ML041190543
| ML041190543 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek (DPR-016) |
| Issue date: | 04/02/2004 |
| From: | Exelon Corp |
| To: | Tam P Office of Nuclear Reactor Regulation |
| References | |
| -RFPFR 2000-EMG-3200.01A, Rev 11, 2000-EMG-3200.01B, Rev 13, 2000-EMG-3200.02, Rev 17, 2000-EMG-3200.11, Rev 11 | |
| Download: ML041190543 (179) | |
Text
Telephone No. (609) 971-4652 RM Dept.
An Exelon Company DOCUMENT TRANSMITTAL April 2, 2004 To: PETER S TAM-USNRC Sr. Project Manager Copy Serial #72 WASHINGTON DC 20555 PLEASE NOTE: ITIS IMPERATIVE THAT YOU NOTIFYRM OF ADDRESS CHANGES!!
FILE INSTRUCTIONS:
DESTROY OUTDATED:
2000-EMG-3200.01A REV.
11 2000-EMG-3200.01A REV. 10 2000-EMG-3200.01B REV. 13 2000-EMG-3200.01B REV. 12 2000-EMG-3200.02 REV. 17 2000-EMG-3200.02 REV. 16 2000-EMG-3200.11 REV. 11 2000-EMG-3200.11 REV. 10 FAILURE TO COMPLY WITH REQUIRED ACTION, WITHIN FIVE (5) WORKING DAYS OF THIS REQUEST, COULD RESULT IN A CAP.
REQUIRED ACTION: 1. ADD REVISION TO YOUR CONTROLLED COPIES.
- 2. DESTROY OUTDATED MATERIAL.
- 3. RETURN TRANSMITTAL SIGNED AND DATED.
SIGN AND RETURN TO: RECORDS MANAGEMENT, OCAB-1 NAME:
DATE:
YOUR SIGNATURE ON THIS FORM INDICATES THAT YOU HAVE FILED THE CURRENT REVISION. THIS SIGNED FORM CAN BE USED FOR AUDITING PURPOSES.
AG5942 (08/02) fXU-l5
OYSTER CREEK NUCLEAR GENERATING, Number AB erte STATION PROCEDURE EMG-3200.01A An ExeW.ma Title Revision No.
RPV CONTROL - NO ATWS 11 Applicability/Scope Usage Level Responsible Office EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK lOPERATIONS Effect'e/ate Prior Revision 10 incorporated the This Revision 11 incorporates the following Temporary Changes:
following Temporary Changes:
N/A N/A LIST OF PAGES (all pages rev'd to Rev. 11) 1.0 to 3.0 El-1 E2-1 to E2-3 E3-1 E4-1 to E4-2 E5-1 to E5-7 EG-1 to E6-3 E7-1 to E7-3 E8-1 to E8-2 E9-1 E10-1 to E10-5 Ell-l E12-1 to E12-4 E13-1 E14-1 to E14-2 E15-1 to E15-2 E16-1 to E16-2 E17-1 to E17-6 OYSTER CREEK CONTROLLED DISTRIBUTION 1 2 DOCUMENT SERIAL NUMBER_....
IRMC Signature Concurring Organization Element Date Originator
/s/
EOP COORDINATOR 3/16/04 Concurred By
/s/
EOP COMMITTEE 3/16/04 s
DIRECTOR ENGINEERING 3/20/04
/s/
PLANT OPERATIONS DIRECTOR 3/23/04 ADDroved By
/5/PLANT MANAGER 3/24/04 I
(320001A) 1.0
AL M
OYSTER CREEK NUCLEAR GENERATING
{ Number Bmerg en lSTATION PROCEDURE ENMG-3200:01A
-Title Revision-No.-
R PN CONTROL - NO ATWS 11 Applicability/Scope Usage Level Responsible Office EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK OPERATIONS Effective Da/e Prior Revision 10 incorporated the This Revision 11 incorporates the following Temporary Changes:
following Temporary Changes:
N/A N/A LIST OF PAGES (all pages rev'd to Rev. 11) 1.0 to 3.0 El -1 E2-1 to E2-3 E3-1 E4-1 to E4-2 E5-1 to E5-7 E6-1 to E6-3 E7-1 to E7-3 E8-1 to EB-2 E9-1 E10-1 to E10-5 Eli-i E12-1 to E12-4 E13-1 E14-1 to E14-2 E15-1 to E15-2 E16-1 to E16-2 E17-1 to E17-6 Signature l Concurring Organization Element Date Originator EOP COORDINATOR
/
dY Concurred By EOP COMMITTEE 3
A te=
DIRECTOR ENGINEERING 43
/B PLANT OPERATIONS DIRECTOR 3' Ž t
Approved By PLANT MANAGER 3
(32000A) 1.
(320001A)
- 1. 0
AmerGen OYSTER CREEK NUCLEAR GENERATING Number An bxma Co
---STATION-PROCEDURE -
- EMG-3200.01A- --- -
Title Revision No.
RPV CONTROL - NO ATWS 11 1.0 PURPOSE 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
2.1 Procedures AD-OC-103, EOP-SAM Program Control 308, Emergency Core Cooling System Operation 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 BR E1183, Elem Diagram for Cleanup Isolation Valve V-16-2 BR E1184, Elem Diagram for Cleanup Isolation Valve V-16-14 GE 112C2248, Sht 2, Connection Diagram llF 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 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 (320001A) 2.0
A.erGen OYSTER CREEK NUCLEAR GENERATING Number Anw nyj STATION -PROCEDURE
- -EMG-3200.01A Title Revision No.
RPV CONTROL - NO ATWS 11 3.0 PRECAUTIONS AND LIMITATIONS 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 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 4.10 4.11 4.12 4.13 4.14 4.15 4.16 4.17 Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment Attachment RPV Control -
No ATWS EOP Flowchart,_EMG-3200-OlA Rev.5 Support Procedure 1, Confirmation of Automatic Initiations and Isolations Support Procedure 2, Feed and Condensate System Operation Support Procedure 3, CRD System Operation Support Procedure 4, Operation of the Core Spray System Support Procedure 5, Fire Water for RPV Water Level Control Support Procedure 6, Condensate Transfer for RPV Water Level Control Support Procedure 7, Liquid Poison for RPV Water Level Control Support Procedure 8, Lineup for Condensate System Injection Support Procedure 9, Lineup for Core Spray System Injection Support Procedure 10, Stopping Injection from the Core Spray System Support Procedure 11, Alternate Pressure Control -
Isolation Condensers Support Procedure 12, Alternate Pressure Control -
EMRVs Support Procedure 13, Alternate Pressure Control -
Clean-up in Recirculation Mode Support Procedure 14, Alternate Pressure Control -
Clean-up in Letdown Mode Support Procedure 15, Alternate Pressure Control -
Isolation Condenser Tube Side Vents Support Procedure 56, Injecting the CST via Core Spray I
(320001A)
- 3. 0
AMerGen OYSTER CREEK NUCLEAR GENERATING Number
-STATION PROCEDURE
-EMG-3200.01A Title Revision No.
RPV CONTROL - NO ATWS 11 ATTACHMENT A Attachment A to EMG-3200.01A, RPV Control -
NO ATWS EOP Flowchart, EMG-3200.01A Rev.5.
(320001A/S3)
EI-1
Procedure EMG-3200.01A Support Proc-i Rev. 11 Attachment B Page 1 of 3 SUPPORT PROCEDURE 1 CONFIRMATION OF AUTOMATIC INITIATIONS AND ISOLATIONS 1.0 PREREQUISITES 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 4
Reactor Isolation IF Any of the following conditions exist:
- RPV water level at or below 86 in. and not bypassed
- Steam tunnel temperature at or above 180 0F
- Any steam line flow at or above 4.0x106 ibm/hr Reactor mode switch in RUN and RPV pressure at or below 850 psig
- Main steam line radiation at or above 800 units AND no ATWS condition exists THEN Confirm closed the following:
__NSO3A
__NS04A
__NS03B IC VENTS V-14-1,-19
_V-14-5,-20 RX SAMPLE V-24-30 (llF)
V-24-29 (llF)
DW AIR SUPPLY V-6-395 (llF)
NS04B Scram IF A Reactor Scram is initiated Discharge AND Volume Isolation SDV HI-HI LVL SCRAM switch is not in BYPASS, THEN Confirm closed the following:
NORTH SDV Vents & Drains SOUTH SDV Vents & Drains OVER (32000lA/S4)
E2-1
Procedure EMG-3200.01A Support-Proc Rev. 11 Attachment B Page 2 of 3 SYSTEM OPERATING DETAILS IC-A IF 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 IF 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 Cleanup IF Any of the following conditions exist:
System RPV water level at or below 86 in. and not bypassed
- Drywell pressure at or above 3.0 psig
V-16-1
__V-16-14 V-16-2
__V-16-61 Shutdown IF 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 closed the following SDC Isolation Valves:
V-17-54 V-17-19 Isolation IF RPV water level is at or below 86 in.,
Condenser Initiation THEN confirm initiation of both Isolation Condensers.
Core Spray IF Any of the following conditions exist:
System RPV water level at or below 86 in. and not bypassed.
Start Drywell pressure at or above 3.0 psig and not bypassed.
THEN Confirm start of one Main Pump and one Booster Pump in each Core Spray System if not bypassed.
(320001A/S4)
E2-2
Procedure EMG-3200.01A Support-Proc-1 Rev. 11 Attachment B Page 3 of 3 SYSTEM OPERATING DETAILS Primary Containment Isolation IF Any of the following conditions exist:
- RPV water level at or below 86 in. and not bypassed.
Drywell pressure at or above 3.0 psig and not bypassed.
THEN Confirm closed the following valves that are not required to be open by the Emergency Operating Procedures:
System DW Vent/Purge Torus Vent Torus 2" Vent Bypass DWEDT DW Floor Sump Torus/Rx Bldg.
Vacuum Breakers TIP Valves DW 2" Vent Bypass N2 Purge N2 Makeup Valve No.
V-27-1 V-27-2 V-27-3 V-27-4 V-28-17 V-28-18 V-28-47 V-22-1 V-22-2 V-22-28 V-22-29 V-26-16 V-26-18 Common Ind.
V-23-21 V-23-22 V-23-13 V-23-14 V-23-15 V-23-16 V-23-17 V-23-18 V-23-19 V-23-20 (Panel 11F) it,,
(Panel 11F)
(Panel llF)
(Panel 11F) it (Panel 11F)
(Panel l1F)
(Panel (Panel 11F) 12XR)
(Panel 12XR) i.
(Panel 12XR) i, (320001A/54)
E2 -3 (320001A/S4)
E2-3
Procedure EMG-3200.01A Support Proc-2 Rev. 11 Attachment C Page 1 of 1 SUPPORT PROCEDURE 2 FEED AND CONDENSATE SYSTEM OPERATION 1.0 PREREQUISITES Directed to maintain RPV level with the Feed and Condensate Systems by the Emergency Operating Procedures.
2.0 PREPARATIONS None 3.0 PROCEDURE 3.1 IF RPV water level is increasing, THEN select one Feedwater Pump to be the operating pump and trip the Feedwater Pumps NOT selected.
3.2 Control RPV water level using the following:
- Feedwater Regulating valves.
- MFRV Block Valves.
- Feedwater Low Flow valves.
- Heater Bank Outlet Isolation valves.
- Feedwater and Condensate pumps.
3.3 IF RPV water level cannot be restored and maintained below 160 in.,
THEN close the Heater Bank Outlet Isolation valves for the operating pumps.
3.4 IF RPV water level reaches 170 in.,
THEN trip any operating Feedwater pump.
3.5 IF RPV water level reaches 170 in.
AND RPV pressure is below 350 psig (the shutoff head of the Condensate pumps),
THEN close all Heater Bank Outlet Isolation valves.
3.6 IF RPV water level continues to increase, THEN trip the operating Condensate Pumps.
(320001A/S5)-
E3-1
Procedure EMG-3200.01A
-Support Proc-3 Rev. 11 Attachment D Page 1 of 2 SUPPORT PROCEDURE 3 CRD SYSTEM OPERATION 1.0 PREREQUISITES Directed to maintain RPV level with the CRD System by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE NOTE There are three methods of injection using the CRD system:
- 1.
Scram reset and controlling with the CRD Flow Control Valve (NC30).
- 2.
Post scram injection (with the scram not reset) through the CRDs.
- 3.
Post scram injection using bypass flow and controlling with the CRD Bypass Valve V-15-30.
3.1 Confirm running all available CRD Pumps (Panel 4F).
3.2 l
CAUTION Operating one CRD pump at greater than 150 gpm may result in a lpump trip.
IF the scram has been reset, AND CRD bypass flow is not required (based on flow rate required),
THEN control CRD flow using the in-service Flow Control Valve NC-30.
OVER (320001A/S6)E
.E4-1
3.3 IF THEN 3.4 IF THEN 3.5 IF THEN Procedure EMG-3200.01A Support Proc-3 Rev. 11 Attachment D Page 2 of 2 CRD bypass flow is desired for RPV water level control, complete the following, l.Confirm the scram reset.
2.IF the scram cannot be reset, THEN close CRD Charging Header Supply Valve V-15-52 (RB 23 SE).
AND throttle open CRD Bypass Valve, V-15-30 (RB 23 SE), so as not to exceed 150 gpm flow for one or two pump operation.
RPV water level cannot be maintained below 160 in.,
- 2. Throttle closed CRD Flow Control Valve NC-30.
RPV water level reaches 170 in.,
trip the operating CRD pumps.
(320001A/S6)
E4-2
Procedure EMG-3200.01A Support Proc Rev. 11 Attachment E Page 1 of 7 SUPPORT PROCEDURE 4 OPERATION OF THE CORE SPRAY SYSTEM 1.0 PREREQUISITES Use of the Core Spray System for RPV level control has been directed by the Emergency Operating Procedures.
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 IF THEN Core Spray System actuating signals are present, 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 1F/2F).
2.2 This procedure requires the use of an MB-i and PA-235 key.
3.0 PROCEDURE CAUTION Core Spray suction strainer plugging may occur due to debris in the Primary Containment and result in a loss of Core Spray System Flow.
3.1 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.
IF THEN Bus iC or 1D are being supplied by an Emergency Diesel Generator, verify that adequate load margin is available so as NOT to exceed EDG load limit when starting Core Spray Pumps.
OVER (320001A/S7)
Procedure EMG-3200.01A Support Proc-4 Rev. 11 Attachment E Page 2 of 7 3.2 CAUTION NPSH problems will develop on all operating pumps if more than 4 Containment Spray/Core Spray Main pumps are operated at the same time.
IF 4 Containment Spray/Core Spray Main pumps are in operation, THEN secure Containment Spray pumps as necessary to run Core Spray pumps.
3.3 Confirm one Core Spray Main Pump is running in each system (Panel 1F/2F).
3.4 WHEN Core Spray Main Pump discharge pressure increases above 105 psig (Sys 1) or 140 psig (Sys 2) (Panel 1F/2F),
THEN as directed by the LOS, confirm a Core Spray Booster Pump in each system is operating (Panel IF/2F).
3.5 WHEN RPV pressure is less than 310 psig, THEN as directed by the LOS, restore and maintain RPV water level by cycling the Core Spray Parallel Isolation valves as required (Panel 1F/2F).
3.6 CAUTION Operation of Core Spray pumps with flow above the NPSH or vortex limits may result in equipment damage.
When operating beyond any flow limits, periodic evaluations should be made to verify that continued operation beyond these limits is still required.
Monitor the NPSH and Vortex limits of running Core Spray pumps per Figures A and B.
IF NPSH limits are reached, THEN secure the booster pump in the system with NPSH limitation.
3.7 IF all Core Spray pumps that are running are not required to assure adequate core cooling, THEN Perform the following:
- 1. Inform the LOS.
- 2. Secure the Core Spray pumps that are not required to assure adequate core cooling.
(320001A/S7)
E5-2
Procedure EMG-3200.01A Support Proc-4 Rev. 11 Attachment E Page 3 of 7 3.8 IF THEN no Core Spray pumps in a system are operating, verify Core Spray KEEP FILL TROUBLE (B-3-d) alarm is not illuminated.
3.9 Core when NOTE Spray System pumps will operate on minimum recirculation flow the Parallel Isolation Valves are closed.
3.10 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 excess vibration.
NOTE The Test Flow Return Valves throttle in the open direction only.
IF 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 lA21B/RB 23 E)
- System 2 V-20-26 (MCC lB21A/RB 23 NE)
OVER (320001A/S7)
Procedure EMG-3200.01A Support Proc-4 Rev. 11 Attachment E Page 4 of 7
- 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)
- 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 LOS.
3.11 Continue to monitor Core Spray System operation and evaluate system performance in accordance with Steps 3.6 through 3.10.
(320001A/S7)
Procedure EMG-3200.01A
.Support Proc-4 Rev. 11 Attachment E Page 5 of 7 FIGURE A CORE SPRAY VORTEX LIMIT 100 90 80 TORUS WATER 70 -
LEVEL fin) 60-^wnr 40 0
200 4000 6000 8000 100)0 120])
14000 160])
180 20000 TOTAL CORE SPRAY & CONTAINMENT SPRAY FLOW (gpm)
OVER (32000iA/S7)
. E5-5
Procedure EMG-3200.01A Support Proc-4 Rev. 11 Attachment E Page 6 of 7 FIGURE B CORE SPRAY NPSH LIMrr H
G STATIC G l HEAD ADJUSTMENT F
FROM FIG. C E
D Sm 3500 4500 A
M P
230 220 210 -
200 -
190 180 -
Torus Temperatire 170 - -
(F) 160 -
150 - _
140 - -
130 -
120 - -
110 - _
2500 B
H i
E G
F iSTATIC E
HEAD ADJUSTMENT
§ FROM D
FIG. C C
4500 A 5000 3000 3500 4000 Punp Flow (gpm)
(320001A/S7)
E5 -~6
Procedure EMG-3200.01A Support Proc-4 Rev. 11 Attachment E Page 7 of 7 FIGURE C CORE AND CONTAINMENT SPRAY STATIC HEAD CURVE 5
4 3
Li
=
(n 0.
W Cto 2
1 0
1.5 0.5
-0.5
-1.5
-2.5
-1
-2
-3 100 110 120 130 140 150 190 200 Torus Water Level (in)
PSTRAINER VALUE TOTAL (TORUS)
PSTRAINER FLOW (PSL)
(GPM) c 5000 0.3 5000 -
7500 0.5 7500 -
10000 0.8 10000 -
12500 1.2 12500 -
15000 1.6 15000 -
17500 2.1 17500 -
18400 2.3 18400 -
20000 2.7 (320001A/S7)
Procedure EMG-3200.01A Support Proc-5 Rev. 11 Attachment F Page 1 of 3 SUPPORT PROCEDURE 5 FIRE WATER FOR RPV WATER LEVEL CONTROL 1.0 PREREQUISITES 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 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 (Panel IF/2F).
3.0 PROCEDURE 3.1 Determine which Core Spray System is to be used for Fire Water Injection.
- System 1 -
Continue at step 3.2.
- System 2 -
Continue at step 3.3.
3.2 Injecting Firewater Via Core Spray System 1 3.2.1 Verify Core Spray System 1 is not available (Panel IF/2F).
3.2.2 Place the Core Spray System 1 Main Pump control switches in the PULL-TO-LOCK position (Panel IF/2F).
3.2.3 Close Tell-Tale Drain valve, V-20-91 (RB 23 North or North 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 Open Fire Water Supply valve, V-20-83 (RB 23 North or North Side RB outside).
3.2.6 Confirm open Core Spray System 1 Discharge valve, V-20-12 (Panel 1F/2F).
OVER (320001A/S8)
E6-1
Procedure EMG-3200.01A Support Proc-5 Rev. 11 Attachment F Page 2 of 3 3.2.7 Confirm closed Core Spray System 1 Test Flow Return valve, V-20-27 (Panel IF/2F).
3.2.8 Close Core Spray System 1 Pump Suction valves, V-20-32 and V-20-3 (Panel 1F/2F).
3.2.9 NOTE Overriding Core Spray initiation logic may be required.
WHEN directed by the LOS, THEN open either Core Spray System 1 Parallel Isolation valve, V-20-15 or V-20-40 (Panel 1F/2F).
