ML20203B607

Rev 1 to Procedure 10006-C, Reactor Trip Review

ML20203B607
Person / Time
Site:	Vogtle
Issue date:	07/14/1985
From:	GEORGIA POWER CO.
To:
Shared Package
ML20203B604	List: ML20203B600 ML20203B607
References
10006-C, NUDOCS 8604180214
Download: ML20203B607 (19)

Text

ATTACllMENT B

Approyd Procedura No, Vogtle Electric Generating Plant 10006

• N Y. Nfs M. NUCLEAR OPERATIONS g,,,,,0n g .

cate 1 1[nl86 Unit Georgia Power e s. no.

1 or 19

,_ _ ) _. . -

~

REACTOR TRIP REVIEW 1.0 PURPOSE This procedure provides instructions to collect and document pertinent information concerning Reactor Trips, to determine their cause, and,to ascertain the status and proper functioning of safety-related equipment necessary to make the determination that the affected Unit can be restarted safely.

2.0 DEFINITIONS 2.1 Condition I The cause of the trip is known and has been corrected:

all safety-related equipment functioned properly during the trip.

2.2 Condition II The cause of the trip is not known and/or some safety-related equipment functioned in an abnormal or degraded manner during the trip.

3.0 INSTRUCTIONS Figure 1 provides a flow chart that may be used as a general guide for completing a " Reactor Trip Report",

Data Sheet 1, and making the determination that the affected unit can be restarted safely.

8604180214 860411 4 PDR ADOCK 0500 E

CONTINUED rQ3101A MC41SJ

l - o.

PROCEDURE NO. REVISION PAGEWO.

- 0006-C 3.1 PRECAUTIONS 4

3.1.1 Reactor trips and ensuing transients to stable conditions must be carefully evaluated to ensure l - malfunctions are. identified prior to authorizing unit startup.

4 4 3.1.2 Any malfunctions (either equipment or operator related) j must be carefully evaluated to ensure that necessary

! corrective: actions have been implemented prior to l authorizing unit startup. This includes satisfactory functional testing of repaired equipment, required surveillances completed, or initiation of required follow up' actions.

i 3.1.3 If any time during the post trip review it is determined that a safety related action that should nave occurred when its appropri, ate set point was j reached did not, notify the On-Shift Operations l l

Supervisor (OSOS).

3.2 FREQUENCY j

3.2.1 A " Reactor Trip Report" Data Sheet 1 shall be completed l

+

as soon as practical whenever a reactor trip.has a occurred with more than one control rod withdrawn and

{ fuel in the vessel. (Does not include rod drop time testing.)

3.3 REACTOR TRIP REPORT 3.3.1 As soon as practical following a reactor trip, the Shift Technical Advisor shall complete a " Reactor Trip l 4

Report" Data Sheet 1. Any abnormality should be i

recorded. Its significance can be determined during the review. For items that cannot be verified, indicate so on the trip report and why. In the absence j~

of an STA, the Operations Supervisor shall designate someone to complete the report.

3.3.2 The STA and On-Shift Operations Supervisor shall I, i analyze the event to determine-its cause and the following: )

a. Did all major safety-related and other important 1

equipment involved in the trip operate as l expected?

i J

CONTINUED i

mm

. - - . _ _ _ _ _ - _ - . _ _ . . . . - _ , . _ _ _ . . - - - - . , . . . , . . - . , . . _ _ . _ . ~ , . . - _ . _ - .

. . . _ - _ . . - . - , _ , _ . - , _ - _ , . . _ _ ~ - . . . , , . . -

PROCEDURE NO. REVISION PAGE No.

10006-C 1 3 of 19 i b. Is it is acceptable to restart the reactor? .

They shall look beyond the obvious indications to diagnose the cause of the event and evaluate the plant response. They shall review available',

i information throughly,_looking for: (1) abnormal indications or degraded trends in equipment performance, (2) events occurring out ofLthe i normal or anticipated sequence, (3) failed or degraded response of equipment to control signals,

i. (4) unusual chemistry results or radiation readings, and (5) unanticipated alarms.

. 3.3.3 Reactor Trip Personnel Statements, Data Sheet 2.should j be completed by the persons involved with the trip and included with the Reactor Trip Report, Data Sheet 1.

Reactor Trip Personnel Statements may be completed by individuals or groups of individuals as long as it j promotes an accurate event recopatruction.

i 3.3.4 The Shift Technical Advisor and the On-Shift Operations I i Supervisor are responsible for event classification (the Operations Superintendent will resolve disag,reements). For Condition I' trips-the On-Shift l

{ Operations Supervisor has authority to restart the reactor. For Condition II trips only the General l 1 Manager, or his designee, can authorize reactor restart.

