ML20046B527
| ML20046B527 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/29/1993 |
| From: | Aguado J GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| References | |
| PROC-930729, NUDOCS 9308050046 | |
| Download: ML20046B527 (200) | |
Text
7 gf Document Transmittal P
N o. O 't 2 7 ,1g 93 To:
A.W. Droraerick-USNRC Sr. Project Manager Copy Serial #72 Mail Station P-137 20555 Washington D.C.
FILE CURRENT DESTROY OUTDATED 2000 EMG INDEX ENTIRE 2/10/93
?non FMC TNT 1FY TUTmr 7 /27 /93 2000-EMG-3200.01A Entire Rev. ] 2000-EMG-3200.01 A Entire Rev. 0 2000-EMG-3200.01B Entire Rev. 1 2000-EMG-3200.01B Entire Rev. 0 l
2000-dig-3200.02 Entire Rev. 9 2000-EMG-3200.02 Entire Rev. 8 2000-EMG-3200.04A Entire Rev. 1 2000-EMG-3200.04A Entire Rev. 0 2000-EMG-3200.'04 B Entire Rev. 1 2000-EMG-3200.04B Entire Rev. 0 2000-EMG-3200.05 Entire Rev. 4 2000-EMG-3200.05 Entire Rev. 3 2000-EMG-3200.08A Entire Rev. 1 2000-EMG-3200.08A Entire Rev. 0 ,
2000-EMG-3200.08B Entire Rev. 1 2000-EMC-3200.08B Entire Rev. O r
2000-EMG-3200.10 Entire Rev. 5 2000-EMG-3200.10 Entire Rev. 4 2000-EMG-3200.11 Entire Rev. 5 2000-EMG-3200.11 Entire Rev. 4 2000-EMG-3200.12 Entire Rev. 2 2000-EMG-3200.12 Entire Rev. 1 ,
R: Quired Action:
Add revision to your controlled copies. DESTROY OUTDATED Name J. Aeuado i
O Return Outdated Material with this Transmittal Sign and return this transmittal document Location 0 C D C C-Acknowledged as indicated above:
~
Nzme 9308050046 930729 hDR ADOCK 05000219 " " ___Date hi I PDR L Acoo122411.a3 l
07/27/93 Page 1 of 2
(";
\j t; d
2000-EMG-3200 SERIES INDF2 THIS INDEX LISTS CURRENT PROCEDURES, THEIR REVISION AND EFFECTIVE DATE.
PROCEDURE HISTORY MAY BE ACCESSED IN CARIRS DATA BASE EA20.
Page No. Date 1 07/27/93 2 07/27/93 l
i OYSTER CREEK CONTROLLED DISTRIP;UTION ,
DOCUMENT SERIAL NUMBER b
INFO. MGMT. - DCC O
4 07/27/93 Page 2 of 2 2000-EMG-3200 SERIES PROCEDURES LaSt Rev. No. Date 2000-EMG-3200,01A RPV CONTROL - NO ATWS 1 07/29/93 p 2000-EMG-3200.01B RPV CONTROL - WITH ATWS 1 07/29/93 2000-EMG-3200.02 PRIMARY CONTAINMENT CONTROL 9 07/29/93 2000-EMG-3200.04A EMERGENCY DEPRESSURIZATION-NO ATWS 1 07/29/93 2000-EMG-3200.04B EMERGENCY DEPRESSURIZATION-WITH ATWS 1 07/29/93 2000-EMG-3200.05 STEAM COOLING 4 07/29/93 2000-EMG-3200.08A RPV FLOODING - NO ATWS 1 07/29/93 2000-EMG-3200.08B RPV FLOODING - WITH ATWS 1 07/29/93 2000-EMG-3200.10 CONTAINMENT FLOODING S 07/29/93 2000-EMG-3200.ll SECONDARY CONTAINMENT CONTROL 5 07/29/93 2000-EMG-3200.12 RADIOACTIVITY RELEASE CONTROL 2 07/29/93 A
V O
M le U1Nuslear O = ER CR = = C = R cE= = = G STATION PROCEDUAE Ner EMG-3200.01A 7
O Title RPV CONTROL - NO ATWS Revision No.
1 Applicability / Scope Responsibi. Office t PLANT ENGINEERING k EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 2200 This document is within QA plan scope X Yes No ,
Effective Date Safety Reviews Required X Yes No (07/19/93) 07/29/93 i I
Prior Revision 0 incorporated the This Revision 1 incorporates the following Temporary Changes: following Temporary Changes: -
N/A N/A ,
LIST OF srrr,unys PAGES PAGE REVISION PAGE REVISION PAGE REVISION 1.0 1 E6-2 1 E15-1 1 2.0 0 E6-3 1 E15-2 1 3.0 1 E7-1 1 E16-1 1 4.0 1 E7-2 1 E16-2 1 El-1 1 E7-3 1
, E2-1 1 E8-1 1 i E2-2 1 EB-2 1 E3-1 1 E9-1 1 i E4-1 1 E10-1 1 ES-1 1 E10-2 1 E5-2 1 E11-1 1 ES-3 1 E12-1 1 ,.
55-4 2 "22-2 2 E5-5 1 E13-1 1 OYSTER CREEK E5-6 1 E24-1 CONTROLLED DISTRIBUTION
- fJDCUIviENT SERIAL NUMBER N INFO. MGMT. - DCC ]
1 Signature Concurring Organization Element Date
^
Originator - 'C ,
EOP COORDINATOR l- ,
Concurred By 7/Md,.,,g EOP COMMITTEE 'y)f/fg ke(yj,4 PLANT ENGINEERING DIRECTOR IT[93
-hMMg MGR, PLANT OPERATIONS fy 1
Approved By MM% VICE PRESIDENT & DIRECTOR, OC 7. [%
(320001A) l 1.0 !
i
t LI3E Etall" OYSTER CREEK NUCLEAR GENERATING Number ;
. STATION PROCEDURE EMG-3200.01A Title Revision No.
I rs 1.0 PURPOSq The purpose of the RPV Control - No ATWS Procedure is to:
- ~ ~ - - - - - ~ - - - -- - - - ~ -
~ Maintain adequate core cooling Cooldown the RPV to cold shutdown conditions ;
2.0 REFERENCES
i 2.1 Procedures
- 107.4, EOP Program Control
- 308, Emergency Core Cooling System Operation ,
2.2 Drawings
- BR 2002, Main, Extraction & Aux Steam System ,
P
- BR 3029, DC Control Elem Diagram
- BR E1102, Emer Condenser Isol Outlet valve V-14-35
- BR E1183 Elem Diagram for Cleanup Isolation Valve V-16-2
- BR E1184, Elem Diagram for Cleanup Isolation Valve V-16-14 l i
- GE 112C2248, Sht 2, Connection Diagram 11F
- GE 148F262, P&ID - Emergency Condenser System
- GE 148F444, P&ID - Cleanup Demineralizer System
- GE 157B6350, Sht 153,. Cleanup System AC Isol valve Elem Diagram l
- GE 237E566, Sht 4 Rx Protection System Elem Diagram 2.3 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.4 2000-STD-1218.04, EOP Writer's Guide O
(320001A) 2.0 l
OYSTER CREEK NUCLEAR GENERATING Number I STATION PROCEDURE BfG.3200.01A Title Revision No.
O arv couraot-no Arws 1 1
3.0 PRECAUTIONS AND LIMITATIONS L 3.1 This procedure gives guidance to the operator for bypassing isolation signals scrams which is a departure from the Oyster Creek Technical Specifications. It is permissible to take actions which depart from the plant's Technical Specifications during emergency conditions as authorized by 10 CFR 50.54(x).
4.0 ATTACHMENTS 4.1 Attachment A - RPV Control - No ATWS EOP Flowchart DWG: GU 3E-200-08-008 Sh 1 1
4.2 Attachment B - Support Procedure 1, Confirmation of Automatic Initiations and Isolations 4.3 Attachment C - Support Procedure 2, Feed and Condensate System Operation 4.4 Attachment D - Support Procedure 3, CRD System Operation >
4.5 Attachment E - Support Procedure 4, Operation of the Core Spray System 4.6 Attachment F - Support Procedure 5, Fire Water for RPV Water Level Control ,
4.7 Attachment G - Support Procedure 6, Condensate Transfer for RPV Water Level control 4.8 Attachment H - Support Procedure 7, Liquid Poison for RPV Water Level Control 4.9 Attachment I - Support Procedure 8, Lineup for Condensate System Injection 4.10 Attachment J - Support Procedure 9, Lineup for Core Spray System Injection 4.11 Attachment K - Support Procedure 10, Stopping Injection from the Core Spray System t
O (320001A) 3.0
'f NusIear OYSTER CREEK NUCLEAR GENERATING S m Io. ,,0C m a, Number me,_noo.ou 3
.y '
Title Revision No.
O arv cournot - no irws 1 I
4.12 Attachment L - Support Procedure 11, Alternate Pressure Control - ),
Isolation Condensers 4.13 Attachment M - Support Procedure 12, Alternate Pressure Control -
EMRVs ,
4.14 Attachment N - Support Procedure 13, Alternate Pressure Control -
Clean-up in Recirculation Mode 4.15 Attachment 0 - Support Procedure 14, Alternate Pressure Control -
Clean-up in Letdown Mode 1 4.16 Attachment P - Support Procedure.15, Alternate Pressure Control -
Isolation Condenser Tube Side Vents O ,
e O
(320001A) 4.0
g- OYSTER CREEK NUCLEAR CENERATING Number g STATION PROCEDURE B{G 3200,0g Title Revision No.
O RPV CONTROL - NO ATWS 1 k-ATTACHMENT A Attachment A to EMG-3200.01A, RPV Control - NO ATWS, is the RPV Control - NO ATWS EOP Flowchart, DWG: GU 3E-200-08-008, Sht 1, Rev. 1.
9 O
f I
e O
(320001A/5) El-1
~
Procedure EMG-3200.01A Rgv. 1
~
Attachment B Page 1 of I SUPPORT PROCEDURE 1 CONFIRMATION OF AUTOMATIC INITIATIONS AND ISOLATIONS b
1.0 PREREOUISITES Confirmation of automatic initiations and isolations has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE Confirm the following isolations/ starts not required to be bypassed by the Emergency Operating Procedures:
SYSTEM OPERATING DETAILS Reactor H Any of the following conditions exist:
Isolation
- RPV water level at or below 86 in.
- Steam tunnel temperature at or above 180*F
- Any steam line flow at or above 4.0x106 lbm/hr n
- Reactor mode switch in RUN and RPV pressure at or below 850 psig b e M.ain steam line radiation at or above 800 units THEN Confirm closed ie following:
MSIVs IC VENTS RX SAMPLE NSO3A V-14-1,-19 V-24-30 (11F)
NSO4A V-14-5,-20 V-24-29 (11F)
NS03B DW AIR SUPPLY NSO4B V-6-395 (11F)
IC-A E IC-A is ruptured Isolation THEN Confirm closed the following:
IC ISOLATION VALVES IC VENTS V-14-30 V-14-34 V-14-5 V-14-31 V-14-36 V-14-20 IC-B E IC-B is ruptured Isolation THEN Confirm closed the following:
IC ISOLATION VALVES IC VENTS V-14-32 V-14-35 V-14-1 V-14-33 V-14-37 V-14-19 (320001A/6) E2-1
Procedure EMG-3200.01A Rev. 1 Attcchment B Page 2 of 1 SYSTEM OPERATING DETAII.S Cleanup II Any of the following conditions exist:
System
- RPV water level at or below 86 in.
Isolation
- Drywell pressure at or above 3.0 psig THEN Confirm closed the following Cleanup Isolation valves: h V-16-1 V-16-14 V-16-2 V-16-61 Shutdown IE Any of the following conditions exist:
Cooling
- RPV water level at or below 86 in.
System
- Drywell pressure at or above 3.0 psig Isolation THEN Confirm c1csed the following:
SDC SYSTEM ISOLATION VALVES V-17-54 V-17-19 Core Spray IE Any of the following conditions exist:
System
- RPV water level at or below 86 in.
Start
- Drywell pressure at or above 3.0 psig THEN Confirm start of one Main Pump and one Booster Pump in each Core Spray System.
Primary IE Any of the following conditions exist:
Containment
- RPV water level at or below 86 in.
Isolation
- Drywell pressure at or above 3.0 psig THEN Confirm closed the following valves that are not required to be open by the Emergency Operating Procedures:
System valve No.
DW Vent / Purge V-27-1 (Panel 11F)
V-27-2 V-27-3
- V-27-4 "
Torus Vent V-28-17 (Panel 11F)
V-28-18 Torus 2* Vent Bypass V-28-47 (Panel IIF)
DWEDT V-22-1 (Panel 11F)
V-22-2 DW Floor Sump V-22-28 (Panel 11F)
V-22-29 Torus /Rx Bldg. V-26-16 (Panel 11F) vacuum Breakers V-26-18 TIP Valves Common Ind. (Panel 11F)
DW 2* Vent Bypass V-23-21 (Panel 12XR)
V-23-22 N2 Purge V-23-13 (Panel 12XR)
V-23-14 V-23-15
- V-23-16
! N2 Makeup V-23-17 (Panel 12XR)
V-23-18 V-23-19 V-23-20 (320001A/7) E2-2
- Procrdurs EMG-3200.01A Rrv. 1 Attachment C Page 1 of 1 SUPPORT PROCEDURE 2
\ FEED AND CONDENSATE SYSTEM OPEAATION l 1.0 PREREOUISITES Directed to maintain RPV level with the Feed and Condensate Systems by the p Emergency Operating Procedures.
2.0 PREPARATIONS None j 3.0 PROCEDURE 3.1 IE RPV water level is increasing, THEN select one Feedwater Pump to be the operating pump and trip the Feedwater Pumps EQI selected.
3.2 Control RPV water level using the following: i
- Reactor Level Setdown Program (if initiated) (Panel 4F).
i
- Feedwater Regulating valves (Panel SF/6F).
- Feedwater Low Flow valves (Panel SF/6F).
- Heater Bank Outlet Isolation valves (Panel SF/6F).
- Feedwater and Condensate pumps (Panel SF/6F).
3.3 IE RPV water level cannot be maintained below 160 in. TAF, THEN close the Heater Bank Outlet Isolation valves for the operating pumps (Panel SF/6F).
3.4 II RPV water level reaches 170 in. TAF, THEN trip any operating Feedwater pump (Panel SF/6F).
3.5 IE RPV water level reaches 170 in. TAF AND RPV pressure is below 350 psig (the shutoff head of the Condensate pumps),
THEN close all Beater Bank Outlet Isolation valves (Panel 5F/6F).
3.5.1 II RPV water level continues to increase, THEN trip the operating Condensate Pumps (Panel 5F/6F).
O (320001A/8) E3-1
Proceduro EMG-3200.01A R3v. 1 Attechmint D Page 1 of 1 SUPPORT PROCEDURE 3 CRD SYSTEM OPERATION 1.0 PREREOUISITES h Directed to maintain RPV level with the CRD System by the Emergercy Operating Procedures.
2.O PREPARATION None 3.0 PROCEDURE
- CAUTION *
- Operating two pumps at greater than 150 gpm or one pump at greater *
- than 90 gpm may result in a pump trip.
- 1. Start all available CRD Pumps (Panel 4F).
AND throttle open CRD Bypass Valve V-15-30 so as not to exceed 150 gpm flow for two pump operation 91 90 gpm for one pump operation.
3.2 H RPV water level cannot be maintained below 160 in.TAF, THEN 1. Throttle closed CRD Bypass Valve, V-15-30 (RB 23 SE), if open.
- 2. Throttle closed CRD Flow Control Valve (Panel 4F).
3.3 H RPV water level reaches 170 in.,
THEN trip the operating CRD pumps. (Panel 4F).
O (320001A/9) E4-1
. Procsduro EMG-3200.01A Rav. 1 Attachment E Pags 1 of i SUPPORT PROCEDURE 4
( OPERATION OF THE CORE SPRAY SYSTEM 1.0 PREREOUISITES Use of the Core Spray System for RPV level control has been directed by the Emergency Operating Procedures, p 2.0 PREPARATION NOTE Manual control of the core spray system after auto initiation can only be accomplished after all initiating signals are overridden and the logic is reset.
2.1 IE Core Spray System actuating signals are present THEN override the Core Spray initiation logic by depressing the OVERRIDE switches for all the sensors that are lit and depressing all ACTUATED switches, whether lit or unlit (Panel IF/2F).
2.2 This procedure requires the use of an MB-1 and PA-235 key.
3.0 EEOCEDURE 3.1 **************************************************************************
- CAUTION
- f Am
- Diesel Generator overload will result if a Core Spray Main and
- Booster Pump are started with a Diesel Generator load of greater *
- than 2000 KW.
j II Bus IC or ID are being supplied by an Emergency Diesel Generator, ,
THEN verify that adequate load margin is available so as NOT to exceed EDG load limit when starting Core Spray Pumps.
3.2 Confirm one Core Spray Main Pump is running in each system. (Panel IF/2F) !
l 3.3 WHEN Core Spray Main Pump discharge pressure increases above 105 psig )
(Sys 1) or 149 psig (Sys 2) (Panel IP/2F),
THEN confirm a Core Spray Booster Pump in that system operating (Panel 1F/2F).
3.4 WHEN RPV pressure is less than 310 psig THEN Restore and maintain RPV water level as directed by the GSS/GOS by cycling the Core Spray Parallel Isolation Valves as required.
(Panel IF/2F).
(320001A/10) ES-1
\
I
-i -
Procsdure EMG-3200.01A
. Rev. 1 Atttchment 2 Page 1 of 1
() 3.5 Observe the NPSH and Vortex limits of Figures A and B.
3.5.1 Maintain Core Spray Pump flow less than Figure B.
3.5.2 Maintain total Core Spray and containment Spray flow less than ty Figure A.
3.6 NOTE Booster pump operation is HQI required for injection to occur. .
- CAUTION *
- Operation of two booster pumps with only one main pump in a *
- system may result in pump damage.
- IE all Core Spray pumps that are running are not required to assure adequate core cooling, THEN inform the GOS/GSS and secure the Core Spray pumps that are not required to assure adequate core cooling.
3.7 If the Core Spray pumps in a system are not operating, THEN verify Core Spray KEEP FILL TROUBLE (B-3-d) alarm is not illuminated and Pump Minimum Flow Valves are closed (Panel 1F/2F).
3.8 NOTE Core Spray System pumps will operate on minimum recirculation flow when the Parallel Isolation Valves are closed.
If the Core Spray pumps are operated for greater than 30 minutes on minimum recirculation flow, AND conditions permit, THEN dispatch an operator to check the operating Core Spray pumps for excessive vibration.
(320001A/11) E5-2
Proctdure EMG-3200.01A Rev. 1
~
Attachment E
~
Page 1 of 5 3.9 FOTE The Test Flow Return Valves throttle in the open direction only. ,
IE Core Spray Parallel Isolation Valves are required to be cycled to maintain RPV level for a time period in excess of two (2) hours, THEN increase Core Spray System flow by completing the following:
- 1. . Unlock and place the breaker for the Test Flow Return Valve in the ON position. [
- System 1 V-20-27 (MCC 1A21B/RB 23 E)
- System 2 V-20-26 (MCC IB21A/RB 23 NE) 4
- 2. Throttle open the Test Flow Return Valve and increase system flow to greater than 2000 gpm.
- System 1 V-20-27 (Keylock RB 51 NW)
O o
- 3. Throttle the Test Flow Return valve as required to maintain total Core Spray Flow (per system) 2000 to 5000 gpm and RPV water level as directed by the GSS/GOS.
l O ,
(320001A/12) ES-3
)
i
O4 Procedure EMG-3200.01A RQv. 1 Attachment E Page i of i A FIGURE A
- V CORE SPRAY VORTEX LBIIT h
100-- ,
~
./ -
90--
80 (;<
~
n.
r TORUS 70- /, ,'
WATER -
~ '
LEVEL (in) > -
O- 60 r-j-
~
J 5
[
40_
b 7
> [ >
. i .
30 . #
4 .
- i 4 , 4
- i .
i a 0 2 4 6 8 10 12 14 16 18 20 TOTAL CORE SPRAY AND CONTAINMENT SPRAY FLOW (x1000 gpm)
O (320001A/13) ES-4
4
~
Frocsdure EMG-3200.01A Rev. 1 l Attachment E Page i of i Q FIGURE B CORE SPRAY NPSH LBiff I L
m
's ? t-e , 6: I.'
M M iE915 i ifi.i
- M swanssamma iiiii4 E mL l'
G ,
180 TORUS STATIC
,% . F TEMP ' .1 _ _ _ _ HEAD
(* F) 170 ADJUSTMENT D FROM i 160 FIG. C l 150 B
140 WHEN PUMP NZO1C IS RU NING A 120 . .
2500 3000 3500 4000 4500 5000 PUMP FLOW (gpm) j :
- m. m w = =p - n- .- .y= .
G
' ""' ~
'%AW: D
[5 T F C l C
160 WHEN PUMP NZO1C B 150 !
iS NOT RUNNING A 2500 3dOO 3 adOO 4500 5dOO PUMP FLOW (gom) j l
l O 1 l
(320001A/14) ES-5 l l
Procedure EMG-3200.01A R;;v. 1 Attachment E .
Page i of 1 [
i FIGURE C .
CORE SPRAY TORUS OVERPRESSURE ADJUSTAENT -
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129 158 187 100 110 120 130 140 150 160 170 180 190 200 TORUS WATER LEVEL (In) con e u-sa-e- n o N
(320001A/15) ES-6 -
Proceduro EMG-3200.01A Rsv. 1 Attschment F ,
. Page 1 of }
SUPPORT PROCEDURE 5 f
FIRE WATER FOR RPV WATER LEVEL CONTROL 1.0 EEEREOUISITES RPV water level control using Fire Water via the Core Spray System has been "
directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 II Core Spray actuating signals are present, IHEN override Core Spray initiation logic by depressing the OVERRIDE switches for all the sensors that are lit and depressing all ;
ACTUATED switches, wheter lit or unlit.
3.0 PROCEDURE 3.1 NOTE Overriding Core Spray initiation logic may be required.
O IE Core Spray System 1 pumps are not available, THEN inject fire water as follows:
3.1.1 Confirm stopped the Core Spray Main and Booster Pumps on i Core Spray System 1 (Panel 1F/2F).
3.1.2 Place the Core Spray System 1 Main Pump control switches in the PULL TO LOCK position (Panel 1F/2F).
3.1.3 Close Tell-Tale Drain valve, V-20-91 (RB 23 North or North Side RB outside).
3.1.4 Confirm running all Diesel Fire Pumps by placing their contol switches in MAN position (Panel 13R).
l 3.1.5 Open Fire Water Supply valve, V-20-83 (RB 23 North or j i
North Side RB outside).
3.1.6 Confirm open Core Spray System 1 Discharge Valve, O V-20-12 (Panel 1F/2F). ,
I (320001A/16) E6-1 '
l
Proc duro EMG-3200.01A Rpv. 1
~
Attachment F Page 1 of 1 J
3.1.7 Confirm closed Core Spray System 1 Test Flow Return l l
Valve, V-20-27 (Panel 1F/2F).
3.1.8 Close Core Spray System 1 Pump Suction valves, V-20-32 k and V-20-3 (Panel 1F/2F).
3.1.9 EHIH directed by the GSS/GOS THEN open either Core Spray System 1 Parallel Isolation Valve, V-20-15 or V-20-40 (Panel IF/2F).
3.2 NOTE Overriding Core Spray initiation logic may be required.
II Core Spray System 2 pumps are not available, TIIEN inject fire water as follows:
3.2.1 Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 2 (Panel IF/2F).
3.2.2 Place the Core Spray System 2 Main Pump control switches in the PULL TO LOCK position (Panel IF/2F). ,
3.2.3 Close Tell-Tale Drain Valve, V-20-90 (RB 23 South, or South Side RB outside).
3.2.4 Confirm running all Diesel Fire Pumps by placing their control switches in MAN position (Panel 13R).
r O
(320001A/17) E6-2 t
i
^
Proc duro EMG-3200.OlA-Rgv. 1 Attachment F
=
Page 1 of }
3.2.5 Open Fire Water Supply Valve, V-20-82 (RB 23 South or South Side RB outside).
3.2.6 Confirm open Core Spray System 2 Discharge Valve, V-20-18 F (Panel IF/2F). _
3.2.7 Confirm closed Core Spray System 2 Test Flow Return valve, V-20-26, (Panel IF/2F).
3.2.8 Close Core Spray System 2 Pump Suction Valves, V-20-33 and V-20-4 (Panel 1F/2F).
3.2.9 WHEN directed by the GSS/GOS THEN open either Core Spray System 2 Parallel Isolation valve, V-20-21 or V-20-41 (Panel 1F/4F).
(320001A/18) E6-3
5~
Procedure EMG-3200.01A Rav. 1 Attachment G
Page 1 of 1 SUPPORT PROCEDURE 6 CONDENSATE TRANSFER FOR RPV WATER LEVEL CONTROL U
1.0 PREREOUISITES The use of the Condensate Transfer System via the Core Spray System for RPV water level control has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 IE Core Spray actuating signals are present, THEN override Core Spray initiation logic by depressing the OVERRIDE switches for all the sensors that are lit and depressing all ACTUATED switches, whether lit or unlit.
2.2 This procedure requires the use of an MB-1 key.
3.0 PROCEDURE NOTE Overriding Core Spray initiation logic may be required.
IE Core Spray System 1 pumps are not available, NLQ Fire Water to Core Spray System I is not in service, THEN inject Condensate Transfer via the Core Spray System as follows:
3.1.1 Place the Core Spray System 1 Main Pump control switches in PULL-TO-LOCK position. l l
3.1.2 Unlock and open Regulator Bypass Valves, V-11-110 and V-11-111 (RB $1 NW).
3.1.3 Confirm open Core Spray System 1 Discharge Valve, V-20-12 (Panel IF/2F).
O (320001A/19) E7-1
l Procsduro EMG-3200.01A ,
Rgv. I e Attachment G Page Z of }
O 3.1.4 Confirm closed Core Spray System 1 Test Flow Return Valve, V-20-27 (Panel IF/2F).
3.1.5 Start all available Condensate Transfer Pumps (Panel SF/6F). Fj 3.1.6 Close Core Spray System 1 Pump Suction valves V-20-32 and V-20-3 (Panel 1F/2F).
3.1.7 WHEN directed by the GSS/GOS, THEN open either Core Spray System 1 Parallel Isolation valve, V-20-15 or V-20-40 (Panel 1F/2F).
3.2 NOTE Overriding Core Spray initiation logic may be required, i IF Core Spray System 2 pumps are not available, O - ,
Fire Water to Core Spray System 2 is not in service, THEN inject Condensate Transfer via the Core Spray System as follows:
3.2.1 Place Core Spray System 2 Main Pump control switches in the PULL-TO-LOCK position.
3.2.2 Unlock and open Regulator Bypass Valves, V-11-109 and V-11-108 (RB 75 S).
3.2.3 Confirm open Core Spray System 2 Discharge Valve, V-20-18 (Panel IF/2F).
O (320001A/20) E7-2 i
I
Procedure EMG-3200.01A .
Rpv. 1 l
~
Attachment G l Page 2 of 1 i
O i
3.2.4 Confirm closed Core Spray System 2 Test Flow Return Valve, V-20-26 (Panel IF/2F).
I 3.2.5 Start all available Condensate Transfer Pumps (Panel SF/6F).
3.2.6 Close Core Spray System 2 Pump Suction Valves V-20-33 and V-20-4 (Panel 1F/2F).
3.2.7 WHEN directed by the GSS/GOS, THEN open either Core Spray 2 Parallel Isolation Valve, V-20-21 or V-20-41 (Panel IF/2F).
O O .
(320001A/21) E7-3
Procrduro EMG-3200.01A R;v. 1 Attachment H Page 1 of 2 O SUPPORT PROCEDURE 7 LIOUID POISON FOR RPV WATER LEVEL COh"rROL 1.0 PREREOUISITES ti RPV water level control using the Standby Liquid Control System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 This procedure requires the use of an HB-1 key.
3.0 PROCEDURE 3.1 IE Rx building 95 Ft. elevation is accessible and time permits, THEN perform the following to lineup Demineralized Water for injection via the SLC System:
3.1.1 Unlock and close Standby Liquid Control Tank Outlet valve V-19-4, (RB 95 West).
3.1.2 Unlock and open Test Tank Outlet Valve V-19-11, (RB 95 West). _
3.1.3 Fill test tank by performing the following:
- 1. Open Demin Water Isolation valve V-12-14 (RB 95 West).
- 2. Open Test Tank Demin Water Supply Valve V-19-12 (RB 95 West).
3.1.4 Inform the GSS/GOS that Demineralized Water has been lined up to the SLC System.
3.2 ********************************************************
- CAUTION
- Due to pressure fluctuations, Fuel Zone Level
- Indicator Channels 'A' and 'C' will not provide *
- accurate indication of reactor water level if a
- Standby Liquid Control Pump is injecting into the *
- RPV and should not be used.
- WHEN directed by the GSS/GOS, THEN Start SLC Pump A by placing the STANDBY LIffUID CONTROL Keylock in the FIRE SYS 1 position (Panel 4F).
(320001A/22) E8-1
3 1
Proendure EMG-3200.01A l Rav. 1 Attachment H
.- Page 1 of 1
)
3.3 II Pump A does HQI start QB System 1 Squib Valve does HQI fire THEN Start SLC Pump B by placing the STANDBY LIQUID h CONTROL Keylock in the FIRE SYS 2 position (Panel 4F). t 3.4 Monitor system parameters for proper system performance.
3.5 II Demineralized Water is being used for injection, IHEN throttle Test Tank Demin Water Supply Valve V-19-12 ;
(RB 95 West) as required to maintain a constant level in i the Test Tank.
l O
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I (320001A/23) ES-2
Procrduro EMG-3200.01A R:v. 1 Attschment I Page 1 of 1 SUPPORT PROCEDURE 8 l O LINEUP FOR CONDENSATE SYSTEM INJECTION l
j 1.0 PREREOUISITES V
Confirmation of the lineup for Condensate System injection has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Confirm open: (on Panel SF/6F)
- HEATER BANK INLET Valves V-2-7 V-2-8 V-2-9
- HEATER BANK OUTLET valves V-2-10 V-2-ll V-2-12
- MFRV A BLOCK Valve V-2-740
- MFRV C BLOCK Valve V-2-741 3.2 Confirm all.available Condensate Pumps running. A B
C 3.3 Confirm 2 Condensate Demineralizers are in service for each operating Condensate Pump 3.4 Confirm all Feedwater Regulating Valve Controllers in MAN position. ID11A ID11B ID11C 3.5 Confirm all Feedwater Regulating Valves open. A B
C J
O (320001A/24) E9-1
1 Procedure EMG--3200.01A Rev. 1 Attachment J Page 1 of 2, SUPPORT PROCEDURE 9 Q LINEUP FOR CORE SPRAY SYSTEM INJECTION 1.0 PREREOUISITES g:
Confirmation of the lineup for Core Spray System injection has been directed by the Emergency Operating Procedures. .
2.0 PREPARATION None 3.0 PROCEDURE l 3.1 Confirm open Core Spray System 1 and 2 Pump Suction valves (Panel IF/2F). V-20-32 V-20-3 V-20-33 V-20-4 3.2 Confirm closed Core Spray System 1 and 2 Test Flow Return Valves in each system (Panel IF/2F). V-20-27 1 V-20-26 l l
3.3 Confirm at least one Core Spray System Main Pump ,
operating in each system (Panel 1F/2F). NZOIA NZO1C .
NZO1B NZO1D i l
3.4 NOTE Booster pump operation is L1QI required for injection to occur.
..................................................... j
- CAUTION *
- . i
- Operation of two booster pumps with only one )
- main pump in a Core Spray System may result in
- i
- main pump damage.
