ML043550103
| ML043550103 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/18/2004 |
| From: | Gody A Operations Branch IV |
| To: | Venable J Entergy Operations |
| References | |
| 50-382/04-301, ES-301, ES-301-1, NUREG-1021, Draft Rev 9 50-382/04-301 | |
| Download: ML043550103 (9) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Waterford 3_________________ Date of Examination: 11/15/04___
Examination Level (circle one): RO / SRO Operating Test Number: ____1___
Administrative Topic Describe activity to be performed:
(See Note)
Conduct of Operations JPM - Perform Review of a Manually Generated Estimated Critical Position. Candidate must determine the validity of the ECP based on given initial conditions.
Conduct of Operations JPM - Determine Surveillances Required to be Performed to Recommence Core Alterations Based on Data from Previous Precore Alteration Checklist.
Equipment Control JPM - Review and Approve an EOS. Applicant must find 4 errors with the provided EOS.
Radiation Control JPM - Determine Actions/Restrictions Required for a Containment Entry at Power.
Emergency Plan JPM - Review and Approve a Notification Message Form. The applicant must find four errors in the provided form based on provided initial conditions.
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
NUREG-1021, Draft Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Waterford 3_________________ Date of Examination: 11/15/04___
Examination Level (circle one): RO / SRO Operating Test Number: ____1___
Administrative Topic Describe activity to be performed:
(See Note)
Conduct of Operations JPM -Perform a Shutdown Margin Calculation with one dropped CEA.
Conduct of Operations JPM - Determine Allowable Power Ascension Rate using Fuel Preconditioning Guidelines and Given Initial Conditions.
Equipment Control JPM - Perform RO review of a manually generated Tagout. The candidate must find 4 major errors associated with the Tagout.
Radiation Control Not Selected Emergency Plan JPM - Activate the Emergency Response Data System (ERDS).
NOTE: All items ( 5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
NUREG-1021, Draft Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Waterford 3 Date of Examination: 11/15/04 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: 1 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Safety Code* Function
- a. Makeup to the VCT Using the Auto Makeup Mode D, S, L, A 1 (Selected Boric Acid Makeup Pump Trips)
- b. PNPO Immediate Operator Actions on CR Evacuation D, C, A 3
- c. Perform Anticipated Transient System Check (DRTS) D, S, L 7
- d. Re-energize A3S From A2 with EDG A Loaded (EDG Trips M, S, A 6 on Overspeed during Paralleling Operations)
- f. Perform Ac tions on a Recirculation Actuation (Leak on M, C, L, A 2 Suction Line)
- h. Align CARS for Containment Pressure Control D, S 5 Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U
- i. Place a Gas Decay Tank on Decay N, R 9
- j. Line up Potable Water to Instrument Air Compressors D, L 8 during Control Room Evacuation (No Fire)
- k. Startup A Safety Related Battery Charger (High Voltage D, A 6 Shutdown)
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA NUREG-1021, Draft Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Waterford III Date of Examination: 11/15/04 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: 1 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Safety Code* Function
- a. Makeup to the VCT Using the Auto Makeup Mode D, S, L, A 1 (Selected Boric Acid Makeup Pump Trips)
- b. PNPO Immediate Operator Actions on CR Evacuation D, C, A 3
- c. Perform Anticipated Transient System Check (DRTS) D, S, L 7
- d. Re-energize A3S From A2 with EDG A Loaded (EDG Trips M, S, A 6 on Overspeed during Paralleling Operations)
- f. Perform Actions on a Recirculation Actuation (Leak on M, C, L, A 2 Suction Line)
Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U
- i. Place a Gas Decay Tank on Decay N, R 9
- j. Line up Potable Water to Instrument Air Compressors D, L 8 during Control Room Evacuation (No Fire)
- k. Startup A Safety Related Battery Charger (High Voltage D, A 6 Shutdown)
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA NUREG-1021, Draft Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Waterford 3 Date of Examination: 11/15/04 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: 1 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Safety Code* Function
- a. Makeup to the VCT Using the Auto Makeup Mode D, S, L, A 1 (Selected Boric Acid Makeup Pump Trips)
- b. PNPO Immediate Operator Actions on CR Evacuation D, C, A 3
e.
f.
g.
h.
Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- i. Place a Gas Decay Tank on Decay N, R 9
- j. Line up Potable Water to Instrument Air Compressors D, L 8 during Control Room Evacuation (No Fire) k.
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA NUREG-1021, Draft Revision 9
Appendix D Scenario Outline Form ES-D-1 Facility: Waterford III Scenario No.: 1 Op-Test No.: 1 Examiners: ____________________________ Operators: __________________________
Initial Conditions: IC-20, 100%, MOC Turnover: RCP 1A Anti - Reverse Rotation Device Temperature experienced a step change from 175ºF to 195ºF two days ago. Charging pump AB has been OOS for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to replace a cracked pump block. CS Pump A has been OOS for 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> to replace the pump impeller.
Event Malf. No. Event Type* Event No. Description After the crew takes the shift, the in-service PZR pressure control channel fails low. The crew should implement OP-901-120, PZR 1 RX14A I-RO/SRO Pressure Control Malfunction, Subsection E0 and E1.
After transferring to the non-faulted PPCS Channel, a S/G1 Narrow Range control channel instrument fails high causing the controllers for FWCS 1 to shift to manual. The crew should implement OP-901-201, Steam Generator Level Control Malfunction, and control S/G 1 level manually. Post trip, the Main and Startup Feed 2 SG05A I-BOP/SRO Reg Valve controllers must be placed in a RTO condition.
