ML20206H678
| ML20206H678 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/23/1986 |
| From: | PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | |
| Shared Package | |
| ML20206H672 | List: |
| References | |
| 0S1000.08, S1000.08, NUDOCS 8606260263 | |
| Download: ML20206H678 (14) | |
Text
ENCLOSURE TO SBN-1137 STATION OPERATING PROCEDURE COVER FORM A.
IDENTIFICATION REVISION 00 NUMBER 0S1000.08 TITLE POST TRIP REVIEW ORIGINATOR E. Madej B.
TECHNICAL REVIEW DATE SIGNATURE TITLE Unit Shift Supervisor
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OS1000.08 Ptgs 1 Rev. 00 POST TRIP REVIE'J s
Revision Page No.
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Revision Form No.
OS1000.08A 00 b
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OS1000.08 Page 1 Rev. 00 TABLE OF CONTENTS 1.0 OBJ ECTIVE
2.0 REFERENCES
3.0 PRECAUTIONS 4.0 LIMITATIONS AND SETPOINTS 5.0 PREREQUISITES 6.0 PROCEDURE 7.0 FIGURES None 8.0 FORMS OS1000.08A, Post Reactor Trip /Saf ety Injection Revtew O
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OS1000.08 Page 3 Rev. 00 1.0 OBJECTIVE The objective of this procedure is to establish the requirements for performing a formal post trip review for all reactor trip and safe,ty injection events.
be met This procedure also establishes the requirements and criteria that must prior to the startup following a trip event.
2.0 REFERENCES
Nuclear Regulatory Commission letter dated July 8',1983, Suspense File 2.1 83-28 Subject, " Required Actions Based on Generic Implications of Salem ATWS Events."
2.2 REF:
(T.S. e.4.1) 2.3 Nuclear Regulatory Guide, Section 1.16, Report of Operation Inforsation, Events of Public Interest.
2.4 Institute of Nuclear Power Operations, Good Practice, OP-211, Post Trip Reviews.
2.5 Code of Federal Regulations, Title 10, Part 50.73, Licensee Event Report System.
3.0 PRECAUTIONS the 'FIRST OUT' annunciator until the f ault is identified.
Do not reset 4.0 LIMITATIONS AND SETPOINTS None 5.0 PREREQUISITES None 6.0 INITIAL CONDITIONS j
Rx trip has occurred.
INITIALS /DATE 7.0 PROCEDURE 7.1 Af ter completion of a reactor trip or safety injection the control room personnel shall perform the
- event, following:
f 7.1.1 Verify Nuclear Regulatory Commission notifica-tion has been made per Nuclear Regulatory Guide, Section 1.16, Report of Operation Information, Events
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of Public Interest by the Shif t Superintendent.
7.1.2 Obtain a copy of event data f rom MPCS, Video Alars Archive Review and the Analog Post Mortem print-
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out.
7.1.3 Obtain the following charts:
7.1.3.1 SG narrow range levels
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OS1000.08 Page 4 Rev. 00 i
INIT[ALS/DATE 1
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7.1.3.2 Pressurizer level j
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7.1.3.3 Pressurizer pressure i
I 7.1.3.4 Tave 7.1.3.5 Reactor coolant loop Th and T dide f
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range I'
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7.1.3.6 Nuclear. power range NR-45
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I 7.1.3.7 Other charts as required by event.
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7.1.4 Make a copy of unit journal concerning events
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.j just prior to event and during event.
7.1.5 Complete the Post Reactor Trip / Safety Injection
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Review, Form OS1000.08A.
7.1.6 Forward the original and three copies of the completed Post Reactor Trip / Safety Injection Review form
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and all obtained charts to the unit shift supervisor.
7.2 The unit shift supervisor shall perform the following:
7.2.1 Verify the Nuclear Regulatory Commission notifi-
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cation has been made by the Shif t Superintendent.
I 7.2.2 Verify that the Post Reactor Trip / Safety
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Injection Review form is properly completed.
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7.2.3 Evaluate the post trip review to determine if l
7.2.3.1 All equipment and systems functioned as
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designed during the event.
7.2.3.2 The cause of the event is clea'ely iden-
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tified.
