ML20095H999
| ML20095H999 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/31/1984 |
| From: | Public Service Enterprise Group |
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| Shared Package | |
| ML20095H943 | List: |
| References | |
| NUDOCS 8408290149 | |
| Download: ML20095H999 (53) | |
Text
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4 C.0MMON POWER / CONTROL SYSTLY FAILURES EVALUATION REPORT AUGUST 1984 .
, PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CRFEK GENERATING STATION
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CONTENTS PARAGRAPH PAGE 1.0 OBJECTIVES 3
2.0 CONCLUSION
S 3 3.0 ANALYSIS METHODOLOGY 3 3.1 Define Control Systems 4 3.2 Identify Loads 4 3.3 Define Bus Structure 5 3.4 Determine Critical Loads 6 3.5 Summarize Critical Loads 6 3.6 Analyze Combined Effects 6 3.7 Compare Results to Hope Creek Generating 6 Station FSAR Chapter 15 3.8 Additional Single Failure in a Mitigating System 6 3.9 Analyze Exceptions 6 3.10 Modify / Augment Chapter 15 6 4.0 BUS LOSS
SUMMARY
RESULTS AND CHAPTER 15 COMPARISON 8 APPENDIX A Bus Tables A-1 APPENDIX B Eli6:ination Criteria B-1 APPENDIX C Load Tables C-1
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j ILLUSTRATIONS FIGURE PAGE 1 AC POWER BUSES 8 2 ( AC POWER BUSES 9
- 3. DC POWER BUSES I 10
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C00990N POWER / CONTROL SYSTEMS FAILURES EVALUATION REPORT FOR THE HOPE CREEK GENERATING STATION 1.0 OBJECTIVES The objectives of this evaluation report are as follows:
i
- Perform an analysis in response to the NRC concern stated in FSAR question 421.51 that the failures of power sources, which provide power or electrical signals to multiple control systems, could result in consequences outside the bounds of the Hope Creek Generating Station Final Safety Analysis Report (FSAR) Chapter 15 analyses and would require actions or responses beyond the capability of operators or safety systems.
e Provide a positive demonstration that adequate review and analysis has been performed to ensure that despite such failures the conse-quences of the FSAR Chapter 15 analyses are bounding, and no conse-I quences beyond the capability of operators or safety systems would result.
e Provide additional analyses necessary to ensure the effects of the 4 worst-case limiting event are bounded by those of the events analyzed
, in FSAR Chapter 15 with the assumption that there is a single active
! failure in a safety system required to mitigate the effects of the event.
l
2.0 CONCLUSION
S I
l The information contained herein, supplemented by the existing FSAR l Chapter 15 transient analyses, documents an evaluation of the Hope Creek Generating Station for control systems interaction by electrical means.
The conclusion of this evaluation is that the limits of minimum critical l power ratio (MCPR), peak vessel and main steaaline pressures, and peak i fuel cladding temperature for the expected operational occurrence category .
of events would not be exceeded as a result
- of common power source fail-ures. Althcush transient category events have been postulated as a result of this study, the net effects have been positively determined to be less severe than and bounded by the events in Chapter 15. It should be noted i that this study used the event-consequence logic of the Chapter 15 analy-
! sis, but it started the logic chain from a specific source (e.g., a single bus failure) rather than a system condition (e.g. , feedwater runout). By I approaching the study in this meaner, a great deal of confidence can be i placed in the study conclusions. The soundness of the total plant design
] is demonstrated by its being tolerant of these effects.
l 3.0 ANALYSIS METHODOLOGY I
- To achieve the objectives discussed in Section 1, a comprehensive method-
- ology was developed for the analysis of the control systems capable of l affecting reactor water level, pressure or power in the Hope Creek Gener-i ating Station (HCGS),
l i
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. 1 The electrical control systems failure analysis was conducted in the following manner:
ACTIVITY
- Define Control Systems
- Identify Loads .
- Define Bus Structures ,
- Determine Critical Loads ;
- Summarize Critical Loads
- Analyze Combined Effects
- Compare Results to Chapter 15 /
- Additional Single Failure in a Mitigating Safety System
- Analyze Exceptions
- Modify / Augment Chapter 15 3.1 DEFINE CONTROL SYSTEMS s
The scope of control systems to be analyzed was established by first compiling a ' complete list of the ' Hope Creek Generating Station (HCGS) systems and subsystems. Next, the list was reviewed to confine the analysis to only those systems with the potential to affect reactor pressure vessel (RPV) pressure, water level, or power.
)
In order to ensure that all necessary systems were considered, certain elimination criteria, which documented the justification for not analyzing that system further (see Appendix B), were established. If there were any uncertainty as to whether or not a system met the criteria, it was retained for further analysis. Those systems that met the criteria for elimination were removed from the complete system list, leaving the following list of control systems for analysis.
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System Designation l MPL/M-System # System (B21) Nuclear Boiler Process Instrumentation (B21) Jet Pump Instrumentation -
(B21) Steam Leak Detection System (B31) Reactor Recirculation System (C11) Control Rod Drive Hydraulic / Reactor Manual Control Systems (C32) Feedwater Control System (C51) Neutron Monitoring System (D11) Process Radiation Monitoring System-(G33) Reactor Water Cleanup System (M1) Main Steam System (Turbine-Generator System)
(M2) Extraction Steam System (M3/M4) Vents, Drains and Heaters System (MS) Condensate System (M6) Feedwater System (M7) Condenser Air Removal System (M9) Circulating Water System (M10) Service Water System (M11/M12) Safety Auxiliaries Cooling System (M13) Reactor Auxiliaries Cooling System (M14) Turbine Auxiliaries Cooling System (M15) Compressed Air System (M16) Condensate Demineralizer System (M19) Lube Oil System (M25) Plant Leak Detection System (H26) Radiological Monitoring System (M28) Generator Gas Control System (M29) Turbine Sealing Steam System (M31) Reactor Feed Pump Turbine Steam System (M57) Containment Atmosphere Control System (M59) Primary Containment Instrument Gas System (M69/M70) Gaseous Radwaste System (Offgas System)
(M71) Liquid N2 for Purge and Containment Inerting System (M82) Turbine Building Supply and Exhaust Vent System (M83/M84) Reactor Building Supply and Exhaust Vent System (M86) Drywell Vent Control System (M87) Chilled Water System (M89) Auxiliary Building Control Area Vent Control
(
(M90) Auxiliary Building Control Area Chilled Water System 3.2 IDENTIFY LOADS A set of system bus-load tables were assembled, each providing information on the loads. These tables identified all electrical loads of the control systems defined by the methodology described in Paragraph 3.0. Each load was listed with its power bus source, circuit description, and failure
! mode on power loss with primary and secondary effects. Samples of load j tables are included in Appendix A.
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e 3.3 DEFINE BUS STRUCTURE Potential sources for control system interaction by electrical means were established by formulating the bus structure as follows: Bus trees (see Figures 1, 2 and 3) were constructed using one-line diagram information to show power distribution from the highest level not previously analyzed (the highest level previously analyzed is the loss of offsite power) down to the lowest level of plant distribution (motor control centers, instru-ment busses, etc.).
3.4 DETERMINE CRITICAL LOADS The loads with the potential for initiating events affecting RPV pressure, water level, and power were identified. The elimination criteria estab-lished earlier for the system list, as defined in Appendix B, were used in the component review to determine which individual loads required further consideration or could be deleted from the analysis. If there was any uncertainty as to whether or not a - load met the elimination criteria, it was retained for further analysis. The numerical code associated with an elimination criterion was assigned to each eliminated load in the load tables discussed in Paragraph 3.2.
3.5 SUMMARIZE CRITICAL LOADS Noncritical loads were deleted from the load tables, and the remaining loads were grouped together by their common power busses. These tables are shown in Appendix C.
The primary effect column in Appendix C lists the component failure effect and resulting component failures that would lead to the secondary effect.
The secondary effect is the - final macro failure that could effect RPV pressure, water level or power. In some cases there is no effect.
Because this analysis reviews all interactions that potentially could result in a previously unanalyzed transient, no-effect failures indicate the soundness of plant design.
3.6 ANALYZE COMBINED EFFECTS This portion of the analysis provided the basis for determining the worst case combinations of load and system failures that are credible events considering their interconnection by power distribution. Using the combined effects of a failure at the lowest level bus as a starting point, the next higher bus was postulated to fail, and the total effects at that level were analyzed. This process was continued up to the highest bus level. The combined effects at the lowest bus level are included in the Appendix C tables. Worst case effects at the higher levels are summarized i in Section 4. The combined effects at intermediate bus levels less severe than their associated higher bus combined effects were analyzed but not ,
included in Section 4. The more severe intermediate level combined l effects analyses are formally represented along with their associated higher bus analysis.
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l E_______________. __ .,
3.7 COMPARE RESULTS TO FSAR CHAPTER 15 .
The. consequences of all postulated control system interaction events !
initiated by electrical means, were then compared to the consequences of i the events analyses described in Chapter 15 of the FSAR. A review of the information in the Appendix C tables was conducted in the course of developing the bus summaries of Section 4. At each bus level of the combined effects analysis, the review evaluated the effects as to whether they would be bounded by the consequences of a specific Chapter 15 event analysis. Section 4 includes these evaluations and considers the worst case effects.
3.8 ADDITIONAL SINGLE FAILURE IN A MIIIGATING SAFETY SYSTEM The consequences of the postulated common bus loss events, detailed in Section 4, are all bounded by the consequences of Chapter 15 transients.
For each bounded bus-loss event, the mitigating safety systems were identified according to the FSAR Chapter 15 event description. One additional worst case single failure in a mitigating safety system was then postulated for each event, taking into consideration the bus loss effects. No bus loss was identified wherein an additional single failure in a mitigating safety system would cause the failure of that system to perform its intended safety function.
An an example of this process, consider AC Bus 10A101 from Section 4.0.
The Chapter 15 bounding event is the Loss of Feedwater Flow, described in HCGS FSAR 15.2.7. The event scenario includes a vessel low water level (L3) scram trip from the ReSctor Protection System (RPS), which performs a mitigating function. The loss of AC Bus 10A101 together with an addi-tional single failure in the RPS was postulated. The RPS would not be prohibited from inserting the control rods, a function required for ,
mitigating the effects of the transient. This process was followed for each mitigating safety system identified for the Loss of Feedwater Flow event. Each mitigating safety system in the Loss of Feedwater Flow event scenario was able to perform its intended safety function considering the bus loss and an additional single failure.
The above process was repeated for each identified bounding FSAR Chap-ter 15 event.
3.9 ANALYZE EXCEPTIONS No failure scenarios were identified with consequences that were not directly bounded by those of the events analyses described in FSAR Chapter 15.
3.10 MODIFY CHAPTER 15 IF NECESSARY As a result of this analysis, no modification of FSAR Chapter 15 was found 1
to be necessary.
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4,0 BUS LOSS
SUMMARY
RESULTS AND CHAPTER 15 COMPARISONS AC BUS 10A101 Loss of this bus would result in the following effects:
- 1) Secondary condensate pumps A, B and C recirculation valves will open.
l The compressed air compressors are inoperative.
2)
- 3) Secondary condensate pump B stops.
The opening of secondary condensate pumps recirculation valves A, B and C and the stopping of the secondary condensate pump would result in a trip ;
of reactor feedwater turbines A, B and C on low suction pressure. This j would cause a reactor scram on low water 1Evel and the consequences of l this. event are bounded by the Loss of Feedwater Flow (FSAR 15.2.7) event. I An additional- single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.2.7.
Loss of an intermediate bus would result in a loss of compressed air. The consequences of this event are bounded by the Loss of Compressed Air event (FSAR 15.9.6, event 8). This event is much slower than the loss of feedwater flow.
Loss of any other intermediate busses ancillary to AC bus 10A101 have combined effects events with no consequences more severe than those discussed for higher bt, 10A101.
AC BUS 10A102 Loss of this bus would result in the following effects:
- 1) Secondary condensate pump A recirculation valve will open.
- 2) Secondary condensate pumps A and C and primary condensate pump C stop.
3.' Feedwater heater train A is isolated, and the extraction steam is dumped to condenser A.
The effects of this bus loss are bounded by the Loss of Feedwater Flow (FSAR 15.2.7) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.2.7.
Loss of intermediate bus will isolate feedwater heater train A and cause less than a 100'F reduction in feedwater temperature. The consequences of this event are bounded by the Loss of Feedwater Heating (FSAR 15.1.1) event. An additional single failure in a mitigating safety system also would result in a bounded event, as di::ssaed in FSAR 15.2.7.
i Loss of an intermediate bus would result in runback of recirculation pump B due to secondary condensate pump C stopping, but recirculation pump A would be locked at last speed. The consequences of this event are less 13-2135 8-
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- severe than the One Recirculation Pump Trip (FSAR 15.3.1) event. An
, additional single failure in a mitigating safety system also would result
. in a bounded event, as discussed in FSAR 15.3.1.
Failure of any other intermediate busses ancillary to AC bus 10A102 would have combined effects events with no consequences more severe than those discussed for higher bus 10A102.
ACBUS10Alb3 l
Loss of this bus would result in a main turbine trip. The consequences of this event are bounded by the Turbine Trip - Bypass On (FSAR 15.2.3) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.2.3.
AC BUS 10A104 Loss of this bus would result in recirculation runback when secondary condensate pump C stops. The consequences of this event are less severe than the ,0ne Recirculation Pump Trip (FSAR 15.3.1) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.3.1.
AC BUS 10A501 Loss of this bus would result in recirculation runback due ta the circu-lating water pumps IBP501 and IDP501 stopping. The consequences of this event are less severe than the One Recirculation Pump Trip (}'SAR 15.3.1) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.3.1.
AC BUS 10A502 Loss of this bus would result in recirculation runback due to the circu-lating water pumps A and C stopping. The consequences of this event are less severe than the One Recirculation Pump Trip (FSAR 15.3.1) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.3.1.
AC BUS 10A110 Loss of this bus would result in a recirculation pump A trip with runback j of recirculation pump B. The consequences of this event are bounded by the Two Recirculation Pumps Trip (FSAR 15.3.1) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.3.1.
l AC BUS 10A120 Loss of this bus would result in recirculation pump B trip with runback of recirculation pump A. The consequences of this event are bounded by the Two Recirculation Pumps Trip (FSAR 15.3.1) event. An additional single failure in a mitigating safety system also would result in a bounded event, as siiscussed in FSAR 15.3.1.
