ML18087A745

Rev 1 to Post-Reactor Trip/Safety Injection Review & Startup Approval Requirements.

ML18087A745
Person / Time
Site:	Salem
Issue date:	03/13/1983
From:	Public Service Enterprise Group
To:
Shared Package
ML18087A720	List: ML18087A719 ML18087A721 ML18087A722 ML18087A723 ML18087A724 ML18087A726 ML18087A727 ML18087A728 ML18087A729 ML18087A730 ML18087A732 ML18087A733 ML18087A734 ML18087A735 ML18087A736 ML18087A737 ML18087A738 ML18087A739 ML18087A740 ML18087A741 ML18087A742 ML18087A743 ML18087A745 ML18087A746 ML18087A747 ML18087A748 ML18087A749 ML18087A750 ML18087A751 ML18087A752 ML18087A753
References
AD-16, NUDOCS 8303160607
Download: ML18087A745 (17)

Text

SALEM GENERATING STATION

• OPERATIONS DEPART~NT DOCUMENT APPROVAL COVER SHEET Post Reactor Trip/Safety Injection Review and Startup Approval Requirements

'NO.:

Remarks: ____ ______________________________.

AD-16 seven....-,__,

Unit: 1/2 pages of text, one - six page form, one - two Rev.:

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1 page form, revised to incorporate SORC and Nuclear Support review for all reactor trips and safety injectionE also added Sequence of Events Checklist Safety Related Review (Ref. AD-13): S/R yes~-x-~ no

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t Author's Checklist Comp~eted: yes ___x_ _

Author i}~~...._.:f~

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QA ** Date 3/ 13/~3 I I SORC ** Date. 3fe/.1"3 General Manager ** Date _z /; 3/b

• required for SPM documents only

-+required for EOP validation acceptance only

• • required for safety related documents and fire protection docume*nt*s Salem Unit 1/2 r-9303160607 saog~j MASTER ;

] ~DR ADOCK 0500 PDR 2 ' .

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ADMINISTRATIVE DIRECTIVE - 16 POST REACTOR TRIP/SAFETY INJECTION REVIEW and STARTUP APPROVAL REQUIREMENTS 1.0 PURPOSE The purpose of* this dir~ctive is to establish the requirements to perform a formal post trip review for all Reactor Trip and Safety Injection events. This directive also establishes the requirements and criteria that must be met prior to the startup of either unit following a trip event or upon return of the units after outages.

2.0 RESPONSIBILITIES 2.1 In the event of a Reactor Trip or Safety Injection, the Senior Shift Supervisor shall:

2.1.1 Ensure that a post trip review of the event has been performed in accordance with the specific directions in Section 3.0 of this directive.

Form AD-16-A "Post Reactor Trip/Safety Injection Review Report" shall be used when performing this review. This report shall be completed and reviewed.with the appropriate management personnel prior to leaving the-Station or

• 2.1.2 requesting approval to startup the affected unit

• Evaluate the post trip review to determine if:

a) All equipment and systems functioned as designed during the event.

b) The cause of the event is clearly identified.

2.1.3 Notify the Operations Manager of the event and the subsequent findings of the report. (The Operations Manager may elect to conduct this review by telephone in direct conference with the Senior Shift Supervisor.)

2.2 The STA qualified Shift Supervisor shall assist and advise the Senior Shift Supervisor in the compiling of data and evaluation of the report *

• Salem Unit 1/2 1 Rev. 1

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AD-16

• 2.3 In the event of a Reactor Trip or Safety Injection, the Operations Manager shall:

2.3.1 Perform the following prior to granting approval for startup:

a) Review the post trip report with the Senior Shift Supervisor.

b) Ensure that the report was properly prepared and evaluated.

c) Ensure that the cause of the event has been properly identified.

d) Ensure that all equipment and systems functioned as designed during the event and recovery actions.

e) Evaluate the event to determine if there are any corrective actions required prior to the startup of the affected unit.

f) As necessary, request additional technical

• support, to evaluate the event and ensure that the cause is clearly identified and the required corrective actions have been initiated.

2.3.2 Grant approval for startup in accordance with Section 4.0 of this directive if all of the requirements listed above are met satisfactorily.

2.3.3 Deny approval for startup if one or more of the requirements listed above is not satisfactorily met. If this is the case, direct the Senior Operations Supervisor to conduct an investigation of the event.