3.2.10WHEN RPV pressure is less than 310 psig, THEN as directed by the LOS, restore and maintain RPV water level by cycling the Core Spray Parallel Isolation valves as required (Panel 1F/2F).
3.3 Injecting Firewater via Core Spray System 2 3.3.1 Verify Core Spray System 2 is not available (Panel 1F/2F).
3.3.2 Place the Core Spray System 2 Main Pump control switches in the PULL-TO-LOCK position (Panel 1F/2F).
3.3.3 Close Tell-Tale Drain valve, V-20-90 (RB 23 South, or South Side RB outside).
3.3.4 Confirm running all Diesel Fire Pumps by placing their control switches in MAN position (Panel 13R).
(320001A/S8)
E6-2
Procedure EMG-3200.01A Support Proc-5 Rev. 11 Attachment F Page 3 of 3 3.3.5 Open Fire Water Supply valve, V-20-82 (RB 23 South or South Side RB outside).
3.3.6 Confirm open Core Spray System 2 Discharge valve, V-20-18 (Panel 1F/2F).
3.3.7 Confirm closed Core Spray System 2 Test Flow Return valve, V-20-26, (Panel IF/2F).
3.3.8 Close Core Spray System 2 Pump Suction valves, V-20-33 and V-20-4 (Panel 1F/2F).
3.3.9 NOTE Overriding Core Spray initiation logic may be required.
WHEN directed by the LOS THEN open either Core Spray System 2 Parallel
- 3. 3. 10 WHEN THEN Isolation valve, V-20-21 or V-20-41 (Panel 1F/2F).
RPV pressure is less than 310 psig, as directed by the LOS, restore and maintain RPV water level by cycling the Core Spray Parallel Isolation valves as required (Panel 1F/2F).
(320001A/S8)
E6-3
Procedure EMG-3200.01A Support Proc-6 Rev. 11 Attachment G Page 1 of 3 SUPPORT PROCEDURE 6 CONDENSATE TRANSFER FOR RPV WATER LEVEL CONTROL 1.0 PREREQUISITES 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 This procedure requires the use of an MB-1 key and access to the Rx.
Bldg.
2.2 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 (Panel 1F/2F).
3.0 PROCEDURE 3.1 Determine which Core Spray System is to be used for Condensate Transfer Injection.
- System 1 -
Continue at step 3.2.
- System 2 -
Continue at step 3.3.
3.2 Injecting Condensate Transfer via Core Spray System 1 3.2.1 Verify the following:
- 1. Core Spray System 1 is not available.
- 2. Fire Water is not being injected via Core Spray System 1.
3.2.2 Place the Core Spray System 1 Main Pump control switches in PULL-TO-LOCK position (Panel IF/2F).
3.2.3 Unlock and open Regulator Bypass valves, V-11-110 and V-l1-ill (RB 51 NW)
OVER (320001A/S9)
E7-1
Procedure EMG-3200.01A Support Proc-6 Rev. 11 Attachment G Page 2 of 3 3.2.4 Confirm open Core Spray System 1 Discharge valve, V-20-12 (Panel 1F/2F).
3.2.5 Confirm closed Core Spray System 1 Test Flow Return valve, V-20-27 (Panel IF/2F).
3.2.6 Start all available Condensate Transfer Pumps (Panel 5F/6F).
3.2.7 Close Core Spray System 1 Pump Suction valves V-20-32 and V-20-3 (Panel 1F/2F).
3.2.8 NOTE Overriding Core Spray initiation logic may be required.
WHEN directed by the LOS, THEN open either Core Spray System 1 Parallel Isolation valve, V-20-15 or V-20-40 (Panel 1F/2F).
3.2.9 WHEN RPV pressure is less than 310 psig, THEN as directed by the LOS, restore and maintain RPV water level by cycling the Core Spray Parallel Isolation valves as required (Panel 1F/2F).
3.3 Injecting Condensate Transfer via the Core Spray System 2 3.3.1 Verify the following:
- 1. Core Spray System 2 is not available.
- 2.
Fire Water is not being injected via Core Spray System 2.
3.3.2 Place Core Spray System 2 Main Pump control switches in the PULL-TO-LOCK position (Panel 1F/2F).
3.3.3 Unlock and open Regulator Bypass valves, V-11-109 and V-11-108 (RB 75 S).
3.3.4 Confirm open Core Spray System 2 Discharge valve, V-20-18 (Panel 1F/2F).
(320001A/S9)
E7-2
Procedure EMG-3200.01A Support Proc-6 Rev. 11 Attachment G Page 3 of 3 3.3.5 Confirm closed Core Spray System 2 Test Flow Return valve, V-20-26 (Panel 1F12F).
3.3.6 Start all available Condensate Transfer Pumps (Panel 5F/6F).
3.3.7 Close Core Spray System 2 Pump Suction valves V-20-33 and V-20-4 (Panel 1F/2F).
3.3.8 NOTE Overriding Core Spray initiation logic may be required.
WHEN directed by the LOS, THEN open either Core Spray System 2 Parallel Isolation valve, V-20-21 or V-20-41 (Panel IF/2F).
RPV pressure is less than 310 psig, 3.3.9 WHEN THEN as directed by the LOS, restore and maintain RPV water level by cycling the Core Spray Parallel Isolation valves as required (Panel 1F/2F).
(320001A/S9)
E7-3
Procedure EMG-3200.01A Support Proc-7 Rev. 11 Attachment H Page 1 of 2 SUPPORT PROCEDURE 7 LIQUID POISON FOR RPV WATER LEVEL CONTROL 1.0 PREREQUISITES 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 MB-1 key.
3.0 PROCEDURE 3.1 IF 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 LOS that Demineralized Water has been lined up to the SLC System.
3.2 CAUTION Due to pressure fluctuations, Fuel Zone Level Indictor Channels
'A; and 'C' will not provide accurate indication of RPV water level if a Standby Liquid Control Pump is injecting into the RPV and should not be used.
WHEN THEN directed by the LOS, start SLC Pump A by placing the STANDBY LIQUID CONTROL Keylock in the FIRE SYS 1 position (Panel 4F).
OVER (320001A/Sl0)
E8-1
Procedure EMG-3200.01A Support Proc-7 Rev. 11 Attachment H Page 2 of 2 3.3 IF Pump A does NOT start OR 3.4 System 1 Squib Valve does NOT fire THEN start SLC Pump B by placing the STANDBY LIQUID CONTROL Keylock in the FIRE SYS 2 position (Panel 4F).
IF 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.
Monitor system parameters for proper system performance.
3.5 (320001A/S10)
E8-2
Procedure EMG-3200.01A Support Proc-8 Rev. 11 Attachment I Page I of 1 SUPPORT PROCEDURE 8 LINEUP FOR CONDENSATE SYSTEM INJECTION 1.0 PREREQUISITES 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 5F/6F)
- HEATER BANK INLET Valves V-2-7 V-2-8 V-2-9
- HEATER BANK OUTLET Valves V-2-10 V-2-11 V-2-12
- MFRV A BLOCK Valve V-2-740
- MFRV C BLOCK Valve V-2-741 3.2 Confirm 2 Condensate Demineralizers are in service for each operating Condensate Pump 3.3 Confirm all available Condensate Pumps running.
3.4 Confirm all Feedwater Regulating Valve Controllers in MAN position.
3.5 Confirm all Feedwater Regulating Valves open.
3.6 Unless otherwise directed by the LOS, maximize injection using the Condensate System while maintaining Hotwell level constant.
(320001A/Sll)
E9-1
Procedure EMG-3200.01A Support Proc-9 Rev. 11 Attachment J Page 1 of 5 SUPPORT PROCEDURE 9 LINEUP FOR CORE SPRAY SYSTEM INJECTION 1.0 PREREQUISITES Confirmation of the lineup for Core Spray System injection has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE CAUTION Core Spray suction strainer plugging may occur due to debris in the Primary Containment and result in a loss of Core Spray System Flow.
3.1 Confirm open Core Spray System 1 and 2 Pump Suction Valves (Panel 1F/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 1F/2F).
V-20-27 V-20-26 3.3 CAUTION NPSH problems will develop on all operating pumps if more than 4 Containment Spray/Core Spray Main pumps are operated at the same time.
IF 4 Containment Spray/Core Spray Main pumps are in operation, THEN secure Containment Spray pumps as necessary to run Core Spray pumps.
3.4 Confirm one Core Spray System Main Pump operating in each system (Panel IF/2F).
SYS1 SYS2 OVER (320001A/S12)
E10-1
Procedure EMG-3200.01A Support Proc-9 Rev. 11 Attachment J Page 2 of 5 3.5 As directed by the LOS, confirm one Core Spray System Booster Pump operating in each system (Panel IF/2F).
3.6 Confirm open Core Spray System 1 and 2 Discharge valves (Panel 1F/2F).
SYS1 SYS2 V-20-12 V-20-18 3.7 WHEN THEN RPV pressure decreases to 310 psig, confirm open at least one Core Spray Parallel Isolation valve in each System (Panel IF/2F),
SYS 1 SYS 2 3.8 NOTE Maximum Flow is achieved with one main pump and one booster pump running and both parallel isolation valves open in each system. A Maximize injection into the RPV with the operating Core Spray Systems.
3.9 CAUTION Operation of Core Spray pumps with flow above the NPSH or vortex limits may result in equipment damage.
When operating beyond any flow limits, periodic evaluations should be made to verify that continued operation beyond these limits is still required.
Monitor the NPSH and Vortex limits of the running Core Spray pumps per Figures A and B.
3.10 IF NPSH limits are reached, THEN secure the booster pump in the system with NPSH limitation.
(320001A/S12)
E10-2
Procedure EMG-3200.01A Support Proc-9 Rev. 11 Attachment J Page 3 of 5 FIGURE A CORE SPRAY VORTEX LIMIT Iaw 90 80 4
+
4
+
+
4
+
TORUS WATER LEVEL (on) 70 4-1*
1 1--
I I
60 50 40 4
4-4 4
(99.
52) 0 2000 4000 600 8(000 10)0 12000 14000 TOTAL CORE SPRAY & CONTAINMENT SPRAY FLOW (gpm) 16000 180W1 20000 OVER (320001A/S12)
ElO-3
Procedure EMG-3200.01A Support Proc-9 Rev.
11 Attachment J Page 4 of 5 FIGURE B CORE SPRAY NPSH LIMIT 230' 220-210-200 190 ISO0 Torus Temperature 170 (F) 160 H
STATIC G
HEAD AWUSTMENT F
FROM FIG. C E
D 130 120 110_
2500 3500 4000 4500 SOOO Pump Row (Upm)
A B
C 230 220 210 200 190 180 Torus Temperature 170 F) 160
\\
IS NO RUNN 150 I
H G
STATIC E
HEAD ADJUSTMENT FROM D
FIG. C C
140 130 120 110 2500 3000 3500 4000 Pimp Flow (gpm) 4500 A B 5000 (320001A/S12)
E10-4
4 3
LU.
z 2
CA
._l 1
1
-2 Procedure EMG-3200.01A Support Proc-9 Rev. 11 Attachment J Page 5 of 5 FIGURE C CORE AND CONTAINMENT SPRAY STATIC HEAD CURVE 1.5 0.5 I
_-0.5
-1.5
-2.5
-3 I i
1_ _
1 i
i
-r"w !
100 110 120 130 140 150 160 170 180 190 200 Torus Water Level (in)
PSTRAINER VALUE TOTAL (TORUS)
PSTRAINER FLOW (PSL)
(GPM)
< 5000 0.3 5000 -
7500 0.5 7500 -
10000 0.8 10000 -
12500 1.2 12500 -
15000 1.6 15000 -
17500 2.1 17500 -
18400 2.3 18400 -
20000 2.7 (320001A/S12)
E10-5
Procedure EMG-3200.01A Support Proc-10 Rev. 11 Attachment K Page 1 of 1 SUPPORT PROCEDURE 10 STOPPING INJECTION FROM THE CORE SPRAY SYSTEM 1.0 PREREQUISITES Stopping Core Spray injection has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE When directed by the LOS, 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 NOT required to be open to assure adequate core cooling.
3.4 Secure Core Spray Booster Pumps NOT required to assure adequate core cooling by placing their respective control switch in STOP (Panel 1F/2F).
3.5 Secure Core Spray Main Pumps NOT 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 NOT illuminated.
(320001A/S13)
E11-1
Procedure EMG-3200.01A Support Proc-l1 Rev. 11 Attachment L Page 1 of 4 SUPPORT PROCEDURE 11 ALTERNATE PRESSURE CONTROL SYSTEMS ISOLATION CONDENSERS 1.0 PREREQUISITES RPV pressure control using the Isolation Condensers has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Procedure for Isolation Condenser A 3.1.1 Confirm Recirculation Pump A tripped.
IF recirculation Pump A cannot be tripped from the Control Room, THEN trip the recirculation Pump A Supply Breaker locally at 4160V Bus 1A.
3.1.2 CAUTION If RPV water level exceeds 180 in., initiation of an isolation condenser can cause water hammer to occur.
Verify RPV water level is below 160 in.
3.1.3 IF Isolation Condenser A has isolated on a high flow condition caused by Recirculation Pump operation, THEN restore the IC to operation as follows:
- 1. Open Steam Supply valves V-14-30 & V-14-31 by placing their control switches in the OPEN position (Panel 1F/2F).
OVER (320001A/S14)
E12-1
Procedure EMG-3200.01A Support Proc-li Rev. 11 Attachment L Page 2 of 4
- 2. Open DC Condensate Return valve V-14-34 by placing its control switch in the OPEN position (Panel 1F/2F).
- 3. Open AC Condensate Return valve V-14-36 by placing its control switch in the OPEN position (Panel IF/2F).
- 4. Reset the Isolation Condenser isolation signal using the Isolation Condenser Reset pushbutton (Panel 4F).
- 5. Restore all Isolation Condenser A valve control switches to their AUTO position.
3.1.4 Confirm open DC condensate return valve V-14-34 (Panel IF/2F).
3.1.5 Control RPV pressure as directed by the LOS by cycling V-14-34.
3.1.6 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).
(320001A/S14)
E12-2
Procedure EMG-3200.01A Support Proc-11 Rev. 11 Attachment L Page 3 of 4 3.2 Procedure For Isolation Condenser B 3.2.1 Confirm Recirculation Pump E tripped.
IF recirculation Pump E cannot be tripped from the Control Room, THEN trip the recirculation Pump E supply breaker locally at 4160V Bus 1A.
3.2.2 CAUTION If RPV water level exceeds 180 in., initiation of an isolation condenser can cause water hammer to occur.
Verify RPV water level is below 160 in.
3.2.3 IF Isolation Condenser B has isolated on a high flow condition caused by Recirculation Pump operation, THEN restore the IC to operation as follows:
- 1. Open Steam Supply valves V-14-32 & V-14-33 by placing their control switches in the OPEN position (Panel 1F/2F).
- 2. Open DC Condensate Return valve V-14-35 by placing its control switch in the OPEN position (Panel 1F/2F).
- 3.
Open AC Condensate Return valve V-14-37 by placing its control switch in the OPEN position (Panel IF/2F).
OVER (320001A/S14)
E12-3
Procedure EMG-3200.01A Support Proc-11 Rev. 11 Attachment L Page 4 of 4
- 4. Reset the Isolation Condenser isolation signal using the Isolation Condenser Reset pushbutton (Panel 4F).
- 5. Restore all Isolation Condenser B valve control switches to their AUTO position.
3.2.4 Confirm open DC condensate return valve V-14-35 (Panel 1F/2F).
3.2.5 Control RPV pressure as directed by the LOS by cycling V-14-35.
3.2.6 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).
(320001A/S14)
E12-4
Procedure EMG-3200.01A Support Proc-12 Rev. 11 Attachment M Page 1 of 1 SUPPORT PROCEDURE 12 ALTERNATE PRESSURE CONTROL SYSTEMS EMRVs 1.0 PREREQUISITES 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 in.
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 NR108B NR108C NR108E 3.4 Monitor Torus water temperature.
(320001A/S15)
E13-1
Procedure EMG-3200.01A Support Proc-13 Rev. 11 Attachment N Page 1 of 2 SUPPORT PROCEDURE 13 ALTERNATE PRESSURE CONTROL SYSTEMS CLEAN-UP IN RECIRCULATION MODE 1.0 PREREQUISITES 1.1 RPV pressure control using the Reactor Water Cleanup System in Recirculation Mode has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 Confirm that a Cleanup System line break does not exist (Alarms D-l-d/D-2-d).
2.2 Open the EOP BYPASS PLUGS panel in the rear of Panel 3F.
2.2.1 Remove the bypass plug from position BP2 and insert into position BP1.
2.2.2 Remove the bypass plug from position BP4 and insert into position BP3.
2.2.3 Remove the bypass plug from position BP6 and insert into position BP5.
2.2.4 Remove the bypass plug from position BP8 and insert into position BP7.
2.3 Obtain a flat head screwdriver from the EOP Tool Box in the Control Room.
2.4 Open the front panel of Auxiliary Relay Panel ER-215-087 (A/B Battery Room).
2.4.1 Remove bypass plug 1 (upper left hand corner).
2.4.2 Remove bypass plug 2 (upper left hand corner).
OVER (320001A/S16)
E14-1
Procedure EMG-3200.01A Support Proc-13 Rev. 11 Attachment N Page 2 of 2 3.0 PROCEDURE When directed by the LOS, perform the following:
3.1 Bypass and isolate Cleanup Filters as follows:
3.1.1 Open V-16-83, Filter Bypass Valve (RB 75).
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 IF 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 Heat Exchanger.
Maximum flow allowed is 1750 gpm.
3.5 Maintain RPV pressure as directed by the LOS throttling RBCCW flow to the NRHX.
(320001A/S16)
E14-2
Procedure EMG-3200.01A Support Proc-14 Rev. 11 Page 1 of 2 SUPPORT PROCEDURE 14 ALTERNATE PRESSURE CONTROL SYSTEMS CLEAN-UP IN LETDOWN MODE 1.0 PREREQUISITES 1.1 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 PROCEDURE 3.1 Confirm that a Cleanup System line break does not exist (Alarms D-l-d/D-2-d).
3.2 IF Cleanup System is not in service, THEN place the system in service in accordance with Procedure 303, Reactor Cleanup Demineralizer System.
3.3 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).
3.4 Open Discharge to Condenser Valve V-16-60 (Panel 3F).
3.5 Commence Letdown Flow to the main condenser by throtting open Discharge Flow Controller FCV-ND-22 (Panel 3F).
3.6 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.
3.7 Maintain NRHX outlet temperature below 1300F 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.
OVER (320001A/S17)
E15-1
Procedure EMG-3200.01A Support Proc-14 Rev. 11 Page 2 of 2 3.8 Adjust letdown flow rate by throttling FCV-ND-22 to establish required cooldown rate or pressure band.
3.9 IF NRHX outlet temperature cannot be maintained less than 1300F AND the system trips, THEN Perform the following:
- 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.
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. Contact I & C Department to inhibit the NRHX 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 3.3 through 3.6 to establish letdown flow.
- 6. Adjust letdown flow rate by throttling FCV-ND-22 to establish required cooldown rate or pressure band.
(320001A/S17)
E15-2
Procedure EMG-3200.01A Support Proc-15 Rev. 11 Attachment P Page 1 of 2 SUPPORT PROCEDURE 15 ALTERNATE PRESSURE CONTROL SYSTEMS IC TUBE SIDE VENTS 1.0 PREREQUISITES 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 Open the EOP BYPASS PLUGS panel inside of Panel 1OXF.
2.2.lRemove the bypass plug from position BP2 and insert it into position BP1.
2.2.2Remove the bypass plug from position BP4 and insert it into position BP3.
OVER (320001A/S18)
E16-1
Procedure EMG-3200.01A Support Proc-15 Rev. 11 Attachment P Page 2 of 2 3.0 PROCEDURE 3.1 Verify that RPV Water Level is below 180 in.
3.2 Confirm open the Isolation Condenser Steam Inlet Valves (lF/2F) for the Isolation Condensers to be used.
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 llF) for the Isolation Condensers to be used.
Isolation Condenser A V-14-5 V-14-20 Isolation Condenser B V-14-1 V-14-19 3.4 Control Reactor pressure as directed by the LOS by cycling the tube side vents designated in Step 3.3.
