ML20070L845
| ML20070L845 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/14/1991 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML20070L843 | List: |
| References | |
| NUDOCS 9103200291 | |
| Download: ML20070L845 (272) | |
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siGNAtung . ALITHotel210 REPMESENTATIVE l TITLE DATI e','
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The Unit 1 Training Simulator is utilized for Unit 2 Simulator Tr'aining.
I Performance tests are those of Unit 1. See Certitication Report Section for differences between Unit 1 and Unit 2.
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The schedule for annual performance, testing is that of Unit 1.
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TABLE..0F.COMTENTS section Page A. PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . 1 A.1 SIM'ULATOR INFORMATION . . . . . . . . . . . . . . . 1 A.l.1 General . . . . . . . . . . . . . . . . . . . 1 h A.1.2 Control Room . . . . . . . . . . . . . . . . . 1
. A.1.3 Instructor Interface . . . . . . . . . . . . . 4 A.1.4 Operating Procedures for Reference Plant . 10 I
A.1.5 Changes since Last Report . . . . . . . . . 10 A.2 SIMULATOR DESIGN DATA . . . . . . . . . . . . . . . 10
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A.3 SIMULATOR TESTS . . . . . . . . . . . . . . . . . . 11 A.3.1 Computer Real Time Test . . . . . . . . . . 11 A.3.2 Steady-State and Normal Operations Tests . . 11 A.3.3 Transient Tests . . . . . . . . . . . . . . 12 A.3.4 Malfunction Tests . . . . . . . . . . . . . 13
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A.4 SIMULATOR DISCREPANCY RESOLUTION AND UPGRADING PROGRAM . . . . . . . . . . . . . . . . . . . . . . 13 A.E ANNUAL SIMULATOR OPERABILITY TESTING . . . . . . . la I A.5.1 A.5.2 Annual Tests .
Quadrennial Tests 13 14 A.6 DIFFERENCES BETWEEN UNITS . . . . . . . . . . . . . 16 A.6.1 Systems Design Differences . . . . . . . . . 17 A.6.2 Technical Spacification Differences . . . . 18 A.6.3 Procedure Differences . . . . . . . . . . . 19 A.6.4 Control Room Instrument / Control Location . . 21 A.C.5 Operational Characteristic Differences . . . 21 Attachments Tabs simulator Malfunctions. . . . . . . . . . . . . . . . . . A Simulator Local Operator Actions. . . . . . . . . . . . B.1 Simulator Component Failures. . . . B.2 l
Simulator Distable Overrides. . . . . . . . . . . . . . B.3 Certification Test Procedures Index . . . . . . . . . . . C Test J.batracts - Normal Operations. . . . . . . . . . . D.1 I Test Abstracts - Special Simulator Tests. . . . . . . .
Test Abstracts - Malfunctions . . . . . . . . . . . . .
Test Abstracts - Baseline Transients. . . . . . . . . .
D.2 D.3 D.4 l' Test Abstracts - Steady-State Tests . . . . . . . . . .
Test Abstracts - Plant Transients . . . . . . . . . . .
Certification Test Discrepancies. . . . . . . . . . . . .
D.5 D.6 E
Certification ANSI /ANS-3.5 Exceptions . . . . . . . . . . F I
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I FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION REPORT A. PURPOSE This report contains the required information for certification of the simulator for use in conducting operating tests for Farley Nuclear Plant operators as required by 10 CFR 55.45(b) (2) (iii) . The requirements of Reg. Guide 1.149 for a dual plant simulation facility have also been addressed.
A.1 8INULATOR INFORMATION I A.1.1 General I The Alabama Power Company owned oimulator is used to train both Farley Nuclear Plant Unit 1 and Unit 2 plant operators. The simulator is modeled after Unit 1, a 865 MWe Westinghouse PWR plant, but because of the near exact I duplication of the two plants it is considered a plant specific simulator for both units. The simulator was constructed by Westinghouse during the early 1980's. The first training was conducted in July 1983.
A.1.2 Control Roon A.1.2'.1 Control Room Physical Arrangement The simulator main control room, "at the controls area" duplicates that of the Unit 1 main control room, "at the controls area" with five exceptions:
(1) The Unit 2 portion of the Shift Supervisor's workstation is not duplicated.
I (2) One cabinet containing controlled drawings is located in a slightly different position than in Unit 1.
(3) Unit 1 and Unit 2 Turbine generator condition monitor log typers, located in the Unit 1 I portion of the main control room, are not present.
I (4) The main turbine control printers are located on the opposite sido of the control room from Unit 1.
(5) Unit 1 TSC cameras are not present in the simulator main control room but video cameras utilized for training purposes are installed.
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FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION REPORT All other furniture, drawing cabinets, line printers, keyboards, CRTs and procedure racks are identical in appearance, location and function to those l in the Unit 1 main control room "at the controls area".
Certain panels located outside the "at the controls I area" have also been included within the scope of simulation. While these panels are not in the same physical location as in the plant, all controls and indicators are duplicated and are functional.
A.1.2.2 Panels / Equipment Figure 1 Shows the physical arrangment of Unit 1 control room pancis and equipment. The Farley Nuclear Plant simulator duplicates the panels listed below with the exceptions noted:
Panel Correct Number Panel Description Location Notes 1 MAIN CONTROL BOARDS YES 2 INCORE NUCLEAR INSTRUMENTATION YES 3 PROCESS AND AhEA RADIATION MONITORING YES 4 EXCORE NUCLEAR INSTRUMENTATION YES I 5 EMERGENCY POWER BOARDS (UNIT I AND II) YES 6 BALANCE OF PLANT PANELS-SAFETY RELATED- YES 7 SOLID STATE PROTECTION LOGIC A NO 1 8 ROD CONTROL LIFT DISCONNECT SWITCH BOX YES 9 MAIN TURBINE SUPERVISORY INSTRUMENTATION YES 10 PLANT COMPUTER LOG PRINTER YES 11 PLANT COMPUTER ALARM PRINTER YES 12 PLANT COMPUTER /SPDS MONITOR YES 13 PLANT COMPUTER /SPDS KEYBOARD YES 14 INADEQUATE CORS COOLING HARGIN PROCESSOR CABINET NO 3 I 2
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FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION REPORT I Panel Number Panel Description correct Location Notes 15 HOT SHUTDOWN PANEL A NO 2 16 HOT SHUTDOWN PANEL B NO 2 17 HOT SHUTDOWN PANEL C NO 2 18 HOT SHUTDOWN PANEL D NO 2 19 HOT SHUTDOWN PANEL E NO 2 20 HOT SHUTDOWN PANEL F NO 2 El HOT SHUTDOWN PANEL G NO 2 57 TURBINE CONTROL LOG PRINTER NO 4 58 TURBINE CONTROL ALARM PRINTER NO 4 NOTES: (1) Train A only, both trainn are identical.
(2) Actual panels are located in NON-RAD Auxiliary l Building in various rooms. The simulator panels are located in one room adjacent to the simulator main control room.
(3) Both trains are located in a single cabinet.
I (4) The printers are located on the opposite side of the control room in the simulator.
A complete verification of the face front I appearance of all simulated panels was completed in November of 1990. This was accomplished by an item by item comparison of the simulated panels with video tape I taken of the Unit 1 panels. No discrepancies deemed to be significant to training were dicovered. Minor differencen as listed below have been corrected:
(1) Meter legends, (2)
I (3)
Missing labels, Label formats, (4) Range color coding, (5) Minor span differences.
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FARLEY NUCLEAR PLAWT SIMULATOR - CERTIFICATAJN REPORT Simulator Change Requests (SCR's) were initiated and implemented in accordance with training center ,
procedure FNP-0-TCP-14.0, Implementation of Simulator l Hodifications, to resolve the discrepancies.
A.1.2.3 Systems All plant systems, both fluid and electrical, deemed applicable to operator training and he.ving l .
controls / indications on simulated panels are modeled.
Additionally, those systems which are remotoly operated and are required to provide input to main simulation I models are also provided. All systems are integrated as necessary to perform plant evolutions and malfunctions and to duplicate the response expected in the reference plant.
A.1.2.4 Simulator Control Room Environment I The Parley Simulator control room environment is virtually identical to that in the plant. Lighting I levels, floors, ceiling, furniture, rod step counter noise and annunciator horns are duplicated to a high degree of accuracy. In addition, all communications .
systems including phones, PA systems and sound powered I phone jacks are present and fully functional.
A.1.3 Instructor Interface A.1.3.1 Initial Conditions The Farley Simulator is programmed to have up to 60 initial conditions available. The following list describes the initial conditions available for training.
IC DESCRIPTION 1 BOL XE/FR SRO 9 CPS 1843 PPM...UOP-1.2 D0100 ECC I 2 3
MOL XE/FR SRO 9 CPS 1236 PPM...UOP-1.2 D0100 ECC EOL EE/FR SRO 9 CPS 725 PPM...UOP-1.2 D0100 ECC I 4 5
BOL XE/FR SRO 9 CPS 1399 PPM...UOP-1.3 D0100 ECC TRIP +2HR MOL XE/FR SRO 9 CPS 1309 PPM...UOP-1.3 D0100 ECC TRIP 48HR
FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION REPORT I IC DESCRIPTION 6 EOL XE/FR SRO 9 CPS 1355 PPM...UOP-1.3 D0100 ECC TRIP +13HR 7 BOL XE/ EQ 10C'S D0221 1447 PPM 8___ MOL XEjFQ 100% D0221 767 PPM 4 EOL XE/EQ 100% D0221 220 PPM I 10__
11 BOL XE/UP SRO 40 CPS 1843 PPM..UOP-1.2 D0100 ECC C094 STPS BOL XE/UP 13% PWR D6111 1838 PPM TURBO 1700 RPM TV CNTRL 12 BOL XE/UP 9% PWR D0107 1841 PPM TURB0 0 RPM 13 BOL XE/UP 12% PWR D0111 1838 PPM TURB0 1800 RPM 14 MOL XE/UP 11% PWR D0136 1234 PPM TURBO 1800 RPM 15 EOL XE/UP 9% PWR D0150 725 PPM TURB0 1800 R,PM 16 BOL XE/UP 25% PWR 00148 1849 PPM.... RAMP UP FROM 0%
17 BOL XE/UP 72% PWR D0180 1778 PPM.... RAMP UP FROM 0%
18 BOL XE/UP 51% PWR D0181 1467 PPM.... RAMP DOWN FROM 100%
19 BOL XE/UP 2% PWR DO 96 1841 PPM....UOP-1.2 PRIOR TO SGPP 20 MODE 3 365F 42.*l PSI *300 PPM...UOP-2,2 C/D PRIOR TO RHR .
21 MODE 5 90F 90 PSI 1887 PPM...UOP-1.3 PRIOR TO RCP 22 MODE 5 158F 400 PSI 1800 PPM...UOP-1.1 H/U PRIOR TO BUBL 23 MODE 4 317F 380 PSI 1797 PPM...UOP-1.1 M/U PRIOR OFF RHR 24 MODE 5 128F 360 PSI 1781 PPM...UOP-2.2 C/D PRIOR TO SOLID 25 BOL XE/FR IRO E- 8 AMPS 1841 PPM...UOP-1.2 D0100 ECC D095 26 MODE 5 102F 374 PSI 1884 PPM...UOP-1.1 SOLID &RCP RUNNING 27- Available for instructor use 50 1 51- Periodic backup snaps (overy 3 min.)
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FARLEY NUCLEAR PLANT SIMULATOR = CERTIFICATION REPORT I
A.1.3.2 Malfunctions A complete description of all malfunctions available on the simulator is included as attachment A.
The following list of malfunctions were tested in I accordance with ANSI /ANS-3.5, Section 3.1.2, and cross referenced to test procedure and ANSI /ANS-3.5 requirement. This represents 33% of the total number of malfunctions available on the sinualtor.
ANSI 'IEST SECTION PROCEDURE MALF _
3.1.2(la) FNP-SIM-CTP-2.50 RCS4 I 3.1.2(1b) FNP-SIM-CTP-2.48 FNP-SIM-CTP-2.56 RCS1 RHR4 3.1.2(1c) FNP-SIM-CTP-2.49 RCS2 3.1.2(1d) FNP-SIM-CTP-2.43 PRS 3 FNP-SIM-CTP-2.44 PRSS 3.1.2(2) FNP-SIM-CTP-2.1 AUX 1 3 .1. 2 ( 3 ) FNP-SIM-CTP-2.12 EPS1 I FNP-SIM-CTP-2.13 FNP-SIM-CTP-2.14 FNP-SIM-CTP-2.15 EPS2 EPS3 EPS4 FNP-SIM-CTP-2.16 I FNP-SIM-CTP-2.17 FNP-SIM-CTP-2.18 EPS6 EPS7 EPS8 FNP-SIM-CTP-2.19 EPS9 FNP-SIM-CTP-2.20 EPS10 FNP-SIM-CTP-2.21 EPS11 FNP-SIM-CTP-2.22 EPS12 3.1.2(4) FNP-SIM-CTP-2.51 RCSS 3.1.2(5) FNP-SIM-CTP-2.4 CND4 FNP-SIM-CTP-2.5 CND5 FNP-SIM-CTP-2.6 CND6 3.1.2(6) FNP-SIM-CTP-2.2 I 3.1.2(7) FNP-SIM-CTP-2.55 AUX 4 RHR1 3.1.2(8) FNP-SIM-CTP-2.3 CCW1 3.1.2(9) FNP-SIM-CTP-2.24 FWM11 I
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FARLEY WUCLRAR PLANT SINULATOR - CERTIFICATION REPORT ANSI TEST SECTION _
PROCEDURE MALF 3.1.2(10) FNP-SIM-CTP-2.59 FWM1 3.1.2(11) FNP-SIM-CTP-2.27 TWM26 FNP-SIM-CTP-2.53 RCS10 3.1.2(12) FNP-SIM-CTP-2.9 CRF14 FNP-SIM-CTP-2.10 CRF15 3.1.2(13) FNP-SIM-CTP-2.7 CRF2 FNP-SIM-CTP-2.8 CRF3 3.1.2(14) FNP-SIM-CTP-2.52 RCS8 3.1.2(15) FNP-SIM-CTP-2.2 CND4 FNP-SIM-CTP-?. 39 PCS1 3.1.2(16) FNP-SIM-CTP-2.58 TUR16 3.1.2(17) FNP-SIM-CTP-2.34 MSS 10 3.1.2(18) FNP-SIM-CTP-2.11 CVC10 FNP-SIM-CTP-2.45 PRS 10 I FNP-SIM-CTP-2.46 FNP-SIM-CTP-2.47 PRS 11 PRS 12 3.1.2(19) TNP-SIM-CTP-2.39 PCS1 I _
3.1.2(20) FNP-SIM-CTP-2.29 FNP-SIM-CTP-2.30 FWM27 FWM28 I FNP-SIM-CTP-2.31 FNP-SIM-CTP-2.32 MSS 1 MSS 2 3.1.2(21) FNP-SIM-CTP-2.36 NIS1 I -
FNP-SIM-CTP-2.36.1 FNP-SIM-CTP-2.36.2 FNP-SIM-CTP-2.36.3 NIS4 NIS2 NIS5 I FNP-SIM-CTP-2.37 FNP-SIM-CTP-2.37.1 FNP-SIM-CTP-2.37.2 NIS6 NIS7 NIS8 FNP-SIM-CTP-2,38 NIS10 I FNP-SIM-CTP-2.38.1 FNP-SIM-CTP-2.38,2 NISO NIS11 I 3.1,2(22) FNP-SIM-CTP-2.25 FNP-SIM-CTP-2.26 FNP-SIM-CTP-2,27 FWM12 FWM13 FWM15 I FNP-SIM-CTP-2.28 FNP-SIM-CTP-2.33 FNP-SIM-CTP-2.35 FWM26 MSS 7 MSS 11 FNP-SIM-CTP-2.53 RCS10 FNP-SIM-CTP-2.54 RCS11 FNP-SIM-CTP-2.57 TUR11 l
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FARLEY NUCLEAR FLANT SIMULATOR - CERTIFICATION REPORT I ANSI SECTION TEST PROCEDURE MALF 3.1.2(23) FNP-SIM-CTP-2.41 PCS5 FNP-SIM-CTP-2.23 FWM4 I 3.1.2(24) 3.1.2(25)
FNP-SIM-CTP-2.40 NOT APPLICABLR To PCS4 N/A PWR I
A.1.3.3 Controls Provided for Items outside control Room All items modeled in the simulator which are I expected to be operated outside the control room are controlled via the instructor interface with Local Operator Actions. ,A complete listing of all Local Operator Actions is provided as Attachment D.1.
A.1.3.4 Additional special Instructor / Training Features Available In addition to Valfunctions and Local Operator I actions, the Parley liimulator has the following instructor / training 1'entures available.
(1) Annunciator overrides - Any annunciator can be driven either on or off from the instructor station.
(2) Panel overrides - Any main control board switch contact, potentiometer, meter or light can be overridden from the instructor station, independent of the computed model output.
(3) Plant Parameters - A limited number of I parameters, (i.e. radiation levels, atmospheric pressure and temperatures, selected tank levels, etc.) can be modified via the instructor station.
(4) Comoonent Failunqn - Failures to components, such as loss of electrical power, indication, or I control air can be implemented from the instructor station for tha pumps, valves and controllers listed in Attachment B.2.
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, FARLEY WUCLEAR PLMIT SIMULATOR - CERTIFICATICW REPORT (5) Bintable Overriday - Distables listed in Attachment B.3 can be overridden as tripped or reset and/or the satpoint can be displayed and altered via the inntructor station.
(6) Eachng - Ten snapshots are reserved as backup I sr.apshots . .The backup snapshots are taken typically every three minutes but this is adjustable. These backup snapshots allow the l ins.tructor to return the simulator back to a previous condition and repeat operations.
(7) Freeze - The instructor has the ability to I freeze the simulation at any time, and then go t'o run and continue.
(8) Sigsneed - The speed of almulation can be varied from the instructor station. This is most useful in slowing down simulation to observe and discues events. The increase in simulation I speed is also available.
(9) Out of Limits - The simulation is constantly monitored for specific plant design limits being exceeded. Such limits being exceeded would indicate that the simulation has progressed ,
beyond plant design limits. If the lir.its are exceeded, the simulation freezes, the control boards blink at a steady rate, and a nessage is I displayed on the instructor console. This alerts the instructor and the students that the simulation may not be realistic. The instructor can evaluate the situation and go to run and I continue simulation if desired, or re-initialize the simulator.
I (10) huxiliary Instructor console --Instructor control can be transferred from the instructor booth to a portable instructor console located on the simulator floor. This portable instructor station duplicates all features incorporated in the primary instructor station.
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'nMl YARLEY NUCLEAR PLANT SINULATOR = CERTIFICATION REPORT (11) Remote Instructor Control - A selected number of instructor features can be implemented from a hand held remote device. This device is I approximately the size of a hand held calculator, and can be operated from the vicinity of the simulator main control room or I instructor booth.
A.1.4 Operatinq Procedures for Reference Plant I The procedures used on the Farley Simulator are actual controlled copies of the Unit 1 plant procedures.
A.1.5 Changes Since Last Report This is the initial certification report.
A.2 SIMULATOR DESIGN DATA The Farley Simulator design database is defined as the following documents:
(1) Plant drawings including P&ID's, electrical and elementary logics; (2) Plant procedures containing information on setpoints, operational steps and characteristics; (3) Plant lesson plans containing system descriptions and operations; (4) Plant data consisting of . logs, plant computer lic.;ings, surveillance test results, and startup test data; (S) Vendor manuals associated with plant equipment operated from the main control boards; (6) Vendor summary reports containing plant core physics data for actual plant fuel loads; (7) The Simulator Change Request (SCR) database whics. is utilized to initiate, track, test and document both software and hardware changes to the simulator; I
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I FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION REPORT (8) The Production Change Notification (PCN) database which is utilized to document the review and implementation of PCN's applicable to the simulator I following implementation in the plant. The PCN's reviewed reflect modifications to the plant as well as changes made to documents considered part of the simulator design database.
The simulator was constructed utilizing these documents as they existed during the early 1980's. Modifications have subsequently been documented via the aforementioned SCR 1 database.
A.3 SIMULATOR TESTS Certification test procedures document the performance of the simulator for the various categories of requirements specified by ANSI /ANS-3.5. Attachment C provides an index of all Certification Test Procedures and their titles, cross-( referenced to the applicable ANSI /ANS-3.5 section. All tests
-were conducted by qualified and trained individuals who hold or nave-held an SRO license or certification.
A.3.1 Computer Real Time Test ,
Certification Test-Procedure FNP-SIM-CTP-1.7 verifics the simulator real time capability. The results are summarized in the test abstract included in Attachment D.2.
_ -A.3.2 8tsady-8 tate and Normal Operations Tests (1) Steady-State Stability - Test procedure FNP-SIM-CTP-4.0 evaluates the simulator's stability for a I 60 minute period at 100% power. Results of this test are summarized in the test abstract included in Attachment D.5. Any Exceptions are listed in Attachment F.
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FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION REPORT (2) Steady-State-Plant Comoarisons - The following test procedures compare the simn~; tors steady state performance to the reference plant:
PROCEDURE l TITLE FNP-STM-CTP-1.6 Core Physics Testing )
FNP-SIM-CTP-4.1 Steady-State Comparison to Reference Plant FNP-SIM-CTP-4.2 Steady-State Thermal !
Calorimetric Comparison
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The results of these tests are summarized as test L
abstracts included in Attachment D.2, and Attachment D.5. Discrepancies for all tests are summarized in Attachment E. Any exceptions to the ANSI /ANS-3.5 standards are listed in Attachment F.
p) Normal ODerations - These tests evaluate the simulator's performance while conducting normal plant operations using the reference plant procedures. The results of these tests are summarized as test abstracts included in Attachment D.l. Discrepancies for all tests are surmarized in Attachment E.
A.3.3 Transient Tests (1) Plant Transients - Tests which duplicate actual events that have occurred in the reference plant were: performed. The simulator's response was compared to actual plant-data and information available. The results of these tests are summarized as test abstracts included in Attachment lI-i D.6. Discrepancies for all tests are summarized in Attachment E.
(2) D.gseline Transients - Ten baseline transients, as recommended by ANSI /ANS-3.5, Appendix B, were run L -
to evaluate the simulator's performance under expected and severe accident transient conditions.
The results of these tests are included in test abstracts found in Attachment D.4. All test discrepancies are summarized in Attachment E. ..
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l- ; FARLEY WUCLEAR PLANT SIMULATOR - CERTIFICATION REPORT I A.3.4 Malfunction Tests I Those malfunctions listed in Section A.1.3.2 of this report were tested. The results of these tests are summarized as test abstrccts included in Attachment D.3.
Discrepancies for all tests are summarized in Attachment E.
Any-exceptions of the ANSI /ANS-3.5 requirements are listed in Attachment F.
A.4 SIMULATOR DISCREPANCY RESOLUTION AND UPGRADING PROGRAM I Training Conter Procedure FNP-0-TCP-14.0, Implementation of Simulator Modifications, describes the methodology used to identify, track, implement, test and document changes made to I the simulator hardware and software. These changes may be a result of plant design modifications, a change in scope of simulation because of new training emphasis, or descrepancies
-- discovered during training or simulator testing. This ensures simulatcr performance closely matches that of the referenced plant and hardware configuration is duplicated in the simulated areas.
A.5 ANNUAL SIMULATOR' OPERABILITY TESTING.' .
In order to ensure simulator perforrance and verify its operability, annual _ testing will be conducted. This testing will normally be accomplished in the 4th quarter each year.
- A.5.1 Aunual Tests A select set of tests will be conducted each year.
TYPE OF TEST TEST PROCEDURES Special Tests FNP-SIM-CTP-1.7 FNP-SIM-CTP-1.8 Steady-State FNP-SIM-CTP-4.0 FNP-SIM-CTP-4.1 I -
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FARLEY NUCLRAR PLANT SIMULATOR - CERTIFICATION REPORT
- n "I. TYPE OF TEST l TEST PROCEDURES Baseline Trar.sient FNP-SIM-CTP-3.1 I. FNP-SIM-CTP-3.2 FNP-SIM-CTP-3.3 FNP-SIM-CTP-3.4 I FNP-SIM-CTP-3.5 FNP-SIM-CTP-3.6 FNP-SIM-CTP-3.7 I ,= %
FNP-SIM-CTP-3.8 FNP-SIM-CTP-3.9 FNP-SIM-CTP-3.10 A.5.2 Quadrennial Tests In addition to the annual tests, listed in A.5.1, the following tests will be conducted according to the schedule indicated:
YEAR TYPE OF TEST TEST PROCEDURES Year 1 Normal Operations FNP-SIM-CTP-1.0 (1991)
Malfunctions FNP-SIM-CTP-2.1 FNP-SIM-CTP-2.2 FNP-SIM-CTP-2.3 FNP-SIM-CTP-2.4 I FNP-SIM-CTP-2.5 FNP-SIM-CTP-2.6 FNP-SIM-CTP-2.16 I FNP-SIM-CTP-2.20 FNP-SIM-CTP-2.21 FNP-SIM-CTP-2.39 FNP-SIi4 -CTP-2. 4 4 I FNP-SIM-CTP-2.48 FNP-SIM-CTP-2.50 I
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I Year 2 (1992)
Normal Operations FNP-SIM-CTP-1.1 FNP-SIM-CTP-1.2 Malfunctions FNP-SIM-CTP-2.12 FNP-SIM-CTP-2.15 FNP-SIM-CTP-2.19 FNP-SIM-CTP-2.22 FNP-SIM-CTP-2.27 FNP-SIM-CTP-2.38 FNP-SIM-CTP-2.38.1 FNP-SIM-CTP-2.38.2 FNP-SIM-CTP-2.42 I FNP-SIM-CTP-2.43 FNP-SIM-CTP-2.49 FNP-SIM-CTP-2.53 FNP-SIM-CTP-2.55 I FNP-SIM-CTP-2.56 FNP-SIM-CTP-2.57 FNP-SIM-CTP-2.59 Year 3 Norac1 Operations FNP-SIM-CTP-1.3 (1993)
Malfunctions FNP-SIM-CTP-2.11 FNP-SIM-CTP-2.13 FNP-SIM-CTP-2.14 FNP-SIM-CTP-2.'17 I FNP-SIM-CTP-2.18 FNP-SIM-CTP-2.23 FNP-SIM-CTP-2.31 I FNP-SIM-CTP-2.32 FNP-SIM-CTP-2.34 FNP-SIM-CTP-2.35 FNP-SIM-CTP-2.40 I FNP-SIM-CTP-2.45 FNP-SIM-CTP-2.46 FNP-SIM-CTP-2.47 FNP-SIM-CTP-2.52 FNP-SIM-CTP-2.54 FNP-SIM-CTP-2.58 I
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FARLEY NUCLEAR PLANT SIMULATOR = CERTIFICATION REPORT Year 4 Normal Operations FNP-SIM-CTP-1.4 (1994)
Malfunctions FNP-SIM-CTP-2.7 FNP-SIM-CTP-2.8 FNP-SIM-CTP-2.9 '
FNP-SIM-CTP-2.10 I FNP-SIM-CTP-2.24 FNP-SIM-CTP-2.25 FNP-SIM-CTP-2.26 I FNP-SIM-CTP-2,27 FNP-SIM-CTP-2.28 FNP-SIM-CTP-2.29 FNPcSIM-CTP-2.30 I FNP-SIM-CTP-2.33 FNP-SIM-CTP-2.35 FNP-SIM-CTP-2.36.
I FNP-SIM-CTP-2.36.1 FNP-SIM-CTP-2,36.2 FNP-SIM-CTP-2.36.3 FNP-SIM-CTP-2.37 FNP-SIM-CTP-2.37.1 FNP-SIM-CTP-2.37,2 FNP-SIM-CTP-2.38 FNP-SIM-CTP-2.38.1 FNP-SIM-CTP-2.38.2 .
FNP-SIM-CTP-2.41 FNP-SIM-CTP-2.51 FNP-SIM-CTP-2.53
! . FNP-SIM-CTP-2.54 FNP-SIM-CTP-2.57 l
[g . A description of these tests can be found in r5 Attachment C. For subsequent years, this test schedule i will be reviewed and repeated on a four year cycle.
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A.6 DIFFERENCES BETWEEN UNITS l This section consists of a summary of the analysis of the differences between Unit 1 and Unit 2 at Farley Nuclear Plant in compliance with Regulatory Guide 1.149. Differences in systems design, operational characteristics, control room instrumentation / control locations, procedures and Technical Specifications were. reviewed. Although the simulator.is I modeled after the Unit 1 control room and reference design data-the simulator is considered plant specific for training of Unit 2 operators. Unit 1 and Unit 2 at Plant Farley are I
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l FARLEY NUCLEAR PLANT SINULATOR = CERTIFICATION REPORT l
l lE virtually identical in both design and operation. Based on E this analysis, Alabama Power Company feels that the differences noted are acceptable with respect to the use of the simulator for Unit 2 operator training and that the I simulator meets the requirements of ANSI /ANS-3.5-1985 for Farley Unit 2.
I Differences that do exist between the two units result from either permanent differences that exist because the two units share some systems or parts of systems or because of
'I temporary differences from modifications being made to one unit or the'other to improve operability or maintenance.
These temporary differences are short lived since similar modifications are made to the other unit in a timely manner.
I The permanent differences have been investigated and are covered in detail in Operator License Training Lesson Plar OPS-52108H.
A.6.1 Systems Design Differences The following system and component design differences, pertainent to control operation exist between Unit 1 and Unit 2 (1) Fire Protection Storace Tanks. Service Water Sucolv ,
A service water connection to the fire protection pump suction is installed on Unit 2 to serve as a backup source of water to the fire protection system.
(2) Reactor vessel Water Level Indication - This indication is used for mid-loop operation. Level is direct reading in feet on Unit 2 and is a dual digit readout in inches on Unit 1. _This difference is being eliminated during.the Unit i refueling outage, upcoming in March.1991.
(3) Sumo Pumos - The Unit 2 containment and auxiliary building sump pumps require reactor makeup water as I a source for pump seal water. The auxiliary building sump pumps have low seal water flow trip protection with the reset switch located on the Balance of Plant panel. ,
(4) Electrical Systems - The Unit I high voltage switchyard is 230KV while Unit 2 is 500KV. Startup transformer distribution to the Unit 1 4160V -
reactor coolant pump busses is opposite to that of I
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FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION REPORT 1 .
I Unit 2. The only Major load differences are associated with the 4150V busses 1C and 2C. Bus 1C supplies power to the Emergency operations Facility I and Bus 2C supplies power to the Low Level Rad-Waste Building.
(5) Residual Heat Removal System - MOV-8880A and B are I. motor operated RHR system valves which isolate the RHR discharge to the cold legs. They are normally open during plant operation and are controlled from I the MCB. A dif*erence in valve numbering exists between the two units. On Unit 1, MOV-8888A is Train-A and MOV-8888B is Train-B. On Unit 2, MOV-8888B is Train-A ,.while MOV-8888A is Train-B.
(6) Service Air System - Unit i supplies service air to the service building. Unit 1 breathing and I emergency air to containment can be isolated while Unit 2 supply cannot.
I A.6.2 TechLical 3pecification Differences The Technical Specification review consisted of a page I. by page comparison of the Unit 1 and Unit 2 Technical Specification documente. Differences exist but are more applicable to the written examination environment and have I no impact on manipulative operations and are therefore considered insignificant. The differences are:
(1) Area Temperature Monitorina (Tech. Spec. 3.7.13) -
1 Only Unit 2 Technical Specifications require that temperatures, other than containment temperature, I be maintained within prescribed limits. These limits ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures.
(2) Onsite Power Distribution Systems AC Distribution -
Ooeratina (Tech. Soec. 3.8.2.11 - Unit 1 and Unit 2 Technical Specifications differ from one another on this limiting condition for operation (LCO). Unit 2 requires that the 120 volt alternating current I (AC) vital busses be energized from a fully operational inverter capable of being supplied by either the normal or alternate power source. Unit 1 does not specify from where the 120 volt AC vital I busses must be energized, only that they must.
Unit 2, actions statement b, specifically addresses I
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FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION REPORT the required actions if an inverter is inoperable.
(3) Onsite Power Distribution Systems AC Distribution -
I Shutdown (Tech. Soec. 3.8.2.2) - The Unit 2 shutdown specification, like the above described operating specification, specifically states that an operable 120 volt AC vital bus will be one that is powered from an inverter.
(4) Containment Penetration conductor Overcurrent I Protection Devices (Tech. Socc. 3.8.3.1) - Only Unit 2 Technical Specifications require that all containment penetration conductor overcurrent devices shall be operable.
(5) MOV Thermal Overload Protection Devices (Tech.
Spec. 3.8.3.2) - Only Unit 2 Technical Specifications require MOV thermal overload protection devices be operable. The operability ensures devices will not prevent safety-related valves from performing their design function.
A.6.3 Procedure Differences The operating procedures for Unit 1 and Unit 2 were reviewed for tangible differences. The scope of this review was limited to those procedures used primarily in the initial license or retraining programs. Review emphasis was focused on simulator application significance as well as the abnormal and emergency operational r environments to be consistent with Regulatory Guide 1.149.
l Procedures that were reviewed were selected from the following:
System operating Procedures............... SOP Unit Operating Procedurus.................UOP l Surveillance Test Procedures..............STP l Annunciator Response Procedures...........ARP Abnormal Operating Procedures.............AOP Emergency Event Procedures................EEP Event Specific Procedures................. ESP l Emergency Contingency Procedures..........ECP lE Functional Restoration Procedures.........FRP lE Critical Safety Function Procedures....... CSP I
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FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION REPORT
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The following is a brief synopsis of the results of thi:1 review process:
(1) S.Q.P_'a - No significant differences exist.
(2) UOP's - Minor word processing and step sequence
-g- differences as well as some heatup and cooldown g surveillance numbering and testing differences exist.
- (3) STP's - No significant differonces exist.
