ML20086B547

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Pnpp Simulator Four Yr Test Rept.
ML20086B547
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 06/30/1995
From:
CENTERIOR ENERGY
To:
Shared Package
ML20086B543 List:
References
NUDOCS 9507050444
Download: ML20086B547 (8)
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i Perry Nuclear Power Plant Simulator  ;

Four Year Test Report '

Introduction

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The Perry Nuclear Power Plant (PNPP) Simulation Facility Certification was submitted to the Director, Office of Nuclear Reactor Regulation on June 28, 1991. This report is being submitted in accordance with 10 CFR 55.45(b)(5)(ii) on the fourth anniversary of the Certification Submittal. ,

This report describes performance testing conducted on the simulation facility.  ;

from July 1991 through June 1995, discusses performance test failures and ,

discrepancies during the same period. Attachment 1 to this report, Four  ;

Year Test Schedule, provides a schedule for performance testing for the period July 1995 through June 1999. i The owner / operator of the simulator is the Cleveland Electric Illuminating Company, a subsidiary of Centerior Energy Corporation. The Simulator is located  !

at the Perry Nuclear Power Plant in North Perry Village, Ohio, approximately 35 ,

miles northeast of Cleveland, Ohio. The simulator vendor was S3 Technologies l Company of Columbia, MD. The reference plant, PNPP Unit 1, consists of a General Electric Boiling Vater Reactor (BWR/6) rated at 3379 MVTh.

The Simulator was declared ready for training on November 11, 1991. ,

i Additional information regarding the PNPP Unit 1 Simulation Facility is included .l in the Initial Certification package, and is also available upon request.  !

Performance Tests Conducted June 1991 - June 1995 i

Performance tests conducted from June 1991 through November 1991 vere within the -

scope of initial certification performance testing, as documented in letter PY-CEI/NRR-1418L dated December 6, 1991. The conduct of these tests was not credited to the four year performance testing program which began after initial certification performance testing was complete.

Performance tests for the PNPP Unit 1 Simulator vere completed per the schedule included in the initial certification report. In a few instances, some tests were carried over to a subsequent testing period due to 1) simulator and personnel scheduling conflicts due to implementation of PNPP Training Programs, and 2) a delay in the start of the four year testing period to December 1991 due to late delivery of the simulator. In those cases, the affected tests were perfcrmed early in the subsequent period and prior to regularly scheduled tests.

Rescheduling of tests did not violate the intent of performing approximately 25%

performance testing per year.

All scheduled tests have been completed. )

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Perry Nuclear Pover Plant Simulator

~Four Year Test Report Page 2 of 2 Performance Test Discrepancies' June 1991 - June 1995 Discrepancies documented during Performance Tests were categorized as minor and major. Minor discrepancies are'those which did not invalidate the test results or cause the test to be considered a failure. Major discrepancies caused the test results to not meet the criteria established for each type of test in ANSI /ANS 3.5-1985, resulting in test failures when compared to the criteria.

There are 22 minor discrepancies, discovered during the conduct of Simulator performance testing during this reporting period, which remain to be corrected.

These discrepancies are documented in Simulator Discrepancy Packages (SDP). A description of the Simulator Discrepancy Package program is contained in the initial certification submittal.

Uncorrected test failures are as follows:

1. Test T.4.4.1.1, 25% Power Heat Balance, performed on 2/20/95, did not meet the 12% steady state criteria for two critical parameters; turbine output and final feedvater temperature. Reference SDP 95-0024. This discrepancy is scheduled to be corrected by 12/31/96.
2. Test T.4.5.3.20, USAR Analyzed Accident Anticipated Transient Without SCRAM (ATVS) with MSIV Closure, performed 9/15/94. This test did not meet acceptance criteria in that RPV level response was more severe (less conservative) than the USAR Chapter 15 analysis results. Reference SDP 94-0179. This discrepancy is scheduled to be corrected by 12/31/95.