- Confirm required Core Spray System Booster Pumps in each system operating (Panel 1F/2F). NZO3A NZO3C NZO3B NZO3D (320001A/25) E10-1
~
Proctdure EMG-3200.01A R;v. 1 Attachment J Page 1 of 2
%./ 3.5 Confirm open Core Spray System 1 and 2 Discharge Valves (Panel 1F/2F). V-20-12 V-20-18 b 3.6 WHEN RPV pressure decreases to 310 psig, THEN Confirm open at least one Core Spray Parallel Isolation Valve in each System (Panel IF/2F), V-20-15 M V-20-40 maximize system flow irregardless V-20-21 of NPSH or Vortex limits. V-20-41 O
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(320001A/26) E10-2 l
1 i
_ __ _ _ _ . _ __\
Procaduro EMG-3200.01A Rpv. 1 Attachment K Page 1 of 1 O
SUPPORT PROCEDURE 10 STOPPING INJECTION FROM THE CORE SPRAY SYSTEM 1.0 PREREOUISITES Stopping Core Spray injection has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE ;
When directed by the GOS/GSS, perform the following:
3.1 Depress the OVERRIDE switches for all sensors that are lit (Panel IF/2F).
3.2 Depress LLL ACTUATED switches whether lit or unlit (Panel IF/2F).
3.3 Confirm closed Core Spray Parallel Isolation Valves HQI s required to be open to assure adequate core cooling.
3.4 Secure Core Spray Booster Pumps EQI required to assure adequate core cooling by placing their respective control switch in STOP (Panel IF/2F).
3.5 Secure Core' Spray Main Pumps EQT required to assure adequate core cooling by placing their respective control switch in STOP (Panel IF/2F). ;
3.6 Verify Core Spray KEEP FILL TROUBLE (B-3-d) alarm is HQI illuminated.
O (320001A/27) E11-1 i
i 1
- ._ -_ -.___ - 1
Procedure EMG-3200.01A Rev. 1 Attachment L !
o Page 1 of 2 1
Q SUPPORT PROCEDURE 11 ALTERNATE PRESSURE CONTROL SYSTEMS ISOLATION CONDENSERS V
1.0 PREREOUISITES RPV pressure control using the Isolation Condensers has been directed by the Emergency Operating Procedures.
2.0 PREPARATION i l
None 1 3.0 PROCEDURE 3.1 Procedure for Isolation Condenser A 3.1.1 Confirm Recirculation Pump A tripped.
3.1.2 ***********************************************
- CAUTION *
- If reactor water level exceeds 180* TAF, *
- initiation of an isolation condenser can *
- cause water hammer to occur.
- Verify Reactor level is below 160 inches TAF.
3.1.3 Open DC condensate return valve V-14-34 (Panel 1F/2F).
3.1.4 Control reactor pressure in specified band by 1
1 cycling V-14-34.
i I
3.1.5 Make up to IC shell to maintain IC level between l l
4.8 Ft. and 7.7 Ft. by cycling Isolation Condenser A l l
Make-Up Valve V-11-36 (Panel SF/6F).
(320001A/28) E12-1
Proczduro EMG-3200.01A l Rpv. 1 Attachment L Page 1 of 1 i
3.2 Procedure For Isolation Condenser B 3.2.1 Confirm Recirculation Pump E tripped. .
k 3.2.2 .................****.......****...............
- CAUTION *
- If reactor water level exceeds 180' TAF, *
- initiation of an isolation condenser can *
- cause water hammer to occur.
- Verify Reactor Level is below 160 inches TAF.
3.2.3 Open DC condensate return valve V-14-35 (Panel 1F/2F).
3.2.4 Control reactor pressure in specified band by cycling V-14-35.
3.2.5 Make up to IC shell to maintain IC level between 4.8 Ft. and 7.7 Ft. by cycling Isolation Condenser B Make-Up Valve V-11-34 (Panel 5F/6F). ,
t 0
L I
e (320001A/29) E12-2 !
Procedure EMG-3200.01A Rev. 1 Attachment M Page 1 of 1
[- SUPPORT PROCEDURE 12 ALTERNATE PRESSURE CONTROL SYSTEMS EMRVs @
1.0 PREREOUISITES RPV pressure control using the EMRVs has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Verify that Torus water level is above 90 inches.
3.2 Place the selected EMRV control switch in the MAN position (Panel 1F/2F).
3.3 Control reactor pressure in the specified band by opening the EMRVs in the following sequence:
NR108A NR108D NR108B NR1051C NR108E 3.4 Monitor Torus water temperature.
l I
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(320001A/30) E13-1 l
1
Procedure EMG-3200.01A Rev. 1
- Attachment N '
Page 1 of 2 '
O SUPPORT PROCEDURE 13 ALTERNATE PRESSURE CONTROL SYSTEMS CLEAN-UP IN RECIRCULATION MOD'. (
1.0 PREREOUISITES
~
RPV pressure control using the Reactor Water Cleanup System in Rec!*culation Mode has been directed by the Emergency Operating Procedures.
2.0 PREPARATION When directed by GSS/GOS, perform the following:
2.1 Open the EOP BYPASS PLUGS panel in the rear of Panel 3F.
2.1.1 Remove the bypass plug from position BP2 and insert into position BPl.
2.1.2 Remove the bypass plug from position BP4 and insert into position BP3.
2.1.3 Remove the bypass plug from position BP6 and insert into position BP5.
2.1.4 Remove the bypass plug from position BPB and insert into position BP7. ,
2.2 Obtain a flat head screwdriver from the EOP Tool Box in the Control Room.
2.3 Open the front panel of Auxiliary Relay Panel (A/B Battery Room) ER-215-087.
2.3.1 Remove bypass plug 1 (upper left hand corner).
2.3.2 Remove bypass plug 2 (upper left hand corner).
O (320001A/31) E14-1
o4; Procedure EMG-3200.01A Rsv. 1 Attachment N Page 2 of 1 3.0 PROCEDURE When directed by the GSS/GOS, perform the following 3.1 Bypass and isolate Cleanup Filters as follows:
3.1.1 Open V-16-83, Filter Bypass Valve (RB 75). L 3.1.2 Close Filter Outlet Valve ND28A or ND28B (RB 75).
3.2 NOTE The remote valve operators to valves V-16-102, V-16-113, and V-16-114 have been disconnected. ,
Bypass and isolate the Cleanup Demineralizer: ,
3.2.1 Open Demineralizer Bypass valve V-16-113 (RB 75 SW).
3.2.2 Close Demineralizer Outlet Valve V-16-114 (RB 75 SW).
3.2.3 Close Demineralizer Inlet valve V-16-102 (RB 75 SW).
3.3 II Cleanup System is not in service THEN Place the system in service in accordance with Procedure 303, Reactor Cleanup Demineralizer System. i 3.4 Maximize RBCCW flow to the Non-Regenerative Beat Exchanger.
Maximum flow allowed is 1750 gpm.
3.5 Maintain RPV pressure within desired band by throttling RBCCW flow to the NRHX.
l t
(320001A/32) E14-2 1
Procsdure EMG-3200.01A Rgv. 1 Attachment O Page 1 of 2 SUPPORT PROCEDURE 14 ALTERNATE PRESSURE CONTROL SYSTEMS i p
CLEAN-UP IN LETDOWN MODE '
1.0 PREREOUISITES 3.1 RPV pressure control using the Reactor Water Cleanup System in Letdown Mode has been directed by the Emergency Operating Procedures.
1.2 Boron Injection is not required.
2.0 PREPARATIONS None 3.0 PROGEDURE 3.1 II cleanup System is not in service l THEN place the system in service in accordance with Procedure 303, Reactor Cleanup Demineralizer System. l 1
3.2 Confirm closed the following valves: ;
- Discharge to Radwaste V-16-57 (Panel 3F).
- Discharge to Condenser V-16-60 (Panel 3F).
- Discharge Flow Controller FCV-ND-22 (Panel 3F).
3.3 Open Discharge to Condenser Valve V-16-60 (Panel 3F). j 3.4 Commence Letdown Flow to the main condenser by throtting l t
open Discharge Flow Controller FCV-ND-22 (Panel 3F). ,
3.5 Carefully monitor Cleanup System Flow and make necessary r l
adjustments with System Flow Controller FCN-ND-16 (Panel 3F) i to maintain proper differential pressures acroso demineralizer and filter elements.
3.6 Maintain NRHX outlet temperature below 130*F by either reducing Letdown Flow using FCV-ND-22 (Panel 3F) or increasing RBCCW Flow through the NRHX using valve V-5-122 (RB 51 SE). Maximum RBCCW Flow allowed is 1750 gpm.
3.7 Adjust letdown flow rate by throttling FCV-ND-22 to establish t
, required cooldown rate or pressure band.
\
(320001A/33) E15-1 !
i Procedure EMG-3200.01A Rev. 1 Attachment O Page 1 of 1 i
( ,
3.8 IE NRHX outlet temperature cannot be maintained less than 130*F HEE 0:
the system trips THEN 1. Bypass and isolate the Cleanup Filter: ,
- a. Open V-16-83, Filter Bypass Valve (RB 75).
- b. Close Filter Outlet Valve ND28A or ND28B (RB 75).
2.
EQ.TJ The remote valve operators to valves V-16-102, ,
v-16-113, and V-16-114 have been disconnected.
i Bypass and isolate the Cleanup Demineralizer: l
I
- 3. Contact I & C Department to inhibit the NRHX i
outlet high temperature as follows:
- a. At RK05 (75' Elev.), rotate the dial on !
TIS-1J33 counterclockwise until the maximum trip setting is obtained.
- 4. Return the Cleanup System to service in accordance I with Procedure 303, Reactor Cleanup Demineralizer !
System. !
- 5. Perform Steps 3.2 through 3.5 to establish !
letdown flow, f
- 6. Adjust letdown flow rate by throttling FCV-ND-22 to establish required cooldown rate or pressure f
band. ,
(320001A/34) E15-2 J
Procedure EMG-3200.01A Rev. 1 Attachment P
_' Page 1 of 1 SUPPORT PROCEDURE 15 ALTERNATE PRESSURE CONTROL SYSTEMS IC TUBE SIDE VENTS I!
1.0 PREREOUISITES RPV pressure control using the Isolation Condenser Tube Side Vents has been directed by the Emergency Operating Procedures, i 2.0 PREPARATION Perform the following in preparation for using the IC Tube Side Vents for RPV l pressure control.
2.1 Verify the following.:
- 1. Isolation Condensers are not required to be isolated.
- 2. Main Condenser is intact.
- 3. Offsite radioactivity release rate is expected to remain below the release rate which requires an Unusual Event.
- 2.2 Confirm that the Isolation Condenser Vent Valve control switches for the Isolation Condensers to be used are in the normal mid-position (Panel 11F).
Isolation Condenser A V-14-5 V-14-20 ;
Isolation Condenser B V-14-1 V-14-19 2.3 Open the EOP BYPASS PLUGS panel inside of l
Panel 10XF.
2.3.1 Remove the bypass plug from position BP2 and insert it into position LPl.
2.3.2 Remove the bypass plug from position BP4 and insert it into position BP3.
O (320001A/35) E16-1 i
e Procedure EMG-3200.01A Rev. 1 Attachm:nt P l Page 1 of 1 3.0 PROCEDURE 3.1 Verify that RPV Water Level is below 180 in. TAF.
3.2 Confirm open the Isolation Condenser Steam Inlet Valves (IF/2F) for the Isolation Condensers to be used.
K Isolation Condenser A V-14-30 V-14-31 _
Isolation Condenser B V-14-32 V-14-33 3.3 Open the Isolation Condenser Tube Side vents (Panel 11F) for the Isolation Condensers to be used. }
t Isolation Condenser A V-14-5 V-14-20 Isolation Condenser B V-14-1 !
r V-14-19 I
3.4 Control Reactor pressure in specified band by cycling the tube side vents designated in Step 3.3.
O L 1
I i
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O (320001A/36) E16-2 l
OYSTER CREEK NUCLEAR GENERATING Number l Ir U Nualear STAT 10, PROCEDURE mo-noo.oin !
Title Revision No.
' i Applicability / Scope Responsible Office PLANT ENGINEERING EMERGENCY OPERATING PROCEDURE POR OYSTER CREEK 2200 This document is within QA plan scope X Yes___No Effective Date Safety Reviews Required X Yes_ _No (07/19/93) 07/29/93 Prior Revision 0 incorporated the This Revision _ _1 incorporates the following Temporary Changes: following Temporary Chenges:
N/A N/A LIST OF EFTECTIVE PAGES PAGE REVISION PAGE REVISION PAGE REVISION 1.0 1 E8-1 1 E16-1 1 2.0 0 E9-1 1 E16-2 1 3.0 1 E9-2 1 E16-3 1 4.0 1 E10-1 1 E16-4 1 El-1 1 E11-1 1 E16-5 1 E2-1 1 E11-2 1 E16-6 1
,/] E2-2 1 E12-1 1 E16-7 0 (f E3-1 1 E12-2 1 E17-1 1 E4-1 1 E13-1 1 E17-2 1 ES-1 1 E13-2 1 E17-3 1 E6-1 1 E14-1 1 E17-4 1 E6-2 1 E14-2 1 C0(STER CREEK lt' 2 l":'co8TacM'd o t"flSTRIBUTION E7-3 E7-4 1
1 ElpDCUMENT E l ., I~ 1 SER!AL NUT 'TriR . 7k_
INFO. MGMT. - DCC Signature Concurring Organization Element Date
^ '
Originator -
EOP COORDINATOR ,
Concurred By M [ygg/ EOP COMMITTEE y PM hQ4 PLANT ENGINEERING DIRECTOR hr[/9 3 hhhh, MGR, PLANT OPERATIONS 'J TS O
()
Approved ny Q Am%
vICE rRESIDENT s DIRECTOR, OC 7, g,9 3 (320001B) 1.0
GUCl88r '87"" C"""" "'cI2^^ C""^TI" STATION PROCEDURE
"""ber EMG-3200.01B Title Revision No.
RPV CONTROL - WITH ATWS 0 1.0 PURPOSE The purpose of the RPV Control - With ATWS Procedure is to:
Maintain adequate core cooling Shutdown the reactor Cooldown the RPV to cold shutdown conditions
2.0 REFERENCES
2.1 Procedures
- 107.4, EOP Program Control
- 308, Emergency Core Cooling System Operation 2.2 Drawings
- BR 2002, Main, Extraction & Aux Steam System
- BR 2006, Flow Diagram Closed Cooling Water System
- BR 2011, Shts 1 & 2, Flow Diagram - H&V Reactor Bldg.
- BR 3029, DC Control Elem Diagram
- BR E1102, Emer Condenser Isol Outlet Valve V-14-35
- BR E1183, Elem Diagram for Cleanup Isolation Valve V-16-2
- BR E1184, "lem Diagram for Cleanup Isolation Valve V-16-14
- GE 112C2248, Sht 2, Connection Diagram 11F
- GE 112C2654, Sht 3, Panel 2R Connection Diagram
- GE 148F262, P&ID - Emergency Condenser System
- GE 148F444, P&ID - Cleanup Demineralizer System
- GE 157B6350, Shts 117, 118, 153, Cleanup System AC Isol Valve Elem Diagram O
(320001B) 2.0 l
l
.m OYSTER CREEK NUCLEAR GENERATING Ntrnbar STATION PROCEDURE EMG-3200.01B Title Revision No.
- GE 237E566, Shts Ia, Ib, 2, 4, & 5, Rx Protection System Elem 1:
Diagram
- NU 5060E6003, Shts 1 - 3, Core Spray / RBCCW Drywell Isolation Elem Diagram 2.3 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.4 2000-STD-1218.04, EOP Writer's Guide 3.0 PRECAUTIONS AND LIMITATIONS 3.1 This procedure gives guidance to the operator for bypassing isolation signals and automatic scrams which is a departure from the Oyster Creek Technical Specifications. It is permissible to take actions which depart from the plant's Technical Specifications during emergency conditions as authorized by 10 CFR 50.54(x).
4.0 ATTACHMENTS 4.1 Attachment A - RPV Control - With ATWS EOP Flowchart DWG: GU 3E-200-08-009 Sht 1 4.2 Attachment B - Support Procedure 1, Confirmation of Automatic Initiations and Isolations 4.3 Attachment C - Support Procedure 16, Bypassing MSIV LO-LO Level Isolatic. Interlocks 4.4 Attachment D - Support Procedure 17, Termination and Prevention of Injection ,
4.5 Attachment E - Support Procedure 18, Bypassing RBCCW Isolation l Interlocks !
4.6 Attachment F - Support Procedure 19, Feedwater/ Condensate and CRD System Operation 4.7 Attachment G - Support Procedure 20, Low Pressure Injection During an ATWS O
(320001B) 3.0
i
?
OYSTER CREEK NUCLEAR GENERATING Number 7[
STATION PROCEDURE EMG-3200.01B
,^ Title Revision No.
V) RPV CONTROL - WITH ATWS 1 4.8 Attachment H - Support Procedure 10, Stopping Injection from the Core >
Spray System 4,9 Attachment I - Support Procedure 11, Alternate Pressure Control Systems - Isolation Condensers 4.10 Attachment J - Support Procedure 12, Alternate Pressure Control Systems - EMRVs 4,11 Attachment K - Support Procedure 13, Alternate Pressure Control Systems- Clean-up in Recirculation Mode 4.12 Attachment L - Support Procedure 14, Alternate Pressure Control Systems - Clean-up in Letdown Mode 4.13 Attachment M - Support Procedure 15, Alternate Pressure Control Systems - I C Tube Side Vents 4.14 Attachment N - Support Procedure 21, Alternate Insertion of Control Rods
[V') 4.15 Attachment O - Support Procedure 22, Initiating the Liquid Poision System 4.16 Attachment P - Support Procedure 23, Alternate Boron Injection with the Clean-up System 4.17 Attachment 0 - Support Procedure 24, Alternate Boron Injection with the Feed & Condensate System I
i 4
1 1
I
, ^s V
(320001B) 4.0 1
1
OYSTER CREEK NUCLEAR GENERATING Number k{',l@f STATION PROCEDURE EMG-3200.01B Title Revision No.
(1 RPV CONTROL - WITH ATWS 1 V
ATTACIIF&LG_A Attachment A to E!!G-3200.01B, RPV Control - With ATWS is the RPV Control - With ATWS E0P Flowchart, DWG: GU 3E-200-08-009, Sht 1, Rev. 1.
w)
,r 'y
\j -
(320001B/5) El-1
Proceduro EMG-3200.01B R;v. 1 Attechment B Page 1 of 1
\
\,")
SUPPORT PROCEDUIE 1 CQEFIRMATION OF AUTOMATIC INITIATIONS AND ISOLATIONS V
1.0 PREREOUISITES Confirmation of automatic initiations and isolations has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE Confirm the following isolations/ starts not required to by bypassed by the Emergency Operating Procedures:
SYSTEM OPERATING DETAILS Reactor IE Any of the following conditions exist:
Isolation
- RPV water level at or below 86 in.
- Steam tunnel temperature at or above 180*F
- Any steam line flow at or above 4.0x106 lbm/hr
- Reactor mode switch in RUN and RPV pressure at or below i
7-s 5 850 psig
'Nm- /
- Main steam line radiation at or above 800 units THEN Confirm closed the following:
MSIVs IC VENTS RX SAMPLE NSO3A V-11-1,-19 V-24-30 (11F)
NSO4A V-14-5,-20 V-24-29 (11F)
NS03B Dw AIR SUPPLY NSO4B V-6-395 (11F)
IC-A IE IC-A is ruptured Isolation THEN Confirm closed the following:
IC ISOLATION VALVES IC VENTS V-14-30 __ _V-14-34 V-14-5 V-14-31 V-14-36 V-14-20 IC-B IE IC-B is ruptured Isolation THEN Confirm closed the following:
IC ISOLATION VALVES IC VENTS V-14-32 V-14-35 V-14-1 V-14-33 V-14-37 V-14-19 i )
v (320001B/6) E2-1
Proc;duro EMG-3200.01B Rav. 1 Attechment B Page 2 of 1 f SYSTEM OPERATING DETAILS i'
Cleanup II Any of the following conditions exist:
System
- RPV water level at or below 86 in.
Isolation a Drywell pressure at or above 3.0 psig 7 HEN Confirm closed the following Cleanup Isolation valves: h V-16-1 V-16-14 V-16-2 V-16-61 Shutdown IE Any of the following conditions exist:
Cooling
- RPV water level at or below 86 in.
System
- Dry'rell pressure at or above 3.0 psig Isolation THEN Confirm closed the following:
SDC SYSTEM ISOIATION VALVES V-17-54 V-17-19 Core Spray IE Any of the following conditions exist:
System
- RPV water level at or below 86 in.
Start
- Drywell pressure at or above 3.0 psig THEN Confirm start of one Main Pump and one Booster Pump in each Core Spray System.
Primary IE Any of the following conditions exist:
e Containment
- RPV water level at or below 86 in.
( Isolation
- Drywell pressure at or above 3.0 psig THEN Confirm closed the following valves that are not required to be open by the Emergency Operating Procedures:
Svstem Valve No.
DW Vent / Purge V-27-1 (Panel 11F)
V-27-2 V-27-3 V-27-4 Torus vent V-28-17 (Panel 11F)
V-28-18 Torus 2" Vent Bypass V-28-47 (Panel 11F)
DWEDT V-22-1 (Panel 11F)
V-22-2 DW Floor Sump V-22-28 (Panel 11F)
V-22-29 Torus /Rx Bldg. V-26-16 (Panel 11F)
Vacuum Breakers "
V-26-18 TIP Valves Common Ind. (Panel 11F)
DW 2" Vent Bypass V-23-21 (Panel 12XR)
V-23-22 N2 Purge V-23-13 (Panel 12XR)
V-23-14
- V-23-15 V-23-16 N2 Makeup V-23-17 (Panel 12XR)
V-23-18 V-23-19 V-23-20 O
(320001B/7) E2-2
Proceduro EMG-3200.01B R;v. 1 Attachment C Page 1 of 1 O SUPPORT PROCEDURE 16 RYPASSING MSIV LO-LO LEVEL ISOLATION INTERI,0CKS V
1.0 PREREOUISITES Bypassing of the MSIV Lo-Lo level isolation interlocks has been directed by the Emergency Operating Procedures.
2.0 FFEPARATION None 3.0 PROCEDURE 3.1 Obtain four (4) bypass plugs from the EOP Tool Box in the Control Room.
3.2 Open the EOP BYPASS PLUGS panel in the rear of Panel 6R.
3.2.1 Insert a bypass plug in position BPl.
3.2.2 Insert a bypass plug in position BP2.
() 3.3 Open the EOP BYPASS PLUGS panel in the rear of Panel 7R.
3.3.1 Insert a bypass plug in position BPl.
3.3.2 Insert a bypass plug in position BP2.
3.4 Place the ISOL SIGNAL BYPASS V-6-395 switch in BYPASS position (Panel 11F).
3.5 Inform the GSS/GOS shat the MSIV LO-LO Level Isolation Interlock has been bypassed.
(320001B/8) E3-1 w->
Proesdura EMG-3200.01B Rev. 1 Attachment D Page 1 of 1 o
U SUPPORT PROCEDURE 17 TERMINATION AND PREVENTION OF INJECTION 1.0 PREREOUISITES Termination and prevention of injection has been directed by the Emergency Operating Procedures.
2.0 PREPARATIQN 2.1 If Core Spray actuating signals are present, THEN OVERRIDE Core Spray initiation logic by depressing the override switches for all the sensors that are lit and depressing all ACTUATED switches, whether lit or unlit.
3.0 PROCEDURE 3.1 Terminate and prevent Condensate and Feedwater injection by performing the following at Panel SF/6F:
3.1.1 Trip all operating Feedwater Pumps.
3.1.2 Confirm one Condensate Pump running.
3.1.3 Place all individual FRV Controllers in MAN position.
3.1.4 Close all Feedwater Regulating Valves.
3.1.5 Close the Low Flow Valves.
3.2 NOTE Overriding Core Spray initiation logic may be required.
Terminate and prevent Core Spray injection by performing the following at Panel IF/2F:
3.2.1 Confirm all Core Spray Parallel Isolation Valve closed.
3.2.2 Confirm all operating Core Spray Booster Pumps tripped.
3.2.3 Confirm all Core Spray Main Pump control switches in PULL TO LOCK position.
rs (320001B/9) E4-1
Proc duro FMG-3200.01B Rpv. 1 Attachment E
~t Page 1 of 1 m
b SUPPORT PROCEDURE 18 BYPASSING RBCCW ISOLATION INTERLOCKS 1.0 PREREOUISITES Bypassing of the RBCCW isolation has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 NOTE After completing the following steps, valves V-5-147, V-5-166 and V-5-167 will only operate from the Control Room. All automatic operation is removed.
In the rear of Panel 2R, open the EOP BYPASS PLUGS panel.
2.1.1 Remove the bypass plug from position BPl.
2.1.2 Remove the bypass plug from position BP2.
3.0 PROCEDURE 3.1 Confirm open RBCCW Isolation Valves (Panel 1F/2F)
= V-5-147
- V-5-166
- V-5-167
- V-5-148 3.2 Start all available DW RECIRC FANS by placing their respective control switches in ON (Panel 11R).
3.3 Place the ISOL SIGNAL BYPASS V-6-395 switch in BYPASS position (Panel 11F).
O v
(320001B/10) ES-1
Proc; dure EMG-3200.01B Rgv. 1 Attachment F Page 1 of 2
-w (d 's SUPPORT PROCEDURE 19 FEEDWATER/ CONDENSATE AND CRD SYSTEM OPERATION 1.0 PREREOUISITES F Directed to maintain RPV level with the Feed, Condensate and CRD Systems by the Emergency Operating Proceduren.
2.0 PPEPARATION None 3.0 PROCEDURE
....****....** .....****** .********............. ****o*...***...... ***..
- CAUTION *
- A large power excursion and substantial core damage could result from *
- a rapid increase in injection into the RPV.
- 3.1 Feedwater/ Condensate 3.1.1 Confirm one Condensate Pump and one Feedwater Pump operating.
3.1.2 Control RPV Water level using the following:
1
(N
- Reactor Level Setdown Program (if initiated)
\ ',
- Feedwater Regulating Valves
- Feedwater Low Flow Valves
- Heater Bank Outlet Isolation Valves
- Feedwater and Condensate Pumps l
3.1.3 II RPV water level cannot be maintained below 160 in. TAF, THEN close the Heater Bank Outlet Isolation Valve for the operating pump.
3.1.4 IE RPV water level reaches 170 in. TAF, THEH trip the operating feedwater pump.
3.1.5 lE RPV water level reaches 170 in. TAF l
AND RPV pressure is below 350 psig (shutoff head of the Condensate Pumps),
IHEN close all Heater Bank Outlet Isolation Valves.
3.1.6 IE RPV water level continues to increase,
,m,
( THEN trip the operating Condensate Pumps.
(320001B/12) E6-1 l
I Procsdure EMG-3200.01B Rev. 1 Attachment F Page 1 of 2 3.2 CRD NJ
- CAUTION =
- Operating two pumps at greater than 150 gpm or one pump at
- h
- greater than 90 gpm may result in a pump trip.
- 3.2.1 If CRD bypass fic<w is required for RPV water level control, THEN 1. Start all availe.ble CRD Pumps (Panel 4F).
- 3. Monitor flow on Flow Gage FI-225-2 (RB 23)
MID throttle open CRD Bypass Valve V-15-30 (RB 23) so as not to exceed 150 gpm flow for two pump operation gr 90 gpm for one pump operation.
3.4 IF RPV vater level cannot be maintained less than 160 in. TAF, THEN 1. Throttle closed CRD Bypass Valve, V-15-30 (RB 23), if opened i
- 2. Throttle closed CRD Flow Control Valve (Panel 4F) 3.5 IE RPV water level reaches 170 in. TAF, AND l the CRD System is EQT required for rod insertion, l THEN trip any operating CRD pump (Panel 4F).
I i
(320001B/13) E6-2 i
1 1
Proc; dura EMG-3200.01B R v. 1 Attcchment G Page 1 of 4 q SUPPORT PROCEDURE 20 V
LOW PRESSURE INJECTION DURING AN ATWS 1.0 PREREOUISITES w
Injecting water with Low Pressure Systems has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 IE Core Spray activating signals are present, THEN override Core Spray initiation logic by depressing the OVERRIDE switches for all the sensors that are lit and depressing all ACTUATED switches, whether lit or unlit.
2.2 The procedure for using Condensate Transfer for injection requires the use of an MB-1 key.
3.0 PROCEDURE i
( l
\ NOTE Overriding Core Spray initiation logic may be required.
3.1 II Core Spray System 1 is to be used to inject Fire Water, THEN perform the following:
3.1.1 Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System I (Panel IP/2F).
3.1.2 Place Core Spray System 1 Main Pump control switches in PULL TO LOCK position (Panel IF/2F).
3.1.3 Close Tell-Tale Drain valve, V-20-91 8 23 North or North Side RB outside).
3.1.4 Confirm running all Diesel Fire Pumps by placing their control switches in MAN position (Panel 13R).
3.1.5 Confirm open Core Spray System 1 Discharge Valve, V-20-12 (Panel IF/2F).
(320001B/13) E7-1
Proc;duro EMG-3200.01B Rzv. 1 Attechment G Page 2 of 4 !
3.1.6 Confirm open either Core Spray System 1 Parallel Isolation 7-i .
valve, V-20-15 or V-20-40 (Panel 1F/2F).
i 3.1.7 Confirm closed Core Spray System 1 Test Flow Return Valve, V-20-27 (Panel IF/2F).
3.1.8 Close Core Spray System 1 Pump Suction valves V-20-32 and V-20-3 (Panel 1F/2F).
3.1.9 Slowly throttle open Fire Water Supply valve, V-20-83
~
(RB 23 North or North Side RB outside) as required to maintain RPV Level.
3.2 IE Core Spray System 2 is to be used to inject Fire Water, THEN perform the following:
3.2.1 Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 2 (Panel 1F/2F).
- 3.2.2 Place Core Spray System 2 Main Pump control swtiches in PULL TO LOCK position (Panel 1F/2F).
3.2.3 Close Tell-Tale Drain Valve, V-20-90 (RB 23 South or South Side RB outside).
3.2.4 confirm running all Diesel Fire Pumps by placing their control switches in MAN position (Panel 13R).
3.2.5 Confirm open Core Spray System 2 Discharge Valve, V-20-18 (Panel IF/2F).
3.2.6 Confirm open either Core Spray System 2 Parallel Isolation valve, V-20-21 or V-20-41 (Panel IF/2F).
3.2.7 Confirm closed Core Spray System 2 Test Flow Return Valve, V-20-26 (Panel IF/2F).
3.2.8 Close Core Spray System 2 Pump Suction Valves V-20-33 and V-20-4 (Panel IF/2F).
' E7-2 (320001B/14)
f Proc; dure EMG-3200.01B Rsv. 1 Attechm:nt G Page 3 of i f _.
3.2.9 Slowly throttle open Fire Water Supply valve, V-20-82
\s ,/ (RB 23 South or South Side RB outside) as required to maintain RPV Level.
3.3 II Core Spray System 1 is to be used to inject Condensate Transfer, THEN perform the following:
3.3.1 Confirm stcpped the Core Spray Main and Booster Pumps in Core Spray System 1 (Panel IF/2F).
3.3.2 Place Core Spray System 1 Main Pump control swtiches in PULL TO LOCK position (Panel IT/2F).
3.3.3 Unlock and open Regulator Bypass valves, V-11-110 and l
V-11-111 (RB 51 NW).