After the crew addresses OP-901-201, RCP 1A Anti Reverse Rotation Device (ARRD) Temperature starts rising. The crew should implement OP-901-130, RCP Malfunction, Subsections E0 and E6.
R-RO The temperature continues to rise until the crew is required to 3 RC33A N-BOP/SRO perform a plant shutdown in accordance with OP-010-005, Plant Shutdown.
After the crew satisfies the reactivity manipulation two CEAs drop, requiring a manual reactor trip, OP-901-102, CEDMCS or CEA Malfunction, Subsection D, Immediate Operator Actions. After RD02A01 tripping the reactor the crew should go to OP-902-000, Standard 4 RD02A02 C-RO/SRO Post Trip Actions.
The Main Turbine fails to trip automatically on the reactor trip, 5 RP03 C-BOP/SRO requiring the SNPO to manually trip the Main Turbine.
After the crew diagnoses to OP-902-001, a Feedwater Line Break occurs inside containment on S/G 1. The crew should transition to 6 FW38A M-ALL OP-902-004, Excess Steam Demand Recovery.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: Waterford III Scenario No.: 2 Op-Test No.: 1 Examiners: ____________________________ Operators: __________________________
Initial Conditions: IC-27, 61%, EOC Turnover: FWPT B was secured 3 days ago to determine cause of a high vibration problem. RCP 1A Anti - Reverse Rotation Device Temperature experienced a step change from 175ºF to 195ºF two days ago. Charging pump AB has been OOS for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to replace a cracked pump block. CS Pump A has been OOS for 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> to replace the pump impeller.
Event Malf. No. Event Type* Event No. Description After the crew takes the shift, SUT A fails requiring evaluation of AC offsite circuits operability, Technical Specification 3.8.1.1.
1 ED02C C-SRO OP-903-066 must be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
After the crew evaluates Technical Specification requirements, the in-service letdown flow control valve fails closed. The crew should implement OP-901-112, Charging or Letdown Malfunction, 2 CV30A2 C-RO/SRO Subsection E0 and E2.
After the crew implements OP-901-112, Containment Fan Cooler A trips. The crew should start the idle Containment Fan Cooler i n accordance with OP-008-003, Containment Cooling System, 3 CH01A C-BOP/SRO Subsection 6.1 and evaluate Tech Spec 3.6.2.2 and 3.4.5.1.
After the crew places the alternate letdown flow control valve in service, RCP 2B shaft seizure occurs, resulting in automatic reactor trip signals being generated and loss of the offsite power source to RP01A-D Train A safety buses. The reactor fails to trip automatically or by RP02A-D manual pushbuttons, however, Diverse Reactor Trip pushbuttons 4 RC03D C-RO/SRO work.
EDG A output breaker fails to close automatically. The BOP should manually close the EDG A output breaker. Startup Feed Reg Valve 1 fails closed on the trip, requiring the BOP to take manual control of Main Feed Reg Valve 1 to restore S/G 1 level. Charging Pump A fails to auto start post trip, requiring the RO to manually start Charging Pump A. The crew should implement OP-902-000, EG12A1 C-BOP Standard Post Trip Actions (SPTAs). During the verification of CV02A C-RO SPTAs a Main Steam Line Break outside containment occurs on FW20A2 C-BOP S/G 2. The crew should diagnose to OP-902-004, Excess Steam 5 MS-13B M-All Demand Recovery.
After the crew diagnoses to OP-902-004 and S/G dryout occurs, a Steam Generator Tube Rupture occurs in S/G 2. The crew should 6 SG01B M-ALL implement OP-902-008.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Facility: Waterford III Scenario No.: 3 Op-Test No.: 1 Examiners: ____________________________ Operators: __________________________
Initial Conditions: IC-10, 100%, BOC Turnover: RCP 1A Anti - Reverse Rotation Device Temperature experienced a step change from 175 ºF to 195 ºF two days ago. Charging pump AB has been OOS for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to replace a cracked pump block. CS Pump A has been OOS for 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> to replace the pump impeller.
Event Malf. No. Event Type* Event No. Description After the crew takes the shift, the PPS Channel B S/G 1 narrow range level instrument fails high. The crew should evaluate TS 3.3.1 and 3.3.2 and take required actions to bypass the S/G Level High, S/G Level Low and S/G Delta-P trips for S/G 1 in PPS Channel 1 SG10B I-BOP/SRO B within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
After the crew bypasses the affected PPS bistables, CEA 20 drops into the core. The crew should implement OP-901-102, CEDMCS or CEA Malfunction, Subsection E0 and E1. The crew should also implement OP-901-501, PMC or COLSS Malfunction, Subsection E0 2 RD02A20 C-All and E2..
Within 15 minutes of the dropped CEA the crew must start a power R-RO reduction in accordance with OP-901-212, Rapid Plant Power 3 N/A N-BOP/SRO Reduction.
After the reactivity manipulation is satisfied, the in-service PZR pressure control channel fails high. The crew should implement OP-901-120, PZR Pressure Control Malfunction, Subsection E0 and E1. After transferring to the non-faulted PPCS Channel. PZR Spray Valve B remains open requiring implementation of OP-901-120, Subsection E3. This requires manually tripping the reactor and securing at least RCP 1B. After the RCP is secured the Spray Valve RX14A closes. The crew should continue in OP-902-000 and diagnose to 4 RC14B1 C-All OP-902-001, Reactor Trip Recovery.
After the crew commences implementation of OP-902-001, a Small SI02B Break LOCA occurs. The crew should transition to OP-902-002.
SI01A C-BOP HPSI pump A trips on overcurrent. HPSI Pump B fails to auto start 5 RC23D M-ALL requiring the BOP to perform a manual start.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor