ML17229B013
| ML17229B013 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/12/1999 |
| From: | Stall J FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-99-32, NUDOCS 9902260043 | |
| Download: ML17229B013 (44) | |
Text
P, CATEGORY 1 P
REGULATORY INFORMATION DISTRIBUTIOOSYSTEM (RIDE)
ACCESSION NBR;9902260043 DOC.DATE: 99/02/12 NOTARIZED: NO DOCKET FACIL:50-..335 St. Lucie Plant, Unit 1, Florida Power &, Light Co. 05000335
, 50>589.St. Lucie Plant, Unit 2, Florida Power & Light Co.. 05000389 AUTH.NA?4E .. AUTHOR AFFILIATION STALL,J.A. Florida Power &. Light Co.
RECIP:NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Forwards 1999 plant reference simulator certification rept for St Lucie,Units 1 & 2,per. 10CFR55.45(b)(5)(ii) 10CFR55.45(b) (5) (vi) .Rept contains description & schedules A for correcting test failures & testing completed.
T DISTRIBUTION CODE': ADO SD COPIES RECEIVED: LTR 1 ENCL 1 SIZE, TITLE: Simulator Facility Certification - GL-90-08 E NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL GLEAVES,W 1 1 INTERNA E CENTER 01 1 1 EXTERNAL: NRC PDR 1 1 D
E N
WASTETH NOTE TO ALL MRIDSM RECIPIENTS:
PLEASE HELP US TO REDUCE TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTR1BUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 3 ENCL 3
Florida Powers Light Company,6351 S. Ocean Orive, Jensen Beach, FL34957 February 12, 1999 L-99-32 10 CFR 55.45 10 CFR 50.4 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 RE: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 1999 Plant-Referenced Simulator Certification Re rt Pursuant to 10 CFR 55.45(b)(5)(ii) and 10 CFR 55.45 (b)(5)(vi), attached is the 1999 Plant-Referenced Simulator Certtftcatt'on Report for St. Lucie Units 1 and 2. This report is required every four years. The original certification was submitted on February 21, 1991, by FPL letter L-91-48. FPL letter L95-04 submitted the 1995 Plant Referenced Simulator Certijication Report on February 15, 1995. The rcport is required to contain a description and schedule for correcting test failures, a description of the testing completed, and a description and schedule of testing, if different, to be performed during the next four year interval.
The required information is included in the enclosed report. Section 1 is a list of certification tests performed by year during the past four years. Section 2 is a list of open deficiencies identified during the interval tests and includes the scheduled completion dates. Section 3 identifies the single plant change/modification that has not yet been incorporated into the simulator. Section 4 is a list of additions, deletions, and revisions to the certification test program. Section 5 is the test schedule for the next interval. Section 6 includes abstracts of new test procedures to be included in the next interval.
Please contact us ifthere are any questions about this submittal.
Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/GRM 2 t> 0 r~'r 4 7 cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant 9902260043 9902i2 PDR ADQCK 05000335 P PDR an FPL Group company
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D St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 1 ST. LVCIE UNITS 1 AND 2 1999 PLANT REFlHU<RICED SIMULATOR CERTIFICATIONREPORT
4 St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 I 99-32 Enclosure Page 2 SECTION 1 CERTIFICATION TEST LIST FOR PERIOD 1995-1998
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L99-32 Enclosure Page 3 Certification Tests Performed in 1995 Cert. Test Certification Test Title Reactor Tri 0'RN-001 TRN-002 Loss Of All Feedwater TRN-003 Main Steam Valve Closure TRN-004 Loss Of All Rc s TRN-005 Loss Of One RCP TRN-006 Turbine Tri From (15% Power TRN-007 Maximum Rate Power Ram TRN-008 Lar e Break LOCA With LOOP TRN-009 Mslb Inside Containment TRN-010 Failed 0 en PZR Safet Valve With No HPSI MAL-002 Ra id Gross Failure Of Multi le Steam Generator Tubes MAL-005 Small Break Loca MAI 006 Failed 0 en PORV With Loss Of Off-Site Power MAL-008 Loss Of Instrument Air Com ressors MAL-010 Loss Of Off-Site Power With Both Diesel Generators Failin MAL-017 Loss Of Condenser Level Control MAL-025 Loss Of Both Main Feedwater Pum s MAL-046 Wide Ran e Nuclear Instrumentation Failed Hi h MAL-050 T-Cold Failed Hi h n ut To RPS MAL-054 Rcs Flow Steam Generator Differential Pressure Instrument Failure MAL-068 Antici ated Transient Without Scram Atws NPE-001 Reactor Plant Heatu Cold To Hot Standb NPE-002 Nuclear Startu From Hot Standb NPE-003 Turbine Startu And Generator S nchronization NPE-005 Plant Shutdown From Rated Power To Cold Shutdown SST-001 Stead State Test At100% Power SST-002 Stead State Test At 30, 50 And 70% Power
