ML20132D402
| ML20132D402 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/23/1985 |
| From: | CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | |
| Shared Package | |
| ML20132D388 | List: |
| References | |
| PAP-1602, NUDOCS 8509300161 | |
| Download: ML20132D402 (19) | |
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-O Page: i THE CLEVEIAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT OPERATIONS MANUAL
+M TITLE:
POST REACTOR SCRAM EVALUATION i
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OM1A: PAP-1602 Page: 11 Post Reactor Scram Evalustion PAP-1602 Table of Contents
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Section Title Page 1.0 PURPOSE 1
2.0 SCOPE 1
3.0 RISPONSIBILITY 1
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4.0 REFERENCES
2 5.0 DEFINITIONS 2
5.1 Tys.e I Scrans 2
5.2 Type II Scrams 2
5.3 Type III Scrans 3
5.4 Type IV Scramr.
3 5.5 Scram 3
6.0 DETAILS 3
6.1 General 3
6.2 Data Collection 4
6.3 Post-Scram inves.t ig,ation 5
6.4 Restart Decision 6
6.5 Post-Scram Evaluation Report Review 7
s.6 In-Bouse Operating Experience Review 7
6.7 Records 7
7.0 ATTACHMENTS 8
7.2 At tachment 1 - Fom: PAP-1602-1 (Sheets a-g),
9 Post-Scram Evaluation Report 7.2 At tachme nt 2 - Fo rm: PAP-1602-2 Personnel 16 Stat ement D
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OM1A: PAP-1602 Page: iii List of Ef fective Pages Page Revision s
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( 'l OM1A FAP-1602 Page: 1 POST REAC11)R SCRAM EVALUATION u.
1.0 PURPOSE
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To ensure a thorough and systematic evaluation of plant scram data in order to properly diagnose the cause of reactor scrams, ascer-tain the proper functioning of safety-related and other important
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equipment prior to restart, and to make the determination that the plant can be restarted safely.
2.0 SCOFE This procedure applies to all unscheduled Reactor Scrams at the Ferry Nuclear Power Plant.
This procedure does not apply to Reactor Scrass that are the planned results of approved tests. This procedure does not address report-ability requirements for Reactor Scrams. Reportability requirements are contained in FAF-0603.
3.L Es? M?:311!n 3.1 The H.'neger, Ferry Flant Operatione Deprrtment (FPC3) or hie desiguated alterr. ate, is respons!Lle for authorinns the Shif t Supervisor to restart the plant following a scram.
3.2 The General Supervising Engineer, Technical Section,' is responsible for providing personnel to investigate a scram, providing input to the Manager, FPOD, regarding the decision to restart, and reviewing and sube.itting the Scram Evaluation Report.
3.3 2.e Stif Supervis;:: (55), is responsible for classif ying the sc:a::
and for making recommendations to the Manager, PF0D, for plant re-start.
3.4 The Shif t Technical Advisor (STA), is responsible for providing post scram data and preliminary evaluations of plant performance including whether equipment functioned as designed. He is also responsible for completing the initial investigation of the scram and for making a recommendation to the SS as to the classification of the scram.
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l Page: 2 3.5 The Plant Operations Review Committee (PORC) is responsible for re-viewing all Scram Evaluation Reports and for recommending approval
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for restart af ter Type IV scrama.
3.6 Plant personnel involved with the reactor scram are responsible for providing the STA with objective comments that describe their obser-vations of and/or participation in the reactor scram.
Y 3.7 The In-house Operating Experience Review Program Coordinator is responsible for ensuring lessons learned from unscheduled reactor scrams are used to improve plant ' safety and reliability and to transfer in-house experience of generic interest to the industry.
4.0 REFERENCES
4.1 INPO Cood Practice OP-211, Post-Trip Reviews.
4.2 NRC Ceneric letter 83-28.
4.3 NUREG-1000. Generic Implications of AWS Events at the Salem Nucle-at Pe-e: rien t.
4.4 C57-71. Rea: tor Scram.
4.5 PAP-06C3, Ter.hnical Specification Reportabic Occurrer.ces.
5.0 DEFINITIONS 5.1 Type I Scrams The cause of the scram 1e positively known and has been corrected; an safc:y-related and other iciportant eq.i; mat fenctioncd properly during the scram.
5.2 Type II Scrans The cause of the scram is positively known and has been corrected; some safety-related and/or other important equipment did not func-tion properly; however, either th'e malfunction has been corrected or does not prohibit a startup.
