ML20212A319
| ML20212A319 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/02/1986 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17326B269 | List: |
| References | |
| 12-PMP-4021-TRP, NUDOCS 8612220374 | |
| Download: ML20212A319 (111) | |
Text
, o con = un INDIANA & MICHIGAN ELECTRIC CD.11PANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEU Procedure No. hpf[1 N Revmon No. 1 TmE REACTOR TRIP REVIEW SCCPE CF REv!SICN : Major revision. Re-organized to reduce re-dundancy and to comply with PMI 2010. Added sign-off sheets 6 and 16 in response to'SOER 83-07. Added sign-off sheets 7, 8, 17 and 18 to assist in organizing procedural require-ments and assignments pri'or to reactor restart authorization. Changed the Reactor Trip Breaker Undervoltage response requirement from a time measurement to observed only. Incorpor-ated PC's 1 & 2. Organized sign-off sheets 1-8 for Unit 1 and 11-18 for Unit 2.
SIG::ATURES REVISION NUMBER Rev. 1 PREPARED BY f[ gio%, { g 0 Pn NT HEAD $86 Q{#1.ubt, i \ .J ,&-M /
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- Q 12 PHP 4021 TRP.001 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER Page 1 of 10 Revision 1 Page 2 of 10 Revision 1 Page 3 of 10 Revision 1 Page 4 of 10 Revision 1 Page 5 of 10 Revision 1 Page 6 of 10 Revision 1 Page 7 of 10 Revision 1 Page 8 of 10 Revision 1 Page 9 of 10 Revision 1 Page 10 of 10 Revision 1 SIGNOFF SHEET 1 Page 1 of 8 Revision 1 Page 2 of 8 Revision 1 ,
Page 3 of 8 Revision 1 Page,4 of 8 Revision 1 Page 5 of 8 Revision 1 Page 6 of 8 Revision 1 Page 7 of 8 Revision 1 l Page 8 of 8 Revision 1 I
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SIGNOFF SHEET 2 Page 1 of 1 Revision 1 l
Page 1 of 5 Rev. 1
12 PMP 4021 TRP.001 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISIOff NUMBER SIGNOFF SHEET 3 Page 1 of 1 Revision 1 SIGNOFF SHEET 4 Page 1 of 3 Revision 1 Page 2 of 3 '
Revision 1 Page 3 of 3 Revision 1 SIGNOFF SHEET 5 Page 1 of 10 Revision 1 Page 2 of 10 Revision 1 Page 3 of 10 Revision 1 Page 4 of 10 Revision 1 Page 5 of 10 Revision 1 Page 6 of 10 Revision 1 Page 7 of 10 Revision 1 Page 8 of 10 Revision 1 Page 9 of 10 Revision 1 Page 10 of 10 Revision 1 SIGNOFF SHEET 6 Page 1 of 1 Revision 1 SIGNOFF SHEET 7 Page 1 of 1 Revision 1 SIGNOFF SHEET 8 Page 1 of 1 Revision 1 Page 2 of 5 Rev. 1
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, ,_ 12 PMP 4021 TRP.001 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER SIGNOFF SHEET 11 Page 1 of 6 Revision 1 Page 2 of 6 Revision 1 ,
Page 3 of 6 Revision 1 Page 4 of 6 Revision 1 Page 5 of 6 Revision 1 Page 6 of 6 Revision 1 SIGNOFF SHEET 12 Page 1 of 1 Revision 1
'iIGNOFF SHEET 13 Paga 1 of 1 Revision 1 SIGNOFF SHEET 14 Page 1 of 3 Revision 1 Page 2 of 3 Revision 1 Page 3 of 3 Revision 1 SIGNOFF SHEET 15 Page 1 of 10 Revision 1 Page 2 of 10 Revision 1 Page 3 of 10 Revision 1 Page 4 of 10 Revision 1 Page 5 of 10 Revision 1 Page 6 of 10 Revision 1 Page 7 of 10 Revision 1 Page 8 of 10 Revision 1 Page 9 of 10 Revision 1 Page 10 of 10 Revision 1 Page 3 of 5 Rev. 1
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- 12 PMP 4021 TRP.001 1
LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER SIGNOFF SHEET 16 Page 1 of 1 Revision 1 SIGNOFF SHEET 17 Page 1 of 1 Revision 1 SIGNOFF SHEET 18 Page 1 of 1 Revision 1 APPENDIX A Page 1 of 40 Revision 1 Page 2 of 40 Revision 1 Page 3 of 40 Revision 1 Page 4 of 40 Revision 1 Page 5 of 40 Revision 1 Page 6 of 40 Revision 1 Page 7 of 40 Revision 1 Page 8 of 40 Revision 1.
Page 9 of 40 Revision 1 Page 10 of 40 Revision 1 .
Page 11 of 40 Revision 1 Page 12 of 40 Revision 1 Page 13 of 40 Revision 1 Page 14 of 40 Revision 1 Page 15 of 40 Revision 1 Page 16 of 40 Revision 1 Page 17 of 40 Revision 1 Page 18 of 40 Revision 1 Page 4 of 5 Rev. 1
12 PMP 4021 TRP.001 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER Page 19 of 40 Revision 1 Page 20 of 40 Revision 1 Page 21 of 40 Revision 1 Page 22 of 40 Revision 1 Page 23 of 40 Revision 1 Page 24 of 40 Revision 1 Page 25 of 40 Revision 1 Page 26 of 40 Revision 1 Page 27 of 40 Revision 1 Page 28 of 40 Revision 1 Page 29 of 40 Revision 1 Page 30 of 40 Revision 1 Page 31 of 40 Revision 1 Page 32 of 40 Revisicn 1 Page 33 of 40 Revision 1 Page 34 of 40 Revision 1 Page 35 of 40 Revision 1 Page 36 of 40 Revision 1 Page 37 of 40 Revision 1 Page 38 of 40 Revision 1 Page 39 of 40 Revision i Page 40 of 40 Revision 1 APPENDIX B i
Page 1 of 2 Revision 1 Page 2 of 2 Revision 1 Page 5 of 5 Rev. 1
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, ,_ 12 PMP 4021.TRP.001 u.
.. u INDIANA & MICHIGAN ELECTRIC COMPANY '
.e DONALD C. COOK NUCLEAR PLANT l.0 TITLE Reactor Trip Review A 2.0 OBJECTIVE k ~%
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To determine the exact cause of a Reactor' Trip.-
2.1 '
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2.2 To ensure all required automatic responses assdciated with a reactor trip have either functionsd properly or ?
have been investigated and resolved'. +y *
.2.3 To establish re'quirements for a Reactor restart.
3.0 REFERENCES
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3.1 References on which the Procedure is b,ased. ^ {\
3.1.1 NUREG 0977 and NUREG 1000, Vol'l'describ1ng ,
the ATWS events at Salem Nuclear Generating Station. $
4 3.1.2 The NRC's " Salem Restart-Status Report" of March 28, 1983 response.
u 3.1.3 Generic letter 83-28, " Required 13 Actions based * $'
on Generic Implications of SAyEM(ATWS t Events",
July 8, 1983.
- C' N ,- o 3.1.4 AEP:NRC:0838A - response to Generic l'etter 83-28. ( '
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t' 3.1.5 INPO Good Practice OP-211, "Pos t Trip.
Reviews", 9/83.
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3.1.6 10CFR50).73 (IV). ,
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. g. s 3.1.7 1-OHP 4031.001.002 Rev. 15 andD2,-OHP 1 4021.001.002 Rev. 9.
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3.1.8 Oconee Nuclear Station directive', ; -. \
Investigation of Un'it Trips, Revision of s-10/23/75.
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," 3-i 3.1.9 Oconee Nuclear Station Perfornance Manual, Section 4.7, Support of React'or Trips, Revision.of 2/16/83.
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3.1.10 Memo, V. VanderBurg to W.G., Smith 6/30/83.
3.1.11 SOER 83-7 ' Inadvertent Reactor Trips Caused by '
Instru.dentation and Control Problems.'
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12 PMP 4021.TRP.001 3.2 References to assist in procedure implementation.
3.2.1 Elementary Diagrams 3.2.1.1 98501 - 98515, Reactor Protection and Safeguards Logic Diagrams.
3.2.1.2 98361 - 98377, Elementary Diagrams for Protection System and Safeguards, Train A.
3.2.1.3 98381 - 98397, Elementary Diagrams for Protection System and Safeguards, Train B.
3.2.1.4 1-93101, 2-98101, 2-98102, Turbine
, Control.
3.2.1.5 98211, Steam Generator Feedwater Turbine E. 98212, Steam Generator Feedwater Turbine W.
3.2.1.6 98021, Generator and Transformer Dif ferential'.
3.2.1.7 98120, Turbine Events Monitor an'd Miscellaneous Recorders ~.
3.2.1.8 98655, 98656, 98657, Operations Sequence Monitor.
3.2.1.9 98665, 98666, 98667, Oscillograph.
3.2.2 1200-A,B,C,G, one Line Electrical Diagrahs.
3.2.3 Recorder Chart Index, 4/21/81 Revision.
3.2.4 Hathaway H634 Manual, Issue #5, May 1973.
3.2.5 Hathaway H-559 Manual, Issue #1, April 1970.
3.2.6 Westinghouse Dill P250 Manual, 1/68 Revision.
3.2.7 Westinghouse P250 Continuous Monitoring System Manual S2C-08A, issued 11/68.
3.2.8 S2G-09B Westinghouse Post Trip Review Program Description, original issue.
3.2.9 D. C. Cook Plant operating records.
3.2.10 Appendix A: Miscellaneous information relating to the Operation of Trip Monitoring Devices.
Page 2 of 10 Rev. 1
_, . 12 PMP 4021.TRP.001 4.0 DETAILED PROCEDURE 4.1 Responsibilities 4.1.1 The Shift Supervisor (SS) has the overall responsibility for the safe and reliable operation of the plant. The Shift Technical Advisor Section (STA) is responsible for the coordination of this procedure, the thoroughness and completeness of the procedure.
As directed by the STA Supervisor, the STA is responsible for the drafting of the review report.
4.1.2 The use of "Not Applicable"-is allowed for the
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completion of the procedure. 'N/A' will be written in the sign off space with an explanation describing the reason. for not being applicable. This will then be followed by the initials of the person making this decision and the date of this decision.
4.2 Definitions 4.2.1 The classification scheme differentiates between " minor" and " major" safety-related equipment. The classification is relative and no implication is intended that " minor" -
equipment is unimportant. Whether a failure has serious safety significance shall be determined by those classifying the event.
4.2.1.1 A " Major Equipment Failure" is where failure of equipment could have a substantial adverse impact on a normal plant shutdown or an accident situation.
Such failures merit examination by the PNSRC prior to plant start-up. Examples:
Failure of an auxiliary feedpump to start when required, failure of a reactor trip breaker to open, failure of a turbine trip system to depressurice.
4.2.1.2 A " Minor Equipment Failura" is where failure of equipment does not have a substantial adverse impact on a normal plant shutdown or accident situation.
Examples of minor equipment failures:
Failure of a single reactor trip instrur.entation channel or feedwater isolation actuation slightly below the Technical Specification value of 554*.
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.,' . 12 PMP 4021.TRP.001 4.3 SignOff Sheets 4.3.1 The Signoff Sheets are sorted into two sets.
The first set, Signoff Sheets 1 thru 8 is for Unit One and the second set, Signoff Sheets 11 thru 18 is for Unit Two. When directed by the detailed procedure to use a signoff sheet, the first number is associated with Unit One and the second number, in brackets (), is associated with Unit Two. To avoid confusion, discard the signoff sheets from the unaffected Unit.
4.2.2 Signoff Sheet #6 (16), ' Corrective Action Review', is required to be completed and reviewed prior to " Reactor Restart Authorization", (4.8). This Signoff sheet will be initiated by the STA section with input from all affected departments who will sign the applicable subsection. Procedural defects will be only those procedure related errors which are due to logic errors, misprints, or failure to address a situation and not those errors related to personnel noncompliance or misunderstandings. Noncompliance will be a personnel error. Section C on Signoff Sheet #6 (16) is to be completed for personnel errors or precedural defects only. Section F on Signoff Sheet #6 (16) will be signed by the Plant Manager or his designee prior to recommendation of Reactor Restart Authorization.
4.3.3 Signoff Sheet #7 (17) is to be used as a guide for the requirements of the different event conditions.
4.3.4 Signoff Sheet 8(18) is to be used by u. .A for tracking the status of any items requiring action prior to " Reactor Restart Authorization".
Required action could be to repair malfunctional l' equipment, make procedural changes, install additional work controls, provide additional training, etc. These would be for items causing the Reactor Trip or problems as the result of the Reactor Trip. The status of Job Orders, Procedural Changes, etc. , will be monitored and noted on signoff sheet 8(18) by the STA.
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, . 12 PMP 4021.TRP.001 4.4 PREREQUISITES 4.4.1 E-0, " Reactor Trip or Safety Injection" and/or other Emergency Operating Procedures directed to be performed by E-O have been performed to where the plant is stable.
And 4.4.3 A reactor Trip has occurred that was not part of a preplanned event of a surveillance test procedure.
And 4.4.4 Appropriate notification has been made as specified in PMI 7030, " Condition Reports and Plant Reporting", Attachment No 2, "Immediate Notifications by the Shift Supervisor of j significant events."
4.5 DATA COLLECTION 4.5.1 The Operations Department is to check the relays on Panel G and the A panels. Use Signoff Sheet #1 (11) and place an X to '
4 indicate actuated status. Actuated status is indicated by targets being shown or indicating lights being unlit. Relays with indicating lights are shown with a
- by the relay number on Signoff Sheet #1 (11). If the Reactor Trip occurred with the turbine reset, the Operations Department is to check the First Hit annunciator in the.EHC Cabinet, Unit One only. Record the "First Hit" on Signoff Sheet #1.
4.5.2 The I&C Section is responsible - for collecting copies of the charts listed on Signoff Sheet 2 (12), " Chart Collecitons". These copies are to include portions of the trace prior to
!, and following the Reactor Trip. Copies are to a
be l'beled appropriately.
4.5.3 All personnel involved with the Reactor Trip are to complete Signoff Sheet 3 (13),
" Personnel Interview Form". As a minimum, the Unit Supervisor, the Control Room Reactor Operators and the Shift Supervisor are to complete these forms. The STA is to review these forms with the individuals to ensure completeness.
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.' . 12 PMP 4021.TRP.001 4.5.4 Using data obtained from the OSM, complete Signoff Sheet 4 (14), " Trip Response Times".
4.5.5 With the assistance of a Licensed Control Room Operator, the STA is to complete Signoff Sheet 5 (15), " System Status Response".
