ML20086K179

Amend 2 to Failure Modes & Effects Analysis

ML20086K179
Person / Time
Site:	Beaver Valley
Issue date:	01/31/1984
From:	STONE & WEBSTER ENGINEERING CORP.
To:
Shared Package
ML20086K174	List: ML20086K170 ML20086K179 ML20086K189
References
NUDOCS 8401260331
Download: ML20086K179 (26)

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BVPS-2 FMEA f) v INSERTION INSTRUCTIONS FOR FMEA AMENDMENT 2 Remove old pages and insert Amendment 2 pages as instructed below.

Transmittal letters along with these insertion instructions should either be filed or entered in Volume 1 in front of any existing letters, instructions, distribution lists, etc.

LEGEND 1

Remove / Insert Columns Entries beginning with "T" designate table numbers. All other entries are page numbers:

2-1 = Table 2-1 3-3 = Page 3-3 EP-1 = Page EP-1 vii = Page vii 4

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1-1/2 = Page 1-1 backed by Page 1-2 T6-1(1 of 4)/2 of 4 = Table 6-1, Sheet 1 of 4, backed by Sheet 2 of 4 Location Column Ch = Chapter, S = Section, Ap = Appendix Remove Insert Location Book 1 l -

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INSERTION INSTRUCTIONS FOR FMEA' AMENDMENT 2 (Cont)

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BVPS-2 FMEA SECTION 1

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\_/ INTRODUCTION ,

1.1 PURPOSE OF ANALYSIS The purpose of the failure modes and effects analysis (FMEA) is to l demonstrate and verify how the requirements of General Design criteria (GDC) of Title 10, Code of Federal Regulations, Part 50 (10 CFR 50), l Appendix A, and IEEE Standard 279-1971, Criteria for Protection Systems of Nuclear Power Generating Stations, are satisfied. FMEAs are performed on the Class 1E instrumentation and controls and electrical power portions of the balance of plant (BOP) safety-related systems in a nuclear power plant to determine if they will meet the single failure criteria. The analysis considers the loss to vital equipment of electrical power and control systems under postulated accident and failure conditions.

1.2 REQUIREMENT FOR ANALYSIS The FMEAs and their associated analyses of the single failure criteria are submitted to satisfy the requirements of 10 CFR 50.34 (b) (2), with specific guidance on scope provided by USNRC Regulatory Guide 1.70, Standard For:aat and Content of Safety Analysis Reports for Nuclear Power Plants, Revision 3, November 1978, Section 7.3.2.

f-~3 Further guidance is provided in the following documents:

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1. IEEE Standard 308-1974, Class IE Power Systems for Nuclear Power Generating Stations, l

2. IEEE Standard 379-1977, Application of the Single Failure Criterion to Nuclear Power Generating Station Class IE Systems, l

3. USNRC Regulatory Guide 1.32, Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants, and l

4. USNRC Regulatory Guide 1.53, Application of the Single Failure Criterion to Nuclear Power Plant Protection Systems.

USNRC NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Edition, July 1981, also identifies the systems that require FMEAs to be performed on them.

1.3 FAULT TREE ANALYSIS The fault tree is a technique by which failures that can contribute to an undesired event are systematically and deductively organized from a top event down to subordinate events. It is pictorially represented by rectangular blocks connected by logic gates, all placed together in a tree-shaped configuration. The fault tree analysis (FTA) identifies all failure modes which are significant to the failure of the system, the

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Amendment 2 1-1 January 1984

BVPS-2 FMEA failure paths from the failed items up through the fault tree to a single top event, and any single failures that may result in the failure of the system to perform its intended safety function. The FTA provides a visual display of how the system can malfunction. The failure information in the FTA, when assigned computer - readable codes, can be l converted into a document called the FMEA.

1.4 FAILURE MODES AND EFFECTS ANALYSIS The FMEA is a plain language computerized tabulation of the failure information taken from the FTA. The failure information in the fault tree, having been assigned unique computer codes, is computer program-processed and printed out in an organized fashion. The tabulation identifies the component, its failure mode, the method of failure detection, and its effect on the system. This document is the auditable record of the failure analysis performed on the instrumentation and controls and electrical power portions of a BOP safety-related system.

