ML17335A279

Forwards Cook Nuclear Plant Simulation Facility four-year Rept IAW 10CFR55.45(b)(5)(ii).Additionally Included Are NRC Forms 474

ML17335A279
Person / Time
Site:	Cook
Issue date:	10/08/1998
From:	Powers R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1134B, NUDOCS 9810140199
Download: ML17335A279 (66)

Text

CATEGORY 1 REGUL'AT Y INFORMATION DXSTRIBUTIO SYSTEM (RIDS)

ACCESSION NBR:9810140199 DOC.DATE: 98/10/08 NOTARIZED: YES DOCKET ¹ FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana M

05000315

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50-316 Donald C.

Cook Nuclear Power.Plant, Unit 2, Indiana M

05000316 AUTH.24AME AUTHOR AFFILIATION POWERS,R.P.

Indiana Michigan 'wer Co.

(formerly Indiana 6 Michigan El'e RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Forwards Cook Nuclear Plant simulation facility four-year C

rept IAW 10CFR55.45 (b) (5) (ii).Additionally included are NRC A

Forms 474.

DISTRIBUTION CODE: A005D COPIES RECEIVED:LTR ENCL TITLE: Simulator Facility Certification - GL-90-08 SIZE:

NOTES:

RECIPIENT ID CODE/NAME STANG,J COPIES LTTR ENCL 1

RECIPIENT ID CODE/NAME COPIES LTTR ENCL 0

INTERNAL FILE NTER 0

EXTERNAL: NRC PDR 1

1 1

1 D

0 N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.

TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 3

ENCL 3

Indiana Michigan ~

Power Company 500 Circle Drive Buchanan, Ml 491071373 October 8, 1998 AEP:NRC:1134B Docket Nos.:

50-315 50-316 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Mail Stop 0-Pl-17 Washington, D.C. 20555-0001 Gentlemen:

Donald C.

Cook Nuclear Plant Units 1 and 2

Simulation Facility Four Year Report In accordance with 10 CFR 55.45(b)(5)(ii), American Electric Power Company hereby submits to the Commission the Cook Nuclear Plant Simulation Facility four-year report.

This report encompasses both unit 1

(50-315) and unit 2

(50-316).

Additionally included are form NRC-474s for both docket numbers.

If additional information is

required, please contact Mr.

Tim Vriezema at (616)465-5901, x3001.

Sincerely, P.

Powers Vice President

" SelORN TO AND SUBSCR E

BEFORE ME pit

,;THIS DAY OF 1998 Notary b ic VALERfELBQMLt.

My Commission Expires ~ Puhio, Berrien CCenly, I 9

/jmc Attachments 9810140199

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U.S, Nuclear Regulatory Commission Page 2

AEP:NRC:1134B J.

A. Abramson J.

L. Caldwell, w/attachments MDEQ DW

& RPD NRC Resident Inspector, w/ attachments J.

R.

Sampson, w/attachments

U.S. Nuclear Regulatory Commission Page 3

AEP:NRC'1134B bc:

T.

P. Beilman - w/attachments E.

R. Eckstein/D.

R. Hafer/K.

R. Baker J. J.

Euto FOLIO w/attachments B. J. Hickle G.

Honma J.

B. Kingseed/G.

P. Arent/ M. J.

Gumns J.

F. Stang, Jr.,

NRC Washington, DC w/attachments

ATTACHMENT 1 TO AEP:NRC:1134B SIMULATION FACILITY CERTIFICATION

NRC FORM 474 (5-95)

U.S. NUCLEAR REGULATORY COMMISSION

/

SIMULATIONFACILITYCERTIFICATION APPROVED BY OMB: NO. 31604136 EXPIRES: 06r3tr96 Esbmsted burden per res For>>e to comply with this mandatory informstkxt coiiacbon request 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, Wis information is used to ceibfy a sbnubrtion fscgity. Forward comments regarding burden estimate to the Inlonnsbon and Records Management Branch (T4 F33), U.S. Nuclear Regulatory Commission, Washington, DC 20555.

0001 ~ and to the Paperwork Reduction Project (31504138), Office of Management snd Budget, Washington, DC 20503. NRC may not conduct or sponsor, snd a person Is not required lo respond to, s cotlsctiorl of informatioA unless it displays a uurrentiy valid OMB control nisriber.

INBTRUQTIQNB: This form is lo be filed for initial cerbfication. recerbficstion (d required). snd for any change to a simutaticn facibty performance tesbng planmade aller initial submittal cf such s plan. provide the following infoimsbon snd check the appropnsts box to indicate reason for submitbd.

FACILITY LICENSEE COOK NUCLEARPLANT AMERICANELECTRIC POWER COMPANY DOCKET NUMBER

'~ 315 DATE 8/20/98 This is to cerbfy that 1.

The above named facilitylicensee is using s simulation faabty consisting solely cf s ptantMsranced slmutstor that meets the requirements of 10 CFR 55.45.

2.

Documentabon is evaibible for NRC review Ina~ with 10 CFR 55A5g>).

3, This simulsticn fscibty meets the guidance contained br ANSIiANs3.5-1 955 or ANsl/ANs 3.5.1 993, as endorsed by NRQ Regulatory Guide 1.149.

Ifthere are any ExcEPTIQNs to the cerbfication of this item, cHEGK HERE I ] snd descnbe fullyon sddkonal pages as necessary.

NAME (or otteridendficadon) AND LOCATION OF SIMULATIONFACILITY.

COOK TRAININGCENTER ONE COOK PLACE BRIDGMAN,MI 49106 BIMUtATIQNFAQILITYpERFORMANCE TEST ABSTRACTS ATTACHED. (For performance tests conductedin lhe pekxf encfng with the dale ofthis cerdficabon)

DE 5c RipTIQN oF pERFQRMANGE TEsTING coMpLETED. (Altach sdrdd'oner pages ss neosssery snd idendiy lhe stem desaipbon being condnued)

No performance testing was performed specific to Cook Unit One during thc last four year period.

Performance testing of the simulator was performed in accordance with the testing schedule per thc certification submittal in thc Four Year Report of August 1994.

Refer to the Cook Plant Simulator Four Year Rcport Unit Two for performance testing abstract and completion dates.

BIMULATIQNFACtLITYPERFORMANCE TESTING SCHEDULE ATTACHED. (Fcv the conducf ofappnuimsleiy 25'fpedonnsnce tests per year forthe four~sr pedod commencing with lhe dele ofthis cerdlicsdon.)

DFscRlpTIQN oF pERFoRMANGE TESTING TQ BE CONDUCTED. (Alfsch eddidonsl pages as necessary and idendry the rrem descrtpdon being condnued)

No performance testing willbe performed specific to Cook Unit 1. Refer to the Cook Plant Simulator Four Year Report Unit Two, Attachment 2 for thc schcdulc of certification testing to bc performed over the next four year period on the Unit Two simulator.

Approximately 25% of all malfunction testing is schcdulcd annually.

pERFORMANCE TESTING piANCHANGE. (For any rrxxdifcadon lo a perrbrmsnce iesdng plan submitted on s previbus certigcadon)

DF scRIFTIQN QF pFRFQRMANGE TEsTING pLAN cHANGE (Allsch eddidonai pages as necessary and idendry lhe rrem descnpdon being condrrued)

See attached, Cook Plant Simulator Four Year Rcport Unit Two, for a description of pcrformancc test schedule changes.

RFQERTIFIQATIQN (Descdba correcbve acdons taken, attach nisults ofcompleted perfonnance fasting in accordance wild fg cFR 5565(b)(5)(v).

(Attach addi'ionsi pages as necessary and fdendfy theitem descripdon being continued)

Any false stalemenl or omission in this documenL inctudeg attachments, msy be subject to civiland cnminsl ssncticns.

I cerbly under penalty of periury that the inlcnnsten in this document snd attachments is bue and correcL SIGNATURE AUTHOR D REPRESENTATIVE Ina~ with 10 CFR 55.5. Communicatior>>. Ibis foun shag be submitted to the NRQ as fogows:

BY MAILADDRESSED TO:

DIRECTOR, OFFICE OF NUCLEAR REACTQR REGULATIQN U.S. NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20S564001 BY DELIVERYIN PERSON TO THE NRC OFFICE AT; DATE

/o/i/gr ONE WHITE FUNT NORTH 116SS ROCKVILLE PIKE ROCKVILLE, MD

DONALDC. COOK NUCLEARPLANTSIMULATOR FOUR-YEAR REPORT UNIT 1 A.

Purpose The Cook Nuclear Plant simulator is used in the licensing of operations personnel and is therefore required to meet the criteria established in 10 CFR 50.55 Subpart E, Section 55.45.

To comply with 10 CFR 55.45, a report to the Commission, which identifies simulator testing status, must be submitted every four years from original date of certification.

The purpose of this report is to satisfy this reporting requirement for the Cook Nuclear Plant simulator.

B.

References 1.

Title 10, Code ofFederal regulations, Part 55, "Operator Licenses",

Subpart E, Section 45.

2.

U.

S. Nuclear Regulatory Guide 1.149 "Nuclear Power Plant Simulation Facilities for use in Operator License Examinations".

3.

ANSI 3.5, 1985, "Nuclear Power Plant Simulators for use in Operator Training".

C.

Reporting Requirements The requirements ofthis report as outlined in 10 CFR 50.55 are:

1.

Identification of any uncorrected performance test failures and a schedule for correction of such performance failures, if any.

Subpart E Section 55.45 (b)(5)(ii).

2.

A description of performance testing completed for the simulation facility. Subpart E, Section 55.45 (b)(5)(vi).

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0

3.

A description ofthe performance tests, ifdifferent, to be conducted on the simulation facility during the subsequent four-year period.

Subpart E, Section 55.45 (b)(5)(vi).

4.

A schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.

Subpart E, Section 55.45 (b)(5)(vi).

D.

Discussion The Cook Nuclear Plant simulator is modeled to Cook Unit 2 and functions to provide training for both Units of the Cook Nuclear Plant.

The following reviews are intended to provide reasonable assurance that the original certification study of differences between units has not been significantly impacted, and that operator performance is not indicating a declining trend as a result of simulator training on the Unit 2 simulator.

Unit 2 four-year report is also provided herein.

Unit 1 specific plant modifications installed from January 1,

1994, to present have been reviewed to determine the impact of those changes upon the original certification differences study, This evaluation determined that, as a result of design changes made in the Unit 1 control room, training on Cook Nuclear Plant Unit 2 simulator would not result in an operator error resulting in a challenge to a critical safety function in Unit 1.

2.

Unit 1 plant condition reports, written between January 1, 1994 to

present, with causal codes identifying training qualification methods/content and operations identified as the involved department, have been reviewed.

This review identified no cases in which training on the Unit 2 simulator resulted in an error in operation ofUnit 1.

3.

Reactor trips occurring in the four-year period since the previous report submitted in August 1994 have been reviewed. This review determined that the lack of unit specific simulator training on Unit 1 had no impact on these events.