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AC BUS 10A401 Loss of this bus would result in the following effects:
- 1) A main turbine trip.
- 2) The opening of the turbine bypass valves.
- 3) Trips of the primary condensate pumps A, B and C on condenser hotwell low-low level.
l l
4)
A trip of feedwater turbine A with the recirculation runback circuits disabled. ,
The consequences of the loss of this bus are bounded by the Turbine Trip -
Bypass On (FSAR 15.2.3) event. An additional single failure in a miti-gating safety system also would result in a bounded event, as discussed in FSAR 15.2.3.
The loss of an intermediate bus would result in a trip of feedwater turbines A, B and C, causing reactor scram on low water level. The consequences of this event are bounded by the Loss of All Feedwater Flow (FSAR 15.2.7) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.2.7.
Loss of any other intermediate busses ancillary to AC bus 10A401 would have combined effects events with no consequences more severe than those discussed for AC bus 10A401.
AC BUS 10A402 Loss of this bus would result in the following effects:
- 1) A main turbine trip.
The consequences of the loss of this bus are bounded by the Turbine Trip -
Bypass On (FSAR 15.2.3) event. An additional single failure in a miti-gating safety system also would result in a bounded event, as discussed in FSAR 15.2.3.
Loss of an intermediate bus would result in a recirculation runback. The consequences of this event are bounded by the One Recirculation Pump Trip (FSAR 15.3.1) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.3.1.
Loss of any other intermediate busses ancillary to AC bus 10A402 would have combined effects events with no consequences more severe than those discussed for AC bus 10A402.
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AC BUS 10A403 Loss of this bus would result in the following effects:
- 1) A main turbine _ trip.
- 2) Trip reactor feedwater turbine C.
The consequences of the loss of this bus are bounded by the Turbine Trip -
Bypass On (FSAR 15.2.3) event. An additional single failure in. a miti-gating safety system also would result in a bounded event, as discussed in FSAR 15.2.3.
Loss of an intermediate bus would result in a recirculation runback. The ,
consequences of this event are bounded by the One Recirculation Pumps Trip !
(FSAR 15.3.1) event. An additional single failure in a mitigating safety l system also would result in a bounded event, as discussed in FSAR 15.3.1. l Loss of any other intermediate busses ancillary to AC bus 10A403 would have combined effects with no consequences more severe thac those dis-cussed for AC bus 10A403.
AC BUS 10A404 Due to disabling of the turbine trip solenoid, loss of this bus would result in a failure to trip the main turbine on receipt of the actual trip signal. There are no consequences due to loss of this bus.
Failure of ancillary intermediate busses would result in and could have no more severe effects than those of a main turbine trip. The consequences of a main turbine trip are bounded by the Turbine Trip - Bypass On (FSAR 15.2.3) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.2.3.
DC BUS 10D470 Loss of this bus would result in the following effects:
- 1) A trip of reactor feedwater turbine C.
- 2) Increased flow of the reactor feedwater turbines A and B.
- 3) Obviation of the main turbine trip by the disabling of the turbine trip solenoid.
The feedwater turbine C trip and increased flow demand to feedwater pump turbine A and B would result in a reactor scram on low water level. The i -
consequences of this event are bounded by the Loss of Feedwater Flow (FSAR 15.2.7) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.2.7.
Loss of an intermediate bus would result in main turbine trip and reactor l scram on high water level (bypass valves open). The consequences of this i event are bounded by the Feedwater Controller Failure - Maximum Demand I'
l t
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(FSAR 15.1.2) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.1.2.
Loss of any_ other intermediate busses ancillary to DC bus 10D470 would have combined effects that have no consequences more severe than those discussed for DC bus 10D470.
DC BUS 10D480 Loss of this bus would result in a trip of the reactor feedwater turbine.
The consequences of this event are bounded by the Two Recirculation Pumps Trip (FSAR 15.3.1) event. An additional single failure in a mitigating safety system also would result in a bounded event, as discussed in FSAR 15.3.1.
Loss of an intermediate bus would result in a main turbine trip on high water level. The consequences of this event are bounded by the Feedwater Controller Failure - Maximum Demand (FSAR 15.1.2) event. An additional single failure in a mitigating safety system ' also would result in a bounded event, as discussed in FSAR 15.1.2.
Loss of any other intermediate busses ancillary to DC bus 10D480 would have combined effects that have no consequences more severe than those discussed for DC bus 10D470, 13-2135 12
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i AC POWER BUSES 4
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ALT PWR ALT PWR ALT PWR ALT PWR IDD483 IBD483 icd 483 IAD483 18D318 IDD318 IAD318 ICD 318 FIGURE 3 '
D.C. POWER BUSES
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AerEND!X A BUS TABLE 3 i I I I I I I I rhonCT Nort CREEE l STSTEn CONThots INSTR m MTATION imADS
" (" ' ^"8 l AND
- l EtnCTS WinIN SYSTEn l l EFFECT (WITNIN 3e usN.)
a REACn N WATERonER si STSTsnS m , ,l AND INeurs REC I "DEsChirTION) 8 1 , EnECTS m OnER , g
, g rRINCirAL FUNCTION g DIE To bus BASS SYSTEnS NESSURE AND M E MECT OF INrVT g g g g SYSTEn IEEDWATER CONTm0L l l l l 1 l l l 1 REACTOR NicN uvEL l ThirS RFr TURetNE AND l NONE - ONE MDItE NIGN I NONE l D l NONE I LEVEL SBCNAL Fpon B21 - l-
- 1 TRIP "s" (C32-N004s) I nAIN Tuks:NE ON RECEarT I LEVEL SIGNAL REQUIRED 1 l l l ND EFFECT xFnk l l OF 2/3 ("A". "B", "C") l l l l l RRCS SIGNAL - NO EFFECT 1 1
{;
l l NIGN LEVEL SIGNALS l l l l l sus 10D4s0 1 -
l l l 1 l l l l SRU-6 (C32-NollB) l !
l rohERS DIFF rRESS InTRS I PER TEtzCON 4/87/84 l NONE l A l FEEDWATER FIEW IN- l l <
MCC I 1 FoR FEED runr "a* l WITN C.W. nA: AN l l l CREASES WNICN INCREASES 1 l I I DISCNAact, FEEDWATER l "sNCREASE FLOW" 5IGNAL l l WATER livEL, CDLIArSES 1 1 l ]
PANEL IDD31s (82SVde) l (C32-N002a) l FLOW "B" INIIT, AND l WILL BE SENT TO Tile 1 l 1 ColtE VOIDS, INCarasse i I ,
I (C32-N004s/E6248) i REACTOR LEVEL "a" 1 FEED runr$ CONTMOL 1 1 u r0NER AND STEAM FIDW l l '
CIRCu 7 I i 1 1 1 1: 1 1 l l l 501 FImW INDICATION i NONE ID ' IIONE I I I i l REsuLTS IN No EFFECT l l l l l DWc. No. REV. l l 1 ON RECORC CAVITATION 1 1 l l l l l l INTERinCE l l ,1 l
AE I l
1 l l l d l 1 1 I I NOME - ONE MORE MIGN l NONE i D 1 NONE I l SN 1 l l LEVEL SIGNAL REQUIRED 1 l l l l 1 l l 1 l l l l CE 729E629 10 IED l(C32-N017) 1 INDICATES WIDE RANGE I NONE l NONE l D l NONE . I IIONE I l l 1 l l 1 l 1 79tE404AC 4 t/D 1 l l l l l l l 1 l l 1 1 1 1 1 ConnENTS: l l l l l l l l l l 1 l l l 1 l l l 1 l l l l
1 l l l l 1 l 1 l l l 1 I i l l 1 REsruNsists ENciNtER: 1 I i l 1 l l l ED SCNRuLL l l 1 1 1 1 1 l l l l 1 l l l l un l l l l l l l l 4/12/s4 1 l ll l l l l l l 1 l l REVIEWED BY: l l 1 1 i 1
l 1 l l 1 R. vasto CODE CLASSIFICATION FOR EFFECTS ON RF. ACTOR PARAnETERS:
"A" - If9EDI ATE (<l nlN.) AND DIRECT "B" - InnEDIATE RUT INDIRECT "C" - EFFECT IS DELAYF.D "D" - NO EFFECT ON REACTOR PARAnETERS (c30 MIN.)
A-1 4
- . a APPENDIE A RUS TARLES l sTSTEn CONTROLS AND I I I' I C' I I I INsTRUMNTATION laADS I I 1 I EFFECT (WITNIN 30 plN.) 0 INPUTS RECEIVED FROM I
I ON RuS (nrL # AND I h l
- I O; ON RsACTOR WAnR IzvEL, 0 OTNER SYSTEMS MS I
EnECTS vlTNIN STstEn l E m CTS ON oTNER I g ymream8 AND FOMR rRnJECT NortCMEE I!DEscalPTION) PRINCIPAL FUNCTION DUE 70 RUS IDSS SYSTEMg lDl l EFFECT OF INFUT l TE. AF. AC-102 FEEINATER 1, TEEDWATER/enemm2TE l l l l l l MATER VENT AND DRAls 11 rnemmaTE TRAIN *A* li MATER 12 VEL CON"BOL l 'l l l l l ll San 0TE CONTROL PANEL l li l l l l l_
FEEDWATER MATER IIVEL VALVES FAIL CLOSED ll CAUSES SLIQff C SLIONT IDES IN FEED-BUS l l NORMAL CONTROL I DECMASE IN l l WATER. M ATING CAUSES i l l l LT/LIC/LV-1464A, FEEDWATER M ATING l SLIGNT INCMASE IN l 10R ul023 l l LT/LIC/LV-1506A, l NEUTRON FLUE / REACTOR l NCC l I LT/LIC/LV-15144, FOMR I l Wat htsh u hs) l l LT/LIC/LV-1523A, i
lI i
!i l pangt noglo3 I l LT/LIC/LV-1532A ,1 ll l l l l l l CIRCUIT l l FREDCATER MATER 12 VEL ll VALVES FAIL OPEN 1, NOME l'D I l l l l RIGN 12 VEL CONTROL ll ll 11 ll l l l l LT/LIC/LV-1451A, 11 ll li I, l ll DWG No, MV. l l LT/L8C/LV-1501A, 11 ( i l l LT/LIC/LV-1583A, l l l l LT/LIC/LV-1521A, l l l AE E-1410-0 3 l l LT/LIC/LV-15314 l l ll l ,
== "- '
l l l l 1 og l l l l l ll 1, l l l l i I 1 l l l 11 l 1: ll
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l l l 1 1 I l l l l I ! l l j l l l ll l II l MsFONSIBIs ENalNEER: 1 1 I l ll 1 c~
l l l 'li l, . 1 un: 1 I l l l l I l 3 I 5/l/84 1 l l REVIEM D BT:
- 8. CNEN CODE CLASSIFICATION FOR EFFECTS ON REACTOR PARAfETERS:
"A" - IPDEDIATE (<l plN.) AND DIRECT
- B" - IP9EDIATE RUT INDIRECT "C" - EFFECT IS DELATED g.g *D" - NO EFFECT ON REACTOR PARADETERS (<30 NIN.)
APPENDIX B CRITERIA FOR ELIMINATION OF SYSTEMS AND COMPONENTS 0F SYSTEMS FROM THE CONTROL SYSTEMS FAILURE ANALYSIS l Elimination Criterion
- Basis N1 Nonelectrical components (i.e., mechanical and structural components); however, associated functions that are electrically controlled or controlling (including signal inputs to electrical systems) may be relevant to the analysis. N1 examples are
)
piping, tanks, turbines, etc.
N2 Instrumentation with no direct or indirect controi'ing function or passive input (such as a permissive signal) into control logic. Instrumentation and other dedicated inputs to the process computer, as well as the computer itself, are excluded.
Operator actions as a result of indications are not considered control functions for the control systems failure analysis.
N3 Control systems and controlled components (i.e., pumps, valves)^
that have no direct or indirect interaction with reactor opera-tion / parameters. Examples are communications, most unit heaters and controls, lighting controls, ventilation control systems for exterior building, machine shop equipment, refueling or main-tenance equipment controls, etc.
N4 Control systems and controlled components (i.e., pumps, valves) i that do interact or interface with reactor operating systems but cannot affect the reactor parameters (water level, pressure or i reactivity) either directly or indirectly.
N5 ' Systems or components that cannot affect reactor parameters within 30 minutes of the loss of any power bus or combination thereof.
N6 Systems that are not used during normal power operation. For example, start-up, shutdown or refueling systems not used during normal operation may be eliminated.
N7 Electrical components involved in distribution, tranformation or interruption of power; however, controls for these components mey need to be considered if loss of such control power may lead to failure of other electrical busses.
l N8 Safety systems, except for their response to conditions brought about by control systems failures. Example: A level 3 scram will be assumed for a loss-of-feedwater event.
- In some cases, more than one of these criteria may apply.
l l
B-1 13-2133
l l
9 -o APPENDIX B CRITERIA FOR ELIMINATION OF SYSTEMS AND COMPONENTS I
. OF SYSTEMS FROM THE CONTROL SYSTEMS FAILURE ANALYSIS I GE I l RELATED I ~MPL I ELIMINATION I P&ID NO. CRITERION SYSTEM / SUBSYSTEMS 1 l l I. REACTOR SYSTEMS I I I M42 i B21 1 * 'l Nuclear Boiler Vessel Instrumentation i I I M25 l B21 1
- I Steam Leak Detection System
. I I l M43 I B31 1
- I Reactor Recirculation System I I l-M26 I D11 1
- I Process Radiation Monitoring System i I I M44/M45 1 G33 l
- I Reactor Water Cleanup System (RWCU) l I I M46/M47 l C11 l
- I Control Rod Drive Hydraulics System I I l M48 i C41 1 N8/N6 i Standby Liquid Control System (SLC) i I I M49/M50 I E51 1 N8/N6 l Reactor Core Isolation Cooling (RCIC) l I l M51 1 E21 1 N8/N6 l Residual Heat Removal System (RHR) 1 I I M52 1 E21 i N8/N6 i Core Spray System (CS) l I I M55/M56 l E41 1 N8/N6 i High Pressure Cooling Injection (HPCI) l I l l C71 I N8 I Reactor Protection System (RPS) i 1 1 M41 i B21 1 N8 i Automatic Depressurization System (ADS) l I l M42 i B21 1
- I Jet Pump Instrumentation System I I I M41 1 B21 I N8 I Nuclear Steam Supply Shutoff System i I I Various l I N8 I Primary Containment Isolation System I I I l C22 i N8 l Redundant' Reactivity Control System i I I M72 l l N8/N6 l Main Steam Isolation Valve Sealing System i I I M53/M54 l j N3 l Fuel Pool Cooling & Torus Water Cleanup I I l M57 l l l Containment Atmosphere Control l I I M58 I I N8/N6 i Containment Hydrogen Recombination System I I I
( M57 l 1 N1 1 Primary Containment Vacuum Relief System l' l l l l l l CSI I
- I Neutron Monitoring System I I I
- To be included in analysis.