1.5

SUMMARY

The failure modes and effects analysis, a systematic, organized, analytical procedure for identifying the possible modes of failure and evaluating their consequences was performed on the BOP safety-related and protective systems of Beaver Valley Power Station -

Unit 2. The scope of failure analysis, the methodology used to develop fault trees, the results of analyses, and an illustratwe example are described in the sections that follow. The detailed results of the analyses, in the form of FMEAs, are presented in computer output format in Appendix A of this document.

Amendment 2 1-2 January 1984

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l BVPS-2 FMEA TABLE 2-1 SAFETY-RELATED SYSTEMS AND THEIR REFERENCE DOCUMENTS Sys System Descr Flow Diagrams / E lemen ta ry

[ MEA [1] SVstem Title Code FSAR Section One-Linesf21 Diao ransf 31 1

5-4 Condensate & Feedwater FWS 10.4.7 RM-45A/13 11E/2, 11F/3, 11ER Sh 3/1

Systems S 5-13 Aux i l i a ry Feedwa te r fWA/FWE 10.4.9 RM-45A/13, RP 45B/2 3A/7, SC/7, 12A/3, l System 120/3, SDE/8, SDU/8, SEE/7, SEU/8, 6JV/4, l

6JW/4, 6JX/4, 11K/7, i

11AB/8, 11JA/2, 11JB/2 l 5-15 Steam Generator Blowdown BDG 10.4.8 RM-41A/11, RM-99A/11, 3E/8, 3H/9, 3L/8, 3M/8, j System RM-100A/12 11K/8, 11X/7, 11Y/7, SDE/7, SEE/7, 11BK/4 8-9 Emergency Diesel Gen- ECF 9.5.4 hM-72A/9 6NS/2, 6NT/2

( e ra to r f ue l O i l Sto rage

& Transfer System i

12-7 Prima ry Component Cooling CCP 9.2.P.1 RM-470/11, RM-47D/10, SG/8, 12A/3, 128/3, Water System RM-77A/8, RM-77B/8, SCH/8, SDG/10, 5DH/10, l 'i

' RM-77C/8, RM-77E/8, 500/8, SEG/9, SEH/10, I RM-77F/8, f<M-770/11, SEU/8, 6FL/6, 6FM/4, j RM-77H/3 6FS/6, 6FT/4, 6CE/3, j 6RL/5, 6RM/4, 6RN/4,

6RP/4, 11JA/1, 11lB/1, l J 11FZ Sh 3/1 l 14-15 Reactor Plant & Process SSR 9.3.2.1 RM-99A/11 11AH/5 Sampling System 15-2 Main Steamline isolation MSS 10.3 RM-41A/9, RM-58A/6 11Q/2, 11AC/6, 11AD/4, System 11AS/2, 11AT/2, 11AU/3, 1

11BW/1, 11EH/3 17-1 SWS RM-47B/11, RM-47C/10 SDN/10, SDP/7, SDU/8, l

) Station Service Water System 9.2.1 SEE/7, SEN/8, SEP/8, SEU/8, 6GA/4, 6GC/4, l j 6GE/3, 6MR/4, 6MS/1, 4

• GNQ/4, 11FX/ Prelim 1

21-1 Control Room Ventilation HVC 9.4.1 RB-84C/7 6JD/4, 6JE/3, 6JF/4, l 6UP/2, 6UQ/4, 11CL/3, 1 System i 11CN/3, 11CQ/3, 11CX/3 i

21-2 Control Building Venti- HVC 9.4.1 RB-84A/5 3K/9, 60M/5, 60N/4 i

lation System i

Amendment 2 1 of 4 January 1984 l

BVPS-2 FMEA TABLE 2-1 (Cont)

Sys System Descr Flow Diagrams / E l emen ta ry FNEA(1) System Title Code FSAR Section One-Lines (2) Diao rams ( 3 )

