ML17301A052

Rev 0 to Operating Procedure 0030119, Post-Trip Review.

ML17301A052
Person / Time
Site:	Saint Lucie
Issue date:	08/11/1983
From:	Storke B FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17214A376	List: ML17214A375 ML17301A052
References
0030119, 30119, NUDOCS 8308160263
Download: ML17301A052 (15)

Text

FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT OPERATING PROOEDORE NIPIEER 0030119 REVIS ION 0 1 TITLE: POST TRIP REVIEW 2~ PREPARED BY: Bob Storke 3~ SUBCtMMITTEE REVIEW BY: Dan West for FPL NED 4~ REVIEWED BY FACILITY REVIEW GROUP 5~ APPROVED BY ~ 0+~>'MPLANT MANAGER 6~ REVIEWED BY F R G 7~ APPROVED BY PLANT MANAGER 83081602h3 830811 PDR ADOCK 05000389 P PDR I

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Page 1 of 5 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT OPERATING PROCEDURE AMBER 0030119 REVISION 0

1.0 Title

Post Trip Review 2.0 Review and A royal:

Reviewed by Facility Review Group 1983 Approved by ~lant Manager dZ~r'9 fZ Revision Reviewed by F R G 19 Approved by Plant Manager 19 3.0 ~Pet ose:

This procedure will identify any abnormal circumstances associated with a plant trip by'evaluating plant conditions immediately prior to and immediately after the trip.

4.0 . Limits and Precautions:

4~1 If the cause of the plant trip cannot be determined by the Nuclear Plant Supervisor the unit will not be returned to power until the events associated with the trip are evaluated by the Facility Review Group e 5~0 Related S stem Status:

N/A 6 0

References:

N/A A signed copy of this procedure with the applicable strip charts and printouts attached shall be retained in the plant files.

Page 2 of 5 ST ~ LUCIE PLANT OPERATING PROCEDURE NUMBER 0030119, REVISION 0 POST TRIP REVIEW

8.0 Instructions

F 1 This procedure will be performed following any unplanned reactor trip after plant conditions have been stabilized. The procedure need not be performed following a planned shutdown.

8 ' Input from all plant personnel is vital to the correct identification of the cause of the plant trip and of any related malfunctions.

8.3 . All data pertinent to the- plant trip should be collected and kept with this procedure. If recorder charts are used in this evaluation, a clear copy should be made, and the chart returned- to its recorder..

8~4 All blanks on, the "POST-TRIP REVIEW CHECK SHEET" should be filled in, use N/A where not applicable.

'Page 3 of 5 sb 3m ST ~ LUCIE PLANT OPERATING PROCEDURE NUMBER 0030119, REVISION 0 POST TRIP REVIEW POST TRIP REVIEW CHECK SHEET (Page 1 of 3)

(I) UNIT NO, REACTOR S/D NO. DATE / /

(2) Reactor trip actuated by: ) j MANUAL ( (

AUTO (RPS)

A. Reason for Manual Trip:

B. RPS trip unit initiating Reactor Tripf

l. If hi pressurizer pressure trip, did PORV reclose?

(3) All TCEs opee2 [ [YES +[NO All CEA Rod bottom lights2 [ [YES [ [NO A. Actuation Time: Time Last TCB Open (SOE)

Time of Trip Signal (SOE)

Difference (4) Safety Features Actuation Required (Check)

SIAN MS IS DIAS APAS CSAS A. If any system was required, did it function properly'l ) (YES ( )NO (5) First out annunciator RTGB 102/202:

(6) Plant Electrical Alignment (Check)

BEFORE TRIP AFTER TRIP Auxiliary Transformer Startup Transformer Diesel Generator (7) Pressurizer pressure and level. control normal? ( (YES ( (NO

Page 4 of 5 ST ~ LUCIE PLANT OPERATING PROCEDURE NUMBER 0030119, REVISION 0 POST TRIP REVIEW POST TRIP REVIEW CHECK SHEET Page of (8) Steam Generator Feed: (Check)

BEFORE TRIP AFTER TRIP A B A B MAIN FEED AUXILIARYFEED (9) Did secondary systems function properly'BCS YES NO Feed Reg System YES NO Generator Lockout YES ~ NO (10) Plant Conditions immediately prior to trip:

(11) Reason for Reactor Trip:

(12) Any unusual conditions during Rx trip or trip. recovery:

(13) Any unusual or unexplained annunciators during trip or trip recovery:

(14) NRC notified within one (1) hourV ( (YES ( )NO

Page 5 of 5 ST ~ LUCIE PLANT OPERATING PROCEDURE NUMBER 0030119, REVISION 0 POST TRIP REVIEW POST TRIP REVIEW CHECK SHEET Page 3 of 3 (15) Emergency Plan implemented? (YES f /NO (if YES, give classification and explain)

( 16) Will maintenance be required prior to returning to power? ( (YES ( /NO (If YES,. explain)

(17) Attach DDPS, SOE printouts, and any other printout or chart used to determine cause of reactor trip or to show any abnormal condition during trip. I (18) Additional Remarks:

(if NO was answered in Step 2(b), 3, 4(A), 7 6 9, explain)

(19) The cause of reactor trip has been identified, no abnormal conditions exist. The plant can safely be returned to power.

Nuclear Plant Supervisor S,T,Ai

~,C II 1

FLORIDA POWER 6 LIGHT C(MPANY ST. LUCIE PLANT OPERATING PROCEDURE NN BER-00301 19 REViSION 0 s

1.0 Title

Post Trip Review 2.0 Review and An royal:

Reviewed by Approved by Revision

'dt Facility Review Group Reviewed by F M<

R G

~~ ~ant Manager P 2S 198'~~~

19J' 19 Approved by Plant Manager 19 3.0 ~Por ose:

This procedure will identify any abnormal circumstances associa'ted with a plant trip by evaluating plant conditions immediately prior to and immediately after the trip.

