PSIG
- a. IF three SW pumps operating and either loop pressure less than 40 psig, THEN trip the reactor and go to E-O.
REACTOR TRIP OR SAFETY INJECTION.
IF only two SW pumps operating and either loop pressure less than 45 psig.
THEN start one additional SW pump (243 kw each pump).
- b. IF either SW loop pressure is less than 55 PSIG with three SW pumps running AND cause can NOT be corrected, THEN initiate a controlled shutdown while continuing with this procedure (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN).
EOP AP-SW.1 TITLE:
SERVICE WATER LEAK REV:
13 PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
o If SW is lost to any safeguards equipment, the affected component should be declared inoperable and appropriate actions taken as required by ITS, Section 3.
o CNMT sump A level of 10 feet is approximately 6 feet 6 inches below the bottom of the reactor vessel.
4 Check For SW Leakage In CNMT:
a.
Check Sump A indication o
Sump A level
- INCREASING
-OR-
o Sump A pump start frequency-INCREASING (Refer to RCS Daily Leakage Log)
- b. Evaluate Sump A conditions:
- 1) Verify Leakage within capacity of one Sump A pump (50 gpm)
- 2) Check Sump A level
- LESS THAN 10 FEET
- b. Plant shutdown should be considered, consult plant staff.
EOP:
AP-SW.1 TITLE:
SERVICE WATER LEAK REV:
13 PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
~
~
1 I 1
4
~ t 0
~ I
~
4 I
~
~
~ I 1
4
~
0 t
~
~
4 1
~
4 1
0 I 1
0 t 0
0 0
~
~
CAUTION BEFORE ISOLATING SW TO CNMT RECIRC FANS, REFER TO ITS SECTION 3.6.6 FOR OPERABILITY REQUIREMENTS.
NOTE:
o One Reactor Compartment cooling fan should be running whenever RCS temperature is greater than 135'F.
o CNMT recirc fan condensate collector level indicators may be helpful in identifying a leaking fan cooler.
5 Check CNMT fan indications:
o CNMT recirc fan collector dump frequency NORMAL (Refer to RCS Daily Leakage Log) o CNMT recirc fan SW flows APPROXIMATELY EQUAL (INTER BLDG basement by IBELIP) o Reactor compartment cooler SW outlet pressures
- APPROXIMATELY EQUAL (INTER BLDG SAMPLE HOOD AREA)
~ Cooler A - PI 2232
~ Cooler B - PI 2141 Dispatch AO to perform Attachment SW LOADS IN CNMT as necessary.
WHEN CNMT SW leak location identified, THEN go to Step 9.
EOP:
AP-SW ~ 1 TITLE:
SERVICE WATER LEAK REV:
13 PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6 Dispatch AO To Screenhouse To Perform The Following:
- a. Verify idle SW pump check valve closed o
Idle pump shaft stopped o
Idle pump discharge pressure ZERO (unisolate and check local pressure indicator)
- b. Investigate for SW leak in Screenhouse NO EXCESSIVE LEAKAGE INDICATED
- a. Notify Control Room of any indication of check valve failure.
- b. Perform the following:
- 1) Identify leak location.
IF increase in leakage from underground header indicated, THEN isolation of header should be considered (Refer to Attachment SW ISOLATION)
- 2) Notify Control Room of leak location.
NOTE:
Refer to Attachment SW ISOLATION for a list of the major non-safeguards loads supplied by each service water header.
7 Check Indications For Leak Location:
o AUX BLDG sump pump start frequency NORMAL (Refer to RCS Daily Leakage Log) o Annunciator L-9, AUX BLDG SUMP HI LEVEL - EXTINGUISHED Dispatch AO to the specific area to investigate for leakage.
o Annunciator L-17.
INTER BLDG SUMP HI LEVEL - EXTINGUISHED
~'
EOP:
AP-SW.1 TITLE:
SERVICE WATER LEAK REV 13 PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 8 Dispatch AO To Locally Investigate For SW Leakage And To Monitor Operating Equipment
~ Turbine BLDG
~
SAPW pump room
EOP:
AP-SW.1 TITLE:
SERVICE WATER LEAK REV:
13 PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE: If SW is lost to either D/G. refer to ER-D/G ~ 2, ALTERNATE COOLING FOR EMERGENCY D/Gs. if cooling is required.
9 Evaluate SW Leak Concerns a.
Check SW pump status
- AT LEAST THREE PUMPS RUNNING
THEN start third SW pump.