4.6 Data Analysis NOTE: This Section should be performed by all those classifying the event.
- 4.6.1 Review Signoff Sheet 1 (11) " Relay Targets" for abnormal items. These items are then to be listed on Signoff Sheets 6 (16) and/or 8 (18).
- 4.6.2 Review the charts obtained [see Signoff Sheet 2 (12)]. Any traces which are abnormal and appear to be the result of degraded equipment are to be noted on Signoff Sheets 6 (16) and/or 8 (18).
- 4.6.3 Review Signoff Sheet 3 (13 ), " Personnel Interview Form". Any _ items noted in these interviews pertaining to procedural defects, personnel noncompliance, misunderstandings or equipment problems are to be listed on Signoff Sheets 6 (16) and/or 8 (18).
- 4.6.4 Review Signoff Sheet 4 (14), " Response Times". The Trip Response Times are to be compared to those responses from past Reactor Trips. These Time Responses may differ from past trips because of sequential differences due to varying initiating events. Where Responses Times differ from past Time Responses, verify it is not due to degraded equipment. When degraded equipment has been identified, the equipment is to be listed on Signoff Sheets 6 (16) and/or 8 (18).
- 4.6.5 Review Signoff Sheet 5 (15), " System Status and Response". Include any equipment malfunctions on Signoff Sheets 6 (16) and/or 8 (18).
- Requires Signoff Page 6 of 10 Rev. 1
12 PMP 4021.TRP.001 4.6.6 Determine and list the exact cause of the Reactor Trip from the following applicable information sources:
Source Cause of Reactor Trip OSM P-250 Post Trip Review P-250 Table of Alarms Interviews Others 4.7 EVENT CLASSIFICATION 4.7.1 A Reactor Trip is classified by one of the next 3 conditions.
4.7.1.1 The reactor trip is classified a Condition I event if the cause of the event is known (4.6.6), no major discrepancies in time responses due to degraded equipment (4.6.4) and no indication of improperly functioning safety related equipment.
4.7.1.2 _The reactor trip is classified a Condition II event if the cause of the
. trip is positively known (4.6.6), and some minor safety related equipment did not function properly. However, the malfunction has been corrected and the status of events or equipment malfunction directly related to the trip do not prevent a restart.
4.7.1.3 The Reactor Trip is classified a Condition III event if the cause of the trip is not positively known, or some minor safety related equipment malfunctioned during the event and has not been repaired, or some major safety related equipment malfunctioned during tdue event, whether or not repairs have been made.
4.7.2 Revi'ew of 4.6, " Data Analysis", which has been summarized on Signoff Sheets 6 (16) and 8 (18) and in step 4.6.6 has determined the Rector Trip Event is classified as follows:
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12 PMP 4021.TRP.001 4.7.2.1 Concurrence between the SS and STA classifies the event as a Condition I event.
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STA There is a disagreement between the SS and STA on the RX Trip event being a Condition I event. The Operations Superintendent along with SS or STA have decided to classify the event as a condition I event.
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SS or STA 4.7.2.2 The Operations Superintendent and STA concur that the event satisfies the criteria for Condition II events.
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STA There is a disagreement between the Operations Superintendent and STA on the Reactor Trip event being classified a Condition II event. The Assistant Plant Manager Production, along with the Operations Superintendent or STA have decided to classify the event as a Condition II event.
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Asst. PM/ Prod.
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OPS Supv or STA Page 8 of 10 Rev. 1
.' . 12 PMP 4021.TRP.001 4.7.2.3 The Operations Superintendent and STA concur the Reactor Trip event satisfies the criteria for Condition III events.
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STA There is a disagreement between the Operations Superintendent and STA on the Reactor Trip event being classified a Condition III event. The Assistant Plant Manager-Production, along with the Operations Superintendent or STA have decided to classify the event as a Condition III event.
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Asst. PM/ Prod
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OPS Supv or STA 4.8 REACTOR RESTART AUTHORIZATION 4.8.1 For Condition I events with concurrence between the SS and STA (4.7.2.1), the SS has the authority and recommends the restart of the effected unit to the Plant Manager.
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SS 4.8.2 For Condition I events without concurrence between the SS and STA (4.7.2.1), the Operations Superintendent has the authority and recommends the restart of the effected unit to the Plant Manager.
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OPS Supv i 4.8.3 For Condition II events with concurrence
. between the Operations Superintendent and STA (4.7.2.2), the Operations Superintendent has the authority and recommends the restart of the effected unit to the Plant Manager.
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12 PMP 4021.TRP.001 4.8.4 For Condition II events without concurrence between the Operations Superintendent and STA (4.7.2.2) the Assistant Plant Manager-Production has the authority and recommends the restart of the effected unit to the Plant Manager.
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Asst PM Prod 4.8.5 For Condition III events (4.7.2.3) all open items associated with the trip must be reviewed by the PNSRC with no unresolved safety questions.
The PNSRC has the authority and recommends the restart of the effected unit to the Plant Manager.
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12 PttP 4021 TRP.001 - . ,
REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 1 .
. PANEL G RELAY TARGETS UNIT 1 (IIAA) (HAA)
TI T2 T3 Til T12 T13 Turbine Generator Excitation Turbine Hyd Stator Trans. 1 Valves Relays Relays Trip Cooling Sudden
- Soleniod Trip Pressure T4 T5 T6 T12 ,
TIS T16 Turbine Transformer Emerg. P.ll. Trans. lAll Trans. ICD Trans 1 Hech. Trip Relays Trip Gen. Sudden Sudden Tap Chgr Solenoid Panel Pressure Pressure Hndt in UNIT DIFFERENTIAL (llEA) OVERALL DIFFERENTIAL (llEA) 87X-U1 87XI-UI 87X2-UI 87X-0A1 87XI-0Al 87X2-0Al i
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o' 12 PHP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNGFF SilEET I .
PANEL A RELAY TARGETS UNIT 1 Panel -
Panel Panel A-11 A-10 A-9 I
I SIT-11A SIN- SIT-11B 51'12CD 25-TCD SI 12AB 25 TAB Pil. I 711!! Pil.1 SIT-11A SIT-11B 87-TCDLD 87-TCDLD 87-TCLD 87-TABLD 87-TABLD 87-TABLD Pil . 3 Pil.3 Pil.1 Pil.2 Fil . 3 Pil .1 PH.2 Pil. 3 I
87-DGAB 87-DGAB 87-DCAB 87T-101CD 87T-101CD 87T-101CD 87T-101AB 87T-101AB 87T-101AB !
PH.1 PH.2 PH.3 PH.I PH.2 PH.3 PH.1 Pil.2 PH.3 [
i 87T-11A 87T-11A 87T-IIA TR101CD Voltage Low TR101AB Voltage Low Pli.1 Pi!. 2 Pl!. 3 Pil.1 Pl!.2 PH.3 PH.1 Pif. 2 Pil. 3 1 * * * *
- 87T-IIB 87T-llB 87T-11B SITN- 251TN- SITN- 251TN-Pil.1 PH.2 PH.3 101CD 101CD 101AB 101AB 51-DGAB SIN-DGAB 51-DGAB 4KV TilD Vol; Low 4KV TilA Voltage Low PH.1 PH.3 Pl!.1 PH.2 Pil.3 PH.1 PH.2 Pil. 3 Page 4 of 7 Rev. 1 -
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12 PHP 4021 TRP.001 .
REACTOR TRIP REVIEW PROCEDURE =
SIGNOFF SilEET I t
PANEL A REI.AY TARGETS UNIT 1 Panel Panel A-13 A-12 SIT-IIC SIN-T11C 51T-11D 87 RCPI 87 RCP) 87 RCPI Pil.1 Pil .1 Pil.1 Pil. 2 Pil . 3 SIT-11C SIT-IID 87 RCP2 87 RCP2 87 RCP2 Pil. 3 PH.3 Pil.1 Pil.2 Pil .3 87-DGCD 87-DGCD 87-DGCD 87-TBNC 87-TBNC 87-TBHC Pli.1 PH.2 Pl!.3 Pil.1 Pil. 2 Pfl.3 8)T-11C 87T-11C 87T-11C 87-TCMC 87-TCMC 87-TCHC Pil.1 PH.2 Pil.3 PH.1 Pli. 2 Pil.3 f
87T-11D 87T-IID 87T-11D 87-RCP3 87-RCP3 87-RCP3 Pil.1 PH.2 Pil.3 PH.1 Pil. 2 Pil.3 51DGCD SIN- SIDGCD 87-RCP4 87-RCP4 87-RCP-4 Pfl.1 DGCD PH.3 PH.1 PH.2 PH.3 Page 5 of 7 Rev. 1
12 PHP 4021 TRP.001
- REACTOR TRIP REVIEW PROCEDURE *-
SIGNOFF SIIEET I UNIT ONE SWITCHGEAR COMPLEX RELAY TARGETS TIME DATE PERFORHED BY:
RC Pump Bus and T-bus 4KV Switchgear:
List all relay targets actuated. Specify "1", "3", or "N" where applicable. Note alarm lights lit
("GF", "0T", PL, etc.).
Reset Breaker Inst rument No. Name Attempted Successful 600 V Safety Bus Switchgear List all relay targets actuated. Include relays on back of breaker panels (0),2,3 feeder relays).
Reset Instrument No. Name Attempted Successful
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. . 12 PHP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 2 UNIT 1 CHART COLLECTION The I & C Section is to obtain a copy of the following charts for all Reactor Trips:
Pressurizer Water Level Pressurizer Pressure Operations Sequence Monitor P-250 Trend (Post Trip Review)
P-250 Alarm (Sequence of Events)
Control Room Log Wide Range Temperature, All Four Loops.
As specified by the cogaizant STA, the I & C section is to obtain a copy of any chart associated with the specific transient causing the trip.
As specified by the cognizant STA, obtain a copy of charts associated with any equipment which has malfunctioned:
Charts Reviewed By: /
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- 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDLRE SIGNOFF SLEET 3 UNIT ONE PERSONNEL INTERVIEW FORM Person. interviewed ' Role in Event Description of the event:
Include the plant conditions prior to the trip, your indications that a problem existed, your action as a result of those indications, noted equipment l malfunctions or inadequacies, and any identified procedure deficiencies.
INTERVIEWED BY REVIEWED BY /
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Page 1 of 1 Rev. I n_
. a 12 PHP 4021 1kP.001 ,
REACTOR TRIP REVIEW PROCEDURE .
SIGNOFF SilEET 4 kEACTOR TklP EXPECTED RESPONSE (UI)
Acceptance Expected Response Data Type Requirement Time Criteria Point # (Initial Event) Pleas All 0 0 44 Reactor Trip Breaker A Me.a s Al1
- 45 Reactor Trip Breaker B Meas All
- 46 Reactor Trip Breaker Undervoltage coil A tiea s Obsv Yes 47 Reactor Trip Breaker Undervoltage coil B Meas Obsv Yes Control Rods Buttom Of,sv All Yes 4
Mechnical Trip Operated (Turb) Ol+sv All
- 112 WtlFPT Vacuum Trip IIca s WMFPT V.sc Trip Reset
- 98 EMFPT Vacuum Trip th as ENFPT Vac Trip Reset
- 118 WtlFPT liyilr Pr Low flea s WrfFPT Ryet _*
104 EMFPT liydr Pr 1.ow flea s EMFPT Reset
- Feedwater Isolation Olesv On Main Feed Yes WMDAFP Start Obsv On Main Feed, Aux feed on standby Yes Et!DAFP Start Obsv On Main Feed, Aux feed on standby Yes TDAFP Start Obsv On Main Feed, Aux Yes feed on standby If start signal required
- - To be compared to past trips as per 4.6.4 Page 1 of 3 Rev. 1
12 PHP 4021 TRP.001 -
REACTOR TRIP REVIEW PROCEDURE -
SIGNOFF SHLET 4 TURBINE TRIP EXPECTED RESPONSE (UI)
Acceptance Expected Response Data Type Requirement Time Criteria (Initial Event) Heas 0 0 006 RT-Turbine Trip + P7 Heas Turbine Reset & above P-7
- 140 Hech Trip Oper Meas Turbine Reset
- 141 Emerg Gov OV3P Trip Heas Turb Reset
- 127 NT Reheat VA Cl. Meas Turb Reset
- 126 NT Stop VA CL Heas Turb Reset
- 157 overall Di f f Oper Heas Turb Reset
- 137 EHC Trip Sys Trip Heas Turb Reset
- 147 TRB Oil Bufpp Run Heas Turb Reset
- 153 STM Seal PR I.uw Heas Turb Reset
- Steam Dump Actuation Obsv Tavg Mode Yes
- - To be compared to past trips as per 4.6.4 Page 2 of 3 Rev. 1
12 PMP 4021 TRP.001
- REACTOR TRIP REVIEW PROCEDURE
- SIGNOFF SHEET 4 GENERATOR TRIP EXPECTED RESPONSE (Ul)
Acceptance Expected Response Data Type Requireeient Time criteria (Initial Event) 0 0 Mech Trip Oper Meas Generator Exciter 157 Overall Diff Oper Meas Generator Exciter
- 159 Alterx Diff Oper Meas Generator Exciter
- 156 Generat Motoring Meas Generator Exciter
- 164 Unit /Sys Freg Hi Lo Meas Generator Exciter
- 151 Gen Cool Flow to Meas Generator Exciter 162 Gen Cool Trip Oper Meas Generator Exciter Trans To Normal Reserve Obsv Gen Supplies Auxiliaries Yes Generator Field Breakers Open Obsv Field Breaker Closed Yes Generator output Breakers Open obsv Paralleled Yes i
I
[
- - To be compared to past trips as per 4.6.4 1
REVIEWED ItY / l
/
/
Page 3 of 3 Rev. I
~
7 12 Pr!P 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SEEET 5 UNIT ONE SYSTEM STATUS AND RESPONSE Nuclear Instrumentation List all NI drawer " negative rate" trip status lights which are energized.
Source Range instrument power restored automatically as designed (both channels)
Major equipment out of service:
Describe any abnormal conditions (such as
' loss of detector voltage' or ' channel in test' ) or behavior noticed during the transient.
Reactor Coolant Pumos Describe circumstances, including place in sequence of events, of any RCP trips (manual or automatic) which occurred during the transient.
Describe effect of reactor transient on leakoff flows.
Describe any behavioral abnormalities noticed during the transient.
Page 1 of 10 Rev. 1
..l* .
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SIEET 5 UNIT ONE RCS Pressure Control control statu; prior to trip (man / auto)
Backup heaters "on" banks
" auto" banks Pressure channels selected (control /bistables) /
Pressurizer PORV's blocked prior to transient:
Spray valves in " auto" Did pressurizer PORV's or safeties lift during transient? Describe circumstances.
Major equipment out of service:
Describe any behavioral abnormalities noticed during the transient Pressurizer Level Control Control Status prior to trip (man / auto) 3 Charging pump in service Charging flow controller (QRV-251 or Recip speed controller) status prior to trip (man / auto)
Level channels selected (control /bistables) /
Describe any behavioral abnormalities noticed during the transient.
