ML20077S008

Simulator Performance Testing Rept

ML20077S008
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/17/1995
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20077S000	List: 1CAN019502, Forwards ANO-1 Simulator Performance Testing Rept ML20077S008
References
NUDOCS 9501230225
Download: ML20077S008 (155)

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SIMULATOR MODIFICATION CONTROL 1 l i

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ANO TRAINING ADMINISTRATIVE GUIDELINE SIMULATOR MODIFICATION CONTROL REVISION 5 June 1, 1994 APPROVAL:

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SIMUL %1 DR SUPPORT SUPERVISOR

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.O TABLE DE CONTENTS I.O OBJECTIVE 2.0 DEFINITIONS 2.1 DATABASE CwudGE REQUEST (DBCR) ,

2.2 DESIGN CHANGE PACKAGE (DCP) 2.3 DESIGN CONCEPT DOCCMENT (DCD) 2.4 DESIGN DATA BASE (DDB) .

2.5 DISCREPANCY 2.6 DISCREPANCY REPORT (DR) ,

2.7 SIMUIATOR INSTRUCTOR (SI) 2.8 LIMITED CHANGE PACKAGE (LCP) 2.9 MODIFICATION 2.10 PLANT CHANGE (PC) 2.11 PLANT MODIFICATION (PM) 2.12 PROBLEM i 2.13 PROBLEM VALIDATION 2.14 REJECTED 2.15 SIMULATOR ENGINEER (SE) 2.16 SIMULATOR ENHANCEMENT i 2.17 SIMULATOR MODIFICATION (SM) i 2.18 SIMUIATOR TRAINING GROUP SUPERVISOR 2.19 SM DESIGN PACKAGE V 2.20 SOFTWARE CHANGE REQUEST (SCR) 2.21 SOFTWARE MODULE 2.22 SOFTWARE SIMULATION SYSTEM 2.23 SOFTWARE SPECIALIST 2.24 SYSTEM MODULE 2.25 SIMUIATOR SUPPORT SUPERVISOR (SSS) l 2.26 TEMPORARY MODIFICATION (TM) 3.O REQUIREMENTS 3.1 SOURCES OF SIMULATOR MODIFICATIONS (SM) 3.1.1 MODIFICATIONS TO REFERENCE FIANT 3.1.2 SIMULATOR PROBLEMS 3.1.3 SIMULATOR ENHANCEMENTS 3.1.4 SIMUIATOR SPECIFICATION CHANGE 3.2 SIMULA'IOR MODIFICATION (SM) FLOWPATH 3.2.1 IDElfrIFICATION OF THE PROBLEM 3.2.2 PROBLEM VALIDATION 3.2.3 SIMULATOR ENGINEER (SE) RECEIPT OF DR 3.2.4 AITrHORIZATION TO DEVELOP SIMULATOR MODIFICATION 3.2.5 60FTWARE/ HARDWARE DEVELOPMENT 3.2.6 DEVELOPMENT OF INITIAL TEST 3.2.7 DOCUMENTATION UPDATE 3.2.8 SIMULATOR MODIFICATION CLOSED G

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3 i O 4.0 CONFIGURATION MAMAGEMBfT SYSTEM (CMS)

, 4.1 FUNCTIONS PROVIDED 4.2 DR/PM 4.3 DDB r 4.4 DRAWINGS 4.5 JOB REQUEST r 4.6 MANUALS 4.7 VENDORS 4.8 SIMUIATOR AVAILABILITY 4.9 PREVENTATIVE MAINTENANCE TRACKING i 5.0 ATTACHMENTS l

FIG 1 SIMULATOR MODIFICATION PROCESS DIAGRAM ,

FIG 2 SIMULATOR DISCREPANCY REPORT FIG.3 DISCREPANCY REPORT CONTINUATION SHEET FIG 4 JOB REQUEST FORM FIG 5 SIMULA'IUR MODIFICATION SOFTWARE DESIGN FIG 6 SIMULATOR MODIFICATION TEST PLAN ,

FIG 7 WORK INCOMPLETE TAG 1

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1.0 OBJECTIVE To establish guidelines for the design, tracking, installation, documentation, and modifications to the Entergy Operations, ANO Unit I and II Simulators.

2.0 DEFINITIONS 2.1 Database Chance Reauest (DBCR) : Request for a database change due to changes in the reference plant, usually due to a plant modification.

2.2 Desion Chance Packace (DCP) : A collection of documentation providing the specifics of a plant modification.

2.3 Desion Concent Document (DCD): A document that describes the scope of simulation for each plant system.

2.4 .Desian Data Base [QQD.l.: A collection of data consisting of reference plant drawings, manuals, perforwance data and other documents that defines the plant being sinulated.

2.5 Discrecanev

A difference between observed performance and the current data base.

(h Q 2.6 Discrecancy Reoort (DR) : A form used to identify discrepancies (problems) and needed corrections and/or upgrading of the Simulator hardware and/or software and initiates the review and correction process.

2.7 Simulator Instructor (SI) : An instructor currently certified by the NRC to conduct Simulator training and appointed by the Supervisor of Simulator Training as the interface between the Operations Training group and the Simulator Support group or his appointed designee.

2.8 Limited Chance Packaoe (LCP) : A design package Lhat does not require a technical specification change.

2.9 Modifications

Any addition, deletion or change to simulation software or hardware.

2.10 Plant chance .1Pfd.. Documentation of a change to the reference plant which does not change a plant drawing or procedure.

2.11 P.lgnt Modification iPE) : Term used to describe one or all of the "ollowing - PC, DBCR, SCR, DCP, TM.

2.12 Problem: A difference between observed performance and expected or desired performance, p

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5 PJgbing Validation: The process of ensuring the simulator problem

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2.13 report identifies a valid problem.

i 2.14 Reieeted: The proposed software revision is not satisfactory.

2.15 SimulELgr Enoineer (SE). An individual responsible for changes in the performance of the simulators. The engineer will be designated by the Simulator Support Supervisor.

2.16 Simulator Enhancement: A simulator modification which will result in any of the following:

1. Addition of data to the Design Data Base.

2. Elimination of simulation design simplifications or assumptions.

3. Increasing the capability of the Simulator.

2.17 Simulator Modification lfML: A change in the simulation software or hardware.

2.18 Simulator Trainino Suoervisor (SS): Individual responsible for simulator training programs and the completion of performance / operability test as well as compliance with established regulations.

2.19 gg Desien Packaoe: The document that defines what the SM is to accomplish (specification or requirement) and now (design) the SM

[h is going to accomplish it.

L) 2.20 Software Chance Recuest (SCR) : Request for a software change due to changen in the reference plant, usually due to a plant modification.

2.21 Software Module: A unit of software whose source code is contained in one file.

2.22 Software Simulation System: The simulation system consi.-ts of the software necessary to execute and control the simulat_on. This shall include the job streams necessary to load, save, restoIJ and unload the simulation system.

2.23 Software Soecialis_t: An individual responsible for performing modifications on support software.

2.24 System Module: A software module that simulates a portion of a particular plant system.

2.25 Simulator Succort Suoervisor .(SSS) : Individual responsible for hardware and software maintenance of Simulators and its peripheral equipment at the training center.

2.26 Temocrary Modification lIMl: Modification to the reference plant

,_ that is not permanent.

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3.0 REQUIREMENTS 3.1 Source gi gg: It is intended that a Simulator modificatisa be initiated from one of four sources. These sources as well as a discussion of each follows:

3.1.1 Modificati.DDR 12 Shi Reference Plant: As modifications to a Simulator's reference plant are made (i.e., TM, DCP, PC, DBCR, SCR, LCP),

appropriate training and engineering evaluation of these modifications may result in the necessity to implement similar modifications into the Simulator.

Discrepancy Reports initiated as a result of a plant modifica tion (PM) should normally be cleared within one year after review.

NOTE: This typo ef Simulator modification will require updating of the Design Data Base.

3.1.2 Simulator Problem: As a result of trainee or Simulator Instructor feedback a problem with the current simulation system may be identified. Once reviewed, a SM may be initiated in order to resolve the problem. Discrepancy Reports initiated as a

/N result of observed improper simulator performance

(_-) should normally be cleared within three months.

3.1.3 Simulator Enhancements: It may become desirable to enhance the simulation beyond its current capabilities. If discussions between the Simulator Instructor and the Simulation Engineer result in an agreement to enhance the Simulator, a SM may be initiated. Discrepancy Reports initiated as a result of simulator enhancements should be cleared as simulator development time permits.

NOTE: This type of modification may result in the addition of data to the Design Data Base, the elimination of simulation design simplifications or assumptions, or extend the current scope of simulation.

3.1.4 Simulator Soecification Chance: From time to time it may become necessary to add, replace, or modify non-simulation software such as operating system software or system utilities, etc. Also, it may become necessary to modify the Simulator's hardware design. A SM should be initiated in order to document these type of changes. A Discrepancy Report initiated es a result of simulator p, specification changes should be cleared as simulator l

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V HQIE: This type of SM may require a change to the Design Data Base.

3.2- Simulator Modification ElgE Path: Any change to the simulator must be accompanied by documentation of the changes to be made.

Therefore a path to represent the flow of information is presented below. Please refer to Figure 1 for a process diagram.

3.2.1 Identification gi the Problem: Problems with the Simulator are generally discovered by Instructors or Operators in re-qualification, but may also be identified by others. '

It is the responsibility of all individuals to complete a Discrepancy Report (DR) upon observation of a discrepancy such that the perceived discrepancy can be validated and corrected at the earliest possible date. The following instructions will assist in completing these forms so that problems can be expeditiously resolved. The instructions have been keyed to circled item numbers on the attached DR form (Fig. 2). These DR forms are color coded for each '

unit with Unit 1 being RED and Unit 2 being BLUE. Items l 1-6 shall be completed by the originator of the DR when the discrepancy is detected.  !

O Item 1 Unit *The unit on which the discrepancy was

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observed. l Item 2 Date *The date the discrepancy was observed.

Item 3 Rept by *DR originator.

Item 4 Desc Prob

• Provide sufficient information and/or data '

such that the problem can be resolved by the Engineers with minimal assistance from the originator. If additional space is required, use the Continuation section located on the back of the DR form.

Item 5 PM#

• Enter a Plant Modification number if one

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applies to this DR. For plant mod, enter the l DCP #, SCR #, DBCR #, LCP, or PC # if  !

applicable. Proceed this number with L-LCP, l P-PC, S-SCR, or D-DBCR. No preceding letter required for DCP.

Item 6 Continued *If a Cont. Sheet is required, indicate by checking box. This will refer to the back of the form. Refer to figure 3 for an example of '

l this sheet.

3.2.2 Problga Validation: Upon receipt of the DR with the appropriate sectivt completed and supporting data, the SS shall determine 1: the prcblem is valid. If the problem j is not valid, an explana. ion Ke'.1 be attached to the DR 1 and both er.71 be re" arned to L 9 originator. If the  !

nroblem ic val.d, the

• shall the.: check the '

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( ); problem has been previously identified. If the problem has been identified, this shall be noted on the DR and the DR shall be returned to the originator. If the problem has not been previously identified, the SI should complete items 7-9.

Item 7 Source

• Identifies the category under which the DR originated.

Item 8 Priority

• Priority level of the DR based on training value. The criteria for priority selection is as follows:

1 - Training cannot be performed.

2 = Many facets of training cannot be performed.

3 - Some facets of training cannot be performed.

4 = Only a particular facet of training cannot be performed.

5 = Does not affect training or is deemed an enhancement.

Item 9 Priority Assigned *SS signs and dates after the above items have been completed.

3.2.3 Simulator Encineer ,,(H),Receiot gf a DE1 Upon receiving a (O

,) DR, the SE completes items 10-12 on the DR form (Fig 2).

Item 10 CMS Desc

• Enters a brief description of the overall scope of the DR.

Item 11 Initiated

• Signs and dates initiating the DR.

Item 12 Assigned To *The Engineer assigned to fix the problem.

3.2.4 Authorization 12 Develon Simulator Modification: Once the DR has been assigned, it is the responsibility of the Simulator Support Supervisor (SSS) to either approve, disapprove, or defer each DR proposed by the Simulator Engineer (SE). This action may take place as soon as the DR is initiated or may be delayed until manpower and cost considerations have been more carefully analyzed.

Disapproval of a DR shall be accompanied with an explanation of why the SM is not to proceed. Deferral of the SM means that implementation should not proceed until a specified event takes place (e.g., existing component requires replacement, final design data becomes available, etc.). Deferral shall be accompanied by a paragraph explaining the terms of the SM implementation. In any case, on the DR form (Fig. 2), items 13-14 shall be completed by the Simulator Support Supervisor.

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9 Item 13 Approved

• Sign and date to indicate approval of V[~T the DR for design and development or indicate disapproval or deferral.

Item 14 Due Date 'eA due date is also assigned by the SSS.

Upon completion of this portion of the DR form, the DR and/or DCP are entered into the Configuration Management System (CMS) . A DR number will automatically be assigned by the system in the format of W-XXX where W is the year and XXX is the next sequential log number for that year. Once CMS generates this number, it should be written in the space designated as items 15-16 in Figure 2. t Item 15 DR# *DR number generated by CMS Item 16 DDB#

• Enter Design Data Base Doc. No. if DR is not associated with a PM, then this number will be 000.XX.000 where XX is the year in DR#, If DR is associated with a PM, DDB# will be next sequential number in the DDB system. CMS will automatically assign this number. All DR's are filed in the design database under the specified number.

3.2.5 Software / Hardware Develooment: If any changes are necessary to the hardware, a design shall be submitted by the Simulator Engineer to the Hardware Technician. This design shall be of sufficient (7'}

(y,- detail for the technician to make all changes and shall follow established conventions for wiring, labeling, component installation, etc. A job request as shown in figure 4 shall be used as a cover sheet and tracking mechanism for a hardware design. Copies of a?.1 hardware procurement documents '

shall be part of this design package.

Any hardware work that is left incomplete shall be tagged appropriately with a Work Incomplete Tag. (Fig' 7)

If the SM requires software modifications, a ,

software design shall be developed by the Simulator '

Engineer (SE), Fig. 5 should be used for software design. At a minimum, the software design shall contain the file names of all source code modules that are to be modified as well as a description for the changes that are to be made to each section of a software module. Also, a listing of DATARASE/ GLOBAL changes should be a part of the software design.  ;

Accepted programming conventions shall be followed l in the software design. Referring to the DR form (Fig. 2), items 17-20 shall be completed by the ,

Simulator Engineer. '

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Item 17 Taken Item 18 Models

• Final action taken to correct DR.

• 4 letter model designation of models changed (ex. RKCR)

Item 19 Impi By *First initial and Last name Item 20 Date *Date of initial test and completion of work on development disk.

Any changes to the simulator software must be done in the following ranner:

1. Program History

-Identifier (initials followed by a sequential number i.e.

BH01,RR02, etc.)

- Discrepancy Report Nunter

- Date revision was made originally to code

- Date module was updated and placed in training load

- Any comments, descriptions, PM number, etc.

2. Model Documentecion

- Place the identifier on each line changed. This must be preceded by an (!) .

3. Use and Store

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- Always use the SM of a model or the highest T?. Store

[ '% in the next highest T?. (ex. if T2_RCFL is the highest,

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USE T2_RCFL and S7DRE as T3_RCFL)

4. Compile /' Catalogue

- Compile and Catalogue the new test file (T?)

3.2.6 Develcoment 21 Initial Test: Any SM that requires software modifications shall be tested by the SI or preferably, the originator of the DR. The test shall be designed to ensure that the modified Simulator meets the requirements specified by the DR. The test should consider prerequisites, if any that must be met prior to performing the test and shall indicate the necessity for updating simulator initial conditions files. It is the responsibility of the person (s) developing the test to consider, as a minimum, the necessity of testing any of the following:

a. Digital Inputs h. I/O Override

b. Analog Inputs i. Monitored Parameters

c. Lamp Check j. Logic Response

d. Meter Test k. Transient Response

e. Recorder Functions 1. Dynamic Response

f. Remote Functions m. Steady-State

[w/ j g. Malfunctions n. Switch Check

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.The process taken to perform a test shall be documented on the Simulator DR Test Plan (Fig. 6) .

If rejected, remedial design efforts should proceed. Once corrective action has been taken, modified appropriate sections l of the test previously used shall be prepared and run as j indicated above. l Upon clearing a DR on the development system, the Training Disks must be updated with the new software. The following steps will successfully update the Training Disks from a satisfactorily tested software change.

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1. Save test file to magnetic tape from Development  !

Disk.

Note: Verify that no other Test Files (T?) are on l

Si.mulator Load.

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2. Restore Test File to Training Disk from Magnetic Tape.

3. Compile and Catalogue Test File on Training Disk -

4. If test is satisfactory, store the test file as SM_????

5. Scratch !est File f

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6. Move to lievelopment Disk

7. Store test file as SM_????

8. Scratch tant file s

Referring to the DR form (Fig. 2), items 21-22 shall be used by the SI to record the acceptance or rejection of the software / hardware modification on the training load.

Item 21 Test Sat *If test is satisfactory, indicate here with a signature.

Item 22 Date

• Indicate the date of the satisfactory l test. This becomes the clear date of the DR. .

3.2.8 Documegattigst Dodate: The documentation update consist primarily of the DR package with the proper simulator ..

software design. Accuracy of the modification documentation can be maintained with the use of the DR/DCP packages and the controlled plant documentation. All drawings and documents provided by our vendors are located in our design database for review.

Therefore, all functional specifications, DCD's, and ,

drawings for both units are no longer.being updated from the baseline with the exception of the following:

Unit 1 Farnel drawings 5

12 Process drawings

['} Logic drawings

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Panel electrical distribution drawings Functional Specs not associated with plant systems Unit 2 DCD's not associated with plant systems The above documents have been determined to be necessary for proper maintenance of the simulators. The Simulator Engineer (SE) is responsible for the required updates.

