ML20247M792
| ML20247M792 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 07/31/1989 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20247M747 | List: |
| References | |
| PROC-890731, NUDOCS 8908020230 | |
| Download: ML20247M792 (46) | |
Text
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RGv 6 ow ATTACHMENT 6 July, 1989 PWR OPERATION 3 GUIDELINE NbHBER 12 SIMULATOR TESTING PROGRAM A. PURPOSE The purpose-of this guideline is to establish a program to test the simulator in accordance with'the requirements of:
ANSI /ANS-3.5-1985: Nuclear Power Plant Simulators for Use in Operator Training
- Reg Guide 1.149: Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations 10 CFR 55.45: Operating Tests
- NUREG-1258: Evaluation Procedure for Simulation Facilities Certified Under 10 CFR 55 B.
REFERENCES:
- ANSI /ANS-3.5-1985: Nuclear Power Finnt Siatulators for Use in s Operator Training
- Reg Guide 1,149: Nue' tear Power Plant Simulation Facilities for Use in Operator License Examinations
-- 10 CFR 55.45: Operating Tests NUREG-1256: Fvaluation Procedure for Simulation Facilities Certified Under 10 CFR 55 q90802O230 890727 618M/251M/1 7/89 DR ADOCK 05000454 PDC
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' July, 1989 PWR OPERATIONS GUIDELINE NUMBER 12 SIMULATOR TESTING PROGRAM
C. PROCEDURE
This guideline will address both the testing administration and specifica'lly which tests and analysis are required for the simulator initial testing program, which compares the Byron Station startup test data and the Braidwood Station startup test date to the Braidwood Simulator acceptance test program, as well as the subsequent simulator annual testing program which reaffirms the fidelity of the simulator and assures the reliability and consistency of the simulation process from year to year.
- 1. Testing Administration Each test which is performed will have attached to it a Simulator Performance Test Cover Sheet, Attachment A. Each cover sheet gives a brief summary of the status of each test. On the cover sheet, the test team shall indicate:
- a. The test number, title, date performed and disc used.
- b. Any work request written as a result of performing the test, include on the cover sheet the work request number and brief description. Upon correcting a work request, the initials of the. tester and the date shall aise be eutered on the cover sbeet,
- c. Test status One or more of the fo139 wing may be checked:
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PWR OPERATIONS GUIDELINE NUMBER 12 I
. SIMULATOR TESTING PROGRAM !
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_1) Test completed satisfactorily.
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1 l The test was performed and parameters are within the I
acceptance criteria. In addition, no work request has been written, or a work request has been written and completed l
which-is relatively minor and does not require a complete I i retest. In addition, list any Deviation Record numbers (DR
- ) that are written. Attachment D, Simulator Testing Record, shall be used to document any deviations.
- NOTE ***********************************
- NO TEST CAN MEET THE PASS CRITERIA IF ANY REFERENCED WORK REQUEST IS NOT COMPLETED AND SIGNED OFF ON THE SIMULATOR PERFORMANCE TEST COVER SHEET.
- 2) After correction of above work request (s), tests results are satisfactory.
The test was performed and most parameters are within the acceptance criteria. However, work request (s) have been written for items which are minor in nature and have no significant effect on the test results. Therefore, a complete retest is not necessary. However, at a minimum the affected portion of the test shall be retested. This will include all parameters which were initially outside the acceptance criteria. After cerzectior,of the work request, the test can be coneldsred satkafactory and so indicated on the test cover sheet after the affected portion of the test is 1* tested.
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R:.y 6-July, 1989 PWR OPERATIONS GUIDELINE NU!EER 12 SIMULATOR TESTING PROGRAM
- 3) Test results unsatisfactory. Retest the entire test after.
correction of the above work request (s).
Work request (s) were. written having a significant impact on the test results. A complete retest is necessary. This.
would require use of an additional cover sheet and copy of the test procedure. ~DO NOT DISCARD THE FAILED TEST PROCEDURE! File it with the appropriate test for that year.
- d. . Signature Block-Sign the test as being completed only after the Test Completed Satisfactorily line has been checked.
- 2. Simulator Initial Testing Program The simulator initial testing program will be run during 1988. The purpose of this program is to compare the simulator response to actual measured performance by the Braidwood and Byron startup tests. It shall consist of:
o Simulator operability tests.
o Comparison between Braidwood plant startup tests and the simulator's acceptance test program.
- a. fimulatcr Operability Tests
- 1) Ensure that *:he following tests were satisfactorily comMete6 during the factory v4cceptance test procedure:
a) Computer reel time test.
b) Each malft.netior. test.
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- 2) Perform the following tests:
a) Steady state test #SS-1.
b)' Real time test.#RT-1.
c) Transient performance tests.-
(1) Manual-reactor-trip #TR-1.
(2) Simultaneous trip of all feedwater pumps #TR-2.
(3) Simultaneous closure of all main steam isolation valves #TR-3.
(4) Simultaneous trip of all reactor coolant pumps
- TR-4.
(5) Trip of any single reactor coolant pump #TR-5.
(6) Main turbine trip (without immediate reactor trip) #TR-6.
(7) Maximum rate power ramp #TR-7.
(8) Maximum size reactor coolart system rupture combined with loss of all offsite power #TR-8.
(9) Maximum size unisolable main steam line rupture
- TR-9.