Page 2 of 10 Rev. 1
3
, , 12 PMP 4021 TRP.001 ,
REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5 UNIT ONE CVCS Makeup Prior to transient, blender line contained (acid, pri. water, blend)
Makeup in auto with ' start' signal?
(yes/no)
Control and Shutdown Rods Full insertion of all control and shutdown rods verified.
Rods that did not insert:
Rod control status prior to trip (auto / man)
Was the rod control status changed during the transient? If so, when in the sequence of events?
Major equipment out of service:
Describe any behavioral abnormalities noticed during the transient.
Main Feedwater/ Steam Generator Level Operating main feed pumps tripped on reactor trip (yes/no/OOS)
EMFP WNFP Page 3 of 10 Rev. 1 I .
. .. 12 PliP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5 UNIT ONE Feed water isolation received when Tavg
<554*F. Valves closed (yes/no)
FRV210 FRV220 FRV230 FRV240 FMO201 FMO202 FMO203 '
FMO204 Feedpump control status prior to trip (auto / man)
East feedpump speed control West feedpump speed control DP controller Feedpump steam supply prior to trip East feedpump (reheat / main / aux)
West feedpump (reheat / main / aux) i Feedwater regulating valve status prior to trip (auto / man)
FRV210 FRV220 FRV230 FRV240 Condensate bypass valve status prior to trip (auto / man)
CRV224 Feedwater Heater level controls in manual prior to trip:
Major equipment out of service:
i i
E i
Page 4 of 10 ,
Rev. I 1
._ . _ . - . - . - __ _ _ _ - - _ _ _ _ . , _ . _ ~ - _ . . _ . ~ _ _ _ _ _ . , . _ _ _ _ _ _ . _ _ _ _ _ . , _ , , _ . . - . . -. _ , _ _ , , , _ _ _ _ . , _ _ _ _ _ _ _
1
.- .r 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW P?.0CEDURE.
SIGNOFF SIGIT 5 UNIT ONE Describe any behavioral abnormalities noticed during the transient.
'MDAFP's. started automatically on trip of main feedpumps EMDAFP WMDAFP TDAFP opearated? Describe circumstances and approximate duration of operation.
Did operator intervene in the TDAFP response (place in manual or trip)? If so, when in the sequence of events?
Describe the response of the S/G levels.
Describe any behavioral abnormalities noticed during the transient.
Steam Dump / Steam Generator Pressure Relief Control status prior to trip (Tavg/ Steam Pressure)
If in Tavg mode, steam dump valves modulated to maintain Tavg $547. (yes/no)
If Tavg dropped below S41*F, steam dump blocked (yes/no)
Page 5 of 10 Rev. 1
12 PrtP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 5 UNIT ONE Did steam dump valve open prior to trip (yes/no)? If yes desribe.
If vacuum trip, did steam dump valves stay closed (yes/no)?
Control status of atmospheric steam dumps prior to trip (auto / manual)
MRV 213 MRV 223 MRV 233 MRV 243 Did atmospheric steam dumps operate during transient (yes/no)? If yes, describe (automatically, manually, circumstances).
Was the control status of atmospheric steam dumps chat.ged during the course of the transient? If so, when in the sequence of events? ,
Did steam generator safeties lift during transient (yes/no)? If yes describe.
Major equipment out of service.
Describe any other behavioral abnormalities noticed during transient.
Page 6 of 10 Rev. I a
. .. 12 PMP 4021 TRP.001 REACIOR TRIP REVIE'd PROCEDURE SIGNOFF SHEET 5 UNIT ONE
. Main Turbine /MSR Was there a turbine runback (yes/no)'.
If yes, provide best estimate of power change and the time in sequence of events when it occurred.
Did the operator intervene in the turbine runback? If so, when in the sequence of events?
Turbine trip: Main turbine stop, control, and intercept valves closed Controlling device prior to trip (load limiter / operating device)
Set rates loading unloading Were valve or misc turbine tests in progress when the trip occurred?
Which one?
Did exhaust hood sprays actuate (yes/no)?
Vacuum breakers opened following trip?
(yes/no)
' Hogging' SJAE's in service following trip?
(yes/no)
Page 7 of 10 Rev. 1
3
.. 12 PMP 4021 ThP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SEEET 5 UNIT ONE MSR in service prior to trip?
(no/ partial / full)
Did any MSR safety valves lift during the transient (yes/no/ identify)?
Major equipment out of service:
Describe any behavioral abnormalities noticed during the transient.
Generator / Electrical Generator trip. This will occur 30 seconds ,
after the reactor trip unl'ess it results from
, a generator event.
Output breakers open (yes/no)
K K1 Exciter breaker open (yes/no)
If auxiliaries were suppled by the generator, were auxiliaries automatically transferred to normal reserve (yes/no/NA)? Describe any failures.
Diesel generators operated?
Describe curcumstances.
Page 8 of 10 Rev. 1
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SliEET 5 UNIT ONE Any CRID or CRP bus switched to alternate supply? Describe circumstances.
(OSM point 154, white light on G panel, ann 19 drops 20 + 40, ann 20 drop 80 + 100).
Major equipment out of service:
Describe any behavioral abnormalities noticed during transient.
Safety Injection 6
Was the event associated with an SI (yes/no)?
If yes, did verification of automatic actuations indicate failure of any required response (yes/no)?
If yes, list actuations not received, reason if known, and whether the response was successfully initiated manually.
List major equipment out of service.
Describe any abnormalities noticed in the response of the safety injection system.
Page 9 of 10 l Rev. 1 I
i
.' +
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDLTE SIGNOFF S}EIT 5 UNIT ONE Phase B Was there a phase B (yes/no)?
If yes, did verification of automatic actuations indicate failure of any required response (yes/no)?
If yes, list actuations not received, reason if known, and whether the response was successfully initiated manually.
List major equipment out of service.
Describe any abnormalities noticed in the response of the CTS System.
Miscellaneous List any major plant equipment not covered above which is out of service and could have had an effect on the progression of the transient.
Describe any behavioral abnormalities of systems not covered above which may affect plant safety.
COMPLETED BY REVIEWED BY /
/
/
Page 10 of 10 Rev 1
T
, . 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SEET 6 UNIT ONE CORRECTIVE ACTION REVIEW A. Trip signal which initiated RPS:
B The determined cause of the trip signal was: (check one)
- 1. Equipment Failure -
- a. Failed component:
- b. Mode of failure:
- c. Spurious:
- d. Is this a repetive failure?
- 2. Procedural defect (see procedure step 4.3)
- 3. Personnel Error (see procedure step 4.3)
STA: S.S. ;
Departments Affected:
C. Description of error: (ccmplete only if B.2 or B.3 apply) i (include interviews with affected personnel in P.T.R. package).
STA signature: Reviewed by: Dept's Affected:
D. Immediate actions required to mitigate the failure or error prior to restart of Unit:
STA signature: Dept's Affected:
E. Actions proposed to prevent recurrence:
STA signature: Dept's Affected:
Reviewed by /
/
Page 1 of 1 Rev. 1
4 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 7 Unit One This checklist is to assist in organizing the requirements for reactor restart. The event condition determined by 4.7 " Event Classification" should be circled below and the other two columns N/A'd. The space provided is to be initialed and dated by the STA when the associated requirement has been completed.
Condition Condition Condition One Event Two Event Three Event Signoff Sheet 1 / / /
Signoff Sheet 2 / / /
Signoff Sheet 3 / / /
Signoff Sheet 4 / / /
Signoff Sheet 5 / / /
Signoff Sheet 6 / / /
Signoff Sheet 8 / / /
PNSRC Approval N/A N/A /
j Page 1 of 1 Rev. 1
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 8 UNIT ONE Items Requiring Action Assignments Status Time and Date Status of Item Requiring Action STA Page 1 of 1 Rev. 1
r 12 PHP 4021 TRP.001 .
REACTOR TRIP REVIEW PROCEDURE SIGNOFF SILEET 11 -
PANEL G RELAY TARGETS UNIT 2 l
l (HAA) (HAA) (HAA) l l
l TI7 TIS 719 TI T2 T3 Til T12 1 Maia Transf Main Transf Main Transf Turbine Generator Excitation Turbine Stator l Sudden Sudden Sudden Valves Relays Relays Tripping Cooling
! Press. PH.1 Press. PH.2 Press. PH.3 (Right Sys) Trip l
T23 T21 T4 T5 T6 Trs=s. 2AB Trans 2CD Turbine Trans former Emerg. P. B.
Sudden Sudden Tripping Relays Trip Press Press (Left Syst) Gen. Panel ,
- UNIT DIFFERENTIAL (HEA) OVERALL DIFFERENTIAL (KEA) l 27X-U2 87XI-U2 87X2-U2 87X-QA2 87XI-QA2 87X2-OA2 l
l .
1 I
- l l -
i h
I l
~
l :
^
j ,
i
! Page 1 of 6 l Rev. 1 i
. ; .! . ii . ; : , T -
~ '.
A l O3 T3 G3 e4 - - -
n- 7H 7H 7M aA 8P 8P 8P P
E R
U D
E A C O2 T2 G2 O - - -
R 7H 7M 7H P 8P 8P 8P 1 W 0E 0.V1I PE1 A RR O1 T1 G1 T T - . - . - .
PE 7H 7M 7H 1I E 8P 8P 8P 6 2RH 2TS f 4 o RF POF 21 MTO PCN e .
AG gv 2EI ae 1 RS S PR T
E G
R A
T Y2 A l LT e3 EI n-RN aA U P 8 A A 3 5 8 2 L
E N N N 9 A 9 5 l' 5 1 G Z 3 5 8 2 A3 7H 8P l F e2 A n- -
aA 4 P 6 S S G A2 G -
- - 1 7H 6 5 8P 9 1 F
A1 G 7H 4 8P 6
)
- . . - . - - _ - .- . - _ . - . - . - . - . . - . - - . - ~. - - . . ~ . - - - . _ ~ _ - - . . - - . _ - . - _. . _ . . ..
l -
12 PHP 4021 TRP.001 ' '
REACTOR TRIP REVIEW PROCEDURE .i SIGNOFF SHEET 11 ,
PANEL A RELAY TARGETS IMIT 2 Panel Panel Panel A-7 A-8 A-9 t
125A 25 TAB 87T-AB 87T-AB 87T-AB 87T-CD 877-CD 87T-CD 87T-201AB 87T-201AB 87T201AB PH.1 PH.2 PH.3 PH.I Pil.2 PM.3 PH.1 PH.2 PH.3 SITM-AB 251TN- SITN-CD 251TN- SITN- TR-201AB 251TN AB CD 201AB Volt Low 201AB PM.1* PM.2* PH.3*
T21A Volt Low PH.1* PH.2* PH.3*
- Relay is Actuated when white light is unlit. !'
Page 3 of 6 Rev. 1
- n. , ,m., , - _ , _ _ - -.m,- - - - , - , , . , .
12 PHP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 11 ,
PANEL A RELAY TARGETS UNIT 2 Panel Panel Panel A-10 A-Il A-12 l
l
~
l 25-TCD $1T-21A SIN-T218 SIT-21B 87-RCPI 87-RCPI 87-RCPI PH.1 PH.1 PH.1 PH.2 PH.3 51T-21A SIT-21B 87-RCP2 87-RCP2 87-RCP2 .
PH.3 PH.3 PH.1 PH.2 PH.3 ,
1 .
l 87-DCAB 87-DGAB 87-DCAB 87-TBMC 87-TBMC 87-TBMC PH.1 P11.2 PH.3 PH.1 PH.2 PH.3 877-201CD 87T-201CD 87T-201CD 87T-2]A 87T-21A 87T-21A 87-TCHC 87-TCMC 87-TCMC k Pi!.1 PH.2 PH.3 PH.1 PH.2 PH.3 Pd.1 PH.2 PH.3
- SITN- TR-201CD 251TN- 87T21B 87T21B 87T21B 87-RCP3 87-RCP3 87-RCP3 201CD Volt Low 201CD PH.1 PH.2 PH.3 PH.1 PH.2 PH.3 PH.12 PH.2* PH.3*
T21D Volt Low SIDCAB 51NDGAB SIDGAB 87-RCP4 87-RCP4 87-RCP4 PM.l* PH.2* PH.32 PH.1 PH.3 PH.1 PH.2 PH.3
- Relay is Actusted when white light is unlit.
l Page 4 of 6 i Rev. 1 .
l I
12 PftP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SMEET 11 PANEL A REIAY TARGETS tlNIT 2 Panel A-13 l .
l l 51T-21C SIhT-21C 517-21D PH.I PH.1 l
l SIT-21C 517-21D l PM.3 Pli.3 l
$7-DGCD 87-DCCD 87-DCCD PH.I PH.2 PH.3 {
! 87-721C 87-721C 87-T21C PM.I PN.2 PM.3 Ii 87T-21D 877-21D 877-21D i
- j Ph.1 PM.2 PH.3 t'
51-DCCD SIN-DGCD 51-DGCD i PM.1 PM.3 6
=
i Page 5 of 6 I Rev. I !
12 PHP 4021 TRP.001 ,
REACTC3 TRIP REVIEW PROCEDURE S1GNOFF SHEET I1 .
l UNIT TWO l
SWITCHGEAR COttPl.EX RELAY TARGETS ,
TlHE DATE PERFORNED BY:
RC Pump 3us and T-bus 4KV Switchgear:
List all relay targets actuated. Specify "1", "3", or "N" where applicable. Note alarm lights lit
("GF", "CT" PL, etc.).
keset Breaker Instrument No. Name Attempted Successful i,00 V Safety kus Switchgear .
List all r+1ay targets actuated. Include relays on back of breaker panels (feeder relays).
- Reset Instrument No. Name Attempted Successful
- COMPIETED BY / REVIEW.D BY /
/
/
Page 6 of 6 kev. 1
, 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 12 l
l UNIT 2 I
CHART COLLECTION l
l The I & C Section is to obtain a copy of the following charts for all Reactor Trips:
l Pressurizer Water Level l Pressurizer Pressure Operations Sequence Monitor P-250 Trend (Post Trip Review)
P-250 Alarm (Sequence of Events)
Control Room Log Wide Range Temperature, All Four Loops.
As specified by the cognizant STA, the I & C section is to obtain
< a copy of any chart associated with the specific transient l causing the trip.
l l
l l
l As specified by the cognizant STA, obtain a copy of charts j associated with any equipment which has malfunctioned:
l Charts Reviewed By: /
/
l 1
/
l Page 1 of 1 Rev. 1 l
l _
- -, . 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 13 UNIT TWO PERSONNEL INTERVIEW FORM Person interviewed Role in Event Description of the event:
Include the plant conditions prior to the trip, your indications that a problem existed, your action as a result of those indications, noted equipment malfunctions or inadequacies, and any identified procedure deficiencies.