2.3.4 Personally review the report, recommend any corrective actions, and sign the report on page AD-16-A-5.

2.3.5 Forward the completed report to the Senior Operations Supervisor for additional processing.

2.4 The Senior Operations Supervisor shall:

2.4.1 Incorporate the event into the Reactor Trip/Safety Injection history trending system

• Salem Unit 1/2

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2 Rev. 1

AD-16

• 2.4.2 Make two complete copies of the report.

copies shall go to:

a)

These

• The Technical Department for assistance in preparing the Licensee Event Report or other reports as appropriate.

b) The Nuclear Support Department in order to conduct an independent review of the trip event.

2.4.3 Maintain the original report on file for future reference.

2.4.4 Conduct an investigation of the event if the Operations.Manager denies startup approval.

Present the findings to the Station Operations Review Committee.

2.4.5 If approval for startup has been granted by the Operations Manager, present the report to the Station Operations Review Committee for review.

2.4.6 Prepare a summary report on the.event and issue

• 2.5 it to all pertinent Operations Department personnel in accordance with the Information Directives System.

The Nuclear Support Department shall perform an independent review of each Reactor Trip/Safety Injection. Upon completion of the review, Nuclear Support shall make recommendations to the station for corrective actions which may prevent this type of event from re-occuring in the future.

3.0 TRIP EVENT REVIEW PROCESS 3.1 The Senior Shift Supervisor shall ensure that:

3.1.1 The required information on Form AD-16-A concerning the condition of the unit prior to the event is correct and has been recorded.

3.1.2 The evolutions in progress prior to the event that may be involved in the cause of event or could have contributed to the cause of the event have been recorded *

• Salem Unit 1/2 3 Rev. 1

AD-16

• Examples:

a. Unit startup was in progress, feedwater control was in manual control.

b. Unit startup was in progress, problems were encountered with inservice equipment or control systems. (Stearn Dump was in manual, Stearn Generator Feed Pump controls were erratic, Atmospheric relief valves were being used to dump steam,_ etc.).

c. A rapid reduction in unit load was required due to loss of circulators, condenser vacuum, condensate pump, heater drain pump, condensate strainers were partially clogged.

d. Surveillance testing was in progress on the Solid State Protection System.

e. Maintenance or trouble shooting was in progress.

3.1.3 All equipment that was out of service that could have contributed to the event has been identified and -recorded.

Examples:

a. Stearn Dumps were not available.

b. Number llA and llB circulators were out of service.

c. The positive displacement charging.pump was Cleared and Tagged for repairs.

d. Feedwater heater string was bypassed or out of service for repairs .

• Salem Unit 1/2 4 Rev. 1

AD-16

• 3.1.4 The proper classification of the event, the time that the event was declared, the time that the event was terminated, and that all the necessary notifications were made is documented in the report. Attach the original copy of the Emergency.Procedure to the report package.

3.1.5. The P-250 computer s~quence of events printout has been reviewed and the Sequence of Events Checklist (Form AD-16-B) has been completed to verify the cause !Of the event and ensure that all 1

equipment and systems performed* as.designed and in the proper and expected s~quence. If this can not be determined by the people available on shift, contact the Technical Department for assistance. The subsequent alarms listed on the Sequence of Events Checklist are not listed in the

• order in which they should occur: this will vary with the event. In addition, the Feed Pump Turbine Stop Valves will only close on a Safety Injection signal: therefore, they are not applicable to a Reactor Trip. Attach the print out to the report package.

• 3.1.6 All control room recorder charts have been reviewed for unexpected or unusual parameter changes during th~ event. Attach the appropriate recorder chart~:

or copies of the charts to the report package.

Ensure all tracings are identified on the charts and the time is clearly marked.

3.1.7 All alarms which were received which were out of the ordinary for the event and alarms which should have been received but were not have been recorded.

Include a review of the overhead alarms, console alarms, P-250 alarms, and the Auxiliary Alarm Typewriter. Attach the printout from the Auxiliary Alarm Typewriter and the P-250 alarm printout.

3.1.8 Fact finding sessions a.re conducted, as required, with the .appropriate personnel to determine the cause of the event, actions taken and observed sequence of events.

3.1.9 The explanation of the cause of the event is recorded.

3 .1.10 The corrective actions taken during th_e event to mitigate the consequences of the* event and bring the unit to a stable condition are recorded *

• Salem Unit 1/2 5 Rev. 1

AD-16

• 3.1.11 Any equipment out of service which would prevent the unit from being returned to service has be~n recorded.