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i 7.2.4 Review the MPCS, Video Alarm Archive Review, and Analog Post Mortem Printout to determine if
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7.2.4.1 Cause of event is evident i
7.2.4.2 All systems and equipment performed as f
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designed and in the proper and e'xpected sequence, 7.2.5 Review charts and verify that all tracings are
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identified and the time is clearly marked.
i 7.2.6 Conduct a fact finding session with the appespriate personnel to determine the cause of l
discuss actions taken and discuss the event,
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observed sequence of events.
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OS1000.08 Page 5 Rev. 00 INITIALS /DATE 7.2.7 List the corrective actions taken by the oper-ators during the event to mitigate the consequences of the event, and explain why these actions were
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taken.
7.2.8 Document the classification of the event, the time the event was declared and the time,that the event was terminated. Attach a copy of the if emergency procedure followed during the event
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required.
7.2.9 Forward the completed review package to
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the STA/shif t superintendent.
7.3 The STA/ shift superintendent shall perform the following:
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7.3.1 Review the post trip package.
7.3.2 Evaluate the event to determine if there are corrective actions required to startup, and take
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corrective actions as necessary.
7.3.3 Ensure that the report was properly prepared
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and evaluated.
7.3.4 Ensure that the cause of the event has been
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proper 1/ identified.
7.3.5 Ensure that all equipment and systems functioned as designed during the event and recovery actions.
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7.3.6 Upon satisfactory completion of the review and evaluation of the post trip review, recommend the reactor startup as long as the evaluation of the trip event clearly indicates the cause of the event and that all equipment and systems functioned
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as designed.
7.3.7 If the cause of the event has not been clearly determined and there is a question concerning the proper perf ormance of eq'aipment and systems during the event, then an investigation shall be conducted by the station
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operation review committee prior to startup.
7.3.8 Forward the completed review package to the station
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manager or assistant station manager or operation manager.
7.4 The station manager /aasistance station manager / operation m.inager shall perform the following:
7.4.1 Review the completed post trip package.
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7.4.2 If required request the station operations review committee to investigate the reactor trip /
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safety injection.
OS1000.03 Page 6 Rev. 00 INITIALS /DATE 7.4.3 Have Operations Manager prepare a summary report on the event and issue it to all pertinent
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operations dept.rtment personnel.
7.4.4 Maintain the original report on file for
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future reference.
7.4.5 Forward copies of the post trip review to the following departments.
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7.4.5.1 Engineering services
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7.4.5.2 Operations engineering group 7.4.5.3 The training center manager,
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licensed training.
7.5 If required the station operations review committee shall perform the following:
7.5.1 The coexittee shall perform a complete
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investigation cf the trip event.
7.5.2 Request technical assistance from engineering services and or the operations engineering group as
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necessary.
7.5.3 Make a complete report to the Station Manager.
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7.6 The station manager / assistant station manager /
of the operations manager shall authorize restart unit after determination that the unit can be
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restarted safely.
8.0 FINAL CONDITIONS Cause of Rx trip has been determined.
9.0 FIGURES None 10.0 FORMS OS1000.08A, Post Reactor Trip / Safety Injection Review s
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run t1.. L m..... n L....f
Page 1 of 7 POST REACTOR TRIP / SAFETY INJECTION REVIEW Date of Event Time of Event Unit conditions 'helor to event Reactor Power 4
Mode
'F d
T,ye l
Pressurizer Level I
Pressurizer Pressure psig Megawatt Electrical mwe Boron Concentration pps Control Rod Position steps 1
Personnel Assignments Shif t Supervisor Unit Shif t Supervisoe Senior Control Room Operator l
Control Room Operator Primary A0 Secondary A0 Outbuildings A0 i
Other i
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r OS1000.08A Rev. 00 1
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Page 2 of 7 POST REACTOR TRIP /SAFSTY INJECTION REVIEW (cont.)
Evolutions in progress at the onset of the event :
Surveillance Testing Yes No Yes No Maintenance Unit Startup or Shutdown Yes No Other Acttvitles Which Could Yes No Have Contributed to Event If yes to any ques *. ion, describe each circumstance.in detail.
t' the Were any of the following out of service or inoperable at j
onset of the event?