INTERVIEWED BY REVIEWED BY /
/
/
Page 1 of 1 Rev 1 A
12 PHP 4021 TRP.001 ~
REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 14 ,
UNIT TWO REACTOR TRIP EXPECTED RESPONSE (U2)
Expected Response Data Type Requirement Time Criteria (Initial Event) Neas All 0 0 44 Reactor Trip Breaker A Neas All
- 45 Reactor Trip Breaker B Neas All
- 46 Reactor Trip Breaker Undervoltase coil A Obsv All Yes 47 Reactor Trip Breaker Undervoltage coil B Obsv All Yes Control Rods Botton Obsv All Yes 131 Main Turbine Lef t System Trip Heas All -
132 Main Turbine Right System Trip Mcas All
- 111 WMFPT Vacuum Trip Meas WMFPT Vac Trip Reset
- 99 EMFPT Vacuum Trip neas EMFPT Vac Trip Reset
- 114 WMFPT Emergency System Trip Heas WMFPT Reset
- 102 EMFPT Emergency System Trip Mcas EMEPT Reset
- Fredwater Isolation (<554*F) obsv On Main Feed Yes WHDAFP Start Obsv On Main Feed, Aux feed on standby Yes EMBAFP Start Obsv On Main Feed, Aux feed on standby Yes TDAFP Start Obsv On Main Feed, Aux Yes feed on standby If start required ,
- - To be compared to past trips as per 4.6.4 Page 1 of 3 kev. 1
l 12 PMP 4021 TRP.001
- REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 14 ,
UNIT TWO TUhblE TRIP EXPECTED RESPONSE (U2) ;
Acceptance Erpected Response Data Type Requirement Time Criteria (luitial Event) Meas Turb Reset 0 0 131 Main Turbine 1ef t Systes Trip Heas Turb Reset
- 132 Main Turbine Right System Trip Meas Turb Reset
- 151 Left Emergency Circuit Trip (<8.5 psig) Meas Turb Reset
- 152 Right Emergency Carcuit Trip (<8.5 psig) Mens Turb Reset
- 137 Contaal Fluid Safety Circuit Trip Heas Turb Reset
- 139 Auxilliary Lute Oil Pump Turb keset
- __ Meas 140 West Emerrency Lube Oil Pump Running Meas Turb Reset
- l 141 East Emerrency Lube Oil Pump Running Mcas Turb Reset
- l 121 Main Turi ane Stop Valves _ Closed Meas Turb Reset
- l 122 Main Turbine Intercept Valves Closed Meas Turb Reset
- 6 kcactor T_r p f rom Turbine Trip Meas Above P-7
- 115 Overall Dafferential Generator Trip -
from Turbine Stop Valves Closed Meas Turb Reset
- Steam Dump Ac t uat ion obs lavg Mode Yes
}
?
- - To be compared to past trips as per 4.6.4 Page 2 of 3 Rev. I
. 1 12 PHP 4021 TkP.001 REACTOR TRIP REVIEW PROCEDURE ,
SIGNOFF SHEET 14 LMIT TWO GENERATOR TkIP EXPECTED RESPONSE (U2)
Acceptance Expected Response Data Type Requirement Time Criteria (Initial Event) Meas Generator Exciter 0 0 131 h im Turbine Left System Trip Meas Generator Exciter
- 132 h im Tubine Right System Trip Meas Generator Exciter
- Transfer to Normal Reserve Obs Gen Supplies Auxiliaries Yes Generator Field Breakers Open obs Field Breaker Closed Yes Generator Output breakers Open Obs Paralleled Yes
- - To be compared to past trips as per 4.6.4 Reviewed by /
/
/
Page 3 of 3 Rev. I
~
- 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE ~
SIGNOFF SHEET 15 ,
UNIT TWO SYSTEM STATUS AND RESPONSE Nuclear Instrumentation List all NI drawer " negative rate" trip status lights which are energized.
! Source Range instrument power restored I
automatically as designed l (both channels) l Major equipment out of service:
1 i
Describe any abnormal conditionc (such as
' loss of detector voltage' or ' channel in test'1 or behavior noticed during the trans:.ent.
Reactor Coolant Pumps Describe circumstances, including pince in sequence of events, of any RCP trips i (manual or automatic) which occurred l
during the transient.
Describe effect of reactor transient on leakoff flows, t
l Describe any behavioral abnormalities
! noticed during the transient, l
l .
t Page 1 of 10 :
Rev. 1 j t
b o . 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE l
SIGNOFF SKEET 15 ;
UNIT TWO l
! RCS Pressure Control Control status prior to trip (man / auto)
Backup heaters "on" banks
" auto" banks Pressure channels selected (control /bistables) /
Pressurizer PORV's blocked prior to l transient:
! Spray valves in " auto" l Did pressurizer PORV's or safeties lift l during transient? Describe circumstances.
l Major equipasent out of service Describe any behavioral abnormalities noticed during the transient Pressuricer Level Control control Status prior to trip l (man / auto) l i Charging pump in service Charging flow controller (QRV-251 or Recip
! speed controller) status prior to trip l (man / auto) l Level channels selected (control /bistables) /
Describe any behavioral abnormalities noticed during the transient.
l l Page 2 of 10 l
Rev. 1
^
12 PMP 4021 TRP.001 f REACTOR TRIP REVIEW PROCEDURI SIGNOFF SKEET 15 UNIT TWO l
CVCS Makeup i Prior to transient, blender line contained (acid, pri, water, blend) i i
Makeup in auto with ' start' signal?
(yes/no) l l
l Control and Shutdown Rods Full insertion of all control and shutdown rods verified.
l Rods that did not insert:
Rod control status' prior to trip (auto / man) l Was the rod control status changed during the l
transient? If so, when in the sequence of events?
l Major equipment out of servicer Describe any behavioral abnormalities noticed during the transient.
Main Feedwater/ Steam Cenerator Level l
Operating main feed pumps tripped on reactor trip (yes/no/cos) l EMFP l WMFP l
Page 3 of 10 l Rev. 1
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDUR SIGNOFF SHEET 15 UNIT TWO Feed water isolation received when Tavg
<554*F. Valves closed (yes/no) l FRV210 FRV220 FRV230 i
FRV240 l FMO201 l FMO202 l FMO203 l FMO204 Feedpump control status prior to trip (auto / man)
East feedpump speed control West feedpump speed control DP controller Feedpump steam supply prior to trip l East feedpump (reheat / main / aux)
West feedpump (reheat / main / aux)
- Feedwater regulating valve status prior to l trip (auto / man) l l FRV210 FRV220 FRV230 FRV240 i
Condensate bypass valve status prior to trip (auto / man)
CRV224
! Feedwater Heater level controls in manual prior to trips i
l l
Major equipment out of service:
Page 4 of 10 Rev. 1 i
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURI SIGNOFF SHEET 15 UNIT TWO Describe any behavioral abnormalities noticed during the transient.
Auxiliary Feedwater MDAFP's started automatically on trip of main feedpumps EMDAFP WMDAFP TDAFP opearated? Describe circumstances and approximate duration of operation.
Did operator intervene in the TDAFP response (place in manual or trip)? If so, when in the sequence of events?
I Decribe the response of the S/G levels.
l I
Describe any behavioral abnormalities noticed during the transient.
l l
l l Steam Dump / Steam Generator Pressure Relief Control status prior to trip (Tavg/ Steam Pressure)
If in Tavg mode, steam dump valves modulated to maintain Tavg $547. (yes/no)
If Tavg dropped below 541*F, steam dump blocked (yes/no)
Page 5 of 10 Rev. 1
l 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 15 UNIT TWO l Did steam dump 'ralve open prior to trip
- (yes/no)? If yes desribe.
l If vacuum trip, did steam dump valves stay l closed (yes/no)?
Control status of atmospheric steam dumps prior to trip (auto / manual) l
, MRV 213 l MRV 223 MRV 233 MRV 243 Did atmospheric steam dumps operate during transient (yes/no)? If yes, describe (automatically, manually, circumstances).
Was the control status of atmospherie steam
, dumps changed during the course of the transient? If so, when in the sequence of events?
l l
l Did steam generator safeties lift during
, transient (yes/no)? If yes describe.
l Major equipment out of service.
Describe any other behavioral abnormalities noticed during transient.
I i
i
- Page 6 of 10 l Rev. 1 l
12 FMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 15 UNIT TWO Main Turbine /MSR Was there a turbine runback-(yes/no)?
If yes, provide best estimate of power change and the time in sequence of events when it occurred.
Did the operator intervene in the turbine runback? If so, when in the sequence of events?
Turbine trip: Main turbine stop, control, and intercept valves closed controlling device prior to trip (load limiter / operating device)
Set rates loading unloading were valve or misc turbine tests in progress when the trip occurred?
Which one?
Did exhaust hood sprays actuate (yes/no)?
) Vacuum breakers opened following trip?
(yes/no)
' Hogging' SJAE's in service following trip?
. (yes/no)
Page 7 of 10 Rev. 1
. .. ..a._. ... . . . .
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 15 UNIT TWO MSR in service prior to trip?
(no/ partial / full)
Did any MSR safety valves lift during the transient (yes/no/ identify)?
. Major equipment out of service:
Describe any behavioral abnormalities noticed during the transient.
I Generator / Electrical Generator trip. This will occur 30 seconds after the reactor trip unless it results from a generator event.
output breakers open (yes/no)
Al A2 Exciter breaker open (yes/no)
If auxiliaries were suppled by the generator, were auxiliaries automatically transferred to normal reserve (yes/no/NA)? Describe any failures.
Diesel generators op6 rated?
Describe curcumstances.
Page 8 of 10 Rev. 1 w - 1
._ ,s 12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 15 UNIT TWO Any CRID or CRP bus switched to alternate supply? Describe circumstances.
(OSM Point 156, white light on G panel, ann 20 drops 80+100, ann 19 drops 20+40 Major equipment out of service:
Describe any behavioral abnormalities noticed during transient.
Safety Injection Was the event associated with an SI (yes/no)?
If yes, did verification of automatic actuations indicate failure of any required response (yes/no)?
If yes, list actuations not received, reason if known, and whether the response was successfully initiated manually. -
List major equipment out of service.
Describe any abnormalities noticed in the response of the safety injection system.
Page 9 of 10 Rev. 1
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 15~
UNIT TWO Phase B Was there a phase B (yes/no)?
If yes, did verification of automatic actuations indicate failure of any required response (yes/no)?
If yes, list actuations not received, reason if known, and whether the response was successfully initiated manually.
List major equipment out of service.
Describe any abnormalities noticed in the response of the CTS System.
Miscellaneous.
List any major plant equipment not covered above which is out of service and could have had an effect on the progression of the ,
transient. -
Describe any behavioral abnormalities of systems not covered above which may affect plant safety.
COMPLETED BY REVIEWED BY /
/
/
Page 10 of 10 Rev. 1
.. . . . . . . . . - . . ~ . . .. .
'~ '
12 PMP 4021 TRP.001
. REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 16 UNIT TWO CORRECTIVE ACTION REVIEW A. Trip signal which initiated RPS:
B The determined cause of the trip signal was: (check one)
- 1. Equipment Failure -
- a. Failed component:
- b. Mode of failure:
- c. Spurious:
- d. Is this a repetive failure?
- 2. Procedural defect (see procedure step 4.3)
- 3. Personnel Error (see procedure step 4.3)
STA: S.S.
Departments Affected:
C. Description of error: (complete only if B.2 or B.3 apply)
(include interviews with affected personnel in P.T.R. package).
STA signature: Reviewed by: Bept's Affected:
D. Immediate actions required to mitigate the failure or error prior to restart of Unit:
STA signature: Dept's Affected:
E. Actions proposed to prevent recurrence:
STA signature: Dept's Affected:
REVIEWED BY /
/
Page 1 of 1 Rev. 1 m
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURE SIGNOFF SHEET 17 Unit Two This checklist is to assist in organizing the requirements for reactor restart. The event condition determined by 4.7
" Event Classification" should be circled below and the other two columns N/A'd. The space provided is to be initialed and dated by the STA when the associated requirement has been completed.
Condition Condition Condition One Event Two Event Three Event Signof f Sheet 11 / / /
Signoff Sheet 12 / / /
Signoff Sheet 13 / / /
Signoff Sheet 14 / / /
Signoff Sheet 15 / _ / /
Signoff Sheet 16 / / /
Signoff Sheet 18 / / /
PNSRC Approval N/A N/A /
Page 1 of 1 Rev. 1
._ ~
12 PMP 4021 TRP.001 REACTOR TRIP REVIEW PROCEDURI:
SIGNOFF SHEET 18 UNIT TWO Items Requiring Action Assignments
- Status Time and Date Status of Item Requiring Action STA
}
Page 1 of 1 Rev. 1
~
.. _ . _ - =. .
12 PMP 4021.TRP.001 APPENDIX A APPENDIX A: Miscellaneous Information Relating to the Operation of Trip Monitoring Devices.
1 i
i Page 1 of 40 Rev. 1
- m. s
i I
- '<. l 12 PMP 4021.TRP.001 APPENDIX A I. HATHAWAY OPERATIONS SEQUENCE MONITOR The sequence monitor provides a printed record of the operation of certain selected events. It has the capacity to monitor 192 on-off points and produces a line item output on a printer located in the control room when any one of the monitored points indicates an abnormal condition. Forty five points are used to monitor events related to reactor trip initiation or reactor trip circuit breaker position, 6 points monitor condensate or hotwell pumps, 13 points monitor feedwater' heater extreme high level events, 6 points monitor onsite power diesel generators, 22 points monitor the main feedwater pumps, 40 points monitor the main turbine-generator, and 8 points monitor the step-up and auxiliary transformers and miscellaneous items.
The operations sequence monitor permits discrimination for contact closures which occur more than 2 milliseconds apart.
A contact closure will result in a line item printout on a dedicated printer located in the control room. The line item contains a 3 digit number for the day of the year, a 4 digit number for the hours a minute, a 2 digit number for the second, a 3 digit number for the milliseconds, an "A" indicating an off normal condition, a 3 digit number to identify the event to the operator. A sample output is attached to the end of this section.
The following information elaborates on the meaning of particular alarms that commonly appear as a result of reactor trips.
Page 2 of 40 Rev. 1 m
~ '
12 PMP 4021.TRP.001 APPENDIX A A. UNIT I 019 Reactor Trip, S.G. Lo Lo Water Level, Loop 4.
This alarm is a typical example of a signal from the RPS initiating a trip.
044 Reactor Trip Breaker Tripped, Train A.
This alarm originates from breaker position limit switches. It indicates the breaker is actually open.
