ML20094E144
| ML20094E144 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 05/10/1995 |
| From: | Mervine M VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| BVY-95-50, TDL-95-07, TDL-95-7, NUDOCS 9511070084 | |
| Download: ML20094E144 (10) | |
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y VERMONT YANKEE NUCLEAR POWER CORPORATION Ferry Road, Brattleboro, VT 05301-7002 May 10,1995 BVY 95-50 TDL 95-07 (8o2) 257-5271 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 194%
References:
(a) 10 CFR 55.5
Subject:
Simulator Facility Certification in accordance with the provisions of 10 CFR 55.5, attached is a four year update for the certification of the Vermont Yankee Simulator.
If you have any questiorts, please call me at (802) 258-4153 or E-mail - mervine@ yankee.com.
Sincerely,
~
A -.-
Mark L. Mervine Training Manager Attachment c:
Document Control Desk - Washington, DC USNRC Project Manager - VYNPS USNRC Resident inspector - VYNPS (Without Attachment) 9511070004 950510 PDR ADOCK 05000271 P
PDR l
NRC FORM 474 U.S. NucWAR REGLAATORY COMMISSION AP N ED BY W R NO.3 N t3e (14t2)
O EST!MATEO SURCEN PER RESPONSE TO COMPLY WITH THis AFORMATION Cot.LECTION REQUEST.
120 HOURS.
F08tWARO SIMULATION FACluTY CERTIFICATION c""'"'8"'*"**"""*'"58"^
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RECOAOS MANAGEMENT SRANCH iMN88 77tal, US NUCLEAR REGULATORY COMutS$ON. WASHINGTON, OC 206$5M1, ANO TO THE PAPERWORK REOUCTION PRCLJECT (3150 0138), C#FiCE OF MANAGEMENT l
ANO SUOGET. WASHINGTON. OC 20503.
DEITRJCTIONS: That form to to ee fued har mes ceMcum, rueMcmion pf regt.pred), and for any cnange to a tenulation facdoty performar.co test.ng plan made aner enstlei suomdtas of
.,.a a oian. P,onde m. fono.ng meermne and en.c me aco, conn. som ediese recon h>r suom.nm.
FACIUTY OOCKET NUMBER Vermont Yankee Nuclear Power Station 271 UCENSEE OATE Vermont Yankee Nuclear Power Corporation 4/19/95 Thrs a to ceey mat:
1.
The noo,e named facddy scenue e useg a manutate facety conosteg soisy of a piant reweeced smusmor mm meets the requiremones of to CFR !$.a5.
- 2. Occumerwatson e avalacie for NRC rewow in accordance with to CFR SS aSte).
1 Thee serpulate Pacddy mees me gunoance contained e ANSU ANS3.5,1985,as endorsed by NRC Regulatory Gusde 1.149.
v me...e ey earnONs to me c.ecs on ce m.s n.m. cacx mm [ ] ed desene. uy on addeone pages a n.cosuy.
NAME for over nrenascace) ANO LOCAT10N OF SMULATON FACIUTY, Vermont Yankee Training Center Ferry Road Brattleboro, Vermont 05301 SMULATION FACIUTY PERFORMANCE TEST ABSTRACTS ATTACHEO. (For pelormance tears conducted et me pened endmg we me date of e e carencaoortJ y
csSCaeTiON OF PERFORMANCE TESTWo COuetETEO. snach easema nese a neceany and,d-et me am duensee e.ng connueas Performance Testing Completed - See Attachment 1 of this Report
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X ee due et em cereneseat>
OESCRPTION OF PERFORMANCE TESTWG TO SE CONOUCTED. pason adeeone pages as necessey eso sowery ee stern oncopoon bemy conenved)
Performance Testing Scheduled - See Attachment 2 of this Report PERFORuucE TESTWo pun CHANoE. (For =>y mediacaeon to a ner*>rmane ses>mp anari suerr tred on a areacus cereacaeorti GISCRPTION OF PERF0F%tANCE TESTWO PLAN CHANGE Maaca addreens pages as necessay awf sceno4 ee esen desenpoon ces conenved)
Not Applicable RECERT1FDCAT10N (Deacnee correcove aceans taken anach resuMs of cometeredpe,formance reseng m accorda,ce we 90 CFR $$ 4S(b)(S)M paan adeoons o.gu a necouay and,de,n ee em ducnoeon se,ng conenved>
Any rose um.mem or omisson a m.s docuenent, eciudeg anacnteents, may e. sveiece to ca,n and comem sanctions I catey under penany at pequry mm in informeion m mm document and attaenments is true and correct.