After the SM has been accepted and implemented into the new training pack, the remaining update packages shall be incorporated into the reference documents by whatever means is currently being utilized (local control, Document Control, Engineering Records, etc). Referring to the DR form (Fig. 2) ,

items 23-24 shall be completed by the SE.

Item 23 Update Complete *To be completed after the update of all the documentation associated the DR.

Item 24 Date updated eIndicate the date the documentation was updated and indicate what was updated by

/"* checking the boxes marked: DOC - DCD or

( other written documentation, DRW -

Drawing, and NA - Not applicable.

3.2.8 SM_ Closed: It is the responsibility of the SSS to review the completed DR status file for clarity and legibility in preparation for entry into the Configuration Management System. Upon successful review, the SSS shall officially close out the DR by completing items 25-26 on the DR form (Fig. 2).

Item 25 DR Package eIf documentation update was completed as required, the SSS or his designated alternate shall verify that the documentation update was made and all other requirements were completed.

Item 26 Date eDate of review 4.0 Configuration Management System (CMS)

The Design Data Base File provides the accountability of all data and defines the status of the simulator. The maintenance of the DDB is not only regulated but necessary to maintain simulator fidelity. In the Configuration Management System, several files for each simulator unit

(N reside to support DDB, DRs, and PM's. The DR file provides a record of all i

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(~'T DRs and PMs written. The DDB file provides the information concerning the '

() Design Databases.

4.1 The CNS provides the following functions:

a. Establishes a baseline record (DDB)

b. Maintains a current data base of simulator design (DDB)

c. Tracks plant changes affecting simulator design and operation (PM)

d. Tracks plant changes not affecting simulator design and operation l (PM)

e. Trt>cks differences between the simulator and the simulator design bases (DR)

f. Tracks identified improvements needed in simulator design (DR)

g. Maintains additional databases used by Simulator Support which includes drawings, job request, manuals, vendors, availability, and preventative maintenance.

4.2 DR/PM (Tracked by the same file in CMS) 4.2.1 Discrepancy Reports (DRs)

a. Discrepancy Reports (DRs) are the focal point of all simulator modifications. No change is done on the simulator without a DR. The exception is routine hardware maintenance which is tracked by the Job Request System.

b. The DR file provides accountability for all the

/~'T information located on the DR form (Fig 2). All

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information is stored in this file for easy access,

c. Update of the DR file is done from the DR form per the attached flow chart (Fig 1).

4.2.2 Plant Modifications

a. Plant Modifications are tracked with the DR database file with a field for PM number. If the record has a PM number and no DR number, then the PM has been reviewed and does not affect the simulator. If the record has a PM number and a DR number, then the PM does affect the simulator and a Design Database Number is assigned, with the normal DR information entered.

b. The PM portion of the DR file provides accountability for the review of PM's and their associated implementation into the simulator,

c. Update of PM's is done through the training center PM review process which utilizes TEAR (Training Evaluation and Review) forms. Upon receipt of the TEAR, Simulator Support reviews the PM and makes the determination of simulator requiremento. The PM information is entered into CMS from a TEAR forti regardless of these

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requirements.

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Verification should be done semiannually to verify that .

all PM's have been reviewed by simulator support. This is done by cross checking with the TANDUM system as well as "

the. training center tracking programs.

P 4.3 Design Data Base (DDB)

a. The DDB file maintains a record of all entries into the design ,

database for the simulatcr. This includes all the baseline documents used during procurement and installation as well as current information such as technical manuals, drawings, power plant data, transient data, performance / operability test, and  :

any plant modifications or resolved discrepancies that have been made to the simulator

b. The DDB file provides accountability for all the modifications that have been made to the baseline simulator and reference f plant since procurement. ,

c. The DDB file is updated when a new item is added to the Design Data Base. At this time a number is_ assigned automatically by the CMS system. This number is in the form of WWW.XX YYY where WWW is a 3 digit system number, XX is the year, and YYY is a sequential number assigned by CMS. The WWW prefix was used in the early configurations, however, typically these digits are '

'000'. All DR's cleared in a specified year not associated with  ;

a Plant Modification (PM) are assigned the number 000.XX.000. ,

NOTE: The following are other files maintained by CMS which ,

are not directly related to simulator certification or ANSI 3.5. ,

4.4 Drawings

a. The Drawings file provides accountability for information pertaining to the simulator drawings for each unit. Items 1 include drawing number, sheet, revision, title, etc.

b. This file is not currently maintained with revisions, modification dates, etc. However, new drawings that are created are added to the file. Th file does represent the drawings that we currently have on n and.

4.5 Job Request

a. A Job Request file is maintained for tracking request made to the hardware staff.

b. Once the JR is written, it is entered into CMS and a JR number is assigned. When the work is complete and testing is satisfactory, the date the job was cleared is entered into CMS.

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a. The manuals database tracks all the manuals kept in the simulator support library for easy search for reference i material.  ;

b. Data is entered in this system by each member of simulator support when a new volume needs to be added to the simulator ,

library.  !

4.7 Vendors

a. The vendors database tracks the names, addresses, etc of any  !

vendor / contact that we may encounter in day to day operations.

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b. This data is entered by anyone on the system based on personal '

need.

4.8 Availability '

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a. The availability database is used on each unit to track the simulators availability as a percentage of time available to time scheduled. +

b. The data is provided to simulator support by the Simulator O Training Supervisor at the beginning of each month for the previous month. This information is entered and various reports are generated based on this information.

4.9 Preventative Maintenance i

a. The preventative maintenance file is used to maintain a record .

of the activities that need to be performed on the equipment used by simulator support and the period between activities.

b. This data is determined by the simulator engineers and the  ;

hardware technicians. Simulator support is notified when a task ,

has been completed and this date is entered into the system. i CMS provides a list of those tasks that are due to be performed and those that are delinquent.

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l (Oj Section 2 EXCEPTIONS TO ANSl/ANS 35.-1985 Attachment to NRC Form 474 Section 3.1.2, " Plant Malfunctions", contams a list of malfunctions that shall be included in the simulator and specifies in itern 12 the ability to simulate control rod failures including uncoupled rod and drifting rods be provided. The Unit I simulator does not presently have that specific capability, but our present capabilities in the area of rod malfunctions are more than adequate to provide the operators with the necessary training '

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SECTION 3 REFERENCE PLANT MODIFICATIONS INCORPORATED ON THE UNIT I SIMULATOR PERIOD BETWEEN 01/17/91 TO 01/06/95 DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 88-195 ADD BREATHING AIR St STEM TO SIMULATION.' JLG WTR/ MIS 80-1126 8/3/91 90-027 SECOND STAGE STEAM ISOLATION SECONDARY 89-1062 5/24/91 90-063 ANNUNCIATOR UPGRADE PHASE II LOGICS / CTRL 87-1071 8/18/91 90-093 CHANGE PCV3021 & PCV3028 TO CV's INST. AIDS 86-1001 7/8/91 90-096 INSTALL BAAT HIGH LEVEL ALARM AS PER PC 90- LOGICS / CTRL P90-7005 8/28/91 90-167 HPl/ AUX SPRAY STRATIFICATION MONITOR INST. AIDS 89-1018 9/12/91 90-168 OTSG SETPOINTS AND ICS SAFE STATES LOGICS / CTRL 88-10 % 9/26/91 90-169 ICS SIGNALS AUTO SELECTION LOGICS / CTRL 87-1041 9/8/91 90-170 RAD MONITOR INTERLOCK TO SERVICE WATER CLG WTR/ MIS 88-1092 8/29/91 90-210 RCP SEAL RECORDER LOCATION PANELS 86-1051 4/20/91 90-212 MAIN CHILLER ADDITION EL GEN /DIST. 88-1013 9/12/91 91-024 ATWS LOGICS / CTRL 85-1042 5/24/91 91-025 MOV ADDITION TO DH-7A & DH-7B LOGICS / CTRL 85-1051 7/21/91 PageI

Y  %)  %.J DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 91-026 CV1050/CV1410 AITFOCLOSURE HANDSWTTCHES LOGICS / CTRL 86-1129 8/4/91 91-027 CV7446 MOD, ADD SV7479 LOGICS / CTRL 87-1022 6/10/91 91-028 CV1009 POWER SUPPLIES LOGICS / CTRL 87-1057 8/18/91 91-029 CHANGE CV2613 2667 STROKE TINES LOGICS / CTRL 87-1099 6/14/91 91-030 ADD T40A/B LEVEL CONTROLS LOGICS / CTRL 88-1070 6/11/91 91-031 LPl/RB SPRAY RECORDER LOGICS / CTRL 90-1043 8/23/91 91-032 LTOP SETPOINT CHANGES CLG \VTR/ MIS 90-1062 8/19/91 91-033 RX TRIP SIGNAL TO MFW LP HP VALVE LOGICS / CTRL L90-5002 8/29/91 91-034 DISTILLER DRAIN & HIGH LEVEL PUMPS SECONDARY 90-1021 7/8/91 9l-035 GENERATOR OVEREXCITIATION/ GROUND EL GEN /DIST. 85-1092 9/20/91 91-036 PENETRATION ROOM VENT MODS, STROKE TINES LOGICS / CTRL 87-1106 8/29/91 9l-037 MUAP VALVE STROKE TINES LOGICS / CTRL 88-1087 6/17/91 91-038 CV1410/CV1050 STROKE TIMES LOGICS / CTRL 38-1088 6/14/91 91-039 CV1213/1215 STROKE TIMES LOGICS / CTRL 88-1089 6/8/91 91-040 CV1407/1408 STROKE TihES LOGICS / CTRL 88-1090 6/14/91 91-041 DECAY IEAT ALARMS LOGICS / CTRL 89-1044 9/8/91 91-042 CHANGE CV1428/29 TO MOV LOGICS /CFRL 89-1050 7/21/91 Page 2

/3 f) f) h V d DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 91-043 MSR SHELL & SEPARATOR DRAIN CHECK VALW SECONDARY 90-1023 7/8/91 9g.o44 NEW STARTUP BOILER LOGICS / CTRL 83-1167 4/22/92 91-045 CHANGE MU13 TO CV1275 LOGICS / CTRL 85-1050 6/8/91 91-046 ADD NEW AIR HANDLER TO RX BLDG CLG WTR/ MIS 87-1088 7/22/91 91-047 MODIFY TURBINE GENERATOR TRIP SEQUENCE LOGICS / CTRL 88-1083 9/20/91 91-048 T-40 A/B DUMP VALVE MODS LOGICS / CTRL 90-1024 7/8/91 93.o49 ADD REFUELING COMMUNICATIONS PANELS 89-1042 8/29/91 l

(91-050 ADD CVS TO P8A/B DISCHARGE LOG!'ECTRL 89-1063 8/19/91 {

91-051 P75 RECIRC VALVE TO YARWAY SECONDARY 90-1019 9/24/91 GLAND SEAL REGULATOR LOGICS / CTRL 90-1020 9/11/91

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91-053 ADD ACCUMULATORS TO CV3814 & 3815 LOGICS / CTRL 90-1032 8/19/91 91-054 HIC 3021 A AND HIC 3028A LOGICS / CTRL 90-1035 4/14/92 t 91-055 ISO BUSS ANALYSER POWER DEPENDENCY LOGICS / CTRL L90-5012 9/11/91 (91-057 LOVEJOY CONTROL MIN / MAX CHANGE LOGICS / CTRL P90-7082 9/11/91 91-067 ADD SPDS DIAG SCREEN SPDS SPDS.064 6/13/91 91-068 ADD PZR SURGE LINE TEMP SPDS SPDS.095 5/13/91 91-070 STOP SPUROUS DH ALARMS ON SPDS SPDS D5.121 5/13/91 Page 3 l

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91-072 SWAP AOTSG/BOTSG INDICATORON ATOG SPDS SPDS.068 6/13/91 91-073 ADD NEW HPI FLOWS TO SPDS SPDS SPDS.090 6/13/91 91-074 ADD MET TOWER DATA TO SPDS SPDS DS.Il6 5/23/91 91-075 CORRECT SPDS CODE SPDS SPDS.085 5/6/91 91 076 CORRECT DH DISPLAY SCREEN SPDS SPDS.082 6/13/91 91-077 ADD HPIINSTRUMENTATION TO SPDS SPDS D5.118 5/12/91 91-078 CHANGE E.V. CONVERSION SPDS D5.119 5/6/91 91-079 CHANGE E.V. CONVERSIONS SPDS D5.120 5/6/91 91-080 SPDS APPROACH TO CRITICAL SPDS SPDS 069 8/18/91 91-081 SPDS DECAY HEAT DISPLAY MOD SPDS SPDS.062 6/14/91 91-115 SPDS TRATEI SPDS D5.130 7/20/91 9l-119 SPDS PCMI SPDS SPDS.096 7/22/91 91-149 SPDS DH ALARMS SPDS SPDS.087 9/13/91 91-166 SPDS CHANGE SW SUCTION PRESSURE SPDS D5.131 11/4/91 91-167 MODIFY ICC DISPLAY SPDS SPDS.093 9/13/91 91-168 SPDS UPDATE GRAPHIC MENUS SPDS SPDS.072 3/4/92 Page 4

O O O DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 91-169 SPDS ADD BUS STATUS SPDS D5.128 3/15/92 91-181 LIGHTS FLASH SPDS D5.128 9/29/91 91-224 ANNUNCIATOR UPGRADE 111 LOGICS / CTRL 87-1072 8/10/92 91-225 H2 PURGE SYSTEM ISOL LOGICS / CTRL L91-5020 3/15/92 91-234 REMOVE FW 2874-3 FW 2876-3 LOGICS / CTRL 90-1025 3/15/92 91-236 CRD PROGRAMMER REPLACEMENT LOGICS / CTRL 88-1102 3/29/92 92-001 CV-1000 STROKE TIME LOGICS / CTRL L90-5029 3/22/92 92-002 CV1300 AND CVl301 STROKE TIME LOGICS / CTRL L90-5030 3/22/92 92-003 CV 2624 STROKE TIME LOGICS / CTRL L90-5031 3/22/92 92-004 CV 3640 THRU CV 3646 STROKE TIMES LOGICS / CTRL L90-5033 3/22/92 92-032 MSR DRAIN TANK LEVEL LOGICS / CTRL 88-1070 3/8/93 92-039 INSTALL NEW PLANT COMPUTER PMS-COMPUT 90-1067 8/28/92 92-040 ADDITION OF MOTOR OPERATORS TO DECAY HEA LOGICS / CTRL 90-l % 9 4/12/92 92-051 CV1219/20/27/28 REPLACEMENT LOGICS / CTRL 87-1097 3/29/92 92-032 CV1400/1401/1404 MODS LOGICS / CTRL L91-5010 3/22/92 92-053 VSF 9 POSITION SWITCH LOGICS / CTRL L91-5018 4/5/92 92-054 RE2400 REPLACEMENT LOGICS / CTRL 89-1021 9/19/93 Page 5

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DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 92-055 REMOVE VFP7A THROUGH H FILTERS LOGICS / CTRL P90-7059 3/15/92 92-081 EDG LOAD SEQUENCE TIMER MOD LOGICS / CTRL 92-1003 4/12/92 92-082 MODIFICATION OF EFIC REMOTE SWITCH MATRIX LOGICS / CTRL P91-7062 4/5/92 92-083 T-11 LOW LEVEL ALARM CHANGE LOGICS / CTRL P92-7003 3/22/92 92-084 DROPS ALARM ANNUNCIATOR MODIFICATION LOGICS / CTRL P91-7064 4/5/92 92-089 [OT-91] SW PUMP DISCHARGB PRESS LOW LOGICS / CTRL L91-6007 3/22/92 92-090 EDG VENTILATION DAMPER INDICATION LOGICS / CTRL L91-5025 3/27/92 924)91 PZR SPRAY VALVE HAND SWITCH MOD LOGICS / CTRL L91-5005 3/22/92 92-092 HPI LUBE OIL PUMP LOGIC CHANGE LOGICS / CTRL L92-5002 3/29/92 92-135 REMOVE LOW VOLTAGE TRIP ON YII EL GEN /DIST. P91-7056 6/22/92 92-136 PRESSURIZER HEATER MODS. LOGICS / CTRL P92-7033 12/30/92 92-152 EDG ROOM FAN DAMPER POSITION LOGIC CHANG LOGICS / CTRL L91-5025 9/21/92 92-155 CHANGE ICW FLOW RATES LOGICS / CTRL 83-1030 9/14/92 92-183 UPDATE PMS BURNUP PROGRAM PMS-COMPUT SW92-1000 8/24/92 92-184 ADD AVG POWERTO PMS PMS-COMPUT SW92-1001 8/24/92 92-185 ALLOW PMS TO RSTART NASP AT ANY EFPD PMS-COMPUT SW92-1006 8/24/92 92-1I;6 CORRECT PMS SDS MENU HANGUPS PMS-COMPUT SW92-1007 8/24/92 Page 6

d V v DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 92-187 ALLOW PMS DIRECT PRINTING PMS-COMPUT SW92-1009 8/24/92 92-188 ADD PMS FUNCTION TO ADD INCORES TO SCAN PMS-COMPlJr SW92<1011 8/24/92 92-189 AT PMS STARTUP HOLD NASP UNTIL PROC RUNNI PMS-COMPUT SW92-1014 8/24/92 92-190 ADD PMS WATCHDOG FUNCT!ON PMS-COMPUT SW92-1015 8/24/92 92-191 CHANGE PMS DIGITAL UPDATE RATE PMS-COMPUT SW92-1016 8/24/92 92-192 SET PMS NASP POINT TO LOCAL PMS-COMPUT SW92-1017 8/24/92 92-193 REMOVE PMS ALARM POINT FOR ROD #35 PMS-COMPUT SW92-1018 8/24/92 92-195 MODIFY PMS MFW SELECTION LOGIC IN NASP PMS-COMPUT SW92-1002 8/24/92 92-212 SPDS TEMP INCORE TEMP SPDS D5.135 10/8/92 92-213 SPDS CHANGE PZR TEMP TO T1001 SPDS SPDS.107 10/8/92 92-214 SPDS CHANGE RCS DIGITAL SPDS SPDS.108 10/8/92 92-215 SPDS CHANGE INPUTS OF CET HIGH TEMP ALARM SPDS SPDS.I10 10/8/92 92-216 SPDS CHANGE QUALITY CIECK FOR HOT LET LEV SPDS SPDS.109 10/8/92 c2-217 SPDS RETRANSLATE FMFWAl SPDS D5.134 10/8/92 92-218 SPDS ADD TRATEL TO IEATUP/COOLDOWN SCREE SPDS SPDS.100 10/8/92 92-219 SPDS REMOVE MODES TO TEMP INCORES SPDS D5.136 10/8/92 92-220 SPDS REMOVE CWA MODS SPDS SPDS.111 10/8'92 Page 7