(320001A/S18)
E16-2
Procedure EMG-3200.01A Support Proc-15 Rev. 11 Attachment Q Page 1 of 6 SUPPORT PROCEDURE 56 INJECTING THE CST VIA CORE SPRAY 1.0 PREREQUISITES 1.1 Lining up one core spray system for CST Suction has by the Emergency Operating Procedures.
2.0 PREPARATION been directed 2.1 Verify that the Reactor Building and NW Corner Room are accessi 2.2 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 (Panel 1F/2F).
2.3 This procedure requires the use of an MB-1 key.
3.0 PROCEDURE ble.
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.
3.1 Determine which Core Spray System is to be used for CST injection.
- System 1 -
Continue at Step 3.2.
- System 2 -
Continue at Step 3.3.
3.2 Injecting the CST via Core Spray System 1 3.2.1 Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 1 (Panel IF/2F).
3.2.2 Place Core Spray System 1 Main Pump control switches in PULL-TO-LOCK position (Panel IF/2F).
3.2.3 Close Core Spray Pump Suction valves V-20-3 and V-20-32 (Panel 1F/2F).
OVER (320010/S19)
E17-1
Procedure EMG-3200.01A Support Proc-15 Rev. 11 Attachment Q Page 2 of 6 3.2.4 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 lB21A/RB 23 NE) 3.2.5 Confirm closed the Test Flow Return valve V-20-27 (Panel 1F/2F).
3.2.6 Unlock and open the following CST supply valves:
- V-20-1 (NW Corner Room)
- V-20-5 (NW Corner Room)
- V-20-34 (NW Corner Room) 3.2.7 IF Bus 1C or iD are being supplied by a Emergency Diesel Generator, THEN verify that adequate load margin is available so as NOT to exceed EDG load limit when starting Core Spray Pumps.
3.2.8 Start Core Spray System 1 Main Pump NZO1A or NZOlC (Panel 1F/2F).
3.2.9 Confirm open Core Spray System 1 Discharge valve V-20-12 (Panel 1F/2F).
3.2.10 Confirm open either Core Spray System 1 Parallel Isolation valve V-20-15 or V-20-40 (Panel 1F/2F).
(320010/S19)
E17-2
Procedure EMG-3200.01A Support Proc-15 Rev. 11 Attachment Q Page 3 of 6 3.2.11 As directed by the LOS start the Core Spray Booster Pump associated with the running main pump or the other main pump in Core Spray System 1.
3.2.12 Restore and maintain RPV water level as directed by the LOS, by cycling the Core Spray Parallel Isolation valves as required (Panel IF/2F).
3.2.13 Make up to the CST as necessary per Step 3.4 of this procedure.
3.3 Injecting the CST via Core Spray System 2 3.3.1 NOTE Overriding Core Spray initiation logic may be required.
Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 2 (Panel 1F/2F).
3.3.2 Place Core Spray System 2 Main Pump control switches in PULL-TO-LOCK position (Panel IF/2F).
3.3.3 Close Core Spray Pump Suction valves V-20-4 and V-20-33 (Panel IFM2F).
3.3.4 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 lA21A/RB 23 SW) 3.3.5 Confirm closed the Test Flow Return Valve V-20-26 (Panel IF/2F).
3.3.6 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)
OVER (320010/S19)
E17-3
Procedure EMG-3200.01A Support Proc-15 Rev. 11 Attachment Q Page 4 of 6 3.3.7 IF Bus 1C or iD are being supplied by a Emergency Diesel Generator, THEN verify that adequate load margin is available so as NOT to exceed EDG load limit when starting Core Spray Pumps.
3.3.8 Start Core Spray System 2 Main Pump NZO1B or NZOlD (Panel 1F/2F).
3.3.9 Confirm open Core Spray System 2 Discharge valve V-20-18 (Panel IF/2F).
3.3.10 Confirm open either Core Spray System 2 Parallel Isolation valve V-20-21 or V-20-41 (Panel lF/2F).
3.3.11 As directed by the LOS, start the Core Spray Booster Pump associated with the running main pump or the other main pump in Core Spray System 2.
3.3.12 Restore and maintain RPV water level as directed by the LOS by cycling the Core Spray Parallel Isolation valves as required (Panel 1F/2F).
3.3.13 Makeup to the CST as necessary per Step 3.4 of this procedure.
(320010/S19)
E17-4
Procedure EMG-3200.01A Support Proc-15 Rev. 11 Attachment Q Page 5 of 6 3.4 Making-up to the CST Determine which CST makeup source will be used.
- Firewater Makeup to the CST -
Continue at Step 3.4.1
- Demin Water Makeup to CST -
Continue at Step 3.4.2
- High Purity Waste Sample Tanks to the Hotwell -
Continue at Step 3.4.3.
3.4.1 Firewater Makeup to the CST
- 1.
Close the Telltale Drain Valve V-9-11 (Condensate Transfer Bldg).
- 2.
Unlock and open the Fire Water Isolation valve V-9-9 (Condensate Transfer Bldg).
- 3.
Open the Fire Protection to CST Isolation valve V-ll-247 (Condensate Transfer Bldg).
- 4.
Confirm both Diesel Fire Pumps are running by placing their control switches in MAN position (Panel 13R).
3.4.2 Demineralized Water Makeup to the CST
- 1.
Open Manual Isolation valves V-12-47 and V-12-49 (Condensate Transfer Bldg).
- 2.
Open Flow Control valve V-12-48 (Condensate Transfer Bldg).
- 3.
Start all available Demineralized Water Transfer pumps (Panel 13R).
- 4.
Open Demineralized Trailer Outlet valve V-10-383.
- 5.
Open the Supply valve to the Carbon Filter V-10-382.
OVER (320010/S19)
E17-5
Procedure EMG-3200.01A Support Proc-15 Rev. 11 Attachment Q Page 6 of 6
- 6.
Place the No. 1 Filter Feed Pump control switch to the ON position (Turbine Building Basement).
- 7.
IF the No. 1 Filter Feed Pump does not start, THEN Place the No. 2 Filter Feed Pump control switch to the ON position.
- 8.
Adjust the running Pump Discharge valve V-10-24 (Pump No. 1) or V-10-26 (Pump No. 2), as required to maintain inlet pressure at 90-100 psig.
- 9.
Throttle the chain operated Makeup System Outlet valve, V-55-70, as necessary to obtain approximately 75 gpm as read on the Final Effluent Flow Recorder (Turbine Building Basement).
3.4.3 Transfer of High Purity Waste Sample Tanks to the Hotwell
- 1.
Direct Radwaste to transfer both High Purity Waste Sample Tanks to the Hotwells in accordance with Procedure 351.2, High Purity Waste System.
- 2.
Inform Radwaste that no chemistry samples are required for the transfer.
(320010/S19)
E17-6
mer
-e, OYSTER CREEK GENERATING Number SAINPROCEDURE Can STATION y
EMG-3200.01B..
Title Revision No.
RPV CONTROL - WITH ATWS 13 Applicability/Scope Usage Level Responsible Department EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 1
OPERATIONS Effective z
ax Prior Revision 12 incorporated the This Revision 13 incorporates the following Temporary Changes:
following Temporary Changes:
N/A N/A LIST OF PAGES (all pgs.
rev'd to Rev. 13) 1.0 to 3.0 El-l E2-1 to E2-3 E3-1 E4-1 E5-1 to E5-2 E6-1 to E6-2 E7-1 to E7-5 E8-1 E9-1 to E9-4 E10-1 Ell-l to E11-2 E12-1 to E12-2 E13-1 to E13-2 E14-1 to E14-7 E15-1 E16-1 to E16-7 E17-1 to E17-8 OYSTER CREEK CONTROLLED DISTRIBUTION /7 DOCUMENT SERIAL NUMBER IRMC l
Signature Concurring Organization Element Date Orininator
/s/
EOP COORDINATOR 3/16/04 Concurred By
/s/
EOP COMMITTEE 3/16/04
_/s/_DIRECTOR ENGINEERING 3/20/04
/s/
PLANT OPERATIONS DIRECTOR 3/23/04 Approved By
/s/
PLANT MANAGER 3/24/04 (20001B) 1.0
a
_OYSTER CREEK GENERATING 1
Number i^ii 5ers:t I..
STATION PROCEDURE EMG-3206.01B An Exelon/
I Compaiy
-Title..
Revision.No.
RPV CONTROL - WITH ATWS 13 Applicability/Scope Usage Level Responsible Department EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK OPERATIONS I
Effectiy e Date incorporates the Changes:
Prior Revision 12 incorporated the following Temporary Changes:
This Revision 13 following Temporary N/A N/A LIST OF PAGES (all pgs. rev'd to Rev. 13) 1.0 to 3.0 El-l E2-1 to E2-3 E3-1 E4-1 E5-1 to E5-2 E6-1 to E6-2 E7-1 to E7-5 E8-1 E9-1 to E9-4 E10-1 E1l-l to E11-2 E12-1 to E12-2 E13-1 to E13-2 E14-1 to E14-7 E15-1 E16-1 to E16-7 E17-1 to E17-8 S,
gnature Concurring Organization Element Date Originator EOP COORDINATOR V
Concurred By
/1EOP COMMITTEE 3
0 DIRECTOR ENGINEERING
____________PLANT OPERATIONS DIRECTOR Approved By 2PLANT MANAGER V
(20001B) 1.0
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
- AD-OC-103, EOP-SAM 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, Elem 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 GE 237E566, Shts la, lb, 2, 4, & 5, Rx Protection System Elem 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 (20001B) 2.0
AmerGe n.
OYSTER CREEK GENERATING Number M a-bprf STATION PROCEDURE EMG-3200.01B.
Title Revision No.
RPV CONTROL - WITH ATWS 13 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 4.2 Attachment A
B 4.3 Attachment C -
4.4 Attachment 4.5 Attachment D
E RPV Control -
With ATWS EOP Flowchart EMG-3200.01B Rev.5 Support Procedure 1, Confirmation of Automatic Initiations and Isolations Support Procedure 16, Bypassing MSIV LO-LO Level Isolation Interlocks Support Procedure 17, Termination and Prevention of Injei Support Procedure 18, Bypassing RBCCW Isolation Interlocks Support Procedure 19, Feedwater/Condensate and CRD System Operation Support Procedure 20, Low Pressure Injection During an A' Support Procedure 10, Stopping Injection from the Core Spray System ction I
4.6 Attachment F -
4.7 Attachment 4.8 Attachment G
H rws 4.9 Attachment I -
4.10 Attachment J -
4.11 Attachment K -
4.12 Attachment L -
4.13 Attachment M -
Support Procedure 11, Alternate Pressure Control Systems -
Isolation Condensers Support Procedure 12, Alternate Pressure Control Systems -
EMRVs Support Procedure 13, Alternate Pressure Control Systems-Clean-up in Recirculation Mode Support Procedure 14, Alternate Pressure Control Systems -
Clean-up in Letdown Mode Support Procedure 15, Alternate Pressure Control Systems -
I C Tube Side Vents Support Procedure 21, Alternate Insertion of Control Rods Support Procedure 22, Initiating the Liquid Poison System Support Procedure 23, Alternate Boron Injection with the Clean-up System Support Procedure 24, Alternate Boron Injection with the Feed & Condensate System
- 4. 14
- 4. 15 4.16 Attachment Attachment Attachment N
0 P
4.17 Attachment Q -
(20001B)
- 3. 0
AmerGen OYSTER CREEK GENERATING Number STATION PROCEDURE
_ EMG-3200.01B.
Title Revision No.
RPV CONTROL - WITH ATWS 13 ATTACHMENT A Attachment A to EMG-3200.01B, RPV Control - With ATWS is the RPV Control -
With ATWS EOP Flowchart, EMG-3200.01B Rev.5.
I (20001B/S3)
El-l
Procedure EMG-3200.01B Support Proc-i Rev. 13 Attachment B Page I of 3 SUPPORT PROCEDURE 1 CONFIRMATION OF AUTOMATIC INITIATIONS AND ISOLATIONS 1.0 PREREQUISITES 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 4
Reactor Isolation IF Any of the following conditions exist:
- RPV water level at or below 86 in. and not bypassed
- Steam tunnel temperature at or above 180 0F
- Any steam line flow at or above 4.0x106 lbm/hr
- Reactor mode switch in RUN and RPV pressure at or below 850 psig
- Main steam line radiation at or above 800 units AND no ATWS condition exists THEN Confirm closed the following:
__NSO3A
__NS04A
__NS03B IC VENTS V-14-1,-19 V-14-5,-20 RX SAMPLE
___V-24-30 (11F)
V-24-29 (11F)
DW AIR SUPPLY
__V-6-395 (11F)
NS04B Scram IF A Reactor Scram is initiated Discharge AND Volume Isolation SDV HI-HI LVL SCRAM switch is not in BYPASS, THEN Confirm closed the following:
NORTH SDV Vents & Drains SOUTH SDV Vents & Drains OVER (20001B/S4)
E2-1
Procedure EMG-3200.01B Support Proc-i Rev. 13 Attachment B Page 2 of 3 SYSTEM OPERATING DETAILS IC-A IF 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 IF 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 Cleanup IF Any of the following conditions exist:
Isolation RPV water level at or below 86 in. and not bypassed Drywell pressure at or above 3.0 psig RWCU HELB Alarms THEN Confirm closed the following Cleanup Isolation valves:
V-16-1
__V-16-14 V-16-2
__V-16-61 Shutdown IF 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 closed the following SDC Isolation Valves:
V-17-54
__V-17-19 Isolation IF RPV water level is at or below 86 in.,
Condenser Initiation THEN confirm initiation of both Isolation Condensers.
Core Spray IF Any of the following conditions exist:
Start RPV water level at or below 86 in. and not bypassed.
Drywell pressure at or above 3.0 psig and not bypassed.
THEN Confirm start of one Main Pump and one Booster Pump in each Core Spray System if not bypassed.
(20001B/S4)
E2-2
Procedure EMG-3200.01B Support Proc-i Rev. 13 -
Attachment B Page 3 of 3 SYSTEM OPERATING DETAILS Primary Containment Isolation IF Any of the following conditions exist:
RPV water level at or below 86 in. and not bypassed.
Drywell pressure at or above 3.0 psig and not bypassed.
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 of V-27-3 V-27-4 Torus Vent V-28-17 (Panel 11F)
V-28-18 It Torus 2" Vent Bypass V-28-47 (Panel 11F)
DWEDT V-22-1 (Panel 11F)
V-22-2 if DW Floor Sump V-22-28 (Panel 11F)
V-22-29 is 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 V-23-18 V-23-19 V-23-20 (Panel 12XR)
(20001B/S4)
E2-3
Procedure EMG-3200.01B Support Proc-16 Rev. 13 Attachment C Page 1 of 1 SUPPORT PROCEDURE 16 BYPASSING MSIV LO-LO LEVEL ISOLATION INTERLOCKS 1.0 PREREQUISITES Bypassing of the MSIV Lo-Lo level isolation interlocks has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 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 BP1.
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 llF).
3.5 Inform the LOS that the MSIV LO-LO Level Isolation Interlock has been bypassed.
(20001B/S5)
E3-1
Procedure EMG-3200.01B Support Proc-17 Rev. 13 Attachment D Page 1 of 1 SUPPORT PROCEDURE 17 TERMINATION AND PREVENTION OF INJECTION 1.0 PREREQUISITES Termination and prevention of injection has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Inform the operator controlling reactor pressure and the LOS that the Isolation Condensers will initiate when RPV level reaches lo-lo water level.
3.2 Terminate and prevent Core Spray injection by performing the following at Panel 1F/2F:
3.2.1 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 (Panel lF/2F).
3.2.2 Confirm all Core Spray Parallel Isolation Valve closed.
3.2.3 Confirm all operating Core Spray Booster Pumps tripped.
3.2.4 Confirm all Core Spray Main Pump control switches in PULL-TO-LOCK position.
3.3 Terminate and prevent Condensate and Feedwater injection by performing the following at Panel 5F/6F:
3.3.1 Trip all operating Feedwater Pumps.
3.3.2 Confirm one Condensate Pump running.
3.3.3 Place all individual FRV Controllers in MAN position.
3.3.4 Close all Feedwater Regulating Valves.
3.3.5 Close the Low Flow Valves.
(20001B/S6)
E4-1
Procedure EMG-3200.01B Support Proc-18 Rev. 13 Attachment E Page I of 2 SUPPORT PROCEDURE 18 BYPASSING RBCCW ISOLATION INTERLOCKS 1.0 PREREQUISITES Bypassing of the RBCCW isolation has been directed by the Emergency Operating Procedures AND the RBCCW system is NOT isolated due to a LOCA or Main Steam Line Break (MSLB) in the Drywell.
2.0 PREPARATION 2.1 CAUTION Reinitiating RBCCW flow to the Drywell following a LOCA or MSLB in the Drywell may cause a water hammer to occur and subsequent piping failure.
Verify that the RBCCW System is not isolated due to high Drywell pressure/low RPV water level conditions.
2.2 IF the RBCCW System is isolated due to high Drywell pressure/low RPV water level, THEN inform the LOS and do not attempt to reinitiate the RBCCW System flow to the Drywell.
2.3 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.
2.3.1 Remove the bypass plug from position BP1.
2.3.2 Remove the bypass plug from position BP2.
OVER (20001B/S7)
Procedure EMG-3200.01B Support Proc-18 Rev. 13 Attachment E Page 2 of 2 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 llF).
(20001B/S7)
E5-2
Procedure EMG-3200.01B Support Proc-19 Rev. 13 Attachment F Page I of 2 SUPPORT PROCEDURE 19 FEEDWATER/CONDENSATE AND CRD SYSTEM OPERATION 1.0 PREREQUISITES Directed to maintain RPV level with the Feed, Condensate and CRD Systems by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE CAUTION A large power excursion and substantial core damage could result from a rapid increase in injection into the RPV.
I 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:
- Feedwater Regulating Valves
- MFRV Block Valves
- Feedwater Low Flow Valves
- Heater Bank Outlet Isolation Valves
- Feedwater and Condensate Pumps 3.1.3 IF RPV water level cannot be restored and maintained below 160 in.,
THEN close the Heater Bank Outlet Isolation Valve for the operating pump.
3.1.4 IF RPV water level reaches 170 in.,
THEN trip the operating feedwater pump.
OVER (20001B/S8)
E6-1
Procedure EMG-3200.01B Support Proc-19
-Rev -:13 Attachment F Page 2 of 2 3.1.5 IF RPV water level reaches 170 in.,
AND RPV pressure is below 350 psig (shutoff head of the Condensate Pumps),
close all Heater Bank Outlet Isolation Valves.
RPV water level continues to increase, trip the operating Condensate Pumps.
THEN 3.1.6 IF THEN 3.2 CRD 3.2.1 IF Control Rods cannot be driven using CRD AND CRD bypass flow is desired for RPV water level
- control, THEN
- 1. Start all available CRD Pumps.
AND throttle open CRD Bypass Valve V-15-30 (RB 23 SE) so as not to exceed 150 gpm flow for one or two pump operation.
water level cannot be maintained less than 3.2.2 IF RPV 160 in.,
THEN
- 2. Throttle closed CRD Flow Control Valve.
3.2.3 IF RPV water level reaches 170 in.,
AND the CRD System is NOT required for rod insertion, THEN trip any operating CRD pump.
(20001B/S8)
E6-2
Procedure EMG-3200.01B Support Proc-20 Rev. 13 Attachment G Page I of 5 SUPPORT PROCEDURE 20 LOW PRESSURE INJECTION DURING AN ATWS 1.0 PREREQUISITES Injecting water with Low Pressure Systems has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 IF 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 (Panel lF/2F).
using Condensate Transfer for injection, access to the Rx. Bldg. is available and that operator has an MB-1 key.
2.2 IF THEN
- 3. 0 PROCEDURE 3.1 Determine which RPV injection source is to be used:
- Firewater via Core Spray System 1 -
step 3.2
- Firewater via Core Spray System 2 -
step 3.3
- Condensate Transfer via Core Spray System 1 -
step 3.4
- Condensate Transfer via Core Spray System 2 -
step 3.5 Core Spray -
step 3.6 3.2 Injecting Fire Water via Core Spray System 1.