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E.

Implementation Requirement

¹1:

Uncorrected performance test failures and a

schedule for correction ofsuch performance failures.

Refer to Cook Nuclear Plant Simulator, Four-year Report Unit 2 for a list of performance test failures and scheduled correction dates.

Requirement ¹2: Description of performance testing performed in the last four-year period.

No performance testing was scheduled specific to Unit 1

as identified in the previous four-year report dated August 31, 1994.

Refer to Cook Nuclear Plant Simulator Four-year Report Unit 2 for performance testing abstract and completion dates.

Requirement ¹3: Description of performance tests, ifdifferent, to be conducted on the simulation facilityduring the subsequent four year period.

No performance testing specific to Unit 1 is scheduled for the next four-year period. Allperformance testing willbe conducted on the Unit 2 simulation load only. Refer to Cook Nuclear Plant Simulator Four-year Report Unit 2 for a list of certification tests to be performed on the simulator in the next four-year period.

Requirement ¹4: Schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.

No performance testing specific to Unit 1 is scheduled for the next four-year period. Allperformance testing willbe conducted on the Unit 2 simulation load. Refer to Cook Nuclear Plant Simulator Four-year Report Unit 2 for a list of certification tests to be performed on the simulator in the next four-year period.

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ATTACHMENT 2 TO AEP:NRC:1134B SIMULATION FACILITY CERTIFICATION

U.S. NUCLEAR REGULATORY'OMM(SS(ON APPROVED BY OMB: NO. 31$M138 NRC FORM 474 (8-95)

EXPIRES: 08I31I98 Estimated burden per response to comply with this rnsndstNy information collection request:

120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />. This Information Is used to certify a simulation facility. FNwsrd comments regarding txsden estimate lo the Infomstion and Records Management Branch (T4I F33), U.S. Nudesr Reguhrtory Ccmmisshn. Washington, DC 20555.

0001, and to the Paperwok Reducdcn Project (31500138).

Office of Management snd Budget, Washington, DC 20503. NRC msy not conduct or sponsor, snd a person ls not required lo respond to. a collecdon of information unless d displays a currently valid 0MB contml nlnber.

SIMULATIONFACILITYCERTIFICATION INBTRUGTIDNs: This fom is tp be fded for initial ceitifcsbon, secertrficsten (d required), snd for any change to a sinutstion facibty perlormsnce testing plan made sear initial submittal ot such a pisn. provide the following information snd check the appropriate box to indicate reason for submittal.

FACIUIY LICENSEE COOK NUCLEARPLANT AMERICANELECTRIC POWER COMPANY DOCKET NUMBER,

<O-316 DATE 8/20/98 This Is to certify thaL 1,

The above named facilityticensee is using a simulation facilityconsisting solely of s plsntreferenced simulator that meets the requirements of 10 CFR 55.45.

2.

Drxxsnentsticn is avalable for NRc review in accordance with 10 cFR 55.45(b),

3.

This simulation facilitymeets the guidance contained kt ANSVANS 3.5.1985 or ANSVANS 3.5-1993. as endorsed by NRC Regutstay Guide 1.149.

IfIhere are any ExcEpTIDNs to the cerufication of INs item, cHEGK HERE [ ] and describe fullyon additional pages ss necessary.

NAME (or other rdenbltcsbon) AND LOCATIQN OF SIMULATIDNFAGILITY.

COOK TRAININGCENTER ONE COOK PLACE BRIDGMAN,MI 49106 siMULATIDNFAGILRYpERFoRMANGE TEsT ABSTRAGTs ATI'AGHED. (For penbnnsnce tests conducted In the pen'od encfng wththe dsle of this cerbrfcstion)

DFscRipTIDN oF pERFQRMANGE TEsTING cOMpLETED. (Alfsch adrkbonsr pages es iiecesssiy and Idenbry the ilem description being conb'rived)

Scc attached, Cook Plant Simulator Four Year Report Unit Two, Attachment One.

SIMULATIONFACILITYPERFORMANCE TESTING SCHEDULE ATTACHED. (For the conduct ofsPProxlmsrely 25'of Perfonnance rests Per year forthe four~sr Period X

commencing w'lh the dste of trris cempcedon.)

DFscRlpTIDN oF pERFDRMANGE TESTING TO BE CONDUCTED. (Alrsch arkkbonsr pages es necessary sndidenbiy the item descnpbon being conbnued)

Scc attached, Cook Plant Simulator Four Year Rcport Unit Tvvo, Attachment Two.

pERFORMANCE TESTING plAN CHANGE, (For any morbifcsb'on ro e perfonnance faring plan submitted on s prevrbus cerblfcsb'on)

DEscRIpTIDN oF pERFORMANCE TESTiNG PLAN CHANGE (Altsch eddilionsi pages as necessary and Idenbiy the item descnpbon being conbnued)

Sce attached, Cook Plant Simulator Four Year Report UnitTwo (Page 5 of5).

REcERTIFIcATIQN (Descnbe corrective ecdons taken. errsch resorts ofcompleted perfonnance festfng In accordance wth 10 cFR 5%45(b)(5)(v).

(Allsch arkbb'onsl pages ss necessary end kfenb+ the ilem descrfpbbn being condnued)

Any false statement or omission in Qvs documenL ktctuding attachments, msy be subtect to civiland cnminal sancucns.

I cerufy under penalty of peiiuiy that the infcnnsuon in this document and attachments is true and correcL SIGNATURE AUTHORIZED REPRESENTATIVE TITLE u/

In accordance vnth 10 CFR 55.5. Commuivcatens, this form shall be submitted to the NRc ss fotkiws:

BY MAILADDRESSED TO:

DIRECTOR, OFRCE OF NUCLEAR REACTOR REGULATION U.S. NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 205554001 BY DELIVERYIN PERSON TO THE NRC OFFICE AT:

DATE Nylfr ONE WHITE FUNT NORTH 1155$ ROCKVILLEPIKE ROCKVILLE, MD

DONALDC. COOK NUCLEARPLANTSIMULATOR FOUR-YEARREPORT UNIT2 E.

Purpose The Cook Nuclear Plant simulator is used in the licensing of operations personnel and is therefore required to meet the criteria established in 10 CFR 50.55 Subpart E, Section 55.45.

To comply with 10 CFR 55.45, a report to the Commission which identifies simulator testing status must be submitted every four years from original date of certification.

The purpose of this report is to satisfy this reporting requirement for the Cook Nuclear Plant simulator.

F.

References 4.

Title 10, Code ofFederal regulations, Part 55, "Operator Licenses", Subpart E, Section 45.

5.

U. S. Nuclear Regulatory Guide 1.149 "Nuclear Power Plant Simulation Facilities for use in Operator License Examinations".

6.

ANSI 3.5, 1985, "Nuclear Power Plant Simulators for use in Operator Training".

G.

Reporting Requirements The requirements ofthis report as outlined in 10 CFR 50.55 are:

2.

Identification of any uncorrected performance test failures and a schedule for correction of such performance failures, if any.

Subpart E, Sections 55.45 (b)(5)(ii).

2.

A description of performance testing completed for the simulation facility.

Subpart E, Section 55.45 (b)(5)(vi).

3.

A description of the performance tests, ifdifferent, to be conducted on the simulation facility during the subsequent four-year period.

Subpart E, Section 55.45 (b)(5)(vi).

Page 1 of 5

4.

A schedule for the conduct ofapproximately 25 percent of the performance

~

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tests per year for the subsequent four years.

Subpart E, Section'55.45 (b)(5)(vi).

H.

Implementation Requirement ¹1: Uncorrected performance test failures and a schedule for correction ofsuch performance failures.

Uncorrected performance test failures include:

DR 98026:

RCS mass increase due to cycling ofa RHR system check valve during plant cooldown.

DR 98054:

During plant heatup to mode 5, shutting down the RHR pump caused loop return temperature to'omentarily spike low.

These tests are scheduled for completion within one year of origination dates.

DR 98026 Completion date:

Prior to 3/4/99.

DR 98054 Completion date:

Prior to 6/2/99.

Requirement ¹2:

Description of performance testing performed in the last four-year period.

ANSI 3.5, 1985 Appendix A lists the requirements relative to certification testing for nuclear plant simulators.

These requirements fall into four separate categories.

1.

Computer Real Time Tests-Verification of real time simulation by the simulator.

2.

Steady State and Normal Plant Evolution Performance Tests.

a)

Steady State Tests-Verification of simulator stability and verification that process parameter values reflect actual reference plant values.

b) Normal Plant Evolution Performance Tests-Verification of simulator ability to perform in accordance with reference plant operating procedures.

3.

Transient Tests-Testing of simulator's ability to reproduce a defined set oftransients.

Page 2 of 5

4.

Malfunction Testing-Testing of each generic malfunction to verify simulator response and system interaction.

Computer Real Time Testing.

ANSI 3.5, 1985 requires real time verification to ensure the simulation dynamic performance is in the same time base relationships, sequences, durations, rates and accelerations as the dynamic performance of the reference plant.

The Cook Nuclear Plant simulator uses Real Time Executive Tasks (RTEXEC) to ensure that the simulator remains in real time during all simulation.

This task uses a frame counter routine to ensure an overtime abort and simulator "freeze" condition occurs ifthe Real Time Executive Task fails to execute in the allotted time period.

Simulator real-time tests have been performed annually with no failures identified. See Attachment 1 (page 2) for test performance dates.

Steady State and Normal Plant Evolutions Testing.

To ensure compliance with the standard regarding simulator steady state operation, the simulator has been operated for periods of one hour without operator action at rated thermal power conditions.

Computed values were collected at half second intervals over the one hour time period. This data has been verified accurate against actual plant data and heat balance information within the tolerances for critical and non-critical parameters as established in ANSI 3.5, 1985.

The data has also been plotted and verified not to vary more than 2% from original values.

Additional Steady State Testing has been performed at three additional power levels for which plant data exists.

Simulator and reference plant data for critical and non-critical parameters have been recorded and verified not to deviate from the tolerances stated in ANSI 3.5, 1985.

See Attachment 1 (page 3) for Steady State Test abstract and performance dates.

Normal plant evolutions are tested and verified against the criteria established in ANSI 3.5 Section 3.1.1 annually per the certification schedule in the four year report submitted August 31, 1994.

These tests are performed in accordance with approved plant procedures.

See Attachment 1 (page

4) for Normal Plant Evolution test abstract and performance dates.

In addition to testing performed by simulator personnel, these evolutions have been tested as an integral step ofthe Reactor Operation Replacement training program.

This program involves continuous operation (per Page 3 of 5

approved plant procedures) of the simulator from full power to half loop conditions, and from half loop conditions back to fullpower operation by instructors and SRO candidates with numerous years of plant operating experience.

ANSI 3.5 tests not listed or performed on a regular schedule are clarified below.

