ML17227A402: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(6 intermediate revisions by the same user not shown)
Line 2: Line 2:
| number = ML17227A402
| number = ML17227A402
| issue date = 04/24/1992
| issue date = 04/24/1992
| title = In-House Event Rept 92-023:on 920421,Turbine Generator Failed to Trip During Manual Reactor Trip.Root Cause Analysis Still in Progress.Solenoid Valves Removed & Sent to Independent Lab for Analysis
| title = In-House Event Rept 92-023:on 920421,turbine Generator Failed to Trip During Manual Reactor Trip.Root Cause Analysis Still in Progress.Solenoid Valves Removed & Sent to Independent Lab for Analysis
| author name = SAGER D A
| author name = Sager D
| author affiliation = FLORIDA POWER & LIGHT CO.
| author affiliation = FLORIDA POWER & LIGHT CO.
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 6
| page count = 6
}}
}}
=Text=
{{#Wiki_filter:ACCELERATED Dl/RIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION        DISTRI BUTION SYSTEM    ( RI DS )
ACCESSION NBR:9205010133              DOC.DATE: 92/04/24    NOTARIZED: NO            DOCKET FACIL:50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co.                      05000389 AUTH. NAME .          AUTHOR AFFILIATION SAGER,D.A.          Florida    Power & Light Co.
RECIP.NAME            RECIPIENT AFFILIATION
                        - Document      Control Branch (Document    Control Desk)
==SUBJECT:==
In-House Event Rept 92-023:on 920421,turbine generator failed to trip during manual reactor trip. Root cause analysis still in progress. Solenoid valves removed & sent to independent lab for analysis.
  .DISTRIBUTION CODE: IE22D          COPIES RECEIVED:LTR      I ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
l    SIZE:
RECIPIENT              COPIES          RECIPIENT            COPIES ID  CODE/NAME            LTTR ENCL      ID CODE/NAME        LTTR ENCL            D PD2-2 LA                    1    1    PD2-2 PD                1      1 NORRIS,J                    1    1                                                D INTERNAL: ACNW AEOD/DOA 2,
1 2
1 ACRS AEOD/DSP/TPAB 2
1 2
1 AEOD/ROAB/DSP                2    2    NRR/DET/EMEB 7E          1      1 NRR/DLPQ/LHFB10              1    1    NRR/DLPQ/LPEB10          1      1 NRR/DOEA/OEAB                1  ". '1    NRR/DREP/PRPB11          2      2 NRR/DST/SELB 8D              1    1,    NRR/DST/SICB8H3          1      1
            ~/~S.T PLB8D1              1    1    NRR/DST/SRXB 8E          1  '  1 REG  FILE      02          1    1    RES/DSIR/EIB            1 FILE  01          1    1 EXTERNAL: EG&G BRYCE,J.H                3    3    L ST LOBBY  WARD      "1      1 NRC PDR                      1    1    NSIC MURPHY,G.A          1      1 NSIC POORE,W.                1    1    NUDOCS FULL TXT          1      1 D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR              32  ENCL    32
P.O. Box 128, Ft. Pierce, FL 34954.0128 g g I 4-8Q.
L-92-129 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.            20555'E:
St. Lucie Unit                  2 Docket No. 50-389 Event Date: April 21, 1992 Turbine        Tri Failure Please    find attached the preliminary internal problem report of our plant event which occurred on April 21, 1992. Pursuant to 10 CFR 50.73 a Licensed Event Report will be submitted within 30 days of the event date.
Please contact us          if there    are any questions about          this submittal.
Very  truly yours, Vice President St. Lucie Plant DAS/JJB/kw cc:  Stewart D. Ebneter, Regional Administrator, Region                            II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant DAS/PSL 4681-92 5'205010133 5'20424 PDR  ADOCK 05000385' PDR an FPL Group company
ST. LUCIE PLANT IN HOUSE EVENT REPORT 92-023 TURBINE GENERATOR FAILED TO TRIP FOLLOWING MANUALREACTOR TRIP UNIT: 2                                        DATE: APRIL 21, 1992 I. INITIALPLANT CONDITIONS On April 21, 1992, St. Lucie Unit 2 was shutting down for a scheduled refueling outage.
Reactor power was at approximately 12%.
II. EVENT DESCRIPTION A scheduled Reactor-Turbine shutdown was in progress on Unit 2. During the shutdown, power moved to the top of the core as expected.          Existing procedural guidance on Axial Shape Index (ASI) was being employed to minimize its affects.
When three out of four Local Power Density Pre-Trips on thc Reactor Protection
.System came in, the Nuclear Plant Supervisor (NPS) instructed the Reactor Control Operators to manually trip the Unit. A manual reactor trip was initiated, but the turbine did not trip. Several attempts were made to trip the turbine using the Turbine Trip push button with no success and thc Nuclear Watch Engineer tripped the turbine from the front standard.