Performance Test Schedule July 1995 - June 1999 The content of the Perry Simulator performance test schedule for the following four years is identical to the original schedule submitted with the initial certification. A complete description of each test, including references to ANSI /ANS 3.5 criteria, may be found in TAB C of the initial certification package. The complete schedule for the tests to be performed in each of the next four years is contained in Attachment 1.

END OP REPORT l

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.F;ur Ycar Tast Rep 2rt L i Attachment 1

,Page 1 of 5 i

l Four Year Test Schedule  ;

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Section 1.0.of this schedule provides the list of the performance tests which j

are conducted annually.- Sectica 2.0 lists, by year, the tests.that will be j conducted-in years 1 through 4 after filing this report. These schedules  !

l represent performance of approximately 25% of performance tests per year.

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L 1.0 ANNUAL TESTING  !

A. Computer Real Time Test

1. T.2.7.1 ' Spare Time Verification ,

l l l B. Steady State Performance Tests

1. T.4.4.1.1 - 25% Power Heat Balance f
2. T.4.4.1.2 - 50% Power Heat Balance ,
3. T.4.4.1.3 - 75% Power Heat Balance )
4. T.4.4.1.4 - 100% Power Heat Balance  !
5. T.4.4.1.5 - 100% Power Stability Test '

t C. Benchmark Transient Tests )

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1. T.4.4.2.01 - Manual Scram 1
2. T.4.4.2.02 - Simultaneous Trip of All Feedvater Pumps  !
3. T.4.4.2.03 - Simultaneous Closure of All MSIV's  !
4. T.4.4.2.04 --Simultaneous Trip of All Recire Pumps  !
5. T.4.4.2.05 - Single Recire Pump Trip  !
6. T.4.4.2.06 - Main Turbine Trip without Reactor Scram l l, 7. T.4.4.2.07 - Maximum Rate Power Ramp (100% - 75% - 100%) 1

! 8. T.4.4.2.08 - Maximum Size LOCA with Loss of Offsite Power i

[ 9. T.4.4.2.09 - Maximum Size Unisolable Main Steam Line Rupture- l

10. T.4.4.2.10 - Simultaneous Closure of MSIV's with Single j l Stuck Open Safety / Relief Valve  :

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- PhrryNucl0rPsvarPltntSiculstor F;ur Y:Or T:st R port Attachment 1

,Page 2 of 5 Four Year Test Schedule 2.0 PERIODIC TESTING A. Year 1 (July 1995 through June 1996)

1. Core Performance Tests
a. T.4.2.1 - Reactor Core Xenon Transient Test
2. Normal Plant Evolutions
a. T.4.3.1 - Cold Shutdown To Reactor Critical
b. T.4.3.2 - Reactor Critical To Turbine Synchronized
3. Transient Tests
a. T.4.5.1.02.AN01 - Annunciator Input Optical Isolator Failure
b. T.4.5.1.06.ED17 - Loss of 125V DC Distribution Panel
c. T.4.5.1.12.IA01 - Air Receiver Leak
d. T.4.5.1.17.NH01 - SRM Detector (pre-amp) Failure
e. T.4.5.1.18.0G03 - Off Gas System Leak Upstream Adsorbers
f. T.4.5.1.22.RH02 - Residual Heat Removal System Pipe Break
g. T.4.5.1.27.TH01 - Recire Loop Rupture (DBA LOCA)
h. T.4.5.1.27.TH27 - Main Steam Line Rupture In Steam Tunnel
4. Halfunction Scenario
a. T.4.5.3.01 - Loss of Feedvater Heating (RRFC In Auto)
b. T.4.5.3.02 - Loss of Feedvater Heating (RRFC In Manual)
c. T.4.5.3.03 - Feedvater Controller Failure-Maximum Demand
d. T.4.5.3.04 - Pressure Regulatory Failure-Open
e. T.4.5.3.22 - PEI Halfunction Scenario #1
f. T.4.5.3.23 - PEI Halfunction Scenario #2
g. T.4.5.3.24 - PEI Halfunction Scenario #3
h. T.4.5.3.25 - PEI Halfunction Scenario #4 l

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[ .F:ur Yccr T:st R: port Attachment l' I page 3 of 5 Four Year Test Schedule B.- Year 2 (July'1996 through June 1997)

