ML20126H253

Rev 7 to Procedure AP.28, Post-Trip Transient Rept

ML20126H253
Person / Time
Site:	Rancho Seco
Issue date:	08/02/1984
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20126H184	List: ML20126H180 ML20126H253
References
AP.28, TAC-52793, NUDOCS 8506100300
Download: ML20126H253 (22)

Text

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.i 08-02-84 P0b75P  !

D-0061P g .

AP.28  ;

POST TRIP TRANSIENT REPORT l

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1.0 PURPOSE .

.1 Pre-Startup Actions To provide-a systematic method for diagnosing the cause(s) of a reactor trip, ascertaining the proper functioning of safety-related and other s important equipment during the trip, detemining any detrimental effect on plant equipment caused by the trip, and making the detemination that the *'

plant can be restarted safely. .

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.2 Subsequent Actions (Usually Post-Startup)

To provide for a detailed account of the trip, and to develop and adopt long-tem corrective actions to be taken.

2.0 REFERENCES

.. am.

.1 NO-001 Coordinated Commitment Log

( .2 -Adapted from INPO Good Practice-OP-211 ,

.3 Engineering and Quality Control Guidelines, MEG.203 ,

.4 Technical Specifications 6.2.2.g. 6.5.5.1, 6.9.4.1. 6.10.2.f

.5 Administrative Procedures 1, 3, 17, 22, 39

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.6 Plant Operations Manual, Procedure A.75 -- Plant Computer

.7 Code of Federal Regulations, 10 CFR 50.72 3.0 PROCEDURE

.1 Overview CAllTION:

Instructions for each step shall be followed in this sequence.

.1 Plant trip or transient occurs.

.2 The Shift Supervisor initiates this procedure.

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<. Rev. 7

(. AP.28-1

[*ASEE!!8sha: PDR-

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s PROCEDURE (Continued) 3.1 .3 Personnel statements gathered and machine generated data is collected.

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.4 The STA reviews the assembled infomation for completeness.

.5 Trip witnesses' shift may end now, at the earliest.

.6 The Shift Supervisor and STA perfom a nuclear safety assessment.

, .7 The Plant Superintendent may allow restart here (at the earliest).

.8 Engineering and Quality Control Engineer writes a Trip Report.

.9 The Plant Review Committee discusses and amends the Tri;i Report and

, its recommended correct 1ve actions.

.10 The Plant Superintendent reviews and approves the amended report and its mcommended corrective actions.

.2 Plant Trip or Transient j

.1 For the punoses of this procedure, a plant trip is when a generator, turbine, or reactor trip occurs that is not a part of a planned plant l l

progression.

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.2 At the discretion of the Shift Supervisor, this procedure may be initiated for non-trip transients.

.3 At the discretion of the Engineering and Quality Control Superintendent, this procedure may be entered for a non-trip transient. If their shift had ended, the witnessing Operations crew has no requirement to complete their sections of this procedure. ,

CAUTION:

f If any of the Primary System Safety Valves, PSV-21506, PSV-21507, or PSV-21511, lifted or failed to lift when required, an Occurrence Description Report must be initiated in accordance with AP.22. (Reference Technical Specification 6.9.4.1.j)

.3 Initiation (Pre-Startup)

Notify the NRC in accordance with 10 CFR 50.72.

Once the plant is in a condition where the Shift Supervisor judges that data gathering will not impede the Operator's control of the plant, this procedure is initiated. If plant conditions change, any licensed Operator may interrupt this procedures' perfomance temporarily.

If it is the Engineering and Quality Control Superintendent's decision to enter this procedure, see Step 3.2.3.

Rev. 7 AP.28-2

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• A .

, PROCEDURE (Continued) 3.4 Data Gathering

.1 Machine Generated Time-mark all strip charts adjacent to the pen.

For the pm-startup evaluation, some strip charts need not be retrieved, but can be left in place for the trip report writer.

Leave those traces that show a single downwards trend. Strip charts may be snipped and left with the data package, or removed from recorder and copied. If snipped, the chart s remaining roll should have an explanatory note.

CAUTION:

Bailey computer " sequence of Events" and " Memory Trip Review" functions, if cancelled, are lost.