(10) Slow primary system depressurization to saturation #TR-10.
- b. Compare Byron starttp test results, Brafdvood startup test results and the simulator acceptance test program for the following tests:
- 1. Initial Criticality
- 2. Determination of Core Power Range 618M/251M/5 7/89
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- 3. Rod Worth Test i
- 4. Isothermal Temperature Coefficient Measurement
- 5. . Boron Worth Test i
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-3. Simulator Annual Testing Program The intent of the simulator. annual testing program is to:
- Verify overall simulator model completeness and integration.
- Verify the current simulator performance against the steady.
state and transient tests performed in 1988 (baseline data).
The program consists of annual steady. state, real time, and transient tests as well as 25% of the malfunction tests as specified in Attachment B and Attachment C. In addition, normal operations testing and surveillance testing shall be performed each year. Valve stroke time testing shall be performed biennially. For purposes of this guideline, a year shall begin on October 7 and end on October
- 6. The simulator annual testing program shall commence October 7, 1988 (Date of initial Simulator Certification)..
- a. Annual Steady State Test Annually, perform the Steady State Operability Test #SS-1.
- b. Annual Real Time Test q Annually, perform the Real Time Test 4RT-1.
- c. Annual T.tannient Tects Annurtly, perform the following transient tests:
(1) Manual reactor trip #TR-1.
(3) Simultaneous trip cf all feedwater pumps #fR-2.
(3) Simultanocus closure of all main steam isolation i
valves #TR-3.
618M/251M/6 7/89
Rev 6 y July, 1989 NA N~ PWR OPERATIONS GUIDELINE NUMBER'12 SIMULATOR TESTING PROGRAM.
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(4) Simultaneous' trip of all reactor coolant. pumps
- TR-4.
(5) Trip of any single reactor coolant pump #TR-5.
(6) . Main turbine trip (without immediate reactor trip) #TR-6.
(7) Maximum rate power ramp #TR-7.
'(8) Maximum size reactor coolant system rupture combined with loss of all offsite power #TR-8.
(9) Maximum size unisolable main steam line rupture
- TR-9.
(10) Slow primary system depressurization to saturation #TR-10.
- d. Annual Normal Operations Test Annually, perform the Normal Operations Test (N0-1.
- e. Annual Surveillance Test Annually, perform the Surveillance Test #SV-1.
- f. Biennial Valve Stroke Time Test Biennially, perform the Valve Stroke Time Test #ST-1.
- g. Malfunction Tests
- x******** soII *****a***9********m****************
- ANT NE'd M3LFUNCTION SHALL BL TESTED IN THE YEAR-IT IS TURHED OVEk FOR TRAINING AND AT LEAST EVERY FOUR YEARS TREREAFTER,,
- TRS NEW MALTUNCTIO9 SHOULD BE ADDEF SUCH THAT AN EVEN
- hALTU7CTION TESTIIF; DISTRIBUTION (~ 25% PER TEAR) WILL BE- *-
- MAINTAINED.
l- <s********************************************************n***********
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July, 1989 PWR OPERATIONS GUIDELINE NUMBER 12 SIMULATOR TESTING PROGRAM The simulator annual testing program for malfunction tests is on a four year cycle such that approximately 25% of the malfunction tests will be performed each year. Attachment B identifies the frequency and proposed testing schedule for each simulator certified malfunction. Attachment C identifies the frequency and proposed testing schedule for each simulator non-certified malfunction. During the performance of each malfunction test, the test team shall update each Malfunction Description Sheet.
At a minimum, this update shall verify that each Malfunction Description Sheet is complete and includes the first annunciator (s) received.
- h. Simulator vs. Station Hardware Comparison A simulator to Braidwood Unit One hardware comparison will be performed within six months after the completion of each Braidwood Unit One refueling cutage. Braidwood Unit One photographs or detailed comparison sheets similar to the forms used in NUREG-1258 may be utilized for the comparison. Nottd differences between the station and the simulator will bc l corrected by the Work Request process or the difference will be documented in the Simulator Certification Report.
- i. Malfunction Assessment Review Program j Byron and Braidwood LER's and other industry events shail be reviewed semi-annually to assess their potential impact on I simulation. This review shall determine the LET.'s and industry events selected for testing. Each of the selected 618M/251M/8 7/89 l
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Rev 6 July,'1989 1
PWR OPERATIONS GUIDELINE NUMBER 12 SIMULATOR TESTING PROGRJ.M LER's/ industry events shall use'a simulator test procedure to
. check the simulator response. . Attachmect E, Simulator LER' Test Procedure, will be used in conjunction with a Simulator Performance Test. Cover Sheet, Attachment A, to document the results of each test. The LER's/ industry events, once tested satisfactory, will be referenced and included as an event for the applicable. malfunction in the Malfunction Description Book.
Any special notes required to duplicate the test response may.
also be included in the Malfunction Description. The Byron /Braidwood Operations Simulator Training Supervisor shall designate the LER's/ industry events that will be selected for testing. The results of the Malfunction Assessment Review shall be filed in REP-81.
j . Test Results The results of p'.eulator testing shall be documented in each y*.nt's ";eolator Certification Report. . Deficiencies will be handled by two methods. The first method is to write a Work Request for those items which require simulator software or hardware work. The second method.is to document the deficiency on the Simulator Testing Record, Att.tchment D. The Deviation Record (DR) is for those items that are outside of the acceptance criteria yet do not require correction. For example, the Steacy State Test compares Braidwood Startup Data to the simulator. If an initial simulator parameter did not fall within 2 2% of the same Braidwood parameter, then the 618M/251M/9 7/89 a__-.
