ML20092P677

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Procedure 23, Post-Trip Evaluation
ML20092P677
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 02/09/1984
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20092P675 List:
References
23, NUDOCS 8407090245
Download: ML20092P677 (15)
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~* NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 REVIEWED BY: Plant Operations Review Committee Mee g No.84-005 Date 02/07/84 Date Z I APPROVED BY: ( _ / -

(Op#rdtions Superin endent /

APPROVED BY: _

Date Resident Manager Pane No. 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Rev. No. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 hp[kh p

0 PDR 3

Rev. No. O Date 02/07/84 Page 1 of 15

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  • - NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION
  • PROCEDURE NO. 23

1.0 PURPOSE

The purpose of this procedure is to collect pertinent information concern-ing a reactor scram, to analyze the scram, to assure the plant responded as designed, and to assure a safe and timel; return to power operation.

2.0 APPLICABILITY

This procedure is used to evaluate the causes of unplanned plant shut-downs.

3.0 REFERENCES

1. FSAR
2. Cycle Reload Analysis
3. Technical Specification

4.0 DEFINITIONS

4.1 Data Sheet 1 - A summary of plant opersting conditions before and during the transient.

4.2 Data Sheet 2 - A log for deficiencies noted during the event and subsequent analysis.

4.3 Cause - The origin of an event (usually an equipment malfunction, procedural, or personnel error).

5.0 RESPONSIBILITIES

5.1 Shift Technical Advisor Following a reactor scram, complete Data Sheet 1 to the extent possible. This should not interfere with his primary responsibilities and in fact may aid him in diagnosing potential plant problems.

5.2 On-Shift Operators Aid Shift Technical Advisor in completing Data Sheet 1, not to inter-fere with their primary responsibility of controlling the plant.

5.3 Shift Supervisor

1. Ensure this standing order is implemented.
2. Ensure plant personnel attend post-trip briefing.

Rev. No. O Date 02/07/84 Page 2 of 15 .

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER POST TRIP EVALUATION

  • PROCEDURE NO. 23 TITLE:
3. Aid Operations Superintendent in the transient analysis.

5.4 Operations Superintendent or designated SRO.

1. . Analyze data collected to. ensure that the plant responded as designed.
2. Ensure deficient items are noted and corrective actions initiated.

5.5 Plant Operations Review Committee

1. Review all unanticipated reactor trips prior to restart where the cause is:
a. Unknown or
b. Safety related equipment functioned in an abnormal manner and the cause is undetermined or deficiencies remain un-resolved.
c. Abnormal radiation or chemistry occurred.
2. Recommends to the Resident Manager or designated alternate course of action to be taken in cases a, b, and c above.

5.6 The Resident Manager or his designated alternate makes the decision to restart the reactor.

6.0 SPECIAL INSTRUCTIONS / REQUIREMENTS:

7.0 PROCEDURE

7.1 When a reactor scram occurs, the Shift Technical Advisor with the aid of plant operators shall complete Data Sheet 1. Any data not~

collected ditring the event should be obtained from records, computer printouts, or post trip logs.

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7.2 The operating shift, when relieved from duty, shall conduct a post =

l event. critique. Any plant personnel who were involved in maintenance and testing related to the event shall attend the critique. The critique shall be documented on an Occurrence Report Critique form per AP-8.2. - Any system abnormalities, procedure inadequacies, equipment '

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malfunctions shall'be noted in Data Sheet 2. The critique form shall

' be attached to' the scram report along with any written statements I _ pertaining to the event.

l Rev. No. O 1

02/07/84 Page 3 of 15' J

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r NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTHENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 7.3 The Operations Superintendent or a designated SRO shall review the data collected following the event. He shall complete Data Sheet 2 for each significant material discrepancy found during the event.

Generally, these should include major equipment failures such as failure to isolate, failure to initiate, and the like.

7.4 1. The Operations Superintendent or alternate shall review the data sheets and post event critique sheet. He shall write a brief summary of the event. Included will be recommendations for re-start and any corrective actions required prior to restart.

2. If the post trip evaluations result in any of the following, the Plant Operations Review Committee shall analyze the event and determine corrective action required prior to restart.

7.4.2.1 The cause of the scram cannot be positively determined, or deficiencies remain unresolved.

7.4.2.2 Safety related equipment functioned in an abnormal manner and the cause is undetermined or deficiencies remain unresolved.

7.4.2.3 Chemistry results and/or radiation readings are not normal.

7.5 The Resident Manager or his designated alternate shall make the decision to restart.

7.6 The Operations Superintendent or alternate shall review the event and initiate any training that is appropriate to prevent reoccurrence.