(4) ARP's - Several minor differences exist, such as: '
a) The control room ventilation systems are shared and alarms are annunciated on Unit 1.
b) The fire protection system is shared and most of the alarms are annunciated on Unit 1.
l c) Seismic events are alarmed on Unit 1.
d) Security events are alarmed on Unit 1.
e) There.are several miscellaneous outside system differences that alarm on their respective units.
(5) AOP's - No significant differences exist.
(6) ERP's - ERP's include the EEP's, ESP's, ECP's, GP's and CSF procedures. ERP's on Unit 2 have been revised to better meet the guidelines of the l
ERP Writer's Guide, AP74. As a result, differences l do exist between Unit :. Tnd Unit 2. Unit 1 ERP's l will be revised during the second quarter of 1991.
Simulator trainees use only controlled copies of procedures during training sessions. Unit 1 procedures are i
- g. normally used but selected Unit 2 procedures are available g' fur reference in the simulator and training library if needed. The simulator is a3so used to evaluate plant i procedures while under development but not considered part of.the set of procedures incorporated in the licensing
~ training program.
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FARLEY NUCLEAR PLAL'r SIMULATOR - CERTIFICATION REPORT A.6.4 control Room Instrument / Control Location With some systems being-shared between both units, controls for shared components exist on only one of the unit control boards. These differences include (1) Service Water System - Service water system header I isolation valves to the pond and wet pit are shared and controlled from the Unit 2 main control board.
4 (2) Containment Coolina - The containment coolers for both units are equipped with high vibration trips.
The reset switches for Unit 1 coolers are not
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located on the control board panels. The Unit 2 reset switches are on the Balance of Plant panel.
(3) Ventilation Systems - The control room ventilation I systems are-shared and indications / controls are on the Unit 1 panels.
A.6.5 Operational Characteristic Differenpes
,3 (1) Steam Generator Feed Pumn controller - The
'g differential pressure programs for maintaining feed regu.lating valve control ~are s13ghtly different.
I (2) Auxiliary Feedwater System - The 1A motor driven auxiliary feedwater pump produces approximately 10 l percent-more feedwater flow than the other motori driven auxiliary feedwater pumps due.to a different impeller design. 9 (3) Residual Heat Removal System - To ensure that the
! residual heat removal '(IUCR) pumps do not overheat oor vibrate at low flows, a miniflow return line is l downstream of each RHR heat exchanger and
! discharges to the pump suction lines. A control' valve (FCV-602A and B) located in each miniflow line is actuated by a signal from the pump I discharge flow transmitters (FIS-602A and B).
control valves open when the RHR pump discharge flow is less that 710 gpm on Unit 1, 1337 gpm on The Unit 2. They close when the flow exceeds 1327 gpm
_I en Unit 1, 2200 gpm on Unit 2.
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UNIT I MAIN CONTROL ROON
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SHIFi' Shin FOREMAN !9 SUPV.\
OFFICE STATION 13 I1 0 SECURITY 1 h
CENTRAL 1o ALARM ' 3 STATION l
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48 l 24 47 45 44 43 42 41 40 7 39 38 37 36 35 34 33 32 46 31 30 29 28 27 26 14 25 23 22 21 h
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I !EGEND f PANEL 21 DC DISTRIBUTIDW CABINET EOUIPMENT UNIT 2 22 AC DISTRIBUTION CABINET
- - - 23 DC DISTRIBUTION CABINET JNIT 1 24 AC DISTRIBUTION CABINET 25 INADEQUATE CORE COOLING MARGIN PROCESSOR CABINET 26 RELAY RACK 27 CHARCOAL FILTER TEMPERATURE ALARM PANEL 28 FIRE PROTECTION ALARM PANEL 29 SEISMIC INSTRUMENTATION 30 CABINET NOT USED
. 31 REACTOR VESSEL LEVEL PROCESSOR CABINET 32 REACTOR VESSEL LEVEL PROCESSOR CABINET 33 METAL IMPACT MONITORING CABINET 34 GROSS FAILED FUEL DETECTOR CONTROL PANEL 35 AUXILIARY SAFEGUARDS CABINET A TRAIN 8E , 36 AUXILIARY SAFEGUARDS CABINET B TRAIN 37 AUXILIARY RELAY CABINET #2 38 AUXILIARY RELAY CABINET #1 BC : 39 SOLID STATE PROTECTION INPUT B 40 SOLID STATE PROTECTION LOGIC B 41 SOLID STATE PROTECTION OUTPUT B k I? 42 SAFE GUARDS -TEST CABINET B 43 SOLID STATE PROTECTION INPUT A 44 SOLID STATE PROTECTION OUTPUT A 45 SAFE GUARDS TEST CABINET A 46 STEAM GENERATOR FEEDPUMP CONTROLLER 47 MAIN TURBINE CONTROLLER 48 HUMIDIFIER 49 7300 SERIES INSTRUMENTATION CABINETS (PROTECTION) 50 7300 SERIES INSTRUMENTATION CABINETS (CONTROL) 51 BEARING TEMPERATURE MONITORING & METEROLOGICAL PANEL 52 POST LOCA HYDROGEN ANALYZERS 53 CONTROL ROOM VENTILATION RADIATION MONITOR 54 MAIN TURBINE CONTROL ENGINEERS CONSOLE 55 CONTAINMENT PURGE RADIATION MONITORS 56 7300 SERIES INSTRUMENTATION CABINETS (BALANCE OF PLANT) 59 POST LOCA HYDROGEN RECOMBINER PANEL 60 POST LOCA HYDROGEN RECOMBINER PANEL NOTE: RED COLOR DENOTES " AT THE CONTROLS AREA" BLUE COLOR DENOTES OTHER SIMULATED PANELS GURE 1 REFERENCE CERTIFICATION REPORT PAGE 2 FOR LEGEND 9/o3 2o029 ' -o 1 - -
ATTACEMENT h SIMULATOR MALFUNCTION 8 MALF DESCRIPTION AUX 1 INSTRUMENT AIR LINE BREAK AUX 2 RWST LEAK AUX 3 RIVER WATER PUMP TRIP (ON MAXIMUM OF FOUR PUMPS)
AUX 4 I AUX 5 AUX 6 SERVICE WATER PUMP TRIP (ON MAXIMUM OF FOUR PUMPS)
SERVICE
- WATER POND DAM BREAK DELETED c( DO NOT USE ) BREAK AUX 7 A TRAIN SERVICE WATER DILUTION BYPASS VALVE V563 FAILURE I AUX 8 AUX 9 AUX 10 CONTAINMENT SPRAY PUMP TRIP FUEL HANDLING ACCIDENT WASTE GAS DECAY TANK NUMBER 1 LEAK CCW1 CCW PUMP TRIP CCW2 CCW PIPE BREAK CCW3 CCW HEAT EXCHANGER TEMPERATURE ELEMENT FAILURE I. CCW4 CCW5 LETDOWN HEAT EXCHANGER TUBE LEAK CCW TO RCP OIL COOLER VALVE MOV-3182 FAILURE CCW6 '
'RCP 1A THERMAL BARRIER LEAK CCW7 CCW FROM RCP THERMAL BARRIER VALVE HV-3045 FAILURE I- CCW8 SEAL WATER HEAT EXCHANGER TUBE LEAK CCW9 CCW TO LETDOWN HEAT EXCHANGER VALVE TV-3083 CONTROL FAILURE CCW10 .CCW TO RHR HEAT EXCHANGER 1B VALVE MOV-3185B FAILURE
, .CND1-- , CIRCULATING WATER PUMP TRIP CND2 CONDENSER TUBE LEAK IN CONDENSER A
-I CND3 CND4 GLAND SEALING STEAM FAILURE STEAM JET AIR EJECTOR FAILURE CND5 HOTWELL FILL CONTROLLER CP-4055F FAILURE CND6 HOTWELL DUMP CONTROLLER CP-4055G FAILURE CRF1 ROD DRIVE MG SET TRIP CRF2 RODS FAIL TO MOVE IN AUTOMATIC' CRF3 RODS FAIL TO MOVE IN MANUAL CRF4 SHUTDOWN BANK RODS FAIL TO MOVE l3 CRF5 CONTROL BANK RODS FAIL TO MOVE J CRF6 CRF7 UNCONTROLLED ROD MOTION
! UNCONTROLLED INDIVIDUAL RCCA ASSEMBLY WITHDRAWAL I CRF8 TREF FAILURE WITHIN ROD CONTROL
! CRF9 IMPROPER BANK OVERLAP l CRF10 -AUTOMATIC ROD SPEED CONTROLLER FAILURE
-CRF11 CONTROL ROD POSITION STEP COUNTER FAILURE CRF12 DRPI - LOSS OF VOLTAGE TO COIL CRF13 DRPI - OPEN OR SHORTED COIL (ON MAXIMUM OF FOUR MECHANISMS)
CRF14 STUCK ROD (ON MAXIMUM OF FOUR MECHANISMS)
CRF15 DROPPED ROD (ON MAXIMUM OF FOUR MECHANISMS)
I- CRF16 ROD EJECTION (ON MAXIMUM OF FOUR MECHANISMS)
CVC1 LETDOWN ISOLATION VALVE FAILURE CVC2 LETDOWN LINE BREAK INSIDE CONTAINMENT 1 ATTACHMENT A
SIMULATOR I . MALFUNCTIONS I KALF DESCRIPTION
,,ml CVC3 LETDOWN ORIFICE ISOLATION VALVE FAILS CVC4 SEAL WATER RETURN RELIEF V8121 STICKS AFTER LIFTING CVCS LETDOWN CONTAINMENT ISOLATION VALVE V8152 FAILURE CVC6 LETDOWN PRESSURE CONTROL VALVE PCV-145 CONTROL FAILURE CVC7 LETDOWN TEMPERATURE ELEMENT TE-143 FAILURE CVC8 RCS FILTER PLUGGED CVC9 VCT DIVERT VALVE LCV-115A CONTROL FAILURE I CVC10 CVC11 CVC12 VCT LEVEL TRANSMITTER FAILURE BORON ANALYZER FAILURE CHARGING PUMP TRIP I '
CVC13 CVC14 CVC15 CHARGING FLOW CONTROL VALVE FCV-122 FAILURE CHARGING LINE BREAK INSIDE CONTAINMENT AUXILIARY SPRAY VALVE HV-8145 FAILS MAKEUP CONTROL FAILURE IN ALL MODES I CVC16 CVC17 CVC18 BORIC ACID TRANSFER PUMP TRIP REACTOR MAKEUP WATER TRANSFER PUMP TRIP CVC19 BORIC ACID FILTER PLUGGED I CVC20 CVC21 CVC22 BORIC ACID FLOW TRANSMITTER FT-113 FAILURE BORIC ACID TO BLENDER VALVE FCV-113A FAILURE REACTOR MAKEUP WATER TO BORIC ACID BLENDER VALVE FCV-114 I CVC23 CVC24 CVC25 REACTOR MAKEUP TO VCT INLET VALVE FCV-114'A FAILURE SEAL INJECTION FLOW CONTROL VALVE HCV-186 CONTROL FAILURE SEAL INJECTION FILTER 1A PLUGGED ,
SEAL WATER RETURN LINE BREAK OUTSIDE CONTAINMENT I CVC26 CVC27 CVC28 RCP NUMBER 1 SEAL FAILURE RCP NUMBER 2 SEAL LEAK CVC29 RCP NUMBER 3 SEAL LEAK CVC30 BTRS TEMPERATURE ELEMENT 381/386 FAILURE CVC31 BTRS CHILLER UNIT FAILURE CVC32 BORON INJECTION TANK RECIRC ISOLATION VALVE V8945 FAILURE EPS1 DEGRADED GRID VOLTAGE - LOSS OF ALL OFF-SITE POWER EPS2 4160 BUS TRIP (ON MAXIMUM OF FIVE BREAKERS)
I EPS3 EPS4 EPSS EMERGENCY 4160V BUS TRIP (ON MAXIMUM OF FOUR BREAKERS)
DIESEL GENERATOR FAILURE ESSENTIAL PROTECTION DIESEL GENERATOR FAILURE DUE TO NON-ESSENTIAL PROTECTION
.g EPS6 STARTUP TRANSFORMER FAILURE (ON MAXIMUM OF TWO TRANSFORMERS) g- EPS7 600V LOAD CENTER TRIP EPS8 600V MCC TRIP EPS9 120 VAC VITAL INSTRUMENT INVERTER FAILURE I EPS10 EPS11 EPS12 120 VAC VITAL INSTRUMENT DISTRIBUTION PANEL TRIP 120 VAC DISTRIBUTION PANEL TRIP 125 VDC. DISTRIBUTION BUS TRIP ,
EPS13 DIESEL SEQUENCER CONTROL POWER FUSE FAILURE FWM1 AUX FEED PUMP TRIP FWM2 TDAFP SPEED CONTROL FAILURE I FWM3 MDAFP SUCTION LINE RUPTURES IN AUXILIARY BUILDING !
g 2 ATTACHMENT A
ATTACEMENT.A SIMULATOR MALFUNCTIONS MALF DESCRIPTION I FWM4 FWM5 FWM6' MDAFW FCV FAILURE CONDENSATE PUMP TRIP CONDENSATE PUMP MINI FLOW VALVE FAILURE TWM7 LOW PRESSURE HEATER BYPASS VALVE V903 FAILURE FWM8 LOW PRESSURE FEEDWATER HEATER TUBE LEAK FWM9 HEATER DRAIN TANK 1A CONDENSER DUMP VALVE V915A FAILURE FWM10 HEATER DRAIN PUMP TRIP FWM11 SGFP TRIP FWM12 SGFP.1A/1B FAILURE OF AUTO TRIP FWM13 SGFP TURBINE SPEED CONTROL FAILURE .
FWM14 SGFP 1B SPEED CONTROL OSCILLATES FWM15 FEEDWATER HEADER PRESSURE TRANSMITTFR PT-508 FAILURE FWM16 SGFP MINI FLOW VALVE FAILURE FWM17 FEEDLINE BREAK ON 1A SGFP DISCHARGE I FWM18 FWM19 HIGH PRESSURE FETrDWATER HEATER 6B TUBE LEAK FEEDLINE BREAK OUTSIDE CONTAINMENT IN COMMON FW HEADER
- FWM20 S/G B FEELINE BREAK OUTSIDE CONTAINMENT FROM FWCV l FWM21 S/G FEEDWATER CONTROL VALVE FAILURE FWM22 S/G LEVEL' CONTROLLER UNSTABLE FWM23 S/G FW CONTROL VALVE SEAT LEAKAGE FWM24 FW BYPASS-VALVE FAILURE FWM25 FEEDWATER FLOW TRANSMITTER FAILURE FWM26 S/G LEVEL CHANNEL FAILURE (PROTFCTION AND CONTROL)
FWM27 S/G C FEEDLINE BREAK OUTSIDE CNTMNT,DOWN FROM STOP CHECK I- FWM28 S/G FEEDLINE BREAK INSIDE CONTAINMENT MSS 1 STEAMLINE BREAK INSIDE CONTAINMENT I MSS 2 MSS 3 MSS 4 STEAMLINE BREAK OUTSIDE CONTAINMENT UPSTREAM OF MSIV STEAMLINE A SAFETY VALVE V010A FAILURE TO RESEAT MAIN STEAM ISOLATION VALVE CLOSES MSS 5 STEAMLINE PRESSUPE TRANSMITTER FAILURE gCONTROL AND PROT)
MSS 6 STEAMLINE PRESSURE TRANSMITTER: FAILURE (PROTECTION ONLY)
MSS 7- STEAMLINE FLOW TRANSMITTER FAILURE MSS 8 ATMOSPHERIC RELIEF VALVE CONTROL FAILURE MSS 9 MAIN STEAM HEADER BREAK MSS 10 STEAM DUMP-VALVES FAIL TO OPERATE IN T-AVE MODE MSS 11 STEAM HEADER PRESSURE CONTROLLER PT-464 FAILURE MSS 12 STEAM DUMP COOLDOWN VALVES CONTROL FAILURE; INTERLOCKS MSS 13 -STEAM DUMP BANK 3 VALVES CONTROL FAILURE MSS 14 STEAM DUMP VALVE STUCK NIS1 SOURCE RANGE CHANNEL FAILURE NIS2 SOURCE RANGE CHANNEL HIGH VOLTAGE FAILURE NIS3 SOURCE RANGE CHANNEL NOISY
- NIS4 SOURCE RANGE CHANNEL FAILURE TO DISCONNECT NISS SOURCE RANGE BLOWN FUSE l NIS6 INTERMEDIATE RANGE CHANNEL FAILURE NIS7 INTERMEDIATE RAriGE CHANNEL COMPENSATING VOLTAGE FAILURE
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SIMULATOR '
MALFUNCTIONS MALF DESCRIPTION NIS8 INTERMEDIATE RANGE BLOWN FUSE I- NIS9 NIS10 POWER RANGE CHANNEL DETECTOR FAILURE POWER RANGE CHANNEL FAILURE NIS11 POWER RANGE BLOWN FUSE PCS1 INADVERTENT REACTOR TRIP PCS2 INADVERTENT CONTA1NMENT ISOLATION I PCS3 PCS4 PCSS INADVERTENT SAFETY INJECTION ACTUATION REACTOR TRIP FAILURE (AUTO,MANNUAL, MECHANICAL)
SAFEGUARD ACTUATION AND CI FAILURE PCSG L AND N CONTROL SYSTEM POWER SUPPLY FAILURE
,I PCS7 PCSB PLANT COMPUTER FAILURE COMPUTER CRT FAILURE TO UPDATE PCS9 UNIT 2 SAFETY INJECTION PRS 1 PRESSURIZER STEAM SPACE BREAK PRS 2 PRESSURIZER SPRAY VALVE FAILURE E PRS 3 PRESSURIZER RELIEF VALVE FAILURE E PRS 4 PRESSURIZER RELIEF VALVE FAILS TO RESEAT AFTER OPEN PRS 5 PRESSURIZER SAFETY VALVE FAILURE PRS 6 PRESSURIZER SAFETY VALVE FAILS TO RESEAT AFTER OPENING PRS 7 PRESSURIZER PRESSURE MASTER CONTROLLER FAIIURE PRS 8 PRESSURIZER VARIABLE HEATER CONTROL FAILURE PRS 9 PRESSURIZER PRESSURE CHANNEL FAILURE (PROTECTION)
PRS 10 PRESSURIZER PRESSURE CHANNEL FAILURE (CONTROL)
PRS 11 PRESSURIZER LEVEL MASTER CONTROLLER FAILURE PRS 12 PRESSURIZER LEVEL CHANNEL FAILURE PRS 13 PRESSURIZER VAPOR SPACE TEMPERATURE CHANNEL TE-454 FAILURE RCS1 REACTOR COOLANT SYSTEM LEAK ig RCS2 LOCA g RCS3 REACTOR VESSEL FLANGE LEAK RCS4 STEAM GENERATOR TUBE LEAK RCSS REACTOR COOLANT PUMP TRIP RCS6 REACTOR COOLANT PUMP LOCKED ROTOR RCS7 VARIABLE RCS BORON CONCENTRATION RCS8 FUEL CLADDING FAIURE RCS9 CORE LOADING ERROR' RCS10 LOOP PROTECTION RTD FAILURE RCS11 LOOP CONTROL RTD FAILURE RCS12 RCS LOOP FLOW TRANSMITTER FAILURE RCS13 WIDE RANGE RCS PRESSURE CHANNEL FAILURE RHR1 RHR PUMP TRIP RHR2 RHR HX DISCHARGE VALVE FAILURE -
l RHR3- RHR HX BYPASS VALVE CONTROL FAILURE RHR4 RHR HX BYPASS LINE BREAK l RHR5 CONTAINMENT SUMP TO RHR PUMP SCREENS FOUL 4 ATTACHMENT A
ATTACHMENT h 8IMULATOR MALFUNCTIONS MALF DESCRIPTION RHR6 RHR PUMP SUCTION RELIEF VALVE FAILS RMS1 AREA RADIATION MONITOR FAILURE RMS2 PROCESS RADIATION MONITOR FAILURE RMS3 APD RADIATION MONITOR AIR FLOW FA'ILURE TUR1 INADVERTENT TURBINE TRIP TUR2 TURBINE PROTECTION TRIP FAILURE I- TUR3 GOVERNOR VALVE NUMBER OSCILLATION TUR4 TURBINE VIBRATION TUR5 TURBINE WATER INDUCTION I. TUR6 TUR7 LOSS OF EHC HYDRAULIC FLUID PUMP OPERATOR INPUT / OUTPUT FAILURE TUR8 DEHC SPEED SIGNAL LOST I TUR9 TUR10 TUR11 DEH FIRST STAGE PRESSURE TRANSMITTER FAILURE DEH MEGAWATT TRANSDUCER FAILURE TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILURE TUR12 MSR TEMPERATURE CONTROL FAILURE TUR13 MSR 1A RELIEF VALVE FAILURE TUR14 MSR 1B SECOND STAGE REHEATER TUBE LEAK TUR15 TURBINE INTERCEPT VALVE FAILURE TUR16 GENERATOR AUTO VOLTAGE REGULATOR FAILURE TUR17 GENERATOR HYDROGEN TEMPERATURE CONTROLLER FAILURE TUR18 TURBINE LOAD DEMAND FAILURE (LOAD REJECTION)
=
TUR19 GENERATOR WINDING PROGRESSIVE FAILURE TUR20 GENERATOR HYDROGEN LEAKAGE TUR21 ANALOG INPUT TO DEH OPC FAILURE I TUR22-TUR23 BEARING VIBRATION TRANSMITTER FAILURE FUNCTION KEY FAILURES I
I -
I s A m cuMENT A g
ATTACEMENT_B.1 SIMULATOR !
LOCAL OPERATOR ACTIONS ITEM DESCRIPTION I - '
ACIB1 SUPPLY BRKR TO SOLA TRANSFORMER G ACIB2 SUPPLY BRKR TO SOLA TRANSFORMER H ,
ACIB3 SERVICE WATER BATT CHARGERS 1/2 CONTROL ACIB4 SERVICE WATER BATT CHARGERS 3/4 CONTROL ;
ACIS1 120 VOLT VITAL BUS 1A SWITCH ACIS2 120 VOLT VITAL BUS 1B SWITCH ACIS3 120 VOLT VITAL BUS 1C SWITCH ACIS4 120 VOLT VITAL BUS 1D SWITCH ACISS XFER IPC TO ALT PWR SUPPLY AFWB1 PUMP-1A MDAFW PUMP SUPPLY BKR RACKOUT I AFWB2 AFWB3 PUMP-1B MDAFW PUMP SUPPLY BKR RACKOUT MOV-3350A AFW TO SG A STOP VALVE BKR RACKOUT AFWB4 MOV-3350B AFW TO SG B STOP VALVE BKR RACKOUT I AFWB5 AFWR1 AFWV1 MOV-3350C AFW TO SG C STOP VALVE BKR RACKOUT AUX FEED TURBINE OVERSPEED TRIP SIGNAL 4
V-015C&D AFW PUMP SUPPLY.XCONN FROM SERVICE WTR AFWV2 V-015A&B AFW PUMP SUPPLY FROM SERVICE WTR AFWV3 V-017D MDAFW SG-A FCV INLET ISO VLV l AFWV4- V-017E MDAFW SG-B FCV INLET ISO VLV ;
AFWV5 V-017F MDAFW SG-C FCV INLET ISO VLV AFWV6 V-017A TDAFW FCV INLET ISO TO A-SG AFWV7 V-017B TDAFW SG-B FCV INLET ISO VLV APWV8 V-017C TDAFW SG-C FCV INLET ISO VLV AFWV9 V-501 CST TO MDAPW PUMPS SUPPLY VALVE AFWV10 V-502 CST TO TDAFW PUMP SUPPLY VALVE AFWV11 V-004A MDAFP-A SUCTION VALVE I
'l sAFWV12 V-004B MDAFP-B SUCTION VALVE i
5 AFWV13 V-005 TDAFP SUCTION VALVE
- AFWV14 V-009A MDAFP-A MINIFLOW VALVE
- 3- AFWV15 V-009B MDAFP-B MINIFLOW VALVE g AFWV16 V-008 TDAFP MINIFLOW VALVE 1 AFWV17 V-021A AFW LOOP-A RECIRC VALVE TO CST L AFWV18 V-021B AFW LOOP-B RECIRC VALVE TO CST L
AFWV19 V-021C AFW LOOP-C RECIRC VALVE TO CST AIRS 1 EMERGENCY AIR COMPRESSORS AIRV1 V-001 CNMT-OC SERVICE AIR ISO VLV AIRV2 V-002 CNMT-IC SERVICE AIR ISO VLV L 'AIRV3 V-136A N2 TO PZR PORV'S (CYL-A)
AIRV4 V-136B N2 TO PZR PORV'S (CYL-B)
AIRV5 HV-2228 INST AIR /N2 TO PORV'S (PHASE-B)
AIRV6 V-901 SERVICE AIR ISO VLV AIRV7 V-094 ALTERNATE INSTRUMENT AIR TO PORV'S MALF AUX AIRV8 V-950 ESSENTIAL AIR TO OUTSIDE EQUIP. - MALF AUX 1 -
AIRV9 V-134 INST AIR TO PZR PORV (NORM)
AIRV10 V-903 ESSENTIAL INSTRUMENT AIR TO TURBINE BLDG AIRV11 V-560 UNIT-1/ UNIT-2 AIR SYSTEM CROSS CONNECT j 1 ATTACHMENT B.1
ATTACKMENT.B.1 SIMULATOR LOCAL OPERATOR ACTIONS 1
ITEM DESCRIPTION AIRV12 V-902 INSTRUMENT AIR DRYER BYPASS VALVE I AIRV13 AIRV14 V-904 NON-ESSENTIAL INSTRUMENT AIR TO SERVICE BLD HV-2935A EMER BREATHING AIR-CYL SUPPLY ISO AIRV15 HV-2935B EMER BREATHING AIR-SERV AIR ISO AIRV16 HV-2935C EMER BREATHING AIR-CNMT NON-ESS HDR ISO i
ASSV1 AUX BOILER LOAD VALVE ASSV2 AUX STEAM U1/U2 CROSS-CONNECT VALVE ASSZ1 AUX STM BOILER SUPER HEATER AUTO LEAK MALF !
ASSZ2 AUX STEAM UNIT 2 STATUS l BTRV1 TCV-381B BTRS REHEAT HX BYPASS VALVE BTRV2 TCV-381A BTRS REHEAT HX ISO VLV BTRV3 V-7028A BTRO CHILLER PUMP DISCHARGE VALVE BTRV4 V-7028B BTRS CHILLER PUMP DISCHARGE VALVE BTRV5 V-7051 BTRS CHILLER PUMP DISCHARGE X-CONN VALVE
. BTRZ1 BORON SATURATION RATIO - BTR DEMIN 1A BTRZ2 BORON SATURATICN RATIO - BTR DEMIN 1B BORON SATURATION RATIO - BTR DEMIN 1C BTRZ3 BTRZ4 BORON SATURATION RATIO - BTR DEMIN 1D BUSBl 800 PINCKARD TO S/U 1A BKR BUSB2 806 PINCKARD TO SWD BUS 2 BKR BUSB3 816 WE9B TO SWYD BUS 2 BKR I BUSB4 BUSB5 820 E.BAINBR TO S/U 1B BKR 826 E.BAINBR TO SWD BUS 2 BKR BUSB6 830 GA POOL TO S/U 2B BKR BUSB7 836-S/U 2B TO SWD BUS 2 BUSB8 904 S/U 1A TO SWYD BUS 1 BKR BUSB9 924 S/U 1B TOSWYD BUS 1 BKR
!g BUSB10 934 S/U 2A TO SWYD BUS 1 BKR
.3 BUSD1 909 S/U 1A HIGH SIDE DISC SW BUSD2 925 S/U 1B HIGH SIDE DISC SW BUSD3 937 S/U 2A HIGH SIDE DISC SW BUSD4 885 S/U 2B HIGH SIDE DISC SW BUSD5 935 AUTO XFMR BANK DISC SW BUSD6 915 MAIN XFMR DISC SW CCWB1 MOV-3031A RMW SUPPLY TO CCW SURGE TANK-A BKR RACKOUT CCWB2 MOV-3031B RMW SUPPLY TO CCW SURGE TANK-B BKR RACKOUT CCWD1 PUMP-B CCW PUMP TRAIN-A/B DISCONNECT CCWV1 V-034 CCW SEAL WATER HTX INLET ISO VLV CCWV2 V-031 CCW LETDOWN HTX INLET ISO VLV CCWV3 V-004A CCW HTX-1A INLET ISO VLV CCWV4 V-004B CCW INLET TO CCW HTX-1B -
CCWV5 V-004C CCW INLET VALVE TO CCW HTX-1C
ATTACHMENT.B.1 SIMULATOR LOCAL OPERATOR ACTIONS ITEM DESCRIPTION CCWV8 -V-008C CCW HX-1C OUTLET ISO VLV CCWV9 V-116 RMW/DEMIN WTR MAKEUP ISO TO CCW SURGE TK-A CCWV10 V-120 RMW/DEMIN WTR MAKEUP ISO TO CCW SURGE TK-B CCWV11 V-123 LETDOWN HX OUTLET TCV 3083 BYPASS VALVE I CCWV12 CCWV13 CCWV14 V-037 CCW SEAL WATER HTX OUTLET ISO VLV V-033A&B CCW LETDOWN HTX TCV-3083 ISO VLV V-076 CCW TO EXCESS HTX INLET ISO VLV CCWV15- V-079 CCW TO RCDT HTX INLET ISO VLV CCWV16 V-110A CCW RHR 1B-HTX/ PUMP COOLER RETURN ISO CCWV17 V-110F CCW TO RHR-1A HTX/ PUMP COOLER RETURN ISO CCWV18 V-045 DEMIN WATER SUPPLY TO CCW SURGE TANKS CCWV19 V-113A CCW TRAIN-A SURGE TANK DRAIN VALVE CCWV20 V-113B CCW TRAIN-B SURGE TANK DRAIN VALVE CCWV21 V-009A&B CCW HX 1A TO 1B OUTLET X-CONN VALVE I CCWV22 CCWV23 FCV-3009 CCW HX 1B OUTLET (JACKED OPEN AFTER RACKED V-003A&B CCW PUMP 1A TO 1B DISCH HDR X-CONN VALVE CCWV24 V-003C&D CCW PUMP-1C TO 1B DISCHARGE XCONN VALVE I CCWV25' CCWV26 CCWV27 V-144A CCW PUMP-1A MINIFLOW VALVE V-144B CCW PUMP-1B MINIFLOW VALVE V-144C CCW PUMP-1C MINIFLOW VALVE CCWV28 V-086A RCP A THERMAL BARRIER INLET VALVE CCWV29 V-086B RCP B THERMAL BARRIER INLET VALVE CCWV30 V-086C RCP C THERMAL BARRIER INLET VALVE CCWV31 V-091A RCP A THERMAL BARRIER OUTLET ISO VLV I CCWV32
-CCWV33 CCWV34 V-091B RCP B THERMAL BARRIER OUTLET ISO VLV V-091C RCP C THERMAL BARRIER OUTLET ISO VLV V-085A RCP A THERMAL BARRIER / OIL COOLER INLET CCWV35 V-085B RCP B THERMAL BARRIER OIL COOLER INLET CCWV36 V-085C RCP C THERMAL BARRIER / OIL COOLER INLET CCWV37 V-088A/89A RCP A OIL COOLER INLET VALVES CCWV38 V-088B/89B RCP B OIL COOLER INLET VALVES I- CCWV39 CCWV40 V-088C/89C RCP C GIL' COOLER INLET VALVPS V-065 CCW TO RECYCLE EVAP CONDENSER INLE'1 CCWV41 V-066 CCW TO RECYCLE EVAP VENT CONDENSER INLET CCWV42 V-067 CCW TO RECYCLE EVAP DIST COOLER INLL"r CCWV43 V-075 CCW RECYCLE EVAP CONDENSER / COOLER INLET ISO CCWV44 V-059 CCW WASTE EVAP CONDENSER / COOLER INLET ISO I CCWV45 CCWV46 CCWV47 V-048 CCW TO WASTE EVAP CONDENSER INLET ISO V-049 CCW TO WASTE EVAP VENT CONDENSER INLET ISO V-050 CCW TO WASTE EVAP DIST COOLER INLET VALVE CCWV48 V-038A&B CCW TO HYDROGEN RECOMBINER A/B INLET VALVE CCWV49 V-043A&B CCW TO WASTE GAS COMPRESSOR A/B INLET ISO CCWV50 V-023A&B CCW TRAIN-A SUPPLY TO CHG PUMP-1B SEAL HTX CCWVS1 V-023C&D CCW TRAIN-B SUPPLY TO CHG PUMP-1B SEAL HTX I- CCWVS2 CCWV53 V-024A&B CCW TRAIN-A RETURN FROM CHG PUMP-1B SEAL HT V-024C&D CCW TRAIN-B RETURN FROM CHG PUMP-1B SEAL HT CCWV54 V-137A CCW TO CHARGING PUMP-A COOLERS CCWV55 V-137B CCW TO CHARGING PUMP-B COOLERS 3 ATTACHMENT B.1
@}lCKMENT B.1 SIMULATOR LOCAL OPERATOR ACTIONS ITEM _
DESCRIPTION ,
V-137C CCW TO CHARGING PUMP-C COOLERS I CCWV56 CCWV57 CCWV58 V-023A&B CCW TRAIN XCONN TO CHARGING PUMP COOLERS V-3404A CCW SUPPLY TO RHR PUMP-A OIL COOLER CCWV59 V-009C&D CCW HX IC TO 1B OUTLET X-CONN VALVE CCWV60 V-3404B CCW SUPPLY TO RHR PUMP-B OIL COOLER CCWV61 V-110B&C CCW PUMP 1A TO 1B INLET X-CONN VALVE CCWV62 V-110D&E CCW PUMP 1C TO 1B INLET X-CONN VALVE CCWV63 HV-2229 CCW SUPPLY VALVE TO SAMPLE COOLERS CHGB1 PUMP-1A CHARGING PUMP SUPPLY BKR RACKOUT I CHGB2 CHGB3 CHGB4 PUMP-1B CHARGIMG PUMP TRAIN-A BKR RACKOUT PUMP-1B CHARGING PUMP TRAIN-B BKR RACKOUT PUMP-1C CHARGING PUMP SUPPLY BKR RACKOUT CHGD1 PUMP-1B CHARGING PUMP DISCONNECT CHGD2 PUMP-3282 SUMP PUMP DISCONNECT CHGD3 MOV-8130A CHG PUMP SUCTION HDR XCONN DISCONNECT CHGD4 MOV-8130B CHG PUMP SUCTION HDR XCONN DISCONNECT CHGD5 MOV-8131A CHG PUMP SUCTION HDR XCONN DISCONNECT CHGD6 MOV-8131B CHG PUMP SUCTION HD XCONH DISCONNECT CHGD7 MOV-8132A CHG PUMP DISCH HDR X-CONN BKR RACKOUT I ,
CHGD8 CHGD9 CHGD10 MOV-8132B CHG PUMP DISCH HDR X-CONN BKR RACKOUT MOV-8133A CHG PUMP DISCH HDR XCONN DISCONNECT MOV-8133B CHG PUMP DISCH HDR XCONN DISCONNECT
- CHGD11 MOV-8886 TRAIN-A CHG PMP TO RCS HL ISO BKR RACKOUT CHGD12 MOV-8884 TRAIN-B CHG PMP TO RCS HL ISO BRK RACKOUT CIRB1 PUMP-1A CIPC WATER PUMP SUPPLY BKR RACKOUT I CIRB2 CIRV1 CIRV2 PUMP-1B CIRC WATER PUMP SUPPLY BKR RACKOUT V-501A CIRC WATER OUTLET VALVE CONDENSER-1 V-501B CIRC WATER OUTL2T VALVE CONDENSER-2 l
l CIRV3 V-502A CIRC WATER OUTLET VALVE CONDENSER-1 CIRV4 V-502B CIRC WATER OUTLET VALVE CONDENSER-2 CIRV5 V-503A CIR WATER INLET VALVE CONDENSER-1 l
'g CIRV6 V-503B CIR WATER INLET VALVE CONDENSER-2 g CIRV7 V-504 A CIR WAIER INLET VALVE CONDENSER-A CIRV8 V-504B CIRC WATER INLET VALVE CONDENSER-2 CIRV9 V-506A COOLING TOWER-A CIRC WATER ISO VLV CIRV10 V-506B COOLING TOWER-B CIRC WATER ISO VLV CIRV11 V-506C COOLING TOWER-C CIRC WATER ISO VLV CIRV12 V-554A COOLING TOWER-A CIR WATER BYPASS VLV CIRV13 V-554B COOLING TOWER-B CIR WATER BYPASS VLV I- CIRV14 V-554C COOLING TOWER-C CIR WATER BYPASS VLV CIRV15 V-586 COOLING TOWER BLOWDOWN ISO VLV CNDB1 PUMP-1A CONDENSATE PUMP SUPPLY BKR RACKOUT -
CNDB2 PUMP-1B CONDENSATE PUMP SUPPLY BKR RACKOUT CNDB3 PUMP-1C CONDENSATE PUMP SUPPLY BKR RACKOUT CNDV1 V-516A CONDENSATE PUMP-A DISCHARGE VALVE 4 ATTACHMENT B.1
ATTACEMENT B.1
- SIMULATOR LOCAL OPERATOR ACTIONS ITEM DESCRIPTION V-516B CONDENSATE PUMP-B DISCHARGE VALVE I CNDV2 CNDV3 CNDV4 V-516C CONDENSATE PUMP-C DISCHARGE VALVE HOTWELL DUMP VALVE TO RIVER CNDV5 HOTWELL DUMP TO CST I CNDV6 CNDV7 CNDV8 V-505 CST CONTROL VLV - FILL VALVE V-506 INLET TO CST - FILL VALVE V-507 OUTLET FROM CST I CNDV9 CNDV10 CNDV11 V-501 RMWST CONTROL VALVE - FILL VALVE
.V-511 OUTLET FROM RMWST V-512 INLET TO RMWST - FILL VALVE CNDV12 V-539 BYPASS TO DWST VALVE I- CNDV13 CNDV14 CONDENSER VACUUM BREAKER MANUAL ISO VLVS HOGGER MANUAL ISO VLVS CNDV15 V-903 LOSS OF LOAD VALVE STATUS CNDV16- V-531A CONDENSATE FROM SJAE-A CNDV17 V-531B CONDENSATE FROM SJAE-B CNDV18 V-518A LP HTR 1A-2A COND INLET ISO VLV CNDV19 V-520A LP HTR 1A-2A COND OUTLET ISO VLV I- CNDV20 V-519A LP HTR 1A-2A COND BYPASS VALVE CNDV21 V-521B LP HTR 3B-4B COND INLET ISO V-523B LP HTR 3B-4B COND OUTLET ISO VLV I CNDV22 CNDV23 CNDV24-V-522B LP HTR 3B-4B COND BYPASS VALVE V-524A LP HTR SA COND INLET ISO VLV CNDV25 V-525A LP HTR SA COND OUTLET ISO VLV CNDV26 V-529A LP HTR SA COND BYPASS VALVE
'2iMZ1 CNMT LEAK WITH RADIATION DETECTION CNMZ2 CNMT LEAK WITHOUT RADIATION DETECTION CNSBl PUMP-1A CNMT SPRAY PUMP SUPPLY BKR RACKOUT CNSB2 PUMP-1B CNMT SPRAY PUMP SUPPLY BKR RACKOUT I CNSV1 CNSV2 CNSV3 V-8831 CNMT SPRAY. ADDITIVE TANK DRAIN VALVE V-8833 CNMT SPRAY ADDITIVE TANK OUTLET VALVE CNMT SPRAY ADDITIVE TANK FILL VALVE CN3V4 V-8824A CNMT SPRAY PUMP-1A TO RWST TEST LINE I ChSV5 CNSV6 V-8824B CNMT SPRAY PUMP-1B TO RWST TEST LINE V-8825 CNMT SPRAY TO RWST TEST LINE ISO CNSV7 V-8828 RWST/ EDUCTOR TEST LINE ISO CRFA1 MANUAL ROD SPEED FOR CONTROL BANKS CRFA2 ROD BANK OVERLAP COUNTER CONTROL BANK ',A' P/A CONVERTER (WITH CRF14)
I CRFA3 CRFA4 CRFA5 CONTROL BANK 'A' P/A CONVERTER (WITH CRF13)
CONTROL BANK 'B' P/A CONVERTER (WITH CRF16)
CRFA6 CONTROL BANK 'B' P/A CONVERTER (WITH CRF15)
I CRFA7 CRFA8.
CONTROL BANK 'C' P/A CONVERTER (WITH CRF18)
CONTROL BANK 'C' P/A CONVERTER (WITH CRF17)
CRFA9 CONTROL BANK 'D' P/A CONVERTER (WITH CRF20)
CRFA10 CONTROL BANK 'D' P/A CONVERTER (WITH CRF19) 5 ATTACHMENT B.1
4 ATTACHMENT _Bi1 SIMULATOR.
LOCAL OPERATOR ACTIONS ITEM DESCRIPTION I- .._n Chia 11 DETECTOR BOTTOM CORE LIMIT CRFA12 DETECTOR TOP CORE LIMIT CRFA13 CALIBRATE BOTTOM CORE LIMIT CRFA14 CALIBRATE TOP CORE LIMIT CRFA15 I. CRFA16 CG/E/S BOTTOM CORE LIMIT CG/E/S TOP COREIMIT CRFB1 BYPASS-A' REACTOR TRIP BYPASS BREAKER CRFB2 BYPASS-B REACTOR TRIP BYPASS BREAKER CRFB3 MG SET-B SUPPLY BREAKER CRFB4 MG SET-A SUPPLY BREAKER CRFS1 DRPI ALTERNATE POWER SUPPLY SWITCH I CRFZ1 CRFZ2 P/A CONVERTOR DISABLE MASTER CYCLER P0 SIGNAL: GRP 1 NEXT TO MOVE CRFZ3 MASTER CYCLER P+ SIGNAL: GRP 2 NEXT TO MOVE CVCA1 PCV-8155 VCT N2 6UPPLY REGULATOR SETPOINT '
CVCA2 V-8156 VCT H2 SUPPLY REGULATOR SETPOINT
.CVCA3 V-8157 VCT HI PRESSURE VENT REGULATOR SETPOINT CVCA4 PCV-7800 VCT PURGE PRESSURE REGULATOR SETPOINT CVCB1 MOV-8105 SEAL WATER INJ ISO BKR RACKOUT CVCP1 PUMP-1A BRS PUMP 1 SPEED RE-FEED PUMP 1A I ,
CVCP2 CVCV1 PUMP-1B BRS PUMP 2 SPEED RE-FEED PUMP 1B V-8403 FCV-122. MANUAL BYPASS VALVE CVCV2 V-8402B FCV-122 INLET ISO VLV CVCV3 V-8408A PCV 145 INLET ISO VLV
SISM1 MOV-8801A BIT DISCHARGE ISOLATION VALVE SISM2 MOV-8801B BIT DISCHARGE ISOLATION VALVE SISM3 MOV-8803A BIT INLET ISOLATION VALVE SISM4 MOV-8803B BIT INLET ISOLATION VALVE SMPA1 HV-3103 PRZR LIQUID SAMPLE ISOLATION VALVE SMPA2 HV-3332 PRZR LIQUID SAMPLE ISOLATION VALVE SMPA3 HV-3104 PRZR STEAM SAMPLE ISOLATION VALVE SMPA4 HV-3331 DRZR STEAM SAMPLE ISOLAITON VALVE I SMPA5 SMPA6 HV-3765 RCS LOOP 2 &3 SAMPLE ISOLATION VALVE HV-3333 RCS LOOP 2&3 SAMPLE ISOLATION VALVE SMPA7 HV-3334 ACCUMULATOR SAMPLE ISOLATION VALVE SMPA8 HV-3766 ACCUMULATOR SAMPLE ISOLATION VALVE SMPA9 HV-3328 SG-1A BLOWDOWN SAMPLE ISOLATION VALVE SMPA10 HV-3329 SG-1B BLOWDOWN SAMPLE ISOLATION VALVE SMPAll HV-3330 SG-1C BLOWDOWN SAMPLE ISOLATION VALVE SVWM1 MOV-3024A EMERGENCY SVC WTR FROM CNMT CLR-1A SVWM2 MOV-3024B EMERGENCY SVC WTR FROM CNMT CLR-1B I SVWM3 SVWM4 MOV-3024C SVC WTR PROM CNMT COOLERS MOV-3024D SVC WTR FROM CNMT COOLERS SVWM5 MOV-3019A SVC WTR TO CNMT CLR-1A SVWM6 MOV-3019B SVC WTR TO CNMT CLR-1B SVWM7 MOV-3019C SVC WTR TO CNMT COOLERS SVWM8 MOV-3019D SVC WTR TO CNMT COOLERS SVWM9 MOV-3441A SVC WTR FROM CNMT CLR-1A.
SVWM10 MOV-3441B SVC WTR FROM CNMT CLR-1B SVWM11 MOV-3441C SVC WTR FROM CNMT CLR-1C SVWM12 MOV-3441D SVC WTR FROM CNMT CLR-1D SVWM13 MOV-3131 SVC WTR FROM RCP MOTOR AIR COOLER SVWM14 MOV-3149 SVC WTR TO FLDN HTX & BTRS CHILLERS l SVWM15 MOV-3150 SVC WTR TO BLDN HTX & BTRS CH;LLERS l SVWM16 MOV-3134 SVC WTR FROM RCP MOTOR AIR COOLERS SVWM17 MOV-3135 SVC WTR TO RCP MOTOR AIR COOLERS SVWP1 SERVICE WATER PUMP 1A SERVICE WATER PUMP 1B I SVWP2 SVWP3 SVWP4 SERVICE WATER PUMP 1C TRAIN-A SERVICE WATER PUMP 1C TRAIN-B SVWP5 SERVICE WATER PUMP 1D SVWP6 SERVICE WATER PUMP 1E -
5 ATTACHMENT B.2
l l
AT.TAMMENT B(1 1
SIMULATOR COMPONENT FAILURE 8 ITEM
^
DESCRIPTION I i
- 3 WPSA1 LWP-HV-7126 RCDT VENT LINE ISOLATION VALVE
' B WPSA2 LWP-HV-7136 RCDT PUMPS DISCRARGE LINE ISO VALVE WPSA3 LWP-HV-7150 RCDT VENT LINE ISOLATION VALVE l I
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4 I
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e A m c-EsT e.2 y
ATTACEMENT.B.3 SIMULATOR BISTABLE OVERRIDES ITEM DESCRIPTION B1012 PB951B1 CNMT PRESSURE HI-1 CH 2 B1013 PB952B1 CNMT PRESSURE HI-1 CH 3 B1014 PB953B1 CNMT PRESSURE HI-1 CH 4 B1022 PB951B2 CNMT PRESSURE HI-2 CH 2 I B1023 B1024 B1031 PB952B2 CNMT PRESSURE HI-2 CH 3 PB953B2 CNMT PRESSURE HI-2 CH 4 PB950A CNMT PRESSURE HI-3 CH 1 I B1032 B1034 B1081 PB951A CNMT PRESSURE HI-3 CH 2 PB953A CNMT PRESSURE HI-3 CH 4 TB412C2 OTDT ROD STOP LOOP 1 B1082 TB422C2 OTDT ROD STOP LOOP 2 I B1083 B1091 TB432C2 OTDT ROD STOP LOOP 3 TB412B2 OPDT ROD STOP LOOP 1 B1092 TB422B2 OPDT ROD STOP LOOP 2 B1093 TB432B2 OPDT ROD STOP LOOP 3 B2011 RCP-1 UV UNDERVOLTAGE RELAY TRIP I B2012 B2013 B2021 RCP-2 UV UNDERVOLTAGE RELAY TRIP RCP-3 UV UNDERVOLTAGE RELAY TRIP RCP-1 UF UNDCRFREQUENCY RELAY TRIP B2022 I B2023 B2041 RCP-2 UP UNDIRPREQUENCY RELAY TRIP RCP-3 UP UNDERPREQUENCY RELAY TRIP FB414A RCS LOW FLOW LOOP 1 CH 1 B2042 F8415A RCS LOW FLOW LOOP 1 CH 2 I B2043 B2051 B2052 FB416A RCS ICW FLOW LOOP 1 CH 3 FB424A RCS LOW FLOW LOOP 2 CH 1 FB425A RCS LOW FLOW LOOP 2 CH 2 B2053 F426A RCC LOW FLOW LOOP 2 CH 3 B2061 FB434A RCS LOW FLOW LOOP 3 CH 1 B2062 FB435A RCS ICW FLOW LOOP 3 CH 2
'3 B2063 FB436A RCS LOW FLOW LOOP 3 CH 3 g B2071 TB412C1 RCS OVERTEMP DELTA T LOOP 1 B2072 TB422C1 RCO OVERTEMP DELTA T LOOP 2 P2073 TB432C1 RCS OVERTEMP DELTA T LOOP 3 B2081 TB412B1 RCS OVERPOWER DELTA T LOOP 1 i B2082 TB422B1 RCS OVERPOWER DELTA T LOOP 2 l B2083 TB432B1 RCS OVERPOWER DELTA T LOOP 3 i B2091 TB41201 RCS LOW TAVG LOOP 1 B2092 TB422D1 RCS LOW TAVG LOOP 2 B2093 TB432D1 RCS LOW TAVG LOOP 3 B2101 TB412E RCS LO-LO TAVG LOOP 1, I. B2102 TB422E RCS LO-LO TAVG LOOP 2 B2103 TB432E RCS LO-LO TAVG LOOP 3 B2111 NC41R PR REACTOR TRIP HIGH STPT CH 41 I B2112 B2113 NC42R PR RE'CTOR TRIP HIGH STPT CH 42 NC43R PR RE,.CTOR TRIP HIGH STPT CH 43 B2114 NC44R PR REACTOR TRIP HIGH STPT CH 44 B2121 NC41K PR REACTOR TRIP RATE NEGATIVE CH 41 1 ATTACHMENT B.3
VfTACEMENT 3.3 SINULATOR B25 TABLE OVERRIDES 1 TEN l ,
DESCRIPTION NC42K PR REACTOR TRIP RATE NEGATIVE Cil 42 I B2122 B2123 B2124 NC43K PR REACTOR TRIP RATE HEGATIVE CH 43 NC44K PR REACTOR TRIP RATE NEGATIVE CII 44 B2171 PB455D PZR LOW P2 ESSURE SI Cil 1 B2172 PB456D PZR LOW PRESSURE SI CH 2 B2173 PB457D PZR LOW PRESSVRE SI Cl! 3 B2181 LB459A PZR IIIGli NAT!3 LEVEL Clll I B2182 B2183 B2201 LB460A PZR HIGli NATER LEVEL CH 2 LB461A PZR IIIGH WATER LEVEL CII 3 PB455C PZR LOW PRESSURE REACTOR TRIP Cil 1 I B2192 d2193 B2201 PB456C PZR LOW PRESSURE REACTOR TRIP Cl! 2 PB457C PZR LOW PRESSURE REACTOR TRIP CH 3 PB455A PZR HIGH :?RESSURE CH 1 B2202 PB456A PZR llIGil PRESSURE Cil 2 B2203 PB457A PZR llIGH PRESSURE Cl! 3 B3011 NC31D SR REACTOR TRIP CII 31 I B3012 B3021 B3022 NC32D SR REACTOR TRIP Cll 32 NC35F IR REACTOR TRIP Cli 35 NC36F IR REACTOR TRIP Cl! 36 I B3031 B3032 B3041 ,
Nc35D NIS IR.P-6 CH 35 NC36D NIS IR P-6 C1 36 NC41N NIS PR P-8 Cll 41 B3042 NC42N NIS*PR P-8 CH 42
.I B3043 B3044 NC43N NIS PR P-8 CH 43 NC44N NIS PR P-8 CH 44 B3051 NC41M NIS PR P-10 CH 41
. B3052 NC42M NIS PR P-10 CH 42 B3053 NC43M NIS PR P-10 Cll 43 B30B4 NC44M NIS PR P-10 Cil 44 I B3062 B3063 B3064 NC42P PR REACTOR TRIP LOW STPT CH 42 NC43P PE REACTOR TRIP LOW STPT CH 43 NC44P PR REACTOR TRIP LOW STPT Cl! 44 B3071 PB455B P-11 CH 1 B3072 PB456B P-11 CH 2 B3073 PB457B P-11 CH 3 B3083 PB446Al TUR IMP CH PRESS a 10% F.P. CH 3 I B3084 B3091 B3092 PB447El TUR IMP CH PRESS > 10% F.P. Cil 4 NC41S NIS PR P-9 CH 41 NC42S NIS PR P-9 CH 42 I B3093 B3094 NC43S NIS PR P-9 CH 43 NC44S NIS PR P-9 CH 44 B4011 LB474B LOOP 1 LOW WTR LEV Cl! 1 I B4012 B4013 LB475B LOOP 1 LOW WTR LEV CH 2 FB478B LP1 STM/FDW MISMATCH LOW FDW FLOW Cll 3 B4014 FB478A LP1 STM/FDW MISMATCli LOW FDW FLOW CH 4 B4021 LB484B LOOP 2 LOW WTR LEV CH 1 2 ATTACIIMENT B. 3
ATTACEMENT...R t3 ,
SINULATOR BISTABLE OVERRIDES ITEM DESCRIPTION I m B4022 LB485B LOOP 2 LOW WTR LEV Cl! 2 I B4023 B4024 FB488B IS2 STM/FDW MISMATCH LOW FDW FLOW CH 3 FB488A LP2 STM/FDW MISMATCH LOW FDW FLOW Cl! 4 B4031 LB494B LOOP 3 LOW WTR LEV CH 1 I B4032 B4033 B4034 LB495B LOOP 3 LOW WTR LEV Cl! 2 FB498B LP3 STM/FDW MISMATCH LOW FDW FLOW CH 3 FB498A LP3 STM/FDW MISMATCH LOW FDW FLOW Cll 4 I B4041 B4042 B4043 LB474A S/G 1 LO-LO WTR LEV Cl! 1 LB475A S/G 1 LO-LO- WTR LEV Cil 2 LB476A S/G 1 LO-LO- WTR LEV CH 3 B4051 LB484A S/G 2 LO-LO WTR LEV Cl! 1 B4052 LB485A S/G 2 LO-LO WTR LEV CII 2 B4053 LB486A S/G 2 LO-LO WTR LEV CH 3 B4061 LB494 A S/G 3 LO-LO WTR LEV Cl! 1 I B4063 B4071 B4072 LB496A S/G 3 LO-LO WTR LEV CH 3 LB474C S/G 1 HI-HI LEV Cl! 1 LB475C S/G 1 HI-HI LEV CH 2 I B4073 B4081 B4082 LB4760 S/G 1 HI-ill WTR LEV Cll 3 LB484C S/G 2 HI-III LEV C11 1 LB485C S/G 2 HI-HI LEV Cl! 2 B4083 LB486C S/G 2 HI-HI LEV CH 3 I B4091 B4092 LB494C S/G 3 HI-HI LEV CH 1 LB495C S/G 3 HI-HI LEV CH 2 B4093 LB496C S/G 3 HI-l!I LEV Cll 3 I B4102 B4103 B4104 PB474B2 P1-P2 HIGli STEAM LINE DIFF PRESSURE Cl! 2 PB475B3 P1-P2 HIGH STEAM LINE DIFF PRESSURE Cli 3 PB476B2 P1-P2 HIGli STEAM LINE DIFF PRESSURE CH 4 B4112 PB494B2 P1-P3 HIGH STEAM LINE DIFF PRESSURE Cl! 2 B4113 PB495B2 P1-P3 HIGli STEAM LINE DIFF PRESSURE Cl! 3 B4114 PB496B2 P1-P3 HIGli STEAM HINE DIFF PRESSURE CH 4 B4122 PB474B1 P1-P2 HIGH STEAM IINE DIFF PRESSURE Cl! 2 I B4123 B4124 PB475B1 P1-P2 HIGH STEAM lINE DIFF PRESSURE Cll 3 PB476B1 P1-P2 HIGH STEAM LINE DIFF PRESSURE CH 4 B4132 PB484B2 P2-P3 HIGH STEAM LINE DIFF PRESSURE CH 2 B4133 PB485B2 P2-P3 HIGH STEAM LINE DIFF PRESSURE CH 3 l B4134 PB486B2 P2-P3 HIGli STEAM IINE DIFF PRESSURE CII 4 B4142 PB484B1 P2-P3 HIGli STEAM LINE DIFF PRESSURE CH 2
.g B4143 PB485B1 P2-P3 HIGH STEAM LINE DIFF PRESSURE CH 3 l5 B4144 PB486B1 P2-P3 !!IGH STEAM LINE DIFF PRESSURE Cl! 4 i B4152 PB494B1 P1-P3 HIGH STEAM LINE DIFF PRESSURE CH 2 i B4153 PB495B1 P1-P3 HIGH STEAM LINE DIFF PRESSURE CH 3
( B4154 PB496B1 P1-P3 HIGH STEAM LINE DIFF PRESSURE CH 4 B4163 FB474A LP1-HIGH STEAM LINE FLOW CH 3 B4164 FB475A LP1 HIGH STEAM LINE FLOW CH 4
- I B4173 B4174 FB484A LP2 HIGGli STEAM LINE FLOW CH 3 FB485A LP2 !!IGli STEAM LINE FLOW CH 4 B4183 FB494A LP3 HIGH ETEAM LINE FLOW CH 3 B4184 FB495A LP3 HIGli STEAM LINE FLOW CH 4 I 3 ATTACHMENT B.3
l ATTACHMENT _B13 SIMULATOR ,
BIRTABLE OVERRIDES ITEM DESCRIPTION B4192 PB474A LOOP 1 LOW STEAM LINE PRESSURE I B4193 B4194 PB485A LOOP 2 LOW STEAM LINE PRESSURE PB496A LOOP 3 LOW STEAM LINE PRESSURE F4141 FB414A RCS LOW FLOW LOOP 1 CH 1 F4152 FB415A RCS LOW FLOW LOOP 1 Cl! 2 F4163 FB416A RCS LOW FLOW LOOP 1 CH 3
'g F4241 FB424A RCS LOW FLOW LOOP 2 Cl! 1 W F4252 FB425A RCS LOW FLOW LOOP 2 011 2 F4263 FB426A RCS LOW FLOW LOOP 2 Cil 3 .
F4341 FB434A RCS LOW FLOW LOOP 3 Cil 1 I F4351 F4361 FB435A RCS LOW TLOW ICOP 3 CH 2 FB436A RCS LOW FLOW LOOP 3 CH 3 F4741 FB474A LP1 HIGH STEAM LINE FLOW CH 3 I F4751 F4781 F4782 FB475A LP1 HIGli STEAM LINE FLOW Cl! 4 FB478A LP1 STM/FDW MISMATCH LOW FDW FLOW Cl! 4 FB478B LP1 STM/FDW MISMATCH LOW FDW FLOW CH 3 I F4783 F4784 F4841 FB478C SG1 STM/FDW MISMATCil:FDW>STM PROT CllAN 3 FB478D SG1 STM/FDW MISMATCH STM>FDW PROT CHAN 4 FB484A LP2 HIGH STEAM LINE FLOW CH 3 F4851 FB485A LP2 !!IGH STEAM LINE FLOW CH 4 I F4881 F4882
F4883 FB488C SG2 STM/FDW MISMATClit FDW>STM PROT CIIAN 3 L I F4941 F4951 F4981 PB494A LP3 HIGH STEAM LINE FLOW Cl! 3 FB495A LP3 HIGH STEAM LINE FLOW CH 4 FB498A LP3 STM/FDW MISMATCH LCW FDW FLOW Cil 4 E F4982 FD498B LP3 STM/FDW MISMATCH 1CW FDW FLOW Cll 3 E F4983 FB498C SG3 STM/FDW MISMATCH FDW>STM PROT CHAN 3 F4984 FB498D SG3 STM/FDW MISMATCH STM>FDW PROT Cl!AN 4 L L4591 LB459A PZR HIGli WATER LEVEL CH1 L4592 LB459C LOW PRZR LEV, BLKS !!TRS & LCV 459 L4593 LB459D HIGli DEV PZR LEV /BU HTRS ON L4594 LB459E LOW LEVEL DEVIATION L4601 LB460A PZR HIGH WATER LEVEL CH 2 l L4602 LB460C1 HIGH PZR LEVEL l L4603 LB460C2 LOW PRZR LEV, BLKS HTRS & LCV 460 L4611 LB461A PZR HIGH WATER LEVEL CH 3 l L4741 LB474A S/G 1 LO-LO WTR LEV Cll 1 lg L4742 LB474B LOOP 1 LOW WTR LEV CH 1
'g L4743 LB474C S/G 1 HI-HI LEV Cl! 1 L4751 LB475A S/G 1 LO-LO- WTR LEV CH 2 L4752 LB475B LOOP 1 LOW WTR LEV CH 2L l L4761 LB476A S/G 1 LO-LO- WTR LEV CH 3 -
L4762 LB476C S/G 1 HI-III WTR LEV CH 3 L4781 LB478D1 SG1 LOW LEVEL DEVIATION L4782 LB478D2 SG1 HIGH LEVEL DEVIATION O
ATTACEMENT B.3 SIMULATOR BISTABLE OVERRIDES ITEM DESCRIPTION L4841 LB484A S/G 2 LO-LO WTR LEV Cl! 1 L4842 LB484B LOOP 2 LOW WTR LEV CH 1 L4843 LB484C S/G 2 HI-HI LEV CH 1 L4851 LB485A S/G 2 LO-LO WTR LEV Cl! 2 I L4852 14853 L4861 LB485B LOOP 2 LOW WTR LEV CH 2 LB485C S/G 2 III-HI LEV CH 2 LB486A S/G 2 LO-Lo WTR LEV Cll 3 e
L4862 I L4881 L4882 LB486C S/G 2 HI-HI LEV Cli 3 LB488D1 SG2 LOW LEVEL DEVIATION LB488D2 SGR HIGH LEVEL DEVIATION L4941 LB494A S/G 3 LO-LO WTR LEV Cli 1 L4942 LB494B LOOP 3 LOW WTR LEV Cl! 1 L4943 LB494C S/G 3 HI-l!I LEV CH 1 L4951 LB495A S/G 3 LO-Lo WTR LEV Cl! 2 I L4952 L4953 L4961 LB495B LOOP 3 LOW WTR LEV CH 2 LB495C S/G 3 !!I-HI LEV Cli 2 LB496A S/G 3 LO-Lo WTR LEV Cl! 3 -
I L4962 L4981 L4982 LB496C S/G 3 III-HI LEV CH 3 LB498D1 SG3 LOW LEVEL DEVIATION LB498D2 SG3 HIGH LEVEL DEVIATION NI311 NC31D SR REACTOR TRIP Cil 31 NI321 NC32D SR REACTOR TRIP Cl! 32 ,
HI351 NC35F IR REACTOR TRIP CH 35 I NI352 NI353 NI361 NC35E IR HIGH FLUX ROD STOP Cl! 35 NC35D NIS IR P-6 CH 35 Nc36F IR REACTOR TRIP CH 36 I NI362 NI363 NI411 NC36E IR HIGli FLUX ROD STOP CH 36 NC36D NIS IR P-6 CH 36 NC41R PR REACTOR TRIP HIGH STPT CH 41 NI412 NC41P PR REACTOR TRIP LOW STPT CH 41 NI413 NC41L IR HIGH FLUX ROD STOP CH 41 NI414 NC41K PR REACTOR TRIP RATE NEGATIVE Cil 41 NI415 NC41U PR REACTOR TRIP RATE POSITIVE CH 41 I NI416 NI417 NI418 NC41N NIS PR P-8 CH 41 NC41S NIS PR P-9 CH 41 NC41M N1S PR P-10 CH 41 I NI421 NI422 NI423 NC42R PR REACTOR TRIP !!IGli STPT CH 42 NC42P PR REACTOR TRIP LOW STPT CH 42 NC42L IR HIGH FLUX ROD STOP CH 42 NI424 I NI425 NI426 NC42K PR REACTOR TRIP RATE NEGATIVE CH 42 NC42U PR REACTOR TRIP RATE POSITIVE CH 42 NC42N NIS PR P-8 Cl! 42 NI427 NC42S NIS PR P-9 CH 42 I NI428 NI431 NI432 NC42M NIS PR P-10 CH 42 NC43R PR REACTOR TRIP llIGH STPT CH 43 NC43P PR REACTOR TRIP LOW STPT CH 43 NI433 NC43L IR !!IGH FLUX ROSD STOP CH 43 5 ATTAcHsENT e.3 g
hTTACEMENT_B 3
, SIMULATOR BISTABLE OVERRIDE 8 l ITEM DESCRIPTION NI434 NC43K PR REACTOR TRIP RATE NEGATIVE CH 43 NI435 NC43U PD REACTOR TRIP RATE POSITIVE CH 43 NI436 N?t3N HIS PR P-8 CH 43 NI437 NC43S NIS PR P-9 CH 43 I NI438 NI441 NI442 NC43M NIS PR P-10 CH 43 NC44R PR REACTOR TRIP HIGH STPT CH 44 NC44P PR REACTOR TRIP LOW STPT CH 44 NI443 NC44L IR HIGH FLUX ROD STOP CH 44 I NI444 NI445 NC44K PR REACTOR TRIP RATE NEGATIVE CH 44 NC44U PR REACTOR TRIP RATE POSITIVE CH 44 NI446 NC44N NIS PR P-8 CH 44
- NI447 NC44S NIS PR P-9 CH 44 NI448 NC44M MIS PR P10 CH 44 I P4441 P4442 P4443 PB444F LOW DEV, PRZR PRESS /BU HTRS ON PB444E HI PZR DEVIATION PB444B HI PZR DEVIATION ENABLE PORV PCV444B I P4451 P4452 P4453 PB445A HI PZR PRESSURE ENABLE PORV PCV445A PB445B LOW PZR PRESSURE PD445C HI PZR PRESSURE P4461 PB446B BLX AUTO ROD WITHDRAWAL C-5 P4462 PB446A1 TUR IMP CH PRESS > 10% F.P. CH 3 P4471 PB447El TUR IMP CH PRESS > 10% F.P. CH 4 .
P4472 PB447A SUDDEN LOSS OF TUR LOAD I P4551 P4552 P4553 PB455A PZR HIGH PRESSURE CH 1 PB455B P-11 CH 1 PB455C PZR LOW PRESSURE REACTOR TRIP CH 1 I P4554 P4561 P4562 PB455D PZR LOW PRESSURE SI CH 1 PB456A PZR HIGH PRESSURE CH 2 PB456B P-11 CH 2 P4563 PB456C PZR LOW PRESSURE REACTOR TRIP CH 2 I P4564 P4571 PB456D PZR LOW PRESSURE SI CH 2 PB457A PZR HIGH PRESSURE CH 3 P4572 PB457B P-11 CH 3 I P4573 P4574 P4751 PB457C PZR LOW PRESSURE REACTOR TRIP CH 3 PB457D PZR LOW PRESSURE SI CH 3 PB475B1 P1-P2 HIGH STEAM LINE DIFF PRESSURE CH
- I P4752 P4761 P4762 PB475B2 P1-P2 HIGH STEAM LINE DIFF PRESSURE CH 3 PB476B1 P1-P2 HIGH STEAM LINE DIFF PRESSURE CH 4 PB476B2 P1-P2 HIGH STEAM LINE DIFF PRESSURE CH 4 P4841 PB484B1 P2-P3 HIGH STEAM LINE DIFF PRESSURE CH 2 I P4842 P4851 PB484B2 P2-P3 HIGH STEAM LINE DIFF PRESSURE CH 2 PB485A LOOP 2 LOW STEAM LINE PRESSURE P4852 PB485B1 P2-P3 HIGH STEAM LINE DIFF PRESSURE CM 3 I P4853 P4861 P4862 PB485B2 P2-P3 HIGH STEAM LINE DIFF PRESSURE CH 3 PB486B1 P2-P3 HIGH STEAM LINE DIFF PRESSURE CH 4 PB486B2 P2-P3 HIGH STEAM LINE DIFF PRESSURE CH 4 P4941 PB494B1 P1-P3 HIGH STEAM LINE DIFF PRESSURE CH 2 ATTACRMENT B.3 I
6
. 1 ATIhCXMENT B.3 8IMULATOR l BI8 TABLE OVERRIDES ITEM _
DESCRIPTION P4942 PB494B2 P1-P3 HIGH STEAM LINE DIFF PRESSURE CH 2 P4951 PB495B1 P1-P3 HIGH STEAM LINE DIFF PRESSURE CH 3 l P4952 PB495B2 P1-P3 HIGH STEAM LINE DIFF PRESSURE CH 3 P4961 PB496A LOOP 3 LOW STEAM LINE PRESSURE I P4962 P4963 P9501 PB496B1 P1-P3 HIGH STEAM LINE DIFF PRESSURE CH 4 PB496B2 P1-P3 HIGH STEAM LINE DIFF PRESSURE CH 4 PB950A CNMT PRESSURE HI-3 CH 1 I P9511 P9512 P9513 PB951A CNMT PRESSURE HI-3 CH 2 PB951B1 CRMT PRESSURE HI-1 CH 2 PB95182 CNMT PRESSURE HI-2 CH 2 P9521 PB952A1 CNMT PRESSURE HI-3 CH 3 I P9522 P9523 PB952B1 CNMT PRESSURE HI-1 CH 3 PB952B2 CNMT PRESSURE HI-2 CH 3 P9531 PB953A CNMT PRESSURS HI-3 CH 4 P9532 PB953B1 CNMT PRESSURE !!I-1 CH 4 P9533 PB953B2 CNMT PRESSURE HI-2 CH 4 R70A1 R70-A PRI-SEC N-16 STEAMLINE MONITOR LOOP-A R70B1 R70-B PRI-SEC N-16 STEAMLINE MONITOR LOOP-B R70C1 R70-C PRI-SEC N-16 STEAMLINE MONITOR LOOP-C RCP11 RCP-1 UNDERVOLTAGE RELAY TRIP RCP12 RCP-1 UNDERFREQUENCY RELAY TRIP RCP21 RCP-2 UNDERVOLTAGE RELAY TRIP I RCP22 RCP31 RCP32 RCP-2 UNDERFREQUENCY RELAY TRIP RCP-3 UNDERVOLTAGE RELAY TRIP RCP-3 UNDERFREQUENCY RELAY TRIP S4081 SB408C1 AUTO RODS IN S4082 SB408C2 AUTO RODS OUT S4091 ZB409E CTRL BK D WITHDRAWAL LIMIT ; ROD STOP S4092 ZB409Al BANK A LOW LIMIT S4093 ZB409A2 BANK A LO-LO LIMIT l S4094 ZB409B1 BANK B LOW LIMIT l S4095 ZB409B2 BANK B LO-LO LIMIT S4096 ZB409C1 BANK C LOW LIMIT S4097 ZB409C2 BANK C LO-LO LIMIT I S4098 S4099 ZB409D1 BANK D LOW LIMIT ZB409D2 BANK D LO-LO LIMIT T4081 TB408J2 DEVITREG/TAVG HI 2, TURBINE TRIP
'I T4082 T4083 TB408A2 LOOP 1 TAVG > AUCT TAVG TB408B1 AUCT TAVG > LOOP 2 TAVG T4084 TB408B2 LOOP 2 TAVG > AUCT TAVG l T4085 TB408C1 AUCT TAVG > LOOP 3 TAVG -
T4086 TB408C2 LOOP 3 TAVG > AUCT TAVG l T4087 TB400F1 DEV TREF /TAVG, HI 1, LOAD REJ T4088 TB408F2 DEV: TREF /TAVG, HI 2, LOAD REJ 7 ATTACHMENT B.3
l ATIACJOtENT 3.3 SIMULATOR 53NTABLE OVERRIDED ITEM DESCRIPTION l T4089 TB408J1 DEVITREP/TAVG, HI 1, TURBINE TRIP I T4091 T4092 TB409A1 AUCT DELTA T > LOOP 1 DELTA T TB409A2 LOOP 1 DELTA T > AUCT DELTA T l
l l
T4093 TB409B1 AUCT DELTA T > IOOP 2 DELTA T I I T4094 T4095 T4096 TB409B2 LOOP 2 DELTA T > AUCT DELTA T TB409C1 AUCT DELTA T > LOOP 3 DELTA T TB409C2 LOOP 3 DELTA T > AUCT DELTA T I T4121 T4122 T4123 TB412B2 OPDT ROD STOP LOOP 1 TB412C2 OTDT ROD STOP LOOP 1 TB412B1 RCS OVERPOWER DELTA T LOOP 1 T4124 TB412C1 RCS OVERTEMP DELTA T LOOP 1 I T4125 T4126 TB412D1 RCS LOW TAVG LOOP 1 TB41202 RCS HIGH TAVG LOOP 1 T4127 TB412E RCS LO-LO TAVG LOOP 1 T4221 TB422B2 OPDT ROD STOP LOOP 2 T4222 TB422C2 OTDT ROD STOP LOOP 2 T4223 TB422B1 RCS OVERPOWER DELTA T LOOP 2 3 T4224 TB422C1 RCS OVERTEMP DELTA T LOOP 2
'E T4225 TB422D1 RCS LOW TAVG LOOP 2 T4226 TB422D2 RCS HIGH TAVG LOOP 2 T4227 TB422E RCS LO-LO TAVG LOOP 2 I
T4321 T4322 TB432B2 OPDT ROD STOP LOOP J TB432C2 OTDT ROD STOP LOOP.3L T4323 TB432B1 RCS OVERPOWER DELTA T LOOP 3 I T4324 T4325 T4326 TB432C1 RCS OVERTEMP DELTA T LOOP 3 TB432D1 RCS LOW TAVG LOOP 3 TB432D2 RCS HIGH TAVG LOOP 3 T4327 TB432E RCS LO-LO TAVG LOOP 3 I
I I
I I -
lI l 8 ATTACHMENT B.3
l N EC SIMULATOR ,
CERTIFICATION TEST PROCEDURES PROCEDURE ANSI SECTION PERFORMANCE TEST TITLE FNP-SIM-CTP-1.0 3 .1.1 ( 1) Startup of Unit from Cold Shutdown to Hot Standby FNP-SIM-CTP-1.1 3.1.1(2),(3) Startup of The Unit from Hot Standby to Minimum Load FNP-SIM-CTP-1.2 3.1.1(2),(6) Power Operations - Minimum Load to 100% Power FNP-SIM-CTP-1.3 3 .1.1 ( 8 ) Power Operations - 100%
Power to Minimum Load FNP-SIM-CTP-1.3.1 3 .1.1 ( B ) Shutdown from Minimum Load to Hot Standby I FNP-SIM-CTP-1.4 3 .1.1 ( 8 ) Shutdown of Unit from Hot Standby to Cold Shutdown FNP-SIM-CTP-1.5 3.1.1 ( 4 ) , ( 5) Startup of Unit Following an at Power Reactor Trip FNP-SIM-CTP-1.6 3.1.1(9) Core Physics Testing FNP-SIN-CTP-1.7 3.1.2 Si'aulator Real Time Test I FNP-SIM-CTP-1.8 4.3 Operating Limits Exceeded Test FNP-SIM-CTP-1.9 3.1.1(10) Operator Conducted Surveillance Testing FNP-SIM-CTP-2.1 3.1.2(2) Failure of Instrument Air System FNP-SIM-CTP-2.2 3.1.2(6) Service Water Pump Trip FNP-SIM-CTP-2.3 3.2.1(8) CCW pump Trip FNP-SIM-CTP-2.4 3.1. 2 ( 5) , (15) Steam Jet Air Ejector Failure FNP-SIM-CTP-2.5 3.1.2(5) llotwell Fill Controller CP-4055F Failuro FNP-SIM-CTP-2.6 3.1.2(5) llotwell Dump Controller -
CP-4055G Failuro FNP-SIM-CTP-2.7 3.1.2(13) Rods Fail to Movo in, Auto l
1 ATTACHMENT C
hTIAGEMENT..C 8INULATOR CERTIFICATION TEST PROCEDURE 3 PROCEDURE ANSI SECTION PERFORMANCE TEST TITLE _
FNP-SIM-CTP-2.8 3.1.2.(13) Rods Fail to Move in Manual FNP-SIM-CTP-2.9 3.1.2(12a) Stuck Rod FNP-SIM-CTP-2.10 3.1. 2 (12d& e) Dropped Rod FNP-SIM-CTP-2.11 3.1.2(18) VCT Level Transmitter Failure FNP-SIM-CTP-2.12 3.1.2(3) Degraded Grid Voltage -
Loss of All offsite Power FNP-SIM-CTP-2.13 3.1.2(3) 4160V Bus Trip FNP-SIM-CTP-2.14 3.1.2(3) Emergency 4160V Bus Trip FNP-SIM-CTP-2.15 3.1.2(3) Diesel Generator Failure -
Essential Protection FNP-SIM-CTP-2.16 3.1.2(3) Startup Transforner Failure FNP-SIM-CTP-2.17 3.1.2(3) 600V Load Center Trip FNP-SIM-CTP-2.18 3.1.2(3) 600V Motor Control Center Trip I FNP-SIM-CTP-?.19 3.1. 2 ( 3 ) , (11) 120VAC Vital Instrument Inverter Failure
.E FNP-SIM-CTP-2.20 3.1.2(3) 120V Vital Instrumentation E Distribution Panel Trip FNP-SIM-CTP 2.21 3.1.2(3) 120VAC Distribution Panel Trip FNP-SIM-CTP-2.22 3.1.2(3) 125VDC Distribution Panel l Trip FNP-SIM-CTP-2.23 3.1.2(23) MDAFW FCV Failure FNP-SIM-CTP-2,24 3.1.2(9) SGFP Trip FNP-SIM-CTP-2.25 3.1.2(22) SGFP Failure to Auto Trip FNP-SIM-CTP-2.26 3.1.2(22) SGFP Turbine Speed Controller Failure 2 ATTACHMENT C
ATIActDIENT C l
SIMULATOR CERTIFICATION TEST PROCEDURES PROCEDURE ,
ANSI SECTION PERFORMANCE TEST TITLE FNP-SIM-CTP-2.27 3.1.2(22) Feedwater Header Pressure I FNP-SIM-CTP-2.28 Transmitter PT-508 Failure 3.1. 2 ( 2 2 ) , (11) S/G Level Channel failuro PNP-SIM-CTP-2.29 3.1.2(20) S/G Feedline Dreak Outside I Containment, Downstream of Stop Check Valve I FNP-SIM-CTP-2.30 3.1.2(20) Feedline Break Inside Containment 3.1.2(20) Steamline Break Inside I FNP-SIM-CTP-2.31 Containment FNP-SIM-CTP-2.32 3.1.2(20) Steamline Break Outside I Containment, Upstream of MSIV FNP-SIM-CTP-2.33 3.1.2(22) Steamline Flow Transmitter
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FNP-SIM-CTP-2.34 3.1.2(17) Steam Dump Valves Fail to Operate in T-ave Mode .
FNP-SIM-CTP-2.35 3.1.2(22) Steam Header Pressure Controller PT-464 Failure FNP-SIM-CTP-2.36 3.1.2(21) Source Range Channel Failure FNP-SIM-CTP-2.36.1 3.1.2(21) Failure of Source Range Channel High Voltage to Disconnect FNP-SIM-CTP-2.36.2 3.1.2(21) Source Range Channel High I Voltage Failure FNP-SIM-CTP-2.36.3 3.1.2(21) Source Range Blown Fuse FNP-SIM-CTP-2.37 3.1.2(21) Intermediate range Channel Failure FNP-SIM-CTP-2.37.1 3.1.2(21) I.R. Channel Gamma Compensation Failure FNP-SIM-CTP-2.37.2 3.1.2(21) Intermediate Range Blown -
Fuse I
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ATTACXKEMT Q SIMULATOR CERTIFICATION TEST PROCEDURES PROCEDURE ANSI SECTION PERFORMANCE TEST TITLE FHP-SIM-CTP-2.38 3.1.2(21),(11) Power Range Channel Failure PHP-SIM-CTP-2.38.1 3.1. 2 (21) , (11) Power Range Channel Detector Failure FNP-SIM-CTP-2.38.2 3.1. 2 ( 21) , (11) Power Range Blown Fuse FNP-SIM-CTP-2.39 3.1.2(19) Inadvertent Reactor Trip FNP-SIM-CTP-2.40 3.1.2 ) Reactor Trip Dreakers Fall To Open FNP-SIM-CTP-2.41 3.1.2(23) Safeguard Actuation and Containment Isolation Failure FNP-SIM-CTP-2.42 3.1.2(1c) Pressurizar Steam Space Break FNP-SIM-CTP-2.43 3.1.2(1d) Pressurizer Relief Valve Failure FNP-SIM-CTP-2.44 '
3.1.2(1d) Pressurizer Safety Valve
. Failure FNP-SIM-CTP-2.45 3.1.2(18) Pressurizer Pressure Channel Failure I FNP-SIM-CTP-2.46 3.1.2(18) Pressurizer Level Master controller Failure FNP-SIM-CTP-2.47 3.1.2(18) Pressurizer Level Channel Failure FNP-SIM-CTP-2.48 3.1.2(1b)
I Reactor Coolant System Leak FNP-SIM-CTP-2.49 3.1.2(1c) Loss of Coolant Accident I FNP-SIM-CTP-2.50 3.1.2(la) Steam Generator Tube Leak FNP-SIM-CTP-2.51 3.1.2(4) Reactor Coolar.L Pump Trip FNP-SIM-CTP-2.52 3.1.2(14) Fuel Cladding Failure l FNP-SIM-CTP-2.53 3.1. 2 (2 2 ) , (11) RCS Loop Protection RTD -
Failure j 4 A m cHsesT C
1 LTTACKKENT_C SIMULATOR CERTIFICATION TEST PROCEDtTRES PROCEDITRE _
ANSI SECTION PERFORMANCE TEST TITLE FNP-SIM-CTP-2.54 3.1.2(22) RCS Loop control RTD Failure FNP-SIM-CTP-2.55 3.1.2(7) RHR Pump Trip FNP-SIM-CTP-2.56 3.1. 2 (1b) RHR HTX Bypass Line Break FNP-SIM-CTP-2.57 3.1.2(22) Turbine First Stage I Pressure Transmitter Failure 3.1. 2 (1?)
I FNP-SIM-CTP-2.50 Generator Auto Voltage Regulator Failure FNP-SIM-CTP-2.59 3.1.2(10) AFW Pump Trip FNP-SIM-CTP-3.1 B2.2(1) Manual Reactor Trip I FNP-SIM-CTP-3.2 B2.2(2) Simultaneous Trip of all Feedwata'r Pumpa FNP-SIM-CTP-3.3 Simultaneous closure of I B2.2(3)
All Main Steam Isolation Valves FNP-SIM-CTP-3.4 B2.2(4) Simultaneous trip of All Reactor Coolant Pumps FNP-SIM-CTP-3.5 B2.2(5) Trip of any Single Reactor Coolant Pump FNP-SIM-CTP-3.6 B2.2(6) Main Turbine Trip (Less than P-9 Setpoint)
FNP-SIM-CTP-3.7 B2.2(7) Maximum Rate Power Ramp (100% Down to 75% and back up to 100%)
FNP-SIM-CTP-3.8 B2.2(8) Maximum Size Reactor Coolant System Rupture I Combined with Loss of all offsite Power FNP-SIM-CTP-3.9 B2.2(9) Maximum Size Unisolabic
- Main Steam Line Rupture -
5 ATTACHMENT C
ATTACEMENT_C SIMULATOR CERTIFICATION TEST PROCEDURES PROCEDURE ANSI SECTION PERFORMANCE TEST TITLE FNP-SIM-CTP-3.10 B2. 2 (10) Slow Primary System Depressurization to
.I Saturated Condition using pressurizer Relief or Safety Valve Stuck Open FNP-SIM-WP-4.0 4.1(2) One Hour Steady State Operations Test FNP-SIM-CTP-4.1 4.1(3),(4) Steady State Comparison to Reference Plant i 4 .1,( 2 ) Steady State Thermal I FNP-SIM-CTP-4.2 Calorimetric Comparison j
FNP-SIM-CTP-5.1 4.2.2 Loss of source range instruments due to two power range instruments being de-energized FNP-SIM-CTP-5.2 4.2.2 Reactor Trip caused by Inadvertent Deenergization of 4160 Volt Bus 1H FNP-SIM-CTP-5.3 4.2.2 Reactor Trip Due to Inverter 1A Failing while I Power Range Channel NI-42 Was Being Tested FNP-SIM-CTP-5.4 4.2.2 Unit 1 Reactor Trip Due to I- Under-frequency on the Reactor Coolant Pump Buses FNP-SIM-CTIP-5.5 4.2.2 DEH Malfunction Resulting in Safety Injection and Reactor Trip FNP-SIM-CTP-5.6 4.2.2 Load Rejection l
6 ATTACHMENT C
&TT&CRKENT.DJ GERTIFICATION TEST ABSTRACTS NORMAL OPERATIONS
- PROCEDURE PROCEDURE TITLE PAGE FHP-SIM-CTP-1.0 STARTUP OF UNIT FROM COLD SliUTDOWN TO IlOT STANDBY......................... 1 FNP-SIM-CTP-1.1 STARTUP OF UNIT TROM HOT STANDBY TO MINIMUM LOAD........................ 3 FNP-SIM-CTP-1.2 POWER OPERATIONS - MINIMUM LOAD TO 100% POWER............................. 5 FNP-SIM-CTP-1.3 POWER OPERATIONS - 100% POWER TO MINIMUM LOAD........................... 7 FNP-SIM-CTP-1.3.1 S!!UTDOWN FROM 14INIMUM LOAD TO HOT STANDBY..........................,. 9 FNP-SIM-CTP-1.4 SHUTDOWN OF UNIT FROM HOT STANDDY TO COLD S!!UTDOWN....................... 11 FNP-SIM-CTP-1.5 STARTUP OF UNIT FOLLOWING A REACTOR TRIP................................... 13 I .
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ATTACHMENT D.1
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FNP-SIM-CTP-1.0 FARLEY WUCLEAR PLANT SIMULATOR = CERTIFICATION TEST ABSTRACT 1
TEST IDENTIFICATION PROCEDURE FNP-SIM-CTP-1.0 REV8 0 TYPE Normal Operations TITLEt Startup of Unit From Cold Shutdown to llot Standby I REQUIREMENT 81 e
ANSI 3.5-1985 Section 3.1.1(1) , Plant startup - cold to hot standby APPROVED BYt C. Mclean DATE APPROVEDI 9/5/90 TEST SCOPE I INITIAL CONDITIONS: The simulator is running and operat ing in cold shutdown in accordance with procedure FNP-1-UOP-I 2.2. The applicable initial conditions of procedure FNP-1-UOP-1.1 are already met.
TEST INITIATOR: Perform procedure FNP-1-UOP-1.1, Operate the Plant from Cold Shutdown to llot Standby.
PURPOSE: To evaluate the simulator's capability to perform continuous real time simulation of Unit 1 plant operations from cold shutdown to hot standby.
TERMINATION: Tenninate with the plant maintained in hot standby conditions in accordance with procedure FNP-1-UOP-1*.
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, FNP-SIM-CTP-1.0 TEST RESULTS
- DATE PERFORMED: 10/15/90 PERFORMED BY R. Taylor BASEL1WE DATAt Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCRIPANCIE8: None DEFICIENCIES REPORTED: None EECEPTION8 None RESULTS: Satisfactory REVIEWED BY R. Wiggins
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COMMITTEE REVIEW ,
' REVIEW COMMITTEE MEMBERS PRESENT: J. Osterheltz I. L. Williams R. Wiggins C. Me, lean DATE APPROVED: 02/06/91 ll .
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FNP-SIM-CTP-1.1 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT
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TEST IDENTIFICATION PROCEDUREt FNP-SIM-CTP-1.1 REY: 0 TYPE: Normal Operations
-fITLE Startup of Unit From Hot Standby REQUIREMENTS
- ANSI 3.5-1985 Section 3.1.1(2)&(3),
Nuclear startup from hot standby to rated I- power, and turbine startup and generator synchronization .
APVROVED BY C.,Mclean DATE APPROVED: 9/5/90
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TEST SCOPE' INITIAL CONDITIONS: The simulator is maintained at hot standby in accordance with the
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initial conditions of procedure FNP-
'[#,4 1-UOP-1.2.
L. TEST INITIATORt Perform procedure FNP-1-UOP-1.2, Startup of Unit from Hot Standby to Minimum Load.
PURPOSE: To evaluate the simulator's capability to perform continuous real time simulation of Unit 1 plant I ,
operations from hot standby to minimum load.
TERMINATION: Terminate when the simulator being maintained at minimum loa.. in accordance with procedure FNP-1-UOP-1.2.
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FNP-SIM-CTP-1.1 I TEST RESULTS DATE PERFORMED: 10/17/90 PERFORMED BY R. Taylor BASELINE DATAt. Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None -
e EECEPTIONS: None RESULTS: Satisfactory REVIEWED BY R. Wiggins I
. COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz
'L. Williams R. Wiggins
-I C. Mclean DATE APPROVED: 02/06/91 I
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FNP-SIM-CTP-1e2 r -
FARLEY WUCLEAR PLANT SINULATOR - CER'fIFICATION TR8T ABSTRACT I
TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-1.2 REY: O TYPE: Normal Operations
- TITLE Power Operations - Minimum Load to 100%
REQUIREMENTS: ANSI 3.5-1985 Section 3.1.1(2)&(6),
I Nuclear startup from hot standby to rated power, and load changes DATE APPROVED: 9/S/90 I APPROVED BY C. Mclean, I TEST SCOPE I INITIAL CONDITIONS: The simulator is in hot standby and being maintained in accordance with the initial conditions of prneedure FNP-1-UOP-3.1.
TEST INITIATOR: Using procedure FNP-1-UOP-3.1, operate the plant to a base load of 100% power.
PURPOSE: To evaluate the simulator's I capability to perform continuous real time simulation of Unit 1 power operations.
. TERMINATION: Terminate with the simulator being maintained at base load conditions of 100% power in accordance with I. procedure FNP-1-UOP-3.1.
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FNP-SIM-CTP-1.8 TEST RESULTS DATE PERFORMED: 10/18/90 PERFORMED BY R. Taylor BASELINE DATA: Plant P.~cedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIE8 REPORTED: None EECEPTIONS: None RFSULTS: Satisfactory REVIEWED BY: R. Wiggins I .
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz L. Williams R. Wiggins
.I C. Mclean DATE APPROVED: 02/06/91 I.
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FNP-SIM-CTP-1.3 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-1.3 REV 0 TYPE: Normal Operations TITLE: 100% to Minimum Load I REQUIREMENTS: ANSI 3.5-1985 Section 3.1.1(8), Plant shutdown from rated power to hot standby APPROVED BY C. Mclean DATE APPROVED: 9/5/90 I TEST SCOPE I- INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP I TEST INITIATOR:
UCP-3.1.
Operate the plant to minimum load I conditions per procedure FNP-1-UOP-3.1, Power Operations.
I PURPOSE: To evaluate the simulator's l capability to perform continuous l real time simulation of Unit 1 power
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operations from 100% power to minimum load.
TERMINATION: Terminate with the simulator at l3 minimum load and being maintained in l@ accordance with the initial i conditions of procedure FNP-1-UOP-t 2.1.
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FNP-SIM-CTP-1e3 TEST RESULTS .
DATE PERFORMED: 10/19/90 PERFORMED BY R. Taylor BASELINE DATA: Plant Procedures,. Plant Specific Data, Best Escitate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED - None EXCEPTIONSt None RESULTS Satisfactory REVIEWED DY R. Wiggins COMMITTEE REVIEW I REVIEW COMMITTEM MEMBERS PRESENT: J. Osterholtz L. Williams R. Wiggins DATE APPROVED: 02/06/91 I .
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FNP-SIM-CTP-1.3.1 i
FARLEY NUCLEAR PIANT SIMULATOR - CERTIFICATION TEST ABSTRACT
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TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-1. 3.1 REV t O TYPE: Normal Oporations TITLE: Shutdown from Minimn> Load to Hot Standby I REQUIREMENT 8: ANSI 3.5-1985 Section 3.1.1(8), Plant shutdown to hot standby APPROVED BY: C. Mclean DATE APPROVEUt 10/19/90 I.
I TEST SCOPE INITIAL CONDITIONS The simulator is being maintain 6d at minimum load (15-20%) in accordance with procedure FNP-1-UOP-3.1.
TEST INITIATOR: Perform procedure FNP-1-UOP-2.1, Shutdown of Plant to Hot Standby Conditions.
PURPOSE: To evaluate the simulator's -
capability to perform continuous I real time simulation of Unit 1 shutdown from minimum load to hot standby, TERMINATION: Terminate with the simulator being maintained in hot standby in accordance with the initial I- conditions of procedure FNP-1-UOP-2.2.
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FNP-SIM-CTP-1.3.1
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TEST RESULTS
. DATE PERFORMED: 10/19/90 PERFORMED BY R. Taylor BASELINE DATA: Plant' Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None EXCEPTIONS: None RESULTS: Satisfactory REVIEWED BY R. Wiggins I COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT:
I- J. Osterholtz L. Williams R. Wiggins C. Mclean DATE-APPROVED: 02/06/91 I '
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FNP-SIM-CTP-1.4 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-1.4 REY: 0 TYPE: Normal Operations TITLE: Shutdown of Unit From Hot standby to Cold Shutdown REQUIREMENTS: ANSI 3.5-1985 Section 3.1.1(8), Plant cooldown to cold shutdown conditions APPROVED BY C. Mclean DATE APPROVED: 9/5/90 I TEST SCOPE INITIAL CONDITIONS: The simulator is running and maintaining hot standby conditions in accordance with procedure FNP UCP-2,2 after shutdown from 100%.
TEST INITIATOR: Perform procedure FNP-1-UOP-2.2, g Shutdown of Unit from Hot Standby.to 3 ,
Cold Shutdown.
PURPOSE: To evaluate the simulator's I capability to perform continuous real time simulation of Unit 1 operations from hot standby to cold shutdown.
TERMINATION: Terminat'e with this simulator being maintained in cold shutdown in -
accordance with procedure FNP-1-UOP-2.2.
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FNP-SIM-CTP-1.4 1
I: TEST RESULT 8 DATE' PERFORMED: 10/30/90 PERFORMED BY R. Taylor BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIE8 REPORTED: None EXCEPTION 8 None RESULT 8 Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz L. Williams R. Wiggins C. Mclean DhTE APPROVED: 02/06/91 9
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FNP-SIM-CTP-1.5 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDUREt FNP-SIM-CTP-1.5 REY: 0 TYPE: Normal Operations TITLE: Startup of Unit Following an at Power Renctor Trip REQUIREMENTS: ANSI 3.5-1985 Section 3.1.1(4)&(5),
Reactor trip followed by recovery to rated power; Operations at hot standby
, APPROVED DY: C. Mclean DATE APPROVED: 9/5/90 I
TEST SCOPE INITIAL CONDITIONS: The simulator is running and I operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Trip the reactor and perform procedure FNP-1-UOP-1.3 and startup the plant and return to 100% power.
PURPOSE: To evaluate the simulator's capability to perform continuous real time simulation of Unit 1 operations during a startup of the unit following an'at power reactor trip.
TERMINATION: Terminate when the plant is returned to 100% steady state power and maintained in accordance with procedure FNP-1-UOP-3.1.
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FNP-SIM-CTP-1.5 4
TEST RESULTS DATE PERFORMED 12/18/90 PERFORMED BY R. Taylor EA8ELINE DATAs Plant Procedures, Plant Specific Data, Best Estimate Judgement DEBCREPANCIE8: None DEFICIENCIE8 REPORTED: None EECEPTIONS: None 5
RESULTS Satisfactory REVIEWED BY R. Wiggins il COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT J. Osterholtz L. Williams R. Wiggins C. Mclean DATE APPROVED: 02/06/91 4
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ATTACHMENT D.1 CERTIFICATION TEST ABETRACTS I SPECIAL SIMULATOR TESTS I
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PROCEDURE PROCEDURE TITLE PAGE 1
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FNP-SIM-CTP-1.6 CORE PERFORMANCE TESTING............... 1 FNP-SIM-CTP-1.7 SIMULATOR REAL TIME TEST............... 3 FNP-SIM-CTP-1.8 OUTSIDE OPERABLE LIMITS TEST........... 5 FNP-SIM-CTP-1.9 OPERATOR CONDUCTED SURVEILLANCE........ 7 I-I I
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, FNP-SIM-CTP-106 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST AB8 TRACT TEST IDENTIFICATION PROCEDURE: FNP-SIF-CTP-1.6 REV 0 TYPE: Core Physics TITLE: Core Performance Testing REQUIREMP.NTS: ANSI 3.5-1985 Section 3.1.1(9), Core performance testing such as measurement of reactivity coefficients and control I rod worth using permanently installed instruments -
I APPROVED BY: C. Mclean DATE APPROVED: 09/28/90 I TEST SCOPE INITIAL CONDITIONS: Hot zero power, all rods out, xenon in accordance with specific test requirements.
TEST INITIATOR: Run the CORETEST program in the background to evaluate core physics parameters of the simulator.
.I PURPOSE: To evaluate the simulator's core physica parameters.
TERMINATION: Each test is self-terminating in accordance with the CORETEST l program.
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FiiP-SIM-CTP-1.6 I TEST RESULTB ,_
DATE PERFORMED: 10/5/90' PERFORMED BYt P. Pappenfus BASELINE DATM Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIE8: None DEFICIENCIES REPORTED: None
. EXCEPTIONS 3 Tests were run utilizing background I test programs rather than manually operating controls and reading from permanently installed instrumentation. The background I- ,
program test is faster and provides a more accurate indication of the simulated core physics parameters.
.I_ RESULTS: Satisfactory REVIEWED BY: R. Wiggins I -
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT ' J. Osterholtz ,
L. Williams R. Wiggine C. Mclean DATE APPROVED: 02/06/91 ,
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FNP-SIM-CTP-1.7 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-1.7 REY: 0 TYPE Real Time Test TITLE: Simulator Real Time Test REQUIREVENTS: ANSI 3.5-1985 Section 3.1.2, The simulator shall be capable of simulating continuously, and in real time, plant g operations of the reference plant.
APPROVED BY C. Mclean DATE APPROVED: 9/28/90 I '
TEST SCOPE INITIAL CONDITIONS The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Two options:
(1) Test during steady-state operation, (2) Test with a LOCA malfunction active.
PUPPOSE: To evaluate the simulator's I capability to run in real time during steady state operations and during interrupt intense transient conditions.
TERMINATION: Terrinate the test after running for 5 minutes and recording the processor duty cycles.
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. I FNP-SIM-CTP-1o7 I TEST RESULTS DATE. PERFORMED: 9/28/90 PERFORMED BY P. Pappentus BASELINE DATA: Not Applicable DESCRIPANCIES: Nono DEFICIENCIES REPORTEUs None EECEPTIONS: None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW l-I REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz L. Williara R. Wiggins DATE APPROVED: 02/06/91 L .
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FNP-SIM-CTP-1.8 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT I TEST IDENTIFICATIC'.4 PROCEDURE: FNP-SIM-CTP-1.8 REY: 0 TYPE: Special Test TITLE: Simulator Operating Limits Test REQUIREMENTS ANSI 3.5-1985 Section 4.3, In order to avoid negative training which could result from simulator operation during events, administrative controls or other means shall be provided to alert the .
I instructor when certain parameters approach values indicative of events beyond the' implemented model or known l plant behavior.
! APPROVED BY C. Mclean DATE APPROVED: 9/28/90 l
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INITIAL CONDITIONS:
Simulator is running and operating L at 100% steady-state power in l accordance with procedure FNP-1-UOP-3.1.
TEST INITIATOR: Manipulate RCS pressure to exceed design limits.
lg PURPOSE: To evaluate the simulator's response W ,
when operating limits are exceeded.
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- TERMINATION
- Terminate the test when the expected l results are observed.
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TEST RESULTS ,
DATE PERFORMED: 9/28/90 PERFORMED BYt P. Pappenfus BASELINE DATA: Not applicable DESCREPANCIES: None DEFICIENCIES REPORTED: None EECEPTIONS: None RESULTS: ' Satisfactory REVIEMED BY R. Wiggins COMMITTEE REVIEW
~ REVIEW COMMITTEE MEMBERf4 PRESENT: J. Osterholtz L. Williams
- R. Wiggins
- C. Mclean 3
- . - DATE APPROVED: 07./06/91 lI I
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FNP-SIM-CTP-1.9 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT I
TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-1.9 REV1 0 TYPE: Surveillance
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TITLE: Operator Conducted Surveillance Testing ANSI 3.5-1985 Section 3.1.1(10),
I REQUIREMENT 88 operator conducted surveillance testing on safety-related equipment or systems APPROVED BY: C. Mclean DATE APPROVED 11/14/90 I TEST SCOPE INITIAL CONDITIONS: Establish conditions in accordance with the initial conditions of the respective surveillance test being l T*ST INITIATOR:
performed.
Perform the surveillance tests specified by the procedure.
PUKPOBW To evaluate the simulator's response to operator conducted surveillance I testing.
TERMINATION: Terminate when all the surveillance I test procedures have been completed for those functions which can be performed in the main control room.
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FNP-SIM-CTP-1.9 TEST RESULT 8 DATE PERFORMED: 12/14/90 PERFORMED BYt P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: The source range high flux at shutdown alarm was found to have an incorrect setpoint.
DEFICIENCIEC REPORTED: SCR 90.220, High Flux at Shutdown Alarm Setpoint.
I EXCEPTIONS: None RESUL'ts: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz L. Williams R. Wiggins C. Mclean DATE APPROVED: 02/06/91 .
