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 50-316 Donald C. Cook Nuclear Power .Plant, Unit 2, Indiana M 05000316 AUTH.24AME

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AUTHOR AFFILIATION POWERS,R.P.

~ ~ Indiana Michigan

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'wer Co. ~ (formerly Indiana 6 Michigan El'e

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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 Forms 474. A DISTRIBUTION CODE: A005D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Simulator Facility Certification - GL-90-08 NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 STANG,J 1 INTERNAL FILE NTER 0 1 1 EXTERNAL: NRC PDR 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

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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 My Commission Expires ~ VALERfE L BQMLt.

Puhio, Berrien CCenly, I 9

/jmc Attachments 9810140199 '781008 PDR ADOCK 05000315 P PDRr

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U.S, Nuclear Regulatory Commission AEP:NRC:1134B Page 2 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 AEP:NRC'1134B Page 3 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

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 31604136 EXPIRES: 06r3tr96 NRC FORM 474 (5-95)

/ 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.

SIMULATION FACILITYCERTIFICATION 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 COOK NUCLEAR PLANT '~

DOCKET NUMBER 315 LICENSEE DATE AMERICANELECTRIC POWER COMPANY 8/20/98 This is to cerbfy that

2. Documentabon is evaibible for NRC review In a~

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

with 10 CFR 55A5g>).

3, This simulsticn fscibty meets the guidance contained br ANSIiANs 3.5-1 955 or ANsl/ANs 3.5.1 993, as endorsed by NRQ Regulatory Guide 1.149.

If there are any ExcEPTIQNs to the cerbfication of this item, cHEGK HERE I ] snd descnbe fully on sddkonal pages as necessary.

NAME (or otteridendficadon) AND LOCATION OF SIMULATIONFACILITY.

COOK TRAINING CENTER ONE COOK PLACE BRIDGMAN,MI 49106 BIMUtATIQNFAQILITY pERFORMANCE TEST ABSTRACTS ATTACHED. (For performance tests conductedin lhe pekxf encfng with the dale of this cerdficabon)

DE 5c Rip TIQN 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.

BIMULATIQNFACtLITY PERFORMANCE TESTING SCHEDULE ATTACHED. (Fcv the conducf of appnuimsleiy 25'f pedonnsnce tests per year for the four~sr pedod commencing with lhe dele of this cerdlicsdon.)

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

No performance testing will be 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 piAN CHANGE. (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 of completed 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 civil and cnminsl ssncticns. I cerbly under penalty of periury that the inlcnnsten in this document snd attachments is bue and correcL SIGNATURE AUTHOR D REPRESENTATIVE DATE

/o/i/gr In a~

fogows:

with 10 CFR 55.5. Communicatior>>. Ibis foun shag be submitted to the NRQ as DIRECTOR, OFFICE OF NUCLEAR REACTQR REGULATIQN BY DELIVERY IN PERSON TO THE NRC OFFICE AT; ONE WHITE FUNT NORTH 116SS ROCKVILLE PIKE BY MAILADDRESSED TO:

U.S. NUCLEAR REGULATORY COMMISSION ROCKVILLE, MD WASHINGTON, DC 20S564001

DONALD C. COOK NUCLEAR PLANT SIMULATOR 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 of Federal 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 of this 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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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).

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 of Unit 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 of such 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, if different, to be conducted on the simulation facility during the subsequent four year period.

No performance testing specific to Unit 1 is scheduled for the next four-year period. All performance testing will be 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. All performance testing will be 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

NRC FORM 474 U.S. NUCLEAR REGULATORY'OMM(SS(ON APPROVED BY OMB: NO. 31$ M138 EXPIRES: 08I31I98 (8-95) 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.

SIMULATION FACILITYCERTIFICATION 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.

INBTRUG TIDNs: 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 DOCKET NUMBER, COOK NUCLEAR PLANT <O- 316 LICENSEE DATE AMERICANELECTRIC POWER COMPANY 8/20/98 This Is to certify thaL 1, The above named facility ticensee is using a simulation facility consisting 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 facility meets the guidance contained kt ANSVANS 3.5.1985 or ANSVANS 3.5-1993. as endorsed by NRC Regutstay Guide 1.149.

If Ihere are any ExcEpTIDNs to the cerufication of INs item, cHEGK HERE [ ] and describe fully on additional pages ss necessary.

NAME (or other rdenbltcsbon) AND LOCATIQN OF SIMULATIDNFAGILITY.

COOK TRAINING CENTER ONE COOK PLACE BRIDGMAN,MI 49106 siMULATIDNFAGILRY pERFoRMANGE 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.

SIMULATIONFACILITY PERFORMANCE TESTING SCHEDULE ATTACHED. (For the conduct of sPProxlmsrely 25'of Perfonnance rests Per year for the 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 Unit Two (Page 5 of 5).

REcERTIFIcATIQN (Descnbe corrective ecdons taken. errsch resorts of completed 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 civil and cnminal sancucns. I cerufy under penalty of peiiuiy that the infcnnsuon in this document and attachments is true and correcL SIGNATURE AUTHORIZED REPRESENTATIVE TITLE DATE u/ Nylfr In accordance vnth 10 CFR 55.5. Commuivcatens, this form shall be submitted to the NRc ss fotkiws: BY DELIVERY IN PERSON ONE WHITE FUNT NORTH BY MAILADDRESSED TO: DIRECTOR, OFRCE OF NUCLEAR REACTOR REGULATION TO THE NRC OFFICE AT: 1155$ ROCKVILLE PIKE U.S. NUCLEAR REGULATORY COMMISSION ROCKVILLE, MD WASHINGTON, DC 205554001

DONALD C. COOK NUCLEAR PLANT SIMULATOR FOUR-YEARREPORT UNIT 2 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 of Federal 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 of this 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, if different, to be conducted on the simulation facility during the subsequent four-year period. Subpart E, Section 55.45 (b)(5)(vi).

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4. A schedule for the conduct of approximately 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 of such performance failures.

Uncorrected performance test failures include:

DR 98026: RCS mass increase due to cycling of a 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 of transients.

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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 (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 of the 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 full power 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.

All transient 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 of new RETACT model) and also in October 1996 (testing of simulator rehost running on the Windows NTYi platform).

The data collected in the performance of these 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 of all 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.

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Requirement ¹3: Description of performance tests, if different, to be conducted on the simulation facility during 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 following were deleted from the malfunction list:

RD12: Failure of control 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 following were 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: MSIV mechanical 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.

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ATTACHMENT1 COOK PLANT SIMULATORCERTIFICATIONTESTING This attachment consists of testing information relative to the Cook Plant Simulator certification requirements. The sections of this 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 of the rehosted simulator configuration.

Normal Plant Evolutions scheduled for the first two quarters of 1996 were deferred to the last half of 1996. This was done to correspond to the testing of the 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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COOK NUCLEAR PLANT SIMULATOR REAL TIME TEST REPORT Test Number Title Date Tested CRT-1 COMPUTER REAL TIME TESTING 1/12/94 CRT-1 COMPUTER REAL TIME TESTING 3/13/95 CRT-1 COMPUTER REAL TIME TESTING 4/4/96 CRT-1 COMPUTER REAL TIME TESTING 3/28/97 CRT-1 COMPUTER REAL TIME TESTING 4/17/98 Page 2 of 16 Attachment 1

COOK NUCLEAR PLANT SIMULATOR STEADY STATE TESTING REPORT Test Number Title ower Level Date Tested SS-1 STEADY STATE (30%) 3/28/94 SS-2 STEADY STATE (47%) 6/26/94 SS-3 STEADY STATE (75%) 8/28/94 SS-4 STEADY STATE (100%)* 12/19/94 SS-1 STEADY STATE (30%) 3/1 3/95 SS-2 STEADY STATE (47%) 6/30/95 SS-3 STEADY STATE (75%) 10/4/95 SS-4 STEADY STATE (100%)* 12/17/95 SS-1 STEADY STATE (7%) 3/30/96 SS-2 STEADY STATE (33%) 6/12/96 SS-1 STEADY STATE (30%) 12/16/96 SS-2 STEADY STATE (47%) 12/16/96 SS-3 STEADY STATE (75%) 12/17/96 SS-4 STEADY STATE (100%)* 10/12/96 SS-1 STEADY STATE (27%) 3/31/97 SS-2 STEADY STATE (47%) 9/23/97 SS-3 STEADY STATE (75%) 6/25/97 SS-4 STEADY STATE (100%)* 12/30/97 SS-1 STEADY STATE (27%) 3/27/98 SS-2 STEADY STATE (47%) 6/2/98