3.2.1 Verify Condensate Transfer is not being injected via Core Spray System 1.
3.2.2 NOTE Overriding Core Spray initiation logic may be required.
Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 1 (Panel 1F/2F).
3.2.3 Place Core Spray System 1 Main Pump control switches in PULL-TO-LOCK position (Panel 1F/2F).
3.2.4 Close Tell-Tale Drain Valve, V-20-91 (RB 23 North or North Side RB outside).
3.2.5 Confirm running all Diesel Fire Pumps by placing their control switches in MAN position (Panel 13R).
3.2.6 Confirm open Core Spray System 1 Discharge Valve, V-20-12 (Panel 1F/2F).
OVER (20001B/S9)
E7-1
Procedure EMG-3200.01B Support Proc-20 Rev. 13 Attachment G Page 2 of 5 3.2.7 Confirm open either Core Spray System 1 Parallel Isolation Valve, V-20-15 or V-20-40 (Panel 1F/2F).
3.2.8 Confirm closed Core Spray System 1 Test Flow Return Valve, V-20-27 (Panel 1F/2F).
3.2.9 Close Core Spray System 1 Pump Suction Valves V-20-3 and V-20-3 (Panel 1F/2F).
3.2.10 Slowly throttle open Fire Water Supply Valve, V-20 (RB 23 North or North Side RB outside) as required tc maintain RPV Level.
3.3 Injecting Fire Water via Core Spray System 2.
3.3.1 Verify Condensate Transfer is not being injected via Core Spray System 2.
2 3
I 3.3.2 NOTE Overriding Core Spray initiation logic may be required.
Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 2 (Panel IF/2F).
3.3.3 Place Core Spray System 2 Main Pump control switches in PULL-TO-LOCK position (Panel IF/2F).
3.3.4 Close Tell-Tale Drain Valve, V-20-90 (RB 23 South or South Side RB outside).
3.3.5 Confirm running all Diesel Fire Pumps by placing their control switches in MAN position (Panel 13R).
3.3.6 Confirm open Core Spray System 2 Discharge Valve, V-20-18 (Panel 1F/2F).
3.3.7 Confirm open either Core Spray System 2 Parallel Isolation Valve, V-20-21 or V-20-41 (Panel IF/2F).
3.3.8 Confirm closed Core Spray System 2 Test Flow Return Valve, V-20-26 (Panel 1F/2F).
(20001B/S9)
E7-2
Procedure EMG-3200.01B Support Proc-20
.Rev.-13 Attachment G Page 3 of 5 3.3.9 Close Core Spray System 2 Pump Suction Valves V-20-33 and V-20-4 (Panel IF/2F).
3.3.10 Slowly throttle open Fire Water Supply Valve, V-20-82 (RB 23 South or South Side RB outside) as required to maintain RPV Level.
3.4 Injecting Condensate Transfer via Core Spray System 1.
3.4.1 Verify Fire Water is not being injected via Core Spray System 1.
3.4.2 NOTE Overriding Core Spray initiation logic may be required.
Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 1 (Panel IF/2F).
3.4.3 Place Core Spray System 1 Main Pump control switches in PULL-TO-LOCK position (Panel 1F/2F).
3.4.4 Unlock and open Regulator Bypass valves, V-11-110 and V-11-111 (RB 51 NW).
3.4.5 Confirm open Core Spray System 1 Discharge Valve, V-20-12 (Panel IF/2F).
3.4.6 Confirm open either Core Spray System 1 Parallel Isolation valve, V-20-15 or V-20-40 (Panel IF/2F).
3.4.7 Confirm closed Core Spray System 1 Test Flow Return Valve, V-20-27 (Panel IF/2F).
3.4.8 Start all available Condensate Transfer Pumps (Panel 5F/6F).
3.4.9 Close Core Spray System 1 Pump Suction Valves V-20-32 and V-20-3 (Panel IF/2F).
OVER (20001B/S9)
E7-3
Procedure EMG-3200.01B Support Proc-20 Rev. 13 Attachment G Pages4 of 5 3.5 Injecting Condensate Transfer via Core Spray System 2.
3.5.1 Verify Firewater is not being injected via Core Spray System 2.
3.5.2 NOTE Overriding Core Spray initiation logic may be required.
Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 2 (Panel 1F/2F).
3.5.3 Place Core Spray System 2 Main Pump control switches in PULL-TO-LOCK position (Panel IF/2F).
3.5.4 Unlock and open Regulator Bypass valves, V-11-109 and V-11-108 (RB 75 S).
3.5.5 Confirm open Core Spray System 2 Discharge Valve, V-20-18 (Panel IF/2F).
3.5.6 Confirm open either Core Spray System 2 Parallel Isolation Valve, V-20-21 or V-20-41 (Panel 1F/2F).
3.5.7 Confirm closed Core Spray System 2 Test Flow Return Valve, V-20-26 (Panel IF/2F).
3.5.8 Start all available Condensate Transfer Pumps (Panel-5F/6F).
3.5.9 Close Core Spray System 2 Pump Suction Valves V-20-33 and V-20-4 (Panel IF/2F).
3.6 Injection with the Core Spray Main Pump CAUTION Core Spray suction strainer plugging may occur due to debris in the Primary Containment and result in a loss of Core Spray System Flow.
3.6.1 Confirm open Core Spray Pump Suction Valve for pump to be started (Panel IF/2F).
(20001B/S9)
E7-4
Procedure EMG-3200.01B Support Proc-20
-Rev.
13'-
Attachment G Page 5 of 5 3.6.2 CAUTION Diesel Generator overload will result if a Core Spray Main Pump is started with a Diesel Generator load of greater than 2250 kw.
IF Bus lC or ID are being supplied by a Emergency Diesel Generator, THEN verify that adequate load margin is available so as NOT to exceed EDG load limit when starting Core Spray Main Pumps.
3.6.3 CAUTION NPSH problems will develop on all operating pumps if more than 4 Containment Spray/Core Spray Main pumps are operated at the same time.
IF 4 Containment Spray/Core Spray Main pumps are in operation, THEN secure Containment Spray pumps as necessary to run Core Spray pumps.
3.6.4 Start one Core Spray Main Pump (Panel IF/2F).
3.6.5 Confirm open the selected system Discharge Valve (V-20-12 or V-20-18). (Panel 1F/2F) 3.6.6 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) 3.6.7 As directed by the LOS, start a Main Pump in the other Core Spray System, or open additional Parallel Isolation Valves.
(20001B/S9)
E7-5
Procedure EMG-3200.01B Support Proc-10 Rev. 13 Attachment H Page I of 1 SUPPORT PROCEDURE 10 STOPPING INJECTION FROM THE CORE SPRAY SYSTEM 1.0 PREREQUISITES Stopping Core Spray injection has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE When directed by the LOS, 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 1F/2F).
3.3 Confirm closed Core Spray Parallel Isolation Valves NOT required to be open to assure adequate core cooling.
3.4 Secure Core Spray Booster Pumps NOT required to assure adequate core cooling by placing their respective control switch in STOP (Panel IF/2F).
3.5 Secure Core Spray Main Pumps NOT 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 NOT illuminated.
(20001B/SIO)
E8-1
Procedure EMG-3200.01B Support Proc-il Rev. 13 Attachment I Page I of 4 SUPPORT PROCEDURE 11 ALTERNATE PRESSURE CONTROL SYSTEMS ISOLATION CONDENSERS 1.0 PREREQUISITES RPV pressure control using the Isolation Condensers has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Procedure for Isolation Condenser A 3.1.1 Confirm Recirculation Pump A tripped.
IF Recirculation Pump A cannot be tripped from the Control Room, THEN trip the Recirculation Pump A Supply Breaker locally at 4160V Bus 1A.
3.1.2 CAUTION If RPV water level exceeds 180 in., initiation of an isolation condenser can cause water hammer to occur.
Verify RPV water level is below 160 in.
3.1.3 IF Isolation Condenser A has isolated on a high flow condition caused by Recirculation Pump operation, THEN restore the IC to operation as follows:
- 1.
Open Steam Supply valves V-14-30 & V-14-31 by placing their control switches in the OPEN position (Panel 1F/2F).
- 2.
Open DC Condensate Return valve V-14-34 by placing its control switch in the OPEN position (Panel 1F/2F).
OVER (20001B/Sll)
E9-1
Procedure EMG-3200.01B Support Proc-li Rev.
13 Attachment I Page 2 of 4
- 3.
Open AC Condensate Return valve V-14-36 by placing its control switch in the OPEN position (Panel IF/2F).
- 4.
Reset the Isolation Condenser isolation signal using the Isolation Condenser Reset pushbutton (Panel 4F).
- 5.
Restore all Isolation Condenser A valve control switches to their AUTO position.
3.1.4 Confirm Open DC condensate return valve V-14-34 (Panel IF/2F).
3.1.5 Control RPV pressure as directed by the LOS by cycling V-14-34.
3.1.6 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).
(20001B/Sll)
E9-2
Procedure EMG-3200.01B Support Proc-1l Rev. 13 Attachment I Page 3 of 4 3.2 Procedure For Isolation Condenser B 3.2.1 Confirm Recirculation Pump E tripped.
IF Recirculation Pump E cannot be tripped from the Control Room, THEN trip the Recirculation Pump E Supply Breaker locally at 4160V Bus 1A.
3.2.2 CAUTION If RPV water level exceeds 180 in., initiation of an isolation condenser can cause water hammer to occur.
Verify RPV water level is below 160 in.
3.2.3 IF Isolation Condenser B has isolated on a high flow condition caused by Recirculation Pump operation, THEN restore the IC to operation as follows:
- 1.
Open Steam Supply valves V-14-32 & V-14-33 by placing their control switches in the OPEN position (Panel 1F/2F).
- 2.
Open DC Condensate Return valve V-14-35 by placing its control switch in the OPEN position (Panel 1F/2F).
- 3.
Open AC Condensate Return valve V-14-37 by placing its control switch in the OPEN position (Panel 1F/2F).
- 4.
Reset the Isolation Condenser isolation signal using the Isolation Condenser Reset pushbutton (Panel 4F).
- 5.
Restore all Isolation Condenser B valve control switches to their AUTO position.
OVER (20001B/Sll)
E9-3
Procedure EMG-3200.01B Support Proc-11 Rev. 13 Attachment I Page 4 of 4 3.2.4 Confirm open DC condensate return valve V-14-35 (Panel 1F/2F).
3.2.5 Control RPV pressure as directed by the LOS cycling V-14-35.
3.2.6 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).
(20001B/Sll)
E9-4
Procedure EMG-3200.01B Support Proc-12 Rev.-13 Attachment J Page I of 1 SUPPORT PROCEDURE 12 ALTERNATE PRESSURE CONTROL SYSTEMS EMRVs 1.0 PREREQUISITES 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 in.
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:
NR1O8A NR108D NR108B NR108C NR108E 3.4 Monitor Torus water temperature.
(20001B/S12)
E10-1
Procedure EMG-3200.01B Support Proc-13 Rev. 13 Attachment K Page I of 2 SUPPORT PROCEDURE 13 ALTERNATE PRESSURE CONTROL SYSTEMS CLEANUP IN RECIRCULATION MODE 1.0 PREREQUISITES 1.1 RPV pressure control using the Reactor Water Cleanup System in Recirculation Mode has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 Confirm that a Cleanup System line break does not exist (Alarms D-l-d/D-2-d).
2.2 Open the EOP BYPASS PLUGS panel in the rear of Panel 3F.
2.2.1 Remove the bypass plug from position BP2 and insert into position BP1.
2.2.2 Remove the bypass plug from position BP4 and insert into position BP3.
2.2.3 Remove the bypass plug from position BP6 and insert into position BP5.
2.2.4 Remove the bypass plug from position BP8 and insert into position BP7.
2.3 Obtain a flat head screwdriver from the EOP Tool Box in the Control Room.
2.4 Open the front panel of Auxiliary Relay Panel ER-215-087 (A/B Battery Room).
2.4.1 Remove bypass plug 1 (upper left hand corner).
2.4.2 Remove bypass plug 2 (upper left hand corner).
OVER (20001B/S13)
E11-1
Procedure EMG-3200.01B Support Proc-13 Rev. 13 Attachment K Page 2 of 2 3.0 PROCEDURE When directed by the LOS, perform the following 3.1 Bypass and isolate Cleanup Filters as follows:
3.1.1 Open V-16-83, Filter Bypass Valve (RB 75).
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 IF 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 Heat Exchanger.
Maximum RBCCW flow allowed is 1750 gpm.
3.5 Maintain RPV pressure as directed by the LOS by throttling RBCCW flow to the NRHX.
(20001B/S13)
E11-2
Procedure EMG-3200.01B Support Proc-14 Rev. 13 Attachment L Page I of 2 SUPPORT PROCEDURE 14 ALTERNATE PRESSURE CONTROL SYSTEMS CLEANUP IN LETDOWN MODE 1.0 PREREQUISITES 1.1 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 PROCEDURE 3.1 Confirm that a Cleanup System line break does not exist (Alarms D-1-d/D-2-d).
3.2 IF Cleanup System is not in service THEN place the system in service in accordance with Procedure 303, Reactor Cleanup Demineralizer System.
3.3 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).
3.4 Open Discharge to Condenser Valve V-16-60 (Panel 3F).
3.5 Commence Letdown Flow to the main condenser by throttling open Discharge Flow Controller FCV-ND-22 (Panel 3F).
3.6 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.
3.7 Maintain NRHX outlet temperature below 1300F 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.
3.8 Adjust letdown flow rate by throttling FCV-ND-22 to establish required cooldown rate or pressure band.
OVER (20001B/S14)
E12-1
Procedure EMG-3200.01B Support Proc-14 Rev. 13 Attachment L Page 2 of 2 3.9 IF NRHX outlet temperature cannot be maintained less than 13 0°F AND 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. Bypass and isolate the Cleanup Demineralizer:
NOTE The remote valve operators to valves V-16-102, V-16-113, and V-16-114 have been disconnected.
- b.
Close Demineralizer Outlet Valve V-16-114 (RB 75 SW).
- 3. Contact I & C Department to inhibit the NRHX 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 letdown flow.
- 6. Adjust letdown flow rate by throttling FCV-ND-22 to establish required cooldown rate or pressure band.
(20001B/S14)
E12-2
Procedure EMG-3200.01B Support Proc-l5 Rev. 13 Attachment M Page I of 2 SUPPORT PROCEDURE 15 ALTERNATE PRESSURE CONTROL SYSTEMS IC TUBE SIDE VENTS 1.0 PREREQUISITES 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 Open the EOP BYPASS PLUGS panel inside of Panel lOXF.
2.2.1 Remove the bypass plug from position BP2 and insert it into position BP1.
2.2.2 Remove the bypass plug from position BP4 and insert it into position BP3.
OVER (20001B/SlS)
E13-2
Procedure EMG-3200.01B Support Proc-15 Rev. 13 Attachment M Page 2 of 2 3.0 PROCEDURE 3.1 Verify that RPV water level is below 180 in.
3.2 Confirm open the Isolation Condenser Steam Inlet Valves (lF/2F) for the Isolation Condensers to be used.
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 llF) for the Isolation Condensers to be used.
Isolation Condenser A V-14-5 V-14-20 Isolation Condenser B V-14-1 V-14-19 3.4 Control Reactor pressure as directed by the LOS by cycling the tube side vents designated in Step 3.3.
(20001B/S15)
E13-2
Procedure EMG-3200.01B Support Proc-21 Rev. 13 Attachment N Page I of 7 SUPPORT PROCEDURE 21 ALTERNATE INSERTION OF CONTROL RODS 1.0 PREREQUISITES Insertion of Control Rods utilizing alternate methods has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Manual Rod Insertion 3.1.1 Confirm all available CRD pumps are running.
3.1.2 Close Charging Header Supply valve V-15-52 (RB 23 SE).
3.1.3 Place Reactor Mode Switch in REFUEL.
3.1.4 Place the ROD WORTH MINIMIZER keylock in BYPASS.
3.1.5 Close CRD DRIVE WATER PRESSURE CONTROL NC18 (Panel 4F) to maximize CRD drive water differential pressure.
3.1.6 IF CRD Bypass valve V-15-30 is open for RPV injection, THEN close CRD Bypass valve V-15-30 (RB 23 SE).
3.2 Identify whether an ELECTRICAL ATWS or an HYDRAULIC ATWS is in progress.
SYMPTOMS INDICATOR ELECTRICAL HYDRAULIC Group scram solenoids ENERGIZED DE-ENERGIZED Scram air header PRESSURIZED DEPRESSURIZED Individual scram lights (4F)
CLOSED OPEN ELECTRICAL ATWS -
Continue in Section 4.0 HYDRAULIC ATWS -
Continue in Section 5.0 OVER (20001B/S16)
E14-1
Procedure EMG-3200.-OB Support Proc-21 Rev. 13 Attachment N Page 2 of 7 4.0 ELECTRICAL ATWS NOTE Alternate methods of control rod insertion for electrical ATWS may be performed in any order or concurrently as applicable.
4.1 Vent the Scram Air Header 4.1.1 Close Scram Air Header isolation valve V-6-175 (RB 23 SE).
4.1.2 Open Scram Air Header drain valve V-6-409 (RB 23 SE).
4.1.3 WHEN control rods are no longer moving in, THEN
4.2 De-energize the Scram Solenoids 4.2.1 IF MSIVs are OPEN, THEN place RPS Channel I and II Subchannel Test Keylocks IA, IB, IIA and IIB in the Trip position (Panels 6R/7R).
WHEN the control rods are no longer moving in, THEN confirm the RPS Channel I and II Subchannel Test keylocks in the NORMAL position.
4.2.2 IF MSIVs are CLOSED, THEN place both 100 amp Main RPS breakers in OFF (Panels 6R/7R).
WHEN the control rods are no longer moving in, THEN confirm both 100 amp Main RPS breakers in ON.
4.3 Increase CRD Cooling Water Differential Pressure 4.3.1 Confirm all available CRD pumps are running.
4.3.2 Close Charging Header Supply valve V-15-52 (RB 23 SE).
4.3.3 Increase CRD cooling water differential pressure by closing CRD Cooling Water PCV NC40 (Panel 4F).
4.3.4 IF CRD Bypass valve V-15-30 is open for RPV injection, THEN close CRD Bypass valve V-15-30 (RB 23 SE).
(20001B/S16)
E14-2
Procedure EMG-3200.01B Support Proc-21 Rev. 13 Attachment N Page 3 of 7 4.4 Open Individual Scram Test Switches 4.4.1 Confirm all available CRD pumps are running.
4.4.2 Confirm open SDV vent and drain valves (Panel 4F).
4.4.3 CAUTION While performing this procedure, potentially radioactive steam may be released and Reactor Building airborne contamination levels may increase.
Individually open the scram test toggle switch on Panel 6XR for a control rod not inserted.
4.4.4 Monitor Reactor Building airborne radiation levels.
4.4.5 WHEN the control rod stops moving, THEN close the scram test toggle switch.
4.4.6 Repeat steps 4.4.3 and 4.4.5 as required in order to insert control rods.
NOTE This method is to be used ONLY if all other insertion methods fail.
4.5 Vent the Control Rod Drive Over Piston Volume NOTE If no CRD pumps are available, this method may still be used provided reactor pressure is greater than 600 psig.
CAUTION While performing this procedure, potentially radioactive steam will be released from the drain line effluent and Reactor Building airborne contamination levels may increase.
4.5.1 Confirm all available CRD pumps are running.
4.5.2 Close Cooling Water PCV Isolation valve V-15-24 (RB 23 SE).
4.5.3 Close Exhaust Header Root valve V-15-25 (RB 23 SE).
4.5.4 Close Stabilizer Unit Outlet valve V-15-40 (RB 23 SE).
4.5.5 Confirm closed Cooling Water PCV Bypass valve V-15-131 (RB 23 SE).
4.5.6 Open drain valve V-15-74 (RB 23 SE).
4.5.7 Evacuate the Reactor Building.
4.5.8 Place Reactor Mode Switch in REFUEL.
4.5.9 Insert control rods manually from Panel 4F.
OVER (20001B/S16)
E14-3
Procedure EMG-3200.01B Support Proc-21 Rev. 13 Attachment N Page 4 of 7 4.5.10 Monitor Reactor Building airborne radiation levels.
