ML17309A568
| ML17309A568 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/25/1995 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| PROC-950125, NUDOCS 9502060321 | |
| Download: ML17309A568 (51) | |
Text
PRIORI EY (ACCELERATED RIDS PROCESSING REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)
P 0
ACCESSION NBR:9502060321 DOC.DATE: 95/01/25 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION WIDAY,J.A.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION I
JOHNSON,A.
Project Directorate I-3 (PDl-3)
(Post 941001)
R
SUBJECT:
Revised emergency operating procedures, including procedures index,Rev 8 to AP-CVCS.1, "CVCS Leak," Rev 3 to Att-2.3, "Attachment SW Loads in CNMT"
& Rev 4 to Att-5.0, "Attachment Cond to S/G." W/950125 ltr.
DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR 'NCL SIZE:
TITLE: OR Submittal:
- Plans, Imp ement'g Proce ures, C
R NOTES:License Exp date in accordance with 10CFQ2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 PD INTERNAL: FILE CENTER 0:
NUDCCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 RECIPIENT XD CODE/NAME JOHNSON,A NRR/DRSS/PEPB NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 D
C N
TO ALL"RIDS" RECIPIEY'TS:
PLEASE HELP US TO REDUCE iVKSTE!COYTACT'I'!IE DOCI:iIEYTCONTROL DESk, ROOM Pl-37 (E$T. 504-OS3 ) TO I'.LIXII%ATEYOI.'R %ANIL PRO%I DISTRIIIUTIONLIS'I'S I'OR DOCI.'MEN'I'S YOL'OY."I'ITI'.D!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 7
ENCL 7
wprirzs rwirzz ZÃi I urietuu ROCHESTER GASANDELECTRICCORPORATION o 89EASTAVENUE, ROCHESTER, N.Y. 14649<001 JOSEPH A. WIDAY Rant Monogor Ghna Nuclear Pkat TELEPHONE AREACODE 718 546.2700 January 25, 1995 Mr. Allen Johnson Project Directorate I-3 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
Dear Mr. Johnson:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very Truly Yours, A
oseph A. Wid JAW/jdw xc:
Mr. Lee Bettenhausen, USNRC, Region 1
Resident Inspector, Ginna Station RGS.E Nuclear Safety 5. Licensing 9502060321 950125 PDR ADOCK 05000244 F
Page 2
Enclosures:
AP Procedures Index Attachment Procedures Index E Procedures Index ECA Procedures Index ES Procedures Index F Procedures Index FR Procedures Index AP-CVCS.1 Revision 8 ATT-2.3 Revision 3 ATT-5.0 Revision 4 ATT-19.0 Delete this procedure
I
'I OCHESTER GAS AND ELECTRIC CORPORA GINNA STATION PROCEDURE CHANGE NOTICE PROCEDURE NO.k REV. NO.
INITIATIONDATE NEW PROCEDURE PERMANENT CHANGE TEMPORARY - REVIEW ONLY TEMPORARY - PERMANENT PERIODIC REVIEW INITIATOR RESPONSIBLE MANAGER PLANT STAFF DUTY ENGINEER SHIFT SUPERVISOR
" EXPIRATIONDATE PORC REVIEW BY DATE (FOR TEMPORARY PCN'S ONLYJ ONE TIME USE ONLY EQUIPMENT ID REASON:
PORC RECOMMENDATION:
APPROVAI.