July, 1989 PWR OPERATIONS GUIDELINE NUMBER 12 SIMULATOR TESTING PROGRAM acceptance criteria would not'be met. However, the simulator parameter may be at a nominal value while the Braidwood parameter fell within its expected range during startup testing. Each deviation sh.'1 be approved by the Byron /Braidwood Operations Simulator Training Supervisor. The
'results of the malfunction tests shall also be documented in each year's Simulator Certification Report. If a malfunction fails, a Work Request shall be written to correct the failure.
In addition, a record of all "Not Authorized For Use" mal. functions shall be kept current and placed in the Simulator Malfunction Description Book. This "Not Authorized For' Use" a
letter shall designate the malfunctions currently unavailable for training and the letter shall be approved by the Byron /Braidwood Operations Simulator Training Supervisor. A copy of the "Not Authorized For Use" letter shall be filed in SIM-BW-1C3-YR.
- k. Incorporating design data into the simulator Simulator design data control is required to provide a means for on-going verification of simulator performance. This verification shall be accomplished by:
- 1) Verifying that appropriate Braidwood Unit One Startup Tests are performed on the simulator and the results of each simulator test are compared to the station test. Test comparison failures will be handled by the Work Request 618M/251M/10 7/89
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PWR OPERATIONS GUII)ELINE NUMBER 12 SIMULATOR TESTING PROGRAM procens. This verification is required prior to January )
I 29, 1990 (Braidwood Unit One date of commercial operation ]
plu.s 18 months).
- 2) Reviewing Braidwood Unit One modifications at least once per year and revising the simulator based on engineering and training value assessment. The simulator will be revised, as appropriate. Simulator modifications may precede Braidwood Unit One modifications based on training value.
- 3) Evaluating student feedback and updating the simulator design data base, as appropriate.
- 1. Revisions to PWR Operations Guidelic3 Number 12.
File any revised PWR Operations Guideline Number 12 in OPS-21D.
- A4 I 5/ron/BraidwoodOperati .;
Simulator Training Supe or 618M/251M/ll 7/89 w_
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PWR OPERATIONS GUIDELINE NUMBER 124 7 s. , SIMULATOR TESTING PROGRAM
~ ATTACHMENT A
' SIMULATOR PERFORMANCE TEST COVER SHEET
. TEST NUMER:L DATE:
TEST TITLE:
DISC USED:-
WORK REQUESTS:
WORK' CORRECTED REQUEST NUMBER BRIEF DESCRIPTION INITIALS- DATE-4 TEST STATUS: CHECK HERE
- 1. Test completed satisfactorily, DR #
have been written.
INITIALS /DATE
- 2. After correction of the epove work request (s),
INITIALS /DATE test results are satisfactory.
- 3. Test results unsatisfactory. Retest the entire INITIALS /DATE test after correction of the above work request (s).
TEST COMPLETE: DATE:
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July, 1989 PWR OPERATIONS GUIDELINE NUMBER 12 SIMULATOR TESTING PROGRAM ATTACHMENT B SIMULATOR CERTIFIED MALFUNCTION TEST SCHEDULE ANNUAL TESTING PERIOD (Month / Year)
MALFUNCTION 1989 1990 1991 1992 MALFUNCTION NUMBER DESCRIPTION Acoreximate test date (cuarter/vear)
AUX-1 Loss of Instrument Air 1/90 AUX-2 RWST Leak 1/90 AUX-3 Cire Water Pump Trip 1/90 AUX-4 Essential Service Water Pump Trip 1/90 AUX-12 Loss of Service Air 1/89 AUX-13 Loss of Non-Essential Service Water 1/90 Inadvertent ContrJ1 Room Isolation 1/92 AUX-17 Non-Essential Service Water Header Leak 1/02 AUX-18 Letdown Heat Exchanger Tubs Leak 1/91 CCV-1 CCW Heat Exchanger's Loss of Coolant Flow 1/91 CCW-2 Loss of CCW to Letdown Heat Exchanger 1/91 CCW-4 Loss of CCW to RHR Heat Exchanger 1/92 CCW-5 CCW Pump Trip 1/92 CCW-6 Seal Wtr Heat Exchanger Tube Leak 1/92 CCW-7 CCW-8 RHR Heat Exchanger Tube Leak 1/89 CCW-9 RCP Therral Barrier Leak 1/89 CCW-11 CCW Heat Exchanger Tube Leak 1/90 CCV-13 CCW Surge Tank "A" Leak 1/90 CCW-14 CCW Surge Tank "B" Leak 1/90 CCW-15 CCW System Leak 1/90 1 Los! of Condenser Vacuum 1/91 CND-1 Hotwell Level Controller Failure 1/92 CND-2 CND-3 Circulating Water Tube Leak in Condenser 1/89 Boric Acid Flow Transmitter (FT-110) 1/91 CVC-1 Failure i VCT Divert Valve Failure (112A) 1/91 !