4.5.11 WHEN control rods are no longer moving in, THEN 1. Close V-15-74 (RB 23 SE).
- V-15-40 V-15-25 V-15-24 5.0 HYDRAULIC ATWS NOTE Alternate methods of control rod insertion for hydraulic ATWS may be performed in any order or concurrently as applicable.
5.1 Reset the Scram and Manually Scram the Reactor 5.1.1 Confirm all available CRD pumps are running.
5.1.2 Place the ARI Normal/Bypass switch in the BYPASS position (Rear of Panel 8R).
5.1.3 Depress the ARI Manual Reset pushbutton.
5.1.4 IF RPS automatic scram signals are present (except SDV HI-HI level),
THEN perform the following unless already completed in Step 5.2.4:
- 1.
Obtain four (4) bypass plugs from the EOP tool box.
- 2.
Open the EOP BYPASS PLUGS panel in the rear of Panel 6R and, Insert a bypass plug in BP5 Insert a bypass plug in BP6
- 3.
Open the EOP BYPASS PLUGS panel in the rear of Panel 7R, and, Insert a bypass plug into BP5 Insert a bypass plug into BP6 5.1.5 If necessary, place the SDV HI LVL BYPASS switch to BYPASS.
(20001B/Sl6)
E14-4
Procedure EMG-3200.01B Support Proc-21 Rev. 13 Attachment N Page 5 of 7 5.1.6 Reset the scram by depressing the Scram Reset Buttons.
5.1.7 Confirm open the SDV Vent and Drain valves (Panel 4F).
5.1.8 WHEN the SDV LEVEL HI-HI alarms (H-1-b and H-2-b) clear, THEN manually scram the reactor by depressing the scram buttons.
5.1.9 Repeat steps 5.1.6 through 5.1.8 as required to insert control rods.
5.2 Open Individual Scram Test Switches 5.2.1 Confirm all available CRD pumps are running.
5.2.2 Place the ARI Normal/Bypass switch in the BYPASS position (Rear of Panel 8R).
5.2.3 Depress the ARI Manual Reset pushbutton.
5.2.4 IF RPS automatic scram signals are present (except SDV HI-HI level).
THEN perform the following unless already completed in Step 5.1.4:
- 1. Obtain four (4) bypass plugs from the EOP tool box.
- 2. Open the EOP BYPASS PLUGS panel in the rear of Panel 6R and,
- Insert a bypass plug into BP5 Insert a bypass plug into BP6
- 3. Open the EOP BYPASS PLUGS panel in the rear of Panel 7R and, Insert a bypass plug into BP5
- Insert a bypass plug into BP6 5.2.5 If necessary, place the SDV HI LVL BYPASS switch to BYPASS.
5.2.6 Reset the scram by depressing the Scram Reset Buttons.
5.2.7 Confirm open SDV Vent and Drain valves (Panel 4F).
OVER (20001B/S16)
E14-5
Procedure EMG-3200.01B Support Proc-21 Rev. 13 Attachment N Page 6 of 7 5.2.8 CAUTION While performing this procedure, potentially radioactive steam may be released and Reactor Building airborne contamination levels may increase.
Individually open the scram test toggle switch on Panel 6XR for a control rod not inserted.
5.2.9 Monitor Reactor Building airborne radiation levels.
5.2.10 WHEN the control rod stops moving, THEN close the scram test toggle switch.
5.2.11 Repeat steps 5.2.8 and 5.2.10 as required in order to insert control rods.
5.3 Increasing CRD Cooling Water Differential Pressure 5.3.1 Confirm all available CRD pumps are running.
5.3.2 Close Charging Header Supply valve V-15-52 (RB 23 SE).
5.3.3 Increase CRD cooling water differential pressure by closing CRD Cooling Water PCV NC40 (Panel 4F).
5.3.4 IF CRD Bypass valve V-15-30 is open for RPV injection, THEN close CRD Bypass valve V-15-30 (RB 23 SE).
NOTE This method is to be used ONLY if all other insertion methods fail.
5.4 Vent the Control Rod Drive Over Piston Volume NOTE If no CRD pumps are available, this method may still be used provided reactor pressure is greater than 600 psig.
CAUTION While performing this procedure, potentially radioactive steam will be released from the drain line effluent and Reactor Building airborne contamination levels may increase.
5.4.1 Confirm all available CRD pumps are running.
(20001B/S16)
E14-6
Procedure EMG-3200.01B Support Proc-21 Rev. 13 Attachment N Page 7 of 7 5.4.2 Close Cooling Water PCV Isolation valve V-15-24 (RB 23 SE).
5.4.3 Close Exhaust Header Root valve V-15-25 (RB 23 SE).
5.4.4 Close Stabilizer Unit Outlet valve V-15-40 (RB 23 SE).
5.4.5 Confirm closed Cooling Water PCV Bypass valve V-15-131 (RB 23 SE).
5.4.6 Open drain valve V-15-74 (RB 23 SE).
5.4.7 Place Reactor Mode Switch in REFUEL.
5.4.8 Insert control rods manually from Panel 4F.
5.4.9 Monitor Reactor Building airborne radiation levels.
5.4.10 WHEN control rods are no longer moving in, THEN 1. Close V-15-74 (RB 23 SE).
- V-15-40
- V-15-25
- V-15-24 (20001B/S16)
E14-7
Procedure EMG-3200.01B Support Proc-22 Rev. 13 Page I of 1 SUPPORT PROCEDURE 22 INITIATING THE LIQUID POISON SYSTEM 1.0 PREREQUISITES Initiation of Standby Liquid Control System has been directed by the Emergency Operating Procedures.
2.0 PREPARATIONS None 3.0 PROCEDURE CAUTION Due to pressure fluctuations, Fuel Zone Level Indicator Channels "A" and "C" will not provide accurate indication of RPV 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 I 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 annunciates (G-l-b).
- 5. SQUIB VALVE OPEN Alarm annunciates (G-2-b).
3.3 IF the above expected indications do NOT occur, THEN
- 1.
Place the STANDBY LIQUID CONTROL Keylock in the opposite position to use the other system.
- 2.
Verify proper operation using step 3.2 (20001B/S17)
E15-1
Procedure EMG-3200.01B Support Proc-23 Rev. 13 Attachment P Page I of 7 SUPPORT PROCEDURE 23 ALTERNATE BORON INJECTION WITH THE CLEANUP SYSTEM 1.0 PREREQUISITES 1.1 Injection of Boron via the Cleanup System has been directed by the Emergency Operating Procedures.
2.0 PREPARATION 2.1 Confirm that a Cleanup System line break does not exist.
(Alarms D-1-d/D-2-d).
NOTE 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.
2.2 Open the EOP BYPASS PLUGS panel in the rear of Panel 3F.
2.2.1 Remove the bypass plug from position BP2 and insert into position BPI.
2.2.2 Remove the bypass plug from position BP4 and insert into position BP3.
2.2.3 Remove the bypass plug from position BP6 and insert into position BP5.
2.2.4 Remove the bypass plug from position BP8 and insert into position BP7.
2.3 Obtain a flat head screwdriver from the EOP Tool Room in the Control Room.
2.4 Open the front panel of Auxiliary Relay Panel ER-215-087 (A/B Battery Room).
2.4.1 Remove bypass plug 1 (upper left hand corner).
2.4.2 Remove bypass plug 2 (upper left hand corner).
OVER (20001B/S18)
E16-1
Procedure EMG-3200.01B Support Proc-23 Rev. 13 Attachment P Page 2 of 7 3.0 PROCEDURE When directed by the LOS, perform the following:
3.1 IF no recirculation pump is running, THEN
- 1. Confirm at least one recirculation loop suction and 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 closed 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 IF the 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).
3.5.2l CAUTION If Sludge Receiver Tank level is over nine (9) feet, thel 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 ft.
level increase will occur per backwash.
(20001B/S18)
E16-2
Procedure EMG-3200.01B Support Proc-23 Rev. 13 Attachment P Page 3 of 7 3.5.3 NOTE Only one set of Filter Recycle Valves are capable of being open at any one time.
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.
- 2.
ND-23A(B), Air Inlet Valve, opens.
- 3.
ND-25A(B), 1 in. 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.
- 8.
ND-24A(B), Vent/Overflow Valve, opens.
- 9.
ND-29A(B), Backwash Inlet Valve, opens.
- 10.
ND-29A(B), Backwash Inlet Valve, closes.
- 11.
ND-24A(B) closes.
- 12.
ND-26A(B) closes.
OVER (20001B/S18)
E16-3
Procedure EMG-3200.01B Support Proc-23 Rev. 13 Attachment P Page 4 of 7 3.6 IF 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 IF the contents of the SLC Storage Tank is being injected using 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 Filter Aid Precoat Tank by performing Steps 3.9.1 through 3.9.4.
3.9.1 Connect a hose downstream of V-19-22, Pump A Suction Header Drain Valve (RB95), and route the free end to the Filter Aid Precoat Tank.
Insert it through the hinged lid at the top and secure.
3.9.2 Unlock V-19-22, Pump A Suction Header Drain Valve.
3.9.3 Open V-19-22, Pump A Suction Header Drain Valve and fill the Filter Aid Precoat Tank to 90% full by gravity draining the SLC Storage Tank.
3.9.4 Close V-19-22, Pump A Suction Header Drain Valve.
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 position.
3.15 Start the Precoat Pump in HAND position.
3.16 Open ND25A(B), 1 in. Vent Valve (to RBEDT).
(20001B/S18)
E16-4
Procedure EMG-3200.01B Support Proc-23 Rev. 13 Attachment P Page 5 of 7 3.17 WHEN a steady stream of water is observed in the sightglass downstream of Valve ND-25A(B)
OR 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).
3.18 IF the Cleanup Filter Precoat Tank has reached the low level
- limit, THEN repeat Steps 3.9.3 through 3.17.
3.19 NOTE During valving operations allow sufficient time for the (Red, Green) valve indication lights to completely change over.
Inject boron in accordance with Steps 3.19.1 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 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 programmer 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.
OVER (20001B/S18)
E16-5
Procedure EMG-3200.01B Support Proc-23 Rev. 13 Attachment P Page 6 of 7 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) 3.21 Repeat Steps 3.9 through 3.20 until the contents of the SLC Storage Tank are injected into the reactor.
NOTE Steps 3.22 through 3.37 are used to mix and inject powdered boron using the Cleanup System and the Precoat Tank.
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-Q068-E,J) and 001-512-2000-1 (Bin 2-Q064-E) respectively.
Although only six (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' elevation.
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 HOLD position.
3.30 Start the Precoat Pump in HAND position.
3.31 Open ND-25A(B), 1 in. Vent Valve (to RBEDT).
(20001B/S18)
E16-6
3.32 WHEN OR THEN 3.33 IF THEN Procedure EMG-3200.01B Support Proc-23 Rev. 13 Attachment P Page 7 of 7 a steady stream of water is observed in the sightglass downstream of valve ND-25A(B),
the Cleanup Filter Precoat Tank low level alarm annunciates,
- 1. Place the Precoat Pump control switch to OFF.
- 2. Close valves ND-25A(B), V-16-107 and ND-30A(B).
the Filter Aid Precoat Tank has reached the low level limit,
- 1. Fill the Filter Aid Precoat Tank with condensate to a level of 80%.
- 2. Repeat Steps 3.27 through 3.32.
he Precoat Tank Agitator and Dust Evacuator.
Stop t 3.34 3.35 NOTE During valving operations, allow sufficient time for the (Red, Green) valve indication lights to completely change over.
Inject 3.35.1 3.25.2 boron in accordance with Steps 3.35.1 through 3.35.4.
Open ND-27A(B), Filter Inlet Valve, by placing its selector switch to the OPEN position.
NOTE 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.
(20001B/S18)
E16-7
Procedure EMG-3200.01B Support Proc-24 Rev. 13 Attachment Q Page 1 of 8 SUPPORT PROCEDURE 24 ALTERNATE BORON INJECTION WITH THE FEED AND CONDENSATE SYSTEM 1.0 PREREQUISITES 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-Q068-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 transfer 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.
(Con Demin Area) 2.4 Confirm open FR & ST Bypass Valve V-2-788. (Regen Room) 2.5 Confirm closed Resin Transfer Piping Cross-Connect Valve V-2-786 and FR & ST Inlet Valve V-2-787.
(Regen Room) 2.6 Check closed pressure breaker valves V-2-S-7 and V-2-S-9, by observing closed (green) indicating lights.
OVER (20001B/S19)
E17-1
Procedure EMG-3200.01B Support Proc-24 Rev. 13 Attachment Q Page 2 of 8 3.0 PROCEDURE When directed by the LOS, perform the following:
3.1 Addition of Borax and Boric Acid into the Cation Tank NOTE 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.a. Backwash Main Menu, select the MANUAL OPERATION function.
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.
3.1.3 WHEN the cation tank is vented and drained, THEN close rinse outlet valve V-2-C-2.
3.1.4 Open rinse inlet valve V-2-C-8 until the tank is approximately 30% full, then close V-2-C-8.
3.1.5 NOTE Equipment for performing this step is located on the EOP Locker on the Heater Bay Roof.
On the heater bay roof, perform the following:
3.1.5.1 Manually open pressure gauge isolation valve V-2-743 and verify that the cation tank is depressurized, then close V-2-743.
3.1.5.2 Confirm closed cation tank resin fill valve V-2-742.
(20001B/S19)
E17-2
Procedure EMG-3200.01B Support Proc-24 Rev. 13 Attachment Q Page 3 of 8 3.1.5.3 Remove the flange above V-2-742.
Insert the funnel and hook up the water hose.
The funnel and hose are located on the east wall of the Turbine Building, directly in-line with the fill valve.
3.1.5.4 Open cation tank resin fill valve V-2-742.
3.1.5.5 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 drums is approximately 45 minutes.
Open Domestic Water Valve V-10-562 and add three drums of Boric Acid and three drums of Borax to the cation tank one scoop at a time.
Alternate scoops of boric acid and borax when filling cation tank.
3.1.5.6 WHEN all six drums have been added OR cation tank is 75% full, THEN close Domestic Water Valve V-10-562 and resin fill valve V-2-742.
3.1.6 IF cation tank level is not approximately 75% full, THEN open rinse inlet valve V-2-C-8 until cation tank level indicates approximately 75% full, then close V-2-C-8.
3.1.7 Open air inlet valve V-2-C-3, and air mix cation tank contents for 5-10 minutes, then close V-2-C-3.
3.1.8 Close vent valve V-2-C-4, and confirm closed vent valve V-2-C-14.
OVER (20001B/S19)
E17-3
Procedure EMG-3200.01B Support Proc-24 Rev. 13 Attachment Q Page 4 of 8 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 performing the following:
3.2.1.1 Verify the following valves are closed:
- Condensate Inlet V-2-D-ll
- 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.
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.
- 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 (20001B/S19)
E17-4
Procedure EMG-3200.01B Support Proc-24 Rev. 13 Attachment Q Page 5 of 8 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.
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 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-2-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.
OVER (20001B/S19)
E17-5
Procedure EMG-3200.01B Support Proc-24 Rev. 13 Attachment Q Page 6 of 8 3.3.1 NOTE A KA10 Key is required for entry into the Condensate Transfer Building.
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.
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 NOTE An MB-1 Key is required to complete Step 3.3.4.
Isolate the reactor feed pump minimum flow lines by unlocking and closing V-2-230 (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. (Turbine Bldg Mezzanine)
(20001B/S19)
E17-6
Procedure EMG-3200.01B Support Proc-24 Rev. 13 Attachment Q Page 7 of 8 3.4 NOTE 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 string outlet valve open.
3.4.2 Confirm demineralizer inlet valve is cracked open.
3.4.3 Vent the demineralizer as follows:
- 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-8 and other demineralizer units recycle valve are closed.
3.4.4 NOTE Minimize venting of Borated Water from the demineralizer.
CAUTION All air must be vented from the demineralizer before placing unit in service.
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.
3.4.6 Open outlet valve V-2-D-12 to put Condensate Demineralizer in service.
OVER B/S19)
E17-7 (20001
Procedure EMG-3200.01B Support Proc-24 Rev. 13 Attachment Q Page 8 of 8 3.5 IF THEN 3.6 IF THEN 3.7 Return additional Boron is required, repeat Steps 3.1 through 3.4 directed by the LOS, return system to normal per Procedure 319.
to the J.O. Backwash Main Menu by pressing the HOME key.
(20001B/S19)
E17-8
BOYSTER CREEK NUCLEAR GENERATING Number STATION PROCEDURE EMG-3200.02 Title Revision No.
PRIMARY CONTAINMENT CONTROL 17 Applicability/Scope Usage Level Responsible Department EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 1
OPERATIONS Effec~eDate Prior Revision 16 incorporated the This Revision 17 incorporates the following Temporary Changes:
following Temporary Changes:
N/A N/A List of Pages (all pages rev'd to Rev. 17) 1.0 to 4.0 El-l E2-1 to E2-3 E3-1 to E3-2 E4-1 to E4-4 E5-1 to E5-2 E6-1 to E6-4 E7-1 to E7-4 E8-1 to E8-3 E9-1 to E9-2 E10-1 to E10-2 E11-2 to E11-2 E12-1 to E12-2 E13-1 to E13-2 E14-1 to E14-6 E15-1 to E15-4 E16-1 to E16-2 E17-1 E18-1 to E18-2 E19-1 to E19-4 E20-1 to E20-2 E21-1 to E21-4 OYSTER CREEK E22-1 to E22-4 CONTROLLED DISTRIBUTION 7t DOCUMENT SERIAL NUMBER_
IRMC Signature Concurring Organization Element Date Originator
/s/
EOP COORDINATOR 3/16/04 Concurred By
/s/
EOP COMMITTEE 3/16/04
/s/
DIRECTOR ENGINEERING 3/20/04
/s/
PLANT OPERATIONS DIRECTOR 3/23/04 Approved By
/s/
PLANT MANAGER 3/24/04 (320002)
- 1. 0
A " rt ',l-l OYSTER CREEK NUCLEAR GENERATING Number Title Revision No.
PRIMARY CONTAINMENT CONTROL 17 Applicability/Scope Usage Level Responsible Department EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK 1
OPERATIONS Effectivfe Date Prior Revision 16 incorporated the following Temporary Changes:
N/A This Revision 17 incorporates the following Temporary Changes:
N/A List of Pages (all pages rev'd to Rev. 17) 1.0 to 4.0 E1-1 E2-1 to E2-3 E3-1 to E3-2 E4-1 to E4-4 E5-1 to E5-2 E6-1 to E6-4 E7-1 to E7-4 E8-1 to E8-3 E9-1 to E9-2 E10-. to E10-2 E11-1 to E11-2 E12-1 to E12-2 E13-1 to E13-2 E14-1 to E14-6 E15-1 to E15-4 E16-1 to E16-2 E17-1 E18-1 to E18-2 E19-1 to E19-4 E20-1 to E20-2 E21-1 to E21-4 E22-1 to E22-4 I
Signature Concurring Organization Element Date Originator EOP COORDINATOR Concurred By EOP COMMITTEE 3 { /0
/
DIRECTOR ENGINEERING
>PLANT OPERATIONS DIRECTOR Approved By 1
?
44 PLANT MANAGER V
&I (320002) 1.0
AmerGen.
OYSTER CREEK NUCLEAR GENERATING Number Abdmampr STATION PROCEDURE EMG-3200.02 Title Revision No.
PRIMARY CONTAINMENT CONTROL 17 1.0 PURPOSE The purpose of the Primary Containment Control Procedure is to:
- Protect equipment in the Primary Containment
- Maintain Primary Containment integrity
2.0 REFERENCES
2.1 Procedures AD-OC-103, EOP-SAM Program Control 310, Containment Spray System Operation 312, Reactor Containment Integrity and Atmosphere Control 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, lb, 2 & 6, Rx Protection System Elem Diagram GE 706E841, Vent & Effluent Rad Monitor Elem Diagram GU 3D-822-17-1002, 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 2.3 2000-GLN-3200.01, OC Plant Specific Technical Guidelines 2.4 2000-STD-1218.04, EOP Writer's Guide (320002)
- 2. 0
AmBer e OYSTER CREEK NUCLEAR GENERATING Number on STATION PROCEDURE EMG-3200.02 Title Revision No.