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5.3 Type III Scrams The cause of the scram is not positively known but is judged by the e
SS to be spurious and to have a reasonably low potential for reoc-l currence. In addition, there is no indication that any safety-related or other important equipment functioned in an abnormal manner during the scram.
1 5.4 Type IV Scrams The cause of the scram is not positively known.
f and /or Some safety-related or other important equipment functioned in an abnormal or degraded manner during the scram and the malfunction has not been corrected.
5.5 Scram A Reactor Protection System actuation that results in the deener-r,itatic c'
ct s. p L;'t solenoid valve s, ir.3:+ t ien c f ce...: _1 :od s.
a ener iration of tie backup scram pilot solenoid velver, at.d tl.e iselation of the stra: discharge volume.
6.0 DETAILS E
6.1 General The post-scram evaluation process is a 6-step process consisting of the following:
Ste; Ren; w.r tbility 1.
Data Collection STA 2.
Initici investigation and STA rec ommended scram classification 3.
Scram Classification Shif t Supervisor 4.
Restart decision Manager. PPOD or designated alternate 5.
Scram investigation CSE, Technical Section and C.
review PORC
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Page: 4 6.
Lessons learned, In-house operating experience Follow-up actions review progran coordinator.
I The overall objective of the evaluation is to determine the accept-t I
ability of performing a reactor restart. The Post Scram Evaluation S
f Report (Attachment 1), guides and documents the scram review pro-Any unscheduled reactor ocram will require a post scram cess.
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evaluation process to be initiated. The post scram evaluation shall be initiated af ter plant conditions have stabilized. This evaluation shall not distract the Shif t Supervisor, operating personnel, or the STA from their primary ~ responsibility of monitor-ing plant parameters and maintaining the plant in a safe condition.
6.2 Data Collection The purpose of the data collection phase of the post scram evalua-tion is to gather sufficient data to reconstruct the transient from prior to the initiating signal until plant parameters have stabil-1 sed.
6.2.1 The STA will complete Sections I and II of Attachment 1 and vill also collect the required infer:ntion liste? in Saction V.
Etripchart recordings must accurately reflect real tics to be.e meanirgful information.
If necessary, annota:e the chart paper vith a time cark, chart speed, and time scale. The STA is recponsible for ensuring that all data required in Sections I,11 and V is securate and is collected in a timely esnner.
The qaality of the scram investigation and r.. start decasien is dependent upon the collected data.
6.2.2 Individuals involved in the scram, as determined by the STA, will provide the STA with a written statement of their involve-ment by filling out a Personnel Statement, Attachment 2.
These statements shall be written to include:
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Plant ccaditions prior to the trip.
2.
First indication that a problem existed.
3.
Individual's actions as a result of the indications.
4.
Subsequent indications and plant response including manual actions.
5.
Noted equipment malfunctions or inadequacies.
6.
Procedure deficiencies noted during the incident.
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In some cases, it may be appropriate for the SIA to interview
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personnel or to conduct a critique with all personnel involved in the scram. If either of these techniques are used, the i
type of information listed above should be obtained.-
y 6.3 Post-Scram Investigation i
I The STA is responsible for the initial post-scram investigation.
The purpose of this investigation is to determine the cause of the scram and to assess the plant's readiness to return to operation.
6.3.1 The STA will reconstruct the transient uaing the collected data.
A chronological description of the transient will be developed in Section III of Attachment 1 using the Sequence-t of-Events (SER) printout as a base.
tion will include pertinent alarms, trips, actuations (manualThis chronologi l
and automatic), and isolations and will incorporate plant parameters for clarification. If the SER printout is not available, note this fact in Section III and reconstruct the transient using available data.
6.3.2 If possible, corpe'e the re.cnnstruction of events with sirflar r
transients descrf Lt3 in the Final Safety Anclysis Report or previour data pacr. ages for similar trips.
This will assist in identifying abnormal or degraded indications.
The transient reconstruction shall also be compared with the required pro-cedure actio = t-determine the af fect of the procedure actiere cr. thc pisut response.
6.3.3 The STA shall analyze and evaluate the event reconstruction and event comparison to deterndne the cause of the scram and the following:
1.
if all safety-related and other important equipment s ov 9' v-3 in the scra; opercted as anticipated or expected.
2.
if the scram / transient caused any detrimental effects on plant equipment.
3.
if any problems affect the other unit.
4.
if it is acceptable to restart the Reactor.