Core performance testing (3.1.1.9) is performed on the'simulator when core cycle upgrades are made on the simulator (currently the same cycle as the reference plant).

Operations surveillance tests (3.1.1.10) are performed on an as needed basis within the operations training program using approved plant procedures.

3. Transient Testing.

Alltransient tests required by ANSI 3.5, Appendix B section B.2.2 have been conducted on the simulator per the certification schedule submitted in the August 1994 four-year report.

Additionally, complete retesting of all eleven transients was performed in May 1996 (testing ofnew RETACT model) and also in October 1996 (testing of simulator rehost running on the Windows NTYi platform).

The data collected in the performance ofthese tests is collected at one half second intervals and has been compared to best estimate. information or actual plant data where actual plant data was available.

Refer to Attachment 1

(pages 5-7) for Transient test abstract and performance dates.

Dates for the RETACT testing and rehost testing have also been included.

4.

Malfunction Testing.

The Cook Nuclear Plant simulator has 317 malfunctions used to introduce transients and/or faults into the simulator for operator training.

All malfunctions have been tested in the previous four year period with approximately 25% tested annually. Additionally, a complete retest ofall malfunctions was performed as part of the simulator upgrade project (simulator rehosting to Windows N~ platform).

Refer to Attachment 1 (pages 8-15) for Malfunction test abstract and performance dates.

Page 4 of 5

Requirement

¹3: Description of performance tests, if different, to be conducted on the simulation facilityduring the subsequent four year period.

Changes to the performance testing over the next four year period include the following:

Malfunction test schedule has been modified from the last report to reflect the deletions and additions to the current malfunction list.

The followingwere deleted from the malfunction list:

RD12:

Failure ofcontrol rods to move. This malfunction has been replaced by new malfunction RD20 to improve malfunction accuracy.

RX22:

SG programmed level signal failure.

SG level setpoint is now a constant 44% and level program is no longer used.

The followingwere added to the malfunction list:

CH03:

Wide range containment pressure transmitter failure.

CH04:

Containment leakage.

CV34:

Chg. Flow instrument failure.

FP06:

Fire protection storage tank leak FW58:

Condensate Booster Pump failure to auto start.

MS22: MSIVmechanical binding.

RD20:

Rod Control power cabinet failure.

RP22:

RPS relay K621X2 failure.

RX15:

Steam dump system failure to respond.

TP06:

Stator Cooling Tube leakage.

The Normal Plant Evolution schedule has been reduced to a four year test program in place of the current yearly testing.

There is no standard for testing programs and our past practice has been to do all the tests annually.

Since there have been few malfunctions identified and for economic reasons, the testing frequency has been reduced, The Special Transient testing category has been deleted from the testing schedule.

These were in-house tests not associated with ANSI 3.5, 1985.

Requirement ¹4:

Schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.

Attachment 2

outlines the schedule for certification testing to be performed over the next four year period.

Approximately 25% of all malfunction testing and Normal Plant Evolutions are scheduled annually.

Page 5 of 5

ATTACHMENT1 COOK PLANTSIMULATORCERTIFICATIONTESTING This attachment consists of testing information relative to the Cook Plant Simulator certification requirements.

The sections ofthis attachment are:

Computer Real Time testing Normal Plant Evolution (NPE) testing Steady State testing Transient testing Malfunction testing All testing has been completed per requirements of ANSI 3.5, 1985 as amended by Regulator Guide 1.149.

Deviations from test schedule submitted in the 1994 four year report follow:

Special Transient Test (ST-4) scheduled for the last quarter of 1995 was not completed or all data pertaining to the test was lost.

This test was not identified as being untimely until it became due in the last quarter of 1996.

This is an in-house test not required by ANSI 3.5, 1985 appendix A.

Special Transient Tests (ST-1,2,3) scheduled for the first 3 quarters of 1996 were deferred to the last quarter of 1996.

This was done to correspond to the testing ofthe rehosted simulator configuration.

Normal Plant Evolutions scheduled for the first two quarters of 1996 were deferred to the last halfof 1996. This was done to correspond to the testing ofthe rehosted simulator configuration.

Steady State Tests scheduled for the third quarter of 1996 was deferred to the last quarter of 1996.

This was done to correspond to the testing of all steady state power levels in the rehosted simulator configuration.

Page 1 of 16 Attachment 1

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II II J%

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'ki~sf A

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Test Number CRT-1 CRT-1 CRT-1 CRT-1 CRT-1 COOK NUCLEARPLANTSIMULATOR REALTIMETEST REPORT Title COMPUTER REAL TIMETESTING COMPUTER REALTIMETESTING COMPUTER REALTIMETESTING COMPUTER REAL TIMETESTING COMPUTER REALTIMETESTING Date Tested 1/12/94 3/13/95 4/4/96 3/28/97 4/17/98 Page 2 of 16 Attachment 1

COOK NUCLEARPLANTSIMULATOR STEADYSTATE TESTING REPORT Test Number SS-1 SS-2 SS-3 SS-4 SS-1 SS-2 SS-3 SS-4 SS-1 SS-2 SS-1 SS-2 SS-3 SS-4 SS-1 SS-2 SS-3 SS-4 SS-1 SS-2 Title ower Level STEADY STATE (30%)

STEADY STATE (47%)

STEADY STATE (75%)

STEADY STATE (100%)*

STEADY STATE (30%)

STEADY STATE (47%)

STEADY STATE (75%)

STEADY STATE (100%)*

STEADY STATE (7%)

STEADY STATE (33%)

STEADY STATE (30%)

STEADY STATE (47%)

STEADY STATE (75%)

STEADY STATE (100%)*

STEADY STATE (27%)

STEADY STATE (47%)

STEADY STATE (75%)

STEADY STATE (100%)*

STEADY STATE (27%)

STEADY STATE (47%)

Date Tested 3/28/94 6/26/94 8/28/94 12/19/94 3/1 3/95 6/30/95 10/4/95 12/17/95 3/30/96 6/12/96 12/16/96 12/16/96 12/17/96 10/12/96 3/31/97 9/23/97 6/25/97 12/30/97 3/27/98 6/2/98

• Stability testing performed in conjunction with steady state test at rated power.

Page 3 of 16 Attachment 1

COOK NUCLEARPLANTSIMULATOR NORMALPLANTEVOLUTIONPERFORMANCE TESTING Test Number NPE-1 NPE-1 NPE-1 NPE-1 NPE-1 NPE-2 NPE-2 NPE-2 NPE-2 NPE-2 NPE-3 NPE-3 NPE-3 NPE-3 NPE-4 NPE-4 NPE-4 NPE-4 NPE-5 NPE-5 NPE-5 NPE-5 NPE-5 NPE-6 NPE-6 NPE-6 NPE-6 NPE-6 NPE-7 NPE-7 NPE-7 NPE-7 Title RCS FILLANDVENT RCS FILLANDVENT RCS FILLANDVENT RCS FILLANDVENT RCS FILLANDVENT HEATUP FROM MODE 5 TO MODE 3 HEATUP FROM MODE 5 TO MODE 3 HEATUP FROM MODE 5 TO MODE 3 HEATUP FROM MODE 5 TO IVIODE 3 HEATUP FROM MODE 5 TO MODE 3 REACTOR STARTUP REACTOR STARTUP REACTOR STARTUP REACTOR STARTUP POWER ESCALATION POWER ESCALATION POWER ESCALATION POWER ESCALATION POWER REDUCTION POWER REDUCTION POWER REDUCTION POWER REDUCTION POWER REDUCTION PLANT COOLDOWN PLANT COOLDOWN PLANT COOLDOWN PLANT COOLDOWN PLANT COOLDOWN RCS DRAINTO HALF LOOP RCS DRAINTO HALF LOOP RCS DRAINTO HALF LOOP RCS DRAINTO HALF LOOP Date Tested 1/17/94 3/18/95 10/11/96 3/31/97 3/20/98 6/26/94 6/27/95 10/6/96 4/28/97 6/2/98 8/28/94 10/4/95 11/2/96 6/3/97 12/20/94 10/3/95 9/29/96 12/1/97 6/27/94 3/19/95 8/12/96 3/17/97 3/27/98 9/26/94 6/26/95 8/14/96 6/24/97 6/1/98 12/21/94 3/17/95 10/9/96 8/8/97 Page 4 of 16 Attachment 1

COOK NUCLEARPLANTSIMULATOR TRANSIENTTESTS Test Number Trans 1

Trans 1

Trans 1

Trans 1

Trans 1

Trans 1

Trans 1

Trans 2 Trans 2 Trans 2 Trans 2 Trans 2 Trans 2 Trans 3 Trans 3 Trans 3 Trans 3 Trans 3 Trans 4 Trans 4 Trans 4 Trans 4 Trans 4 Trans 5

, Trans5 Trans 5 Trans 6 Trans 6 Trans 5 Trans 5 Trans 6 Trans 6 Trans 6 Trans 6 Trans 6 Trans 6 Trans 7 Trans 7 Trans 7 Trans 7 Trans 7 Trans 8 Title MANUALREACTOR TRIP MANUALREACTOR TRIP MANUALREACTOR TRIP MANUALREACTOR TRIP MANUALREACTOR TRIP MANUALREACTOR TRIP MANUALREACTOR TRIP TRIP OF ALLMAINFEEDPUMPS TRIP OF ALLMAINFEEDPUMPS TRIP OF ALLMAINFEEDPUMPS TRIP OF ALLMAINFEEDPUMPS TRIP OF ALLMAINFEEDPUMPS TRIP OF ALLMAINFEEDPUMPS CLOSURE OF ALLMSIV'S CLOSURE OF ALLMSIV'S CLOSURE OF ALLMSIV'S CLOSURE OF ALLMSIV'S CLOSURE OF ALLMSIV'S TRIP OF ALLREACTOR COOLANT PUMPS TRIP OF ALLREACTOR COOLANT PUMPS TRIP OF ALL-REACTORCOOLANT PUMPS TRIP OF ALLREACTOR COOLANT PUMPS TRIP OF ALLREACTOR COOLANT PUMPS TRIP OF REACTOR COOLANT PUMP ¹23 TRIP OF REACTOR COOLANT PUMP ¹23 TRIP OF REACTOR COOLANT PUMP ¹23 TRIP OF REACTOR COOLANT PUMP ¹23 TRIP OF REACTOR COOLANT PUMP ¹23 TRIP OF REACTOR COOLANT PUMP ¹23 TRIP OF REACTOR COOLANT PUMP ¹23 MAINTURBINETRIP W/0 REACTOR TRIP MAINTURBINE TRIP W/0 REACTOR TRIP MAINTURBINETRIP W/0 REACTOR TRIP MAINTURBINE TRIP W/0 REACTOR TRIP MAINTURBINE TRIP W/0 REACTOR TRIP MAINTURBINE TRIP W/0 REACTOR TRIP MAXIMUMPOWER RAMP 100%-75%-100%