046 Reactor Breaker Undervoltage, Train A.
This alarm indicates the undervoltage trip attachments have operated. They report late in spite of the fact UVTA's actuate the trip breakers for reactor trips other than manual trips. This situation results from the fact that the auxiliary relay the reports the event is part of an RL circuit. The delay is ~200 msec. 112 WMFP Vaccuum Trip As indicated on elementary, Dia 1-98212-5 coordinate H-3, this alarm indicates a vacuum trip has occurred.
1118 WMFP HYDR. Press Low.
This alarm results when the MFP Hydr. Oil pressure reaches 130 psi dec.
140 Mechanical Trip Operated.
This alarm indicates a turbine trip has been initiated. As indicated on elementary diagram 1-98101, the following trip signals will initiate this alarm:
- 1) Overall differential Page 3 of 40 Rev. 1
= , .
12 PMP 4021.TRP.001 APPENDIX A
- 2) Unit differential
- 3) Thrust bearing wear & low bearing oil trip
- 4) MSR level
- 5) Turbine high vibration trip
- 6) Turbine solenoid trip
- 7) Loss of stator cooling turbine trip
- 8) Turbine low vacuum trip
- 9) EHC low hydraulic press trip
- 10) EHC trip system press trip
- 11) Turbine shaft P.P. low oil press trip
- 12) EHC master trip
- 13) Rx trip train A + SG HI HI or S.I.
156 Generator Motoring As indicated on elementary Dia 1-98021-2 coordinates C1, this alarm results from: (All valves closed or control valves at no load position) and (generator output breakers closed).
B. UNIT II
. 019 Reactor Trip, S.G. Lo Lo Water Level, Loop 4 This alarm is a typical example of a signal from the RPS initiating a trip.
044 Reactor Trip Breaker Tripped, Train A This alarm originates from breaker position limit switches. It indicates the breaker is actually open.
(verbal comment by T. King)
Page 4 of 40 Rev. 1 m
12 PMP 4021.TRP.001 APPENDIX A 046 Reactor Breaker Undervoltage, Train A This alarm indicates the undervoltage trip attachments (UVTA's) have operated. They report late in spite of the fact UVTA's actuate the trip breakers for reactor trips other than manual trips. This situation results from the fact that the auxiliary relay that reparts, the event is part of an RL circuit. The delay is typically ~200 msec. 131 Main Turbine Left System Trip Chis alarm indicates a turbine trip has been initiated. As indicated on Elementary Diagram 2-98101, coordinate D-2, the following trip signals will initiate this alarm:
- 1) Turbine solenoid trip control switch
- 2) Unit overall differential
- 3) Transformer and generator unit differential
- 4) Thrust bearing position trip
- 5) Moisture separator reheater high level trip
- 6) Turbine vibration
- 7) Lube oil pressure low
- 8) Loss of stator cooling
- 9) Reactor trip, SI, or steam generator hi-hi
- 10) Turbine low vacuum trip
- 11) High exhaust hood temperature Page 5 of 40 Rev. 1 n )
.. . 12 PMP 4021.TRP.001 APPENDIX A 137 Main Turbine Control Fluid Safety Circuit Tripped As indicated on Elementary Diagram 2-98101, coordinate H1, this signal results from pressure switch 63X TSP indicating low pressure in the safety fluid circuit. It is operated by pressure switch 2515 on the Turbine Control Diagram, Figure PGS-4B-11 in the training manuals.
151 Left Emergency Circuit Tripped As indicated on Elementary Diagram 2-98102, coordinate D-7, this alarm results from pressure switch 63 ECL indicating that emergency circuit pressure dropped below 8.5 psig. It is operated by pressure switch 4591 on the Turbine Contrcl Diagram, Figure PGS-4B-11 in the training manual.
NOTE: 63 indicates a pressure switch on an elementary diagram.
158 Generator Motoring As indicated on Elementary Diagram 2-98021-2, coordinates D2, this alarm results from: (all valves closed OR control valves at no load position) AND (generator output breakers closed) 165 Turbine valve Trip overall Differential 4
As indicated on Elementary Diagram 2-98021-2, this signal results from a trip of the unit overall differ-ential by turbine valves closed and required delays.
111 FPTW Vacuum Trip Page 6 of 40 Rev. 1
~
[' .. . . . . . . . .: -
12 PMP 4021.TRP.001 APPENDIX A As indicated on Elementary, Diagram 98217-3, coordinate D-4, this alarm indicates a vacuum trip has occurred. It is operated by limit switch 33X BVTW on a mechanical linkage. This mechanical linkage is operated by all trips (verbal coment by T. King) and is expected for FPT trips initiated with the vacuum trip reset.
114 FPTW Emergency System Trip As indicated on Elementary Diagram 2-98217, coordinate H-3, this signal results from pressure switch 63X BESTW indicating low pressure in the emergency circuit.
NOTE: 33 indicates a limit switch on an elementary diagram.
NOTE: 63 indicates a pressure switch on an elementary diagram.
Page 7 of 40 Rev. 1
12 PMP 4021.TRP.001 APPENDIX A SAMPLE OSM OUTPUT Page 8 of 40 Rev. 1
- - m v. ...........n..5' * :L.; .
- 0 26 1630 00 40! 7 JD0 ;CCO3d 2 TECT PT 026 1730 00 c00 7 000 DCCC0K 2 TEST PT 12 PMP 4021.TRP.001 026 1830 00 400 T 000 DCCCOM 2 TEST PT APPENDIX A 026 1930 00 401 T 000 OCC00K 2 TEST PT 026 2030 00 401 T 000 DCC00K 2 TEST PT 026 2130 00 401 7 000 CCC00K 2 TEST PT 026 2215 OS 210 A 058 CG2A8 HEA CPER 026 2226 03 820 A 260 CG 2AB START
- 026 2230 00 401 7 000 CCC00K 2 TEST PT 026 2330 00 400 T 000 CCC00K 2 TOST PT 027 0030 00 400 T 000 DCC00K 2 TEST PT 0 27 0130 00 401 ? 000 DCCC0K 2 TEST PT 027 0230 00 401 7 003 OCC00K 2 TEST PT j3
[' ,{
027 0330 00 401 T 000 DCC00K 2 TEST PT f 0 27 0350 53 105 A 375 HTR IC LEVEL HI rg y A 0 27 0424 5S 082 A 149 MT VAC TRIP BLOCKED ^ '
~
0 27 0424 59 019 A 149 MT VAC TRIP BLOCKED '
027 0425 23 307 A 158 GENERAT MOTORING -- (
027 0425 25 128 A 313 RT LP3FCVT FL LO 0 27 0425 25 217 A 245 UEACT BKR TRIP B 027 0425 25 237 A 044 REACT BKR TRIP A 027 0425 25 261 A 13! MT L SYSTEM TRIP O* 0425 25 282 A 132 MT R SYSTEM TPIP 02' 04 2 5 2 5 4 3 6 A 0 0 8 PT LP I TD'.'T FL LO OOP 0425 0 27 25 461 A 151 LEFT EMERG CKT TRIP 0425 25 463 A 006 RT TURS TRIP 4 P7 027 027 0425 25 489 A !!! FPTV VACUUM TRIP 0 27 0425 25 535 A 099 TPTE VACUUM TRIP A425 25 610 A 029 RT Pt'RG PNRATE TR 0 27 C425 25 635 A 046 PEACT SKP. '"1 A
- 027.0425 25 639 A 047 *EACT SKR*fjV B '
027 0425 027 342525 25654 656AA~ 010 *T LP3FCVT FL LO
- 137 MT CONFL SAFCHT ,78 027 0425 26 224 A 102 FPTE EFE*G5YS TP 027 0425 26 242 A 075 HTR I C L E'IEL H !
027 0425 26 296 A 102 FFTE EFEPGSYS TR 027 0425 26 669 A 114 FFT*/ EMERCSYS TR 0 27 0425 27 480 A 016 RT SG1 L E'I EX LO 027 0425 27 756 A 016 *T 3GI LE*/ IM LO 3 27 0425 27 324 A 313 r? SG3 LEV EX LO 027 0425.23 999 A 017 *T SG2 LEV EX LC 227 0425 23 595 A 009 RT L?2FCVT FL LO 027 0425 2B 644 A 019 97 SG3 LEV EX LO 027 0425 29 895 A 010 PT.LP3FDYT FL LO 0 27 3425 2B 924 A 009 "T LP2FCt'T FL LO 0 27 3425 29 370 A 017 PT SG2 LEV EX LO 0 27 0425 29 174 A 000 RT LPlFO"T FL LO 0 27 3425 29 448 A O!! F .' LP4FCYT FL LC 027 0425 29 855 A 011 "T LP4FOT FL LO 0 27 0425 3? 220 A 019 FT SC4 L E'I EX LG 227 0425 34 467 A ! ! 3 FFT'.' CCNTC I L ?". LO 027 0425 34 845 A 101 FFTE C01.TCIL PR LC 0 27 0425 35 271 A 101 FFTE CONTC;L PR LO 0 27 3425 36 217 A 011 PT LP4FCVT FL LC -
0 27 0425 35 38G A ! ! 3 FFT CONTOIL ?* LO 0 27 0425 36 661 A 009 PT LP2F0VT FL L3 0 27 0425 35 868 A 101 F?TE CCNTOIL PP LO 027 2425 23 207 A all ST LP4FCYT FL LO 2 27 0425 38 622 A 009 RT LP2FO'?T FL LC 027 0425 38 763 A 310 FT LP3FOYT FL LO 027 0425 38 799 A O!! RT LPAFDVT FL LO Page 9 of 40 0 27 0425 38 Bl6 A DOS 97 LPITDYT FL LO Rev. 1 0 27 0425 39 248 A O!! "7 LP4FCVT FL LO 027 0 27 0425 0425 3939698 26% A 003 A .711 a7 ST L ? LPIF vT FL L3 4 FO','T FL L3
= .
12 PMP 4021.TRP.001 APPENDIX A II. ESTERLINE ANGUS TURBINE EVENT MONITOR.
The turbine event monitor is a dual unit strip chart recorder. Each of the 2 charts has 20 on-off points. The speed of the continuously moving charts is changed after a trip initiation so that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of chart are advanced through the recorder in 24 seconds. Fast speed on Unit I is 3 inches /sec.
Fast speed on Unit II is 1.5 inches /sec. The chart speed then returns to normal and a trip initiation event recurs. Two points, one on each chart, are used to monitor the Train A and Train B reactor trip circuit breakers, 2 points monitor electrical lockout relays which indicate an electrical system level trip, 16 points monitor the position of turbine emergency and pre-emergency valves Page 10 of 40 Rev. 1
. I
12 PMP 4021.TRP.001 APPENDIX A (stop and interceptor valves). The remaining points monitor various turbine trip initiating events.
The time discrimination between events is approximately 20 milliseconds when the chart is in high speed operation.
The data is displayed on 2 strip charts. Each point operates a heat pen which leaves a continuous trace on the thermally sensitized chart. The pens trace a printed line on the chart to indicate a normal condition. The pen moves off the printed line to a position approximately midway between the printed lines for 2 adjacent points to indicate an off normal condition. A sample strip chart is attached to the end of this section.
L Page 11 of 40 Rev. 1
12 PMP 4021.TRP.001 APPENDIX A UNIT I PEN IDENTIFICATIONS Equipment or Device Being Stylus number Chart Monitored
- 1.
- Unit differential
- 2.
- Overall differential
- 3.
- Reactor trip TR-A
- 4.
- Reactor trip TR-B
- 5.
- Mechanical trip
- 6.
- AEP to master trip
- 7.
- EHC master trip
- 8.
- Back-up overspeed trip
- 9.
- Loss of speed
- 10.
- Loss of station battery j 11.
- Trip system pressure EHC
. 12.
- Mechanical overspeed trip operated
- 13.
- Mechanical trip operated
- 14.
- Power load unbalance
- 15.
- AEP EHC trip system
- 16.
- Stop valves closed
- 17.
- Reheat and Intercept valves closed
- 18.
- Vibration trip operated
- 19.
- Trip system pressure HFA 2
- 20.
- Time Stylus Number, Chart 2 Equipment or Device 3 21. Stop valve No. 1 closed i 22. Stop valve No. 2 closed
- 23. Stop valve No. 3 closed
- 24. Stop valve No. 4 closed
, 25. Reheat valve No. 1 closed
- 26. Reheat valve No. 2 closed
- 27. Reheat valve No. 3 closed
- 28. Reheat valve No. 4 closed
- 29. Reheat valve No. 5 closed
- 30. Reheat valve No. 6 closed
- 31. Intercept valve No. 1 closed
- 32. Intercept valve No. 2 closed
- 33. Intercept valve No. 3 closed
- 34. Intercept valve No. 4 closed
., 35. Intercept valve No. 5 closed
- 36. Intercept valve No. 6 closed
- 37.
- Thrust bearing wear or low bearing oil trip operated
- 38.
- Low vacuum trip operated
- 39.
- Moisture separator trip operated
- 40. Time
! *Those devices that will automatically activate the turbine sequence of events monitor hi-speed drive when operated.
Page 12 of 40 Rev. 1
12 PMP 4021.TRP.001 APPENDIX A .
UNIT II PEN IDENTIFICATIONS Equipment or Device Being Stylus number Monitored
- 1.
- Unit differential
- 2.
- Overall differential
- 3.
- Reactor bkr tripped TR-A
- 4.
- Reactor bkr tripped TR-B
- 5.
- Turbine trip left. system
- 6.
- Loc Vacuum trip operated
- 7.
- Condenser A low Vacuum trip
- 8.
- Condenser B low Vacuum trip
- 9.
- Condenser C low Vacuum trip
- 10. Spare
- 11. Spare
- 12.
- Left emergency ckt tripped
- 13.
- Right emergency ckt tripped
- 14.
- Feed pump turbine "E" & "W" emergency trip
- 15.
- Turbine trip right system
- 16.
- Stop valves closed
- 17.
- Reheat stop and intercept valves closed
- 18.
- Vibration trip operated
- 19.
- Cont. fluid safety circ.
tripped
- 20. Time Recorder Points 21-40 Stylus Number Equipment or Device
- 21. No. 1 stop valve closed
- 22. No. 2 stop valve closed
- 23. No. 3 stop valve closed
- 24. No. 4 stop valve closed
- 25. No. 1 reheat stop valve closed
- 26. No. 4 reheat stop valve closed
- 27. No. 2 reheat stop valve closed
- 28. No. 5 reheat stop valve closed
- 29. No. 3 reheat stop valve closed
- 30. No. 6 reheat stop valve closed
- 31. No.1 intercept valve closed
- 32. No. 4 intercept valve closed
! *Those devices that will automatically activate the turbine sequence of events monitor hi-speed drive when operated.