II I. EVENT SEQUENCE St. Lucie Unit 2 was performing a scheduled reactor shutdown for refueling purposes. During the plant shutdown ASI approached its upper (negative) limit.
Coordination at controlling ASI within limits and maintaining reactor coolant temperature due to Xenon building in became more difficult. When reactor power was decreased to about 12%, control rod insertion had no effect on making ASI less negative and three of the four Reactor Protection System Local Power Density pre-trips came in. At this point, the NPS instructed the Reactor Control Operators to manually trip the unit and the manual reactor trip pushbuttons on RTGB (Reactor Turbine Guage Board) 204 and RTGB 201 were depressed at 0238 with the turbine trip pushbutton on RTGB 201 being depressed approximately two seconds later; however, the turbine did not trip. Standard Post Trip Actions from Emergency Operating Procedure (EOP) 1 were implemented.
When the turbine trip pushbutton was depressed, thc Governor Valves indicated closed but the Throttle Valves, Reheat Valves, and Intercept Valves indicated open.
Auto Stop Oil and the Emergency Trip Header indicated pressures of approximately 100 psi and 2000 psi, respectively.      The megawatt recorder indicated ninety megawatts. Several morc attempts were made to trip the turbine using the pushbutton, but they were unsuccessful. At this point, the Reactor Control Operator opened the Generator output Breakers 8W52 and 8W49, secured the voltage regulator, stopped the Digital Electrohydraulic (DEH) pumps, closed the Main Stcam Isolation Valves (MSIV), and broke condenser vacuum.
IHE¹ 92-023, 4-24-92 SHEET  1 OF 3
III. EVENT SEQUENCE (cont'd)
The Assistant Nuclear Plant Supervisor instructed the Nuclear Watch Engineer to trip the turbine from the Front Standard.      At 0241 all the turbine valves closed.
EOP-2, Reactor Trip Recovery, was then completed wi'th two sets of satisfactory Safety Status Checks, the plant was stabilized, and the Turbine Shutdown      Procedure'as
                                                                                              'unction re-entered.
IV. EVENT EVALUATION A)      PLANT RESPONSE The plant response to this event was as expected with the exception of the failure of the turbine to trip. Upon the reactor trip signal, the four Control Element Drive Mechanism (CEDM) Bus undervoltage relays should de-energize. This should energize (open) the 20 ET solenoid valve and drain the electro-hydraulic fluid from the emergency trip header ( Sec attachment ¹I). The 20 AST trip solenoid coil should simultaneously energize, pull down the mechanical trip lever, and dump the auto stop oil header. Decreasing auto stop oil pressure allows the Interface valve to open and dump the electo-hydraulic fluid emergency trip header.              When auto stop oil pressure  decreases  to 45  psi, pressure switches 63-1  AST  and 63-2 AST should lock in, actuating  a  generator    primary  lockout  which  trips the  generator output breakers.
The same result should be obtained when attempting to trip the turbine via the Turbine Trip Pushbutton. A multi-discipline team is investigating to determine why the turbine failed to trip when the trip signals were initiated.
B)    SAFETY SIGNIFICANCE The plant response to this event is bounded by section 15.1.5 of the PSL Unit 2 Final Safety Analysis Report (FSAR), "Increased Heat Removal by the Secondary System"as further described below..
12% Power Trip, No Operator Action Scenario.
MSIV's auto close at 600 psig. Cooldown terminated.
Core decay heat released via Main Steam Safety Valves (MSSV)
Cooldown rate bounded by limiting FSAR cooldown event.
100% Power Trip, No Operator Action Scenario.
Possible Safety Injection Actuation-Signal (SIAS) but no actual injection.
Automatic MSIV closure after 66 seconds.
Fuels RETRAN analysis validates that no core damage will occur.
100% Power Trip with multiple FSAR Chapter 15 Accident Scenario.
Operators trained on the simulator for multiple failure events beyond design basis.
Excess stcam demand events are simulated and procedurally addressed by the EOP's.
IHE¹ 92-023, 4-24-92 SHEET 2 OF 3
IV. EVENT EVALUATION(cont'd)
C)      ROOT CAUSEANALYSIS A multi-discipline Turbine Investigation Team is performing a root cause analysis of this event. A Letter of Instruction, 2-LOI-T-67, "Evaluation of Turbine Solenoid Trip Function," was written to evaluate the operation of the turbine manual and automatic trip functions. Deficiencies identified are noted below. Root cause analysis is still in progress.
