ML032481249
| ML032481249 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/26/2002 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-390/02-301, 50-391/02-301 | |
| Download: ML032481249 (9) | |
Text
Draft Submittal (Pink Paper)
- 1. Operating Test Simulator Scenarios WATTS BAR EXAM 2002-301 50-390 NOVEMBER 26 &
DECEMBER 9 13,2002 -
Appendix D Scenario Outline Form ES-D-1 Facility: Watts Bar Nuclear Plant Scenario No.: 1 Op-Test No.: 301-2002 Examiners: Operators:
Initial Conditions:
Rx Power 38%, ramping up per GO-4,Step 5.1 .I 1 Imp-IN on turbine control Turnover:
1A MD 'W out of service Event Event No. Description 1 P imp falls low PT-1-73 Affects auto rod control Tref program Steam dumps Should require RO to take manual control of control rods. BOP may have to take actions for steam dumps, not sure. To continue ramp, with this instrument failed should require the RO to manually operate the rods.
Tech Spec 3.3.1 condition S (FWIO) Condensate Pump Recirc valve falls open Failure should drop feed pressure low enough to get Main Feed Pump suction alarm.
At the power level at this point, it shouldn't cause a ramp down or trip. Key is that suction pressure remain above 100 psig. The ARP provides some diagnostics but no guidance as to what to do with the vaive. The expectation is that the BOP will close the valve. Otherwise. the continued ramp up may not be possible.
I N Place 2"6feed pump In service 4 Failure of FT-62-I42 Inhibits ability to dilute Th's failure will affect the R O s ability 10 dilute. There are no alarms, so it will be necessary to require dilution in th:s timeframe for h'm to diagnose the failure. Also.
t t IS unclear whether or not he can man-ally wor< around this problem. Otherwise. we may have to "fix" the proolem to continue.
Failure of EHC Auto control Turbine power begins to increase. The rate of increase be set by the simulator operator. The intent is to set the rate for a very slow increase. There are no alarms specific to this component failure. I would expect that the BOP would have some MCB capability to piace the turbine in manual or some means to stop the increase.
This is the last event prior to the Major Transient. So if they trip, we will go straight into the MT.
Maln Steam Line Break Outside Contalnment At the point that the crew either gets control of the turbine ramp or trips, this malfunctionwill be input. Assuming that they haven't tripped, the intent isto ramp this in starting at a rate similar to the rate that was caused by the EHC failure and increase it as necessary to drive them into the EOPs.
POST MSlV I C fails to close and 1B MDANV pump fails to start MT The scenario ends after SI is reset and RCS parameterr are stable.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)aior
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Appendix D Scenario Outline Form ES-D-1 Facility: Watts Bar Nuclear Plant Scenario No.:_2 Op-Test No.: 301-200:
Examiners: Operators:
Initial Conditions:
Rx Power 100%
Turnover:
1B MDAFW out of Li-I-EK No. I Event Event Description TY Pe*
I C #IC Heater Extraction valve falls closed There are no alarms. It is expected that heater levels will begin swinging around and (Bop) same efficiency loss. The BOP is expected to determine that the valve has shut anc to reopen it. (can be any heater, want the one with the most visible effects)
I Pressurizer Level Transmitter LT-68339 Falls Low Annunciators for PZR Level Hi/LO and PZR Level Lo-heaters OFF and Letdown (Ro, Closed illuminate RO should determine an instrument failure and go to AOI 20,
' SRO) Malfunction of the PZR level control system. Manual control of charging should be I taken, the channel transferred and letdown returned to service. SRO should revieu TS 3.3.1, condition X.
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N Event #3: Stroke IST AOV (TBD) and get 0 0 s stroke time (Normal for BOP)
Exercise Tech Spec for SRO (BOP, SRO) 4 (CV52) Event #4: Fail Letdown Pressure Control Transmitter PT-62-81 high Annunciator for Letdown Hx return high temp illuminates. RO Should recognize high letdown flow and take manual control.
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$A Main Feedwater Turbine vibration High Annunciators for 1A MFWPT Abnormal and Turbine Vibration high C(SRO) Loss of 125VDC Vital Battery Board 111 This event causes several annunciators, removes control power from the TDAFVV pump and control power from the A train ESF bus. This, in effect, takes away the remaining two AFW pumps. It also starts all 4 EDGs. A number of TS's will apply, both electrical and AFW.
C 1B EDG failure Need some kind of failure which requires the BOP to take action to shutdown EDG.
(Bop, ThiswillalsobeaTechSpecfortheSRO (If BOPtakesverifiableactionswiththeDC SRO) bus failure, this event could be droped)
8 (FW93) R #3 Heater Drain Tank Level reference leg failure (c for This event causes the #3 HDT to empty, causing HDT pump cavitation. This can BOP?) result in a runback. If it doesn't, we will force a rampdown with 1A feed pump vibration.
9 (RD08)
I Rods fall to move on demand Rods \".I fail IO move in either auto or manual. RO will have lo trip Rx due to inabil:ly to follow load reduction. May go lo AOI-2. Malfunction of Rod control system prior lo tripping. This is also a Tech Spec if we are here long enough.
lIt 10 (RPOIC) M(ALL) A-When RO altempts to trip the Rx. ilwill not trip either manually or by auto signal. Will need to manually open trip breakers or MG set breakers.
Post (FW06) Post MT event: Standby Feedwater pump falls At this point, there should be no feedwater available and drive the crew into FR-H.l.