1. Core Performance Tests
a. T.4.2.2 - Core Flux Distribution Test
b. T.4.2.5 - Core Thermal Performance Test 2 .- Normal Plant Evolutions
a. T.4.3.3 - Power Increase To 100% Power
3. Transient Tests
a. T.4.5.1.04.CUO3 - Reactor Vater Cleanup System Pipe Break Outside Containment (Steam Tunnel) b.. T.4.5.1.07.EG01 - Main Generator Lockout Relay Trip
c. T.4.5.1.12.IA02 - Instrument Air Line Leak
d. T.4.5.1.17 NM02 - IRM Detector (pre-amp) Failure
e. T.4.5.1.18.0G04 - Off Gas System Leak' Downstream Adsorbers
f. T.4.5.1.23.RP02 - Inadvertent Initiation of Alternate Rod Insertion
g. T.4.5.1.27.TH19 - RPV Level Inst Reference Leg Break
h. T.4.5.1.28.TU01 - Main Shaft Oil Pump Degradation

-4. Halfunction Scenarios  !

a. T.4.5.3.05.- Inadvertent Safety Relief Valve Opening
b. T.4.5.3.06 - Inadvertent RHR Shutdown Cooling Operation i
c. T.4.5.3.07 - Pressure Regulator Failure-closed i
d. T.4.5.3.08 - Generator Load Reject Vith Bypass Valves i
e. T.4.5.3.09 - Generator Load Reject Without Bypass' Valves  ;

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f. T.4.5.3.10 - Turbine Trip
g. T.4.5.3.11 - Loss of AC Power (Loss of. Aux Transformer)  !
h. T.4.5.3.26 - PEI Malfunction Scenario #5 (part 1) l
i. T.4.5.3.27 - Evaluation Malfunction Scenario #1  :
j. T.4.5.3.28 - Evaluation Malfunction Scenario #2  !
k. T.4.5.3.29 - Evaluation Malfunction Scenario #3  :
1. T.4.5.3.30 - Evaluation Malfunction Scenario #4 ,
m. T.4.5.3.31 - Evaluation Malfunction Scenario #5 i i

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  • - Perry Nuclear Power Plant Simulator Four Year Test Report Attachment 1

,Page 4 of 5 Four Y_ ear Test Schedule (July 1997 through June 1998)

C. Year 3

1. Core Performance Tests
a. T.4.2.3 - Core Thermal Power vs. Recire Flow Test T.4.2,4 - Core flux Response to Rod Hovement b.
2. Normal Plant Evolutions d
a. T.4.3.4 Power Decrease to Turbine / Generator Unloade
3. Transient Tests a.

b.

T.4.5.1.06.ED06 - Loss of 480V Bust.4.5.1.09.FWO2 Fe Dryvell Condenser Air Inleakage

c. T.4.5.1.15.HC01
d. T.4.5.1.17.NH03 - LPRM Detector Failure Control Rod Drift - int.4.5.1.25.SW01 - Nuclear Clos
e. T.4.5.1.21.RD03
f. Piping Leakage g.

T.4.5.1.27.TH2O - RPV Level Inst Variable Leg 3rcak

4. Halfunctions Scenarios (both a.

b.

T.4.5.3.12 - Failure of RHR Shutdown CoolingT.

Flow Control Valves)

c. T.4.5.3.14 - Recirculation Pump Seizure d.

T.4.5.3.16 - Recirculation Pump Shaft Shear

e. T.4.3.3.32Evaluation

- Evaluation Malfunction Halfunction Scenario #6 Scenario #7 T.4.5.3.33 f.

g. T.4.5.3.34 Evaluation Halfunction Scenario #8 T.4.5.3.35 h.
i. Evaluation Malfunction Scenario #9T

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/ ibrry Nuclear 1P:v;r Plcnt'Simulctori

Four_Yccr.Tcst Raport

, - Attachment l' JPage 4 ofl5<

Four Year Test Schedule C. Year 3 (July.-1997-through June 1998)-

1.- Core. Performance Tests

a. T.4.2.3 - Core Thermal Power vs. Recire Flow Test.
b. T.4.2.4'- Core flux Response to Rod Movement