CVC-2 PCV-131 Control Failure 1/91 l CVC-3 Charging Header HCV-182 Control Failure 1/91 CVC-4 Failure of PDP Charging Pump Speed 1/91 CVC-5 Control RCP Seal Failure 1/91 CVC-6 (VC-14 Boric Acid Transfer Pump Trip 1/89 !
(VC-15 Plugged CVCS Filters 1/89 (VC-16 Letdown Line Leak Inside Containment 1/89 CVC-17 Charging Line Leak Inside Containment 1/89 CVC-18 Loss of Charging Pump 1/89 CVC-19 Primary Water Maka-o Pump Trip 1/89 CVC-20 CVCS Various Valve Failures 1/90 CVC-21 VCT Level Malfuretion 1/90 CVC-23 Make-up Control Failure 1/90 CYC-26 CVCS Demineralizers Depletion 1/90 CVC-27 Letdown Le:Jk Outside Containment 1/90 CVC-28 Seal Injection Leak 1/91 618M/251M/13 7/89
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i PWR OPERATIONS GUIDELINE NUMBER 12 L SIMULATOR TESTING PROGRAM
. ATTACHMENT B SIMULATOR CERTIFIED MALFUNCTION TEST SCREDULE ANNUAL TESTING PERIOD (Month / Year)J MALFUNCTION MALFUNCTION 1989 1990 1991' 19921 NUMBER DESCRIPTION ; Acoroximate test date (cuarter/vear)
CRF-1 Rods Fail To Move < 1/90
'CRF-3 Improper Bank Overlap .1/90 CRF-4 Dropped Rod 1/90 CRF-5 Dropped Rods 1/90 CRF-6 Rod Ejection 1/90
- CF5-7 Uncontrolled Rod Motion 1/90.
CAF-8 ' Auto Rod Speed Controller Failure 1/92 1/92
..CRF-9 Tref Failure CRF DRPI - Loss of Voltage 1/92 CRF-11' DRPI - Open or Shorted Coll 1/92.
'CRF-13 Stuck Rod 1/92 Rod Control System Failure 1/92-
)CRF -'CRF-15 Power Cabinet Urgent Failure . 1/89 i CRF Logic Cabinet Urgent or Non-Urgont 1/89 Failure
, CRF-17= Rod Bank Misalignment 1/89 CRF-18 ~ Rod. Stops Fall 1/89
~CRF-19 Urgent Failure in Logic section of 1/89 Shutdown Banks C, D and'E
.CRF-20 Reactor Trip Failure- 1/89
.CRF-21 Manual Reactor Trip Failure 1/90 CRF-23 OTAT Setpoint Failure 1/90 CRF OPAT Setpoint Failure 1/90 CRF-25 Under-Voltage on RCP Buses 1/90 CRF-26 Under-Frequency on RCP Buses 1/90 EPS-1 Loss of Off Site Power 2/91 EPS-2 Main Generator. Voltage Regulator Failure 2/91 EPS-3 345 KV Switchyard Bus Trip 2/91 EPS-4 Loss of Non ESF Bus 2/91 EPS-S Loss of ESF Bus 2/91 EPS-6' Diesel Generator Failure 2/91 EPS-7 Loss of D.C. Distribution Bus 2/92 EPS-8 Loss of 120 VAC ESF Instrument Bus 2/92 EPS-9 Load Rejection 2/92 EPS-10 Loss of 6.9 KV Bus 2/92 EPS-11 Loss of Feed to 480 Volt ESF Bus or MCC 2/92 EPS Failure of System Aux Transformer (SAT) 2/89
'EPS-14 Failure of Unit Aux Transfonner (UAT) 2/89 EPS-17. 120 VAC Instrument Bus Inverter Failure 2/89 EPS-18 Main Generator Enciter Failure 2/89 EPS-20 Loss of SX Cooling to Diesel Generator 2/90 EPS-21 Safeguard Shutdown Relay Failure 2/90 EPS-22 Diesel Generatcr Failure to 2/90 Flash Generator Field 618M/251M/14 7/89
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PWR OPERATIONS GUIDELINE NUMBER 12 SIMULATOR TESTING PROGRAM.
ATTACHMENT B SIMULATOR CERTIFICO MALFUNCTION TEST SCHEDULE
> , ANNUAL TESTING PERIOD (Month / Year)
, MALFUNCTION MALFUNCTION- 1989 1990 1991 1992
, NUfGER- DESCRIPTION Acoroximate test date (auarter/vear)
.FWM . Main Feedwater Pump Trip 2/91' i' FWM-21 a Condensate Pump Trip 2/91 FWM Steam Generator Feedwater Control 2/91 Valve Failure .
FWM-4. Feedwater Flow Transmitter Failure 2/91 FWM-5 Turbine Driven Feedwater Pump Speed 2/91
' Control Failure FWM-6 ' Heater Drain Pump Trip - 2/91
? 'FWM-7 Feedwater Heater Bypass Valve Failure 2/91 FW8 Feed Line Break Inside Containment 2/92 FW9 ' Feed Line Break Outside Containment 2/92.
FWM-10 Feedwater Pump Speed Control Oscillates -2/92 F W 11- ~ Feedwater Mester Tube Break' 2/92 C.1-12 Auxiliary Feedwater Pump Trip ' 2/92 F W 13 Loss of Feedwater Pump Speed Control ~ 2/92 F W 14 Main Feedwater 011. Pump Failure 2/92 F W 18 Feedwater Regulation Bypass Valve Failure 2/89 '
'F W 19- Feedwater Preheater Bypass Malfunction 2/89 F W 20 Aux Feedwater Valve Malfunction 2/89 F W 21- . Aux Feedwater Line Rupture 2/90 FW24 Start-up Feed Pump Trip 2/90 FW26 Steam Generator Tempering Line Break 2/90 FW28 Leak in CST 2/90 MSS-1 Steam Pressure Detector Failure 2/91 MSS-2 -Steamline Break Inside Containment 2/91
-MSS-3 Steamline Break Outside Containment 2/91 KSS-5 Main Steam Isolation valve (s) Failure 2/91 MSS-6 Steam ' Generator Atmospheric Relief 2/32 1 Valve Failure MSS-7 Steam Dump Cooldown Valves Control 2/92 i' Failut e MSS-B Steam Dump Control Failure 2/92 MSS-9 Stuck Steam Dump Valve 2/92 MSS-10' Main Steam Hender Steam Leak 2/89 MSS-11 Steam Flow Detector Failure 2/89 MSS-13 Steam Generator Safety Valve Failure 2/89 MSS-14 Steam Line Pressure Detector (PT-507) 2/90 Failure
. MSS-15 MSR Relief Valve Failure 2/90
. MSS-16 Turbine Driven MFP Control Valve Failure 2/90
,. MSS MSIV Bypass Valve Failure 2/90 MSS-18 Steam Generator Atmospheric Relief 2/90 Valve Failure 618M/251M/15 7/89
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'PWR OPERATIONS GUIDEL2NE NUMBER 12 SIMULATOR TESTING PROGRAM ATTACHMENT B SIMULATOR CERTIFIED MALFUNCTION TEST SCHEDULE ANNUAL TESTING PERIOD (Month / Year) -
MALFUNCTION ' MALFUNCTION 1989 1990 1991- 1992 NUMBER DESCRIPTION Approximate test date (cuarter/vear) ,,
NIS-1 Source Range Chsnnel Failure . 2/91 NIS-2 Intermediate Range Channel Failure 2/91 NIS-3 Power Range Channel Failure 2/91 NIS Intermediate Range Channel Genna 2/91' Compensation Failure N!S-7' . Power Range Detector Failure '2/92 NIS-3 Source Range Channel High Voltaco Failure 2/92 NIS-10 . Inadvertent Fuel Loading 3/89
,NIS-11 Improper Detector Overlap .
3/89 Source Range Discriminator. Failure 2/90
./NIS-12
>'NIS-15 Leak Into Guide Tube for Incore Detector 2/90 PCS-1 Reactor Trip Breaker Failure 3/91
-PCS-2 : First Stage Pressure Transmitter Failure 3/91 PCS-3 Stewn Generator Level Control Failure 3/92 PCS-4' Unstable Steam Generator Level Controller 3/92
.PCS-5 Inadvertent Safety Injection Actuation 3/89
< PCS-6 Inadvertent Containment Isolation (Phase A) 3/89 PCS-7 Inadvertent Containment Isolation (Phase B) 3/90 PCS-8 Failure of Safety Injertion to Actuate 3/90 PCS-9 Failure of Steam Generator Level Program 3/90 PCS-10 Failure of'Feedwater Isolation to Actuate 3/91'
.,7 PRS-1 Pressurizer Pressure Channel Failure 3/91 l PRS-2 Pressurizer Level Channel Failure 3/91 PRS-3' Fa cssurizer Spray Valve Failure 3/91 PRS-4 Pressurizer Relief Valve f ailure 3/91
. Pressurizer Safety Vaive Failure 3,'92 PRS -6 l PRS-7 Pressurizer Pressure Master Controller 3/92
. Failure PkS-8 Pressurizer Level Master Contro11e* 3/92 Failure PRS-9 Pressurizer Steam Space Leak 3/89 PRS-11 Pressurizer Power Operated Relief Valve 3/89 Stuck Open PRS-17 Failure of PRS PORV Block valves 3/90 RCS-1 Faulty Primary RTD (Narrow Range) 3/91 RCS-2. Steam Generator Tube Leak 3/91 RCS-3 Reactor Coolant Pump Trip 3/91 PCS-4 Reactor Coolant Pump Locked Rotor 3/91 RCS-S~ LOCA (LArge)- 3/91 RCS-6 RCS Leak 3/92 l PCS-7 Reactor Vessel Flange Leak 3/92 61BM/251M/16 7/89
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ATTACHMENT B SIMULATOR CERTIFIED MALFUNCTION TEST SCHEDULC ANNUAL TESTING PERIOD (Month / Year)