4.0 Limits and Precautions:

4.1 If the cause of the plant trip cannot be determined by the Nuclear Plant Supervisor the unit will not be returned to power until the events associated with the trip are evaluated by the Facility Review Groups 5.0 Related S stem Status:

N/A 6.0

References:

N/A 7.0 Records Re uired:

A signed copy of this procedure with the applicable strip charts and printouts attached shall be retained in the plant files.

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POST TR?P

'!'V U.! 8 E R ') 0 3 i) ! l REVIEW n,

8.0 Ins tructions:

8.1 This procedure will be performed following any unplanned reactor trip after plant conditions have been stabilized. The procedure need not be performed following a planned shutdown.

8.2 Input t. ~m all plant personnel is vital to the correct identification of the cause of the plant trip and of any related malfunctions.

8.3 All data pertinent to the plant trip should be collected and kept with this procedure. If recorder charts are used in this evaluation, a clear copy should be made, and the chart returned to its recorder.

8 4 All blanks on the "POST-TRIP REVIEW CHECK SHEET" should be filled in, use N/A where not applicable.

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1 1 1 I ~

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"!'.i/A'i' '( i'8!lCEDiJR ';: 4'i~! i)i'.2,'I'I 3(' i" POST TR IP Ri V IEW POST TRIP REVIEW CHECK SHEET (Page } of 3)

( 1) UNIT NO. REAC1'OR S/D NO. DATE / / TIME (2) Reactor trip actuated by: j j MANUAL j j AUTO (RPS)

A. Reason for Manual Trip:

B. RPS trip unit initiating Reactor Trip?

l. If hi pressurizer pressure trip, did PORV reclose?

(3) All TCBs open? j jYES j jNO All CEA Rod bottom lights? j jYES j jNO A. Actuation Time: Time Last TCB Open (SOE)

Time of Trip Signal (SOE)

Difference (4) Safety Features Actuation Required (Check)

SIAN MS IS DIAS AE AS CS AS A. If any syst: em was required, did it function properly? j jYES j jNO (5) First out annunciator RTGB 102/202:

(6) Plant Electrical Alignment (Check)

BEFORE TRIP AFTER TRIP Auxiliary Trans former S tartup Trans former Diesel Generator (7) Pressurizer pressure and level control normal? j j YES j jNO

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! ':."'"'.!'ii'.!;DUB!'. i"i< 0!'.l( l! i! ') '  !

T!< I!' i'.'~',!:W "'OST POST TRIP REVIEW CHECK SHEET Page of (8) Steam Generator Feed: (Check)

BEFORE T AFTER TRIP A B A B I MAIN FEED

)

AUXILIARYtern FEED (9) 'id secondary systems function properly?

SBCS YES NO Feed Reg S ys YES NO Generator Lockout YES NO (10) Plant Conditions immediately prior to trip:

(ll) Reason for Reactor Trip:

(12) Any unusual conditions during Rx trip or trip recovery:

(13) Any unusual or unexplained annunciators during trip or trip recovery:

(14) NRC notified within one (1) hour? i lYES i iNO

<>P!.RAT LYLY:::!:(l<'.EDi>RE ViJ.! BE!',:>O 3O: i 9.

R'.;'OST TRIP REVIEW POST TRlF REVIEW CHECK SHEET Page 3 of 3 (15) Emergency Plan implemented? j YES j jNO (if YES, give classification and explain)

( 16) Will maintenance be required prior to returning to power? j j YES ) j NO (If YES, explain)

(17) Attach DDPS, SOE printouts, and any other printout or chart used to determine cause of reactor trip or to show any abnormal condition during trip.

(18) Addi tional Remarks:

(if NO was answered in Step 2(b), 3, 4(A), 7 6 9, explain)

(19) The cause of reactor trip has been identified, no abnormal conditions exist. The plant can safely be returned to power.

Nuclear Plant Supervisor S.T.A

APPENDIX A TO I 2-PR/PSL-1 1.0 The descriptions listed below provide a scope of those activities which have been determined as requiring one or more aspects of the PSL Quality Program.

A. Those items described in the FSAR as being safety related, or seismically or post loca qualified. This includes clarifying documents such as Instrument Lists, Piping & Valve Line Lists, P&ID's, Drawings and original equipment specifi-cations.

B. PC/M items identified as being safety related, seismically or post loca qualified.

C. 10CFR-71, Radwaste Shipping.

D. 10CFR-20, Radiation Protection.

E. Activities specified in the PSL Technical Specifications.

F. Activities under the jurisdiction of the ASME Boiler &

Pressure Vessel, the IEEE and associated codes when referenced in items A & E above.

G. Calibration of Measuring and Testing Equipment used for activities within the scope of the quality program.

H. Contractor activities on items within the scope of the quality program.

I. Replacement activities or items within the scope of this docu-ment.

J. Fire Protection activities outlined in the PSL Fire Protection Program.

K. Security activities outlined in the PSL Security Plan.

L. Environmental activities specified in PSL Environmental Permits.

M. Plant Start-up activities.

N. Certain consumable items for Plant Maintenance that are listed by Quality Control as being included in the program.

2.0 The scope of the program delineated in this instruction or associated procedures may be changed by utilizing revision and approval methods included in QI 5-PR/PSL-l.

3.0 The approval authority for revising specific technical, FSAR and PC/M items impacting the quality program is vested with Power Plant Engineering (EPP).