Because the utility typer must be shared for real-time monitoring and trip data gathering, call up only one -

Bailey function at one time.

.2 Record the retrieved printouts and strip charts on Enclosure 4.1.

Complete Enclosures 4.1 and 4.2.

.3 Plant ' Personnel Statements After the plant is in a safe, stable condition, the Shift Supervisor shall ensure each individual involved in the trip (e.g., reactor operators, maintenance technicians, etc.) provides a statement concerning his/her involvement in the reactor trip. These statements may be obtained in one of the following ways: 1) self-written statements; 2) interviews with personnel involved in the reactor trip: 3) critique with all involved personnel.

Use Enclosure 4.3. Read and initial statements of nearby personnel so that, with your statement's assistance, an accurate and complete picture results. Restrict statements to facts concerning the event; the facts should be stated chronologically, if possible.

The written statements shall be included in the reactor trip data package to assist in the event reconstruction.

.5 Data Completeness Doublecheck (Pre-Startup)

.1 The STA will review the collected data.

.2 Any followup questions are best asked at this time, while the events are fresh in everyones' mind. Use " Remarks" areas for the documentation space.

/ Rev. 7

_ (, AP.28-3

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l PROCEDURE (Continued) 3.6 Time to Release Individuals From Shift The goal is to finish the completeness doublecheck before releasing individuals from their shift. Exceptions are:

.1 The Shift Supervisor detemines that the individual will otherwise work beyond limits of Technical Specification 6.2.2.g.

.2 By exemption by the Operations Superintendent or higher management.

.7 Nuclear Safety Assessment (Pre-Startup)  :

.1 Analysis of Transient The Shift Supervisor, or SRO designate, and the duty STA will mconstruct the transient by completing Enclosure 4.4 using the i collected data. A chronological description of the event will be <

developed, using all available data. Pertinent alams trips, actuations, and isolations will be listed or marked on the sequence-of-events or alarm type printout. Pertinent plant parameters should be incorporated into the chronological list of i events during the reconstruction.

.2 The trip and transient shall be compared to the expected trip response, based on-the training and experience of the duty licensed operators. s CAUTION:

FSAR transients are " worst case" or limiting conditions. Do not assume that because a transient did not result in peak parameters exceeding the FSAR values that the plant response was acceptable.

.3- If found desirable by the Shift Supervisor, a comparison with

< previous trip reports or FSAR transients should be made.

.4 Analysis of Equipment Behavior NOTE:

l Look beyond the obvious indications to diagnose the cause of the trip and evaluate the plant response. Review the available information thoroughly. Look for (1) abnomal indications or degraded trenas in equipment perfomance, (2) events occurrir.g out of the nomal or anticipated

! sequence, (3) failtd or degraded response of equipment to control signals, (d ) unusual chemistry results or radiation readings, and (5) u1anttipated alams.

' .1 Determine:

i Rev. 7 l- AP.28-4 l

e 3 _

,, PROCEDURE (Continued)

\ 3.7 . 4 .1 .1 If all major safety-related and other important equipment involved in the trip ~ operated as anticipated or expected, and

.2 If the trip / transient caused any detrimental effects on plant equipment, and  :

.3 The root cause of the trip.

.5 Perfomance Summary (Pre-Startup) i The maximum and minimum values of selected parameters shall be .

comparsd with the Type I and Type II Acceptance Criteria in Enclosure 4.5.

.6 Trip Classification _

Based on the results of the analysis and evaluation of the plant trip and subsequent response, the Shift Supervisor or SRO designate, and

- the Duty STA shall classify the event as one of the following conditions (on Enclosure 4.6):

.1 Type I The cause of the trip is positively known and has been

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corrected; all safety-related and other important equipment functioned properly during the trip.

(c ,

.2 Type II The cause of the trip is positively known and has been corrected; some safety-related and/or other important equipment did not function properly during the trip; however, the malfunction has either been corrected or the failed equipment is not needed for reactor startup.

.3 , Type III

.1 The cause of the trip is not positively known, or .

.2 Some safety-related or other important equipment did not function properly and the malfunction has not been corrected, and the failed equipment is needed to start up.

If the Shift Supervisor did not actually perfom the trip

. investigation, he shall review and approve the event investigation and classification.

