ML20209B339

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Simulator Four Yr Test Rept
ML20209B339
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 06/28/1999
From:
CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20209B330 List:
References
NUDOCS 9907060386
Download: ML20209B339 (8)
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, j June 28,1999 Perry Nuclear Power Plant Simulator Four Year Test Report Introduction i ne Perry Nuclear Power Plant (PNPP) Simulation Facility Certification was submitted to the Director, Office of Nuclear Reactor Regulation on June 28,1991 and supplemented with an additional report on December 6,1991. This report is being submitted in accordance with 10 CFR 55.45(b)(5)(ii) on the eighth anniversary of the Certification <

Submittal. This is our second four-year test report. I 1

This report describes performance testing conducted on the simulation facility from June 1995 through June 1999, discusses performance test failures and discrepancies during the same period, and provides a schedule for performance testing for the period June 1999 through June 2003.

De Simulator is located at the Peny Nuclear Power Plant, operated by the I irstEnergy Nuclear Operating Company in North Peny Village, Ohio, approximately 35 miles northeast of Cleveland, Ohio. De simulator vendor was S3 Technologies Company of Columbia, MD. He reference unit, PNPP Unit 1, consists of a General Electric Boiling Water Reactor (BWR/6) rated at 3579 MWIh.

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

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

Performance Tests Conducted June 1995- June 1999 Performance tests for the PNPP Unit 1 Simulator were completed per the schedule included in the previous Test Report, with the following exception. Eight tests beginning with "T.4.2", titled " Core Performance Tests" were removed from the performance test cycle to reduce person-hours spent on unnecessary activities. No rimulator related codes or standards require these tests be performed on an annual or periodic frequency.

In a few instances, tests were carried over to a subsequent testing period due to simulator and personnel scheduling conflicts in order to support needed PNPP Training Programs. In those cases, the affected tests were performed early in the subsequent period and prior to regularly scheduled tests. Rescheduling of tests continues to support the intent of performing approximately 25% performance testing per year.

All scheduled tests with the exception of the eight tests discussed above have been completed.

Performance Test Discrepancies June 1995 - June 1999 Discrepancies documented during Performance Tests were categorized as minor and major. Minor discrepancies are l

those that do 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, resulting in a test failure.

Here are five minor discrepancies, discovered during the conduct of Simulator performance testing during this reporting period, which remain to be corrected. nese discrepancies are documented in Simulator Discrepancy Packages (SDP). A description of the Simulator Dis::epancy Package program is contained in our initial certification submittal. Additional details regarding these discrepancies or the modification program are available upon request.

Uncorrected test failures are as follows:

9907060386 990628 PDR ADOCK 05000440 P PDR

. Perry Nuclear Power Plant Simulator Four Year Tcst Report June 28,1999 Page 2 0f 2

1. Test T.4.4.2.8, Maximum Size LOCA With Loss Offsite Power, performed on 5/3/99. He thermal-hydraulic model experienced instability during the rapid (Iow pressure) reflood of the reactor vessel following the initial blowdown stage of the LOCA.
2. Test T.4.5.1.27.TII01, System L.evel Failures - DBA Loss of Coolant Accident, performed on 9/25/95. Water l

level in the in-core region of reactor vessel did not remain higher than the level of the jet pump throat, or 50 i inches below the top of active fuel, during the reflood stage, as predicted by USAR analysis.

3. Test T.4.5.3.42, Malfunction Scenario - Scenario #5, Part 2, performed on 5/14/99. This scenario exercises PEI B13 (ATWS) with a loss of level indication and control rods stuck out, forcing the crew to emergency l depressurize and then flood the reactor vessel. During the flooding stage, the reactor goes critical and power i rises rapidly. During the test, the thermal-hydraulic model failed causing a simulator halt when power rose above the source range. j The above referenced failures are related to the reactor vessel thermal-hydraulic model. A decision whether or not to replace this model will be made by December 31,1999.

Correction of Previousiv Reported Test Failures i

In June of 1995, two uncorrected test failures were reported.

1. Test T.4.4.1.1,25% Power lleat Balance, performed on 2/20/95, did not rocet the 2% steady state criteria for two critical parameters: turbine output and final Feedwater temperature. 4
2. Test T.4.5.3.20, USAR Analyzed Accident Anticipated Transient Without SCRAM (ATWS) 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.

These failures have been corrected. Test T.4.4.1.1 was performed satisfactorily on 6/20/96 and Test T.4.5.3.20 was performed satisfactorily on 12/1/95.

Performance Test Schedule June 1999 - June 2003 (includine Description of Performance Testine Plan Chanee)

The content of the Perry Simulator performance test schedule for the following four years is contained in 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.

The test schedule varies from the one submitted in the June 1995 test report with the deletion of eight tests rmmbered T4.2.1 through T4.2.8, titled Core Performance Tests. Otherwise, the schedules are the same.

COMMITMENT ne above referenced failures are related to the reactor vessel thermal-hydraulic model. A decision whether or not to replace this model will be made by December 31,1999.