,' MALFUNCTION' 1989- 1990 '1991 .1992
.. MALFUNCTION NUMBER' DESCRIPTION Acoroximate test date Iduarter/vear)
RCS-9 RCS Loop Flow Transmitter Failure 3/92-RCS-12 -RCP Shaft 8reak '3/89 RCS-14 RCS Fuel Element Failure 3/89 RCS-15'. RCS Wide Range Pressure Transmitter 3/89 Failure RCS-16' RCS Wide Range RTD Failure 3/90 RHR-1 RHR Pump Trip; 3/91
-RHR-2 RHR Heat Exchanger Flow Control Valve - 3/91 l
Failure L RHR-3 RHR HX Bypass Valve Control Failure 3/91 RHR-4 RHR HX Bypass Line Leak- 3/92 RHR-5. Safety Injection. Pump Failure 3/92
-RHR-6 S. I.. Accumulator Malfunction 3/92 RHR-7 Containment Spray Pump Failure 3/89 RHR RHR Aute Switchover Malfunction . 3/89 RHR-9 RCFC 7ailure 3/89 RHR-11 . RWST Level Transmitter Malfunction 3/90 TUR-l' Inadvertent . Turbine Trip 3/91 l
TUR-2. Turbine Vibration 3/91 TUR-7'- Stator Water Cooling Trouble 3/92 TUR41-- TV/GV Servo Failure - Valve Fails Open .3/92' TUK-12: Turbine Auto Runback 3/92 Tull Turbina Trip Failure 3/89 TUR-14 DD!C - Govr,rnor Valve A4 Oscillation 3/89 Loss of Power to Emergency Overspeed Trip 1/69 .y l TUR-18 1 Cabin.st (IPA 38J) -
TU4-19' Turbine Trip on Low Load. Indication 3/90 TUR-21 Stator Cooling Water Purap Trouble 3/90 1UR-22 Seal Oil System Pump Trips 3/90 a
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July,' 1989 i PWR OPERATIONS GUIDELINE NUMBER 12 SIMULATOR TESTING PROGRAM ATTACHMENT C
. SIMULATOR NON-CERTIFIED MALFUNCTION TEST SCHEDULE
=
NOTE
- Although Attachment C Malfunctions are '
- Non-Certified Malfunctions, these
- malfunctions shall be testad every 4 years *
- per ANSI /ANS-3.5 - 1985 .nd Reg. Guide
- 1.149 guidance. These malfunctions may be *
- used to enhance simulator training. *
..........s...................................
ANNUAL TE' STING PERIOD (Month / Year)
MALFUNCTION 1989 1990 1991 1992 p MALFUNCTION NUMBER DESCRIPTION Aooreximate test date (cuarter/vearl AUX-5 Leak in Primary Water Storage Tank 1/92 AUX-6 CRT Malfunction 1/92 AUX-7 Loss of Annunciator Panels 1/92 AUX-8 Control Room Ventilation Malfunction 1/92 AUX-9 Loss of Computer 1/89 AUX-10 SSPS Demultiplexes Failure 1/89 AUX-11 Loss of Annunciator Horn 1/89 AUX-14 Loss of Fire Protection Pressure System 1/90 AUX-15 Less of Spent Fuel Pit Co' oling Pump 1/90 AUX-16 Loss of Spent Fuel Pit Level 1/90 CCW-3 RCP Thermal Barrier Low CCW Flow 1/91 CCW-10 CCW Low Discharge Pressure 1/89 .
I CCW-12 CCW Radiation Detection 1/90 CND-4 Cire Water Pump Discharge Valve Failure 1/90 CVC-7 BTRS-Temperature Controller TE-381 1/91 Failure BTRS-Chiller Pump Failure 1/92 CVC-8 BTRS-Failure of Chiller Unit 1/92 CVC-9 BTRS-Failure of Demin Bypass (HCV-387) 1/92 CVC-10 BTRS-Temp Controller (TE-386) Failure 1/92
.CVC-11 BTRS-TK-381A&B Failure 1/92 ;
CVC-12 BTRS-TK-386 Failure 1/92 CVC-13 CVC-22. VCT Pressure Malfunction 1/90 .
CVC-24 BTRS Domineralizers Depletion 1/90 CVC-25 BTRS-FK-375 Failure 1/90 i
Rod Drive MG Set Trip 1/91 CRF-2 Rod Position Step Counter Failure 1/92 CRF CRF-22 Bank D Withdrawa*6 Interlock Failure 1/90 CRF-27 Reactor Trip Oypass Breaker Failure 1/90 4
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)
Rev 6 July, 1989 PWR OPERATIONS GUIDELINE NUMBER 12 SIMULATOR TESTING PROGRAM ATTACHMENT C SIMULATOR NON-CERTIFIED MALFUNCTION TEST SCHEDULE ANNUAL TESTING PERIOD (Month / Year)
MALFUNCTION MALFUNCTION 1989 1990 1991 1992 NUMBER DESCRIPTION Acoroximate test date (cuarter/vear)
EPS-12 Synchroscope Failure 2/92 !
D.C. Power to M.