B-2 13-2133
a O APPENDIX B CRITERIA FOR ELIMINATION OF SYSTEMS AND COMPONENTS
. OF SYSTEMS FROM THE CONTROL SYSTEMS FAILURE ANALYSIS I E I I .
RELATED l MPL I ELIMINATION I P&ID NO. CRITERION SYSTEM / SUBSYSTEMS M41 1 1 N3 l Safety Relief Valve Position Indication l- 1 I I C11 1
- I Reactor Manual Control System i I I M59 I I
- I Primary Containment Instrument Gas System I I I Various l l N6/N8 I Remote Shutdown Systez l I I M38 l l N6 l Post Accident Liquid & Gas Sampling i I I
- To be included in analysis.
l B-3 l 13-2133 o
l - --. . ._
APPENDIX B CRITERIA FOR ELIMINATION OF SYSTEMS AND COMPONENTS
. OF SYSTEMS FROM THE CONTROL SYSTEMS FAILURE ANALYSIS I E l l RELATED l MPL l ELIMINATION l P&ID NO. CRITERION SYSTEM / SUBSYSTEMS l l 1 II. TURBINE / GENERATOR SYSTEM i I l M1 l l
- l Main Steam System i I I I I
- l Main Turbine System l l l l l
- l Turbine Control System I l l M2 l l
- I Extraction Steam System i 1 1 M3/M4 l l
- I Heater Vent & Drain System i 1 I M5 l l *- l Condensate System i I I M6 l l
- I Feedwater System I ! l l C32 I
- l Feedwater Control System l l l M7 l l
- I Condenser Air Removal System I I I M8 l l N5 I Condensate & Refueling Water Storage & Transfer I I I M16 I I
- I Condensate Demineralizer I I I M19 l 1
- I Lube Oil System I l l M29 l l
- I Turbine Sealing Steam i I I M31 l l
- l Reactor Feed Pump Turbine Steam System I I I M9 l l
- I Circulating Water System I I i 1 1
- I Generator System I I I I I
- I Generator Excitation System l l l M28 l l
- I Generator Gas Control System l l l
- To be included in analysis.
, B-4 13-2133
APPENDIX B CRITERIA FOR ELIMINATION OF SYSTEMS AND COMPONENTS l 0F SYSTEMS FROM THE CONTROL SYSTEMS FAILURE ANALYSIS I E I I RELATED l MPL l ELIMINATION I P&ID NO. CRITERION SYSTEM / SUBSYSTEMS I l l III. AUXILIARY SYSTEMS I l l l l N8/N6 1 Diesel Generator System I I I M30 l I N8/N6_ l Diesel Engine Auxiliary System i I I M20 l l N3/N6 I Auxiliary Boiler Fuel Oil System I I I M21 l l N3/N6 l Auxiliary Steam System I I I 4
M10 l I
- I Service Water System i I I M11 l l
- l Safety Aux Coo.'.ing (SAC), Reactor Building i I I M12 l l
- I Safety Aux Cooling, Aux Building I I I M13 l l
- I Reactor Auxiliary Cooling (RAC) l I I M14 l l
- l Turbine Auxiliary Cooling i I I M24 I I N5 I Circulation & Service Water Hypochlorination &
I l l CW Acid Injection I I I MIS l l
- l Compressed Air System i I I M18 I I N4 I Demineralizer Water Makeup Storage & Transfer I I l M22 l l N3 I Fire Protection -
I I I M23 l l N4 I Process Sampling i l l M25 i B21 1
- I Plant Leak Detection System
- i I I M26 l l
- I Radiological Monitoring System i I I M33 I I N3 I Low Volume & Oily Wastewater Treatment i I I M17 I I N3 i Fresh Water Supply i I I M71 1 I
- I Liquid N 2f r Purge & Containment Inerting i I I M94/M97 I I N3 i Building Drainage System
. I I I l
M99 I I N6 l Primary Containment Leak Testing I I I I I N3 l Site Environs Radiation Monitoring i I I M98 I I N3 1 Domestic Water System
!. I I I I
- To be included in analysis.
i B-5 l 13-2133
o .
APPENDIX B CRITERIA FOR ELIMINATION OF SYSTEMS AND COMPONENTS 0F SYSTEMS FROM THE CONTROL SYSTEMS FAILURE ANALYSIS I a l l RELATED I MPL I ELIMINATION 1 P&ID NO. CRITERION SYSTEM / SUBSYSTEMS I I I IV. HEATING, VENTILATION, AIR CONDITION AND l 1 l COOLING (HVAC) SYSTEMS I I I M36/M37 l l N3 l Guard House HVAC System l l l M73/M74 1 1 N3 l Admin. Building & Warehouse HVAC System l l l M82 l l
- l Turbine Building Supply & Exhaust Vent System l l 1 M83/M84 l l
- l Reactor Building Supply & Exhaust Vent System I I l (FRVS) l l l M86 l l
- 1 Drywell Vent Control System l l 1 M88 l l N3 l Auxiliary Bldg-Diesel Area Vent Control System I I l M89 l l
- I Auxiliary Bldg-Control Area Vent Control System I I I l M92 l l N3 1 Auxiliary Bldg - RW Area Vent Control System i I I M93 l 1 N3 1 Aux Bldg-Service Area & TSC Vent Control System l l l M87 1 1
- I Chilled Water System i I I M90 l l
- l Aux Bldg - Control Area Chilled Water System l l l M95 l l N3 1 Misc Structure & Yard Bldgs Vent Control Systems 1 I I M96 l l N3 l Plant Heating' System
- To be inc8uded in analysis.
B-6 13-2133
o t APPENDIX B CRITERIA FOR ELIMINATION OF SYSTEMS AND COMPONENTS 0F SYSTEMS FROM THE CONTROL SYSTEMS FAILURE ANALYSIS l GE l l RELATED I MPL l ELIMINATION l
, P&ID No. CRITERION SYSTEM / SUBSYSTEMS l l l V. RADWASTE SYSTEM l l l M69/M70 l l
- l Gaseous Radwaste System l l 1 M61/M62 l l N3 i Liquid Radwaste System M63/M64 l l l .
M65 l l l l 1 l M66/M67 l l N3 l Solid Radwaste System M68 l l l l l l l l l l 1 1 I I l l
- To be included in analysis.
B-7 13-2133 )
l 1
o .
APPENDIX B CRITERIA FOR ELIMINATION OF SYSTEMS AND COMPONENTS
- 0F SYSTEMS FROM THE CONTROL SYSTEMS FAILURE ANALYSIS I E I I REIATED l HPL'I ELIMINATION I P&ID NO. CRITERION SYSTEM / SUBSYSTEMS I l
l l- l VI. ELECTRICAL SYSTEMS I I I l l N3 I Communication System i I I I I N3 i Lighting System i I I I I
l
- To be included in analysis.
l 13-2133 i
I c
APPENDIX C j
( NOPE CREEE CONTROL CorBt0N POWER FAILURE ANALYSIS I
SECONDARY EFFECT COMBIM D EFMCTS SYSTEM COMPOWElfT DESCRIPTION l PRIMARY EFRCT l l i l l 1 i 1_ l I l FOR COMBIMD EFFECTS, l l CMILED WATER l 1CEI11 WAm CHILMR l Altro START CNILER l NONE l l S E SECTION 4 l l l l l STANDING BY (OTHER TWO I i l RuMNING) l l l 1- 1 I I I lC t l I I Ir STANDBY CHILMR NOT I l l l 1 I <~ l AVAIIABM INCREASE IN I l l l l l
lS l I I 1
I DRYW LL PRESSURE l
l l
l l 1 l l l l l Ir NO CultuD WATER, l l l l l l .
l l 1 l REACTOR SCRAM AND MPCI l l l l l INITIATION ON MIGH l 1 1 l DRYWELL PRESSURE I l l l l l l 1 1 l l l 1 l l l l I l CHIL11D WATER l 1 API 61 CHILLED WATER l l l l l l l l l IF ANY ESSENTIAL BUS l START PlatP STANDING BY l N05 l NOH I 1 l 1 (10A410, 10A402, l (OTHER RUNNING) l l l l 1 10A403, 10A404) IDST l l l l l 1 l l l AtrF0 SWITCM TO REACTOR l l l 1 l
l AUXILIARY COOLING l l l l l l l l l l l 1 SYSTEM (RACS) 1 1 I I l 1 1 l AC RECIRC LUBE OIL l PLtiPS STOP 1 NONE l l l l RECIRCULATION SYSTEM l l l l l l l PUMPS Al AND B1 i i Atr!O TRANSFER TO LUBE l l l 1 o I l l l 1 OIL PUMPS A2,32 l l l m l
- l l (10B140) I I l 1 i i l l i l m I 1 10K107 AUI OIL PUMP NOT l NONE l l I o I COMPRESSED MR SYSTEM l ISV7889 SOMNOID l AVAILABE l l l l
l . l ACTUATING 10E107 AUX l l l l ,
l l l MECH OIL PUMP l 1 l l 1 ,-
l l l l OSV7ss5 SOLEN 0ID l 00E107 AUX OIL PUMP NOT l Il0NE l l 1 l
l l ACTUATING 00E107 AUK l AVAIIABLE (008186) l l l I I l MECH OIL PUMP 1 1 l l l l l l l 1 I
d l l l l l l-I I S 1 I l I 1 1 l 1 1 l l I R $ l l 1 1 % g ,, I l l l l
-; a o ll l l l l l l
l 9 5- l l l l l 1 l 3 58 l l l l 2 < d "S l I 1 l 1 I I
u*2 l l l l .
l l l l
C-l
. . a J
APPENDIX C Core 98 POWER / SYSTEMS CONTROL FAILURE ANALYSIS
[
U SECONDARY EFFECT COMBINED EFFECTS l l SYSTEM lCOMPONENTDESCRIPTION l PRIMARY EFFECT l l l 1 l so i l l l e l CONDENSATE SYSTEM l SECONDART CONDENSATE l SECONDARY CONDENSATE l RECIRCUMTION RUMBACE l REACTOR SCRAM ON I N l.
l l WATER MVEL l l I m l l PUMP B CONTROL CIRCUITS l PUMP B STOPS TRIP l l ,'
1 m l l l REACTOR FEED PUMP B. l
- l l l FIm DECREASE TO B5% l 1 l l
N l l SECONDARY CONDENSATE I VALVE OPENS REDUCING l REACTOR SCRAM ON IM l l l ta M l i i PUMP 3 RECIRC VALVE l FEEDWATER FI M , I WATER MVEL l .