21-6 Main Steam & Feedwater HVT 9.4.9 RB-85A/6 3A/8, SDU/8, SEU/8, Va lve Area Venti lation 6BB/6, 6BC/5, 6ET/1, System 6EU/1, 11FV/1 21-7 Sa fegua rds Area Venti lation HVK 9.4.11 RB-85B/2 6EK/5 System 21-8 Cable Vault & Rod Control HVR 9.4.12 RB-95B/2 6EH/5, 6JM/3, 11R/4 Area Ventilation System 21-18 Supplementa ry Leak Col- HVS 6.5.3.2 RB-85C/4 7D/6, 12A/3, 500/8, lection and Release 6AG/4, 6AJ/6, 688/5, System 6BC/5, 11CE/3, 11CF/3, 11CG/3, 11011/3, 11 CJ / 3, 11CK/3, 11C P/3, 11CR/3, 11JA/1 21-19 Containment Purge Ai r HVR 9.4.7.3 RB-85D/4 6UA/3, 6UB/2 System 21-21 Auxiliary Building & Rad- HVP 9.4. RB-85D/4, RB-85C/4 6EQ/3, 6ER/3, 11CA/3, waste Area Ventilation 11CB/3 System 21-23 P r i ma ry intake Structure HVW 9.4.8 RB-84B/3 6EX/5, 11DP/1 Ventilation System 21-34 Diesel Gene ra to r HVD 9.4.6 RB-848/3 6EP/3, 11DS/?, 11DT/2, l Building Ventilation System 11JA Sh 1/2 & Sh 2/1 21-55 Emergency Swi tchgea r Room HVZ 9.4.10.3 RB-84A/5 SDU/8, 688/5, 6BW/5, Ventilation System 6B2/3, 11DU/2, 11DV/2 21-56 Battery Room Ventilation HVZ 9.4.10.2 RB-84A/S 6EB/5 System 22-5 Class 1E AC Power System ENS 8.3.1 RE-1F/3, RE-1AW/2 SDA/9, SDB/6, SDT/7, 500/8, SEA /8, SEB/5, SEU/8 22-6 Emergency Diesel Gene ra to r ECA 9.5.6 - 12H/2, 12J/2, 12M/2, Starting System 12N/2, SDA/9, SDU/8, SEA /8, SEU/8 22-6.1 Engineered Safety Features ECS 8.3.1.1.8 - 12A/3, 12B/3, 5DA/10, l Load Sequencing 508/6 Amendment 2 2 of 4 Janua ry 1984 O O O

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BVPS-2 FMEA I

1 TABLE 2-1 (Cont)

Sys System Descr Flow Diagrams / E l ementa ry i FMEAf11 System Title Code FSAR Section One-Lines (21 piao rams t 3 )

22-6.5 Emergency Diesel Gene ra to r EGS 9.5.5 - 12D/3, 12E/3, 12F/2, l Spurious Trip 9.5.7 12G/2, 12K/2, 12L/2, SDA/9, SEA /8 22-8 480 V AC Emergency Power EJS 8.3.1.1.3 RE-1C/3, RE-1J/3 SDT/7, SET /7, 6BA/4 Supply 22-10 Class 1E DC Power System BYS -8.3.2 RE-1AR/2, RE-1AW/2 6Y/E 22-12 Vital Bus Uninterruptible VBS 8.3.1.1.17 RE-1AW/2 -

Power System I 25-4 RCS-Pump, Hot / Cold Leg, RCS 5.4.13 RM-75A/10 SF/10, SAF/10, 5BF/10, Bypass isolation 10.4.4 6FA/3, 6FB/4, 6FC/4,

• 6FD/4, 6FE/4, 6KS/3 I RM-75B/10, RM-79C/10 11L/3, 6FC/3, 6HZ/3, 25-6 RCS-Pressurizer Control RCS 5.4.10 60E Sh 2/4 3' 25-7 Residual Heat Removal RHS 5.4.7 RM-76A/11 6RW/3, 6RU/5, 6RV/5, System 11AB/6, 11GF Sh 1/3 e

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2/2, 11GN Sh 1/3, 2/3, 3/3, 4/3, & 5/2 l