Major Equipment Yes No Protection Systems or Trains Yes No Control Systems Yes No Indicating Lights or Alar.ns Yes No If yes to any question, describe each circumstance in detail.
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OS1000.08A Rev. 00
Page 3 of 7 I
POST REACTOR TRIP / SAFETY INJECTION REVIE'4 (cont.)
Description of Event Reactor trip initiation?
Yes No Automat ic?
Yes No If no, explain Wy not.
If yes, give the teattor first out annuneLator.
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I Safety injection initiated? Yes No Automat ic?
Yes tb If no, explain why not.
If yes, give the cause from the reactor f irst out annunciator.
Did safety injection equipment actuate as designed?
Yes tb If no, list equipment that did not actuate and describe cause f o r malf unct io n.
f What is the classificatton of the event as defined in emergency procedure?
Declared
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Terminated:
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Date Time Date Time
- 4ere all of notifications made: Yes
!b If no, explain why not.
l Att tch emergency procedure to this report.
OSL000.08A Rev. 00 j
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Page 4 of 7 POST REACTOR TRIP / SAFETY INJECTION REVIEW (cont.)
Does the sequence of events printout from printe'r SCXX-2756 agree with the reactor first out annunciator which was received?
Yes No If no, explain differences and any apparent reason (s) for the discrepancy.
1 Attach the video alarm archive review to the report package.
Do the recorder charts indicate any trends which may have contributed to the event?
Yes No If yes, explain in detail.
Attach the recorder charts to the report package.
Were any alarm abnormalities noted?
Yes No If yes, explain in detail.
Attach the Analog Post Mortem Printout to the package.
Did any process parameter indicate abnormally prior to or following the trip?
Yes No If yes, explain in det.all.
OS1000.08A Rev. 00 C------------------------.
Pagt 5 Of I POST REACTOR TRIP / SAFETY INJECTION REVIEW (cont.)
Explain in detail the sequence of events sich led to the initiation of the event and the actions performed to place the plant in a stable condition.
0$1000.08A Rev. 00
Page 6 of 7 POST REACTOR TRIP / SAFETY INJECTION REVIEW (co nt. )
t t
e r
I Sequence of Events l
t ime.
Reactor trip or safety injection signal sequence start
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Event Rx Trip Event Safety Injection i
a Tech. Spec.
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Subsequent Alarms Required Time MPCS Time I
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Reactor Trip Bkr A NA i
Reactor Trip Bkr B NA Reactor Trip Aux Bkr A NA Reactor Trip Aux Bkr B NA Reactor Manual Trip 1 NA 1
Reactor Manual Trip 2 NA 1
Turbine Trip Reactor Trip NA HP Turb SV-1 Part, Rx Trip NA
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HP Turb SV-2 Part, Rx Trip NA i
HP Turb SV-3 Part. Rx Trip NA HP Turb SV-4 Part, Rx Trip NA f
Gen. Bkr Trip NA j
Emerg. Feed Pump, Mo tor i60sec j
Emerg. Feed Pump, Turbine j( 60 see d
i List as necessary:
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1 i
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1 I
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For Tech. Spec. required times, see Table 3.3-2 and/or 3.3-4.
1 Ost000.08A i
Rev. 00 l
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Page 7 of 7 I
i POST REACTOR TRIP / SAFETY INJECTION REVIEW j
( con t. )
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Corrective Actions i
Is there any equipment out of service which would prevent 1
the unit from being returned to service?
Yes No j
If yes, explain in detail.
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Are there any technical specifications in ef fect which would j
prevent the unit from returning to service?
I Yes No l
If yes, Lis t below.
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I there any corrective actions which should be performed Are before returning unit to service?
Yes No j
j If yes, explain in detail.
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l Report prepared by:
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SCR0/CR0 Date Time 4
Report reviewed by:
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Unit Shif t Supervisor Date Time RECOMMEND STARTUP t
Report Reviewed:
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STA/Shif t Superintendent Date Time YES NO i
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Approved for startups STA MGR/ ASST STA MGR/0PS HGR Da te Time J
OS1000.08A e
Rev. 00 f
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