3.3.4 Confirm open Core Spray System 1 Discharge Valve, V-20-12 (Panel IF/2F).
3.3.5 Confirm open either Core Spray System 1 Parallel Isolation valve, V-20-15 or V-20-40 (Panel 1F/2F).
3.3.6 Confirm closed Core Spray System 1 Test Flow Return valve, v-20-27 (Panel 1F/2F).
3.3.7 Start all available Condensate Transfer Pumps (Panel SF/6F).
3.3.8 Close Core Spray System 1 Pump Suction Valves V-2-32 and V-20-3 (Panel IF/2F).
3.4 II Core Spray System 2 is to be used to inject condensate Transfer, THEN perform the following:
3.4.1 Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 2 (Panel 1F/2F).
3.4.2 Place Core Spray System 2 Main Pump control swtiches in PULL TO LOCK position (Panel 1F/2F).
3.4.3 Unlock and open Regulator Bypass valves, V-11-109 and V-11-108 (RB 75 S).
3.4.4 Confirm open Core Spray System 2 Discharge Valve, V-20-18 (Panel IF/2F).
f E7-3
(, (320001B/15)
Procrdura EMG-3200.01B R;v. 1 Attachment G l Piga 4 of 1 l l
3.4.5 Confirm open either Core Spray System 2 Parallel
() Isolation valve, V-20-21 or V-20 *1 (Panel 1F/2F).
3.4.6 Confirm closed Core Spray System 2 Test Flow Return i Valve, V-20-26 (Panel 1F/2F).
3.4.7 Start all available Condensate Transfer Pumps (Panel 5F/6F).
3.4.8 Close Core Spray System 2 Pump Suction valves V-20-33 and V-20-4 (Panel IF/2F).
3.5 II injection with the Core Spray Main Pump is directed, THEN inject with Core Spray as follows:
3.5.1 Confirm open Core Spray Pump Suction Valve for pump to be started (Panel IF/2F).
3.5.2 **********************************************************
- CAUTION *
- Diesel Generator overload will result if a Core Spray *
-w g
'"')
- Main Pump is started with a Diesel Generator load of
- greater than 2250 kw.
- IE Bus IC or ID are being supplied by a Emergency Diesel Generator, THEN verify that adequate load margin is available so as E2I to exceed EDG load limit when starting Core Spray Main Pumps.
3.5.3 Start one Core Spray Main Pump (Panel IF/2F).
3.5.4 Confirm open the Selected System Discharge Valve (V-20-12 or V-20-18). (Panel IF/2F) 3.5.5 Open a Parallel Isolation Valve in the selected system, (V-20-15, V-20-40, v-20-21 or V-20-41).
(Panel IF/2F)
( 3.5.6 Start additional Main Pump or open additional Parallel Isolation Valves as directed by the GSS/GOS.
(320001B/16) E7-4
f Proc dura EMG-3200.01B Rev. I
?.ttachment H
^
Page 1 of 1 im
(
'" } SUPPORT PROCEDURE 10 STOPPING INJECTION FROM THE CORE SPRAY SYSTEM 6-1.0 PREREOUISITES Stopping Core Spray injection has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE When directed by the GOS/GSS, perform the following:
3.1 Depress the OVERRIDE switches for all sensors that are lit (Panel 1F/2F).
3.2 Depress ALL ACTUATED switches whether lit or unlit (Panel IF/2F).
3.3 Confirm closed Core Spray Parallel Isolation Valves HQI required to be open to assure adequate core cooling.
3.4 Secure Core Spray Booster Pumps EQI required to assure adequate core cooling by placing their respective control switch in STOP (Panel 1F/2F). __
3.5 Secure Core Spray Main Pumps HQI required to assure adequate core cooling by placing their respective control switch in STOP (Panel IF/2F).
3.6 Verify Core Spray KEEP FILL TROUBLE (B-3-d) alarm is HQI illuminated. ;
l 1
o E8-1 (320001B/17) l
I t Procadura EMG-3200.01B
> Rgv. 1 Attachment I Page 1 of 2 m
i i SUPPORT PROCEDURE 11 LJ ALTERNATE PRESSURE CONTROL SYSTEMS ISOLATION CONDENSERS 6
1.0 PREREOUISITES RPV pressure control using the Isolation Condensers has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PFOCEDUFE 3.1 Procedure for Isolation Condenser A 3.1.1 Confirm Recirculation Pump A tripped.
3.1.2 *********************************************
- CAUTION *
- If reactor water level exceeds 180" TAF, *
/~N
- initiation of an isolation condenser can
- k-
- cause water hammer to occur.
- Verify Reactor level is below 160 inches TAF.
3.1.3 Open DC condensate return valve V-14-34 (Panel 1F/2F).
3.1.4 Control reactor pressure in specified band by cycling V-14-34.
3.1.5 Make up to IC shell to maintain IC level between 4.8 Ft. and 7.7 Ft. by cycling Isolation Condenser A Make-Up Valve V-11-36 (Panel 5F/6F).
v (320001B/18) E9-1
Procsdure EMG-3200.01B Rgv. 1
[ Attachment I Page 2 of 1 3.2 Procedure For Isolation Condenser B 3.2.1 Confirm Recirculation Pump E tripped.
I '.
3.2.2 ****.... ************************************
- CAUTION *
- If reactor water level exceeds 180" TAF, *
- initiation of an isolation condenser can *
- cause water hammer to occur.
- Verify Reactor Level is below 160 inches TAF.
3.2.3 Open DC condensate return valve V-14-35 (Panel IF/2F).
P 3.2.4 Control reactor pressure in specified band by cycling V-14-35.
3.2.5 Make up to IC shell to maintain IC level between 4.8 Ft. and 7.7 Ft. by cycling Isolation Condenser B Make-Up Valve V-11-34 (Panel SF/6F).
l l
l (320001B/19) E9-2 1
1
e Procsdura EMG-3200.01B Rgv. 1
,' Attachment J Page 1 of 1 SUPPORT PROCEDURE 12 ALTERNATE PRESSURE CONTROL SYSTEMS EMRVs g 1.0 PREREOUISITES RPV pressure control using the EMRVs has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None i 3.0 PROCEDURE 3.1 Verify that Torus water level is above 90 inches.
3.2 Place the selected EMRV control switch in the MAN position (Panel IF/2F).
3.3 control reactor pressure in the specified band by opening the EMRVs in the following sequence:
NR108A NR108D NR10BB NR108C NR108E 3.4 Monitor Torus water temperature.
T I
O I
(320001B/20} E10-1 i
~
Procrdure EMG-3200.01B Rav. 1 Attachment K Page 1 of 1 O SUPPORT PROCEDURE 13 i
ALTERNATE PRESSURE CONTROL SYSTEMS CLEANUP _IN RECIRCULATION MODE b 1.0 PREREOUISITES RPV pressure control using the Reactor Water Cleanup System in Recirculation Mode has been directed by the Emergency Operating Procedures.
2.0 PREPARATION When directed by GSS/GOS, perform the following:
2.1 Open the EOP BYPASS PLUGS panel in the rear of Panel 3F.
2.1.1 Remove the bypass plug from position BP2 and insert into position BPl.
2.1.2 Remove the bypass plug from position BP4 and insert into position BP3.
2.1.3 Remove the by es plug from position EP6 and insert into position BPS.
2.1.4 Remove the bypass plug from position BP8 and insert into position BP7.
2.2 Obtain a flat head screwdriver from the EOP Tool Box in the Control Room.
2.3 Open the front panel of Auxiliary Relay Panel ER-215-087 (A/B Battery Room).
Remove bypass plug 1 (upper left hand corner).
Remove bypass plug 2 (upper left hand corner).
O (320001B/21) E11-1 l
t
Procedure EMG-3200.01B Rev. 1 Attachment K Page 2 of I l l
3.0 PROCEDURE I
When directed by the CSS /GOS, perform the following 3.1 Bypass and isolate Cleanup Filters as follows:
3.1.1 Open V-16-83, Filter Bypass Valv6 (RB 75). *!
3.1.2 Close Filter Outlet Valve ND28A or ND2BB (RB 75).
3.2 E2IE The remote valve operators to valves V-16-102, V-16-113, and V-16-114 have been disconnected.
Bypass and isolate the Cleanup Demineralizer:
3.2.1 Open Demineralizer Bypass Valve V-16-113 (RB 75 SW). i 3.2.2 Close Demineralizer Outlet Valve V-16-114 (RB 75 SW). {
3.2.3 Close Demineralizer Inlet Valve V-16-102 (RB 75 SW).
3.3 II Cleanup System is not in service ;
THEN Place the system in service in accordance with Procedure 303, Reactor Cleanup Demineralizer System. !
3.4 Maximize RBCCW flow to the Non-Regenerative Beat Exchanger. +
Maximum RBCCW flow allowed is 1750 gpm.
3.5 Maintain RPV pressure within desired band by throttling RBCCW flow to the NRHX. j J
' Ell-2 (320001B/22)
Proccduro EMG-3200.01B Rev. 1
, Attachment L Page 1 of 2
('l)
' SUPPORT PROCEDURE 14 ALTERNATE PRESSURE CONTROL SYSTEMS l-CLEANUP IN LETDOWN MODE 1.0 PREREOUISITES 1.1 RPV pressure control using the Reactor Water Cleanup System in Letdown l Mode has been directed by the Emergency Operating Procedures, 1.2 Boron Injection is not required.
2.0 PREPARATIONS None 3.0 PROCEDURE 3.1 II cleanup Sistem is not in service THEN place the system in service in accordance with Procedure 303, Reactor Cleanup Demineralizer System.
3.2 Confirm closed the following valves: 3
()
- Discharge to Radwaste V-16-57 (Panel 3F).
Discharge to Condenser V-16-60 (Panel 3F).
- Discharge Flow Controller FCV-ND-22 (Panel 3F).
3.3 Open Discharge to Condenser Valve V-16-60 (Panel 3F).
3.4 Commence Letdown Flow to the main condenser by throtting open Discharge Flow Controller FCV-ND-22 (Panel 3F).
3.5 Carefully monitor Cleanup System Flow and make necessary adjustments with System Flow Controller FCN-ND-16 (Panel 3F) to maintain proper differential pressures across demineralizer and filter elements.
?.6 Maintain NRHX outlet temperature below 130*F by either reducing Letdown Flow using FCV-ND-22 (Panel 3F) or increasing RBCCW Flow through the NRHX using valve V-5-122 (RB 51 SE).
Maximum RBCCW Flow allowed is 1750 gpm.
3.7 Adjust letdown flow rate by throttling FCV-ND-22 to establish required cooldown rate or pressure band.
5 (320001B/24) E12-1 ;
Procrdure EMG-3200.01B Rev. 1 Attachment L 3
Page 2 of 2
% 3.8 IE NRHX outlet temperature cannot be maintained less than 130*F MD the system trips l!
THEN 1. Bypass and isolate the Cleanup Filter:
- a. Open V-16-83, Filter Bypass Valve (RB 75).
- b. Close Filter Outlet Valve ND28A or ND28B (RB 75).
- 2. Bypass and isolate the Cleanup Demineralizer:
NOTE The remote alve operators to valves V-16-102, V-16-113, and V-16-114 have been disconnected,
- 3. Contact I & C Department to inhibit the NRHX l outlet high temperature as follows: ;
( a. At RK05 (75' Elev.), rotate the dial on TIS-1J33 counterclockwise until the maximum trip setting is obtained.
- 4. Return the Cleanup System to service in accordance with Procedure 303, Reactor Cleanup Demineralizer System
- 5. Perform Steps 3.2 through 3.5 to establish
'etdown flow.
- 6. Adjust letdown flow rate by throttling FCV-ND-22 to establish required cooldown rate or pressure band.
(320001B/24) E12-2
Proctdure EMG-3200.01B Rsv. 1 Attachment M Page 1 of 2 O surroar raocuouas is ALTERNATE PRESSURE CONTROL SYSTEMS IC TUBE SIDE VENTS 1.0 PREREOUISITES RPV pressure control using the Isolation Condenser Tube Side Vents has been directed by the Emergency Operating Procedures.
2.0 PREPARATION Perform the following in preparation for using the IC Tube Side Vents for RPV pressure control.
2.1 Verify the following:
- 1. Isolation Condensers are not required to be isolated.
- 2. Main Condenser is intact.
- 3. Offsite radioactivity release rate is expected to remain below the release rate which requires an Unusual Event.
2.2 Confirm that the Isolation Condenser Vent Valve control switches O for the Isolation Condenser to be used are in the normal mid-position (Panel 11F).
Isolation Condenser A V-14-5 T
V-14-20 Isolation Condenser B V-14-1 V-14-19 2.3 Open the EOP BYPASS PLUGS panel inside of Panel 10XF.
2.3.1 Remove the bypass plug from position BP2 and insert it into position BPl.
2.3.2 Remove the bypass plug from position BP4 and insert it into position BP3.
I (320001B/25) E13-2 I
j l
l
Procsdure EMG-3200.01B Rav. 1 Attachment M
- Page 2 of 1
,~ 3.0 PROCEDURE (N /
s 3.1 Verify that RPV water level is below 180 in. TAF.
3.2 Confirm open the Isolation Condenser Steam Inlet valves (lF/2F) for the Isolation Cordensers to be used, f D Isolation condenser A V-14-30 V-14-31 Isolation Condenser B V-14-32 V-14-33 3.3 Open the Isolation Condenser Tube Side Vents (Panel 11F) for the Isolation Cordensers to be used.
Isolation Condenser A V-14-5 i
V-14-20 Isolation Condenser B V-14-1 V-14-19 3.4 Control Reactor pressure in specified band by cycling the tube side vents designated in Step 3.3.
O
.O (320001B/26) E13-2
. \
Procrdure EMG-3200.01B Rav. 1 l Attachment N l Page 1 of i I I
SUPPORT PROCEDURE 21 l O ALTERNATE INSERTION OF CONTROL RODS I
l l
PREREOUISITES 1.0 L
Insertion of Control Rods utilizing alternate methods has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None.
3.0 PPOCEDURE NOTE Alternate methods of control rod insertion may be performed in any order or concurrently as applicable.
When directed by the GSS/GOS, perform the following:
3.1 Erivino Control Rods 3.1.1 Start available CRD Pumps (Panel 4F).
3.1.2 Place Reactor Mode Switch in REFUEL (Panel 4F).
3.1.3 Place the ROD WORTH MININIZER keylock in BYPASS (Panel 4F).
3.1.4 Increase CRD drive water differential pressure.
3.1.5 Close Charging Header Supply Valve V-15-52 if required (RB 23 SE).
3.1.6 Throttle closed bypass valve V-15-30 as required (RB 23 SE).
3.1.7 Rapidly insert control rods manually ,
(Panel 4F).
O (320001B/27) E14-1
Proc:duro EMG-3200.01B Rav. 1 Attachment N Page 2 of i
, 3.2 Deenercize Scram Solenoids A- 3.2.1 IE MSIVs are closed, THEN place both 100-amp Main RPS Breakers in OFF (Panel 6R/7R). 6 3.2.2 WHEN the control rods are no longer moving in, THEN confirm the 100 amp Main RPS Breakers in ON.
3.2.3 IE MSIVs are open, THEN place RPS Channel I and II Subchannel Test Keylocks IA, IB, IIA and IIB in TRIP position (Panel 6R/7R).
3.2.4 WHEN the control rods are no longer moving in, THEN confirm the RPS Channel I and II Subchannel Test Keylocks in NORMAL position (Panel 6R/7R).
3.3 Ventina the Scram Air Header 3.3.1 Close Scram Air Header Isolation Valve V-6-175 (RB23SE).
3.3.2 Open Scram Air Header Drain valve V-6-409 (RB23SE).
3.3.3 WHEN control rods are no longer moving in, THEN 1. Close Scram Air Header Drain valve V-6-409.
3.4 Manual Scram 3.4.1 Place the ARI Normal / Bypass Switch in BYPASS position (Rear of Panel BR).
3.4.2 Depress the ARI Manual Reset pushbutton (Panel 4F).
3.4.3 IE Defeating RPS logic trips is necessary prior to resetting the scram, THEN perform the following:
,, 3.4.3.1 Obtain four (4) bypass plugs from the EOP Tool Box in the Control Room.
(320001B/28) E14-2
Proc: dura EMG-3200.01B R&v. 1 Attachment N m
Page 3 of i
/~'\ 3.4 ,3.2 Open the EOP BYPASS PLUGS panel in the rear of Panel 6R.
- 1. Insert a bypass plug into BP5.
- 2. Insert a bypass plug into BP6. h 3.4.3.3 Open the EOP BYPASS PLUGS panel in the rear of Panel 7R.
- 1. Insert a bypass plug into BP5.
- 2. Insert a bypass plug into BP6.
3.4.4 Confirm operating all available CRD Pumps (Panel 4F).
3.4.5 Reset the scram by depressing t5e Scram Reset Buttons (Panel 4F).
3.4.6 Confirm open SDV vent and drain valves (Panel 4F).
3.4.7 When the SDV LEVEL HI-HI alarms (H-1-b and H-2-b) clear thg$ manually scram the reactor by depressing the scram buttons (Panel 4F).
3.5 Ooenino Individual Scram Test Switches 3.5.1 Place the ARI Normal / Bypass Switch in Bypass position (Rear of Panel BR).
3.5.2 Depress the ARI Manual Reset pushbutton (Panel 4F).
3.5.3 II Defeating RPS Logic trips is necessary prior to resetting the scram, THEN perform the following:
3.5.3.1 Obtain four (4) bypass plugs from the EOP Tool Box in the Control Room.
3.5.3.2 Open the EOP BYPASS PLUGS panel in the rear of Panel 6R.
- 1. Insert a bypass plug into BPS.
- 2. Insert a bypass plug into BP6.
(320001B/29) E14-3
Proc; dura EMG-3200.01B Rcv. 1 Attechment N P&ga 4 of 1 j
3.5.3.3 Open the EOP BYPASS PLUGS panel in the rear of Panel 7R.
- 1. Insert a bypass plug into BPS.
- 2. Insert a bypass plug into BP6.
3.5.4 Confirm operating all available CRD Pumps (Panel 4F).
3.5.5 Reset the scram by depressing the Scram Reset Buttons (Panel 4F).
3.5.6 Confirm open SDV vent and drain valves (Panel 4F).
3.5.7 ****************************************************
QAUTION While performing this procedure, potentially
- radioactive steam may be released and Reactor *
- Building airborne contamination levels may *
- increase.
- Individually open the scram test switch on Panel 6KR for a control rod not inserted.
3.5.8 Close the scram test switch when the control rod stops moving.
3.5.9 Repeat Steps 3.5.7 and 3.5.8 as required.
3.6 Increasina CRD Coolina Water Differential Pressure 3.6.1 Start available CRD Pumps (Panel 4F).
3.6.2 Close Charging Header Supply valve V-15-52 (RB 23 CE).
3.6.3 Increase CRD cooling water differential pressure.
3.6.4 Throttle closed bypass valve V-15-30 as required (RB 23 SE).
O (320001B\30) E14-4
~
. Procedura EMG-3200.01B Rrv. 1 Attachment N I Page 5 of i NOTE N This method is to be used ONLY if all other insertion methods fail, t
3.7 Ventino Control Rod Drive Over Piston Volume v
UOTE If no CRD Pumps are available, this method may still be used provided Reactor pressure is greater than 600 peig.
- CAUTION *
- While performing this procedure, potentially radioactive steam
- may be released from the drain line effluent and Reactor
- Building airborne contamination levels may increase.
- 3.7.1 Start available CRD pumps (Panel 4F).
3.7.2 Close Cooling Water PCV isolation V-15-24 (RB23SE).
3.7.3 Close Exhaust Header root valve V-15-25 (RB23SE).
3.7.4 Close Stabilizer Unit Outlet valve V-15-40 (RB23SE).
3.7.5 Confirm closed Cooling Water PCV bypass valve V-15-131 (RB 23 SE).
3,7.6 Open drain valve V-15-74 (RB 23 SE).
3.7.7 Place Reactor Mode Switch in REFUEL (Panel 4F).
3.7.8 Insert control rods manually from Panel 4F.
3.7.9 Monitor Reactor Building airborne radiation levels.
3.7.10 WHEN control rods are no longer moving in THEN 1. Close V-15-74 (RB 23 SE).
. v-15-40
. V-15-25 W
. V-15-24 320001B/31) E14-5
l Procrduro EMG-3200.OlB l R2v. I 1 Attachment O !
Page 1 of 1 SUPPORT PROCEDURE 22 .
k INITIATING THE LIOUID POISON SYSTEM 1.0 PREREOUISITES Initiation of Standby Liquid Control System has been directed by the g Emergency Operating Procedures.
2.0 PREPARATIONS None.
3.0 PROCEDURE
- CAUTION *
- Due to pressure fluctuations, Fuel Zone Level Indicator Channel "A" *
- and "C" will not provide accurate indication of reactor water level if *
- a Standby Liquid Control Pump is injecting into the RPV and should not
- be used.
3.1 Place the STANDBY LIQUID CONTROL keylock in the FIRE SYS 1 or FIRE SYS 2 position.
3.2 Verify the following:
- 1. PUMP ON light for selected system illuminated (Panel 4F).
- 2. SQUIBS light for selected system illuminated (Panel 4F).
- 3. PUMP DISCH PRESS greater than Rx pressure (Panel 4F).
- 4. FLOW ON Alarm annuciates (G-1-b).
- 5. SQUIB VALVE OPEN Alarm annunciates (G-2-b).
3.3 If the above expected indications do HQI occur, THEN place the STANDBY LIQUID CONTROL Keylock in the opposite position.
(320001B/33) E15-1
Procedure EMG-3200.01B Rev. 1 Attachment P Page 1 of 2 SUPPORT PROCEDURE 23 ALTERNATE BORON INJECTION WITH THE CLEANUP SYSTEM .
1.0 PREREOUISITES Injection of Boron via the Cleanup System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION E91%
After completing the steps in this section, Cleanup System Valves V-16-1, V-16-2, V-16-14 and V-16-61 will only operate from the control switches in the Control Room. All automatic operation will be removed.
2.1 Open the EOP BYPASS PLUGS panel in the rear of Panel 3F.
2.1.1 Remove the bypass plug from position BP2 and insert into position BPl.
2.1.2 Pemove the bypass plug from position BP4 and insert into position BP3.
2.1.3 Remove the bypass plug from position BP6 and insert into position BPS.
2.1.4 Remove the bypass plug from position BP8 and insert into position BP7.
2.2 Obtain a flat head screwdriver from the EOP Tool Room in the Control Room.
2.3 Open the front panel of Auxiliary Relay Panel ER-215-087 (A/B Battery Room),
2.3.1 Remove bypass plug 1 (upper left hand corner).
2.3.2 Remove bypass plug 2 (upper left hand corner).
) (320001B/33) E16-1
i Procedura EMG-3200.01B i R2v. 1 Attcchment P Page 2 of 1 j 3.0 Procedure i When directed by the GSS/GCS, perform the following:
1 3.1 II no recirculation pump is running, l l
THEN 1. Confirm at least one recirculation loop suction and i discharge valves open other than B loop.
- 2. Close the B recirc loop discharge and discharge bypass valves.
3.2 Bypass and isolate the cleanup filters:
3.2.1 Open V-16-83, Filter Bypass Valve (RB 75).
~
3.2.2 Confirm close ND28A and ND28B, Filter Outlet Valve (RB 75).
3.3 NOTE The remote valve operators to valves V-16-102, V-16-113, and V-16-114 have been disconnected.
Bypass and isolate the Cleanup Demineralizer:
3.3.1 Open V-16-113, Demineralizer Bypass Valve (RB 75 SW).
3.3.2 Close V-16-102, Demineralizer Inlet Valve (RB 75 SW).
3.3.3 Close V-16-114, Demineralizer Outlet Valve (RB 75 SW).
3.4 II Cleanup System is not in service, THEN Place the system in service in accordance with Procedure 303, Reactor Cleanup Demineralizer System.
3.5 Use a backwashed/ empty Cleanup Filter, or backwash a Cleanup Filter as follows:
3.5.1 Confirm Cleanup Filter Backwash Tank full.
(Pressure Gauge on RB 119' El. under tank should indicate -11.6 psig).
3.5.2 ***********************************************************
- CAUTION *
- If Sludge Receiver Tank level is over nine (9) feet, *
- the backwashing sequence can cause contamination of *
- the plant ventilation system via six inch vent.
- Verify Sludge Receiver Tank has sufficient volume to accommodate backwashing a filter. Approximately a 2.5 feet level increase will occur per backwash.
('-
(320001B/34) E16-2
d Proceduro EMG-3200.01B Rev. 1 Attcchment P Page 3 of 2
- O 3.5.3 NOTE Only one set of Filter Recycle Valves are capable of being open at any one time.
n Place cleanup filter in recycle as follows:
- 1. Open ND-31 A(B) Precoat/ Recycle Outlet Valve.
- 2. Start Precoat Pump to selected filter A(B).
- 3. Open ND-30 A(B) Precoat/ Recycle Inlet Valve.
3.5.4 Press ND-35 A(B) Backwash Programmer Control START button, until the A(B) programmer seals in. It is sealed in when the green START and red UNIT IN BACKWASH lights stay on after the button is released.
3.5.5 Place PRECOAT PUMP CONTROL switch in OFF.
3.5.6 The following automatic sequence will occur:
- 1. ND-27A(B), Filter Inlet Valve, closes. l
- 2. ND-23A(B), Air Inlet Valve, opens.
- 3. ND-25A(B), 1" Vent Valve (to RBEDT), opens.
- 4. ND-25A(B) closes.
- 5. ND-30A(B), Precoat (Recycle) Inlet Valve, and ND-31A(B), Back to Precoat Valve, close.
- 6. ND-26A(B), Filter Sludge Tank Inlet Valve opens.
- 7. ND-23A(B), Air Inlet Valve, closes.
B. ND-24A(B), Vent / Overflow Valve, opens.
- 9. ND-29A(B), Backwash Inlet valve, opens.
- 10. ND-29A(B), Backwash Inlet valve, closes. i
- 11. ND-24A(B) closes.
- 12. ND-26A(B) closes. I l
1 O E16-3 (320001B/36)
I Proccdure EMG-3200.01B Rav. 1 i Attachment P
,; Page 4 of 1 ,
3.6 IE the Filter Aid Precoat Tank is being used to mix and add
( ,
powdered Boric Acid and Borax, ,
THEN continue in this procedure at Step 3.22. -
3.7 II the contents of the SLC Storage Tank is being injected using k the Cleanup System, THEN continue in this procedure at Step 3.8.
3.8 Drain the Filter Aid Precoat Tank by opening V-16-117, Filter Aid Precoat Tank Drain Valve. Close V-16-117 when the tank is drained.
3.9 Transfer the contents of the SLC Storage Tank to the Filer Aid Precoat Tank by perf orming Steps 3.9.1 through 3.9.4.
3.9.1 Connect a hose downstream of V-19-29, SLC Storage Tank Drain valve, and route the free end to the Filter Aid Precoat Tank.
Intert it through the hinged lid at the top and secure.
3.9.2 Unlock V-19-29 SLC Storage Tank Drain Valve.
3.9.3 Open V-19-29 and fill the Filter Aid Precoat Tank to 90% full by gravity draining the SLC Storage Tank. ,
O 3.9.4 Close V-19-29.
3.10 Close V-16-108, Filter Recycle Valve.
3.11 Verify V-16-109, Cleanup Filter Return to Precoat Tank, is closed.
3.12 Open ND-30A(B), Precoat/ Recycle Inlet Valve.
3.13 Open V-16-107, Precoat Pump Suction Valve.
3.14 Place ND32, Precoat Pump Discharge Valve, control switch in the HOLD ,
i position.
3.15 Start the Precoat Pump in EAND position.
i 3.16 Open ND25A(B), l' Vent Valve (to RBEDT).
3.17 WHEN a steady stream of water is observed in the sightglass downstream of Valve ND-25A(B) !
QR the Cleanup Filter Precoat Tank low level alarm annunciates, THEN 1. Stop the Precoat Pump.
- 2. Close Valves ND-25A(B), V-16-107, and ND-30A(B).
O (320001B/36) E16-4 I
i 9
Procedure EMG-3200.01B Rev. 1 Aftachment P Page 5 of 1 3.18 IE the Cleanup Filter Precoat Tank has reached the low level' I limit, THEN repeat Steps 3.9.3 through 3.17.
3.19 Y noIs During valving operations allow sufficient time for the (Red, Green) valve indication lights to completely change over.
Inject boron in accordance with Steps 3.19.1 through 3.19.4.
3.19.1 Open the ND27A(B), Filter Inlet Valve, by placing its selector switch to the OPEN position.
3.19.2 NOTE a
When Valve ND28A(B) is placed in AUTO, if the valve does not open or if it opens and then closes, a Cleanup Filter Isolation signal was actuated while the filter was in hold, and the programmer needs to be reset. Instructions for resetting the progranner are contained in Procedure 303, Reactor Cleanup Demineralizer System.
Open ND28A(B), Filter Outlet Valve, by placing its selector switch to the AUTO position.
3.19.3 Close V-16-83, Cleanup Filter Bypass Valve. Allow approximately one (1) minute to ensure that the Filter Outlet-Valve (ND28A(B) remains open.
3.19.4 Operate the Cleanup System in this mode for five (5) minutes.
3.20 Bypass and isolate the cleanup Filters.
3.20.1 Open V-16-83 3.20.2 Close ND27A(B) 3.20.3 Close ND28A(B) l 3.21 Repeat Steps 3.9 through 3.20 until the contents of the SLC Storage l 1
Tank are injected into the reactor. )
O (320001B/37) E16-5 I
_ _ _ _ _ _ _ _ _ _ _ _l
Proceduro EMG-3200.01B Rzv. 1 Attechment P
+ Page 6 of 2
[' 3.22
\
NOTE As required by Section 3.22, Boric Acid and Borax come in approximately 300 lb. barrels and are stored in the warehouse under Stock Numbers 001-512-1800-1 (Bin 2-0068-E,J) and 001-512-2000-1 (Bin 2-0064-E) respectively. Although only six F (6) barrels each are necessary to achieve a cold Boron shutdown weight of 273 lbs., plus a 25 percent conservatism, all available barrels (normally 10 each) should be transported to the Reactor Building 75 ft. elevation.
NOTE Steps 3.22 through 3.37 are used to mix and inject powdered boron using the Cleanup System and the Precoat Tank.
Verify that the Precoat Tank is 80% full and if not, fill with condensate transfer to a level of 80%.
3.23 Start the Precoat Tank Agitator and Precoat Tank Evacuator.
3.24 Add four barrels of Boric Acid and four barrels of Borax to the Filter Aid Precoat Tank and mix thoroughly.
3.25 Close V-16-108, Filter / Recycle Valve.
3.26 Verify V-16-109, Cleanup Filter Return to Precoat Tank Valve, is closed.
3.27 Open ND-30A(B), Precoat/ Recycle Inlet Valve.
3.28 Open V-16-107, Precoat Pump Suction valve. .
3.29 Place ND32, Precoat Pump Discharge Valve, control switch in the BOLD position. !
3,30 Start the Precoat Pump in HAND position.
3.31 Open ND-25A(B), la Vent valve (to RBEDT).
3.32 WHEN a steady stream of water is observed in the sightglass downstream of valve ND-25A(B),
QB the Cleanup Filter Precoat Tank low level alarm annunciates, THEN 1. Place the Precoat Pump control switch to OFF.
- 2. Close valves ND-25A(B), V-16-107 and ND-30A(B).
O E16-6 (320001B/38)
Procedure EMG-3200.01B Rev. O Attachment P Page 7 of 2 3.33 IE the Filter Aid Precoat Tank has reached the low level limit
(
THEN 1. Fill the Filter Aid Precoat Tank with condensate to a level of 80%.
- 2. Repeat Steps 3.27 through 3.32. II 3.34 Stop the Precoat Tank Agitator and Dust Evacuator. ;
3.35 NOTE During valving operations, allow sufficient time for the (Red, Green) valve indication lights to completely change over.
Inject boron in accordance with Steps 3.35.1 through 3.35.4.
