W3P84-0297, Forwards Response to Generic Ltr 83-28,Item 1.1 Requesting Description of Program Ensuring That Unscheduled Reactor Shutdowns Analyzed.Util Employs post-trip Review for Diagnosing Unscheduled Reactor Trips

Forwards Response to Generic Ltr 83-28,Item 1.1 Requesting Description of Program Ensuring That Unscheduled Reactor Shutdowns Analyzed.Util Employs post-trip Review for Diagnosing Unscheduled Reactor Trips

ML20080F051
Person / Time
Site:	Waterford
Issue date:	02/06/1984
From:	Cook K LOUISIANA POWER & LIGHT CO.
To:	Knighton G Office of Nuclear Reactor Regulation
References
GL-83-28, W3P84-0297, W3P84-297, NUDOCS 8402100243
Download: ML20080F051 (10)

Text

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LOUISIANA / 142 DRARONDE STREET POWER & L1GHT/ p o Box 6008 . NEW ORLEANS. LOUISIANA 70174 . (504) 366-2345 UriSNs*vsS[U February 6, 1984 W3P84-0297 3-A1.01.04 Q-3-A20.02.02 L.02 Director of Nuclear Reactor Regulation Attention: Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUB.IECT: Waterford SES Unit 3 Docket No. 50-382 Response to Generic Letter 83-28, Item 1. 1 Post-Trip Review (Program Description and Procedure)

REFERENCE:

(1) W3P84-0288 dated February 6,1984

Dear Sir:

The subject Generic Letter, in Item 1.1, requested a report describing LP&L's program for ensuring that uncicheduled reactor shutdowns are analyzed and that the plant can be restarted safely.

Waterford 3 employs a Post Trip Review (PTR) following unscheduled reactor trips to identify and correct the cause of the trip. The PTR, described in the enclosure to this letter, when used in conjunction with the 3equence of Events and other data capability detailed in Reference (1) affords an effective means for diagnosing unscheduled reactor trips.

Should you have any questions or comments in this matter, please contact Mike Meisner at (504) 363-8938.

i Yours very truly.

S 8 K. W. Cook Nuclear Support & Licensing Manager KWC/MJM/ch Enclosure cc: W.M. Stevenson, E.L. Blake, J. Wilson, G.L. Constable 8402100243 840206 6 i t PDR ADOCK 05000382 A PDR I

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Generic Letter 83-28 1.1 Post-Trip Review (Program Description and Procedure)

Operating Procedure OP-10-01, General Plant Operations, requires, prior to

reclosing the reactor trip breakers and subsequent reactor restart, that a Post Trip Review (PTR) be conducted to identify and correct the cause of an unscheduled reactor trip. The PTR is included as Attachment 1.

To summarize our compliance with the requirements of Generic Letter 83-28,

, Item 1.1:

f 1.1.1 Before reclosing the reactor trip breakers the Shift lupervisor must sign the completed PTR indicating thct the cause of the .

4 unscheduled reactor trip has been corrected.

1.1.2 The STA performs the PTR and the shif t supervisor reviews for completeness / accuracy and approves.

1.1.3 The Shif t Supervisor is SRO licensed and Waterford III trained. -

The STA is a Waterford III trained engineer. The SS/STA qualification and training requirements are detailed in Chapter

! 13.1 of the Waterford FSAR.

I-1.1.4 The plant computer Sequence of Events and other sources of information as described in LP&L's response to Generic Letter 83-28. Item 1.2 (W3PR'e-0288, dated February 6, 1984) will indicate the reason of the unscheduled reactor trip and other pertinent l info rmation. The computer, the PTR data and/or parameter plots will provide the necessary reconstruction information.

1.1.5 The PTR requires a qualified person (STA) to compare the various actual plant parameter plots and findings with that of expected plant behaviour including ECCS.

1.1.6 If the reason.for the unscheduled reactor trip is not identified in less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the STA Co-ordinator and at least two of his-j staff must be notified.

4 1.1.7 A copy of che Waterford.PTR is attached.