'2. Normal Plant Evolutions

a. T.4.3.4 - Power Decrease to Turbine / Generator Unloaded
3. Transient Tests
a. T.4.5.1.06.ED06 - Loss of 480V Bus
b. T.4.5.1.09.FWO2 .Feedvater System Pipe Break Inside Dryvell
c. T.4.5.1.15.MC01 - Condenser Air Inleakage
d. T.4.5.1.17.NM03 - LPRM Detector. Failure
e. T.4.5.1.21.RD03 - Control Rod Drift - In
f. T.4.5.1.25.SWO1 - Nuclear Closed Cooling System Process-Piping Leakage ~
g. T.4.5.1.27.TH2O - RPV Level Inst Variable Leg Break
4. Malfunctions Scenarios
a. T.4.5.3.12 - Failure of RHR Shutdown Cooling
b. T.4.5.3.13 - Recirc Flow Control Failure-decreasing (both Flow Control' Valves)
c. T.4.5.3.14 - Recirculation Pump Seizure
d. T.4.5.3.16 - Recirculation Pump Shaft Shear-
e. T.4.5.3.32 - Evaluation Malfunction Scenario #6
f. T.4.5.3.33 - Evaluation Malfunction Scenario #7
g. T.4.5.3.34 - Evaluation Malfunction Scenario #8
h. T.4.5.3.35 - Evaluation Malfunction' Scenario #9
1. T.4.5.3.36 - Evaluation Malfunction Scenario #10
  • / Pcrry Nucl:Cr P v:r Plcnt Siculator '

F;ur Y;;r Tcst R: port

' Attachment 1

,Page 5 of 5 Four Year Test Schedule D. Year 4 (July 1998 through June 1999)

1. Core Performance Tests
a. T.4.2.6 - Core Suberitical Hultiplication Test
b. T.4.2.7 - Reactor Core Life Test  ;
c. T.4.2.8 - Shutdown Margin Demonstration
2. Normal Plant Evolutions
a. T.4.3.5 - Plant Cooldown to Cold Shutdown ,
3. Transient Tests e
a. T.4.5.1.06.ED09 - Loss of 125V DC Bus
b. T.4.5.1.09.FV03 - Feedvater System Pipe Break Outside '

Containment

c. T.4.5.1.16.HS11 - Steam Seal Header Pressure Regulator Failure  ;
d. T.4.5.1.17.NM10 - Neutron Monitoring Detector Drive Stuck
e. T.4.5.1.21.RD04 - Control Rod Drift - Out
f. T.4.5.1.25.SV02 - Service Water system Process Piping Leakage  !
g. T.4.5.1.27.TH21 - Pover/ Flow Instabilities (IEB 88-07 Supplement 1)
4. Halfunction Scenarios '
a. T.4.5.3.17 - Recire Flow Control Failure-increasing (both !

Flow Control Valves) ,

b. T.4.5.3.18 - Control Rod Drop Accident ,
c. T.4.5.3.19 - Inadvertent High Pressure Core Spray Startup i
d. T.4.5.3.20 - Anticipated Transient Without Scram (ATVS)
e. T.4.5.3.21 - Loss of Off-Site Power
f. T.4.5.3.37 - Evaluation Halfunction Scenario #11
g. T.4.5.3.38 - Evaluation Malfunction Scenario #12
h. T.4.5.3.39 - Evaluation Malfunction Scenario #13
1. T.4.5.3.40 - Evaluation Halfunction Scenario #14 ,
j. T.4.5.3.41 - Evaluation Halfunction Scenario #15
k. T.4.5.3.42 - PEI Halfunction Scenario #5 (part 2) 7

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l NRC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION APPROVED LY Out: NOatse4us  !

I EXPtRES: 10/31/95 ESTIMATED GLfmEN PER FIESPONSE TO COMPLY WITH THIS  !