MAXIMUMPOWER RAMP 100%-75%-100%

MAXIMUMPOWER RAMP 100%-75%-100%

MAXIMUMPOWER RAMP 100%-75%-100%

MAXIMUMPOWER RAMP 100%-75%-100%

MAXIMUMSIZE LOCAWITH BLACKOUT Date Tested 1/22/94 3/27/95 4/4/96 5/10/96 10/10/96 3/28/97 3/27/98 6/10/94 6/26/95 5/1 0/96 10/10/96 5/1/97 5/26/98 8/28/94 10/3/95 5/1 0/96 10/10/96 9/1 8/97 12/17/94 12/17/95 5/1 0/96 10/10/96 12/31/97 1/22/94 3/27/95 4/4/96 5/10/96 10/10/96 3/28/97 3/27/98 6/26/94 6/26/95 5/10/96 10/11/96 5/1/97 6/26/98 8/28/94 10/3/95 5/10/96 10/11/96 9/1 9/97 12/17/94 Page 5 of 16 Attachment 1

Trans 8

~ Trans 8 Trans 8 Trans 8 Trans 9 Trans 9 Trans 9 Trans 9 Trans 9 Trans 9 Trans 9 Trans 10 Trans 10 Trans 10 Trans 10 Trans 10 Trans 11 Trans 11 Trans 11 Trans 11 Trans 11 MAXIMUMSIZE LOCAWITH BLACKOUT MAXIMUMSIZE LOCAWITH BLACKOUT MAXIMUMSIZE LOCAWITH BLACKOUT MAXIMUMSIZE LOCAWITH BLACKOUT MAXIMUMSIZE MAINSTEAMLINE MAXIMUMSIZE MAINSTEAMLINE MAXIMUMSIZE MAINSTEAMLINE MAXIMUMSIZE MAINSTEAMLINE MAXIMUMSIZE MAINSTEAMLINE MAXIMUMSIZE MAINSTEAMLINE MAXIMUMSIZE MAINSTEAMLINE SLOW RCS DEPRESSURIZATION TO SLOW RCS DEPRESSURIZATION TO SLOW RCS DEPRESSURIZATION TO SLOW RCS DEPRESSURIZATION TO SLOW RCS DEPRESSURIZATION TO LOAD REJECTION LOAD REJECTION LOAD REJECTION LOAD REJECTION LOAD REJECTION 12/17/95 5/10/96 10/11/96 12/31/97 1/21/94 3/14/95 4/4/96 5/10/96 10/11/96 3/28/97 3/27/98 6/26/94 6/26/95 5/10/96 10/11/96 5/1/97 9/26/94 10/3/95 5/10/96 10/11/96 9/1 9/97 Page 6 of 16 Attachment 1

COOK NUCLEARPLANTSIMULATOR SPECIAL TRANSIENTTESTING Test Number ST-1 ST-1 ST-1 ST-1 ST-1 ST-2 ST-2 ST-2 ST-2 ST-2 ST-3 ST-3 ST-3 ST-3 ST-4 ST-4 ST-4 Title NATURALCIRC C/D WITHVESSEL HEAD VOID FORMATION NATURALCIRC C/D WITH VESSEL HEAD VOID FORMATION NATURALCIRC C/D WITH VESSEL HEAD VOID FORMATION NATURALCIRC C/D WITHVESSEL HEAD VOID FORMATION NATURALCIRC C/D WITHVESSEL HEAD VOID FORMATION ANTICIPATEDTRANSIENTW/0 SCRAM (ATWS)

ANTICIPATEDTRANSIENTW/0 SCRAM (ATWS)

ANTICIPATEDTRANSIENTW/0 SCRAM (ATWS)

ANTICIPATEDTRANSIENTW/0 SCRAM (ATWS)

ANTICIPATEDTRANSIENTW/0 SCRAM (ATWS)

STEAM GENERATOR TUBE RUPTURE STEAM GENERATOR TUBE RUPTURE STEAM GENERATOR TUBE RUPTURE STEAM GENERATOR TUBE RUPTURE UNIT2 REACTOR TRIP, NOVEMBER 13, 1985 UNIT2 REACTOR TRIP, NOVEMBER 13, 1985 UNIT2 REACTOR TRIP, NOVEMBER 13, 1985 Date Tested 3/30/94 3/31/95 12/20/96 3/28/97 3/27/98 6/10/94 6/26/95 12/20/96 6/25/97 6/2/98 9/29/94 10/6/95 12/20/96 9/26/97 12/17/94 12/20/96 12/30/97 Page 7 of 16 Attachment 1

Test Number COOK NUCLEARPLANTSIMULATOR MALFUNCTIONTESTING Title Date Tested CC06 CS03 CV09 CV26 CW02 ED03 ED07 ED16 ED19 ED20 ED24 EG03 EG11 FP05 FW05 FW30 FW42 FW56 IV[S03 MS12 NI06 NI10 RC03 RC07 RC17 RD08 RD12 RD16 RH15 RP03 RP12 RP20 RX08 RX16 RX24 RX28 SW01 SW05 TC02 SEAL WATERHXTUBE LEAK REFUELING WATER STORAGE TANKLEAK LETDOWNTEMPERATURE CONTROL FAILURE REACTOR COOLANTPUMP ¹1 SEAL FAILURE CW PUMP DISCHARGE VALVEFAILURE LOSS OF RESERVE AUXILIARYTRANSFORMER LOSS OF 480 VAC BUS AUXILIARIESAUTO BUS TRANSFER FAILURE ELECTRICALGRID LOADREJECTION ANNPANEL POWER SUPPLY FAILURE LOSS OF 250 VDC TRAIN "N" BATTERY MG AUTO VOLTAGEREG FAILURETO MANUAL DIESEL GENERATOR FAILURETO TRIP CONTROL ROOM CABLEVAULTFIRE MAINFEEDPUMP TURBINETRIP LP HTR ¹3 LVLCONTROL VALVEFAILURE CONDENSATE STORAGE TANKLEAK FEEDPUMP STEAM SUPPLY CONT FAILURE MAINSTM LINEBREAK OUTSIDE CONTAINMENT MSR DRAINTKALTDRAINLVLCONT FAILURE.

INTERMEDIATERANGE MONITORFAILURE POWER RANGE CHANNELFAILURE RCS LEAK REACTOR COOLANTPUMP LOCKED ROTOR PRESSURIZER PORV FAILURE IN-HOLD-OUTSWITCH FAILURE FAILUREOF CONTROL RODS TO MOVE IRPI FAILURE SI ACCUMULATORN2 PRESSURE LOSS FAILUREOF REACTOR TRIP BREAKER SPURIOUS ACTUATIONOF SI TRAIN "B" K600 RELAYFAILURES PZR SPRAY VALVEAUTO CONTROL FAILURE STEAM DUMP "PRESS CONTROL" ERRATIC OPS FW CONTROL VALVECONTROLLER FAILURE LOSS OF 480V MCC NON ESSENTIAL SERVICE WATER PUMP TRIP ESW PIPING RUPTURE MAINTURBINE FAILURETO TRIP 8/1/94 11/19/94 11/19/94 11/19/94 8/1/94 11/19/94 11/19/94 11/19/94 9/26/94-8/1/94 8/13/94 8/13/94 8/13/94 8/13/94 11/20/94 11/20/94 8/13/94 8/13/94 12/5/94 12/18/94 8/13/94 12/5/94 8/13/94 12/5/94 12/16/94 8/13/94 12/16/94 12/16/94 12/18/94 8/13/94 8/13/94 8/13/94 12/18/94 12/18/94 12/18/94 8/13/94 8/13/94 8/13/94 12/18/94 Page 8 of 16 Attachment 1

1 I'

, II 0

TU03 CC03 CC07 CH02 CS04 CV05 CV10 CV14 CV20 CV27 CV32 CW03 ED04 ED05 ED14 ED18 ED21 EG04 EG08 EG12 FP01 FW01 FW06 FW15 FW19 FW23 FW27 FW31 FW35 FW39 FW43 FW47 FW51 IA01 IA05 MS04 MS09 MS13 MS18 NI03 NI07 NI11 NI15 MAINTURBINEHIGH VIBRATION COMPONENT COOLING WATER RUPTURE COMPONENT COOLING HX TUBE RUPTURE CONTAIN. PRESSURE TRANSMITTERFAILURE RWST LEVELTRANSMITTERFAILURE LETDOWNHEAT EXCHANGER TUBE LEAK NORMALCHG LINELEAKINSIDE CONTAIN.

CHARGING PUMP SUCTION LINELEAKAGE INADVERTENTBORATION REACTOR COOLANTPUMP ¹2 SEAL FAILURE PW FLOW TRANSMITTER(QFC-422) FAILURE TRAVELINGWATER SCREEN FOULING LOSS OF EP SUPPLY TRANS TR-12-EP LOSS OF 4160 VAC BUS LOSS OF 250 VDC BATTERYCHARGER GRID VOLTAGEOSCILLATION 4KV/600V AUXTRANSFORMER LOSS MG AUTO VOLTAGEREGULATOR FAILURE DG SPEED GOVERNOR FAILURE DG OUTPUT BREAKER FAILURETO AUTO CLOSE FIRE PROTECTION SYSTEM RUPTURE MAINFEEDWATER RUPTURE AT SG INLET MFP TURBINE SHEARED SHAFT FEEDWATER CONTROL VALVEFAILURE HP HEATER ¹6 TUBE RUPTURE HP HEATER ¹5 TUBE-RUPTURE LP HTR ¹4 LVLCONTROL VALVEFAILURE LP HEATER ¹3 TUBE RUPTURE COND BOOSTER PP DISCHARGE PIPING RUPTURE CONDENSER TUBE LEAK HEAER DRAINPUMP TRIP AUXFEEDPUMP SUCTION LINELEAKAGE TDAFP TRIP &THROTTLE VALVEFAILURE PLANTAIR COMPRESSOR TRIP CONT AIR SYS RUPTURE IN CONTAINMENT MS LINEBREAKDOWNSTREAM OF SG STOP VLVS MSR TUBE RUPTURE MSR DRAINTKALTLVLCONTROL VALVE FAILURE STEAM DUMP CONTROL VALVEFAILURE INCORRECT SR CHANNELRESPONSE IR IMPROPER COMPENSATION PR CHANNELOUTPUT OSCILLATION POWER RANGE CHANNELBLOWN FUSE 8/13/94 7/17/95 1/14/95 6/20/95 11/14/95 1/14/95 7/17/95 11/14/95 1/14/95 6/20/95 7/17/95 6/20/95 11/14/95 6/20/95 6/26/95 7/17/95 7/17/95 1/14/95 6/26/95 7/17/95 11/14/95 11/17/95 2/12/95 3/3/95 6/26/95 8/28/95 6/26/95 11/17/95 9/13/95 11/17/95 3/3/95 6/26/95 9/13/95 3/3/95 11/17/95 3/6/95 12/31/95 9/13/95 12/31/95 11/17/95 3/6/95 6/26/95 9/28/95 Page 9 of 16 Attachment 1

p II II

RC04 RC08 RC14 RC19 RC25 RC29 RD01 RD05 RD09 RD13 RD17 RH03 RH07 RH12 RM01 RP05 RP09 RP13 RP15 RP17 RX01 RX05 RX09 RX13 RX17 RX21 RX25 SI01 SW02 SW06 TC03 TC07 TC12 TP03 TU01 TU05 CC04 CC08 CS01 CV01 CV06 CV11 CV15 CV21 PRESSURIZER SURGE LINELEAK REACTOR COOLANTPUMP SHAFT BREAK PZR HIGH GAS CONCENTRATION IN VAPOR SPACE PRESSURIZER SAFETY VALVEFAILURE SG BLOWDOWNLINELEAKDOWNSTREAM OF CIV SG BLOWDOWNLINELEAKUPSTREAM OF CIV DROPPED CONTROL ROD EJECT OF ROD WITHRUPTURED MECH HOUSING UNCONTROLLED ROD MOTIONDEMAND(AUTO)