If the Shift Supervisor and STA cannot agree on classification of the transient, the more conservative classification will be the preliminary choice.

,; Rev. 7 1, AP.28-5

PROCEDURE (Continued) 3.7 .7 ' Management Notifications Once the reactor trip event is classified, the Shift Supervisor shall

' inform the Plant Superintendent. If the event is classified as a Type III, the Shift Supervisor shall also inform the Operations Superintendent and the Duty STA shall inform the Superintendent of Engineering and Quality Control.

.8 Restart Decision (Pre-Startup)

.1 Type I and II Events Based upon this classification, the Shift Supervisor can recommend restart of the reactor. Complete Enclosure 4.6.

.2 Type III Event The Operations Superintendent and Engineering and Quality Control Superintendent will direct the further investigation of the trip to determine necessary corrective action before restart. The Plant Superintendent, the Operations Superintendent, and the Superintendent of Engineering and Quality Control will evaluate the classification.

NOTE:

Sources of expertise that should be considered include nuclear steam supply vendors, vendor engineers onsite

. engineering staff, corporate engineering staff, and ~

other experienced. operations and maintenance personnel. ]

The Operations Superintendent and Engineering and Quality Control Superintendent will analyze the event reconstruction, emphasizing the root cause of the trip and the resolution of abnormal or degraded indications. Use available expertise to resolve questions concerning the cause and plant response. Supply the following information to the Plant Superintendent:

.1 The actual or most probable cause of the trip; l

[* .2 The maintenance and testing necessary before reactor restart including additional measures to verify the most probable cause;

(. .3 Additional monitoring or trending required during and/or after -

reactor restart; l

l

.4 Necessary briefings to operations and/or maintenance personnel concerning specific equipment indications or possible

• malfunctions; and

.5 The conditions necessary for a reactor restart.

l Rev. 7 AP.28-6 i

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PROCEDURE: (Continued) .

b 3.8 .3 Plant Superintendent Evaluation and Decision The Plant Superintendent shall evaluate the recommendatioh made by the personnel perfoming the trip investigation. For Type III Events, the Plant Superintendent should consider convening the PRC to myiew the trip investigation prior to reactor restart.

The Plant Superintendent shall ensure the following was done before allowing reactor restart:

.1 The most probable cause of the trip is known and corrected.

.2 Major safety-mlated and other important equipment. functioned properly during the transient, or cormctive maintenance and  !

satisfactory testing has been perfomed or will be completed when plant conditions pemit.

.3 The plant response during the event has been analyzed and the plant responded as anticipeted, or abnomalities are understood and cormcted as required by Technical Specifications except as described below. ,

l If the cause of the trip has not been positively identified, the Plant Superintendent shall determine-if the cause and the cin:umstances surrounding the cause have been analyzed adequately.

,! Adequate measure must be implemented to prevent repetitive challenges to safety systems during future power operations.

' ("_ .9~ Trip Report Writing (Usually Post-Startup) ,

, The Engineering and Quality Control Superintendent appoints the Trip Report Writer. Once the Operations Superintendent allows, the Writer acquires custo# of all collected data: either originals or xerographic copies are acceptable. The Trip Report Writer shall ensure that snipped strip charts are later :, cored in the same boxes as the original rolls. A trip mport number will be obtained from the Surveillance Scheduler or the Engineering and Quality Control Secretary and entered on the Trip Data i Fom. The number issuer will complete a Commitment Transferral Fom and fomard it to the Nuclear Operations Department Commitment Coordinator for a three (3) week followup on the Coordinated Comitment Log. The post-t"1p review data package will be reviewed to detemine its significance to plant safety and m11ab111ty. During the generation of the Trip Report, the event will be evaluated to produce recommendations for corrective actions (e.g., procedure changes, design modifications, operator and plant staff training). A comparison should be made with previous similar trips in order to identify abnormal or degraded conditions. Engineering and Quality Control Guideline HEG.203 contains infonnation on the Trip Report itself.

.10 PRC Review

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Rev. 7

( AP.28-7 l

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l PROCEDURE (Continued) 3.10 .1 Type I and II Events The Trip Report shall be reviewed by the PRC. This review is not required prior to reactor restart.