D)      DEFICIENCIES IDENTIFIED Testing of thc 20 ET Trip solenoid, 20 AST solenoid valve, and the 20 OPC 1 and 2 solenoid valves was performed in accordance with 2-LOI-T-67. The results of this evaluation are as follows:
: 1) 20 ET Solenoid valve Thc original solenoid valve was removed to prescrvc the "as found" condition of the valve. A new solenoid valve was installed and tested satisfactorily. This verified the 20 ET electrical circuits did not contribute to the failures.
: 2) 20 AST Trip Solenoid The solenoid was tested numerous times with two    of thc tests indicative of intermittent circuit problems. A loose connection was found on relay 62 ASTX / pin 6. This connection is in the circuit for all 20 AST trip functions.
Further troubleshooting is continuing.
: 3) 20 OPC 1 and 2 Solenoid Valves One OPC soleniod valve was removed prior to testing for potential failure mode analysis. Testing of one original and onc replacement OPC solenoid valve indicated acceptable operation of the OPC circuits.
V.      CORRECTIVE ACTIONS
: 1. The original 20 ET, 20 OPC-1 and 20 OPC-2 Solenoid valves have been removed and were sent to an independent laboratory for analysis.
: 2. Maintenance is continuing to investigate thc root cause of the intermittent electrical problems of thc 20 AST Trip Solenoid. The circuits of the 20 ET and 20 OPC 1 and 2 Solenoids are also being evaluated to ensure similar problems do not exist.
: 3. Nuclear Fuels is evaluating additional guidance    for ASI control at the end of core life.
: 4. Operations is evaluating additional guidance for EOP-1, "Standard Post Trip Actions", on actions to take for  a reactor trip with no subsequent turbine trip.
IHE¹ 92-023, 4-24-92 SHEET 3 OF 3
e WESTINGHOUSE ELECTRO-HYDRAULIC CONTROL SYSTEM AND AUTO-STOP            OIL SYSTEM EMERGENCY TRIPS
: 1. LOW      AUTO-STOP OIL PRESSURE                      (2/3)
        ~ esatttt
: 2. REACTOR TRIP ('I)
Trtvt                                                            3. MANUAL TRIP                                                        SOLENOID TRIPS tvvaalra lS                                                I I    4. HI-Hl LEVEL IN ANY S/G
                        ~4 I
I I
I I
1 . REACTOR TRIP (A)
: 2. ELECTRICAL OVERSPEED
: 3. LOW EH FLUID PRESSURE
                                                                                                                                                                          ~
I                                                                          4. MANUAL wwat alar                stasttw TTLTa
                              ~                                  3 I
: 5. ETC.
I                                                                              vaccw Z~                                                              I                                                                              tav g                          la                                      l                                  AUTO STOP OIL I                                  PRESSURE SWITCHES CO P L I
I                                                      (3)                          ~tatta Lao aa a. OL tat/
l                                                          ~ ace vaLTC ~
            ~ \rtact tt vatvt                                                  I tvt altar w                                I          I I          I l          I I            I I            I aavt awa            ~ s las ILW                          I T Jtrt 5'7      tvt at taa w I            l Tat Tt                    I I twaatwr    I~~QO g7 tas ttw                                          Iv atatra t a t ala Lava ~
Savtr              a
                                                                                                ~
g          ~
                                                                            ~ Ttawtaa              I I            I  ~tsttataca'vaLva      ~ avt 2o-i OPc                  0 ro Ovsaaaaa tva Qo-2 opg                                                          asf 0 Itat
                                                                                          ~ tL OVERSPEED        PROTECTION CONTROLLER 103K OF NORMAL SPEED                                                AVIO IIOPOILSY5ICII
: 2. GENERATOR OUTPUT BREAKERS OPEN ABOVE A PRESET POWER LEVEL
: 3. CHANGE IN GENERATOR OUTPUT AND TURBINE INLET PRESSURE}}