3.35.1 Open ND-27A(B), Filter Inlet Valve, by placing its selector switch to the OPEN position.
3.25.2 NOTE F
When Valve ND28A(B) is placed in AUTO, if the valve does not open or if it opens and then closes, a Cleanup Filter Isolation signal was actuated while the filter was in hold, and the programmer needs to be reset. To reset programmer refer to Procedure 303, Reactor Cleanup Demineralizer System.
Open ND28A(B), Filter Outlet Valve, by placing its selector switch to the AUTO position.
3.25.3 Close V-16-83, Cleanup System Filter Bypass Valve. Allow approximately one (1) minute to ensure that the Filter Outlet Valve ND28A(B) remains open.
3.25.4 Operate the Cleanup System in this mode for five (5) minutes.
3.36 Bypass and isolate the Cleanup Filters by opening V-16-83 and closing ND27A(B) and ND28A(B).
3.37 Return to Step 3.5 as required to add additional boron. ,
l O
(320001B/39) E16-7
A.
4 Procedure EMG-3200.01B Rev. 1 Attachment O
,- Page 1 of 1 SUPPORT PROCEDURE 24 ALTERNATE BORON INJECTION WITH THE FEED AND CONDENSATE SYSTEM f
1.0 PREREOUISITES Injection of Boron via the Feed and Condensate System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION NOTE The required Boric Acid and Borax come in approximately 300 lb.
barrels and are stored in the warehouse under Stock Numbers 001-512-1800-1 (Bin 2-0068-E,J) and 001-512-2000-1 (Bin 2-Q064-E) respectively. Although only six (6) barrels each are necessary to achieve a cold shutdown Boron weight of 273 lbs. plus a 25 percent conservatism, all available barrels (normally 10 each) should be transported to the Turbine Operating Floor.
2.1 Transport all available barrels of Boric Acid and Borax from the warehouse to the Turbine Operating Floor.
) 2.2 Select a Condensate Demineralizer and tre.nsfer its resin to the Final Rinse & Storage Tank in accordance with Procedure 319, Condensate Demineralizer Resin Regeneration and Transfer System.
2.3 Confirm open Condensate Transfer Supply Valve V-11-14.
2.4 Confirm open FR & ST Bypass Valve V-2-788.
2.5 Confirm closed Resin Transfer Piping Cross-Connect Valve V-2-786 and FR & ST Inlet Valve V-2-787.
3.0 PROCEDURE When directed by the GSS/GOS, perform the following:
3.1 Addition of Borax and Boric Acid into the Cation Tank H2TX Unless otherwise noted, all valve manipulations refer to selecting and operating a valve on the J.O. Backwash MANUAL OPERATION screen.
3.1.1 On the J.O. Backwash Main Menu, select the MANUAL OPERATION function.
O (320001B/40) E17-1
Proceduro EMG-3200.01B Rev. 1 Attachment Q Page 2 of 7 t
3.1.2 Vent and drain the cation tank as follows:
3.1.2.1 Open vent valve V-2-C-4.
3.1.2.2 Open rinse outlet valve V-2-C-2.
U 3.1.3 WHEN the cation tank is vented and drained, '
THEN close rinse outlet valve V-2-C-2.
3.1.4 Confirm the HI/LO select switch on the Condensate Demineralizer Control Panel in the HI position.
3.1.5 Check closed pressure breaker valves V-2-S-7 and V-2-S-9, by observing closed (green) indicating lights.
3.1.6 Open rinse inlet valve V-2-C-8 until the tank is approximately 30%
full, then close V-2-C-8.
3.1.7 On the heater bay roof, perform the following:
3.1.7.1 Manually open pressure gauge isolation valve V-2-743 and verify that the cation tank is depressurized, then close V-2-743. ,
3.1.7.2 Confirm closed cation tank resin fill valve V-2-742.
3.1.7.3 Remove the flange above V-2-742. Insert the funnel and hook up the water hose. The funnel and hose are located l on the east wall of the Turbine Building, directly in-line with the fill valve.
1 7
I l
h l
(320001B/41) E17-2 l J
l
Proc; dure EMG-3200.01B Rsv. 1 Attachment Q Page 3 of 1 3.1.7.4 Open cation tank resin fill valve V-2-742.
NOTE )
Three drums of Borax and three drums of Boric Acid shall be added to the cation tank. The ..
time assumption for the addition of the six M drums is approximately 45 minutes.
3.1.7.5 Open Domestic Water valve V-10-562 and add three drums of Boric Acid to the cation tank. Then add three drums of Borax to the cation tank.
3.1.7.6 WHEN all six drums have been added, THEN close Domestic Water Valve V-10-562 and resin fill valve V-2-742. ,
3.1.8 IE cation tank level is not approximately 75% full, THEN open rinse inlet valve V-2-C-8 until cation tank level indicates approxiamtely 75% full, then close V-2-C-8.
3.1.9 Open air inlet valve V-2-C-3, and air mix cation tank contents for .
5-10 minutes, then close V-2-C-3.
3.1.10 Close vent valve V-2-C-4, and confirm closed vent valve V-2-C-14.
3.2 Transferring Borated Water from the Cation Tank to the Condensate Demineralizer Unit.
NOTE This instruction and subsequent valve management will apply to condensate demineralizer unit 1-1. This same procedure is typical for the remaining demineralizer units.
3.2.1 Ensure the demineralizer to be used is isolated and drained by perforJing the following:
3.2.1.1 verify the following valves are closed:
- Condensate Inlet V-2-D-11
- Condensate Outlet V-2-D-12
- Mixed Resin Inlet V-2-D-13
- Mixed Resin Outlet V-2-D-14
- Recycle Outlet V-2-D-15
- Vent V-2-D-16.
(320001B/43) E17-3
~
E!;
ProcIdura EMG-3200.01B Rsv. 1 Attachment O J Page 4 of 2 O 3.2<1.2 Drain the unit by manually performing the following:
- Confirm closed vent valve V-2-D-100.
- Open header vent valve V-2-D-99. h
- Open recycle drain valves V-2-D-3 and V-2-D-8. ,
- Slowly open demineralizer vent valve V-2-D-16 and recycle outlet valve V-2-D-15.
3.2.2 WHEN the demineralizer is drained, THEN manually close the following valves:
- recycle drains V-2-D-3 and V-2-D-8
- recycle outlet V-2-D-15 3.2.3 Prepare to transfer borated water by opening the following valves:
3.2.3.1 Manually open demineralizer resin inlet valve V-2-D-13.
3.2.3.2 Open transfer valves V-2-T-2 and V-2-T-3.
I l
(320001B/44) E17-4
Procedure EMG-3200.01B Rev. 1 ,
Attachment Q l Page 5 of 2 3.2.4 Pressurize the cation tank by opening cation tank air inlet valve V-2-C-3.
3.2.5 Open cation tank resin outlet valve V-2-C-10 and transfer the b
borated water to the demineralizer unit.
3.2.6 After all borated water has been transferred to the demineralizer, as indicated by J.O. Backwash Panel or local sightglass, close the following valves:
3.2.6.1 Cation tank air inlet V-2-C-3.
3.2.6.2 Cation tank resin outlet v-; . C-10.
3.2.6.3 Transfer valves V-2-T-2 and V-2-T-3.
3.2.6.4 Demineralizer resin inlet V-2-D-13 (manually).
, 3.2.6.5 Demineralizer vent V-2-D-16 (manually).
3.2.6.6 vent header isolation V-2-D-99 (manually).
3.3 *********************************************************************
- CAUTION
- The amount of time condensate flow is allowed to drop below *
- 2400 gpm should be minimized to ensure adequate cooling flow *
- is maintained to condensate system components.
- To prevent loss of boron, isolate the following flow paths using Steps 3.3.1 through 3.3.5.
3.3.1 Isolate the demineralizer discharge to the Condensate Storage Tank by closing the following valves located in the Condensate Transfer Building.
- V-2-42, Cond. Reject to CST Isolation Valve
- V-2-14, Cond. Reject FRV Bypass Valve
- V-2-88, Cond. Reject FRV Bypass Valve 3.3.2 Isolate the demineralizer discharge to the CRD WATER QUALITY LINE BY SHUTTING V-2-122, Flow Control Valve (V-2-124) Inlet Isolation valve, in the Condenser Bay.
l (320001B/44) E17-5 i
I
Procadure EMG-3200.01B Rev. 1 Attachment Q
- Page 6 of 2 ,
3.3.3 Isolate any reactor feedwater strings not required to maintain adequate core cooling by closing their Heater String Outlet Isolation valves (V-2-10, V-2-11, V-2-12).
3.3.4 Isolate the reactor feed pump minimum flow lines by shutting V L 230 (A), 231 (B) and 232 (C), Minimum Flow Isolation Valves, to prevent boron loss.
3.3.5 Isolate Turbine Exhaust Hood Spray by shutting V-2-83, Condenser Hood Spray Isolation Valve.
3.4 FOTE All valve manipulations in this section must be done manually, as these valves are not operated on the J.O.
Backwash MANUAL OPERATION screen.
Place the demineralizer with Borated Water in service in accordance with the following:
3.4.1 Confirm at least one feed string is lined up for injection into RPV with its Condensate Pump running, feed pump running and heater i
string outlet valve open.
3.4.2 Confirm demineralizer inlet valve is cracked open.
3.4.3 Vent the demineralizer as follows:
i
- 1. Check closed auxiliary vent valve V-2-D-100 and open header vent valve V-2-D-99.
- 2. Insure drain valve V-2-D-3, V-2-D-B and other demineralizer ,
units recycle valve are closed.
(320001D/45) E17-6 8
Proccduro EMG-3200.01B Rsv. 1 Attachment Q e Page 7 of 1 i
3.4.4 Minimize venting of Borated water from the ;
demineralizer, u
................................................**........... l CAU M *
- All air must be vented from the demineralizer before * !
- placing unit in service.
- i I
verify proper fill and venting of the demineralizer by cracking open the unit vent valve V-2-D-16 until water runs through the
^
vent sight glass.
3.4.5 Close the unit's vent valve V-2-D-16 and V-2-D-99 when the demineralizer is filled and vented. i 3.4.6 Open outlet valve V-2-D-12 to put Condensate Dcmineralizer in service.
3.5 II additional Boron is required, THEN repeat Steps 3.1 through 3.4 3.6 If directed by the GSS, return system to normal per Procedure 319.
3.7 Return to the J.O. Backwash Main Menu by pressing the BOME key.
?
t (320001B/46) E17-7
OYSTER CREEK CUCLEAR GENERATING Number t,
U M7 STATION PROCEDURE EMG-3200.02 Title
- Revision No.
Q PRIMARY CONTAINMENT CONTROL 9 Applicability / Scope Responsible Office PLANT ENGINEERING EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 2200 h This document is within OA plan scope X Yes No Effective Date Safety Reviews Required X Yes No (07/19/93) 07/29/93 '
Prior Revision B incorporated the This Revision 9 incorporates the following Temporary Changes: following Temporary Changes:
N/A N/A LIST OF srrsunvs PAGES PAGE REVISION P.TGE REVISION PAGE REVISION EAqE REVISION 1.0 9 E8-1 9 E14-6 9 E21-2 9 2.0 9 ES-2 9 E15-1 9 E21-3 9 3.0 9 E8-3 9 E15-2 9 E21-4 9 4.0 9
- E9-1 9 E15-3 9 E22-1 9 !
El-1 9 E9-2 9 E15-4 9 E22-2 9 E2-1 9 E10-1 9 E16-1 9 E22-3 9 E3-1 9 E10-2 9 E16-2 9 E22-4 9 E3-2 9 E11-1 9 E17-1 9 E23-1 9 E3-3 9 E11-2 9 E18-1 9 E23-2 9 E3-4 9 E12-1 9 E18-2 9 E24-1 9 6 E4-1 9 E12-2 9 E19-1 9' E24-2 9 ES-1 9 E13-1 9 E19-2 9 E24-3 9 ES-2 9 E13-2 9 E19-3 9 E25-1 9 E6-1 E14-1 E19-4 g 3 E6-2 9
9 E14-2 9
9 E20-1 g {S U\ 9 E7-1 E14-3 9 E7-2 9
9 E14-4 9 COMMOLLED E20, 9 DISTRIBUTION -
E14-5 $2yt NT SERIAL NUMBER 7 '2 INFO. MGMT n T Signature Concurring Organization Element Date
'/ M' '
Originator /
/. EOP COORDINATOR 'p j Concurred By 7.ef/MMM[ EOP COMMITTEE M P/[J g g(M' PLANT ENGINEERING DIRECTOR -// k') '5 kM)[#k MGR, PLANT OPERATIONS 7h 33
/ 4 0
0 Approved By (320002) hN(M i
VICE PRESIDENT te DIRECTOR, OC 9 d.h3 l
1.O l
l OYSTER CREEK NUCLEAR GENERATING Number 'I
.. hglM7 STATION PROCEDURE EMG-3200.02 l
e' Title Revision No.
'O PRIMARY CONTAINAENT CONTROL 9 I
i 1.0 EURPOSU The purpose of the Primary Containment Control Procedure is to:
- Protect equipment in the Primary Containment
- Maintain Primary Containment integrity l
2.0 REFERENCES
2.1 Procedures
- 107.4, EOP Program Control
- 310
- 312 2.2 Drawings
- BR 2006, Flow Diagram Closed Cooling Water System
- BR 2011, Shts 1 & 2, Flow Diagram - H&V Reactor Bldg
- BR 3017, 460 VAC MCC Elem Diagram Sht 4
- GE 112C2654, Sht 3, Panel 2R Connection Diagram
- GE 157B6350, Shts 117 & 118, RBCCW Valve Elem Diagram
- GE 237E566, Shts la, Ib, 2 & 6, Rx Protection System Elem Diagram
- GE 706E841, Vent & Effluent Rad Monitor Elem Diagram
- GU 3D-822-17-2002, Elem Diagram - Standby Gas Treatment System
- GU 3D-822-21-1000, Flow Diagram - Standby Gas Treatment System
- NU 506036003, Shts 1 - 3, Core Spray /RBCCW Drywell Isolation Elem Diagram
- SN 13432.19-1, Flow Diagram - N2 Purge and Makeup Sys
- SN 15361.03-EC-23, Area Rad Monitoring Elem Diagram O
(320002) 2.0
OYSTER CREEK NUCLEAR GENERATING Number Nrder STATION PROCEDURE EMG-3200.02 l Title Revision No.
9 s
PRIMARY CONTAINMENT CONTROL 2.3 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.4 2000-STD-1218.04, EOP Writer's Guide 3.0 PRECAUTIONS AND LIMITATIOUE .;
3.1 This procedure gives guidance to the operator for bypassing isolation signals and automatic scrams which is a departure from the Oyster j i
Creek Technical Specifications. It is permissible to take actions which depart from the plant's Technical Specifications during emergency conditions as authorized by 10 CFR 50.54 (x).
4.0 ATTACHMETTS, I 4.1 Attachment A - Primary Containment Control EOP Flowchart DWG: GU 3E-200-08-010 sh 1 Attachment B - Support Procedure 25, Initiation of the 0 4.2 Containment Spray System in the Torus Cooling Mode ,
4.3 Atischment C - Support Procedure 26, Determining Bulk Drywell Temperature I
4.4 Attachment D - Support Procedure 27, Maximizing Drywell Cooling l 4.5 Attachment E - Support Procedure 28, Level Instrumentation Availability 4.6 Attachment F - Support Procedure 29, Initiation of the Containment Spray System for Drywell Sprays 4.7 Attachment G - Support Procedure 30, Confirmation of Primary Containment Isolation 4.8 Attachment H - Support Procedure 31, Venting Primary Containment to maintain Pressure Below 3.0 psig 4.9 Attachment I - Support Procedure 32, Venting the Torus for Primary Containment High Pressure (320002) 3.0
d 1
~
OYSTER CREEK NUCLEAR GENERATING Number
{ M7 STATION PROCEDURE DdG.3200.02 t
Title Revision No.
O raininv cour^1xuzur couraot >
4.10 Attachment J - Support Procedure 33, Venting the Drywell for o Primary Containment High Pressure 4.11 Attachment K - Support Procedure 34, Venting the Drywell through the Purge System for Primary Containment High Pressure 4.12 Attachment L - Support Procedure 35, Venting the Torus Through the ,
Hardened Vent 4.13 Attachment M - Support Procedure 36, Venting the Drywell Through the Hardened Vent 4.14 Attachment N - Support Procedure 37, Makeup to the Torus via Core Spray System 4.15 Attachment 0 - Support Procedure 38, Determining Primary Containment Water Level 4.16 Attachment P - Support Procedure 39, Placing the H 2 /02 Monitoring System In Service .
O 4.17 Attachment 0 - Support Procedure 40, Isolation of the Primary Containment Vent and Purge Valves ,
i 4.18 Attachment R - Support Procedure 41, Venting the Torus for ,
Hydrogen Control 4.19 Attachment S - Support Procedure 42, Purging the Drywell for Hydrogen Control ,
1 Attachment T - Cupport Procedure 43, Venting the Drywell for l 4.20 Hydrogen Control (Level Below 461 in) ,
4.21 Attachment U - Support Procedure 44, Venting the Drywell through >
the Rx Building Supply Tans for Hydrogen Control (Level Above 461 in) ,
4.22 Attachment V - Support Procedure 45, Purging the Torus for Hydrogen Control i
4.23 Attachment W - Support Procedure 46, Venting the Torus for Hydrogen Control 4.24 Attachment X - Support Procedure 47, Venting the Drywell for Hydrogen Control (Level Below 461 in) 4.25 Attachment Y - Support Procedure 48, Venting the Drywell for Hydrogen Control (320002) 4.0
T, OYSTER CREEK NUCLEAR GENERATING Number NucImr STATION PROCEDURE EMG-3200.02 Title Revision No.
O raininv cour^1xuzsr courno' -
ATTACHMEfff A g Attachment A to EMG-3200.02, Primary Containment Control, is the Primary Containment Control EOP Flowchart, _
DWG: GU 3E-200-08-010 Sht 1, Rev. 1 4
0 O - m> el-1
Procedure EMG-3200.02 R:v. 9 Attachment B Page 1 of 1 SUPPORT PROCEDURE 25 INITIATION OF THE CONTAINMENT SPRAY SYSTEM IN THE TORUS COOLING MODE 1.0 PREREOUISITES Initiation of the Containment Spray System in the Torus Cooling Mode -
has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 *********************************************************************
- CAUTION *
- Diesel Generator overload will result if a Containment Spray Pump *
- and ESW pump are started with a Diesel Generator load of greater *
- than 2160 KW.
- IE Bus 1C or ID are being supplied by an Emergency Diesel Generator, THEN verify that adequate load margin is available so as NQI to exceed EDG load limit when starting Containment Spray and ESW Pumps.
3.2 Start a Containment Spray Pump as follows:
3.2.1 Select the Containment Spray System to be used by confirming either SYSTEM 1 MODE SELECT or SYSTEM 2 MODE SELECT switch in TORUS CLG position.
3.2.2 Select a Containment Spray Pump to be started.
3.2.3 Place and hold the System Pump Start Permissive Keylock for the selected pump in the appropriate position (Panel 1F/2F).
3.2.4 Start the selected Containment Spray Pump using its control switch (Panel IF/2F).
3.3 Start an associated ESW Pump using its control switch (Panel IF/2F).
3.4 Monitor system parameters for expected performance.
3.5 Start additional Containment Spray and ESW Pumps as directed by the GSS/GOS in accordance with Steps 3.1 thru 3.4.
(320002/6) E2-1
+
Procsdure EMG-3200.02 Rsv. 9 Attachment C Page 1 of i SUPPORT PROCEDURE 26 pfJERMINING BULK DRYWELL TEMPERATURE 1.0 PREREOUISITES i.
Determination of Bulk Drywell Temperature has been directed by the Emergency Operating Procedures.
2.0 PREPARATIONS None 3.0 PROCEDURE R computer point DWTEMP is unavailable or questionable ("Q" for point '
health),
THEN determine drywell bulk temperature by using the appropriate calculation and the following recorders:
- Recorder IA55 (Panel BR)
- Recorder TR-100A (RB 51' Elev.)
3.1 Complete Calculation on Attachment DWT-1.1.
3.2 Calculate Bulk Drywell Temperature (TB) using values from Attachment DWT-1.1.
TB = 0.503 + 0.382 +
(T Avg IA) (T Avg IB) 0.076 + 0.039 (T Avg II) (T Avg III)
TB =
3.2.1 H temperature recorder IA55 is not available, THEN calculate bulk drywell temperature using the following equation:
TB = 0.885 + 0.076 (T Avg IB) (T Avg II)
+ 0.039 ,
(T Avg III) i O (320002/7) E3-1 1
f
_ i Procedure EMG-3200.02 Rav. 9 Attachment C i Page 2 of 4 l
NOTE ;
Thermocouple readings 2 395'F must be read using Plant !
Computer Points or by an instrument technician using instrumentation for Type T thermocouples.
3.2.2 II any T/C 105 indicates 2395'F, THEN check T/C 107 reading for confirmation of high temperature conditions.
3.2.3 II two out of three T/C 105's indicate 315*F < T > 325'F, THEN evaluate drywell cooling using Procedure OPS-3024.09, Drywell Cooling System - Diagnostic and Restoration Actions.
3.2.4 II two out of three T/C 105's indicate T 2 325'F, THEN initiate a plant shutdown in accordance with Procedure 203.1, Plant Shutdown to Hot Standby.
3.3 II bulk drywell temperature cannot be determined using the plant computer, 8HE an operator is not i= mediately available to monitor Drywell
) temperature at 51' elev. QE Temperature Recorder TR-100A is ,
not available, ,
THEN determine bulk drywell temperature by averaging the inlet temperatures of the operating Drywell Recire. Fans. (Points 11, 12, 13, 14, and 15 from recorder IA55 on Panel BR). ,
3.3.1 IE less than three Drywell Recirc Fans are running, IHKH calculate bulk drywell temperature by averaging the temperatures of the GEMAC narrow and wide range reference legs (Points 40, 41, and 42 from recorder IA55 on Panel BR).
(320002/8) E3-2 f
Procsdure EMG-3200.02 Rev. 9 Attachment C Page 3 of 1 ATTACEMENT DWT-1.1 Temperature readings from the following thermocouples can be obtained locally from the recorder or from the plant computer by identified ID points. L NOTE ,
Thermocouple readings >395'F must be read using Plant Computer _ Points or by an instrument technician using instrumentation for Type T thermocouples.
- 1. IF one thermocouple reading is not available (i.e. downscale or upscale)
THEN remove it from the T Avg calculation and decrease the denominator by one number.
- 2. Calculate T Avg IA by completing the following: ,
From Recorder IA55 (Panel 8R) or the Plant Computer, record the following data:
Recorder Point COMP ID PT Value (*F)
PT.35 = TE-100A,El. 33' Recirc Pump Motor Inlet Air "A" 'TE100A' 3
PT.36 = TE-100B,E1. 33' Recirc Pump Motor Inlet Air *B* 'TE100B'
+
PT.37 = TE-100C,El. 33' Recirc Pump Motor Inlet Air "C" 'TE100C'
=
=
TE-100D,El.
TE-100E,El.
33' 33' Recirc Recirc Pump Pump Motor Motor Inlet Inlet Air Air
- D"
- E'
'TE100D'
'TE100E' Calculate T Avg IA T Avg IA = PT.35 + PT.36 + PT.37 + PT.38 + PT.39 5 *F
- 3. Calculate T Avg IB by completing the following:
b
- From Recorder TR-100A (RB 51' Elev.) or the Plant Computer, record the following data:
Recorder Point COMP ID PT Value (*F)
PT.1 = TE-103A,El. 50' Safety Valve Area 'TE103A' PT.2 = TE-103B,El. 50' Safety Valve Area 'TE103B' PT.3 = TE-103C,El. 50' Safety Valve Area 'TE103C' 1 PT.4 = TE-103D,El. 50' Safety Valve Area 'TE103D' PT.5 = TE-103E,El. 50'. Safety valve Area 'TE103E' Calculate T Avg IB
! T Avg IB = PT.1 + PT.2 + PT.3 + PT.4 + PT.5
- g 5 *F 4
(320002/9) E3-3 l
I l
1 l
1
, Procedure EMG-3200.02 Rev. 9 l Attachment C
.~ Page 4 of 4
- 4. Calculate T Avt II by completing the following:
From Recorder TR-100A (RB 51' Elev.) or the Plant Computer, record the following data:
5 Pecorder Point COMP ID PT Value f*F)
PT.6 = TE-104A,El. 93' Rx Vessel Bellows Seal Area 'TE104A' PT.7 = TE-104B,El. 93' Rx Vessel Bellows Seal Area 'TE104B' PT.8 = TE-104C,El. 93' Rx Vessel Bellows Seal Area 'TE104C' PT.9 = TE-104D,El. 938 Rx Vessel Bellows Seal Area 'TE104D' PT.10 = TE-104E,El. 93* Rx Vessel Bellows Seal Area 'TE104E' Calculate T Avg II T Avg II = PT.6 + PT.7 + PT.8 + PT.9 + PT.10
=
5 *F
- 5. Calculate T Avg III by completing the following: ,
From Recorder TR-100A (RB 51' Elev.) or the Plant Computer, record the following data:
Recorder Point COMP ID PT Value f*F)
PT.11 = TE-105A,El. 95' Rx Head Flange Area 'TE105A' PT.12 = TE-105B,El. 95' Rx Head Flange Area 'TE105B' .
'TE105C' PT.13 = TE-105C,El. 95' Rx Head Flange Area Calculate T Avg III T Avg III = PT.11 + PT.12 + PT.13__
3 *F f
4 (320002/10) E3-4 l
I ... -, - - . . . . -,. , -
Procrdure EMG-3200.02 Rpv. 9 Attachment D Page 1 of 1
( SUPPORT PROCEDURE 27 MAXIMIZING DRYWELL COOLING 1.0 PREREOUISITES L The operation of all available drywell coolers has been directed by the Emergency Operating Procedures. -
2.0 PREPARATION 2.1 FOTC After completing the following steps, valves V-5-147, v-5-166 and V-5-167 will only operate from the Control Room. All automatic operation is removed.
In the rear of Panel 2R, open the EOP BYPASS PLUGS panel.
2.1.1 Remove the bypass plug from position BPl.
2.1.2 Remove the bypass plug from position BP2.
3.0 PROCEDURE 3.1 Confirm open RBCCW Isolation Valves (Panel IF/2F)
- V-5-147
- V-5-166
- V-5-167
- V-5-148 3.2 Start all available DW RECIRC FANS by placing their respective control switches in ON (Panel 11R).
3.3 Place the ISOL SIGNAL BYPASS V-6-395 switch in BYPASS position (Panel 11F). i 3.4 *****************************************************************
- CAUTION *
- A rapid decrease in Drywell temperature could cause a cor-
- responding drop in Drywell Pressure and possible deinertion.
- Operate DW RECIRC FANS (Panel 11R) as required to control Drywell temperature.
O (320002/11) E4-1
Proctdure EMG-3200.02 Rav. 9 Attachment E Page 1 of 2 SUPPORT PROCEDURE 28 LEVEL INSTRUMENTATION AVAILABILITY t
1.0 PREREOUISITES The evaluation of RPV Water Level Instruments has been directed by the Emergency Operating Procedures.
2O PREPARATION None 3.0 PROCEDURE An RPV water level instrument may be used to determine RPV water level only when all the following conditions are satisfied for that instrument.
3.1 Verify that the temperatures of the following instrument reference leg vertical runs as read on recorder TR-IA55 on Panel BR are below RPV saturation temperature.
Level Instrument Temo Instrument No. Recorder Poini Temperature NR GEMAC A (LT-1D13A) TE-130-450 40 NR GEMAC B (LT-1D13B) TE-130-451 41 WR GEMAC (LT-1A12) TE-130-452 42 YARWAY A (LT-RE05/19A) TE-130-453 43 YARWAY B (LT-RE05/19B) TE-130-454 44 i
1 i
1 O
(320002/12) ES-1
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+ (-i -3, .
- f Procrduro EMC-3200.02
, g3y, 9
,a. ;[1 3$A ${b Y) h ^^- Attachment E
.,. ; Page 2 of 2.
s F5 ..
/ 3 k i /
g .
r o
W 450 f
e f
9~
. .. g t .
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E '
i s / ;
E 350 f m f E ._l l
' f I 300 - -
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2 t' ! I j i 2 ! ! 1 !
7 250 - , g I
1 l l j i i
! I i i i 200 0 100 200 300 400 500 600 700 800 900 1000 1100 RPV PRESSURE tps g)
RPY Saturouon Temperature 3.2 For each instrument below, the instrument reads above the minimum indicated level or the reference leg temperature is below the maximum run temperature.
GEMAC NARROW RANGE Indicated level above 104 in.
(90 - 180 in.)
M Ref. leg temperature below 420*F YARWAY Indicated level above 100 in.
(85 - 185 in.)
E Ref. leg temperature below 460*F GEMAC WIDE RANGE Indicated level is greater than the (70 - 430 in.) value listed for the reference leg temperature.
Ref Leo Temo. Indicated Level 1
40 - 150*F Above 85 in. 1 150 - 250*F Above 100 in. 1 250 - 350*F Above 120 in.
350 - 450*F Above 145 in.
450 - 550*F Above 175 in. ;
1 (320002/13) ES-2 1
l I
- J Proc durs EMG-.3200.02 Rpv. 9 Attachment F
- 4 Page 1 of 1
$ SUPPORT PROCEDURE 29 INITIATION OF THE CONTAINMENT SPRAY SYSTEM TOR DRYWELL SPRAYS 1.0 PREREQUISITES Manual initiation of Drywell Sprays has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 Select the Containment Spray System to be used by confirming either SYSTEM 1 MODE SELECT or SYSTEM 2 MODE SELECT switch in DW SPRAY position (Panel IF/2F).
2.2 Verify that the system TORUS CLG DISCHARGE valve closes and DW SPRAY DISCHARGE valve opens (Panel IF/2F).
3.0 PROCEDURE 3.1 ************************************************************
- CAUTION *
- Diesel Generator overload will result if a Containment *
- Spray pump and ESW pump are started with a Diesel *
- Generator load of greater than 2160 KW.
- c-)
IE Bus IC or ID are being supplied by an Emergency Diesel Generator, THEN verify that adequate load margin is available so as EQI to exceed EDG load limit when starting Containment Spray and ESW pumps.
3.2 WHEN directed to initiate Drywell sprays, THEN complete the following:
- 1. Confirm'the Reactor Recirculation Pumps tripped (Panel 3F).
- 2. Confirm the Drywell Recirc Fans tripped (Panel 11R).
3.3 Start a Containment Spray Pump as follows:
3.3.1 Select a Containment Spray Pump to be started.
3.3.2 Place and hold the System Pump Start Permissive Keylock for the selected pump in the appropriate position (Panel IF/2F).
3.3.3 Start the selected Containment Spray Pump using its control switch (Panel IF/2F).
(Oj (320002/14) E6-1
Proc: dura EMG-3200.02 Ruv. 9 Attachment F Page 2 of 1 0 3.4 Start an associated ESW Pump using its control switch (Panel 1F/2F).
3.5 Monitor System parameters for expected performance.
V.
3.6 ************************************************************
- CAUTION *
- Diesel generator overload will result if a containment *
- spray pump and ESW pump are started with a diesel *
- generator load of greater than 2160 KW.
- Start additional Containment Spray and ESW Pumps in accordance with Steps 3.3, through 3.5 as directed by the GSS/GOS.
3.7 WHEN Torus QE Drywell pressure drops below 1 psig, THEN confirm termination of drywell sprays.
3.8 IE Containment Spray Pumps fail to trip, IHEN place the respective system MODE SELECT switch in TORUS CLG position.
i l
l g
(320002/15) E6-2
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Procsdure EMG-3200.02 Rpv. 9 Attachment G
" Page 1 of 2 O SUPPORT PROCEDURE 30 CONFIRMATION OF PRIMARY CONTAINMENT ISOLATION j 6'
1.0 PREREOUISITES Confirmation of Primary Containment isolation has been directed by the Emergency i
Operating Procedures.
l 2.0 PREPARATION l l
l None i I
3.0 PROCEDURE 3.1 Confina closed the following valves that are not required to be open by the Emergency Operating Procedures:
System' Valve No.
