ML20129E033
| ML20129E033 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/03/1984 |
| From: | TOLEDO EDISON CO. |
| To: | |
| References | |
| PROC-840703, NUDOCS 8507300226 | |
| Download: ML20129E033 (50) | |
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POST TRIP REVIEW GUIDELINES July 3, 1984 Purpose The purpose of this booklet is to provide guidance on the performance of a review of a plant transient or trip. This is intended as generic guidance only and is not intended to cover every possible event. Each event should be reviewed on an individual basis with the scope of review determined by the type of event.
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8507300226 840703 hDR ADOCK 05000346 PDR
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e Transient analysis is basically divided into four phases:
1.
Data Collection 2.
Data Analysis 3.
Support of Outside Organizations 4.
Report Preparations and Review These guidelines will discuss each of the four phases.
1.
DATA COLLECTION 1.1 Information Available The capability to record and recall the plant info rma tion necessary to assist in the determination of the cause or causes of unscheduled reactor trips currently exists at Davis-Besse Unit 1.
Digital indications (e.g., on/off, open/close, etc.)
and key analog information are recorded by various transient monitoring systems during a reactor trip for subsequent analysis.
The Plant Process Computer records and displays both digital and analog information. The Data Acquisition and Display System (DADS) located in the Technical Support Center also provides a means for recording and displaying analog information. An additional source of analog information used to support post trip efforts comes from the Control Room strip chart recorders.
These systems provide the primary sources of information used for trip analysis at Davis-Besse Unit 1.
Plant Process Computer The Plant Process Computer monitors digital and analog informa-tion from all major plant systems. Approximately 2,500 digital points and 2,000 analog points are fed into the computer. Some of this information is manipulated and stored for plant performance monitoring purposes, and all of the information is available to the Control Room operator in various display formats. Three functions of the Plant Process Computer provide information useful for transient analysis ef forts. These functions include the Sequence of Events Monitor, the Post Trip Review, and the Alarm Printout.
The Sequence of Events (SOE) Monitor is designed to provide a sequential list of important plant events. All inputs to this function are digital. The list of monitored points is provided as Enclosure 1.
A change of state of any of these digital points is recorded in the SOE file along with the time of occurrence. The time of occurrence listed with the event is based on computer clock time and recorded to the nearest five milliseconds. The SOE file can hold up to 256 records. Once the SOE file is filled, subsequent events replace the oldest recorded event in the file. The first event to be recorded in the file triggers an indicator to the operator that an SCE monitored event has occurred. This indication is cleared, and the SOE file is emptied when the operator requests a printout of - - - - - - - - -
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the SOE file. Enclosure 2 illustrates the format of information presented in the SOE printout.
The Post Trip Review function is designed to record selected analog information for a period of time before and af ter a reactor trip. The list of parameters monitored by this function is provided in Enclosure 3.
The most recent 15 minutes of historical values for these parameters is maintained in a rolling file.
In the event of a reactor trip, this rolling file is frozen and data for the next 15 minutes is recorded. An indication that the Post Trip Review function has been initiated is provided to the operator. The opecator may then request the Post Trip Review printout which clears the file. The Post Trip Review printout provides parametric data in engineering units given at 15 second intervals f rom 15 minutes prior to the trip until 15 minutes after the trip. Enclosure 4 provides a sample of one segment of a Post Trip Review prtntout. Note that some 4
of the parameters monitored have scan intervals of more than 15 seconds. Consequently, some data may be repeated in successive 15 second records. The parameters monitored for the Post Trip Review function were chosen as a part of the original plant process computer design. The variables monitored are key parameters of the major primary and secondary systems which could indicate abnormal trends that may lead to, or result from, a reactor trip. Normally inoperative safety systems are not monitored by this function. The scan intervals selected for the parameters were based on the anticipated rates of change of the individual parameters, and multiplexing hardware and memory capacity limitations that existed at the time of the initial design.