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DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 92-221 SPDS MODIFY (JTR POINTS SPDS D5.137 10/862 92-222 SPDS CHANGE MISC LO ENG UNITS SPDS DS.138 10/8/92 92-223 SPDS CHANGE HI ENG LIMIT FOR F1236 SPDS D5.139 10/8/92 92-224 SPDS MODIFY CYCLE DEPENDENT CONSTANTS SPDS SPDS.ll2 10/8/92 92-225 SPDS MODIFY NDIT CURVE SPDS SPDS.104 10/8/92 92-226 SPDS ADD DATABASE POINTS SPDS DS.141 10/8/92 92-227 SPDS MODIFY SCM CURVE SPDS SPDS.ll4 10/8/92 92-235 PMS ADD BOOL POINT P3919 PMS-COMPUT DB92-1002 10/9/92 92-236 PMS FREE FORM PRINTOUTS PMS-COMPIJT SW92-1029 10/9/92 92-237 PMS EXTENT ARCHIVE FILE PMS-COMPUT SW92-1030 10/9/92 92-238 PMS FIX (JTQUEZ PMS-COMPUT SW92-1021 10/9/92 92-239 PMS ADD NASP POINT PMS-COMPUT SW92-1019 10/9/92 92-240 PMS USE ACTUAL FLOW IN CTPA CALC PMS-COMPUT SW92-1028 10/9/92 l 92-241 PMS EXTEND ARCHIVE FILE TO 7 DAYS PMS-COMPUT SW92-1027 10/9/92 1

92-242 PMS START CALC PWR LEVEL CHECK PMS-COMPUT SW92-1026 10/9/92 92-243 PMS CORRECT NASP ABORT PMS-COMPUT SW92-1023 10/9/92 92-244 PMS INITIALIZE QUALITIES AS GOOD PMS-COMPlTT SW92-1025 10/9/92 Page 8

. 1 DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 92-245 PMS MISC DATABASE CHANGES PMS-COMPUT DB92-1001 10/9/92 l 92-255 K02 B8/E8 SHOULD BE BLANK PANELS 87-1072 12/30/92 93-(m NEW 1/A COMPRESSORS LOGICS / CTRL 92-1021 9/5/93 93-017 PMS REMOVE DIVIDE BY 0 PMS-COMPUT SW92-1022 2/9/93 93-018 PMS - CHANGE ASSEMBLY ID FOR ASSEMBLY 169 PMS-COMPUT SW92-1033 2/9/93 93-019 PMS CHANGE POINTS IDENTIFIED BY DBCR PMS-COMPUT DB92-1003 2/9/93 93-020 SPDS - DELETE R7400 SPDS D5.142 2/9/93 93-021 PMS - CHANGE RCS LEAK RATE PMS-COMPUT SW93-1007 2/16/93 93-022 PMS ADD NEW P& ID DISPLAYS PMS-COMPUT SWs3-1002 2/9/93 93-029 PMS - ENABLE LOGIC PROCESS LOGICALS PMS-COMPUT SW92-3003 2/9/93 93-042 INSTALL ICS BACKUP TO MLSI MFW ISOL LOGICS / CTRL 91-1008 9/12/93 93-054 UNIT 1 CHEMISTY POINT ADDITION SECONDARY 92-1010 12/3/93 93-080 MODIFY DA OUT 2 PMS-COMPUT SW93-3013 5/17/93 93-082 DHR VORTEX MONITORING PRIMARY 91-1013 10/24/93 93-089 ADD MU1235-3 (PZR LEVEL BYPASS) PRIMARY 86-1028 5/14/93 93-090 LIMIT SCM INPUT TEMP 200F TO 700F LOGICS / CTRL 84-1051E 5/14/93 93-091 B5 AND B6 UNDERVOLTAGE RELAY SETPOINT CH EL GEN /DIST. 92-1007 5/21/93 Page 9

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LJ DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 93-098 SETPOINT CafANGE DATABASE P93-7022 5/21/93 l

93-103 INSTALL IIANDSWITCH COVERS PANELS L92-5038 9/26/93 93-104 CV1206 AND CV1234 STROKE TIME LOGICS / CTRL L91-5011 9/5/93 93-105 STROKE TIME EFW MOVS LOGICS / CTRL 91-1012 9/5/93 93-106 MAIN TURBINE LOW VACUUM TRIP SETPOINT CHA LOGICS / CTRL P93-7010 9/5/93 93-111 CORRECT POWER DEPENDANCY OF RB PRESSURE LOGICS / CTRL 83-1023 9/5/93 93-122 INSTALL B2 TO B7 CROSSTIE EL GEN /DIST. L92-5027 9/18/93 93-123 BLACK BATTERY ADDITION EL GEN /DIST. 90-1051 10/13/93 93-124 REPLACE ESF SWITCH GEAR SEQ RELAYS LOGICS / CTRL 92-1016 9/19/93 93-12_5 STROKE TIME FOR CVl416 LOGICS / CTRL 92-1011 9/26/93 93-126 INSTALL 22 KV REGULATOR EL GEN /DIST. 93-1003 9/26/93 93-171 REPLACE QUENCH TANK INDICATOR LOGICS / CTRL L93-5023 II/7/93 93-205 REPLACE MAKEUP FLOW INDICATOR PANELS L93-5012 12/31/93 93-212 CHANGE SUCTION PRESSURE ALARM ON P7A/B LOGICS / CTRL P92-7004 10/5/93 93-220 STROKE TIME CV2625/2675 LOGICS / CTRL L93-5016 10/10/93 93-224 STH DIESEL SETUP WORK EL GEN /DIST. 89-1022 6/21/94 93-225 MOVE CARD READER CABINET PANELS P92-7089 9/7/94 Page 10

( f Q) -I DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 93-255 PMS ADD F1238 TO PLANT COMPUTER PMS-COMPUT 93-1018 1In/93 93-338 PMS-CORRECT NASP ABORT PMS-COMPUT SW93-1022 lin/93 93-339 REMOVE SPARE TRANSMITTER PDS66r-3 LOGICS / CTRL P93-7069 11/7/93 93-340 NEW HIGH SETPOINT FOR EHC OIL PRESSURE LOGICS / CTRL P93-7027 11/18/93 94-046 SPDS MODIFY MENU DISPLAY SPDS SPDS.126 1/23/94 94-047 SPDS MODIFY CALCULATED RCS PRESSURE SPDS SPDS.125 1/23/94 94-048 SPDS INHIBIT ALARM PRINTING SPDS SPDS.I18 1/21/94 94.o49 SPDS UPDATE CYCLE CONSTANTS SPDS SPDS.133 1/26/94 94-050 SPDS MODIFY HU/CD/P&T CURVES SPDS SPDS.129 1/23/94 94-051 SPDS CHANGE ENG UNITS FOR ElHl/2 SPDS DBCR 5.148 1/26/94 94-052 SPDS ADD VORTEX WARNING SPDS SPDS.124 7/lI/94 94-091 ADD HIGH SOURCE RANGE TO K08 LOGICS / CTRL L93-5032 94-105 DELETE H2 SUPPLY LOW TO K05-D5 LOGICS / CTRL P93-7047 2/27/94 94-126 REMOVE DIESEL RUNNING INTERLOCK FOR VEF24 LOGICS / CTRL P93-7082 7/11/94 94-127 CHANGE OUT LENS COVER FOR CV-1248 PANELS P93 7060 4/17/94 94-171 REPLACE TI-2223 AND TI-2225 ON C09 PANELS L94-5002 94,g99 ARTS ALARM FOR MFW AT 7% & 9% LOGICS / CTRL P93-7012 8/22/94 Pagei1

O O O DR NUMBER DESCRIPTION CATEGORY PLANT MOD DATE NUMBER CLEARED 94-256 LOW CONDENSER VACUUM ANNUNCIATOR LOGICS /CIRL P94-7026 11/21/94 4

94-258 CV2806 STROKE TINE LOGICS /CIRL L94-5016 9/15/94 94-281 MODIFY SIMULATOR CEILING FOR VSF 9 MOD CLG WTR/ MIS L92-5032 94-282 EFW STROKE TINES, CV2620 2627 2670 LOGICS / CTRL 93-1008 10/10/94 94-283 CV-1052 STROKE TIME LOGICS / CTRL L94-5010 94 2g4 CV7443 7445 7447 7449 LOGICS / CTRL L94-5003 94-315 NEW POWER SUPPLY FOR P64 EL GEN /DIST. 92-1032 94-316 ADD LOW LEVEL INTERLOCK ON T20 TO PS2 LOGICS / CTRL P94-7064 94-317 ADD VALVES AND CONTROLS FOR SW WATER HA CLG WTR/ MIS 92-1019 94-330 REPLACE PMS PRINTER PMS-COMPUT L94-5019 94-331 POWER DEPENDENCY FOR WEATIER INPUT FROM EL GEN /DIST. P94-7049 94-332 NEW MFW VENTURI SECONDARY 94-1003 94-333 REPLACE INVERTERS & BATTERY CHARGES EL GEN /DIST. 93-1010 Page 12

m-,,_ . _ - - - . _ _ _ _

O Sectioo 4 SIMULATOR OPERABILITY TEST 1995-1998

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,. ARKANSAS NUCLEAR ONE UNIT 1 SIMULATOR OPERABILITY TEST YEAR 5 (FirSt Cycle)

REVISION 5.0 January 4,1995 DATE COMMENCED:

DATE COMPLETED:

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-TE APPROVAL: c N'r2 ///[f8

/ dATE SUPV., SIMULATOR TpNG .

h-SUPV., SIMULA7DR SUPPORT I. 4 9c DATE i 80 h<'-9f MGR h AND EMERG. PLANNING DATE O .

._ -... _._ ._ _ _ _ ~ _ _ .

l UNIT 1 OPERABILITY TEST  ;

i FORWARD l

The Simulator Operability Test will be performed annually. The collected data will be '

evaluated, discrepancies, if any, explained and attached to the Annual Simulator Report.

The Operability Test will provide the data to document satisfactory simulator response on an ongoing basis. It is required that all malfunctions listed in ANS-3.5,1985,3.1.2 '

and the operation test be tested every 4 years and a minimum of 25% tested each  !

year. '

The lists provided are suggested and should be followed. In the event that specific l conditions warrant a change in the events / malfunctions being performed, the Supervisor, Simulator Training will be informed of the necessary changes or revision to ensure that the changes are re-incorporated to meet the aforementioned  ;

requirements of ANS 3.5,1985.  !

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OPERABILITY TEST 1 January 4,1995 i

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TABLE OF CONTENTS U

A. SIMULATOR REAL TIME TEST . . . ... . . .. .. . .. . 4 B. NORMAL OPERATIONS TEST .. . . . . . .. . 9 NORMAL OPERATING PROCEDURES .. . .... . 18 PROCEDURE STEPS THAT WERE NOT COMPLETED . . .. ,, 19 COMPLETED CONTROL ROOM LOGS . . . ... . . 20 ,

C. STEADY STATE OPERATIONS TEST . . . .. . . . . 21 40% RATED POWER .. .. .. . ..... .. . . .. 29 66% RATED POWER .. . .. .. . . . .. 30 100% RATED POWER ,. .. . ... 31 D. SURVEILLANCE TEST . . . . . . . 32 COMPLETED SURVElLLANCE TESTS . .. . . . 34 ,

PROCEDURE STEPS THAT WERE NOT COMPLETED . . .. . . . 40 SURVEILLANCE PROCEDURES ... . .. . .. . 41 E. TRANSIENT TEST .. . . .. .. . ... ... .. ... .... 42 MANUAL REACTOR TRIP . ..... ........ .. ..... . ... . 50 ,

SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS . .. . 51 SIMULTANEOUS CLOSURE OF BOTH MSIVs ... . . .. .. 52 SIMULTANEOUS TRIP OF ALL RCPs . .. . . ... .. 53 ,

TRIP OF ONE RCP . ...... . .... . . . . .. . . . 54 MAIN TURBINE TRIP AT 40% POWER WITHOUT A REACTOR TRIP .. 55 MAXIMUM RATE POWER RAMP .. ...... ...... . 56 MAXIMUM SIZE RCS RUPTURE AND LOSS OF OFFSITE POWER . . . . 57 MAXIMUM SIZE UNISOLABLE MAIN STEAM LINE BREAK . . . . 58 s SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATION . 59 TIME IN LIFE TEST . ... , . . ... . . .. . . .. 60 F. MALFUNCTION TEST .... . . ..... . . . . . .. 61 MALFUNCTION CAUSE AND EFFECTS LISTING FOR MALFUNCTIONS TO BE TESTED .... ... 89 G. RETEST ITEMS FROM LAST OPERABILITY TEST . . . . .. ... 90 l

OPERABill1Y TEST January 4,1995 2

REFERENCES ........... .. ..... . . ..... ...... .. . 91 Q .

LIST OF POINTS RECORDED DURING TRANSIENT TEST USING HISTORICAL DATA LOG #1 ... . . .. 92 LIST OF POINTS RECORDED DURING TRANSIENT TEST USING HISTORICAL DATA LOG #2 ... . .. .. 93 LIST OF POINTS RECORDED DURING TRANSIENT TEST USING HISTORICAL DATA LOG #3 . . . . .... . 94 LIST OF POINTS RECORDED DURING TRANSIENT TEST USING HISTORICAL DATA LOG #4 ... .. ... 95 LIST OF POINTS RECORDED DURING TRANSIENT TEST ,

USING HISTORICAL DATA LOG #5 . . ... ... .. 96 t DR LOG . ................. ...... ...... . . ..... 98 SUBJECT MATER EXPERT EXPERIENCE

SUMMARY

. . . . . . .. 99 CHRONOLOGICAL LOG . . . ..... .......... .. ... . .100 DELOGGING HISTORICAL DATA LOGS . . . ...... .... .. 101 OPERABILITY TEST STAFF ... . . .. .. . .. . .. .102 O

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I O OPERABILITY TEST 3 January 4,1995

i A. SIMULATOR REAL TIME TEST  :

?

1.0 DISCUSSION  ;

The purpose of this test is to assure that the Simulator is running in real time. I Real-time calculations may be performed on-line by load module RTTEST - ,

[r which resides on the RSX. -It calculates a real-time ratio by continually dividir ,

elapsed simulator time by elapsed real time. l This test will also gather CPU spare cycle time statistics for normal, transient, and emergency operations. l 2.0 REFERENCE (S) ,

2.1 ANS-3.5,1985 A3.1, ANS NPP Simulator for Operator Training.  !

2.2 ANO Unit-1 Instructor Station User Guide. i 2.3 REALTIME program O  ;

. 3.0 EQUIPMENT l

3.1 ANO-1 Simulator ,

. 3 4.0 INITIAL CONDITIONS j t

4.1 100% Power, IC-2 f

5.0 ACCEPTANCE CRITERIA j 5.1 REAL-TIME ratio will be greater than 98% for all test case.=.

5.2 CPU spare cycle time will be greater than 0% for all test cases.  ;

O OPERABILITY TEST 4 January .4,1995 i

6.0 NON-ACCEPTANCE OF SIMULATOR RESULTS c 6.1 If the Simulator REAL-TIME ratio or spare cycle time do not meet the tcceptance criteria in 5.0, adjustments will be made before the Simulator is used for routine training.

7.0 PROCEDURE - NORMAL OPS INIT 7.1 Initialize to 100% Rated Power (10-2).

Place Simulator in RUN.

7.2 Using Z:CPUSP obtain the CPU spare cycle time for the RSX 4

by entering the following at the TSM prompt:

7.2.1 TSM>! ACTIVATE Z:CPUSP 7.3 Obtain data from printer and record the minimum spare cycle times here. .

CPU 7.4 On a RSX terminal, type TSM>RT. After 2 minutes, place simulator in FREEZE. Record here the final displayed value of RTRATIO.

REALTIME RATIO MODELXC =

REALTIME RATIO MODELXI =

REALTIME RATIO MODELXM =

REALTIME RATIO MODELXK =

REALTIME RATIO MODELXL =

AVG REAL TIME RATIO =

OPERABILITY TEST s January 4,1995

)

g.y 8.0 PROCEDURE - TRANSIENT OPERATION y) INIT 8.1 Initialize to 100% Rated Power (IC-2). Place simulator in RUN. Trip the reactor.

8.2 Using Z:CPUSP obtain the CPU spare cycle time for the RSX by entering the following at the TSM prompt:

8.2.1 TSM>! ACTIVATE Z.CPUSP i

8.3 Record the minimum spera times here.

CPU 8.4 On a RSX terminal, type TSM>RT. After 2 minutes, place simulator in FREEZE. Record

~

here the final displayed value of RTRATIO.

REALTIME RATIO MODELXC =

REALTIME RATIO MODELXI =

REALTIME RATIO MODELXM =

REALTIME RATIO MODELXK =

REALTIME RATIO MODELXL =

AVG REAL TIME RATIO =

.i OPERABILITY TEST s January 4,1995 l

1 9.0 PROCEDURE - EMERGENCY OPERATION O

A/ INIT 9.1 Initialize the 100% Rated Power (IC-2). Place simulator in RUN. Activate malfunction for a 100%

MSLB outside containment on A OSTG.