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I St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L99-32 Enclosure Page 4 Certification Tests Performed in 1996 Cert. Test ¹ Certification Test Title TRN-001 Reactor Trip TRN-002 Loss Of All Feedwater TRN-003 Main Steam Valve Closure TRN-004 Loss Of All Reps TRN-005 Loss Of One RCP TRN-006 Turbine Trip From (15% Power TRN-007 Maximum Rate Power Ramp TRN-008 Large Break LOCA With LOOP TRN-009 Mslb Inside Containment TRN-010 Failed Open PZR Safety Valve With No HPSI MAL003 LOCA Outside Containment In The Letdown System MAL-009 Loss Of Off-Site Power MAL 012 Loss Of MA Instrument Bus MAL-013 Loss Of Non-Safety Vital AC MAL-026 Loss Of All Feedwater Pumps MAI 030 One Dropped Rod Test MAL-032 Freeze Control Rod Drive System MAL-035 Trip Generator From 100% Power MAL-042 Main Steam Line Break Outside Containment MAL-045 Large Feedwater Line Break Inside Containment MAL-047 Linear Power Range Failed High MAL-051 T-Cold (Rrs) Failed High MAL-055 Feedwater Flow (Input To 3-Element Controller)
MAL-059 Rwt Level Transmitter (Safety Channel) Failure MAL-062 Alarm Window Incorrectly Actuates MAL-064 ESFAS Failure With Small Break LOCA MAL-066 MSIS Fails To Actuate MAL-067 AFAS Fails To Actuate MAL-068 Anticipated Transient Without Scram (Atws)
SST-001 Steady State Test At 100% Power SST-002 Steady State Test At 30, 50, And 70% Power
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 I 99-32 Enclosure Page 5
'ertification Tests Performed in 1996 Cert; Test ¹ Certification Test Title SUR-002 Isothermal Temperature Coefficient Determination SUR-004 Aro Critical Boron Concentration Determination SUR-005 Plant Heat Balance SUR-008 Surveillance Requirements For Shutdown Margin, Modes 2, 3, 4, And 5 Subcritical SUR-018 Boron Flow Test
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A St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 6 Certification Tests Performed in 1997 Cert. Test 0 Certification Test Title TRN-001 Reactor Trip TRN-002 Loss Of AllFeedwater TRN-003 Main Steam Valve Closure TRN-004 Loss Of All Reps TRN-005 Loss Of One RCP TRN-006 Turbine Trip From (15% Power TRN-007 Maximum Rate Power Ramp TRN-008 Large Break LOCA With LOOP TRN-009 Mslb Inside Containment TRN-010 Failed Open PZR Safety Valve With No HPSI MAL-001 Complete Rupture Of One Steam Generator U-Tube MAL-004 Large Break LOCA With LOOP MAL-007 Loss Of Instrument Air: Air Header Rupture MAL-011 Loss Of A Safety Related AC Bus MAL-021 Loss Of Shutdown Cooling From Suction Valve Closure MAL-022 Loss Of One CCW Header MAL-024 RCS Leak Into CCW From RCP Seal Cooler MAL-028 One Stuck Rod MAL-029 One Uncoupled Rod During Startup MAL-031 One Slipped Rod Test MAL-034 Turbine Trip From (15% Power MAL-038 Pressurizer Pressure And Level Control Failures MAL039 Reactor Coolant Volume Control Failures MAL-040 Reactor Trip Initiated By A Low Steam Generator Level MAL-041 Double Ended MSLB In Containment MAI 043 Failed Open Main Steam Safety Valve MAL-048 Steam Generator Level Instrument Failure MAL-052 Rcs Hot Leg Temperature Monitor (Control Channel) Failure 1VGG 056 Steam Flow (Input To 3-Element Controller) Failure MAL-058 Containment Radiation Monitor Failure (Esfas)
MAI 060 Annunciator Panel Failures
I St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 7 t Certification Tests Performed. in 1997 Cert. Test ¹ Certification Test Title MAI 065 RAS Fails To Actuate NPE-004 Reactor Trip And Recovery To Rated Power SST-001 Steady State Test At 100% Power SST-002 Steady State Test At 30, 50, And 70% Power SUR-003 Rod Worth Measurement SUR-009 Reactor Coolant System Inventory Balance SUR-010 Wide Range Nuclear Instrumentation Channels Functional Test SUR-012 Reactor Protection System Periodic Logic Matrix Test SUR-013 Cea Periodic Test SUR-014 Turbine Valve Testing SUR-015 Hydrogen Recombiner Test