} l 0 "" ~
l l l l l l TRIPPING FEEDWATER l g l l PUMPS A, B, AND C ON l l l I o l l l Im SUCTION PRESSURE I l l l -
1 l
l l l 1 l l l l l FEEDWATER VENTS, DRAINS l FEEDWATER NEATER TRAIN l CIDSE NORMAL DRAINS 70 l lIONE l l
l g l AND HEATERS SYSTEM l B MVEL, DRAIN AND l NEATER TRAIN 3 I
l l
l l l l l 1 DUMP VALVES
>- l l LVl4645, LVl506B, I l l l l l l 0 t l LV15143 LV15238, l l l
~
l Lvl5328 l l l l l l l -
l LVl4518 VALVE l DUMP EXTRACTION STEAM i NONE l l l
l l l LV1505B VALVE l TO MAIN CONDENSER B l l l l LV15138 VALVE l l l l l l l LV15213 VALVE l l 1 l l l l LVl5318 VALVE l l l l l l l l l NEATER TRAIN B HI MI l LEVEL SWITCHES FAIL l REDUCE FEEDWATER NEAT- l REDUCE FUDWATER NEAT- 1
- I I I M VEL SWITCHES l CLOSED CAUSING MV16208 l ING BY MSS THAN 100*F l ING BY M SS TNAN 100*F l l l AND NVl638B VALVES TO l l l l l l l 1* lCuSE. I l l l l 1 l l l 1 i SERVICE AIR COMPRESSORS l BOTH COMPRESSORS l MAIN STEAM ISouTION l REACTOR SCRAM ON I M l l l COMPRESSED AIR SYSTEM l l l 00Kl07 AND 10K107 l DISABMD l VALVES Cl43URE IN l WATER MVEL l l CONTROL CIRCUITRY l l MINUTES l l
- l l l l MANUAL STARTUP OF l l l l 1 l l l 10E100 AIR COMPRESSOR l l l l
l l InSS Or INSTRUMENT AIR l l l l l l l IF NOT AVAILABM l l l l 1 I l l (10Y409) l l l l 4 I l I l l o l 1 l VALVE OPENS REDUCING l REACTOR SCRAM ON IM l l l l CONDENSATE SYSTEM l SECONDARY CONDENSATE l > l l PUNP C RECIRC VALVE l FEEDWATER FIA57, I WATER MVEL l l O l l TRIPPING FEEDWATER l l l l l
~
l l l PUMPS A, B, AND C ON l l l l
l l LOW SUCTION PRESSURE l l l l
l l l l l l l l l
l FEEDWATER VENTS, DRAINS l NEATER TRAIN C HI MI l LEVEL SWITCHES FAIL l REDUCE FEEDWATER HEAT- l l l
l LEVEL SWITCHES l CLOSED CAUSING MV1620C l ING B1 LESS THAN 100*F l l l l AND HEATERS SYSTEM l l AND HV1638C VALVES To l l l l l l l CloSE l l l t l I l l l l l 1
C-2 I
4]
APPENDIX C C0fet0N POWER / SYSTEMS CONTROL FAILURE ANALYSIS l CONBINED EFFECTS l SYS m lCOMPONENTDESCRIPTION PRIMARY EFFECT l l SECONDARY EFFECT l
l i i i l s, 1 1 I NOME l l I l GENERATOR SYSTEM l GENERATOR STATOR COOL- l PittP 1APil9 STOPS l l l l 1 O l 1 ING WATER PUNP IAPil9 1 IF AVAIIABLE, AUTO l l l i l l l l TRANSFER TO PUNP lsPil9 I l l ,
i l l I (10B120) I i l
1 I
1 I
1 1 1
l l 1 I CNILuD WATER l ICP161 CNILMD WATER l START Pt9tP STANDING BY l NONE l l ,
1 l l l PUMP l (OTNER RuMNING) l l I l i I i l i l 1 l l 1 l l IF ANY ESSENTIAL 308 l i l (10A401, 10A402, l l l l l '
l l l l l l 10A403,10A404) IDST l l '
l l l l l l Aur0 sWITCM TO REACTOR l l l AUXILIARY COOLING l l l l l l l l- l l l l SYS m (RACS) l I i l i I l l )
1 PUMP STOPS I NONE l NONE l I g i TURsINE-GENERATOR l NYDRAULIC ENC PUMP l l l l 1
l SYSTEM l 1APil6 l 25 l l TuRsINE TRIP IF ltPil6 l l l l l 0 l l NOT AVAILAS M l l l l l
~
l I I l l 1 l l SV1650A B.C SECONDARY l VALVES FAIL OPEN AND l REACTOR SCRAM ON IDW l REACTOR SCRAM ON IDW {
1 l CONDENSATE SYS m l l CONDENSATE PittP i DISCNARGE TO MAIN l MVEL I MVEL J l l _l l RECIRC VALVES l CONDENSERS l l ;
l o_ 1 1 l l 1 1
I > 1 1 l REACTOR FEED PttiP A. R l l l I I O l l
~
l AND C TRIP ON IDW l l l l 1 l l 1 SUCTION PRESSURE l l l l 1 1 l l I l l l 1 1 1 1 1 1 1 1 l i 1 COMPRESSOR 10K107 LUBE l OIL PUMP STOPS l NONE l NOME I l COMPRESSED AIR SYS m l )
1 OIL PUMP l l l l 1 l l )
l l l l LOSE AIR COMPRESSOR IF 1 '
)
' l AUXILIARY LUBE OIL PittP l l l ,
l 1 i I m l l NOT AVAI M8M (ISV7889 l l 1 I l l
- l l ON 108130) l I ,
I l I I I I l A 1 l 1 l OIL PUMP NOT AVAILAB E , 1 NONE l l l 0, l TURBINE-GENERATOR l TURBINE MOTOR SUCTION l USED DURING STARTUP I l l l l SYS m l OIL PLAtP 10P108 I I I l l 1 1
1 1 I i l l 1 l DE-ENERGIZE IDSS OF l Lose CAPABIITY TO TRIP l NONE l l m l GENERATOR SYS m l COOLING WATER PANEL I TURBINE ON IDSS OF l l l o i l CIRCulTS l STATOR COOLING WATER I i l TRIP CIRCUIT l STATOR COOLING WATER l p l l i I (PUMPS APil9 AND BPil9) l l i o I i l
- l 1 I I l l c-3
APPEND 11 C Cortl0N POWER / SYSTEMS CONTROL FAILURE ANALYSIS SECONDARY EFFECT COMBINED EFFECTS l SYSTEM CortPONENT DESCRIPTION l PRIMARY EFFECT l l l l l 1 I - l l l RECIRCUu TION RUMBACE l FOR COMBINED EFFECTS, l i N l CONDENSATE SYSTEM l PRIMARY CONDENSATE PUMP l PUMP ICP102 STOPS l l SEE SECTION 4 I l ~0 l l ICP102 l I i Il <o l l GENERA M SYS M I l l GENERA M STATOR COOL- l PtMP IBPil9 STOPS 1
l IF AVAILABLE AUTO l l l
1 - l l ING WATER PtMP IBPil9 l l TRANSFER TO PtMP 1AP119 l l l l l IF AVAILABLE, ALTTO l (105110) i I l l TRANSFER TO PUMP 1AP119 l l l I l I l l (103110) i REACTOR AT OPERATING l l l l l l POWER WITN RECIRCUM - 1 l 4 l l l 1 l l l TION PUMPS IDCEED AT l .
l I l
/ I l l MST SPEED I I I l I I 1
o + m@ WATER SYSM l IBPl61 CHILIJtD WATER l START PUMP STANDING BY I NONE l l l g l l l l PtR"P. IF ANY ESSENTIAL l (OTHER RUNNING) l l l l l BUS (10A401, 10A402, I l l In l l l l l i 10A403, 10A404) LOST, I 1 0 l l l 1 - 1 I AUTO SWITCH TO REACTOR l l l l AUXILIARY C00MNG l l l 1 l 1 l l l l l SYSTEM (RACS)
I I I l l 1 I I SECOPDARY CONDENSATE l RECIRCULATION RUMBACE 'l RECIRCUMTION RUMBACE l l l W M M kE SYSTEM l SECONDARY CONDENSATE l
l PUMP C CONTROL CIRCUITS I PUMP C STOPS. TRIP l l l l l l l REACTOR FEED PUNP C. l l 1 I l l i I FIDW DECREASES TO 85%. l l
( 1 I
! l l l 1 I FEEDWATER VENTS, DRAINS l FEEDWATER NEATER TRAIN l CLOSE NORMAL DRAINS TO l NONE l l I l l I AND NEATERS SYS M l C LEVEL, DRAIN AND l NEATER TRAIN C l
! l I DUMP VALVES l l l I I
/ N l l LV1414C, LV1506C, l l l 1 0 l l LVl514C, LV1523C, I l l l 6
l LV1532C l l l l l
! 4
% l l 1 I I l o l l l l LVI45tC VALVE l DUMP EXTRACTION STEAM l NOME I - J l
- l l LVl505C VALVE I TO MAIN CONDENSER C l l l l l l LVl513C VALVE I l l l
l l LVl521C VALVE l l l l l l l LV1531C VALVE l l l l 0 l l 1 1 I l 1 f I l
- l RECIRCULATION SYSTEM i SCOOP TUBE FOR PUNP A l SCOOP TUBE IDCES IN l RECIRCULATION PUMP A I RECIRCULATION PUMP A 1 l GQ l l l POSITION I REMAINS AT LAST SPEED l REMAINS AT LAST SPEED l o. l l l O o l l l 1 l
I
~~
J ~
l l l I i c
l PtMP REMAINS AT UST l l l l l l l .$ l l l SPEED l
I l
l l
l l
l l l l l 1 l l 1 l C- V
. , s APPENDIX C Cotet0N POWER /SYSTDtS CONTROL FAILURE ANALYSIS PRIMARY EFFECT SECONDARY EFFECT . COMRINED EFFECTS l, SYSTEM lCottPONENTDESCRIPTION l l l I
, L-
~
'l l l l l l l RECIRCULATION SYS M l'AC RECIRC LusE OIL l PUltPS STOP ,
l NONE l REACTOR SCRAM ON I N l l l WATER HVEL I 1"
i l
l l P!4tPS A2 AND R2 l s l
l AUTO TRANSFER To LUBE jf l , l%
I l 1 x? 011. rump Al AND Rt ! l r j '
~ ^
_ l-(lost 30) '
10 l l l l 1
l l' l l % '! n/ -
lt l _ .
l' " ^
l TURRINE cENERATOR l !!YDRAULIC INC PUMP i $WE, TURir?NE TRIP IF l HONE l -
l$
l l SYa m l 14116 l l-JMP IAPil6 Nir, AVAIL vl I > l 1%
I l l A4!J (10R112) i I '- I,.-
l - l l - I l- l l. r i I I CONDENSATE STSTEM i SECONDART CONDEN MTE l SECONDART ru nrusATE l RECIRCUMTION RUNRACK l'ItECIRCUMTION RUNRACE l l so l I etalP A CONTROL CIRCUITS l PUHF A TRIP REACTcs l 1
.i l S l l l FEED PUMP A, FLOW j ~l 1
-l i
l . l l l DECREASES TO 351 l l .N l l l l 7 l 1 I i 1 ~l SECONDART CONDENSATE '1 VAIVE OPENS REDUCinc l REACTcz SCRAM ON IM' l REACTOR SCRAM ON LOW l*^
l l l PIRIP A RECIRC VALVE l FLEDWATER FIM, I WATER LEVEL ,. ' I WATER LEVEL
- l s i I l l TR1rPlea FErWAm , l N l
_l I emes A, 3. MD C ON - ' ,1 l l 1 l .l ~
i l Im sucrION PRErsuRE l J l l I.n '
I I ' ,
l l -. l -1 - : /l ,- _.- 1 I l m WATER VENTS, DRAINS l FFEDWATER NEATER TRAIN l CLDSR NORMAL DRAINS To l.h0NE l / l l t, l AND E ATERS SYSTEM l A LEVEL, DRAIN AND l EATER TRAIN A ~l '
l , l
" l ,~
1 e. l l DUMP VALVES I I l l
l j< ,7 $ 3 l l l LV1464A, LV1506A.
l LV1514A, LVM23A, l
l l
l
" J' - l l
l l
c' > l 1 LVI532A l l l l I w l 6, .,. # ~ l 1 ' .
l l -
l 1
? -O l l LVl451A u LVE I DUMP EXTRACTION STEAM ' l WONE l l l < e: "o s l l LVl505A VALVE l 70 MAIN CONDENSER A - l l l l l l LV1513A VALVE l ) l l #
v ., ;
I l 1 LV1521A VALVE l - l l l l l l LVI531A VALVE l l l l l l l l 'l I l l l l NEATER TRAIN A MI MI l LEVEL SWITC ES FAIL i M DWA m NEATING l M DWATER NEATING l
. l l l uvEL SWITCNES l CIASED CAUSING NV1620A l REDUCED BY LESS THAN l REDUCED PY MSS TNAN I I i i i AND NV1638A TO FAIL l 100*F l 100*F l i l l 1 CInSED l l l 1 l l l 1 I l l l W.cIRCUuTION SYSm l SCOOP TURE CIRCUITS FOR l SCOOP TURE IDCEED IN l RECIRCUMTION PUMP R I RECIRCULATION PtRIP R l i -
r= l .l PlatP R l POSITION l REMAINS AT LAST SPEED l REMAINS AT IAST SPEED. l 2 l l 1 I l Y l l l l l l< r >- I I l PUMP REMAINS AT IJST i e v. g 0,. l l 1 SPEED l l l
1 1
l a-8 3, l l l 1 1'8 l I l l 1 l :
C-5
APPENDIE C CotMON POWER / SYSTEMS CONTROL FAILURE ANALYSIS COMBINED EFFECTS SYSTEM lCOMPONENTDESCRIPTION PRIMARY EFFECT l l SECONDARY EFFECT l l ,
l l l i 1 i i 1 I N I NONE l 1 I PROCESS RADIATION l NIGN RADIATION TRIP l % REACTOR SCRAM TRIP i l I I I MONITORING SYSTEM l CIRCUITS 1 (CNANNELS AI AND A2) 1 I I I I I I I 1 l I I I REACTOR SCRAM IF CNAN- l l l I*
1 I l 1 NELS AI OR A2 TRIPPED l I
I I l$
I J 1
l 1
i I
1 g REACTOR MAIN SMAM iM i l l
l ISouTION TRIP (CNAN- l 1 i 1 l<f l t l l 1 NELS AI AND A2) l l 1
!ff i-lg 1
l t
l
! MAIN SnAM ISouTION Ir !
l CNANNEIS 31 OR B2 1 TRIPPED l
1 l
l 1
I i l I i I i l l l i MIGN TEMPERATURE TRIP 1 % MAIN STEAM ISOLATION I NONE l 1 LEAE DETECTION SYSTEM l TRIP (CNANNELS AI & A2) l l l l 1 l CIRCUITS 1 I I i 1 l 1 l I I I l 1 I l l l 1 IS0 u n REACTOR WATER I NONE l l l l l CLEANUP 1 l l l l l 1 I l l l l l l ISouTE MAIN STEAM i l I l l l l l l l DRAIN VALVES 1
l i i l I i i l l 1 RPS BUS "A" BACEED UP 1 I l l l l I l l BY ALTERNATE BUS 108491 1 l l i I 1 I i 1
I I i 1 l l 1 I RECIRCULATION PUMPS A I RECIRCUuTION PUMPS A I I RECIRCuuTION sTSTEM l CONTROL CIRCUITS FOR I PUMP MOTORS LOCEED AT I I AND B REMAIN AT LAST l AND R REMAIN AT uST l l l RECIRCUuTION PUMP l uST SPEED l 1 SPEED l SPEED l l l MOTORS A AND 8 SCOOP l 1 l 1
.I TUaES DEMAND SIGNAL I l 1 l I I I I I 1 I I I I I i 1 ,"
I I l 1 I I I l I I I I I I I l I I I l 1 l I I I I i 1 1 1 I
' i 1 1 l I I l i I I I I I I I I I i 1 ,
I I i i i i 1 1 I I I I I I I 1 1 I i 1 i 1 I I I 1 I l 1 I
I I I I I I
C- lo
.z
~
,, APPENDIX C s -
Corst0N POWt.R/SYMEMS CONTROL FAILURE A4ALYSIS y - .,
. SECONDARY EFFECT ContinD EFFECTS
,, l SYSTEM lCOMPONENTDESCRIPTION PRIMARY EFFECT l l l l l l l--- l l l 1 MAIN TISRINE TRIP IN l MAIN 7tstsIIIE TRIP IN I l
1 0FTGAS SYSTEM i UNIT I AND C00990N I IDSE STEAM JET AIR l l RECOMElNER ANALYZER I EJECTOR l 101 1 MINUTEE ON IAd i 101 1 MINL"fES ON IAW l l }
i PANELS I I CONDENSER VACULDS I CONDENCEP YACUt91 l 1 l A l 1 1 1. 1 - I
~
l _ l A155724 MIG'I NYDROGEN 1 DE-ENERGlZE AIS5724 i MAIN T*.MtBINE TRIP i hAIN TilWBINE TRIP .I-I O O l- I-I l l TRIP SOIEJ101D 1 l
- I I I I < I ..I I IDSE STEAM JET AIR
'I .