3.1.12 All Technical Specification or Adminstrative Action Statements that are required to be cancelled prior to reactor startup have been recorded. (Administrative Action Statements as identified in other Operations Department Directives, such- as defined in OD-12.)

3.1.13 Any corrective actions that are required prior to the unit's return to service are recorded.

3.1.14 The names and assigned positions of all individuals involved in the event are recorded.

3.2 The Senior Shift Supervisor shall confer with the STA qualified Shift Supervisor ~n order to review and evaluate the report. When both are satisfied with the conclusions, each shall sign and date the report.

3.3 The Operations Manager shall be briefed by the Senior Shift Supervisor on the report. At that time, a determination shall be made a$ to whether approval should be granted for startup as defined in Section 4.0 of this directive.

4.0 APPROVAL REQUIREMENTS FOR REACTOR STARTUP 4.1 Startup Approval After Controlled Shutdowns.

4.1.1 The approval for reactor startup after planned unit outages for maintenance/refueling activities shall be obtained from the Operations Manager-Salem Operations. If the Operations Manager is not available then the individuals who are authorized to assume the Operations Manager's responsibilities may .authorize the reactor startup.

4. 2 Startup Approval After Reactor T_rips/Safety Injection Events.

4.2.1 Prior to requesting approval to startup the reactor after any Reactor Trip or Safety Injection, the Post Trip Review must be completed and evaluated *

• Salem Unit 1/2 6 Rev. 1

AD-16

• 4.2.2 Upon satisfactory completion of the review and evaluation of the Post Trip Review, the Operations Manager may authorize 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 as designed.

4.2.3 If the Operations Manager-Salem Operations is not available then the individuals who are authorized to assume the Operations Manager's responsibilities may authorize the reactor startup.

4.2.4 If the cause of the event has not been clearly determined or there is question concerning the proper performance of equipment or systems during the event, then an investigation shall be conducted and the results of the investigation shall be reviewed by the Station Operations Review Committee. Upon completion of the evaluation of the event by the Station Operations Review Committee, the Committee shall make recommendations to the General Manager-Salem

• Operations on reactor startup. Upon completion of the review and satisfactory determination that the unit can be restarted safely, the General Manager-Salem Operations may authorize the reactor startup.

END OF PROCEDURE FINAL PAGE

• • Salem Unit 1/2 7 Rev. 1

ADMINISTRATIVE DIRECTIVE - 16 POST REACTOR TRIP/SAFETY INJECTION REVIEW REPORT CONDITIONS PRIOR TO EVENT Date of Event ~~~~~~-

Time of Event -~~~~

Affected Unit Unit Conditions Prior to the Event Reactor Power  %

Personnel Assignments SSS ~~~~~~~~~~~~~~-

SS De-s~k~N-C-0~~~~~~~~~~~-

Bo a rd NCO ~~~~~~~~~~-

Pr i rn a r y EO ~~~~~~~~~~-

Secondary EO ---.,.~~~~~~~~-

SS ups Shift Technician Other-s~~~~~~~~~~~~~

Shift Electricia-n~~~~~~-

(Relay Dept., I&C, Maint., Maplewood Lab etc.)

What evolutions were in progress at the onset of the event:

Surveillance Testing Yes No Trouble Shooting or Maintenance Yes - - - No Unit Startup or Shutdown Activities Yes - No Other Activities which could have contributed to the - --

event Yes No If the answer to any of the above questions is yes, describe the circumstances in detail.

Were any of the following out of service or inoperable at the onse of the event:

Major Equipment Yes No Protection Systems or--=--=-- Trains Yes _ __

No No Control Systems Yes ---

If the answer to any of the above questions is yes, describe the circumstances in detail .

• Salem Unit 1/2.

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AD-16-A-1 Rev. 1

• DESCRIPTION OF THE EVENT Reactor Trip Initiation Automatic Yes No If no, explain why.

Safety Injection Initiated Yes- : - - - - - : No If initiated, was it automatic Yes No If no, explain why.

What is the classific~tion of the event as defined in EP I-0?

---.......----=---=-----=---------=-=-~

Time Declared Time Terminated Were all of the -required notifications made? - - - - - - -

Yes No Attach Emergency Procedure - - to - Report Package.

Does the Sequence of Events Printout from the P-250 agree with the First.Out Annunciator which was received?

