U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5

Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5

ML20206H114
Person / Time
Site:	Clinton
Issue date:	05/05/1999
From:	Mcelwain J ILLINOIS POWER CO.
To:	NRC (Affiliation Not Assigned)
Shared Package
ML20206H116	List: ML20206H123 U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5
References
RTR-REGGD-01.149, RTR-REGGD-1.149 U-603201, NUDOCS 9905110056
Download: ML20206H114 (6)

Text

lilinois Pow r Company 8 9. ,A P.O. Box 678 Clinton,IL 61727 Tel 217 935-8881 x3900 Fax 217 935-4632 John P. McElwain Chief Nuclear Officer P@WER EUE '

An Illinova Company May 5, 1999 (

Director, Office of Nuclear Reactor Regulation 10CFR55.45 .-

U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Clinton Power Station Training Simulator E

Subject:

Certi6 cation Report Four-Year Update

t

Dear Sir:

5j In accordance with 10CFR55.45(b)(5), Illinois Power (IP) submits the enclosed four-year updated certification report for the Clinton Power Station (CPS) training simulator.

NRC Form 474, Simulation Facility Certification, is enclosed along with the I updated certi6 cation report which was developed in accordance with Regulatory Guide i-1.149 and American National Standards Institute /American Nuclear Society standard ANSI /ANS 3.5-1993, " Nuclear Power Plant Simulators for Use in Operator Training." __

The enclosed report describes the performance testing completed and provides a description of and schedule for the performance testing planned during the next four years. .-

Ifyou have any questions regarding this report, please contact J. A. Hanson, .

Director-Nuclear Training Department at (217) 935-8881, extension 3614, or M. D.

Tindill, Lead Simulator Specialist, at (217) 935-8881, extension 3978.

Sincerely yours, John P. McEl ain y

=

ChiefNuclear Officer

\

/

9905110056 990505 PDR Y ADOCK 05000461 PDR -

r n '~

U493201 !

Page 2 Enclosures cc: NRC Clinton Licensing Project Manager

. NRC Resident Office, V-690 Regional Administrator, Region III, USNRC Illinois Department ofNuclear Safety i

l

l I t **

l - - -

i NRC FORM 474 I8"I U.S. NUCLEAR REGULATORY COMMISSIOh APPROVED BY OMR: NO. 31504138 EXPIRES 08/31/2001 f

l i Estimated request 12 burden per response e comply mfwmaten vnth trus collecton mand Wu a commennr.0 h,ours The mlormatrm a used k costify aam Forward 1 ~ -

ga dma burden es=ma= = me Recena uanga g eranch (r e Fss). u S l SIMULATION FACILITY CERTIFICATION M*"m"*8"'*e'c"ib%*ei'Ai"tE'"oTn&Ei-d ada M4* 3

20503 hn m con cooiecton does n me NRC may not conduct or sponsor. ad a - a .otnoe display lim number.

a currentlyvaled required = OMB c,em.p mformahon collecbon (NSTRUCTIONS:

wn P-, ~r. This forrn a to be fded for elbal cerufcanon, fecerbficaten (d toquwed). and for any change b a rimulaton facdsty perbrmance testmg plan made l

e- .e - me .-or,,te m .ndieeio re. on for se, mew it u anittai of suon FQCiuTY Clinton Power Station, Unit No. I OOCKET NUMBER 50-461

! LEENSEE i

Illinois Power Co. DATE Theo a lo certify that 1

2 The above named facehty hLensee m usmg a semuleDon faulity consmbng solely of 8 plant referenced sNnulator that meets the seguiremm's of 10 CFR $$ 42 Drumental.on m evadable for NRC review m accordance wsth 10 CFR 55 45(b) 1 This ammtsbun *ncQty(nests the gudar.ca cedamed in ANSIIANS 3 51965 or ANSl/ANS 3 51993, endored t,y NfC Regulatory Gude 1149 ti thene ara nny ElrCEPTIONS to me certhcation of this dem CHEsa HERE l @ ena descr.be fusty on additsnal pages as necouary WAfAE (crother afenhnceIm) ANO LOCATION OF SIMULAflON FACILfrY, Clinton Power Station Main Control Room Simulator Clin ~on t Power Station Clinton, Illinois X swUtATxxuACil rwORMANc6 ms? ABSTRACTS ATTACsEo. (r-p.hmence asia conoucer m ee pamd sadmg we me dem or era cwencenoa) essCRiPTiON OF PERFORMANCE TESTING COMPterEo unech add.teneiMes necess y and.denary she dern dricrigeon nemy cenerved)

See the Clinton Power Station Simulator Certification Report,Section II.G.