END OF REPORT

I Perry Nuclear Power Plant Simuletor t Four Year Test Report June 7,1999 Attachment i Page1of5 Four Year TestSchedule Below is the list of the performance tests that are conducted annually. Pages 2 through 5 list (by year) the tests that will be conducted in years I through 4 after filing this report. These schedules represent performance of approximately 25% of performance tests per year.

1.0 ANNUAL TESTING A. Computer Realtime Test

1. T.2.7.1 - Spare Time Verification B. Steady State Performance Tests 1 J
1. T.4.4.1.1 - 25% Power Heat Balance
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 C. Benchmark Transient Tests l
1. T.4.4.2.01 - Manual Scram
2. T.4.4.2.02 - Simultaneous Trip of All Feedwater Pumps J
3. T.4.4.2.03 - Simultaneous Closure of All MSIVs l
4. T.4.4.2.04 - Simultaneous Trip of All Recirc Pumps
5. T.4.4.2.05 - Single Recirc Pump Trip l
6. T.4.4.2.06 - Main Turbine Trip without Reactor Scram
7. T.4.4.2.07 - Maximum Rate Power Ramp (100% - 75% - 100%)
8. T.4.4.2.08 - Maximum Size LOCA with Loss of Offsite Power
9. T.4.4.2.09 - Maximum Size Unisolabls Main Steam Line Rupture
10. T.4.4.2.10 - Simultaneous Closure of MSIVs with Single Stuck Open Safety / Relief Valve

', '. Perry Nuclear Power Plant Simuhtor

  • Four Y6ar Test Report June 7,1999 Attachment i Page 2 of 5 Four Year TestSchedule 2.0 PERIODIC TESTING i

A. Year 1 (July 1999 through June 2000)

1. Normal Plant Evolutions
a. T.4.3.1 - Cold Shutdown To Reactor Critical
b. T.4.3.2 - Reactor Critical To Turbine Synchronized {

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2. 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.lA01 - Air Receiver Leak
d. T 4.5.1.17.NM01 - SRM Detector (pre-amp) Failure
e. T.4.5.1.18.OG03 - 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 l 1

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3. Malfunction Scenarios
a. T.4.5.3.01 - Loss of Feedwater Heating (RRFC In Auto)
b. T.4.5.3.02 - Loss of Feedwater Heating (RRFC in Manual)
c. T.4.5.3.03 - Feedwater Controller Failure-Maximum Demand
d. T.4.5.3.04 - Pressure Regulator Failure-Open
e. T.4.5.3.22 - PEI Malfunction Scenario #1
f. T.4.5.3.23 - PEl Malfunction Scenario #2
g. T.4.5.3.24 - PEl Malfunction Scenario #3
h. T.4.5.3.25 - PEI Malfunction Scenario #4

, . Perry Nuclear Power Plant Simulator

'Four Year Test Report June 7,1999 Attachment i Page 3 of 5 Four Year TestSchedule B. Year 2 (July 2000 through June 2001)

1. Normal Plant Evolutions
a. T.4.3.3 - Power increase To 100% Power
2. Transient Tests
a. T.4.5.1.04.CUO3 - Reactor Water 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.lA02 -Instrument Air Line Leak
d. T.4.5.1.17.NM02 - IRM Detector (pre-amp) Failut e
e. T.4.5.1.18.OG04 - Off Gas System Leak Downstream Adsorbers
f. T.4.5.1.23.RP02 -Inadvertent Initiation of Altemate 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
3. Malfunction Scenarios
a. T.4.5.3.05 -Inadvertent Safety Relief Valve Opening l
b. T.4.5.3.06 -Inadvertent RHR Shutdown Cooling Operation
c. T.4.5.3.07 - Pressure Regulator Failure-closed
d. T.4.5.3.08 - Generator Load Reject With Bypass Valves
e. T.4.5.3.09 - Generator Load Reject Without Bypass Valves
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)
1. 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 l

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'. Perry Nuclect Power Plant Simulator l

  • Four YearTest Report June 7,1999 Attachment 1 Page 4 of 5 Four Year TestSchedule .

l C. Year 3 (July 2001 through June 2002)

1. Normal Plant Evolutions
a. T.4.3.4 - Power Decrease to Turbine / Generator Unloaded
2. Transient Tests
a. T.4.5.1.06.ED06 - Loss of 480V Bus
b. T.4.5.1.09.FWO2 - Feedwater System Pipe Break inside Drywell
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.SWD1 - Nuclear Closed Cooling System Process Piping Leakage I
g. T.4.5.1.27.TH2O - RPV Level Inst Variable Leg Break
3. Malfunction 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