The Alarm Printout function provides an historical listing of both digital and analog information recorded when the monitored parameters enter a predetermined alarm state. Essentially, all digital and analog input points are monitored for alarm status.
Alarm messages are recorded as they occur on the alarm printer along with the time of occurrence. No operator action is required to initiate the Alarm Printout. All digital points are scanned once per second, and a change of point status is identified on the alarm printer. Analog points are scanned at varying intervals (either 1, 5,15, 30, or 60 second intervals) and are compared at each scan to a predetermined alarm value. Each time the parameter exceeds the alarm limit or returns to within Ifmits, the event is recorded on the Alarm Printout. An example of a section of the Alarm Printout is provided in Enclosure 5.
The Plant Process Computer consists of redundant MODCOMP Classic 7870 CPUs. The CPUs are powered from separate uninterruptable instrumentation buses YAU and YBU. The uninterruptable buses are supplied from the station battery backed 250 volt DC power supply system through an inverter.
Power can also be supplied to the bus from a nonessential regulated instrumentation bus through a static transfer switch within the inverter. The redundant CPUs were installed during the 1982 Refueling Outage 2-
t as a part of the overall project to upgrade the Plant Process Computer system. The multiplexers providing inputs to the processors will be replaced in future outages. The multiplexers are currently supplied from YBU, consequently, a loss of YBU will interrupt all three transient monitor functions of the Plant Process Computer. The DADS will still be functional. As the multiplexers are replaced, they will be equipped with redundant power supplies.
Data Acquisition and Display System (DADS)
The DADS, located in the Technical Support Center, was designed a
as a part of the emergency response facilities at Davis-Besse Unit 1.
The primary function of the system is to provide information to emergency response personnel in the Technical Support Center to assist in evaluating plant status in an accident situation. Consequently, those variables important to determining the safety status of plant systems and the proper functioning of safety systems are inputs to the DADS.
While the DADS receives inputs from numerous sources, such as the Meteorological Tower and the Plant Process Computer, the inputs of _importance to the transient monitoring function are supplied through a separate multiplexer (the Validyne). The list of parameters supplied by this multiplexer is provided in.
The scan rate for these variables is approximately once per second. Data is recorded at that rate for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a rolling file. Access to information in this data file is possible in several formats.
Individual points or groups of points can be examined by a CRT or a line printer output. Additional output formats are being developed and will include the use of a printer / plotter to provide graphical trends.
The Prime Comupter stores information from both the MODCOMP and Validyne inputs. These values can be called up and printed out per Section 1.2.
The power supply tor the multiplexer located in the station is YAU. The power supply for the DADS computer system is independent of the station electrical system. The Davis-Besse Administration Building (DBAB) which houses the Technical Support Center and the DADS, is supplied from a construction feeder independent of the three 345 KV lines connected to the station grid. The DBAB electrical system supplies an emergency response facilities bus which can also be fed by an emergency diesel generator through an automatic transfer switch. The emergency response facilities bus in turn feeds an uninterruptable distribution network. Power to the uninterruptable distribution network is backed up by a battery driven system through a static transfer switch which assures continuous operation of the DADS computer system. The emergency i
battery system is charged from the emergency response facilities bus.
E Strip Chart Recorders In the event that the Plant Process Computer and the DADS are unable to perform their transient monitor functions, the Control Room strip chart recorders act as a backup source of information for transient analysis. Due to the compressed time scales of the strip chart recorders, the information cannot be used for sequence of events determination and the limited number of parameters recorded make determination of the cause of a tran-sient very difficult. However, the parameters that are recorded are important major system parameters such as pressurizer level, Reactor Coolant System (RCS) pressure, steam generator levels, feedwater flows, etc.
The information available on the strip chart can be very useful in assuring that major system upsets did not occur as a result of the transient. Strip chart recorders are also useful in recognizing long term trends that may be indicative of problems leading to, or resulting from, a transient.
