ML20091A694

Rev 0 to Operations Dept Procedure ODP-ZZ-00015, Reactor Trip Review

ML20091A694
Person / Time
Site:	Callaway
Issue date:	05/12/1984
From:	Sampson S UNION ELECTRIC CO.
To:
Shared Package
ML20091A687	List: ML20091A682 ML20091A694
References
ODP-ZZ-00015, ODP-ZZ-15, NUDOCS 8405300061
Download: ML20091A694 (9)

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ODP-ZZ-00015

i. May 12, 1984 Revision 0 CALLAWAY PLANT OPERATIONS DEPARTMENT PROCEDURE ODP-ZZ-00015 REACTOR TRIP REVIEW l

RESP. DEPT. O 1A O iONA PREPARED BY .

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i This procedure contains the following:

. Pages 1 through 5 Attachments 1 through 1 Appendices through Checklist through INFORMATION ONLY #'.rm 6 J\lC0 FR0__D  %

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ODP-ZZ-00015 Procsd. No.

Rev. O Table of Contents-l Section Page Number

1.0 Purpose and Scope

1 2.0 - Definitions 1 3.0 Responsibilities 1 4.0 Procedure 2 4.1 Data Collection 2 4.2 Post Reactor Trip Investigation 3 4.3 Restart Decision 4

. 4.4 Post Start Up Review 5 5.0 Records 5 g

Attachment 1 - Reactor Trip Report 9

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Proc 3d. No. ODP-ZZ-00015 Rev. O REACTOR TRIP REVIEW 1.0 PURPOSE AND SCOPE This procedure provides a systematic method for diagnosing the cause of reactor trips, ascertaining the proper functioning of sdfety-related equipment prior to restart, and making the determination that the plant can be restarted safely.

2.0 DEFINITIONS 2.1 Cause - the root initiator of an event, usually an equipment malfunction, procedural error, or personnel error. When the cause is corrected, the possibility of the event recurring is minimized.

I 2.2 Preliminary Safety Assessment - a systematic review of events preceding and following a reactor trip conducted to determine if the plant exceeded design specifications.

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3.0 RESPONSIBILITIES 3.1 Shift Supervisor (SS)_

The shift supervisor is responsible, with the STA, for the investigation phase of the reactor trip review. If the investigation phase is performed by another SRO licensed individual,'the shift supervisor shall review and approve the results of the iavestigation.

3.2 Shift Technical Advisor (STA)

The STA is responsible for collecting the information on Attachment 1, Reactor Trip Report. The STA is also responsible, with

- the S.S., for the= investigation phase of the reactor trip review.

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Procsd. No. ODP-ZZ-00015 Rev. O I 3.3 Plant Personnel Plant personnel involved in the unscheduled  !

trip are responsible for providing the STA with objective comments that describe their observations of and or participation in the 4 1

trip event. l 3.4 l On-Site Review Committee (ORC)  ;

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The On-Site Review Committee (ORC) is i responsible for reviewing reactor trip j reports. The ORC shall review the post-trip

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report prior to restart, if the cause of the j trip is not positively known and/or some safety-related equipment functioned in an

]- abnormal or degraded manner during the trip and the malfunction has not been corrected j or prevents a reactor start up due to tech-

{, nical specification.

3.5 Independent Safety Engineering Group (ISEG) 1 The Independent Safety Engineering Group ,

1 (ISEG) is responsible for ensuring lessons

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learned from unscheduled reactor ' trip events '

are used to improve plant safety and relia-i bility and to transfer in-house experience of generic interest to the industry.

1 3.6 Supervising Reactor Engineer The Supervising Reactor Engineer is respon-i sible for reviewing Reactor Trip Reports.

He~shall make comments as he deems necessary

and include them with the report.

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1 4.0 PROCEDURE 4

4.1 Data Collection i

l 4.1.1 The STA shall collect the data on Attachment 1

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s i Proccd. No. ODP-ZZ-00015

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After the plant is in a safe rs stable condi-4.1.2g tiennthe individuals involvr.d 'in the reactor trip(e.g. , Operating Supervisor , Unit Reac-tor Operator, I&C Technician, etc.) shall be interviewed, by the STA, to determine the facts surrounding the reactor trip.

4.2 ' . Post Reactor Trip Investigation 4.2.1 1 The S.Svf or O.S., and the STA shall recon-

' struct the transient, on Attachment 1, using

,all of the collected data. ,

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4. 2.1. k A chronological description should be developed, using the sequence of events printout as a base. All pertinent alarms, trips, actuations and isolations should be incorporated.

4.2.1.2 When pdssible the reconstruction should be I compated;with similar transients described in the PSAR or other Reactor Trip Reports.