MT 1A MDAFW breaker has no control power, but can be started by manually closing the breaker at the SO board per Step 7 of FR-H.l. We will allow that success path, after an appropriate time to achieve the action locally. Rx trip breakers may require cycling, based on any SI status, to reset Feedwater Isolation. This will require local action at the switchgear based on the AlWS failure. If they go this path, the standby feed pump will trip. Any other procedural path to success is acceptable (le. Main feedwater pumps, condensate pumps or feed and bleed)
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The scenario ends afler a success path is with 1A MDAFW or any secondaiy pump) 11, (R)ea vity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1
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Facility: Watts Bar Nuclear Plant Scenario No.:_3 Op-Test No.: 301-200; Examiners: Operators:
Initial Conditions:
Rx Power 100%
Turnover:
1B MDAFW out c Event Event Type Description T
1 (RP08) I Event #I Permissive
- P-4 failure There is no action to take other than the Tech Spec. However, this permissive affects (SRo) the subsequent operation of Feedwater Isolation, SI block, Turbine Trio and Steam Dump control. Also, illuminates Auto SI Blocked annunciator 2 (CVOS) I VCT Level Transmitter LT-62-130 Fails High RO should have to take manual control of the VCT divert valve. Auto makeup and (Ro) Charging pump suction roll to RWST defeated.
4-Shift on service orifices 3 1 Normal for BOP. May have to direct SRO to get BOP to do this
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(CV16) C Letdown Relief Valve fails open (CV16)
RO should isolate letdown and place excess letdown in service. Key annuciator wil (Ro) be Low Press Letdown relief high temp. Could let BOP do excess letdown as a normal and let the RO shift the orifices as a prelude to the relief valve lift.
5 (RW20) RCW Pump Trip with standby pump failing to start (Didnt see canned auto-stan inh bit, need lo discuss w l simuiatoi operator)
BOP shoLld start the standby pump.
R Main Generator Field Temperature High Wewant thistemperatureincreasetobeslowenoughtogivethecrewandopportunity (ALL) to diagnose the problem and perform a rapid ramp down to less than 50 %power and manually trip the turbine. Note: VCT level will not auto-roilto RWST if VCT level gets out of control.
I Feedwater Header Pressure Transmitter falls high PT-3-1 This failure causes the main feed pumps to roil back to idle. BOP will be required tc (Bop) take manual control of feed pump speed. Ramp in slowly enough for crew to diagnose and take control. If crew trips the Rx above 50%. the steam dumps ma) behave differently than expected.
M Event # 8: Steam Generator Tube Rupture on I C S I 0 Ramp in after either Rx trip or turbine trip. Ramp rate sufficient to require expeditious (ALL) action to prevent Steam Generator from going solid. Crew must recognize auto SI blocked and manually SI.
Post (S109K) Failure of Control Room Isolation Train A BOP should pick this up during E-0. Also, look for effects on feedwater isolation due MT to P.4.
Scenario Enrl: Breakflow is stopped
Appendix D Scenario Outline Form ES-D-1 Facility: Watts Bar Nuclear Plant Scenario N o . : m e Op-Test No.: 301-2002 Examiners: Operators:
Initial Conditions:
Rx Power 100%
Turnover:
1B MDAFW out c
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Event No.
1 Malf. No. Event Type*
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Event Description
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2 (N108B) I N42 channel fails low Will require manual control of C 8 D SIG by BOP (unclear as to how significant the (Bop, impact is) TS for SRO SRO) 3 Tavg control falls low TAwsignalfails low (530 Deg. F), steam dumps will not open even if armed while in TAW mode: control rods will step out until 220 steps, and Pzr level program will go to 24.7 YO.
Should require RO to take manual control of PZR level and control rods is IC has them less than 220 steps.
4 (CCO7A) 1A CCW pump trips wl auto start of 18 blocked Requires BOP to manually start 1B CCW pump TS for SRO (CCO3B) 5 Sudden Pressure Trip of C CCST transformer Coupled with the transformer trip, Rx MOVNent Board 1A1-A (EDIBA) fails to auto transfer. This removes power from the A train BIT outlet which sets up the post MT event, along with MOVs in several otherA train ESF systems. TS for SRO 6
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(CV17) RWL) 1 Event #6: A RCP #I seal failure Should be ramped in at a rate that will require immediate, but controlledshutdown.
7 PS 68-340H falls high Fails open spray valves, RO must take manual control (RC05E) 8 (S106) Event #E: SI cold leg pipe break Small break LOCA ramped in siowly 10 allow diagnosis and manual trip and SI Posl Train B BIT outlet isolation valve, FCV-63-25, fails to open Train A BIT outlet is de-energized due to lost Rx MOV board 1Al-I, therefore all flow MT is isolated through the BIT. Operators should catch this by Step 9 of E-0 or sooner.
Scenario ends with transition to ES-1.2 (N)ormal, (R)ea ivity, (I)nstrument, (C)omponent, (M)ajor
ES-301 Administrative Topics Outline Form ES-301-1 (R8, S l l Facility: -Watts Bar Date of Examination: -1 1/9-13/02-Examination Level (circle one): RO I SRO Operating Test Number: 1 li Administrative Describe method of evaluation:
- 2. TWO Administrative Questions
- a. Calculate the Estimated Critical Position (NEW)
- b. Complete Shift Turn Over Checklist (NEW)
Complete Shift Daily Surveillance Log Mode One and Evaluate Surveillance Log. (NEW)
Access a High Radiation Area (NEW)
Classify the Event per the REP (Security Event)-SRO (NRC-JPM-NEW)
Medical Emergency Response (RO) (NEW)