1.2 Technical Section Function It has become a Technical Section function to collect all the available plant data and have copies given as soon as possible to rue Assistant Station Superintendent (Steve Quenncz), Opera-ticns (Dale Miller), NRC Resident Inspector (Walt Rogers), and I&C (acting I&C Engineer). This job normally requires a trip to the Control Room to retrieve the alarms (at least 20 minutes prior to trip and for an hour after), the SOE printout and the Post Trip Review (may have to ask the operators to print out).
If possible, attempt to set up a post trip meeting which includes operators from the shift that was on.
Copies of the Reactor Operator Log and Unit Log should also be obtained when completed (usually not until the day after the trip).
If possible, talk with the operators which are on shif t.
The purpose of this interview is to record pertinent information as seen by the operator during a transient condition. The interview should be conducted as soon as possible af ter the event.
Typical questions are:
1.
Briefly describe plant conditions prior to the trip.
(Include Integrated Control System (ICS) mode and pertinent testing, operations, or maintenance in progress or recently completed.)
2.
What was the first indication or alarm which keyed you to a problem? What actions did you take as a result of these indications?
3.
Were any alarms or indications out of service or did any fail during the course of the transient? Did any indications or alarms mislead you? Could the Control Room alarms or controls have been relocated in such a manner to have aided your actions on this transient?
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Did existing plant procedures provide adequate action for this transient? Was it necessary to take action beyond their scope.
5.
What additional information or guidance do you feet would have assisted you during the transient?
6.
Summarize the transient including both indications and actions. Discuss any equipment problems observed.
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The data from the Prime Computer must be manually hard copied within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the trip as follews:
1)
Go to the Technical Support Center Computer Room and turn on the orange line printer (the "run" light should be "on",
the "off" light should be lit unless the printer is in the act of printing).
2)
Turn on a Technical Support Center Ramtek terminal and push reset button located at the rear of the keyboard.
3)
At the Ramtek terminal:
(NOTE:
two runs, one of 35 minutes length and 30 seconds interval, and a second of 5 minutes at. I second interval provide the best data)
ENTER: LOGIN_TSC lilt:
f function key (hard copy) 3 111T:
f functica key (to obtain Validyne data)
OR f functi n key (for selected MODC0!!P points) 3 2
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ENTER: point number i
ENTER: P (to output to line printer) l l
ENTER: beginning hours and minutes IDIMM i
ENTER: starting time using IlllMM format Run 1: use 5 minutes before trip l
(normally use 5 minutes before trip)
Run 2: use 1 minute before trip l
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ENTER: number of minutes wanted to display l
ENTER: how long in IfilMM i
Run 1: use 30 minutes l
(normally 31 minutes)
Run 2: use 5 minutes l
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ENTER:
interval desired in seconds l
ENTER:
interval in minutes or <CR> for 30 seconds Run 1: use 30 seconds l
Run 2: use I second l
l ENTER: point number or "ALL" for all Validyne l
points l
l Data will now be printed
- l Data will now be printed
- 4)
To exit, enter LO
- If data does not print, do not repeatedly attempt to request printouts since all requests will be remembered and printed when the system returns to working order. Call for assistance f rom Computer personnel. -
The Prime data can be displayed on the Ramtek terminal and a video copy of the display obtained on the Tektronix hard copy printer.
1)
Go to the TSC, turn on Tektronix Video copy printer and let warm up.
2)
Turn on a Ramtek terminal and press reset button located at the rear edge of the keyboard.
3)
At the Ramtek:
ENTER: LOGIN_ LARRY _SMARTI ENTER: DIS i
ENTER: OB ENTER: SEG_9 DISPLAYS e
EVTER: 4 (to plot data vs. time)
E HER:
1 (for CRT display)
ENTER: 2 (to access 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> circular file data)
ENTER:
1 (always) j HIT: Return if data displayed looks OK when presented for review i
ENTER: Point number (NOTE:
If a Validyne point is requested, V must prefix the point number, i.e., VT801 RCP 2-1 Te VZ675 HN FV S/0 CTRL VLV 1)
Data will now be displayed and updated on the terminal.