PRIMARY CONTAINMENT CONTROL 17 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 4.2 Attachment 4.3 Attachment 4.4 Attachment 4.5 Attachment 4.6 Attachment 4.7 Attachment 4.8 Attachment 4.9 Attachment 4.10 Attachment 4.11 Attachment 4.12 Attachment 4.13 Attachment A -
Primary Containment Control EOP Flowchart EMG-3200.02 Rev. 5 B -
Support Procedure 1, Confirmation of Automatic Initiations and Isolations C -
Support Procedure 25, Initiation of the Containment Spray System in the Torus Cooling Mode D -
Support Procedure 26, Determining Bulk Drywell Temperature E -
Support Procedure 27, Maximizing Drywell Cooling F -
Support Procedure 28, Level Instrumentation Availability G -
Support Procedure 29, Initiation of the Containment Spray System for Drywell Sprays H -
Support Procedure 31, Venting Primary Containment to maintain Pressure Below 3.0 psig I -
Support Procedure 32, Venting the Torus for Primary Containment High Pressure J -
Support Procedure 33, Venting the Drywell for Primary Containment High Pressure K -
Support Procedure 34, Venting the Drywell through the Purge System for Primary Containment High Pressure L -
Support Procedure 35, Venting the Torus Through the Hardened Vent I
M -
Support Procedure Hardened Vent 36, Venting the Drywell Through the (320002)
- 3. 0
Amerten.
OYSTER CREEK NUCLEAR GENERATING Number AnEaWCompapy STATION PROCEDURE EMG-3200.02 Title Revision No.
PRIMARY CONTAINMENT CONTROL 17 4.14 Attachment N - Support Procedure 37, Makeup to the Torus via Core 4.15 4.16 4.17 4.18 4.19 4.20 4.21 Attachment Attachment Attachment Attachment Attachment Attachment Attachment 0
P Q
R S
T U
Spray System Support Procedure 38, Determining Primary Containment Water Level Support Procedure 39, Placing the H2/02 Monitoring System In Service Support Procedure 40, Isolation of the Primary Containment Vent and Purge Valves Support Procedure 41, Venting the Torus for Hydrogen Control Support Procedure 42, Purging the Drywell for Hydrogen Control Support Procedure 43, Venting the Drywell for Hydrogen Control (Level Below 461 in.)
Support Procedure 44, Venting the Drywell through the Rx Building Supply Fans for Hydrogen Control (Level Above 461 in.)
Support Procedure 45, Purging the Torus for Hydrogen Control 4.22 Attachment V -
(320002)
- 4. 0
AmerGen.
OYSTER CREEK NUCLEAR GENERATING Number STATION PROCEDURE EMG-3200.02 Title Revision No.
PRIMARY CONTAINMENT CONTROL 17 ATTACHMENT A Attachment A to EMG-3200.02, Primary Containment Control, is the Primary Containment Control EOP Flowchart, EMG-3200.02 Rev. 5.
(320002/3)
El-1
Procedure EMG-3200.02 Support Proc. 1 Rev. 17 Attachment B Page I of 3 SUPPORT PROCEDURE 1 CONFIRMATION OF AUTOMATIC INITIATIONS AND ISOLATIONS 1.0 PREREQUISITES 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 IF Any of the following conditions exist:
Isolation
- RPV water level at or below 86 in. and not bypassed
- Steam tunnel temperature at or above 1800 F
- Any steam line flow at or above 4.0x10 6 ibm/hr
- Reactor mode switch in RUN and RPV pressure at or below 850 psig
- Main steam line radiation at or above 800 units AND no ATWS condition exists THEN Confirm closed the following:
__NSO3A
__V-14-1,-19 V-24-30 (llF)
__NS04A V-14-5,-20 V-24-29 (11F)
__NS03B DW AIR SUPPLY NS04B V-6-395 (llF)
Scram IF A Reactor Scram is initiated Discharge AND Volume Isolation SDV HI-HI LVL SCRAM switch is not in BYPASS, THEN Confirm closed the following:
NORTH SDV Vents & Drains SOUTH SDV Vents & Drains OVER E2-1 (320002/4)
Procedure EMG-3200.02 Support Proc. 1 Rev. 17 Attachment B-Page 2 of 3 SYSTEM OPERATING DETAILS IC-A IF 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 IF 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 Cleanup IF Any of the following conditions exist:
System RPV water level at or below 86 in. and not bypassed
- Drywell pressure at or above 3.0 psig
V-16-1
__V-16-14
__V-16-2 V-16-61 Shutdown IF Any of the following conditions exist:
Cooling RPV water level at or below 86 in.
Isolation Drywell pressure at or above 3.0 psig THEN Confirm closed the following SDC Isolation Valves:
V-17-54 V-17-19 Isolation IF RPV water level is at or below 86 in.,
Condenser Initiation THEN confirm initiation of both Isolation Condensers.
Core Spray IF Any of the following conditions exist:
System RPV water level at or below 86 in. and not bypassed.
Start
- Drywell pressure at or above 3.0 psig and not bypassed.
THEN Confirm start of one Main Pump and one Booster Pump in each Core Spray System if not bypassed.
(320002/4)
E2-2
Procedure EMG-3200.02 Support Proc. I Rev. 17 Attachment B Page 3 of 3 SYSTEM OPERATING DETAILS Primary Containment Isolation IF Any of the following conditions exist:
- RPV water level at or below 86 in. and not bypassed.
- Drywell pressure at or above 3.0 psig and not bypassed.
THEN Confirm closed the following valves that are not required to be open by the Emergency Operating Procedures:
System DW Vent/Purge Torus Vent Torus 2" Vent Bypass DWEDT DW Floor Sump Torus/Rx Bldg.
Vacuum Breakers TIP Valves DW 2" Vent Bypass N2 Purge Valve No.
V-27-1 V-27-2 V-27-3 V-27-4 V-28-17 V-28-18 V-28-47 V-22-1 V-22-2 V-22-28 V-22-29 V-26-16 V-26-18 Common Ind.
V-23-21 V-23-22 V-23-13 V-23-14 V-23-15 V-23-16 (Panel llF) of of (Panel llF)
(Panel llF)
(Panel llF)
(Panel 11F)
(Panel llF)
(Panel 11F)
(Panel 12XR)
(
(Panel 12XR)
N2 Makeup V-23-17 V-23-18 V-23-19 V-23-20 (Panel 12XR)
J.
(320002/4)
E2 -3 (320002/4)
E2-3
Procedure EMG-3200.02 Support Proc. 25 Rev. 17 Attachment C Page 1 of 2 SUPPORT PROCEDURE 25 INITIATION OF THE CONTAINMENT SPRAY SYSTEM IN THE TORUS COOLING MODE 1.0 PREREQUISITES 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 CAUTION Containment Spray suction strainer plugging may occur due to debris in the Primary Containment and result in a loss of Containment Spray System Flow.
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 2150 KW.
IF 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 Containment Spray and ESW Pumps.
3 I CAUTION NPSH problems will develop on all operating pumps if more than 4 Containment Spray/Core Spray Main pumps are operated at the same time.
IF 4 Containment Spray/Core Spray Main pumps are in operation, THEN do not start additional Containment Spray pumps until Core Spray Main pumps can be secured.
OVER (320002/5)
E3-1
Procedure EMG-3200.02 Support Proc. 25 Rev. 17 Attachment C Page 2 of 2 3.3 Start a Containment Spray Pump as follows:
3.3.1 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 (Panel 1F/2F).
3.3.2 Select a Containment Spray Pump to be started.
3.3.3 Place and hold the System Pump Start Permissive Keylock for the selected pump in the appropriate position (Panel 1F/2F).
3.3.4 Start the selected Containment Spray Pump using its control switch (Panel 1F/2F).
3.4 Start an associated ESW Pump using its control switch (Panel 1F/2F).
3.5 CAUTION Operation of Containment Spray pumps with flow above the NPSH or vortex limits may result in equipment damage.
When operating beyond any flow limits, periodic evaluations should be made to verify that continued operation beyond these limits is still required.
Monitor system parameters for expected performance.
3.6 Start additional Containment Spray and ESW Pumps as directed by the LOS in accordance with Steps 3.1 thru 3.5.
3.7 IF all Containment Spray pumps that are running are not required for Torus cooling, THEN inform the LOS and secure the Containment Spray pumps that are not required for Torus cooling.
(320002/5)
E3-2
Procedure EMG-3200.02 Support Proc. 26 Rev. 17 Attachment D Page I of 4 SUPPORT PROCEDURE 26 DETERMINING BULK DRYWELL TEMPERATURE 1.0 PREREQUISITES Determination of Bulk Drywell Temperature has been directed by the Emergency Operating Procedures.
2.0 PREPARATIONS None 3.0 PROCEDURE 3.1 Determine Bulk Drywell Temperature using computer point DWTEMP.
IF 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 8R)
- Recorder TR-100A (RB 51' Elev.)
3.2 IF an operator is not immediately available to monitor Drywell temperature at 51' elev.
OR Temperature Recorder TR-1OOA is not available, THEN determine bulk drywell temperature by averaging the inlet temperatures of the operating Drywell Recirc. Fans.
(Points 11, 12, 13, 14, and 15 from recorder IA55 on Panel 8R).
3.2.1 IF less than three Drywell Recirc Fans are running, THEN 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 8R).
OVER (320002/6)
E4-1
3.3 IF THEN 3.3.1 3.3.2 Procedure EMG-3200.02 Support Proc. 26 Rev. 17 Attachment D Page 2 of 4 temperature recorder TR-100A can be used, determine bulk drywell temperature as follows:
Complete calculation on Attachment SP-26-1.
Calculate Bulk Drywell Temperature (TB) using values from Attachment SP-26-1.
TB = 0.503
+ 0.382
+
(T Avg IA)
(T Avg II)
(T Avg IB) 0.076
+ 0.039 (T Avg III)
TB =
- 1. IF 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)
NOTE Thermocouple readings > 3950 F must be read using Plant Computer Points or by an instrument technician using instrumentation for Type T thermocouples.
- 2. IF THEN
- 3. IF THEN
- 4. IF THEN any T/C 105 indicates >395 0F, check T/C 107 reading for confirmation of high temperature conditions.
two out of three T/C 105's indicate 315 0F < T > 3250F, evaluate drywell cooling using Procedure OPS-3024.09, Drywell Cooling System -
Diagnostic and Restoration Actions.
two out of three T/C 105's indicate T > 325 0F, initiate a plant shutdown in accordance with Procedure 203.1, Plant Shutdown to Hot Standby.
(320002/6)
E4-2
Procedure EMG-3200.02 Support Proc. 26 Rev. 17 Attachment D Page.
of 4 I
ATTACHMENT SP-26-1 l Temperature readings from the following thermocouples can be obtained locally from the recorder or from the plant computer by identified ID points.
NOTE Thermocouple readings >3950 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 (OF)
PT.35
'1__
PT.36 PT.37 PT.38 PT.39 TE-lOQA,El.
TE-lOOB,El.
TE-lOOC,El.
TE-lOOD,El.
TE-lOE,El.
33' 33' 33' 33' 33' Recirc Recirc Recirc Recirc Recirc Pump Pump Pump Pump Pump Motor Motor Motor Motor Motor Inlet Inlet Inlet Inlet Inlet Air Air Air Air Air "A"l "Br' "D"'
"IE"
'TEIOOA'
'TE1OOB'
'TE1OOC'
'TE1OOD'
'TE1OOE'
- 3. Calculate T Avg IB by completing the following:
- From Recorder TR-100A (RB 51' Elev.) or the Plant Computer, record the following data:
Recorder Point PT.1
= TE-103A,El. 50' Safety Valve Area PT.2
= TE-103B,El. 50' Safety Valve Area PT.3 = TE-103C,El. 50' Safety Valve Area PT.4
= TE-103D,El. 50' Safety Valve Area PT.5 = TE-103E,El. 50' Safety Valve Area
OVER COMP ID PT
'TE103A'
'TE103B'
'TE103C'
'TE103D'
'TE103E' Value (°F)
(320002/6)
E4-3
Procedure EMG-3200.02 Support Proc. 26 Rev. 17 Attachment D Page 4 of 4
- 4. Calculate T Avg II by completing the following:
- From Recorder TR-100A (RB 51' Elev.) or the Plant Computer, record the following data:
Recorder Point PT.,
PT.'
PT.
PT. ]
PT.
6 = TE-104A,El. 93' R 7 = TE-104B,El. 93' R 8 = TE-104C,El. 93' R 9 = TE-104D,El. 93' R LO = TE-104E,El. 93' R
- Calculate T Avg II x
x x
x x
Vessel Vessel Vessel Vessel Vessel Bellows Bellows Bellows Bellows Bellows Seal Seal Seal Seal Seal Area Area Area Area Area COMP ID PT
'TE104A'
'TE104B'
'TE104C'
'TE104D'
'TE104E' Value (OF)
T Avg II = PT.6 + PT.7 + PT.8 + PT.9 + PT.10 5
OF
- 5. Calculate T Avg III by completing the following:
- From Recorder TR-10OA (RB 51' Elev.) or the Plant Computer, record the following data:
Recorder Point PT.11 PT. 12 PT.13
= TE-105A,El. 95' Rx
= TE-105B,El. 95' Rx
= TE-105C,El. 95' Rx Head Flange Area Head Flange Area Head Flange Area COMP ID PT
'TE105A'
'TE105B'
'TE105C' Value (OF)
(320002/6)
E4-4
Procedure EMG-3200.02 Support Proc. 27 Rev. 17 Attachment E Page I of 2 SUPPORT PROCEDURE 27 MAXIMIZING DRYWELL COOLING 1.0 PREREQUISITES The operation of all available drywell coolers has been directed by the Emergency Operating Procedures AND the RBCCW System is NOT isolated due to a LOCA or MSLB in the Drywell.
2.0 PREPARATION 2.1 CAUTION Reinitiating RBCCW flow to the Drywell following a LOCA or MSLB in the Drywell may cause a water hammer to occur and subsequent piping failure.
Verify that the RBCCW System is not isolated due to high Drywell pressure/low RPV water level conditions.
2.2 IF the RBCCW System is isolated due to high Drywell pressure/low RPV water level, THEN inform the LOS and do not attempt to reinitiate the RBCCW System flow to the Drywell.
2.3 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.
2.3.1 Remove the bypass plug from position BPI.
2.3.2 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 OVER (320002/7)
E5-1
Procedure EMG-3200.02 Support Proc. 27 Rev. 17 Attachment E Page 2 of 2 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 llF).
3.4 CAUTION l
A rapid decrease in Drywell temperature could cause a corresponding drop in Drywell Pressure and possible deinertion.
II Operate DW RECIRC FANS (Panel lR) as required to control Drywell temperature.
(320002/7)
Procedure EMG-3200.02 Support Proc. 28 Rev. 17 Attachment F Page I of 4 SUPPORT PROCEDURE 28 LEVEL INSTRUMENTATION AVAILABILITY 1.0 PREREQUISITES The evaluation of RPV Water Level Instruments has been directed by the Emergency Operating Procedures.
2.0 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 Record the temperatures of the following instrument reference leg vertical runs as read on recorder TR-IA55 on Panel 8R or the Plant Process Computer.
Level Instrument Temp Instrument No.
Recorder Point Temperature NR GEMAC A (LT-lD13A)
TE-130-450 40 NR GEMAC B (LT-lDl3B)
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 OVER (320002/8)
E6-1
Procedure EMG-3200.02 Support Proc. 28 Rev. 17 Attachment F Page 2 of 4 3.2 NOTE If reference leg temperatures are in the UNSAFE REGION of the curve, that instrument may not be used until an engineering evaluation of reference leg conditions has been performed.
Verify that the instrument reference leg temperatures are in the SAFE REGION of the RPV Saturation Temperature Curve.
RPV Saetrafion Temperature 600-z 550-l1l 5400-zw w 450 w400 Safe Regio z 350 2
300 x
250-____
200 0
200 400 600 800 1000 RPV PRESSURE (psig)
(320002/8)
EG-2
Procedure EMG-3200.02 Support Proc. 28 Rev. 17 Attachment F Page 3 of 4 3.3 NOTE Instruments may be used only when in the Safe Region of the curve.
If the instrument goes in the Unsafe Region of the curve, it may not be used again until it returns to the Safe Region, at which time it is valid for level indication response.
For each instrument below, the instrument reads in the Safe Region of its respective curve.
GEMAC NARROW RANGE 90- 180im 106 104 -
102 -
C)_100
- L 1
-Safe Region u<
98 E
96-E 94_
E 92~
200 300 400 Reference Leg Temperature (F) 500 OVER (320002/8)
E6-3
Procedure EMG-3200.02 Support Proc. 28 Rev. 17 Attachment F Page 4 of 4 Yarway 85-185 in.
105 CD 10 Safe Region
-J 10 CD 95 EU X
C %= 90 200 300 40050 Reference Leg Temperature (F) 500 GEMAC Wide Range 210 -
-190
, 170.X l _170 -
Safe Region
'LL15
- o i-130 -
~ ~11o.
E 90-70 MAN 50-50 150 250 350 450 550 Reference Leg Temperature (F).
(320002/8)
E6-4
Procedure EMG-3200.02 Support Proc. 29 Rev. 17 Attachment G Page 1 of 4 SUPPORT PROCEDURE 29 INITIATION OF THE CONTAINMENT SPRAY SYSTEM FOR 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 CAUTION Containment Spray suction strainer plugging may occur due to debris in the Primary Containment and result in a loss of Containment Spray System Flow.
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.
IF 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 Containment Spray and ESW pumps.
OVER (320002/9)
E7-1
Procedure EMG-3200.02 Support Proc. 29 Rev. 17 Attachment.G Page 2 of 4 3.2 WHEN directed to initiate Drywell sprays, THEN complete the following:
- 1. Confirm all Reactor Recirculation Pumps tripped.
- 2. Confirm the Drywell Recirc Fans tripped (Panel llR).
3.3 CAUTION NPSH problems will develop on all operating pumps if more than 4 Containment Spray/Core Spray Main pumps are operated at the same time.
IF 4 Containment Spray/Core Spray Main pumps are in operation, THEN do not start additional Containment Spray pumps until Core Spray Main pumps can be secured.
3.4 Start a Containment Spray Pump as follows:
3.4.1 Select a Containment Spray Pump to be started.
3.4.2 Place and hold the System Pump Start Permissive Keylock for the selected pump in the appropriate position (Panel IF/2F).
3.4.3 Start the selected Containment Spray Pump using its control switch (Panel IF/2F).
3.5 Start an associated ESW Pump using its control switch (Panel IF/2F).
3.6 CAUTION Operation of Containment Spray pumps with flow above the NPSH or vortex limits may result in equipment damage.
When operating beyond any flow limits, periodic evaluations should be made to verify that continued operation beyond these limits is still required.
Monitor System parameters for expected performance.
(320002/9)
E7-2
Procedure EMG-3200.02 Support Proc. 29 Rev. 17 Attachment G Page 3 of 4 3.7 NOTE Valves V-5-147, 166 and 167 do not seal in when the control switch is taken to CLOSE.
The control switch must be held in CLOSE until the valve indicates closed.
Confirm the following RBCCW Isolation valves closed (Panel 1F/2F):
- V-5-147
- V-5-148
- V-5-166
- V-5-167 3.8 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 3.6 as directed by the LOS.
3.9 IF while performing the following steps, Containment Spray Pumps fail to trip, THEN place the respective system MODE SELECT switch in TORUS CLG position.
3.10 Maintain primary containment pressure in a band of 4 to 12 psig unless otherwise directed by the LOS as follows:
3.10.1 Secure Drywell Sprays when Drywell pressure drops to 4 psig.
3.10.2 WHEN Torus or Drywell pressure increases to 12 psig, THEN initiate Drywell Sprays in accordance with Steps 3.3 through 3.6.
3.11 IF any Core Spray Booster pump is running AND Torus OR Drywell pressure drops to 2 psig, THEN confirm termination of Drywell Sprays due to NPSH concerns.
OVER (320002/9)
E7-3
Procedure EMG-3200.02 Support Proc. 29 Rev. 17 Attachment.G Page 4 of 4 3.12 IF no Core Spray Booster pump is running AND Torus OR Drywell pressure drops below 1 psig, THEN confirm termination of Drywell Sprays to prevent deinertion of the Primary Containment.