'Yes No If no, explain whi-c~h-F~i-rst Out was received and any apparent reasons for the discrepancy. (eg. Two alarm conditions actuated simultaneously)

Attach Printout to Report Package.

Do the recorder charts indicate any trends which may have contributed to the event?

Yes No--=,---......

If yes, explain in detail.

Attach .Recorder Charts to Report Package *

• Salem Unit 1/2 AD-16-A-2 Rev. 1

• Were there any alarms which annunciated which were unusual for the event? Yes No

---,,-~

If yes, explain in detail.

Were there any alarms which should have annuciated but did not?

Yes No If yes, explain in-detail

• Salem Unit 1/2* AD-16-A-3 Rev. 1

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• Explain in detail the sequence of events which led to the initiation of the event and the actions performed to place in a stable condition. Include the observations and actions of specific individuals. Attach additional pages as required *

• Salem Unit 1/2 AD-16-A-4 Rev. 1

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--~--* . ...... ~-.~----*. -~---* ....,__*_____ .......... ,.....*__ ,_., _____ *. _, .... - . .

• 1 CORRECTIVE ACTIONS Is there any equipment out of service which would prevent the unit from being returned to service?

Yes No If yes, explain in-detail. --

Are there any Technical Specification or Administrative Action Statements in effect which would prevent the unit from returning to service? (Administrative Action Statements are described in OD-12 or other Operations Department documents)

Yes No If yes, list below.- - -

Tech Specs Admin.

Are there any corrective actions which should be performed before

• returning the unit to service, such as repa_irs which should be made?

Yes No =---~

If yes, explain. Provide specific recommendations as appropriate.

Report Prepared By Date Time

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Report Reviewed With____________ Date______ Time Approval to startup granted by Date Time STA Qualified Shift Supervisor Date Time (Signature)

Senior Shift Supervisor Review Date_ _ _ _ __ Time (Signature)

• Salem Unit l/2 AD-16-A-5 Rev. 1

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• FOLLOWUP Corrective actions required to prevent reoccurrence of this event.

• Report Reviewed By Operations Manager NOTE:

(signature)

Date Time This review is not required prior to authorizing startup.

Station Operations Review Committee Review Chairman Meeting No. Date

• Salem Unit 1/2 AD-16-A-6 Rev. 1

• SEQUENCE OF EVENTS CHECKLIST Reactor Trip or Safety Injection signal sequence start time:

REACTOR TRIP SIGNAL INITIATED AT cycles SAFETY INJECTION SIGNAL INITIATED AT cycles sequence start

1. cycles time in which alarm Subsequent Alarms linto sequence was initiated REACTOR MAIN TRIP BKR A TRIP* .- -.- -

REACTOR MAIN TRIP BKR B TRIP  :

REACTOR TRIP AUXl BKR A TRIP  :

REACTOR TRIP AUXl BKR B TRIP ..- -.- -

REACTOR MAN TRP 1 NT TRIP . .

• REACTOR MAN 'J.'RP l 'J.'IU!'

REACTOR MAN TRP 2 NT TRIP REACTOR MAN TRP 2 TRIP TURBINE STOP VA 11 CLOSED TURBINE STOP VA 12 CLOSED  :

TURBINE STOP VA 13 CLOSED

_.....,_~-*

TURBINE STOP VA 14 CLOSED ..- -.- -

TURBINE TRIP TRIP .- -.- -

TURBINE TRIP CONSOLE TRIP  :

TURBINE REMOTE EMERG TRIP TRII  :

• Salem Unit 1/2 AD-16-B-l Rev. 1

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sequence start

1. cycles time in which alarm Subsequent Alarms . into sequence was initiated 1.3. AUX FW PUMP TURBINE STOP.VA NT CL ..- -..- -

'r!;:

11 SGFP TURBINE HRH STOP VA CLOSED .- -.- -

12 SGFP TURBINE MS STOP VA CLOSED ..- -:- -

11 AUX FW PUMP START .- -.- -

12 AUX FW PUMP START .- -.- -

12 SGFP TURBINE HRH STOP VA CLOSED .- -.- -

11 SGFP TURBINE MS STOP VA CLOSED .- -.- -

Salem Unit 1/2 AD-16-B-2 Rev. 1

Appendix G Operations Directives OD-10, Removal and Return of Safety Related Equipment to an Operable Status OD-15, Use of Operations Department Procedures