25-13 RCS-Reactor Coolart Let- RCS 5.4.1 RM-75A/10, RM-79C/10 11J Sh 1/6, 6HX/3, down 6HY/3, 6JN/2, 6QC/4,

! 11AF Sh 1/5, 11AJ/5 26-1 High Head Safety injection SIS 6.3 RM-75A/10, RM-79A/11, SDL/8, 5DM/6, 50U/9, j System RM-79C/10, RM-79D/9, SEL/6, SEU/9, 6HS/3, RM-85B/9, RM-87A/11, 6HT/3, 6JJ/9, 6JK/7, j RM-87B/11 11AL/6, 11FZ Sh 3/1,

SEM/9, 6JG/4, 6JH/4 l 26-2 Low Head Safety injection SIS 6.3 RE-21S/4, RE-21V/4 3B/9, 3E/8, 3F/8, l i system 3H/9, 7C/6, 12A/3, 128/3, SDA/9, SDB/6, I SDR/6, SDS/7, 500/8, .

' SEA /8, SEB/5, 5ER/6, a

SES/7, SEU/8, 6HD/4, j

6HR/4, 60W/4, 6QY/3, 6RA/3, 11AL/4 l

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1 Amendment 2 3 of 4 Janua ry 1984 f

BVPS-2 FMEA TABLE 2-1 (Cont)

Sys System Descr Flow Diagrams / E l emen ta ry FMEAll) System Title Code FSAR Section One-Lines (2) Diaaramsf3) 27-1 Reci rculation Spray System RSS 6.2.2.2.2 RM-47B/12, RM-85A/11 3 11 / 9 , 12A/3, 12B/3, SDA/9, SDB/6, 500/6, SDR/6, SEA /8, SEB/5, SEQ /6, SER/6, 6GF/4, 6GJ/4, 6GK/4, 6GL/4, 6HA/4, 6HB/4, 6HC/4, 6HD/4, 60W/4 27-9 Quench Spray System QSS 6.2.2.2.1 RM-85c/10 3B/9, 3E/8, 3F/8, 3H/9, 12A/3, 12B/3, 5DA/9, SDK/9, SDU/8, SEA /8, SEK/9, SEU/8, 6DU/1, 6JA/4, 6JB/4 6JC/4, 110Y/1, 110Z/1 27-10 Containment Vacuum Leakage CVS 6.2.6 RM-88A/10 6DV/4, 6QQ/4, 11AC/4 Moni toring System 27-12 Containment Isotation LMS 6.2.4 RM-88A/10 11M/5, Westinghouse l Signal initiation SW200-1.409-001-024D System 27-13 Combustible Gas Control HCS 6.2.5 RM-110A/10 11T/2, 6FY/3 System 29-8 Spent fuel Pool Cooling SFC 9.1.3 RM-82A/12 6ND/5, 6RJ/3

& Cleanup System (1) Prefix FMEA numbers shown with "12241-FMEA "

(2) P re f i x Flow Diagram /One-Line numbers shown with "12241 "

(3) Prefix Elementa ry Diagram numbers shown with "12241-E "

Amendment 2 4 of 4 Janua ry 1984 O O O

BVPS-2 FMEA l' h . More contacts must fail for failure to be detectable Q

. Periodic test

. Periodic inspection

. Undetectable It is possible that a failure is either not detectable or that more devices must fail to have a detectable failure. Should the ccmponent failure be one of these, a system design change usually must be implemented to make all failures readily detectable.

3.4 SINGLE FAILURE EXAMINATION After development of the fault tree, all of its branches are examined for any single component failure that leads directly to the top event by utilizing the computer process described in the following section.

Where a single failure that could cause loss of the system safety function is identified, the design is evaluated to determine if any compensating features are available that could provide the function. If no compensating features are available, a system design change is required. The tree is then revised to include the change and reexamined for single failure possibility. If the single failure has been eliminated, the design change is then implemented. l f) 3.5 COMPUTER CODING AND OUTPUTS s_.