PORC COMMENTS ORMODIFICATIONS'ISAPPROVAL FPc PORC REVIEW DAT EFFECTIVE DATE CATEGORY 1.1 PS'S REVIEW ORIGINAL
IA II
REPORT NO ~ 01 REPORT NAHE: DOC-P001 DOC TYPE:
PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 06/16/94 07:36 PAGE 1
PRE PARAHETERS:
DOC TYPES -
PRAP STATUS:
RECA PRER PRES PROCEDURE TITLE PROCEDURE NUHBER AP-CCM.1 AP-CCM.2 AP-CCM.3 AP-CR.1 AP-CVCS.1 AP-CVCS.2 iAP-CM.1 iAP-ELEC.1
,AP,-ELEC.2 AP-ELEC.3 AP-FM.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 AP-SW.1 AP TURB. i LEAKAGE INTO THE COHPONE COOLING LOOP LOSS OF CCM DURING POMER OP RATION LOSS OF CCM - PLANT SHUTDOWN CONTROL ROOH INACCESSIBILITY CVCS LEAK DELETED LOSS OF A CIRC 'MATER PUHP LOSS OF N?A OR 128 TRANSFORHER SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEH LOM FREQUE LOSS OF 12A AND/OR 128 TRANSFORHER (BELOW 350 F)
PARTIAL OR COHPLETE LOSS OF HAIN FEEDMATER LOSS OF INSTRUHENT AIR ABNORHAL PRESSURI2ER PRESSURE CONTINUOUS CONTROL ROO WITNDRAMAL/INSERTION RCC/RPI HALFUNCTION DROPPED ROO RECOVER RCP SEAL HALFUNCTION REACTOR COOLANT LEAK LOSS OF REACTOR C
ANT FLOW HIGH REACTOR LANT ACTIVITY SHUTDOWN OCA LOSS RNR LO S OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS SERVICE WATER LEAK TURBINE TRIP WITHOUT RX TRIP REQUIRED 5 YEARS ONLY:
REV EFFECT DATE LAST REVIE'M NEXT ST REVIEW XX 04/21/93 DE 005 04/21/93 04/
/93 10/21/95 EF 010 007 06/09+/
/'I'I/94 03/06/93 09/06/95 EF 02/11/94 08/11/96 EF 1
06/09/94 03/06/93 09/06/95 EF 009 04/21/93 04/21/93 10/21/95 EF 007 07/02/93 07/02/93 01/02/96 EF 005 11/01/91 11/01/91 '5/01/94 EF 005 06/04/93 06/04/93 12/04/95 EF 00 04/23/93 04/23/93 10/23/95 EF 000 4 23/93 04/23/93 10/23/95 EF 007 02/05 02/05/93 08/05/95 EF 007 11/01/91 007 06/09/94
+01/91 10/08%/
05/01/94 EF 04/08/96 EF 006 04/23/93 04/23/93 10
/95 EF 003 04/07/94 04/07/94 10/07/96 009 03/06/93 03/06/93 09/06/95 EF 004 03/27/92 03/27/92 09/27/94 EF 009 07/29/93 07/29/93 01/29/96 EF 007 05/07/93 05/07/93 11/07/95 EF 009 06/09/94 06/04/93 12/04/95 EF 010 04/23/93 04/23/93 10/23/95 EF 008 06/04/93 06/04/93 12/04/95 EF 012 05/01/93 05/01/93
'11/01/95 EF 007 06/09/94 05/08/92 11/08/9 EF
4c t
REPORT NO. 01 REPORT NAME: DOC-P001 DOC TYPE:
PRAP GINNA NUCLEAR PSIER PLANT PROCEDURES INDEX ABHORNAL PROCEDURE 06/16/94 07:36 PAGE 2
PARAHETERS:
DOC TYPES - PRAP PROCEDURE HUHBER AP-TURB.2 AP-TURB.3
'AP-TURB.4 AUTOHATIC TURBINE RUNBACK TURBINE VIBRATIONS LOSS OF CONDEHSER VACUUN PROCEDURE TITLE PRE PRECA PRER PRES STATUS:
5 YEARS ONLY:
REV EFFECT LAST NEXT ST DATE REVIEII REVIE'u 012 06/04/93 06/04/93 12/04/95 EF 006 03/26/93 03/26/93 09/26/95 EF 008 04/07/94 03/26/93 09/26/95 EF TOTAL FOR PRAP 28
REPORT NO.