SIGNATURE - AUTHORZEO REPRESENTAnvE TITLE DATE 3,
Training Manager y gg
/
p Vermont Yankee Nuclear Power Corp in accoreance.[ lo CFR SS S. Cornmunicahons. mes form snad te submstted to me NRC as fonows:
SY MM. AOORESSEO TO-DIFECTOR, OfTICE OF NUCLEAR FEACTOR FEGULATION SY OEUVERY W PERSON ONE wtWTE FLNT NORTH U.1 NUCLIAR FEGLA.ATORY rmaeterw TO THE NRC OFcCE AT:
115e6 FOCKW1E PME WASHINGTON, DC 2cessmot ROCKW1E, MD NycpoRu474 0 0-921 PRNTEO ON RECYCLEO PAPER
VERMONT YANKEE PLANT SIMULATOR FOUR YEAR CERTIFICATION REPORT I.
Introduction i
The Vermont Yankee Plant Four Year Certification Report is a supplement to the Simulation Facility Certification form (NRC Form-474), the Simulator Annual Certification Report, and Simulator Administration Procedures. This report briefly provides a description of the simulator, a summary of past four years performance testing and an outline of performance testing to be performed during the next four years. Additional information concerning specific tests is available upon request.
II.
References
- Title 10, Code of Federal Regulations, Part 55, " Operators' Licenses."
- ANSI /ANS 3.51985 American Nuclear Society " Nuclear Power Mant Simulators for use in Operator training."
- U.S. Nuclear Regulatory Commission Regulatory Guide 1.149, April 1987
" Nuclear Power Plant Simulation Facilities for use in Operator License Examinations."
III. Simulator Information Simulator Type:
Reference Plant Simulator Manufacturer:
Singer Link Company Owner / Operator:
Vermont Yankee Nuclear Power Corp.
Reference Plant:
Vermont Yankee Plant Location:
Vernon, Vermont Plant Type:
Boiling Water Reactor Plant Rating:
1593 MWth Date Ready for Training:
March 6,1986 Type of Report:
Four Year Certification
VERMONT YANKEE PLANT SIMULATOR
~
FOUR YEAR CERTIFICATION REPORT (Continued)
IV. Simulator Procedures The Simulator is controlled, operated, tested and modified utilizing the following procedures:
Simulator Administrative Procedures Vermont Yankee Plant Operating Procedures Vermont Yankee Training Department Directives V. Simulator Design Database Controlled drawings, wiring diagrams and plant procedures are used as a bases for logic and system flow calculations. The plant setpoint change requests and design changes are also used as inputs for the Simulator data base. Plant data from logs, charts and the process computer are used when ever possible to compare actual plant data to simulator data, ensuring that the simulator data base closely matches the plant. Feedback from Licensed Plant Operators and the Operations Training Group, using the Simulator Configuration Management system, is an essential part of maintaining the simulator up-to-date with the plant.
VI. Major changes to the simulator environment since the last report Facility Environment Channes:
Simulator Instructor Station booth and Instructor Interface replacement.
Complete replacement ofInstructor Station hardware and software with user friendly graphicalinterface.
Back panel emergency lighting added.
Back panel overhead emergency lighting added to enhance Simulator fidelity during loss of AC power conditions.
VERMONT YANKEE PLANT SIMULATOR FOUR YEAR CERTIFICATION REPORT (Continued)
Simulation Sonware Changes:
Primary Containment Complete model replacement. Installation of a 31 node containment model replacing original 3 node model providing a more detailed and realistic response to accident conditions.
Secondary Containment Complete model replacement. State of the art multi-nodal containment model replacing original single node model. Providing a more realistic response to malfunctions in the Secondary Containment.
I
- Annunciators Code rewritten in FORTRAN and enhanced Simulator Operating Systems Encore MPX and S3 software upgraded Simulator Instructor Station Sonware upgrade VII. Documentation The results of the annual simulator testing are documented in the Annual Simulator Testing Report and is maintained on site. The Report contains the information required in ANSI /ANS-3.5, Nuclear Power Plant Simulators for use in Operator Training.
l VERMONT YANKEE PLANT SIMULATOR l
FOUR YEAR PERFORMANCE TEST ABSTRACT (ATTACHMENT 1) 191 1.
1.
ANSUANS 3.5 Bl.1 Startup, Shutdown and Steady State Tests l
2.
ANSUANS 3.5 3.1.1 Normal Plant Evolutions l
~ 3.
ANSUANS 3.5 4.3 Simulator Operating Limits 4.
ANSUANS 3.5 bl.2 Transient Performance Tests 5.
Computer Real Time Verification 6.
ANSUANS 3.5 A3.4 Malfunction Tests No uncorrected performance failures remain from the 1991 certification testing.
1992 1.
ANSUANS 3.5 Bl.1 Startup, Shutdown and Steady State Tests 2.
ANSUANS 3.5 3.1.1 Normal Plant Evolutions 3.
ANSUANS 3.5 4.3 Simulator Operating Limits 4.
ANSUANS 3.5 bl.2 Transient Performance Tests 5.
Computer Real Time Verification 6.