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

Page 3 of 16 Attachment 1

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

COOK NUCLEAR PLANT SIMULATOR TRANSIENT TESTS Test Number Title Date Tested Trans 1 MANUALREACTOR TRIP 1/22/94 Trans 1 MANUALREACTOR TRIP 3/27/95 Trans 1 MANUALREACTOR TRIP 4/4/96 Trans 1 MANUALREACTOR TRIP 5/10/96 Trans 1 MANUALREACTOR TRIP 10/10/96 Trans 1 MANUALREACTOR TRIP 3/28/97 Trans 1 MANUALREACTOR TRIP 3/27/98 Trans 2 TRIP OF ALL MAIN FEEDPUMPS 6/10/94 Trans 2 TRIP OF ALL MAIN FEEDPUMPS 6/26/95 Trans 2 TRIP OF ALL MAIN FEEDPUMPS 5/1 0/96 Trans 2 TRIP OF ALL MAIN FEEDPUMPS 10/10/96 Trans 2 TRIP OF ALL MAIN FEEDPUMPS 5/1/97 Trans 2 TRIP OF ALL MAIN FEEDPUMPS 5/26/98 Trans 3 CLOSURE OF ALL MSIV'S 8/28/94 Trans 3 CLOSURE OF ALL MSIV'S 10/3/95 Trans 3 CLOSURE OF ALL MSIV'S 5/1 0/96 Trans 3 CLOSURE OF ALL MSIV'S 10/10/96 Trans 3 CLOSURE OF ALL MSIV'S 9/1 8/97 Trans 4 TRIP OF ALL REACTOR COOLANT PUMPS 12/17/94 Trans 4 TRIP OF ALL REACTOR COOLANT PUMPS 12/17/95 Trans 4 TRIP OF ALL-REACTOR COOLANT PUMPS 5/1 0/96 Trans 4 TRIP OF ALL REACTOR COOLANT PUMPS 10/10/96 Trans 4 TRIP OF ALL REACTOR COOLANT PUMPS 12/31/97 Trans 5 TRIP OF REACTOR COOLANT PUMP ¹23 1/22/94 Trans5 TRIP OF REACTOR COOLANT PUMP ¹23 3/27/95 Trans 5 TRIP OF REACTOR COOLANT PUMP ¹23 4/4/96 Trans 6 TRIP OF REACTOR COOLANT PUMP ¹23 5/10/96 Trans 6 TRIP OF REACTOR COOLANT PUMP ¹23 10/10/96 Trans 5 TRIP OF REACTOR COOLANT PUMP ¹23 3/28/97 Trans 5 TRIP OF REACTOR COOLANT PUMP ¹23 3/27/98 Trans 6 MAIN TURBINE TRIP W/0 REACTOR TRIP 6/26/94 Trans 6 MAIN TURBINE TRIP W/0 REACTOR TRIP 6/26/95 Trans 6 MAIN TURBINE TRIP W/0 REACTOR TRIP 5/10/96 Trans 6 MAIN TURBINE TRIP W/0 REACTOR TRIP 10/11/96 Trans 6 MAIN TURBINE TRIP W/0 REACTOR TRIP 5/1/97 Trans 6 MAIN TURBINE TRIP W/0 REACTOR TRIP 6/26/98 Trans 7 MAXIMUMPOWER RAMP 100%-75%-100% 8/28/94 Trans 7 MAXIMUMPOWER RAMP 100%-75%-100% 10/3/95 Trans 7 MAXIMUMPOWER RAMP 100%-75%-100% 5/10/96 Trans 7 MAXIMUMPOWER RAMP 100%-75%-100% 10/11/96 Trans 7 MAXIMUMPOWER RAMP 100%-75%-100% 9/1 9/97 Trans 8 MAXIMUMSIZE LOCA WITH BLACKOUT 12/17/94 Page 5 of 16 Attachment 1

Trans 8 MAXIMUMSIZE LOCA WITH BLACKOUT 12/17/95

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

COOK NUCLEAR PLANT SIMULATOR SPECIAL TRANSIENT TESTING Test Number Title Date Tested ST-1 NATURALCIRC C/D WITH VESSEL HEAD VOID 3/30/94 FORMATION ST-1 NATURALCIRC C/D WITH VESSEL HEAD VOID 3/31/95 FORMATION ST-1 NATURALCIRC C/D WITH VESSEL HEAD VOID 12/20/96 FORMATION ST-1 NATURALCIRC C/D WITH VESSEL HEAD VOID 3/28/97 FORMATION ST-1 NATURALCIRC C/D WITH VESSEL HEAD VOID 3/27/98 FORMATION ST-2 ANTICIPATEDTRANSIENT W/0 SCRAM (ATWS) 6/10/94 ST-2 ANTICIPATED TRANSIENT W/0 SCRAM (ATWS) 6/26/95 ST-2 ANTICIPATEDTRANSIENT W/0 SCRAM (ATWS) 12/20/96 ST-2 ANTICIPATEDTRANSIENT W/0 SCRAM (ATWS) 6/25/97 ST-2 ANTICIPATEDTRANSIENT W/0 SCRAM (ATWS) 6/2/98 ST-3 STEAM GENERATOR TUBE RUPTURE 9/29/94 ST-3 STEAM GENERATOR TUBE RUPTURE 10/6/95 ST-3 STEAM GENERATOR TUBE RUPTURE 12/20/96 ST-3 STEAM GENERATOR TUBE RUPTURE 9/26/97 ST-4 UNIT 2 REACTOR TRIP, NOVEMBER 13, 1985 12/17/94 ST-4 UNIT 2 REACTOR TRIP, NOVEMBER 13, 1985 12/20/96 ST-4 UNIT 2 REACTOR TRIP, NOVEMBER 13, 1985 12/30/97 Page 7 of 16 Attachment 1

COOK NUCLEAR PLANT SIMULATOR MALFUNCTIONTESTING Test Number Title Date Tested CC06 SEAL WATER HX TUBE LEAK 8/1/94 CS03 REFUELING WATER STORAGE TANK LEAK 11/19/94 CV09 LETDOWN TEMPERATURE CONTROL FAILURE 11/19/94 CV26 REACTOR COOLANT PUMP ¹1 SEAL FAILURE 11/19/94 CW02 CW PUMP DISCHARGE VALVEFAILURE 8/1/94 ED03 LOSS OF RESERVE AUXILIARYTRANSFORMER 11/19/94 ED07 LOSS OF 480 VAC BUS 11/19/94 ED16 AUXILIARIESAUTO BUS TRANSFER FAILURE 11/19/94 ED19 ELECTRICAL GRID LOAD REJECTION 9/26/94-ED20 ANN PANEL POWER SUPPLY FAILURE 8/1/94 ED24 LOSS OF 250 VDC TRAIN "N" BATTERY 8/13/94 EG03 MG AUTO VOLTAGE REG FAILURE TO MANUAL 8/13/94 EG11 DIESEL GENERATOR FAILURE TO TRIP 8/13/94 FP05 CONTROL ROOM CABLE VAULTFIRE 8/13/94 FW05 MAINFEEDPUMP TURBINE TRIP 11/20/94 FW30 LP HTR ¹3 LVLCONTROL VALVEFAILURE 11/20/94 FW42 CONDENSATE STORAGE TANK LEAK 8/13/94 FW56 FEEDPUMP STEAM SUPPLY CONT FAILURE 8/13/94 IV[S03 MAINSTM LINE BREAK OUTSIDE CONTAINMENT 12/5/94 MS12 MSR DRAIN TK ALT DRAIN LVLCONT FAILURE. 12/18/94 NI06 INTERMEDIATERANGE MONITOR FAILURE 8/13/94 NI10 POWER RANGE CHANNEL FAILURE 12/5/94 RC03 RCS LEAK 8/13/94 RC07 REACTOR COOLANT PUMP LOCKED ROTOR 12/5/94 RC17 PRESSURIZER PORV FAILURE 12/16/94 RD08 IN-HOLD-OUT SWITCH FAILURE 8/13/94 RD12 FAILURE OF CONTROL RODS TO MOVE 12/16/94 RD16 IRPI FAILURE 12/16/94 RH15 SI ACCUMULATORN2 PRESSURE LOSS 12/18/94 RP03 FAILURE OF REACTOR TRIP BREAKER 8/13/94 RP12 SPURIOUS ACTUATION OF SI 8/13/94 RP20 TRAIN "B" K600 RELAY FAILURES 8/13/94 RX08 PZR SPRAY VALVEAUTO CONTROL FAILURE 12/18/94 RX16 STEAM DUMP "PRESS CONTROL" ERRATIC OPS 12/18/94 RX24 FW CONTROL VALVECONTROLLER FAILURE 12/18/94 RX28 LOSS OF 480V MCC 8/13/94 SW01 NON ESSENTIAL SERVICE WATER PUMP TRIP 8/13/94 SW05 ESW PIPING RUPTURE 8/13/94 TC02 MAINTURBINE FAILURE TO TRIP 12/18/94 Page 8 of 16 Attachment 1