E SIMULATION FACIUTY PERFORMANCE TESTING SCHEDULE ATTACHED. (Frw me conduct of optireanneasy 25 pecent c(perhmence fests per peer h commencmg we Me date ofItms cerhticehon)

DESCRIPTION OF PERFORMANCE TESTING TO BE CONOUCTED. Mllech edd.tmalpages as necessay and afentd)r me dem descrip6an eseng con 6nueG)

See the Clinton Power Station Simulator Certification Report,Section I.G for description and Attachment 6 for the testing schedule.

l I

l PERFORMANCE TESTlHG PLAN CHANGE (Fa any modsfcebon b a perhmence sesbng,oen submstred on a preveus cwericaban)

CISCRsPTION OF PERFORMANCE TESTING PLAN CHANGE (Anoch edorhonetpages as necessay and afenkt)r me dem susseruptmn beme conknued)  :'

I k

n I

RECERTlFICATION (Ooscrsbo scrrecewe echons anken, atlech results ofcompJesedperhmence 6eshng m eccadence we f0 CFR SS dSib)($)te) fatech additmelpages es necessay and atenkfy be dern descruptmn komg conhnued) l Ony falso statement e.ec,,rn.nts or omessen m tres document, mcLuding attachments.

m .u. .e correa i may be sub ect to cui and enmmal sanctons I cerbfy under penalty of per}ury that th l

TURE - AUTk ED REPRESENTATIVE TITLE DATE Chief Nuclear Officer [p in accordance enth 10 CFR $$ 5. C:mmenons. Bus term shan be submitted to the NRC as follows 97 Mall ADORESSED TO DIRECTOR, OFFICE OF NUCLEAR REACTOR REGULATION BY DEUVERYIN PERSON ONE WHITE FUNT NORTH U.S. NUCLEAR REOULATORY COs#MuS80N TO THE NRC OFFICE AT.

WASHINGTON. DC 205554001 11555 ROCKVILLE PIKE ROCKVILLE, MO NRC FORM 414 (81996)

PRINrED ON RECYCLED PAPER l

1

(

l ee 's Reaulatory Guide 1.149 Revision 2 (April 1996) ExMons

• Nuclear Power Plant Simulation Facilities For Use In Operator License Examinations The Clinton Power Station Simult. tion Facility complies with the requi;cments of Regulatory Guide 1.149 with the following clarifications and exceptions:

l

1.

Reference:

Paragraph C.l.1 - Exception is taken to the blanker statement that the simulation facility should meet the requirements of ANSVANS 1.5-1993. The simulation facility used at Clinton Power Station meets the requirements of ANSUANS 3.5-1993 with the exceptions and clarifications identined in this document on Regulatory Guide 1.149 Revision 2 exceptions.

2. Reference Paragraph C.I.2 - It is clarified that IP compliance positions to ANSI Standards included and referenced in ANSUANS 3.5-1993 are addressed under the appropriate Regulatory Guide listed in Section 1.8 of the CPS USAR.

l

3.

Reference:

Paragraph C.I.3 -It is clarified that the simulator at Clinton Power Station uses a third type ofinstructor interface in addition to the " Malfunctions" and " Overrides" that are defined in ANSUANS 3.5-1993. His third type ofinterface is called a " Remote " Remotes interface with the soAware models and have been dcd. ped to allow the instructors to perform normal plant evolutions that would normally be performed by plant operating personnel working outside of the Main Control Room environment. Some typice! -t~ of these Remotes would be starting / stopping pumps, opening / closing valves, and placing filter demineralizers in service or removing them from service. While these Remotes may in fact cause indications to change in the Main Control Room, the changes that are seen are expected changes as a result of normal plant equipment / system manipulation. While Remotes do have the capinbility to be used as Malfunctions to challenge the students in the course of training, very few of them are so used.

Those Remotes which are used as Malfunctions in training materials will be certified as required in Regulatory Position C.I.5 for Malfunctions. Those Pomanen which are not used as Malfunctions will be reviewed and validated in the same manner as Overrides.

4.

Reference:

ANSUANS 3.5-1993, Paragraph 5.0 - E-P is taken to the requirements of Section 5.0 of ANSUANS 3.5-1993. There are already various programs on site that perform the functions described in this section. Illinois Power will utdnze these programs in conjunction with simulator specific programs to proyule a configuration management method for the CPS Simulator. His method is described as follows:

The CPS Simulator does not maintain a separate and unique design niatahame The simulator source code configuration management process supports accountability to the level desired for simulator modeling data. Source code configuration management is combined with tim processes used for identifying, tracking, and documenting simulator hardware changes and simulator discrepancies to provide an overall simulator configuration management process Clinton Power Station maintains stringent configuration a anagement controls for power plant equipment and components. Identification of plant changes that have the potential to require changes to the simulator hardware or soAware is an integral part of the plant configuration process. Including the simulator as part of the design process for plant modifications allows for the immarhane identification of simulator impacts These impacts are then tracked and their resolutions documented using simulator specific programs and processes Including the simulator as a part of the design process ensures that all design changes that could affect the simulator are identified and tracked. It also eliminates the need for a separate annual review of all plant modifications for simulator impact.

a i .

Other souras ofinput for simulator upgrade / modification include such thmas as Licensee Event Reports, Sigmficant Operating Event Reports, pid. revisions, student faadhack, etc. The Nuclear Training Department performs ongoing reviews of such sources ofinformation for ,

possible impact on any of the training programs. 'Ihe panitatar is included in the review of these sources. Any ainnitatar impacts that are identafled as a result of these reviews are then tracked and their resolutions documented using simulator specific programs and processes Plant modifications which are determined to be relevant to the training program are implemented on the simulator within 24 months of their plant inservice date. Other changes which have been determined to be relevant to the training program are implemented based upon their training impact.