I lihIN 7tRBINE TRIP IN I ,'I .,'
I 9 h l -
I STEAM SUPPLY VALVES
-1 10 t 1 MINUTES ON IoW .I
~
l l o I. 1 PV5641 Axe sV5640 i EJECTOR l
i I I FAIL CLO6ED 1 1 CONDENSER VAC1Att l i 1 i l I 1 I I i 1 .I I i 1
l i 1 l i 1 1 I I I l 1 I I I I I I I I' _.s 1 I i 1 I i l 1 i
I I I I I 1
I I I I i I I I
.I i i ^
i 1 > 1 i
i 1 i . I I ~ I. 1 I
i I I I i 1 I i 1 I i 1 1 '
I I l l I i 1
I I I I I i I
l i i l i I I I I I i i i I
I I I I i - .I I )
i 1. I I I l I I -
1 1 ~l I I I I l -
1 i 1 I I I I I I l'c 1 1 6
I 1
'I I I I I I i 1 1 'l i I i i 1 1 I - I t i i l l l i I i 1 .
I I f I 'I i i l i I +
- I l- '. 1 I I
1 I I I l' I I I ':
I I i 1 1 1 l i 1 1 I 1 1 I
-1 I I I i - I .. 1 I I I i _I I I I
i 1 1 I I 1 I
i 1 l i l I I i l i l 1 1
~~
l i I I i 1 1
C- 7
APPENDIX C C0tm0N POWER /STSTEMS CONTROL FAILURE ANALYSIS COMBIMD EFMCTE l STSTEM lCOMPONENTDESCRIPTION PRIMART EFFECT l l SECONDARY EFFECT l -l ,
l l t i I I 1 -- 1 I REclRCULATION RUNBACK l RECIRCULATION RUNBACE l I I CONDENSATE STSTEM l SECONDARY CONDENSATE l PtMP ICP137 STOPS l l l l l l 1 PtMP ICP131 I I I I l 1 l I f i MAIN WBE OIL PtMP l LUBE Olt PLMP STOPS l NONE l ,
Io I-o j I COMPRESSED AIR STSTEM i i OPl7B TO COMPRESSOR I ( l I a I 00K107 l START AUX (108130) M CM l l l ,
I< - -
1 l l LUBE OIL PUMP 00Pl79 l l l Io so 10 l i !
0 0 i l 4
1- O t 1 l l l l l O I l i
I I I l-1 1 I I I I 1 I l
l % REACTOR SCRAM TRIP l NOK l l I I PROCESS RADIATION l HIGH RADIATION TRIP l l CIRCUITS l (CNAIGIELS Bl AND B2) l l
[ l MONITORING SYSTEM I I 1 1 I I 1 l i I REACTOR SCRAM IF CHAN- l l I l I l l l l l l NEIS Al OR A2 TRIPPED I I I i 1 1 l
l % REACTOR MAIN STEAM l NOK I l 1 l l l ISOLATION TRIP (CNAN- l l l l g i l l l l o, I I I NELS Bl AND B2) 1 I I I I I
I + I l l MAIN STEAM ISO MTION I l l I in l l l i IF CNANNELS Al OR A2 l l l g i l l l l l TRIPPED 1 o l i 1 1 1 l 1 I l l NIGH TENDERATURE TRIP l 4 MAIN STEAH ISO MTION l NONE I l l uAK DETECTION STSTEM l l l l 1 CIRCUITS l TRIP (CHANNELS BI & B2) l i I I I l 1 l l l l ISOLATE REACTOR WATER l l l l l l l l CLEANUP l l l 1 I 1 1 1 l 1 l l ISOLATE MAIN STEAM l l l l l l I I DRAIN VALVES l l I I I r l 1 I I 1 l l l i RPS bus ~B" BACKED UP l l I i l l 1 1 I I BT ALTERNATE BUS 10B131 l 1 I I i 1 l 1 1 l l l l 1 I I I 1 1 I 1 1 I I I I I I I 1 l l l l 1 i 1 l 1 I I I I I I I 1 I I 1 1 1 I I I I I I 1 I I I 1 I l 1 l l l l l
C-B
- , ,s, APPENDIX C Colet0N P0bER/SYSTDIS CONTROL FAILINE ANALYSIS SETWDARY EmCT COMBINED EFFECTS l SYS m lCOMPONENTDESCRIPTION PRIMARY E m CT l l l l l I I I i l 1 1
~ I RECIRCULATION RUNRACE I l l CIRCULATING WATER I CIRCUIATING WATER PUMPS l PitfPS IRP501 AND 1DP501 1 RECIRCULATION RIMBACE l STOP l l l I i l IkP501 AND IDP501 I
- 1 1 I I '
1 1 I I I I i $ 1 l
1 I I I I I < 1 1 1 I I I o -
1 1 I I i 1 1 l 1 i 1 'l I I I I I I I i i l i I I I I I I I 1 1 I I I 1 I i I i i i l I
i l i I i I i I I I I I l t I I i l i I i I i 1 i l l I I I I 1 I I 1 I i l i l 1 I 1 1 I I i l 1 I I I I 1 1 I I I I I I I I 1 1 1 l l 1 1 1 1 1 I l l 1 I I I I 1 1 1 1 I I I I i 1 I i i ! I I i I i l i l i l l I I i 1 l l I I I I i 1 1
I i 1 I i 1 I I I I I I 1 I 1 l l l 1 i l I I I I I I I
i i i i i i l i I 1 i l i 1 I I I i 1 I I I I I I l- I ,
I I I l 1 1 I l I 1 I I i 1 1 1 1 1 1
i l 1 I I I i 1 1 I I I I I I I I i I I I I I I I 1 1 1 1 1 1
i 1 i l l- 1 I 1 I I l l l 1 C-9 i
APPEllDIX C C0tMON POWER / SYSTEMS CONTROL FAILURE ANALYSIS 4
rRIMARY EFFECT SECONDARY EFFECT COMRINED EFFECTS '
l l SYSTEM lCOMPONENTDESCRIPTION l l l l I i i i l i 1 1 l CIRCUuTING WATER I CIRCL'IATING WATER PUMPS l PUMPS 1AP501 AND l RECIRCU MTION RUNRACK l RECIRCUIATION RUNRACK I l d i SYSTEM i IAP501 AND ICP501 1 ICP501 STOP i l i I I 1N I l
I i
I I i l l'
I I < I I o . I CIRt.UuTING WATER l NV2152C CONTROL CIRCUIT I NV2152C AND NV2152D l NONE I I- O l SYSTEM i l FAIL AS IS (IN POSITION)I I I m l i I a o 1 i i I 1 m 1 I NV2152n C0errROL CIRCUIT 1 i 1 1-e i 1 I
1
- 0 1
I I
I I
i I
1 1 I I
~
l i I i l i 1 I i I i 1 l l I I I I I I I I I i 1 1 I i 1 CIRCUuTING WATER I NV2152A CONTROL CIRCUIT l NV2152A AND NV2152R l NOME J l l i SYSTEM l l FAIL AS IS (IN POSITION)l i I I w I I I i 1 1 I o I i XV2152R CONTROL CIRCUIT I 1 l l t m i I i 1 1 1 I m i i 1 I 1 I
1 i
1 o 1 1 1 1 l
1 1 1 I I i 1 I 1 i l i 1 I I i 1 1 1 1 1 1 CIRCUIATING WATER I NYDRAULIC FLUID PIMPS l FIAW CONTROL VALVES I NONE l l l c4 l SYSTEM l AS$17, RS$17 AND CS$17 1 NV2152A, NV2152R AND 1 I i 1 I I NV2152C REMAIN IN IAST l 1 1 1
I
" I 1 l POSITION I I 1 i
E I I I . 1 1 1 l
O l l l IDSE CIRCUuTING WATER I l l l
1 I I I IF NYDRAULIC 12AK l i I I I I I EXISTS 1 1 I i 1 1 1 1 I I I I I I i 1 1 i 1 1 1 1 1 I
l i I I I I I I I i 1 i I i l 1 I I i l i 1 1 1 l 1 1 1 1 1 1 1 1 1 1
1 1 I .I 1 l l l l 1 'I l I '
i i i i *I i 1 1 I I I ,1 1 I I i 1 1 '1 I 1 I
- I i 1 'I I I l C.-lo i
APPENDIX C C0fRt0N POWER / SYSTEMS CONTROL FAILURE ANALYSIS SECONDARY E m CT COMRI ED E m CTS l SYSTEM lCOMPCi:ENTDESCRIPTION PRIMARY E m CT l l l l i i i l i l l i RECIRCUuTION SYSTEM l Ptetr MOTOR 1AP201 i MOTOR STOPS I M CIRCUMTION PIRtr A i i TRIP l l i I i 1 I I -
1 I I f l 1 I i MOTOR STOPS l IBONE I McIRCULATION RlRIRACK 1 I COMPRESSED AIR SYSTEM l AIR COMPRESSOR 10E107 l I I I ON SINC!z PUMP I I I It0 TOR l i AUTOMATIC STARTUP 0F l l e l l 1 1 i i i I i 1 AIR COMPRESSOR 00E107 l i i i i i i l MCIRCUMTION RUNRACK I RECIRCU MT!uN BlWRACE I I l CONDENSATE SYSTEM l PRIMARY CONDENSATE PUMP l POTOR STOPS I I I MOTOR 1AP102 I i 1 .'
I 1 I I I I i 1 l l I MOTOR STOPS I I i l SECONDARY CONDENSATE l l l 1 l PtMP MOTOR 1AP137 l 1
l l l 1 O I l I -1 1
i 1AEll! WATER CNILU R 1 i NOR I I CNILIED WATER SYSTEM I I I
4 i < 1 1 I I 1 1 O I I IDEll! WATER CNILIER l AUTO START CNILIER l I I I .I 1 STANDING RT (OTNER TWO I 1 I 1 1 i I I RuMNINc) i I I I I 1 I l l l l 1 IF STANDRY CNILIER NOT I i 1 1 AVAILABLE INCREASE IN l l 1 l l l l 1 i DRYWELL PRESSURE I 1 1
1 1 I I i 1 l 1 I I I I I I I 1
i i l i i I i 1 1 1
- I I i 1 l 1 l l l 1 1 I I I I 1
- i 1 l I i l I I i 1 I I I i 1 i I I I I I I I I I I i 1 I I i i i l 1 I I I I I I i l 1 I l i i i l i I
I i i l i i l l I i l i i i i i i 1 i l I I I I
- I I I I I I I i 1 I I I I I I I I I 1 1 i I i 1 i l I i i 1 1 l 1
i l i i i 1 i i i i i l I
C-Il
APPENDIX C CoretDN POWER / SYSTEMS CONTROL FAILURE ANALYSIS .
SECONDARY E M CT COMRINED E m CTS l l SYS M lCOMPONENTDESCRIPTION PRIMARY E m CT l l l l 1 I l l 1 I 1
I RECIRCUuTION SYSM I PtmP MOTOR lap 201 i et0 TOR STOPS I REClitCULATION PUMP R l l I
1 I I I TalP 1 I 1
I I I I I i I I l CONDENSATE SYS M 1 PRIMARY CONDENSATE I MOTOR STOPS 1 RECIRCU MTION RINEACE I RECIRCUuTION RUMBACE l
l l PUMP MOTOR ISP102 l l l Oli SINCIE PUMP i I i i i i I I I
l l l SECONDARY CONDENSATE I MOTOR STOPS. l l 1 l PUMP ft0 TOR IBF137 1 1 l l l l 1 I I I i l 1 l COMPRESSED AIR SYSTEM l AIR COMPRESSOR 00E107 1 MOTOR STOPS l NOME l 1
, I I i i NOTOR I 1 I I g l l l AIFF0MATIC STARTUP OF l l l l l l 1 9 l l l AIR COMPRESSOR 10E107 l 1 I I I I 1 4 1 1 I W il WA M chi m R I A m S M T CNIRER I NOME I l I
O I CNIRED WA M M M I I l STANDING BY (OTHER TWO I I l I I I I I RUNNING) i I I I I I I i 1 l l 1 I IF STAND 0Y CHILER NOT I l 1 l
1 1 1 i AVAluBD. INCREASE IN I i 1 1 I I I DRYWELL PRESSURE l l 1 I i 1 1 I 1 I I I I I i 1 1 1 I i l i i 1 1 1 1 1 1 1 1 1 I I I I 1 1 I i 1 1 I I I I i ~1 I I i I
I I I I i i I i
I I i l i I 1 1 1 I I 1 1 I I I I i 1 1 I I i l I i I
I I i I i 1 I i i I I I I i l I I I l i 1 I
I I I I I I
i 1 1 l I i I
1 I I I I l l
-1 I I I l l 1
'1 1 1 I I i 1 1 I I I l l 1 1 1 1 i 1 1 1 I
I I I i l l l I I I I I l I I I I i i I
C-12.