Each event gate and con.ponent block of the fault tree is assigned a unique, computer-readable, identifier code. This identifier code, along with the associated component / device identification number (Mark No.)

and failure description of that gate or block, is entered into the l computer for processing.

l The computer program examines the identifier codes of the fault tree for any single component failures that lead to the top event. The cut set subroutine of the computer program performs the determination of single failure. It can also uncover those cases where an undetectable failure exists in combination with another failure to lead to the top event.

l The FMEA subroutine of the program utilizes the coded fault tree data to i produce the tabulated printouts. These printouts of the failure analyses performed on the BOP safety-related systems can be found in Appendix A.

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Amendment 2 3-3 January 1984

BVPS-2 FMEA TABLE 6-1 SYSTEM DESIGNATORS System System Designator System Description Code A Safety Injection System - Low Pressure SIS l

B 125 V DC Class 1E Power System BYS l

C 3ervice Water System SWS D Residual Heat Removal System RHS E 4,160 V AC Class IE Power System ENS F Auxiliary Feedwater System FWA/FWE G Emergency Diesel Generator Systems EGA/EGF/EGS H Combustible Gas Control System HCS I Not used ,

i J 480 V AC Emergency Power Supply EJS

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s.. l l K HVAC - Service Building HVL HVAC - Main Steam and Feedwater Valve HVT Area L Not used --

M Main Steamline Isolation System MSS Steam Generator Blowdown System BDG l

N HVAC - Control Building / Room HVC f 0 Not used --

P Primary Component Cooling Water System CCP Q Quench Spray System QSS R Recirculation Spray System RSS l

S Not used --

T Not used --

l O) t U Amendment 2 1 of 2 January 1984

. , , - . , - , - -. - - - - ,.,w,., , 7,, -.------e-~,.- - n,-.+-r - - - -, , . - , . , . . , ----.,--n .,,r-r- v,--, -- ,,,,--m,ep w-r

BVPS-2 FMEA TABLE 6-1-(Cont)

System System O

Designator System Description Code U Condensate and Feedwater System FWS V HVAC - Diesel Generator Building HVD W Safety Injection System - High Pressure SIS Reactor Coolant System - Pressurizer RCS Control Reactor Coolant System - Reactor Coolant RCS Letdown l X Not used --

Y Containment Isolation Signal ISC Initiation System Reactor Coolant System - Pump, Hot / Cold RCS Leg, Bypass Isolation Z HVAC - Safeguards Area HVK Containment Purge Air System HVR 1 Spent Fuel Pool Cooling and SFC Cleanup System 2 Vital Bus Uninterruptible Power System VBS 3 HVAC - Primary Intake Structure HVW 4 HVAC - Emergency Switchgear Room HVZ l 5 HVAC - Auxiliary Building HVP 6 Containment Vacuum Leakage Monitoring System CVS l HVAC - Battery Roon HVZ 7 Supplementary Leak Collection and Release System HVS 8 HVAC - Cable Vault and Rod Control Area HVR 9 Reactor Plant and Process Sampling SSR System Amendment 2 2 of 2 January 1984

h BVPS-2 FMEA APPENDIX A

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TABLE OF CONTENTS Tab Number System Title Sheets i

FMEA-5-4 Condensate and Feedwater System 10 FMEA-5-13 Auxiliary Feedwater System (Controls) 34 FMEA-5-15 Steam Generator Blowdown System 12 FMEA-8-9 Emergency Diesel Generator Fuel Oil Storage and Transfer System 5 FMEA-12-7 Primary Component Cooling Water System 162 FMEA-14-15 Reactor Plant and Process Sampling System 3 FMEA-15-2 Main Steamline Isolation System 145~

FMEA-17-1 Station Service Water System 47 FMEA-21-1 Control Room Ventilation System 25 FMEA-21-2 Control Building Ventilation System 10

%s FMEA-21-6 Main Steam and Feedwater Valve Area Ventilation System 12 FMEA-21-7 Safeguards Area Ventilation System 2 FMEA-21-8 Cable Vault and Rod Control Area *~

Ventilation System FMEA-21-18 Supplementary Leak Collection and

! Release System 84 FMEA-21-19 Containment Purge Air System 7 FMEA-21-21 Auxiliary Building Ventilation System 8 FMEA-21-23 Primary Intake Structure Ventilation System 4 i