DW Vent / Purge V-27-1 (Panel 11F)
V-27-2 V-27-3 V-27-4 Torus Vent V-28-17 (Panel 11F)
V-28-18 Torus 2" Vent Bypass V-28-47 (Panel 11F)
DWEDT V-22-1 (Panel 11F) __
V-22-2 DW Floor Sump V-22-28 (Panel 11F)
V-22-29 Torus /Rx Bldg. V-26-16 (Panel llF)
Vacuum Breakers V-26-18 TIP Valves Common Ind. (Panel 11F)
(320002/16) E7-1
y Proerdure EMG-3200.02 Rev. 9 Attachment G Page 2 of 2 I
i I
DW 2" Vent Bypass V-23-21 (Panel 12XR) {
l V-23-22 i N2 Purge V-23-13 (Panel 12XR) h V-23-14 "
V-23-15 V-23-16 N2 Makeup V-23-17 (Panel 12XR)
V-23-18 V-23-19 V-23-20 O .
O (320002/17) E7-2
Procrdure EMG-3200.02 R@v 9 Attachment H Page 1 of J.
SUPPORT PROCEDURE 31 VENTING TIIE PRIMARY CONTAINMENT TO MAINTAIN PRESSURE BEIAW 3.0 PSIG i-1.0 PREREOUISITES Venting of the Primary Containment has been directed by the Emergency Operating Procedures.
2.0 PREPARATION Nor; 3.0 PROCEDURE 3.1 R the GSS/GOS directs usage of SGTS for venting, THEN perform the following:
- 1. Select a SGTS Train for operation by placing the STANDBY GAS SELECT switch in position SYSTEM 1 or SYSTEM 2.
- 2. Place the fan control switch Jr the train selected in the HAND position.
O- 3. Close the SGTS CROSSTIE V-28-48 (Panel 11R)
- 4. Secure operating Reactor Building Supply Fans by placing the respective control switches in OFF position (Panel 11R).
- 5. Immediately secure Exhaust Fan EF 1-5 (or EF 1-6) by placing control switch in STOP position (Panel 11R).
- 6. Close V-28-21 and V-28-22 by placing the EXH VALVES TO MAIN EXHAUST control switch in CLOSE position.
- 7. Close V-28-42 and V-28-43 by placing the MAIN SUPPLY HEADER VALVES TO DW control switch in CLOSE position.
- 8. Open Torus Vent valve V-28-18 (Panel 117).
- 9. Cycle V-28-47 to maintain Drywell pressure ;
below 3.0 psig (Panel 11F).
(320002/18) E8-1 O .
T
Procaduro EMG-3200.02 Rsv. 9 Attachment H
_- Page 2 of a
- 10. II the Torus cannot be vented, THEN perform the following:
- a. Inform the GSS/GOS.
- b. Open the Drywell vent valve V-23-21 u
(Panel 12XR).
- c. Cycle Drywell vent valve and V-23-22 (Panel 12XR) to maintain Drywell pressure below 3.0 psig.
- 11. WHEN the primary containment is being vented through SGTS, __
THEN perform the following:
- a. Notify Chemistry that Rx Bldg. ventilation has been secured so that they can shift the stack RAGEMS DEFAULT SYSTEM CONTROL switch to DEFEAT.
- b. Confirm that the final SGTS lineup has the F
preferred system in operation, and V-28-48, SGTS CROSSTIE DAMPER is closed.
- c. Confirm running Turbine Building Exhaust Fan EF 1-7 or one Radwaste Bldg. Exhaust fan, EF 1-16 or EF 1-17, to maintain a minimum stack flowrate/ exit velocity of 50 fpm. .
3.2 IE the GSS/GOS directs usage of Rx. Bldg. ventilation for venting, _
f THEN perform the following:
- 1. Open Torus vent valve V-28-18 (Panel 11F). l
- 2. Cycle Torus Vent valve V-28-47 (Panel 11F) to maintain Drywell pressure below 3.0 psig. ,
D (320002/19) E8-2 I
Proc:duro EMG-3200.02 Rsv. 9 Attachment H Page 3 of 1
- 3. II the Torus cannot be vented, THEN perform the following:
- a. Inform the GSS/GOS.
- b. Open the Drywell vent valve V-23-21 (Panel 12KR).
- c. Cycle Drywell vent valve and V-23-22 (Panel 12XR) to maintain Drywell pressure below 3.0 psig.
O 6
(320002/20) E8-3
y Procedure EMG-3200.02 R3v. 9 '
Attcchment I Page 1 of 2 SUPPORT PROCEDURE 32 l VENTING THE TORUS FOR PRIMARY CONTAINMENT HIGH PRESSURE j l
1.0 PREREQUISITES '
i Torus venting has been directed by the Emergency Operating Procedures.
2.0 PREPARATION ,
Perform the following steps in preparation for venting the Torus via the Reactor Building ventilation system.
2.1 verify Torus water level is below 348 in.
2.2 Evacuate personnel from the Reactor Building.
2.2.1 Sound the Reactor Building Evacuation Alarm /
Time Date '
2.2.2 Make the announcement " Primary Containment Ventina will commence in accroximately 5 minutes. All !
L nersonnel evacuate the Reactor Buildina immediatelv".
2.3 Select a SGTS Train for operation and place its fan control switch in HAND (Panel 11R).
2.4 Place the control switch for V-28-48, SGTS CROSSTIE, in CLOSED (Panel 11R).
2.5 Confirm Reactor Building Supply Fans secured (Panel llR).
2.6 Confirm Reactor Building Exhaust Fan secured (Panel 11R).
2.7 Confirm that the Reactor Mode Selector Switch is E22 in f the RUN position.
2.8 Obtain one (1) bypass plug from the EOP Tool Box in the I Control Room, c
2.9 **********************************************************
- CAUTION * ,
- The containment isolation function of the following *
- valves is bypassed when the High Drywell Pressure *
- and Reactor Low-Low Water Level isolation signals *
- are defeated: ,
- Drywell Nitrogen Makeup Valves (V-23-17 and V-23-18) *
- Torus Nitrogen Makeup Valves (V-23-19 and V-23-20
- Open the EOP BYPASS PLUGS panel in the rear of Panel 10XF. ,
2.9.1 Insert a bypass plug in position BPS.
2.10 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
4 2.10.1 Remove the bypass plug in position BP4.
2.10.2 Insert a bypass plug in position BPl.
(320002/21) E9-1
I Proctduro EMG-3200.02 l R v. 9
- Attechment I j
,- Page 2 of 2 l 2.11 Place the TORUS /DRYWELL ISOLATION VALVE BYPASS PERMISSIVE j keylock switch in the TORUS position (Panel 11F).
2.12 Place the TORUS /DW VENT AND PURGE ISOL VLVS HI l RAD BYP keylock switches for both Channels 1 & 2 !
i in the BYPASS position (Panel 11F).
2.13 Inform GSS/GOS that the Torus is ready to be vented ,
via the Torus Vent valves. ,
3.0 PROCEDURE !
When directed by the GOS/GSS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 11R).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves V-28-21 and V-28-22 (Panel 11R) .
3.3 WHEN at least five minutes has passed since sounding the Reactor Building evacuation alarm, THEN inform the GSS/GOS and start Reactor p
Building Exhaust Fan 1-5.
3.4 Open Torus Vent valves V-28-18 and V-28-47 (Panel 11F).
3.5 Inform the GSS/GOS that Torus venting via V-28-18 and V-28-47 has commenced. >
+
3.6 Control Torus pressure as directed by the GSS/GOS by cycling the Torus vent valves as required.
3.7 ************************************************************* '
- CAUTION *
- Ventilation ductwork failure can occur when venting *
- through V-28-17 with torus pressure greater than 2 psig.
- WHEN direct'ed by the GSS/GOS, THEN open torus vent valve V-28-17 (Panel 11F).
3.8 Control Torus pressure as directed by the GSS/GOS by ;
cycling Torus vent valves as required. ,
(320002/22) E9-2 ;
t
q.
l Procrdure EMG-3200.02 ,
Rav. 9 l Attachment J l Page 1 of 2 l SUPPORT PROCEDURE 33 I
VENTING THE DRYWELL FOR PRIMARY CONTAINMENT HIGH PRESSURE l 1.0 PREREOUISITES 6 Drywell venting has been directed by the Emergency Operating Procedures.
2.0 PREPARATION Perform the following steps in preparation for venting the Drywell via the Reactor Building ventilation system.
2.1 Verify Primary Containment water level is below 461 in.
2.2 Evacuate personnel from the Reactor Building.
2.2.1 Sound the Reactor Building Evacuation Alarm. /
Time Date 2.2.2 Make the announcement " Primary Containment Ventina will commence in aporoximately five minutes. All
' personnel evacuate the Reactor Buildino inmediatelv".
2.3 Select a SGTS Train foi operation and place its fan control switch in KAND (Panel 11R).
2.4 Place the control switch for V-28-48, SGTS CROSSTIE, i
in CLOSED (Panel 11R).
2.5 Confirm Reactor Building Supply Fans secured (Panel 11R).
2.6 Confirm Reactor Building Exhaust Fan secured (Panel 11R).
2.7 Confirm that the Reactor Mode Selector is HQI in the RUN position.
2.8 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
2.8.1 Remove the bypass plug in position BP4.
2.8.2 Insert the bypass plug in position BPl.
4 O (320002/23) E10-1
Proc 2 dura EMG-3200.02 Rpv. 9 Attachment J Page 2 of 1 0 2.9 Place the TORUS /DRYWELL ISOLATION VALVE BYPASS PERMISSIVE keylock switch in the DRYWELL position (Panel 11F).
U 2.10 Inform the GSS/GOS that the Drywell is ready to be vented via the Drywell 2 inch vent valves.
3.0 PROCEDURE When directed by the GSS/GOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 11R;. j 3.2 Confirm open Reactor Building Main Exhaust Isolation valves, V-28-21 and V-28-22 (Panel 11R). !
3.3 WHEN at least five minutes has passed since sounding the Reactor Building evacuation alarm, THEN inform the GSS/GOS and start Reactor Building Exhaust Fan 1-5.
3.4 Open Drywell vent valves V-23-21 and V-23-22 (Panel 12KR).
3.5 Control Drywell pressure as directed by the GSS/GOS by cycling V-23-21 or V-23-22. ,
h a
I t
6 a i
(320002/24) E10-2 l 1
Prsesduro EMG-3200.02 Rsv. 9 Attachment K
- Page 1 of 1 SUPPORT PROCEDURE 34
(~ VENTING THE DRYWELL THROUGH THE PURGE SYSTEM FOR PRIMARY CONTAINMENT HIGH PRESSURE 1.0 PREREOUISITES Drywell venting through the Purge System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION Perform the following steps in preparation for venting the Drywell via the Drywell Purge System and Reactor Building Ventilation System.
2.1 Evacuate personnel from the Reactor Building.
2.1.1 Sound the Reactor Building Evacuation Alarm. /
Time Date 2.1.2 Make the announcement " Primary Containment Ventina will commence in approximately five minutes. All personnel evacuate the Reactor Buildino immediatelv".
2.2 Select a SGTS Train for operation and place its fan in HAND (Pnl 11R) 2.3 Place Control switch for V-28-48, SGTS CROSSTIE, to the CLOSED position (Panel 11R).
2.4 Confirm Reactor Building Supply Fans are secured (Panel 11R).
2.5 Confirm Reactor Building Exhaust Fan secured (Panel 11R).
2.6 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
2.6.1 Remove the bypass plug from position BP4.
2.6.2 Insert the bypass plug into position BPl.
2.7 *************************************************************
- CAUTION
- The containment isolation function of the following * *
- valves is bypassed when the CNTMT VENT AND PURGE
- ISOLATION BYPASS Keylock is in the BYPASS position: *
- Drywell Ventilation Isolation valves (V-27-1,2,3 and 4).*
- Drywell Nitrogen Purge Inlet Valves (V-23-13 & V-23-14).* !
- Torus Nitrogen Purge Inlet Valves (V-23-15 & V-23-16).
- i Place the CNTMT VENT AND PURGE ISOLATION BYPASS Keylock in BYPASS (Panel 12XR).
. (320002/25) E11-1 r
m Procedura EMG-3200.02 Rav. 9 Attachment K Page 2 of 1 2.8 Place the TORUS /DW VENT AND PURGE VLVS ISOL
( HI RAD BYPASS Keylock switches for both channels 1 and 2 in the BYPASS position (Panel 11F).
2.9 Confirm that the Torus to Reactor Building Vacuum Breaker (Absorp Cham Vac Rel V-26-16 and 18) control switch is in CLOSE position (Panel 11F).
2.10 Inform the GSS/GOS that the Drywell is ready to be vented via the Drywell Purge valves.
3.0 PROCEDURE When directed by the GSS/GOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 11R).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves V-28-21 and V-28-22 (Panel 11R).
() 3.3 WHEN at least five minutes has passed since sounding the Reactor Building evacuation alarn, ,
THEN Inform the GSS/GOS and start Reactor Building Exhaust Fan 1-5 (Panel 11R).
3.4 Confirm closed Drywell Air Supply Valves V-28-42 and V-28-43 (Panel 11R).
3.5 ******************************************************************
- CAUTION *
- Ventilation ductwork failure WILL occur when venting through *
- V-27-3 and V-27-4 with Drywell pressure greater than 2 psig
- Open Drywell Purge Valve V-27-3 and V-27-4 (Panel 11F).
3.6 Control Drywell pressure as directed by the GSS/GOS, by cycling i
V-27-3 as required.
O E11-2 (320002/26)
Procrdure EMG-3200.02 Rpv. 9 Attachment L Page 1 of 2 ,
(- SUPPORT PROCEDURE 35 VENTING THE TORUS THROUGH THE HARDENED VENT i,
1.0 PREREOUISITES Torus venting through the hardened vent has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 This procedure requires the use of an MB-1 key.
2.2 Verify Torus level is less than 348 in.
2.3 Verify Primary Containment H2 concentration is below 1.5%.
2.4 Verify CNTMT HI RANGE RAD HONITOR Channels 1 and 2 are reading below 2 x 104 R/HR (Panel 2R).
2.5 Confirm at least one exhaust fan; 1-5, 1-6, or 1-7 (Panel llR) is running.
2.6 Confirm N2 Purge isolation valve V-23-195 closed (Outside Rx. Bldg., NE Corner).
2.7 Unlock and close N2 Purge inlet valve V-23-357 (Outside Rx. Bldg. NE Corner) 2.8 Unlock and open the hardened vent stack isolation valve V-23-358 (Outside Rx. Bldg., NE Corner) 1 2.9 Inform the GSS/GOS that the Torus is ready to be vented through the hardened vent.
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4 Procsdure EMG-3200.02 Rpv. 9 Attachment M T Page 2 of 1 3.0 PROCEDURE When directed by the GSS/GOS, complete the following:
3.1 Make the following announcement: " PRIMARY CONTAINMENT VENTING IS ABOUT TO COMMENCE. ALL PERSONNEL ARE ADVISED TO STAND CLEAR OF THE b RX. BLDG. FAN PAD. THE STACK AND THE RCA YARD. NORTH AND EAST OF THE
. RX. BLDG."
3.2 *******************************************************************
CAUTION *
- The containment isolation function of the following valves is *
- bypassed when the CNTMT VENT AND PURGE ISOLATION BYPASS *
- keylock is in the BYPASS position: *
- Drywell ventilation Isolation valves (V-27-1, 2, 3, and 4). *
- Drywell Nitrogen Purge Inlet Valves (V-23-13 & V-23-14). *
- Torus Nitrogen Purge Inlet Valves (V-23-15 & V-23-16).
- Place the CNTMT VENT AND PURGE ISOLATION BYPASS keylock in BYPASS (Panel 12XR).
3.3 Open Torus nitrogen purge inlet valves V-23-15 and V-23-16
, (Panel 12XR).
3.4 Inform the.GSS/GOS that Torus venting has begun.
3.5 Control Torus pressure as directed by cycling V-23-16 (Panel 12KR).
(320002/28) E12-2 1
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Proc; dure EMG-3200.02 R,sv. 9 Attachment M Page 1 of 2 O ' SUPPORT PROCEDURE 36 VENTING THE DRYWELL THROUGH THE HARDENED VENT 1.0 PREREOUISITES t Drywell venting through the hardened vent has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 This procedure requires the use of an MD-1 key.
2.2 Verify Primary Containment H2 concentration is below 1.5%
2.3 Verify CNTMT HI RANGE RAD MONITOR Channels 1 and 2 are reading below 2 x 104 R/HR (Panel 2R).
2.4 Confirm at least one exhaust fan; 1-5, 1-6, or 1-7 (Panel 11R) is running.
2.5 Confirm N2 Purge isolation valve V-23-195 closed (Outside Rx. Bldg. NE Corner).
2.6 Unlock and close N2 Purge inlet valve V-23-357 (Outside Rx. Bldg, NE Corner) 2.7 Unlock and open the hardened vent stack isolation valve V-23-358 (Outside Rx. Bldg., NE Corner) 2.8 Inform the GSS/GOS that the Drywell is ready to be vented through the hardened vent.
(320002/29) E13-1 i
Proctdure EMG-3200.02 Rev. 9 Attachment M Page 2 of 2 3.0 PROCEDURE when directed by the GSS/GOS, complete the following:
3.1 Make the following announcement: " PRIMARY CONTAINHENT VENTING IS ABOUT TO COMMENCE. ALL PERSONNEL ARE ADVISED TO STAND CLE8.R OF THE EX. BLDG. FAN PAD, THE STACK AND THE RCA YARD. NORTH AND EAST OF THE EK. BLDG."
3.2 *******************************************************************
- CAUTION *
- The containment isolation function of the following valves is *
- bypassed when the CNTMT VENT AND PURGE ISOLATION BYPASS *
- keylock is in the BYPASS position: *
- Drywell Ventilation Isolation Valves (V-27-1, 2, 3, and 4). *
- Drywell Nitrogen Purge Inlet Valves (V-23-13 & V-23-14). *
- Torus Nitrogen Purge Inlet Valves (V-23-15 & V-23-16).
- Place the CNTMT VENT AND PURGE ISOLATION BYPASS keylock in BYPASS (Panel 12XR).
3.3 open Drywell nitrogen purge inlet valves V-23-13 and V-23-14 (Panel 12XR).
3.4 Inform the GSS/GOS that Drywell venting has begun.
3.5 Control Drywell pressure as directed by cycling V-23-14.
(320002/30) E13-2
Proccdure EMG-3200.02 Rpv. 9 Attachment N Page 1-of 1 Q SUPPORT PROCEDURE 37 MAKEUP TO THE TORUS VIA CORE SPRAY SYSTEM 1.0 PREREOUISITEF t 1.1 Makeup to the Torus via the Core Spray System has been directed by the Emergency Operating Procedures.
1.2 One Core Spray System is available and not required to assure adequate core cooling.
1.3 The Reactor Building is accessible.
2.0 PFEPARATIQN 2.1 E Core Spray actuating signals are present, TEEN override Core Spray initiation logic by depressing the OVERRIDE switches for all the sensors that are lit and depressing a_ll ACTUATED switches, whether lit or unlit.
2.2 An MB-1 key is required if lining up the CST as source of Torus water makeup 3.0 PROCEDURE 8 NOTE Overriding Core Spray initiation logic may be required 3.1 H Core Spray System I has been designated to be used, T_H_El{ Perform the following:
3.1.1 Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System I (Panel 1F/2F).
3.1.2 Close Core Spray System 1 Suction valves V-20-3 and V-20-32 (Panel IF/2F).
3.1.3 Confirm closed Core Spray System 1 Parallel Isolation valves V-20-15 and V-20-40 (Panel IF/2F).
(320002/31) E14-1 l 1
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" Proceduro EMG-3200.02 Rsv. 9 Attachment N i Page 2 of i c 3.1.4 II the NW Corner Room is accessible AED O the CST is the source of Torus water makeup, THElj perform the following:
- 1. Place the breakers for Core Spray Pump Suction Valves V-20-3 and V-20-32 in the OFF position.
- V-20-32 Bkr. (MCC IB21A/RB 23 NE)
- 2. Unlock and open the following CST supply valves:
- V-20-1 (NW Corner Roon)
- V-20-5 (NW Corner Room)
- V-20-34 (NW Corner Room)
- 3. Start Core Spray System 1 Main Pump NZO1A or NZOIC.
3.1.5 II the NW Corner Room is EQI accessible, THEN perform the following to use fire water as the
() source of Torus water makeup:
- 1. Close Tell-Tale Drain valve V-20-91 (North Side RB).
- 2. Start the Diesel Fire Pumps by placing their switches in MAN position (Panel 13R). ,
- 3. Open Fire Protection Supply Valve V-20-83 (North Side RB).
- 4. Place Core Spray System 1 Main Pump control switches in the PULL TO LOCK position ,
(Panel IF/2F).
3.1.6 Unlock and place the breaker for Torus Test Flow Return Valve V-20-27 in the ON position (MCC 1A21B/RB 23 E).
3.1.7 Open Test Flow Return valve V-20-27 (Keylock RB 51'NW) l
es Proceduro EMG-3200.02 R2v 9 Attachment N Page 3 of i 3.1.8 WHEN Torus level is greater than 143 in. but less than 154 in. ,
[\. THEN perform the following:
- a. Close the Test Flow Return Valve V-20-27 (keylock RB 51 NW).
- b. Secure the Core Spray System 1 Main Pumps started in Step 3.1.4.3. _
- 2. II fire water was the source of Torus water makeup, 1
THEN perform the following:
- a. Close the Test Flow Return Valve V-20-27 (keylock RB 51 NW)
- b. Close Fire Protection Supply Valve V-20-83 (North Side RB).
- c. Secure the Diesel Fire Pumps by taking their control switches in AUTO position (Panel 13R).
O d. Open Tell-Tale Drain valve V-20-91 (North Side RB).
3.1.9 when filling is no longer reqaired:
'THEN close and lock the following valves:
V-20-1 (NW Corner Room)
- V-20-5 (NW Corner Room)
- V-20-34 (NW Corner Room)
- 2. Confirm closed Torus Test Flow Return Valve V-20-27 (Panel IF/2F)
- 3. Place and lock the breaker for V-20-27 i
in the OFF position (MCC 1A21B/RB 23 E) l
- 4. Confirm the breakers for Core Spray Pump Suction valves V-20-3 and V-20-32 in the ON position. l
(320002/33) E14-3
Proc duro EMG-3200.02 R v. 9 Attachment N -
Page 4 of i
- 5. Open Core Spray Pump Suction Valves V-20-3 and
( V-20-32 (Panel IF/2F).
- 6. II Fire water was the source of torus water makeup, I THEN return Core Spray System 1 Main Pump control switches to the normal mid position (Panel 1F/2F).
7.
Verify Core Spray KEEP FILL TROUBLE (B-3-d) alarm is not illuminated and Pump Minimum Flow Valves are closed (Panel 1F/2F).
NOTE Overriding Core Spray initiation logic may be required.
3.2 IE Core Spray System 2 has been designated to be used, THEN perform the following:
3.2.1 Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 2 (Panel 1F/2F).
3.2.2 Close Core Spray System 2 Suction valves V-20-4 and V-20-33 (Panel IF/2F).
Confirm closed Parallel Isolation valves V-20-21
( 3.2.3 and V-20-41 (Panel IF/2F). ;
3.2.4 II the NW and SW Corner Rooms are accessible MD the CST is the source of Torus water makeup, THEN perform the following:
- 1. Place the breakers for Core Spray Pump Suction valves V-20-4 and V-20-33 in the OFF position.
V-20-4 Bkr (MCC IB21A/RB 23 NE)
V-20-33 Bkr (MCC 1A21A/RB 23 SW)
- 2. Unlock and open the following CST supply valves:
- V-20-1 (NW Corner Room)
- V-20-2 (SW Corner Room)
- V-20-35 (SW Corner Room)
- 3. Start Core Spray System 2 Main Pump NZO1B or NZO1D.
\ (320002/34) E14-4
3 Procedura EMG-3200.02 Rev. 9 Attcchment N Page 5 of i 3.2.5 II the NW or SW Corner Room is HQI accessible THEN perform the following to use firewater as the
(
source of Torus water makeup:
- 1. Close Tell-Tale Drain valve V-20-90 8'
(South Side RB).
- 2. Start the Diesel Fire Pumps by placing their switches in MAN position (Panel 13R)
- 3. Open Fire Protection Supply Valve V-20-82 (South Side RB).
- 4. Place Core Spray System 2 Main Pump control switches in the PULL TO LOCK position (Panel IF/2F).
3.2.6 Unlock and place the breaker for Torus Test Flow Return valve V-20-26 in the ON position (MCC IB21A/RB 23 NE).
3.2.7 Open Test Flow Return valve V-20-26 (Keylock RB 75 SW).
3.2.8 WHEN Torus level is greater than 143 in but less than 154 in.,
THEN perform the following:
- b. Secure the Core Spray System 2 Main Pumps started in Step 3.2.4.3
- 2. IE fire water was the source of Torus water makeup, THEN perform the following:
- a. Close the Test Flow Return Valve V-20-26 .
- b. Close Fire Protection Supply l Valve V-20-82 (South Side RB).
- c. Secure the Diesel Fire Pumps by taking their control switches in AUTO position (Panel 13R). I l
- d. Open Tell-Tale Drain Valve V-20-90 l (South Side RB).
[\_)') i (320002/35) E14-5
y-Procedura EMG-3200.02 R::v. 9 Attachment N Page 6 of i 3.2.9 When filling is no longer required:
- 1. R the CST was the source of Torus water makeup, THEN close and lock the following valves:
V-20-1 (NW Corner Room)
V-20-2 (SW Corner Room)
V-20-35 (SW Corner Room)
- 2. Confirm close Torus Test Flow Return valve V-20-26 (Panel IF/2F).
- 3. Place and lock the breaker for V-20-26 in the OFF position (MCC IB21A/RB 23 NE).
- 4. Confirm the breakers for Core Spray Pump Suction valves V-20-4 and V-20-33 in the ON position.
- V-20-4 Bkr (MCC IE21A/RB 23 NE)
V-20-33 Bkr (MCC 1A21A/RB 23 SW)
- 5. Open Core Spray Pump Suction valves V-20-4 and V-20-33 (Panel IF/2F).
- 6. R Fire water was the source of torus water makeup, O THEN return Core Spray System 2 Main Pump control switches to the normal mid position (Panel IF/2F).
- 7. Verify Core Spray KEEP FILL TROUBLE (B-3-d) alarm is not illuminated and Pump Minimum Flow Valves are rinsed (Panel IF/2F).
O (320002/36) E14-6 l
Procsduro EMG-3200.02 Rsv. 9 Attachment O Page 1 of 4 SUPPORT PROCEDURE 38 DETERMINING PRIMARY CONTAINMENT WATER LEVEL 1.0 PREREOUISITES ..
e; 1.1 Determination of Primary Containment Water Level has been directed by the Emergency Operating Procedures.
12 Primary Containment Water Level is greater than the range of the wide range torus level recorder (0-360 inches) on Panel 16R.
2.0 IREPARATION None _ _
3.0 PROCEDURE 3.1 Calculate Primary Containment Water Level by completing the following:
3.1.1 Record Torus pressure from one of the following:
- 1. Digital indicator on Panel 4F
- 2. Computer Point ID PTIP12
- 3. PT-IP12 on Panel IF/2F P(Torus) = psig 3.1.2 Record Drywell pressure from PI-IP08 on Panel IF/2F P(DW) = _____ psig 3.1.3 Calculate AP AP = P(Torus) - P(DW) = paid 3.1.4 II AP is greater than 16 psid THEN continue at Step 3.2 of this procedure 3.1.5 Determine Primary Containment Water Level using Figure 38-1.
3.2 II Torus - DW AP is greater than 16 psid THEN calculate Primary Containment Water Level by completing the following:
3.2.1 Record Torus pressure from one of the following:
- 1. Digital indicator on Panel 4F
- 2. Computer Point ID PTIP12
- 3. PT-IP12 on Panel 1F/2F P(Torus) = psig E15-1 l (320002/37)
Procedure EMG-3200.02 R3v. 9 Attachment O
, - Page 2 of 1 3.2.2 Record Dryewll pressure from Sample Entry Pressure gauge on H2/02 Panel IT-1B or IT-1A (Reactor Bldg El. 75'). P(H2 /0
- 2) psig 3.2.3 Calculate AP AP = P(Torus) - P(H2 /0 2 )- paid 3.2.4 Determine Primary Containment Water Level using Figure 38-2.
e s
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Procedura EMG-3200.02 N be nt O '
Page 3 of.i Fiaure 38-1 O fontainment Water Level Deterinination Usina DW Pressure Indication From Panel 1F/2F 800- - -- -- - -- ---- --. . . -- -.--
775 .
750 ;-'.
- .= -. -
725 - -
700 = -- - - -- -
-j . - ---
675= -
O650= -- - ---- - -
l 1 ,
W625"
= 600-
- - - - -- -- ' ~
a w 575- - - ; -- :- - '
), . . . . .
y "550- -- - -- - -- -- -- : ;--- :- ;- ; ;
a: <
w525- .
<t y500- -
- - :- 7 475 -
.. (4.7 psid; 461 inches)- . . .
450- .
425- A 400= ,
3751 (1'.3 psidh 365 i.nch'es). . .
3501 7 yj7 i 1 r-l- 1 r 7 y r 7 p q 7 --l l 0 1 2 3 4 5 6 7 8 9 101112131415161718 P(Torus) - P(DW) = psid '
\s (320002/41) E15-3
Proc:durs EMG-3200.02 Rtv. 9 Attachment O
- Page 4 of i Ficure 38-2 Containment Water Level Determination Usina DW Pressure Indication From the H /,2 Panels (RB 75')
1300-.-. .
1275h -!--:-.- -!
-i- :- ...
1250r- -
i-1225:- ..
- (31;.9 ' psi;d,1212 Inches) 1200, , , , , , , ,,,,,,,,,,,
1175h' - - -L- -i- ! :
- - -! -i-:
1150H. - : -- -
f.-!----
m1125- : .: :
w
I 1100' o : . .
z 1075.
E 1050 :- -
(25.6 psid j. 1040 inches) d1025- - -
q w 1 0 0 0 _- ..
J -
e w
975r - -
-~. . ..
~ 950+ - -
< /
3 925:- / - - ---
./ .
900'-
.- / -
875 .f < - -
/ .
850+ ./ -
825- y 800- .
y' - --
775- - - - - '-
750 l J lIlI El1l-lI-l-lll-Il-lI-l 15161718 19 20 21 22 23 2425 26 27 28 29 30 31 32 33 34 35 P(Torus) - P(H2/02) = psid O <>2eee2 4e> 1,--
- ?-. 1 I
i Procedurs EMG-3200.02 Rsv. 9 Attichment P Page 1 of 2 O SUPPORT PROCEDURE 39 PLACING THE H2/02 MONITORING SYSTEM IN SERVICE 1.0 PREREOUISITES I Placing the H2/02 Monitoring System in service has been directed by the Emergency Operating Procedures. '
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Placing Channel A in service (Panel 16R):
3.1.1 Place switch for V-38-37 to OPEN 3.1.2 Place switch for V-38-38 to OPEN 3.1.3 Place switch for V-38-39 to OPEN 3.1.4 Place switch for V-38-40 to OPEN NOTE When switching to the ANALYZE mode, a system trouble alarm may occur due to analyzer cell low flow.
3.1.5 Place mode switch in ANALYZE.
3.1.6 IE DW H2/02 SYS A TROUBLE alarm (C-8-f) annunciates, THEN acknowledge the alarm and reset by depressing the ALARM RESET pushbutton (Panel 16R). .
