IR 05000271/1998002
| ML20203E448 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/20/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20203E442 | List: |
| References | |
| 50-271-98-02OL, 50-271-98-2OL, NUDOCS 9802270054 | |
| Download: ML20203E448 (12) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION I
Docket No:
50 271 Report No:
50 271/98 02(OL)
Licensee:
Vermont Yankee Nuclear Power Corporation Facility:
Vermont Yankee Nuclear Power Station
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Brattleboro, VT i
Date:
February 10,1998 Chief Examiner:
T. Fish, Operations Engineer Approved By:
Richard J. Conte, Chief Operator Licensing and Human Performance Branch Division of Reactor Safety
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9002270054 980220 PDR ADOCK 05000271 V
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EXECUTIVE SUMMARY A simulator retake examination (Part C, only) was administered to one senior reactor operator appilcant on February 10,1998, at the Vermont Yankee Nuclear Power Training Center. The test met NRC expectations for a quality examination The applicant passed the retake examination, I
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Benett Details
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L._.Qaetations
Operator Training and Qualifications
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05.1 Qoerator initial Examinations a.
Scope A simulator retake examination was administered to one senior reactor operator (upgrade) applicant on February 10,1998. The examination was administered in accordance with NUREG 1021," Examiner Standards," Interim Revision 8.
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b.
Observations The applicant performed well on the simulator, Indicating he had adequately addressed the deficiencies exhibited during his previous exam. The scenario contained more than the minimum number of attributes necessary to effectively evaluate the applicant's performance, c.
Conclusions The applicant passed the simulator examination and was subsequently issued a senior reactor operator license.
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Attachment: Simulator Scenario
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e ATTACHMENT 1 SRO SIMULATOR EXAMINATION l
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SCENARIO EVENTS Simulation Facility: Vermont Yankee Scenario No.1 Examiner:
Candidate:
Scenario Objectives: Evaluate crew ability to swap an operating feedwater pump with the standby pump, respond to an inoperability of two APRMs, determine that a loss of keep fil' capability has occurred, and implement abnormal and emergency operating procedures for a feedwater bicak outside containment with a concurrent loss of high pressure injection. Success path is to emergency depressurize and reflood using low pressure ECCS.
Turnover: 100% reactor power, BOL, C Reactor Feedwater Pump has high vibration and seal leakage. Management has directed that power be reduced to 98%, the B Reactor Feedwater Pump started and the C Feedwater Pump secured. Power reduction using recirculation flow has been recommended by Reactor Engineering at 1%/ min. APRM A failed downscale during the last shift and troubleshooting is in progress. The A CRD Pump is tagged out and uncoupled with maintenance work in progress.
Initial Conditions: IC 19, APRM A failed downscale NM05A at 0% and bypassed with a caudon tag. Place B CRD Pump in service and remove A CRD Pump from service. Rack
out A CRD Pump breaker RDR14.
Preinsert:
ED12A Failure of Bus I to Fast Transfer I/O DI 06A4S05 to OFF Bkr 13 Control Switch Falls to Close
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No Malf Type Description I (:00)
NA N
Swap of Reactor Feedwater Pumps i-2 (:18)
NM06D I
APRM D inoperable failure 3 (:31)
Remates C
Loss of ECCS keep fill. When AO ls set to investigate,
CSR07 report O that a severe leak on 1 inch Condensate
CSR08 Transfer line at strainer S64 3 has been detected.
I RilR01 Valves V6413, V6414A, and V64-52A must be RiiR02 closed to isolate the leak. Tech Spec determination on
operability of ECCS. If ordered to realign keep fill, it
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will not be performed durina this scenario i
4 (:40)
FW21 at MT Feedwater break outside containment
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100%, 120 l
5 (:40)
ED12A I
Failure of 4KV Bus I to fast transfer and cannot be
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I/O DI manually transferred.
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06A4S05 to OFF
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6 (:42)
RDR04 C
Close B CRD Pump discharge valve. Simulates
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cloaaed pump discharse strainer 5 (:41)
RC01 C
RCIC Trip when auto start received 6 (:41)
IIP 01 C
HPCI Trip when auto start received
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FWO8C C
Trip C FWP if operators attempt to restart
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8 (:45)
SLR C
Close SLC common discharge simulates clogged SLC
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piping. Insert if operators attempt to inject with SLC
For the Simulator Operator:
1. Approximately 3 minutes aAer the pumps are swapped insert APRM D Failure 2. Approximately 3 minutes aner the SRO has determined the proper action for the rod
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l block function with the two APRMs inoperable, insert the loss of keep fill.
l 3. Approximately 3 minutes aAer the operator has determined the proper action for the
loss of keep fill, insert the feedwater break.
l 4. As the high pressure systems auto star: or are started by the operators, insert the
l appropriate malfunction to prevent the system from injecting.
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Op Test No: 1 Scenario No.1 Event No.1 Event Description: Power Reduction and Swap of Reactor Feedwater Pumps Time Position Applicant's Actions or Behavior ROI Reduces reactor power using recirculation flow at less than or equal to 1% per minute.
ROl/RO When directed to swap feedwater pumps, uses OP 2172 Section D.
Closes B Feedwater Pump discharge valve (FWD-4B)
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l Starts B Feedwater Pump verifying pump breaker closes, discharge
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valve opens, min flow valve opens then recloses, and aux lobe oil -
l pump stops i
Runs all three pumps until system and pump parameters have
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stabilized.
Secures C Feedwater Pump by closing discharge valve, verift ing
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y aux oil pump starts, and opening the pump breaker when discharge valve is closed or pump amps are less than 400 amps.
