2CAN128704, Certifies That Plant Consists Solely of plant-ref Simulator as Defined in 10CFR55.4 & Meets NRC Regulations.W/Nrc Form 474,exceptions Taken to Ansi/Ans 3.5-1985,performance Test Abstract & Description of Scheduled Performance Testing
| ML20147C578 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/07/1987 |
| From: | James M. Levine ARKANSAS POWER & LIGHT CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20147C583 | List: |
| References | |
| 2CAN128704, NUDOCS 8801190281 | |
| Download: ML20147C578 (5) | |
Text
("[1 ARKANSAS POWER & LIGHT COMPANY December 7, 1987 2CAN128704 Mr. Thomas E. Murley Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Certification of Unit 2 Simulation Facility
Dear Mr. Murley:
In accordance with 10 CFR 55.45.b.5, Arkansas Power & Light Company here9y certifies to the Commission that t.be ANO Unit 2 Simulation Facility consists solely of a plant-referenced simulator as defined in Part 55.4 and meets the Commission's regulations. NRC Form 474, Simulation Facility Certification, including the exceptions taken to ANSI /ANS 3.5-1985, a performance test abst.ract and a description of scheduled performance (operability) testing are attached.
Sincerely, d'
- y. M.
evine Executive Director ANO Site Operations JML/WEP:djj Attachments cc:
Mr. T. G. Campbell w/Att.
Mr. E. C. Ewing w/Att.
Mr. D. R. Howard w/Att.
Mr. R. Martin (hTC) w/Att.
Mr. G. Dick (NRC) w/Atte r
ANO-DCC w/Att.
@l, 8801190281 071207 PDR ADOCK 05000368 y
PDR P
I (
PAEPAGE F4 PALDOtt SOUTH UTIL ; TIES SYSTF*A
s
- r N/.C comu 474 U S. NUCLE AR REQULATORY COseMIE810N iso ( 9 Approvee av OMe
!M's"eW" SIMULATION FACILITY CERTIFICATION IMeh INSTRUCTIONS. This form is to be feled for initial certification, recertif<ation hf required), and for any change to a simulation facility performance testing plan made af ter enitial submittal of such a plan. Provide the following information. and check tne approoriate box to indicate reason for submittal.
F ACILIT Y DOCK E T NUM O E R Arkansas Nuclear One - Unit 2 54368 LICE NSE E DATE Arkansas Power & Licht COrnanv 12/08/87 TNe e io cena shes i me snow aemed loceev trerese in wesag a emwwea recery coneseeg some, of e ensat4e*eeced emuwor thei weets me neower f
r eneevi the owsosace contenee e ANSie Ahs 3 S.1910. en voorsed ev hec Rogueiorv Gwee i 14e one 3 ocewmentaaoa o evences ear NaC revw= m acc'wate es 10 CFR ' 96 46 2 es omvet oa tecery eroence usin to CFA
- s6 einbl. N mee are ea, J
esceoiene to me cond<erea of een 2 scowe. chece **e Q eae esecree Ne on ecomene ooges se asceenery w
NAME for orner noentricate/ AND LOCATlON OF SIMULATION F ACILITY Rt. 3. Box 137G. Russellville, AR 72801 y $1MULATION F ACILITY FE R F ORM ANCE T E ST A8$T R ACTS ATT ACH E D- (For performence rests condwted en the persod enarny.pth the care or thus correfecarel O E SCRl91 ION OF FE R F 0RM ANCE T E STtNG COM9L E T E D iattach addersonalpagetsI as necouery, and roents!y the trem desenpre brong contraved)
See Attachment "ABSTRACT: Performance Test Development, Conduct and Evaluation" e
SIMUL ATIC?e F ACILliY PE Rf ORM ANCE. TE STING SCHE DULE ATT ACHED t/or the condwr o soproesoinarety 2M of performece rests per yeer ror ree tove reer persod r
X cornirencong evork rhe dare of thus cerftf<er*D4 l OESCR n9TlON OF 9E R5 0RM ANCE TESTING TO 8E CONOUCTED LAttach ecodstronetpagets) as necessery, ed noento9y the rtem orncenernon be,ng conernnc)
See Attachment "Arkansas Nuclear One, Unit 2 - Simulator Operability Test" 1
l l
l 9E R9 OR M ANCE T EST1NG 9L AN CH ANG E. IFor car raodoftatron to a performance tettmp pica submitted on a preveous certsfocatoon) l oEsCRirTuON OF FE RFORu ANCE T EsisNa 9LAN Cu ANGE tarracn add.r.onerpaarisi as naesserr. and.oer,rrir use stem orsce,ption ee.no conemusai l
l Not Applicable l
l I
l n E CE R 16 IC A f tO% (Desrrnor correc row actsons tsa en. crrach resv rs of compwreo performance testrng in sesorcrenta wth 10 CF R 4 6$ 45rost$ttvs.