9.2 Using Z:CPUSP obtain the CPU spare cycle times for the RSX by entering the following at the TSM prompt:

9.2.1 TSM>! ACTIVATE Z:CPUSP 9.3 Record the minimum spare cycle times here.

CPU 9.4 On a RSX terminal, type TSM>RT. After 2 minutes, place Simulator in FREEZE. Record here the final displayed value of RTRATIO.

REALTIME RATIO MODELXC =

REALTIME RATIO MODELXI =

REALTIME RATIO MODELXM =

REALTIME RATIO MODELXK =

REALTIME RATIO MODELXL =

AVG REAL TIME RATIO =

10. FINAL CONDITIONS 1 l

10.1 Data has been recorded and saved verifying computer j Real Time during normal, transient, and emergency l situations.

)

1 10.2 Spare cycle times exceed 0% for all cases recorded.

i 10.3 Real-Time ratios exceed 98% for all cases recorded.

10.4 List any DISCREPANCIES on Attachment A-1.

O OPERABILITY TEST 7 January 4,1995 l

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.,,, . . . - . . . . . - - ~ _ . . - . . - .__. =, . - . .-

t ATTACHMENT A-1,REAL-TIME TEST I h DISCREPANCY LIST l STEP NUMBER DESCRIPTION D.R.' # l NONE NONE NONE  :

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I OPERABILITY TEST a January 4,1995 1

,s B. NORMAL OPERATIONS TEST

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1.0 DISCUSSION Normal operations are performed to demonstrate the ability to operate the Simulator in accordance with reference plant operating procedures.

Normal operations v.ill be tested by splitting the normal operations test into four segmentF, one of which will be tested each year.

2.0 REFERENCE (S) 2.1 ANS 3.5,1985, 3.1.1, ANS NPP Simulator for Operator Training.

2.2 ANO Unit 1 Operating Procedures, Attachment B-1.

3.0 EQUIPMENT 3.1 Stop watch.

4.0 INITIAL CONDITIONS

( 4.1 Initial plant conditions will be as stated in Section 7.0.

v 5.0 ACCEPTANCE CRITERIA 5.1 The Simulator will perform, without distraction from training, reference plant normal operations.

5.2 Reference plant normal operations can be performed on the simulator using only operator action normal to the referenced plant.

6.0 NON ACCEPTANCE OF SIMULATOR RESULTS 6.1 Non acceptance is the inability of the Simulator to perform reference plant normal operations using only operator actions normal to the reference plant or performance that distracts from training.

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'v OPERABILITY TEST s January 4,1995 l

_ - - - _ _ _ - _ - _____-_-____A

6.2 Non acceptance of Simulator performance shall halt the routine

( training involving such operations. Discrepancies shall be recorded, k -l) models enhanced, and retested as required.

7.0 PROCEDURE 7.1 Using the latest revision of the reference plant procedure, perform the following operations:

The test will be split as follows:

a. In year one.1995. the plant will be initialized at 100% power and will be brought to hot standby power by plant procedures and this test procedure. (Step 7.1.3) Also, perform reactor trip recovery from 100% (Step 7.1.1).

b. In year two.1996. the simulator will be initialized at 25% power and will be brought to cold shutdown condition using plant procedures and this test procedure. (Step 7.1.4)

c. In year three.1997. the simulator will be initialized in cold shutdown, a plant heatup/startup to hot standby power will be done using plant procedures and this test procedure. (Step 7.1.5)

(g) Also, perform 70% power steady state with 3 RCPs to hot shutdown and return to 70% power. (Step 7.1.2)

d. In year four.1998. of the cycle, the simulator will be initialized at hot standby power and as directed and by plant procedures will be brought to 100% power. (Step 7.1.6)

NOTE: Procedures are to be initiated / signed as appropriate.

NOTE: All procedure steps that cannot be simulated shall be marked NS. These steps are to be listed on Attachment B-2 and explained. The steps of the procedure that are marked N/A as allowed by the procedure are not to be listed on Attachment B-2.

NOTE: Initial Conditions (ICs) will be stored as designated.

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V OPERABILITY TEST to January 4,1995 ;

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t 4

5

, NOTE: Use Fast Time for Xenon and Pressunzer Heatup as ,

I appropriate.

t NOTE: The following Control Room Logs shall be completed during this test:

a. Switchboard Log 1015.03A-5

b. CBO Turbine Log 1015.03A-6

c. CBO Reactor Log 1015.03A-7 -

d. Reactor Power History, 1015.03A-8 L Tilt, and imbalance Log

e. Unit One WCO Tech 1015.03A-19 Spec Logsheet 7.1.1 Reactor Trip Recovery from 100% Power INIT (Year One,1995)

1. Recall IC-2,100% Power

2. Complete set of control room logs l

3. Manually trip the reactor.

4. Carry out all required steps of EOP 1202.01 Reactor Trip.

5. Verify the reactor is stable at Hot Shutdown.

6. Establish IC-19, Hot Shutdown Post Trip.

7. Calculate the value of Xenon 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post trip.

8. Use fast time Xenon and establish new Xenon concentration for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post trip.

9. Establish IC-20, Hot Shutdown 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post trip.  ;

10. Complete OP1102.006, Reactor Trip / Outage Recovery.

11. Using plant procedure OP1102.002, start up the plant to 20%.

OPERABILITY TEST 11 January 4,1995

n INIT

( 12. Establish the following ICs while increasing M) reactor power to 20%.

IC-13 535' F Group 1 rods out ,

IC-14 535' F Safety rods out IC-15 Reactor Critical at 1E-8 amps IC-16 2% from startup IC-17 7% from startup IC-1815% from startup

13. Using plant procedure OP1102.004, increase power to 100%.

14. Ensure all normal operating logs are signed, dated and reviewed when this test is complete.

15. Put all signed procedures, completed log sheets, and required forms into a binder marked for this evolution. Do not include any surveillances, completed surveillances will be placed into a separate binder.

O OPERABILITY TEST 12 January 4,1995

.7.1.2 70% Power Steady State with 3 RCPs to Hot INIT

' (].

Shutdown and Return to 70% Power.

(Year Three,1997) ,

1. Recall 100% power, equil XE, MOL. (IC-2)

2. Complete set of control foom logs

3. Using plant procedure OP1102.004, reduce power ,

to < 60%.

Using plant procedure OP1103.006, stop the C 4.

reactor coolant pump.

5. Using plant procedure OP1102.004, increase ,

power to 70%. L f

6. Use fast time Xenon, TCF1, on the IA console to equalize and stabilize Xenon for 70%

reactor power.

7. Establish IC-4 at 70% reactor power with 3 RCPs _ .

f running.

O 8. Using plant procedure OP1102.004, reduce power

• to 20%.

9. Using plant procedure OP1102.010, reduce power to hot shutdown.

10. Using plant procedure OP1102.002, startup the plant to 20%.

11. Using plant procedure OP1102.004, increase power to 70%.

12. Ensure all normal operating logs are signed dated, and reviewed when this test is complet.'.

l

13. Put all signed proceoures, completed log sheets, and required forms into a binder marked for this evolution. Do not include any surveillances; completed surveillances will be placed into a separate binder.

OPERABILITY TEST 13 January 4,1995

INIT

.! 7.1.3 100% Power to Hot Standby

k. (Year One,1995) '

1. Recall 100% power, Equil Xe, MOL.

2. Complete set of control room legs

3. Establish the following 'Cs while reducing power to 20%.

IC-5 80% 4 RCP TRANS XE ,

IC-6 50% 2 MFP TRANS XE IC-7 35% 1 MFP TRANS XE _,

IC-8 25% 1 MFP TRANS XE

4. Using plant procedure, OP1102.004, reduce power to 20%. Do not exceed 30%/ hour rate  :

of change.

5. Using plant procedure OP1102.010, shut down the plant to hot standby.  ;

6. Ensure all normal operating logs are signed,

( dated, and reviewed when this test is i complete.

7. Put all signed procedures, completed log sheets, and required forms into a binder marked for this evolution. Do not include any surveillances; completed surveillances will be placed into a separate binder.

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OPERABILITY TEST 14 January 4,1995

h INIT +

(7 v'-

7.1.4 25% to Cold Shutdown -

(Year Two,1996)  ;

1. Recall 25% power, equil Xenon.  ;

2. Complete control room logs

3. Establish the following ICs while shutting down:

IC-9 290' Cooldown in Progress ___

IC-10 CSD stm in Pzr,DH cooling

4. Using plant procedure OP1102.010, shutdown and cooldown the plant to cold shutdown.

5. Ensure all normal operating logs are signed, dated, and reviewed when this test is complete.

t

6. Put all signed procedures, completed log sheets, and required forms into a binder marked for this evolution. Do not include any surveillances; .

completed surveillances will be placed into a separate binder.

O V OPERABILITY TEST 15 January 4,1995

INIT

(.~)

7.1.5 Cold Shutdown to 2% Power.

(Year Three,1997)

1. Recall cold shutdown; no Xenon.

2. Complete control room logs

3. Using plant procedure OP1102.02, heatup/startup the plant to 20% power.

4. Establish the following ICs while starting up:

IC-11 CSD 225# Steam in Pressurizer IC-12 435' F 1650# HU in Progress IC-13 534' F Group One Out IC-14 534' F Safeties Out IC-15 Reactor Critical at 10E-8 Amps IC-16 2% From Startup AFW Pump On

5. Ensure all normal operating logs are signed, dated and reviewed when this test is complete.

6. Put all singed procedures, completed log sheets, bi and required forms into a binder marked for this evolution. Do not include any surveillances; completed surveillances will be placed into a separate binder.

,q V OPERABILITY TEST 16 January 4,1995

1 l

l INIT jf 7.1.6 2% Power to 100% Power ,

. (Year Four,1998)

1. Recall 2% power, equil Xenon.

2. Complete control room logs

3. Establish the following ICs while starting up:

IC-17 7% From Startup Main Turbine Off IC-1815% From Startup Main Turbine On f

4. Using plant procedures OP1102.002 and '

OP1102.004, raise plant power to 100%.

5. Ensure all normal operating logs are signed, dated, and reviewed when this test is complete.

6. Put all signed procedures, completed log sheets, ,

and required forms into a binder marked for this evolution. Do not include any surveillances, completed surveillances will be placed into a l separate binder.

O 8.0 FINAL CONDITIONS The normal power operations are completed. All operating logs are filled out, signed and included in Attachment B-3. All required ICs are established.

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OPERABILITY TEST 17 January 4,1995

ATTACHMENT B-1

-i NORMAL OPERATING PROCEDURES O

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O OPERABILITY TEST 18 January 4,1995

ATTACHMENT B-2 PROCEDURE STEPS THAT WERE NOT COMPLETED  :'

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PROCEDURE:

STEP # REASON FOR NON-COMPLETION k OPERABILITY TEST is January 4,1995

ATTACHMENT B-3 COMPLETED CONTROL ROOM LOGS O

OPERABILITY TEST 20 January 4,1995

_ .- _. -_ _ - ~ _ _ . - _ - - _ ._- ._ _ __ . __

O C. STEADY STATE OPERATIONS TEST M ,

1.0 DISCUSSION Stability of the Simulator is to be demonstrated by establishing a Steady State ,

condition and monitoring parameter variation with respect to time. Simulator computed values are also to be compared to reference plant data at various power levels. i 2.0 REFERENCE (S) -

2.1 ANS 3.5,' 1985,4.1, A.3.2, ANS NPP Simulators for Operator Training.  !

2.2 ANO Unit 1 instructor Aids Manual 3.0 EQUlPMENT l 3.1 Stop Watch 3 3.2 Personal computer with communications and spreadsheet software.

f O 4.0 INITIAL CONDITIONS l 4.1 ' Initial Plant Conditions will be as stated in this procedure. i 5.0 ACCEPTANCE CRITERIA '

5.1 The simulator computed values for steady state, full power operation with the reference plant control system configuration shall be stable and not vary -

more than +/- 2% of the initial values over a GO minute period. :i i

5.2 Simulated computed values of critical parameters shall agree with the '

reference plant within +/- 2% of the instrument range and shall not detract from training.

5.3 Simulator computed values of non-critical parameters shall agree with the reference plant within +/- 10% of the instrument range and shall not detract  :

from training.  ;

l O OPERABILITY TEST 21 January 4,1995 j

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Y NOTE: The OTSG Operate range levels are not to be considered as critical

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parameters due to the dynamic nature of a B&W OTSG. The levels

. change at the reference plant due to fouling and efficiency that are

- not readily identified and have no effect on training within the small band the level changes. The levels indicated on the data sheets are taken from March 1993 control room logs.

6.0 NON ACCEPTANCE OF SIMULATOR RESULTS 6.1 Non acceptance is defined as any critical parameter value outside the range set forth in Section 5.0.

6.2 Non acceptance shall halt the routine training involving such operations. Discrepancies shall be recorded, models enhanced, and retested, as required.

NOTE: If evaluation of collected simulator data is unsatisfactory, rerun appropriate portions of data collection after adjustments are completed.  ;

NOTE: Non-critical parameters will be compared by Operator observation only and will not be saved.

7.0 PROCEDURE-7.1 Obtain Simulator Data for 40% Power INIT 7.1.1 Recall the desired power with equilibrium xenon. / / ,

40 66 100 7.1.2 Verify steady state conditions. / /

40 66 100 7.1.3 To start recording Historical Data, enter the / /

following at the lA console: 40 66 100 HSTR < ENTER > 5 < ENTER > 0 < ENTER >

1 < ENTER > 3600 < ENTER > Y < ENTER >

7.1.4 Start the stop watch to measure 20 minutes. / /

At 20 minutes, HSUS< ENTER > at the lA console. 40 66 100 O

V OPERABILITY TEST 22 January 4,1995

I l

O . INIT 7.1.5 The following Control Room Logs shall be

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/ /  ;

completed during this test: 40 66 100 a Switchboard Log 1015.03A-5

b. CBO Turbine Log 1015.03A-6

c. CBO Reactor Log 1015.03A-7

d. Reactor Power History, 1015.03A-8  :

Tilt, and imbalance Log

e. Unit One WCO Tech 1015.03A-19 Spec Logsheet 7.1.6 The first line of readings on the above listed / /

logs shall be filled out in advance from the 40 66 100 plant logs taken at the same reference power.

7.1.7 The log sheets shall be reviewed to terify / /

fidelity to the plant readings. The logs are 40 66 100 to be retained in Attachment C-1, C-2 or C-3 as appropriate. ,

7.1.8 Fill in the data sheets that follow. The Simulator / /

data col:3cted must be between the max and min 40 66 100 l limits listed on each data point. The cause of any point not being between the max and min shall be determined and corrected. The test shall be repeated to prove performance at steady state.

7.1.9 Delogging the Historical Data Log File refer to / /

Attachment 9. 40 66 100 7.1.10 Attach all graphs and the data printouts to / /

Attachment C-1, C-2 or C-3 as appropriate. 40 66 100 I

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C,D OesRABitir< TEST aanuary4,,ee5 23 l

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t INIT- 1 7.2 Obtain Simulator Data for 66% power.

2 - -  :

t 7.2.1 Repeat steps 7.1.1 through 7.1.10 for 66 % power.  !

7.3 .Obtain Simulator Data for 100% power.  !

i 7.3.1 Repeat steps 7.1.1'through 7.1.10 for 100% power. i Historical data shall be run >60 minutes at 100% power.  !

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l OPERABILITY TEST u January 4,1995 i

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7.4 Delogging Simulator Data i

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. 7.4.1 40% rated power Reference Plant Simulator D::scription Tag Actual Min Max Min Value Max Value Racetor Power TRNT0005 40.0 39.2 40 8 Core Thermal Megawatts RXMWTCOR 1027 1006 1047 G2nerated Watts GNJA100 300 280 320 ,

Teve ULA351G 579 577 581 A OTSG Pressure IMA35201 900 878 922 A OTSG Operate Range Level STAA755G 13* 3* 23' Prsssuruer Level FRL1000 220 214 226 B OTSG Steam Temperature TRT2631 590 577 603 Boron Concentration RCX0008 716 675 757 B OTSG Pressure IMA35202 900 678 922 B OTSG Operate Range Level STAA756G 13* 3* 23' Prsssur2er Water Temperature PRT1001 647 633 661 RCS Pressure RCP002 2155 2095 2215 A OTSG Steam Temperature TRT2681 595 583 607 A Main Feedwater Temperature STAA7251 370 360 380 A Main Feedwater Flow STA35241 1855E6 1.73E6 1.97E6 Loop A Cold Leg Temperature ULA35181 SG9 567 571 Loop A Hot Leg Temperature ULA35171 589 587 591 Group 7 Rod Posmon RDGRPAVE(7) 129.6 126.7 132.5 B Main Feedwater Temperature STAA7252 370 360 380 t

B Main Feedwater Flow STA35242 185E6 1.73E6 1.97E6 Loop B Cold Leg Temperature ULA35182 569 567 571 loop B Hot Leg Temperature ULA35172 589 587 591 r

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OPERABILITY TEST 25 January 4,1995 l

_7.4.2 66% Rated Power Reference Plant Simulator Desenption Tag Actual Min Max Min Value Max Value Riactor Power TR NT0005 66 63.5 68 5 Core Thermal Megawatts RXMWTCOR 1695 1661 1729 G1nerated Watts GNJA100 555 535 575 Teve ULA351G 579 577 581 A OTSG Pressure IMA35201 905 883 927 A OTSG Operate Range Level STAA755G 28* 18* 38' Prissunrer Level PRL1000 220 214 226 B OTSG Steam Temperature TRT2631 600 588 612 Baron Concentration RCX0008 640 599 581 B OTSG Pressure IMA35202 905 883 927 8 OTSG Operate Range Level STAA756G 28* 18' 38' l

.-s_.. -.