Latest revision as of 21:23, 29 October 2019

In-House Event Rept 92-023:on 920421,turbine Generator Failed to Trip During Manual Reactor Trip.Root Cause Analysis Still in Progress.Solenoid Valves Removed & Sent to Independent Lab for Analysis
ML17227A402
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 04/24/1992
From: Sager D
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-023, 92-23, L-92-129, NUDOCS 9205010133
Download: ML17227A402 (6)
v • d • e


Text

ACCELERATED Dl/RIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRI BUTION SYSTEM ( RI DS )

ACCESSION NBR:9205010133 DOC.DATE: 92/04/24 NOTARIZED: NO DOCKET FACIL:50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME . AUTHOR AFFILIATION SAGER,D.A. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

- Document Control Branch (Document Control Desk)

SUBJECT:

In-House Event Rept 92-023:on 920421,turbine generator failed to trip during manual reactor trip. Root cause analysis still in progress. Solenoid valves removed & sent to independent lab for analysis.

.DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR I ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:

l SIZE:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-2 LA 1 1 PD2-2 PD 1 1 NORRIS,J 1 1 D INTERNAL: ACNW AEOD/DOA 2,

1 2

1 ACRS AEOD/DSP/TPAB 2

1 2

1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 ". '1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1, NRR/DST/SICB8H3 1 1

~/~S.T PLB8D1 1 1 NRR/DST/SRXB 8E 1 ' 1 REG FILE 02 1 1 RES/DSIR/EIB 1 FILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST LOBBY WARD "1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 D

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32

P.O. Box 128, Ft. Pierce, FL 34954.0128 g g I 4-8Q.

L-92-129 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555'E:

St. Lucie Unit 2 Docket No. 50-389 Event Date: April 21, 1992 Turbine Tri Failure Please find attached the preliminary internal problem report of our plant event which occurred on April 21, 1992. Pursuant to 10 CFR 50.73 a Licensed Event Report will be submitted within 30 days of the event date.

Please contact us if there are any questions about this submittal.

Very truly yours, Vice President St. Lucie Plant DAS/JJB/kw cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant DAS/PSL 4681-92 5'205010133 5'20424 PDR ADOCK 05000385' PDR an FPL Group company

ST. LUCIE PLANT IN HOUSE EVENT REPORT 92-023 TURBINE GENERATOR FAILED TO TRIP FOLLOWING MANUALREACTOR TRIP UNIT: 2 DATE: APRIL 21, 1992 I. INITIALPLANT CONDITIONS On April 21, 1992, St. Lucie Unit 2 was shutting down for a scheduled refueling outage.

Reactor power was at approximately 12%.

II. EVENT DESCRIPTION A scheduled Reactor-Turbine shutdown was in progress on Unit 2. During the shutdown, power moved to the top of the core as expected. Existing procedural guidance on Axial Shape Index (ASI) was being employed to minimize its affects.