ROD GROUP FAILURETO MOVE ROD GROUP STEP COUNTER FAILURE RHR HX BYPASS FLOW CONTROL VALVEFAILURE RHR NORMALSUCTION LINELKINSIDE CONT SI LOOP CHECK VALVELEAKAGE AREA RADIATIONMONITORFAILURE REACTOR COOLANT FLOW TRANSMITTERFAILURE FAILUREOF FW ISOLATIONTRIP TO OCCUR FAILUREOF CI PHASE A TO AUTO ACTUATE SPURIOUS ACTUATIONOF CI PHASE A FAILUREOF CI PHASE B TO MANUALLYACTUATE RCS HOT LEG PRESSURE TRANSMITTERFAILURE PRESSURIZER LVLTRANS FAILURE PZR PRESSURE MASTER CONTROLLER FAILURE STEAM DUMP "TAVG"CONTROLLER FAILURE SG PRESSURE TRANSMITTERFAILURE SG FEED FLOW TRANSMITTERFAILURE FEEDWATER CONTROL VALVEOSCILLATION SAFETY INJECTION PUMP TRIP NESW PIPING RUPTURE IN TURBINEBUILDING FP TURBINE OIL COOLING CONTROLLER FAILURE MAINTURBINEAUTO TRIP FAILURE MAINTURBINE INTERCEPT VALVEFAILURE MAINTURBINE SPEED SIGNALFAILURE i MG STATOR COOLING SYSTEM RUPTURE AUXILIARYLUBE OILPUMP TRIP MAINTURBINE BEARING FAILURE MISC CCW HEADER RUPTURE INSIDE CONT.

CCW LEAKAGEINTO RCP BEARING OILRES.

CONTAINMENTSPRAY PUMP TRIP LETDOWN LINERUPTURE INSIDE CONT.

LETDOWN PRESS CONT VLVFAILURE(QRV-301)

NORMALCHG LINELEAKOUTSIDE CONTAINMENT VCT LEVELCONTROL VALVEFAILURE INADVERTENTDILUTION 11/14/95 3/6/95 9/28/95 6/26/95 11/17/95 6/30/95 3/13/95 6/26/95 9/28/95 9/28/95 11/20/95 11/20/95 10/2/95 3/13/95 11/20/95 6/26/95 10/2/95 11/14/95 6/30/95 3/13/95 6/27/95 10/2/95 11/14/95 1/14/95 6/26/95 10/2/95 11/20/95 9/28/95 3/13/95 6/30/95 11/20/95 11/20/95 11/20/95 6/30/95 6/20/95 10/2/95 12/19/96 12/20/96 6/25/96 7/1/96 7/1/96 7/1/96 7/1/96 7/2/96 Page 10 of 16 Attachment 1

CV28 CV33 ED01 ED08 ED10 ED17 ED22 ED26 EG05 EG09 EG13 FP02 FW02 FW07 FW16 FW20 FW24 FW28 FW32 FW36 FW40 FW44 FW48 FW52 IA02 IA04 MS01 MS05 MS10 MS14 MS21 NI04 NI08 NI12 RC01 RC05 RC09 RC15 RC21 RC26 RD02 RD06 RD10 RD14 REACTOR COLANTPUMP ¹3 SEAL FAILURE BA FLOW CONTROLLER (QFC-421) FAILURE LOSS OF 345KV BUS NO. 1.

LOSS OF 600V MCC LOSS OF 120 VAC CONTROL ROOM POWER LOSS OF PLANT LIGHTING LOSS OF SWITCHGEAR CONT POWER TRAINB LOSS OF 765KV DUMONTLINE MG OUTPUT BREAKER FAILURETO TRIP DG VOLTAGECONTROL FAILURE DG OUTPUT BREAKER FAILURETO CLOSE INADVACT OF CHARCOALFILTFIRE PROT.

MFW RUPTURE BEFORE SG CHECK VALVE MAINFEEDPUMP TURBINEBEARING FAILURE HP HEATER ¹6 LVLCONT TRANSMITTERFAILURE HP HEATER ¹5 LVLCONT TRANSMITTERFAILURE HP HEATER ¹5 STEAM INLETRUPTURE LP HEATER ¹4 TUBE RUPTURE LP HEATER ¹3 STEAM INLETRUPTURE COND BOOSTER PP RECIRC VALVEFAILURE HOTWELLLEVELCONTROLLER FAILURE HEATER DRAINPUMP BEARING FAILURE AUXFEEDPUMP AUTO START FAILURE STEAM BOUND AFW PUMP PLANTAIRSYSTEM RUPTURE CONT AIR SYS RUPT IN TURBINEBUILDING MS LINEBREAKAT SG EXIT MAINSTEAM POWER RELIEF VALVELEAK MSR COIL DRAINTANKLVLCONT FAILURE MSR STEAM SUPPLY VALVEFAILURE AUXSTM 150¹ HDR CONTROL VALVEFAILURE SR ENERGIZATIONAT POWER (P10 FAILURE)

PR CHANNELUPPER DETECTOR FAILURE AUDIOCOUNT RATE CHANNELFAILURE RCS COLD LEG LOOP RUPTURE REACTOR VESSEL HEAD FLANGE LEAK REACTOR COOLANTPUMP TRIP RPESSURIZER SPRAY VALVEFAILURE PRT RUPTURE DISC FAILURE FAILEDFUEL ELEMENT BROKEN CONTROL ROD UNCONT ROD BANKCONTINUOUS WITHDRAWL CR MOVE OPPOSITE TO DEMANDSIGNAL IMPROPER BANKOVERLAP 12/20/96 12/20/96 6/26/96 6/26/96 6/28/96 12/19/96 12/20/96 6/26/96 7/2/96 12/20/96 12/20/96 12/20/96 7/3/96 7/3/96 12/20/96 12/20/96 7/8/96 7/8/96 12/20/96 12/20/96 7/8/96 7/22/96 7/22/96 12/20/96 7/23/96 7/23'/96 7/23/96 7/23/96 7/23/96 12/20/96 12/20/96 7/24/96 12/19/96 7/24/96 10/11/96 7/24/96 7/24/96 7/31/96 12/19/96 10/10/96 8/6/96 8/6/96 7/31/96 10/10/96 Page 11 of 16 Attachment 1

RD18 RH04 RH08 RH13 RM02 RP06 RP10 RP14 RP18 RX02 RX06 RX10 RX14 RX18 RX22 RX26 SI02 SW03 SW07 TC04 TC09 TC13 TP05 TU06 CC01 CC05 CC09 CCIO CS02 CV02 CV08 CV12 CV16 CV25 CV30 CW01 ED12 ED13 ED23 ED25 EG01 EG06 EG10 EG14 ROD CONTROL MG SET TRIP RHR HX FLOW CONTROL VALVEFAILURE RWST SUPPLY LINETO RHR PUMP RUPTURE SI ACC TANKCHECK VALVELEAKAGE PROCESS RADIATIONMONITORFAILURE SPURIOUS STEAM LINEISOLATION FAILUREOF SI TO ACTUATE-AUTOMATIC FAILUREOF CI PAHSE A TO MANUALACT SPURIOUS ACTUATIONOF CI PHASE B RCS HOT LEG TEMP TRANS FAILURE(NR)

PZR CALLEVELTRANSMITTERFAILURE PZR WATER LEVELCONT OSCILLATION STEAM DUMP PRESSURE CONTROLLER FAILURE MS TURB BYPASS HDR PRESS TRANS FAILURE SG PROGRAMMED LEVELSIGHNALFAILURE FP TURBINE SPEED CONTROLLER FAILURE SAFETY INJECTION PUMP SHEARED SHAFT NESW RUPT ON LWR CONT VENT CLR SUPPLY MT OILTEMPERATURE CONTROLLER FAILURE MAINTURBINE STOP VALVEFAILURE MAINGENERATOR LOAD LIMITERFAILURE TURBINERUNBACKFAILURE STATOR COOLING WTR SYS HIGH CONDUCTIVITY TURBINE BLADEEJECTION COMPONENT COOLING WATER PUMP TRIP MISC CCW HDR RUPTURE IN AUXBUILDING CCW LEAKON RHR PUMP SUPPLY LINE CCW LEAKAGEINTO RCP L. BRNG OILRESERV.

CONTAIN. SPRAY PUMP SUCTION BLOCKAGE LETDOWN LINERUPTURE OUTSIDE CONTAIN.