The STA shall also review the available information for 1)ab-normal indications or degraded trends in equipment performance,
- 2) events occurring out of the normal or anticipated sequence,
- 3) failed or degraded response of equipment to control signals.
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- 4) unusual chemistry results or radiation readings, and
- 5) unanticipated alarms. The SIA will complete Section IV of Attachment 1.
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6.3.4 The STA will perform a Preliminary Safety Assessment of the scram and subsequent plant response. Examine the maximum and minimum values of critical plant parameters indicated in
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Section V of Attachment 1.
Cospare these values with Tech-nical Specification values. Document this Safety Assessment t
i by complating Section V of Attachment 1.
6.3.5 Based on the results of the analysis and evaluation of the plant scram and subsequent response the STA will recommend a classification of the event as a Type I, II, III, or IV Scram.
6.3.6 The STA will complete the cover sheet for the Post-Scram Evaluation Report. All Scram Reports will be numbered as follows:
U-YY-NN l
1s a sequential number starting at 01 each year is the year is the unit number The STA will maintain a log of the Scram Numbers. The STA will review the S: t sm Evaluation Report and sign the cover sheet.
6.3.7 The Shift Supervisor will review the Scram Evaluation Report, classify the scra= and sign the cover sheet.
6.3.8 For Type 1, Ripe II or Type III scraas, the SS may reconn al to the Manager, PPOD, that the reactor restart be initiated.
For Type IV scrams, the restart will be postponed until fur-ther investigation is performed.
.I 6.3.9 The SS will forward the Evaluation Report to the GSE. Tech-nical Section for revian.
o.4 Eastart Deci_.icn 6.4.1 The Manager, PPOD (or designated alternate) will authorize the unit startup considering the following:
a.
The'cause of the trip is known and corrected, and b.
Safety-related and other important equipsent functioned properly during the transient, or corrective maintenance and satisfactory testing has been performed or will be 3
completed when plant conditions permit, and The plant response during the transient has been analyzed c.
and the plant responded as anticipated, or all abnormali-ties are understood and corrected as required by Techni-cal. Specifications.
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0 OM1A: PAP-1602 Page: 7 If the cause of the Scram has not been positively identified, the Manager, PPOD, shall determine if the cause and the-cir-cuestances surrounding the cause have been analyzed adequately.
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Type IV Scrans must be reviewed by PORC prior to a restart decision being reached.
6.5 _ Post-Scram Evaluation Report Review
~6.5.1 The CSE. Technical Section, will review the Post-Scram Evaluation Report for the f ollowing:
1.
Ensure that the cause of the scram has been correctly identified.
2.
Ensure that equipment and systems functioned as designed during the transient scram recovery actions.
3.
Evaluate the data in the Evaluation Report to determine if there are any additional corrective actions required prior to startup of the unit.
6.5.2 Upon completion of his review of the Post-Scram Evaluation Report, thr CSE, Technical Section, will sign and dote Lt.e tha.t and forward the repcrt to PORC for review.
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6.5.3 PORC will review the Post-Scram Evaluation Report to identify sny uc3erlyf eg or geretic problems and also review, pri,r to restart, Type IV Scica E.cluation Reports and will reces:4nd a course of action to the Manager, PPOD, for recovering the plant. PORC will evaluate the Scram to determine'if addition-al corrective actions (procedure changes, design modifications, I
training requirements, etc.) need to be implemented.
6.6 In-House Operating Experience Review 6.6.1 A copy of the Scras Evaluation Report will be sent to the In-House Operating Experience Review Coordinator so that corrective actions and lessons-learned will be identified to prevent reoccurrence. Be will evaluate the Scram to determine the need for dissemination of lessons learned to the rest of the industry.
6.7 Records 6.7.1 The Post-Scram Evaluation Report and its Attachments will be i
retained for the life of the plant.
6.7.2 (l
A copy of the Scram Evaluation Report shall be sent to the Training Section General Supervisor.
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OM1A: PAP-1602
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Page: 8 7.0 ATTACHMENTS 3e
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7.1 Attachment 1 - Form: PAP-1602-1 (Sheets a-g), Post-Scram Evalua-tion Report.
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7.2 Attachment 2 - Form: PAP-1602-2, Personnel Statement.
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,e OM1A: PAP-1602 Page: 9 i
Form:
PAP-1602-la
[i Sheets a-g a
f Post-Scram Evaluation Report i
PERRY NUCLEAR POWER FIANT r
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. Unit Scram No.