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&TTAQ][ MENT. D. 3 CERTIFICATION TEST ABSTRACTS MALFUNCTION 8 PROCEDURE PROCEDURE TITLE PAGE FNP-SIM-CTP-2.1 FAILURE OF INSTRUMENT AIR SYSTEM...... 1 I FNP-SIM-CTP-2.2 SERVICE WATER PUMP TRIP............... 3 FNP-SIM-CTP-2,3 CCW PUNP TRIP......................... 5 FNP-SIM-CTP-2,4 STEAM JET AIR EJECTOR FAILURE......... 7 FNP-SIM-CTP-2.5 HOTWELL FILL CONTROLLER CP-4055F FAILURE............................... 9 I FNP-SIM-CTP-2.6 HOTWELL DUMP CONTROLLER CP-4,055G FAILURE............................... 11 FNP-SIM-CTP-2.7 RODS FAIL TO MOVE IN AUTO............. 13 FNP-SIM-CTP-2.8 RODS FAIL TO MOVE IN MANUAL........... 15 FNP-SIM-CTP-2.9 STUCK ROD............................. 17 FNP-SIM-CTP-2.10 DROPPED ROD........................... 19 FNP-SIM-CTP-2,11 VCT LEVEL TRANSMITTER FAILURE......... 21 FNP-SIM-CTP-2.12 DEGRADED GRID VOLTAGE - LOSS OF ALL OFFSITE POWER..................... 23 FNP-SIM-CTP-2.13 4160V BUS TRIP........................ 25 I FNP-SIM-CTP-2.14 EMERGENCY 4160v BUS TRIP.............. 27 I FNP-SIM-CTP-2.15 DIESEL GENERATOR FAILURE - 5'SSENTIAL PROTECTION............................ 29 FNP-SIM-CTP-2.16 STARTUP TRANSFORMER FAILURE........... 31 FNP-SIM-CTP-2.17 600V LOAD CENTER TRIP................. 33 FNP-SIM-CTP-2,18 600V MOTOR CONTROL CENTER TRIP...-..... 35 I FNP-SIM-CTP-2.19 120VAC VITAL INSTRUMENT INVERTER FAILURE............................... 37 FNP-SIM-CTP-2.20 120VAC VITAL INSTRUMENTATION DISTRIBUTION PANEL TRIP............... 39 -
FNP-SIM-CTP-2.21 120VAC DISTRIBUTION PANEL TRIP........ 41 I .
ATTACKMENT_Dr3 CERTIZI.QATION TEST. ABSTRACTS KALFUNCTION8 PROCEDURE PROCEDURE TITLE PAGE FNP-SIM-CTP-2.22 125VDC DISTRIBUTION BUS TRIP.......... 43 FNP-SIM-CTP-2.23 MDAFW FCV FAILURE..................... 45 FNP-SIM-CTP-2.24 SGFP TRIP............................. 47 FNP-SIM-CTP-2.25 SGFP FAILURE TO AUTO TRIP............. 49 FNP-SIM-CTP-2.26 SGFP TURBINE SPEED CONTROLLER FAILURL. 51 FNP-SIM-CTP-2.27 FEEDWATER HEADER PRESSURE TRANSMITTER PT-408 FAILURE........................ 53 FNP-SIM-CTP-2.28 S/G LEVEL CHANNEL FAILURE............. 55 FNP-SIM-CTP-2.29 S/G FEEDLINE BREAK OUTSIDE CONTAINMENT DOWNSTREAM OF STOP CHECK VALVE........ 57 FNP-SIM-CTP*2.30 FEEDLINE BREAK INSIDE CONTAINMENT..... 59 FNP-SIM-CTP-2.31 STEAMLINE BREAK INSIDE CONTAINMENT.... 61 FNP-SIM-CTP -2. 3 2 STEAMLINE BREAK OUTSIDE CONTAINMENT, UPSTREAM OF MSIV.........,............ 63 FNP-SIM-CTP-2.33 STEAMLINE-FLOW TRANSMITTER FAILURE.... 65 FNP-SIM-CTP-2.34 STEAM DUMP VALVES FAIL TO OPERATE I IN T-AVE MODE......................... 67 FNP-SIM-CTP-2.35 STEAM HEADER PRESSURE CONTROLLER PT-464 FAILURE........................ 69 FNP-SIM-CTP-2.36 SOURCE RANGE CHANNEL FAILURE.......... 71 FNP-SIM-CTP-2.36.1 FAILURE OF SOURCE RANGE HIGH VOLTAGE TO DISCONNECT......................... 73 FNP-SIM-CTP-2.36.2 SOURCE RANGE CHANNEL HIGH VOLTAGE FAILURE............................... 75 FNP-SIM-CTP-2.36.3 SOURCE RANGE BLOWN FUSE............... 77 FNP-SIM-CTP-2.37 INTERMEDIATE RANGE CHANNEL FAILURE.... 79 I FNP-SIM-CTP-2.37.1 I.R. CHANNEL GAMMA COMPENSATION FAILURE............................... 81 I .
ATTACHMENT D.3
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ATTACHMENT _Di3 CERTIFICATION TEST ABSTRACTS 1
XALFUNCTIONS I PROCEDURE PROCEDURE TITLE PAGE FNP-SIM-CTP-2.37.2 INTERMEDIATE RANGE BLOWN FUSE......... 83 FNP-SIM-CTP-2.38 POWER RANGE CHANNEL FAILURE........... 85 FNP-SIM-CTP-2.38.1 POWER RANGE CHANNEL DETECTOR FAILURE., 87 FNP-SIM-CTP-2.38.2 POWER RANGE BLOWN FUSE................ 89 FNP-SIM-CTP-2.39 INADVERTENT REACTOR TRIP.............. 91 FNP-SIM-CTP-2.40 REACTOR TRIP BREAKERS FAIL TO OPEN.,... 93 I FNP-SIM-CTP-2.41 SAFEGUARD ACTUATION AND CONTAINMENT ISOLATION FAILURE..................... 95 FNP-SIM-CTP-2.42 PRESSURIZER STEAM SPACE BREAK......... 97 F6P-SIM-CTP-2.43 PRESSURIZER RELIEF VALVE FAILURE...... 99 FNP-SIM-CTP-2.44 PRESSURIZER SAFETY VALVE FAILURE...... 101 FNP-SIM-CTP-2.45 PRESSURIZER PRESSURE CHANNEL FAILURE.. 103 FNP-SIM-CTP-2.46 PRESSURIZER LEVEL MASTER CONTROLLER FAILURE............................... 105 FNP-SIM-CTP-2.47 PRESSURIZER LEVEL CHANNEL FAILURE..... 107 FNP-SIM-CTP-2.48 REACTOR COOLANT SYSTEM LEAK .......... 109 FNP-SIM-CTP-2.49 LOSS OF COOLANT ACCIDENT (LOCA)....... 111 FNP-SIM-CTP-2.50 STEAM GENER! TOR TUBE LEAK............. 113 FNP-SIM-CTP-2.51 REACTOR COOLLNT PUMP TRIP............. 115 FNP-SIM-CTP-2.52 FUEL CLADDING FAILURE................. 117 FNP-SIM-CTP-2.53 RCS LOOP PROTECTION RTD FAILURE....... 119 FNP-SIM-CTP-2.54 RCS LOOP CONTROL RTD FAILURE.......... 121 l
I FNP-SIM-CTP-2.55 RHR PUMP TRIP......................... 123 FNP-SIM-CTP-2.56 RHR HX BYPASS LINE BREAK.............. 125 FNP-SIM-CTP-2.57 TURBINE FIRST STAGE PRESSURE l TRANSMITTER FAILURE................... 127 ATTACRMENT D.3
e ATTACHMENT D.3 CERTIFICATION _ TEAT _AB.S. TRACTS MALFUNCTIONS PROCEDURE _ _ _ _ _
PROCEDURE TITLE PAGE FNP-SIM-CTP-2.58 GENERATOR AUTO VOLTAGE REGULATOR FAILURE............................... 129 FNP-SIM-CTP-2.59 AFW PUMP TRIP......................... 131 1
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ATTACHMENT D.3
FNP-SIM-CTP-2.1 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.1 RUVs 0 TYPE Malfunction TITLE: Failure of Instrument Air I REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(2), Loss of instrument air to the extent that the whole system or individual headera can lose pressure and affect the plant's static and dynamic performance APPROVED BY C. Mclean DATE APPROVED 12/12/90 TEST SCOPE 2NITIAL CONDITIONS: The simulator is running and operating at.50% steady acato power in accordance with procedu.a FNP UOP-3.1.
TEST INITIA'20R Tect three options, Malfunction PCS4, Option - 3, block automatic reactor trip, concurrent with:
(1) Malfunction AUX 1A, turbine building instrument ajr header leak, (2) Malfunction AUX 1B, auxiliary building instrument air header leak, (3) Malfunction AUX 1C, containment instrument air header leak.
PURPOSE: To ensure proper performance of valves, indications and alarms for a loss of instrument air pressure to l respective c.1pply headers.
TERMINAT. ION: Terminate when all the indications, alarms and valves are checked for proper responso to loss of instrument air.
!I 1 ATTACHMENT D.3
FNP-SIM-CTP-201 TEST RE8tTLTS
- DATE PERFORMED: 12/12/90 PERFORMED BYs P. Pappenfus I ACCEPTANCE CRITERIA: Plant Procedures, Plant Specific Data, Best Pstimate Judgement DESCREPANCIES: Nineteen valves were found to have not failed due to loss of instrument air to the approprir a supply header DEFICIENCIES REPORTED: SCR 90.219 Instrument Air Failure -
Improper Valve Response EECEPTIONS: None RESULTS: Satisfactory REVIEWED BY R. Wiggins I-I' COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams R. Wiggins C. Mclean DATE APPROVED: 12/13/90 l
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, F.iP-SIM-CTP-8 2 FARLEY WUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT
, , , TEST IDENTIFICATION _ _
PROCEDUR): (!C-SIM-CTP-2.2 REY: 0 TYPE Malfunction TITLE: Service Water Pum,. Trip I ;
REQUIREMENTS ANSI 3.5-1985 Section 3.1. 2 (6) , Loss of service water or cooling to individual components l APPROVED BY C. Mclean DATE APPROVEDI 9/5/90 I T,EST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-stato power in accordance with procedure FNP UOP-3.1 TE8T INITIATOR Malfunction AUX 4A, Option - Pump 1A.
PURPOSE: To ensure proper response of the simulator to a degraded service water system condition.
TERMINATION: Terminate when all alarms and indications are checktsd for proper I response to a loss of Service Water Pump 1A.
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FNP-SIM-CTP-2.2 TEST RESULT 5
- DATE PERFORMED: 9/20/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCRIPANCIE8: None DEFICIENCIES REPORTED: None EECEPTIONS: None RESULTS: Satisfactory REVIEWED BYt R. Wiggins COMNITTEE REVIEW I REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams R. Wiggins DATE APPROVED: 12/13/90 I
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FNP-SIM-CTP-3.3 FARLEY NUCLEAR PLANT SIMDLATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDUREt TNP-SIM-CTP-2.3 REVt 0 TYPE Malfunction TITLE CCW Pump Trip ANSI 3.5-1985 Section 3.1.2 (0) , Loss of I REQUIREMENTS component cooling system er cooling to individual components APPROVED BY C. Mclean DATE APPROVED 9/7/90 I TEST SCOPE INITIAL CONDITIONS: The simulater is running and operating at 100% steady-stato power in accordance with procedure FNP I UOP-3.1.
TEST INIT*-? ort Malfunction CCW1C, Option - Pump 1C.
PURPOSE: The purpose of this test is to evaluate the simulator response to degraded CCW system flow conditions.
TERMINATION: Terminate five minutes after the malfunction is cleared and the CCW I system is returned to normal operation.
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FNP-SIM-CTP-3.3
- TEST RESULTS DATE PERFORMED 9/20/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIE8 None DEFICIENCIES REPORTED: None EECEPTION8: None RESULTS: Satisfactory REVIEWED BY R. Wiggins I COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams R. Wiggins I C. Mclean DATE APPROVED: 12/13/90 I
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, FNP-SIM-CTP-8 4 FARLEY NUCLEAR PLANT SIMULATOR CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDUREt FNP-SIM-CTP-2.4 REVt 0 TYPE Malfunction TITLE Steam Jet Air Ejector Failure I REQUIREMENTS ANSI 3.5-1985 Section 3.1.2(5), Loss of condenser vacuum including loss of condenser level control APPROVED BYt C. Mclean DATE APPROVED: 9/5/90 -
I TEST SCOPE INITIAL CONDITION 81 The simulator is running and operating at 30% steady-state power in accordance with procedure FNP I UOP-3.1.
TEST INITIATOR: Malfunctior. CND4A, Option - fall I pressure ;egulator to O psia, with 30 seconds ramp time.
I PURPOSE To evaluate the simulator's response to a loss of condenser vacuum due to failure of a supply steam regulator for one of the main condenser steam air ejectors.
TERMINATION: Terminate the test 5 minutes after I the immediate actions of procedure FNP-1-AOP-3.0 and FNP-1-EEP-0 are completed.
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l FNP-SIM-CTP-3 4 TEST RE80LT5 DATE PERFORMED: 9/20/90 PERFORMED BY: P. Pappenfus I BASELINE DATA Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIEst None DEFICIENCIES REPORTED: None EECEPTION8: None RESULTS: Satisfactorf REVIEWED BY R. Wiggins COMMITTEE REVIEW I REVIEW COMMITTEE MEMBERS PRESENTt W. Vanlandingham L. Williams R, Wiggins -
DATE APPROVED 12/13/90 I
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FNP-SIM-CTP-2o5 I FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.5 REV 0 TYPE Malfunction TITLE: Hotwell Fill Controller CP-4055F Failure I REQUIRENENTS: 'AHSI 3.5-1985 Section 3.1.2(5), Loss of ec ondenser vacuum including loss of condenser level control APPROVED BY1 C. Mclean DATE APPROVED: 9/5/90 I TEST BCOPE INITIAL CONDITIONS The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction CNDS, Two options tested:
(1) Fill valve failed open, ramp time 10 seconds, (2) Fill valve failed closed, ramp time 10 seconds.
PURPOSE: To evaluate the simulator's response to a failure of the condenser hotwell fill valve.
TERMINATION: Terminate the test five minutes
- 3 after operator actions are taken to i3 manually control hotwell level and the hi/lo alarm is cleared.
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FNP-SIM-CTP-2.5 TEST RE8 ULT 8 DATE PERFORMED: 9/20/90 PERFORMED BY P. Peppenfus I BA8ELIME DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPAMCIES: None DEFICIENCIE8 REPORTED: None EXCEPTIOW8 None RESULT 88 Satisfactory REVIEWED BY: R. Wiggins COMMITTEE REVIEW W. Vanlandingham I REVIEW COMMITTEE MEMBERS PRESENT:
L. Williams R. Wiggins C. Mclean I DATE APPROVEDt 12/13/90 lI l
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FNP-SIM-CTP-2e6 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURBs FNP-SIM-CTP-2.6 REV 0 TYPE Malfunction TITLEt Hotwell Dump controller CP-4055G Failure REQUIREMENT 88 ANSI 3.5-1985 Section 3.1.2 (5) , Loss of l I condenser vacuum including loss of '
condenser level control APPROVED BY C. Mclean DATE APPROVEDI 9/5/90 I .
TEST SCOPE _
I INITIAL CONDITION 88 The simulator in running and operating at 100% steady-state power in accordance with procedure FNP 00P-3.1.
I TEST INITIATOR: Malfunction CND6, Two options (1) Test hotwell dump valve failed open, ramp time 10 seconds, I (2) Test hotwell dump valve failed closed, ramp time 10 seconds.
PURPOSE: To evaluate the simulator's response
'I to a loss of the condenser hotwell dump valve control.
l TERMINATION: . Terminate the test five minutes
, after operator actions are taken to
! manually control hotwell level and hi/lo hotwell level alarm is clear.
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FNP-SIM-CTP-2o6 TEST RESULT 5 .
DATE PERFORMED: 9/20/90 PERFORMED BYt P. Pappenfun 4 BASELINE N t'At Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCRIPANCIts None DEFICIENCIES REPOkTED: None IRCEPTIONS None RESULTS Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW , ._
W. Vanlandingham I REVIEW COMMITTEE MEMBER 8 PRESENT L. Williams R. Wiggins DATE APPROVED: 12/13/90 I
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o FNP-SIM-CTP-2.7 FARLEYNUCLEARPIkNTSINULATOR-CERTIFICATIONTESTABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.7 REV 0 TYPE Malfunction TITLE Rods Fall to Move in Auto REQUIREMENTS ANSI 3.5-1985 Section 3.1.2(13),
Inability to drive control rods APPROVED BYt C. Mclean DATE APPROVED 9/7/90 I .
TEST SCOPE I INITIAL CONDITIONS The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR Malfunction CRF2, followed by a 50%
load rejection.
PURPOSE To evaluate the simulator's response to a failure of the rod control system to function in automatic.
TERMINATION: Terminate the test after turbine load is stabilized, RCS Tave is restored to within 1.5 degrees of Tref and all expected indications are observed.
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FNP-SIM-CTP-8 7 TEST RESULTS DATE PERFORMED 9/21/90 PERFORNED BY P. Pappenfue EASELINE DATA: Plant Procedures, Plant Specific Data, Bes'; Estimate Judgement DESCRIPANCIES None DEFICIENCIES REPORTED: None EECEPTIONS None RESULTSt Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham I. L. Williams R. Wiggins DAT11 APPROVED 12/13/90 I .
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FNP-SIM-CTP-3.8 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.8 REvt 0 TYPE: Malfunction TITLE Rods Fail to Move in Manual I REQUIREXENTS:
ANSI 3.5-1985 Section 3.1.2(13),
Inability to drive control rods APPROVED BY C. Mclean DATE APPROVED: 9/7/90 I
I TEST SCOPE I INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
I TEST INITIATOR:
Malfunction CRF3 followed by a load rejection to 500 MWe.
PURPOSE To evaluate the simulator's response-to a failure of the rod control system to function in manual mode.
TERMINATION: Terminate the test after turbine load is stabilized, RCS Tavg is I returned to within 1.5 degrees of Tref and all expected indications are observed.
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FNP-SIM-CTP-208 fEST RESULTS DATE PERFORMED: 9/21/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific l Data, Best Estimate Judgement DESCRIPAMCIES: None DEFICIENCIE8 REPORTED: None RECEPTIONS None RESULT 8: Satisfactory REVIEWED BYt R. Wiggins I
COMMITTEE REVIEW I I REVIEW COMMITTEE MEMBERS PRESENTt W. Vanlandingham L. Williams R. Wiggins C. Mclean I DATA APPROVED 12/13/90 E
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THP-SIM-CTP-2.9 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT
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TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.9 REY: 0 TYPE Malfunction TITLEt Stuck Rod ANSI 3.5-1985 Section 3.1.2(12), Control I REQUIREMENTSt rod failure APPROVED BY C. Mclean DATE APPROVED: 9/11/90 TEST SCOPE I INITIAL CONDITIONS The simulator is running and operating at 100% steady-stato power in accordance with proceduro FNP UOP-3.1.
I TEST INITIATOR Malfunction CRF14A, Option -
Trippable, rod K6.
PURPOSE: To evaluate the simulator's responso to a stuck control rod.
TERMINATION: Terminate the test after inserting a manual reactor trip and verifing the correct status of the stuck control I rod.
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TNP-SIM-CTP-8 9 TEST RESULTS '
DATE PERFORMED 9/24/90 PERFORMED BY8 P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCRIPANCIEst None DEFICIRWCIES REPORTED None EXCEPTIONS: None RESULT 88 Satisfactory REVIEWED BY R. Wiggins COMMITThg' REVIEW g REVIEW COMMITTEE MEMBERS PRESENT! W. Vanlandingham 3 L. Williams R. Wiggins DATE APPROVED: 12/13/90 l -
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FNP-SIM-CTP-2.10 l
l FARLEY NUCf *AX PT&ll' BINULATOR - CERTIFICATION TEST ABSTRACT j TEST IDENTIFICATION l
PROCEDUREt FNP-SIM-CTP-2.10 REV8 0 TYPE Malfunction l TITLE Dropped Rod i
I REQUIREMENT 8 ANSI 3.5-1985 Section 3.1.2(12), Control rod failure APPROVED EY C. Mclean DATE APPROVED: 9/10/90 TEST SCOPE INITIAL CONDITIONS:
I The simulator is running and operating at 50% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction CRF15A, Option -
Stationary Coil, Rod K6.
PURPOSE To evaluate the simulator's response to a dropped control rod.
TERMINATION: Terminate the test after clearing the malfunction and recovering the dropped rod per procedure FNP-1-AOP-19.0 and restoring Tavg to normal.
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FNP-SIN-CTP-2.10 TEST RESULT 8 DATE PERFORMED 9/24/90 PERFORMED BYs P. Pappenfus I BASELINE DATA: Plarc Procedures, Plant Specific Data, Best Estimato Judgement DESCRIPANCIE8 None DEFICIENCIES REPORTED: None EXCEPTIONS None RESULT 8: Satisfactory REVIEWED BYt R. Wiggins I
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRE 8ENT: W. Vanlandingham L. Williams R. Wiggins I C. Mclean DATE APPROVEDs 12/13/90 I
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, FNP-SIM-CTP-2.11 FARLEY NUCLEAR PLANT SINULATCR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.11 REY: 0 TYPE: Malfunction TITLE: VCT Level Transmitter Failure REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(18), Failure of reactor coolant pressure and volume ,
.I control systems APPROVED BY C. Mclean .DATE APPROVED 9/11/90 TEST SCOPE INITIAL CONDITIONS I The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
I' TEST INITIATOR: Malfunction CVC10B - Four options tastedt (1) Channel LT-115 failed high, (2) Channel LT-115 failed low, (3) Channel LT-112 failed high, (4) Channel LT-112 failed low.
PURPOSE To evaluate the simulator's response to a failure of the various VCT level transmitters both high or low.
I TERMINATION: Terminate each test 5 minutes after all anticipated indications and alarms are observed for the respective failed channel.
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FNP SIM-CTP-2011 TEST RESULTS DATE PERFORMED: 9/24/90 PERFORMED BYt P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIE8: Charging pump flow continued with no level in the VCT.
DEFICIENCIES REPORTED: SCR 90.097, Charging Flow with VCT level = 0 EXCLPTION#8 None RESULTCt Satisfactory REVIEWED BYt R. Wiggins COMMITTEE REVIEW-REVIEW COMMITTEE MEMBERS PRE 8ENT4 W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED: 12/13/90 I
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FNP-SIM-CTP-2.12 I !
FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.12 REV 0 TYPE: Malfunction TITLE Degraded Grid Voltage - Loss of All Offsite Power ANSI 3.5-1965 Section 3.1.2(3a), Loss or I
- REQUIREMENTS
, degraded electrical power to the station, including loss of offsite power l APPROVED BY: C. Mclean DATE APPROVED: 12/11/90 I TEST SCOPE ,
INITIAL CONDITIONS The simulator is runnic operating at 100% steady' e power in accordance with procedure '.JP UOP-3.1.
TEST INITIATOR: Malfunction EPS1, Option - d voltage, 120 seconds ramp t- .
PURPOSE: To evaluate the simulator's response I to a degraded grid voltege and a subsequent loss of all r!Csite power.
TERNINATION: Terminate when all appropriate busses are de-energized, picked up by emergency diesels, sequencers I fully timed out, and all expected alarms and indications are observed.
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1 FNP-SIM-CTP-2.32 1
TEST RESULT 8 DATE PERFORMED 12/11/90 PERFORMED BY P. Pappenfus EASILINE DATA: Plant Proceduras, Plant Specific Data, Best Estimate Judgsment DESCRIPANCIE8 None LwFICIENCIES REPORTED: None IECEPTIONS None RESULT 88 Satisfactory REVIEWED BY R. Wiggins I COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENTI W. Vanlandingham L. Williams R. Wiggins
.l C. Mclean DATE APPROVED: 12/13/90 I
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FNP-SIM-CTP-2013 FARLEY WUCLEAR PLANT SINULATOR = CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE FNP-SIM-CTP-2.13 REY: 0 TYPE Malfunction TITLE 4160V Bus Trip ANSI 3.5-1985 Section 3.1.2(3d), Loss of I REQUIREMENT 8 power to the plant's electrical distribution buses APPROVED BYI C. Mclean DATE APPROVED: 9/11/90 TEST SCOPE INITIAL CONDITIONS The simulator is running and operating at 100% steady-state power in accordance with procedure PHP UOP-3.1.
TEST INITIATOR: Malfunction EPS2, Option - Failure of breaker DB01.
PURPOSE: To ensure the simulator's response to a 4160V bus breaker trip.
TERMINATION: Terminate when buses 1A and 1B transfar to the startup transformers and all expected alarms and indications are observed.
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ritT>=6TM-CTP-2 013 TEST RE8ULTS ,
DRTE PERFORMED: 9/24/90 PERFORMED B't: P. Pappenfus BASELINE DRTAR Plant Procedures, Plant Specific Data, Plant Electrical Distribution Diagrams, Best Estimate Judgement DESCREPAMCIES$ One bank of control room lighting did not respond to the loss of I power.
DEFICIENCIES REPORTED: SCR 90.095, Control Room Lighting EXCEPTIONS None RESULTS Satisfactory REVIEWED BY R. Wiggins b COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT! W. Vanlandingham L. Williams R. Wiggins C. Mclean DRTE APPROVEDI 12/13/90 I -
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FNP-SIM-CTP-2.14 FARLEY WUCLEAR PLANT SINULATOR - CERTIFICATION TEST AB8 TRACT TEST IDENTIFICATION PROCEDURE FNP-SIM-CTP-2.14 REY: 0 TYPEt Malfunction TITLE: EMERGENCY 4160V BUS TRIP REQUIREMENT 88 ANSI 3.5-1985 Section 3.1.2(3c), Loss of I emergency power APPROVED BY C. Mclean DATE APPROVED: 9/11/90 TEST SCOPE INITIAL CONDITIONS: The simulator is running and I operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR Malfunction EPS3A, Option Unit 1, Breaker DG13.
PJRPOSE To evaluate.the simulator's response to an emergency 4160V bus breaker trip.
TERMINATION: Terminate the test when all expected alarms and indications are observed.
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27 ATTACHMENT D 3
FNP-SIM-CTP-2.14 TEST RESULT 5 DATE P,ERFORMED 9/24/90 PERFORNED BY: P, Pappenfus EAsELINE DATA: Plant Procedures, Plant Specific -
Data, Plant Electrical Distribution Diagrams, Best Estimate Judgenent DESCRIPANCIES None DEFICIENCIES REPORTED 8 None EXCEPTIONst None RESULTSt Satisfactory REVIEWED BY R. Wiggins
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I COMMITTEPs REVIEW l I REVIEW COMMITTEE MEMBERfl PRE 8ENT! W. Vanlandingham L. Williana R. Wiggins
,g Cs Mclean ,
!3 DATE APPROVED 12/13/90
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PNPeSIM-CTP-2.15 FARLEY WUCMtAR PLANT L1(ULATOR - CERTIFICATION TEST ABSTRACT
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TEST IDf} TIFIC A' ION PROCEDURE: FNP-SIM-CTP-2.15 REV8 0 TYPE Malfunction TITLES Diesel Generator Failure - Essential Protection REQUIREMENTst ANOI 3.5-1985 Section 3.1.2(3c), Loss of nInorgency generators APPEDVED BY: C. Mclean DATE 7,PPROVED: 9/11/90 ]
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TEST SCOPE _
INITIAL CONCITIONS The simulator 13, running and I operating at 100% steady-state poWor 4n accordarice with procedure ntP UOP-3.1, i
TEST I'NITIATOR: Malfunction EPS48, Option 2 -
Differential Failure.
PURPOSE: To evaluate the sinulator's responso to a failure of'a dioso; generator I due to an essential protection trip.
TEAMIWATION: Toriainote when all expected alan's and indications are observod.
h I TECT RESULTS g Di.TE PERI'ORMED 9/24/90 PERFORMED DY: P. Pappenfus
, BASELINE DATA: Plant Procedures, Plant Specific Data, Da.it Estimate Judgement DESCREPANCIES Nono DEFICIENCIES REPokTED: None EXCEPTIONS None .
RESULTS: Satisfactory REVIEWED DY R. Viggins l 29 ATTACHMENT D.3 lI .
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FNP-SIM-CTP-2.15 '
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams I R. Wiggins
- c. Mclean DATE APPROVEDs 12/l,3/90 I
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FNP-SIM-CTP-2.16 I.
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FARLEY NUCLRAR PLANT SINUIO. TOR - CERTIFICATION TEST AB8 TRACT
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TEST 1DENTIFICATION*
PROCEDURE: FNP-SIM-CTP-2.16 REV 0 TYPE: Malfunction TITLE: Str.rtup Transformer Failure REQUIRENENT8: ANSI 3.5-1985 Section 3.1. 2 (3b) , Loss or I degraded electrical power to the station, including loss of offsite power APPROVED BY: C. Mclean DATE APPROVED: 9/1?/90 I _
TEST cdCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction EPS6A, Option 2 -
Startup Transformer 1B.
PURPOSE: To evaluate the simulator's responso I to a failure of a Startup Transformer.
TERNINATION: Terminate after the B1G sequencer I. has completed sequencing and all expected indications and alarms are observed.
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31 ATTACHMENT D.3 I
%SIM-CTP-2,16 L
TEST.RESULTS , ,
DATE PERFORMED: 11/6/90 PERFORMED BY P. P, s BASELINE DATA: Plant Procedures, Pl; , Specific Data, Plant Electrical Distribution Diagrams DESCREPANCIMS: None
. DEFICIENCIES REPORTED None EECEPT7CNS: None RESULTS: Satisfactory REVIEWED BY R. Wiggins I COMMITTEE REVIEW I REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams R. Wiggins C. Mclean DATE APPROVEDt 12/13/90
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. FNP-SIM-CTP-3.17 FARLEY NUCLMAR PLANT SIMULATOR = CERTIFICATION TEST AB8 TRACT I -
TEST IDENTI)"lCATION _,
PROCEDURE: FNP-SIM-CTP-2.17 REVt 0 TYPE Malfunction TITLEt 600V Load Center Trip REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(3d), Loss of I power to the plant's elect.rical distribution buses APPROVED BY: C. Mclean DATE APPROVED: 9/12/90 I TEST SCOPE INITIAL CONDITIONS The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATORt Malfunction EPS7A, Option - LCC-1D.
PURPOSE: To evaluate the simulator's response to' loss of a 600V Load Center.
TERNINATION: Terminate when all the expected indications and alarms are observed.
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FNP-SIM-CTP-2.17 TEST RESULTS DATE PERFORMED: 9/24/90 PERFORMED BYt P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Plant Electrical Distribution Diagrams DESCPTPANCIES: CRDM Fans 1A and 1B power supplies are reversed.
DEFICIENCIES REPORTED: SCR 90.094, CRDM Fan Power Supplies.
EECAPTIONS: Nono.
'tESULTS: Satisfactory REVIEWED BY R. Wiggins I
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham I L. Williams R. Wiggins C. Mclean DATE APPROVED: 12/13/90 I
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= FNP-SIM-CTP-2018 g- _
FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.18 REVt 0 TYPE: Malfunction TITLE: 600V Motor Control Center Trip REQUIRENENTS: ANSI 3.5-1985 Section 3.1.2(3d), Loss of power to the plant's electrical distribution buses APPROVED BYt C. Mclean ,
DATE APPROVED 9/20/90 TEST SCOPE I INITIAL CONDITIONS: The simulator is running and operating at 100% steady-stato power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction EPS8B, Option - MCC 1V.
PURPOSE: To evaluate the simulator's response to a 600V motor control center trip.
TERMINATION: Terminate when all expected indications and alarms are observed.
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l 35 ATTACHMENT D.3
lg FNP-5IM-CTP-8o18 TEST RESULTS DATE PERFORMED 9/25/90 PERFORXED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Plant Electrical Distribution Diagrams DESCREPANCIES: Eight of the loads off MCC-lv did not de-energize when the bus was dead. ,
DEFICIENCIES REPORTED: SCR 90.098, Electrical Loads not Lost During Malfunction EPS8B
-I Testing.
EXCEPTIONS None RESULTS: Satisfactory REVIEWED BY R. Wiggins I
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams R. Wiggins C. Mclean DATE APPROVED: 12/13/90
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FNP-SIM-CTP-2.19 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST AB8 TRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.19 R17: 0 TYPE Malfunction TITLE: 12CVAC Vital Instrunent invertet Failure REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(3e), Loss of I power to the individual instrumentation buses that provide power to control room indication or plant control functions affecting the plant's response APPROVED BY C. Mclean DATE APPROVED: 10/23/90 I
TEST SCOPE ,
IFITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power I- in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction EPS9A, Op' tion - Inverter 18.
I PURPOSE: To evaluate the simulator's response to a 120VAC vital instrument inverter failure.
TERMINATION: Terminate when all the expected indications and alarms are observed.
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FNP-SIM-CTP-2e19 I;
TEST RESULT 8 DATE PERFORMED: 11/06/90 PERFORMED BY P. Pappenfus
- BASELINE DATAt Plant Procedures, Plant Specific Data, Best Estimate Judgement DE8CREPANCIES: None DEFICIENCIES REPORTED: None EECEPTIONS None RESULTS Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW '
REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams I- R. Wiggins C. Mclean DATE APPROVED: *2/13/90 l
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FNP-SIM-CTP-2020 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST AB8 TRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.20 REV 0 TYPE Malfunction TITLE: 120VAC Instrument Distribution Panel Trip REQUIREMENTS ANSI 3.5-1985 Section 3.1.2(3e), Loss of I
power to the individual instrumentation ,
buses that provide power to control room indication or plant control functions affecting the plant's response APPROVED BY C. Mclean DATE APPROVED: 11/5/90 I
TEST SCOPE INITIAL CONCITIONS: The simulator in running and I operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction EPS10A, Option -
Inverter 1A.
I PURPOSE: To evaluate the simulator's response to a 120VAC vital instrumentation distribution panel trip.
TERMINATION: Terminate when all the expected indications and alarms are observed.