Dar==witatian unique to the simulator such as input / output system schematics, simulator hardware configuration, and simulator equipment vendor manuals are snaintained by the j simulator support group. Resources from other areas such as DraAing and Document Control are used where needed to augment the simulator support group. ,

l The simulator test program is based primarily upon hard plant data. Should hard plant data not i be available, plant specific engineering analysis data is utilized. The use of safety analysis data is minimal for the simulator. Operator input is used to provide information and fine tuning data.

The need for changes to the scope of simulation are determined based on the results of the reviews performed by the Training Department.

5. Refe ence: ANSI /ANS 3.5-1993, Paragraph 4.1.3.1 - This paragraph requires that the computed valuce of parameters not specifically identafled in the following ni ps,-?+ shall be validated to missch reference unit data within 10% of the reference unit instruniant loop range. It is clarified that the parameters idanadied in the sub-paragraphs of this section are included in the certification tests that are performed on the simulator. In addition to these parameters other selected plant parameters are monitored as a part of the tests. These additional parameters are selected based on their ability to show overall simulator performance as compared to actual plant performance. 'Ihese additional parameters are a liniited set and do not include all other values or parameters calculated on the sinnitatar. Only these additional parameters / values selected for testing are required to be venfied to be within 10% of the plant values.

6.

Reference:

ANSI /ANS 3.5-1993, Paragraph 4.1.3.1 ' Ibis paragraph requires that the simulator instrument error be no greater than that of the comparable meter, recorder, and related instrument system of the reference plant. E Tian is taken to this requirement. The instruments used in the CPS Simulator are penodscally cliackad by venfying that they indicate correctly at three different scale positions. These scale positions are generally zero scale with no input signal, full scale with a full input signal, and mid-scale with one-half of the full input signal. Other scale positions may be used as appropnate for the instrument being evaluated.

naranse of the way that the output from the sinalation niadala is handled these checks provide the naremmary assurance that instruments are responding and indicating correctly.

7.

Reference:

ANSI /ANS 3.5-1993, Paragraph 4.1.2 - This paragraph requires that the limits of sinnularian are identified as part of the sinnlator design data base. As noted in item 4 above Clinton Power Station does not use a separate design data base. F-Tia= is taken to this requirement. The limits of simulation are maintainad in the samulator sonware and do autannatically notify the instructors when a limit has been exceeded.

8.

Reference:

ANSI /ANS 3.5-1993 Paragraph 4.2.1.2 -TMs paragraph discusses the training value assessments that are to be performed for devistsons that have been identified. It is clanfied that this assessment is included as a part of the rotmal evaluation of all identified simulator problems and that it is not a separate maneaminant and is not required to be documented separately.

., . j

9.

Reference:

ANSI /ANS 3.5-1993, Paragraph 4.2.1.4 - This paragraph discusses the training value assessments that are to be performed for deviations that have been identified. It is clanfied that this assessment is included as a part of the normal evaluation of all idantdied simulator problems and that it is not a separate amma== ment and is not reqmrod to be dacumented separately.

10.

Reference:

ANSI /ANS 3.5-1993, Paragraph 4.2.2.1 -This paragraph discusses the trainira value mana===ents that are to be pr4v.d for deviataons that have been identafied It is clanfied that this assessment is included as a part of the normal evaluation of all identified sinmlatar problems and that it is not a separate assessment and is not required to be documented separately.

I 1.

Reference:

ANSI /ANS 3.5-1993, Paragraph 4.2.2.2 - This paragraph discusses the training value manaamments that are to be performed for deviations that have been identified It is clarined that this mana== ment is included as a part of the normal evaluation of all identified simulator problems and that it is not a separate assemament and is not required to be documented separately.

12. Reference Paragraph C.I.6 F-Tiaa is taken to this paragraph As noted in item 4 above a separate design data base is not utilimd at Clinton Power Station The plant modification process requires that the simulator see all plant modificataons that will impact either the physical hardware or the software models. 'Ihis is an in-line evalustaon and as such allows the simu8ator  :

to be aware of the latest plant design. Simulator changes that are identified as a result of reviews l of these modification packages are tracked and incorporated into the simulator based on priorities I established by the training t.c m. In addition to the in-line review of plant modification I packages the simulator certification tests include a physical fidelity venfication test. This test consists of comparing the actual control room hardware with the simulator panels. Any j discrepanew are identified as simulator problems which then receive the normal evaluation that I all identified simulator problems receive. The physical fidelity test serves as a backup to the in- j line review of plant moddication packages. These steps assure that the simulator maintains the requisite physical fidelity with the main control room. A separate annual review of plant modifications is not required to be performed.

13.

Reference:

Paragraph C.I.7 -It is clanfied that while Appendix A, Appendix B, and Appendix C referenced in this paragraph are considered to be integral parts of the standard, they are only used for guid=* and as av ,aian