It shop 1d also be compared with the required procedure actions to determine the affect of

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those agtions on plant response.

4.2.2 3 .The S.S., or,0.S., and the STA shall analyze 3 and evaluate the event. reconstruction to

( ditermine the cause of the trip and the

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4.2.2,1 (12 safety related and other important equip-ment involved in the trip operated as expected.

, 4.2.2.2 I$thetripcausedanydetrimentaleffects j on plant equipment.

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4.2.2.3 If'it is acceptable.to restart the reactor.

4.2.3 The S.S., or O.S., and the STA shall also in the course of their r.eview, look for:

4.2.3.1 4 Abnormal indications or degraded trends in

., equipment performance.

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1 Proccd. No. ODP-ZZ-00015 Rev. 0 4.2.3.2 Events occurring out of the normal or antic- l ipated sequence 4.2.3.3 Failed or degraded response of equipment to its control signals 4.2.3.4 Unusual chemistry results or radiation read-ings 4.2.3.5 Unanticipated alarms 4.2.4 The Superintendent, Operations (S. O.) shall be informed during normal working hours or the Emergency Duty Officer (EDO) during OFF-NORMAL hours.

4.2.5 The S.S. shall ensure an Incident Report is filled out in accordance with APA-ZZ-00500, Non-conforming Operations Reporting and Cor-

.g rective Actions.

4.3 Restart Decision 4.3.1 For the following, the S.O. during normal working hours or EDO during off-normal hours

. shall authorize reactor start-up:

4.3.1.1 The cause of the trip is positively known and has been corrected; all safety-related equipment functioned properly, or 4.3.1.2 The cause of the trip is positively known and has been corrected; some safety related equipment did not function properly, however the malfunction has been corrected and a technical specification does not prohibit a start up 4.3.2 For the following, the On-Site Review Com-mittee (ORC) shall authorize reactor start up:

4.3.2.1 The cause of the trip is not positively known and/or some safety-related equipment functioned in an abnormal or degraded manner during the trip and the malfunction has not been corrected.

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I Procsd. No. ODP-ZZ-00015 Rev. 0 4.4 Post Start Up Review 4.4.1 The S. S. shall send the completed Reactor Trip Report to the Superintendent, Opera-tions (S. O.) for his review.

4.4.2 The S. O. shall send the Reactor Trip Report to the Supervising Reactor Engineer for his review.

4.4.3 The Supervising Reactor Engineer shall send the original Reactor Trip Report to the Sup-erintendent, Compliance for inclusion into the Incident Report as an Attachment.

4.4.3.1 The Supervising Reactor Engineer shall send a copy of the Reactor Trip Report to the In-dependant Safety Evaluation Group (ISEG).

4.4.4 The ISEG shall review the Reactor Trip I

Report for:

4.4.4.1 Screening, to determine its generic signifi-cance to plant safety and reliability.

4.4.4.2 Evaluation, to determine additional correc-tive actions and/or lessons learned for operator and plant staff training 4.4.4.3 Dissemination to the Industry,if justified.

5.0 RECORDS S.1 QA Record S.1.1 Reactor Trip Report as an Attachment to the Incident Report.

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J Proced. No. ODP-ZZ-00015 Rev. O REACTOR TRIP REPORT

1. Date/ Time of Trip

2. Trip No.

3. I.R. No.

4. S.S.

5. STA

6. U.R.O.'s

7. Status of the Plant Prior to the Trip:

Procedure No.

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8. Plant Response

a. Obtain a copy of the applicable charts (check if included)

1. Rx Pwr 4. RCS Th 1,2,3,4

2. Pzr Lvl 5. MS Press 1,2,3,4

3. Pzr Press 6. SG Lvl

b. Obtain a printout from: (check if included)

1. Event Recorder 3. Post Trip Log

2. Alarm Printer 4. Loose Parts Monitor

c. Obtain copies of pertinent logs (ie,.S.S., U.R.O., E.O.)

9. Sequence of Events (chronological sequence):

10. Probable Cause: l l

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ATTACHMENT 1 Page 1 of 2 j

Procad. No. ODP-ZZ-00015 Rev. O

11. System / Component with Inadequate Performance:

System / Component Description  !

12. S. O. or EDO Permlssion to Start-Up:

S. O./EDO Date/ Time

. STA Date/ Time S. S.

g Date/ Time

13. Superintendent, Operations Review Comments:

Superintendent, Operations Date/ Time 14 Supervising Reactor Engineer Review Comments:

Supervising Reactor Engineer Date/ Time i

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ATTACHMENT 1 Page 2 of'.2 1 1

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