.2 Type III Event If directed by the Plant Superintendent, the PRC will review a Type III Event before a. reactor restart is commenced. In any case, a condition. III Trip Report will receive a PRC review.

.3 PRC amendments may be made on Enclosure 4.7 without retyping the ,

report. Justify amendments to recommended corrective actions.

,- .11 Plant Superintendent Review and Approval (Usually Post-Startup)

Submit the amended report to the Plant Superintendent for approval of the recommended corrective actions.

NOTE:

Quality Aissurance tracks the implementation of the mcommended corrective actions.

.12' Dissemination to the Industry (Time Frame Independent of Startup)

The Supervisor of Regulatory Compliance will detennine what, if any. -s infonnation on the trip will be useful to the industry, and is responsible ")

for its dissemination via Nuclear Network, subject to Plant Superintendent approval.

.13 Retention The trip report and data package shall be retained for the life of the

- plant. (

Reference:

Technical Specification 6.10.2.f) 4.0 ENCLOSURES

.1 Trip Data

.2 Secondary Safety and Dump Valves Temperature Stickers Data Sheet

.3 Plant Personnel Statements

.4 Analysis and Evaluations

.5 Performance Summary

.6 Event Type

.7 Trip Report Amendment and Approval Rev. 7 AP.28-8 ,,

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ENCLOSURE 4.1- -

r TRIP OATA Trip No.

NOTE:

Of prime importance are those values or observations that are only obtainable from witnesses. Operator's statements must be completed before the end of their shift except as waived by the Operations Superintendent or higher management or Technical Specification 6.2.2.g would be violated.

1. Plant Conditions Immediately Prior to Trip:

2. Testing / Maintenance or Contributing / Complicating Factors Prior to Transient: ,

NONE/AS FOLLOWS i

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/ Rev. 7

\ AP.28-9

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ENCLOSURE 4.1 (Continued)

. TRIP DATA

3. Standby Equipment Response / Status:

CAUTION:

Circle only one status per period.

During During Pre-Trip At Post-Trip

'.. Transient Trip Transient How, Why, and Remarks HPI Pump A On/Off On/Off On/Off MU Pump On/0ff ,

' On/Of f. On/Off HPI Pump B On/0ff On/Off On/0ff SFV-23811 HPI Nozzle Open/ Shut Open/ Shut Open/ Shut 5FV-23809 HPI Nozzle Open/ Shut Open/ Shut Open/ Shut 5FY-Z351Z HPI Nozzle Open/ Shut Open/ Shut Open/ Shut g 5FV-23810 HPI Nozzle Open/ Shut Open/ Shut Open/ Shut Aux Feed Pump P-318 On/Off On/Off On/Off Aux teeG Pump P-319 On/Off On/Off On/Off Secondary Safety Open/ Shut Open/ Shut Open/ Shut Valves Atmospher1C Dump Open/ Shut Open/ Shut Open/ Shut Valves Turbine Bypass Open/ Shut Open/ Shut Open/ Shut Valves A-oldu BTU Limits In/ Normal In/ Normal In/ Normal 6-olds BTU Limits In/ Normal In/ Normal In/ Normal Rev. 7 AP.28-10

,.-.,---,-------e----. -_.__ _-

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ENCLOSURE 4.1 (Continued) 1: . TRIP DATA 7

5, '

3. Standby Equipment Response / Status: (Continued)

During During Pre-Trip At Post-Trip Transient Trip Transient How, Why, and Remarks sig so11er E-360 Run/Off Run/Off Run/Off 4

Small Boiler E-365 Run/Off Run/Off Run/Off Throttle Stops Not C1/Cl Not C1/C1 Not C1/Cl On HISS Indication Governor Valves ' Not C1/Cl Not C1/Cl Not C1/Cl On HISS Indication RH Stops Not C1/Cl Not C1/Cl Not C1/Cl '

On HISS Indication RH Intercepts Not C1/Cl Not C1/Cl Not C1/Cl On HISS Indication

4. Other Equipment- Response:

1 Taken to Manual Perfomance Anytime Acceptable Remarks Rx - SG Master Yes/No Yes/No f ,

{ ATc Yes/No Yes/No Rx Master Yes/No Yes/No Diamond CR0 Yes/No Yes/No Loop "A" FW Demand Yes/No Yes/No I