7.7 This report shall be forwarded to Document Control Center for filing.

8.0 FIGURES

8.1 Figure 1 - Scram Report Cover Sheet 8.2 Data Sheet 1 8.3 Data Sheet 2 Rev. No. O Date 02/07/84 Page 4 of 15 .

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 FIGURE 8.1 I I I I I DATE I I I I SCRAM REPORT l 1 1 I I I I I I I . EVENT DESCRIPTION I

!. I I I I I I I I I I l 1 l

! I I

l. I I I 4

I I I I l 1 l

I I-1 l l

! 1 I I I I I l I i I i

L I l I I I -1 1 I i

I .

I-l PORC REVIEW REQUIRED MEETING NUMBER I I I

1 TRAINING REQUIRED YES/NO I I I f

l s

Rev. No. O Date 02/07/84 Page -5 'of 15~ .

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~* - NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK-NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 DATA SHEET 1 Figure 8.2 CONDITIONS PRIOR TO EVENT Shift Personnel

. Shift Supervisor Shift Technical Advisor Aesistant Shift Supervisor Control Room Operator Senior Nuclear Operator Auxiliary Operators (1)

(2)

(3)

(4)

Initial Conditions Hnde Switch Position Power Level Thermal Elect Reactor Pressure poig Reactor Water Level in Core Flow mlb/hr Steam Flow mlb/hr FW Flow mlb/hr Procedures in Progress-Major equipment, protection and control systems out of service or inoperable at time of event Completed By:

.Rev. No. 0 Date 02/07/84 Page 6 of 15 .

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b NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 DATA SHEET 1 (CONTINUED)

SCRAM / TRANSIENT CHECKLIST Event Leading Up To Scram / Transient RPS Sensor Causing Scram SCRAM Discharge Volume Hi Level Trip SCRAM Bus Lights Extinguished SCRAM Discharge Volume Vent and Drain Valves Close All Rods Verified Full In Isolations (Yes/No or N/A)

GP I Cause Time Reset GP II Cause- Time Reset HPCI Time Reset RCIC Time Reset RWCU System Time Reset Recire Pump Trip A B NA-Cause Time Time Restarted A B ADS Initiation (Y/N) All Valves Open (Y/N - List)

HPCI Start Auto Manual Inject (Y/N) Trip (Y/N) Cause RCIC Start Auto Manual Inject (Y/N) Trip (Y/N) Cause CS A Start Auto Manual Inject (Y/N) _ Trip (Y/N) Cause CS B Start Auto Manual Inject (Y/N) Trip (Y/N) Cause Rev.'No. O Date -02/07/84 Page 7 of 15 ...

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ,

OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 DATA SHEET 1 (CONTINUED)

LPCI A Start Auto Manual Inject (Y/N) Trip (Y/N) Cause LPCI B Start Auto Manual Inject (Y/N) Trip (Y/N) Cause feedpump A Trip Cause Restarted B Trip Cause Restarted Level Control (narrative)

Level Highest in. Source Lowest in. Source Pressure Control (narrative)

Pressure Highest psig Lowest psig SRV's that lifted: Auto Manual 10100 10200 10300 10400 10500 10600 AC Electrical Busses Energized: 4160V L-15 L-16 L-25 L-26 10300 10400 Load Centers Load Centers 600V EDG A Start Auto Manual Tied Trip Cause EDG B Start Auto Manual Tied Trip Cause __

EDG C Start Auto Manual Tied Trip Cause EDG D Start Auto Manual Tied Trip Cause All DC Electrical Busses Energized:

Protective Relay Trips:

Rev. No. O Date 02/07/84 Page 8 of 15 .

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 DATA SHEET 1 (CONTINUED)

SBGT A Start Auto Manual S8GT B Start Auto Manual Abnormal Alarms: Rad. Monitor, Electrical, etc.

Notifications Made: NRC Time Method Load Dispatcher Management Emergency Notifications Other Mise Notes, LCO's initiated, equipment, problems, etc.

Completed By:

Reviewed By:

Rev. No. 0 .

Date 02/07/84 Page 9 of 15 ,

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  • - .NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION
  • PROCEDURE NO. 23 DATA SHEET 1 (CONTINUED)

LOGIC CHECK SECTION Drywell Pressure For each setpoint, ensure that all required actions occurred and indicate maximum and minimum values with a bar graph.

Verification Bar Graph Set point (psi) Action (Y/N or N/A) 2.7 Reactor Scram Group II Isolation HPCI Initiation RHR Pump Starts A B C D CS Pump Starts A B Stdby. D/G Starts A B C D SBGT Starts ADS Perm alarm Alarm Reactor Water Level for each setpoint, ensure that all required actions occurred and indicate maximum and minimum values with a bar graph.