. (320002/9)
E7-4
Procedure EMG-3200.02 Support Proc. 31 Rev. 17 Attachment H Page I of 3 SUPPORT PROCEDURE 31 VENTING THE PRIMARY CONTAINMENT TO MAINTAIN PRESSURE BELOW 3.0 PSIG 1.0 PREREQUISITES Venting of the Primary Containment has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 Determine method to be used to vent the Primary Containment.
- Vent via SGTS -
continue at Step 3.2
- Vent via Normal Building Ventilation -continue at Step 3.3.
3.2 IF the LOS directs venting the Primary Containment via SGTS, 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 for the train selected in the HAND position.
- 3. Close the SGTS CROSSTIE V-28-48 (Panel liR)
- 4.
Secure operating Reactor Building Supply Fans by placing the respective control switches in OFF position (Panel 1iR).
- 5.
Immediately secure Exhaust Fan EF 1-5 (or EF 1-6) by placing control switch in STOP position (Panel liR).
- 6.
Close V-28-21 and V-28-22 by placing the EXH VALVES TO MAIN EXHAUST control switch in CLOSE position (Panel llR).
OVER (320002/10)
E8-1
Procedure EMG-3200.02 Support Proc. 31 Rev. 17
-Attachment H Page 2 of 3
- 7. Close V-28-42 and V-28-43 by placing the MAIN SUPPLY HEADER VALVES TO DW control switch in CLOSE position (Panel liR).
- 8. Open Torus Vent valve V-28-18 (Panel 11F).
- 9. Cycle V-28-47 to maintain Drywell pressure below 3.0 psig (Panel 11F).
- 10.
IF the Torus cannot be vented, THEN perform the following:
- a. Inform the LOS.
- b.
Open the Drywell Vent valves V-23-21 and V-23-22 (Panel 12XR).
- c. Cycle Drywell Vent valve V-23-21 or V-23-22 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 preferred system in operation, and V 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.
(320002/10)
E8-2
Procedure EMG-3200.02 Support Proc. 31 Rev. 17 Attachment H Page 3 of 3 3.3 IF the LOS directs venting the Primary Containment via Rx. Bldg. ventilation, THEN perform the following:
- 1. Open Torus Vent valve V-28-18 (Panel llF).
- 2. Cycle Torus Vent valve V-28-47 (Panel llF) to maintain Drywell pressure below 3.0 psig.
- 3. IF the Torus cannot be vented, THEN perform the following:
- a.
Inform the LOS.
- b. Open the Drywell Vent valves V-23-21 and V-23-22 (Panel 12XR).
- c. Cycle Drywell Vent valve V-23-21 or V 22 to maintain Drywell pressure below 3.0 psig.
(320002/10)
Procedure EMG-3200.02 Support Proc. 32 Rev. 17 Attachment I Page I of 2 SUPPORT PROCEDURE 32 VENTING THE TORUS FOR PRIMARY CONTAINMENT HIGH PRESSURE 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. (Panel 1F/2F) 2.2 Evacuate personnel from the Reactor Building.
2.2.1 Sound the Reactor Building Evacuation Alarm Time 2.2.2 Make the announcement "PRIMARY CONTAINMENT VENTING WILL COMMENCE IN APPROXIMATELY 5 MINUTES.
ALL PERSONNEL EVACUATE THE REACTOR BUILDING IMMEDIATELY.
STAND CLEAR OF THE STACK AND THE RX. BLDG. FAN PAD."
2.3 Select a SGTS Train for operation and place its fan control switch in HAND (Panel liR).
2.4 Place the control switch for V-28-48, SGTS CROSSTIE, in CLOSED (Panel liR).
2.5 Confirm Reactor Building Supply Fans secured (Panel liR).
2.6 Confirm Reactor Building Exhaust Fan secured (Panel 11R).
2.7 Confirm that the Reactor Mode Selector Switch is NOT in the RUN position.
2.8 Obtain one (1) 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) g Torus Nitrogen Makeup Valves (V-23-19 and V-23-20)
Open the EOP BYPASS PLUGS panel in the rear of Panel 1OXF.
2.9.1 Insert a bypass plug in position BP5.
OVER (320002/11)
E9-1
Procedure EMG-3200.02 Support Proc. 32 Rev. 17 Attachment I Page 2 of 2 2.10 Open the EOP BYPASS PLUGS panel in the rear of Panel llR.
2.10.1 Remove the bypass plug in position BP4.
2.10.2 Insert a bypass plug in position BP1.
2.11 Place the TORUS/DRYWELL ISOLATION VALVE BYPASS PERMISSIVE keylock switch in the TORUS position (Panel IIF).
2.12 Place the TORUS/DW VENT AND PURGE ISOL VLVS HI RAD BYP keylock switches for both Channels 1 & 2 in the BYPASS position (Panel IIF).
2.13 Inform LOS that the Torus is ready to be vented via the Torus Vent valves.
3.0 PROCEDURE When directed by the LOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 1lR).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves V-28-21 and V-28-22 (Panel 1lR).
3.3 WHEN at least five minutes has passed since sounding the Reactor Building evacuation alarm, THEN perform the following:
- 1. Inform the LOS.
- 2. Start Reactor Building Exhaust Fan 1-5 (Panel 1iR).
3.4 Open Torus Vent valves V-28-18 and V-28-47 (Panel 11F).
3.5 Inform the LOS that Torus venting via V-28-18 and V-28-47 has commenced.
3.6 Control Torus pressure as directed by the LOS by cycling the Torus vent valves as required.
3.7 CAUTION Ventilation ductwork failure WILL occur when venting through V-28-17 with torus pressure greater than 2 psig.
WHEN directed by the LOS, THEN open Torus Vent valve V-28-17 (Panel llF).
3.8 Control Torus pressure as directed by the LOS by cycling Torus Vent valves as required.
(320002/11)
E9-2
Procedure EMG-3200.02 Support Proc. 33 Rev. 17 AttachmentJ Page I of 2 SUPPORT PROCEDURE 33 VENTING THE DRYWELL FOR PRIMARY CONTAINMENT HIGH PRESSURE 1.0 PREREQUISITES 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 2.2.2 Make the announcement "PRIMARY CONTAINMENT VENTING WILL COMMENCE IN APPROXIMATELY FIVE MINUTES. ALL PERSONNEL EVACUATE THE REACTOR BUILDING IMMEDIATELY.
STAND CLEAR OF THE STACK AND THE RX. BLDG. FAN PAD."
2.3 Select a SGTS Train for operation and place its fan control switch in HAND (Panel liR).
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 1lR).
2.7 Confirm that the Reactor Mode Selector is NOT in RUN.
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 BP1.
OVER (320002/12)
E10-1
Procedure EMG-3200.02 Support Proc. 33 Rev. 17 Attachment J Page 2 of 2 2.9 Place the TORUS/DRYWELL ISOLATION VALVE BYPASS PERMISSIVE keylock switch in the DRYWELL position (Panel 11F).
2.10 Inform the LOS that the Drywell is ready to be vented via the Drywell 2 inch Vent valves.
3.0 PROCEDURE When directed by the LOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 1lR).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves, V-28-21 and V-28-22 (Panel llR).
3.3 WHEN at least five minutes has passed since sounding the Reactor Building evacuation alarm, THEN perform the following:
- 1.
Inform the LOS.
- 2.
Start Reactor Building Exhaust Fan 1-5.
3.4 Open Drywell Vent valves V-23-21 and V-23-22 (Panel 12XR).
3.5 Control Drywell pressure as directed by the LOS by cycling V-23-21 or V-23-22.
(320002/12)
E10-2
Procedure EMG-3200.02 Support Proc. 34 Rev. 17 Attachment K Page I of 2 SUPPORT PROCEDURE 34 VENTING THE DRYWELL VIA THE PURGE SYSTEM FOR PRIMARY CONTAINMENT HIGH PRESSURE 1.0 PREREQUISITES 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 2.1.2 Make the announcement "PRIMARY CONTAINMENT VENTING WILL COMMENCE IN APPROXIMATELY FIVE MINUTES. ALL PERSONNEL EVACUATE THE REACTOR BUILDING IMMEDIATELY.
STAND CLEAR OF THE STACK AND THE RX. BLDG. FAN PAD."
2.2 Select a SGTS Train for operation and place its fan in HAND (Pnl llR) 2.3 Place Control switch for V-28-48, SGTS CROSSTIE, to the CLOSED position (Panel liR).
2.4 Confirm Reactor Building Supply Fans are secured (Panel liR).
2.5 Confirm Reactor Building Exhaust Fan secured (Panel 1lR).
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 BP1.
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).
Place the CNTMT VENT AND PURGE ISOLATION BYPASS Keylock in BYPASS (Panel 12XR).
OVER (320002/13)
Ell-1
Procedure EMG-3200.02 Support Proc. 34 Rev. 17 Attachment K Page 2 of 2 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 liF).
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 LOS that the Drywell is ready to be vented via the Drywell Purge valves.
3.0 PROCEDURE When directed by the LOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel lR).
3.2 Confirm open Reactor Building Main Exhaust Isolation Valves V-28-21 and V-28-22 (Panel lR).
3.3 WHEN at least five minutes has passed since sounding the Reactor Building evacuation alarm, THEN perform the following:
- 1. Inform the LOS.
- 2. 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 liR).
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 llF).
3.6 Control Drywell pressure as directed by the LOS, by cycling V-27-3 as required.
(320002/13)
E11-2
Procedure EMG-3200.02 Support Proc. 35 Rev. 17 Attachment L Page I of 2 SUPPORT PROCEDURE 35 VENTING THE TORUS VIA THE HARDENED VENT 1.0 PREREQUISITES 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 minimum detectable (1.5% on H2 /02 Monitor).
2.4 Verify CNTMT HI RANGE RAD MONITOR Channels 1 and 2 are reading below 2 x 104 R/HR (Panel 2R).
2.5 Confirm at least one Reactor Bldg. or Turbine Bldg. exhaust fan; 1-5, 1-6, or 1-7 (Panel lR) 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) 2.9 Inform the LOS that the Torus is ready to be vented via the Hardened Vent.
OVER (320002/14)
E12-1
Procedure EMG-3200.02 Support Proc. 35 Rev. 17 Attachment L Page 2 of 2 3.0 PROCEDURE When directed by the LOS, complete the following:
3.1 Make the following announcement:
"PRIMARY CONTAINMENT VENTING VIA THE HARDENED VENT WILL COMMENCE IN APPROXIMATELY FIVE MINUTES.
ALL PERSONNEL EVACUATE THE REACTOR BUILDING.
STAND CLEAR OF THE 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 LOS that Torus venting has begun.
3.5 Control Torus pressure as directed by the LOS by cycling V-23-16 (Panel 12XR).
(320002/14)
E12-2
Procedure EMG-3200.02 Support Proc. 36 Rev. 17 Attachment M Page I of 2 SUPPORT PROCEDURE 36 VENTING THE DRYWELL VIA THE HARDENED VENT 1.0 PREREQUISITES 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 MB-1 key.
2.2 Verify Primary Containment H2 concentration is below the minimum detectable (1.5% on the H2/02 Monitor) 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 Reactor Bldg. or Turbine Bldg. exhaust fan; 1-5, 1-6, or 1-7 (Panel llR) 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 LOS that the Drywell is ready to be vented via the Hardened Vent.
OVER (320002/15)
E13-1
Procedure EMG-3200.02 Support Proc. 36 Rev. 17 Attachment M Page 2 of 2 3.0 PROCEDURE When directed by the LOS, complete the following:
3.1 Make the following announcement:
"PRIMARY CONTAINMENT VENTING VIA THE HARDENED VENT WILL COMMENCE IN APPROXIMATELY FIVE MINUTES.
ALL PERSONNEL EVACUATE THE REACTOR BUILDING.
STAND CLEAR OF THE 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 Drywell nitrogen purge inlet valves V-23-13 and V-23-14 (Panel 12XR).
3.4 Inform the LOS that Drywell venting has begun.
3.5 Control Drywell pressure as directed by the LOS by cycling V-23-14.
(320002/15)
E13-2
Procedure EMG-3200.02 Support Proc. 37 Rev. 17 Attachment N Page I of 6 SUPPORT PROCEDURE 37 MAKEUP TO THE TORUS VIA CORE SPRAY SYSTEM 1.0 PREREQUISITES 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.
2.0 PREPARATION 2.1 Verify the Reactor Building is accessible.
2.2 An MB-1 key is required if lining up the CST as source of Torus water makeup.
2.3 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 (Panel IF/2F).
3.0 PROCEDURE 3.1 Determine which Core Spray System is to be used to makeup to the Torus.
- System 1 -
Continue at Step 3.2.
- System 2 -
Continue at Step 3.3.
3.2 Makeup to the Torus via Core Spray System 1 3.2.1 NOTE Overriding Core Spray initiation logic may be required.
Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 1 (Panel lF/2F).
3.2.2 Close Core Spray System 1 Suction valves V-20-3 and V-20-32 (Panel IF/2F).
OVER (320002/16)
E14-1
Procedure EMG-3200.02 Support Proc. 37 Rev. 17 Attachment N Page 2 of 6 3.2.3 Confirm closed Core Spray System 1 Parallel Isolation valves V-20-15 and V-20-40 (Panel 1F/2F).
3.2.4 IF the NW Corner Room is accessible, AND the CST is the source of Torus water makeup, THEN perform the following:
- 1. Place the breakers for Core Spray Pump Suction Valves V-20-3 and V-20-32 in the OFF position.
- V-20-32 Bkr. (MCC lB21A/RB 23 NE)
- 2. Unlock and open the following CST supply valves:
- V-20-l (NW Corner Room)
- V-20-5 (NW Corner Room)
- V-20-34 (NW Corner Room)
- 3. Start Core Spray System 1 Main Pump NZO1A or NZOlC.
3.2.5 IF the NW Corner Room is NOT 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).
3.2.6 Unlock and place the breaker for Torus Test Flow Return Valve V-20-27 in the ON position (MCC lA21B/RB 23 E).
(320002/16)
E14-2
Procedure EMG-3200.02 Support Proc. 37 Rev. 17 Attachment N Page 3 of 6 3.2.7 Open Test Flow Return valve V-20-27 (Keylock RB 51'NW).
3.2.8 WHEN Torus level is greater than 143 in. but less than 154 in.,
THEN perform the following:
- 1. IF the CST was the source of Torus water
- makeup, 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. IF fire water was the source of Torus water
- makeup, 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).
- d. Open Tell-Tale Drain Valve V-20-91 (North Side RB).
3.2.9 When filling is no longer required:
- 1.
IF the CST was the source of Torus water makeup, 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 lF/2F)
OVER (320002/16)
E14 -3
Procedure EMG-3200.02 Support Proc. 37 Rev. 17 Attachment N Page 4 of 6
- 3. Place and lock the breaker for V-20-27 in the OFF position (MCC lA21B/RB 23 E)
- 4. Confirm the breakers for Core Spray Pump Suction Valves V-20-3 and V-20-32 in the ON position.
V-20-3 Bkr (MCC 1A21A/RB 23 SW)
V-20-32 Bkr (MCC lB21A/RB 23 NE)
- 5. Open Core Spray Pump Suction Valves V-20-3 and V-20-32 (Panel lF/2F).
- 6. IF Fire water was the source of torus water makeup, 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.
to the Torus via Core Sorav Svstem 2 3.3 Make up NOTE 3.3.1 Overriding Core Spray initiation logic may be required.
Confirm stopped the Core Spray Main and Booster Pumps in Core Spray System 2 (Panel IF/2F).
3.3.2 Close Core Spray System 2 Suction valves V-20-4 and V-20-33 (Panel 1F/2F).
3.3.3 Confirm closed Parallel Isolation valves V-20-21 and V-20-41 (Panel 1F/2F).
3.3.4 IF the NW and SW Corner Rooms are accessible AND 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 lB21A/RB 23 NE)
(320002/16)
E14-4
3.3.5 IF THEN Procedure EMG-3200.02 Support Proc. 37 Rev. 17 Attachment N Page 5 of 6
- 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 NZOIB or NZO1D.
the NW or SW Corner Room is NOT accessible perform the following to use firewater as the source of Torus water makeup:
- 1. Close Tell-Tale Drain Valve V-20-90 (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).
3.3.6 Unlock and place the breaker for Torus Test Flow Return Valve V-20-26 in the ON position (MCC lB21A/RB 23 NE).
3.3.7 Open Test Flow Return valve V-20-26 (Keylock RB 75 SW).
3.3.8 WHEN Torus level is greater than 143 in. but less than 154 in.,
THEN perform the following:
- 1. IF the CST was the source of Torus water makeup, THEN perform the following:
- b. Secure the Core Spray System 2 Main Pumps started in Step 3.2.4.3
- 2. IF fire water was the source of Torus water makeup, THEN perform the following:
OVER (320002/16)
E14-5
Procedure EMG-3200.02 Support Proc. 37 Rev. 17 Attachment N Page 6 of 6
- b. Close Fire Protection Supply Valve V-20-82 (South Side RB).
- c. Secure the Diesel Fire Pumps by taking their control switches in AUTO position (Panel 13R).
- d. Open Tell-Tale Drain Valve V-20-90 (South Side RB).
3.3.9 When filling is no longer required:
- 1. IF 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 closed Torus Test Flow Return Valve V-20-26 (Panel 1F/2F).
- 3. Place and lock the breaker for V-20-26 in the OFF position (MCC lB21A/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 lB2lA/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. IF Fire water was the source of torus water makeup, THEN return Core Spray System 2 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.
(320002/16)
E14-6
Procedure EMG-3200.02 Support Proc. 38 Rev. 17 Attachment O Page I of 4 SUPPORT PROCEDURE 38 DETERMINING PRIMARY CONTAINMENT WATER LEVEL 1.0 PREREQUISITES 1.1 Determination of Primary Containment Water Level has been directed by the Emergency Operating Procedures.
2.0 PREPARATION None 3.0 PROCEDURE 3.1 IF Primary Containment Water Level is greater than the range of the wide range Torus level recorder (0-360 inches) on Panel 16R.
THEN 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 1F/2F P(Torus) =
psig 3.1.2 Record Drywell pressure from PI-IP08 on Panel 1F/2F P(DW) =
psig 3.1.3 Calculate AP AP = P(Torus) -
P(DW) =
psid 3.1.4 IF AP is greater than 16 psid, THEN continue at Step 3.2 of this procedure 3.1.5 IF AP is less than 16 psid, THEN determine Primary Containment Water Level using Figure SP-38-1.
OVER (320002/17)
E15-1
Procedure EMG-3200.02 Support Proc. 38 Rev. 17 Page 2 of 4 3.2 IF 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 IF/2F P(Torus) =
3.2.2 Record Drywell pressure from Pen 3 of Recorder 12XR-6 (Panel 12XR)
P(DW) psig 3.2.3 Calculate AP AP = P(Torus) -
P(DW)=
psid 3.2.4 Determine Primary Containment Water Level using Figure SP-38-2.
?sig (320002/17)
E15-2
Procedure EMG-3200.02 Support Proc. 38 Rev. 17
.- Attachment 0 Page 3 of 4 Figure SP-38-1 Containment Water Level Determination Using DW Pressure Indication From Panel lF/2F 800 775 750 725 700 675 650 625 C
Z 600 (n w M 2j 575
° 0r
'-- 550 525 500 475 450 425 400 375 350 I I I/d 7
I/
/
7
/
I I I II I I I 1 1 II l
I A I1 T 1IL (4.7 psid, 461 Indies)
I I
r (.3 sid 36 iches) 0 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 P(Torus)-P(DW) (psid)
OVER (320002/17)
E15-3
Procedure EMG-3200.02 Support Proc. 38 Rev. 17 Page 4 of 4 Figure SP-38-2 Water Level Determination Usina DW Containment Pressure Indication From Pen 3 of Recorder 12XR-6 (Panel 12XR) r-Z-
-1 V) w M
0: _j 0- 0:wI--
9 1300 1275 1250 1225 1200 1175 1150 1125 1100 1075 1050 1025 1000 975 950 925 900 875 850 825 800 775 750 (31.9 psid, 1212 Inches)
(25.6 psid, 1040 inches) r_
_~
T1 1
1 1
i __
15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 P(Torus)-P(DW) (psid) 34 35 (320002/17)
E15-4
Procedure EMG-3200.02 Support Proc. 39 Rev. 17 Attachment P Page I of 2 SUPPORT PROCEDURE 39 PLACING THE H2/02 MONITORING SYSTEM IN SERVICE 1.0 PREREQUISITES 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 3.1.6 3.2 Placing 3.2.1 3.2.2 3.2.3 3.2.4 Place mode switch in ANALYZE.