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To obtain a video copy of the Ramtek display:
With the display finished updating, press the black button beside the tenninal and the video copy will be automatically f
taken.
If it is desired to freeze the display during updating, the terminal can be frozen by hitting " control" "S" (simultaneously).
To resume updating:
HIT: " control" "Q"-(simultaneously) 5)
To exit program:
HIT:
" Break" key i
ENTER:
"Q" ENTER: LO 3 f
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The printer / plotter is being programmed to have a fixed set of plots (see Enclosure 10 for list) be printed by manual command.
l Presently, only Larry Konopka can use this feature. This will, l
in the future, be the primary method of data retrieval. Details l.
of use will be added later.
2.
DATA ANALYSIS Data analysis is the most difficult part of the post trip review process. Every analysis is different since every event is different.
Some points need to be checked for almost every event, and the i
following provides an indication of the extent of the review required.
The SOE and Alarm Printcut must be reviewed to verify the safety systems operated as required. This means verifying not only why some channels tripped, but also verifying that all channels that should have tripped did trip. Enclosure 7 provides a list of all SOE points and what causes the SOE to initiate. has a list of specific points to be checked.
The plots must be reviewed to determine if the overall plant response was acceptable. After a trip, the main feedwater control valves are closed, the startup feedwater valves are targeted to approximately 20% open, and the main feed pump speed is increased to target (approxi-mately 4600 RPM) by the rapid feedwater reduction system. Steam generator levels should be maintained at 35 inches (and rapid feedwater reduction startup feedwater valve target released). The main steam safety valves should rescat at approximately 960 PSIG and Tave should tend towards 551*F.
Pressurizer level should reach a minimum of 10-20 inches if originally at full power (higher if originally at lower power).
RCS pressure should not fall below 1800 PSIG unless problems occur with main steam safety valves (MSSV)s resetting or makeup flow is inadequate. Cold leg temperature will most likely rise for the first 10-20 seconds from the drastically increasing steam generator pressure, i
but will then cend toward 550'F.
Since 100% FP is 48'F AT (Th - Tc),
the post trip AT is approximately 2-3*F for the first 20 minutes (dependent on decay heat load).
The drastic changes in steam generator pressure will cause momentary glitches in the steam generator level t ransmitters. These ara to be expected since the level transmitters are just AP indicators.
l High deaerator levels have been a problem post trip.
It appears the Deaerator Level Control Valve #2 fails to close and the equalizing valve caused both deaerator levels to increase. Monitor both deaerator levels ar.4 the time the condensate pumps are reduced to one operating.
All turbine bypass valves should normally open initially after the l
trip and then close during the MSSV blowdown. The atmospheric vents I
should open when steam generator pressure rises above 1025 PSIG (providing no Steam and Feedwater Rupture Control System (SFRCS) actuation),
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1 RCS pressure, pressurizer level, and RCS Tave should have nearly identical curve shapes until the makeup pumps have added significant volume (1-2 minutes). RCS pressure is the most sensitive indicator of RCS temperature; the RTDs and thermowells response time, as well as the loop transport time, adds a significant time delay (5-15 seconds) in the sensing of actual Tave during a rapid cooloat tempera-ture change.
One additional caution is necessary on using the out-of-core power range NIs. These detectors are monitoring core neutron Icakage, which is affected drastically by changes in cold leg temperature (approximately.5% FP per *F).
If Te increases 6'F, indicated core power will increase 3% without any actual change in core power.
The analysis performed depends largely on the transient. A closure of one main steam isolation valve (MSIV) requires a much more detailed review than a " screwdriver" trip. An imbalance trip requires a detailed core physics review, while an electro-hydraulic control (EHC) induced transient may require a significant review of the secondary plant. Common sense and an inquisitive attitude must be maintained throughout the review. Murphy's Law definitely applies to nuclear power; Don't assume anything worked like it should.
3.
SUPPORT OF OUTSIDE ORGANIZATIONS The Technical Section provides support to the TAP Team and places information on NETWORK to provide information to outside organizations.