01 REPORT NAHE: DOC-P001 DOC TYPE: PRATT PARAMETERS:
DOC TYPES - PRATT PROCEDURE NUHBER PROCEDURE TITLE STATUS:
GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EOP ATTACHHENTS 5 YEARS ONLY:
REV EFFECT DATE LAST REVIE'W NEXT ST REVIEW 07/26/94 13:00 PAGE 1
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 ATT-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-12.0 ATT-13.0 ATTACHMENT AT POWER CCW ALIGHHENT ATTACKHENT AUX BLDG SW ATTACHHENT HIN SWi ATTACHMENT S'W ISOLATION ATTACHHENT SW LOADS IN CNMT ATTACHHENT CI/CVI ATTACHHENT CHHT CLOSURE ATTACHHENT CNHT RECIRC FANS ATTACHMENT COHO TO S/G ATTACHMENI'AFW ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP ATTACHHENT COND VACUUH ATTACHHENT CR EVAC ATTACHMENT DC LOADS ATTACHMENT 0/G STOP ATTACHHENT GEN DEGAS ATTACHHEHT NONVITAL ATTACHMENT Sl/UV ATTACHHEHT LETDOWN ATTACHHENT EXCESS L/0 ATTACHMENT FAULTED S/G ATTACHHENT IA CONCERNS ATTACHHENT IA SUPPLY ATTACHHENT N2 PORVS ATTACHHENT NC 001 07/26/94 02/19/93 08/19/95 EF 003 07/26/94 04/21/93
'IO/21/95 EF 001 07/26/94 03/26/93 09/26/95 EF 003 07/26/94 07/29/93 01/29/96 EF 002 07/26/94 05/14/92 11/14/94 EF 003 07/26/94 02/11/94 08/11/96 EF 002 07/26/94 02/11/94 08/11/96 EF 003 07/26/94 06/17/93 12/17/95 EF 003 07/26/94 05/15/92 11/15/94 EF 003 07/26/94 10/11/91 04/11/94 EF 001 07/26/94 03/04/94 09/04/96 EF 001 07/26/94 03/26/93 09/26/95 EF 001 07/26/94 03/26/93 09/26/95 EF 003 07/26/94 01/26/94 07/26/96 EF 003 07/26/94 02/'l9/93 08/19/95 EF 005 07/26/94 02/11/94 08/11/96 EF 003 07/26/94 02/19/93 08/19/95 EF 003 07/26/94 02/19/93 08/19/95 EF 005 07/26/94 01/26/94 07/26/96 EF 002 07/26/94 02/03/93 08/03/95 EF 004 07/26/94 06/11/93 12/11/95 EF 001 07/26/94 07/02/93 01/02/96 EF 001 07/26/94 07/02/93 01/02/96 EF 002 07/26/94 02/03/93 08/03/95 EF 002 07/26/94 02/03/93 08/03/95 EF
0
REPORT NO. 01 REPORT NAHE: DOC-P001 DOC TYPE:
PRATT PARAHETERS:
DOC TYPES - PRATT GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EOP ATTACHHENTS STATUS:
07/26/94 13:00 PAGE 2
5 YEARS ONLY:
PROCEDURE NUMBER 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-16.0 ATT-17.0 ATT-17.1 ATT-18.0 ATT-19.0 ATT-20.0 ATT-21.0 PROCEDURE TITLE ATTACHMENT NORHAL RHR COOLING ATTACHHENT RHR COOL ATTACHHENT RHR ISOL ATTACHMENT RHR HPSH ATTACHHENT RKR SAMPLE ATTACHHENT RHR SYSTEH ATTACHHENT RHR PRESS REDUCTION ATTACHMENT'CP START ATTACHMENT RCP DIAGNOSTICS ATTACHHENT SEAL COOLING ATTACHHENT RUPTURED S/G ATTACHHENT SD. 1 ATTACHHENT SD-2 ATTACHMENT SFP -