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FNP-SIM-CTP-2.20' TEST RE8ULTS DATE PERFORMED 11/6/90 PERFORMED BY: P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Plant Electrical Distribution Drawings DESCREPANCIES: Ten MCB indications did not fail on loss of power as expected.
DEFICIENCIEW REPORTED: SCR 90.199, 120VAC Inverter 1A Failure Response Not Obtained
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EXCEPTIONS None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams R. Wiggins C. Mclean DATE APPROVED 12/13/90 ,
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FNP-SIM-CTPc=2 0 21 FARLEY NUCLEAR PL7J.iT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE': FNP-SIM-CTP-2,21 REVt 0 TYPE Malfunction TITLE 120VAC Distribution Panel Trip REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(3e), Loss of I power to the individual instrumentation buses that provide power to control room indication or plant control functions affecting the plant's response APPROVED BY: C. Mclean DATE APPROVED: 11/5/90 l
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TEST SCOPE INITIAL CONDITIONS: The plant is in MODE 3, with all control rods inserted.
TEST INITIATOR: Malfunction EPS11B - Panel 1K trip.
PURPOSE: To evaluate the simulator's response to a 120VAC distribution panel trip.
l TERMINATION: Terminate the test when all expected l
alarms and indications are observed.
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41 ATTACHMEi?T D.3
FNP-SIM-CTP-2.21: l i
TEST RESULTS DATE PERFORMED 11/6/90 PERFORMED BY P. Pappenfus ,
BASELINE DATA: Plant Procedures, Plant Specific Data, Power Plant Electric'l Wiritj Diagrams, Best Estimate Judgement DESCREPANCIES: Some items on the BOP do not fail on a loss of power as they should DEFICIENCIE8 REPCRTED: SCR 90.200, 120VAC Panel 1K Power Failure Response Not obtained.
EXChPTIONS: None RESULTS: Satisfactory REVIEWED BY: R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESEWT W. Vanlandingham L. Williams R. Wiggins C. Mclean DATE APPROVEDs, 12/13/90 .
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FNP-SIM-CTP-2.22 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT I
TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.22 REV 0 TYPE: Malfunction TITLMt 125VDC Distribution Bus Trip REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(3e), Loss of power to individual instrumentation buses I that provide power to control room indication of plant control functions affecting the plant's response APPROVED DY: C. Mclean DATE APPROVED: 11/26/90 I
TEST SCOPE INITIAL CONDITIONS: The simulator is running and I operating at 10% power, maintaining feed on the bypass feedwater regulating valves, and the turbine not latched.
TEST INITIATOR: Malfunction EPS12B, B train 125VDC distribution failure.
PURPOSE: To evaluate the simulator's response to a 125VDC distribution bus trip.
TERMINATION: Terminate the test when all expected alarms and indications are observed.
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43 ATTACHMENT D.3
FNP-SIM-CTP-2.22 1
-TEST RESULT 8 I..
DATE PERFORMEDs. 12/7/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Plant Electrical Diagrams DESCREPANCIES Several valves identified by the
.I procedure table did not lose
-indication as expected.
Some Valves identifed by the procedure did not fail in the mode expected.
No local operator action is available to transfer Train B EPB annunciators between Unit 1 & 2.
Several valves which should be.
powered from A-Train 125VDC I. deenergized from only a loss of B-Train 125VDC.
DEFICIENCIES REPORTED: SCR 90.214 B-Train 125VDC Power Supplies.
SCR 90.215 EPB Annunciator Transfer LOA.-
SCR 90.216 A-Train 125VDC Power I' Supplies.
l EECEPTIONS: None
!I l RESULT 8 Unsatisfactory REVIEWED BY R. Wiggin's 1
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Venlandingham L L. Williams l
R. Wiggins
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FNP-SIM-CTP-So23 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST AB8 TRACT I
TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.23 REV 0 TYPE: Malfunction TITLE MDAFW FCV FAILURE REQUIRENENTS: ANSI 3.5-1985 Section 3.1.2(2. Passive I malfunctions in systems, such an engineered safety features, emergency feedwater systems APPROVED BY C. Mclean DATE APPROVED: 10/2/90 TEST SCOPE I INITIAL CONDITIONS: The simulator is running and operating in hot standby, mode 3 or I startup, mode 2 in accordance with procedure FNP-1-UOP-1.2.
TEST INITIATOR: Malfunction FWM4A - Two options:
(1) FCV failed open, (2) FCV failed closed.
PURPOSE: To evaluate the simulator's response I to a failure of a MDAFW flow control valve.
.l TERMINATION: Terminate the test five minutes E after all expected indications and alarms are observed.
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FNP-SIM-CTP-2e23 1
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l TEST RESULT 8 DATE PERFORMED: 10/2/90 PERFORMED BY P. Pappenfus BASELINE DATA Plant Procedures, Plant Specific Data, Best Estimate Judgement
-DESCREPANCIESt None DEFICIENCIES REPORTED: None I EECEPTIONS: None RESULT 8: Satisfactery REVIEWED BY: R. Wiggins.
COMMITTEE REVIEW kEVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams R. Wiggins DATE APPROVED: 12/13/90 I
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ATTACHMENT D.3 I
FNP-SIM-CTP-2.24 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT
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TEST IDENTIFICATION PROCEDURE FNP-SIM-CTP-2.24 REVt 0 TYPE Malfunction TITLE: SGFP TRIP ANSI 3.5-1985 Section 3.1.2(9), Loss of I REQUIREMENTS normal feedwater or Normal feedwater system failure APPROVED BY: C. Mclean DATE APPROVED: 10/2/90 I TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
- TEST INITIATOR: FWM11A - SGFP Pump 1A Trip PURPOSE To evaluate the simulator's response to a steam generator feed pump trip.
TERMINATION: Terminate the test five minutes after the reactor trips due to low steam generator level.
I TEST RESULTS DATE PERFORMED 1 11/3/90 PERFORMED BY: P. Pappenfus
,a BASELINE DATA: Plant Procedures, Plant Specific lg Data, Best Estimate Judgement 1
- DESCREPANCIES None 1
DEFICIENCIES REPORTED: None EXCEPTIONS: None -
RESULTS: Satisfactory REVIEWED BY R. Wiggins I
47 ATTACHMENT D.3
FNP-SIM-CTP-3 24 COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham-L. Williams R. Wiggins C. Mclean DATE APPROVED: 12/13/90 I ;
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FNP-SIM-CTP-2.25 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.25 REV 0 TYPE Malfunction TITLE: SGFP Failure To Auto Trip I REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(22), Process instrumentation, alarms, and control system failures APPROVED BY C. Mclean DATE APPROVED: 10/2/90 I TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP I UOP-3.1.
TEST INITIATOR: Malfunction FWM12,. Option - Block pump 1A auto trip.
PURPOSE To evaluate the simulator's response
,g to a SGFP failing to trip 5 automatically.
TERMINATION: Terminate the test five minutes after the affected pump is tripped locally.
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49 ATTACHMENT D.3 I
FNP-SIM-CTP-2.25 TEST RESULTS DATE PERFORMED: 10/3/90 PERFORMED DY: P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: Main feed pump auto trip failure ma1. function FWM12 - Automatic trip I block worked correctly, but when tripped manually, the feed pump did not stay fully tripped.
DEFICIENCIES REPORTED: SCR 90.099 - Main Feed Pump Auto Trip Failure Malfunction FWM12 EECEPTIONS:. None RESULTS: Satisfactory REVIEWED BY: R. Wiggins I
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams-R. Wiggins C. Mclean .
DATE APPROVED: 12/13/90
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FNP-SIM-CTP-2.26 l
TARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT
,I TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.26 REY: 0 TYPEt Malfunction ,
TITLE SGFP Turbine Speed Controller Failure ANSI 3.5-1985 Section 3.1.2(22), Process I REQUIREMENTS:
instrumentation, alarms and control system failures APPROVED BYt C. Mclean DATE APPROVED: 10/2/90 I.
TEST SCOPE TNITIAL CONDITIONS: The simulator is running and operating at 100% steady state power in accordance with procedure FNP U0P-3.1 TEST INITIATOR: Malfunction FWM13, Two options:
(1) Speed failure of 100%,
(2) Speed failure of 0%.
PURPOSE: To evaluate the simulator's response to a failure of the SGFP speed controller.
TERMINATION: Terminate when all the anticipated I indications are observed, the failed speed controller is placed in manual and feed pump speed is returned to normal.
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-FNP-SIM-CTP-2.26
. TEST RESULTS DATE '?ERFORMED: 10/3/90 PERFORMED BYt P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DE8CREPANCIE8 None DEFICIENCIES REPORTED: None EECEPTIONS: None RE8 ULT 8 Satisfactory REVIEWED BY: R. Wiggins I
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams R. Wiggins i C. Mclean DATE APPROVED: 12/13/90 ,
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FNP-SIM-CTP-2e2',
i FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2,27 REY: 0 TYPE Malfunction TITLE: Feedwater Header Pressure Transmitter PT-408 Failure REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(22), Process instrumentation, alarms, and control system failures APPROVED BY C. Mclean DATE APPROVED: 10/3/90 -
TEST SCOPE INITIAL CONDITIONS: The simulator is running and l operating at 50% steady-state power l in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction FWM15, Two optionst (1) PT-508 failed to O psig, 30 second ramp time, (2) PT-508 failed to 1400 psig, 30 second ramp time.
PURPOSE: To evaluate the simulator's response to a failure of the feedwater header pressure transmitter, PT-508.
TERMINATION: Terminate when either the plant trips due to low steam generator I levels or when feed pump speed control has been placed in manual, and feed pump RPM is returned to the pre-malfunction value.
53 ATTACHMENT D.3
FNP-SIM-CTP-2e27 TEST RESULTS DATE PERFORMED 10/3/90 PERFORMED BY P..Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None EECEPTION8: None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham I L. Williams R. Wiggins C. Mclean DATE APPROVED 12/13/90 I-l l
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FNP-SIM-CTP-2.2B FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST AD8 TRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.28 REVt 0 TYPE: Malfunction TITLE S/G Level Channel Failure
' ANSI 3.5-1985 Section 3.1.2(22), Process I REQUIREMENTS:
dnstrumentation, alarms, and control system failures APPROVED BY C. Mclean DATE APPROVED: 10/2/90 I TEST SCOPE INITIAL CONDITION 8: '
The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UDP-3.1.
TEST INITIATCRs Malfunction FWM26A and FWM26B, Four options:
(1) Level channel LT-474, protection channel, failed to 100%,
I ramp time, 30 second (2) Levol channel LT-474, protection channel, failed to 0%, 30 second ramp time, I (3) Level channel LT-473, control channel, failed to 100%, 30 second ramp time, (4) Level channel LT-473, control channel, failed to 0%, 30 second ramp time.
PURPOSE: To evaluate the simulator's response to a failure of a steam generator I level channel, either protection or control.
I TERMINATION: Terminate the test when all expected alarms and indications are observed.
I 55 ATTACHMENT D 3
FNP-SIM-CTP-2,28 l
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TEST R28 ULT 8 c . ,
DATE F.RFOR".ED:
M 10/3/90 PERP6RE20 BY: P. Poppenfus BASELINE DATA: Plant Procadgres, Plant Specific j Data, Best Estimate Jtadgement DESCREPANCIE8: None {
l DEFICIENCIES REPORTED: None l li EECEPTIONS: None l RESULTS: Satisfactory REVIEWED BYt R. Wiggina l
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESEWT W. Vanlandingham L. Williams i R. Wiggins ;
I C. Mclean DATE APPROVED 12/13/90 i
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FNP-SIM-CTP-2.29 J
FARLEY NUCL'AR PLANT SINULATOR - CERTIFICAT N TEST MSTP.ACT TEST IDENTIFICATION , __
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PROCEDURE: FNP-SIM-CTP-2.29 REV 0 TYPE: Malfunction I TITLEt S/G Feedline Break outside Containmelit, Downetream of Stop Check Velve l
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REQUIREMEt?tS ANSI 3.5-1985 Section 3.1.2(20), Main steam lines as well os akin feed line break I APPROVED BY C. Mclean DATE APPROVEOt 10/2/90 ; 4 I INITIAL CONDITIC,NS TEST SCOPE The simulator is running and
__J operating at 100% steady state power
.I in accordance with procedure FNP UOP-3.1.
I TEST INITIATORS Malfunction FWF27, option - bresk size 20E+6 lbm/hr, 600 second ramp time.
PURPOSE: To evaluate the simulator's response to a ateam generator feedline break outside of containment, downstream ot' the stop check valve.
l TERMINATION: Terminate the test ofter isolating the steam generator, establishing criteria for and terminating Safety Injectiori.
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I 57 ATTACHMENT D.3
7 F.}P-SIM-CTP-2.29 i
, . TAT .F. ltE.C'".*sTS i
b & W PERFORMED: .* 0/4/00 P!3tFORi!ED BY: P. Pappenfus j,i/ 2AA$iTNE DATAs Pln,1t Procedures, Plant Specific
'9ata, Best Estimate Judgement l
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'AFSt!RE1WidIES : None t .hg DEF2CERNCIES REPORTED: None EXCEPTIOW8 None
-REGULT/l S tisfactory REVTEWED BY: R. Wiggins c
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COMMITTEE REVIEW , _, ,
REVIEW CVMMITTEE MEMBERS PRESENT: W. Vanlandingham c- L. WilliaMG R. Wiogins .,
C. Mclean 1
DATF,A1 PROVED: 12/13/90 I
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FNP-SIM-CTP-3 30 FARLEY WUCLEAR PLANT SIMULATOR ~ CERTIPICATION TEST ABSTRACT TEST .iDr.NTIFICATION PROCEDURE: FNP-SIM-CTP-2.30 REVt 0 TYPE: Malfunction TITLE Feedline Break Inside Containment ANSI 3.5-1985 Section 3.1.2(20), Main I REQUIREMENTS steam line as well as main feed line break APPROVED BYt C. Mclean DATE APPROVED 10/2/90 TEST SCOPE INITIAL CONDI'TIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP I UDP-3.1.
TEST INITIATOR: Malfunction FWM28C, Option - break I size 4.0E+6 lbm/hr, ramp time 300 seconds.
I PURPOSE: To evaluate the simulator's response to a feedline break insido containuent.
TERMINATION: Terminate after all actions are taken per ommergency procedures, the generator is isolated and safety l injection criteria is achieved.
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I'NP-SIM-CTP-2 . 3 0 TEST RESULTS DATE PERFORMED: 10/5/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCRIPANCIEst None DEFICIENCIES REPORTED: None EECEPTION8: None RESULT 8 Satiwfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW
~E REV;LW COMMITTEE MEMBERS PRESENT! W. Vanlandinghan 5 L. Wil11ama R. Wiggins DATE APPROVED 12/13/90 I
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__ _ a a .. s m , _ _ _ . - _a - _.4 _ _a FNP-SIM-CTP-2.31 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDfiRE: FNP-SIM-CTP-2.31 REY: 0 TYPE: Malfunction TITLE Steamline Break Inside Containment I REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2 (20) , Main steam line as well as main feed line break APPROVED BY C. Mclean DATE APPROVED: 10/18/90 I TEST SCOPE INITIAL CONDITIONSt The simulator is running and operating at 100% steady-state power in accordanr/e with procedure FNP I UOP-3.1 TEST INITIATOR: Malfunction MSS 1A, Option - break I size 1.2E+7 lbm/hr, ramp time 60 seconds.
I PURPOSEt To evaluate the simuletor's response to a main steamline bank inside containment.
TERMINATION: Terminate after completing actions of the emergency procedures and establishing Safety Injection termination criteria.
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FNP-SIM-CTP-2.31 TEST RESULTS DATE PERPORMED: 10/20/90 PERFORMED 13Y: P. Pappentus RAsELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCRIPANCIES: None DEFICIENCIES REPORTED: None EXCEPTIONS None RESULTS: Satisfactory REVIEWED BY: R. Wiggins I COMMITTEE REVIEW ,
REVIEW COMMITTEE MEMBERS PRE 8ENT! W. Van 7ar.dingham L. Willlah's R. Wiggins C. Mcle'an DATE APPROVED: 12/13/90 I
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FNP-SIM-CTP-2.32 l
FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATICN TEST ABSTRACT TEST IDENTIFICATION PROCEDUREt FNP-SIM-CTP-2.32 REV1 0 TYPE Malfunction TITLE: Steamline Break Outside Containment, Upstream of MSIV I REQUIRENENT88 ANSI 3.5-1985 Section 3.1.2(20), Main steam line as well as main feed line break APPROVED BY C. Mclean DATE APPROVED 1.0/18/90 TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-stato power in accordance with procedure FNP I UOP-3.1.
TEST INITIATOR Haltunction MSS 2A, Option - break I size to 1.2E+7, ramp time 60 seconds. '
PURPOBE To evaluate the simulator's response to a main steamline break outside of containment and upstrsam of the MSIV.
TERNINATION: Terminate after emergency procedure
. actions are taken, the generator is I isolated and safety injection termination criteria is met.
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TEST RESULTS DATE PERFORMED: 11/7/90 PERFORMED BYt P. Pappenfus BASILINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DE8CREPANCIEs None DEFICIENCIES REPORTED: None O
EXCEPTIONS None RESULTS Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW I
REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams '
R. Wiggins C. Mclean DATE APPROYED: 12/13/90 I
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FNP-SIM-CTP-3.33
" FARLEY NUCLEAR P! ANT SINULATOR - CERTIFICATION TEST ABSTRACT B .
TEST IDENTIFICATION PROCEDURE FNP-SIM-CTP-2.33 REV 0 TYPE: Malfunction TITLE Steamline Flow Transmitter Failure ANSI 3.5-1985 Section 3.1.2(22), Process I REQUIREMENT 88 instrumentation, alarms and control system failures APPROVED BY C. Mclean DATE APPROVED 10/18/90 I TEST SCOPE INITIAL CONDITIONS: The simulator is running nd operating at 100% steady-state power in accordance with procedure FNP I UOP-3.1.
TEST INITIATOR Malfunction MSS 7A, Two optionst (1) Flow channel FT-474 failed high, ramp time 120 seconds, (2) Flow channel FT-474 failed low, ramp time 120 seconds.
PURPOSE To evaluate the simulator's response to a failure of a steamline flow transmitter. -
I TERMINATION: Terminate after all anticipated indications are observed and steam I generator levels are controlled in manual.
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FNP-SlM-CTP-2.33 l
TEST RESULTS DATT PERFORMEDI 10/20/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCRIPANCIES: None DEFICIENCIES REPORTED: None EXCEPTION 88 None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW W. Vanlandingham I REVIEW COMMITTEE MEMBERS PREBERT:
L. Williams R. Wiggins C. Mclean I DATE APPROVEDI 12/13/90 ,
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. FNP-SIM-CTP-2.34 FARLEY NUCLEAR PIANT SIMULATOR - CERTIFICATION TEST AB8 TRACT
, TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.34 REY: 0 TYPE: Malfunction TITLE: Steam Dumps Fall to Operate in T-Ave Mode I REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(17), Failure in automatic control systems that affect reactivity and core heat removal APPROVED BY C. Mclean DATE APPROVED . 10/8/90 I TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-stata power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction MSS 10 active and I commence a load decrease to 600 Mwe at 200 MW/ min.
PURPOSE To evaluate the simulator's response to a failure of the steam dumps to operate in the T-AVE mode.
TERMINATION: Terminate after Tave is returned to within i 5 degrees.
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FNP-SIM-CTP-2.34 TEST RESULT 8 .
DATE PERFORMED 10/20/90 PERFORMED BY: P. Pappenfus BASELINE DATA Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCRIPANCIES: None DEFICIENCIES REPORTED: None EECEPTIONS None RESULT 88 Satisfactory REVIEWED BY: R. Wiggins I- COMMIT'rEE REVIEW I REVIEW COMMITTEE MEMBERS PRESENT! W. Vanlandingham L. Williams R. Wiggins
- c. Mclean ,
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TNP-SIM-CTP-2o35 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST A98 TRACT
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TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.35 REY: 0 TYPEt Malfunction TITLE: Steam header Pressure Controller PT-464 Failure
' REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(22), Process e instrumentation, alarms and control system failures APPROVED BY C. Mclean DATE APPROVED: 10/22/90 I TEST SCOPE INITIAL CONDITIONS: The simulator is running with the reactor critical, 7-10% power, waiting to roll the main turbine.
TEST INITIATOR: Malfunction MSS 11, Two options:
(1) Pressure transmitter, PT-464, I. . failed low, ramp time 30 seconds, I (2) Pressure transmitter, PT-464, failed high, ramp time 30 seconds.
PURPOSE: To evaluate the simulator's response to a failure of PT-464, input to the steam header pressure controller.
I TERMINATION: Terminate the test when all expected alarms ad indications are observed.
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-FNP-SIM-CTP-2.35 TEST RESULT 8 DATE PERFORMED 10/24/90. PERFORMED BY P. Pappenfus BASELINE DATA Plant Procedures, Plant 3pecific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIE8 REPORTED: None EXCEPTIONS: None RESULT 8 Satisfactory REVIEWED BY R. Wiggins I COMMITTEE REVIEW REVIEW COMMITTEE MEMBER 8 PRE 8ENT W. Vanlandingham L. Williams R. Wiggins I C. Mclean DATE APPROVED 12/13/90 if I
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FNP-SIM-CTP-2.36 I FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.36 REY: 0 TYPE: Malfunction TITLE: Source Range Channel Failure I REQUIRENENTS ANSI 3.5-1985 Section 3.1.2((21),
Nuclear instrumentation failure APPROVED BY C. Mclean DATE APPROVEDI 10/18/90 TEST SCOPE INITIAL CONDITIONSt The simulator is running ar.d maintaining hot standby cc..Jitions, prior to a reactor startup.
TEST INITIATOR Malfunction NIS1A, Option - failure value 10 CPS, ramp time 60 seconds.
I PURPOSE To evaluate the simulator's response to a source range channel failure.
TERMINATION: Terminate the test when all expected alarms and indications are observed.
TEST RESULTS DATE PERFORMED 10/20/90 PEkrORMED BY P. Pappenfuc BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None EXCEPTIONS None RESULTS: Satisfactory REVIEWED BY: R. Wiggins I
71 ATTACHMENT D.3
FNP-SIM-CTP-3.36 COMMITTEE REVIEW REVIEW COMMITTEE XEMBERS PRESENT: W. Vanlandingham L. Williams l R. Wiggins C. Mclean DATE APPROVED 12/13/90 I
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l TNP-SIM-CTP-2.36.1 FARLEY NUCLEAR PLANT SIN TOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURT. FNP-SIM-CTP-2.36.1 REV 0 TYPE: Malfunction TITLE: Failure of Source Range High Voltage to Disconnect I REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(21), Nuclear Instrumentation Failures APPROVED BYt C. Mclean DATE APPROVED: 10/18/90 I
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TEST SCOPE I INITIAL CONDITIONS The simulator is running and operating in hot standby in accordance with procedure FNP-1-UOP-1.2 TEST INITIATORt Malfunction NIS4B.
PURPOSE: To evaluate the simulator's response to a failure of the source range high voltage to disconnect.
TERMINATION: Terminate after reactor power increases above P-10 setpoint, and I all indications and alarms are observed.
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1 FNP-SIM-CTP-2.36.1 TEET RESULTS l DATE PERFORMED 10/20/90 PERFORMED BY P. Pappenfus i R BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement ;
DESCREPANCIE8: Nona l DEFICIENCIES REPORTED: None EXCEPTIONS None RESULTS: Gatisfactory REVIEWED BY R. Wiggins I COMMITTEE REVIEW I REVIEW COMMITTEE MEMBERS PRESENT: W. Vanla14dingham L. Williams R. Wiggins C. Mclean DATE APPROVED 12/13/90 I
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FNP-SIM-CTP-2.36.2 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.36.2 REY: 0 TYPE Malfunction TITLE: Source Range Channel High Voltage Failure l REQUIREMENT 8 ANSI 3.5-1985 Section 3.1.2(21), Nuclear 5 instrumentation failure APPROVED BYt C. Mclean DATE APPROVED 10/18/90 I
I TEST SC, OPE I INITIAL CONDITIONS: The simulator is running and operating in hot standby in accordance with procedure FNP-1-UOP-1.2.
TEST INITIATOR: Malfunction NIS2B, Option - voltage failure to 2500 volts.
I PURPOSE: To evaluate the. simulator's response to a source range channel high voltage failure.
TERMINATION: Terminate the test when all expected alarms and indications are observed.
I TEST RESULTS l DATE PERFORMED! 10/24/90 PERFORMED BY P. Pappenfus l
BASELINE DATA: Plant Procedures, Plant Gpecific Data, Best Estimate Judgement DESCREPANCIES: None
'I DEFICIENCIES REPORTED: None EXCEPTIONS: None ~
l RESULTSt Satisfactory REVIEWED BY R. Wiggins l
75 ATTACHMENT D.3
FNP-SIM-CTP-2.36.2 ,
i COMMITTRE REVIEW REVIEW COMMITTEE MEMBERS PRESENT! W. Vanlandingham I L. Williams R. Wiggins C. Mclean DATE APPROVEDI 12/13/90 I
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FNP-SIM-CTP-2.36.3 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST A:38 TRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.36.3 REV8 0 TYPE: Malfunction TITLE: Source Range Blown Fuse I REQUIRENENTS: ANSI 3.5-1985 Section 3.1.2(21), Nuclear Instrumentation Failure APPROVED BY: C. Mclean DATE APPROVED 10/18/90 I TEST SCOPE
, INITIAL CONDITIONS: The simulator is running and maintaining hot standby conditions in accordance with procedure PHP , UOP-1.2.
TEST INITIATOR: Malfunction NISSA.
PURPOSE: To evaluate the simulator's response to a source range blown fuse.
TERMINATION: Terminate the test when all expected i
alarms and indications are observed.
I TEST RESULTS DATE PERFORNED: 10/20/90 PERFORNED BY: P. Pappenfus lI
( BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estime,te Judgement DESCREPANCIES None l
DEFICIENCIES REPORTED: None EXCEPTIONS None RESULTS: Satisfactory REVIEWED BY: R. Wiggins I
77 ATTACHME:NT D.3
a -- + w-- Ge Ab + -- 6 i' -~A-A.m. -Ewuum,,,.L-a. Os-4 .42- A,-dn,J 4 a 4- e .a ss.,.m. r.s_4A6. Asn,mua FNP-SIM-CTP-2e36.3 I CoxxrTT arvrE.
REVIEW COMMrTTF.E MEMBERS PRE 8ENTt W. Vanlandingham L. Williams R. Wiggins DAT.1 APPROTEDI 12/13/90 e
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FNP-SIM-CTP-2.37 I .
IFARLEYWUCLRARPLAFTSINULATOR~CERTIFICATI
'I TEST IDENTIFICATION PROCEDURE: FNP-SIM-0TP-2.37 REY: 0 TYPE Malfunction TITLE: Intermediate Range Channel Failure REQUIRENENTS ANSI 3.5-1985 Section 3.1.2(21), Nuclear Instrument Failure APPROVED BY: C. Mclean DATE APPROVED 10/18/90 TEST SCOF2 INIT7.AL CONDITIONS The simulator is running with the reactor critical and power being maintained less than 10%.
TEST INITIATOR: Malfunction NIS68, Option- failure value 1.0E-3 amps.
PURPO8Et To ovalurte the simulator's response to an intermediate range channel failure.
TERMINATION: Terminate the test when all expected alarms and indications are cbserved.
.I TEST RESULTE DATE PERFORNED 10/20/90 PERFORMED BY: P. Pappenfus Llm BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIE8: None l DEPICIENCIES REPORTED: None EXCEPTION 88 None RESULTS Satisfactory REVIEWED DY R. Wiggins I
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FNP-SIM-CTP-2.37 .
I COMMITTEE REVIEW _
REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham I- L. Williams R. Wiggins C. Mclean DATE APPROVED: 12/13/00 )
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I FNP-SIM-CTP-2.37e1 I FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.37.1 REV 0 TYPE Malfunction TITLE I.R. Channel Gamma Compensation Failure REQUIREMENTS: ANSI 3.5-1985 Section 2.37.1, I.R.
Channel Gamme Compensation Failure APPROVED BY C. Mclean DATE APPROVED: 10/18/90 I
TEST SCOPE INITIAL CONDITIONSt The simulator is running and operating at 100% steady-state power I in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction HIS7A, Two Optionst (1) Compensation voltage failed low, '
1E-10 amps, -
(2) Compensation voltage failed high, -7E-10 amps.
PURPOSE: To evaluate the simulator's response to an intermediate range channel gamma compensation failure.
TERNINATION: Terminate the test when all expected alarms and indications are observed. ,
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FNP-SIM-CTP-2o37.1 I TEST RESULTS DATE PERFORMED: 10/22/90 PERFORMED BYi P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific I Data, Best Estimate Judgement DESCREPANCIE#: None DEFICIENCIES REPORTED: None r
IECEPTIONS: None RESULTS Satisfactory REVIEWED BY: R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams I R. Wiggins '
C. Mclean DATE APPROVED: 12/13/90 I
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I FNP-SIM-CTP-2.37.2 FARLEY NUCLEAR PLANT SINULA*0R - CERTIFICATION TEST ABSTRACT I TEST IDEN7IFICATION PROCEDUREt FNP-SIM-CTP-2.37.2 REV8 0 TYPEt Malfunction TITLE Intermediate Range Blown Fuse REQUIREMENT 88 ANSI 3.5-1985 Section 3.1.2(21), Nuclear Instrumentation Failure APPROVED BYt C. Mclean DATE APPROVED 10/18/90 I TEST SCOPE INITIAL CONDITION 81 The simulator is running with the reactor critical and power less than 10%.
TEST INITIATOR Malfunction NIS8A, Two options (1) Blown control power fuse, (2) Blown instrument power fuse.
PURPOSE To evaluate the simulator's response to an intermediate range instrument blown fuse.
TERMINATIONt Terminate the test when all expected alarms and indications are observed.
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FNP-SIM-CTP-2.37.2 TEST RESULTS DATE PERFORMED 10 0/90 PERFORhED BY P. Pappenfus BASELINE DATA Plant Procedures, Plant Specific I Data, Boat Estimate Judgement DESCRIPRNCIES: The high level rod stop light and I bistabic spara light did not come on when the instrument fuse was blevn.
I DEFICIENCIE8 REPORTED: SCR 90.131, I.R. HIS Blown Instrument Fuset Distables Not Coming In.
EECEPTIONS: None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW _
REVIEW COMMITTEE MEMBERS PRESENTl W. Vanlandingham I L. Williams R. Wiggine O. Mclean DRTE APPROVED: 12/13/90 I
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I , FNP-81M-CTP-2.38 I
FARLEY NUCLRAR PLANT WINULATOR - CERTIFICATION TEST AP6TkACT
.r .J I TEST IDENTIFICATION _ _ .
PROCEDURES FNP-SIM-CTP-2.?8 REV8 0 TYPE: Malfunctjen I
TITLRt Power Range Channel Failure REQUIREMENTS. AhST .5-1985 Section 3.1.2(21), Nuclear Intetrumentation Philure APPROVED BYt C. Mclean DATE APPROVZDs 10/18/90 I TEST SCOPE INITIAL CONDITION 8 The simulator is running and oporating at 100% steady-state power in accordance with procedure FNP 00P-3.1.
't TX8T INITIATORt Malfunction NIS10C, Two options:
I (1) Power range fails high, 115%,
(2) Power range fails low, 0%.
PURPOBEt To evaluate the simulator's response to a power range channel failure.
TERMINATION: Tezuinate the test when all expected alarms and indications are observed.
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I FNP-SIM-CTP-8.38 g -
TE!;T AESULTS .
DATE PERFORMED 10/22/90 PEDFORWZD BYt P, Pappenfus BASELINE DATA: Plant Pricedures, Plant Specific
'N % , Best Estimate Judganent DESCREPANCIES: None DEFICIENCIES REPORTED None EECEPTION8: None RESULT 81 Satisfactory REVIEWED BY R. Wigginti COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT! W. Vanlandingharn L. Williams R. ,/iggina I C. Mclean DATE APPROVED: 12/13/90 I
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FAGEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST AB8 TRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.38.1 REVt 0 TYPE: Malfunction TITLE: Power Range Channel Failure h
REQUIRf.MENTS: ANSI 3.5-1985 Section 3.1.2(21), Nuclear e Instrumentation Failure APPROVED BY: C. Mclean DATE APPROVED: 30/18/90 TEST SCOPE INITIAL CONDITIONS: The simulatot is running and operating at 100% steady-state power I in accordance with procedure FNP UOP-3.1, with control rods in automatic mode.
TEST INITIATOR: Malfunction NIS9H, Two options:
(1) Channel detector failed high, 5 milliamps, (2) Channel detector failed low, o milliamps.
PURPOSE: To evaluate the simulator's response to L power range channel detector I failure. 9 TERMINATION: Terminate the test when al? expected alarms and indications are observed.
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FNP-SIM-CTP-2.3e.1 g
TEST RESULTS DATE PERFORMED 10/22/90 PERFORMED BY P. Pappenfus JA8ELINE DATA: Plant Procedures, Plant Specific I DESCREPANCIES:
Data, Best Estimate Judgement None DEFICIENCIES REPORTED: None ExCOTICAIS: None RESULTS: Satisfactory P1HVIEWED BYt R. Wiggins 9J l 4:
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED: 12/13/90
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I. FNP-SIM-CTP-2.38.2 FARLEY NUCLEAR PLMIT SIMULATOR - CERTIFICATION TEST ABSTRAC I- TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.38.2 REY: 0 TYPE: Malfunction TITLE: Power Range Blnwn Fuse REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(21), Nuclear Instrumentation Failure APPROVED BY C. Mclean DATE APPROVED: 10/19/90 TEST SCOPE INITIAL CONDITIONS: The simulator is running and opereting.at 100% steady-state power I in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction NIS11B, Two options:
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PURPOSEt To evaluate the simulator's response to a power range blown fuse.
TERMINATION: Terminate the tsst when all expected alarms and indications aru observed.