FMEA-21-34 Diesel Generator Building Ventilation System 7 FMEA-21-55 Emergency Switchgear Room Ventilation System 15 FMEA-21-56 Battery Room Ventilation System 2 1

Amendment 2 A-i January 1984 f

BUPS-2 FMEA TABLE OF CONTENTS (Cont)

Tab Number System Title Sheets O

FMEA-22-5 Class 1E AC Power System 30 FMEA-22-6 Emergency Diesel Generator Starting System 6 FMEA-22-6.1 Engineered Safety Features Load Sequencing 19 FMEA-22-6.5 Emergency Diesel Generator Spurious Trip 10 FMEA-22-8 480 V AC Emergency Power Supply 11 FMEA-22-10 Class 1E DC Power System 6 FMEA-22-12 Vital Bus Uninterruptible Power System 7 FMEA-25-4 RCS - Pump, Hot / Cold Leg, Bypass Isolation 9 FMEA-25-6 RCS - Pressurizer Control 8 FMEA-25-7 Residual Heat Removal System 53 FMEA-25-13 RCS - Reactor Coolant Letdown 17 l FMEA-26-1 High Head Safety Ir.jection System 127 FMEA-26-2 Low Head Safety Injection System 64 FMEA-27-1 Recirculation Spray System 34 FMEA-27-9 Quench Spray System 34 l FMEA-27-10 Containment Vacuum Leakage Monitoring System 4 FMEA-27-12 Containment Isolation Signal Initiation System 2 FMEA-27-13 Combustible Gas Control System 10 FMEA-29-8 Spent Fuel Pool Cooling and Cleanup System 4 1

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l Amendment 2 A-il January 1984 l

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22-6.-3 G00112A3 S2-EGSAAX1 COIL PERIODIC TEST DSL 2-1 AUTO LOAD SEQ FAILS

] FAILS 22-6.-D G00212A3 52-EGSAAX2 COIL PERIODIC TEST DSL 2-1 A'JTO LOAD SEQ FAILS -

FAILS 22-6.-D G00312A3 52-EGSAAX3 COIL PERIODIC TEST DSL 2-1 AUTO LOAD SEQ FAIL 4 FAILS

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'2-6.-AF G00r412A3 52-Et4 SAC PERIODIC TEST DSL TO LOAD SEQ FAILS C0:4 TACT 77 FAILS OPEtt

22-6.-AF G00512A3 525-ENSAC PERIODIC TEST DSL 2-1 AUTO LOAD SEf1 FAILS C0!4 TACT 77 tiO ACT SIGHT.L

, 22-6.-Y G00612A2 1-EGSAAX INDICATING LIGHT DSL 2-1 AUTO LOAD SEQ FAIL 3 j

RESET COIL FAILS IN CCWROL ROCil 22-6.-Y G00712A2 3-EGSAAX1 INDICATIrlG LIGHT DSL 2-1 AUTO LOAD SEQ FAILS I

CONTACT 113 IN CCNTROL ROOH FAILS CPEN 22-6.-AG G00012A3 3-ECSAAX1 COIL PERICOIC TEST DSL 2-1 AUTO LOAD SEQ FAILS FAILS 22-6.-AG G00912A3 EGS11 TN A PERIODIC TEST EGS11 TN A CatiTACT ES-1 CPEN CCt4 TACT ES-1 FAILS OPEN 22-6.-AG G01012A3 EGS11 1N A PERICDIC TEST ECS11 TN A CONTACT ES-1 OPEtt (DIESEL EtIER TN A C0t4 TACT ES-1 STRT SIGNAL)

', It0 ACT SIGt4AL 22-6.-AG G01112A3 EGS11 TH A PERIODIC TEST EGS11 TN A CONTACT ES-2 OPEN (DIESEL EttF4 TN A CO:4 TACT ES-2 STRT SIGNAll it3 ACT SIGNAL 22-6.-AG G01212A3 EGS11 TN A PERIODIC TEST EGS11 TN A CONTACT ES-2 OPEN j C0:4 TACT ES-2 FAILS OPEN 22-6.-H Gt'4312A3 62-EGSAA COIL PERIODIC TEST DSL 2-1 AUTO LOAD SFQ FAILS FAILS 22-6.-T G01412A3 62-EGSAA PERIODIC TEST DSL 2-1 Auto LOAD SEQ FAILS CCNTACT 3 J FAILS OPEN 1