IF 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).
Channel B in service (Panel 16R):
Place switch for V-38-41 to OPEN.
Place switch for V-38-43 to OPEN.
Place switch for V-38-44 to OPEN.
Place switch for V-38-46 to OPEN.
OVER (320002/18)
E16-1
Procedure EMG-3200.02 Support Proc. 39 Rev. 17 Attachment P Page 2 of 2 NOTE When switching to the ANALYZE mode, a system trouble alarm may occur due to analyzer cell low flow.
3.2.5 Place mode switch in ANALYZE.
3.2.6 IF DW H2/02 SYS B TROUBLE alarm (C-8-g) annunciates, THEN acknowledge the alarm and reset by depressing the ALARM RESET pushbutton (Panel 16R).
3.3 Record time.
Time 3.4 NOTE 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 and inform the LOS (320002/18)
E16-2
Procedure EMG-3200.02 Support Proc. 40 Rev. 17 Attachment Q Page 1 of 1 SUPPORT PROCEDURE 40 ISOLATION OF THE PRIMARY CONTAINMENT VENT AND PURGE VALVES 1.0 PREREQUISITES Isolation of the Primary Containment Vent and Purge Valves has been directed by the Emergency Operating Procedures.
2.0 PREPARATION NONE 3.0 PROCEDURE Confirm closed the vent and purge valves that Primary Containment Pressure Control.
System Valve No.
DW Vent/Purge V-27-1 V-27-2 V-27-3 V-27-4 are NOT being used for Panel 11F
- lpF, lF liF Torus Vent Torus 2" Vent Bypass DW 2" Vent Bypass N2 Purge N2 Makeup V-28-17 V-28-18 V-28-47 V-23-21 V-23-22 V-23-13 V-23-14 V-23-15 V-23-16 V-23-17 V-23-18 V-23-19 V-23-20 1lF lpF lpF 12XR 12XR 12XR 12XR 12XR 12XR 12XR 12XR 12XR 12XR (320002/19)
E17-1
Procedure EMG-3200.02 Support Proc. 41 Rev. 17 Attachment R Page I of 2 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 2.2.2 Make the announcement, "PRIMARY CONTAINMENT VENTING WILL COMMENCE IN APPROXIMATELY 5 MINUTES.
ALL PERSONNEL EVACUATE THE REACTOR BUILDING IMMEDIATELY.
STAND CLEAR OF THE STACK AND THE RX. BLDG. FAN PAD."
2.3 Select a SGTS Train for operation and place its fan control switch in HAND (Panel liR).
2.4 Place control switch for V-28-48, SGTS CROSSTIE, in CLOSED (Panel llR).
2.5 Confirm Reactor Building Supply Fans secured (Panel llR).
2.6 Confirm Reactor Building Exhaust Fan secured (Panel llR).
2.7 Confirm that the Reactor Mode Selector Switch is NOT in the RUN position (Panel 4F)._
2.8 Obtain one (1) 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)
Open the EOP BYPASS PLUGS panel inside Panel 1OXF.
2.9.1 Insert a bypass plug in position BP5.
OVER (320002/20)
E18-1
Procedure EMG-3200.02 Support Proc. 41 Rev. 17 Attachment-R Page 2 of 2 2.10 Open the EOP BYPASS PLUGS panel in the rear of Panel 11R.
2.10.1 Remove the bypass plug from position BP4.
2.10.2 Insert a bypass plug into position BP1.
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 BYP keylock switches for both Channels 1 and 2 in the BYPASS position (Panel llF).
2.13 Inform the LOS that the Torus is ready to be vented via the Torus Vent valves.
3.0 PROCEDURE When directed by the LOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel 1lR).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves V-28-21 and V-28-22 (Panel llR).
3.3 WHEN at least five minutes have passed since sounding the Reactor Building Evacuation Alarm, THEN perform the following:
- 1.
Inform the LOS.
- 2.
Start Reactor Building Exhaust Fan 1-5 (Panel 1lR).
3.4 Open Torus Vent valves V-28-18 and V-28-47 (Panel 11F).
3.5 Inform the LOS that Torus venting via V-28-18 and V-28-47 has commenced.
3.6 CAUTION Ventilation ductwork failure WILL occur when venting through V-28-17 with torus pressure greater than 2 psig.
WHEN Torus pressure is below 2 psig, THEN inform the LOS and open Torus Vent valve V-28-17 (Panel 11F).
3.7 Control hydrogen concentration as directed by the LOS by cycling Torus Vent valves as required.
(320002/20)
E18-2
Procedure EMG-3200.02 Support Proc. 42 Rev. 17 Attachment S Page 1 of 4 SUPPORT PROCEDURE 42 PURGING THE DRYWELL FOR HYDROGEN CONTROL 1.0 PREREQUISITES Purging the Drywell has been directed by the Emergency Operating Procedures.
2.0 PREPARATION Perform the following steps in preparation for purging the Drywell.
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)
- 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 llF).
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 LOS that nitrogen purging of the Drywell is ready to commence.
OVER (320002/21)
E19-1
Procedure EMG-3200.02 Support Proc. 42 Rev. 17
- Attachment.
.S Page 2 of 4 3.0 PROCEDURE When directed by the LOS, perform the following:
NOTE 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 at the Nitrogen Station:
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 fan which blows down.
Hearing and eye protection is required.
Place the control switch for M-23-1 in HAND position.
(320002/21)
E19-2
Procedure EMG-3200.02 Support Proc. 42 Rev. 17 Attachment S Page 3 of 4 the nitrogen supply tank outlet the inlet and outlet valves for 3.3 Crack open, then completely open to vaporizer valve V-23-268.
3.4 Crack open, then completely open the selected heater:
3.5 3.6 HTR-854-165 HTR-854-166 Inlet Valve V-23-363 V-23-365 Outlet Valve V-23-364 V-23-366 Place the thermostatic regulating valve in service by opening valves V-23-186 and V-23-187.
Select a Grove Reducer and open the appropriate inlet, outlet 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 Supply 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-854-1732 is 55 psig.
3.7.2 Verify purge flow on the NITROGEN PURGE & MAKEUP FLOW Recorder (Panel 12XR).
OVER (320002/21)
E19-3
Procedure EMG-3200.02 Support Proc. 42 Rev. 17 Attachment S Page 4 of 4 3.7.3 NOTE Initial temperature could be 20 to 30'F above nominal setpoints of 800F. After 5 to 10 minutes, dependent 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 N2 temperature 65-95 F as indicated on the PURGE N2 TEMP gauge (Panel 12XR).
3.7.4 IF ambient temperature is greater than 80 F, AND N2 temperature is above 95 F as indicated on the PURGE N2 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 LOS 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).
(320002/21)
E19-4
Procedure EMG-3200.02 Support Proc. 43 Rev. 17 Attachment T Page I of 2 SUPPORT PROCEDURE 43 VENTING THE DRYWELL FOR HYDROGEN CONTROL (LEVEL BELOW 461 IN.)
1.0 PREREQUISITES 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 2.2.2 Make the announcement, "PRIMARY CONTAINMENT VENTING WILL COMMENCE IN APPROXIMATELY FIVE MINUTES.
ALL PERSONNEL EVACUATE THE REACTOR BUILDING IMMEDIATELY.
STAND CLEAR OF THE STACK AND THE RX. BLDG. FAN PAD".
2.3 Select a SGTS Train for operation and place its fan control switch in HAND (Panel liR).
2.4 Place control switch for V-28-48, SGTS CROSSTIE, in CLOSED (Panel lIR).
2.5 Confirm Reactor Building Supply Fans secured (Panel liR).
2.6 Confirm Reactor Building Exhaust Fan secured (Panel 1lR).
2.7 Confirm that the Reactor Mode Selector switch is NOT in RUN.
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 BPI.
2.9 Place the TORUS/DRYWELL ISOLATION VALVE BYPASS PERMISSIVE keylock switch in the DRYWELL position (Panel 11F).
2.10 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 llF).
OVER (320002/22)
E20-1
Procedure EMG-3200.02 Support Proc. 43 Rev. 17 Attachment T Page 2 of 2 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-27-1,2,3 & 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).
2.12 Inform the LOS that the Drywell is ready to be vented via the Drywell Vent valves.
3.0 PROCEDURE When directed by the LOS, complete the following:
3.1 Reset the Reactor Building Ventilation System by momentarily depressing the system RESET pushbutton (Panel liR).
3.2 Confirm open Reactor Building Main Exhaust Isolation valves, V-28-21 and V-28-22 (Panel llR). -
3.3 WHEN at least five minutes have passed since sounding the Reactor Building Evacuation Alarm, THEN perform the following:
- 1. Inform the LOS.
- 2. Start Reactor Building Exhaust Fan 1-5 (Panel llR).
3.4 Open Drywell Vent valves V-23-21 and V-23-22 (Panel 12XR).
3.5 Inform the LOS that Drywell venting via V-23-21 and V-23-22 has commenced.
3.6 WHEN Drywell Pressure is below 2 psig, THEN perform the following:
- 1. Inform the LOS.
- 2. Open Drywell Vent valves V-27-1 and V-27-2 (Panel llF).
3.7 Control hydrogen concentration as directed by the LOS by cycling Drywell Vent valves as required.
(320002/22)
E20-2
Procedure EMG-3200.02 Support Proc. 44 Rev. 17 Attachment U Page I of 4 SUPPORT PROCEDURE 44 VENTING THE DRYWELL VIA THE Rx BUILDING SUPPLY FANS FOR HYDROGEN CONTROL (LEVEL ABOVE 461 IN.)
1.0 PREREQUISITES 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 HAND (Panel llR).
2.2 Place control switch for V-28-48, SGTS CROSSTIE, in CLOSE (Panel liR).
2.3 Confirm Reactor Building Supply Fans secured (Panel llR).
2.4 Confirm Reactor Building Exhaust Fan secured (Panel llR).
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 llR).
2.6 Place TORUS/DW VENT AND PURGE ISOL VLVS HI RAD BYPASS keylock switches for both Channels 1 and 2 in BYPASS (Panel llF).
2.7 Confirm Reactor Building to Torus Vacuum Breakers V-26-16 and V-26-18 control switch in CLOSE position (Panel 1lF).
OVER (320002/23)
E21-1
Procedure EMG-3200.02 Support Proc. 44 Rev. 17
.Attachment-U Page 2 of 4 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 & 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 the BYPASS position (Panel 12XR).
2.9 Obtain two (2) 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 NOTE 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 automatic damper of one Reactor Building Supply Fan:
Supply Fan Automatic Damper 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.
(320002/23)
E21-2
Procedure EMG-3200.02 Support Proc. 44 Rev. 17 Attachment U Page 3 of 4 2.11.3 Secure the automatic damper in the open position by tightening the wing nuts on the damper positioning device.
2.11.4 Confirm open the manual damper downstream of the supply fan chosen.
Supply Fan Manual Damper 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 device 2.12 Evacuate personnel from the Reactor Building and Main Office Building 2.12.1 Sound the Reactor Building Evacuation Alarm.
Time 2.12.2 Make the announcement, "PRIMARY CONTAINMENT VENTING WILL COMMENCE IN APPROXIMATELY FIVE MINUTES. ALL PERSONNEL EVACUATE THE REACTOR BUILDING AND MAIN OFFICE BUILDING IMMEDIATELY".
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 switch in FULL RECIRC position (SYS A Panel llR/SYS B Panel 9XR).
2.13.2 Confirm exhaust fan EF-1-24 control switch is OFF (Control Room behind Panel llF) and its damper is closed (CR Bathroom)
OVER 12/23)
E21-3 (3200C
Procedure EMG-3200.02 Support Proc. 44 Rev. 17 Attachment U Page 4 of 4 3.0 PROCEDURE When directed by the LOS, complete the following:
CAUTION An unmonitored, ground level release of radioactive gases will result from venting the primary containment 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 the Reactor Building evacuation alarm THEN inform the LOS and perform the following:
3.2.1 Open drywell air supply valves V-28-42 and V-28-43 (Panel llR).
3.2.2 Open drywell purge valves V-27-3 and V-27-4 (Panel llF).
3.3 Inform the LOS that Drywell Venting has commenced.
3.4 Control hydrogen concentrations as directed by the LOS by cycling the Drywell Vent valves as required.
(320002/23)
E21-4
Procedure EMG-3200.02 Support Proc. 45 Rev. 17 Attachment V Page I of 4 SUPPORT PROCEDURE 45 PURGING THE TORUS FOR HYDROGEN CONTROL 1.0 PREREQUISITES 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)
- 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 CRAM VAC REL (Torus to Reactor Building Vacuum Breakers, V-26-16 and V-26-18) control switch in the CLOSE position (Panel llF).
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 LOS that nitrogen purging of the Torus is ready to commence.
OVER (320002/24)
E22-1
Procedure EMG-3200.02 Support Proc. 45 Rev. 17 Attachment V Page 2 of 4 3.0 PROCEDURE When directed by the LOS, perform the following:
NOTE 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 at the Nitrogen Station:
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 fan which blows down.
Hearing and eye protection is required.
Place the control switch for M-23-1 in HAND position.
(320002/24)
E22-2
Procedure EMG-3200.02 Support Proc. 45 Rev. 17 Attachment.V 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 Inlet Valve V-23-189 V-23-190 Outlet Valve V-23-191 V-23-192 Suoply 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-854-1732 is 55 psig.
3.7.2 Verify purge flow on the NITROGEN PURGE & MAKEUP FLOW Recorder (Panel 12XR).
OVER (320002/24)
E22-3
Procedure EMG-3200.02 Support Proc. 45 Rev. 17 Attachment V Page A of 4 3.7.3 NOTE Initial temperature could be 20 to 300 F above nominal setpoint of 80*F.
After 5 to 10 minutes, dependent on ambient temperature, temperature will stabilize.
CAUTION The temperature range of 650-950 F as read in the Control Room is important to prevent brittle fracture and cracking of piping within the containment.
Confirm N2 temperature 65-95 F as indicated on the PURGE N2 TEMP gauge (Panel 12XR).
3.7.4 IF ambient temperature is greater than 80'F AND N2 temperature is above 950F as indicated on the PURGE N2 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 LOS that Torus purging has commenced.
3.9 WHEN directed by the LOS to secure the nitrogen purge, THEN Close Torus purge valves V-23-15 and V-23-16 (Panel 12XR).
(320002/24)
E22-4
A OYSTER CREEK NUCLEAR GENERATING Number PAL.J I.2~ awe>;" a STATION PROCEDURE 5(-Zui A PECO Enemgy/BM h Energy CorranyrV Title Revision No.
SECONDARY CONTAINMENT CONTROL 11 Applicability/Scope Usage Level Responsible Department EMERGENCY OPERATING PROCEDURE FOR OYSTER CREEK OPERATIONS Effecti, 7 te Prior Revision 10 incorporated the This Revision 11 incorporates the following Temporary Changes:
following Temporary Changes:
N/A N/A LIST OF PAGES (all pgs. rev'd to Rev. 11) 1.0 to 3.0 El-l E2-1 to E2-2 E3-1 OYSTER CREEK CONTROLLED DISTRIBUTION DOCUMENT SERIAL NUMBER-IRMC Signature Concurring Organization Element Date Originator EOP COORDINATOR 3
lo
/0 Concurred By EOP COMMITTEE A
DIRECTOR ENGINEERING
- ____6___e__
PLANT OPERATIONS DIRECTOR Approved By I
s PLANT MANAGER y
I i
(320011) 1.0
Amgewfdch I OYSTER CREEK NUCLEAR GENERATING lNumber An_ _xo Cn STATION PROCEDURE EMG-3200.11 An Jbmln Corpany
-Title Revision No.
SECONDARY CONTAINMENT CONTROL 11 1.0 PURPOSE 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 integrity or limit the release from the Secondary Containment.
2.0 REFERENCES
2.1 Procedures AD-OC-103, EOP-SAM 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
Amarfewm An Exelon Company I OYqTVR CREF.RI MtW.LEAR GENERATING I
STATION PROCEDURE Number EMG-3200.1 1 Title SECONDARY CONTAINMENT CONTROL Revision No.
11 4.0 ATTACHMENTS 4.1 Attachment A -
Secondary Containment and Radioactivity Release Control EOP Flowchart EMG-3200.11 & EMG-3200.12 Rev. 5 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
(320011)
- 3. 0
A 4M V r f An Exelon Company I novr P rFF1Tz N1TJ7T.AR r.FNVRATING(
l -
STATION PROCEDURE Number EMG-3200.1 1
+
Title SECONDARY CONTAINMENT CONTROL Revision No.
11 ATTACHMENT A Attachment A to EMG-3200.11, Secondary Containment Control, is the Secondary containment and Radioactivity Release Control EOP Flowchart, EMG-3200.11 & EMG-3200.12 Rev.5 I
(320011/S3)
El-l
Procedure EMG-3200.11 Support Proc -
49 Rev. 11 Attachment B Page 1
of 2 SUPPORT PROCEDURE 49 CONFIRMATION OF SECONDARY CONTAINMENT INITIATIONS AND ISOLATIONS 1.0 PREREQUISITES 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 llR).
- 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 OVER (320011/S4)
E2 -1
Proceaure tML-jzVU.11 Support Proc -
49 Rev. 11 Attachment B Page 2 of 2
3.4 Reactor Building Supply Fans trip (Panel llR)
- SF 1-12 SF 1-13
- SF 1-14 3.5 Operating Reactor Building Exhaust Fan trips (Panel IlR)
- EF 1-5 or,
- EF 1-6 3.6 Drywell Ventilation Supply Valves Close (Panel IlR)
- V-28-42
- V-28-43 3.7 WHEN proper flow is established in the selected SGTS Train, THEN Confirm the following:
- 1. SGTS Crosstie V-28-48 closes (Panel lR).
- 2. The non-selected SGTS Fan trips (Panel llR).
- 3. The non-selected SGTS Train inlet and discharge valves close (Panel IlR).
- 4. The running SGTS Train orifice valve closes (Panel lIR).
(320011/S4)
E2 -2
Procedure EMG-320U.11 Support Proc -
50 Rev. 11 Attachment C Page 1
of 2 SUPPORT PROCEDURE 50 REACTOR BUILDING VENTILATION RESTART 1.0 PREREQUISITES The restart of Reactor Building Ventilation has been directed by the Emergency Operating Procedures.
2.0 PREPARATION When directed by the LOS, perform the following:
2.1 Verify that the Reactor Building Ventilation Effluent Monitors (REACTOR BUILDING VENT MANIFOLD NO. 1 AND NO.2)are reading less than 9 mREM/hr (Panel 2R).
2.2 Open the EOP BYPASS PLUGS panel in the rear of Panel llR.
2.2.1 Remove the bypass plug from Position BP4.
2.2.2 Insert the bypass plug into Position BPI.
3.0 PROCEDURE When directed by the LOS, perform the following:
3.1 Open the EXH. VALVES TO MAIN EXHAUST V-28-21 and V-28-22 (Panel llR).
3.2 Reset the Reactor Building Ventilation System by depressing the RX BLDG. VENT ISOLATION RESET button (Panel llR).
I I
3.3 CAUTION Steps 3.4 and 3.5 should be completed immediately after starting Exhaust Fan EF-1-5 in order to preclude damage to Ventilation System Ducts.
Start REACTOR BUILDING EXHAUST FAN EF 1-5 by placing its control switch in START (Panel 1IR).
3.4 Confirm control switch for MAIN SUPPLY HEADER VALVES TO DW V-28-42 and V-28-43 in CLOSE (Panel llR).
3.5 Select and start two of the following Reactor Bldg Supply
- Fans, SF 1-12, SF 1-13, and SF 1-14, by placing their control switches in ON (Panel lIR).
(320011/SS)
E3-1