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FNP-SIM-CTP-2.38.2 g-TEST RESULTS DATE PERFORMED 10/22/90 PERFORMED BY: P. Pappenfus BASELINE DATA: Plant Procedures, Plent Specific I Data, Best Estimate Judgement DESCREPANCIES: Annunciator F23 did not alarm.
I Status light 12.2 did not illuminate. Rate bistable and spare bistable status lights did not turn on with a blown instrument fuse.
DEFICIENCIES REPORTED: SCR 90.132, Power Range NIS blown Instrument Power Fuse.
EXCEPTIONS: None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham I L. Williams R. Wiggins DATE APPROVED: 12/13/90 I
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FNP-SIM-CTP-2.39 I. FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.39 REV 0 TYPE Malfunction TITLE: Inadvertent Reactor Trip REQUIREMENTS: AN'SI 3.5-1985 Section 3.1.2(19), Reactor trip APPROVED BY: C. Mclean DATE APPROVED: 10/18/90 TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power 3 in accordance with procedure FNP J UOP-3.1.
I TEST INITIATOR: Malfunction PCS1A.
I PURPOSE: To evaluate the simulator's response to an inadvertent reactor trip.
TERMINATION: Terminate the test after observing
, proper responsc. of indication and alarms and establishing hot standby conditions in accordance with procedure FNP-1-UOP-2.1.
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FNP-SIM-CTP-2.39 I TEST RESULTS
- DATE PERFORMED: 10/22/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific
- Data, Best Estimate Judgement DESCREPANCIES
- None DEFICIENCIES REPORTED: None EXCEPTIONS None RESULTS Satisfactor'f REVITiWED BYt R. Wiggins COMMITTEE REVIEW
, REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham l L. Williams R. Wiggins
.I' C. Mclean f-B' DATE APPR vra : 12/13/90 W . ..J l- ,
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I.- FNP-SIM-CTP-3.40 I FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.40 REV 0 TYPE: Malfunction TITLE: Reactor Trip Breakers Fail to Open REQUIREMEkC8 ANSI 3.5-1985 Section 3.1.2(24), Failure of the automatic trip system APPROVED BY: C. Mclean DATE APPROVED 10/18/90 I
TEST SCOPE
-INITIAL CONDITIONS The simulator is running and operating at 100% steady-state power I in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction PCS4, Nine options:
I (1) A-Train auto trip f ailure, (2) B-Train auto trip failure, (3) Both trains auto trip failure, (4) A-Train manual trip failure, (S) B-Train manual trip failure, I. (6) Both trains manual trip failure, (7) A-Train mechanical failure, (B) B-Train mechanical failure, (9) Both trains mechanical failure.
PURPOSE: To evaluate the simulator's response I_ to a failure of one or all of the reactor trip breakers to open.
TERMINATION: Terminate the test after observing proper control rod position and trip breaker status.
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MfP-SIM-CTP-2.40 I TEST RESULTS
-DATE PERFORMED 10/22/90 PERFORMED BY P. Pappenfus Plant Procedures, Plant Specific I BASELINE DATA:
Data, Best Estimate Judgement DESCREPANCIEst None DEFICIENCIES REPORTED: None EECEPTIONS None RESULTS: Satisfactory REVIEWED BY R. Wiggins I -
l COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PREBENT W. Vanlandingham L. Williams R. Wigginn C. Mclean DATE APPROVED: 12/13/90 I
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I FNP-SIM-CTP-2.41 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT I TEST IDENTIFICATION PROCEDURES. FNP-SIM-CTP-2.41 REY: 0 TYPE: Malfunction TITLE: Safeguard Actuation and Containment Isolation Failure I REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(23), Passive malfunctions in systems, such as I engineered safety features, emergency feedwater systems
- APPROVED BY: C. Mclean DATE APPROVED: 10/18/90
! TEST SCOPE lE' E
INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
lI' I ' TEST INITIATOR: Malfunction PCSSB and Malfunction PCS5A with a f#ilure value of 100%.
lI PURPOSE: To evaluate the simulator's response to a safeguards actuation and containment isolation failure.
TERMINATION: Terminate the test after procedure
.g FNP-1-EEP-0, Reactor Trip or Safety
!3 Injection directs you to branch to FNP-1-EEP-1.
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I 95 ATTACHMENT D.3
FNP-SIM-CTP-2,41 I TEST RESULTS l
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DATE PERFORMED:- 11/6/90 PERFORMED BY P. Pappenfus BADELINE DATA:
I Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None t
EECEPTIONS None RESULT 82 Satisfactory REVIEWED BY: R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams R.*Wiggins I- C. Mclean DATE APPROVED I .12/13/90 I4
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I FNP-SIM-CTP-FNP-SIM-CTP-2.42 I F l-FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.42 REV 0 TYPE Malfunction
. TITLE: Pressuriter Steam Space Break REQUIREMEL*TS ANSI 3.5-1985 Section 3.1. 2 (1b) , Loss of coolant inside and outside primary containment APPROVED BY: C. Mclean DATE APPROVED 10/18/90 TEST SCOPE INITIAL CONDITIONS: The simulator is running and I operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction PRS 1, Option - Leak size of 800 gpm, ramp time 300 seconds.
I PURPOSE: To evaluate the simulator's response to a pressurizer steam space break.
TERMINATION: Terminate the test when the pressurizer is solid and RCS pressure is above saturation conditions and stabilized.
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I FNP-SIM-CTP-FNP-SIM-CTP-2.42 I TEST RESULTS P. Panoenfus DATE PERFORMED: 11/7/90 PERFORMED BY BASELINE DATAt Plant Procedures, Plant Specific I Data, Best Estimate Judgement DESCREPANCIES None I_ DEFICIENCIE8 REPORTED: None EXCEPTIONS None RESULTS: Satisfactory REVIEWED s'J'. R. Wiggins COMMITTEE REVIEW I REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED: 12/13/90 I
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FNP-SIM-CTP-2043 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT, I TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.43 REV: 0 TYPE: Malfunction TITLE: Pressurizer Relief Valve Failure REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(1d), Loss of coolant, failure of safety and relief valves APPROVED BY: C. Mclean, DATE APPROVED: 10/18/90 I
TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at-100% steady-state power I'. in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction PRS 3A, Option - Relief valve failed full open, 5 seconds ramp time. -
PURPOSES To evaluate the simulator's response to a pressurizer relief valve failing open.
TERMINATION: Terminate the test when the failed I power operated relief interlock.
-function is observed, the isolation valve is closed manually and RCS pressure is returned to normal.
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I FNP-SIM-CTP-2.43 I TEST RESULTS DATE PERFORMED 11/7/9e PERFORMED BY P. Pappenfus BASELINM DATA: Plant Procedures, Plant Specific I Data, Best Estimate Judgement DESCREPANCIES Hone DEFICIENCIES REPORTED: None EXCEPTIONS:- None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENTt W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED: 12/13/9e I
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I FNP-SIM-CTP-8.44 ,
FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION _
PROCEDURES FNP-SIM-CTP-2.44 REY: 0 TYPE: Malfunction TITLEt' Pressurizer Safety Valve Failure REQUIREMENTS: ANSI 3.5-1985 Soction 3.1.2(1d), Loss of coolant, failure of safety and relief valves APPROVED BY C. Mclean DATE APPROVED: 10/18/90 TEST SCOPE INITIAL CONDITIONS: The simulator is running and I operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction PRSSA, Option - Safety valve A failed 100% open, ramped for
- 5. seconds.
I PURPOSES To evaluate the simulator's response to a pressurizer safety valve failing open.
TERMINATION: Terminate the test after the I pressurizer is taken solid, RCS pressure increases and stabilizes above saturation conditions, and all expected indications and alarms are I observed.
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A FNP-SIM-CTP-2.44 TEST RESULTS DATE PERFORMED: 12/2/90 PERFORMED BY T. Blindauer EASELINE DATA Plant Procedures, Plant Specific Data, Owners Group Studies, Best Estimate Judgement DESCREPANCIES: RCS pressure response oscillated and I' _ did not correspond to expected results from owners Group studies.
DEFICIENCIES REPORTED: SCR 90.217, Pressurizer Stuck Safety Valve Response EECEPTIONS: None RESULTS: Unsa.tisfactory REVIEWED BY: R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT -W. Vanlandingham -
L. Williams R. Wiggins C. Mclean DATE APPROVED: 12/13/90 lI l
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102 ATTACHMENT U.3
FNP-SIM-CIP-2 . 4 5 FARLMY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.45 REV s . O TYPE: Malfunction TITLE: Pressurizer Pressure Channel Failure ANSI 3.5-1985 Section 3.1.2(18), Failure REQUIREMENT 88 of reactor coolant pressure and volume e control systems APPROVED BY C. Mclean DATE APPROVED: 10/19/90 TEST SCOPE INITIAL CONDITIONat The simulator is running and operating at 100% steady-stat'e p.,' cur I-. in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction PRS 10A, Two options:
(1) Pressure channel PT-444 failed high, 2500 psig, (2) Pressure channel PT-444 failed low, 1850 psig.
PURPOSE: To evaluate the simulator's response to a failure of a pressurizer LI- pressure channel.
TERMINATION: Terminate the test when all expected alarms and indications are observed.
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103 ATTACHMENT D.3
FNP-SIM-CTP-2.45 l
TEST RESULTS l DATE PERFORMED: 10/23/90 PERFORMED BY P. Pappe11fus
'g BASELINE DATA: Plant Procedures, Plant Specific l lg Data, Best Estimate Judgement DEDCREPANCIESt. None DEFICIENCIES REPORTED: Nono l
~ EXCEPTIONS: None RESULTS: Satisfactory REVIEWED BY: R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams R. Wiggins C. Mc1can DATE APPROVED: 12/13/90 I
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104 ATTACHMENT D.3 i
FNP-SIM-CTP-2.46 I FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST AB8 TRACT ,
l TEST IDENTIFICATION I PROCEDURE: FNP-SIM-CTP-2.46 REY: 0 TYPE: Malfunction TITLE: Pressurizer Level Master Controller Failure REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(18), Failure of reactor coolant pressure and volume control systems APPROVED BY C. Male &n DATf, APPROVED: 10/19/90 i
TEST SCOPE IMITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power I. in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction PRSil, Two options:
- l) Pressurizer level' master controller failed high, 100%,
(2) Pressurizer level master controller failed low, 0%.
! PURPOE*1 To evaluate the simulator's response l to a failure of the pressurizer l level master controller.
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- TERMINATION
- Terminate the test when all expected l-indications and alarms are observed, a functional control channel is selected, and pressurizer level is trending towards normal.
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105 ATTACHMENT D.3
I FNP-SIM-CTP-2e46
'I TEST RESULTS DATE PERFORMED 10/22/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIE8: None DEF:l'CIENCIE8 REPORTED: None EECEPTIONS None RESULTS: Satisfactory REVIEWED BY: R. Wiggins COMMITTEE __ REVIEW REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED: 12/13/90 lI lI I
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FNP-SIM-CTP-2.47 I FARLEY NUCLEAR PLANT SIMULATOR - CERTIPICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.47 REV 0 TYPE: Malfunction TITLE: Pressurizer Level Channel Failure I REQUIREMENTS ANSI 3.5-1985 Section 3.1.2(1S), Failure of reactor coolant pressure and volume control systems APPROVED BY C. Mclean DATE APPROVEDt 10/19/90 I
TEST SCOPE
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INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power I in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction PRS 12A, Two options:
(1) Pressurizer level channel LT-459 failed low, 0%, 30 seconds ramp time, (2) Pressurizer level channel LT-459 I failed high, 100%, 30 seconds ramp time.
PURPOSE: To evaluate the simulator's response I to a failure of a pressurizer level channel providing plant protection and control.
TERMINATION: Terminate the test when all the expected indications and alarms are observed, a functional level channel
.I- is selected, and pressurizer level is trending towards normal.
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I 107 ATTACHMENT D.3
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FNP-SIM-CTP-2.47 I TEST RESULTS DATE PERPORMED: 10/23/90 PERFORMED BY: P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific I Data, Ftst Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None
-EECEPTIONS: None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW .
.IW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams R. Wiggins C. Mclean
-DATE APPROVED: 12/13/90 I
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FNP-SIM-CTP-2048 I FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.48 REVI O TYPE: Malfunction TITLE: Reactor Coolant System Leak REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(1c), Large and small reactor coolant breaks including demonstration of saturation I- conditions APPROVED BY: C. Mclean DATE APPROVED: 10/19/90 TEST SCOPE I INITIAL CONDITIONS: The simulator is running and operating at 100% steady state power in accordance with procedure FNP
- UOP-3.1.
TEST INITIATOR: Malfunction RCS1A, Reactor Coolant system Leak, Two options: ,
(1) Leak size of 100 gpm ramped for 120 seconds, within the capacity of a charging pump, (2) Leak size of 280 gpm, ramped for 120 seconds, larger than the I capacity of a charging pump.
PURPOSE: To evaluate the simulator's response to a reactor coolant system leak.
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TERMINATION: Terminate the test when all expected alarms and indications are observed.
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I. FNP-SIM-CTP-2.48 I TEST RESULTS DATE PERFORMED 12/3/90 PERFORMED BY: T. Blindauer i BASELIKE DATA: Plant Procedures, Plant Specific I Data, Best Estimate Judgement DESCREPANCIES: R24 alarm setpoint was found to be incorrect.
DEFICIENCIES REPORTED: SCW 90.213, R-24 High Setpoint EECEPTIONS: None RESULTS: Satisfactory REVIEWED BY: R. Wiggins I T I' COMMITTEE REVIER REVIEW COMNITTEE MEMBERS PRESENT W. Vanlandingham L. Williams I. R. Wiggine C. Mclean DATE APPROVED: 12/13/90
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4 B FNP-SIM-CTP-?.49 FARLEY NUCLEAR PLAPT SINULATOR - CERTIFICATION TEST ABSTRACT 6 a
I TEST IDENTIFICATION PROCEDURE: FNP-SIM-C19-2.49 REY: 0 TYPE: Malfunction TITLE Loss of Coolant Accident REQUIREMEPTS ANSI 3.5-1985 Section 3.1.2(1c), Large l
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and small reactor coolant breaks including demonstration of saturation condition
-} APPROVED BYt C. Mclean DATE APPROVEL: 10/19/90 I TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP I UOP-3.1.
TEST. INITIATOR Malfunction RCS2A, pesign basis loss of coolant accident.
PURPOSE: To evaluate the simulator's_ response to a loss of coolant accident.
TERMINATION: Terminate the test when all exeisted indications and alarms are obs'erved and actions are taken per emergency procedures FNP-1-EEP-0 and FNP EEP-1.
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I 111 ATTACaxENT D.2
FNP-SIM-CTP+2.49 I TEST RESULTS DATE PERFO.1LMED 11/28/90 PERFORMED LY: T. Blitidauer BASELINE DATA Plant PTocedttres, Plant Specific Data, Best'Betimate Judgement DESCREPANCIES: Containment cooler oublet temperatures were observed to trend I. below the freezing point.
I DEFICIENCIES REPORTED: SCR 90.212, Containment Cooler Outlet Temperfstures Durir.g LOCA.
EXCEPTIONS None .
I- -RESULTS Satisfactory REVIEWED BY,3 R. Wiggins
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COMMITTEE REVIEN REVIEW COMMITTEE MEMBERS PRESENT F. Vanlandinghfm
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Williams R. Wiggins C. Mclean ,
DATE APPROVED: 12/13/90 I
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'I- FNP-SIM-CTP-2.00 I 11 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT I _
TEST IDENTIFICATION PROCEDURE: FNP-SIM"CTP-2.50 REVt 0 TYPE: Malfunction TITLE: Steam Generator Tube Leak REQUIREMENT 88 ANSI 3.5-1985 Section 3.1.2(la), Loss of coolant, significant PWR steam generator leaks APPROVED DYr C..Mslaan DATE APPROVED: 11/28/90 L- -- _
TEST SCOPE INITIAL COWUITIOM9t The simulator is running and
,3- operating at 100% steady-state power
'3 in accordance with procedure FNP -
UOP-3.1.
TEST INITIATOR Malfunction RCS4A, Steam generator tube leak, Option - leak size 600 gpm, 50 second ramp time. .
, PURPOSE: To evaluate the simulator's response l to a steam generator tube leak.
TERMINATION: Torminate the test when all actions are taken per proce.dures FNP-1-EEP-3, Steam Generator Tube Rupture, and FNP-1-EEP-0, Reactor Trip or Safety l Injection.
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I 113 ATTACHMEUT D.3
FNP-SIM-CTP-2.90 l -
TEST RESULTS DATE PERFORMED 11/28/90 PERFORMED BYs T. Blindauer BASELINE DATA Plant Procedures, Plant Specific I. Data, Best Estimate Judgement DESCREPANCIE8f None
- I1 DEFICIENCIES REPORTED
- None RECEPTIONSt None RESULTS . Satisfactory REVIEWED BY R. Higgins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams I R. Wiggins C. Mclean DAT3 APPM?ED8 12/13/90
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114 ATTACHMENT D.3
FNP-SIM-CTP-2.51 FARLEY NUCLRAR PLANT SINULATOR = CERTtFICATION TEST A3fTRACT I TEST IDENTIFICATION PROCEC8lRE t FNP-SIM-CTP-2.51 REV8 0 TYPE Halfunction TITLE Reactor Coolant Pump Trip REQUIREMENTS ANSI 3.5-1985 Section 3.1. 2 (4 ) , Loss of forced core coolant flow due to single or multiple pump failurs ;
APPROVED BY: C. Mclean DATE APPROVED: 10/22/90 I
TEST SCOPE INITIAL CONDITION 88 The simu?ator is running al.d I operating Jt 25% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Mal
- unction RCS5A, RCP 1A trip.
D1 . POSE: To evaluate the simulator's response I to a single reactor coolant pump trip below the permissive P-8 setpoint.
TERNINATION: Terminate the test when all reoctcc coolant loop temperatures and flows have stabilized for 10 minutes.
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lI in l5 115 AMACHMENT D. 3
I TEST RESULTS i DA",E Pr%FORhi,0 10/24/90 PERFORMED BYt '? . Pappenfus 6ASELINE DATRt Plant Procedures, Plant SpecifAc
'I DEbCRIPANCIE88 Data, Best Estimate Judgement None DEFICIRMCIES REPORTED: None EECEPTION88 None
,I RESULT 8: datisfactory REVIEWED T,Ti R. WJggins COMMITTEE REVIEW Rr7IEW COMMITTEE MEMBERS PRESENT! W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED: 12/13/90 I-I I
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I TNP-SIM-CTP-2.52 I FARLEY WLICLEAR PLANT SINULATOR - CERTIFICATION TEST ABCTRACT i
I TEDT IDENTIFICATION PROCEDUREt FNP-SIM-CTP-2.52 REV 0 TYPE Malfunction TITLE: Fuel Cladding Failure REQUIREKENTS ANSI 3.5-1985 Section 341.2(14), Fuel cladding failure resulting in high I activity in reactor coolant or off gas and the associated high radiation alarms KPPROVED BYt C. Mclean DATE APPROVED: 10/19/90 I -_
TEST SCOPE I INITIAL CONDITIONS: The sinulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
I TEST INITIATOR: Malfunction RCSD, Option - 10 uc/cc.
To evaluate the silmulator's response PURPOSE:
I^ to a fuel cladding failure.
I TERMINATION: Terminate the test 15 minutes after verifying all indication and alarms occur as expected.
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I FNP-SIM-CTP-2e52 TEST RESULT _8, DATE PERFORMED 10/22/90 PERFORMED BY P. Pappenfus ,
BASELINE DATA Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANcIES: The seal table area monitor showed I little or no increase in radiation level.
DEFICIENCIES REPORTED: SCR 90.133, Radiation Monitor Response VS Gross Failed Fuel Malfunction.
EECEPTIONS: None j RESULTS: Satisfactory REVIEWED BYt R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams R. Wiggins C. Mclean -
DATE APPROVED: 12/13/90 I
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I FNP-SIM-CTP-8 53 l
FARLEY WUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT t.
TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.53 REV8 0 TYPE: Malfunction TITLE: RCS Loop Protection RTD Failure REQUIRRNENTS ANSI 3.5-1985 Section 3.1.2(22), Process instrumentation, alarms, and control system failures APPROVED BY C. Mclean DATE APPROVED: 10/22/90 I TEST SCOPE INITIAL CONDITIONS The simulator is running and operating at 100% steady-state power I in accordance with procedure FNP UOP-3.1.
TEST INITIATORt Malfunction RCS10A or RCS100, Four options
. (1) Cold leg RTD, TE-412D failed I low, 510 degrees, 30 seconds ramp time, I (2) Cold leg RTD, TE-412D failed high, 650 degrees, 30 seconds ramp time, (3) Hot leg RTD, TE-412B failed high, 650 degrees,.30 seconds ramp time, (4) Hot leg RTD, TE-4128 failed low, 530 degrees, 30 seconds ramp time.
PU". POSE: To evaluate the simulator's rosponse to a failure of an RCS loop l protection system RTD.
TERMINATION: Torminate the test after observing proper indication and alarm response, selecting the failed RTD out of the circuit, and returning -
Tave to normal.
119 ATTACHMENT D.3
FNP-SIM-CTP-3.53 I . TEST RESULT 8 DATE PERFORMED: 10/23/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None EECEPTIONS None RESULT 88 Satisfactory REVIEWED BY R. Wiggins I'
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENTt W. Vanlandingham L. Williams E R. Wiggins B C. Mclean DATE APPROVED 12/13/90 I
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FN3-SIM-CTP-2.54 l l
i FARLEY NUCLEAR PLANT SINULATOR - CERTIFICA'I' ION TEST ABSTRACT l l
TEST IDENTIFICATION PROCEDURE: FHP-SIM-CTP-2.54 REY: 0 TYPE Malfunction TITLE: RCS Loop Control RTD Failure REQUIRENENTS: adSI 3.5-1985 Section 3.1.2(22), Process Instrumentation, alarms, and control system failures APPROVED BY C. Mclean DATE APPROVED 10/22/90 I .
TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction RCS11A or RCS11D, Four options:
(1) Cold leg RTD, TE-411D, failed low, 510 degrees, 30 seconds ramp, I (2) Cold leg RTD, TE-411D, failed high, 630 degrees, 30 seconds ramp, (3) Hot leg RTD, TE-411B, failed low, 510 degrees, 30 seconds ramp, (4) Hot leg RTD, TE-411B, failed high, 630 degrees, 30 seconds ramp.
PURPOSE: To evaluate the simulator's response to a failure of an RCS loop control I_ system RTD.
TERNINATION: Terminate the test after observing I proper indications and alarms, the failed channel is selected out of the control circuit, and Tave is I returned to normal.
121 ATTACHMENT D.3
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FNP-SIM-CTP-2.54 TEST RESULTS DRTE PERFORMED: 10/23/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Proceduras, Plant Specific Data, Best Estimate Judgement l
DESCRIPANCIEst None I DEFICIENCIES REPORTED: None EECEPTIONS: None l l
RE8ULTS Satisfactory REVIEWED BYt R. Wiggins ,
I COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT4 W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED 12/13/90 I
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FNP-ftIM-CTP-2.55 FARLEY Ik' CLEAR PLAN 7 >INULATOR - CERTIFICATION TEST AB8 TRACT TEST IDENTIFICATION ,
PROCEDURE: FNP-SIM-CTP-2.55 REV1 0 TYPE: Malfunction TITLE: RHR Pump Trip REQUIRENENTS: ANSI 3.5-1985 Section 3.1.2(7), Loss of shutdown cooling APPROVED BY C. Mclean DATE APPROVED 10/22/90 TEST 8 COPE INITIAL CONDITION 8: The simulator is running and operating in Mode 4 in accordance I with procedure FNP-1-UOP-2.2, RHR train B in service and lined up for letdown. .
TEST INITIATOR: Malfunction RHR1B, RRR pump 1B trip.
PURPOSE: To evaluate the simulator's response to an RHR pump trip.
TERNINATION: Terminate the test when all expected alarms and indications are observed, the malfunction is cleared and the RHR pump fault reset.
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5 FNP-SIM-CTP-2.55 I TEST RESULTS DATE PERFORMED: 12/6/90 PERFORMED BY: P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific I Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None EECEPTIONS: None RESULTS Satisfactory REVIEWED BYt R. Wiggins I COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED: 12/13/90 I. h I
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I FNP-SIM-CTP-2.56 l
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FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST AUSTRACT I
_ _ _ _ wa I TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.56 REV 0 TYPE Mal unction TITLE RHR HX Bypass Line Break REOUIREMENT8: N'9I 3.5-1985 Section 3.1.2(1b), Loss of coulant, inside and outside primary containment APPROVED BY C. Mclean DATE APPROVED: 10/22/90 t
TEST SCOPE INITIAL CONDITIONS: The simulator is running and operat).ng its cold shutdown, Mode 5 I in accordance with procedure FNP UOP-2.2, B Train RHR in-service, lined up to letdown.
TEST INITIATOR: Malfunction RHR4B,_ Option - leak i cize 600 gpm, 60 seconda ramp time. -
PURPOSE To evaluate the simulator's response to a leak in the RHR heat exchanger bypass line.
- TERMINATIOWs Terminate the test when all expected alarms and indications are observed.
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FNP-SIM-CTP-2.56 TEST RESULT 5 DATE PERFORMEDI 12/6/90 PERFORMED BY P. Pappenfus BAdILINE DATA: Plant Procedures, Plant Specific I Data, Beat Estimate Judgement DESCRIPANCIEst None DEFICIENCIES REPORTED: None EECEPTIONS None RESULT 8 Satisfactory REVIEWED BYt R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENTI W. Vanlandingham L. Williams R. Wiggins I C. Mclean DATE APPROVED: 12/13/90 I
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126 ATTACHMENT D.3
I FNP-SIM-CTPo2.57 I FARLEY NUCLEAR PIJ.NT 8INULATOR - CERTIFICATION TEST ABST) TACT I TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.57 REV 0 TYPEt Malfunction TITLE: Turbine First Stage Pressure Transmitter Failure REQUIREMENTS: ANSI 3.5-1985 Section 3.1.2(22), Process instrumentation alarms and control system failures APPROVED BY C. Mclean DATE APPROVEDI 10/22/90 TEST SCOPE INITIAL CONDITIONS: The simulator is running and I operating at 70% steady-stato power in accordance with procedure FNP UCs 1.
TEST INITIATOR: Malfunction TUR11A or TUR11B, Two optionut I (1) Transmitter PT-446 failed high, 700 psi, 20 seconds ramp time, I (2) Transmitter PT-447 failed low, O psi, 20 seconds ramp time.
PUR?OSE: To evaluate the simulator's response I to a failure of a turbine first stage pressure transmitter.
I T13RMINATION: Terminate the test when all expected alarms and indications are observed.
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127 ATTACHMENT D.3
FNP-SIM-CTP-2057 l
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TEST RESULT 8 l
DATE PERFORMED: 10/24/90 PERFORMED BYt P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None EECEPTIONS: None RESULT 88 Satisfactory REVIEWED BY: R. Wiggins I .
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT4 W. Vanlandingham L. Williams R. Wiggins I C. Mclean DATE APPROVED 12/13/90 I
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FNP-SIM-CTP-2.58 FARLEY NUCLEAR PLANT 8IMULATOR - CERTIFICATION TEST ABSTRACT I TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.58 REV 0 TYPE: Malfunction TITLE: Generator Auto Voltage Regulator Failure REQUIREMENT 8 ANSI 3.5-1985 Section 3.1.2(16),
Generator Trip APPROVED BY C. Mclean DATE APPROVED: 10/22/90 I TEST SCOPE INITIAL CONDITIONS The simulator is running and operating at 100% steady-state power in accordance with procedura FNP UOP-3.1.
TEST INITIATOR: Malfunction TUR16, Option - set at I 140% normal voltage, ramp tima 120 seconds.
, I PURPOSE: To evaluate the simulator's response to a failure of the main generator auto voltage regulator, resulting in a generator trip.
TERMINATION: Terminate the tent when all expected I alarms and indications are observed, ll i
the generator output breakers trip open, the turbine and reactor trip, and plant loads shift to the startup transformers.
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I 129 ATTACHMENT D.3
I FNP-SIM-CTP-2.58 I TEST RESULTS DATE PERFORMEDI 10/24/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIE8: None DEFICIENCIES REPORTED: None EECIPTIONS: None RESULTSt Satisfactory REVIEWED BYt R. Wiggin.
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT! W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED 12/13/90 I l
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FNP-SIM-CTP-2059 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST AB8 TRACT r-TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-2.59 REY: 0 TYPE: Malfunction TITLE: AFW Pump Trip REQUIRENZNTS: ANSI' 3.5-19f.5 Section 3.1.2(10), Loss of all f,eedwater APPROVED BY: C. Mclean DATE APPROVED: 11/14/90 I
TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power I in accordance with procedure FNP -
UOP-3.1.
TEST INITIATOR: Malfunctions FWM1A, FWM1B, FWM1C, and a manual safety injection initiated from the main control boards.
PURPOSE: To evaluate the simulator's response to a loss of all normal and emergency feedwater.
TERMINATION: Terminate the test when all expected alarms and indications are observed.
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131 ATTACHMENT D.3
I FNP-SIM-CTP-2.59 TEST RESULTS DATE PERFORMED: 11/21/90 PERFORMED BY: P. Pa.ppenfus BASELINE DXTA: Plant Procedures, Plant Specific I Data, Best Estimate Judgement DESCRIPANCIES None DEFICIENCIES REPORTED: None EECEPTIONS: None RESULT 8: Satisfactory REVIEWED BY R. Wiggins I
COMMITTEl' REVIEW __
REVIEW COMMITTEE MEMBER 8 PRESENT W. Vanlandingham L. Williams I R. Wiggins C. Mclean DATE APPROVED: 12/13/90 I
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1I hTTACKMENT D.4 CERTIFICATION TEST _ABAIBAQTA BASELINE TRANBIENTS I PROCEDURE PROCEDURE TITLE PAGE FNP-SIM-CTP-3.1 MANUAL REACTOR TRIP.................... 1 FNP-SIM-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS........................ 3 FNP-SIM-CTP-3.3 SIMULTANEOUS CLOSURE OF ALL MAIN STEAM ISOLATION VALVES....................... 5 FNP-SIM-CTP-3.4 SIMULTANEOUS TRIP OF ALL REACTOR COOLANT PUMPS.......................... 7 .
FNP-SIM-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP................................... 9 I FNP-SIM-CTP-3.6 MAIN TURBINE TR1P...................... 11 FNP-SIM-CTP-3.7 MAXIMUM RATE /OWER RAMP................ 13 FNP-SIM-CTP-3.8 MAXIMUM SIZE REACTOR COOLANT SYSTEM RUPTURE COMBINED WITH LOSS OF ALL OFFSITE POWER...................... 15 FNP-SIM-CTP-3.9 MAXIMUM SIZE UNISOLABLE MAIN STEAM LINE RUPTURE........................... 17 FNP-SIM-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO I SATURATED CONDITION USING PRESSURIZER RELIEF OR SAFETY VALVE STUCK OPEN...... 19 I .
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FHP-SIM-CTP-3.1 I
FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURBt TNP-SIM-CTP-3.1 REV 0 TYPE Baseline Transient TITLE: Manual Reactor Trip REQUIREMENTS: ANSI 3.5-1985 Section 5.4.2(3) & App. B, Section D.2.2(1), Verify simulator I performance against the transient criteria of 4.2 for a benchmark set of transiento.
APPROVED BYt C. Mclean DATE APPROVED: 9/20/90 I TEST 8 COPE INITIAL CONDITION 8 The simulator is running and operating at 100% steady-state power in accordance with procedure FHP I UOP-3.1.
.
- TEST INITIATORt, Manually trip the reactor.
PURPOSEt To evaluate the simulator's response to a manual reactor trip from rated power with no operator action.
TERMINATION: Terminate the test thirty minutes after tripping the reactor.
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1 ATTACllMENT D.4
I FNP-SIM-cTP-3.1 I ,
TEST RESULT 8 DATE PERFORMED: 9/9/90 PERFORMED BY P. Pappenfus BASELINE DATA Plant Procedures, plant Specific I Data, Best Estimate Judgement DESCREPANCIES: Steam generator wide range level is I not calibrated to the proper 100%
steady-stato value, and during a trip, the transient response does I not correspond to what le expected in the plent.
Steam dumps appeared fully open I before turbine valves tripped fully closed. In addition, the steam dump capacity seems excessive.
DEFICIENCIES REPORTED: SCR 91.005 - Steam Generator Wide Range Level Response SCR 90.211 - Steam Dump Capacity Appears to be High EECEPTIONS None RESULTS: Satisfactory REVIEWF.D BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMSERS PRESENT: J. Osterholtz I L. Williams R. Wiggins C. Mclean DATE APPROVED: 02/06/91 I
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FNP-SIM-CTP-3.2 I FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICA7 TON PROCEDURE: FNP-SIM-CTP-3.2 REY: 0 TYPE: Daneline Transient TITLE: Simultaneous Trip of all Feedwater Pumps REQUIRENENTS: ANSI 3.5-1985 Section 5.4.2(3) & App. D, Section B.2.2(2), Verify simulator I performance against the transient criteria of 4.2 for a benchmark set of transients. .
APPROVED BY C. Mclean DATE APPROVED: 9/20/90 TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP I UOP-3.1.
TEST INITIATOR: Manually trip both main feedwater l PURPOSE:
pumps at the same time.
To evaluate the simulator's response to a simultaneous trip of both feedwater pumps with no operator action.
TERNINATION: Terminate the tone 30 minutes after both feedwater pumps are trippr,d.
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I FHP-SIM-CTP-3.2 I TEST RESULTS C I O DATE PER:'ORMEDI 10/10/90 PERFORMED BYt P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIESt None DEFICIENCIES REPORTED: None EXCEPTIONS: None RESULTS: Satisfactory REVIEWED BYt R. Wiggins I COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT J. Osterholtz L. Williams R. Wiggins C. Mclean DATE APPROVED: 02/06/91 I
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FNP-SIM-CTP-3.3 I FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT I TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-3.3 REV 0 TYPE Bar711ne Transient TITLE Simultaneous Closure of all Main Steam Isolation Valves REQUIREMENTS ANSI 3.5-1985 Section 5.4.2(3) & App. B, Section B.2.2(3), verify simulator performance against the transient criteria of 4.2 for a benchmark set of transients I APPROVED BYt C. Mclean DATE APPROVED: 9/20/90 TEST 8 COPE INITIAL CONDITIONS The simulator is running and operating at 100% steady-state power I in accordance with procedure FNP UOP-3.1.