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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 8 CertiTication Tests Performed in 1998 Cert. Test ¹ Certification Test Title TRN-001 Reactor Trip TRN-002 Loss Of All Feedwater TRN-003 Main Steam Valve Closure TRN-004 Loss Of All Reps TRN-005 Loss Of One RCP TRN-006 Turbine Trip From (15% Power TRN-007 Maximum Rate Power Ramp TRN-008 Large Break LOCA With LOOP TRN-009 Mslb Inside Containment TRN-010 Failed Open PZR Safety Valve With No HPSI MAL-014 Loss Of 2B/2BB DC Bus MAI 015 Loss Of All Reps; Natural Circulation Cooldown MAL-016 Slow Condenser Vacuum Leak MAL-018 Loss Of One ICW Header MAL-019 Rupture Of One ICW Header MAI 020 Loss Of Shutdown Cooling MAL-023 Rupture Of "B" CCW Header MAL-025 Loss Of Both Main Feedwater Pumps MAL-027 Failed Power Supply To One RPS Channel MAL-033 Excessive Reactor Coolant Activity MAI 036 Inadvertent Dilution At Power MAI 037 Steam Bypass Control System Valve Pails Open MAL-044 Small Feedwater Line Break Outside Containment hGQ 049 Containment Pressure Transmitter Failure MAL-053 Rcs Hot Leg Rtd Failure MAL-057 Steam Generator Pressure Transmitter Failed Low MAL-061 Alarm Window Fails To Actuate MAT 069 Hot Shutdown Control Panel Cooldown MAL070 Loss Of One Heater Drain Pump From 100% Power SST-001 Steady State Test At 100% Power SST-002 Steady State Test At 30, 50, And 70% Power
I fl St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L99-32 Enclosure Page 9
. Certification Tests Performed in 1998 Cert.; Test"¹ .. ',.-:--~---':-':,".: Certification- Test;-.:Title SUR-006 Moderator Coefficient Determination At Power SUR-011 Diesel Generator Monthly Test Note: The following certification test numbers were deleted as noted in Table 3-2, St. Lucie Certification Test Matrix, of the Initial Certification Report dated February 15, 1991 SUR-001 SUR-007 SUR-016 SUR-017 SUR-019 MAL-063
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 I 99-32 Enclosure Page 10 SECTION 2 OPEN DISCREPANCY REPORTS ON CERTIFICATION TESTS
~ C St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 11 During the previous certification interval, a total of 21 deficiency reports have been written during certification tests. Of these 21 deficiency reports, none remain open at the conclusion of the interval.
I St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 12 SECTION 3 PLANT CHANGESMODIFICATIONS (PC/M)
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 13 Of the plant change/modifications (PC/M) reviewed and approved for incorporation in the Simulator, only two remain outstanding.
- 1. PC/M 95178-2 has replaced the outdated Tracor Westronics recorders on the Unit 2 HVAC panel with a newer model recorder. Replacement recorders are on order for the Simulator HVAC panel. The expected completion date for this PC/M is July 2000.
- 2. The reactor turbine gage boards (RTGB) and other cabinets in the plant have been repainted a different color. The schedule for painting the Simulator has not been determined.
I St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 I 99-32 Enclosure Page 14 SECTION 4 ADDITIONS, DELETIONS, AND REVISIONS TO THE CERTIFICATIONTEST PROGRAM
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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 15
- Pa'ordure No. '.-'
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Pr ocedure Bescriptioii',,:...,
MAL-069 Hot Shutdown Control Panel Cooldown The original initial condition of this certification test has the Simulator in hot standby with control already established at the Hot Shutdown Panel. In order to increase the dynamic scope of this test, the initial condition of the test has been changed to steady state 100% power. This change allows the certification test to include the Simulator's response to all of the applicable initial steps of 2-ONP-100.2, Control Room Inaccessibility. These steps include the tripping of the reactor and turbine, the securing of RCPs and other system components, and finall the transfer of control to the Hot Shutdown Panel.