o e wroone po.,wasn o, norenury og,nenr4 ene erom erscraperon twn cortron es I A rrecn r
v l
Not Applicable l
8 te7t, v oe' pewt, et se rve y inei iae.atorerai.oa.n in i r e w imew i on om*on a it i oocument..ncivom etisc ameats. m,, c4 swowet to ci..# ano cr.m.ac u etions s
.e a a
drMa**eet 8893 etteC# IPe*ii to t'we s'VI c08'oct l
SIGN ATURE AUTHORIZED REPRESENTATNE lf'fLE lDATE a
4 /d L mp Executive Director ANO Site Operations dh lei cccordance auif 10 CIh a 55 5. Comm n> cations, inis form snau be submitted to the NRC as toiiom u
Mall ADDRESSED TO. Director,0ffsee of Nuclear Reactor Regulation BY Of Live RY IN PE RSON U.S. Nuclear Regulatory Commission TO THE NRC OFFICE AT.
7920 Norfolk Aeonue Washmeton, DC 20555 Bethesda, MO
ERC871425 Rev. 12/03/87 ATTACHMENT 1 TO NRC FORM 474 EXCEPTIONS TO ANSI /ANS-3.5, 1985 i
l 1
l
ERC871425 Rev. 12/03/87 Exception 1 Section 3.1.2 contains a list of malfun tions that shall be included in the simulator and specifies in Item 12 /that the ability to uncouple rods be prcvided.
The Unit 2 Simulator does not presently have that specific capability, but our present capabilities in the area of rod malfunctions are more than adequate to provide the operators with the necessary training related to rod operation.
Exception 2 Section 4.3 states in part that "administrative controls or other means shall be provided to alert the Instructor when certain parameters ap-proach values indicative of cvents beyond the implemented model or known plant behavior".
We have identified no conditions that place the simu-lator into a configuration that is different from observed or predicted plant response under the same set of circumstances.
If such a condition is identified in the future and can't be resolved, we will provide a method of alerting the Instructor.
Exception 3 Section 3.3.2 states in part that "the systems that are operated outside the Control Room or that provide some impact to the simulator models and are necessary to perform reference plant evolutions described in 3.1.1 shall be simulated".
During the conduct of the performance test the simulator was taken from Cold Shutdown to 100% Power and returned to Cold Shutdown using approved ANO Unit 2 procedures.
The few steps that couldn't be completed were physical in nature requiring action in the plant and provide no input to the simulator.
Examples of these are:
1)
Physically racking down breakers, although in-dication in the Control Room is consistent with breaker configuration.
2)
Flushing LPSI heat exchangers.
3)
Taking vibration readings, local pressure readings and local temperature readings.
4)
Adding hydrzaine to the Condensate Systems.
These do not impact training in any way.
l We do have the capabilityaof calling up the N-9 check pro-gram (Incore Instrument Configuration Verification) and TILT-2 on the Critical Application Processing System.
2 l
ERC871425 Rev. 12/03/87 In the latter portion of the Degraded Power tab the Emergency Operating Procedure requires that plant busses be selectively unloaded by going into the plant and physically opening the individual breakers. This is designed to reduce the load that the Emergency Diesel Generator will pick up when back-feeding a non-vital 4160V bus.
The simulator is fully capable of back-
. feeding these busses.
The Electrical Distribution System models the power supplies and loads supplied by busses exactly, but we do not have the capability of opening some of the breakers on non-vital 480V motor control centers from the Simulator control console.
The impact on training is that the load on the EDG will be slightly higher than the load seen at the plant.
l l
i l
i 9
l l
3 l
-