Pr:ssunter Water Temperature PRT1001 647 633 661 RCS Pressure RCP002 2155 2095 2215 A OTSG Steam Temperature TRT2681 600 588 612 A Main Feedwater Temperature STAA7251 420 410 430 A Main Feedwater Flow STA35241 3 3E6 3.18E5 3 42E6 Loop A Cold Leg Temperature ULA35181 564 562 566 Loop A Hot Leg Temperature ULA35171 595 593 597 Group 7 Rod Position RDGRPAVE(7) 129 6 126.7 132.5 B Main Feedwater Temperature STAA7252 420 410 430 i

~

l B Main Feedwater Flow STA35242 3.3E6 3.18E6 3 42E6 j Loop B Cold Leg Temperature ULA35182 SC4 562 566 l l

Loop B Hot Leg Temperature ULA35172 595 593 597 l l

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(s OPERABILITY TEST 26 January 4,1995

I 7.4.3 100% Rated Power Reference Plant Simulator Description Tag Actual Min Max Min Value Max Value R3 actor Power TRNT0005 100 97.5 102.5 Core Thermal Megawatts RXMWTCOR 2568 2517 2619 GInerated Watts GNJA100 886 866 906 Teve ULA351G 579 577 581 A OTSG Pressure IMA35201 900 876 924 A OTSG Operate Range Level STAA755G 63* 53* 73*

Pr:ssurger Level PRL1000 216 210 222 B OTSG Steam Temperature TRT2631 593 579 607 Boron Concentration RCX0008 870 829 911 B OTSG Pressure IMA35202 900 876 924 B OTSG Operate Range Level STAA756G 64* 54' 74*

Prtssuruer Water Temperature PRT1001 647 633 661 RCS Pressure RCP002 2155 2095 2215 j A OTSG Steam Temperature TRT2681 587 573 601 i

A Main Feedwater Temperature STAA7251 454 444 464 l A Main Feedwater Flow STA35241 5 46E6 5.34E6 5.58E6 Loop A Cold Leg Temperature ULA35181 559 545 573 Loop A Hot Leg Temperature ULA35171 602 589 615 Group 7 Rod Position RDGRPAVE(7) 129 6 126 7 132.5 B Main Feedwater Temperature STAA7252 454 444 464 B Main Feedwater Flow STA35242 5 46E6 5 34E6 5.58E6 l

Loop B Cold Leg Temperature ULA35182 559 545 573 Loop B Hot Leg Temperature ULA35172 602 589 615 l l

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\ OPERABILITY TEST 27 January 4,1995

I 7.4.4 Attach Simulator Data G

Attachment C-1,40% Rated Power Data Attachment C-2,66% Rated Power Data Attachment C-3,100% Rated Power Data ,.

8.0 FINAL CONDITIONS Steady State tests for 40%,66% and 100% are completed. All control room logs are filled out and signed. All required Simulator data points are delogged from historical data, printed out to hard copy and saved to a computer. All logs and printouts are attached to the appropriate Attachment C-1, C-2, or C-3. ,

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OPERABILITY TEST 2s sanuary 4,1995

A a.. . . = . . , - u- .. - a . - - - -u.---a - . - - - ,-~-n 9

ATTACHMENT C-1

. 40% RATED POWER i

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i OPERABILITY TEST 2s January 4,1995 f

.__%_% a 4 , ..m .-_. - .A. - m .--a m a . a .- -

ATTACHMENT C-2 66% RATED POWER O

OPERABILITY TEST so January 4,1995 l

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l ATTACHMENT C-3 O 100% RATED POWER l

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O O OPERABILITY TEST 31 January 4,1995

D. SURVEILLANCE TEST 1.0 DISCUSSION The Surveillance Test is perfomled to demonstrate the ability to perform Normal Operations surveillances in accordance with reference plant procedures. The following criteria was used to select which surveillances will be run: '

Safety related and routinely performed by operations l

- Requires control room manipulations

- Provide training value Sort < surveillances have been deleted or added due to the changing needs of Operator training. The symbol A95 will be used to indicate me addition of a new surveillance during 1995, and Deleted 95 to indicate deleting a surveillance. (Use A9X and Deleted 9X for future years) 2.0 REFERENCE (S) 2.1 AN S-3,5,1985, 3.1.1, ANS NPP Simulators for Operator Training.

2.2 ANO Unit 1 Surveillance Test Procedures, 1102,1103,1104,1105, 1106,1304,1305 Series.

3.0 EQUIPMENT i 3.1 Stop Watch 4.0 INITIAL CONDITIONS ,

4.1 Plant Conditions will be as required by Attachment D-1.

4.2 When possible, the surveillance may be completed during normal operations tests.

5.0 ACCEPTANCE CRITERIA 5.1 The Simulator will perform, without oistraction from training, reference plant surveillance procedures.

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[

n January 4,1995 OPERABILITY TEST

D. SURVEILLANCE TEST 1.0 DISCUSSION The Surveillance Test is performed to demonstrate the ability to perform Normal Operations surveillances in accordance with reference plant procedures. The following criteria was used to select which surveillances will be run:

Safety related and routinely performed by operations ,

Requires control room manipulations '

Provide training value - ,

Some surveillances heve been deleted or added due to the changing needs of Operator training. The symbol A95 will be used to indicate the addition of a new surveillance during 1995, and Deleted 95 to indicate deleting a surveillance. (Use A9X and Deleted 9X for future years) 2.0 REFERENCE (S) 2.1 ANS-3.5,1985, 3.1.1, ANS NPP Simulators for Operator Training.

2.2 ANO Unit 1 Surveillance Test Procedures, 1102,1103,1104,1105, 1106,1304,1305 Series.

3.0 EQUIPMENT 3.1 Stop Watch 4.0 INITIAL CONDITIONS 4.1 Plant Conditions will be as required by Attachment D-1.

4.2 When possible, the surveillance may be completed during normal operations tests.

5.0 ACCEPTANCE CRITERIA 5.1 The Simulator will perform, without distraction from training, reference plant surveillance procedures.

O OPERABILITY TEST 32 January 4,1995

5.2 The simulator shall satisfactorily perform each surveillance. If the surveillance requires a Job Order to correct the reference plant, then the

(}

L. Test Director shall write a DR to correct the simulator response.

6.0 NON ACCEPTANCE CRITERIA 6.1 Non acceptance is defined as the inability to perform surveillance tests, or those that detract from training.

6.2 Non acceptance shall halt routine training involving such operations.

Discrepancies shall be recorded on a DR and logged on attachment R-8 DR log, models enhanced, and retested, as required.

7.0 PROCEDURE 7.1 Using the latest revision of the referenced plant operating procedures, perform the surveillances for the indicated year as listed in Attachment D-1.

7.2 Each surveillance shall be filled out completely. There shall be no blanks that are not filled.

7.3 The Test Director shall sign as the Shift Supervisor and Operations icT Management.

c) 7.4 All steps that can not be completed shall be explained on Attachment D-

2. Completed Attachment D-2 forms will be placed in the binder for Attachment D-2.

7.5 Any surveillance that is found as unsatisfactory shall be repeated after the simulator is corrected. The failed surveillance shall be retained and remain with the satisfactory surveillance test.

7.6 Completed surveillance forms will be placed in the binder for Attachment D-1 and the Test Director shall initial the surveillance listing, Attachment D-1, as sat or unsat.

8.0 FINAL CONDITIONS Surveillance tests are completed and recorded on the index of Attachment D-1.

All surveillance forms are in the Attachment D-1 binder. All steps that can't be completed are recorded on attachment D-2.

p OPERABILITY TEST 33 January 4,1995 .

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ATTACHMENT D-1 I

v. COMPLETED SURVEILLANCE TESTS l

l Required Year l Plant of Surveillance Description Condition Initials Cycle 1015.02 Att A Verification of DH Removal CSD 1 and "LTOP" When RCS is (SauUnsat)  ;

5300* F 1015.02 Att F Verification of DH System CSD 2 .

Alignment (SaUUnsat) 1102.01 Supp 1 RCS High Point Vent Note 1 3 Operability Check. (SaVUnsat) i 1104.04 Supp 6 DH Suct isol Vivs CV-1050 & Note 2 4 CV-1410 Leak Test (SaVUnsat) ,

1102.01 Supp 3 Main Steam & MFW isol Note 3 1 Valve Test (SaUUnsat)  ;

e 1102.10 Supp 1 Low Temp Overpressure Note 5 4 Protection Alarm Test (SaVUnsat)  ;

i 1103.05 Supp 1 Exercising of Pzr Electromatic CSD 1 Relief Viv (PSV-1000) (SaVUnsat) 1103.13 Supp 1 RCS Leak Rate Determine Power Oos .

3 i When RCS Leakage is Not Being (SaVUnsat)

Returned to RCS 1104.01 Supp 1 Core Flood Check Vive Test Note 4 4 .

(CF-1 A, CF-18, DH-14A, (SaVUnsat)  !

DH-148)  ;

1104.02 Supp 1 RCS Loop A HPl MOV Power Oos 1 Quarterly Test (SaVUnsat) 1104.02 Supp 2 RCS Loop B HPI MOV Power Oos 2 Quarterly Test (SaVUnsat)

OPERABILITY TEST u January 4,1995 P

-- - _._er w-- e v +-t M 11m-k

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l ATTACHMENT D-1, (CONTINUED)

COMPLETED SURVEILLANCE TESTS Required Year Plant of Surveillance Description Condition Initials Cycle 1104.02 Supp 3 HPl Pump P-36A Test Power Ops 3 l

1104.02 Supp 4 HPl Pump P-3SB Test Power Oos 4 l (SauUnsat)  !

l

, 1104.02 Supp 5 HPl Pump P-36C Test Power Oos 1 j (SaUUnsat) l 1104.02 Supp 6 RCP Seal Bleedoff CV Note 6 2 Stroke Test (SaUUnsat) l 1104.02 Supp 7 HPl Flow Path Verification CSD 3 (SaUUnsat) 4 1104.02 Supp 8 MU & P System Check Valve CSD 4 )

and CV Stroke Test (SaVUnsat) 1104.04 Supp 1 LO Press Inj (DH) Pump P-34A Power Ops _,_

1 l & Components Quarterly Test (SaVUnsat) 1104.04 Supp 2 LO Press Inj (DH) Pump P-348 Power Ops 2

& Components Quarterly Test (SaUUnsat) 1104.04 Supp 3 DH Suct MOV & Injection CSD 3 Check Valve Stroke Test (SaVUnsat) 1104.05 Supp 2 RB Spray NAOH Addition Power Oos 4 Valves Quarterly Tesi (SauUnsat) l 1104.05 Supp 3 RB Spray Pump P-35A Power Oos 1 Quarterly Test (SaVUnsat) l 1104.05 Supp 4 RB Spray Block (CV-2400 & Power Ops 2 CV-2401) Stroke Test (Sat /Unsat)

,Q V OPERABILITY TEST 35 January 4,1995

ATTACHMENT D-1, (CONTINUED)

(,,)

V COMPLETED SURVEILLANCE TESTS Required Year Plant of Surveillance Description Condition initials Cycle 1104.05 Supp 5 RB Spray Pump P-35B Power Ops 3 Quarterly Test (SaUUnsat) 1104.29 Supp 1 Service Water Pump P-4A Test Power Oos 4 (SaVUnsat) 1104.29 Supp 2 Service Water Pump P-4B Test Power Oos 1 (Sauunsat) 1104.29 Supp 3 Service Water Pump P-4C Test Power Ops 2 (SaVUnsat) 1104.31 Supp 1 liydrogen Sampler C178 Test Any 3 g (SaUUnsat) 1104.31 Supp 2 Hydrogen Sampler C179 Test Any 4 (SaUUnsat) 1104.31 Supp 3 Hydrogen Recombiner M55A Any 1 Functional Test (SaVUnsat) 1104.31 Supp 4 Hydrogen Recombiner M55B Any 2 Functional Test (SaUUnsat) 1104.31 Supp 5 M55A Heatup Test Power Ops 3 (SaVUnsat) 1104.31 Supp 6 MSSB Heatup Test Power Ops 4 (SaUUnsat) 1104.33 Supp 3 Monthly RB Cooling Unit Test Any 1 (SaUUnsat) 1104.33 Supp 4 RB Purge System Test CSD 2 (SaVUnsat) r.

OPERABILITY TEST 3s January 4,1995

ATTACHMENT D-1, (CONTINUED)

COMPLETED SURVEILLANCE TESTS Required Year Plant of Surveillance Description Condition - Initials Cycle 1104.33 Supp 5 RB Cooling Units VCC-2C & Power Oos 3 VCC-2D Flow Test (Sat /Unsat) 1104.33 Supp 6 RB Cooling Units VCC-2A, Power Oos 4 VCC-2B Flow Test (Sat /Unsat) 1104.36 Supp 1 DG1 Monthly Test Any 1 (Sauunsat) 1104.36 Supp 2 DG2 Monthly Test Any 2 (Sat /Unsat) 1104.36 Supp 9 DG1 Endurance & Load Reject Anv 3 Test (Sat /Unsat) 1104.36 Supp 10 DG2 Endurance & Load Reject Any 4 Test (SaVUnsat) 1104.43 Supp 1 Penetration Room Ventilation Any 1 Lead System Moathly Test (Sat /Unsat) 1104,43 Supp 2 Penetration Room Ventilation Any 2 Standby Monthly Test (Sat /Unsat) l 1104.43 Supp 3 Penetration Room Ventilation Any 3 Sys 18 Month Surveillance Test (Sat /Unsat) j 1105.05 Supp 2 EFIC Functional Test CSD 4 (Sat /Unsat)  :

1105.09 Supp 1 Absolute & Relative Position Power Oos 1-Indication Comparison (Sat /Unsat) i OPERABILITY TEST 37 January 4,1995

ATTACHMENT D-1, (CONTINUED) s.,

'b/ _ COMPLETED SURVEILLANCE TESTS Required Year ,

Plant of Surveillance Description Condition Initials Cycle 1106.06 Supp 1 Electric Emergency FWP (P-78) Power Oos 2 Test (Monthly) (SaVUnsat) 1106.06 Supp 2 Steam Driven Emergency FWP Power Oos 3 (P-7A Test (Monthly) (SaVUnsat) t 1106.06 Supp 3 Emergency FW Valve Stroke Power Oos 4 Test (SaVUnsat) 1106.06 Supp 4 EFW Flow Path & Automatic CSD 1 Actuation Verification (SaVUnsat) 1106.09 Supp 1 Turbine Overspeed Trip Test 20% Power 2  !

(SaUUnsat) ,

O 1305.06 Integrated ES System Check CSD (SaVUnsat) 4 1305.07 Supp 1 Normal Operation Valve Stroke Power Ops 1 Times (Sat /Unsat) 1305.07 Supp 2 Cold Shutdown Valve Stroke CSD 2 ,

Times (SaVUnsat) 1305.07 Supp 3 Monthly Misc Safety Systems Power Oos 3 Status Verification (SaVUnsat) 1305.16 Supp 2 Monthly Safe Shutdown Inst Power Ops _ 4 Channel Checks (Sut/Unsat) .

1305.29 Refueling Off-Site Power CSD 1 Surveillance (SaVUnsat) l OPERADILITY TEST 3s January 4,1995

ATTACHMENT D-1, (CONTINUED)

COMPLETED SURVEILLANCE TESTS l

NOTE: l

1. . Plant in Cold Shutdown, RCS Pressure 100 to 200 PSIG

2. Heatup from CSD, RCS Pressure 1200, < 300 PSIG _ i

3. Heatup from CSD, RCS Temperature 1270, < 280* F

4. RCS Cooldown, RCS Pressure > 900 PSIG f

5. Highest Tcold temperature <304* F  !

6. RCS pressure >150 PSIG.

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ATTACHMENT D-2

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() PROCEDURE STEPS THAT WERE NOT COMPLETED PROCEDURE:

STEP # REASON FOR NON-COMPLETION W

O OPERABILITY TEST 40 January 4,1995 l

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ATTACHMENT D-3 SURVEILLANCE PROCEDURES s

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i OPERABILITY TEST 41 January 4,1995

l E. TRANSIENT TEST 1.0 DISCUSSION Tha intent of the Transient Test is to verify simulator performance. Transients must be capable of continuing until such time that a stable, controllable and safe condition is attained which can be continued to a Cold Shutdown condition or until the Simulator operating limits are exceeded.

2.0 REFERENCE (S) 2.1 ANO-3.5,1985,4.2.1,4.3, A3.3 ANS NPP Simulators For Operator Training 3.0 EQUIPMENT 3.1 Stop Watch 3.2 Personal computer with communacations and spreadsheet software.

4.0 INITIAL CONDITIONS

\~> 4.1 All transients commence at 100% Rated Power, unless otherwise noted.

5.0 ACCEPTANCE CRITERIA 5.1 Observable changes in the parameters correspond in direct;on to those expected from plant data or best estimate data and do not violate the physicallaws of nature.

6.0 NON ACCEPTANCE OF SIMULATOR RESULTS 6.1 Simulator results that would detract from positive training and thc3e declared unacceptable by evaluation based on acceptance criteria, will not be used for routine training.

t OPERABILITY TEST 42 January 4,1995

7.0 PROCEDURE ,

NOTE: After initiation of transient, Operators are to take only the actions as directed by this test document.

NOTE: All transients are to be carried to a stable plant condition. i l

7.1 Test Director shall brief the crew as to their expected actions to ensure the l accuracy and repeatability of these tests. l 7.2 Perform the following transients: '

7.2.1 Manual Reactor Trip ~lNIT  ;

I

1. Recall 100% power.

2. Start Historical Data Log 1.

3. Wait 30 seconds, depress Reactor Trip push button.

4. Minimize letdown. ,

5. Adjust pzr level setpoint to 100". 1

6. Stabilize the plant at hot shutdown.

7. Verify proper actuation of all systems & i carry out all actions required by the appropriate procedures.

Or 8. Delog data by following the instructions in Step 7.3. HSUS< ENTER > at IA console 7.2.2 Simultaneous Trip of all Feedwater Pumps

1. Recall 100% power.

2. Start Historical Data Log 1.

3. Block EFW pump operation.

4. Wait 30 seconds, trip both MFW pumps.

6. Minimize letdown. i

6. Adjust pzr level setpoint to 100".

7. Stabilize the plant at hot shutdown.

8. Verify proper actuation of all systems ~

and carry out all actions required by the appropriate procedures.