- INFORMATION COLLECTION REQUEST: 120 DOURS. FORWARD SIMULATION FACILITY CERTIFICATION * '"

""n'"'8 "Jo*E" m*"*oRuMT"^A L"4,"u'I Tm"f5

,E w I FEGULATOFW COMMISSION. WASHINGTON, DC 205550001, AND TO THE PAPERWORK HEDUCTION PRCLIECT (31504138) OFFICE OF MANAGEMENT AND OUDGFT, WASHNGTON, DC P0503 WISTRUCTIONS: This form is to be II6ed for inthat costecahon, sacertmcation $lt requiredh and for ariy change to a simuishon factiety performance testmg plan made after innial submntal of

. uni e pian. Prowie me fono ing warmeon and ch.cn in. appronn e so, to inden. mason for submme '

FACILRY

  • DOCKET NUMBEH  !

Perry Nuclear Power Plant, Unit No. 1 50- 440 uCENsEE '

oATE Cleveland Electric Illuminating Co. and Centerior Service Co. , et. al. 06/28/95 This in to certWy that I

1. The above named IncNity licensee is using a aamulahon facHfly consMhng sole 4y d a plan 64eferent.ed simulator that meets the sequirements of 10 CFR 55.45.

S. h l is available for NRC review in accordance with 10 CFR 55.45(b).  ;

8. This ownuission facilNy meets the guidance contamed in ANSI /ANS 3.5,1985, en endorsed by NFIC Regulatory Guide 1.149. I f there are any ENCffrTIONS to the seetthcahon of this item, CHECK HERE l ] and descetbo fully on additional pages as necessary .

1 NAME (or amar adoneScapon) AND LOCATION OF SIMULATION F ACluTY, i Perry Nuclear Power Plant Unit 1 Simulator' 10 Center Road i Perry, OH 44081 i SIMULATION FACIUTY PLHFORMANCE TEST ABSTRACTS ATTACHED. (Fwpedbrmance nests sonducted h me pened erming walm me date of me cerescaport)

DEurmVN OF PERFOHMANCE TESTNG COMPLETED. (Arrects addeoriW pages as neceuwy and Mentify me #em desenpean bomp cwenued)

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sSAUULTION FACUTY PEFFORMANCE TESTNG SCHEDULE AITACHED. (For me conduct of w _ ', 2r of pwArmenoe ress pw yer Ar me bur-yew pwdod commencey we X me one of e. .wenceowi)  ;

DESCHIPTION OF PEHFOHMANCE TESTING 10 BE CONOUCTED. (Nrach addeonadpages as necessay and Adenot the Aem descitpoon borng oononued) t See attached report.  !

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PEFFORMANCE TESTING PLAN CHANGE. (For any snodAcaban so e podbamance sesong plan submmed on a prevfois esieAcaport)

DESGWHON OF PEFFOHMANCE TESTNG PLAN CHANGE (Afrech addeonet pages as necesswy and Metery me #em descappan being cononued) I I

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FECERTIV1 CAT 10N (Desenbe correchve arbons takm drach resuRs of compieredperformance teskngin accordance wsm to CFR SS 4S(b)(S)(4 (Anach addeornpagne as recessary and Morely me #em descnpoon kemy carenued)

Any tense stwemem or _ en then cocument, includmg anachments, may be subsect to esvu and snmmes sanctions, a cenny under penetty of pertory that the information m thes document and after ms a true and correct.

suNATum U wpno numcNT inu. DaiE

/'M - Senior Vice President, Nuclear 06/28/95 On acc breence afth to Cl H 55.b, communications, ttus form shen be submmed to the NHC as folk 1ws:

BY Mall ADDFELSED 70- DIRECTOR, OFFICE OF NUCLEAR REACTOR REGULATION BY DELNERY N PERSON ONE WHITE FEINT NORTH U.S. NUCLEAR REOULATORY COMMISSION 10 THE NRC OFFICE AT. ItSSS ROCKVILLE PIKE UrASHINGTON DC 2cS$54 cot ROCKVILLE, MD NIC FOl#A 474 (to B2l PHINTED ON HE CYCL E D PAPER

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