Page 13 of 40 Rev. 1
12 PMP 4021.TRP.001 APPENDIX A Recorder Points 21-40 (cont.)
Stylus Number Equipment or Device
- 33. No. 2 intercept valve closed
- 34. No. 5 intercept valve closed
- 35. Nc. 3 intercept valve closed
- 36. No. 6 intercept valve closed
- 37. Feed pump turbine "E" emergency trip
- 38. Feed pump turbine "W" emergency trip
- 39.
- Moisture separator Hi level trip
- 40. Time
- Those devices that will automatically activate the turbine sequence of events monitor hi-speed drive when operated.
Page 14 of 40 Rev. 1
12 PMP 4021.TRP.001 APPENDIX A SAMPLE TEM STRIP CHARTS Page 15 of 40 Rev. 1
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12 PMP 4021.TRP.001 APPENDIX A III. UNIT I EHC FIRST HIT MONITOR PANEL PS 100 A & B Are the Emergency Trip Pressure Switches which signal the electrical trip system logic that the Emergency Trip System has depressurized.
SPD SIG LOST Activated by concurrent loss of primary and secondary speed signals with turbine speed greater than 200 RPM.
CUST. TRIP Customer trips are the following:
Thrust bearing wear & low bearing oil trip Steam Generator High Level overall differential Unit differential MSR high level Reactor trip (P-7)
Turbine high vibration (l right plus 1 left)
Solenoid trip (Control Switch)
Loss of stator cooling Low condensor vacuum EHC hydraulic pressure low: 1100 PSIG EHC system pressure trip: 800 PSIG Shaft pump oil pressure low > 1300 RPM Safety injection Page 18 of 40 Rev. 1 m
12 PMP 4021.TRP.001 APPENDIX A MA TRIP BUS Indicates that a turbine trip has occured, and ENERGIZER the master trip bus has been energized. Also indicates trip is sealed in.
NO EHC DC Loss of 24 V DC @l800 RPM or 250 V DC if < 1800 INPUT POWER RPM. Verify "No Station Battery" Annunciator in Miscellaneous Turbine Test Cabinet.
BACKUP OVER- Activated by excessive turbine speed.
SPEED TRIP POWER LOAD Initiates rapid control and intercept valve UNBALANCE closure on greater than 40% power / load mismatch.
FAST CLST Rapid closure of intercept valves demanded by IV'S turbine supervisory instruments.
-22 VDC LOST DC supply for electrical control lost. Verify OR indication on lambda power supplies to the left of
+30 VDC LOST the First Hit Panel.
Page 19 of 40 Rev. 1
~
12 PMP 4021.TRP.001 APPENDIX A IV. HATHAWAY OSCILLOGRAPH The unit oscillograph has 32 galvanometers. Each galvanometer will record one analog channel or, if properly modified, 4 on-off functions. Eight galvanometers have been converted to on-off functions and the remaining galvanometers are reserved for electrical analog quantities. The unit has a prefault recording feature where all input quantities are continuously recorded on a magnetic disc. Under normal conditions, the data are erased and current recordings written over tne old space after approximately 100 milliseconds. If one of a specific set of events occurs, the data are recorded on ultra-violet sensitive photographic paper such that the information recorded prior to the event is recorded followed by additional data resulting from the event. The recording is continued for a fixed time period following the event. Recording chart speed may be selected to be either 12" or 3" per second, the usual practice being to record the initial portion of the event at the higner chart speed followed by additional recording at the slower chart speed.
Six points are used to monitor the A and B train reactor trip circuit breaker positions, undervoltage trip initiation, and safety injection actuation, 2 points monitor the start of onsite power diesel generators, 1 point monitors the trip of the feedwater pumps, 10 points monitor turbine initiated events, 7 points monitor generator and excitation events, and 4 traces are used for references to assist in identification of trace Page 20 of 40 Rev. 1 m
12 PMP 4021.TRP.001 APPENDIX A locations. The analog traces record generator phase currents, phase and ground voltages, and field current. l The display provided by the developed photographic paper is a reproduction of the amplitude and wave shapes of the analog electrical quantities. The on-off events are indicated by a continuous straight line trace for a normal condition or the absence of the trace at that location signifying an off normal event. The photographic paper is developed by exposure to ultra-violet light (fluorescent lights are adequate sources) and no wet chemical processes are required. A sample strip chart is included at the end of this section.
The time descrimination between events during higher chart speed is better than 5 milliseconds between events and better than 10 milliseconds during slower chart speed.
Page 21 of 40 Rev. 1 m
l ;,,,j
- _,.
12 PMP 4021.TRP*001 DON ALD C. CCCK 'itlCttAR Pt. ANT _
APPENDIX A
- f fT d1 05Ci110C3AFM l/8'f etACE l 10. TRACE ASSICMT U
eMM ! att n e s*m 1
'f1 Ceeerator Current 81 7000/1
. = I_
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? teare
.#. b tc00/; 37,940 Altn.
k, ,.* ! 3 Cenerator Cartest 33
$ 'l 4 !,
6 Space ,
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3 a
- 4 Spare
, , "g
' 7 Cee. Crounding Trans. Walrate 41.3/t 710 t/ta.
! _ _. - f---
(9) Cen. Ptold C.sreent !ers trrer '_ I--- 8 -
- v. " 9 Cen. field Current ($hnt-4000 A/100 M.7.) 160 4.V./te. 9.46% A/in. ! ,
i l l
- M te are _f j i .
1.1 Cea. Matertas Fot. Vettese .,' 2:0/1 127 f/ts.
12 faare I --- l--
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,- 13 355 KV Fot. Ttatas Trace it00/L 21J v/ta.
.\ ^
j Spare (Carrent) -- '.gI -. L 14 is ...re , . I --
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3 teactor treater Trt2 ped 'S* ; 4 Reactor Breaser UcJer.
I '
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17
-~~ l On/off vetr tre 't' t
,,i Cite freces L-5aterv Injecttaa ' A's *5atet/ Inject 2e l r
'4* ; 3-O tese t Cen. 'A2*!aart; 4.ateset Cen. 'C3' Start. * - lOn/Off '
- 18 3 0% fracass 1-Ref erence; -feed FF. Tart. ' *J '
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CM6 Traces: 1-Main stop 'ralves Closed : Mata Turt. Mech. ~ ~ ~ ~ ~
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. t
- l i QMe Treteet 1*Ref erenset *AC $retee Trip: 3-Reactor . .
Skt. UmJervest Tstp '3'; 4+thruet 8eartas Trip. . Cn/Off s 21 OM4 Traces 1-detsture separator Mt. Level Tete; 2 Vacuum Trip Operettes; 3-Mata Toro. Stan VLt. Tet;I . On/off 22 .
4-t.ube 011 Press. Low ftts.
.4 Traces: 1 selerence; 2 5tator Outlet Coeling Vater Tesp. letsr.; 3 stater 0 Jet Tars. rtp .-Stater ;oet Can.l - On/Off
- 3
?rts e4 Tracest L4eneratar Matartes;
- Catt HEA Sterated t, --- cn/0!!
26 3*4veraki HEA operatedi 6-4&terres 6 Escitattnn *rts.
05Citt. Aa4* ST AAf t:eG $ Ce50 A cat t n u t t o e 1.* 39 Jade rvu tt a ge = *
- 10 9 # AC Da t e #rescurrent * (Met Usad)
- ..:a ov.rm ita e . - . uo vac 3..te Ove r .itas. .. 50 vac Page 22 of 40
...any en/off operatten sti stare e.catte'" Rev. 1, n.
e s
. 12 PMP 4021.TRP.001 uz- - . .ow- - "d*
- so.) Trace Asstanment 9/1.1/(4 R2tto ;
. ,qali.bxati,a
- y
!.\\ \ 1 Cenerator potential E Al-2 volts 220/1 130 v/in.
AU.r;;b
.. . ; i.-
- . , f ,
! Cenerator potential E #2-3 volts 1 1 220/1 128 V/in. ,
,,,,f.
' . .*.: ,Y
~M
, .I s
.$.- ls f r. . . ,_
l . .. : ' -
' . t. .:
.tI 3 Cenerator potential E Al-3 volts . . .
_ . 220/1 124 V/in.
- i. da,.rp%N.,;
- . . T4 R soare ,
- - - _L w~
f- --
'_
- tt_- Sp m
? ra., e a e s i m Y)
. +.-:;
I M
. tr g 'm te ,-p* .. i ,,,, u n m
.? -'Q.
. 8 Cenorator current I #1 7,000/1 $M'.*h ac .
36,119 A/in.! * .
- ,
- e ., q -
4 l 9 dip;
...I l }
Cancrator current I #2 7,000/l . :s
> 36,119 A/in.
s
.. .. y.n 1 g J.'r. s.
[' 10 ..
Cenerator current I A3 7,000/1 43,914 A/in. . , ,
It spare ; . -
T..
~'I 2 q r,u qr,_he.1.L.c.u cie n---t 7[3e,p - - - - - - - .. \
T'- SD aB i L 5 l snar
- 3 (( .. 3 T
a -' ' ,
. t l'f, 16 765 KV timing traca 128 v/in.
Ny--*
9.f{.
. - p. \ CM4 Traces: "A"; 1-04fcrencc: 2-iWctor Breaker Trt@cd 3-Beacter arcake.e Tripped "a": * ' '. $i'.'
17 f 4-Reactor Breaker UndarWltage Trip "A" -
Cn/Off i
@* I. OM4 Traces: ; *;
.' v,l
( ,. -
1
,,, 1-5sfety Injection "A"; 2-kfccy Injection "s"'
18 3-ciesel Generator As Sta ~ 3
U M Eces: hatar Q Mr.nc . . .. - rt: 4-oiesel --
- *M.* . . - - - On/off .-
T 1-h:tw.renco: 2-rku: Pwp Wrbir.a "E" and
'N* Trip; 3-Feod Pwp hrbina "E" ard v ~-
~
19 -
<... Ttte. (!Nrgency); 4-Spra-- On/Off
! 0>t4 Traces: 1-Vacutra Trip Cporated: 2-thin Stcp Valve --
.0 closed: 3 .tm Arctra late Systan Trip; On/Off *
,4. m in h re mc Righr. Siston Trip.
0>t4 Traces: 1-Faferenco: 2-C:ncrol Fluid Safety Cire. -
i*
21 wippc4: 3-Paacter Dreaker Undervoltage on/off e :-
'a4 Traces: Tripj at;.i_-puast Pe.utts Trip
.- 0 -
- .="' 1-tcastu.re Separator Ittevel Trip: 2-Air- .- '
~ - - - ' ' ;22 0t1. H2 Ctif. Press. Ia.# Trips 3-duin Wr- --
bir.o Hagn Vib. Trip: On/Off
% . . L
. . -La2 Oil Press Lod 'in. g
'CMTTr Ges: - G7.Tieren.. co: _
3 . . . . . . - - -
2-Staccc Cutiot Ccotira Watar
~~
23 , Tam Hir;n, 3-Stater Cboliry hrbano Trip: -
On/Off CII4 Traces: 4-is c. t Ccciang Canarator '!Ttp
~ ~~
5 -,
_ c:
. 24 1 Ganoratar tutorirq: 2-Unit Hca Cycratcd:. -- On/Off
. . , . . - 3 <Nort.it Hea Cxc1catten TripC4xarated: 4-Alterrce arti
'HOTC - Tracc sl4 .
.. - . - . . . . . + . - - -
as a spare but doosn't traco because galvanometor is brokor, Page 23 ot' 40' t
Rev. 1 n )
12 PMP 4021.TRP.001 APPENDIX A SAMPLE OSCILLOCRAPH STRIP CHART l
t l
Page 24 of 40
, Rev. 1 1 -
ocuts C. em wCtra puMT 12 PHP 4021.TRP.001 UN t? % . 7 CTCitt0CRAPR APPENDIX A l
TRACg NO . l TRACE A.55 tCNMETT l safM N ??t i ?w 1 Cenerator Potent 141 (Jt-2 Votts 220/1 130 v/tn.
I i 2 Cenerator Poteuttal EJ2-3 Votta 220/1 123 y/ta, i I h ~*
1 0 I
) l 3 Generator PotentL41 cal-1 Valts 2:0/1 12t. v/ta.
I (u I 4 Cenerator Carrent IJ L 7,000/1 34.119 Alta.
3 so re l 6 C.aeriter Neuent v-i ne 1--- t ? 6 't r % .
? e-.,,
8 Ceneratar current IJ2 H]
7.000/1 36.115 Aftn.
9 Cenerator current IJ3 7.000/1 43.914 Al ta.
i 10 _Sf_a te, _,,, _ - - - *- -
$ pere 11_
l ---
t' IToere I -
, , 13 l 1o a re 8 - - - - - .
I; L4 765 fl Ttatsg Trace
- 12G V/ ta.
ll l{i CM. Traces: 1-Aeference; 2-daactar treater trapped ' C' .
l 13 3-Reactor 3 reamer f raoped "S". e-Reactor Sreener Unser m te ne t -* 3 " V'
~~~~
,l Ca/Off QM, 2 races: t-aasety injecttaa 'A'. ;-Sasety inlection T 1
- 6 3-Otanel
.,.-me Ceee.rator A.A Start; -Otesel Gener ; .
I 0*l0ff i
CM4 Traces t-Aeterence; 2-Feed Pump Turetne "E" and "W"
- - H??
Trip (herz;ency)!3-Feed Pt.as furt taa "E" and **e** Trip 08IOII 4-4eare i'ar$[$b t lE ds M 'NIh;* '
- k. io s M.3
..m., ,,, . e,, %.... -m I
Ca/Off uM6 Tracass t-Aeterance; 2-Cancrok f1 w safece Cire. !
- 9 Trtyped; 3-Reactor 8tesiar Undervoltage l l On/0tf i Trip "S*; 4-Thrvat leertas Trip q l I Cr4 Traces: 1-Motsture separacar tit-Level Trtp; 2-AAr-OLL. R; Ottf. Prese. Low Tetpg 3-Main Tur- --
On/Off 20 eine 'itan Vth. Irtp; 4-Lune OL1 Press Law Trt>
QM- Traces: 1-Re 'e r enc e ; 2-Stator cuttet Coottog Water
,L Tara
- .,r~eH14n; e
3-5tator Coottaa Tartine Trip; 4- - ; 0"/Off tt > e. sesr r Tr*. !