RMST ATj'ACHHENT SI FLUSH ATTACHHENT VENT TIME ATTACHHENT RCS ISOLATION REV EFFECT DATE LAST NEXT ST REVIEW REVIEH 003 07/26/94 003 07/26/94 09/05/91 03/05/94 EF I
02/19/93 08/19/95 EF 001 '7/26/94 02/03/93 08/03/95 EF 001 07/26/94 03/27/92 09/27/94 EF 003 07/26/94 03/06/93 09/06/95 EF 001 07/26/94 03/06/93 09/06/95 EF 001 07/26/94 01/26/94 07/26/96 EF 001 07/26/94 01/26/94 07/26/96 EF 002 07/26/94 02/03/93 08/03/95 EF 000 04/07/94 04/07/94 10/07/96 EF 003 07/26/94 02/19/93 08/19/95 EF 001 07/26/94 02/19/93 08/19/95 EF 002 07/26/94 02/03/93 08/03/95 EF 004 07/26/94 09/05/91 03/05/94 EF 004 07/26/94 02/19/93 08/19/95 EF 004 07/26/94 01/26/94 07/26/96 EF 003 07/26/94 02/19/93 08/19/95 EF TOTAL FOR PRATT 42
)
t
~ \\
-0
REPORT NO. 01 REPORT HAME: DOC-P001 DOC TYPE:
PRE GIHNA NUCLEAR POMER PLANT PROCEDURES INDEX EMERGEHCY PROCEDURE 06/16/94 07:36 PAGE 3
PARAMETERS:
DOC TYPES -
PRAP PROCEDURE NUMBER PRE PRECA PRER PRES PROCEDURE TITLE STATUS:
REV EFFECT DATE 5 YEARS ONLY:
LAST NEXT ST REVIE'N REVIEW E-0 E-1 E-2 E-3 REACTOR TRIP OR SAFETY INJECT'ION LOSS OF REACTOR OR SECOHDARY COOLANT FAULTED STEAM GENERATOR ISOLATION STEAM GENERATOR TUBE RUPTURE 019 04/07/94 04/07/94 10/07/96 EF 011 03/26/93 03/26/93 09/26/95 EF 006 07/08/93 07/08/93 01/08/96 EF 015 06/09/94 04/07/94 10/07/96 EF TOTAL FOR PRE
REPORT NO.
01 REPORT NAME: DOC-P001 DOC TYPE:
PRES GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EQUIPMEHT SUB-PROCEDURE 06/16/94 07:36 PAGE 7
PARAMETERS:
DOC TYPES -
PRAP PRE PRECA PRER PRES STATUS:
5 YEARS ONLY:
PROCEDURE NUMBER ES.D.O ES-0.1 ES-0.2 ES.0.3 ES-1 ~ 1 ES-1
~ 2 ES-1.3 ES-3.1 ES-3.2 ES-3.3 PROCEDURE TITLE REDIAGHOSIS REACTOR TRIP RESPONSE NATURAL CIRCULATION COOLDDWH NATURAL CIRCULATION COOLDOWH WITH STEAM VOID IH VESSEL (WITH RVLIS)
SI TERMINATION POST LOCA COOLDOWH AND DEPRESSURIZAT ION TRANSFER TO COLD LEG RECIRCULATIOH POST-SGTR COOLDOWN USIHG BACKFILL POST-SGTR COOLDOWH USING SLOWDOWN POST-SGTR COOLDOWH USING STEAN DUMP REV EFFECT DATE LAST REVIEW NEXT ST REVIEW 009 04/07/94 04/07/94
'lO/07/96 EF 009 04/07/94 04/07/94 10/07/96 EF 007 04/07/94 04/07/94
'lo/07/96 EF 004 04/07/94 04/07/94 10/07/96 EF 010 06/09/94 04/07/94 10/07/96 EF 012 04/07/94 04/07/94 10/07/96 EF 016 04/07/94 03/26/93 09/26/95 EF 008 04/07/94 04/07/94 10/07/96 EF 009 04/07/94 04/07/94 10/07/96 EF 009 04/07/94 04/07/94 10/07/96 EF TOTAL FOR PRES 10
l
REPORT NO.