3.3.5 If the cause of the trip or significant aspects of the

. trip recovery are not understood, a more thorough I i investigation must be made until the cause of the trip i

is known or has been investigated to the fullest reasonable extent before permission to startup shall

, be authorized. If the cause is not known, only the

General Manager, or his designee, can authorize unit l startup. The On-Shift Operations Supervisor has the authority to contact other departments to aid in the j investigation.

NOTE

. The'STA and On-Shift Operations l i Supervisor may change their j initial classification of a 3

reactor trip if more information

! becomes available.

CONTINUED 2

rows

, _ _ . , - - - . , - . _ - . - . - _ . . , _ . . _ . , . . . _ _ _ . . . _ . . _ . _ _ . ~ _ . . . , . . - . . _ - . . - . . _ , _ , - . . _ . _ . ~ , . . . . . - . - - . _ , ,

T  ;

PROCEDURE No. REVISloN PAGE No.

0006-C l .

3.3.6 Procedures requiring revision or requests for personnel training, that are necessary to comply with required corrective actions, should be initiated using Action Item Tracking Forms. The corrective action 3

description should-reference the Action Item Number.

Procedure revision or requested personnel training should not delay unit restart unless deemed necessary l I

by the On-Shift Operations Supervisor.

3.3.7 " Reactor Trip Reports" for Condition II trips will be l reviewed by the Plant Review Board. The Operations Superintendent will ensure that PRB review of such

reports is scheduled in a timely manner. This is

! intended to keep the PRB aware of reactor trips involving possible safety concerns. PRB review of

" Reactor Trip Reports" is not required prior to reactor restart.

3.4 REPORT NUMBERING Each " Reactor Trip Report" will be assigned a sequential number.with the unit number and last two j digits of the current year preceding the assigned number (e.g. 1-84-XXX). The sequence will begin at X-XX-001 (e.g. 1-84-001) at the beginning of each year.

Each unit Shift Supervisor will be resgonsible for keeping a log of " Reactor Trip Reports Data Sheet 4 l f and assigning the sequential number. The log will be kept in the Control Room and updated as each trip occurs.

3.5 REPORT DISTRIBUTION t

I The On-Shift Operations Supervisor shall forward the 4 " Reactor Trip Report" to the Operations Superintendent for review. The report is then sent to Document Control where copies are made and routed to the General 3 Manager, PRB Chairman and all department ,

superintendents for their information. The original -

. will be kept by Document Control for the life of the

plant. ,

i END OF' PROCEDURE TEXT 0

i i

mos

. . . _ . _ . . . . . _ _ . ..,, . .._ _ . ~ . . _ _ _ . . _ . . _ . _ _ _ . . . _ , . _ . . . _ . . . _ . . . _ . . . . ~ _. . . , . _ , _ , . . . _

PROCEDURE NO. REMON M ENO.

10006-C l 5 of 19 l

l l

Reactor Trip (

Occurs I 9 F 1

Rx Trip Report '

Filled-in By f STA j 9 F l Post-Trip Review l

' Completed By l

STA and OSOS

)

Event Condition I ' Classified By & Condition II

' r Event Event STA and OSOS 1 F 1 F Restart Decision General Manager 0505 And PRB Review I

l 9 F Plant Condition Corrected l f )

Restart Decision ,

General Manager I REACTOR TRIP REPORT FLOW CHART Figure 1 703445

PROCEDURE Mo. REVISloN PAGE NO.

Sheet 1 of 11 l

DATA SHEET 1 ,

i REACTOR TRIP REPORT  !

UNIT NO. REPORT NO.

TRIP DATE TRIP TIME  !

i

1. SHIFT PERSONNEL i ;

, e i OSOS  !

SS 4 i

RO i

PO .-  ;

STA I i

\

Other persons involved:

I b '

i

2. PRETRIP CONDITIONS 4

a. Mode Reactor Power Boron Concentration PPM Reactor Coolant System Pressure PSIG i

RCS T,yg *F Pressurizer Level Reactor Coolant Pumps Operating Steam Generator Levels 1 2 3 4 l Generator Electrical Load MWE i

703445

PROCEDURE NO. REVISION PAGE No.