SRO Direct ROI to reduce power to 98% using reactor recirculation flow.
Procedural guidance is OP 0105 Phase 5 reactor Power Decrease.
Power reduction should be approximately 1% per minute.
When power is approximately 98% directs ROI to place B Feedwater Pump in service and remove C Feedwater Pump from service.
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Op-Test No: 1 Scenario No.1 Event No. 2
- Event Description: APRM D Inoperable Failure Time Position Applicant's Actions or Behavior Rol Investigates annuciators on 9-5,1-1 AUTO SCRAM CH B, L 2 NEUTRON MON POWER HI and M 2 APRM B, D, F HI Hl/INOP Determines based on indications that no APRM is high therefore one must be inoperable and the back panel must be investigated.
Bypasses D APRM and remets half scram when ordered by the SRO Receives report from technician that while working on A APRM screwdriver slipped and went bmeina into APRM Cabinet.
SRO Acknowledges inoperable failure of D APRM Directs RO to bypass D APRM and reset the half scram Directs E & C to investigate Enters Technical Specifications Detennines that T. S. 3.1.A and Table 3.1.1 are satisfied since each
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RPS Channel still has two operable instruments Determines that T. S. 3.2.E and Table 3.2.5 Rod Block Actuation
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are not satisfied since A and D APRMs are in the same rod block channel. Recognizes plant is in a 7 day LCO and Rod Block B Channel must be immediately tested for functionality.
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Op-Test No: 1 Scenario No.1 Event No. 3 Event Description: Loss of ECCS Keepfill Time Position Applicant's Actions or Behavior ROl/RO Acknowledge annunciators and relay AO report to SRO.
SRO Determines based on 9 3 annunciators J-6, N-6, and M-4 and report
&om AO sent to investigate that all low pressure ECCS has lost keep fill capability.
Enters The Specs and determines that T. S. 3.5.1 Maintenance of Filled Discharge Pipe cannot be met and all ECCS must be declared inoperable. Per T.S. 3.5.A.6 a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> shutdown is required.
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Op-Test No: 1 Scenario No.1 Event No. 4
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Event Description: Feedwater Rupture Outside Containment
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Time Position Applicant's Actions or Behavior
ROI Evaluates performance of feedwater control, feedwater system, and feedwater reg valves. Determines that all components appear to be
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operating properly but cannot restore level, t
i SRO Enters OT 3113 Reactor low Level Directs reduction in reactor power (translent too quick to reduce Power)
Directs reactor scram when determines that an automatic scram is
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Op Test No: 1 Scenario No.1 Event No. 5 Event Description: Reactor Scram with No Illgh Pressure Injection Time Position Applicant's Actions or Behavior ROl/RO Verifies all control rods inserted
Verifies EDO started Verifies PCIS isolations have gone to compleilon Controls reactor pressure 800 to 1000 psig Opens all SRVs when emergency depressurization is ordered Determines IIPCI and RCIC have tripped.
Inhibits ADS when ordered.
Starts injection systems as ordered (condensate, SLC, CRD, RilR, CS, condensate transfer, fire system, RilR Service Water) and recognizes failure of high pressure systems toinject.
Injects with available systems when ordered.
Attempts to manually transfer Bus 1. Identifies and reports failure of bus to manually transfer.
SRO Enters OT 3100 Reactor Scram and OE 3101 RPV Control on low reactor water level
SRO Determines in response to OT 3100 that scram has occurred and power is less than 2%.
When steam flow is less than.5 mlbm directs mode switch be placed in REFUEL or SIIUTDOWN.
Determines that all control rods are inserted to 02 or beyond.
Directs operators to verify PCIS isolations.
Directs operators to verify ECCS systems start on low-low reactor water level.
Verifies EDGs started on low low water level.
Confirms or directs turbine trip.
SRO For power control in OE 3101, goes to bottom of power leg when determined that all control rods are 02 or beyond.
SRO For pressure control Directs ROl/RO2 to maintain pressure 800 to 1000 psig with SRVs.
Direct cooldown at tale ofless than 100 degrees per hour based on all rods inserted.
Directs ADS be inhibited.
When Emergency Depressurization is required exits pressure control leg and enters OE 3102 Alternate Level Contro! RPV-ED Determines that MSIVs are closed and adequate torus level (5.5 fl)
exists and orders all SRVs opened. Must be performed before water level reaches-43" Critical Task SRO For level control. Directs RPV level be maintained 127" to 177".
Determines that level cannot be maintained above 127" based on feedwater system failure, and trips ofIIPCI and RCIC.
Order restart of CRD and maximize injection to the vessel.
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Attempts to au6 ment.svel control with SLC as only high pressure augmentation system available.
Determines that level cannot be maintained $ove TAF and enters OE 3102 Alternate Level Control Alternate injection.
SRO For Altern:te injection Determines that condensate system is not available based on breac but may or may not consider low pressure ECCS available based on loss of keepfill and failures of HPCI and RCIC. Should identify that no Core Spray Low Pressure Annunciators were received and start two core spray pumps.
Iflow preswre ECCS not available then will commetice lining up ahomate injection systems (RHR Service Water, Fire System,
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Condensate Transfer, SLC)
j When water level reaches TAF determines emergency J
depressurization is required.
Injects with condensate / low pressure ECCS/ alternate systems and
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restores level to TAF within 5 minutes after reactor pressure sches
250 psia. Critical Task SRO Enters OE 3104 cn high torus level.
Monitors torus temperature.
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Commencu actions to verif'y RHR is filled ad use RHR to lower torus level, i
Scenario is finished when the reactor is depressurized and RPV level is above TAF and j
is being r sto d to 127",
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