01 REPORT NAME: DOC-P001 DOC TYPE:
PRFR GINHA NUCLEAR POWER PLANT PROCEDURES INDEX FUNCTIONAL RESTORATION GUIDELINE PROC 06/'I6/94 07:39 PAGE 5
PARAMETERS:
DOC TYPES -
PRF PROCEDURE NUMBER FR-C.1 FR-C.2 FR-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 PRFR PRRSSP PREPIP PRPTT STATUS:
PROCEDURE TITLE
RESPONSE
TO INADEQUATE CORE COOLING
RESPONSE
TO DEGRADED CORE COOLING
RESPONSE
TO SATURATED CORE COOLING RESPOHSE TO LOSS OF SECONDARY HEAT SINK
RESPONSE
TO STEAH GENERATOR OVERPRESSURE
RESPONSE
TO STEAH GENERATOR HIGH LEVEL
RESPONSE
TO LOSS OF NORMAL STEAH RELEASE CAPABILITIES
RESPONSE
TO STEAM GENERATOR LOW LEVEL
RESPONSE
TO HIGH PRESSURIZER LEVEL
RESPONSE
TO LOW PRESSURIZER LEVEL
RESPONSE
TO VOIDS IN REACTOR VESSEL
RESPONSE
TO IHMINENT PRESSURIZED THERHAL SHOCK CONDITION
RESPONSE
TO ANTICIPATED PRESSURIZED THERHAL SHOCK CONDITION
RESPONSE
TO NUCLEAR POWER GENERATION/ATWS
RESPONSE
TO LOSS OF CORE SHUTDOWN
RESPONSE
TO HIGH CONTAINMENT PRESSURE
RESPONSE
TO CONTAINMENT FLOODING
RESPONSE
TO HIGH CONTAINHEHT RADIATION LEVEL 5 YEARS ONLY:
REV EFFECT DATE LAST REVIEW NEXT ST REVIEW 009 009 04/07/94 04/07/94 04/07/94 10/07/96 EF 04/07/94 10/07/96 EF 004 04/09/90 09/23/92 03/23/95 EF 012 04/23/93 04/21/93 10/21/95 EF 002 04/09/90 09/23/92 03/23/95 EF 003 06/17/93 09/23/92 03/23/95 EF 002 04/23/93 04/21/93 10/21/95 EF 002 04/09/90 09/23/92 03/23/95 EF 005 06/09/94 07/29/93 01/29/96 EF 004 05/03/91 07/28/93 01/28/96 EF
'07 06/09/94 04/04/92 10/04/94 EF 010 06/09/94 04/07/94 10/07/96 EF 003 04/04/92 04/04/92 10/04/94 EF 008 04/07/94 04/14/93 10/14/95 EF 004 04/07/94 04/14/93 10/14/95 EF 003 10/16/92 10/14/92 04/14/95 EF 002 04/09/90 09/23/92 03/23/95 EF 003 09/30/92 09/23/92 03/23/95 EF TOTAL FOR PRFR 18
REPORT HO. 01 REPORT HAHE: DOC-P001 DOC TYPE:
PRF GINNA NUCLEAR POWER PLANT PROCEDURES IHDEX CRITICAL SAFElY FUNCTION STATUS PROC 06/16/94 07:39 PAGE 4
PARAHETERS:
DOC TYPES -
PRF PROCEDURE HUNGER PRFR PRRSSP PREPIP PRPTT STATUS:
PROCEDURE TIlLE REV EFFECT DATE 5 YEARS ONLY:
LAST REVIEW NEXT ST REVIEW i F-0 ~ 1 F-0.2 F.0.3 F-0.4 F-0.5 F-0.6 SUBCRITICALITY CSFST CORE COOLING CSFST HEAT SINK CSFST INTEGRITY CSFST CONTAINHEHT CSFST INVENTORY CSFST 001 07/21/89 09/12/91 03/12/94 EF
'03 07/21/89 09/12/91 03/12/94 EF 002 07/09/92 07/09/92 01/09/95 EF 001 07/21/89 09/12/91 03/12/94 EF 002 01/12/90 09/12/91 03/12/94 EF 003 07/09/92 07/09/92 01/09/95 EF TOTAL FOR PRF
EOP:
P-CVCS.1 LITLE:
CVCS LEAK REV' PAGE 1 of 12 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE 6
I( /
PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
st h'
EOP:
P-CVCS.1 CVCS LEAK REV 7
PAGE 2 of 12 A.
PURPOSE This procedure provides the necessary instructions to mitigate the consequences of a CVCS leak.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure is entered from; a.
AP-RCS.1, REACTOR COOLANT LEAK, when conditions indicate a
CVCS leak.
2.
SYMPTOMS The symptoms of CVCS leak are; a.
Annunciator B-9 (B-10),
RCP A(B) LABYR SEAL LO DIFF PRESS 15" H20, lit, or b.
Charging line pressure low, or c.
Annunciator F-14, CHARGING PUMP SPEED, lit, or d.
Annunciator A-4, REGEN HX LETDOWN OUT HI TEMP 395'F, lit, or e.