1 I'

II 0

TU03 MAINTURBINE HIGH VIBRATION 8/13/94 CC03 COMPONENT COOLING WATER RUPTURE 7/17/95 CC07 COMPONENT COOLING HX TUBE RUPTURE 1/14/95 CH02 CONTAIN. PRESSURE TRANSMITTER FAILURE 6/20/95 CS04 RWST LEVEL TRANSMITTER FAILURE 11/14/95 CV05 LETDOWN HEAT EXCHANGER TUBE LEAK 1/14/95 CV10 NORMAL CHG LINE LEAK INSIDE CONTAIN. 7/17/95 CV14 CHARGING PUMP SUCTION LINE LEAKAGE 11/14/95 CV20 INADVERTENTBORATION 1/14/95 CV27 REACTOR COOLANT PUMP ¹2 SEAL FAILURE 6/20/95 CV32 PW FLOW TRANSMITTER (QFC-422) FAILURE 7/17/95 CW03 TRAVELINGWATER SCREEN FOULING 6/20/95 ED04 LOSS OF EP SUPPLY TRANS TR-12-EP 11/14/95 ED05 LOSS OF 4160 VAC BUS 6/20/95 ED14 LOSS OF 250 VDC BATTERY CHARGER 6/26/95 ED18 GRID VOLTAGE OSCILLATION 7/17/95 ED21 4KV/600V AUX TRANSFORMER LOSS 7/17/95 EG04 MG AUTO VOLTAGE REGULATOR FAILURE 1/14/95 EG08 DG SPEED GOVERNOR FAILURE 6/26/95 EG12 DG OUTPUT BREAKER FAILURE TO AUTO CLOSE 7/17/95 FP01 FIRE PROTECTION SYSTEM RUPTURE 11/14/95 FW01 MAINFEEDWATER RUPTURE AT SG INLET 11/17/95 FW06 MFP TURBINE SHEARED SHAFT 2/12/95 FW15 FEEDWATER CONTROL VALVEFAILURE 3/3/95 FW19 HP HEATER ¹6 TUBE RUPTURE 6/26/95 FW23 HP HEATER ¹5 TUBE-RUPTURE 8/28/95 FW27 LP HTR ¹4 LVLCONTROL VALVEFAILURE 6/26/95 FW31 LP HEATER ¹3 TUBE RUPTURE 11/17/95 FW35 COND BOOSTER PP DISCHARGE PIPING RUPTURE 9/13/95 FW39 CONDENSER TUBE LEAK 11/17/95 FW43 HEAER DRAIN PUMP TRIP 3/3/95 FW47 AUX FEEDPUMP SUCTION LINE LEAKAGE 6/26/95 FW51 TDAFP TRIP & THROTTLE VALVEFAILURE 9/13/95 IA01 PLANT AIR COMPRESSOR TRIP 3/3/95 IA05 CONT AIR SYS RUPTURE IN CONTAINMENT 11/17/95 MS04 MS LINE BREAK DOWNSTREAM OF SG STOP VLVS 3/6/95 MS09 MSR TUBE RUPTURE 12/31/95 MS13 MSR DRAIN TK ALT LVLCONTROL VALVE 9/13/95 FAILURE MS18 STEAM DUMP CONTROL VALVEFAILURE 12/31/95 NI03 INCORRECT SR CHANNEL RESPONSE 11/17/95 NI07 IR IMPROPER COMPENSATION 3/6/95 NI11 PR CHANNEL OUTPUT OSCILLATION 6/26/95 NI15 POWER RANGE CHANNEL BLOWN FUSE 9/28/95 Page 9 of 16 Attachment 1

p II II

RC04 PRESSURIZER SURGE LINE LEAK 11/14/95 RC08 REACTOR COOLANT PUMP SHAFT BREAK 3/6/95 RC14 PZR HIGH GAS CONCENTRATION IN VAPOR SPACE 9/28/95 RC19 PRESSURIZER SAFETY VALVEFAILURE 6/26/95 RC25 SG BLOWDOWN LINE LEAK DOWNSTREAM OF CIV 11/17/95 RC29 SG BLOWDOWN LINE LEAK UPSTREAM OF CIV 6/30/95 RD01 DROPPED CONTROL ROD 3/13/95 RD05 EJECT OF ROD WITH RUPTURED MECH HOUSING 6/26/95 RD09 UNCONTROLLED ROD MOTION DEMAND (AUTO) 9/28/95 RD13 ROD GROUP FAILURE TO MOVE 9/28/95 RD17 ROD GROUP STEP COUNTER FAILURE 11/20/95 RH03 RHR HX BYPASS FLOW CONTROL VALVEFAILURE 11/20/95 RH07 RHR NORMAL SUCTION LINE LK INSIDE CONT 10/2/95 RH12 SI LOOP CHECK VALVELEAKAGE 3/13/95 RM01 AREA RADIATIONMONITOR FAILURE 11/20/95 RP05 REACTOR COOLANT FLOW TRANSMITTER FAILURE 6/26/95 RP09 FAILURE OF FW ISOLATION TRIP TO OCCUR 10/2/95 RP13 FAILURE OF CI PHASE A TO AUTO ACTUATE 11/14/95 RP15 SPURIOUS ACTUATIONOF CI PHASE A 6/30/95 RP17 FAILURE OF CI PHASE B TO MANUALLYACTUATE 3/13/95 RX01 RCS HOT LEG PRESSURE TRANSMITTER FAILURE 6/27/95 RX05 PRESSURIZER LVLTRANS FAILURE 10/2/95 RX09 PZR PRESSURE MASTER CONTROLLER FAILURE 11/14/95 RX13 STEAM DUMP "TAVG" CONTROLLER FAILURE 1/14/95 RX17 SG PRESSURE TRANSMITTER FAILURE 6/26/95 RX21 SG FEED FLOW TRANSMITTER FAILURE 10/2/95 RX25 FEEDWATER CONTROL VALVEOSCILLATION 11/20/95 SI01 SAFETY INJECTION PUMP TRIP 9/28/95 SW02 NESW PIPING RUPTURE IN TURBINE BUILDING 3/13/95 SW06 FP TURBINE OIL COOLING CONTROLLER FAILURE 6/30/95 TC03 MAINTURBINE AUTO TRIP FAILURE 11/20/95 TC07 MAINTURBINE INTERCEPT VALVEFAILURE 11/20/95 TC12 MAINTURBINE SPEED SIGNAL FAILURE 11/20/95 TP03 i MG STATOR COOLING SYSTEM RUPTURE 6/30/95 TU01 AUXILIARYLUBE OIL PUMP TRIP 6/20/95 TU05 MAINTURBINE BEARING FAILURE 10/2/95 CC04 MISC CCW HEADER RUPTURE INSIDE CONT. 12/19/96 CC08 CCW LEAKAGEINTO RCP BEARING OIL RES. 12/20/96 CS01 CONTAINMENTSPRAY PUMP TRIP 6/25/96 CV01 LETDOWN LINE RUPTURE INSIDE CONT. 7/1/96 CV06 LETDOWN PRESS CONT VLV FAILURE (QRV-301) 7/1/96 CV11 NORMAL CHG LINE LEAK OUTSIDE CONTAINMENT 7/1/96 CV15 VCT LEVEL CONTROL VALVEFAILURE 7/1/96 CV21 INADVERTENTDILUTION 7/2/96 Page 10 of 16 Attachment 1

CV28 REACTOR COLANT PUMP ¹3 SEAL FAILURE 12/20/96 CV33 BA FLOW CONTROLLER (QFC-421) FAILURE 12/20/96 ED01 LOSS OF 345KV BUS NO. 1. 6/26/96 ED08 LOSS OF 600V MCC 6/26/96 ED10 LOSS OF 120 VAC CONTROL ROOM POWER 6/28/96 ED17 LOSS OF PLANT LIGHTING 12/19/96 ED22 LOSS OF SWITCHGEAR CONT POWER TRAIN B 12/20/96 ED26 LOSS OF 765KV DUMONT LINE 6/26/96 EG05 MG OUTPUT BREAKER FAILURE TO TRIP 7/2/96 EG09 DG VOLTAGE CONTROL FAILURE 12/20/96 EG13 DG OUTPUT BREAKER FAILURE TO CLOSE 12/20/96 FP02 INADVACT OF CHARCOAL FILT FIRE PROT. 12/20/96 FW02 MFW RUPTURE BEFORE SG CHECK VALVE 7/3/96 FW07 MAINFEEDPUMP TURBINE BEARING FAILURE 7/3/96 FW16 HP HEATER ¹6 LVLCONT TRANSMITTER FAILURE 12/20/96 FW20 HP HEATER ¹5 LVLCONT TRANSMITTER FAILURE 12/20/96 FW24 HP HEATER ¹5 STEAM INLET RUPTURE 7/8/96 FW28 LP HEATER ¹4 TUBE RUPTURE 7/8/96 FW32 LP HEATER ¹3 STEAM INLET RUPTURE 12/20/96 FW36 COND BOOSTER PP RECIRC VALVEFAILURE 12/20/96 FW40 HOTWELL LEVEL CONTROLLER FAILURE 7/8/96 FW44 HEATER DRAIN PUMP BEARING FAILURE 7/22/96 FW48 AUX FEEDPUMP AUTO START FAILURE 7/22/96 FW52 STEAM BOUND AFW PUMP 12/20/96 IA02 PLANT AIR SYSTEM RUPTURE 7/23/96 IA04 CONT AIR SYS RUPT IN TURBINE BUILDING 7/23'/96 MS01 MS LINE BREAK AT SG EXIT 7/23/96 MS05 MAINSTEAM POWER RELIEF VALVELEAK 7/23/96 MS10 MSR COIL DRAIN TANK LVLCONT FAILURE 7/23/96 MS14 MSR STEAM SUPPLY VALVEFAILURE 12/20/96 MS21 AUX STM 150¹ HDR CONTROL VALVEFAILURE 12/20/96 NI04 SR ENERGIZATION AT POWER (P10 FAILURE) 7/24/96 NI08 PR CHANNEL UPPER DETECTOR FAILURE 12/19/96 NI12 AUDIO COUNT RATE CHANNEL FAILURE 7/24/96 RC01 RCS COLD LEG LOOP RUPTURE 10/11/96 RC05 REACTOR VESSEL HEAD FLANGE LEAK 7/24/96 RC09 REACTOR COOLANT PUMP TRIP 7/24/96 RC15 RPESSURIZER SPRAY VALVEFAILURE 7/31/96 RC21 PRT RUPTURE DISC FAILURE 12/19/96 RC26 FAILED FUEL ELEMENT 10/10/96 RD02 BROKEN CONTROL ROD 8/6/96 RD06 UNCONT ROD BANK CONTINUOUS WITHDRAWL 8/6/96 RD10 CR MOVE OPPOSITE TO DEMAND SIGNAL 7/31/96 RD14 IMPROPER BANK OVERLAP 10/10/96 Page 11 of 16 Attachment 1

RD18 ROD CONTROL MG SET TRIP 7/31/96 RH04 RHR HX FLOW CONTROL VALVEFAILURE 10/9/96 RH08 RWST SUPPLY LINE TO RHR PUMP RUPTURE 10/9/96 RH13 SI ACC TANK CHECK VALVELEAKAGE 12/19/96 RM02 PROCESS RADIATIONMONITOR FAILURE 10/8/96 RP06 SPURIOUS STEAM LINE ISOLATION 8/6/96 RP10 FAILURE OF SI TO ACTUATE-AUTOMATIC 8/6/96 RP14 FAILURE OF CI PAHSE A TO MANUALACT 12/19/96 RP18 SPURIOUS ACTUATION OF CI PHASE B 8/6/96 RX02 RCS HOT LEG TEMP TRANS FAILURE (NR) 8/7/96 RX06 PZR CAL LEVEL TRANSMITTER FAILURE 12/19/96 RX10 PZR WATER LEVEL CONT OSCILLATION 12/19/96 RX14 STEAM DUMP PRESSURE CONTROLLER FAILURE 8/7/96 RX18 MS TURB BYPASS HDR PRESS TRANS FAILURE 8/7/96 RX22 SG PROGRAMMED LEVEL SIGHNAL FAILURE Deleted RX26 FP TURBINE SPEED CONTROLLER FAILURE 8/8/96 SI02 SAFETY INJECTION PUMP SHEARED SHAFT 12/20/96 SW03 NESW RUPT ON LWR CONT VENT CLR SUPPLY 8/8/96 SW07 MT OIL TEMPERATURE CONTROLLER FAILURE 12/19/96 TC04 MAINTURBINE STOP VALVEFAILURE 8/8/96 TC09 MAINGENERATOR LOAD LIMITERFAILURE 8/8/96 TC13 TURBINE RUNBACK FAILURE 12/20/96 TP05 STATOR COOLING WTR SYS HIGH CONDUCTIVITY 8/8/96 TU06 TURBINE BLADE EJECTION 8/8/96 CC01 COMPONENT COOLING WATER PUMP TRIP 10/13/97 CC05 MISC CCW HDR RUPTURE IN AUX BUILDING 10/27/97 CC09 CCW LEAK ON RHR PUMP SUPPLY LINE 10/27/97 CCIO CCW LEAKAGEINTO RCP L. BRNG OIL RESERV. 10/30/97 CS02 CONTAIN. SPRAY PUMP SUCTION BLOCKAGE 10/27/97 CV02 LETDOWN LINE RUPTURE OUTSIDE CONTAIN. 10/27/97 CV08 LETDOWN LINE RELIEF VLVSV-51 LEAKAGE 10/13/97 CV12 CCP FLOW CONTROL VALVEFAILURE 10/13/97 CV16 VCT LEVEL TRANSMITTER FAILURE 10/13/97 CV25 RCP THERMALBARRIER HX RUPTURE 13/13/97 CV30 REDUCED CCP CAPACITY 10/16/97 CW01 CIRCULATINGWATER PUMP TRIP 10/16/97 ED12 LOSS OF 250 VDC POWER (TRAIN A) 10/16/97 ED13 LOSS OF 250 VDC POWER (TRAIN B) 10/27/97 ED23 LOSS OF SWITCHGEAR CONT POWER TRAIN A 10/27/97 ED25 LOSS OF 765/345KV TRANSFORMER BANK¹4 10/27/97 EG01 MAINGENERATOR TRIP 10/16/97 EG06 DIESEL GENERATOR TRIP 10/16/97 EG10 DIESEL GENERATOR FAILURE TO START 10/16/97 EG14 DG RUNNING RELAY FAILURE 10/23/97 Page 12 of 16 Attachment 1

FP03 DIESEL GENERATOR ROOM CO2 ACTUATION 10/16/97 FW03 MFW RUPT BETWEEN FEEDFLOW ELMT & FRV 10/27/97 FW12 FEEDPUMP TURBINE LUBE OIL SYSTEM LEAK 10/16/97 FW17 HP HTR ¹6 LVLCONTROLLER AUTO FAILURE 10/27/97 FW21 HP HTR ¹5 LVLCONTROLLER AUTO FAILURE 10/27/97 FW25 HOTWELL PUMP TRIP 10/25/97 FW29 LP HTR ¹3 LVLCONT TRANSMITTER FAIL 10/27/97 FW33 LP HEATER BY PASS VALVEFAILURE 10/22/97 FW37 HOTWELL PUMP DISCHARGE PIPING RUPTURE 10/27/97 FW41 HW LEVEL CONTROL TRANSMITTER FAILURE 10/28/97 FW45 HEATER DRAIN PUMP ELO VLVFAILS OPEN 10/23/97 IA03 CONTROL AIR COMPRESSOR TRIP 10/21/97 MS02 MAINSTEAM LINE BREAK AT SG EXIT 10/21/97 MS06 STEAM GENERATOR SAFETY VALVELEAK 10/28/97 MS11 MSR COIL DRAIN TANK LVLCONT LVLFAIL 10/28/97 MS16 STEAM SEAL CONTROLLER FAILURE 10/28/97 NI01 SOURCE RANGE MONITOR FAILURE 10/28/97 NI05 SOURCE RANGE CHANNEL SPIKES 10/28/97 NI09 PR CHANNEL LOWER DETECTOR FAILURE 10/28/97 NI13 SOURCE RANGE INSTRUMENT BLOWN FUSE 10/21/97 RC02 RCS HOT LEG LOOP LEAK 10/28/97 RC06 RCS EMERGENCY VENT LEAKAGE 12/15/97 RC10 RCS COLD LEG LEAK 10/30/97 RC11 REACTOR COOLANT PUMP HIGH VIBRATION 10/28/97 RC12 RCP LOWER BEARING OIL RESERVOIR LEAK 12/15/97 RC16 PRESSURIZER STEAM SPACE MANWAYLEAK 10/29/97 RC23 STEAM GENERATOR TUBE RUPTURE 10/21/97 RC27 RTD BYPASS MANIFOLDFLOW DEGRADATION 10/29/97 RD03 STUCK CONTROL ROD (TRIPPABLE) 10/28/97 RD07 UNCONT ROD BANK CONTINUOUS INSERTION 10/28/97 RD11 AUTO CONTROL ROD SPEED FAILURE 10/28/97 RD15 IRPI POWER LOSS 10/27/97 RD19 IMPOPER ROD WORTH 12/16/97 RH01 RHR PUMP TRIP 10/21/97 RH05 RHR HEAT EXCHANGER TUBE LEAK 10/30/97 RH09 RHR PUMP SUCTION PIPE RUPTURE 10/29/97 RH14 SI ACCUMULATORTANKLEVEL LOW 10/30/97 RM03 EBERLINE AREA RADIATIONMONITOR FAILURES 10/31/97 RP01 REACTOR TRIP ACB AUTO TRIP FAILURE 10/21/97 RP07 ~

FAILURE OF STEAM LINE ISO TO ACTIVATE 10/21/97 RP11 FAILURE OF SI TO ACTUATE-MANUALLY 10/21/97 RP19 TRAIN "A" K600 RELAY FAILURES 10/21/97 RP21 FAILURE OF FWI TRIP TO OCCUR 10/30/97 RX03 RCS COLD LEG TEMP TRANS FAILURE (NR) 10/22/97 Page 13 of 16 Attachment 1

4 II

RX07 REDUCED PRESSURIZER HEATER CAPACITY 10/21/97 RX11 SG RELIEF VALVECONTROLLER FAILURE 10/21/97 RX19 TURBINE IMPULSE TRANSMITTER FAILURE 10/21/97 RX23 SG LEVEL TRANSMITTER FAILURE 10/22/97 RX29 FPC-250 TRANSMITTER FAILURE 10/30/97 SI03 HIGH HEAD SI LINE RUPTURE 10/30/97 SW04 ESSENTIAL SERVICE WATER PUMP TRIP 10/22/97 TC01 MAINTURBINE TRIP 10/22/97 TC05 MAINTURBINE CONTROL VALVEFAILURE 10/22/97 TC10 MAINGEN OPERATING DEVICE FAILURE 10/30/97 TP01 TURBINE AUX COOLING PUMP TRIP 10/22/97 WD01 RELEASE OF RADIOACTIVEGAS FROM GDT 10/30/97 CC02 CCW PUMP FAILURE TO AUTO START 7/13/98 CC06 SEAL WATER HX TUBE LEAK 7/13/98 CH01 CONTAIN. PRESS. RELIEF VLV FAILURE 7/13/98 CS03 REFUELING WATER STORAGE TANK LEAK 7/13/98 CV04 LETDOWWN LINE ORIFICE ISO. VLVFAILURE 7/13/98 CV09 LETDOWN TEMPERATURE CONTROL FAILURE 7/13/98 CV13 CHARGING PUMP TR& 7/13/98 CV17 VOLUME CONTROL TANK LEAKAGE 7/13/98 CV26 REACTOR COOLANT PUMP ¹1 SEAL FAILURE 7/13/98 CV31 BACKPRESSURE CONT VLVFAILURE-QRV-200 7/13/98 CW02 CW PUMP DISCHARGE VALVEFAILURE 7/13/98 ED02 LOSS OF AUXILIARYTRANSFORMER 7/13/98 ED03 LOSS OF RESERVE AUXILIARYTRANSFORMER 7/13/98 ED06 LOSS OF 600 VAC BUS 7/14/98 ED07 LOSS OF 480 VAC BUS 7/14/98 ED11 LOSS OF 250 VDC BUS 7/14/98 ED15 LOSS OF VITALINST BUS STATIC SWITCH 7/14/98 ED16 AUXILIARIESAUTO BUS TRANSFER FAILURE 7/14/98 ED19 ELECTRICAL GRID LOAD REJECTION 7/14/98 ED20 ANN PANEL POWER SUPPLY FAILURE 7/14/98 ED24 LOSS OF 250 VDC TRAIN "N" BATTERY 7/14/98 EG03 MG AUTO VOLTAGE REG FAILURE TO MANUAL 7/14/98 EG07 DG SPEED CONTROL FAILURE 7/14/98 EG11 DIESEL GENERATOR FAILURE TO TRIP 7/14/98 EG15 MG SEAL OIL UNIT PIPING RUPTURE 7/14/98 FP05 CONTROL ROOM CABLE VAULTFIRE 7/14/98 FW05 MAINFEEDPUMP TURBINE TRIP 7/14/98 FW18 HP HTR ¹6 LVLCONTROL VALVEFAILURE 7/14/98 FW22 HP HTR ¹5 LVLCONTROL VALVEFAILURE 7/14/98 FW26 LP HTR ¹4 LVLCONT TRANSMITTER FAIL 7/15/98 FW30 LP HTR ¹3 LVLCONTROL VALVEFAILURE 7/15/98 FW34 CONDENSATE BOOSTER PUMP TRIP 7/15/98 Page 14 of 16 Attachment 1

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FW38 LOSS OF CONDENSER VACUUM 7/15/98 FW42 CONDENSATE STORAGE TANK LEAK 7/15/98 FW46 AUX FEEDPUMP TRIP 7/15/98 FW50 TDAFW PUMP SPEED CONTROLLER FAILURE 7/15/98 FW54 FDWTR RUPT OUTSIDE CONTAINMENT 7/15/98 FW56 FEED PUMP STEAM SUPPLY CONT FAILURE 7/15/98 MS03 MAINSTM LINE BREAK OUTSIDE CONT 7/15/98 MS08 SG STOP VALVEDRIFTS SHUT 7/15/98 MS12 MSR DRAIN TK ALT DRAIN LVLCONT FAIL 7/15/98 MS17 STEAM SEAL CONTROLLER OSCILLATION 7/15/98 NI02 SOURCE RANGE HV FAILURE TO DEENERGIZE 7/15/98 NI06 INTERMEDIATERANGE MONITOR FAILURE 7/15/98 NI10 POWER RANGE CHANNEL FAILURE 7/15/98 NI14 INTERMEDIATERANGE CHANNEL BLOWN FUSE 7/15/98 RC03 RCS LEAK 7/16/98 RC07 REACTOR COOLANT PUMP LOCKED ROTOR 7/16/98 RC13 RCP UPPER BEARING OIL RESERVOIR LEAK 7/16/98 RC17 PRESSURIZER PORV FAILURE 7/16/98 RC24 STEAM GENERATOR TUBE LEAK 7/16/98 RC28 PRESSURIZER INSTRUMENT LINE LEAKAGE 7/16/98 RD04 STUCK CONTROL ROD (UNTRIPPABLE) 7/16/98 RD08 IN-HOLD-OUTSWITCH FAILURE 7/16/98 RD16 IRPI FAILURE 7/16/98 RH02 RHR PUMP SEAL FAILURE 7/16/98 RH06 RHR INJ HDR RELIEF VALVEFAIL (SV-104) 7/16/98 RH11 RHR RET FLOW TRANS FAILURE (IFI-335) 7/16/98 RH15 SI ACCUMULATORN2 PRESSURE LOSS 7/16/98 RP03 FAILURE OF REACTOR TRIP BREAKER 7/16/98 RP08 SPURIOUS FEEDWATER ISLOATION TRIP 7/16/98 RP12 SPURIOUS ACTUATION OF SI 7/16/98 RP16 FAILURE OF CI PHASE B TO AUTO ACTUATE 7/16/98 RP20 TRAIN "B" K600 RELAY FAILURES 7/16/98 RX04 PRESSURIZER PRESSURE TRANS FAILURE 7/16/98 RX08 PZR SPRAY VALVEAUTO CONTROL FAILURE 7/16/98 RX12 MS RELIEF VLV CONTROLLER OSCILLATION 7/16/98 RX16 STEAM DUMP "PRES CONT" ERRATIC OPS 7/17/98 RX20 SG STEAM FLOW TRANSMITTER FAILURE 7/17/98 RX24 FW CONTROL VALVECONTROLLER FAILURE 7/17/98 RX27 FEED PUMP DP CONTROLLER FAILURE 7/17/98 RX28 LOSS OF 480V MCC 7/17/98 SW01 NON ESSENTIAL SERVICE WATER PUMP TRIP 7/17/98 SW05 ESW PIPING RUPTURE 7/17/98 TC02 MAINTURBINE FAILURE TO TRIP 7/17/98 TC06 MAINTURBINE ERRATIC CONTROL VALVE 7/17/98 Page 15 of 16 Attachment 1

4 a TC11 AUTO LOAD SET OSCILLATION 7/17/98 TP02 TURBINE AUX COOLING PIPING RUPTURE 7/17/98 TU03 MAINTURBINE HIGH VIBRATION 7/17/98 Page 16 of 16 Attachment 1

ATTACHMENT2 COOK PLANT SIMULATOR 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 of Appendices A and B of ANSI 3.5, 1985 performance testing.