Sheet 2 of 11 DATA SHEET 1

~

i b. Off Normal Status Of Plant Systems i

Of Safety Systems:

f a

l 4

I 4

c. Tests and Surveillances in Progress:

i

\

1 l

i

) d. Operations in progress at time of Reactor Trip:

4 i

i i

1 1 3. POST TRIP CONDITIONS l

l a. RPS Operation First out annunciator I

List of RPS channels actuated l 1

j i

1 l

)

I f

i l

l 703445

. _ , ~ .._4_ . . , _ _ _ . _ . . . . . . . . - . _ _ . - . . _ . . . . _ . - . . _ . , , , _ . _ . _ _ . _ . _ . _ . . _ _ - . . . _ . _ , . _ , . _ _ . _ . . . .

PROCEDURE No REVISloW PAGE NO.

10006-C y 8 of 19 DATA SHEET 1

, Did the Reactor Trip result from an automatic or manual trip? (Circle one): Auto Manual Comment:

i 1

Did all Reactor Trip Breakers open, and all rod banks i fully insert? (Circle one)

I Yes No i

If no explain: .-

i 1 l l

Did RPS channels actuate conservatively with respect to their intended set points? (Circle one)

Yes No

If no, explain and describe instruments. ,

i

.i Based on available information and above evaluation

! did the RPS function correctly? (Circle one) l Yes No If no, describe corrective action required and reference any supporting documentation: ,

1 l

1 4

hNY

PROCEDURu*: REVISION PAGE NO.

Sheet 4 of 11 i DATA SHEET 1

b. ESFAS Operation Was ESFAS actuation-required? (Circle one) l Yes No l Comment: ,

I l

i l

How was ESFAS actuated (Circle one)

AUTO MANUAL N/A 1

List the ESFAS channels actuated:

I I

! I If two or more ESFAS channels monitoring the same 4 variable reached an ESFAS setpoint, did the ESFAS components actuate without undue delay? (Circle one)

. Yes No 4

If no describe:

I f

Based on available information and the above evaluation .'

did all ESFAS components perform correctly? (Circle one)  !

Yes No If no, describe corrective actions and reference

supporting documentation

1 703445

. . _ . , _ . - ~ - - - - - . - . ~ - - . . . . - - - - - - _ _ - - _ . - _ _ . - - , .-- _ _ _ . _ , . . _ - - - _ - , . ..-~. ,- ~ ____-... ,_, _ - _ - - - . - . . , _ _

PROCEDURE Wo. REVISION PAGE WO.

0006-C Sheet 5 of 11 DATA SHEET 1 l

4. PLANT RESPONSE

a. Documentation Attached Plant Computer Alarm Printout YES NO Plant Computer Pre / Post Trip Logs YES NO ERF Computer Printouts YES NO I

Recorder Chart reproductions YES NO If yes, specify:

I .-

i ERF Computer Trend Prints YES NO 1

) If yes, specify:

i i

?

i I

l

b. Plant response MAX MIN PRZR Pressure PRZR Level

) Tavg l

SGl Level SG2 Level j SG3 Level i

SG4 Level l SG Pressure Did PRZR PORV's open YES NO Did PRZR Safety Valves open YES NO 4

70344$

. _ _ _ . . . - , _ . _ _ _ _ - - . _ _ . - . _ _ . . _ _ ~ . . . . . . . . _ _ . . . _ . . - . _ , _ . _ _ . - . _ _ _ _ . -

PROCEDURE NO. REVISloN , PAGEMO.

Sheet 6 of 11 t DATA SHEET 1 Did SG ARVs open YES NO

- Did SG Safety Valves open YES NO Explain any abnormal responses:

i j  !

1

c. Was any other plant equipment malfunction noticed?

l Comment:

i I 1

! I

, f

5. TRIP IDENTIFICATION AND REVIEW i

a. Sequence of Events. {

i Prepare a written sequence of events using Data Sheet 3 '

from available data and attach to this report.

b. Trip Identification Root Cause of the reactor trip was:

i f

a i

4 i 103445

PPOCEDURE No. R EVISION PAGE NO.

Sheet 7 of 11 DATA SHEET 1 If the root cause of the trip is not apparent, describe l the evaluation in progress and organizations responsible for the evaluation.

t

\

' What corrective actions have been completed or are in progress to correct the root cause of the trip I transient?

i i

)

Identify any off normal occurrences that accompanied the trip.

i I

Did all automatic functions perform correctly?

j (Circle one) 3 Yes No If no, describe corrective action and reference

. supporting documentation.

l l

l l

i 1

i i

103445

.. .= . . _ - . -

PROCEDURE No, REUISION PAGE Ro.