Letdown line low pressure and/or low flow, or f.
Charging Pump Room area monitor R-4 on alarm.
ryg1 Py
%p
~ ~
ae>
~>> v 44
EOP:
P-CVCS.1
'ltTLE:
CVCS LEAK REV' PAGE 3 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED x **% x 0'
x x **0 x x x 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.
x ******
m **x ****************
NOTE:
o Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.
o A local radiation emergency should be declared for any unexplained area radiation monitor alarm.
1 Monitor PRZR Level STABLE AT PROGRAM LEVEL IF PRZR level decreasing, THEN start additional charging pumps and increase speed as necessary to stabilize PRZR level.
IF PRZR level continues to
- decrease, THEN close loop B cold leg to REGEN Hx isolation valve, AOV-427.
IF available charging pumps are running at maximum speed with letdown isolated, AND PRZR level is decreasing, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
U ikC
EOP:
P-CVCS.1 TITLE:
CVCS LEAK REV' PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
IF VCT level decreases to 5%, charging pump suction will swap to the RWST.
This may require a load reduction.
2 Check VCT Makeup System:
- a. Verify the following:
1)
RMW mode selector switch in AUTO
- a. Adjust controls as necessary.
2)
RMW control armed RED LIGHT LIT b.
Check VCT level:
o Level GREATER THAN 20%
-OR-b.
Check letdown divert valve, LCV-112A, aligned to VCT.
Manually increase VCT makeup flow as follows:
o Level STABLE OR INCREASING
- 1) Ensure BA transfer pumps and RMW pumps running.
- 2) Place RMW flow control valve, HCV-111, in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
IF VCT level can NOT be maintained, THEN refer to ER-CVCS.2, REACTOR MAKEUP CONTROL MALFUNCTION, if necessary.
~l ll
- t. '
~
J4 R
gfe
EOP:
P-CVCS.1 1'I TLE:
CVCS LEAK REV 7
PAGE 5 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 3
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 4.
WHEN VCT level greater than 20%,
THEN do Step 3b.
- b. Verify charging pumps aligned to VCT o
LCV-112C open o
LCV-112B closed
- b. Manually align valves as necessary.
4 Check If RCS Leakage In CNMT:
o Check CNMT radiation monitors NORMAL
~ R-2
~ R-7
~ R-10A
~ R-11
~ R-12 o
CNMT sump A pump run frequency NORMAL (Refer to leakage surveillance sheet)
'IF leakage is indicated in CNMT, THEN perform the'ollowing:
- b. Continue with Step 5.
WHEN CNMT cleared for entry, THEN dispatch personnel to investigate CNMT for RCS leakage.
tv
EOP:
P-CVCS.1 TITLE:
CVCS LEAK REV:
7 PAGE 6 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
- x x x
- x x* x x'*****
x
- x x **********
CAUTION RADIATION PROTECTION TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.
x
- x x **x x x x ******************
5 Check If RCS Leakage In AUX BLDG:
a.
Check AUX BLDG radiation monitors NORMAL Dispatch AO To AUX BLDG To Investigate For CVCS Leak (locked area keys required)
~ R-4
~ R-9
~ R-10B
~ R-13
~ R-14 b.
AUX BLDG sump pump'run frequency NORMAL (Refer to leakage surveillance sheet) c.
AUX BLDG sump tank leak rate NORMAL (Refer to leakage surveillance sheet)
0 C ~-
~ I 8P.'
EOP:
P-CVCS.1 CVCS LEAK REV' PAGE 7 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6
Check For Leak In Charging Line To REGEN Hx:
o Annunciator A-4, REGEN HX LETDOWN OUT HI TEMP 395'F EXTINGUISHED o
REGEN Hx le tdown out let temperature LESS THAN 350'F AND STABLE (archive PPCS point ID T0127)
Perform the following:
a.
Close or verify closed loop B
cold leg to REGEN Hx, AOV-427.
b.
Close letdown orifice valves (AOV-200A, AOV-200B, and AOV-202).
- c. Control charging pump speed as necessary to maintain RCP labyrinth seal D/P less than 80 inches.
- d. Close charging flow control
- valve, HCV-142.
e.
Close charging to loop B cold
- leg, AOV-294.
f.