The B&W Resident Engineer (Jim Albert) has his own method of communica-tion with other B&W plants (ELEX) which can also be used as the method of communication between B&W units.
Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the event, the Technical Section should make an entry on NETWORK to the other B&W units describing the event.
If the event has significance beyond the B&W design (such as failure mechanism of MSSVs), an entry should also be made on NETWORK to all operating units.
The Technical Section is responsible for telling the B&W Resident Engineer if a TAP Team site visit is desired. A TAP Team should be called in for most involved transients, but no site visit is necessary for a well understood transient. When requesting a site team, ask for personnel qualified in the area of the equipment involved in the transient; i.e., if ICS operatton is an question, ask for an ICS
" expert".
The Technical Section representative acts as a liaison for the B&W TAP Team. The entrance interview should be well prepared with all information necessary to analyze the event provided to the team.
They should be provided with:
1)
An oral review of the transient details known 2)
All plots, alarms, SOE, post trip review, and operator logs 9
3)
Names, work extension, and schedule of personnel who were on shift during transient 4)
A work area - typically a conference area in the DBAB 5)
Escorts as required into the protected area After the draft report is prepared, we have Duplicating make 10-12 copies. An exit interview is then set up with Steve Quennoz, Bernie Peyer, IEC Engineer, Dale Miller, Louis Simon, other available operators, Shift Technical Advisors, Jim Albert, and the Technical Section representative.
The draft report is then reviewed and several days given to receive comments.
If the TAP Team was not called in, only the NETWORK entry need be completed. Section 4 describes the details of report preparation to be followed.
4.
REPORT PREPARATION AND REVIEW A TAP report will be prepared for all unscheduled reactor trips at Davis-Besse. Reports may also be prepared for other significant events. The purpose of the report is to provide transient event inforniation for all members of the 177 FA Owners Group. The opera-tional experience shared in this program will lead to improved plant reliability and a better understanding of the plant's performance by all participants.
The format of the report should be as follows:
I.
Executive Sununary A.
Plant Name, Data, Time of Trip B.
Brief Description C.
Root Cause D.
Performance Anomalies E.
Lessons Learned II.
Transient Assessment A.
Sequence of Events B.
Plant Performance 1.
Pre-trip Review 2.
Initiating Event 3.
Plant Post-trip Response 4.
Operator Actions / Procedural Adequacy C.
Safety Considerations D.
Assessment Conclusions E.
Annotated Plots The " Executive Summary" section should be a single page containing the following information: plant name, date and time of trip, brief description of the event, including initial power level, root cause of the transient, any performance anomalies, and lessons learned.
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The " Sequence of Events" section should contain those major events or conditions which delineate the progressive course of the transient.
It normally contains a combination of the SOE, alarms, and Reactor Operator Log.
The " Pre-trip Review" section should contain a statement of the plant conditions prior to the transient. Examples to be included would be power level, ICS status, maintenance or testing in progress, and equipment deficiencies.
The " Initiating Event" section should describe the sequence of events and plant conditions leading up to transient initiation. Try not to be repetitive with other sections.
The " Plant Post-trip Response" section should include a discussion of the response of the NSS and BOP from a process point of view; i.e.,
Tave, reactor coolant pressure, pressurizer level, feedwater flow, OTTC level, and main steam pressure. These parameters should be plotted versus time and annotsted to indicate major events, departures, etc., to support the text of this section. Also, this section should include a discussion of performance of components and their departures from the expected. Proposed corrective actions and corrective actions previously completed should be included in the text of this section.
The " Operator Action / Procedural Adequacy" section should include information concerning specific operator actions taken during the transient which have not been included in any previous sections.
Additionally, procedures followed during the transient, and any information which would be beneficial to other operators should be included. This section is of major interest to other operators regarding the TAP report and should be as detailed as possible, Operator interviews, operator logs, computer printout and plant procedures provide good source material. This section should provide an evaluation of the shift operator's ability to use the procedures to mitigate a plant transient. Avoid repetition of earlier sections when possible.