.m. sracens . weneratar *atorkng. ;*satt stea gerated,
- --i 3-Overati Hoa Operateds 6-alterres and 22 Co/Off l E.ccitacton Trip osCitLOC3APM STARTINC SCISO4 CJLil AAttCN
- 1. 3d Undervottage EJt 102 VAC 2. 3d ove rvo ttate (31 123 '/AC ts2 tos vac -
car 129 vac ta3-t - to? v4C -
te3 12s vAC Page 25 of 40 e
- 3. La ovarvatcase 52 vAc 4 Aar3arur 7,er.isa .ti; .t.rt M- 1
12 PMP 4021.TRP.001 APPENDIX A V. P250 SEQUENCE OF EVENTS RECORDING PROGRAM The Sequence of Events Recording program records the sequer.ce of operation of a number of monitored contacts to a high time resolution. When one of the monitored contacts changes state, an interrupt is initiated which causes the P250 to scan each monitored contact for any change from its previous state. The program stores such changes and the cycle count since the first event. A cycle is approximately 20 milliseconds in length. Due to a dead time of 2 milliseconds in the interrupt process, an automatic rebid of the program is programmed for the cycle following each interrupt bid. This is done to avoid loss of contact changes during the dead time. The Sequence of Events Recording program is terminated when either the cycle count reaches 3600 or 25 contact changes have been recorded.
When the program is terminated, an output routine is called.
All collected data are first moved to the output program buffers to free the Sequence of Events Recording program buffers for continued monitoring. The output routine prints the time of the first event in hours, minutes, and seconds. Following this message, the alpha-numeric address, a 36 character contact description, and cycle count from the first event are printed for each contact change. The first event will always have a cycle count of zero. A sample output is included at the end of this section. ,
Page 26 of 40 Rev. 1
o 0 .
12 PMP 4021.TRP.001 APPENDIX A SEQUENCE OF EVENT ADDRESSES (Reference P250 Manual TPS129)
F0403D RCL LO F ABOVE P-8 CAUS RE F0423D RCL LO F ABOVE P-7 CAUS REF F0493D STM LINE HI F SI CAUS RE LO406D STM GEN A LO LO L CAUS RE LO426D STM GEN B LO LO L CAUS RE LO446D STM GEN C LO LO L CAUS RE LO466D STM GEN D LO LO L CAUS RE LO483D PRESSURIZER HI 1 CAUS RE N0005D PWR RNG CHAN HI Q CAUS RE N0010D PWR RNG CHAN LO Q CAUS RE N0024D INTERM RNG HI Q CAUS RE N0029D PWR RNG CHAN HI Q RATE CAUS RE N0036D SOURCE RNG HI Q CAUSE RE P0407D STM LINE A HI DP SI CAUS RE PO427D STM LINE B HI DP SI CAUS RE PO447D STM LINE C HI DP SI CAUS RE PO467D STM LINE D HI DP SI CAUS RE P0483D PRESSURIZER HI P CAUS RE P0488D PRESSURIZER LO P CAUS RE P1003D CONTAINM HI P SI CAUS RE T0498D RCL OVERTEMP DI CAUS RE T0499D RCL OVERPWR DT CAUS RE V0324D RCP BUS UNDER VOLT &P7 CAUSE RE Y0004D REAC MANUAL TR 1 CAUS RE Y0005D REAC MANUAL TR 2 CAUS RE Y0006D REAC MAIN TR BKR A -
Y0007D REAC MAIN TR BKR B Y0026D REAC AUX TR BKR A Y0027D REAC AUX TR BKR B YO320D RCP BUS UNDER FREQ PART RE YO321D RCP BUS UNDER FREQ PART RE YO322D RCP BUS UNDER FREQ PART RE YO323D RCP BUS UNDER FREQ PART RE YO324D RCP BUS UNDER FREQ CAUS RE YO335D UNIT ON LINE TIE OCB Al BKR YO335D UNIT ON LINE TIE OCB A2 BKR YO337D UNIT ON LINE TIE OCB B1 BKR YO390D TB TRIP CAUSE RE YO391D TB STOP VLV A CI PART RE YO392D TB STOP VLV B CI PART RE YO393D TB STOP VLV C CI PART RE YO394D TB STOP VLV D CI PART RE YO400D RCPA BKR OP CAUS RE YO401D STM GEN A LO L & FW F CAUS RE YO420D RCPB BKR OP CAUS RE YO421D STM GEN B LO L & FW F CAUS RE YO440D RCPC BKR OP CAUS RE YO441D STM CEN C LO L & FW F CAUS RE YO460D RCPD BKR OP CAUS RE YO461D STM GEN D LO L & FW F CAUS RE YO480D PRESUZER LO P&L SI CAUS RE YO920D SFTY INJ SET MANUAL 1 CAUS RE Y0921D SFTY INJ SET MANUAL 2 CAUS RE Page 27 of 40 Rev. 1
- )
L NCLA OVLk1 LAP U1 1 h t" 17u.b H 352.0 D E uf-U2b7 AlAHA H1 lu43UA Al e2s; 6t Em et 104304 at Este tuttigar el 8 Sr 339.4 stat '
62L2 &&lka em 104Lb4 al ELL C evt < A6- bl 8 6e 164.5 et 68 0237 Sts&m et 10470A al DCLO ovisitar el 8 $r 360.3 of E4 lu4UuA Al NCLA 1 1AVO S44,7 L ,b32.0 DLuf u2b/ ALAhn LO ,
9237 Stdutatt et tvinid strono. FIREI (VEul af M 2 ASA 560 b47.b L 353.u ULuf D2L7 ALAHA LO lu42uA A1 kCLB a IAvu 103,00 le lair tauSt et Ik c 0 3.h t -2.s ad t'ite &&l6m to 6034Da at umil 6tht halck L&OSS mW lb2.4 H ab2.u ut:Uf U2hu ALAHA HI futbuA At MCLC uVLHICMP ut 3 WP 100hiu Slot main it tak b ik ( 4 U2Lu ALAkn LO iu44uA At kCLC iAUu Er4b.6 L LS2.u tit u t uu4up CV HOLA OVLMPpH tW utV IN COMPulED Su4.2 ,H. 4.u PC g H 2b tl AtAHM li t ab c S 14:0b4D t I at Palm lk tra a 54b.2 L bb2.0 sat ui ,g 182 L u AtAlsn LO l u 4 441 A Al HClu 1 1AVu HD 600260 rua AmG tuam H8 0 galt caus $t ik t 25 P
is2bu eotAhn r H1 pu44p (V kCLC uutHPpH tiP utV fH C onPill L u 304.7 *H 4.u 8-4; U
HClu uVLHPpH UP UEV Ik COMPUILD 1u4.1 il 4.u t* C H 2 S tl AL AHn ill pu4&B CV suiv2p to stor viv e it e ak 6: ik t to ._
tra iu47pA As NCL as OVLHiirir ui a s t- shu.1 . is shu.o ut us' m u2:.u AL Aun est 21db.D L 220u.0 PSlu JO U 2b ts ALAHn LO PU142A Al Cit AHie PflP u l tiCH HDH P
}bsvte in stor viv v at sakt si ik t 2a , , ,
Q ,
025e citia seus raecsan su tes rowta cutoff meOf $
junju in tier viv.c (t eens at_ le t 30 303tio es Sier vtw a to taa,j,g 16 n) , ,__,
m 3044:e sin 6tm t to t 4 su e taus LE IL E O 226, 25 6c4240 sia 6tm e to to t caus at la C 9 *
- 04mbo e kt55uktitL to s taus st 16 t 244 u2dv ALAhn HI uu42p CV k C L tf uVL 6it pH SP UEV #~ M COMPultu 104.0 *H~ 4.u PC m
<0 totu4e sia ban a to to t Caus kt sa t 278 80444u sinLas etotoa taus6L sk c 272 D U2SY INCH HI lu47pA At HCt.u uVL HI Lit 4* ul 1 b r' lb2.2 _ 3 , lb2.u DL IJO y C 278 cf3 tuttes sta sia c to to t caus st la C 2ie tus2su sta sta a to a a ae a taus kl ik -
O 30 0 o sin 6Em a to t a su t caus Et in t 307 C
- nosato sin St u e L e t 4 IW I taus 61 Ik t 30; H
@g
[$
ts 0100 2ssuitten et toca umst 2 zusait sin 4.em 6 to a a tv e taus Et al th t 38) h c
8 en mm totate sin sin a to t a tu t taus et la t J23
%3 Ib42th Sin him b 10 t a tv I taus kt NI Ik t 640 ,
v4 totuto sin Gts a to t 8 is I Caes at t 444 O uJuu ALAHn ts: su4' J uA A3 ni la ht:Lts outk LriP D1 1 EP 3bu.A H Ibu.u Dt ut y4 us = c 47 o m 306sio sin sta e to t s av s caus at >N tutslo ElR La u L t o 8 8 IW 8 tous 6f kl la C 244 P
> la E 30a2
$ uJul t04emo estssualna to r taub at 3NCH H5 lu4JUA Al NCLU OVL hlL MP ul 1 b P.
- Ib2.u ' ~ ' ~ ~ lb2.u 3 ()E Lt 1u3360 umli em tsat ist ete a2 she er C 3474 N
og se s 3*,b umil en tint lit ots at oak er C atie .
alot inn stoututt of twists atte&D . . .____ . - . - . o o
eso Sa tun utt ce tvtals katete. 8Ikst tvtal al n 1,' > rst 63: e
- 30svuo es lair cauSE at ns
'e sett
- - ~
1.n 4 4 D SIA btm ( to L 8 IU l lau5 5E Ik 104480 SIA Giu C to L 4 IW f Caus at ni it s' 2254 6308 t ab 18 6ut ht t of Evlulb 6tt06D -
0103 anatoG Ikt63-OLvitt 2 SIGfrE0 .
12 PMP 4021.TRP.001 APPENDIX A VI. POST TRIP REVIEW PROGRAM.
The Post Trip Review program periodically records a number of pre-selected inputs. These inputs are stored on a disc in a circular buffer, with newer sets of data replacing the older sets.
When a trip occurs, either automatically (Post Trip) or manually (Test Trip), the pre trip data being entered into the circular buffer are frozen.and the data are thereafter stored in a post trip buffer. When this buffer is filled, both sets of data (pre and post) are printed out on the typewriter..
The parameters monitored are analog in nature. At the present time, they include selected RPI indication (for unit 2 only), steam generator feed water flow and steam flow, steam generator narrow range and wide range level, pressurizer level, pressurizer livel setpoint, source range detector output, 4
I i
Page 29 of 40 l Rev. 1
- J
12 PMP 4021.TRP.001 APPENDIX A intermediate range detector output, power range detector output, first stage turbine pressure, steam generator pressure, pressurizer pressure, containment pressure, unit gross electrical output, Taverage, delta T power, overtemperature delta T setpoint, overpower delta T setpoint, wide range cold leg temperatures, pressurizer steam temperatures, T-reference, auctioneered delta T, and auctioneered Tavg. These parameters remain as selected by the computor vendor, Westinghouse Electric Corporation, except for certain RPI indications on Unit 2. The RPI indications were substituted for the four channels of total power range NIS power in order to obtain data on the anomalous response of RPI H-8 upon trip. The individual power range upper Page 30 of 40 Rev. 1
__ . . . _ . _ ~
't *
- 12 PMP 4021.TRP.001 APPENDIX A and lower detector outputs remain in the Post Trip Review output for both units to monitor NIS power range indications.
Eight of the parameters in the previous paragraph are sampled at'2 second intervals 6 seconds before and after the trip. These are total NIS power range power on unit 1 and RPI indications on unit 2, turbine first stage pressure, unit gross electrical output, and auctioneered Taverage. All parameters are sampled at 8 second intervals for 2 minutes before and 3 minutes after the -
trip. These sampling times remain as set by the computor vendor.
The Post Trip Print program first outputs a start message on the appropriate typewriter. It then outputs a line of headings for the values which will be printed in columnar form. The headings consist of the six-character name of the point. The values are printed below their names starting with the oldest set-of data on the first line, the next oldest on the next line and so on until the most recent pre-trip data are printed. Included in each row of data is a column indicating the time. When all the pre-trip data for this set of points are printed, the message POST TRIP DATA - TRIP TIME XXXX is printed. All the post-trip data for l these points are printed in the came format as described above.
After all the post-trip data for these points are finished, the program starts over with another set of data in the same i
format: 6 character names, pre-trip values, trip message, and post-trip values. When all the points have been printed, the program outputs a finished message, unblocks the collection Page 31 of 40 Rev. 1 A
- -nr.
,:- :.~-*- -
12 PMP 4021.TRP.001 APPENDIX A programs, and' exits. A sample output is included at the end of this section.
Page 32 of 40 Rev. 1
~
' = '
12 PMP 4021.TRP.001 APPENDIX A POST TRIP REVIEW ADDRESSES C0010A Cont. Rod Bank B Group 1 Pos M08 (Unit 2 Only)
C0027A Cont. Rod Bank D Group 2 Pos P10 (Unit 2 Only)
C0029A Cont. Rod Bank D Group 2 Pos H08 (Unit 2 Only)
C0075A SD Rod Bank D Group 1 Poc F10 (Unit 2 Only)
F0403A Stm Gen A Feed Wtr in 1 F F0404A Stm Gen A Feed Wtr in 2 F F0405A Stm Gen A Stm Out 1 F F0406A Stm Gen A Stm Out 2 F F0423A Stm Gen B Feed Wtr in 1 F F0424A Stm Gen B Feed Wtr in 2 F F0425A Stm Gen B Sua Out 1 F F0426A Stm Gen B Stm Out 2 F F0443A Stm Gen C Feed Wtr in 1 F F0444A Stm Gen C Feed Wtr in 2 F F0445A Stm Gen C Stm Out 1 F F0446A Stm Gen C Sta Out 2 F F0463A Stm Gen D Feed Wtr in 1 F F0464A Stm Gen D Feed Wtr in 2 F F0465A Stm Gen D Stm Out 1 F F0466A Stm Gen 'D Stm Out 2 F LO400A Stm Gen A Nar Rng 1 L LO401A Stm Gen A Nar Rng 2 L LO402A Stm Gen A Nar Rng 3 L LO403A Stm Gen A Wide Rng L LO420A Stm Gen B Nar Rng 1 L LO421A Stm Gen B Nar Rng 2 L LO422A Stm Gen B Nar Rng 3 L -
LO423A Stm Gen B Wide Rng L LO440A Stm Gen C Nar Rng 1 L LO441A Stm Cen C Nar Rng 2 L LO442A Stm Gen C Nar Rng 3 L LO443A Stm Gen C Wide Rng L LO460A Stm Gen D Nar Rng 1 L LO461A Stm Gen D Nar Rng 2 L LO462A Stm Gen D Nar Rng 3 L LO463A Stm Cen D Wide Rng L LO480A Pressurizer 1 L LO481A Pressurizer 2 L LO482A Pressurizer 3 L
~
LO483A Pressurizer Lvl Control S.P.