Sheet 8 of 11 DATA' SHEET 1 l Did the procedures used adequately cover the required 4

actions?- (Circle one) l Yes No If no, describe required corrective action and

reference the action tracking item number used .

to initiate procedure correction. l t

i .

1 i

Did the operators adequately ha'ndle the event?

(Circle one)  ;

I

! Yes No I NOTE The purpose of this step is to l identify weaknesser in training for the purpose of feedback to 3 operators. Do not address ,

j specific cases of possible 4 personal error. Specific cases of possible personal error shall l be irought to the attention of

! the OSOS or the Operations

! Superintendent as appropriate.

i i If no, describe the corrective action required and i

Plant Operating Orders or Action Tracking item numbers i

{ used to initiate retraining or other actions.

I Was an Emergency Plan EAL reached? Describe level j involved (NUE, Alert, Site Area, General).

l l

1 f

i

)

103445

PROCEDURE No. REVISION PAGE MO.

. 10006-C 1 14 of 19 l.: Sheet 9 of 11

~

DATA SHEET 1 Technical Specifications have been reviewed, and

~

entry into the following LCO's was made as the j -

result of this incident:

i LC0f DESCRIPTION INITIAL (STA)

I i

t 4

j l 1

! 6. TRIP CLASSIFICATION AND STARTUP AUTHORIZATION

a. Trip Classification i

The reactor trip on at  : is a j Date Time condition (circle one):

I II I Signature indicates agreement with condition.

i

/

j shift Technical Advisor Date Time

/

On-shift operations supervisor Date Time  !

j i

'I I

l

.i I

mms

_ _ _ . , , . _ _ _ . . , . _ , . . _ . _ . . . _ _ _ m__ , . . . , . , _ _ _ _ . , _ _

I

• PROCEDURE NO. REVISION PAGE NO.

10006-C 1 15 of 19 Sheet 10 of 11 DATA SHEET 1

, b. Startup Authorization

- For condition I events the On-Shift Operations Supervisor has authority to authorize Unit Startup.

I recognize that the previous trip is a condition I j event and permission is given to perform Unit i Startup.

affected unit

/

On-Shift Operations Supervisor Date Time For condition II events only the General Manager, or l his designee, can authorize reactor restart.

L

! Permission is granted to start-up Unit

! (affected unit) i i  !

! /  !

General Manager Date Time

Comment

i i

l l

5 I

i 4

l I

i m3us

_ _ _ _ _ . - _ _ ~ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - ,

PJX)CEDURE NO, REVISION PAGE NO.

10006-C 1 16 of 19 Sheet 1 of 2 DATA SHEET 2 l

, REACTOR TRIP PERSONNEL STATEMENT REPORT NO.

TRIP DATE TRIP TIME

1. Summarize the sequence of events and actions taken, i

=  !

l l

l l

l

2. Did any automatic system malfunction or require operator intervention?

)

3. Did this reactor trip reveal any procedural inadequacies?

10344$

REVISION PAGE NO, PROCEDURE NO.

. 10006-C 1 '17 of 19 Sheet 2 of 2 DATA SHEET 2 1

If this trip occurred again, what would you do differently?

4.

! 5. Are there any lessons learned from this trip that you l believe should be included in training?

l 1

)

)

i j o. Comments:

l l

1 i

Signature Title Date i

i l

l l

l 1

4 701445

r PROCEDURE NO. REVISION PAGE NO.

. 10006-C 1 18 of 19 Sheet 1 of 1

. DATA SHEET 3

. 4 SEQUENCE OF EVENTS ,

4

- Page of i Rx Trip Report E s TIME EVENT l

.1 i i

.I i

r a

l 4

i i

J l 4

1 l

l

' 1 I

i i

i l

.I l 1

1 6 i

i ,,

i-703445 h\

. , . - , . - . . , . -. .,__-...__,-,--,-..,_,,._........._.--,,...,,.,i

• PAGE NO.

PROCEDURE NO. REVISION 10006-C. 1 19 of 19 2

Sheet 1 of 1 DATA SHEET 4 REACTOR TRIP REPORT LOG J' -

UNIT NO.

i DATE RESTART NUMBER DATE ROOT CAUSE AUTHORIZED t

l 4

.~

4 l

l l

l l

l i,

I i

I i

i

'j

)~

1 1

)

l i

j

)

I 0344$

)

. - . , . . _ . - _ _ - _ _ _ _ . - _ . - . - . - . - - . - - . . _ - _ - . . - - - . - . - . - . , - - - - - - -