The " Safety Considerations" section should include the basis for which safety, as it relates to the transient, has beea considered.
Those bases may include plant design requirements, Final Safety Analysis Report (FSAR) accident analysis, or other information.
The " Assessment Conclusions / Corrective Actions" section should be a summary of the significant aspects of the transient, including departures from expected component and plant performance, suggested /
actual corrective actions, and any preventative measures if not already discussed in the Plant Post-trip Response section. For component failures, list name, model and serial number, manufacturer name, date of installation, etc. Try to give this section a positive, "we're fixing it" tone instead of a "diak sheet".
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t The " Annotated Plots" section should consist of a number of parameter versus time plots annotated with trip times and other important cecurrences (pump starts / stops, emergency Safety Features Actuation System (SFAS) initiation, power operated relief valve (PORV) lif ts,
- main steam relief valve (MSRV) / MSSV lifts, etc.) The Abnormal Transient Operator Guidelines (ATOG) P-T plot should be included in this section.
After the report has been reviewed in the exit meeting and modified by the Technical Section, it is sent out for review (see Laura for distribution). After the date that the comments were due (usually two weeks), the report comments are incorporated, and it is then sent to the Station Review Board (SRB). After SRB review and comment incorporation,- the report will be sent to B&W with the cover letter signed by the Technical Section TAP representative. B&W will place the report in the booklets and distribute to all participating utilities.
The data is then stored in the trip files (along with the Attachment 3 to PP 1102.03 from Operations). Revisions are not normally made to TAP reports, but can be completed if serious errors exist.
This completes the post trip review guidelines - these are only guidelines and are not cast in concrete. Enclosure 9 includes a checklist for post trip review which may be used to ensure no items are missed.
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SEQUENCE OF EVENTS POINTS LIST Auxiliary Transformer 11 Trouble Bus A Electrical Fault Bus B Electrical Fault Bus A to Transformer AC Breaker Bus C2 Trouble Bus D2 Trouble Control Rod Drive (CRD) Trip Confirm CRD Channel AC Any Trip Device CRD Channel BD Any Trip Device Electro Hydraulic Control Emergency Trip System Low Pressure Emergency Diesel Generator 1 Trouble Emergency Diesel Generator 2 Trouble Essential Bus C1 Trouble Essential Bus D1 Trouble Essential Transformer CE 1-1 Trouble (typical CE 1-1, DF 1-1, CE 1-2),
DF 1-2)
Cenerator and Main Transformer Overall Differential Trip Generator Overcurrent Trip Generator Reverse Current Power Trip Generator Field Failure Generator Out of Step Generator Underfrequency Generator Differential Generator Ground Current Page 1 of 3 i ;
Main Feed Pump Turbine (MFPT) 1 Trip (typical MFPTs 1 and 2)
Main Transformer Sudden Pressure Change Moisture Separator Reheater 1 High Level Turbine Trip Moisture Separator Reheater 2 High Level Turbine Trip Reactor Protection System (RPS) Channel 1 Flux / Delta Flux / Flow Trip (typical Channels 1 through ')
4 RPS Channel 1 High Flux / Number of Reactor Coolant Pumps (RCPs) Running Trip (typical Channels I through 4)
RPS Channel 1 Reactor Coolant (RC) Pressure / Temperature (typical Channels I through 4)
RPS Shutdown Bypass High Pressure Trip (typical Channels 1 through 4)
RPS Channel 1 Containment High Pressure Trip (typical Channels 1 through 4)
RPS Channel 1 RC High Pressure Trip (typical Channels I through 4)
RPS Channel 1 RC Low Pressure Trip (typical Channels 1 through 4)
RPS Channel 1 Channel Trip (typical Channels 1 through 4)
RPS Channel I High Flux Trip (typical Channels 1 through 4)
RPS Channel 1 RC High Temperature Trip (typical Channels 1 through 4)
RPS Startup Rate Rod Withdrawal Inhibit RC Pressurizer Low Level Heater Interlock RCP 1-1 Motor Trouble (typical RCPs 1-1, 1-2, 2-1, and 2-2)
Safety Features Actuation System (SFAS) Channel 1 E, rated Water Storage Tank (BWST) Level Low (typical Channels 1 through 4; SFAS Channel 1 Containment Pressure > 38.4 psia (typical Channels 1 through 4)
SFAS Channel 1 Containment Pressure > 18.4 psia (typical Channels 1 through 4)
SFAS Channel 1 RC Pressure < 1650 psig (typical Channels 1 through 4)
SFAS Channel 1 RC Pressure < 450 psig (typical Channels 1 through 4)
Page 2 of 3 -.