N0031A Source Rng Detector 1 Log Q N0032A Source Rng Detector 2 Log Q N0035A Source Rng Detector 1 Log Q N0036A Interm Rng Detector 2 Log Q N0041A PWR Rng 1 Top Detector Q N0042A PWR Rng 1 Bottom Detector Q N0043A PWR Rng 2 Top Detector Q N0044A PWR Rng 2 Bottom Detector Q N0045A PWR Rng 3 Top Detector Q N0046A PWR Rng 3 Bottom Detector Q N0047A PWR Rng 4 Top Detector Q N0048A PWR Rng 4 Bottom Detector Q Page 33 of 40 Rev. 1
12 PMP 4021.TRP.001 APPENDIX A POST TRIP REVIEW ADDRESSES N0049A PWR Rng Channel 1 Q (Unit 1 Only)
N0050A PWR Rng Channel 2 Q (Unit 1 Only)
-N0051A PWR Rng Channel 3 Q (Unit 1 Only)
N0052A- PWR Rng Channel 4 Q (Unit 1 Only)
P0398A Tb First Stage 1 P P0399A Tb First Stage 2 P PO400A Stm Gen A Stm Out 1 P PO401A Stm Gen A Stm Out 2 P PO402A Stm Gen A Stm Out 3 P PO420A Stm Gen B Stm out 1 P PO421A Stm Gen B Stm Out 2 P PO422A Stm Gen B Stm Out 3 P PO440A Stm Gen C Stm Out 1 P PO441A Stm Gen C Stm Out 2 P PO442A Stm Gen C Stm Out 3 P PO460A Stm Gen D Stm Out 1 P PO461A Stm Gen D Stm Out 2 P P0462A Stm Gen D Stm Out 3 P PO480A Pressurizer 1 P PO481A Pressurizer 2 P PO482A Pressurizer 3 P P0483A Pressurizer 4 P P1000A Containment 1 P P1001A Containment 2 P P1002A Containment 3 P .
P1003A Containment 4 P QO340A Unit Generator Gross .
T0400A RCL A 1 T-Avg.
T0403A RCL A 1 DT T0406A RCL A 1 Cold T T0407A RCL Overpwr DT 1 SP T0410A RCL A Overtemperature AT Setpoint T0420A RCL B 1 T-Avg.
T0423A RCL B 1 DT T0426A RCL B Cold T T0427A RCL B Overpwr DT 1 SP T0430A RCL B Overtemp DT 1 SP T0440A RCL C 1 T-Avg.
T0443A RCL C 1 DT T0446A RCL C Cold T T0447A RCL C Overpwr DT 1 SP '
T0450A RCL C Overtemp DT 1 SP T0460A RCL D 1 T-Avg.
T0463A RCL D 1 DT T0466A RCL D Cold T T0467A RCL D Overpwr DT 1 SP T0470A RCL D Overpwr DT 1 SP T0481A Pressurizer Stm T T0496A RC T-Ref.
T0497A RCL Auct. DT T0499A RCL Auct. T-Avg.
Page 34 of 40 Rev. 1
e 12 PMP 4021.TEP.001 APPENDIX A SAMPLE POST TRIP REVIEW OUTPUT Page 35 of 40 Rev. 1
9 12 PMP 4021.TRP.001 APPENDIX A
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12 PMP 4021.TRP.001 '
APPENDIX B 4
PROTECTION AND SAFEGUARDS SETPOINTS TRIP UNIT 1 UNIT 2 DESCRIPTION SETPOINTS SETPOINTS Actual Tech. Spec. Actual Tech. Spec.
- 1) Manual N/A N/A N/A N/A
- 2) Pwr. Range Neutron ~
Flux a) Low 25% $25% 25% 525%
b) High 109% 1109% 109% $109%
- 3) Pwr. Range Flux Rate a) Positive 5% In 2 sec 15% In 2 2 sec 5% In 2 sec $5% In 2 2 sec ;
b) Negative 5% In 2 sec 15% In 2 2 sec 5% In 2 sec 55% in 2 2 see i
- 4) Intermediate Range 25% 125% 25% 525%
Neutron Flux (Current Equival.) (Current Equival.) (Current Equival.) (Current Equival.)
(9.6 x 10 5 amps) (8.1 x 10 5 amps) 7
- 5) Source Range 9 x 10 4 cps $105cps 9 x 10 cps4 5
$10 cps Neutron Flux i
- 6) OTAT As Per Tech Spec As Per Tech Spec
- 7) OPAT As Per Tech Spec As Per Tech Spec
)
- 8) Low PZR. Press 1872 psig 21865 psig 1966 psig 21950 psig ,
- 9) High PZR Press 2378 psig 52385 psig 2378 psig 52385 psig 10)High PZR Lvl. 91% 5921 91% 592%
ll) Loss of Flow 90% 290% 93% 290%
Page 1 of 2 Rev. 1
~~
12 PMP 4D21.TRP.C01 APPENDIX B .
c PROTECTION AND SAFEGUARDS SETPolNTS TRIP UNIT I UNIT 2 ,
DESCRIPTION SETPOINTS SETPOINTS Actual Tech. Spec. Actual Tech. Spec.
i
- 12) S/G Wtr. Lvl. Low-Low 17%(N.R.) 217%(N.R.) 21%(N.R.) 221%(N.R.)
- 13) Stm./ Feed Flow 0.6 x 10 6pph 50.71 x 10 6pph 0.6 x 10 8pph $1.47 x 10 8pph Hismatch W/ Low Coincident with Coincident with Coincident with Coincident with S/G Wtr Lvl 26% (N.R.) 225% (N.R.) 26% (N.R.) 225% (N.R.)
- 14) RCP Undervoltage 3150 Volts 22750 Volts 3150 Volts 22905 Volts
- 15) RCP Underfrequency 58.2 HZ R57.5 HZ 58.2 IlZ 257.5 !!Z i
- 16) RCP Bkr. Position 1/4 Open Bkrs Above P-8 NA 1/4 Open Bkrs. Above NA
- 2/4 Open Bkrs Between P-8, 2/4 Open Bkrs.
P-7 & P-8 between P-7 & P-8
- 17) Turbine Trip a) Low Sys. Press. 800 psig 2800 psig 62 psig B58 psig b) Stop Vlv. Position 1% open 21% open 1% open 21% open
- 18) Safety Injection a) Manual NA NA NA j NA b) High Containment Press 1.1 psig $1.1 psig 1.1 psig 51.1 psig c) Low PZR Press. 1837 psig 21815 psig 1908 psig 21900 psig d) liigh Stm. Line 100 psid $100 psid 100 psid $100 psid Diff. Press.
e) High Sta. Line 1.42 x 108 pph for $1.42 x 108 pph for NA NA Flow Coincident with 0+20% Pwr. Ramped 0+20% Pwr. Ramped to 3.88 x 106 pph at to 3.88 x 106 pph at 100% 100%
Lo-Lo Tavg or 541 F 2541*F NA NA Low Sta. Line Press. 600 psig 2600 psig 600 psig 2600 psig Page 2 of 2 -
Rev. 1 l
ATTACHMENT 2 TO AEP:NRC:0838S DONALD C. COOK NUCLEAR PIANT TABLE OF PARAMETERS IDENTIFIED AS DESIRABLE FOR POST-TRIP REVIEW 4
d I
~M e
Attat:ner:t 2 to AEP:!GC:0838S Page 1 ERM SAIC RERRr TAB 2 AEP W for D. C. Cbok Nix: lear Plant en Desirabl2 B5t Parameters for Post- Parameters listed in the TYR as Not Recorded Trip Review ST TIME:HIS1M Y
- PARAME'IIR/SIGEL FEXX3CIR teLuum SCCR2
- 1. X Omtaiment. Tel*ir=1 1. Buergency Operating Prmartwe E-O requires operator action to verify Cbntalment isolation valves are ciceed and marmally close any contaiment ieleim valves Wilcts are cpen. He believe these actions prtwide the narlammary verification of ciceed valves.
- 2. I control Rod Position 2. Emergency n:=mttrq Prmartww E-0 rurynirus iwiate %.La action to verify all rods are inserted. Operators are regaired to take star-ific actions then autmetic control rod insertion does not cocair, M the cause would be evaluated d.xring a post-trip review.
- 3. X Neutztm Flux Power 3. Hathaway PWims Winnoe Manitor l
3.1 - Point 025 Reactor Trip NIS - Source Range Imvel Trip 3.2 - Point 026 Ranctor Trip NIS - Intermartiate Range Hi Imvel Trip l 3.3 - Point 027 Reactor Trip NIS - Raser Rarge Overpauer Trip Iow Rarge l 3.4 - Point 028 Reactor Trip NIS - Power Range Overpauer Trip Hi@t Rarge 3.5 - R> int 029 Reactor Trip NIS - Power Range Ras-Neg Rate Trip C. X Cmtainment Pr===we 4. Hathawsy Operationearrience Manitors 4.1 - Point 034 Reactor Trip - High Cbntalment Pressure Safety Injecticn l
S. (2) Parameter may be reccxded by Ctntainment Wi*im 5. The Iberline radiation monitoring systaan prints the level then an alarm limit is cither an SCE or time histcry avr,aartari and can prtwide 10 airste averages for the past 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The ocntrol terminal / printer is run frtum an uninterruptible power source
- 6. X cmtaiment Simp Imvel 6. He have redadant Cxmtairument sump level indicators. He do not have a recorder.
L
At*h 2 to 7IP:rgaC:tCDE Page 2 RE TDE HISlWY Pgmast symyrs '
HLamm3R/steg smacE
- 7. I Pr2 mary Systems Prmasawe 7. Methunamy Operations e ary=nce Itmitar (1) Trip Parammt.ar 7.1 - Point 030 Ranctor Trip - Pressuriser Safety Injection 7.2 - Poirt 031 man,+,e Trip - Premeuriser Imr Premmare 7.3 - Peirt 032 Ranctor Trip - Preemariser Mia$t Pressure
- a. I Primary Systema W 8. Methany r*=ratims Segaance ltmitor 8.1 - Po!Je 001 Emactor Trip - Overtemperature Dr s.2 - Point 002 nameter Trip - overycune of
- 9. X Pressariser Luwel 9. Huthmumy Operations Segaance Itmitor (1) Trip Parwar 9.1 - Point 033 Rameter Trip - Preemariser Hisps tentar Iswel
- 10. X Ihnactar rmlart Ptap 10. Huthammy Operations Sagannce Itztitor (1) Trip Pa w. Stattas 10.1 - Poirt 048 Reactor coolant Ptap No.1 Trip 10.2 - Point De Ranctor rhi ne Pi., Iso. 2 Trip 10.3 - Point 050 Emactor thimmt Ptep Iso. 3 Trip 10.4 - Poirt 051 n==r+nr rmlant Ptap 300. 4 Trip M. X X Primary System Mont 11. Hmthmumy Opmrations Segaance Immiter l (1) Trip Parameter 11.1 - Point 003 Rmactor Trip Ikutervoltepe RCP has 11.2 - 701:2 004 meer+ar Trip - Icar Floar RCP/P7 Permissive
! 11.3 - Peirt 005 Reactor Trip - Icar Flcar RCP/34 Permissiva 11.4 - Point 007 *e Trip tkuterfregamcy RCP has u.5 - ten hswe ruksuhnt Primary System nm indicators and believe that infor== tim enmartial to a post-trip revier could be prwidad frtum informatim recorded by the operators.
- 12. (3) Ar=**e recorder gtions Safety Inj: nant, 12. ten have flant iruticators en all Safety Injecticut Ptags and limit maitdt indicators are: system ficar era a SE, Ptmp/ Valves status en hay BOCS valves. Buergency Operatirur Proomkare E-O requires w ha actions system flow ma a TI5t, cr for validatim nitidt irubrutas the pamps * = cyerating and the valves are prtyarly T m status remeder i
positicmad. Any ar== miles are armotated for later use in a post-trip rwient.
in an Sr.
- 13. X Pt51V Raiticri ' 13. Hathasary Operations M=nce Itmitor 13.1 - mire 020 Deactor Trip Safety Injecticri s mamline e pr-e/ficar stamm11ne isolaticri gives iruticaticre of initiation of sicpval. Limit switches are available to determine valve closure arut are subject to cperator verification.
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- 14. X Staan Generat x 14. Hathway Operatiers SegJence Itmitar Pr====r n 14.1 - Poirt 020 naarte Trip - Safety Injmtirwt Stamm Line Preemare/Mcnr Steam Line Yentatier
- 15. X Stamm Generatcr 15. Hathaway Operaticris W=nce 3tmiter (1) Trip Parammeter Invel 15.1 - Point 016 Reactor Trip - Staan Generator Icw/lcar tentar Imuel Icop 1 15.2 - Point 017 Reactor Trip - Stasm Generator Lcar/Icar tGutar Imul Ig 2 15.3 - Point 018 Reactor Trip - Stamma Generator Icw/Icnt *4mter Invel Incy 3 15.4 - Point 019 Reactor Trip - Staen Generatcr Icw/Icar tentar Imvel Incy 4
- 13. X Faarhatter now 16. Hathaney Operaticas Serpannae Itmiter (1) Trip Pa.6 16.1 - Point 008 n==r+- Trip - Iow Pond itutar near Inap 1 16.2 - Point 009 Reactor Trip - Iow Pond teater nanr Incy 2 16.3 - Poirt 010 Reactor Trip - Icar had tentar ncar Iccp 3 16.4 - Poirt 011 h Trip - Iow Feed tentar Flcar Iccp 4
- 17. X Steam Mcnr 17. Hathasary Operaticris Segannae 7tmitor (1) Trip Parame*Jr 17.1 - Poirt 020 Reactor Trip Safety Injectiert Stammline pressure /ficar me-line t_entmeten
- 18. (3) A=++1e Reoceder gticra Anrillary FN 18. now irdicaticri is available cm all anrillary fendustar pups. Beargency Operatirug are: systs ficar cri an ST, Systan.- now, Rap / Prrw= tire E-O recpaires w .'ws acticm to verify =m411mry fN system statsas.
system flow cn a 25t. ce valve Status Any ar== alias of the Alw systamm ==>1rt be recxarded in the post-trip revient prw=rkwe ErpyMEr? S*h recIXtjer ard i M cynted as r O .
cn an S2.
- 19. X AC ard DC System Status 19. Hathaway Operatirug **ywooe 7tmitor (mas voltage) 19.1 - Point 003 n==r= tor Trip thdarvoltage RCP has 19.2 - Poirt 007 Reactor Trip Gaa-,anncy RCP has 19.3 - Point 046 Reactor Brealcar I.hdarvoltage Train "A" 19.4 - Point 047 Reactor Ikeaker thdervoltage Train "B" 19.5 - Raint 060 Diesel Generator 2 AB Start 19.6 - Raint 061 Diesel Generator 2 G Start 19.7 - Poirt 156 GP cri Badaip (Unit 2) Point 154 GP on Backip (thit 1) 20 X PCEU Itsiticus 20. Limit switches are available cn ICRVs ard block valves. h p y Operatiru; Proondure E-O rapires cperator acticrt to verify the ICRV positicrt. Any arrmalies of the pressure relief systs would be hGd in the post-trip review procedure and trwestigater2 as reeded.
- a