MAL070 Loss of One Heater Drain Pump The last Simulator Four-Year Report committed to developing and performing a new Malfunction Certification Test. The new test involved the loss of one Heater Drain Pump (HDP) from 100% power. The report stated that the HDP would be lost due to a malfunction with its electrical breaker. Subsequently, it was decided to use a failure of the 4B Feed Water Heater Alternate Drain to trigger the malfunction and the ultimate loss of the 2B HDP. This scenario was chosen in an attempt to replicate the events of IHE-92-067 closer. This failure examines a larger portion of the Simulator's "balance of plant" response.
The final condition of the certification test has the Simulator stable at approximately 93% power with the 2B HDP off. To restart the 2B HDP and return the Simulator to 100% power, as stated in the report is not necessary. Certification Test NPE-003, Turbine Startup and Generator Synchronization, examines a similar Simulator response when the second HDP is started durin the ower increase'o 100%.
MAL-071 Plant Transient to Solid Plant Operation Due to an increased interest in solid plant operations, a certification test for this condition will be developed and performed during the ensuing four year cycle. The initial conditions will be steady state 100% power. A series of plant malfunctions will then be utilized to take the plant solid. The final condition of the test will be solid plant operations with the RCS temperature and pressure stable and within acce table limits.
St. Lucie Units 1 snd 2 ~
Docket Nos. 50-335 and 50-389 L99-32 Enclosure Page 16 SECTION 5 NIt22T FOUR YEAR TESTING SCMU)ULE
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St. tstcie Units 1 snd 2 ~
Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 17 Certification Test Schedule for 1999 Cert. Test 0 Certification Test Title TRN-001 Reactor Trip TRN-002 Loss Of All Feedwater TRN-003 Main Steam Valve Closure TRN-004 Loss Of All Reps TRN-005 Loss Of One RCP TRN-006 Turbine Trip From (15% Power TRN-007 Maximum Rate Power Ramp TRN-008 Large Break LOCA With LOOP TRN-009 Mslb Inside Containment TRN-010 Failed Open PZR Safety Valve With No HPSI MAL-002 Rapid Gross Failure Of Multiple Steam Generator Tubes MAL-005 Small Break Loca MAL-006 Failed Open PORV With Loss Of Off-Site Power MAL-008 Loss Of Instrument Air Compressors MAL 010 Loss Of Off-Site Power With Both Diesel Generators Failing MAL017 Loss Of Condenser Level Control MAL-022 Loss Of One CCW Header MAL-025 Loss Of Both Main Feedwater Pumps MAI 035 Trip Generator From 100% Power MAL-046 Wide Range Nuclear Instrumentation Failed High MAL-048 Steam Generator Level Instrument Failure MAL-050 T-Cold Failed High (Input To RPS)
MAL-054 Rcs Flow (Steam Generator Differential Pressure) Instrument Failure MAI 058 Containment Radiation Monitor Failure (Esfas)
MAL-066 MSIS Fails To Actuate MAL-068 Anticipated Transient Without Scram (Atws)
MAL-071 Plant Transient To Solid Plant Operation NPE-005 Plant Shutdown From Rated Power To Cold Shutdown SST-001 Steady State Test At 100% Power SST-002 Steady State Test At 30, 50, And 70% Power
St. Lncie Units snd 2 i ~
Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 18 Certification Test Schedule for 2000 Cert. Test Certification Test Title 0'RN-001 Reactor Trip TRN-002 Loss Of All Feedwater TRN-003 Main Steam Valve Closure TRN-004 Loss Of All Reps TRN-005 Loss Of One RCP TRN-006 Turbine Trip From (15% Power TRN-007 Maximum Rate Power Ramp TRN-008 Large Break LOCA With LOOP TRN-009 Mslb Inside Containment TRN-010 Failed Open PZR Safety Valve With No HPSI IVGQ 003 LOCA Outside Containment In The Letdown System MAL-009 Loss Of Off-Site Power MAL-012 Loss Of MA Instrument Bus MAL-013 Loss Of Non-Safety Vital AC MAL-026 Loss Of All Feedwater Pumps MAL-030 One Dropped Rod Test MAI 032 Freeze Control Rod Drive System MAL-042 Main Steam Line Break Outside Containment MAL-045 Large Feedwater Line Break Inside Containment MAL-047 Linear Power Range Failed High MAL-051 T-Cold (Rrs) Failed High MAL-055 Feedwater Flow (Input To 3-Element Controller)