9. Delog data by following the instructions in Step 7.3. HSUS< ENTER > at IA console OPERABILITY TEST 43 January 4,1995 l

l

INIT -

r'% 7.2.3 Simultaneous Closure of all Main Steam U lsolation Valves

1. Recall .100% power.

2. Start Historical Data Log 1.

3. Wait 30 seconds, shut both Main Steam _

isolation Valves.

4. Minimize letdown.  ;

5. Adjust pzr level setpoint to 100" {

6. Stabilize the plant at hot shutdown.

7. Verify proper actuation of all systems i and carry out all actions required by the appropriate procedures.  !

8. Delog data by following the instructions in Step 7.3. HSUS< ENTER > at lA console '

7.2.4 Simultaneous Trip of all Reactor Coolant Pumps l

1. Recall 100% power  !

2. Start Historical Data Log 1.

3. Wait 30 seconds, stop all 4 RCPs.

4. Minimize letdown.

5. Adjust pzr level setpoint to 100".

O- 6. Stabilize the plant at hot shutdown.

7. Verify proper actuation of all systems ,

and carry out all actions required by the appropriate procedures.  ;

8. Delog data by following the instructions '

in Step 7.3. HSUS< ENTER > at IA console e

i i

OPERABILITY TEST u January 4,1995  ;

INIT.

. 7.2.5 Trip of any Single Reactor Coolant Pump

1. Recall 100% power. .  :

. 2. -Stad Historical Data Log 2.

3. Wait 30 seconds, trip "C" RCP. .

4. Minimize letdown.

5.~ Adjust pzr level setpoint to 100". l

^

6. Stabilize the plant at hot shutdown.  !

7. Verify proper actuation of all systems  !

and carry out all actions required by the  :

appropriate procedures.  !

8. Delog data by following the instructions in Step 7.3. HSUS< ENTER > at IA console i 7.2.6 Main Turbine Trip (Maximum Power That Does i Not Cause an immediate Reactor Trip)  !

1. Recall 50% power. ,

2. Start Historical Data Log 1.

3. . Reduce power to 40%.

~4. Wait 30 seconds, trip the main turbine

5. Use the ERV and pressurizer spray to l control RCS pressure while the ICS  :

rutis reactor power back.

6. Stabilize the plant at power less than 15%. t

7. Verify proper actuation of all systems  !

and carry out all actions required by the appropriate procedures.

8. . Delog data by following the instructions- l in Step 7.3. HSUS< ENTER > at IA console

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f OPERABILITY TEST 45 January 4,1995 I

-. ~. . - - . . - - . -. . .--_ - .. . . _ . . .. . .

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INIT

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7.2.7 Maximum Rate Power Ramp (100% Down to 75%

and Back Up to 100%)

1. Recall 100% power.

2. Start Historical Data Log 1.

i' 3. Wait 30 seconds set ICS rate demand J to 10%/ minute. ,

4. Set ULD to approximate value for l' 75% power.

5. Reduce power to 75%. ]

6. Reduce the rate when approaching 75%

power to reduce undershoot. .

7. Adjust the ULD for 100% power and set the rate limit for 10%/ minute.

8. Increase power to 100%.  !

9. Stabilize the plant at 100%. ,

10. Verify proper actuation of all systems and carry out all actions required by j the appropriate procedures.

11. Delog data by following the instructions in Step 7.3. HSUS< ENTER > at IA console  !

O 7.2.8 Maximum Size RCS Rupture Combined with a Loss of Offsite Power  ;

1. Recall 100% power. l

2. Start Historical Data Log 3.

3. Wait 30 seconds, add malfunction MEL183 for loss of offsite power and add malfunction MRC005 at 8.5 ftz,

4. Minimize letdown.

5. Adjust pzr level setpoint to 100".

6. Terminate the test when the RCS leakage and the HPl/LPI are equal and I the CETs are stable at approximately 200* F. 1 I

7. Verify proper actuation of all systems

. and carry out all actions required by I the appropriate procedures.

8. Delog data by following the instructions  :

in Step 7.3. HSUS< ENTER > at IA console i OPERABILITY TEST a January 4,1995 t

r a A

INIT 7.2.9 Maximum Size Un-isolable Main Steam Line Rupture #

1. Recall 100% power.

2. Start Historical Data Log 3.

3. Wait 30 seconds, add malfunction MSG 131 at 3.14 ft 2, inside RB.

4. Minimize letdown.

5. Adjust pzr level setpoint to .100". _

i

6. Stabilize the plant at hot shutdown.

i

7. Verify proper actuation of all systems and carry out all actions required by the appropriate procedures.

8. Delog data by following the instructions in Step 7.3. HSUS< ENTER > at IA console 7.2.10 Slow Primary System Depressurization '

to Saturation Condition Using ERV ,

i

1. Recall 100% power. l

2. Block HPl valves shut.  !

O ADCO CV1219;0 ADCO CV1220;0 ADCO CV1228;0 ADCO CV1227;0 l

ADCO CV1278;0 ADCO CV1279;0 ADCO CV1284;0 ADCO CV1285;0

3. Start Historical Dats Log 4.

4. Wait 30 seconds, open ERV block valve and ERV.

5. After the reactor trips, reduce -

letdown.

6. Stop all RCPs when SCM < 30' F.

7. Adjust pzr level setpoint at 100" .;

8. Stabilize the plant at hot shutdown. *

9. Verify proper actuation of all systems and carry out all actions required by the appropriate procedures.'

10. Delog data by following the instructions . .

in Step 7.3. HSUS< ENTER > at IA console

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W OPERABILITY TEST 47 January 4,'1995 v . . . . - m -.r . , , - . z.w,,, , us.- ,y, ~ ,, w g

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t INIT f(G_./. _ 7.3 Delog the Historical Data Log File. Refer to  !

Attachment R-9. i 7.4 - Graph each parameter that is required by ANS 3.5, Appendix B.2.2.1 through B.2.2.10. Print a graph for a each required parameter showing both actual simulator

response and predicted response. Attach the transient spreadsheet and graphs to the appropriata attachment -

E-1 through E-10.  ;

8.0 - TIME IN LIFE VERIFICATION TEST .i

- 8.1 Time in Life Verification Test Beginning of Life i

1. Recall 1E-8 Amp Power BOL.

2. Fail CV6687 and CV6689 shut using component override (ADCO CV6687;0 & ADCO CV6689;0). i

3. Start Historical Data Log 2.

4. Open the turbine bypass valves 50%. l

5. Log for 20 minutes to allow stabilization. i

6. Delog data by following the instruction in Step 7.3. HSUS< ENTER > at IA console j 8.2 Time in Life Verification Test Middle of Life ,

1. Recall 1E-8 Amp Power MOL.  !

2. Fail CV6687 and CV6689 shut using component override (ADCO CV6687;0 & ADCO CV6689;0).

3. Start Historical Data Log 2.

4. Open turbine bypass valves 50%.

5. Log for 20 minutes to allow stabilization. -

6. Delog data by following the instruction in Step 7.3. HSUS< ENTER > at IA console l

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b OPERABILITY TEST 48 January 4,1995 t

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,O 8.3 Time in Life Verification Test End of Life

,N- .-  ;

4

1. Recall 1E-8 Amp Power EOL.

2. Fail CV6687 and CV6689 shut using component

' override (ADCO CV6687;0 & ADCO 6689;0).  ;

L 3. Start Historical Data Log 2.

4. Open turbine bypass valves 50%. -

5. Log for 20 minutes to allow stabilization.  :

6. Delog data by following the instruction .

1

. in Step 7.3. HSUS< ENTER > at IA console 8.4 Graph the following parameters, place all three time ,

in lives on the same graph. .;

1. Loop A TCOLD.  ;

2. NI-5 Power Range.

8.5 Place graphs in Attachment E-11.

9.0 FINAL CONDITIONS Transients Tests have been run. Evaluations have been made and appropriate problems, if any, noted by Discrepancy Reports. Any Transient Test that requires a DR to correct the simulator response shall be repeated until successful or listed as an exception to ANSI /ANS 3.51985. All data points have been delogged, printed to hard copy, saved to a computer, and included in the appropriate Attachment E-1 i through E-10. All critical data points are graphed against the predicted response, l evaluated to be satisfactory; graph included in the appropriate Attachment E-1 l through E-10 and the spreadsheet printed and placed with graphs.  ;

OPERABILITY TEST 4, January 4,1995

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< 1 A1TACHMENT E-1 1 TRANSIENT TEST MANUAL REACTOR TRIP l TRANSIENT 82.2 (1) .

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Simulator Training 9

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OPERABILITY TEST so January 4,1995 4

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ATTACHMENT E-2

- TRANSIENT TEST SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS TRANSIENT B2.2 (2)

Transient Reviewed by: Date: ,

Simulator Training O

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1 OPERABILITY TEST 51 January 4,1995 I

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A_. ,s. i &,.A4- 44 44ess JaJ d4Je14 J W A - ae *+4.. A e+s.-e --u J4 4 4 ._ 4 &a4 4 +

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4 ATTACHMENT E-3 TRANSIENT TEST SIMULTANEOUS CLOSURE OF BOTH MSIVs TRANSIENT B2.2 (3) ,

9 Transient Reviewed by: Date:

Simulator Training P

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OPERABILITY TEST 52 January 4,1995

2.

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ATTACHMENT E-4

.- TRANSIENT TEST j l

SIMULTANEOUS TRIP OF ALL RCPs

. TRANSIENT B2.2 (4)

. Transient Reviewed by: Date:

Simulator Training 4

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OPERABILITY TEST 53 January 4,1995

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.. - -.. ..- ~.. - ..- . - ..- - .-. -- .

.6:.

I ATTACHMENT E-5 j O

U TRANSIENT-TEST TRIP OF ONE RCP l TRANSIENT B2.2 (5) l l

Transient Reviewed by: Date:

Simulator Training i

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OPERABILITY TEST 54 January 4,1995 t

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. . . - . . - .- .. - .- . .- - . . . .~.. .-.. ._ .- . . . . . - . -

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a ATTACHMENT E-6 y j O TRANSIENT TEST j

MAIN TURBINE TRIP AT 40% POWER WITHOUT A REACTOR TRIP TRANSIENT B2.2 (6)

Transient Reviewed by: Date:

Simulator Training t

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l OPERABILITY TEST ss January 4,1995 m-- =m s-- , --me w em ,,,,,e- - ,rr -v- --- '

',e'--e ----=-+=s- +- ~e-- -~v -- + - -a =--v ~ -=--w---=- --- - - - - = " - - - + - -

L h.

l ATTACHMENT E-7  ;

TRANSIENT TEST I

MAXIMUM RATE POWER RAMP l

~ 100% TO 75% TO 100% ,

TRANSIENT B2.2 (7) l l

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Simulator Training i

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OPERABILITY TEST se January 4,1995 l

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ATTACHMENT E-8 O- TRANSIENT TEST MAXIMUM SIZE RCS RUPTURE AND LOSS OF OFFSITE POWER TRANSIENT B2.2 (8)  !

Transient Reviewed by: Date:  !

Simulator Training I

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$ 5 OPERABILITY TEST 57 January 4,1995

...m._w y . - - - - - - - . - . . , - - , . . , , . .-

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ATTACHMENT E-9 TRANSIENT TEST MAXIMUM SIZE UNISOLABLE MAIN STEAM LINE BREAK  !

TRANSIENT B2.2 (9) i

+ a P

i I Transient Reviewed by: Date:

Simulator Training 4

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k OPERABILIT( TEST sa January 4, W95 i

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ATTACHMENT E-10 TRANSIENT TEST SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATION USING THE ERV WITHOUT HPl ,

l TRANSIENT B2.2 (10)

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OPERABILITY TEST s, January 4,1995 +

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i ATTACHMENT E-11  !

! TRANSIENT TEST }

i TIME IN LIFE TEST +

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i Transient Reviewed by: Date:  !

4 Simulator Training  ;

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OPERABILITY TEST so January 4,1995 l j .

i 5 ___ . . . . , . . - . - . . _ _ . - . _ , _ . . . . . _ _ - _ . _ _ _ . . . , _ . . . _ . _ . _ . , _ , . . _ . - _ _ , . . . _ . . _ __-._.._-.-......-~._t h

, . . . - . - . -- - -. . - - . ..~

j 3

I L F. MALFUNCTION TEST

, [? -'. 1.0 DISCUSSIONI A. All malfunctions that'are required oy either 10CFR55.59.C.3.1 or ANS 3.5  !

1985 Section 3.1.2 and are not tested during the transient testing portion of j the performance test shall be tested by this section. Additionally, any other  !

malfunction to be used as a part of operator training shall be tested by this .

section. A minimum of 25% of the malfunctions used by training will be 1 tested each year.

Some malfunctions have been deleted or added due to the changing needs ,

of Operator training. The symbol A95 will be used to indicate the addition of  !

a new malfunction during 1995, and D95 to indicate deleting a malfunction. l (Use A9X D9X for future years) l l

B. The following assumptions have been utilized in preparing this section:

1) The simulator shall be operated in accordance with approved plant -'

procedures. Symptoms, automatic actions and plant response i described in these procedures will be used to evaluate simulator  !

. performance and there is no attempt to define every possible alarm or i response in the Malfunction cause and effect document, only the major items are listed. *

2) The anticipated plant response is described in the Unit 1 Malfunction Cause and Effects Document. l C. The following termination criteria will be used during malfunction testing: j

1) For malfunctions that do not result in a plant trip but do require a  ;

shutdown, terminate the malfunction test when the shutdown is I initiated. (i.e., RCS leakage > T.S. but <HPl capacity.)  !

2) For malfunctions that result in a plant trip (automatic or manual) terminate the malfunction test when the plant is being controlled in accordance with the appropriate section of the EOP. t

3) For malfunctions not covered by 1 or 2 above, terminate the ,

malfunction test when the plant reaches stable conditions but it is not  !

necessary to recover -i.e., during a dropped control rod from power i malfunction, it is not necessary to withdraw the control rod. l

4) The malfunction has failed to perform correctly.

OPERABILITY TEST si January 4,1995 i

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m D. The following process will be used to conduct and document each

^ '

O-Q malfunction test: ,

l

1) The Test Director will review the malfunction, AOP, EOP, and anticipated plant response with the test personnel prior to each  ;

malfunction test. i

.i

2) Plant response will be compared to the Malfunction Cause.and Effects  !

Document.

3) Deviations will be annotated in the expected plant response section of the Cause and Effects Document. A DR shall be written to correct simulator response and the Cause and Effect Document edited to-include all correct plant response not contained in the Cause and  !

Effect.

4) If the acceptance criteria in section 5.0 have been met, the Test 1 4

Director will sign off the malfunction on the Malfunction Verification List as being accepted. (Attachment F-1) 2.0 REFERENCE (S)' )

I 2.1 ANS-3.5,1985, 3.1.2, 4.2.2, and A3.4.

O 2.2 10CFR55.59.C.3.1.A through AA.

3.0 EQUIPMENT 3.1 None t i

4.0 INITIAL CONDITIONS  !

4.1 Initial Plant Conditions will be as stated in the Mylfunction Cause and Effects  :

Document in the Malfunction Test Condition. t 5.0 ACCEPTANCE CRITERIA i i

l 5.1 Observable change in the parameters correspond in directicn to actual plant  :

data cr to that expected from best estimate and not violate the physical laws -

of nature. '

P 5.2 The simulator shall not fail to cause an alarm or trip if the reference plant I would have caused an alarm or trip. j OPERABILITY TEST s2 January.4,1995 .j i

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5.3 The simulator shall not alarm or trip if the reference plant would not alarm or trip.

6.0 NON ACCEPTANCE OF SIMULATOR RESULTS 6.1 Simulator results that would detract from positive training and those declared unacceptable by evaluation based on acceptance criteria, will rot be used for roatine training.

7.0 PROCEDURE 7.1 Test each malfunction in accordance with the test plan in the Malfunction Cause and Effects document.

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OPERABILITY TEST ss January 4,1995

"- ' ~ ~~~ ~ "

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?._, ;7.1,1 Using Attact. ment F-1 of this procedure, select malfunction to be

( tested during this " year of cycle".

e .

1) Recall the IC as indicated on the Malfunctions Cause and

' Effects, Attachment F-2.

)

2) Enter the malfunction being tested on the lA terminal using the:

severity and magnitude indicated on the Cause and Effecte document.

3) .The only operator actions allowed are listed on the Malfunction Cause and Effects document. All safety systems will be verified. Any automatic actuation or system response that does not occur as an indirect result of this malfunction will nel be causs for unsatisfactory status of this malfunction. A DR will be written for all improper responses.

l

4) The malfunction must perform as indicated on the Malfunction Cause and Effects document. Deviations must be resolved before the malfunction can be determined satisfactory. The  !

Cause and Effects document shall be updated to reflect actual

{

results. ,

p V

5) When the plant has reached a steady state status, hot shutdown or some new steady power, the test can be ,

terminated satisfactorily.

6) If the Simulator Operating Limit (SOL) is reached, the validity of i the alarm must be venfied and a determination made that the simulation has not caused a failure of one of the models. l

\

7) After verifying the malfunction has correctly functioned and all j corrections to the Cause and Effects document have been hand 1 written on the test copy, the Test Director shall sign the satisfactory performance block of Attachment F-1. j l

8) Continue to the next malfunction.

8.0 FINAL CONDITIONS All malfunctions have been tested and the Malfunction Verification List has been -

signed by the Test Director, if problems have been identified a Discrepancy Report  :

has been written to initiate corrective action. The malfunction will be tested again l and when satisfactory, the Test Director will sign for the satisfactory performance.