Page 1 of 11 Attachment 2

l C COOK NUCLEAR PLANT SIMULATOR ANSI 3.5 APPENDICIES A AND B ANNUALTESTING SCHEDULE QTR 1 TR2 TR3 TR4 CRT-1 SS-01 SS-02 SS-03 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 NORMALPLANT EVOLUTION TESTING SCHEDULE 1999 2000 2001 2002 NPE-1 NPE-2 NPE-3 NPE-4 NPE-5 NPE-6 NPE-7 Test Descri tions:

CRT-1 Computer Real Time Test SS-1 Steady State Test 1 SS-2 Steady State Test 2 SS-3 Steady State Test 3 SS-4 Steady State Test 4 Trans-01 Manual Reactor- Trip Trans-02 Trip of all Main Feedpumps Trans-03 Closure of all MSIV's Trans-04 Trip of all Reactor Coolant Pumps Trans-05 Trip of Reactor Coolant Pump 823 Trans-06 Main Turbine Trip W/0 Reactor Trip Trans-07 Maximum Power Ramp 100%-75%-100%

Trans-08 Maximum Size Loca with Blackout Trans-09 Maximum Size Main Steamline Rupture Trans-10 Slow RCS Depressurization to Saturation Trans-11 Load Rejection NPE-1 RCS Fill and Vent NPE-2 Cold Shutdown to Hot Standby NPE-3 Reactor Startup NPE-4 Plant Startup/Power Escalation NPE-5 Power Reduction Page 2 of 11 Attachment 2

4 g NPE-6 Plant Cooldown NPE-7 RCS Drain Page 3 of 11 Attachment 2

MALFUNCTIONTEST SCHEDULE Test Number Title Scheduled CC03 COMPONENT COOLING WATER RUPTURE 1999 CC07 COMPONENT COOLING HX TUBE RUPTURE 1999 CH02 CONTAIN. PRESSURE TRANSMITTER FAILURE 1999 CH03 CONTAIN. PRESSURE TRANSMITTER FAILURE (WR) 1999 CS04 RWST LEVEL TRANSMITTER FAILURE 1999 CV05 LETDOWN HEAT EXCHANGER TUBE LEAK 1999 CV10 NORMAL CHG LINE LEAK INSIDE CONTAIN, 1999 CV14 CHARGING PUMP SUCTION LINE LEAKAGE 1999 CV20 INADVERTENTBORATION 1999 CV27 REACTOR COOLANT PUMP ¹2 SEAL FAILURE 1999 CV32 PW FLOW TRANSMITTER (QFC-422) FAILURE 1999 CW03 TRAVELINGWATER SCREEN FOULING 1999 ED04 LOSS OF EP SUPPLY TRANS TR-12-EP 1999 ED05 LOSS OF 4160 VAC BUS 1999 ED14 LOSS OF 250 VDC BATTERY CHARGER 1999 ED18 GRID VOLTAGE OSCILLATION 1999 ED21 4KV/600V AUX TRANSFORMER LOSS 1999 EG04 MG AUTO VOLTAGE REGULATOR FAILURE 1999 EG08 DG SPEED GOVERNOR FAILURE 1999 EG12 DG OUTPUT BREAKER FAILURE TO AUTO CLOSE 1999 FP01 FIRE PROTECTION SYSTEM RUPTURE 1999 FP06 FIRE PROTECTION STORAGE TANK LEAK 1999 FW01 MAINFEEDWATER RUPTURE AT SG INLET 1999 FW06 MFP TURBINE SHEARED SHAFT 1999 FW15 FEEDWATER CONTROL VALVEFAILURE 1999 FW19 HP HEATER ¹6 TUBE RUPTURE 1999 FW23 HP HEATER ¹5 TUBE RUPTURE 1999 FW27 LP HTR ¹4 LVLCONTROL VALVEFAILURE 1999 FW31 LP HEATER ¹3 TUBE RUPTURE. 1999 FW35 COND BOOSTER PP DISCHARGE PIPING RUPTURE 1999 FW39 CONDENSER TUBE LEAK 1999 FW43 HEAER DRAIN PUMP TRIP 1999 FW47 AUX FEEDPUMP SUCTION LINE LEAKAGE 1999 FW51 TDAFP TRIP & THROTTLE VALVEFAILURE 1999 IA01 PLANT AIR COMPRESSOR TRIP 1999 IA05 CONT AIR SYS RUPTURE IN CONTAINMENT 1999 MS04 MS LINE BREAK DOWNSTREAM OF SG STOP VLVS 1999 MS09 MSR TUBE RUPTURE 1999 Page 4 of 11 Attachment 2

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MS13 MSR DRAIN TK ALT LVLCONTROL VALVE 1999 FAILURE MS18 STEAM DUMP CONTROL VALVEFAILURE 1999 NI03 INCORRECT SR CHANNEL RESPONSE '999 NI07 IR IMPROPER COMPENSATION 1999 NI11 PR CHANNEL OUTPUT OSCILLATION 1999 NI15 POWER RANGE CHANNEL BLOWN FUSE 1999 RC04 PRESSURIZER SURGE LINE LEAK 1999 RC08 REACTOR COOLANT PUMP SHAFT BREAK 1999 RC14 PZR HIGH GAS CONCENTRATION IN VAPOR SPACE 1999 RC19 PRESSURIZER SAFETY VALVEFAILURE 1999 RC25 SG BLOWDOWN LINE LEAK DOWNSTREAM OF CIV 1999 RC29 SG BLOWDOWN LINE LEAK UPSTREAM OF CIV 1999 RD01 DROPPED CONTROL ROD 1999 RD05 EJECT OF ROD WITH RUPTURED MECH HOUSING 1999 RD09 UNCONTROLLED ROD MOTION DEMAND (AUTO) 1999 RD13 ROD GROUP FAILURE TO MOVE 1999 RD17 ROD GROUP STEP COUNTER FAILURE 1999 RD20 ROD CONTROL POWER CABINET FAILURE 1999 RH03 RHR HX BYPASS FLOW CONTROL VALVEFAILURE 1999 RH07 RHR NORMAL DC SUCTION LINE LK INSIDE CONT 1999 RH12 SI LOOP CHECK VALVELEAKAGE 1999 RM01 AREA RADIATIONMONITOR FAILURE 1999 RP05 REACTOR COOLANE FLOW TRANSMITTER FAILURE 1999 RP09 FAILURE OF FW ISOLATION TRIP TO OCCUR 1999 RP13 FAILURE OF CI PHASE A TO AUTO ACTUATE 1999 RP15 SPURIOUS ACTUATION OF CI PHASE A 1999 RP17 FAILURE OF CI PHASE B TO MANUALLYACTUATE 1999 RX01 RCS HOT LEG PRESSURE TRANSMITTER FAILURE 1999 RX05 PRESSURIZER LVLTRANS FAILURE 1999 RX09 PZR PRESSURE MASTER CONTROLLER FAILURE 1999 RX13 STEAM DUMP "TAVG" CONTROLLER FAILURE 1999 RX17 SG PRESSURE TRANSMITTER FAILURE 1999 RX21 SG FEED FLOW TRANSMITTER FAILURE 1999 RX25 FEEDWATER CONTROL VALVEOSCILLATION 1999 SI01 SAFETY INJECTION PUMP TRIP 1999 SW02 NESW PIPING RUPTURE IN TURBINE BUILDING 1999 SW06 FP TURBINE OIL COOLING CONTROLLER FAILURE 1999 TC03 MAINTURBINE AUTO TRIP FAILURE 1999 TC07 MAINTURBINE INTERCEPT VALVEFAILURE 1999 TC12 MAINTURBINE SPEED SIGNAL FAILURE 1999 TP03 MG STATOR COOLING SYSTEM RUPTURE 1999 TU01 AUXILIARYLUBE OIL PUMP TRIP 1999 TU05 MAINTURBINE BEARING FAILURE 1999 CC04 MISC CCW HEADER RUPTURE INSIDE CONT. 2000 Page 5 of 11 Attachment 2