/ Rev. 7

\.. AP.28-11 l

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ENCLOSURE 4.1 (Continued)

TRIP DATA ~~S

4. Other Equipment Response: (Continued)

Taken to Manual Performance Anytime Acceptable Remarks Loop "B" FW Demand Yes/No Yes/No "A" Feed Pump Yes/No Yes/No "B" Feed Pump Yes/No Yes/No "A" Main Feed Valve Yes/No Yes/No "B" Main Feed Valve Yes/No Yes/No "A" Startup Valve Yes/No Yes/No "B" Startup -

Valve Yes/No Yes/No q

..s "A" Turbine Bypasses Yes/No Yes/No "B" Turbine 4

Bypasses Yes/No Yes/No "A" Atmospheric Dump Valves Yes/No Yes/No "B" Atmospheric Dump Valves Yes/No Yes/No Secondary Code Safeties N/A Yes/No Condenser Vacuum N/A Yes/No

Rev. 7 AP.28-12

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7 ENCLOSURE 4.1 (Continued)

TRIP DATA

{s

5. Transient Reactor Coolant System Bounding Values:

NOTE:

If initial value, signify with an asterisk (*).

RCS Parameter Maximum Minimum RCS Loop A Pmssure (PSIG)

RCS Loop B Pressure (PSIG) ,

Pressurizer Level (INCHES)

(*F)

Observed RCS Average Subcooling CooldownMargin,F Rate ----- ----- -

If RCS pressure decrease below 1650 psig, complete the following SFAS Analog Channel Status.

WM Analog HPI Trip Lamp LPI Trip Lamp Channels Channel A bright / die bright /dia Channel B bright / die bright / die Channel C bright / die bright /dia SFAS Digital Analog A Analog B Analog C Channel Trip Lamps Channels Trip Lamp Trip Lamp Trip Lamp 18-HPI bright /dia bright /dia bright / die bright /dia 28-LPI bright / die bright / die bright / die bright /dia 3A-HPI bright / die bright / die bright / dim bright /dia 4A-LPI bright / dim bright / die bright / dim bright / die 6.- Control Rod Breaker Assessment:

- If the Bailey Computer " Sequence of Events" or the alam typer printouts  !

is irretrievable, explain why:

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(' Rev. 7 AP.28-13

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ENCLOSURE 4.1 -(Continued)

- TRIP DATA -3

6. Control Rod Breaker Assessment: (Continued)

RPS Channel Trip Time (From Bailey Computer Group 4)

' Initial Trip Channel: Channel Parameter Time Second Trip Channel: Channel Parameter Time From Alam Typer: : CRD TripC ' onfria (Z004): Time NOTE:

Acceptance criterion is: not more than 2 seconds difference. The Bailey Computer's design can allow an indicated two second difference for simultaneous events.

Control Rod Breaker Opening Time: Subtract Time l

Second Trip Channel From Trip Confirm CRD Breaker Lamp Status on RPS Cabinets:

Cabinet A (A-AC Breaker) Trip Light Bright / Dim Cabinet B (B-AC Breaker) Trip Light Bright / Dim Cabinet C (C-DC Breaker and E Contactor)' Trip Light Bright / Dim .- .,

i Cabinet D (D-DC Breaker and F Contactor) Trip Light Bright / Dim l

7. Transient Secondary Plant Bounding Values:

l Lowest OTSG Startup Range Levels Observed OTSG A: OTSG B:

Lowest OTSG Pressures Observed OTSG A: OTSG B: -

Worst Condenser Vacuums Observed  :

HP: LP:

l REMARKS:

1 l Rev. 7 AP.28-14 /

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ENCLOSURE'4.1 (Continued)

TRIP OATA

{

8. List Equipment Damaged During the Transient:

9. REMARKS: Work Request No. completed to replace temperature recording stickers on Secondary Safety Valves and Atmospheric Dump Valves.

d

10. Required Comouter Printouts:

Attached

1. Bailey: Alarin Summary -- Function 13, Group 1 '

Memory Trip Review -- Function 13, Group 3 Sequence of Events -- Function 13, Group 4 Cont ct Status Summary -- Function 13, Group 5

{, _

Bad Input Summary -- Function 13, Group 7 Deleted Point Summary -- Function 13, Group 8 Delr+ed Honitor Summary -- Function 13, Group 9 Long Ters Data Collection -- OP A.75, Attachment 4.3

2. Com Rm PET: Secondary Code and ADV Printout Completed By

11. Strip Charts Retrieved (Cirtle)

NOTE:

i Retrieving all before startup is not required.