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. OPERABILITY TEST s4 January 4,1995 ,

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l ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST l

1 l N:me Description ANSI Year Date DR No. Uns,at Date Satisfactory 3.5 Of if App init Retest Performance Test Signature MRC001 OTSG A TUBE RUPTURE .1A 1 MRC003 RC HOT LEG LEAK (LOOP A) .1C 1 MRC006 RC COLD LEG LEAK (LOOP B) .18 1 MRC011 LOSS OF RCP L.O. P32A .4 1 MCV018 SEAL NO.1 FAILURE P32D .1 B 1 MCV022 SEAL NO.2 FAILURE P32D .18 1 MCV023 SEAL NO.3 FAILURE P32A .1 B 1 MRC030 RCP LOCKED ROTOR P32D .4 1 MRC034 RCP SHEARED SHAFT P32D .4 1 MRC041 PSV 1002 LIFT & RESET PRESS DRIFT .1 D 1 MTR055 PZR TT 1002 FAILURE .18 1 MZP062 Fall MAKEUP PMP 36B(OPEN CKT) .18 1 MCV066 LEAK IN MAKEUP PUMP 36C SUCTION .18 1 MZP071 P2A MOTOR BEARING HEATUP .9 1 MZP075 FW PUMP 18 FAILURE .9 1 OPERABILITY TEST ss January 4,1995

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Nrme Description ANSI Year Date DR No. Unsat Date Satisfactory >

3.5 Of If App init Retest Performance Test Signature MBC076 STEAM DRIVEN EFWP FAILURE .23 1 MLOO81 FW PMP SUCT PRESS OSCll ACTION None 1 MZP082 P3A MOTOR BEARINGS HEATUP .5 1 MZP086 P8A MOTOR BEARINGS HEATUP .9 1 MCF093 TUBE LEAK FW HTR ESA .9 1 MZP097 P36C MOTOR BEARINGS HEATUP .18 1 MCF102 FW LINE BRK OUTSIDE RX BLDG LP B .20 1 MSW121 P4A MOTOR BEARINGS HEATUP .6 1 MSG 134 MSL B RUPTURE OUTSIDE THE RX BLD .20 1 MTL136 TURB L.O. LOSS (CLR DISCH CLSD) .15 1 MLO140 GLAND SEAL FAILURE .5 1 MSG 143 SHIFT IN PSV 2686 LIFT & RESET .20 1 MTB147 I V CV6825 FAILS CLOSED .22 1 MTB153 NO.1 GOVERNOR VALVE FAILS .22 1 MRH161 LEAK IN DISCHARGE OF DHR PMP 34A .7 1 OPERABILITY TEST ss January 4,1995

_ = - _ _ _ _ _ _ _ _ _ _ _____ . . . - . =_ , _ - - _ _ _ _ _ - - _ _ - - _ _ _ _ _ - - - _ - _ .

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- s) k _/ (M k ,1 ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N::me Description ANSI Year Date DR No. Unsat Date Satisfactory .

3.5 Of if App init Retest Performance Test Signature

! MRH165 LEAK IN DHR COOLER E35A .7 1 MRX169 FUEL CLADDING MECH. FAILURE .14 1 MA1170 IA LEAK DOWNSTREAM OF IA 68 .2 1 MGN171 FAILURE OF MAIN GENERATOR EXCITER .16 1 MGN174 DG 2 FAILURE .3 1 MEL182 UA XFMR FAILURE .3 1 MEL186 LOSS OF 4.16 KV BUS A2 .3 1 MEL190 LOSS OF 480 V BUS B2 .3 1 MEL194 LOSS OF 480 8 BUS B6 .3 1 MEL198 LOSS OF 125 VDC BUS D02 .3 1

, MRC204 LEAK IN RCP Oil COOLER P32D .4 1 MNI234 NI-3 OVER COMPENSATED .21 1 MNI238 NI-7 FAILS LO .21 1 MN1242 NI-7 FAILS HI .21 1 MRP244 FALSE RX TRIP .19 1 OPERABILITY TEST s7 January 4,1995'

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N:me Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of If App init Retest Performance Test Signature MRP247 REACTOR TRIP RELAY KE2 FAILS .24 1 MRD250 UNABLE MANUAL ROD INSERTION .13 1 MES251 FALSE ACTUATION OF ES CHANNEL 1 .22 1 MES255 FALSE ACTUATION OF ES CHANNEL 5 .22 1 MES259 ES CHANNEL 1 FAILS TO ACTUATE .11 1 MES263 ES CHANNEL 5 FAILS TO ACTUATE .11 1 MES267 ES CHANNEL 9 FAILS TO ACTUATE .11 1  :

MRD271 LOSS OF SEQUENCE ENABLE .12 1 MRD276 DROP ROD C11 (GR3-ROD 1 ) .12 1 MRD310 EJECT ROD B8 (GR6-ROD 1 ) .1B 1 MRD351 STUCK ROD C11 (GR3-ROD 1 ) .12 1 MRD388 DEGRDED MOTION ROD E9 GR4-ROD 1 .12 1 MRD424 FAILURE OF CRD B DC HOLD P/S .12 1 MRD428 DROP GROUP 7 RODS .12 5 MTR449 LOOP BTC (TT1048) .22 1 OPERABILITY TEST 68 January 4,1995 ,

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Nr.rne Descriptic'1 ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of If App init Retest Performance Test Signature MEL450 LOSS OF NNI X POWER .3 1 MRC454 LEAK IN RCP COOLER E25A .18 1 MEL460 i 85114 GEN OUTPUT BKR FAILS .3 1 MRC462 RCS LEAK DOWNSTREAM MU45A .18 1 MTR553 SG A MAIN FW START UP (PDT2626) .22 1 MTR557 SG B MAIN FW START UP (PDT2676) .22 1 MTRSS1 GENERATED MW SIGNAL (TWC) .22 1 MTR565 LOOP A TH (TT1011) .22 1 MTR569 'A' OTSG LEVEL OPER (LT2660) .22 1 MTR573 'A' OTSG LEVEL S/U (LT2653) .22 1 MTR577 'A' OTSG PRESS y)T2653) .22 1 MTR581 'B' HDR THRO'ITLE PRESS (PT2633) .22 1 MTR585 'B' OTSG MAIN FW TEMP (TT2679) .22 1 MTR589 LOOP A TC (TT1015) .22 1 MIM593 TURB. A-1 BYP CNTRL VLV (IC23.8) .22 1 OPERABILITY TEST sg January 4,1995

. w ,e ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N:me Description ANSI Year Date DR No. Unsat Date - Satisfactory.

. 3.5 Of If App init Retest Performance . ,

Test Signature MIM597 TURB. B-2 BYP CNTRL VLV(IC23.10) .22 1 MST601 STARTUP FW VLV 'B' (FW23.12) .22 1 MIM605 DEC. TURBINE POSITION (IC18.3D) .22 1 MEC608 CH.A SGB PRESS INITIATE BISTABLE .23 1 OPERABILITY TEST yo January 4,1995

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N me Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of if App init Retest Performance Tes' Signature MRC002 OTSG B TUBE RUPTURE .1A 2 MRC004 RC HOT LEG LEAK (LOOP B) .1 C 2 t' MRC012 LOSS OF RCP L.O. P328 .4 2 MCV015 SEAL NO.1 FAILURE P32A .1 B 2 MCV019 SEAL NO.2 FAILURE P32A .1 B 2 MCV024 SEAL NO.3 FAILURE P328 .1 B 2 MRC027 RCP LOCKED ROTOR P32A .4 2 MRC031 RCP SHEARED SHAFT P32A .4 2 MRC042 PSV 1000 LEAKING .1 D 2 MRC045 PZR STEAM SPACE LEAK .1 B 2 MTR049 PZR LT 1001 FAILURE .18 2 MZP063 Fall MAKEUP PMP 36C(OPEN CKT) .18 2 MCV067 LEAK IN MAKEUP PMP 36A DISCHARGE .18 2 MZP072 P2B MOTOR BEARING HEATUP .9 2 MBC077 LOSS OF INST AIR TO K2A .2 2 OPERABILITY TEST 71 January 4,1995

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MALFUNCTION VERIFICATION LIST Nrme Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of if App init Retest Performance Test Signature MZP083 P3B MOTOR BEARINGS HEATUP ,

.5 2

MZP087 P88 MOTOR BEARINGS HEATUP .9 2 MCF094 TUBE LEAK FW HTR ESB .9 2 MCF099 FW LINE BRK INSIDE RX BLDG LP A .20 2 MCF117 MN FW A CNTL VLV(CV2625) LEAKS .22 2 MSW122 P4B MOTOR BEARING HEATUP .6 2 MSW127 SW LOOP I LEAK IN RX BUILDING .6 2 MSG 131 MSL A RUPTURE INSIDE THE RX BLD .20 2 MTS135 STM LINE BREAK BTWN HP&LP TURB .20 2 MTL136 TURB L.O. LOSS (CLR DISCH CLSD) i.15 2 MSG 144 ' SHIFT IN PSV 2687 LIFT & RESET .20 2 MTB148 i V CV6828 FAILS CLOSED .22 2 MTB154 NO.2 GOVERNOR VALVE FAILS .22 2 MRH162 LEAK IN DISCHARGE OF DHR PMP 348 .7 2 MRH166 LEAK IN DHR COOLER E35B .7 2 OPERABILITY TEST 72 January 4,1995

- - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -____ - - _____---_____ --___ ____ -____ _- . - . _. - . _ _ . - ~ _ -.

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of If App init Retest Performance Test Signature -

MRX169 FUEL CLADDING MECH. FAILURE .14 2 -

MA1170 IA LEAK DOWNSTREAM OF lA G8 .2 2 MGN172 MAIN GEN VOLTAGE REG FAILS .16 2 MGN175 DG 1 FAILS TO AUTO START .3 2 MEL183 LOSS OF OFF SITE POWER .3 2 MEL187 LOSS OF 4.16 KV BUS A3 .3 2 ,

MEL191 LOSS OF 480 V BUS B3 .3 2 i MEL195 LOSS OF 480 V BUS B7 .3 2 MRC201 LEAK N RCP OIL COOLER P32A .4 2 MCW215 PLUGGED CNDNSR TUBE SHEET E11A .5 2 MLO225 LOSS OF GEN HYD COOLING (CV4018) .8 2 MN1235 NI-4 OVER COMPENSATED .21 2 MN1239 NI-8 FAILS LO .21 2 MN1243 NI-8 FAILS HI .21 2 MRP244 FALSE RX TRIP .19 2 OPERABILITY TEST 73 January 4,1995 l

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I ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of If App init Retest Performance Test Signature MRP248 RX TRIP RELAY KE3 FAILS (CRPS) .24 2 MRD250 UNABLE MANUAL ROD INSERTION .13 2 MES252 FALSE ACTUATION OF ES CHANNEL 2 .22 2 MES256 FALSE ACTUATION OF ES CHANNEL 6 .22 2 MES260 ES CHANNEL 2 FAILS TO ACTUATE .11 2 ,

MES264 ES CHANNEL 6 FAILS TO ACTUATE .11 2 MES268 ES CHANNEL 10 FAILS TO ACTUATE .11 2 MRE272 DEFEAT ROD DEMAND (ICS TO CRD) .12 2 MRD277 DROP ROD D4 (GR7-ROD 8) .12 2 MRD312 EJECT ROD (GRS-ROD 12 ) .1 B 2 MRD352 STUCK ROD D4 (GR7-ROD 12) .12 2 MRD389 DEGRDED MOTION ROD D4 (GR7-ROD 8) .12 2 MRD425 FAILURE OF CRD AUXILIARY P/S .12 2 MEL451 LOSS OF NNI Y POWER .3 2 MRC455 LEAK IN RCP COOLER E25B .1 B 2 OPERABILITY TEST 74 January 4,1995

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N :me Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of if App init Retest Performance Test Signature MEL458 PT1021. RCS PRESS TRANSMllTER .22 2 MRC463 RCS LEAK DOWNSTREAM MU45B .18 2 MTR550 SG A SHELL WATER TEMP (TT2664) ,

.22 2 MTR554 SG B SHELL WATER TEMP (TT2614) .22 2 MTR558 'B' OTSG FW FLOW (MAIN)(PDT2677) .22 2 MTR562 RC FLOW LOOP A (PDT1028) .22 2 MTR566 LOOP B TH (TT1042) .22 2 MTR570 'B' OTSG LEVEL OPER (LT2609) .22 2 MTR574 'B' OTSG LEVEL S/U (LT2614) .22 2 MTR578 'B' OTSG PRESS (PT2602) .22 2 MTR582 'A' OTSG MAIN FW TEMP (TT2630) .22 2 MTR586 'A' MFW DELTA P FAILURE .22 2 MTR590 LOOP A TC (TT1018) .22 2 MST598 A MFW SPD SIGNAL FROM ICS TO LJ .22 2 MST602 A LL CONTROL VLV FAILS, CV2622 .22 2 OPERABILITY TEST 75 January 4,1995

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Nrme Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 C .' If App Init Retest Performance Test Signature MRE606 WITHDRAW RODS COMMAND .12 2 MEC609 CH.A SGA LEVEL INITIATE BISTABLE .23 2 MEC612 FALSE ACTUATION OF TRAIN A EFW .22 2 MEC617 P7B ELEC. EFW PMP FAILS TO ACTU. .23 2 MEC618 EFIC FALSE VECTOR CL SIG CV2648 .22 i 2 ,

OPERABILITY TEST 7s January 4,1995

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d ks' ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N;rne Description ANSI Year l Date DR No. Unsat Date Satisfactory 3.5 Of If App init Retest Perfonnance Test Signature MRC001 OTSG A TUBE RUPTURE .1A 3 MRC003 RC HOT LEG LEAK (LOOP A) .1C 3 MRC013 LOSS OF RCP L.O. P32C .4 3 MCV016 SEAL NO.1 FAILURE P32B .1 B 3 MCV020 SEAL NO.2 FAILURE P328 .1 B 3 MCV025 SEAL NO.3 FAILURE P32C .1B 3 MRCO28 RCP LOCKED ROTOR P328 .4 3 MRC032 RCP SHEARED SHAFT P32B .4 3 MVS039 PSV 1000 LIFT & RESET PRESS DRIFT .1D 3 MRC043 PSV 1001 LEAKING .1 D 3 l

MPR046 ALL PZR HEATERS Fall ON .18 3 l MTR050 PZR LT 1002 FAILURE .18 3 MTR054 PZR TT 1000 FAILURE .18 3 MCV058 LETDOWN COOLER E29A TUBE LEAK .1 B 3 i

MCV064 LEAK IN MAKEUP PUMP 36A SUCTION .18 3 l

OPERABILITY TEST 77 January 4,1995

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of If App init Retest Performance -

Test Signature MCV068 LEAK IN MAKEUP PMP 36B DISCHARGE .18 3 MZP073 P2C MOTOR BEARING HEATUP .9 3 i

MTR079 FW BLK VLV TMTR PDT 2700 Fall LO .22 3 MZP084 P3C MOTOR BEARINGS HEATUP .5 3 MCF091 CONDENSATE LINE A LEAK .9 3 MZP096 P36B MOTOR BEARINGS HEATUP .18 3 MCF100 FW LINE BRK INSIDE RX BLDG LP B .20 3 MCF118 MN FW B CNTL VLV(CV2675) LEAKS .22 3 MSW123 P4C MOTOR BEARINGS HEATUP .6 3 MSG 132 MSL B RUPTURE INSIDE THE RX BLD .20 3 MTL136 TURB L.O. LOSS (CLR DISCH CLSD) .15 3 MTM139 TURBINE HI VIBRATION None 3 i

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MSG 141 SHIFT IN PSV 2696 LIFT & RESET .20 3 MIM145 FALSE INC. PULSER SIGNAL TO EHC .22 3 MTB149 I V CV6829 FAILS CLOSED .22 3

' OPERABILITY TEST 7s January 4,1995

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ATTACHMENT F-1 MALFUNCTle', VERIFICATION LIST Name Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of If App init Retest Performance Test Signature MTB155 NO.3 GOVERNOR VALVE BINDS .22 3 MRH160 LEAK IN SUCTION OF DHR PUMP 34A .7 3 MRX169 FUEL CLADDING MECH. FAILURE .14 3 MA1170 IA LEAK DOWNSTREAM OF IA 68 .2 3 MGN171 FAILURE OF MAIN GENERATOR EXCITR .16 3 MGN176 DG 2 FAILS TO AUTO START .3 3 MEL180 NO.1 START UP XFMR FAILURE .3 3 MEL184 LOSS OF 6.9 KV BUS H1 .3 3 MEL188 LOSS OF 4.16 KV BUS A4 .3 3 MEL192 LOSS OF 480 V BUS B4 .3 3 MEL196 LOSS OF 125 VDC BUS D01 .3 3 MRC202 LEAK IN RCP OIL COOLER P328 .4 3 MCW216 PLUGGED CNDNSR TUBE SHEET E118 .5 3 MGN226 LEAK IN GENERATOR HYD COOLER .8 3 MN1228 NI-1 FAILS LO .21 3 OPERABILITY TEST 73 January 4,1995

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MALFUNCTION VERIFICATION LIST i Nrme Description ANSI Year Date DR No. Unsat Date Satisfactory

( 3.5 Of if App init Retest Performance l Test Signature MNi232 NI-3 UNDER COMPENSATED .21 3 l MN1236 NI-5 FAILS LO .21 3 l MN1240 NI-5 FAILS HI .21 3 MRP244 FALSE RX TRIP .19 3 MTB245 MSTR TRIP SOL. FAILS (TURB TRIP) .23 3 l