3.2 Placing Channel B in service (Panel 16R):
3.2.1 Place switch for V-38-41 to OPEN.
3.2.2 Place switch for V-38-43 to OPEN.
3.2.3 Place switch for V-38-44 to OPEN.
3.2.4 Place switch for V-38-46 to OPEN.
NOTE 1 When switching to the ANALYZE mode, a system trouble l alarm may occur due to analyzer cell low flow.
3.2.5 Place mode switch in ANALYZE. j (320002/41) E16-1 O
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a Proccdure EMG-3200.02 Rav. 9 Attachment P
- Page 2 of 2
( 3.2.6 DW H2/02 SYS B TROUBLE alarm II (C-8-g) annunciates, THEN acknowledge the alarm and reset by t,,
depressir.g the ALARM RESFT pushbutton (Panel 16R).
3.3 Record time.
Time 3.4 E014 A five (5) minute stabilization period is required after switching an analyzer from STANDBY to ANALYZE.
After a minimum 5 minute wait time, observe H2 and 02 concentrations.
O (320002/42) E16-2
Procsduro EMG-3200.02 Rav. 9 Attachment Q Page 1 of 1 SUPP RT PR CEDURE 40 O
ISOLATION OF THE PRIMARY CONTAINMENT VENT AND PURGE VALVES 1.0 PREREOUISITES Isolation of the Primary Containment Vent and Purge Valves has been directed by the Emergency Operating Procedures.
2.O PREPARATION NONE 3.0 PROCEDURE
Confirm closed the vent and purge valves that are EQI being used for Primary Containment Pressure Control.
System Valve No. Panel DW Vent / Purge V-27-1 11F V-27-2 11F V-27-3 11F V-27-4 11F Torus Vent V-28-17 11F V-28-18 11F Torus 2" Vent V-28-47 11F Bypass DW 2" Vent V-23-21 12XR Bypass V-23-22 12XR N Purge V-23-13 12XR 2
V-23-14 12XR V-23-15 12XR V-23-16 12XR N Makeup V-23-17 12XR V-23-18 12XR V-23-19 12XR V-23-20 12XR (320002/43) E17-1
Proesdura EMG-3200.02 Rpv. 9 Attachment R Page 1 of 2 O SUPPORT PROCEDURE 41 VENTING THE TORUS FOR HYDROGEN CONTROL 1.0 PREREQUISITES Torus venting has been directed by the Emergency Operating Procedures.
2.0 PREPARATION Perform the following steps in preparation for venting the Torus via the Reactor Building Ventilation System.
2.1 Verify Torus water level is below 348 in.
2.2 Evacuate personnel from the Reactor Building.
2.2.1 Sound the Reactor Building Evacuation Alarm. /
Time Date 2.2.2 Make the announcement, " Primary Containment Ventina will commence in aonroximately 5 minutes.
All personnel evacuate the Reactor Buildina immediately".
2.3 Select a SGTS Train for operation and place its fan control switch in HAND (Panel 11R).
2.4 Place control switch for V-28-48, SGTS CROSSTIE, in CLOSED (Panel 11R).
2.5 Confirm Reactor Building Supply Fans secured (Panel 11R).
2.6 Confirm Reactor Building Exhaust Fan secured (Panel 11R).
2.7 Confirm that the Reactor Mode Selector Switch is EQI in the RUN position (Panel 4P).
2.8 Obtain a bypass plug from the EOP Tool Boy in the Control Room. j 2.9 ***************************************************************** !
- GhyTION *
- The containment isolation function of the following valves is *
- bypassed when the High Drywell Pressure and Reactor Low-Low *
- Water Level Isolation signals are defeated: *
- Drywell Nitrogen Makeup Valves (V-23-17 and V-23-18) *
- Torus Nitrogen Makeup Valves (V-23-19 and V-23-20)
- Open the EOP BYPASS PLUGS panel inside Panel 10XF.
2.9.1 Insert a bypass plug in position BPS.
O (320002/44) E18-1 i
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Proorduro EMG-3200.02.
Rav. 9 Atttchment R Page 2 of 1 0 2.10 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
2.10.1 Remove she bypass plug from position BP4.
2.10.2 Insert a bypass plug into position BPl.
2.11 Place the TORUS /DRYWELL ISOLATION VALVE BYPASS PERMISSIVE r keylock switch in TORUS position (Panel 11F).
2.12 Place the TJRUS/DW VENT AND PURGE ISOL VLVS HI RADL' BYP keylock switches for both Channels 1 and 2 in the BYPASS position (Panel 11F).
2.13 Inform the GSS/GOS that the Torus is ready to be vented via the Torus Vent valves.
3.0 PPOCEDURE When directed by the GSS/GOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 11R).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves V-28-21 and V-28-22 (Panel 11R).
3.3 WHEN at least five minutes have passed since sounding the Reactor Building Evacuation Alarm, THEN inform the GSS/GOS and start Reactor Building Exhaust Fan 1-5 (Panel 11R).
3.4 Open Torus Vent valves V-28-18 and V-28-47 (Panel 11F). 3 3.5 Inform the GSS/GOS that Torus venting via V-28-18 and ;
V-28-47 has commenced.
3.6 WHEN Torus pressure is below 2 psig, THEN inform the GSS/GOS and open Torus Vent valve V-28-17 a
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O (320002/45) E18-2 l 1
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9 Proc: dure EMG-3200.02 Rev. 9 Attachment S
. Page 1 of 4 O surroar raoctnuas42 PURGING THE DRYWELL FOR HYDROGEN CONTROL 1.0 PREREOUISITES ll Purging the Drywell has been directed by the Emergency Operating Procedures.
2.O PREPARATION Perform the following steps in preparation for purging the Drywell.
2.1 Station an Equipment Operator and establish comunications between the Nitrogen Supply Station and the Control Room.
2.2 *****************************************************************
- CAUTION *
- The containment isolation function of the following valves *
- is bypassed when the CNTMT VENT AND PURGE ISOLATION BYPASS *
- Keylock is in the BYPASS position: *
- Drywell Ventilation Isolation Valves (V-27-1, 2, 3 and 4) *
- Drywell Nitrogen Purge Inlet Valves (V-23-13 and V-23-14) *
- Torus Nitrogen Purge Inlet Valves (V-23-15 and V-23-16)
- Place the CNTMT VENT AND PURGE ISOLATION BYPASS keylock (Panel 12XR) in the BYPASS position.
2.3 Confirm that the ABSORP CHAM VAC REL (Torus to Reactor Building vacuum Breakers, V-26-16 and V-26-18) control switch in the CLOSE position (Panel 11F).
2.4 Confirm open Purge Line Isolation Valve V-23-357 (NE corner RB, outside) 2.5 Confirm open Drywell Purge Isolation Valve V-23-195 (NE corner RB, outside) 2.6 Inform the GSS/GOS that nitrogen purging of the Drywell is ready to comence. j l
i l
\ E19-1 (320002/46)
\
Proc dure EMG-3200.02 Rnv. 9 Attachment S Page 2 of 4
'0. PROCEDURE
\ s! When directed by the GSS/GOS, perform the following:
1 NOTE t,
All valves and electrical components, unless noted otherwise, are located at the Nitrogen Pad.
3.1 Line up nitrogen supply to the Drywell by opening valves V-23-13 and V-23-14 (Panel 12XR).
3.2 Prepare the nitrogen vaporizer for purging by completing the following:
3.2.1 Confirm the following knife switches in the ON position:
- SW-854-167
- SW-854-168
- SW-854-165 3.2.2 On the selected heater control cabinet (HTR-854-165 or 166), complete the following:
- Place the power switch in ON position (upper right hand side)
- Place the power contral switch in ON position ,
- Verify that the POWER ON light is lit 3.2.3 Confirm that there is no debris below or in the area around the nitrogen vaporizer.
3.2.4 Place the knife switch for M-23-1 in ON pos.' tion.
t 3.2.5 *********************************************************
- CAUTION *
- The following step will start the nitrogen vaporizer *
- fan which blows down. Hearing and eye protection is
- j
- required. *
....'............................*** ..................... j 1
Place the control switch for M-23-1 in HAND position. l (320002/47) E19-2 l
. .q , -
- k Proesdura EMG-3200.02 Bsv. 9 Attachment S Page 3 of 4 ;
3.3 Crack open, then completely open the nitrogen supply tank outlet to vaporizer valve V-23-268.
3.4 Crack open, then completely open the inlet and outlet valves for -
the selected heater:
HTR-854-165 HTR-854-166 Inlet valve V-23-363 V-23-365 Outlet Valve V-23-364 V-23-366 3.5 Place the thermostatic regulating valve in service by opening valves V-23-186 and V-23-187.
3.6 Select a Grove Reducer and open the appropriate inlet, outlet and supply valves:
Grove Reducer V-23-235 V-23-234 i
Inlet Valve V-23-189 V-23-190 Qutlet valve V-23-191 V-23-192 Sunolv Valve V-23-193 V-23-194 L
3.7 Establish nitrogen purge flow by completing the following: ,
3.7.1 Using a wrench, turn the control valve on top of the selected Grove Reducer in the clockwise direction until pressure as I indicated on PI-854-732 is 55 psig.
3.7.2 Verify purge flow on the NITROGEN PURGE & MAKEUP FLOW Recorder (Panel 12XR).
(320002/48) E19-3
Procrduro EMG-3200.02 R3v. 9 .
Attachment S Page 4 of i gf/ 3.7.3 Initial temperature could be 20 to 30*F above nominal set-points of 80*F. After 5 to 10 minutes, dependent on ambient temperature, temperature will stabilize. i'
- CAUTION *
- The temperature range of 65*-95'F as read in the Control Room *
- is important to prevent brittle fracture and cracking of *
- piping within the containment.
- Confirm N temperature 65-95*F as indicated on the 2
PURGE N TEMP gauge (Panel 12XR).
2 3.7.4 IE ambient temperature is greater than 80*F
. AED N temperature is above 95'F as indicated on the 2
PURGE N TEMP gauge (Panel 12XR)
(
THEN secure the nitrogen vaporizer fan by placing the control switch for M-23-001 in OFF position.
3.8 Inform the GOS/GSS that Drywell purging has commenced.
3.9 WHEN directed to secure the nitrogen purge, THEN close Drywell Nitrogen purge valves V-23-13 and V-23-14 (Panel 12XR).
1 l
I i
k_/
(320002/49) E19-4
)
I
A Proctdure EMG-3200.02 Rey. 9
, Attachment T Page 1 of 1 O SUPPORT PROCEDURE 43 VENTING THE DRYWELL FOR HYDROGEN CONTROL (LEVEL BELOW 461 IN) 1.0 PREREOUISITES Drywell venting has been directed by the Emergency Operating Procedures.
2.0 EEEPARATION Perform the following steps in preparation for venting the Drywell via the Reactor Building Ventilation System.
2.1 Verify Primary Containment water level is below 461 in.
2.2 Evacuate personnel from the Reactor Building.
2.2.1 Sound the Reactor Building Evacuation Alarm. /
Time Date 2.2.2 Make the announcement, " Primary Containment ypntina will commence in aporoximately five minutes.
All personnel evacuate the Reactor Buildino immediatelv".
2.3 Select a SGTS Train for operation and place its fan control switch in EAND (Panel 11R).
2.4 Place control switch for V-28-48, SGTS CROSSTIE, in CLOSED (Panel 11R).
2.5 Confirm Reactor Building Supply Fans secured (Panel 11R).
2.6 Confirm Reactor Building Exhaust Fan secured (Panel 11R).
2.7 Confirm that the Reactor Mode Selector switch is EQI in RUN (Panel 4F).
2.8 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
2.8.1 Remove the bypass plug from position BP4.
2.8.2 Insert the bypass plug into position BPl.
2.9 Place the TORUS /DRYWELL ISOLATION VALVE BYPASS PERMISSIVE keylock switch in the DRYWELL position (Panel 11F).
(320002/50)
E20-1
Proc duro EMG-3200.02 Rzv. 9 Attachment T
_- Page 2 of 2
-~s 2.10 Place the 'IORUS/DW VENT AND PURGE ISOL VLVS HI RAD BYPASS keylock switches for both Channels 1 and 2 in the BYPASS position (Panel 11F).
2.11 *************************************************************
- CAUTION *
- The containment isolation function of the following *
- valves is bypassed when the CNTMT VENT AND PURGE *
- ISOLATION BYPASS is in the BYPASS position: *
- Drywell Ventilation Isolation Valves (V-27-1,273 ,& 4) *
- Drywell Nitrogen Purge Inlet valves (V-23-13 & V-23-14)*
- Torus Nitrogen Purge Inlet valves (V-23-15 & V-23-16)
- Place the CNTMT VENT AND PURGE ISOLATION BYPASS Keylock in BYPASS position (Panel 12XR).
2.22 Inform the GSS/GOS that the Drywell is ready to be vented via the Drywell Vent valves.
3.0 EROCEDURE When directed by the GSS/GOS, complete the following: ,
() 3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 11R).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves, V-28-21 and V-28-22 (Panel 11R).
3.3 WHEN at least five minutes have passed since sounding the Reactor Building Evacuation Alarm, TREN inform the GSS/GOS and start Reactor Building Exhaust 1 Fan 1-5 (Panel 11R).
3.4 Open Drywell Vent valves V-23-21 and V-23-22 (Panel 12XR).
3.5 Inform the GSS/GOS that Drywell venting via V-23-21 and V-23-22 has commenced.
O (320002/51) E20-2
Procedura EMG 3200.02 R v. 9 Attcchment T
/ Page 3 of 1
~
3.6 WHEN Drywell Pressure is below 2 psig, THEN inform the GSS/GOS and open Drywell vent valves V-27-1 and V-27-2.
O O
(320002/52) E20-3 l
\
Proceduro EMG-3200.02 Rev. 9 Attachment U
,. Page 1 of A O surroar raoczouan 44 VENTING THE DRYWELL THROUGH THE Rx BUILDING SUPPLY FANS FOR HYDROGEN CONTROL (LEVEL ABOVE 461 IN) k 1.0 PREREOUISITES Drywell venting has been directed by the Emergency Operating Procedures.
- 2.0 PREPARATION Perform the following steps in preparation for venting the Drywell via the Rx Building Supply Fans.
2.1 Select a SGTS Train for operation and place its fan control switch in RAND (Panel 11R).
2.2 Place control switch for V-28-48, SGTS CROSSTIE, in CLOSE (Panel 11R).
2.3 Confirm Reactor Building Supply fans secured (Panel 11R).
2.4 Confirm Reactor Building Exhaust Fan secured (Panel 11R).
2.5 Confirm closed Reactor Building Ventilation Isolation dampers V-28-1 through V-28-16 and V-28-36 through V-28-39 (Panel 11R).
2.6 Place TORUS /DW VENT AND PURGE ISOL VLVS HI RAD BYPASS keylock switches for both Channels 1 and 2 in BYPASS (Panel 11F).
2.7 Confirm Reactor Building to Torus Vacuum Breakers V-26-16 and V-26-18 control switch in CLOSE position (Panel 11F).
(320002/53) E21-1 v
l
a - .
Proctduro EMG-3200.02 Rpv. 9 Attachment U Page 2 of i g 2.8 **************************************************************
- CAUTION *
- The containment isolation function of the following valves * ,
- is bypassed when the CNTMT VENT AND PURGE ISOI.ATION BYPASS *
- keylock is in the BYPASS position:
- l
- Drywell ventilation Isolation valves (V-27-1,2,3 & 4)
- d
- Drywell Nitrogen Purge Inlet valves (V-23-13 & V-23-14) *
- Torus Nitrogen Purge Inlet valves (V-23-15 & V-23-16)
- Place the CNTMT VENT AND PURGE ISOLATION BYPASS keylock in the BYPASS position (Panel 12XR).
2.9 Obtain two bypass plugs from the EOP Tool Box in the Control Room.
2.10 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R. ,
2.10.1 Insert a bypass plug into position BP2. _
2.10.2 Insert a bypass plug into position BP3.
2.11 FOTE '
The tools that are required to complete this step are stored in the EOP Tool Box in the Control Room.
On the Office Building Roof, perform the following to establish a back flow path through one of the Reactor Building Supply Fans:
2.11.1 Disconnect the air operator linkages on the t
automatic damper of one Reactor Building Supply Fan:
Supply Fan Automatic Dameer SF-1-12 DM-28-42 SF-1-13 DM-28-43 SF-1-14 DM-28-41 2.11.2 Manually open the automatic damper for the supply -
fan selected. ,
2.11.3 Secure the automatic damper in the open position by tightening the wing nuts on the damper positioning device.
)
(320002/54) E21-2
g - -. -
t Procrduro EMG-3200.02 Rsv. 9 Attachment V Page 3 of i 2.11.4 Confirm open the manual damper downstream of the supply fan chosen.
Sucolv Fan Manual Damper i;
SF-1-12 DM-28-46 SF-1-13 DM-28-47 SF-1-14 DM-28-48 2.11.5 Secure the manual damper in the open position by tightening the wing nuts on the damper positioning i device 2.12 Evacuate personnel from the Reactor Building and Main Office Building 2.12.1 Sound the Reactor Building Evacuation Alarm. /
Time Date 2.12.2 Make the announcement, " Primary Containment Ventina will commence in nooroximately five minutes.
All personnel evacuate the Reactor Buildina and ;
e Main Office Buildina immediatelv a .
2.13 *********************************************************
- CAUTION *
- Contamination of the Control Room HVAC System may *'
- result when venting through V-27-3 and V-27-4. * ;
Place the Control Room Ventilation in Full Recirculation Mode as follows:
2.13.1 Place the Control Room HVAC Damper Control rwitch i
in FULL RECIRC position (SYS A Panel 11R/SYS B Panel 9XR).
2.13.2 Confirm exhaust fan EF-1-24 control switch is OFF (wall above EOP Locker) and its damper is closed )
(CR Bathroom) l l
}
(320002/55) E21-3 i
l
? .
Procrduro EMG-3200.02 Rev. 9 Attachment V Page 4 of 4
. 3.0 PROCEDURE
\
When directed by the GSS/GOS, complete the following:
- CAUTION *
- An unmonitored, ground level release of radioactive *
- gases will result from venting the primary contain- *
- ment via the Reactor Building Supply Fans.
- 3.1 Reset the Drywell Isolation Signal by momentarily depressing the DRYWELL ISOLATION reset pushbutton (Panel 4F).
3.2 *********************************************************
- CAUTION *
- Contamination of the Main Office Building may result *
- from venting the primary containment through purge *
- valves V-27-3, V-27-4, and the Reactor Building
- Supply Fans.
WHEN at least five minutes has passed since sounding x !
the Reactor Building evacuation alarm THEN inform the GSS/GOS and perform the following:
- 3.2.1 Open drywell air supply valves V-28-42 and V-28-43 (Panel 11R).
3.2.2 Open drywell purge valves V-27-3 and V-27-4 (Panel IIF).
3.3 Inform the GSS/GOS that Drywell Venting has commenced, i
I (320002/56) E21-4 1
1 l
i
Proccduro EMG-3200.02 Rev. 9 Attachment V Page 1 of 1 O SUPPORT PROCEDURE 45 PURGING THE TORUS FOR HYDROGEN CONTROL 1.0 PREREOUISITES Purging the Torus has been directed by the Emergency Operating Procedures.
2.0 PREPARATION ;_;; .
Perform the following steps in preparation for purging the Torus.
2.1 Station an Equipment Operator and establish communications between the Nitrogen Supply Station and the Control Room.
2,2 **** ..........**...** ........*****.........**...........***.....
- CAUTION *
- The containment isolation function of the following valves *
- is bypassed when the CNTMT VENT AND PURGE ISOLATION BYPASS *
- keylock is in the BYPASS position: *
- . Drywell ventilation Isolation valves (V-27-1, 2, 3, and 4) *
- . Drywell Nitrogen Purge Inlet Valves (V-23-13 and V-23-14) *
(V-23-15 and V-23-16)
- O
- Torus Nitrogen Purge Inlet Valves Place the CNTMT VENT AND PURGE ISOLATION BYPASS keylock (Panel 12XR) in the BYPASS position.
2.3 Confirm that the ABSORP CHAM VAC REL (Torus to Reactor Building vacuum Breakers, V-26-16 and V-26-18) control switch in the CLOSE position (Panel 11F).
2.4 Confirm open Purge Line Isolation Valve V-23-357 (NE corner RB, outside).
2.5 Confirm open Drywell Purge Isolation valve V-23-195 (NE corner RB, outside).
2.6 Inform the GSS/GOS that nitrogen purging of the Torus is ready to commence O (320002/57) E22-1 I l
"?L _
i
+
1 Procsduro EMG-3200.02- ;
Rgv. 9 Attachment V
' Page 2 of f 3.0 PROCEDURE 1
,-s When directed by the CSS /GOS, perform the following:
F.D.IE F
All valves and electrical components, unless noted otherwise, are located at the Nitrogen Pad.
3.1 Line up nitrogen supply to the Torus by opening valves V-23-15 and V-23-16 (Panel 12XR).
3.2 Prepare the nitrogen vaporizer for purging by completing the following:
3.2.1 Confirm the following knife switches in the ON position:
- SW-854-167
- SW-854-168
- SW-854-165 3.2.2 On the selected heater control cabinet (HTR-854-165 or 166), complete the following:
- Place the power switch in ON position (upper right hand side)
- Place the power control switch in ON position.
- Verify that the POWER ON light is lit.
3.2.3 Confirm that there is no debris below or in the area around the nitrogen vaporizer.
3.2.4 Place the knife switch for M-23-1 in ON position.
3.2.5 **********************************************************
- CAUTION *
- The following step will start the nitrogen vaporizer *
- Hearing and eye protection
- fan which blows down.
- is required.
- Place the control switch for M-23-1 in RAND position.
(320002/58) E22-2 l l
~ -- - - - - - - -
-y L J - - -
Proc; dure EMG-3200.02 Rpv. 9 Attachment W Page 3 of 4 O 3.3 Crack open, then completely open the nitrogen supply tank outlet to vaporizer valve V-23-268.
3.4 Crack open, then completely open the inlet and outlet valves for U the selected heater:
HTR-854-165 RfR-854-166 Inlet Valve V-23-363 V-23-365 Outlet valve V-23-364 V-23-366 3 I
I 3.5 Place the thermostatic regulating valive in service by opening valves V-23-186 and V-23-187.
3.6 Select a Grove Reducer and open the appropriate inlet, outlet I
and supply valves:
Grove Reducer V-23-235 V-23-234 Inlet valve V-23-189 V-23-190 Outlet valve V-23-191 V-23-192 Sueolv Valve V-23-193 V-23-194 3.7 Establish Nitrogen purge flow by completing the following:
3.7.1 Using a wrench, turn the control valve on top of the selected Grove Reducer in the clockwise direction until pressure as indicated on PI-854-732 is 55 psig. ;
l 3.7.2 Verify purge flow on the NITROGEN PURGE & MAKEUP FLOW Recorder (Panel 12XR)
(320002/59) E22-3
Proc dure EMG-3200.02 Rsv. 9 Attachment V Page 4 of a l l
3.7.3 l
/~'}
v NOTE i
Initial temperature could be 20 to 30*F above nominal l setpoint of 80*F. After 5 to 10 minutes, dependant on ;
ambient temperature, temperature will stabilize. (
- CAUTION *
- The temperature range of 65*-95'F as read in the Control *
- Room is important to prevent brittle fracture and cracking *
- of piping within the containment. *-
Confirm N temperature 65-95'F as indicated on the 2
PURGE N TEMP gauge (Panel 12XR). !
2 3.7.4 II ambient temperature is greater than 80*F AHD N temperature is above 95'F as indicated on the 2
PURGE N T MP gauge (Panel 12XR),
2 IEEE secure the nitrogen vaporizer fan by placing the control t
switch for M-23-001 in OFF position.
3.8 Inform the GOS/GSS that Torus purging has commenced.
3.9 WHEN directed to secure the nitrogen purge, THEN Close Torus purge valves V-23-15 and V-23-16 (Panel 12XR).
I h
(320002/60) E22-4
Procedure EMG-3200.02 Rev. 9
^
Attachment W Page 1 of 2 SUPPORT PROCEDURE 46 VENTING THE TORUS FOR HYDROGEN CO!PrROL 1.0 PREREOUISITES ,,
Torus venting has been directed by the Emergency Operating Procedures.
2.0 PREPARATION Perform the following steps in prepara'. ion for venting the Torus via the Reactor Building Ventilation System.
2.1 Confirm Torus water level is below 348 in.
2.2 Evacuate personnel from the Reactor Building.
2.2.1 Sound the Reactor Building Evacuation Alarm. /
Time Date 2.2.2 Make the announcement, " Primary Containment ventina will commence in approximately 5 minutes.
All personnel evacuate the Reactor Buildina immediatelv".
2.3 Select a SGTS Train for operation and place its fan control switch in HAND (Panel 11R).
2.4 Place control switch for V-28-48, SGTS CROSSTIE, in CLOSED (Panel 11R).
2.5 Confirm Reactor Building Supply Fans secured (Panel 11R).
2.6 Confirm Reactor Building Exhaust Fan secured (Panel 11R). 7 2.7 Confirm that the Reactor Mode Selector switch is EQI in the RUN position (Panel 4F.
2.B Obtain a bypass plug from the EOP Tool Box in the Control Room.
2.9 ***********************************************************
- CAUTION *
- The containment isolation function of the following *
- valves is bypassed when the High Drywell Pressure *
- and Reactor Low-Low Water Level isolation signals
- are defeated:
- Drywell Nitrogen Makeup Valves (V-23-17 and V-23-18)
- Torus Nitrogen Makeup Valves (V-23-19 and V-23-20)* j Open the EOP BYPASS PLUGS panel inside Panel 10XF.
2.9.1 Insert a bypass plug into position BPS.
2.10 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
(320002/61) E23-1
Proceduro EMG-3200.02 Rsv. 9 Attachment W Page 2 of 2 2.10.1 Remove the bypass plug from position BP4.
2.10.2 Insert the bypass plug into position BPl.
2.11 Place the TORUS /DRYWELL ISOLATION VALVE BYPASS PERMISSIVE keylock switch in TORUS position (Panel 11F).
2.12 Place the TORUS /DW VENT AND PURGE ISOL VLVS HI RAD BYPASS keylock switches for both Channels 1 and 2 in the BYPASS position (Panel 11F).
2.13 Inform the GSS/GOS that the Torus is ready to be vented via the Torus Vent valves.
3.0 PROCEDURE When directed by the GSS/GOS, complete _the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 11R).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves V-28-21 and V-28-22 (Panel 11R).
3.3 WHEN at least five minutes have passed since sounding the Reactor Building Evacuation Alarm, IHEN inform the GSS/GOS and start Reactor Building Exhaust Fan 1-5.
3.4 Open Torus Vent valves V-28-18 and V-28-47 (Panel 11F).
3.5 **********************************************************
- CAUTION *
- Ventilation Ductwork Failure can occur when
- venting through V-28-17 with Torus pressure *
- greater than 2 psig.
Open Torus Vent valve V-28-17 (Panel 11F). 4 3.6 Inform the GSS/GOS that Torus venting via V-28-17, V-28-18 and V-2C-47 has commenced.
3.7 II Containment pressure drops below 0.6 psig THEN 1. Stop Exhaust Fan 1-5 (Panel 11R).
- 2. close Reactor Building Main Exhaust Isolation Valves V ?F 21 and V-28-22 (Panel 11R).
O (320002/62) E23-2 i
Procrdure EMG-3200.02 Rcy. 9 Attachment X Page 1 of 1 SUPPORT PROCEDURE 47 VENTING THE DRYWELL FOR HYDROGEN CONTROL fLEVEL BELOW 461 IN)
I 1.0 PREREOUISITES Drywell venting has been directed by the Emergency Operating Procedures.
2.0 PREPARATION
._=
Perform the following steps in preparation for venting the Drywell via the Reactor Building Ventilation System.
2.1 verify Primary Containment water level is below 461 in.
2.2 Evacuate personnel from the Reactor Building.
2.2.1 Sound the Reactor Building Evacuation Alarm. /
Time Date 2.2.2 Make the announcement, " Primary Containment ventino will commence in acoroximately five minutes.
All personnel evacuate the Reactor Buildina immediatelv".
2.3 Calect a SGTS Train for operation and place its fan control switch in RAND (Panel 11R).
2.4 Place control switch for V-28-48, SGTS CROSSTIE, in CLOSED (Panel 11R).
2.5 Confirm Reactor Building Supply Fans secured (Panel 11R).
2.6 Confirm Reactor Building Exhaust Fan secured (Panel 11R).
2.7 Confirm that the Reactor Mode Selector switch is HQI in RUN (Panel 4F).
2.8 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
2.8.1 Remove the bypass plug from position BP4. I 2.8.2 Insert the bypass plug into position BPl.
l l
l (320002/63) E24-1
4 Proctdure EMG-3200.02 R7v. 9
. Attachment X Page 2 of 2 2.9 Place the TORUS /DRYWELL ISOLATION VALVE BYPASS PERMISSIVE Keylock switch in DRYWELL position (Panel 11F).
2.10 Place the TORUS /DW VENT AND PURGE ISOLATION VLVS HI RAD it BYPASS CHAN keylock switches for both Channels 1 and 2 in the BYPASS position (Panel 11F).
2.11 ******************************************************************
- CAUTION *
- The containment isolation function of the following *
- valves is bypassed when the CNTMT VENT AND PURGE *
- ISOLATION BYPASS Keylock is in the BYPASS position: *
- Drywell Ventilation Isolation Valves (V-27-1, *
- 2, 3 and 4) *
- Torus Nitrogen Purge Inlet Valves (V-23-15 and (V-23 14) *
- Torus Nitrogen Purge Inlet Valves (V-23-15 and (V-23-16)
- Place the CNTMT VENT AND PURGE ISOLATION BYPASS Keylock in the BYPASS position (Panel 12XR).
2.12 Inform the GSS/GOS that the Drywell is ready to be vented via the Drywell Vent valves.
3.0 PROCEDURE When directed by the GSS/GOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 11R).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves, V-28-21 and V-28-22 (Panel 11R).
3.3 WHEN at least five minutes have passed since sounding the Reactor Building Evacuation Alarm, THEN inform the GSS/GOS and start Reactor Building Exhaust Fan 1-5 (Panel 11R) 3.4 Open Drywell vent valves V-23-21 and V-23-22 (Panel 12XR).
(320002/64) E24-2
Proctdura EMG-3200.02 Rsv. 9
~
. Attachment X Page 3 of 1 3.5 ********************************************************
- CAUTION *
- Ventilation ductwork failure can occur when *
- venting through V-27-1 and V-27-2 with drywell *
- pressure greater than 2 psig. *
- .......................***.....**........** ........... t confirm Drywell pressure is below 24 psig and open Drywell Vent valves V-27-1 and V-27-2 (Panel 11F).
3.6 Inform the GSS/GOS that Drywell venting via V-23-21, V-23-22, V-27-1 and V-27-2 has commenced. ,
3.7 II Containment Pressure drops below 0.6 psig.
THEN 1. Stop Exhaust Fan 1-5 (Panel 11R).
- 2. Close Reactor Building Main Exhaust Isolation Valves V-28-21 and V-28-22 (Panel 11R).
1 i
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(320002/65) E24-3 i
l
k Procedure EMG-3200.02 Rev. 9 Attachment Y Page 1 of 2 O SUPPORT PROCEDURE 48 VENTING THE DRYWELL THROUGH THE PURGE SYSTEM POR HYDROGEN CONTROL :
1.0 EBEREOUISITES Drywell venting has been directed by the Emergency Operating Procedures.
2.0 PREPARATION Perform the following steps in preparation for venting the Drywell via the Drywell Purge System and Reactor Building Ventilation System. i 2.1 Evacuate personnel from the Reactor Building.