I i l - ' A'! l FAILURE If0 DES AND EFFECIS At!ALYSIS I 1

II Ii i i 971 Ercro SarETY FEATURES LOAD SECUEH I January 1984

! Amendment 2 i 141 131 121 11 1 I II I I II l 1 -- 1 J.O. 12241 FttFA-22-6.V 2 SH 1l

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. CONTACT 117 IN CONTROL R00:1

-FAILS CPEN j 22-6.-V G03312A3 362-EGSAA FAILS PERIODIC TEST DSL 2-1 AUTO LOAD SEQ FAILS i 22-6.-V G03412A3 3-EGSAAX PERIODIC TEST DSL 2-1 AUTO LOAD SEQ FAILS 1

CONTACT 115 I

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22-6.-H G03812A3 462-EGSAAX PERIODIC TEST DSL 2-1 AUTO LOAD SEQ FAILS CONTACT 3 i FAILS OPEN

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22-6.-H G04012A3 462-EGSAA FAILS PERIODIC TEST DSL 2-1 AUTO LCAD SEQ FAILS

, 22-6.-H G04112A3 3-EGSAAX PERIODIC TEST OSL 2-1 AUTO LOAD SEQ FAILS CONTACT 117 j FAILS CPEN 22-6.-H G04212A3 1-EGSAA PERIODIC TEST DSL 2-1 AUTO LOAD SEQ FAILS j CCNTACT 13 FAILS OPEN 22-6.-H G04412A3 562-EGSAAX COIL PERIODIC TEST DSL* 2-1 AUTO LOAD SEQ Ft.ILS FAILS 22-6.-X G04S12A3 S62-EGSAAX PERIODIC TEST DSL 2-1 AUTO LOAD SEQ FAILS l CCflTACT 3 FAILS OPEN

,22-6.-H G04612A2 1-EGSAAX INDICATItiG LIGHT CSL 2-1 AUTO LOAD SEQ FAILS

CONTACT 223 IN CONTROL R00ft i FAILS OPEN j 22-6.-X G04712A3 S62-EGSAA FAILS PERIODIC TEST DSL 2-1 AUTO LOAD SEQ FAILS 1

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?2-6.-C G20712A2 CNT EGSAA INDICATING LIGHT DSL 2-1 AUTO LOAD SEQ FAILS CONTROL PH IN CONTROL ROOH SH09T CIRCUIT 22-6.-J G21512A3 662-EGSAA PERIODIC TEST DSL 2-1 AUTO LOAD SEQ FAILS CCitTACT 1 TCC FAILS 22-6.-Y G21812A2 1-EGSAA CONTACT 5 INDICATING LIGHT DSL 2-1 AUTO LOAD SEQ FAILS FAILS OPEN IN CONTROL ROctt 22-6.-Y G21912A2 1-EGSAAX INDICATING LIGHT DSL 2-1 AUTO LOAD SEQ FAILS CONTACT 211 IN CONTROL R00tl FAILS OPEN 22-6.-Y G22212A2 1-EGSAAX INDICATING LIGHT DSL 2-1 AUTO LOAD SEQ FAILS OPERATE COIL IN C0tlTROL R00ll EliER3IZED BY SH09T CIRCUIT 22-6.-Y G22312A2 1-EGS%A CONTACT 3 INDICATING LIGHT DSL 2-1 AUTO LOAD SEQ FAILS FAILS CLOSED IN CONTROL RO0tt 22-6.-E G0581283 32-EGSBAX1 COIL PERIODIC TEST DSL 2-2 AUTO LOAD SEQ FAILS FAILS 22-6.-E G05912B3 52-EGSBAX2 COIL PERIODIC TEST DSL 2-2 AUTO LOAD SEQ FAILS FAILS 22-6.-E G0601283 52-EGSBAX3 COIL PERIODIC TEST CSL 2-2 AUTO LOAD SEQ FAILS FAILS 22-6.-AH G06112B3 52-ENSBC PERIODIC TEST DSL 2-2 AUTO LCAD SEQ FAILS CONTACT 77 FAILS CPEN 22-6.-AH G06212B3 52-ENSCC PERIODIC TEST DSL 2-2 AUTO LOAD SEQ FAILS Ito ACTUATION SIGNAL 22 6.-AE G0631202 1-EGSBAX INDICATIt4G LIGHT DSL 2-2 AUTO LOAD SEQ FAILS RESET COIL FAILS IN CONTROL ROOlt l l l l IFAILURE I! ODES AND EFFECTS AtiALYSIS l l l l l l l l l l EftGRD SAFETY FEATURES LOAD SECUEtl I lul 131 121 111 I I II II I I I I I J.O. 12041 Ftt?A-22-6.1/2 SH E.1