MAL-059 Rwt Level Transmitter (Safety Channel) Failure MAL-062 Alarm Window Incorrectly Actuates
~064 ESFAS Failure With Small Break LOCA MAL-067 AFAS Fails To Actuate NPE-001 Reactor Plant Heatup Cold To Hot Standby NPE-002 Nuclear Startup From Hot Standby NPE-003 Turbine Startup And Generator Synchronization SST-001 Steady State Test At 100% Power SST-002 Steady State Test At 30, 50, And 70% Power
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i St. Lucie Units snd 2 ~
Docket Nos. 50-335 and 50-389 I 99-32 Enclosure Page 19 Certification. Test Schedule for 2000 Cert. Test ¹ Certification Test Title SUR-002 Isothermal Temperature Coefficient Determination SUR-004 Aro Critical Boron Concentration Determination SUR-005 Plant Heat Balance SUR-008 Surveillance Requirements For Shutdown Margin, Modes 2, 3, 4, And 5 Subcritical SUR-018 Boron Flow Test
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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 20 Certification Test Schedule for 2001 Cert. Test ¹ Certification Test Title TRN-001 Reactor Trip TRN-002 Loss Of All Feedwater TRN-003 Main Steam Valve Closure TRN-004 Loss Of All Reps TRN-005 Loss Of One RCP TRN-006 Turbine Trip From (15% Power TRN-007 Maximum Rate Power Ramp TRN-008 Large Break LOCA With LOOP TRN-009 Mslb Inside Containment TRN-010 Failed Open PZR Safety Valve With No HPSI MAI 001 Complete Rupture Of One Steam Generator U-Tube MAL-004 Large Break LOCA With LOOP MAL-007 Loss Of Instrument Air: Air Header Rupture MAL-011 Loss Of A Safety Related AC Bus MAL021 Loss Of Shutdown Cooling From Suction Valve Closure MAL-024 RCS Leak Into CCW From RCP Seal Cooler MAL-028 One Stuck Rod MAL-029 One Uncoupled Rod During Startup iVGG 031 One Slipped Rod Test MAL-034 Turbine Trip From (15% Power MAL-038 Pressurizer Pressure And Level Control Failures MAL-039 Reactor Coolant Volume Control Failures MAL-040 Reactor Trip Initiated By A Low Steam Generator Level MAL-041 Double Ended MSLB In Containment MAI 043 Failed Open Main Steam Safety Valve MAL-052 Rcs Hot Leg Temperature Monitor (Control Channel) Failure MAI 056 Steam Flow input To 3-Element Controller) Failure MAL-060 Annunciator Panel Failures MAI 065 RAS Fails To Actuate NPE-004 Reactor Trip And Recovery To Rated Power SST-001 Steady State Test At 100% Power
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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 21 Certification Test Schedule for 2001 Cert. Test 0 Certification Test Title SST-002 Steady State Test At 30, 50, And 70% Power 8UR-003 Rod Worth Measurement SUR-009 Reactor Coolant System Inventory Balance SUR-010 Wide Range Nuclear Instrumentation Channels Functional Test SUR-012 Reactor Protection System Periodic Logic Matrix Test SUR-013 Cea Periodic Test SUR-014 Turbine Valve Testing SUR-015 Hydrogen Recombiner Test
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 22 Certification Test Schedule for 2002 Cert. Test I/ Certification Test Title TRN-001 Reactor Trip TRN-002 Loss Of All Feedwater TRN-003 Main Steam Valve Closure TRN-004 Loss Of All Reps TRN-005 Loss Of One RCP TRN-006 Turbine Trip From (15% Power TRN-007 Maximum Rate Power Ramp TRN-008 Large Break LOCA With LOOP TRN-009 Mslb Inside Containment TRN-010 Failed Open PZR Safety Valve With No HPSI MAL-014 Loss Of 2B/2BB DC Bus MAL-015 Loss Of All Reps; Natural Circulation Cooldown MAL-016 Slow Condenser Vacuum Leak MAL-018 Loss Of One ICW Header MAL-019 Rupture Of One ICW Header MAL-020 Loss Of Shutdown Cooling MAL-023 Rupture Of "B" CCW Header MAL-027 Failed Power Supply To One RPS Channel MAL-033 Excessive Reactor Coolant Activity MAL-036 Inadvertent Dilution At Power MAI 037 Steam Bypass Control System Valve Fails Open MAI 044 Small Feedwater Line Break Outside Containment MAL-049 Containment Pressure Transmitter Failure EGG 053 Rcs Hot Leg Rtd Failure MAI 057 Steam Generator Pressure Transmitter Failed Low MAL-061 Alarm Window Fails To Actuate