f 9
APPENDIX C C0ftt0N POWER / SYSTEMS CONTROL FAILURE ANALYSIS PRIMARY EFIICT SECONDARY EFFECT COMBINED EFFECTS COMPONENT DESCRIPTION l SYSTEM l i I I I i i I l FOR ConBINED EFFECTS, I 1- l SAftTY AUXILIARY l COOLING WATER PtMP 1 IDSE RNR NEAT EXCNANGERSI NOME l IAP210 (LOOP A) 1 COOLING AND TIRBINE l l SEE SECTION 4 1 i i COOLING SYSTEM I I I l l l COOLING IF AUTO TRANS- l I FER 70 STANDBY IAOP NOT I l l I I I~
1 l i 1 AVAllABLE l 1 I l (10A402) PUMP IRP210 l l l lj i l I i I (10A404) PUMP IDP210 lI l 1 1 I I I I I I i l l l I I I I IaSS Or BUS 10A401 I TRANSFERS DRYWELL COOL- 1 I I ,
l 1 1 l l ERS TO REACTOR AUXIL- l l 1 1 I i l l l IARY COOLING SYSTEM i 1 l l I i i l i 1 l INITIATE TACS IS01ATION l MAIN TURBtWE TRIP 1 MAIN TURBINE TRIP l I I SAf17Y AUXILIARY l REMOTE CONTROL PANEL l l l l l l COOLING SYSTEM i IAC201 i 1 1 l 1 1 I I
l h l I
I TACS LOOP SUPPLY VALVES I SACS STANDBY IAOP l MV2522A, E AND F ISOLA- 1 STARTS ALTTOMATICALLY 1
l 1
i l l f i l l o l l TION ON LOW ACCuMUIATOR I I
l l i 1 <
l l PRESSURE CIRCUITRY l PT2509,PT2546,PT2545, I
I I i I
I 1 l l 1 i l l PT2543,PT2523,PT2587 l I I I I l l 1 I
l REACTOR AUXILIARY COOL- 1 PUMP STOPS, CAUSING 1 MAIN TURBINE TRIP IN I MAIN TURBINE TRIP IN l l REACTOR AUXILIARY l 10 1 1 MINUTES I i ING PUMP 1AP209 1 IDSS OF 0FFGAS I 10 i 1 MINUTES ON 1AW i COOLING SYSTEM i 1
l RECOMBINER I CONDENSER VACIRM i l l 1 i l i l i i l l MAIN TURBINE TRIP l l l SAFETY AUXILIARY l TACS IAOP DISH VALVE I INITIATE TACS ISOLATION l TURBINE TRIP I l l I d i COOLING SYSTEM I NV2496A i
l SACS STANDBY IAOP i STARTS AITTOMATICALLY I I I l re 1 1 1 1 I A 1 1 1 I I I I S 1 1 I 1 1 1 l l l 1 I
I I I i 1 1 1 1 1 I i 1 1 1
I l i i 1 1 I I I i 1 l i 1 i 1 1 1 I 1 g g ;
O o ; ; g I I I I
I $ 3 I I 1 I I I a m 1 i
1 1 1 1 I I o o
1 I I I I I 1 1 I i i i l I I I 1 1 i f' Cd i 1 1 l
I
- I I I I I C-13 .
l APPENDIX C Coret0W POWER / SYSTEMS CONTROL FAILURE ANALYSIS SEC01SARY EFf1CT COISIM D EFTECTS SYSTEM C0ftPONENT DESCRIPTION PRIMARY EFIICT l l l i i I I i l I I t, I NONE I MAIN 7tstBINE TRIP .
i DRYWLL VENT CONTROL i DRYW LL C00ER A FANS l LOSS OF DRYWLL l I l l I SYSTEM i i COOLER A l I l 1 i I O I l l l I i I Attr0MATIC STARTUP OF l io l q l i I I It h l I i mmE mm a I l I I I (lob 262) 1 I CQ c9
- l l. ! l l2 2 l
I l
I I I l i I ;
l i I i '
I I i I RECIRCULATION RUMBACE I i REACTOR FEED PUMP l REACTOR FEED PUMP l RECIRCUMTION RUMBACE I I REACTOR FEEL PUMP i 1 i TURBINE A CONTROL I TURBINE A STOPS I l I TURBINE STEAN SYSTEM l l l I
1 I I CIRCUITS I I I l.
1 l l 1 1 \ REACTOR SCRAM TRIP l NOME 1 I M I POWR RAN E NEUTRON l NEUTRON MONITORING i I I 00 i te0NITORING SYSTEM l CIRCUITRY l (CMANNELS AI AND A2) 1 I I I I I I t 1 I I REACTOR SCRAM IF CNAN- 1 l 1 i y i I l l i I i NEL B1 OR B2 TRIPPED I g I I I i 1 _ l l 1 IDSE CAPABILITY 70 1 IDSE CAPABILITY TO l 1 1 TURBINE-GENERATOR l TURBINE fECHANICAL TRIP 1 IDSE CAPABILITY 70 i SOMMOID I E CHANICA RY TRIP I IECNANICALLY 1 RIP MAIN I IECMANICALLY TRIP MAIN l l l SYSTEM l TURBINE I TURBINE I l l TURBINE l l i I I i I 1 l l MAIN TURBINE BYPASS 1 l TIRBINE BYPASS VALVES I MAIN TURBINE BYPASS l MAIN TURBINE BYPASS l l 1 VALVES FAIL OPEN l VALVES FAIL OPEN I l l CONTROL CIRCUIT l VALVES FAIL OPEN l i l 1 1 I I i I I I i 1 1 I i i l I i i i I I I I i I I I i l I 1 I i i I l i l I I i 1 I I I I I 1 1 1 I 1 1 I I I I l I I I I I I i l I I i l i l I I I 1
i 1 I
- 1 I 1
I i l 1 l i I i i l I I
M i i i 1 I I I 1 I O 1 I I I i 1 I w I I I I i 1 2- 1 I I 4
I I I 1 ca l i I l I
I i 1 1 i i i i I i i C -It
APPENDIX C Cortl0N POWER / SYSTEMS CONTROL FAILimE ANALTSIS COMRINED E m CTS l l SYS M lCCelPONENTDESCRIPTION PRIMARY E m CT l l SECONDARY EFFECT l l i i 1 I I .
l rs 1 I mWATER STSm l RFP RECIRC CONTROL l FV1783A DUMPS TO MAIN 1 NOME l l I
l 1 CONDENSER A l l l 1 l VA(VE siVI783A I ,
1 1 I I I I I FEEDWAm VENTS, DRAINS i FEEWAm NEAM TRAIN l REDUCE MAls enunruera A I 1 l I
l AND NEATERS STSTEM i A LEVEL, DRAIN AND 1 VACUUrl I l l l
I I DUMP VEVES I l l l l
l I I I I l 1 l LVI506A V EVE I CIDSE NORMAL DRAINS 70 1 NONE I I l l l
i l l LV1514A VEVE I MEA M TRAIN A l l l' I I LV1523A VEVE I l l 1 I I I LV1532A V EVE I l l l
- I I I I I I I
I EXTRACTION STEAM SYS m l NVI373A VALVE a EXTRACTION STEAM DUMPS l NONE I I <
I i I NVI388A V EVE TO MAIN CONDENSER A l l l l ( l l l l NVl355A VALVE , I 1 1 I NV1377A VALVE I i 1 1 1 i NV1387A VALVE I I I I 1
I Ill I I NV1366A VALVE I I I l I uvt35'A vnvE I I I i l O I 1 NVl367A VALVE l l l l l p 1 I i 1 l l 1 1 .
La. I MOISTURE SEPARATOR 1 DRAIN VALVES FAIL 1 NOME l l I 1 1 CIDSED 1 1 l > I I DRAIN CONTROL VALVES 1 l
I -
1 I LV1363A, Lvl364A I l l 1 l I 1 MAIN TURRINE TRIP IF i 1 l l l 1 l A. R & C DRAIN VEVES 1 1 1 I I I CIDSED I l l I
I I I I l 1 1 I SAFETY AUXILIARY I TACS IDOP SUPPLY VALVES l INITIATE TACS ISOI.ATION 1 MAIN TimRINE TRIP 1 MAIN TURRIME TRIP l I
1 w TING SYS m i NV2522 E AND F I I l l l
l l l 1 1 I l
I I i 1 1 I I
i 1 1 1 1 I I
I I I I I I l i 1 1 1 i I 1 I I I i 1 1 I I l i I I I I
1 I I i 1 1 I I I I I I 1 1 1
I i 1 1 1 1 I
1 1 I I I I i 1 1 I I i 1 I
I I I I l 1
i I I i 1 1 1 1 I I I i l i i 1 1 1 i 1 I
C-IS .
_ _ , _ _ . _ _ _ _ _ . _ . - _ _ . . . . _ . . _ _ _ ._. . _ . _ . . _ _ _ __. _ __ _ s APPElmlX C
, ColSION POWER / SYSTEMS CONTROL FAILIBE ANALYSIS SYSTEM COMPONE.NT DESCRIPTION PRIMARY Ef7ECT SE m Y EFFECT l COISIM D EFFECTS '
l l I es I i i i i I
, 1 I SAFETr AUXILIARY l aAILEY PAIEL IAC655 i TRIP SACS PUMP IAP210 i NOIE I BEACTOR SCRAK 011 IAll I l l COOLING SYSTEn I CONTROL CIRCut m TO I I l uAm laVEL - l l l l SACS PUNP 1AP210 l SACS STANDBY IDOP 1 l l l I I I STARTS AUTOMATICARY l l l c4 l g l l l l l l I f I I mAILEY PANEL 1AC652 l INITIATE ISOP ISOLATION I l l 1 3 I I SACS Im0P SUPPLY WALW I I I l l9 <
l 1
l W2522A I
I I
I I
l I
l I
1 I
f I I I I I l 1M __ l i I I I I IO I I I l l 1 l- 1 I i 1 1 I i . c- l CnnPRESSEo AIR SYSTDI l ErsarsuCY INSTRtBENT l COMFettene NOT l NONE l l l m O I I AIR COMPRESSOR 10E100 l AVAILASix l l l 1
l 8* +
y l
I l
l l
l ConPerannt 00E10 AND 1
l l
l 'l l
I M O I l l 10E107 mERcENCY mACEur l l l t l 0 -
1 I I Isor AVAIIAsix l I l I
l l l l l l I I l l l 'l l 1 l 1 1 I I -I l l l PAIEL 1AC653 l l l l t
l l m DWATER VENTS, DRAINS l LV1506A V R W l CIASE NORMAL DRAINS 10 i NONE I l
! l l AND REATERS l LV1516A VALW I IEATER TRAIN A I I I l l l LV1523A VALW I l l l l
- I l l LVl532A VALM l l l l i l l l l l l l i l l l PAIEL IAC653 -l l l l i I
- I EXTRACTION STEAM SYSTEM i MV1373A V R W l DUMP EXTRACTION STEAM l NONE I l l 'd i I NVisesa vALW l TO MAIN CollDENSER A l l l l + 1 I N1355A VRVE I I i i I o l l MV1377A VALVE l l l 1 l < l l MViss7A VR W I l l l
.: I -
l l MV1366A V R VE l l l l '
I I i l MV1359A VALVE I l l l
! l l l NV1367A VALVE l l l l
- I I I I I I l
! l l PANEL LAC 653 l l l l l l l l MOISTIRE SEPARATOR l DRAIN VALVES FAIL' i NOIE l l 1 l l l DRAIN CONTROL VALE S I CIASED l l l l LV1363 AND LVl364 I l l l I g l l
l l l l nAIN TURBINE TRIP IF l l 1 l I 1 A, 5 AND C DRAIN VALVES I l l i i i I l CIASED l l l l l 1 l l I i 1 I
C-l(o 4
.. g APPENDIX C Corm 0N POER/ SYSTEMS CONTROL FAILIRE ANALYSIS SECONDARY EFFECT COM IED EFFECTS SYSTEM lCOMPONENTDESCRIPTION PRIMARY EFFECT l 1 I I i I l 1 l REACTOR FEED PUMP l REACTOR Im MTER MVEL I I N I REACTOR FEED PUMP l PANEL IAC653 l REACTOR T H D PUMP I TURRINES A B AND C l SCRAM i l l TURsINE STEAM SYSTEM i REACTOR TEED PUMP l TURBINES A. R AND C l IDCEED AT MST SPEED I I l TuRsINE A CONTROL l LDCEED AT LAST SPEED.
i l l CIRCurt DE-ENERGIZED. l l l I I I CIRCUITS I l REACTOR FIED PUMP l RECIRCUuTION RUMBACK I l l l l I I TuRsINE A STOPS, FI m I i I I I I l 1 l DECREASES To 851 l l I I I I l l i l i i i i I I I I I .
1 I l 1 I I I I I l i l i I PANEL 1AC654 i FIEDETER PUMP RECIRC I REACTOR SCRAM ON LOW I I l I I FIEDWATER PtMP RECIRC l VALVES A, B & C FAIL l WTER uvtL I I l l l i VALVES A, B & C CONTROL l OPEN AND DLMP TO CON-l 1 l DENSERS. InSE 1/3 l l I 1 1 I CIRCUIT 1 I FEEDWATER Fim. l l I I I l l 1 l I t l l I DECREASE COMENSER I NOME l l I c0 1 I l I I VACUUM l l 1 I I I
~4 i I I l
1 I
' l l 1 FEEDWATER RIBIBACE l FEEDETER RUNRACE I CIRCUITS A, 8 AND C l l l
I
< l 1 l CIRCUITS A, a AND C i DISABED I
i i l l l DISAB ED l
l I I i i l i i l 4 PANEL IAC653 l TRIP SECONDARY CONDEN- I REACTOR LOW LEVEL SCRAN I I
l SATE PUMPS AND REACTOR l l l 1 l l PRIMARY CONDENSATE l l FEED PUMPS l l l l l PUMPS A B AND C i l CONDENSER NOTELL i i l l l l l l Im-LOW uYEL TRIP I i 1 l l l 1 1 l l CIRCUITRY l I I I I 1 I I l l AIR COMPRESSOR NOT l NONE l I l COMPRESSED AIR SYSTEM l PANEL IAC653 1 EERGENCY AIR I AVAllABE TO RACEUP l i I l l l l i l l COMPRESSOR 10K100 l COMPRESSORS 00K107 AND l l I I I l 10EIO7 I l 1 I I i l l 1 I l MAIN TURBINE TRIP IN l l 1 0FFGAS SYSTEM l PANEL 1AC653 l IDSE STEAM JET AIR 1
l CONTROL CIRCUIT FOR I EJECTOR A l 10 11 MINUTE l 1 l l i 1 l VALVES MV5643A, I I I l I I HV5646, NV5666A l l 1 1 I I l 1 I I l 1 I l 1 1 I l l 1
I i i i I I I l 1 i I I t I I I l 1 1 I I I l I I I I
.t.