s in Control Board Failure 2/89 i EPS-15 EPS-16 Grid Frequency Varies 2/89 l EPS-19 Diesel Generator Electric Speed Control Failure 2/90 )'
EPS-23 Synchronizing Relay Failure 2/90 EPS-24 Failure of 6.9 KV Bus ABT to Transfer 2/91 )
FWM-15 Feedwater Heater Level Control Failure 2/89 FWM-16 Feedwater Tempering Line Malfunction 2/89 FWM-17 Feedwater Isolation & Bypass Malfunction 2/89 FVM-22 Steam Jet Air Ejector Malfunction 2/90 FWM-23 Gland Steam Condenser Malfunction 2/90 ;
Main Feedwater Pump Low NPSH 2/90 :
FWM-25 FVM-27 Feedwater Pressure Detector (PT508) Failure 2/90 l MSS-4 Partial Loss of Reheater Heating Steam 2/91 MSS-12 Steam Generator Feedwater Preheater 2/89 Impingement Plate Failure NIS-5 Failure of Source Range High Voltage 2/92 to Disconnect HIS-6 Noisy Scurce Range Channel 2/92 NIS-9 Failure of Source Range Chanoc1 to Block 3/89 )
NIS-11 Incore Monitoring System Felure 2/90 hlS-14 Stuck Intore Detector 2/90 e95-5 Pressurizer Variable Hester Control 3/92 Failure PPS-10 Pressurizer Back-up Heaters Fail 3/89 l PRS-12 Press:srieer Level Detector Reference Leg 3/89 l
or Variable Leg Loak PRS-13 Pressurizer Relief Tank Lt.ak 3/90 PRS-14 Pressurizer Relief Line RfD Failure 3/90 PRS-15 PRY Level or Pressure Detector Failuro 3/90 PRS-16 RCDT Pumps Fall te Start 3/90 RCS-S Variablo RCS Boron Ccocentration 3/52
.RCS-11 RCP riest Input to RCS 3/89 RCS-13 P.CS Cold Leg Isolation Valvo Interlock 3/89 Failure RCS-17 RTD Manifold Faelty Flow ionditions 3/90 RCS-18 RCP Temperature A! arms 3/90 RCS-19 RCP Lif t Oil Pump Feilure 3/90 l 618M/251M/19 7/89
Rev 6-E- .. .lul y, 1989 -
PWR OPERATIONS GUIDELINE NUMBER'12 SIMULATOR TESTING PROGRAM ATTACNMENT C SIMULATOR hDN-CERTIFIED MALFUNCTION TEST SCHEDULE ANNUAL TESTING PERIOD (Month / Year)
MALFUNCTION MALFUNCTION 1989 1990 .1991' 1992 NUMBER DESCRIPTION ' Accroximate test date f auarter/vear)
Containment Spray Eductor Malfunction 3/90 RHR-10
'RMS-1 Particulate Air Monitor Failure. 3/92-RMS-2 ' Area Radiation Monitor Actuation 3/89 ty RMS-1 Process Radiation Monitor Actuation 3/90
? TUR-3 ' Failure of L.P. Turbine Inlet Pressure 3/91 Sensor (MSUO3) -
'TUR-4 ' Loss of DEHC Speed Channel (s)' 3/91 TUR-5 Loss of DEHC Supervisory Speed Control 3/91 Thanne1~
'TUR-6 DEHC - First 5tage Pressure Transmitter ' '3/92
~
Failure (MS 002)
TUR-8 DEMC - PW Transducer Failure 3/92 TUR DEHC - Computer Failure 3/92
-TUR - Operator Control Panel Pushbutton Sticks 3/92 TUR-15 Turbine Oil Pump Failure 3/S9-TUR-16. Throttle or Governor Valves not Tracking 3/89 Auto TUR-17 Governor Valve Transfer Failure 3/89
.TUR-20 Stator Cooling Water. Conductivity 3/90 TUR-23 Seal Oil Pressure Regulator Failure 3/90 TUR-24 . Vkrious Generator Auxiliary Temperature Controllers 3/90 l fail i
i l
1 618M/251M/20 7/89 i i
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- ATTACHMENT:10 BRAMO@ SWLATOR ANSI /ANS 3.5 CERTIFICATION REPORT INITIAL REPORT, MAY, 1988 l l
1
'A.1.2.2 Panels / Equipment The Braidwood Simulator consists of the following panels / equipment:
1 p-
- a. IPM01J
- b. IPM02J
- c. IPM03J
- d. 1PM04J
- e. IPM05J
- f. IPM06J
- g. IPM07J
- h. IPM08J
- i. 1PM11J
.i . OPM01J
- k. OPM02J
- 1. OPM03J
- m. IPLO4J (Remote Shutdown Panel)
- n. 1PLO5J (Remote Shutdown Panel)
- o. IPLO6J (Remote Shutdown Panel)
- p. RM-11/ESD (IPM14J)
- q. Plant Computer (limited modeling) (1CX05J)
- r. The Braidwood Simulator is partially modeled for IPM12J. The following components are modeled:
- 1) Lift coil disconnect switch box (located at IPM07J).
- 2) WR NI chart recorders.
- 3) Boric acid tank level chart recorder.
- 4) Cnmt drain sump flowrate chart recorder.
- 6) SJAE/GS condenser chart recorder.
- 7) RIL vs. bank position (8-pen) chart recorder.
10c/5 5/88
ATT CHMENT111' TRANSIENT TEST BASELINE DATA' REVIEW BOARD LMembers ' Qualifications-
- 1. Renzi Mertogul' Position - Shift Technical Advisor-Braidwood (TR 1-6) Background - SRO License-Braidwood Units l'&'2
- BS/MS Nuclear Engineering
- Braidwood Station Nuclear Engineer (2 yrs.)
- Braidwood Assistant Technical' Staff Supervisor (1.5 yrs.)
- 2. George Vanderheyden Position - Braidwood Operations Training (TR 8-10) Supervisor Background - SRO License-Braidwood Units 1 &'2
- Braidwood Shift Foreman (1.5 yrs.)
- Braidwood Reactor Operator (2.5 yrs.)
- 3. Danny Ackerman - Position - Braidwood License Operator
-(TR.7) Instructor Background - SRO License-Braidwood Units 1 & 2
- Navy - EWS (8 yrs.)