~069 Hot Shutdown Control Panel Cooldown MAL-070 Loss Of One Heater Drain Pump From 100% Power SST-001 Steady State Test At 100% Power SST-002 Steady State Test At 30, 50, And 70% Power SUR-006 Moderator Coefficient Determination At Power
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 23 Certification Test Schedule for 200? "'"'""-"" "';"-.; . -',
Cert. Test ¹ Certification Test Title SUR-011 Diesel Generator Monthly Test Note: The following certification test numbers were deleted as noted in Table 3-2, St. Lucie Certification Test Matrix, of the Initial Certification Report dated February 15, 1991 SUR-001 SUR-007 SUR-016 SUR-017 SUR-019 MAL-063
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 24 SECTION 6 ABSTRACTS OF NEW TEST PROCEDURF8
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 25 MAL-070 LOSS OF ONE HEATER DRh JN PUMP
5.0 DESCRIPTION
5.1 Approach This scenario is modeled after a Unit 2 event, IHE-92-067, where the 2B Heater Drain Pump tripped while at 100% power. During the event, the 4B Feed Water Heater Alternate Drain, LCV-11-18B, failed to re-close when the water level in the 4B Peed Water Heater returned to normal.
The water drained from the 4B Peed Water Heater to the low-level setpoint, tripping the 2B HDP. This certification test will be initiated by failing high the controller for LCV-11-18B. The controller will signal LCV-11-18B to open fully. The level in the 4B Feed Water Heater will drain down to the low-level setpoint and thereby, trip the 2B HDP. A downpower will then be performed in order to stabilize the Simulator at approximately 93% power.
5.2 Initial Conditions/Final Conditions Initial Conditions:
100% Power, Steady State, Middle Of Life.
Final Conditions:
Stable at approximately 93% power with the 2B HDP off.
5.3 Options The simulator is capable of a loss of a HDP from several different causes. For the purpose of this test, the HDP will trip due to a low level in the 4B Peed Water Heater. This scenario was chosen in an attempt to replicate the events of IHE-92-067.
5.4 Limitations and Assumptions This test involves only a loss of the 2B HDP, and does not include any other possible malfunctions. Due to different idiosyncrasies of individual operators, there will be differences in how the downpower is performed and the how the Simulator is stabilized. Therefore, the various graphs recorded during subsequent certification tests may not agree exactly.
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L99-32 Enclosure Page 26
5.0 DESCRIPTION
- (continued) 5.5 General Certification Test Instructions The Certification Test (CT) provides the specific instructions for operator actions which would be performed in the plant procedures. For each step required to be performed, a space is included in this procedure for the initials of the individual who is performing the test.
6.0 OBJECTIVES
The objectives of this test are as follows:
6.1 Verify the proper response of the simulator to a loss of one HDP pump.
(ANSI 3.5, Section 3.1.2. (18))
6.2 Ensure that the operator was required to take the same action on the simulator to mitigate the consequences of a loss of one HDP pump as would have been required on the reference plant using the plant procedures. (ANSI 3.5, Section 3) 6.3 Verify that the operators/instructors did not observe a difference between the response of the simulator control room instrumentation and the reference plant. (ANSI 3.5, Section 3.1) 6.4 Ensure that the transient showed plant operations of the reference plant, which occurred continuously and in real time. (ANSI 3.5, Section 3.1.1 and 3.1.2) 6.5 Verify that the critical parameters and the other parameters, which were important to the successful completion of this evolution, were displayed on the appropriate instrumentation and provided proper alarm or protective system action, or both. (ANSI 3.5, Section 3.1.1) 6.6 Verify that the loss of one HDP pump interaction with the other simulated systems provides total system integrated response.