2.1.1 Sound the Reactor Building Evacuation Alarm. /
. Time Date 2.1.2 Make the announcement, ' Primary Containment ventine will commence in aooroximately five minutes.
All nersonnel evacuate the Reactor Buildine immediatelv".
2.2 Select a SGTS Train for operation and place its fan control switch in RAND (Panel 11R).
2.3 Place control switch for V-28-48, SGTS CROSSTIE, in CLOSED (Panel 11R).
(
2.4 Confirm Reactor Building Supply Fans secured (Panel IIR).
2.5 Confirm Reactor Building Exhaust Fan secured (Panel 11R),
2.6 Confirm closed Reactor Building Ventilation Isolation dampers V-28-1 through V-28-16 and V-28-36 through V-28-39 (Panel 11R).
2.7 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
2.7.1 Remove the bypass plug from position BP4.
2.7.2 Insert the bypass plug from position BPl.
2.8 ******************************************************************
- CAUTION *
- The containment isolation function of the following *
- valves is bypassed when the CNTMT VENT AND PURGE *
- ISOLATION BYPASS Keylock is in the BYPASS position: *
- Drywell Ventilation Isolation Valves (V-27-1,2,3,
- and 4)
- Drywell Nitrogen Purge Inlet Valves (V-23-13 and (V-23-14)*
- Torus Nitrogen Purge Inlet Valves (V-23-15 and (v-23-16)
- Place the CNTMT VENT AND PURGE ISOLATION BYPASS Keylock in the BYPASS (Panel 12XR).
(320002/66) E25-1
T' I Proc 3 dure EMG-3200.02 Rsv. 9 Attachment Y
' Page 2 of 1 2.9 Place TORUS /DW VENT AND PURGE ISOL VLVS HI RAD BYPASS keylock switches for both Channels 1 and 2 in BYPASS (Panel 11F) 2.10 Confirm Reactor Building to Torus Vacuum Breakers V-26-16 and V-26-18 control switch in CLOSE position (Panel 11F). '!
2.11 Inform the GSS/GOS that the Drywell is ready to be vented via the Drywell Purge Valven.
3.0 PROCEDURE When directed by the GSS/GOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the systes RISET pushbutton (Panel 11R).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves V-28-21 and V-28-22 (Panel 11R).
3.3 WHEN at least five minutes has passed since sounding the Reactor Building evacuation alarm IHEN inform the GSS/GOS and start Reactor Building Exhaust Fan 1-5 (Panel 11R).
3.4 Confirm closed Drywell Air Supply Valves V-28-42 and V-28-43 (Panel 11R).
3.5 ***********************************************************
- CAUTION *
- Ventilation ductwork failure will occur when venting *
- through V-27-3 and V-27-4 with drywell pressure *
- greater than 2 psig. *
- =******************************************************
Open Drywell Purge Valves V-27-3 and V-27-4 (Panel 11F).
3.6 Inform the GSS/GOS that Drywell Venting has commenced.
3.7 IE Containment pressure drops below 0.6 psig, THEN 1. Stop Exhaust Fan 1-5 (Panel 11R).
I
- 2. Close Reactor Building Main Exhaust Isolation i
Valves V-28-21 and V-28-22 (Panel 11R). ]
i
, s (320002/67) E25-2
OYSTER CREEK NUCLEAR GENERATING Number
. Nuslear STAT 10N rRoCEDoRE m e.-3 m .o a Title Revision No.
O tunnosscv nerasssuniz^rion - no ^rws >
Applicability / Scope Responsible Office PLANT ENGINEERING EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 2200 g; This document is within QA plan scope X Yes No Effective Date Safety Reviews Required X Yes _ No (07/19/93) 07/29/93 Prior Revision 0 incorporated the This Revision 1 incorporates the following Temporary Changes: following Temporary Changes:
N/A N/A LIST OF rrrm.Tivn PA M PAGE REVISION 1.0 1 2.0 1 3.0 1 El-1 1 i E2-1 1 E3-1 1 E3-2 1 OYSTER CPEK CONTROL. LED D!E : EUTION l DOCUMENT sanL NU: J E R _ ._7d _
INFO MGMT . nr e Signature ,
Concurring Organization Element Date Originator 10P COORDINATOR 7,
[M/<,7 J Concurred By %[g,.)k,4Jd- EOP COMMITTEE gg ShL PLANT ENGINEERING DIRECTOR k7 fc/ 3 Mjh MGR, PLANT OPERATIONS )qfg3 O /
O Approved By (320004A)
[)h VICE PRESIDENT & DIRECTOR, OC 7 1.0
m OYSTER CREEK NUCLEAR GENERATING Numb 3r STATION PROCEDURE BIG-3200.04A Title Revision No.
O EMERGENCY DEPRESSURIZATION - NO ATWS 1 l.0 PURPOSE I:
The purpose of the Emergency Depressurization - No ATWS Procedure is ts:
Maintain adequate core cooling Cooldown the RPV to cold shutdown conditions
2.0 REFERENCES
2.1 Procedures
- 107.4, EOP Program Control 2.2 Drawings
- BR 2002, Main, Extraction & Aux Steam System
- BR 3029, DC Control Elem Diagram
- BR E1102,- Emer Condenser Isol Outlet Valve V-14-35
- GE 112C2248, Sht 2, Connection Diagram 11F
- GE 148F262, P&ID - Emergency Condenser System
- GE 237E566, Sht 4, Rx Protection System Elem Diagram 2.3 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.4 2000-STD-1218.04, EOP Writer's Guide O
(320004A) 2.0 E
. =.
OYSTER CREEK NUCLEAR GENERATING Number N OI STATION PROCEDURE DIG-3200.04A L
Title Revision No.
O- EMERGENCY DEPRESSURIZATION - NO ATWS 1 3.0 PRECAUTIONS AND LIMITATIONS 1:
3.1 This procedure gives guidance to the operator for byparaing isolation signals and automatic scrams which is a departure froa the Oyster Creek Technical Specifications. It is permissible to take actions which depart from the plant's Technical Specifications during emergency conditions as authorized by 10 CFR 50.54(x).
4.O ATTACHMENTS 4.1 Attachment A - RPV Control - No ATWS EOP Flowchart DWG: GU 3E-200-08-008 sh 2 4.2 Attachment B - Support Procedure 10, Stopping Injection from the Core Spray System 4.3 Attachment C - Support Procedure 52, RPV Depressurization ,
Via The Isolation Condenser Tube Side Vents l
1 (320004A) 3.0 1
r OYSTER CREEK NUCLEAR GENERATING Number gp STATION PROCEDURE EMG-3200.04A
-e Title Revision No.
O tazaccxcv nuratssuaizirion - no irws 1 4
. ATTACHMENT A Attachment A to EMG-3200.04A, Emergency Depressurization - No ATWS, is' the Emergency Depressurization - No ATWS EOP Flowchart, DWG: GU 3E-200-08-008, Sht 2 Rev. 1.
O O .
(320004A/4) El-1
Procedure EMG-3200.04A Rav. 1
, Attachment B Page 1 of 1 O SUPPORT PROCEDURE 10 STOPPING INJECTION FROM THE CORE SPRAY SYSTEM 1.0 EggREOUISITES Stopping Core Spray injection has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE When directed by the GOS/GSS, perform the following:
3.1 Depress the OVERRIDE switches for all sensors that are lit (Panel IF/2F).
3.2 Depress ALL ACTUATED switches whether lit or unlit (Panel 1F/2F).
3.3 Confirm closed Core Spray Parallel Isolation Valves EQI required to be open to assure adequate core cooling.
O 3.4 Secure Core Spray Booster Pumps HQI required to assure adequate core cooling by placing their respective control switch in STOP (Panel IF/2F).
3.5 Secure Core Spray Main Pumps HQI required to assure adequate core cooling by placing their respective control switch in STOP (Panel 1F/2F).
3.6 Verify Core' Spray KEEP FILL TROUBLE (B-3-d) alarm is E2I illuminated.
t l
O (320004A/5) E2-1 l
f Procedure EMG-3200.04A Rev. I Attachment C 4
Page 1 of 2 O SUPPORT PROCEDURE 52 t
RPV DEPRESSURIZATION VIA THE ISOLATION CONDENSER TUBE SIDE VENTS 1.0 PREREOUISITES RPV depressurization using the Isolation Condenser Tube Side vents has been directed by the Emergency Operating Procedures.
2.0 PREPARATION When directed by the GOS/GSS, perform the following, 2.1 verify the following:
- 1. Isolation Condensers are not required to be isolated. j
- 2. Main Condenser is intact.
2.2 Confirm that the Isolation Condenser Vent valve control switches for the Isolation Condenser to be used are in the normal mid-position (Panel 11F).
Isolation Condenser A V-14-5 V-14-20 0 Isolation Condenser B V-14-1 V-14-19 2.3 Open the EOP BYPASS PLUGS panel inside of Panel 10XF.
2.3.1 Remove the bypass plug from position BP2 and insert it into position BPl.
2.3.2 Remove the bypass plug from position BP4 and insert it into position BP3.
3.0 PROCEDURE When directed by the GOS/GSS, perform the following:
3.1 Verify that RPV Water Level is less than 180 in. TAF.
3.2 Confirm open the Isolation Condenser Steam Inlet Valves (IF/2F) for the Isolation Condenser to be used.
Isolation Condenser A V-14-30 V-14-31 Isolation Condenser B V-14-32 V-14-33 O (320004A/6) E3-1 l
Procedure EMG-3200.04A Rev. 1 Attachment C I Page 2 of 2 O
3.3 Open the Isolation Condenser tube side vents (Panel 11F) for the Isolation condenser to be used. .
I Isolation Condenser A V-14-5 V-14-20 Isolation Condenser B V-14-1 v-34-19 O
l i
O (320004A/7) E3-2
OYSTER CREEK NUCLEAR GENERATICG Number Nuslear STiTION rRxEDuRE ruc-32oo.oa Title Revision No.
O EMERGENCY DEPRESSURIZATION - WITH ATWS 1 Applicability / Scope Responsible Office PLANT ENGINEERING i EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 2200 -
This document is within QA plan scope X Yes No Effective Date Safety Reviews Required X Yes No (07/19/93) 07/29/93 Prior Revision 0 incorporated the This Revision 1 incorporates the !
following Temporary Changes: following Temporary Changes:
l 1
N/A N/A LIST OF EFFECTIVE PAGES FACE REVISION 1.0 1 2.0 0 3.0 1 El-1 1 E2-1 1 E2-2 1 O
OYSTER CREEK CONTROLLED DISTRIBUTION DOCUMENT SERIAL NUMBER 7c2 INFO. MGMT. - DCC w W f i ,ia i Signature Concurring' Organization Element Date Originator - EOP COORDINATOR Concurred By "gM,[gg EOP COMMITTEE Mf73
/4 fgg PLANT ENGINEERING DIRECTOR hh/73 hM MGR, PLANT OPERATIONS 7 fg$
I l
0 I n .
Approved By dkgh VICE PRESIDENT & DIRECTOR, OC 7. U 7 3 (320004B) 1.0 l
l 1
OYSTER CREEK NUCLEAR GENERATING Number STATION PROCEDURE EhfG-3200.04B Title Revision No.
O EMERGENCY DEPRESSURIZATION - MTrH ATWS 0
1.0 PURPOSE The purpose of the Emergency Depressurization - With ATWS Procedure is to:
Maintain adequate core cooling Cooldown the RPV to cold shutdown conditions 2.0 REFERENGER 2.1 Proc ;ures
- 107.4, EOP Program Control 2.2 Drawings
- BR 2002, Main, Extraction & Aux Steam System
- BR 3029, DC Control Elem Diagram
- BR E1102,' Emer Condenser Isol Outlet Valve V-14-35
- GE 112C2248, Sht 2, Connection Diagram 11F
- GE 148F262, P&ID - Emergency Condenser System
- GE 237E566, Sht 4, Rx Protection System Elem Diagram 2.3 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.4 2000-STD-1218.04, EOP Writer's Guide 3.0 PRECAUTIONS AND LIMITATIONS 3.1 This procedure gives guidance to the operator for bypassing isolation i signals and automatic scrams which is a departure from the Oyster ,
Creek Technical Specifications. It is permissible to take actions which depart from the plant's Technical Specifications during emergency conditions se authorized by 10 CFR 50.54(x).
O (320004B) 2.0 1
_ _ _ _ _ _ ___________________a
~
OYSTER CREEK NUCLEAR GENERATING Number STATION PROCEDURE EhfG-3200.04B Title Revision No.
O EMERGENCY DEPRESSURIZATION - WITH ATWS .
4.0 ATTACHMENTS 4.1 Attachment A - RPV Control - No ATWS EOP Flowchart DWG: GU 3E-200-08-009 Sh 2 4.2 Attachinent B - Support Procedure 52, RPV Depressurization Via the Isolation Condenser Tube Side Vents e
O 5
O (320004B) 3.0
OYSTER CREEK NUCLEAR GENERATING Number 1 STATION PROCEDURE ENYG-3200.04B A Titic Revision No.
EMERGENCY DEPRESSURIZATION - WITII ATWS 1 ATTACHMENT A Attachment A to EMG-320Q.04B, Emergency Depressurization - With ATWS, is the Emergency Depressurization - With ATWS EOP Flowchart, DWG: GU 3E-200-08-009, Sht 2, Rev. 1.
O k
l l
O "2-~" ->
Procedure EMG-3200.04B
. Rev. 1 Attachment B Page 1 of 1 SUPPORT PROCEDURE 52 RPV DEPRESSURIZATION VIA THE IJOLATION CONDENSER TUBE SIDE VENTS 1.0 PREREOUISITES i RPV depressurization using the Isolation Condenser Tube Side !
Vents has been directed by the Emergency Operating Procedures.
2.0 PREPARATION When directed by the GOS/GSS, perform the following, 2.1 Verify the following:
- 1. Isolation condensers are not required to be isolated. >
- 2. Main Condenser is intact.
2.2 Confirm that the Isolation Condenser Vent valve control switches for the Isolation Condenser to be used are in the normal mid-position (Panel 11F).
Isolation Condenser A V-14-5 V-14-20 Isolation Condenser B V-14-1 V-14-19 2.3 Open the EOP BYPASS PLUGS panel inside of Panel 10XF.
2.3.1 Remove the bypass plug from position BP2 and insert it into position BPl. -
2.3.2 Demove the bypass plug from position BP4 and insert it into position BP3.
3.0 PROCEDURE When directed by the GOS/GSS, perform the following:
3.1 Verify that RPV Water Level is less than 180 in. TAF.
3.2 Confirm open the Isolation Condenser Steam Inlet Valves (IF/2F) for the Isolation Condenser to be used.
Isolation Condenser A V-14-30 V-14-31 Isolation Condenser B V-14-32 V-14-33 O
(320004B/5) E2-1
Proesdure EMG-3200.04B Rev. 1 l j
Af.tachment B Page 2 of 2
, 3.3 Open the Isolation f:endenser tube side vents (Panel 11F) for the Isolation r.ondenser to be used.
1 Isolation Condenser A V-14-5 V-14-20 Isolation Condenser B V-14-1 ;
V-14-19 i i
O ;
1 (320004B/6) E2-2 f l
I l
OYSTER CREEK NUCLEAR GENERATING Number l
. U$ ME STATION PROCEDURE EMG-3200.05 I Title Revision No.
Q STEAM COOLING 4 Applicability / Scope Responsible Office PLANT ENGINEERING !
EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 2200 !!
This document is within QA plan scope X Yes No Effective Date Safety Reviews Required X Yes No .
( (07/19/93) 07/29/93 i Prior R-vision 3 incorporated the This Revision 4 incorporates the f following Temporary Changes: following Temporary Changes:
i N/A N/A >
LIST OF ErrcCn vs PAGES PAGE REVISION 1.0 4 2.0 3 El-1 4 O r
'I .N I': b (O b [ h(
'T TR LiiO DiSTH!fuJTION DUM E NT SER!AL NUMEER _72 IME:r) f,/r'_gA i T r3r r Signature Concurring Organization Element Date ]
Originator p EOP COORDINATOR 5 Concurred By 4//M$c y, /[ EOP COMMITTEE Iy/fyy3
/% @y. PLANT ENGINEERING DIRECTOR I/g /cf 3
- h[h MGR, PLANT OPERATIONS *) fg A3
/ /
O!
O Approved By fkh VICE PRESIDENT & DIRECTOR, OC 7,M)3 j
(320005) 1.0 l
l l
t- OYSTER CREEK NUCLEAR GENERATING Number l g STATION PROCEDURE EMG-3200.05
{
O Title Revision No.
STEAM COOLING 3 1.0 EMEP_QSE b The purpose of the Steam Cooling Procedure is to:
Maintain adequate core cooling
2.0 REFERENCES
2.1 Procedures
- 107.4, EOP Program Control 2.2 - 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.3 - 2000-STD-1218.04, EOP Writer's Guide 3.0 ATTACHMENTS 3.1 Attachment A - Steam Cooling EOP Flovchart DWG: GU 3E-200-08-008 Sht 3 -
O :
O (320005) 2.0
g OYSTER CREEK NUCLEAR GENERATING Number i g STATION PROCEDURE EMG-3200.05 ,
Title Revision No. '
Os' STEAM COOLING 4 r.
ATTACHMENT A I
i i
Attachment A to EMG-3200.05, steam Cooling is the Steam Cooling EOP Flowchart,
- DWG: GU 3E-200-08-008, Sh 3, Rev. 1.
l e
l l
t L
i l
l l
l I
O El-1 (320005/3)
_____ --_-\
s' OYSTER CREEK NUCLEAR GENERATING Number
& Nrrelar STAT 10N PROCEoUmE tuo-32oo.osi Title Revision No.
Q RPV FLOODING - NO ATWS 1 Applicability / Scope Responsible Office PLANT ENGINEERING EMERGENCY OPERATING PROCEDURE POR OYSTER CREEK 2200 II This document is within QA plan scope X Yes No Effective Date Safety Reviews Required X Yes No (07/19/93', 07/29/93 Prior Revision 0 incorporated the This Revision 1 incorporates the following Temporary Changes: following Temporary Changes:
N/A N/A LIST OF EFFECTIVE PAGLS I
PAGE REVISION PAGE REVISION 1.0 1 E6-2 1 2.0 0 E7-1 1 3.0 1 E7-2 1 El-1 1 E2-1 1 E3-1 1 E4-1 1 O E4-2 E4-3 1
1 E5-1 1 t gj 2 OYSTER CREEK E6-1 1 CONTROLLED DIST!-UBUTION DOCUMENT sciuAL NuMcEn 7R INFO McuT nce Signature Concurring Organization Element Date Originator EOP COORDINATOR Concurred sg, EOP COMMITTEE M((93 M,f(L<#g PLANT ENGINEERING DIRECTOR Y/$/g3 kYkd ~
MGR, PLANT OPERATIONS 7 Q fo)$
j o n I -
Approved By j f
k VICE PRESIDENT & DIRECTOR, OC 7.d.7 3 .
O <>>eee -
1.,
"""""""c"^""""^"*
Nuslear STATION PROCEDURE
""='""
DIG-3200.08A 1
Title . Revision No.
RPV FLOODING - NO ATWS 0 1.0 PURPOSE The purpose of the RPV Flooding - NO ATWS Procedure is to:
Maintain adequate core cooling during conditions where RPV water i level cannot be determined and the Reactor is shutdown. !
2.0 REFERENCES
2.1 Procedures
- 107.4, EOP Program Control 2.2 Drawings
- BR 2002, Main, Extraction & Aux Steam System
- BR 3029, DC Control Elem Diagram
- BR E1102, Emer Condenser Isol Outlet Valve V-14-35
- GE 112C2248, Sht 2, Connection Diagram 11F
- GE 148F262, P&ID - Emergency Condenser System
- GE 237E566, Sht 2, Rx Protection System Elem Diagram r 2.3 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.4 2000-STD-1218.04, EOP Writer's Guide 3.0 PRECAUTIONS AND LIMITATIONS ;
3.1 This procedure gives guidance to the operator for bypassing isolation signals and automatic scrams which is a departure from the Oyster Creek Technical Specifications. It is permissible to take actions which depart from the plant's Technical Specifications during emergency conditions as authorized by 10 CFR 50.54(x). .
l 1
(320008A) 2.0 l
l
Nrder 'S'"" c"""" """'"^" """""^""
STATION PROCEDURE EMG-3200.08A Title Revision No.
05 RPV FLOODING - NO ATWS 1 4.0 ATTACHMENTS F 4.1 Attachment A - RPV Flooding EOP Flowchart DWG: GU 3E-200-08-012 sht 1
. .L 4.2 Attachment B - Support Procedure 58, Feed and Condensate System Operation for RPV Flooding .
4.3 Attachment C - Support Procedure 59, CRD System Operation for RPV Flooding 4.4 Attachment D - Support Procedure 60, Core Spray for RPV Flooding 4.5 Attachment E - Support Procedure 61, Fire Water for RPV Flooding 4.6 Attachment F - Support Procedure 62, Condensate Transfer for RPV Flooding 4.7 Attachment G - Support Procedure 63, Liquid Poison for RPV Flooding O
l l
~
O (32000BA) 3.0
OYSTER CREEK NUCLEAR GENERATING Number f_ STATION PROCEDURE D{G.3200.08A Title Revision No.
O RPV FLOODING - NO ATWS 1 ATTACHMENT A t:
Attachment A to EMG-3200 08A, RPV Flooding - No ATWS, is the RPV Flooding - No ATWS EOP Flowchart, DWG: GU 3E-200-08-0012, Sht 1, Rev. 1.
l I
O 1 l
O El-1 (32000BB/4)
i I
Procedure EMG-3200.08A Rev. I t Attachment B !
Page 1 of 1
)
l O~ SUPPORT PROCEDURE 58 1
FEED AND CONDENSATE SYSTEM OPERATION FOR RPV FLOOD 1dG l
1.0 PREREOUISITES RPV Flooding using the Feed and Condensate System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Confirm all available Condensate and Feedwater Pumps are operating.
3.2 Confirm a minimum of 2 Condensate Demineralizers are in service per operating Condensate Pump.
3.3 Confirm open the Heater Bank Outlet valves.
3.4 Confirm open the MFRV Block valves.
3.5 Slowly throttle open the Feedwater Regulating Valves to maintain RPV pressure as directed by the GSS/GOS.
3.6 Monitor Hotwell levels to ensure adequate Condensate Pump NPSH. (Panel SF/6F) 3,7 Maximize Hotwell level makeup (32000BA/5) E2-1
Procsdura EMG-3200.08A
- Rsv. 1 Attechment C
- Page 1 of 1 s
SUPPORT PROCEDURE 59 CRD SYSTEM FOR RPV FLOODING 1.0 PREREOUISITES :
RPV Flooding using the CRD System has been directed by the Emergency Operating Procedures. .
2.0 PREPARATION None 3.0 PROCEDURE
- CAUTION
- Operating two pumps at greater than 150 gpm or one pump at greater
- than 90 gpm may result in a pump trip.
3.1 Confirm all available CRD pumps are running (Panel 4F).
3.2 Open CRD Bypass Isolation valve, V-15-237 (RB 23 SE).
3.3 Monitor Flow on Flow Gage FI-225-2 and throttle open CRD Bypass Valve V-15-30 (RB 23 SE) to maintain RPV pressure as directed by the GSS/GOS, AEE So as not to exceed 150 gpm flow for two pump operation or 90 gpm for one pump operation.
k
~
(32000BA/6) E3-1
Procrdure EMG-3200.08A Rev. 1 Attechment D Page 1 of a SUPPORT PROCEDURE 60 CORE SPRAY FOR RPV FLOODING 1.0 PREREOUISITES RPV Flooding using the Core Spray System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 IE Core Spray actuating signals are present, THEN override Core Spray initiation logic by depressing the OVERRIDE switches for all sensors that are lit and depressing all ACTUATED switches, wheter lit or unlit.
3.0 PROCEDURE 3.1 IE a Non-ATWS condition exists, THEN perform the following:
3.1.1 **************************************************************
s FAUTION
- Diesel Generator overload will result if a Core Spray *
- Main and Booster Pump are started with a Diesel Generator
- t
- load of greater than 2000 kw.
- IE Bus 1C or ID are being supplied by an Emergency Diesel Generator, THEN verify that adequate load margin is available so as NOT to exceed EDG load limit when starting Core Spray Pumps.
3.1.2 Confirm that one Core Spray Main Pump in each system has started (Panel IF/2F).
3.1.3 Confirm that one Core Spray Booster Pump in each system has started (Panel IF/2F).
(320008A/7) E4-1
\
l l
_m.
Procrduro EMG-3200.08A Rev. I s Attachment D Page 2 of 1 WHEN reactor pressure decreases to 310 psig,
( 3.1.4 THEN cycle the Core Spray Parallel Isolation Valves as required to maintain RPV pressure as directed by the GSS/GOS.
3.1.5 NOTE Booster pump operation is HQI required for injection to occur.
II all Core Spray Pumps that are running are not required to assure adequate core cooling.
THEN inform the GOS/GSS and secure the Core Spray Pumps that are not required to assure adequate core cooling.
3.1.6 IE the Core Spray pumps in a system are not operating, THEN verify Core Spray KEEP FILL TROUBLE (B-3-d) alarm is
\ not illuminated and Pump Minimum Flow Valves are closed (Panel 1F/2F).
3.2 IE An ATWS condition exists THEN perform the following:
3.2.1 ***********************************************************
- CAUTION *
- Diesel Generator overload will result if a Core Spray *
- Main Pump is started with a Diesel Generator load of
- greater than 2250 kw.
IE Bus 1C or ID are being supplied by an Emergency Diesel Generator, :
THEN verify that adequate load margin is available so as HQI to exceed EDG load limit when starting Core Spray Pumps.
(32000BA/B) ,
E4-2
Procedure EMG 3200.08A Rev. l' s Attachment D Page 3 of a f O 3.2.2 Start one Core Spray Main Pump. (Panel IF/2F) 3.2.3 Confirm open the selected system Discharge Valve >
(V-20-12 or V-20-18). (Panel IF/2F) I; 3.2.4 Open a Parallel Isolation Valve in the selected system, (V-20-15, V-20-40, V-20-21 or V-20a41).
(Panel IF/2F) 3.2.5 Start additional Main Pump or open additional ,
Parallel Isolation Valves as directed by the GSS/GOS.
l 1
l I
(320008A/9) E4-3
Procedure EMG-3200.08A Rev. 1 Attachment E SUPPORT PROCEDURE 61 FIRE WATER FOR RPV FLOODING H
1.0 PREREQUISITES RPV Flooding using the Firewater System via the Core Spray System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 II Core Spray actuating signals are present, THEN override Core Spray initiation logic by depressing the OVERRIDE switches for all the sensora that are lit and depressing all ACTUATED switches, whether lit or unlit.
3.0 PROCEDURE NOTE Overriding Core Spray initiation logic may be required.
3.1 II Core Spray System I is designated to be used, THEN inject fire water as follows:
3.1.1 Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 1.
3.1.2 Place Core Spray System 1 Main Pump Control Switches in PULL TO LOCK position.
3.1.3 Close Tell-Tale Drain Valve, V-20-91 (RB 23 North or North Side RB outside). l l
l 3.1.4 Confirm running all available Diesel Fire Pumps by placing their control switches in MAN position (Panel 13R).
3.1.5 Open Fire Water Supply valve, V-20-83 (RB 23 North or North Side RB outside). )
(32000BA/10) ES-1
Procedure EMG-3200.08A Rev. 1 !
Attachment E j Page 2 of 1 l
3.1.6 Confirm open Core Spray System 1 Discharge valve, !
V-20-12 (Panel IF/2F).
3.1.7 Confirm open either Core Spray System 1 Parallel Isolation ;
l' valve, v-20-15 or V-20-40 (Panel IF/2F). i 3.1.8 Confirm closed Core Spray System 1- Test flow Return Valve, V-20-27 (Panel 1F/2F). ,
3.1.9 Close Core Spray System 1 Pump Suction Valves, V-20-32 and V-20-3 (Panel IF/2F). 7 NQTE Overriding Core Spray initiation logic may be required.
i 3.2 IE Core Spray System 2 is designated to be used, THEN inject fire water as follows: .
3.2.1 Confirm stopped the Core Spray Main and Booster Pumps
('
in Core Spray System 2.
3.2.2 Place Core Spray System 2 Main Pump Control Switches in PULL TO LOCK position 3.2.3 Close Tell-Tale Drain Valve, V-20-90 (RB 23 South, or South Side RB outside).
3.2.4 Confirm running all available Diesel Fire Pumps by placing their control switches in MAN position (Panel 13R). 1 3.2.5 Open Fire Water Supply Valve, v-20-82 (RB 23 South or !
South Side RB outside). .
3.2.6 Confirm open Core Spray System 2 Discharge Valve, V-20-18 i
(Panel IF/2F).
l (320008A/11) ES-2 l
t
Procedure EMG-3200.08A ;
Rsv. 1 5
Attachment E Page 3 of 1 ,
3.2.7 Confirm open either Core Spray System 2 Parallel Isolation Valve, V-20-21 or V-20-41 (Panel 1F/2F).
3.2.8 Confirm closed Core Spray System 2 Test Flow Return
valve V-20-26, (Panel 1F/2F). ,
3.2.9 Close Core Spray System 2 Pump Soction Valves, v-20-33 and V-20-4 (Panel IF/2F).
l p
O O
(32000BA/12) ES-3
4 Procedure EMG-3200.08A Rev. 1 g
Attachment F Page 1 of 1 O d SUPPORT PROCEDURE 62 8 CONDENSATE TRANSFER FOR RPV FLOODING -
1.0 PREREOUISITES RPV Flooding using the Condensate Transfer System via the Core Spray System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 II Core Spray actuating signals are present, THEN override Core Spray initiation logic by depressing the OVERRIDE switches for all the sensors that are lit and depressing all ACTUATED switches, whether lit or unlit.
2.2 This procedure requires the use of an MB-1 key.
3.0 PROCEDURE NOTE Overriding Core Spray initiation logic may be required.
3.1 II Core Spray System 1 is designated to be used and Fire Water to Core Spray System I is not in service, THEN inject Condensate Transfer as follows:
3.1.1 Place the Core Spray Main Pump control switches in PULL TO LOCK position.
3.1.2 Close Core Spray System 1 Pump Suction Valves V-20-32 and V-20-3 (Panel 1F/2F) 3.1.3 Unlock and open Regulator Bypass valves, V-11-110 and V-11-111 (RB 51).
3.1.4 Confirm open Core Spray System 1 Discharge valve, V-20-12 (Panel IF/2F).
(320008A/13) E6-1
Proceduro EMG-3200.08A Rgv. I s Attachment F Page 2 of 1 I~ \ 3.1.5 Confirm open either Core Spray System 1 Parallel b
Isolation valve, V-20-15 or V-20-40 (Panel IF/2F).
3.1.6 Confirm closed Core Spray System 1 Test Discharge i
valve, V-20-27 (Panel IF/2F).
3.1.7 Start all available Condensate Transfer Fusps (Panel SF/6F).
NOTE ,
Overriding Core Spray initiation logic may be required.
3.2 IF Core Spray System 2 is designated and Fire Water to Core Spray System 2 is not in service, THEN inject Condensate Transfer as follows:
3.2.1 Place the core Spray Main Pump control switches in PULL TO LOCK position.
3.2.2 Close Core Spray System 2 Pump Suction Valves V-20-33 and V-20-4 (Panel IF/2F) 3.2.3 Unlock and Open Regulator Bypass valves, V-11-109 and V-11-108 (RB 75').
3.2.4 Confirm open Core Spray System 2 Discharge valve, V-20-18 (Panel IF/2F).
3.2.5 Confirm open either Core Spray System 2 Parallel Isolation valve, v-20-21 or V-20-41 (Panel IF/2F).
3.2.6 Confirm closed Core Spray System 2 Test Flow Return valve, V-20-26 (Panel IF/2F).
3.2.7 Start all available Condensate Transfer Pumps
. (Panel SF/6F).