XR-00403 Percent FP PR-21092 RCS Press WR LR-21503 Przr Ly1 XR.00205 Log N TR-21023 T PR-20543 hdr Press FR-21027 RbFlow FR-30119 Stm Flow TR-21031 Th FR-20535 FW Flow A TR-21025 Tave FR-20536 FW Flow B PR-21037 RCS Press A LR-20503 SG A Lvl PR-21038 RCS Press B LR-20504 SG B Lvl XR-30504 Turbine Rev. 7 AP.28-15 4

,, - , , , . _ - , - - - - , - - .,-.,,,,n-,w, , . , - -, --

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l ENCLOSUPE 4.2 .l SECONDARY SAFETY AND DUMP VALVES TEMPERATURE STICKERS DATA SHEET )

("X out" Heat-blackened dots) .

ATMOSPHERIC DUMP VALVES PV-20571 PV-20562 A /0000/ /0000/ A /0000/ /0000/

/0000/ 700007 8 /0000/ 7DU007 B C /0000/ M C M /0000/

SECONDARY SAFETIES C 8 A C 8 A /" 180-250F 310-340F Setpoint l.

// / / / / /PV-205/1// / / / PV-ZD56Z// /PSV-20545 ////// P /0000/ /0000/ 1050 psi PSV-20547 P /0000/ /0000/ 1050 psi PSV-20549 *TS-- /0000/ /0000/ 1070 psi PSV-20551 *W8- /uvuu/ 705U07 1070 psi PSV-20553 P /0000/ /0000/ 1090 psi PSV-20533 *P- /0000/ /0000/ 1102 psi PSV-20555 -*r8-- /0u00/ /0000/ 1090 psi PSV-20557 P /0000/ /0000/ 1090 psi PSV-20559 P /0000/ /0000/ 1102 psi

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Setpoint PSV-20558 P /0000/ /0000/ 1102 psi PSV-20556 P /0000/ /0000/ 1090 psi PSV-20554 P /0000/ /0000/ 1090 psi PSV-20552 P /0000/ /0000/ 1090 psi PSV-20550 P /0000/ /0000/ 1070 psi PSV-20534 P 700DF /ooou/ 1102 pst PSV-20548

• t*- 700UU7 /0000/ 1070 psi PSV-20546 P /0000/ /0000/ 1050 psi PSV-20544 t*- /uuuu/ 'fOUUF 1050 psi t'

1 Rev. 7 AP.28-16

ENCLOSURE 4.2 i

SECONDARY SAFETY AND DUMP VALVES. 3 5

TEMPERATURE STICKERS DATA SHEET

("X out" Heat-blackened dots)

ATMOSPHERIC DUMP VALVES PV-20571 PV-20562 A /0000/ /0000/ A /0000/ /0000/

B 755057 7050D7 8 /0000/ 700507 C /0000/ /0000/ C MM [

SECONDARY SAFETIES C B A C 8 A /* 180-250F 310-340F Setpoint

///////PV-ZO571//// / PV-20b62// /PSV-20545 ////// P /0000/ /0000/ 1050 psi PSV-20547 P /0000/ /0000/ 1050 pst PSV-20549 P /0000/ /0000/ 1070 psi PSV-20551 P /uvuu/ 70UOUT 1070 psi PSV-20553 P /0000/ /0000/ 1090 psi PSV-20533 P /0000/ /0000/ 1102 psi PSV-20555 P /uuuu/ /0000/ 1090 psi PSV-20557 P /0000/ /0000/ 1090 psi PSV-20559 P /0000/ /0000/ 1102 psi a4.u... 4.......AA-AA /j. U