LETDOWN LINERELIEF VLVSV-51 LEAKAGE CCP FLOW CONTROL VALVEFAILURE VCT LEVELTRANSMITTERFAILURE RCP THERMALBARRIER HX RUPTURE REDUCED CCP CAPACITY CIRCULATINGWATER PUMP TRIP LOSS OF 250 VDC POWER (TRAINA)

LOSS OF 250 VDC POWER (TRAINB)

LOSS OF SWITCHGEAR CONT POWER TRAINA LOSS OF 765/345KV TRANSFORMER BANK¹4 MAINGENERATOR TRIP DIESEL GENERATOR TRIP DIESEL GENERATOR FAILURETO START DG RUNNING RELAYFAILURE 7/31/96 10/9/96 10/9/96 12/19/96 10/8/96 8/6/96 8/6/96 12/19/96 8/6/96 8/7/96 12/19/96 12/19/96 8/7/96 8/7/96 Deleted 8/8/96 12/20/96 8/8/96 12/19/96 8/8/96 8/8/96 12/20/96 8/8/96 8/8/96 10/13/97 10/27/97 10/27/97 10/30/97 10/27/97 10/27/97 10/13/97 10/13/97 10/13/97 13/13/97 10/16/97 10/16/97 10/16/97 10/27/97 10/27/97 10/27/97 10/16/97 10/16/97 10/16/97 10/23/97 Page 12 of 16 Attachment 1

FP03 FW03 FW12 FW17 FW21 FW25 FW29 FW33 FW37 FW41 FW45 IA03 MS02 MS06 MS11 MS16 NI01 NI05 NI09 NI13 RC02 RC06 RC10 RC11 RC12 RC16 RC23 RC27 RD03 RD07 RD11 RD15 RD19 RH01 RH05 RH09 RH14 RM03 RP01 RP07 RP11 RP19 RP21 RX03 DIESEL GENERATOR ROOM CO2 ACTUATION MFW RUPT BETWEEN FEEDFLOW ELMT&FRV FEEDPUMP TURBINE LUBE OIL SYSTEM LEAK HP HTR ¹6 LVLCONTROLLER AUTO FAILURE HP HTR ¹5 LVLCONTROLLER AUTO FAILURE HOTWELLPUMP TRIP LP HTR ¹3 LVLCONT TRANSMITTERFAIL LP HEATER BY PASS VALVEFAILURE HOTWELLPUMP DISCHARGE PIPING RUPTURE HW LEVELCONTROL TRANSMITTERFAILURE HEATER DRAINPUMP ELO VLVFAILS OPEN CONTROL AIR COMPRESSOR TRIP MAINSTEAM LINEBREAKAT SG EXIT STEAM GENERATOR SAFETY VALVELEAK MSR COIL DRAINTANKLVLCONT LVLFAIL STEAM SEAL CONTROLLER FAILURE SOURCE RANGE MONITORFAILURE SOURCE RANGE CHANNELSPIKES PR CHANNELLOWER DETECTOR FAILURE SOURCE RANGE INSTRUMENTBLOWN FUSE RCS HOT LEG LOOP LEAK RCS EMERGENCY VENT LEAKAGE RCS COLD LEG LEAK REACTOR COOLANT PUMP HIGH VIBRATION RCP LOWER BEARING OILRESERVOIR LEAK PRESSURIZER STEAM SPACE MANWAYLEAK STEAM GENERATOR TUBE RUPTURE RTD BYPASS MANIFOLDFLOW DEGRADATION STUCK CONTROL ROD (TRIPPABLE)

UNCONT ROD BANKCONTINUOUS INSERTION AUTO CONTROL ROD SPEED FAILURE IRPI POWER LOSS IMPOPER ROD WORTH RHR PUMP TRIP RHR HEAT EXCHANGER TUBE LEAK RHR PUMP SUCTION PIPE RUPTURE SI ACCUMULATORTANKLEVELLOW EBERLINE AREA RADIATIONMONITORFAILURES REACTOR TRIP ACB AUTO TRIP FAILURE

~

FAILUREOF STEAM LINEISO TO ACTIVATE FAILUREOF SI TO ACTUATE-MANUALLY TRAIN "A"K600 RELAYFAILURES FAILUREOF FWI TRIP TO OCCUR RCS COLD LEG TEMP TRANS FAILURE(NR) 10/16/97 10/27/97 10/16/97 10/27/97 10/27/97 10/25/97 10/27/97 10/22/97 10/27/97 10/28/97 10/23/97 10/21/97 10/21/97 10/28/97 10/28/97 10/28/97 10/28/97 10/28/97 10/28/97 10/21/97 10/28/97 12/15/97 10/30/97 10/28/97 12/15/97 10/29/97 10/21/97 10/29/97 10/28/97 10/28/97 10/28/97 10/27/97 12/16/97 10/21/97 10/30/97 10/29/97 10/30/97 10/31/97 10/21/97 10/21/97 10/21/97 10/21/97 10/30/97 10/22/97 Page 13 of 16 Attachment 1

4 II

RX07 RX11 RX19 RX23 RX29 SI03 SW04 TC01 TC05 TC10 TP01 REDUCED PRESSURIZER HEATER CAPACITY SG RELIEF VALVECONTROLLER FAILURE TURBINEIMPULSE TRANSMITTERFAILURE SG LEVELTRANSMITTERFAILURE FPC-250 TRANSMITTERFAILURE HIGH HEAD SI LINERUPTURE ESSENTIAL SERVICE WATER PUMP TRIP MAINTURBINETRIP MAINTURBINE CONTROL VALVEFAILURE MAINGEN OPERATING DEVICE FAILURE TURBINEAUXCOOLING PUMP TRIP CC02 CC06 CH01 CS03 CV04 CV09 CV13 CV17 CV26 CV31 CW02 ED02 ED03 ED06 ED07 ED11 ED15 ED16 ED19 ED20 ED24 EG03 EG07 EG11 EG15 FP05 FW05 FW18 FW22 FW26 FW30 FW34 CCW PUMP FAILURETO AUTO START SEAL WATER HX TUBE LEAK CONTAIN. PRESS. RELIEF VLVFAILURE REFUELING WATER STORAGE TANKLEAK LETDOWWNLINE ORIFICE ISO. VLVFAILURE LETDOWNTEMPERATURE CONTROL FAILURE CHARGING PUMP TR&

VOLUMECONTROL TANKLEAKAGE REACTOR COOLANTPUMP ¹1 SEAL FAILURE BACKPRESSURE CONT VLVFAILURE-QRV-200 CW PUMP DISCHARGE VALVEFAILURE LOSS OF AUXILIARYTRANSFORMER LOSS OF RESERVE AUXILIARYTRANSFORMER LOSS OF 600 VAC BUS LOSS OF 480 VAC BUS LOSS OF 250 VDC BUS LOSS OF VITALINST BUS STATIC SWITCH AUXILIARIESAUTO BUS TRANSFER FAILURE ELECTRICALGRID LOADREJECTION ANNPANEL POWER SUPPLY FAILURE LOSS OF 250 VDC TRAIN "N" BATTERY MG AUTO VOLTAGEREG FAILURETO MANUAL DG SPEED CONTROL FAILURE DIESEL GENERATOR FAILURETO TRIP MG SEAL OILUNITPIPING RUPTURE CONTROL ROOM CABLEVAULTFIRE MAINFEEDPUMP TURBINETRIP HP HTR ¹6 LVLCONTROL VALVEFAILURE HP HTR ¹5 LVLCONTROL VALVEFAILURE LP HTR ¹4 LVLCONT TRANSMITTERFAIL LP HTR ¹3 LVLCONTROL VALVEFAILURE CONDENSATE BOOSTER PUMP TRIP WD01 RELEASE OF RADIOACTIVEGAS FROM GDT 10/21/97 10/21/97 10/21/97 10/22/97 10/30/97 10/30/97 10/22/97 10/22/97 10/22/97 10/30/97 10/22/97 10/30/97 7/13/98 7/13/98 7/13/98 7/13/98 7/13/98 7/13/98 7/13/98 7/13/98 7/13/98 7/13/98 7/13/98 7/13/98 7/13/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/14/98 7/15/98 7/15/98 7/15/98 Page 14 of 16 Attachment 1

4 I

I

FW38 FW42 FW46 FW50 FW54 FW56 MS03 MS08 MS12 MS17 NI02 NI06 NI10 NI14 RC03 RC07 RC13 RC17 RC24 RC28 RD04 RD08 RD16 RH02 RH06 RH11 RH15 RP03 RP08 RP12 RP16 RP20 RX04 RX08 RX12 RX16 RX20 RX24 RX27 RX28 SW01 SW05 TC02 TC06 LOSS OF CONDENSER VACUUM CONDENSATE STORAGE TANKLEAK AUXFEEDPUMP TRIP TDAFWPUMP SPEED CONTROLLER FAILURE FDWTR RUPT OUTSIDE CONTAINMENT FEED PUMP STEAM SUPPLY CONT FAILURE MAINSTM LINEBREAK OUTSIDE CONT SG STOP VALVEDRIFTS SHUT MSR DRAINTKALTDRAINLVLCONT FAIL STEAM SEAL CONTROLLER OSCILLATION SOURCE RANGE HV FAILURETO DEENERGIZE INTERMEDIATERANGE MONITORFAILURE POWER RANGE CHANNELFAILURE INTERMEDIATERANGE CHANNELBLOWN FUSE RCS LEAK REACTOR COOLANTPUMP LOCKED ROTOR RCP UPPER BEARING OIL RESERVOIR LEAK PRESSURIZER PORV FAILURE STEAM GENERATOR TUBE LEAK PRESSURIZER INSTRUMENTLINELEAKAGE STUCK CONTROL ROD (UNTRIPPABLE)

IN-HOLD-OUTSWITCH FAILURE IRPI FAILURE RHR PUMP SEAL FAILURE RHR INJ HDR RELIEF VALVEFAIL(SV-104)

RHR RET FLOW TRANS FAILURE(IFI-335)

SI ACCUMULATORN2 PRESSURE LOSS FAILUREOF REACTOR TRIP BREAKER SPURIOUS FEEDWATER ISLOATIONTRIP SPURIOUS ACTUATIONOF SI FAILUREOF CI PHASE B TO AUTO ACTUATE TRAIN "B" K600 RELAYFAILURES PRESSURIZER PRESSURE TRANS FAILURE PZR SPRAY VALVEAUTO CONTROL FAILURE MS RELIEF VLVCONTROLLER OSCILLATION STEAM DUMP "PRES CONT" ERRATIC OPS SG STEAM FLOW TRANSMITTERFAILURE FW CONTROL VALVECONTROLLER FAILURE FEED PUMP DP CONTROLLER FAILURE LOSS OF 480V MCC NON ESSENTIAL SERVICE WATER PUMP TRIP ESW PIPING RUPTURE MAINTURBINE FAILURETO TRIP MAINTURBINE ERRATIC CONTROL VALVE 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/15/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/16/98 7/17/98 7/17/98 7/17/98 7/17/98 7/17/98 7/17/98 7/17/98 7/17/98 7/17/98 Page 15 of 16 Attachment 1

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TC11 AUTO LOAD SET OSCILLATION TP02 TURBINEAUXCOOLING PIPING RUPTURE TU03 MAINTURBINE HIGH VIBRATION 7/17/98 7/17/98 7/17/98 Page 16 of 16 Attachment 1

ATTACHMENT2 COOK PLANTSIMULATOR CERTIFICATIONTEST SCHEDULE The following pages consist of the Cook Nuclear Plant Simulator Certification schedule through the year 2002. This section is designed to meet the requirements ofAppendices A and B ofANSI 3.5, 1985 performance testing.