MRP249 REACTOR TRIP RELAY KE4 FAILS .24 3 MRD250 UNABLE MANUAL ROD INSERTION .13 3 MES253 FALSE ACTUATION OF ES CHANNEL 3 .22 3 MES257 FALSE ACTUATION OF ES CHANNEL 7 .22 3 MES261 ES CHANNEL 3 FAILS TO ACTUATE .11 3 MES265 ES CHANNEL 7 FAILS TO ACTUATE .11 3 MRD269 UNCONTROLLED ROD WITHDRAWL .12 3 MRD273 DROP ROD B8 (GR6-ROD 1 ) .12 3 MRD313 EJECT ROD C9 (GR3-ROD 1 ) .18 3 MRD348 STUCK ROD B8 (GR6-ROD 1 ) .12 3 OPERABILITY TEST so January 4,1995

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N:me Description ANSI Year Date DR No. Unsat Date Satisfactery 3.5 Of If App Init Retest Performance Test Signature MRD385 DEGRDED MOTION ROD B8 (GR6-ROD 1) .12 3 MRD422 DEFEAT SEL GROUP (IN MANUAL) .12 3 MRD426 DROP GROUP 5 RODS .12 3 MEL452 LOSS OF ICS POWER .3 3 MGN454 GENERATOR STATOR GROUND .16 3 MRC456 LEAK IN RCP COOLER E25C .18 3 MEL461 B5118 GEN OUTPUT BKR FALLS .22 3 MRC464 RCS LEAK DOWNSTREAM MU45C .18 3 MTR551 SG A SHELL WATER TEMP (TT2665) .22 3 MTR555 SG B SHELL WATER TEMP (TT2615) .22 3 MTR559 NEUTRON POWER .22 3 MTRS63 RC FLOW LOOP B (PDT1034) .22 3 MTR567 LOOP B TH (TT1039) .22 3 MTR571 'B' OTSG LEVEL OPER (LT2610) .22 3 MTR575 'B' OTSG LEVEL S/U (LT2613) .22 3  ;

l OPERABILIT/ TEST 81 January 4,1995-

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N me Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of if App init Retest Performance Test Signature MTR579 'B' OTSG PRESS (PT2603) .22 3 MTR583 'A' OTSG MAIN FW TEMP (TT2629) .22 3 MTR587 'B' OTSG FW STOP VLV P (PDT2701) .22 3 MTR591 LOOP B TC (TT1044) .22 3 MST599 FWP B SPEED CHNG DEMAND .22 3 MST603 LOW LOAD FW VLV 'B' .22 3 MRE607 INSERT RODS COMMAND .12 3 MEC610 EFIC CH.A LOSS OF POWER .23 3 MEC614 EFIC FALSE VCTR. CL. SIG. CV2620 .22 3 MEC619 FALSE ACTUATION TRAIN B B MSLI .22 3 MEC621 CH.A,B,D INITIATE MDL OUTUT Fall .23 3 OPERABILITY TEST 82 January 4,1995

ATTACH.'.1ENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI l Year Date DR No. Unsal Date Satisfactory 3.5 Of If App init Retest Performance Test Signature MRC002 OTSG B TUBE RUPTURE .1 A 4 MRC004 RC HOT LEG LEAL %.OOP U) .1 C 4 MRC005 RC COLD LEG LEAK (LOOP A) .16 4 M _007 FAILURE OF DARDANELLE DAM .6 4 MRC014 LOSS OF RCP L.O. P32D .4 4 MCV017 SEAL NO.1 FAILURE P32C .1 B 4 MCV021 SEAL NO.2 FAILURE P32C .1 B 4' MCV026 SEAL NO.3 FAILURE P32D .1B 4 MRC020 RCP LOCKED ROTOR P32C .4 4 MRC033 RCP SHEARED SHAFT P32C .4 4 MRC040 PSV 1001 LIFT & RESET PRESS DRIFT .1 D 4 MRC044 PSV 1002 LEAKING .1 D 4 MPR047 ALL PZR HEATERS Fall OFF .18 4 MCV059 LETDOWN COOLER E298 TUBE LEAK .18 4 MZP061 ,

Fall MAKEUP PMo 36A(OPEN CKT) .18 4 OPERABILITY TEST s3 January 4,1995

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N;me Description ANSI Year Date DR No. Unsat Date Satisfactory .

3.5 Of If App init Retest Performance Test Signature MCV065 LEAK IN MAKEUP PUMP 36B SUCTION .18 4 -

MCV069 LEAK IN MAKEUP PMP 36C DISCHARGE .18 4 MRC070 LETDOWN LINE LEAK IN AUX BLDG .1 B 4 MZP074 FW PUMP 1 A FAILURE .9 4 MBC078 LOSS OF INST AIR TO K2B .2 4 MTR080 FW BKL VLV TMTR PDT 2701 FAIL LO .22 4 MZP085 P3D MOTOR BEARINGS HEATUP .5 4 MCN088 CONDENSER VACUUM LEAK .5 4 MCF092_

CONDENSATE LINE B LEAK .9 4 MZP095 P36A MOTOR BEARING HEATUP .18 4 MCF101 FW LINE BRK OUTSIDE RX BLDG LP A .20 4 MSW128 SW LOOP ll LEAK IN RX BUILD .6 4 MSG 133 MSL A RUPTURE OUTSIDE THE RX BLD .20 4 MTL136 TURB L.O. LOSS (CLR DISCH CLSD) .15 4 l MSG 142 SHIFT IN PSV 2697 LIFT & RESET .20 4 l

OPERABILITY TEST 84 January 4,1995 4

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(J ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N:me Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of if App init Retest Performance Test Signature MTB146 i V CV6822 FAILS CLOSED .22 4 MIM150 FREEZE ICS SIG TO EHC(CURR VAL) .22 4 MTB151 GOV.VLV OSC (EHC AUTO CNTL) .22 4 MTB156 NO.1 THROTTLE VALVE BINDS .22 4 MRH164 LEAK IN SUCTION OF DHR PUMP 34B .7 4 MRX169 FUEL CLADDING MECH. FAILURE .14 4 MA1170 lA LEAK DOWNSTREAM OF IA 68 .2 4 MGN172 MAIN GEN VOLTAGE REG FAILS .16 4 MGN173 DG 1 FAILURE .3 4 MEL177 MAIN XFMR FAILURE PHASE A .3 4 MEL181 NO.2 START UP XFMR FAILURE .3 4 MEL185 LOSS OF 4.16 KV BUS A1 .3 4 MEL189 LOSS OF 480 V BUS B1 .3 4 l

MEL193 LOSS OF 480 V BUS B5 .3 4 MEL197 LOAD REJECTION .3 4 OPERABILITY TEST 85 January 4,1995

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of if App init Retest Performance Test , Signature MRC203 LEAK IN RCP OIL COOLER P32C .4 4 MCN227 RUPT OF CONE GER DWNSTRM CS189 .8 4 __

MN1229 NI-2 FAILS LO .21 4 MN1233 NI-4 UNDER COMPENSATED .21 4 MN1237 NI-6 FAILS LO .21 4 I

MN1241 NI-6 FAILS Hi .21 4 MRP244 FALSE RX TRIP .19 4 MRP246 REACTOR TRIP RELAY KE1 FAILS .24 4 ERD 250 UNABLE MANUAL ROD INSERTION .13 4 MES254 FALSE ACTUATION OF ES CHANNEL 4 .22 4 MES258 FALSE ACTUATION OF ES CHANNEL 8 .22 4 MES262 ES CHANNEL 4 FAILS TO ACTUATE .11 4 MES266 ES CHANNEL 8 FAILS TO ACTUATE .11 4 MRD270 UNCONTROLLED ROD INSERTION .12 4 MRD275 DROP ROD F6 (GR6-ROD 8 ) .12 4 OPERABILITY TEST se January 4,1995

O O O ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST N me Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of If App init Retest Performance Test Signature MRD314 EJECT ROD D4 lGR7-ROD 8) .1 B 4 MRD350 STUCK ROD C7 (GRS-ROD 12 ) .12 4 MRD387 DEGRDED MOTION ROD C7 GRS-ROD 12 .12 4 MRD423 FAILURE OF CRD A DC HOLD P/S .12 4 MRD427 DROP GROUP 6 RODS .12 4 MEL453 LOSS OF SPDS (A & B) .3 4 ,

MRC957 LEAK IN RCP COOLER E25D .18 4 MEL459 PT1038, RCS PRESS TRANSMITTER .22 4 MRC465 RCS LEAK DOWNSTREAM MU45D .1 B 4 MEL466 FAILURE OF SU#1 TO A2 AUTOTRIP .3 4 MTR552 SG A MAIN FLOW (PDT2628) .22 4 MTR556 SG B MAIN FLOW (PDT2678) .22 4 MTR560 FREQ. INP TO SPD ERROR .22 4 MTR564 LOOP A TH (TT1014) .22 4 MTRS68 'A' OTSG LEVEL OPER (LT2659) .22 4 e

OPERABILITY TEST 87 January 4,1995

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m  %/ *% d' ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No. Unsat Date Satisfactory 3.5 Of If App Init Retest Performance Test Signature MTR572 'A' OTSG LEVEL S/U (LT2664) .22 4 MTR576 'A' OTSG PRESS (PT2652) .22 4 MTR580 'A' HDR THROTTLE PRESS (PT2683) .22 4 MTR584 'B' OTSG MAIN FW TEMP (TT2680) .22 4 MTR588 'A' OTSG FW FLOW MAIN (PDT2627) .22 4 MST600 STARTUP FW VLV 'A' .22 4 MIM604 INC. TURBINE POSITION .22 4 MEC611 EFIC LOSS OF FILL RATE CONTROL .23 4 MEC620 FALSE ACTUATION TRAIN B A MSLI .22 4 OPERABILITY TEST sa January 4,1995

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ATTACHMENT F-2

. . MALFUNCTION CAUSE AND EFFECTS LISTING  ;

FOR MALFUNCTIONS TO BE TESTED  ;

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i G. RETEST ITEMS FROM LAST OPERABILITY TEST 1.0 DISCUSSION ,

The intent this section is to allow the closure of the annual operability test with some outstanding items remaining. This section will be used to list the items remaining from the last operability test that must be tested this year. This section is not intended to allow violation of the intent of the operability test, but to allow problems to be carried over to the next year and closs last years test.

2.0 PROCEDURE The list in section 3.0 is from last years operability test. Repeat the listed item and sign and date the appropriate box to indicate satisfactory completion. A note has been placed on last years operability test explaining that the item (s) were deferred to this years test.

3.0 ITEMS FOR RETEST 3.1 Real Time Test None  !

i 3.2 Normal Operations Test J None i

3.3 Steady State Test None 3.4 Surveillance Test None 3.5 Transient Test None 3.6 Malfunction Test None 1

OPERABILITY TEST so January 4,1995

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REFERENCES O

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ATTACHMEN' R-1 rT LIST OF POINTS RECORDED DURING TRANSIENT TEST

(_/ USING HISTORICAL DATA LOG #1 Point ID Global Variable Description 1 TRNT0005 (1,1) Reactor Power 2 ULA3513G (1,1) Tave 3 RCP801S (1,1) Pressurizer Pressure 4 RCP002 (1,1) RCS Pressure 5 PRL1000 (1,1) Pressurizer ' evel 6 PRT1001 (1,1) Pressurizer Water Temperature 7 SGW600 (1,1) A OTSG Steam Flow 8 SGW600 (2,1) B OTSG Steam Flow 9 STA35241 (1,1) A OTSG MFW Flow 10 STA35242 (1,1) B OTSG MFW Flow

) 11 RCT006 (1,1) Loop B That 12 RCT005 (1,1) Loop B Tcold 13 IMA35202 (1,1) B OTSG Pressure 14 STAA756G (1,1) B OTSG Operate Range Level 15 STA35232 (1,1) B OTSG Startup Range Level 6

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OPERABILITY TEST 92 January 4,1995

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l

ATTACHMENT R-2

(~') LIST OF POINTS RECORDED DURING TRANSIENT TEST Cr USING HISTORICAL DATA LOG #2 Point ID Global Variable Description 1 TRNT0005 (1,1) Reactor Power 2 RCT002 (1,1) Loop A That 3 RCT006 (1,1) Loop B That 4 RCT003 (1,1) Loop A Tcold 5 RCT005 (1,1) Loop B Tcold 6 IMA35201 (1,1) A OTSG Pressure 7 IMA35202 (1,1) B OTSG Pressure 8 STAA755G (1,1) A OTSG OP Range Level 9 STAA756G (1,1) B OTSG OP Range Level 10 STA35231 (1,1) A OTSG SU Range Level

11 STA35232 (1,1) B OTSG SU Range Level 12 SGW600 (1,1) A OTSG Steam Flow 13 SGW600 (2,1) B OTSG Steam Flow 14 STA35241 (1,1) A OTSG Feedwater Flow 15 STA35242 (1,1) B OTSG Feedwater Flow

~

A V OPERABILITY TEST 93 January 4,1995 l

l

ATTACHMENT R-3

\ LIST OF POINTS RECORDED DURING TRANSIENT TEST

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(- USING HISTORICAL DATA LOG #3 Point ID Global Variable Description 1 RCP801S (1,1) Pressurizer Pressure 2 RCP002 (1,1) RCS Pressure 3 PRL1000 (1,1) Pressurizer Level 4 CAP 010 (1,1) Reactor Building Pressure 5 CAT 010 (1,1) Reactor Building Temperature

,O V

OPERABILITY TEST 94 January 4,1995

ATTACHMENT R-4 LIST OF POINTS RECORDED DURING TRANSIENT TEST

/ USING HISTORICAL DATA LOG #4 Point ID Global Variable Description 1 RCWRCT ERV Flow to Quench Tank 2 RCP801S (1,1) Pressurizer Pressure 3 iRCP002 (1,1) RCS Pressure 4 PRT1001 (1,1) Pressurizer Water Temperature 5 RCT802 (2,1) Pressurizer Steam Temperature 6 PRL1000 (1,1) Pressurizer Level 7 ULA35151 (1,1) A RCS Loop Flow 8 ULA35152 (1,1) B RCS Loop Flow 9 RCT027 (1,1) Surge Line Temperature 10 RCT002 (1,1) Loop A Thot 11 NIS0501 (1,1) Source Range Counts 12 RCLRXVSL (1,1) Reactor Vessel Level 13 PRT1022E (1,1) Margin to Saturation t

a OPERABILITY TEST 95 January 4,1995

ATTACHMENT R-5 r~'y LIST OF POINTS RECORDED DURING TRANSIENT TEST U USING HISTORICAL DATA LOG #5 Point ID Global Variable Description 1 TRNT0005 (1,1) NI-5 Rx Power 2 RCMWTCOR(1,1) Core Power Thermal 3 GNJA100 (1,1) Generator Watts 4 ULA3513G (1,1) Tave 5 IAM35201 (1,1) A OTSG F'ressure 6 STAA755G (1,1) A OTSG Operate Range Level 7 PRL1000 (1,1) Pressurizer Level 8 TRT2631 (1,1) B OTSG Steam Temperature 9 RCXOOOB (1,1) Boron Concentration of the RCS 10 IAM35202 (1,1) B OTSG Pressure 11 STAA756G (1,1) B OTSG Operate Range Level 12 PRT1001 (1,1) Pressurizer Temperature 13 RCP002 (1,1) RCS Pressure 14 TRT2681 (1,1) A OTSG Steam Temperature 15 STAA7251 (1,1) A MFW Temperature 16 RCT003 (1,1) A MFW Flow 17 RCT002 (1,1) Loop A Cold Leg Temp 18 ULA35171 (1,1) Loop A Hot Leg Temp 19 RDGRPAVE (7,1) Group Seven Position (ABS) 4

() OPERABILITY TEST ss January 4,1995

ATTACHMENT R-5, (CONTINUED)

LIST OF POINTS RECORDED DURING TRANSIENT TEST USING HISTORICAL DATA LOG #5 Point ID Global Variable Description 20 STAA7252 (1,1) B MFW Temperature 21 STA35242 (1,1) B MFW Flow 22 RCT005 (1,1) Loop B Cold Leg Temp 23 RCT006 (1,1)

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OPERABILITY TEST s7 January 4,1995

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ATTACHMENT R-7 SUBJECT MATER EXPERT EXPERIENCE

SUMMARY

Subject Education / Years in the Years in Ops Years in Nuc NRC Operator Title Mrtter Expert Degrees Plant Training Navy License F. Uptagrafft B.S. 5 9 8 SRO Operations Trainer il D.E. Smith H.S. 8 12 6 SRO Operations Trainer ll R.E. Stancliff H.S. 8 15 0 SRO Operations Trainer ll J.E. Haynes A.S. 6 8 6 SRO Operations Trainer 11 E.S. Feemster H.S. 10 4 8 SRO Operations Trainer ll K.W. Canitz A.A. 5 10 6 SRO Operations Trainer 11 OPERABILITY TEST ss January 4,1995

1e ,

ATTACHMENT R-8 >

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1.sl CHRONOLOGICAL LOG r

DATE:

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1 aERABILITY TEST too January 4,1995 i

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ATTACHMENT R-9 l

. DELOGGING HISTORICAL DATA LOGS

1. Verify the interface cable is attached to the Serial Port (Com 3, a buffered 10  :

card) of the personal computer.

2. From Windows select the Icon for Delog Sim.

3. Select the correct Delog file number (1 to 5). t

4. Select the correct data frequency ( 1 for 1 second).

5. Enter the file name and file path. DO NOT include an extension.

6. Verify the Title of Graph line 1 is:

UNIT ONE SIMULATOR OPERABILITY TEST 199X

7. Enter the transient name in blank of graph title line 2.

8. Use mouse to start program.

O 9. This will save the data file and send graphs to the printer selected by windows.

V i

ERABILITY TEST 101 January 4,1995

A ATTACHMENT R-10

) OPERABILITY TEST STAFF Position Name Title / License Test Director Test Director Test Director Operator Operator Operator Operator

- Operator Operator l Operator j

2 Operator Operator Simulator Support Staff Simulator Support Staff Simulator Support Staff Simulator Support Staff Simulator Support Staff Simulator Support Staff O

(/ERABILITY TEST 102 January 4,1995 1