i SFAS Channel 1 Contaisunent Radiation High (typical Channels 1 through 4)
Steam and Feedwater Rupture Control System (SFRCS) Full Trip SFRCS Differential Pressure Half / Full Trip Steam Generator (SG) 1 (typical SGs 1 and 2)
Startup Transformer 01 Trouble Startup Transforecc 02 Trouble i
Switchyard Oscillograph Started Switchyard Bus J Differential Switchyard Breaker 34563 Open/ Closed (typical five breakers) i Turbine Generator Mechanical Trip Solenoid Turbine Trip Turbine Generator Master Turbine Trip Turbine Generator Mechanical Trip Valve Trip Turbine Generator Master Trip Solenoid Trip Turbine Bypass Valve 1-1 Open/ Closed (typical six valves) i Unit Seismic Instrumentation Started 4
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I POST TRIP REVIEW POINT LIST Auxiliary Feed Pump Turbine 1 Speed (typical Pumps I and 2)
Channel 1 Power Range Flux (typical Channels 1 through 4)
Channel 1 Power Range Delta Flux (typical Channels I through 4)
Condensate Pump Flow 1
Control Rod Drive Group 5 Position (typical Groups 5 through 8)
Deaerator 1 Storage Tank Level (typical Deaerators 1 and 2)
Generator Gross Megawatts l
High Pressure Condenser Pressure i
High Pressure Condenser Hotwell Level l
High Pressure Turbine First Stage Turbine End Pressure High Pressure Turbine first Stage Generator End Pressure '
i High Pressure Turbine Side 1 Inlet Temperature High Pressure Turbine Side 2 Inlet Temperature l
Low Pressure Condenser Pressure 4
Main Feedwater Average Flow Loop 1 (typical Loops 1 and 2) i Main Feedwater Temperature (typical Loops 1 and 2) i Main reedwater Compensated Flow (typical Loops 1 and 2)
Main Feedwater Pump Turbine 1 Speed (typical Pumps 1 and 2)
Pressurizer Average Level Pressurizer Pressure Reactor Coolant Makeup Tank Level Reactor Coolant Makeup Flow Reactor Coolant Pump (RCP) Seal Injection Flow Page 1 of 2 - -
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RCP l-1 Discharge Cold Leg Narrow Range Temperature (typical RCPs 1-1 and 2-1)
Reactor Coolant System (RCS) Loop 1 Hot Leg Narrow Range Temperature (typical Loops 1 and 2)
RCS Average Temperature RCS Loop 1 Hot Leg Narrow Range Pressure (typical Loops 1 and 2)
RCS Average Hot Leg Total Flow RCS Letdown Boron Concentration Safety Features Actuation System (SFAS) Channel 1 Containment Pressure SFAS Channel 1 Containment Radiation Core Power SFAS Channel 3 Borated Water Storage Tank Level Steam Generator (SG) 1 Full Range Level (typical SGs 1 and 2)
SG 1 Startup Level (typical SGs I and 2)
SG 1 Operate Level (typical SGs 1 and 2)
SG 1 Outlet Temperature (typical SGs 1 and 2)
SG 1 Outlet Pressure (typical SGs 1 and 2)'
SG 1 Feedwater Pressure (typical SGs 1 and 2)
Page 2 of 2
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