. C-lT
APPENDIX C COPRION POWER / SYSTEMS CONTROL FAILURE ANALYSIS I SECONDARY E M CT COMBINED E M CTS l l SYS m lCOMPONENTDESCRIPTION PRIMARY E M CT l l l i I I I I 1_ l I NONE I MAIN TURRINE TRIP 1 l l SAFETT AUXILIARY l COOLING WATER PUMP l IDSE RNR NEAT l l COOLING SYS m i IsP2IO (IAOP 3) 1 EXCNANGER COOLING AND I i 1 1 I I TuRsINE COOLING Ir AUTO I I i 1
I I I i i I I TRANSFER TO STANDBY I
I I I I IDOP NOT AVAIIABu 1 1 l 1 (10A401) PUMP IAP210 1 1 I I l l
Id 1 1 1 (10A402) PUMP ICP210 l l
l 1
10 l l 1 I InSS Or sus 10A402 l 1
l l I .+ 1 I I (
l< l i I TRANSFERS DR M LL COOL- 1
- lO 1 1 I ERS TO MACTOR AUXIL- l 1 1 i I IARY COOLING SYS m 1 I I I~ l l 1 1 I i 1 1 I
1 DRMLL COOuR B FANS l IDSS Or DRmLL COOuR l NONE I RECIRCUIATION RUNDACE l l DRmLL vtNT CONTn0L I I SYS m i Ia 1 i i N I I i 1 1 1
- I o
- 1 l l AUTOMATIC STARTUP OF l l I I a " I i l DRmLL C00mR A I I I I t A I l' 1 (10s252) i I I O i i i l l I p -
I I I I I I I o 1 i - 1 I I i 1 1 I
I i l i i 1 l REACTOR FEED PttlP i REACTOR FEED PUMP 1 RECIRCUIATION RUNBACK l l
, I I REACTOR FEED PUMP l 1 TuRBI R STEAM SYS m 1 TURBINE B CONTROL l TURBINE B STOPS, FIAW l 1 , I I I CIRCu!TS l DECREASES 70 851 I 1 1 I I I I I I I 1 -
I IASE FEEDWATER CONTROL i M D WA M TURBINES I l l en i I l
m I l l SIGNALS A, 3 AND C 1 LOCKED AT IAST SPEED l 1
I 'l IoCEING TuksINES AT l l l l 3 I i
l l 1 IAST SPEFA I 1 l I i I I I 1
i 2
l i FuDWATER CONTROL l FEEDWA m CONTROL l M DWATER TURBINES 1 FEEDWA m TURBINES l l I IACKED AT IAST SPEED l IDCEED AT LAST SPEED 1 1 l l SYS m i CIRCUITS 1
0 l l l l l l ,
1 N I 1 I i 1 1 I
- I I I I i 1 I I I I @ 1 1 1 O I i i l i I I
a i i i i l 1 I o I I I i I y i I I
I I i u 1 1 1 1
I > I l l 1 1 i N -
i I I i l 1 l gl 1 1 I I I I
I I I I I I
C-IS
APPENDIX C CoretDN POWER /SYSTDiS CONTROL FAILURE ANALYSIS' O
SECONDARY EFFECT CONBINED EFFECTS l SYS m lCOMPONENTDESCRIPTION PRIMARY E M CT l l l l I I i l l i I I NOME I rJ i RFP RECIRC C0erra0L 1 avl 7s3B DUMPS 70 MAIN i is0NE i l FuDWATER SYSTEM l l 1 I I I VALVE FV17835 l CONDENSER R I I I I I I I l l l l l FEEDWATER NEATER TRAIN I REDUCE MAIN r w suSER R I i l B uvEL, DRAIN AND I VACIRM i l l l l l I 1 I i l DUMP VALVES 1 I I i 1 1 1
l CIDSE NORMAL DRAINS TO 1 NOINE I I
- 1 I I Lvl5063 VALVE l l LV15143 VALVE I NEATER TRAIN B l l
- i 1 I LV15235 VALVE I i l l 1 1 l I LV15325 VALVE I l l -
4 I I i 1 I I I 1 I I I I I NV1373B VALVE I EXTRACTION STEAM DESIPS l NONE 1 I I I NV13s45 VALVE I TO MAIN CONDENSER R I I I l l l NV13553 VALVE I I I I l l I W13775 VALVE I I 1 I 1 l 1 1 l 1 i NV13s7B VALVE l l 1 I i l i I NV13663 VALVE l l 1 l i l i NV13593 VALVE l i i Nvl3675 VALVE I i 1
' I I l l 3 I I I I I IIONE I I I l MOISTURE SEPARATOR I DRAIN VALVES FAIL I O 1 , 1 I l l DRAIN CONTROL VALVES I CIASED 1 I I I i l I LV13635, LV1364B 1 I i
I I MAIN TURBINF. TRIP IF A, I 1 I ta. I I I I B AND C DRAIN VALVES I I 1 3 I l I CLDSED 1 1 i - 1 I 1 I I l l l 1 I I I i 1 1 I I I I i i i I I i l i I I I 1 I I I 1 1 1 '
l I I I I I I I I I i 1
! I I I i l i I i i I I I I I I I 1 1 1 1 I i 1 I
I I I I 1 I I i i i 1 1 I I I I I I I I I I I I I I I I 1 I I I l 1 I I i 1 1 1 I I I I I 1 1 I 1
I I I I I I I I I I I l I I I C-11
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APPEND 11 C Coret0N POW.R/ SYSTEMS CONTROL FAILt2tE ANALYSIS SECONDARY EFTECT COMBINED EFFECTS l SYSTEM lCOMPONENTDESCRIPTION PRIMARY EFFECT l l l l i i l i i i 1 pg l NOME I RECIRCUIATION RUNBACE I I i uTRACTION STEAM SYSTEM I PANEL ltC653 l DUMP EX18 ACTION STEAM l l l W1373A VALVE I TO MAIN CONDENSER A I I l I i i p l3ssA VALVE I l l l l l l NV1355A V EVE I l l l l l l NV1377A VALVE I 1 l l 1 1 I pl3a7A VALVE l l l l 1 1 I W 1366A V EVE I I l 1 1 I I NVl359A VALVE 1 l 1 1 I l l NV1367A VALVE 1 I l i I I I I I I l i FEEDWATER VENTS. DRAINS l LV1506A VALVE I CIASE NOSHAL DRAINS 70 1 NOME I I I
I I AND NEATERS SYSTEM i LV1514A VALVE I FEEDWATER NEATER TRAIN Al i 1 l l l LV1523A VALVE I I I I I I l LV1532A VALVE I I l l l l 1 1 I I I l
- I I I i 1 !
I d) i REACTOR FEED PUMP 1 PANEL 19C653 REACTOR l REACTOR FEED PLSIP 1 RECIRCUIATION RUNBACE l l 1 f l TURAINE STEAM SYSTEM i F E D PUMP TURRINE I TURBINE B STOPS. FIM i l 1 i I l CONTROL CIncu!TS I DECREASES 70 851. l I l
, I i I i 1 I I g l PANEL 19C653 l PUMP STOPS IF AVAILABIJL I NOME I I l l TuRsINE-cENERATOR I
~
l SYSTEM i NvDaAULIC FLUID PUMP l PUMP IBril6 STARTS I i l l l l 1APil6 I WTOMATICALLY (IRJ444) l l l l 1 I 1 AUTOMATICALLY (IRJ484) l l l t i I I i 1 1 I i 0FrcAS SYSTEM l PANEL IBC653 i LOSE STEAM JET AIR l MAIN TURRINE TRIP IN l l 1 I l CONTROL Clacu1TS 1 EJECTOR I 10 11 MINUTES I 1 l l CONTROL CIRCUIT FOR l l l l I
l l 1 VALVES NV56438 l l l 1 j i l I W5649-1. W 5647 I I I i
! I I W5668 I I i i i i l i i i l i
- I I I I I I I I I I I I I i i i I i 1 1 I I I I I I I I l l l 1 1 I I i 1 I i l 1 i
- I I I I I I I
' I I I I I I I I I I 1 1 1- 1 I I I I I I I I I I '
I I I I I I i 1 I i 1 1 I i 1 1 l 1 1 1 1 I I I l C- I f ,
APPENDIX C Coret0N POWER / SYSTEMS CONTROL TAILURE ANALYSIS COMBIND EFFECTS l SYS m l COMP 0nNTDESCRIPTION PRIMARY EFFECT l l SECONDARY EFFECT l l l 1 I l 1 l l 1 l MAIN TURBINE TRIP l I SAFETY AUXILIARY l COOLING WAm PittP l IASE RNR MAT l NONE I l l l COOLING SYS m l ICP210 (IAOP A) l EXCNANGERS COOLING AND l lg I I I TURBINE COOLING IF AUTO l l l lO l l l TRANSFER TO STAND 8Y l l l l
l* l 1 IAOP NOT AVAIMSLE l l 8 l l l l l 1 00A402) PUMP IBP210 l 18 l __ l i I (10A404) PUMP IDP210 l l l l
l l 1 I l 1 l l l I I l IASS OF 3U510A403 1
l TRANSFERS DRvWELL COOL- l l l l 1 l l I IRS TO REACTOR AUXIL- l l l l 1 l l l l l IARY COOLING SYS m l l I I I 1 I l 1 l MAIN TURBINE TRIP l
= l SAFETY AUXILIARY l TACS IAOP DISM VALVE I INITIATE TACS IS0!ATION l MAIN TURRINE TRIP I l l t 3 o g COOLING SYS m i NV2496C l SACS STANDtY IAOP i START 3 AUTOMATICALLY l l i I m o I i I l 1 I
- I i 1 I l l A I SAFETY AUXILIARY l BAl uY PANEL ICC655 i SACS PUMP ICP210 STOPS l NOME l
l l 1 9 g i COOLING SYS M l AND ICC652 l I I I l l E
- I I l
- 3 l SACS IAOP A SUPPLY l INITIATE IAOP A I 'l l l l l l
l $
l l VALVE CONTROL CIRCUITRY l IS01ATION l NV2522C 1 1 l l l l l 1 I I l 1 1 l a l COMPRESSOR A CONTROL l COMPRESSOR A STOPS l NONE l I l PRIMARY CONTAllRENT I I I i CIRCUITS l COMPRESSOR 5 STARTS I l I INSTRUE NT GAS SYS m l l AUTOMATICALLY I l I E l l i l 1 1 I 1 l l 1 1 I i l l l VALVE FAILS CIDSED, I l l SACS IAOP A SUPPLY l NONE l o _ i SAFETY AUXILIARY l l 1 l r- y l COOLING SYS m i VALVE NV2522C i ISOIATING 1AOP A IF l AVAIIAB12 STANDBY l l l T I I 1 .
l LOOP STARTS AUTO- l l l l M M i l l l l l 3 l 1
l I
l MATICALLY I I I I 1
1 I I l l l 1 I RECIRCULATION RUN5 ACE I l REACTOR FEED PUMP l REACTOR FEED PUMP l REACTOR FEED PIRIP l RECIRCUIATION RIRIBACE I
l N I TuRnINE STEAM SYS m l TURBINE C CONTROL l TURSINE C STOPS. FIAW l l l l I I l Q $ i i CIRCUITS l DECREASES TO B51.
l I I I I m
- I l l l REACTOR SCRAM TRIP l l I o 3
l POWER RANGE NEUTRON I NEUTRON MONITOR l CIRCUITRY l (CNANNELS 51 AND B2) i I I l l MONITORING SYSTEM l I l l I e # I I I i 1 y 0 l l l REACTOR SCRAM IF CNAN- 1 i NEL Al OR A2 TRIPPED l l l l ma ya1
- - l I
l l l l l 1
C-22.
i
m * .
ArrENDIX C Corm 0N POWEa/STSTDIS CONTa0L FAILUaE ANALYSIS ralmaT E m CT SEcomeAaT E M CT COMnINED EFFECTS l STS m l COMr0NErr DESCRIPTION l l l l l 1 I I I 1 1 1 I N I TEEM m m STS m i nFr mEclac CONTn0L I TV17a3C ouMrs 70 MIN I NONE I NONE I I VALVE IV17a3C l en m m e C l l 1 I I l I I I I I I I l l 8 mamm NEAm TRAIN l mEDUCE min enmwn C 1 1 l
l C uvEL, maAIN AND l VACUUM i l I l I I puMr VALVES l l l I I I I I I I I I I
I LV1506C VALVE I CloSE NonMAL DaAINS 70 i NONE I I I l i LV1514C V E W l EAm TRAIN C i l i 1 l 1 1 l I I LV1523C VALVE l l l l l I l l LV1532C VALVE i i i l l I 8 I l I i 1 NV1373C VALVE I EXTaACTION STEAN DUMPS l NOME l TO MAIN en m MSta C l l l l 1 l wisasC VALW l I h l I W1355C VALVE l l l l l 1 O I l n t377C VALVE l l
- I NVI347C VALVE I l I I
- I d- 1 I W1366C VALVE l l 8 l I u. I l I p l359C VALVE I l l l y i l 1 l l NV1367C VALVE I l l i I
~
l I I I I l NOME I I j l l 1 MOISTUaE SEPAaATOs i DaAIN VALVES FAIL I CIDSED I l l I I I naAIN C0Kfn0L VALMS I LV1363C, LVl364C l 1 l 1 1 1 I I I MAIN TUanINE Tatr IF l i I I I A, a AND C DaAIN VALWS l l 1 I I I i Clasto I I I i i i i l i l 1 i i l 1 1 i NUCuAm 30Ima i naAIN VALW S m21-F033, l VALVES FAIL OPEN I NOME l a21-F069, n21-F073 l l l l i i i INSTaulENTATION l l t i I I mEsuCE COWoENSta VAClam l I I I I i 1 I .