CC08 CCW LEAKAGEINTO RCP BEARING OIL RES. 2000 CH04 CONTAINMENTLEAKAGE 2000 CS01 CONTAINMENTSPRAY PUMP TRIP 2000 CV01 LETDOWN LINE RUPTURE INSIDE CONT. 2000 CV06 LETDOWN PRESS CONT VLVFAILURE (QRV-301) 2000 CV11 NORMAL CHG LINE LEAK OUTSIDE CONTAINMENT 2000 CV15 VCT LEVEL CONTROL VALVEFAILURE 2000 CV21 INADVERTENTDILUTION 2000 CV28 REACTOR COLANT PUMP ¹3 SEAL FAILURE 2000 CV33 BA FLOW CONTROLLER (QFC-421) FAILURE 2000 ED01 LOSS OF 345KV BUS NO. 1 2000 ED08 LOSS OF 600V MCC 2000 ED10 LOSS OF 120 VAC CONTROL ROOM POWER 2000 ED17 LOSS OF PLANT LIGHTING 2000 ED22 LOSS OF SWITCHGEAR CONT POWER TRAIN B 2000 ED26 LOSS OF 765KV DUMONT LINE 2000 EG05 MG OUTPUT BREAKER FAILURE TO TRIP 2000 EG09 DG VOLTAGE CONTROL FAILURE 2000 EG13 DG OUTPUT BREAKER FAILURE TO CLOSE 2000 FP02 INADVACT OF CHARCOAL FILT FIRE PROT. 2000 FW02 MFW RUPTURE BEFORE SG CHECK VALVE 2000 FW07 MAINFEEDPUMP TURBINE BEARING FAILURE 'P 2000 FW16 HEATER ¹6 LVLCONT TRANSMITTER FAILURE 2000 FW20 HP HEATER ¹5 LVLCONT TRANSMITTER FAILURE 2000 FW24 HP HEATER ¹5 STEAM INLET RUPTURE 2000 FW28 LP HEATER ¹4 TUBE RUPTURE 2000 FW32 LP HEATER ¹3 STEAM INLET RUPTURE 2000 FW36 COND BOOSTER PP RECIRC VALVEFAILURE 2000 FW40 HOTWELL LEVEL CONTROLLER FAILURE 2000 FW44 HEATER DRAIN PUMP BEARING FAILURE 2000 FW48 AUX FEEDPUMP AUTO START FAILURE 2000 FW52 STEAM BOUND AFW PUMP 2000 FW58 CBP FAILURE TO AUTO START 2000 IA02 PLANT AIR SYSTEM RUPTURE 2000 IA04 CONT AIR SYS RUPT IN TURBINE BUILDING 2000 MS01 MS LINE BREAK AT SG EXIT 2000 MS05 MAINSTEAM POWER RELIEF VALVELEAK 2000 MS10 MSR COIL DRAIN TANK LVLCONT FAILURE 2000 MS14 MSR STEAM SUPPLY VALVEFAILURE 2000 MS21 AUX STM 150¹ HDR CONTROL VALVEFAILURE 2000 NI04 SR ENERGIZATION AT POWER (P10 FAILURE) 2000 NI08 PR CHANNEL UPPER DETECTOR FAILURE 2000 NI12 AUDIO COUNT RATE CHANNEL FAILURE 2000 RC01 RCS COLD LEG LOOP RUPTURE 2000 RC05 REACTOR VESSEL HEAD FLANGE LEAK 2000 Page 6 of 11 Attachment 2

I J RC09 REACTOR COOLANT PUMP TRIP 2000 RC15 RPESSURIZER SPRAY VALVEFAILURE 2000 RC21 PRT RUPTURE DISC FAILURE 2000 RC26 FAILED FUEL ELEMENT 2000 RD02 BROKEN CONTROL ROD 2000 RD06 UNCONT ROD BANK CONTINUOUS WITHDRAWL 2000 RD10 CR MOVE OPPOSITE TO DEMAND SIGNAL 2000 RD14 IMPROPER BANK OVERLAP 2000 RD18 ROD CONTROL MG SET TRIP 2000 RHR HX FLOW CONTROL VALVEFAILURE 2000 RH08 RWST SUPPLY LINE TO RHR PUMP RUPTURE 2000 RH13 SI ACC TANK CHECK VALVELEAKAGE 2000 RM02 PROCESS RADIATIONMONITOR FAILURE 2000 RP06 SPURIOUS STEAM LINE ISOLATION 2000 RP10 FAILURE OF SI TO ACTUATE-AUTOMATIC 2000 RP14 FAILURE OF CI PAHSE A TO MANUALACT 2000 RP18 SPURIOUS ACTUATIONOF CI PHASE B 2000 RP22 RPS RELAY K621X2 FAILURE 2000 RX02 RCS HOT LEG TEMP TRANS FAILURE (NR) 2000 RX06 PZR CAL LEVEL TRANSMITTER FAILURE 2000 RX10 PZR WATER LEVEL CONT OSCILLATION 2000 RX14 STEAM DUMP PRESSURE CONTROLLER FAILURE 2000 RX18 MS TURB BYPASS HDR PRESS TRANS FAILURE 2000 RX26 FP TURBINE SPEED CONTROLLER FAILURE 2000 SI02 SAFETY INJECTION PUMP SHEARED SHAFT 2000 SW03 NESW RUPT ON LWR CONT VENT CLR SUPPLY 2000 SW07 MT OIL TEMPERATURE CONTROLLER FAILURE 2000 TC04 MAINTURBINE STOP VALVEFAILURE 2000 TC09 MAINGENERATOR LOAD LIMITERFAILURE 2000 TC13 TURBINE RUNBACK FAILURE 2000 TP05 STATOR COOLING WTR SYS HIGH CONDUCTIVITY 2000 TU06 TURBINE BLADE EJECTION 2000 CC01 COMPONENT COOLING WATER PUMP TRIP 2001 CC05 MISC CCW HDR RUPTURE IN AUX BUILDING 2001 CC09 CCW LEAK ON RHR PUMP SUPPLY LINE 2001 CC10 CCW LEAKAGEINTO RCP L. BRNG OIL RESERV. 2001 CS02 CONTAIN. SPRAY PUMP SUCTION BLOCKAGE 2001 CV02 LETDOWN LINE RUPTURE OUTSIDE CONTAIN. 2001 CV08 LETDOWN LINE RELIEF VLV SV-51 LEAKAGE 2001 CV12 CCP FLOW CONTROL VALVEFAILURE 2001 CV16 VCT LEVEL TRANSMITTER FAILURE 2001 CV25 RCP THERMALBARRIER HX RUPTURE 2001 CV30 REDUCED CCP CAPACITY 2001 CV34 CHG FLOW INSTRUMENT FAILURE (QFI-200) 2001 CW01 CIRCULATINGWATER PUMP TRIP 2001 Page 7 of 11 Attachment 2

ED12 LOSS OF 250 VDC POWER (TRAIN A) 2001 ED13 LOSS OF 250 VDC POWER (TRAIN B) 2001 ED23 LOSS OF SWITCHGEAR CONT POWER TRAIN A 2001 ED25 LOSS OF 765/345KV TRANSFORMER BANK¹4 2001 EG01 MAINGENERATOR TRIP 2001 EG06 DIESEL GENERATOR TRIP 2001 EG10 DIESEL GENERATOR FAILURE TO START 2001 EG14 DG RUNNING RELAY FAILURE 2001 FP03 DIESEL GENERATOR ROOM CO2 ACTUATION 2001 FW03 MFW RUPT BETWEEN FEEDFLOW ELMT & FRV 2001 FW12 FEEDPUMP TURBINE LUBE OIL SYSTRM LEAK 2001 FW17 HP HTR ¹6 LVLCONTROLLER AUTO FAILURE 2001 FW21 HP HTR ¹5 LVLCONTROLLER AUTO FAILURE 2001 FW25 HOTWELL PUMP TRIP 2001 FW29 LP HTR ¹3 LVLCONT TRANSMITTER FAIL 2001 FW33 LP HEATER BY PASS VALVEFAILURE 2001 FW37 HOTWELL PUMP DISCHARGE PIPING RUPTURE 2001 FW41 HW LEVEL CONTROL TRANSMITTER FAILURE 2001 FW45 HEATER FRAIN PUMP ELO VLVFAILS OPEN 2001 IA03 CONTROL AIR COMPRESSOR TRIP 2001 MS02 MAINSTEAM LINE BREAK AT SG EXIT 2001 MS06 STEAM GENERATOR SFETY VALVELEAK 2001 MS11 MSR COIL DRAIN TANK LVLCONT LVLFAIL 2001 MS16 STEAM SEAL CONTROLLER FAILURE 2001 MS22 MSIV MECHANICALBINDING 2001 NI01 SOURCE RANGE MONITOR FAILURE 2001 NI05 SOURCE RANGE CHANNEL SPIKES 2001 NI09 PR CHANNEL LOWER DETECTOR FAILURE 2001 NI13 SOURCE RANGE INSTRUMENT BLOWN FUSE 2001 RC02 RCS HOT LEG LOOP LEAK 2001 RC06 RCS EMERGENCY VENT LEAKAGE 2001 RC10 RCS COLD LEG LEAK 2001 RC11 REACTOR COOLANT PUMP HIGH VIBRATION 2001 RC12 RCP LOWER BEARING OIL RESERVOIR LEAK 2001 RC16 PRESSURIZER STEAM SPACE MANWAYLEAK 2001 RC23 STEAM GENERATOR TUBE RUPTURE 2001 RC27 RTD BYPASS MANIFOLDFLOW DEGRADATION 2001 RD03 STUCK CONTROL ROD (TRIPPABLE) 2001 RD07 UNCONT ROD BANK CONTINUOUS INSERTION 2001 RD11 AUTO CONTROL ROD SPEED FAILURE 2001 RD15 IRPI POWER LOSS 2001 RD19 IMPOPER ROD WORTH 2001 RH01 RHR PUMP TRIP 2001 RH05 RHR HEAT EXCHANGER TUBE LEAK 2001 RH09 RHR PUMP SUCTION PIPE RUPTURE 2001 Page 8 of 11 Attachment 2