When three out of four Local Power Density Pre-Trips on thc Reactor Protection

.System came in, the Nuclear Plant Supervisor (NPS) instructed the Reactor Control Operators to manually trip the Unit. A manual reactor trip was initiated, but the turbine did not trip. Several attempts were made to trip the turbine using the Turbine Trip push button with no success and thc Nuclear Watch Engineer tripped the turbine from the front standard.

II I. EVENT SEQUENCE St. Lucie Unit 2 was performing a scheduled reactor shutdown for refueling purposes. During the plant shutdown ASI approached its upper (negative) limit.

Coordination at controlling ASI within limits and maintaining reactor coolant temperature due to Xenon building in became more difficult. When reactor power was decreased to about 12%, control rod insertion had no effect on making ASI less negative and three of the four Reactor Protection System Local Power Density pre-trips came in. At this point, the NPS instructed the Reactor Control Operators to manually trip the unit and the manual reactor trip pushbuttons on RTGB (Reactor Turbine Guage Board) 204 and RTGB 201 were depressed at 0238 with the turbine trip pushbutton on RTGB 201 being depressed approximately two seconds later; however, the turbine did not trip. Standard Post Trip Actions from Emergency Operating Procedure (EOP) 1 were implemented.

When the turbine trip pushbutton was depressed, thc Governor Valves indicated closed but the Throttle Valves, Reheat Valves, and Intercept Valves indicated open.

Auto Stop Oil and the Emergency Trip Header indicated pressures of approximately 100 psi and 2000 psi, respectively. The megawatt recorder indicated ninety megawatts. Several morc attempts were made to trip the turbine using the pushbutton, but they were unsuccessful. At this point, the Reactor Control Operator opened the Generator output Breakers 8W52 and 8W49, secured the voltage regulator, stopped the Digital Electrohydraulic (DEH) pumps, closed the Main Stcam Isolation Valves (MSIV), and broke condenser vacuum.

IHE¹92-023, 4-24-92 SHEET 1 OF 3

III. EVENT SEQUENCE (cont'd)

The Assistant Nuclear Plant Supervisor instructed the Nuclear Watch Engineer to trip the turbine from the Front Standard. At 0241 all the turbine valves closed.

EOP-2, Reactor Trip Recovery, was then completed wi'th two sets of satisfactory Safety Status Checks, the plant was stabilized, and the Turbine Shutdown Procedure'as

'unction re-entered.

IV. EVENT EVALUATION A) PLANT RESPONSE The plant response to this event was as expected with the exception of the failure of the turbine to trip. Upon the reactor trip signal, the four Control Element Drive Mechanism (CEDM) Bus undervoltage relays should de-energize. This should energize (open) the 20 ET solenoid valve and drain the electro-hydraulic fluid from the emergency trip header ( Sec attachment ¹I). The 20 AST trip solenoid coil should simultaneously energize, pull down the mechanical trip lever, and dump the auto stop oil header. Decreasing auto stop oil pressure allows the Interface valve to open and dump the electo-hydraulic fluid emergency trip header. When auto stop oil pressure decreases to 45 psi, pressure switches 63-1 AST and 63-2 AST should lock in, actuating a generator primary lockout which trips the generator output breakers.

The same result should be obtained when attempting to trip the turbine via the Turbine Trip Pushbutton. A multi-discipline team is investigating to determine why the turbine failed to trip when the trip signals were initiated.

B) SAFETY SIGNIFICANCE The plant response to this event is bounded by section 15.1.5 of the PSL Unit 2 Final Safety Analysis Report (FSAR), "Increased Heat Removal by the Secondary System"as further described below..

12% Power Trip, No Operator Action Scenario.

MSIV's auto close at 600 psig. Cooldown terminated.

Core decay heat released via Main Steam Safety Valves (MSSV)

Cooldown rate bounded by limiting FSAR cooldown event.

100% Power Trip, No Operator Action Scenario.

Possible Safety Injection Actuation-Signal (SIAS) but no actual injection.

Automatic MSIV closure after 66 seconds.

Fuels RETRAN analysis validates that no core damage will occur.

100% Power Trip with multiple FSAR Chapter 15 Accident Scenario.

Operators trained on the simulator for multiple failure events beyond design basis.

Excess stcam demand events are simulated and procedurally addressed by the EOP's.