1 4

POST TRIP REVIEW PURPOSE The purpose of the POST TRIP REVIEW (PTR) is to identify any malfunction or abnormality 5.nd subsequently provide a more detailed investigation and documentation of an unschedul-ed reactor trip. Also, the PTR provides the necessary information in making the determi-

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nation that the plant can be restarted safely. A PTR is a prerequisite for a reactor re-start following an unscheduled reactor trip.

REFERENCES NUREG - 1000, VOL. 1 Section 2.2 INPO - OP-211, POST TRIP REVIEWS DEFINITIONS_

CAUSE Tha root initiator of an event (usually on equipment error, procedural, or personnel error). When the cause is corrected, the possibility of.the event recurring is mini-mizad.

REACTOR TRIP A m:nual or automatic insertion of control rods into the reactor core to interrupt the resctor's ability to sustain a chain reaction.

SEQUENCE OF EVENTS A hard copy display of the chronological sequence of major plant alarms, trips, and actu tions.

RESPONSIBILITIES DUTY PLANT MANAGER l

Th2 Duty Plant Manager, is responsible for making the decision for a Reactor Restart following a TYPE II Event.

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! OP-10-001 Attachment 8.17 Page 1 of 8

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l SHI!T SUPERVISOR l i

Tha Shif t Supervisor is responsible for safety assessment, review and approval of the PTR.

SHIFT TECHNICAL ADVISOR (STA)

The STA is responsible for collecting infor:stion and documenting the infor=ation on the PTR. The SIA may consult plant personnel for their observation and/or participa-tien in the unscheduled reactor trip event.

CONTROL ROOM SUPERVISOR Tha Control Room Supervisor is responsible for assisting the STA in the reconstruction of tha unscheduled reactor trip, if needed.

STA COORDINATOR AND TWO MEMBERS OF HIS STAFF Th2 STA CO-ORDINATOR and two members of his staff are responsible for the review of tha PTR if the cause of the reactor trip is not positively identified in eight hours.

INSTRUCTIONS Tha PTR is a four step process. The PTR, SEALL NOT, distract the Shift Supervisor, OpsretingP' ersonnel, or STA from their primary responsibility of maintaining the plant in a safe condition.

STEP RESPONSIBILITY (1) Data collection and documentation STA (2) Trip investigation, event recon-Otruction and safety assessment SS/CRS/STA (3) Restart decision Plant Manager or his Designate (4) Forward a copy of the completed PTR to Central Records for record retention.

OP-10-001 Attachment 8.17 Page 2 of 8

WATERFORD III SES POST REACTOR TRIP REVIEW Date Time Prepared By (STA):

Part I IDENTIFICATION OF REACTOR TRIP _

Cause of Trip Date of Trip Time of Trip Initiating Failure Part II INITIAL CONDITIONS Reactor Power  %

No. of RCPS (CIRCLE)

Turbine Man / Auto Turbine Bypass valves Man / Auto Which charging pump (s) on?

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A A/B B M W Pump A On / Off M W Master Cont A Man / Auto MW Speed Cont A Man / Auto MW MN Feed Reg Valve A Man / Auto MW Bypass Valve A Man / Auto MW Pump B On / Off l

l MW Master Cont B Man / Auto l MW Speed Cont B Man / Auto MW MN Feed Reg Valve B Man / Auto M W Bypass Valve B Man / Auto l Attachment.8.17 OP-10-001

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Pressurizer Level Cont Man / Auto l Pressurizer Press Cont Man / Auto Pressurizer Spray Cont Man / Auto CEA Mode Select Switch Position Men / Auto 4

0FF NORMAL STATUS OF ANY SAFETY TRAIN:

RPS SIS CSS CIS

. EW MSIS EMERGENCY POWER ANY SAFETY RELATED TESTING SURVEILLANCES IN PROGRESS

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l OP-10-001 Attachment 8.17 l i - Page 4 '.of 8'  !

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Port III PLANT RESPONSE 1

- l Reactor Protection System Type of Trip Time Did all CEAS drop?

HP Safety Injection System Cause of Actuation Time No. of Trains LP Safety Injection System Cause of Actuation Time ,

No. of Trains Containment Spray System Cause of Actuation Time No. of Trains Containment Isolation System Cause of Actuation Time Emergency Feedwater Actuation Time Which Pumps started?