(32000BA/14) E6-2 ,
1
Proceduro EMG-3200.0BA-Rsv. 1 Attachment G Page 1 of 1 O SUPPORT PROCEDURE 63 LIOUID POISON FOR RPV FLOODING li 1.0 PREREOUISITES RPV Flooding using the Standby Liquid Control System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 This procedure requires the use of an MB-1 key.
3.0 PROCEDURE 3.1 IE Rx Bldg. 95* Elevation is accessible and time permits, THEN perform the following to lineup Demineralized Water for injection via the SLC System:
3.1.1 Unlock and close Standby Liquid Control Tank Outlet
/\ Valve, V-19-4 (RB 95 West).
3.1.2 Unlock and open Test Tank Outlet Valve, V-19-11 (RB 95 West).
3.1.3 Fill Test Tank by performing the following:
- 1. Open Demin Water Isolation Valve V-12-14 (RB 95 West).
- 2. Open Test Tank Demin Water Supply valve V-19-12 (RB 95 West).
............................w.........*******............................
- CAUTION *
- Due to pressure fluctuations, Fuel Zone Level Indicator Channel 'A'
- and 'C' will not provide accurate indication of reactor water level
- if a standby Liquid Control Pump is injecting to the RPV and should
- not be used.
3.2 Start SLC Pump A by placing the standby LIQUID CONTROL Keylock in the FIRE SYS 1 position (Panel 4F).
(320008A/15) E7-1
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Procidure EMG-3200.08A--
Rsv. 1 .J
, Attachment G Page 2 of 2 o'
i' 3.3 IE Pump A does HQI start QB System 1 Squib valve does E2I fire, M THEN Start SLC Pump B by placing the STANDBY LIQUID CONTROL Keylock in the FIRE SYS 2 position (Panel 4F). .
3.4 Monitor system parameters for proper system performance.
3.5 IE Demineralized Water is being used for injection, THEN throttle Test Tank Demin Water Supply Valve V-19-12 (RB 95 West) as required to maintain a constant level in the Test Tank.
(320008A/16) E7-2
OYSTER CREEK CUCLEAR GENERATING Number A E M7. STATION PROCEDURE EMG-3200.08B Title Revision No.
O arv r'ooniso - w1Tu rrws 1 Applicability / Scope Responsible Office PLANT ENGINEERING EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 2200 k This document is within QA plan scope X Yes____No Effective Date Safety Reviews Required X Yes__No (07/19/93) 07/29/93 Prior Revision 0 incorporated the This Revision 1 incorporates the following Temporary Changes: following Temporary Changes:
N/A N/A LIST OF nrrnerivz PAGES F_A_qE REVISION 1.0 1 2.0 0 3.0 1 El-1 1 E2-1 1 E3-1 1 E4-1 1 O E4-2 E4-3 1
1
-s OYSTER CREEK
, CONTROLLED DISTRIBUTION DOCUMENT SER!AL NUMBER _78 INFO. MGMT. - DCC Signature . Concurring Organization Element Date Originator j, EOP COORDINATOR- p
';7/p/? g Concurred By }/[' r,((A/*[ EOP COMMITTEE "
M Wh PLANT ENGINEERING DIRECTOR 9/7/03 j, gMbJM MGR, PLANT OPERATIONS 79 98 O u - -
Q Approved Dy hM% vICE rRESIDENT s DIRECTOR, OC ?-(9 3 (320008B) 1.0 l
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STATION PROCEDURE EMG-3200.08B Title Revision No.
O RPV FLOODING - WITH ATWS 0 l
1.0 PURPOSE L' The purpose of the RPV Flooding - With ATWS Procedure is to: ,
Maintain adequate core cooling during conditions where RPV water level cannot be determined and the Reactor is in an ATWS condition.
2.0 BEFERENCES 2.1 Procedures i
- 107.4, EOP Program Control 2.2 Drawings
- BR 2002, Main, Extraction & Aux Steam System
- BR 3029, DC Control Elem Diagram
?
- BR E1102, Emer Condenser Isol Outlet Valve V-14.-35
- GE 112C2248, Sht 2, Connection Diagram 11F
- GE 148F262, P&ID - Emergency Condenser System
- GE 237E566, Sht 2, Rx Protection System Elem Diagram 2.3 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.4 2000-STD-1218.04, EOP Writer's Guide 3.0 PRECAUTIONS AND LIMITATIONS 3.1 This procedure gives guidance to the operator for bypassing isolation signals and automatic scrams which is a departure from the Oyster f Creek Technical Specifications. It is permissible to take actions l
which depart from the plant's Technical Specifications during emergency conditions as authorized by 10 CFR 50.54(x).
l l
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"*r BfG-3200.08B l
I Title Revision No. I O RPV FLOODING - WITH ATWS 1 I l
1 4.O ATTACHMENTS h 4.1 Attachment A - RPV Flooding EOP Flowchart j DWG: GU 3E-200-08-013 Sh 1 4.2 Attachment B - Support Procedure 58, Feed and Condensate System Operation for RPV Flooding 4.3 Attachment C - Support Procedure 59, CRD System Operation for RPV Flooding 4.4 Attachment D - Support Procedure 60, Core Spray for RPV Flooding O
O (320008B) 3.0 l
g gp OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE Number j- EMG-3200.08B Title Revision No. l
( RPV FLOODING - WITH ATWS 1 ATTACHMENT A 1l Attachment A to EMG-3200.08B, RPV Flooding - With ATWS, la the RPV Flooding -
With ATWS EOP Flowchart, DWG: GU'3E-200-08-0013, Sht 1, Rev. 1.
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Procsdure EMG-3200.08B R;v. 1
, Attachment B i
Page 1 of 1 O SUPPORT PROCEDURE 58 FEED AND CONDENSATE SYSTEM OPERATION FOR RPV FLOQpIFS b
1.0 PREREOUISITES '
RPV Flooding with the Feed and Condensate System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Confirm all available Condensate and Feedwater Pumps are operating.
3.2 Confirm a minimum of 2 Condensate Demineralizers are in service per operating Condensate Pump.
3.3 Confirm open the Heater Bank Outlet valves.
3.4 Confirm open the MFRV Block valves.
3.5 Slowly throttle open the Feedwater Regulating Valves to maintain RPV pressure as directed by the GSS/GOS.
3.6 Monitor Hotwell levels to ensure adequate Condensate Pump NPSH. (Panel SF/6F) 3.7 Maximize Hotwell level makeup.
O O
(320008B/5) E2-1
Procsdure EMG-3200.08B Rev. 1 Attachment C
- Page 1 of 1 i SUPPORT PROCEDURE 59 CRD SYSTEM FOR RPV FLOODING 1.0 PREREOUISITES k RPV Flooding with the CRD System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE
- CAUTION *
- Operating two pumps at greater than 150 gpm or one pump at greater *
- than 90 gpm may result in a pump trip.
- 3.1 Confirm all available CRD pumps are running (Panel 4F).
3.2 Open CRD Bypass Isolation Valve, V-15-237 (RB 23 SE).
3.3 Monitor Flow on Flow Gage FI-225-2 and throttle open CRD Bypass Valve V-15-30 (RB 23 SE) to maintain RPV pressure as directed by the GSS/GOS, 1 Nm so as not to exceed 150 gpm flow for two pump operation or 90 gpm for one pump operation.
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(320008B/6) E3-1 l
I
Procedure EMG-3200.08B Rsv. 1 Attachment D i Page 1 of 2 SUPPORT PROCEDURE 60
~J CORE SPRAY FOR RPV FLOODING 1.0 PREREQUISITES RPV Flooding using the Core Spray System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 IE Core Spray actuating signals are present, TEEN override Core Spray initiation logic by depressing the OVERRIDE switches for all sensors that are lit and depressing all ACTUATED switches, whether lit or unlit.
3.0 PROCEDURE 3.1 II a Non-ATWS condition exists, THEN perform the following:
O 3.1.1 **************************************************************
CAUTION *
- Diesel Generator overload will result if a Core Spray *
- Main and Booster Pump are started with a Diesel Generator
- load of greater than 2000 kw.
II Bus 1C or ID are being supplied by an Emergency Diesel Generator, THEN verify that adequate load margin is available so as EQI to exceed EDG load limit when starting Core Spray Pumps.
3.1.2 Confirm that one Core Spray Main Pump in each system has started. (Panel 1F/2F) . _ _
3.1.3 Confirm that one Core Spray Booster Pump in each system has started. (Panel 1F/2F) ___
O (320008B/7) E4-1
Procsdura EMG-3200.08B Rav._) l
, Attachment D Page Z of 1 Os 3.1.4 WHEN reactor pressure decreases to 310 psig, THEN cycle the Core Spray Parallel Isolation Valves as required to maintain RPV pressure as directed by the GSS/GOS. I:
NOTE Booster pump operation is HQI required for injection to occur.
3.1.5 IE all Core Spray Pumps that are running are not required to assure adequate core cooling, THEN inform the GSS/GOS and secure the Core Spray Pumps that are not required to assure adequate core cooling.
3.1.6 IE the Core Spray Pumps in a system are not operating, IHEN verify Core Spray KEEP FILL TROUBLE (B-3-d) alarm is not illuminated and Pump Minimum Flow Valves are closed (Panel IF/2F). ;
3.2 IE An ATWS condition exists, THEN perform the following:
3.2.1 ***********************************************************
- CAUTION *
- Diesel Generator overload will result if a Core Spray *
- Main Pump is started with a Diesel Generator load of
- greater than 2250 kw.
IE Bus 1C or ID are being supplied by an Emergency Diesel Generator, THEN verify that adequate load margin is available so as HQI to exceed EDG load limit when starting Core Spray Pumps.
(320008B/8) E4-2
Proceduro EMG-3200.08B Rev..J 4
Attachment D Page } of }
3.2.2 Start one Core Spray Main Pump. (Panel 1F/2F) 3.2.3 Confirm open the selected system Discharge valve n (V-20-12 or V-20-18). (Panel IF/2F) 3.2.4 Open a Parallel Isolation Valve in the selected system, (V-20-15, V-20-40, V-20-21 or V-20-41).
(Panel 1F/2F) 3.2.5 Start additional Main Pump or open additional Parallel Isolation Valves as directed by the GSS/GOS.
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OYSTER CREEK NUCLEAR GENERATING Number Nuslear STAT = r = CEDuRE zuc-32oo.1o Title Revision No.
O cour^1xuest r'oonino >
l l
Applicability / Scope Responsible Office PLANT ENGINEERING EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 2200 F This document is within QA plan scope X Yes No Effective Date Safety Reviews Required X Yes No (07/19/93) 07/29/93 Prior Revision 4 incorporated the This Revision 5 incorporates the following Temporary Changes: following Temporary Changes:
N/A N/A LIST OF EFFE NIVE PAGES PAGE REVISION PAGE REVISION 1.0 5 E7-1 5 2.0 4 E7-2 5 3.0 5 E7-3 5 El-1 5 E7-4 5 E2-1 5 E8-1 5 E3-1 5 E8-2 4 E3-2 5 E9-1 5 O E4-1 E5-1 5
5 E9-2 5 f
ES-2 5 E6-1 5 E6-2 5 5
%j OYSTER CREEK ;
CONTROLLED DISTRIBUTION ;
DOCUMENT SERIAL NUf GER _~2d I I N I'O f
w Return Valve V-20-26 (Panel 1F/2F) . 3.2,6 Unlock and open the following CST supply valves: V-20-1 (NW Corner Room) V-20-2 (SW Corner Room) V-20-35 (SW Corner Room) I l 1 1 k (320010/13) E6-3 . Procrdure EMG-3200.10 Rav. 5 Attachment F . . Page 4 of 4 ( 3.2.7 **************************************************** ( . .
- CAUTION *
- Diesel Generator overload will result if a *
- Core Spray Main and Booster Pump are started *
- with a Diesel Generator load of greater than *
- 2000 KW.
- II Bus IC or ID are being supplied by a Emergency Diesel Generator, l THEN verify that adequate load margin is available so as HQI to exceed EDG load limit when starting Core Spray Pumps.
3.2.8 Start Core Spray System 1 Main Pump NZO1B or NZOID (Panel IF/2F). es 3.2.9 Confirm open Core Spray System 2 Discharge a valve V-20-18 (Panel 1F/2F). 3.2.10 Confirm open either Core Spray System 2 Parallel Isolation Valve V-20-21 or V-20-41 (Panel IF/2F). 1 3.2.11 Start the Core Spray Booster Pump associated with I the running main pump or the other main pump as directed by the GSS/GOS. I 1 (320010/14) E6-4 I - ProcIdura EMG-3200.10 l Rev. 5 1 Attachment G - - Page 1 of 4 () SUPPORT PROCEDURE 38 DETERMINING PRIMARY CONTAINMENT WATER LEVEL
- 1. 0 PREREQUISITES h 1.1 Determination of Primary Containment Water Level has been directed by the Emergency Operating Procedures.
1.2 Primary Containment Water Level is greater than the range of the wide range torus level recorder (0-360 inches) on Panel 16R. 2.0 PREPARATION None 3.0 PROCEDURE 3.1 Calculate Primary Containment Water Level by completing the following: 3.1.1 Record Torus pressure from one of the following:
- 1. Digital indicator on Panel 4F
- 2. Computer Point ID PTIP12
- 3. PT-IP12 on Panel IF/2F P(Torus) = osig 0- 3.1.2 Record Drywell pressure from PI-IP08 on Panel IF/2F P(DW) = osig 3.1.3 Calculate AP ,
AP = P(Torus) - P(DW) = osid 3.1.4 II AP is greater than 16 paid THEN continue at Step 3.2 of this procedure. 3.1.5 Determine Primary Containment Water Level using Figure 38-1. 3.2 IE Torus - DW AP is greater than 16 paid, THEN calculate Primary Containment Water Level by completing the following: 3.2.1 Record Torus pressure from one of the following:
- 1. Digital indicator on Panel 4F
- 2. Computer Point ID PTIP12
- 3. PT-IP12 on Panel IF/2F P(Torus) = osig
\ (320020/15) E7-1 l , i Proc dure EMG-3200.10 l Rev. 5 Attachment G Page 2 of 1 0 3.2.2 Record Drywell pressure from Sample Entry l l Pressure gauge on H2/02 Panel IT-1B or IT-1A (Reactor Bldg El. 75'). P(H2 /02 ) D819 i 3.2.3 Calculate AP AP = P(Torus) - P(H2 /02 ) = esid . 3.2.4 Determine Primary Containment Water Level using Figure 38-2. r 3 f f i (320010/16) E7-2 , w - I
- Proc: dure EMG-3200.10 Rsv. 5 Attachment G Page 3 of 1 FIGURE 38-1 CONTAINMENT WATER LEVEL DETERMINATION USING DW PRESSURE INDICATION FROM PANEL 1F/2F l l
l 1 800 ) 775. .- l 1 750= 725 - 700R ' ' ' l l 1 \ 675= . l 0650'- - l 1 . l u 2c 925 . . 1 z 600-l ' ~ O a575-- w -- .- :- : -l---;- :- i-. "550- -- - e 525 w - i <( . . . . . . . l 3 500. ---: ,----s- , 475 - - ~ / (4.7 psidj 451 l'nch'es) f , 450 - / i 425' 400= - --- 375m , (113 psid .. 3 85 in c h'.e s) . - . 3501 r y l r y 1 t 71 t 7 y -[ ppjr1 0 1 2 3 4 5 6 7 8 9 101112131415161718 P(Torus) - P(DW) = psid (320010/17) E7-3 r Proc dura EMG-3200.20 R v. 5 Atitachment G Page 4 of 4 FIGURE 38-2 C.QNTAINMENT WATER LEVEL DETERMINATION USING DW PRESSURE INDICATION FROM THE Hg/Qg PANELS RB 75' .. ., . . .,.. ... .. .... . . .. ...... o ] 3QQ 1275 - '-- 1250i- :- 1225:- - '(31:.9 : psi,d, :121,2 inches) >- - t 1175r- ' - -: -:- ~ 1150;- . . . . . .. '. . .. : . . - t -: m1125L w : /. . I 1100 - - ' u : . . . . E 1075r " z 10 50 :- (25.6 psidj 1040 inches) . ' d 1025 :- w a 1000- . x 9757 - ' - - " -~ w . . . ~ ' - ' <= 950:- - 3 . - - :- : 925'- . 900'- - - 875 ' - - -/ .
- / . .
- ./
850:- 825:- . .- - s- . 800~- j'- ' - - -- 775- ' . 750 l llIll LlIllI-IIIlIll LI 15 1617 18 19 20 21 22 23 24 25 26 27 28.29 30 31 32 33 34 35 ' P(Torus) - P(H2/02) = psid (320010/18) E7-4 Procrduro EMG-3200.10 Rev. 5 Attachment H Page 1 of 2 SUPPORT PROCEDURE 57 OPENING THE MSIVs TO VENT THE RPV 1.0 PREREOUISITES p Opening the MSIVs to vent the RPV has been directed by the Emergency Operating Procedures. 2.0 PREPARATION 2.1 Obtain four (4) bypass plugs from the EOP Tool Box in the Control Room. 2.2 Open the EOP BYPASS PLUGS panel in the rear of Panel 6R. 2.2.1 Insert a bypass plug into position BP3. 2.2.2 Insert a bypass plug into position BP4. 2.3 Open the EOP BYPASS PLUGS panel in the rear of Panel 7R. 2.3.1 Insert a bypass plug into position BP3. 2.3.2 Insert a bypass plug into position BP4. 2.4 Reset the MSIV isolation signal by momentarily depressing g the MAIN STEAM ISOLATION RESET pushbutton (Panel 4F). 2.5 Confirm the TEST SWITCH V-6-395 is in the NOR position (Panel 11F). 2.6 Open the INSTRUMENT AIR ISOLATION VALVE, V-6-395, by placing its control switch in the OPEN position (Panel 11F). 2.7 Inform GSS/GOS that MSIVs are ready to be opened. 3.0 PROCEDURE When directed by the GSS/GOS, perform the following:
- CAUTION *
- Damage to piping or components downstream of the MSIVs *
- could result if MSIVs are opened with differential *
- pressure greater than 360 psid.
- 3.1 Regardless of the differential pressure open the Main Steam Isolation Valves (Panel 11F). l l
) (320010/19) E8-1 l i Procedure EMG-3200.10 t Rsv. 4 Aftachment H , Page 2 of 2 0 3.2 Log each operation of the MSIV and the differential pressure across the valves when opened in the CRO Log. '6 I t 1 (320010/19) E8-2 I Proczdure EMG-3200.10 Rev. 5 i Attachment I I Page 1 of 1 O surroar raocuouas s2 OPENING IC TUBE SIDE VENTS TO VENT THE RPV 1.0 PREREOUISITES Venting the RPV using the Isolation Condenser Tube Side Vents l has been directed by the Emergency Operating Procedures. 2.0 PREPARATICN When directed by the GOS/GSS, perform the following, 2.1 Verify the following:
- 1. Isolation Condensers are not required to be isolated.
- 2. Main Condenser is intact.
2.2 Confirm that the Isolation Condenser Vent valve control switches for the Isolation Condenser to be used are in nonnal mid-position (Panel 11F). Isolation Condenser A V-14-5 V-14-20 Isolation Condenser B V-14-1 V-14-19 2.3 Open the EOP BYPASS PLUGS panel inside of Panel 10XF. 2.3.1 Remove the bypass plug from position BP2 and insert it into position BPl. 2.3.2 Remove the bypass plug from position BP4 and insert it into position BP3. 3.0 P_RLOCEDURE When directed by the GOS/GSS, perform the following: 3.1 Verify that RPV Water Level is less than 180 in TAF. 3.2 Confirm open the Isolation Condenser Steam Inlet Valves (1F/2F) for the Isolation Condenser to be used. Isolation Condenser A V-14-30 V-14-31 Isolation Condenser 11 V-14-32 V-14-33 (320010/21) E9-1 Procsdure EMG-3200.10 Rev. 5 Attachment I 3 Page 2 of 1 0 3.3 Open the Isolation Condenser tube side vents (Panel 11F) i for the Isolation Condenser to be used. Isolation Condenser A V-14-5 b V-14-20 Isolation Condenser B V-14-1 V-14-19 t (320010/22) E9-2 = OYSTER CREEK NDCLEAR GENERATING Number
- , 4 U$lM7 '
STATION PROCEDURE EMG-3200.11 Title Revision No. 1 Q 4 SECONDARY CONTAINMENT CONTROL 5 l Applicability / Scope , Responsible Office l PLANT ENGINEERING EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 2200 N This document is within QA plan scope X Yes _ No Effective Date Safety Reviews Required X Yes No (07/19/93) 07/29/93 Prior Revision 4 incorporated the This Revision 5 incorporates the following Temporary Changes: following Temporary Changes: t?/A N/A LIST OF srrsuTivs PAGES ZAgg REVISION 1.0 5 2.0 4 3.0 5 El-1 5 E2-1 5 E2-2 5 E3-1 5 O OYSTER CREEK CONTROLLED DISTRiBUT!ON DOCUMENT SERlAL NUMSER _78 INFO. MGMT. - DCC Signature Concurring Organization Element Date EOP COORDINATOR' Originator 7 ; Concurred By [f h / [ g g j $ EOP COMMITTEE //phJ dm M , PLANT ENGINEERING DIRECTOR hf7/8) 3 pgh MGR, PLANT OPERATIONS -) V 93 O n i Approved By hkdh VICE PRESIDENT f DIRECTOR, OC ]. 8.h 3 (320011) 1.0 OYSTER CREEK NUCLEAR GENERATING Number g STATION PROCEDURE EMG-3200.11 Title Revision No. s SECONDARY CONTAINMENT CONTROL 4 1.0 PURPOSE b The purpose of the Secondary Containment Control Procedure is to: Protect equipment in the Secondary Containment. Limit the radioactivity release to the Secondary Containment. Maintain Secondary Containment intergrity or limit the release from the Secondary Containment.
2.0 REFERENCES
2.1 Procedures
- 107.4, EOP Program Control
- 329, Rx Bldg. Heating and Ventilation System
- 330, Standby Gas Treatment System 2.2 Drawings
- BR 3017, 460 VAC MCC Elem Diagram Sht 4
- GE 112C2654, Sht 3, Panel 2R Connection Diagram
- GE 706E841, Vent & Effluent Rad Monitor Elem Diagram
- GU 3D-822-17-1002, Elem Diagram - Standby Gas Treatment System
- SN 15361.03-EC-23, Area Rad Monitoring Elem Diagram 2.3 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.4 2000-STD-1218.04, EOP Writer's Guide 3.0 PRECAUTIONS AND LIMITATIONS 3.1 This procedure gives guidance to the operator for bypassing isolation signals which is a departure from the Oyster Creek Technical Specifications. It is permissible to take actions which depart from the plant's Technical Specifications during emergency conditions as authorized by 10 CFR 50.54(x).
(320011) 2,0
7, OYSTER CREEK NUCLEAR GENERATING Number o STATION PROCEDURE EMG-3200.11 Title Revision No.
O_ SECONDARY CONTAINMENT CONTROL 5 4.O ATTACHMENTS be 4.1 Attachment A - Secondary Containment and Radioactivity Release Control EOP Flowchart DWG: GU 3E-200-08-Oll Sht 1 4.2 Attachment B - Support Procedure 49, Confirmation of Secondary Containment.
Initiations and Isolations 4.3 Attachment C - Support Procedure 50, Reactor Building Ventilation Restart i
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""=bar B{G-3200.11 Title Revision No.
SECONDARY CONTAINMENT CONTROL 5 F
ATTACHMENT A Attachment A to EMG-3200.11, Secondary Containment Control, is the Secondary Containment and Radioact,1vity Release Control EOP Flowchart, ,
DWG: GU 3E-200-08-011 Sht 1 Rev. 1. ,
O P
O (320011/4) El-1 i
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Procedure EMG-3200.11
_,Rev. 5 Attachment B Page 1 of _2_
Q SUPPORT PROCEDURE 49 CONFIRMATION OF SECONDARY CONTAINHENT INITIATIONS AND ISOLATIONS h 1.0 PREREOUISITES Confirmation of the isolation of Reactor Building Ventilation and initiation ,
of SGTS has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE confirm the following:
3.1 Both SGTS fans, EF 1-8 and EF 1-9, start (Panel 11R).
3.2 The following Reactor Building Main Supply Header Valves close (Panel 11R).
V-28-1/v-28-2 V-28-3/V-28-4 V-28-5/V-28-6 V-28-7/V-28-8 V-28-9/V-28-10 V-28-11/V-28-12 V-28-13/V-28-14 V-28-15/V-28-16 V-28-36/V-28-37 V-28-38/V-28-39 3.3 Reactor Building Containment Isolation Valves Close (Panel 11R)
V-28-21 V-28-22 O
(320011/5) E2-1
Procsdura EMG-3200.11 Rav. 5 !
_ Attachment B l W Page 2 of _2_ l l
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3.4 Reactor Building Supply Fans trip (Panel 11R)
SF 1-12 SF 1-13 6i SF 1-14 3.5 Operating Reactor Building Exhaust Fan trips (Panel 11R)
EF 1-5 or, EF 1-6 3.6 Drywell Ventilation Supply Valves Close (Panel 11R)
V-28-42 V-28-43 3.7 WHEN proper flow is established in the selected SGTS Train, ,
THEN Confirm the following:
- 1. SGTS Crosstic V-28-48 closes (Panel 11R).
- 2. The non-selected SGTS Fan trips (Panel 11R).
- 3. The non-selected SGTS Train inlet and discharge valves close (Panel 11R).
- 4. The running SGTS Train orifice valve closes (Panel 11R).
b 5
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(320011/6) E2-2 I
a ,. ., - - e
e Procedure EMG-3200.11 Rev. 5 j ' Attachment C Page 1 of 1
,] SUPPORT PROCEDURE 50 REACTOR BUILDING VENTILATION RESTART 1.0 PREREOUISITES 6 The restart of Reactor Building Ventilation has been directed by the Emergency Operating Procedures.
2.0 PPEPARATION When directed by the GOS/GSS, perform the following:
2.1 Verify that the Reactor Building Ventilation Effluent Monitors (Vent Manifold Rad Mon Ch I and Vent Manifold Rad Mon Ch 2) are reading less than 13 MREM /hr (Panel 2R).
2.2 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
2.2.1 Remove the bypass plug from Position BP4.
2.2.2 Insert the bypass plug into Position BPl.
3.0 PROCEDURE When directed by the GOS/GSS, perform the following:
3.1 Reset the Reactor Building Ventilation System by depressing the RESET button (Panel 11R).
3.2 Open the Reactor Building Main Exhaust Dampers V-28-21 and V-28-22 (Panel 11R).
3.3 ***********************************************************
- CAUTION *
- Steps 3.4 and 3.5 should be completed immediately after
- l
- starting Exhaust Fan EF-1-5 in order to preclude damage
- j
- to Ventilation System Ducts.
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........................................................... 1 Start Exhaust Fan EF 1-5 placing its control switch in START (Panel 11R).
3.4 Confirm control switch for V-28-42 and V-28-43 in CLOSE (Panel 11R).
3.5 Select and start two of the following Reactor Bldg Supply Fans, j l
SF 1-12, SF 1-13, and SF 1-14, by placing their control
\
switches in ON (Panel 11R).
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l (320011/7) E3-1
r OYSTER CREEK NUCLEAR GENERATING Number Nusler STiT10N rROCEnuRE zu c 32n.12 Title Revision No.
O a^oio^crivirv an's^ss courno' 2 i
Applicability / Scope Responsible Office !
PLANT ENGINEERING EMERGENCY OPERATING PROCEDURE FOR OYSTFR CREEK 2200 This document is within QA plan scope _.2 Lyes No Effective Date Safety Reviews Required X Yes No (07/19/93) 07/29/93
- Prior Revision 1 incorporated the This Revision 2 incorporates the following Temporary Changes: following Temporary Changes:
N/A N/A LIST OF EFFECTIVE PAGES EAqE A REVISION 1.0 2 2.0 2 El-1 2 E2-1 2 E2-2 2 ,
O .
OYSTER C ~ EcK CONTROLLED DG slBUTION DOCUMENT SERML NUMBER 7 2-. -
INFO. Y,GMT. - DCC t Signature ,
Concurring Organization Element Date Originator j[ h7 EOP COORDINATOR o ?
Concurred By 7g'(([,k,[jf' EOP COMMITTEE ((P/[3 l g, PLANT ENGINEERING DIRECTOR #~/[/ 7 /Cf3 kj % j h MGR, PLANT OPERATIONS ] q$ l l
l l
O Approved By o
MQ I
VICE PRESIDENT & DIRECTOR, OC 7. [.h 3 (320012) 1.0
t OYSTER CREEK NUCLEAR GENERATING Number NI STATION PROCEDURE EMG-3200.12 ,
Title Reviuion No.
RADIOACTIVITY RELEASE CONTROL 2 1.0 PURPOSE The purpose of the Radioactivity Release Control Procedure is to limit th0 radioactivity release into areas outside the Primary and Secondary Containments.
2.0 REFERENCES
2.1 Procedures
- 107.4, EOP Program Control
- 329, Turbine Bldg. Heating and Ventilation System 2.2 - 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.3 - 2000-STD-1218.04, EOP Writer's Guide 3.0 h TTACHMENTS 3.1 Attachment A - Secondary Containment and Radioactivity I
Release Control EOP Flowchart DWG: GU 3E-200-08-011 Sht 1 3.2 Attachmt.nt B - Support Procedure 51, Turbine Building Ventilation Restart r
y f
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(320012) 2.0 I
i i
m OYSTER CREEK NUCLEAR GENERATING Number
$UClear STATroN rRoCEnuRE Euc 3200.12 j
Title - Revision No.
i RADIOACTIVITY RELEASE CONTROL 2 ATTACHMENT A Attachment A to EMG-3200.12, Radioactivity Release Control, is the Secondary Containment and Radioactivity Release Control EOP Flowchart, DWG: GU 3E-200-08-011, Sht 1, Rev. 1.
?
I
Procedura EMG-3200.12 Jav. 2 Attachment B Page 1 of 2 SUPPORT PROCEDURE 51 TURBINE BUILDING VENTILATION RESTART 1.0 PREREOUISITES Restart of Turbine Building Ventilation has been directed by the Emergency Operating Procedures.
2.O PREPARATION None.
3.0 PROCEDURE 3.1 Reset the Turbine Bldg. Ventilation System by momentarily depressing the system RESET pushbutton (Panel 11R).
3.2 If Exhaust Fan EF 1-7 was previously running, THEN start Exhaust Fan EF 1-7 by placing its control switch to START position (Panel 11R).
~
3.3 Ig Exhaust Fan EF 1-6 was previously running, THEN start Exhaust Fan EF 1-6 by placing its control switch to START position (Panel 11R).
3.4 Select and start either Supply Fan SF 1-1 or SF 1-2 by placing its control switch in the ON position (Panel 11R).
3.5 Select and start either Supply Fan SF 1-3 or SF 1-4 by placing its control switch in the ON position (Panel 11R).
l 3.6 Select and start either Supply Fan SF 1-5 or SF 1-6 by placing its control switch in the ON position (Panel 11R).
3.6.1 Verify Exhaust Fan EF 1-4 automatically starts.
O (320012/4) E2-1
Procedura EMG-3200.12
_Bev. 2 i
,- Attachment B I Page 2 of 2 0 3.7 Start Feed and Condensate Pump Room Supply Fan SF 1-7 and Exhaust Fan EF 1-1 by placing their combined control switch to the ON position (Panel 11R).
3.8 IE the TURBINE OPR FLOOR ENT Area Rad Monitor Module R014A-4 (Panel 2R) is EQI alarming, THEN Start TB Operating Floor Exhaust Fan EF 1-33 by placing its l
)
control switch in the ON position (Panel 11R).
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(320012/5) E2-2