(ANSI 3.5, Section 3.3.1) 6.7 Verify that the simulator does not fail to cause an alarm or automatic action that would occur in the reference plant and conversely, does not cause an alarm or automatic action that would not occur in the reference plant for this evolution. (ANSI 3.5, Section 4.2.1(c))
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 27
6.0 OBJECTIVES
(continued) 6.8 Verify that the operator was able to control the transient to a steady state condition if the simulator operating limits were not exceeded. (ANSI 3.5, Section 3)
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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 28 1VGG 071 Plant Transient to Solid Plant Operation
5.0 DESCRIPTION
5.1 Approach This scenario uses a series of malfunctions to place the RCS into a solid condition. The first malfunction is a leak in the auxiliary spray system into the Pressurizer (PZR). This causes the PZR pressure to drop below the Thermal Margin Low-Pressure Trip (TMLP) setpoint resulting in an automatic reactor trip. Following the reactor trip, a second malfunction causes a rupture in the main steam line which blows down one of the Steam Generators. The RCS cooldown and resulting RCS shrink causes the RCS pressure to drop rapidly. The pressure drop is sufficient to initiate SIAS and allow HPSI injection. Once the Steam Generator has blown down, the RCS cooldown is halted and a RCS heat up starts. A third malfunction temporarily disables both of the Atmospheric Dump Valves on the unaffected Steam Generator. This limits the ability of the secondary system to depressurize and effectively remove decay heat from the RCS. The RCS heat up causes a rapid swell in the RCS liquid.
The RCS pressure increases above the PORV setpoint causing them to lift, venting the steam bubble in the PZR to the containment. Once the steam bubble is completely vented, the RCS becomes a solid system.
Once the RCS is solid, one of the ADVs becomes operable again, allowing the removal of decay heat from the RCS.
The test is complete when the RCS pressure and temperature is stabilized within acceptable limits. This will be performed by controlling the charging flow and adjusting steam flow through the available ADV.
5.2 Initial Conditions/Final Conditions Initial Conditions:
100% Power, Steady State, Middle Of Life.
Final Conditions:
RCS in solid condition with the RCS pressure and temperature stabilized and within acceptable limits.
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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-99-32 Enclosure Page 29
5.0 DESCRIPTION
- (continued) 5.3 Options The simulator is capable of being placed in solid plant operations from several different causes. For the purpose of this test, RCS is to be placed in solid plant operations by a rapid cooldown followed by a rapid heat up.
5.4 Limitations and Assumptions This test involves only the placing the plant in solid conditions, and does not include any other possible malfunctions.
5.5 General Certification Test Instructions The Certification Test (CT) provides the specific instructions for operator actions, which would be performed in the plant procedures.
For each step required to be performed, a space is included in this procedure for the initials of the individual who is performing the test.
6.0 OBJECTIVES
The objectives of this test are as follows:
6.1 Verify the proper response of the simulator to solid RCS Plant operations. (ANSI 3.5, Section 3.1.2. (18))
6.2 Ensure that the operator was required to take the same action on the simulator to mitigate the consequences of solid RCS Plant operations as would have been required on the reference plant using the plant procedures. (ANSI 3.5, Section 3) 6.3 Verify that the operators/instructors did not observe a difference between the response of the simulator control room instrumentation and the reference plant. (ANSI 3.5, Section 3.1) 6.4 Ensure that the transient showed plant operations of the reference plant which occurred continuously and in real time. (ANSI 3.5, Section 3.1.1 and 3.1.2)
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 I 99-32 Enclosure Page 30
6.0 OBJECTIVES
(continued) 6.5 Verify that the critical parameters and the other parameters, which were important to the successful completion of this evolution, were displayed on the appropriate instrumentation and provided proper alarm or protective system action, or both. (ANSI 3.5, Section 3.1. 1) 6.6 Verify that the solid RCS Plant operations interaction with the other simulated systems provides total system integrated response.
(ANSI 3.5, Section 3.3.1) 6.7 Verify that the simulator does not fail to cause an alarm or automatic action that would occur in the reference plant and conversely, does not cause an alarm or automatic action that would not occur in the reference plant for this evolution. (ANSI 3.5, Section 4.2.1(c))
6.8 Verify that the operator was able to control the transient to a steady state condition if the simulator operating limits were not exceeded. (ANSI 3.5, Section 3)