Did S/G Level Respond?

Emergency Power Actuation Time?

'Did both Diesels start?

Did both Diesels load?

Loss of site power?

Safety Injection Tanks Actuation Time Pressurizer Codes Time Main Steam Codes Time Codes Reseat Yes/No Did Reactor power cut back actuate?

Did Turbine trip actuate?

Did PZR heaters respond normal?

Did PZR level respond normal?

Did PZR spray respond normal?

Were additional charging pumps started?

Time started Time stopped Did pumps start in Auto / Man?

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• OP-10-001 Page 5 of 8

. Did steam generator level respond noresl?

Did steam generator press respond nort-al?

Was any Auto / Man stations put in Man?

Was an unplanned radiological release?

Part IV TRAI :SIENT DATA RCS Pressure Max psia Min psia RCS Th Loop 1 Max 'F Min 'F Loop 2 Max *F Min 'F Subcool Margin Max 'F Min 'T SG Pressure Loop 1 Max psia Min pisa Loop 2 Max psia Min psia SG Level Loop 1 Max  % Min  %

Loop 1 Max  % Min  %

PZR Level Max  % Min  %

Attach parameter recorder plots of:

Reactor Power (Log).

Pressurizer Level Pressurizer Pressure RC Th 1 -

RC Th 2 RC Tc 1 RC Tc 2 M.S. Pressure 1 --

M.S. Pressure 2 S/G Level 1 S/G Level 2 M.S. Flow 1 M.S. Flow 2 Attach a post trip primary chemistry analysis.

l Attach a copy of the Plant Monitoring Computer (PMC) sequence of I

events for this trip.

l

, Attach a copy of the PTR program from the PMC.

Attach a copy of Pretrip PRI chemistry

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OP-10-001 Page 6 of 8 l

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. Part U PTR SAFETY ASSESSMENT (Circle) i l (a) RCS Pressure remained above setpoint for automatic SI actuation Yes / No (b) RCS Pressure rensined below

, setpoint for PZR Code safety valve actuation Yes / No (c) RCS temperature decrease less than 100*F per hour Yes / No (d) Was Reactor Coolant contained

within the primary RCS and Quench Tank Yes / No (e) Indicated PZR level remained on scale Yes / No 1

(f) Indicated S/G level remained on scale Yes / No

Part VI DESCRIBE ANY UNEXPECTED BEHAVIOR OR INADEQUATE PERFORMANCE Part VII IDENTIFICATION OF NEED FOR ANY FOLLOW UP ACTION Part VIII LIST ALL TECHNICAL SPECIFICATIONS THAT WERE EXCEEDED I

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l Attachment 8.17 l Page 7 of 8 OP-10-001

Part IX WAS NUCLEAR REGULATORY COMMISSION NOTIFIED IN 1 HOUR?

Part X WAS THE STA CO-ORDINATOR AND AT LEAST TWO MDIBERS OF HIS STAFF NOTIFIED IF THE CAUSE OF THE TRIP IS NOT IDENTIFIED IN LESS TdJLN EIGHT HOURS?

Part XI EVENT CONDITION UAS THE CAUSE OF THE REACTOR TRIP, MALFUNCTIONING REQUIRED SAFETY RELATED AND/OR OTHER IMPORTANT PLANT EQUIPMENT, AND TECHNICAL SPECIFICATION CONSTRAINTS BEEN POSITIVELY IDENTIFIED AND CORRECTED?

(Circle) Yes No IF ANSWER IS YES, TYPE I EVENT IF ANSWER IS NO. TYPE II EVENT Part XII PERMISSION TO START UP TYPE I, EVENT SHIFT SUPERVISOR'S PERMISSION TO CLOSE REACTOR TRIP BREAKERS.

SHIFT SUPERVISOR SIGNATURE DATE TIME TYPE II, EVENT DUTY PLANT MANAGER'S PERMISSION TO CLOSE REACTOR TRIP BREAKERS.

DUTY PLANT MANAGER SIGNATURE DATE TIME Attachment 8.17 1 Page 8 of 8 l OP-10-001

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