- b. Dispatch AO to perform the following:
- 1) Split A and B
o Close V-4669 OR V-4760 in B D/G room.
o Close V-4611 OR V-4612 in Screenhouse.
o Close V-4625 OR V-4626 in INT BLDG clean side.
o Close V-4639 OR V-4756 in INT BLDG clean side.
- c. Verify leak location
- IDENTIFIED
- d. Verify plant operating at power e.
Leak isolation at power ACCEPTABLE
- 2) IF plant at power.
THEN initiate a controlled shutdown (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN).
3)
Go to Step 10.
- c. Return to Step 3.
- d. Verify SW system conditions appropriate for plant mode (Refer to ITS Section 3.7.8) and go to Step 10.
- e. IF plant shutdown requir'ed.
THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.
0
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I AP-SW.1 TITLE:
SERVICE WATER LEAK REV:
13 PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 10 Dispatch AO(s)
To Locally Isolate SW Leak As Necessary ll Verify SW Leak Isolated
- a. Monitor SW System Operation o
SW loop header pressure RESTORED TO PRE-EVENT VALUE Archive PPCS point ID loop A P2160 OR loop B P2161) o Both SW loop header pressures STABLE
- a. IF SW leak can NOT be isolated within the affected header, THEN stop SW pumps in the affected loop and go to Step 12.
~ Bus 17 SW pumps B or D
~ Bus 18 SW pumps A or C
- b. Refer to ITS Section 3.7.8 for limiting conditions for operation.
NOTE:
o Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
o An Action Report, per IP-CAP.1.
should be submitted for a SW leak in CNMT.
12 Notify Higher Supervision
-END-
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AP-SW.1 TITLE:
SERVICE WATER LEAK REV:
13 PAGE 1 of 1
AP-SW.1 APPENDIX LIST TITLE 1)
ATTACHMENT SW ISOLATION (ATT-2.2) 2)
ATTACHMENT SW LOADS IN CNMT (ATT-2.3)
V Vx
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ATT-5. 2 TITLE:
ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP REV:
1 PAGE 1 of 1
Superintendent Date 7-4l -5 To rovide Fire Water Coolin to the TDAFW Pum erform the NOTE:
A 12 inch "crescent" wrench will be needed to make the connections.
1.
Obtain the hose from the Turbine Bldg. hose locker (top floor KEY 579).
2.
CLOSE service water root valve to the TDAFW pump thrust bearing and lube oil cooler V-4087C (located on the south side of the pump below MOV-4013).
3.
Check OPEN instrument root valve to PI-2134 SW inlet to TDAFW oil cooler V-4288 (located at the north west corner of the oil sump).
4.
Connect the hose between PI-2134 and the Fire Water Main at valve V-9226.
(V-9226. is located by the S/G blowdown CNMT Isol Valves)
NOTE:
The following action may result in an automatic start of the Diesel Driven Fire Pump.
5.
OPEN Containment hose reel supply drain
& test connection valve V-9226.
6.
VERIFY water i:s being supplied to the TDAFW pump thrust bearing by observing flow past valve V-4089A TDAFW Thrust bearing SW outlet block valve.
Verify PI-2134 indicates less than 150 psig.
7.
Notify the Control Room the attachment is complete.
0 K
~I tI.
1'1 0
A, I
0
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ATT-8.0 ATTACHMENT DC LOADS REV 3
PAGE 1 of 1
Superintendent Date A)
The A and B MFP oil pumps should be shed within 15 minutes to reduce battery-load to guarantee design battery life.
B)
The following DC loads could be shed from the A and B
DC busses, if necessary (obtain DC panel key from SS):
1A MAIN DC DISTRIBUTION PANEL (A battery room):
o Switchgear breaker test cabinet, position 1
o Rod drive MG set control panel, position 4
o Iso phase control, position 5
o Exciter equipment panel, position 6
1B MAIN DC DISTRIBUTION PANEL (B battery room):
o Rod drive MG set control panel, position 3
AUX BLDG DC DIST PANEL 1B (south end bus 16 on column near SI pump recirc valves)
~
o Aux Bldg Heat
& Vent cont.panel, position 1
SCREENHOUSE DC DISTRIBUTION PANEL B (screenhouse near MCC G) o Traveling screen control, position 1
TURB BLDG DC DISTRIBUTION PANEL (TURB BLDG basement near fire water storage tank) o Hydrogen panel for gl generator, position 3
(after degassification) o MCC F, position 5
o Water treatment panel, position 6
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