Page 1 of 11

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COOK NUCLEARPLANTSIMULATOR ANSI 3.5 APPENDICIES AANDB ANNUALTESTING SCHEDULE QTR 1 CRT-1 SS-01 TR2 SS-02 TR3 SS-03 TR4 SS-04 TRANS-01 TRANS-02 TRANS-03 TRANS-04 TRANS-05 TRANS-06 TRANS-07 TRANS-08 TRANS-09 TRANS-1 0 TRANS-11 NORMALPLANTEVOLUTION TESTING SCHEDULE 1999 NPE-1 NPE-5 2000 NPE-2 NPE-6 2001 NPE-3 NPE-7 2002 NPE-4 Test Descri CRT-1 SS-1 SS-2 SS-3 SS-4 Trans-01 Trans-02 Trans-03 Trans-04 Trans-05 Trans-06 Trans-07 Trans-08 Trans-09 Trans-10 Trans-11 NPE-1 NPE-2 NPE-3 NPE-4 NPE-5 tions:

Computer Real Time Test Steady State Test 1

Steady State Test 2 Steady State Test 3 Steady State Test 4 Manual Reactor-Trip Trip ofall Main Feedpumps Closure ofall MSIV's Trip ofall Reactor Coolant Pumps Trip ofReactor Coolant Pump 823 Main Turbine Trip W/0 Reactor Trip Maximum Power Ramp 100%-75%-100%

Maximum Size Loca with Blackout Maximum Size Main Steamline Rupture Slow RCS Depressurization to Saturation Load Rejection RCS Filland Vent Cold Shutdown to Hot Standby Reactor Startup Plant Startup/Power Escalation Power Reduction Page 2 of 11

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NPE-6 Plant Cooldown NPE-7 RCS Drain Page 3 of 11

MALFUNCTIONTEST SCHEDULE Test Number CC03 CC07 CH02 CH03 CS04 CV05 CV10 CV14 CV20 CV27 CV32 CW03 ED04 ED05 ED14 ED18 ED21 EG04 EG08 EG12 FP01 FP06 FW01 FW06 FW15 FW19 FW23 FW27 FW31 FW35 FW39 FW43 FW47 FW51 IA01 IA05 MS04 MS09 Title COMPONENT COOLING WATER RUPTURE COMPONENT COOLING HX TUBE RUPTURE CONTAIN. PRESSURE TRANSMITTERFAILURE CONTAIN. PRESSURE TRANSMITTERFAILURE(WR)

RWST LEVELTRANSMITTERFAILURE LETDOWNHEAT EXCHANGER TUBE LEAK NORMALCHG LINELEAKINSIDE CONTAIN, CHARGING PUMP SUCTION LINELEAKAGE INADVERTENTBORATION REACTOR COOLANTPUMP ¹2 SEAL FAILURE PW FLOW TRANSMITTER(QFC-422) FAILURE TRAVELINGWATER SCREEN FOULING LOSS OF EP SUPPLY TRANS TR-12-EP LOSS OF 4160 VAC BUS LOSS OF 250 VDC BATTERYCHARGER GRID VOLTAGEOSCILLATION 4KV/600V AUXTRANSFORMER LOSS MG AUTO VOLTAGEREGULATOR FAILURE DG SPEED GOVERNOR FAILURE DG OUTPUT BREAKER FAILURETO AUTO CLOSE FIRE PROTECTION SYSTEM RUPTURE FIRE PROTECTION STORAGE TANKLEAK MAINFEEDWATER RUPTURE AT SG INLET MFP TURBINE SHEARED SHAFT FEEDWATER CONTROL VALVEFAILURE HP HEATER ¹6 TUBE RUPTURE HP HEATER ¹5 TUBE RUPTURE LP HTR ¹4 LVLCONTROL VALVEFAILURE LP HEATER ¹3 TUBE RUPTURE.

COND BOOSTER PP DISCHARGE PIPING RUPTURE CONDENSER TUBE LEAK HEAER DRAINPUMP TRIP AUXFEEDPUMP SUCTION LINELEAKAGE TDAFP TRIP &THROTTLE VALVEFAILURE PLANT AIR COMPRESSOR TRIP CONT AIR SYS RUPTURE IN CONTAINMENT MS LINEBREAK DOWNSTREAM OF SG STOP VLVS MSR TUBE RUPTURE Scheduled 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 Page 4 of 11

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MS13 MS18 NI03 NI07 NI11 NI15 RC04 RC08 RC14 RC19 RC25 RC29 RD01 RD05 RD09 RD13 RD17 RD20 RH03 RH07 RH12 RM01 RP05 RP09 RP13 RP15 RP17 RX01 RX05 RX09 RX13 RX17 RX21 RX25 SI01 SW02 SW06 TC03 TC07 TC12 TP03 TU01 TU05 CC04 MSR DRAINTKALTLVLCONTROL VALVE FAILURE STEAM DUMP CONTROL VALVEFAILURE INCORRECT SR CHANNELRESPONSE IR IMPROPER COMPENSATION PR CHANNELOUTPUT OSCILLATION POWER RANGE CHANNELBLOWN FUSE PRESSURIZER SURGE LINELEAK REACTOR COOLANTPUMP SHAFT BREAK PZR HIGH GAS CONCENTRATION IN VAPOR SPACE PRESSURIZER SAFETY VALVEFAILURE SG BLOWDOWNLINELEAKDOWNSTREAM OF CIV SG BLOWDOWNLINELEAKUPSTREAM OF CIV DROPPED CONTROL ROD EJECT OF ROD WITHRUPTURED MECH HOUSING UNCONTROLLED ROD MOTIONDEMAND(AUTO)

ROD GROUP FAILURETO MOVE ROD GROUP STEP COUNTER FAILURE ROD CONTROL POWER CABINETFAILURE RHR HX BYPASS FLOW CONTROL VALVEFAILURE RHR NORMALDC SUCTION LINELKINSIDE CONT SI LOOP CHECK VALVELEAKAGE AREA RADIATIONMONITORFAILURE REACTOR COOLANE FLOW TRANSMITTERFAILURE FAILUREOF FW ISOLATIONTRIP TO OCCUR FAILUREOF CI PHASE A TO AUTO ACTUATE SPURIOUS ACTUATIONOF CI PHASE A FAILUREOF CI PHASE B TO MANUALLYACTUATE RCS HOT LEG PRESSURE TRANSMITTERFAILURE PRESSURIZER LVLTRANS FAILURE PZR PRESSURE MASTER CONTROLLER FAILURE STEAM DUMP "TAVG"CONTROLLER FAILURE SG PRESSURE TRANSMITTERFAILURE SG FEED FLOW TRANSMITTERFAILURE FEEDWATER CONTROL VALVEOSCILLATION SAFETY INJECTION PUMP TRIP NESW PIPING RUPTURE IN TURBINEBUILDING FP TURBINE OIL COOLING CONTROLLER FAILURE MAINTURBINEAUTO TRIP FAILURE MAINTURBINE INTERCEPT VALVEFAILURE MAINTURBINE SPEED SIGNALFAILURE MG STATOR COOLING SYSTEM RUPTURE AUXILIARYLUBE OIL PUMP TRIP MAINTURBINEBEARING FAILURE MISC CCW HEADER RUPTURE INSIDE CONT.

1999 1999

'999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 1999 2000 Page 5 of 11

CC08 CH04 CS01 CV01 CV06 CV11 CV15 CV21 CV28 CV33 ED01 ED08 ED10 ED17 ED22 ED26 EG05 EG09 EG13 FP02 FW02 FW07 FW16 FW20 FW24 FW28 FW32 FW36 FW40 FW44 FW48 FW52 FW58 IA02 IA04 MS01 MS05 MS10 MS14 MS21 NI04 NI08 NI12 RC01 RC05 CCW LEAKAGEINTO RCP BEARING OILRES.

CONTAINMENTLEAKAGE CONTAINMENTSPRAY PUMP TRIP LETDOWN LINERUPTURE INSIDE CONT.

LETDOWN PRESS CONT VLVFAILURE(QRV-301)

NORMALCHG LINELEAKOUTSIDE CONTAINMENT VCT LEVELCONTROL VALVEFAILURE INADVERTENTDILUTION REACTOR COLANTPUMP ¹3 SEAL FAILURE BA FLOW CONTROLLER (QFC-421) FAILURE LOSS OF 345KV BUS NO. 1 LOSS OF 600V MCC LOSS OF 120 VAC CONTROL ROOM POWER LOSS OF PLANTLIGHTING LOSS OF SWITCHGEAR CONT POWER TRAINB LOSS OF 765KV DUMONTLINE MG OUTPUT BREAKER FAILURETO TRIP DG VOLTAGECONTROL FAILURE DG OUTPUT BREAKER FAILURETO CLOSE INADVACT OF CHARCOALFILTFIRE PROT.

MFW RUPTURE BEFORE SG CHECK VALVE MAINFEEDPUMP TURBINE BEARING FAILURE

'P HEATER ¹6 LVLCONT TRANSMITTERFAILURE HP HEATER ¹5 LVLCONT TRANSMITTERFAILURE HP HEATER ¹5 STEAM INLETRUPTURE LP HEATER ¹4 TUBE RUPTURE LP HEATER ¹3 STEAM INLETRUPTURE COND BOOSTER PP RECIRC VALVEFAILURE HOTWELLLEVELCONTROLLER FAILURE HEATER DRAINPUMP BEARING FAILURE AUXFEEDPUMP AUTO START FAILURE STEAM BOUND AFW PUMP CBP FAILURETO AUTO START PLANTAIRSYSTEM RUPTURE CONT AIR SYS RUPT IN TURBINEBUILDING MS LINEBREAKAT SG EXIT MAINSTEAM POWER RELIEF VALVELEAK MSR COIL DRAINTANKLVLCONT FAILURE MSR STEAM SUPPLY VALVEFAILURE AUXSTM 150¹ HDR CONTROL VALVEFAILURE SR ENERGIZATIONAT POWER (P10 FAILURE)

PR CHANNELUPPER DETECTOR FAILURE AUDIOCOUNT RATE CHANNELFAILURE RCS COLD LEG LOOP RUPTURE REACTOR VESSEL HEAD FLANGE LEAK 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 Page 6 of 11

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RC09 RC15 RC21 RC26 RD02 RD06 RD10 RD14 RD18 RH08 RH13 RM02 RP06 RP10 RP14 RP18 RP22 RX02 RX06 RX10 RX14 RX18 RX26 SI02 SW03 SW07 TC04 TC09 TC13 TP05 TU06 CC01 CC05 CC09 CC10 CS02 CV02 CV08 CV12 CV16 CV25 CV30 CV34 CW01 REACTOR COOLANTPUMP TRIP RPESSURIZER SPRAY VALVEFAILURE PRT RUPTURE DISC FAILURE FAILEDFUEL ELEMENT BROKEN CONTROL ROD UNCONT ROD BANKCONTINUOUS WITHDRAWL CR MOVE OPPOSITE TO DEMANDSIGNAL IMPROPER BANKOVERLAP ROD CONTROL MG SET TRIP RHR HX FLOW CONTROL VALVEFAILURE RWST SUPPLY LINETO RHR PUMP RUPTURE SI ACC TANKCHECK VALVELEAKAGE PROCESS RADIATIONMONITORFAILURE SPURIOUS STEAM LINEISOLATION FAILUREOF SI TO ACTUATE-AUTOMATIC FAILUREOF CI PAHSE A TO MANUALACT SPURIOUS ACTUATIONOF CI PHASE B RPS RELAYK621X2 FAILURE RCS HOT LEG TEMP TRANS FAILURE(NR)

PZR CALLEVELTRANSMITTERFAILURE PZR WATER LEVELCONT OSCILLATION STEAM DUMP PRESSURE CONTROLLER FAILURE MS TURB BYPASS HDR PRESS TRANS FAILURE FP TURBINE SPEED CONTROLLER FAILURE SAFETY INJECTION PUMP SHEARED SHAFT NESW RUPT ON LWR CONT VENT CLR SUPPLY MT OILTEMPERATURE CONTROLLER FAILURE MAINTURBINE STOP VALVEFAILURE MAINGENERATOR LOAD LIMITERFAILURE TURBINERUNBACKFAILURE STATOR COOLING WTR SYS HIGH CONDUCTIVITY TURBINEBLADEEJECTION COMPONENT COOLING WATER PUMP TRIP MISC CCW HDR RUPTURE IN AUXBUILDING CCW LEAKON RHR PUMP SUPPLY LINE CCW LEAKAGEINTO RCP L. BRNG OIL RESERV.