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NO ACT SIGMAL 22-6.-AJ G06812B3 EGS21 TN B PERIODIC TEST EGS21 TN B CONTACT ES-2 OPEN (DIESEL Et1ER TN B CONTACT ES-2 STRT SIGNAL)

ND ACT SIGNAL 22-6.-AJ G0691283 EGS01 TH B PERIODIC TEST EGSO1 TH B CONTACT ES-2 OPEN CottTACT ES-2 FAILS OPEN 22-6.-P G0701283 62-EGSBA COIL PERIODIC TEST DSL 2-2 (UTO LOAD SEQ FAILS FAILS 22-6.-Z G0711083 60-EGSBA PERIODIC TEST DSL 2-2 AUTO LOAD SEQ FAILS C0t4 TACT 3 FAILS CDEN 02-6.-P G07:12B2 1-ECSDAX It01CATING LIGHT DSL 2-2 AUTO LOAD SEQ FAILS CCt4 TACT 113 IN C0t1 TROL R00ft FAILS OPEN 22-6.-Z G07312B3 60-EGSDA FAILS PERIOJ1C TEST DSL 2-2 AUTO LOAD SEQ FAILS 22-6.-Z G0741003 3-EGSBAX PERIODIC TEST DSL 2-2 AUTO LCAD SEQ FAILS CONTACT 22S FAILS OPEN 20-6.-Z G07510B3 1-EGSCA CONTACT 7 i'ERICDIC TEST DSL 2 2 AUTO LOAD SEQ FAILS 22-6.-Q FAILS OPEll 2-6.-AH G0771083 3-EGSBAX COIL PERIODIC TEST DSL 2-2 AUTO LCAD SEQ FAILS FAILS 22-6.-AM G07812B3 SCS-EGFDA PERIDDIC TEST DSL 2-2 AUTO LOAD SEQ FAILS CONTACT 79 NO ACT SIGNAL l t l l lF AILUPE IIDDES Ato EFFECTS i 1ALYSIS l l l l l l l 1l l EllGRO SAFETY FEATURES LOAD SEQUEH l 141 131 101 111 1 l l l f I l1 l l l J.O. 12241 F t'E A-22-6 .1/ 2 SH 6l

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22-6.-AB G09012B3 362-EGSDA FAILS PERIODIC TEST DSL 2-2 AUTO LOAD SEQ FAILS

! 22-6.-AB G09112B3 3-EGSBAX PERIODIC TEST DSL 2-2 AUTO LOAD SEQ FAILS

! CONTACT 115 FAILS OPEN I 22-6.-AD G0921283 1-EGSBA PERIODIC TEST DSL 2-2 AUTC LOA 3 SEQ FAILS CONTACT 11 FAILS OPEH j 22-6.-S G09412B3 462-EG2BAX COIL PERIODIC TEST DSL 2-2 AUTO LOAD SEQ FAILS FAILS

! I i l l (FAILUPE tt03ES Ato EFFECTS ANALYSIS l l l l l l l l l l ENGRD SAFETY FEATURES LOAD SEQUEH l 141 13I 121 111 I i i I I I I I I I I J.O. 12241 FifEA-22-6.1/2 SH 7l

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