TEST INITIATOR Close all sin main steam isolation valves simultaneously from the main control board.
PURPOSE: To evaluate the simulator's response I to a simultaneous closure of all Ig main steam isolation valves from
!E rated Power, with no operator actions.
! TERMINATION: Terminate the test thirty minutes I
after the main steam isolation valves are closed.
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I FNP-SIM-CTP-3.3 I TEST RESULTS DATE PERFORMED 11/2/90 PERFORMED BY P. Pappenfus ,
BASELINE DATA: Plant Procedures, Plant Specific I Data, Best Estimate Judgement DESCREPANCIEst None DEFICIENCIES REPORTED: None EECEPTIONS None I
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT J. Osterholtz I L.
R.
C.
Williams Wiggins Mclean DATR APPROVED 02/06/91 I
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FNP-SIM-CTP-3.4 I
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FARLEY NUCLEAR PLANT SIMflLATOR - CERTIFICATION TEST AB8 TRACT l
I TEST IDENTIFICATION ,, )
PROCEDURE: FNP-SIM-CTP-3.4 REY: 0 TYPRI Baseline Transient TITLE: Simultaneous Trip of all Reactor Coolant Pumps i REQUIREMENT 8: ANSI 3.5-1985 Section 5.4.2(3) & App. B, Section B.2.2 (4) , Verify simulator I performance against the transient criteria of 4.2 for a benchmark set of transients.
APPROVED BY: C. Mclean 'DA'fR APPROVEDI 9/20/90 1
TEST SCOPE INITIAL CONDITION 88 The simulator la running and op3 rating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR Trip all three reactor coolant pumps ,
simultaneously from the main' control board.
PURPOSE: To evaluate the simulator's response to a simultaneous trip of all '
reactor coolant pumps from rated power, with no operator actions.
TERMINATION: Terminate the test thirty minutes after the reactor coolan't pumps are tripped.
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7 ATTACHMENT De4
FNP-SIM-CTP-3.4 l
- TEST RESULT 8 I l CATE PERFORXED: 11/4/90 PERFORMED BY P. Pappenfus I
BASELINE DATA: Plant Procedures, Plant Specific I Data, Best Estimate Judgement J DESCREPANCIES: None DEFICIENCIE8 REPORTED: None EECEPTI.ON8: None RESULT 88 Satisfactory REVIE' FED DY R. Wiggins I
COMMITTEE REVIEW _
REVIEW COMMITTEE MEMBERS PRESENT! J. Osterholtz I L.
R.
C.
Williams Wiggins Mclean DATE APPROVED 02/06/91 I
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FNP-SIM-CTP-3.5 ,
FARLEY NUCLEAR PLANT SINULATOR = CERTIFICATION TE8T ABSTRACT l
TEST ID,ENTIFICATION PROCEDURE: FNP-SIM-CTP-3.5 REY: 0 TYPE: Baseline Transient TITLE: Trip of any Single Reactor Coolant Pump REQUIREMENTG ANSI 3.5-1985 Section 5.4.2(3) & App. B, Section B.2.2(5), Verify simulator I performance against the transient criteria of 4.2 for a benchmark set of transients.
APPROVED BY: C. Mclean DATE APPROVED: 9/20/90 I TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 35% steady-state power, less than the P-8 setpoint, in accordance with procedure FNP-1-UOP-3.1. Rod control is in manual mode.
TEST INITIATOR: Manually t'.*1p the 1A reactor coolant pump from the main control board.
I PURPOSE: To evaluate the simulator's response to a trip of a single reactor coolant pump while at power, below the P-8 setpoint, and with no operator actions.
TERNINATION: Terminate the test thirty minutes after the reactor coolant pump is '
j tripped.
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9 9 ATTACHMENT D.4
FNP-SIM-CTP-3.5 I TEST RE81ULTS DATE PERFORMED 11/2/90 PERFORMED BY: P. Pappenfus BASELINE DATA Plart Procedures, Plant Specific Data, Best Ectimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None EXCEPTIONS: None RESULT 8: Satisfactory REVIEWED BY R. Wiggins ,
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz
'.. Williams
_I R. Wiggins C. Mclean DATE APPROVED: 02/06/91 I
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I' FNP-SIM-CTP-3.6 YARLEY NUCLEAR PLANT SIMULATak - CERTIFICATION TEST ABSTRACT
?EST IDENTIFICATION ,
PROCEDURE: FNP-SIM-CTP-3.6 REV 0 TYPE Baseline Transient TITLE: Main Turbine Trip (Less than P-9 Setpoint) l REQUIREMENTS: ANSI 3.5-1985 Section 5.4.2(3) & App. B, Section B. ;t. 2 (6) , Verify simulator I performance against the transient criteria of 4.2 for a benchmark set of transients.
APPROVED BY C. Mclean DATE APPROVED: 9/20/90 I TEST ECOPE INITIAL CONDITIONS The simulator is running and
.- operating at 34% steady-state power in accordance wiEl procedure FNP I UOP-3.1.
TEST INITIATOR: Manually trip the main turbine from I, the main control board.
PURPOSE: To evaluate the simulator's response I to a main turbine trip below the P-9 setpoint, with no operator actions.
Terminate the test thirty minutes I TERMINATIONS-after the main turbino is tripped.
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I 11 ATTAcexENT o.4
FNP-SIM-CTP-3.6 l TEST RESULTS DATE PERFORMED - 9/9/90 PERFORMED BY: P. Pappenfus BASELINE DATA: Plant Proctdures, Plant Specific I- Data, Best Estimate Judgement l DESCREPANCIES: None l
DEFICIENCIES REPORTED: None EXCE IONS: None RESULTS: Satisfactory REVIEWED BY: R. Wiggins I
COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz L. Williams R. Wiggins I- C. Mclean I DATE APPROVED: 02/06/91 I .
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12 ATTACHMENT D.4
FNP-SIM-CTP-3.7 I FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-3.7 REY: 0 TYPE: Baseline Transient TITLE Maximum Rate Power Ramp (100% Down to 75% and Back up to 100%)
REQUIREMENTS ANSI 3.5-1985 Section 5.4.2(3) & App. B, Section B.2.2(7), Verify simulator
.I performance against the tranaient criteria of 4.2 for a benchmark set of transients.
APPROVED BY: C. Mclean DATE APPROVED: 9/20/90 I
TEST SCOPE INITIAL CONDITIONS: The simulator is running and l operating at 100% steady-state power l I- in accordance with procedure FNP UOP-3.1.
TEST INITIATOR Initiate a lohtd decrease to 620MWe, (approximately 75% power), at 200 MW/ min. After the simulator has stabilized from the load decrease, initiate a load increase to 865MWe, (100% power), at 200 MW/ min.
PURPOSE: To evaluate the simulator's response to a maximum rate power ramp from 100%-75%-100% power, with no l TERMINATION:
operator actions.
Terminate the test after completing the power ramp and T-ave is within 11.5 degrees of T-ref.
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<I 13 ATTACHMENT D.4
I FNP-SIM-CTP-3o7 I TEST RESULTS DATE PERFORMED: 11/4/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None EXCEPTIONS None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITF1E MEMBERS Ph8ENT: J. Osterholtz L. Williar.,
I- R. Wiggins C. Mclean DATE APPROVED: 02/06/91
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I FNP-SIM-CTP-3.8 I FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT J
TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-3.8 REV 0 TYPE: Baseline Transient TITLE: Maximum Size Reactor Coolant System Rupture Combined With Loss of all Offsite Power REQUIREMENT 8: ANSI 3.5-1985 Section 5.4.2(3) & App. B, I Section B.2.2(8), Verify simulator performance against the transient criteria of 4.2 for a benchmark set of transients.
APPROVED BY C. Mclean DATE APPROVED: 9/20/90 I
TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power I in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Simultaneously activate malfunction EPS1, Degraded Grid Voltage-Loss of offsite Power, and malfunction RCS2A, DBA LOCA.
PURPOSE: To evaluate the simulator's response I to a maximum size loss of coolant accident combined with loss of all offsite power and no operator actions.
TERMINATION: Terminate the teet thirty minutes after activation cf the malfunctions.
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I 15 ATTACHMENT D.4
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FNP-SIM-CTP-3.8 j
, TEST RESULTS DATE PERFORMED: 9/9/90 PERFORMED BYt P. Pappenfus BASELINE DATA I Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: Containment pressure peaked much higher than the comparison data.
Further investigation needs to be conducted to evaluate what containment pressure response should be on the simulator.
SCR 91.006 - Evaluate Containment I DEFICIENCIES REPORTED Pressure Response During a DBA LOCA EXCEPTIONS: None I RESULTS: Satisfactory REVIEWED BYt- R. Wiggins I
COMMITTEE REVIEW I. REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz L. Williams R. Wiggins C. Mclean DATE APPROVED: 02/06/91 lI L,
l 16 ATTACHMENT D.4
FNP-SIM-CTP-3.9
)
I FARLEY-NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT I TEST IDEY?IFICATION I
PROCEDURE: FNP-SIM-CTP ').9 AEY: 0 TYPE: Baseline Transient TITLE: Maximum Size Uni;dable Itain Steam Line Rupture REQUIRENENTS: ANSI 3.5-1985 Section S.4.2(3) & App. B, Section B.2.2(9), Verify simulator performance against the transient criteria of 4.2 for a benchmark set of
, transients.
APPROVED BY C. Mclean DATE APPROVED: 9/20/90 TEST SCOPE
' INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance.with procedure FNP I. UOP-3.1.
TEST INITIATOR: Activate malfunction MSSIA, option -
I leak rate of 12.0E6 lbm/hr, ramp time 30 seconds.
PURPOSE: To evaluate the simulator's response to a maximum size unisolablo main steam line rupture, with ne operator actions.
TERMINATION: Terminate the tast thirty minutes after the steam line rupture is initiated.
I I 12 ATTACN ENT o.4
I FNP-SIM-CTP-3.9 I TEST RESULTS DATE PERFORMED: 9/9/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific I Data, Best Estimate Judgement DESCREPANCIES: None DEFICIENCIES REPORTED: None EECEPTIONS None RESULTS~ Satisfactory REVIEWED BYt R. Wiggins
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COMMITTEE REVIEW REVIEW COMMITTEE MMMBERS PRESENT: J. Osterholtz L. Williams R. Wiggins
. C. Mclean DATE APPROVED: 02/06/91 I
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l FNP-SIM-CTPe3.10 l l
I- FARLEY NUCLEAR PLANT SINULATOR = CERTIFICATION TEST ABSTRACT j x
TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-3.10 REV 0 TYPE: Baseline Transient TITLE: Slow Primary System Depressur).zation to Saturated condition Using Pressurizer Relief or Safaty valve Stuck open I REQUIRENENTS: ANSI 3.5-1985 Section 5.4.2 (3) & App. B, Section B.2.2(10), Verify simulator performance against the transient criteria of 4.2 for a benchmark set of transients.
APPROVED BY C. M0 lean DATE APPROVED: 9/20/90 TEST SCC,VE INITIAL CONDITIONS: The simulator is running and oporating at 100% steady-state power I~ in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Activate malfunction PRS 5A, option -
fail safety valve 100% open.
PURPOSE: To evaluate the simulator's response to a stuck pressurizer safety valve, i with no operator actions.
TERNINATION: Terminate the test thirty minutes after the safety valve is failed open.
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I. THP-SIM-CTP-3.10 TEST RESULTS _
DATE PERFORMED 9/9/90 PERT'ORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Plant Specific Data, Best Estimate Judgement DESCREPANCIES: Pressure Drops too rapidly from just I a single pressurizer safety valve being open DEFICIENCIES REPORTED: SCR 90.217 - Pressurizer Stuck Safety Valve Nesponse EXCEPTIONS: None RESULTS Satisfactory REVIEWED BY R. Wiggins I
COMMITTEE REVIEW .
-REVIEW COMNITTER MEMBERS PRESENT: J. Osterholtz L. Williams R. Wiggins C. Mclean g DATE APPROVED: 02/06/91 I
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ATTACHMENT D.5 CERTIFICATION TEST ABSTRACTS STEADY-STATE OPERATIONS
-PROCEDURE PROCEDURE TITLE PAGE FNP<-STM-CTP-4 . O ONE HOUR STEADY-STATE OPERATIONS TEST................................... 1 I FNP-SIM-CTP-4.1 STEADY-STATE PLANT COMPARISON TO REFERENCE PLANT........................ 3 e
I FNP-SIM-CTP-4.2 STEADY-STATE THERMAL CALORIMETRIC COMPARISON............................. 5 I
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I ATTAcaMENT D.s
I FNP-SIM-CTP-4.0 FARL3Y NUCLFAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT I TEST IDENTIFICATION PROCEDURE: FNP-SIN-CTP-4.0 REV 0 TYPE: Steady-State TITLE: One Hour Steady-State Operations Test REQUIREMENTS: ANSI 3.5-1985 Section 4.1(2), The simulator computed values for steady-I state, full power operation with the reference plant control system configuration shall be stable and not vary more than 2% of the initial values I over a 60 minute period.
APPROVED BY: C. Mclean DATE APPROVED: 9/7/90 TEST SCOPE I INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP *
, UOP-3.1.
TEST INITIATOR: Run the simulator for sixty minutes with the METERMON program running, g monitoring all simulator meter u outputs for deviation outside acceptable limits.
PURPOSE: To evaluate the steady-state,.
stability performance of the computed values displayed by the I simulator on the main control boards.
TERMINATION: Terminate the test after monitoring all meter outputs for sixty minutes.
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FNP-SIM-CTP-4.0 TEST RESULTS DATE PERFORMED: 12/20/90 PERFORMED BY P. Pappenfus BASELINE DATAt Plant Procedures, Plant Specific I. Data, Best Estimate Judgement DESCREPANCIES None DEFICIENCIES RDPORTED: None j EECEPTIONSW SOMe of the reference plant u displayed indications have signal noise greater than 12%. This noise is also integrated in the I- simulation.- For those meters, the input parameter computed before the ,
noise signal is added on is I monitored for 2% stability criteria.
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.I COMMITTEE REVIEW l
REVIEW COMMITTEE MEMBERS PRESENT: 'J. Osterholtz L. Williams R. Wiggins
, C. Mclean DATE APPRO7ED: 02/06/91
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FNP-SIM-CTP-4.1 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT I TEST IDENTIFICATION _
PROCEDURE FNP-SIM-CTP-4.1 REVt 0 TYPE Steady-State TITLE: Steady-State Plant Comparison to Reference Plant REQUIREMENTS ANSI 3.5-1985 Section 4.1(3) & (4) , The computed values of critical parameters ,
I shall agtee within 2% of the reference plant parameters and shall not detract from trainlog.
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1 The calculated values of noncritical parameters portinent to plant operation, that are included on the simulator E control room panels, shall agree within
.W 10% of the reference plant parameters and shall not detract from training.
APPROVED BY C. Mclean DATE APPROVED: 9/7/90 i TEST SCOPE INITIAL CONDITIONS: Three power levels tested:
- (1) 100% power, (2) 84% power, (3) 32% power.
TEST INITIATOR: Record the critical and non-critical I parameters and evaluate against reference plant data.
TERMINATION: Terminate the test after all parameters specified by the procedure have been recorded.
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FNP-SIM-CTP-401 I TEST RESULTS DATE PERFORMED: 12/20/90 PERFORMED BY: P. Pappenfus BASELINE DATA: Plant Specific Data, Plant Logs and Computer Printouts
. DESCREPANCIES: None DEFICIENCIES REPORTED: None
.g- EECEPTIONS: Appendix B recommends steady-state 3 comparisons be performed at approximately 25%, 75% and 100%
I rated power. Because of plant data availability, the comparisons were actually performed at 32%, 84% and '
100% rated power.
RESULTS: Satisfactory REVIEWED BY R. Wiggins I COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz L. Williams R. Wiggins
- c. Mclean DATE APPROVED: 02/06/91 I
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_ - - _ _ _ _ _ - - - _ - - _ _ - _ _ _ - - _ _ - - _ - - _ _ . _ _ _ . ~
FNP-SIM-CTP-402 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT I TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-4.2 REY: 0 TYPE Steady-State TITLE Steady-State Thermal Calorimetric Comparison REQUIREMENTS: ANSI 3.5-1985 Section 4.1(2), Primary mass and energy balances shall be satisfied.
APPROVED BY C. Mclean DATE APPROVED: 9/11/90 I
TEST SCOPE INITIAL CONDITIONS: Three different power levels testedt (1) 99.8% power,
- (2) 83.62% power, (3) 28,93% power.
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TEST INITIATOR: Record the data specifed by the l
procedure and evaluate the results.
l PURPOSE: To evaluate the simulator mass and I
energy balances between the primary I and secondary systems and compare to reference plant-data.
, TERMINATION: Terminate the test after all the l
data specified by the procedure has been recorded.
,I I s ATTAcuMENT o.s
FNP-SIM-CTP-402 I TEST RESULTS DATE PERFORMED: 12/20/90 PERFORMED BY: P. Pappenfus BASELINE DATA: Plant Procedures, Reference Plant Calorimetrio Data DESCREPANCIES None DEFICIENCIES REPORTED: None EXCEPTIONS: Appendix B suggested steady-state evaluations be performed at approximately 25%, 75% and 100%
power. Because of plant data I availability, actual evaluations were performed at 32%, 84% and 100%.
RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: J. Osterholtz L. Williams i
R. Wiggins
. C. Mclean .
DATE APPROVED: 02/06/91 I.
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5 ATTACIIMENT D.5
I ATTACHMENT D.6 CERTIFICATION TEST ABSTRACTS PLANT TRANSIENTS I PROCEDURE PROCEDURE TITLE ,
PAGE FNP-SIM-CTP-5.1 UNIT 1 LOSS OF BOTH SOURCE RANGE CRANNELS.............................. 1 I FNP-SIM-CTP-5.2 REACTOR TRIP CAUSED BY INADVERTENT DE-ENERGIZATION OF 4160 VOLT BUS 1H... 3 I FNP-SIM-CTP-5.3 HIGH FLUX RATE REACTOR TRIP CAUSED BY 1A INVERTER FAILING WHILE HI-42 WAS BEING TESTED.......................... 5 I ,
FNP-SIM-CTP-5.4 UNIT 1 RFhCTOR TRIP DUE TO UNDER-FREQUENCY ON THE REACTOR COOLANT PUMP BUSES............................ 7 FNP-SIM-CTP-5.5 DEH MALFUNCTION RESULTING IN SAFETY INJECTION AND REACTOR TRIP............ 9 I
FNP-SIM-CTP-5.6 LOAD REJECTION........................ 11 I
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FNP-SIM-CTP-501 1
= FARLMY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST ABSTRACT I TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-5.1 REV: 0 TYPEt Plant Transients TITLEt Unit 1 Loss of Both Source Range Channels REQUIREMENTS: ANSI 3.5-1985 Section 4.2.2, Malfunctions and transients not tested in I accordance with 4.2.1 shall be tested and compared to best estimate or other available information and shall meet the acceptance criteria of 4.2.1(b) .
APPROVED BY: C. Mclean DATE APPROVED: 10/22/90 I TEST SCOPE INITIAL CONDITIONSt The simulator is running in cold shutdown, mode 5, in accordance with procedure FNP-1-UOP-2.2.
TEST INITIATOR Removal of control pcwer fuses for two power r,ange instruments.
PURPOSEt. To evaluate the simulator's response to a loss of control power on two power range instruments with the plant in MODE 5. This procedure duplicates an actual plant transient which resulted in a Licensee Event I , Report being generated,-LER 79-031.
TERMINATION: Terminate the test when all expected alarms and indications are observed.
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FNP-SIM-CTP-Sol l TEST RESULTS DATE PERFORMED 10/24/90 PERFORMED BY P. Pappenfus BASELINE DATA: Plant Procedures, Licensee Event Report, Actual Plant Response DESCREPANCIES: None LEFICIENCIES REPORTED: None EECEPTION8: None I RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MFMBERS PRESENT W. Vanlandingham L. Williams R. Wiggins C. Mclean I.-
DATE APPROVED: 12/1.3/90 g.
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FNP-SIM-CTP-5e2 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST ABSTRACT I .
TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-5.2 REY: 0 TYPE: Plant Transients
- l TITLE Reactor Trip Caused by Inadvertent de-energization 3 of 4160 Volt Bus 1H REQUIREMENTS: ANSI 3.5-1985 Section 4.2.2, Malfunctions and transients not tested in accordance with 4.2.1 shall be tested and compared to best estimate or other.
I aveilable information and shall meet the acceptance criteria of 4.2.1(b) .
APPROVED BY: C. Mclean DATE APPROVED: 10/22/90 I TEST SCOPE I INITIAL CONDITIONS:
The simulator is running and operating at luv% steady-state power in.accordance with procedure FNP UOP-3.1.
TEST INITIATOR 1 Performing surveillance on 1-2A diesel generator, and opening the I wrong supply breaker.
PURPOSE To evaluate the simulator's response to an inadvertent de-energization of 4160 volt bus 1H. The procedure duplicates an actual plant transient which resulted in a Licensee Event
.I Report being generated, LER 87-010-00.
TERNINATION: Terminate the test when all expected alarms and indications are observed.
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FNP-SIM-CTP-5.2 TEST _RESULTS ,
DATE PERFORMED: 10/24/90 PERFORMED BY: P. Pappenfus BASELINE DATA: Plant Procedures, Licensee Event Report, Actual Plant Response DESCREPANCIES: None DEFICIENCIES REPORTED: None EECEPTIONS: None RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams R. Wiggins C. Mclean
. DATE Al? ROVED: 12/13/90 t
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FNP-SIM-CTP-5.3 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION TEST AB8 TRACT TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-5.3 REV 0 TYPE: Plant Transients TITLE: High Flux Rate Reactor Trip Caused by Inverter 1A l Failing WHile NI-42 was Being Tested ANSI 3.5-1985 Section 4.2.2, I'
REQUIREMENTS:
Malfunctions and transients not tested in accordance with 4.2.1 shall be tested and compared to best estimate or other available information and shall meet the acceptance criteria of 4.2.1(b).
APPROVED BY: C. Mclean DATE APPROVED: 10/22/90 TEST SCOPE INITIAL CONDITIONS: The siiaulator is running and operating at 100% steady-state power
, in accordance with procedure FNP UOP-3.1.
TEST. INITIATOR: Perform surveillance FNP-1-STP-41.3,
- NI-42-Power Range Instrument and fail inverter 1A with. malfunction EPS9A.
PURPOSE: To evaluate the simulator's response to a high flux rate reactor trip caused by 1A inverter failing while
, NI-42 was being-tested. This l procedure duplicates an actual plant L transient which resulted in a L Licensee Event Report being l .
generated, LER 87-004-00.
l TERMINATION: Terminate the test when all expected ,
alarms and indications are observed.
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, i FNP=SIM-CTP-So3 l ,
TEST RESULTS DATE PERFORMED: 10/24/90 PERFORMED BY P. Pappentus BASELINE DATAt Plant Procedures, Licensee Event Report, Actual Plant Response DESCREPANCIEst None DEFICIENCIES REPORTED: None EXCEPTIONS None I. RESULTS: Satisfactory REVIEWED BY R. Wiggins COMMITTEE REVIEW REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams R. Wiggins C. Mclean DATE APPROVED: 12/13/90 .
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1 FNP-GIM-CTP-5.4 FARLEY NUCLEAR PLANT SINULATOR - CERTIFICATION TEST AESTRACT 1 l
l TEST IDENTIFICATION PROCEDURE: FNP-SIM-CTP-5.4 REV 0 TYPD: Plant Transients I TITLE: Unit 1 Reactor Trip Due to Under-frequency on the Reactor Coolant Pump Buses REQUIREMENTS: ANSI 3.5-1985 Section 4.2.2, I ,
Malfunctions and transients not tested i~n accordance with 4.2.1 r> hall be tested and compared to best. estimate or other available information and shall meet the acceptance criteria of 4.2.1(b) .
APPROVED BY: C. Mclean DATE APPROVEDJ 11/34/90 ,
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TEST SCOPE I INITIAL CONDITIONS: The simulator is running and operating at 35% steady-state power in accordance with procedure FNP
- l UOP-3.3.
TEST INITIATOR: Trip the turbine without transfering loads to the startup transformer.
PURPOSE: To evaluate the simulator's responso L to a Unit 1-reactor trip due to under-frequency on the reactor l coolant pump buses. This procedure L duplicates an actual plant transient l which resulted in a Licensee Event Report being generated, LER 85-010.
TERNINATION: Terminate the test when all expected I' alarms and indications are observed.
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FNP-SIM-CTP-5.4 I TEST RESULTS DATE PERFORMED 11/21/90 PERFORMED BY: P. Pappenfus BASELINE DATAt Plant Procedures, Licensee Event
. Report, Actual Plant Response DESCREPANCIES: The turbine was slow to coast down
,3- with reactor coolant pumps still E being supplied by the main generator.
DEFICIENCIES REPORTED: SCR 90.210 - Turbine Coast Down Time While Still Under Load Ey;EPTIONS* None t-RESULTS: Satisfactory REVIEWED BYt R. Wiggins I-COMMITTOE REVIEW I REVIEW COMMITTEE MEMBERS PRESENT W. Vanlandingham L. Williams R. Wiggins I'-- C. Mclean DATE APPROVED: 12/13/90
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FNP-SIM-CTP-5.5 FARLEY NUCLEAR PLANT SIMULATOR - CERTIFICATION WEST ABSTkACT
~w TEST IDENTIFICATION PROCEDUREt FNP-SIM-CTP-5.5 REV 0 TYPE Plant Transients E TITLE: DEH Malfunction Resulting in Safety Injection and 3 Reactor Trip ANSI 3.5-1985 Section 4.2.2, I REQUIREMENTS Malfunctiuns and transients not tested in accordance y th 4.2.1 shall be tested and compared to best estimate or other I available information and shall meet the acceptance criteria of 4.2.1(b).
APPROVED BY: C. Mclean DATE APPROVED: 12/3/90 TEST _ SCOPE INITIAL CONDITIONS: The simulator is running and operating at 35% steady-state power in accordance with procedure FNP UOP-3.1.
! TEST INITIATOR: Malfunction TUR18, Option - set load
- l. demand to-900MW, zero ramp time.
PURPOSE: To evaluate the simulator's response
- , to a rapid steam demand increase due to a malfunction of the digital L' electro-hydraulic control system.
l This procedure duplicates an actual -
plant event which resulted in a Licensee Event Report being written, LER 89-006.
TERMINATION: Terminate the test when all expected-alarms and indications are observed.
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FNP-SIM-CTP-5.5 I TEST RESULT 6 ,
DATE PERFORMED: T'iS/90 PERFORMLi' BYt. P. Pappenfus EASELINE DMAt Plant Procedures, Licensate Event l
4 Report, Actual Plant Ressponse ,
DESCREPANCIES: None l
DEFICIENCIES REPORTED: None EECEPTION83 None RESULT 88 Batisfactory REVIEWED BY R. Wiggins COMh1""?DE REVIEW REVItW COMMITTEE MEMBERS PRESENT: W. Vanlandingham L. Williams M R. Wiggins 3 C. Mclean DATE APPROVED: 12/13/90 I - '
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I 10 ATTACHMENT D.6
FNP-SIM-CTP-5.6 I
FARLEY NUCLEAR PLANT SINCLATOR - CERTIFI( ATIOW TEST ABSTRAC'h TEST IDENTIFICATION PROCEDURE FNP-SIM-CitP-5.6 REV 0 TYPE: Plant Transients 72TLE: Load Rejection REQUIRENENT8 ANSI 3.5-1985 Section 4.2.2, !
3; Malfunctions and transiento not tested in i g accordance with 4.2.1 shall be tested and compared to best estimate or other available information and shall meet the acceptance criteria of 4.2.1(b).
APPROVED BY C. Mclean DATE APPROVED: 12/3/90 1 TEST SCOPE INITIAL CONDITIONS: The simulator is running and operating at 100% steady-state power in accordance with procedure FNP UOP-3.1.
TEST INITIATOR: Malfunction TUR18, O}) tion - set load demand to 240MW, 87 second ramp timo.
PURPOS3 To evaluate the simulator 8s response to a 640MW load rejection. This procedure duplicates an actual plant event which resulted in generating an incident report, IR 1-89-40.
TERNINATION: Terminate the test when all expected alarms and indications are observed.
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FNP-SIM-CTP**5.6 I TEST RESULT 8 DRTE DERFORMED: 12/5/90 PERFORMED EY: P. Pappenfus BASELINE DLTA: Plant Procedures, Licensee Event Report, Actual Plant Response DESCRIPANCIES None DEFICIENCIE8 REPORTED: None EECEPTIONS: None MESULT8: Satisfactory REVIEWED BY R. Wiggins I '
COMMITTEE REVIEW REVIEW COMMITTU: MEMBERS PRESENT W. Vanlandingham L. Williams R. Wiggins l ~E >--a , niui,0 C. Mclean I
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ATTAC]D(ENT...E SINULATOR I CERTIFICATION TEST DISCREPANCIES SINULATOR SCHEDULE TEST CHANGE DISCREPANCY FOR i PROCEDURE REQUEST COMPLETION CTP-1.9 SCR 90.220 High Flux at Shutdown Complete Alarm Setpoint CTP-2.1 SCR 90.219 Nineteen Valves have Complete 1 Improper Air Supplies CTP-2.11 SCR 90.097 Charging Flow With VCT Complete Level =0 CTP-2.17 SCR 90.094 CRDM Pan Power Supplies Complete CTP-2.18 SCR 90.098 Electrical Loads not Lost Complete for Malfunction EPSDB CTP-2.20 SCR 90.199 120VAC Inverter A Failure Hardware Response not obtained Required 05/91 CTP-2.21 SCR 90.200 120VAC Panel 1K .ower Hardware I
Failure Response not Obtained Required 05/91 CTP-2.22 SCR 90.214 Train B Power Supplies Incorrect Completn SCR 90.215 Train A Power l Supplies Incorrect complete l SG 90. 216 LOA to Switch Annunciator
! Power Supplies Complete CTP-2.25 SCR 90.099 Main Peod Pump Auto Trip Complete Failure Malfunction FWM12 CTP-2,37.2 SCR 90.131 IR NIS Blown Instrument Complete Fuse Bistable Resptnse CTP-2.38.2 SCR 90.132 PR NIS Blown Instrument Complete Fuse B1 stable Response CTP-2.44 SCR 90.217 Pressurizer Safety Valve Complete Failure Pressure Response CTP-2.48 SCR 90.213 R24 High Setpoint Incorrect complete -
CTP-2.49 SCR 90.212 Containment Cooler Outlet I Temperatures During a LOCA Complete 1 ATTACHMENT E
ATTACJMENT.E I *
, SIMULATOR CERTIFICATION TEST DISCREPANCIES SIMULATOR SCHEDULE l TEST CHANGE DISCR**PANCY FCS l PROCEDURE REQUEST COMPLET.*0N CTP-2.52 SCR 90.133 Seal Table Radiction Complete Monitor Response During Failed Fuel Malfunction CTP-3.1 SCR 91.005 Steam Generator Wide Range Complete Level Response CTP-3.8 SCR 91.006 Peak Containment Pressure During a DBA LOCA Complete CTP-4.1 SCR 91.003 Saturation Margin Tuning Complete to Match Plant Steady-State Values CTP-5.4 $CR 90.210 Turbine Coast Down Time Complete Excessive While Under I Partial Load g CTP-5.6 SCR 90.211 Stean Dump Capacity / Time Complete g Response I
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I ATTACEMETf F SINULATOR CERTIFICATION ANSI /ANS-3 5 EXCEPTIONS ANSI /ANS-3.5 SECTION REASON FOR EXCEPTION 3.1.1(7) Farley Nuclear Plant is not allowed, by Technical Specifications to operate at I sustained power or startup the reactor with less than full reactor coolant flow.
Performance testing under these conditions is considered not applicable to the Parley Nuclear Plant Simulator.
3.1.1(9) Core performance tests were run utilizir.g background programs rather than using permanently installed instrumentation. The background programs test. core I characteristics faster and provide a more accurate inoication of the simulated core physics parameters.
3.1.2(12) All possible rod control failures were tested, including a stuck rod, misaligned rod and e dropped rod. Failures such as uncoupled or drifting rods are not applicable to the Farley Nuclear Plant Simulator.
3.1.2(25) Malfunction for pressure control system failure including turbine bypass failure is applicable to BWR plants only.
4.1 Steady-state comparisons are to be performed at a minimum of three points over the power
, range. Appendix B recommends 25%, 75% and 100% rated power. Because of the availability of plant data, comparisons were 3 actually performed at 32%, 84% and 100%
5 rated power.
4.1(2) The simulator computed values for steady-state must be stable and not vary more than 12% of the ini'.,al value over a 60 minute period. Many of the indications at Plant I Farley, some of them critical parameters, experience instrumentation noise. The noise itself varies greater than 12%. This noise is also modeled on the simulator to provide a realistic response. For those indications, the computed parameter prior to I the noise being added on is checked for 12%
stability criteria.
I 1 ATTACIIMENT F
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ATTACENENT._F 8INULATOR CERTIFICATION ANSI /AN8-3.5 XXCEPTIONS ANSI /AN8-3.5 l- BECTION REASON FOR EXCEPTION 4.1(3 ) ( f) Recirculation flow is not an applicable l
critical parameter for pressurized water roactors, and could not be included as one I of the critical parameters evaluated during performance testing of the Parley Nuclear Plant Simulator.
4.3(5) BWR cuppression pool temperature is not applicable to a pressurized water reac:or I and can not be one of the parameters monitored on the Parley Nuclear Plant simulator to ensure simulation is within operating limits.
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I 2 ATTACHMENT F