IHE¹92-023, 4-24-92 SHEET 2 OF 3

IV. EVENT EVALUATION(cont'd)

C) ROOT CAUSEANALYSIS A multi-discipline Turbine Investigation Team is performing a root cause analysis of this event. A Letter of Instruction, 2-LOI-T-67, "Evaluation of Turbine Solenoid Trip Function," was written to evaluate the operation of the turbine manual and automatic trip functions. Deficiencies identified are noted below. Root cause analysis is still in progress.

D) DEFICIENCIES IDENTIFIED Testing of thc 20 ET Trip solenoid, 20 AST solenoid valve, and the 20 OPC 1 and 2 solenoid valves was performed in accordance with 2-LOI-T-67. The results of this evaluation are as follows:

1) 20 ET Solenoid valve Thc original solenoid valve was removed to prescrvc the "as found" condition of the valve. A new solenoid valve was installed and tested satisfactorily. This verified the 20 ET electrical circuits did not contribute to the failures.
2) 20 AST Trip Solenoid The solenoid was tested numerous times with two of thc tests indicative of intermittent circuit problems. A loose connection was found on relay 62 ASTX / pin 6. This connection is in the circuit for all 20 AST trip functions.

Further troubleshooting is continuing.

3) 20 OPC 1 and 2 Solenoid Valves One OPC soleniod valve was removed prior to testing for potential failure mode analysis. Testing of one original and onc replacement OPC solenoid valve indicated acceptable operation of the OPC circuits.

V. CORRECTIVE ACTIONS

1. The original 20 ET, 20 OPC-1 and 20 OPC-2 Solenoid valves have been removed and were sent to an independent laboratory for analysis.
2. Maintenance is continuing to investigate thc root cause of the intermittent electrical problems of thc 20 AST Trip Solenoid. The circuits of the 20 ET and 20 OPC 1 and 2 Solenoids are also being evaluated to ensure similar problems do not exist.
3. Nuclear Fuels is evaluating additional guidance for ASI control at the end of core life.
4. Operations is evaluating additional guidance for EOP-1, "Standard Post Trip Actions", on actions to take for a reactor trip with no subsequent turbine trip.

IHE¹92-023, 4-24-92 SHEET 3 OF 3

e WESTINGHOUSE ELECTRO-HYDRAULIC CONTROL SYSTEM AND AUTO-STOP OIL SYSTEM EMERGENCY TRIPS

1. LOW AUTO-STOP OIL PRESSURE (2/3)

~ esatttt

2. REACTOR TRIP ('I)

Trtvt 3. MANUAL TRIP SOLENOID TRIPS tvvaalra lS I I 4. HI-Hl LEVEL IN ANY S/G

~4 I

I I

I I

1 . REACTOR TRIP (A)

2. ELECTRICAL OVERSPEED
3. LOW EH FLUID PRESSURE

~

I 4. MANUAL wwat alar stasttw TTLTa

~ 3 I

5. ETC.

I vaccw Z~ I tav g la l AUTO STOP OIL I PRESSURE SWITCHES CO P L I

I (3) ~tatta Lao aa a. OL tat/

l ~ ace vaLTC ~

~ \rtact tt vatvt I tvt altar w I I I I l I I I I I aavt awa ~ s las ILW I T Jtrt 5'7 tvt at taa w I l Tat Tt I I twaatwr I~~QO g7 tas ttw Iv atatra t a t ala Lava ~

Savtr a

~

g ~

~ Ttawtaa I I I ~tsttataca'vaLva ~ avt 2o-i OPc 0 ro Ovsaaaaa tva Qo-2 opg asf 0 Itat

~ tL OVERSPEED PROTECTION CONTROLLER 103K OF NORMAL SPEED AVIO IIOPOILSY5ICII

2. GENERATOR OUTPUT BREAKERS OPEN ABOVE A PRESET POWER LEVEL
3. CHANGE IN GENERATOR OUTPUT AND TURBINE INLET PRESSURE
Retrieved from "https://kanterella.com/w/index.php?title=ML17227A402&oldid=2002735"