Go to Step 9.
rg A
et Cl l Wf 4
R'
~ Q II
EOP:
P-CVCS.1 TITLE:
CVCS LEAK REV' PAGE 8 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
- x **%***4*% ******
4 **********
CAUTION o
IF LEAK EXISTS IN THE LETDOWN LINE, H2 GASES FROM THE VCT MAY DIFFUSE OUT THE LEAK AND CAUSE A HAZARDOUS CONDITION.
o WHILE ON EXCESS LETDOWN, VCT LEVEL MAY BE DECREASED BY MANUALLYDIVERTING EXCESS LETDOWN FLOW TO THE RCDT USING AOV-312.
- x x x x x x
- x x
>'c x x 4' **************
7 Check Normal Letdown:
a.
Normal letdown
- IN SERVICE b.
Check Letdown Indications:
o Letdown flow - APPROXIMATELY 40 GPM o
Low pressure LTDN pressure APPROXIMATELY 250 PSIG o
Pressure control valve, PCV-135, demand APPROXIMATELY 35%
OPEN a.
Perform the following:
- 1) IF excess letdown in service, THEN perform the following:
a) Close excess letdown isolation valve, AOV-310.
b) Close excess letdown flow control valve, HCV-123.
2)
Go to Step 8.
- b. Isolate Normal Letdown:
- 1) Close loop B cold leg to REGEN Hx, AOV-427
- 2) Close letdown orifice valves (AOV-200A, AOV-200B, and AOV-202)
- 3) Control charging pump speed as necessary to maintain RCP labyrinth seal D/P less than 80 inches.
- 4) Close charging flow control
- valve, HCV-142
- 5) Close charging to loop B cold
- leg, AOV-294.
- 6) Establish excess letdown (Refer to Attachment EXCESS L/D).
7)
Go to Step 12.
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P-CVCS.l T!1'LE:
CVCS LEAK REV' PAGE 9 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 8
Check For Leakage To CCW System:
o CCW radiation monitor (R-17)
NORMAL IF leakage to the CCW system is indicated, THEN go to AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.
o CCW surge tank level APPROXIMATELY 50%
AND STABLE 4
- x x x
- x x x x x x x x
- x x****************
CAUTION RCP OPERATION WITHOUT SEAL INJECTION SHOULD BE MINIMIZED.
x
- x
- 0 w*x x ** P **x ***%'************
9 Check RCP Seal Injection Indications:
o Seal injection flows GREATER THAN 6 GPM AND STABLE o
RCP labyrinth seal D/Ps GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL o
RCP seal inlet temperatures STABLE IF RCP seal injection leak is suspected, THEN perform the following:
- a. Verify charging flow control
- valve, HCV-142, open.
IF no charging path through REGEN Hx available, THEN go to Step 15.
IF NOT, THEN seal injection should be maintained.
- c. Attempt to locate and isolate leak.
d.
Go to Step 12.
v lf 4'
hQ c
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P-CVCS.1 T1TLE:
CVCS LEAK REV:
7 PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 10 Check RCP Seal Leakoff Flows:
o RCP seal leakoff flows GREATER THAN 0.25 GPM o
RCP seal leakoff flows STABLE Dispatch AO with a key to the RWST gate to check seal return line for leakage.
IF a seal return line leak is
, indicated downstream of RCP,seal return isolation valve, MOV-313, THEN perform the following:
a.
Close RCP seal return isolation
- valve, MOV-313.
- b. Monitor RCP indications.
- c. Evaluate leak location.
IF
- possible, THEN isolate the seal return line from the VCT.
d.
Go to Step 12.
IF no seal return line leakage indicated in the AUX BLDG, THEN investigate for leakage in CNMT.
11 Evaluate Local Leak Investigation CVCS SYSTEM INTACT IN AUX BLDG Determine if leak can be isolated (Refer to CVCS piping diagrams as necessary).
12 Evaluate Plant Status:
a.
Leak location identified a.
IF CVCS leak NOT indicated, THEN go to AP-RCS.1, REACTOR COOLANT LEAK.
b.
Check RCS conditions:
o Leakage within limits (Refer to leakage surveillance sheet and Tech Spec section 3.1.5) o At least one charging flowpath
- AVAILABLE FOR INVENTORY CONTROL
- b. Perform the following:
- 1) Initiate plant shutdown (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN).