I l i i i I I i
l i l I i I i i l I I I I I I i I I I I 1
I i i i i 1 1 i 1 1 I i I I i I I I I i
- 1 i i i l i i i i I I I l i 1 I I I I i I I I I I I i 1 1 4
I I I I I I I I I I I I I
- 1 I I I I i I I C- 13
APPUDII C C0pMON FoER/STS"JIS CONTROL FAILtRE ANALYSIS ConsINED E m cts lConroNENTDESCalrTIONrnIMAar E m CT SECONDamT frFECT l l SYSTEM l l l l t i i i i i i l BECIBCouTION menarr 1 NgCItcuuTION manner i PJ l REACTot TEED PtMP l PA m L ICC653 i REACTom FEED FunP 1 I I TimaINE STEAn sTSTEM i mEACTom Fun runr i TunsINE C SToe$ l l l I I I Tunsin C Coutmot 1 I I I I i l CInCu1TS I I I I I I I l . I I I 1 CNItun mTEa srsiel I IF 120VAC PANEL IAST I DONE l l i l PANEL ICC653 l
l 1 l mEClaCuuTION rune A i MIN VALVES FAIL OPU l l i i i Motom COOLING m Tsa i mACEUP VALVES FAIL I l l 1 I I VALVES I r u n, OTHE WISE FAIL I I l l l t MVest4At MIN I AS IS l l I I I NVsst4A2 MIN I I l l .
I I I I NV9514s1 aACEur I I i 1 I I l NVs5:4s2 aACEur I i i i i i l i i l i i i FuDmTEa SYSTEM 1 PANEL ICC653 i CIASE NORnAL DRAINS 70 l NOME I l l 1 l LV1506C VALVE I NEATER TRAIN C i I I i f l I LV1514C VALVE l l l l l 00 1 i LV1523C VALVE I I i i 1 -j- l 1 LVtS32C VALVE I DisIP HTRACTION STEM l NONE I I I I I I to mIa enam-na C l l l 1
' 1 I W 1373C VALVE I I I I I U i i NV13ssC VALVE I i 1 1 1
l l N71355C VALVE I i i i I I I W 1377C VALVE I I I i i 1 i NV1387C VALVE l l l l I l NV1366C VALVE I l l l 1
I I NV1359C VALVE I l l l 1
l 1 NV1367C VALVE I I I I l
I I I I I i l 1 I I I I i 1 I I I I I i 1 I I I I I I 1
I I I I I I I
i 1 I I I i l I I I I I i I i i i i 1 1 I I I I I i 1 1 I
I I I I I I I I I i 1 1 1 i
I I I l i I l I i l i l I i l I I I i l I
l l i l i l i 1 I I I 1 1 I
I I I I I I I I I I I l I
C-14 i
APPENDIX C CoeloN POWER /SYSTDRS CONTROL FAILUnE ANALYSIS SYSTDs PRIMaaY E m CT SECONDARY ErrECT COMsINan ErrECTS l lCOMPONENTDESCRIPTION l l l l 8 i i i i 1 i 1
l SAFETY Aux 1LIAar i COOLING WA m rump I toSE Rest NEAT I NoNE I rom COMsINED t m CTS, i I l C00LINc STS m i IDP210 (IDoe s) 1 ExCP. ANGERS COOLING AND 1 i SEE SECTION 4 l l l l l TunsINE C00LINc tr AUTO I I I I I I I TRANSFra TO STANoeY l l 1 1 I I . I IDOP NOT AVAllABIZ l l I l f I i 1 (10A410) PtesP IAP210 1 I I I l l l (10A403) PUMP ICF210 1 I I o I i 1 I y 1 1 1 1 4 I I I IDSS Or auS 10A404 I I l l o 1 I I TRANSFERS DaTWELL COOL- 1 I I I -
1 I I ERS 70 REACT 0m Au1IL- l l l l l 1 I IAaY COOLING SYSTEM l 1 1 I I I I i 1 1 1 I SAFETY AuxtuAaY l TACS IDOP DISM VALVE I INITIATE TACS ISOLATION I MAIN TUnBINE TRIP l MAIN TUmSINE TRIP 1 I . ca i C0ouMG SYSm i NV2696D I SACS STANDBY IDOP l l l 1
- I I I STAaTS AUTOMATICALLY I i 1 I o y i I I I
I I
I I
I I
I s o I I i * -
1 I I I I I I M i l I I i l 1 0 1 I I I I I I 1 I I I I I I cJ l SAIITY AUEILIARY I BAI!1Y PANEL IDC655 i SACS PUMP IDP210 STOPS I i 1 I # 1 COOLING SYSTEM i AND IDC652 1 1 1 1 I
- I i 1 1 1 1 l 'g i I SACS IDOP 3 SUPPLY I INITIATE IDOP R I NOME I I i - 1 I VALVE CONTROL CIRCUITRY I ISOIATION I i 1 1 1 i NV2522D l l l 1 1 I I I I i l 1 1 I i 1 1 I I I I i 1 1 I
! 1 1 1 I i 1 1 I f l PRIMAnt CONTAllBENT l COMPRESS 0m B CONTROL i COMPer u m B STOPS l NOME 1 1 I o l INSTRinsENT GAS SYSTEM i ClaCUITS l COMPRESSon A STAaTS I I I J l
- I I I AUTOMATICALLY I I i I $ I I i i i i 1
1 I I I I I I i 1 1 I I I i ,, I PROCESS RADIATION I 0FFCAS MIGN RADIATION I CIASE SMUTOFF VALVE OF 1 MAIN TURBINE TRIP IN l MAIN TUmSINE TRIP IN 1 I a m 1 MONIT0aING SYSTEM i MONIT0aING CIRCUITRY I THE OFFCAS LINE 70 1 10 1 1 MINtrTE I 10 t i MINUTE I
! I r8
- 1 1 1 STACE. LOSE CAPABILITY l 1 1 i $
- I TUmstNE.cENEaATOs i TUmSINE VitaATION 1 TO TRIP ON MIGN TUmSINE 1 l l
- I -
2 i SYSTEM i SWITCM TSI I VIsaATION. LOSS OF l l 'I j i ? -
1 I I INDICAT0aS I I I I
I i 1 1 1 1 I S' r J l I I I I I C-15
.* \
9' APPENDIX C Cor000N POWER / SYSTEMS CONTROL FAILURE ANALYSIS COISINED EFFECTS SYSTEM lCOMPONENTDESCRIPTION PRIMARY EFIECT l SECONDARY EFFECT l l l i i i 1 I l 1 l l i N 1 1 PANEL IDC653 l l I I 1 NYDRAUtic FLUID PUMP l PittP STOPS IF AVAIIABIA l NONE l 8 TtmsINE-cENERATOR I i l I l SYSTEs l ISPIl6 i PUMP IAPil6 STARTS i I I I I l i l l l l I I l PANEL IDC653 l I IDSE CAPABILITY TO TRIP l DISABIZ MAIN TURBINE l DISAtl1 MAIN T1RBINE l l l TuRalNE ELECTRICAL l I TtRBINE ON 1 TRIPS AS NOTED IN I TRIPS AS IIOTED IN l l l TRIP CIRCu17 1 l I) IDW OIL PRESS 1 PRIMARY EFFECT I PRIMARY EFFECT
! l I l l i (TURsINE) l l l I I l 1 I 2) IDW OIL PRESS I l '
l 1 (cENERATOR) l l l I
l l 1 l 3) IDW NYD FLUID PRESS l 1 i l l l l l i I 4) MOISTURE SEPARATOR A 1 i g i I I I IDW IIVEL I l l i l i l @ l l l 5) MOISTURE SEPARATOR S [
I I f I IDW IIVEL i I t I l 1 6) SMAFT OIL PUMP DISM i i i I q l l l i i PRESS l i g i l l I 1 1 7) MIGH EXMAUST N000 A 1 l TEMP 1 1 1 I I I 1
1 a) ulcM EXMAUST NOOD B I I I ~
l l 1 I
I I I I ne i I l
I 9) MIcM EINAUST NOOD C 1 1 l i I .
TEMP l 1 1 1
l l 1 l l l l l 110) SHAFT VOLTAGE TEST I i TDLEN019 l l l j i l i l I III) IDSS OF STATOR l l I I I i I I COOLING 1 I I l l 1 i 112) TimuST aEARING WEAR I i l i AND IDW OIL PRESS I l 1 I i i I I t
l 113) CUSTOMER TRIPS I 4
I l l 1 i i 114) IDW MAIN CONDENSER l i I Vacuum i i i 1 1 1 1 l i i lis) MECHANICAL SOLENOID l i I TRIP l l l 1 I I I I I I I I I l 1
1 IDSE CAPARILITY 70 TRIP l I I l CONDENSATE SYSTEM 1 PANEL IDC653 I REACTOR FEEDWATER PUMP I i 1
. I I l PRIMARY AND SECONDARY l l TURBINE ON IDSS OF 1 l
! I I I CONDENSATE PUMP TRIP l l, ASSOCIATED PRIMARY OR l l l 1 l CIRCUITRY l l l I l l l SECONDARY CONDENSATE l
i PUMP l i l l 1 I I 1
i I i l I
I' I I i l 1 1 l' I I I I I I I l' I I I I I C-2(.
l i
,, ,g APPENDIX C Coret0N POWER /SYSTEftS CONTROL FAILURE ANALYSIS SECONDARY EFFECT COMBINED EFITCTS SYSTEM lCOMPONENTDESCRIPTION PRIMARY EFFECT l l l l l i I I i i i 1 I RECIRCULATION RUNSACE l RECIRCULATION RUNSACE I ,
i mACTOR FEED PUMP l REACTOR FEED PtatP l REACTOR FEED PUMP A I l TURRINE STOPS, FIDW l l I I TURBINE STEAM SYS M l TURBINE A CONTROL 1
i DEcRE.ASES TO 851 l l 1 I l l CIRCUITS - Corraot l l l PANEL 1ACl32 I i I o f I i i i l i I
F m I I I I I I '
i
- o I i i i i I i 4 i l l l 1
I A - 1 1 I i i l i l
I o
I I REACTOR FEED PUMP l M ACTOR FH D PUMP l REACTOR FEED PlatP l RECIRCUMTION RUNRACE l RECIRCUIATION RUNSACE l
l l
l TURalNE C CONTROL l TURBINE C STOPS, Tim l I l TuRalNE STEAM SYSU M l 1 8 CIRCUITS - PANEL ICCl32 l DEC MASES 70 851 l l l i I l I I l l 1 1 DISABIZ MAIN TURSINE I l l TupsINE-cENERATOR I TURBINE MCNANICAL TRIP l IDSE CAPARILITY 70 l l i SOENOID l MECMANICA RY TRIP l TRIP I i SYS M I l l i l i TURsINE l g i i i i I l _ i i l l i TupsINE TRIP CIRCUITRY l IDSE CAPABILITT To i m l l E ECTRICA RY TRIP l l l l p I l l l I I TURsINE I l 0 1 I I I l 1
1 I I l I TURBINE BYPASS VALVES l TURBINE BYPASS VALVES I MAIN TURBINE BYPASS l 1 IEEDWA M CONTROL l VALVES FAIL OPEN I l i TRIP CIRCult l FAIL OPEN l l SYSTEM I I I i 1 I I l l l ulcu uVEL "C" TRIP l MIGN E VEL "C" TRIP I l l l l l 1 l CIRCulTRY l l l l IF "A" OR "B" TRIPPED, l l l l l l 1
I THEN TRIP REACTOR I l 1 1 l l l NEFM ATER TURRINES AND I l l l l l 1
l l MAIN TURBINE . l l l I I l I I l 1 l MAIN YtNtBINE TRIP ON l l l l l REACTOR FEEDWATER PlatP 1 FEEDWATER FIDW l I HIGH WATER EVEL l l 1 l CONTROL CIRCUITRY "C" l INCREASES i -
1 I I l 1 l t l I REACTOR FEED PUMP l l I I 1 l TURBINES A, 5 AND C AND l l 1 e l l l l l I MAIN TURalNE ulcN WATER I i ,
i l l nVEL "a" g TRIP l l l I l l i l l I I 1 l l l l l l TRIP REACTOR FEED PtMP l l l TURsINES A, 5 AND C AND 1 1 l l l l I l l 1 MAIN TURBINE IF "A" i I l
l l AND "C" HICH WATER l l i l l l l I I MVEL TRIP I 8 I l l I i l i
l 1 i i i l l l C-27
e -9 .s 1 9
APPDIDIX C Corte0N POWER /STSTDeS CONTROL FAILLEtE ANALTsIS SEenamaar EFFECT COMBImD E m cts l l sTsTDt lCostP0mMTDESCRIPTION PRIMART EFFECT l l l l l i I I i i l l WOME I MAIN TURRINE TRIP 1 i i TURsIn -cENERATOR I TISBINE EMERGENCT OIL l No BACKUP TO TURBINE I I I I I srs m i Pt4IP 10Pil2 l MAIN SEAL OIL Ptter i
i O i I i 30ei73 cion2323 i 1 .
I I I I @ l i I I
I I I I I 3- 1 I i I A i i i I I I I I l i 1 O I I i i I - 1 I I REACTOR M D PUMP R I RECIRCuuTION RUNRACE I RECIRCUMTION RWBACE I i i REACTOR m D PUMP I REACTOR m D PUMP c0 i TutsINE a CONTROL I TutsIn STOPS, FIm i I i .
I 1 TutsINE STEAM sTs m 1 I CIRCu1Ts - CONTROL i DEce m r= To ast i I I 1
l
" l l PANEL 19C132 I I I I I
^ I i i i I I I I 4 1 O I I
i i
1 i
1 l I i I l i I 1 i l i I I I I i 1 I l MAIN TURRI m TRIP l I l FEDWATER CONTROL I MIGN IIVEL "B" TRIP 1 RIGIl 114L "B" TRIP 1 N001E I I I I l l sTsTot i CIRCu1TRT I IF "A" OR "C" TRIPPED, I i 1 I I I i T m N TRIP REACTOR FEED 1 1 I I g i l I I I Platr TURBINES AND MAIN I I i _. I I TutsINE I I i I m i I I I i I I I 1 g i l I i I p i i I I I I I
! - 1 i MAIN TURRI m TRIP DN I 1 I I I REACTOR M DWATER PUMP l FEEDWATER FIM l INCA m sa i NIaN WATER uvEL I I l l CONTROL CIRCul m "a" 1
I I I I i I I i I I I I l I i I i i i i I I I i l I I .
l I I I !
1 I I I '
I I I I 1 I I 1 1 1 I i 1 1 I I I I I I I I I I I I I I I I I I i 1 1 I I I I I I I I I I I I I I I I I I i 1 I I I I I I I
, I I I I I I I I I I I I I I I
I I I I i 1 1 I I I I I I I C-28
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