Date/ Time of Scram:
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Scram Classification: Type Scram Cause of Scram:
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i han:.;er. PTO?, notified a:.6 per:sissf or. grec.ted for res: art (Type 1,11, and
'!! sc. rams only)
Shift !$p 3 i$aI
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Shif t Supervisor:
Date:
Shif t Technical Advisor:
Date:
CSE, Technical Secticn:
Date:
4 PORC Meeting No.:
Date:
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OM1A: PAP-1602 Page: 10 (Cont.)
Form:
PAP-1602-lb S
g Post-Scram Evaluation Report j
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Pre-Scram Plant Conditions 1.
Reactor: Critical Suberitical 2.
Power Level:
(1, cps, or range and value) 3.
Mode Switch: Run Startup/Stby Refuel 4.
Turbine Generator: Shchronized lead MWe Shutdown 5.
Recirculation:
15 k 60 Hz Master Auto M: ster Mz: ual Flex Minual Loop Manual FCV Position 6.
Evolutions / Testing in Progress:
7.
Off-Normal Status of Safety Systems:
s II.
Scram Conditions Prescram Scram Post-Scram 1.
Main Steam Flow i
2.
Feedwater Flow I
3.
Total Flow (Recirc.)
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OM1A: PAP-1602 Page:
11
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Form:
PAP-1602-Ic f
Prescram Scram Post-Scram L
1:
4.
Core P
PSID PSID PSID
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5.
RPV Level IN IN IN 6.
7.
Rx Power 1
1 8.
Off-Cas Pretreat-ment Rad Level 9.
Containment PSIC Pressure PSIG PSIG 10.
Suppression Pool
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- F '
'F Teverature 11.
P* art i ut>onse A.
Safety System Actuation and Performance 1.
Is @ tions:
Type Cause Time 1
~2.
ECCS Actuations:
B.
Obtain the hard-copy data listed in Section VI, Attachments.
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OM1A: PAP-1602
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Page:
12 (Cont.)
Pbra:
PAP-1602-1d
-III.
Chronological Description Composed By:
SRO:
STA:
Page of Time
. Event Description i
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. - - + -,. - - - - -, - -,... -
-,..,..,., -. -,.. ~
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h OM1A: PAP-1602 Page: 13
. (Cont.)
Form: PAP-1602-le i
IV.
Analysis and Evaluation Ii-A.
Probable cause of the scram:
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i Comments:
l B.
Unexpected Aspects of Transient. Note previous similar transients to compare with.
C.
Identification of Systems with Inadequate Performance Systan/ Component Description of Problem C-l
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Page:
14 (Cont.)
Fo rm:
PAP-1602-1f
~j V.
Preliminary Safety Assessment
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_a A. List values of the parameters indicated below:
E Min.
Max.
T.S. Limit a.
Steam Dome Pressure psig
( 1325 psig b.
Reactor Vessel Water Level IN TOF Core thermal power vs. Steam
<25%powerwith c.
Dome Pressure dessure (785 psig 25% power with flow (10%
d.
Minimum Critical Power Ratio (MCPR) (Prior to the Scram)
See Tech Spec Figs. 3.2.2-1 &
3.2.2-2 Reactor coolant syster. bestup!
t.
- F/hr I100*F/hr.
Coo'.d x rates f.
Contain:nent Temperature
'F 90*
g.
Suppression Pool Temperature
'F 95*
h.
Drywell Temperature
- F I135' i.
Drywell to Containment psid - 1.5 to + 2.1 psid j.
Comments:
VI.
_ Attachments 1.
Copy of the Unit Log from past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Recorder charts for the following:
a.
Reactor Vessel Level, Upset and Wide Range Core flow c.
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Form: PAP-1602-lg
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d.
E Reactor Pressure, Wide and Narrow Range e.
Feeduster Flcw
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Steam Flow t.
3 Drywell Pressure 3.
Post Trip Log 4.
SER Log 5.
ERIS Sequence of Events Log 6.
Last P1 prior to the scram 7.
Personnel Statements, Form:
PAP-1602-2 I
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16 - LAST Po rm: PAP-1602-2 g
Personnel Statement
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Prepare a handwritten statement describing the scram event sequence and g
plant response as you remember it.
Include the plant conditions prior to the scram, your indications that a problem existed, your actions as a t
result of those indications, noted equipment malfunctions or inadequacies, and any identified procedure deficiencies. Also include any information you consider important to review this unscheduled reactor scram.
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(Use additional sheets if necessary)
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Signa ture Date Time Position:
No. of attached pages PAP 16/C/amh i
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