(inches above) Verification Bar Graph Setpoint (instr. zero) Action (Y/N or N/A) 222.5 Main Turbine Trip RFP Turbine Trip HPCI Turbine Trip RCIC 13-It0V-131 Closed 206.5 High Level Alarm 196.5 Low Level Alarm Runback (if any FWP < 20%

177 Reactor Scram Group II Isolation SBGT Initiation RWCU Isoltion 126.5 Group I Isolation RCIC Auto Initiation HPCI Auto Initiation Recire. Pump Trip A B 59.5 RHR Pumps Start A B C D CS Pumps Start .

A B Standby D/G Start A B C D Rev.-No. 0

.Dete 02/07/84 Page 10 of- 15 ,

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F NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 DATA SHEET 1 (CONTINUED)

CORE AVERAGE FLUX For the following values of power on the appropriate neutron instrumentation, verify the below listed automatic actions occurred. Indicate highest level reached with a bar graph.

Verification Bar Graph Setpoint (APRM) Action (Y/N or N/A) 120% Reactor Scram (fixed) 117% Reactor Scram (Flow Biased, Clamped)

.66W + 54% Reactor Scram (clow Biased) 15% Reactor Scram (When Not in Run)

<2.5% Reactor Scram (With Comp. IRM Hi or INOP In Run Mode)

Verification Setpoint (IRM) Action (Y/N or N/A) 120/125 of Scale Reactor Scram (When Not In Run)

I Rev No. O Date 02/07/84 Page 11 of 15 ,

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i~ + ' NEW YORK POWER AUTHORITY 3AMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING CRDER TITLE: POSI TRIP EVALUATION

  • PROCEDURE NO. 23 1

o DATA SHEET 1 (CONTINUED)

Reactor Pressure-1

! For each setpoint verify that all actions occurred and indicate maximum and minimum values with a bar graph.

Verification Bar Graph Setpoint (psig) Action (Y/N or N/A) 1140. 7 SRV's Lift

1120 ATWOS Recire. Trip. A B 1105 2 SRV's Lift i 1090 2 SRV's Lift 1045 Reactor Scram

-1025 High Pressure Alarm

.. 825 Group I When In Run Verification Bar Graph Setpoint (psig) Action (Y/N or N/A) 450 Permissive _for Opening a CS & RHR Injection Valves 310 Recire. Discharge Valve Close A B 75 SDC Isolation l 50 HPCI Isolation 50 RCIC Isolation Reactor Protection System (RPS) l Action Verification (Y/N or N/A) l t 1. All rods go in 1

! 2. Scram discharge volume trip Recirculation System Runback to No. 2 Limiter Runback to No. 1 Limiter Rev. No. O Date 02/07/84 '

Page 12 of 15 ,

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.- NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 DATA SHEET 1 (CONTINUED)

. Turbine,.

Turbine tripped Manual Auto Cause TSV Scram Annunciated (if > 30". power) Computer Lift Pumps Auto Start Standby EHC Auto Start Turning Gear Auto Start Motor Suction Pump Auto Start Turning Gear Oil Pump Auto Start Emergency Bearing 011 Pump Auto Start (if turning gear oil pump didn't)

I Bypass Valves Controlled Pressure at psig Setpoint at psig i

CONDENSER VACUUM 3

i For the following values of condenser vacuum. Verify that the listed automatic actions occurred. Indicate minimum valves of vacuum during the event with a bar graph.

! Verification-Bar Graph Setpoint ("Hg) Action (Y/N or N/A)

! 8"

  • Group I Isolation Bypass Valve Closure l 20 _ Reactor feed Pump Trip 22.9 Main Turbine Trip

! 24.8 Low Level Alarm 25 to 29 Normal Vacuum

-Reactor water sample isolation valves.

Containment Parameters Maximum Drywell Pressure psia Rev. No. O Date 02/07/84 Page 13 of 15 ,

s NEW YORK POWER AUTHORITY JAMES A. FITZPATRICX NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TI1LE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 DATA SHEET 1 (CONTINUED)

Maximum Torus Pressure psia Drywell Temperatures 'F Maximum Torus Water Temperature *F Torus Level Max in. Min in.

Causes for Significant Increases in any of above:

Drywell Leak Rate Equipment Drain gpm Floor Drain gpm Any system behavior indicative of unusual leakage into drywell Hydrogen Level Before  % After  %

0xygen Level Before  % After  %

Explanation for any changes I

Rev. No. 0

. Date 02/07/04 Page 14 of 15 ,

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. t NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS DEPARTMENT STANDING ORDER TITLE: POST TRIP EVALUATION

  • PROCEDURE NO. 23 DATA SHEET 2 Figure 8.3 ABNORMALITY DISCOVERED IN ANALYSIS Function or Operation in Question Resolution Completed By: Date i

Rev. No.. O Date 02/07/84 Page 15- of 15 .

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