- 4. Kenneth D. Gerling Position - Byron /3raidwood Operations
'(TR 1-10) '
Simulator Training Supervisor Background - SRO License-Byron-1984
- SRO Certification-Zion-1979
- Zion Simulator Instructor
- Operations Department-Quad Cities '7 yrs.)
- Navy - EE5 (6 yrs.)
l 5. Mark Hoffman Position - Byron /Braidwood License Operator l (TR 1-10) Instructor BackEround - SRO Certification-Braidwood Simulator
- BS Chemical Engineering j - Transient & Accident Analysis l Instructor
! - Thermal Hydraulics Instructor
- 6. Russell Coon Position - Byron /Braidwood License Operator (TR 1-10) Instructor Background - SRO Certification-Braidwood Simulator
- Navy - E00W/EWS (8 yrs.)
I i
L______________ _ _ _ _ _ _ _ _ _ _ _ _
i.-.- ,,
TRANSIENT TEST BASELINE DATA REVIEW BOARD Members Qualifications
- 7. Daniel Burton Position - Byron /Braidwood License Operator (TR 1-10) Instructor Background - SRO Certification-Braidwood Simulator
- Navy - EWS (8 yrs.)
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l Steam Header Pressure (psie) Recorder,4 Pen 2 156 1?o /OrG 970 i f Steam Flow - Loop A (10* LB/HR) 1FR-510 , Lr XXX XXX 3.E i Dem Flow - Ecop B (1,QO LB/HR) 1FR-520_, 7. (, XXX XXX ,MNir 3L j
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g{ ant Operating Level (195e-Gross) 1JR-MP003 /orm XXX XXX //rp> !
Qr-Nuclear (%) INR-45 K7 #7 YRS ~ 972_
, rave ( Auctioneered High) (*F) 1TR-412 $~?O $7P TP T g?3
- Loop A * ('F) Recorder 2 Pen 1 510.0 3 7F.4 C F2. 7 8; F2.7
('F) -
Recorder 2 Pen 2 SF00 577. Y S r2.*7 u23 d lg[ve-LoopB (*F) Recorder 2 Pen 3 s M"? 57f.f E32.7 gy . Loop C s 72.7 ,
fare - Loop D (*F) Recorder 2 Pen 4 s n a 5 7F.5 fr23 s Ft.C i7ef ('F) 1TR-412 #T/ XXX XXX M6/ i
%TA T - Loop A (%) 1TR-411 YO 70 /CD PF j'g g 5jihr Setpoint - Loop A (%) 1TR-411 jb f, XXX XXX
@ T Setpoint - Loop A (%) 1TR-411 /Zf XXX XXX Rf 9 Esseuriser Pressure (psic) 1PR-455 219'o 2270 22VC 22.76 q Eessuriser Level (%) ILR-459 , S2. 9'? 5"7 f7 ;
Esas Header Pressure (osio) Recorder 4 Pen 2 *l6F 987. 956 156 1 Esas Flow - I400 A (10' LB/HR) 1FR-510 C7. 2. XXX XXX 7. 6 ,
Steam Flow - Loop B B.JL 3. 5>
(106 E.8/HR) 1FR-520 XXX XXX re feas Flow - Loop C (106 L3/HR) IFR-530 .F. 2E XXX XXX 3. 6.5~ i eas Flow - Loop D ( 1,0 6 LB/HR) 1FR-540 3.2.3- XXX XXX 3. d f- !
p#ifts Generatoe Level-toop A (%) 1FR-510 66/ ::rf 6 ~7 (. 4/ )
, fas Generator Level-Loop 3 (%) 1FR-520 6f // 4P 6 s <
stees Generator Level-Loop C (%) 1FR-530 6 S- (o 7 (l. f G r"'-
l steas Generator Level-Loop D (%) IFR-540 6W- 62. f. 7 6 u, 5--
feedvetor Temperature-Loos, A (*F) TO418K 'f"CA # 5~4/14.0 XXX XXX 4/34. /
feedwater Temperature-tooo B (*F) TO438K 'f bL .4/25 3 XXX XXX v'3 3. V Feedwater Temperature-toop C (*F) TO458N is / et/rl #25~f XXX XXX 6/7 V, o Feedwater Temperature-toop D (*F) TO478N V2 f 5" XXX XXX V73. fo '
Feedwater Flow - Coop A (10* LB/HR) 1FR-510 3. 3 XXX XXX .7. fa .$~
Feedwater F18w - Loco B (106 Lgfpgt) 1FR-520 .7. "2 XXX XXX 3. (a reedwater Flow - toop C (100 LB/HR) 1FR-530 2.2 XXX XXX 3. 7 Feedwater Flow - Loop D (100 LB/HR) 1FR-540 J.n2 XXX XXX 3. 6, Feed Pump Disch. Hdr. Pres. (osio) Recorder 5 Pen 6 s e co em "#1- ass-Feed Pump B Speed (RPM) Recorder 5 Pen S Wo 9F.t o T4 (No
' Control Rod Pos. - Bank C (Steps) U0051 22P "lXX XXX 22P Control Rod Pos. - Bank D (Stops) U0052 /70 XXX XXX .t.2 3 Baron Concentration (PPN) tog Book (3 J2) XXX XXX t- S"'O fhuct. he As M (fe) GB.*U9t l W4 PC.O Ptl O 970 9 f.C o
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