. '. Perry Nuclear Pow:r Plant Simul: tor

  • Four Ysar Test Report June 7,1999 Attachment i Page 5 of 5 Four Year TestSchedule D. y,,ggr 4 (July 2002 through June 2003)
1. Normal Plant Evolutions
a. T 4.3.5 - Plant Cooldown to Cold Shutdown
2. Transient Tests
a. T.4.5.1.06.ED09 - Loss of 125V DC Bus
b. T.4.5.1.09.FWO3 - Feedwater System Pipe Break Outside Containment
c. T.4.5.1.16.MS11 - 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.SWO2 - Service Water System Process Piping Leakage
g. T.4.5.1.27.TH21 - Power / Flow Instabilities (IEB 88-07 Supplement 1)
3. Malfunction Scenarios
a. T.4.5.3.17 - Recirc 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
d. T.4.5.3.20 - Anticipated Transient Without Scram (ATWS)
e. T.4.5.3.21 - Loss of Off-Site Power
f. T.4.5.3.37 - Evaluation Malfunction 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 Malfunction Scenario #14 J. T.4.5.3.41 - Evaluation Malfunction Scenario #15
k. T.4.5.3.42 - PEI Malfunction Scenario #5 (part 2)

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NRC FORM 474 U.S. Nubt. EAR REGULATORY COMMISSION APPa0VED UY oso NO. aleoase ExPoxES: catsisi-

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- $20 ed -- p-- = compe, won.as,m,y Ts.mf onau d a s.t , rnu ce, wo,rn.t o,i ,co t.on f.c F ecta w.,d com,nenis m no bu,oen -t.n e e ine wo,m on .nd Rec.ds M-SIMULATlON FACILITY CERTIFICATION ""F*"'"8""'*""**d"" C""**** *"*"8'm x 205s 0001, wid to the Paperwork Reducts Prg'ect (31504138), Othee of Management and Budget, Washmgtm DC 20603 NRC may not conduct or spons., and a person a nos rowered to respond to, a conectm of mformatson tridess 11 esplays a currently weled OM6 control tsariber 4NSTRUCDONS: ins kvm a lo be fWed for rwhal cartdcatm recartdmahan (d required), and for any change to a semdanon facshty perbrmance lesung plan made after t%el s@mettal of such a paart Provide the fonowmo rWormate and check the appropnes bom to mdicare reason for s@matal FACluTY DOCKET NUM8ER Perry Nuclear Power Plant, Unit 1 440 LICENSEE DATE FirstEnerev Nuclear Oneratine Comoany 6/28/99 The m to certdy that.

1. The atmve named facMy facensee a usm0 e sumAahon feceidy cons #stmg sobsly of a piantveferenced armAelor lhat eneers the rownements of 10 CFR 55 45 2 Documentahan a evadable for NRC review in accordance wei 10 CFR SS 45(b) 3 The somAhon facMy moons the Ouedence contamed m ANSl/ANS 3 5-1965 or ANSFANS 3 61993, es endorsed by NRC RepAarory Guide 1149 if in .e any ExCEPnON: w ine c-unc=>on of ns nom, CHECx NERE [ ] and docnb. uy on .ddd on.1 pag.s - nac.uny NAME (or other aseno6 canon) AND LOCATION OF $NULATION FACILITY.

Perry Nuclear Power Plant Unit i Simulator 10 Center Road Perry, Ohio 44081 SNULATION FACILITY PERFORMANCE TEST ABSTRACTS ATTACHED (For persbrmance fests conductedin the penod encing wth the dale v th#s cerencanon )

DESCRIPTION OF PtRFORMANCE 1ESilNG COMPLETED. (Attacn ecnDonalpages as necessary andmonely itie nom descnpDon Denng conenved.)

SIMULATION FACl4 HY PERFORMANCE TESTING SCHEDULE ATTACHED (For the conduct #appronometely 25'dperibemance tests peryearIbr the1 bur-year penod U commencung wth the date d thes cer6Rcahon)

DESCHIPTION OF PtRFORMANCE TESTING 10 BE CONDUC1ED gAttach a@honalpeges as necessary end edennty the dem descnp00n benng Conhnved)

See attached report.

PERFORMANCE TESTING PLAN CHANGE. (For any motstWahon to a pertbemance teshng plan submrtled on a prevsous ce4Rcanon)

DESCRIPTION OF PERFORMANCE ILSTING PLAN CHANGE (Attach acnhonalpages as necessay and menefy the rtem descnpoon Deng canonued)

See attached report.

RECERTIFICATION (Descnbe conoceve schone taken, attach results of compMtedpersbemance teshng m accontrance wth 10 CFR SS 45(b)(5)(v).

(A!!ach adattsonalpages as necessay and Menhty the trem descnpbon berr'g conhnved)

(my falso stai . ; or omiasson in tNa document, inclueng awwents, may be sutaect to cml and enminal sanctions I certdy unoer penalty of perjury inat the mformenon m he dctument and attachments a true and correct SIGNA RE - AUTHORIZED REPRESENTATIVE TITLE DATE YiCe President - Nuclear 6/28/99 en w; nh to CFR 65 6, commisap hs form shan be submitted to ine NHC es fonows 8Y DELfVERY IN PERSON ONE WHITE FLINT NORTH BY MAIL ADORESSED TO DIRECTOR, OFFICE OF NUCLEAR REACTOR REGULATION TO THE NRC OFFICE AT 11668 ROCKVILLE PtKE U.S. NUCLEAR REGULATORY COMMtSS40N ROCKVILLE, MD WASHINGTON, DC 206464001 NRG FUHM474 (5-95)

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