ANSUANS 3.5 A3.4 Malfunction Tests No uncorrected performance failures remain from the 1992 certification testing.
i 19 2 9
1.
ANSUANS 3.5 Bl.1 Startup, Shutdown and Steady State Tests 2.
ANSUANS 3.5 3.1.1 Normal Plant Evolutions 3.
ANSUANS 3.5 4.3 Simulator Operating Limits 4.
ANSUANS 3.5 bl.2 Transient Performance Tests l
S.
Computer Real Time Verification 1
6.
ANSUANS 3.5 A3.4 Malfunction Tests No uncorrected performance failures remain from the 1993 certification testing.
a
VERMONT YANKEE PLANT SLMULATOR FOUR YEAR PERFORMANCE TEST ABSTRACT (ATTACHMENT 1 CONTINUED) 1994 1.
ANSUANS 3.5 Bl.1 Startup, Shutdown and Steady State Tests 2.
ANSUANS 3.5 3.1.1 Normal Plant Evolutions 3.
ANSUANS 3.5 4.3 Simulator Operating Limits 4.
ANSUANS 3.5 bl.2 Transient Performance Tests 5.
Computer Real Time Verification 6.
ANSUANS 3.5 A3.4 Malfunction Tests No uncorrected performance failures remain from the 1994 certification testing.
l l
VERMONT YANKEE PLANT SIMULATOR FOUR YEAR PERFORMANCE TESTING SCHEDULE (ATTACHMENT 2)
Each year the following tests will be performed:
1.
ANSUANS 3.5 Bl.1 Startup, Shutdown and Steady State Tests a.
Startup from cold to rated power b.
Shutdown to cold conditions from rated power c.
Recovery from plant Scram to rated power d.
Critical (Heat Balance) and non-critical data comparisons at three power levels e.
One hour stability test 2.
ANSUANS 3.5 3.1.1 Normal Plant Evolutions a.
Safety Related Systems Surveillances 3.
ANSUANS 3.5 4.3 Simulator Operating Limits a.
Simulator Out of Limits Test 4.
ANSUANS 3.5 bl.2 Transient Performance Tests i
a.
ANSI Bl.2(1)
Manual Scram b.
ANSI Bl.2(2)
Simultaneous Trip Of All Feedwater Pumps c.
ANSI Bl.2(3)
Simultaneous Closure Of All Main Steam Isolation Valves d.
ANSI Bl.2(4)
Simultaneous Trip Of All Recire Pumps e.
ANSI Bl.2(5)
Single Recirculation Pump Trip f.
ANSI Bl.2(6)
Main Turbine Trip
VERMONT YANKEE PLANT SIMULATOR EOUR YEAR PERFORMANCE TESTING SCHEDULE (ATTACHMENT 2 CONTINUED) g.
ANSI Bl.2(7)
Maximum Rate Power Ramp h.
ANSI Bl.2(8)
Reactor Coolant System Rupture i.
ANSI Bl.2(9)
Maximum Unisolable Main Steam Line Rupture j.
ANSI Bl.2(10)
Simultaneous Closure of All Main Steam Isolation Valves with a Stuck Open Safety Relief Valve 5.
Computer Real Time Verification 6.
ANSI /ANS 3.5 A3.4 Malfunction Tests All mafunctions will be tested in a four year cycle at approximately 25% of a.
all malfunctions per year. The following identifies the system malfunctions to be tested during that year:
1995 1996 ANNUNCIATORS (AN)
CORE SPRAY (CS)
RWCU (CU)
TURBINE (TU)
INSTRUMENT AIR (IA)
PRIMARY CONTAINMENT (PC)
RHR(RH)
MAIN STEAM (MS)
TURBINE CONTROL (TC)
NUCLEAR MONITORS (NM)
ELECTRICAL DIST (ED)
CONTROL RODS (RD)
REACTOR RECIRC (RR) 1997 1998 AUTO DEP SYS (ADS)
ROD CONTROL (RM)
DIESEL GENERATORS (DG)
ROD WORTH MIN. (RW)
REACTOR PROTECTION (RP)
ROD WORTH (RX)
MAIN GENERATOR (EG)
MAIN CONDENSER (MC)
RCIC (RC)
OFF GAS (OG)
CONDENSATE (CD) l l
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t Vermont Yankee Simulator Testing I
i FOUR YEAR CERTIFICATION TESTING PLAN i
l FEBRUARY l BAARCH l
APRIL l
BAAY l
JUIGE l
l AUGUST SEPTEleSER OCTOBER NOVERESER l OECEtt8ER JANUARY JULY
,=
l MALFUNCTION TESTING HEAT BALANCE AND NORMAL OPERATIONS TRM4SIENT AND REAL-TME TESTING I
PREPARE ANNUAL REPORT CONTROL ROOM VERIFICATION l
l t
i 1
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