1 RH14 SI ACCUMULATORTANKLEVEL LOW 2001 RM03 EBERLINE AREA RADIATIONMONITOR FAILURES 2001 RPOl REACTOR TRIP ACB AUTO TRIP FAILURE 2001 RP07 FAILURE OF STEAM LINE ISO TO ACTIVATE 2001 RP11 FAILURE OF SI TO ACTUATE-MANUALLY 2001 RP19 TRAIN "A" K600 RELAY FAILURES 2001 RP21 FAILURE OF FWI TRIP TO OCCUR 2001 RX03 RCS COLD LEG TEMP TRANS FAILURE (NR) 2001 RX07 REDUCED PRESSURIZER HEATER CAPACITY 2001 RX11 SG RELIEF VALVECONTROLLER FAILURE 2001 RX15 STEAM DUMP FAILURE TO RESPOND 2001 RX19 TURBINE IMPULSE TRANSMITTER FAILURE 2001 RX23 SG LEVEL TRANSMITTER FAILURE 2001 RX29 , FPC-250 TRANSMITTER FAILURE 2001 SI03 HIGH HEAD SI LINE RUPTURE 2001 SW04 ESSENTIAL SERVICE WATER PUMP TRIP 2001 TC01 MAINTURBINE TRIP, 2001 TC05 MAINTURBINE CONTROL VALVEFAILURE 2001 TC10 MAIN GEN OPERATING DEVICE FAILURE 2001 TP01 TURBINE AUX COOLING PUMP TRIP 2001 WD01 RELEASE OF RADIOACTIVEGAS FROM GDT 2001 CC02 CCW PUMP FAILURE TO AUTO START 2002 CC06 SEAL WATER HX TUBE LEAK 2002 CH01 CONTAIN. PRESS. RELIEF VLVFAILURE 2002 CS03 REFUELING WATER STORAGE TANK LEAK( 2002 CV04 LETDOWWN LINE ORIFICE ISO. VLV FAILURE 2002 CV09 LETDOWN TEMPERATURE CONTROL FAILURE 2002 CV13 CHARGING PUMP TRIP 2002 CV17 VOLUME CONTROL TANK LEAKAGE 2002 CV26 REACTOR COOLANT PUMP ¹1 SEAL FAILURE 2002 CV31 BACKPRESSURE CONT VLVFAILURE-QRV-200 2002 CW02 CW PUMP DISCHARGE VALVEFAILURE 2002 ED02 LOSS OF AUXILIARYTRANSFORMER 2002 ED03 LOSS OF RESERVE AUXILIARYTRANSFORMER 2002 ED06 LOSS OF 600 VAC BUS 2002 ED07 LOSS OF 480 VAC BUS 2002 ED11 LOSS OF 250 VDC BUS 2002 ED15 LOSS OF VITALINST BUS STATIC SWITCH 2002 ED16 AUXILIARIESAUTO BUS TRANSFER FAILURE 2002 ED19 ELECTRICAL GRID LOAD REJECTION 2002 ED20 ANN PANEL POWER SUPPLY FAILURE 2002 ED24 LOSS OF 250 VDC TRAIN "N" BATTERY 2002 EG03 MG AUTO VOLTAGE REG FAILURE TO MANUAL 2002 EG07 DG SPEED CONTROL FAILURE 2002 EG11 DIESEL GENERATOR FAILURE TO TRIP 2002 Page 9 of 11 Attachment 2

1 0 EG15 MG SEAL OIL UNIT PIPING RUPTURE 2002 BP05 CONTROL ROOM CABLE VAULTFIRE 2002 FW05 MAINFEEDPUMP TURBINE TRIP 2002 FW18 HP HTR ¹6 LVLCONTROL VALVEFAILURE 2002 FW22 HP HTR ¹5 LVLCONTROL VALVEFAILURE 2002 FW26 LP HTR ¹4 LVLCONT TRANSMITTER FAIL 2002 FW30 LP HTR ¹3 LVLCONTROL VALVEFAILURE 2002 FW34 CONDENSATE BOOSTER PUMP TRIP 2002 FW38 LOSS OF CONDENSER VACUUM 2002 FW42 CONDENSATE STORAGE TANK LEAK 2002 FW46 AUX FEEDPUMP TRIP 2002 FW50 TDAFW PUMP SPEED CONTROLLER FAILURE 2002 FW54 FDWTR RUPT OUTSIDE CONTAINMENT 2002 FW56 FEED PUMP STEAM SUPPLY CONT FAILURE 2002 MS03 MAINSTM LINE BREAK OUTSIDE CONT 2002 MS08 SG STOP VALVEDRIFTS SHUT 2002 MS12 MSR DRAIN TK ALT FRAIN LVLCONT FAIL 2002 MS17 STEAM SEAL CONTROLLER OSCILLATION 2002 NI02 SOURCE RANGE HV FAILURE TO DEENERGIZE 2002 NI06 INTERMEDIATERANGE MONITOR FAILURE 2002 NI10 POWER RANGE CHANNEL FAILURE 2002 NI14 INTERMEDIATERANGE CHANNEL BLOWN FUSE 2002 RC03 RCS LEAK 2002 RC07 REACTOR COOLANT PUMP LOCKED ROTOR 2002 RC13 RCP UPPER BEARING OIL RESERVOIR LEAK 2002 RC17 PRESSURIZER PORV FAILURE 2002 RC24 STEAM GENERATOR TUBE LEAK 2002 RC28 PRESSURIZER INSTURMENT LINE LEAKAGE 2002 RD04 STUCK CONTROL ROD (UNTRIPPABLE) 2002 RD08 IN-HOLD-OUTSWITCH FAILURE 2002 RD16 IRPI FAILURE 2002 RH02 RHR PUMP SEAL FAILURE 2002 RH06 RHR INJ HDR RELIEF VALVEFAIL (SV-104) 2002 RH11 RHR RET FLOW TRANS FAILURE (IFI-335) 2002 RH15 SI ACCUMULATORN2 PRESSURE LOSS 2002 RP03 FAILURE OF REACTOR TRIP BREAKER 2002 RP08 SPURIOUS FEEDWATER ISLOATION TRIP 2002 RP12 SPURIOUS ACTUATION OF SI 2002 RP16 FAILURE OF CI PHASE B TO AUTO ACTUATE 2002 RP20 TRAIN "B" K600 RELAY FAILURES 2002 RX04 PRESSURIZER PRESSURE TRANS FAILURE 2002 RX08 PZR SPRAY VALVEAUTO CONTROL FAILURE 2002 RX12 MS RELIEF VLV CONTROLLER OSCILLATION 2002 RX16 STEAM DUMP "PRES CONT" ERRATIC OPS 2002 RX20 SG STEAM FLOW TRANSMITTER FAILURE 2002 Page 10 of 11 Attachment 2

RX24 FW CONTROL VALVECONTROLLER FAILURE 2002 RX27 FEED PUMP DP CONTROLLER FAILURE 2002 RX28 LOSS OF 480V MCC 2002 SW01 'ON ESSENTIAL'ERVICE WATER PUMP TRIP 2002 SW05 ESW PIPING RUPTURE 2002 TC02 MAINTURBINE FAILURE TO TRIP 2002 TC06 MAINTURBINCE ERRATIC CONTROL VALVE 2002 TC11 AUTO LOAD SET OSCILLATION 2002 TP02 TURBINE AUX COOLING PIPING RUPTURE 2002 TP06 STATOR COOLING TUBE LEAKAGE 2002 TU03 MAINTURBINE HIGH VIBRATION 2002 Page 11 of 11 Attachment 2

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ATTACHMENT TO AEP:NRC:1260G9 RESTART PLAN REVISION