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Setpoint PSV-20558 P /0000/ /0000/ 1102 psi PSV-20556 P /0000/ /0000/ 1090 psi PSV-20554 P /0000/ /0000/ 1090 psi PSV-20552 P /0000/ /0000/ 1090 psi PSV-20550 P /0000/ /0000/ 1070 psi PSV-20534 P /uuuu/ /000u/ 1102 pst PSV-20548 P /0000/ /0000/ 1070 pst PSV-20546 P /0000/ /0000/ 1050 psi PSV-20544 v /0000/ /0000/ 1050 psi

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t Rev. 7 AP.28-16 ,

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ENCLOSURE 4.3 f

PLANT PERSONNEL STATEE NTS Attach statements from personnel involved with the trip concerning the events that preceded and followed the trip. Individual or group statements on how they remember the trip events are acceptable.

Name Position Include the plant conditions prior to the trip, your indications that a problem existed, actions taken as a result of those indications, noted equipment malfunctions or inadequacies, and any identified procedure deficiencies. Al so, include any information you consider important to review this unscheduled reactor trip and actions to prevent recurrence.

i (Read and initial those statements of the individuals that were near your location. If there are conflicts, provide more detail of what you saw. All d

observations of equipment malfunctions will be investigated. Use additional sheets if necessary.)

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i 1 / Rev. 7 l k -~ AP.28-17 l

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ENCLOSURE 4.4 ANALYSIS AND EVALUATIONS PR08A8LE CAUSE OF TRIP Coments:

UNEXPECTED ASPECT OF TRANSIENT BEHAVIOR (if event compared with previous similar transient, note the transient with which

. compared)

Compared With l Previous trip on /

Date T1me FSAR Transient page number

)

i IDENTIFICATION OF SYSTEMS WITH INADEQUATE PERFORMANCE l System / Component Description of Problem l

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Rev. 7 '

AP.28-18 ,

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I ENCLOSURE 4.4 (Continued) 7 ANALYSIS AND EVALUATIONS t

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5W Name Dete Tfme Signatum

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Duty sTA Name Date Time Signatum

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> Rev. 7

• - AP.28-19

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ENCLOSURE 4.5 PERFORMANCE

SUMMARY

Maximus Miniaus (a) RCS Pressure Loop A B Loop A B (b) RCS Th Loop A B Loop A B (c) RCS Tc Loop A B Loop A B (d) SG Press Loop A B Loop A B (e) SG Level Loop A B Loop A B TYPE I AND TYPE II TRIP ACCEPTANCE CRITERIA (Circle)

(a) RCS Pressum Remained Above Setpoint Yes No For Automatic SFAS Trip (b) RCS Pressum Remained Below Setpoint Yes No For PZR Code Safety Valve Actuation (c) RCS Temp. Decreased Less than 1005 F/hr Yes No (Tech Spec)

(d) Reactor Coolant Was Contained Within Yes ,

No The Primary RCS and PRT j (e) Indicated PZR Level Remained On Scale Yes No (f) Indicated SG Level Remained Between Yes No 18" indicated (S/U) and 935 (Operate Range)

(g) RPS Channels Did Not Fail to trip Properly Yes No (h) On RPS Trip, All CR0 Breakers Tripped Yes No and the Reactor tripped withfn two seconds of demand (Enclosure 4.1)

(1) Adequate Subcooling Margin Existed Yes No Coments:

s Rev. 7 AP.28-20

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.o ENCLOSURE 4.6 g.

EVENT TYPE Classify trip as Type I, II, or III according to guidelines in procedure.

The event on at 4 is a type Date "lTue I, II, III Signature indicates agreement with condition.

/

snitt supervisor Date Time

/

srA Date Time .

Notification Plant Superintendent notified of event classification /

Date Time Comments:

(,;

PERMISSION TO START UP Plant Superintendent notified and permission granted to start up the reactor.

/

Shift supervisor Date Time

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Duty sIA Date Time Rev. 7

(- AP.28-21

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, i ENCLOSURE 4.7 TRIP REPORT AENDENTS AND APPROVAL 'i Prepared By Engineering / Quality Control Date PRC heendments and Remarks:

1h PRC review of event on , meeti.ng number Minutes of the meeting (s) are attached PRG Ghairman Date Plant Superintendent Remarks:

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u Approved Plant Superintendent Date END Rev. 7 j AP.28-22

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