2)
Go to Step 15.
ti e
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P-CVCS.1 TITLE:
CVCS LEAK REV' PAGE 11 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 13 Check Normal Or Excess Letdown IN SERVICE IF normal letdown desired, THEN perform the following:
- a. Verify charging line flow to REGEN Hx -
GREATER THAN 20 GPM
- b. Place letdown controllers in MANUAL at 40% open.
~ TCV-130
~ PCV-135
- c. Verify letdown isolation valve, AOV-371, OPEN d.
Open B loop cold to REGEN Hx, AOV-427 e.
Open letdown orifice valves as necessary
- f. Place TCV-130 in auto at 105'F
- g. Place PCV-135 in AUTO at 250 psig
- h. Adjust charging pump and HCV-142 as necessary to control PRZR level and RCP labyrinth seal D/P IF normal letdown NOT available, THEN establish excess letdown if desired (Refer to Attachment EXCESS L/D).
(-I r
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P-CVCS.1 CVCS LEAK REV 7
PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 14 Establish Stable Plant Conditions:
a.
PRZR level
- TRENDING TO PROGRAtt
- a. Control charging flow as necessary to restore PRZR level to program.
b.
PRZR pressure
- b. Verify proper operation of PRZR heaters and spray or take manual control of PRZR pressure controller 431K.
IF pressure can NOT be controlled, THEN refer to AP-PRZR. 1, ABNORMAL PRESSURIZER PRESSURE.
NOTE:
Refer to 0-9.3, NRC IMHEDIATE NOTIFICATION, for reporting requirements.
15 Notify Higher Supervision
-END-
4
P-CVCS.1 r I HALF.:
CVCS LEAK REVS 7
PAGE 1 of 1
AP-CVCS.1 APPENDIX LIST TITLES PAGES 1)
Attachment EXCESS LETDOWN
k rp 4 ~
CQP ATT-2.3 tlTLE:
ATTACHMENT SW LOADS IN CNMT REV' PAGE 1 of 1
Superintendent Date 7
("
The following are service water loads in CNMT and associated isolation valves:
NOTE:
o A locked valve key will be required to perform cooler isolation.
Intermediate Bldg.
(clean side):
o CNMT recirc fan A cooler SW inlet V-4627 SW outlet V-4629 (SW LOOP A) o Notify Control Room before isolating SW to any fans.
o Isolate only one CNMT recirc fan cooler at a time.
o CNMT recirc fan B cooler SW inlet V-4628 SW outlet V-4630 (SW LOOP A) o CNMT recirc fan C cooler
~
SW inlet V-4641 SW outlet V-4643 o
CNMT recirc fan D cooler SW inlet V-4642 SW outlet V-4644 (SW LOOP B)
Intermediate Bldg. (hot side sample hood):
NOTE:
Isolate only one Rx Compartment cooler at a time.
o Rx compartment A cooler SW inlet V-4757 SW outlet V-4758 o
Rx compartment B cooler SW inlet V-4635 SW outlet V-4636
I 0
wj II
.J
ATT-5.0 TITLE:
ATTACHMENT COND TO S/G REV 3
PAGE 1 of 1
Superintendent FLOW THROUGH MFW PUMP B
Date 1.
2.
At main control board place MFW Pump B discahrge valve switch to open (MOV-3976).
3.
When MFW pump B discharge valve indicates open, direct AO to open breaker for S/G FWP DISCH VLV 1B, MCC B position 8G.
4.
Ensure condensate trim valve.controller demand at zero.
5.
Place MFW flow control valve and bypass valve controllers in MANUAL.
6.
Ensure at least two condensate pumps running.
FLOW THROUGH MFW PUMP A 1.
2.
At main control board, place MFW Pump A discharge valve switch to OPEN (MOV-3977).
3.
When MFW pump A discharge valve indicates open, direct AO to open breaker S/G FWP DISCH VLV 1A, MCC A position 9J.
4.
Ensure condensate trim valve controller demand at zero.
5.
Place MFW flow control valve and bypass valve controllers in MANUAL.
6.
Ensure at least two condensate pumps running.
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