CONTAIN. SPRAY PUMP SUCTION BLOCKAGE LETDOWN LINERUPTURE OUTSIDE CONTAIN.

LETDOWN LINERELIEF VLVSV-51 LEAKAGE CCP FLOW CONTROL VALVEFAILURE VCT LEVELTRANSMITTERFAILURE RCP THERMALBARRIER HX RUPTURE REDUCED CCP CAPACITY CHG FLOW INSTRUMENTFAILURE(QFI-200)

CIRCULATINGWATER PUMP TRIP 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 Page 7 of 11

ED12 ED13 ED23 ED25 EG01 EG06 EG10 EG14 FP03 FW03 FW12 FW17 FW21 FW25 FW29 FW33 FW37 FW41 FW45 IA03 MS02 MS06 MS11 MS16 MS22 NI01 NI05 NI09 NI13 RC02 RC06 RC10 RC11 RC12 RC16 RC23 RC27 RD03 RD07 RD11 RD15 RD19 RH01 RH05 RH09 LOSS OF 250 VDC POWER (TRAINA)

LOSS OF 250 VDC POWER (TRAINB)

LOSS OF SWITCHGEAR CONT POWER TRAINA LOSS OF 765/345KV TRANSFORMER BANK¹4 MAINGENERATOR TRIP DIESEL GENERATOR TRIP DIESEL GENERATOR FAILURETO START DG RUNNING RELAYFAILURE DIESEL GENERATOR ROOM CO2 ACTUATION MFW RUPT BETWEEN FEEDFLOW ELMT&FRV FEEDPUMP TURBINE LUBE OIL SYSTRM LEAK HP HTR ¹6 LVLCONTROLLER AUTO FAILURE HP HTR ¹5 LVLCONTROLLER AUTO FAILURE HOTWELLPUMP TRIP LP HTR ¹3 LVLCONT TRANSMITTERFAIL LP HEATER BY PASS VALVEFAILURE HOTWELLPUMP DISCHARGE PIPING RUPTURE HW LEVELCONTROL TRANSMITTERFAILURE HEATER FRAIN PUMP ELO VLVFAILS OPEN CONTROL AIR COMPRESSOR TRIP MAINSTEAM LINEBREAKAT SG EXIT STEAM GENERATOR SFETY VALVELEAK MSR COIL DRAINTANKLVLCONT LVLFAIL STEAM SEAL CONTROLLER FAILURE MSIVMECHANICALBINDING SOURCE RANGE MONITORFAILURE SOURCE RANGE CHANNELSPIKES PR CHANNELLOWER DETECTOR FAILURE SOURCE RANGE INSTRUMENTBLOWNFUSE RCS HOT LEG LOOP LEAK RCS EMERGENCY VENT LEAKAGE RCS COLD LEG LEAK REACTOR COOLANTPUMP HIGH VIBRATION RCP LOWER BEARING OIL RESERVOIR LEAK PRESSURIZER STEAM SPACE MANWAYLEAK STEAM GENERATOR TUBE RUPTURE RTD BYPASS MANIFOLDFLOW DEGRADATION STUCK CONTROL ROD (TRIPPABLE)

UNCONT ROD BANKCONTINUOUS INSERTION AUTO CONTROL ROD SPEED FAILURE IRPI POWER LOSS IMPOPER ROD WORTH RHR PUMP TRIP RHR HEAT EXCHANGER TUBE LEAK RHR PUMP SUCTION PIPE RUPTURE 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 Page 8 of 11

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RH14 RM03 RPOl RP07 RP11 RP19 RP21 RX03 RX07 RX11 RX15 RX19 RX23 RX29 SI03 SW04 TC01 TC05 TC10 TP01 WD01 CC02 CC06 CH01 CS03 CV04 CV09 CV13 CV17 CV26 CV31 CW02 ED02 ED03 ED06 ED07 ED11 ED15 ED16 ED19 ED20 ED24 EG03 EG07 EG11 SI ACCUMULATORTANKLEVELLOW EBERLINE AREA RADIATIONMONITORFAILURES REACTOR TRIP ACB AUTO TRIP FAILURE FAILUREOF STEAM LINEISO TO ACTIVATE FAILUREOF SI TO ACTUATE-MANUALLY TRAIN "A"K600 RELAYFAILURES FAILUREOF FWI TRIP TO OCCUR RCS COLD LEG TEMP TRANS FAILURE(NR)

REDUCED PRESSURIZER HEATER CAPACITY SG RELIEF VALVECONTROLLER FAILURE STEAM DUMP FAILURETO RESPOND TURBINE IMPULSE TRANSMITTERFAILURE SG LEVELTRANSMITTERFAILURE

, FPC-250 TRANSMITTERFAILURE HIGH HEAD SI LINERUPTURE ESSENTIAL SERVICE WATER PUMP TRIP MAINTURBINE TRIP, MAINTURBINE CONTROL VALVEFAILURE MAINGEN OPERATING DEVICE FAILURE TURBINE AUXCOOLING PUMP TRIP RELEASE OF RADIOACTIVEGAS FROM GDT CCW PUMP FAILURETO AUTO START SEAL WATER HX TUBE LEAK CONTAIN. PRESS. RELIEF VLVFAILURE REFUELING WATER STORAGE TANKLEAK(

LETDOWWNLINE ORIFICE ISO. VLVFAILURE LETDOWNTEMPERATURE CONTROL FAILURE CHARGING PUMP TRIP VOLUMECONTROL TANKLEAKAGE REACTOR COOLANT PUMP ¹1 SEAL FAILURE BACKPRESSURE CONT VLVFAILURE-QRV-200 CW PUMP DISCHARGE VALVEFAILURE LOSS OF AUXILIARYTRANSFORMER LOSS OF RESERVE AUXILIARYTRANSFORMER LOSS OF 600 VAC BUS LOSS OF 480 VAC BUS LOSS OF 250 VDC BUS LOSS OF VITALINST BUS STATIC SWITCH AUXILIARIESAUTO BUS TRANSFER FAILURE ELECTRICALGRID LOADREJECTION ANNPANEL POWER SUPPLY FAILURE LOSS OF 250 VDC TRAIN "N" BATTERY MG AUTO VOLTAGEREG FAILURETO MANUAL DG SPEED CONTROL FAILURE DIESEL GENERATOR FAILURETO TRIP 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2001 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 Page 9 of 11

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EG15 BP05 FW05 FW18 FW22 FW26 FW30 FW34 FW38 FW42 FW46 FW50 FW54 FW56 MS03 MS08 MS12 MS17 NI02 NI06 NI10 NI14 RC03 RC07 RC13 RC17 RC24 RC28 RD04 RD08 RD16 RH02 RH06 RH11 RH15 RP03 RP08 RP12 RP16 RP20 RX04 RX08 RX12 RX16 RX20 MG SEAL OILUNITPIPING RUPTURE CONTROL ROOM CABLEVAULTFIRE MAINFEEDPUMP TURBINE TRIP HP HTR ¹6 LVLCONTROL VALVEFAILURE HP HTR ¹5 LVLCONTROL VALVEFAILURE LP HTR ¹4 LVLCONT TRANSMITTERFAIL LP HTR ¹3 LVLCONTROL VALVEFAILURE CONDENSATE BOOSTER PUMP TRIP LOSS OF CONDENSER VACUUM CONDENSATE STORAGE TANKLEAK AUXFEEDPUMP TRIP TDAFWPUMP SPEED CONTROLLER FAILURE FDWTR RUPT OUTSIDE CONTAINMENT FEED PUMP STEAM SUPPLY CONT FAILURE MAINSTM LINEBREAK OUTSIDE CONT SG STOP VALVEDRIFTS SHUT MSR DRAINTKALTFRAINLVLCONT FAIL STEAM SEAL CONTROLLER OSCILLATION SOURCE RANGE HVFAILURETO DEENERGIZE INTERMEDIATERANGE MONITORFAILURE POWER RANGE CHANNELFAILURE INTERMEDIATERANGE CHANNELBLOWN FUSE RCS LEAK REACTOR COOLANTPUMP LOCKED ROTOR RCP UPPER BEARING OIL RESERVOIR LEAK PRESSURIZER PORV FAILURE STEAM GENERATOR TUBE LEAK PRESSURIZER INSTURMENTLINELEAKAGE STUCK CONTROL ROD (UNTRIPPABLE)

IN-HOLD-OUTSWITCH FAILURE IRPI FAILURE RHR PUMP SEAL FAILURE RHR INJ HDR RELIEF VALVEFAIL(SV-104)

RHR RET FLOW TRANS FAILURE(IFI-335)

SI ACCUMULATORN2 PRESSURE LOSS FAILUREOF REACTOR TRIP BREAKER SPURIOUS FEEDWATER ISLOATIONTRIP SPURIOUS ACTUATIONOF SI FAILUREOF CI PHASE B TO AUTO ACTUATE TRAIN "B" K600 RELAYFAILURES PRESSURIZER PRESSURE TRANS FAILURE PZR SPRAY VALVEAUTO CONTROL FAILURE MS RELIEF VLVCONTROLLER OSCILLATION STEAM DUMP "PRES CONT" ERRATIC OPS SG STEAM FLOW TRANSMITTERFAILURE 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 Page 10 of 11

RX24 FW CONTROL VALVECONTROLLER FAILURE RX27 FEED PUMP DP CONTROLLER FAILURE RX28 LOSS OF 480V MCC SW01 'ON ESSENTIAL'ERVICE WATER PUMP TRIP SW05 ESW PIPING RUPTURE TC02 MAINTURBINE FAILURETO TRIP TC06 MAINTURBINCE ERRATIC CONTROL VALVE TC11 AUTO LOAD SET OSCILLATION TP02 TURBINEAUXCOOLING PIPING RUPTURE TP06 STATOR COOLING TUBE LEAKAGE TU03 MAINTURBINE HIGH VIBRATION 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 2002 Page 11 of 11

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ATTACHMENT TO AEP:NRC:1260G9 RESTART PLAN REVISION