ML20210C718
| ML20210C718 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/30/1999 |
| From: | Tulon T COMMONWEALTH EDISON CO. |
| To: | Hironori Peterson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20210C715 | List: |
| References | |
| NUDOCS 9907270022 | |
| Download: ML20210C718 (39) | |
Text
Comnuinweattli film >n (ismpan) liraidwoud Generating Station Route *l. Itox H4 l liraceville, 11,60407-9619 Tel Hi 5 458 2801 1
! March 30,1999 Mr. Ilironori Peterson U. S. Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, IL 60532-4351
Dear Mr. Peterson:
1 Enclosed is the integrated examination outline (written and operating test) which Braidwood Generating Station is submitting for review, comment, and approval for the initial License Examination scheduled for the week ofJune 7,1999, at Braidwood Generating Station.
This outline has been developed in accordance with Interim Revision 8 of NUREG-1021 (" Operator Licensing Examiner Standards").
l Please ensure that these materials are withheld from public disclosure until after the examinations are complete.
If you have any questions or concerns, regarding this outline, please contact Terrence Simpkin at (815) 458-2801 extension 2980.
Sincerely, Ti thy J. Tulon Site Vice President Braidwood Nuclear Generating Station j i
Trr/NRC/990170t. doc l 1
l l l No Enclosures l l
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9907270022 990716 REgi N l PDR ADOCK 05000456 v
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l _
- ES-201 Extminiti:n Outlins Fcrm ES-201-2 Quility Assur:nca Chicklist Facility: Date of Examination:
Irutials item Task Description a b c
- a. Verify that the outline (s) fit (s) the appropriate model per ES-401, g
- b. Assess whether all six knowledge and four ability categories are appropriately sampled.
gg T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
g g
- d. Assess whether the repetition from previous examination outlines is excessive.
- 2. a. Using Form ES-3015, verify that the proposed scenario sets cover the required number of S
I normal evolutions, instrument and component failures, and major transients. h
- b. Assess whether there are enough scenario sets (and spares) to test the projected number M and mix of applicants in accordance with the expected crew composition and rotation b
l schedule without compromising exam integrity; ensure each applicard can be tested using at '
least one new scenario and scenarios will not be repeated over successive days. >
g
- c. To the extent possible, assess whether the outline (s) conform (s) with the qualitative and ,4
- y ((/
quantitative criteria specified on Form ES-301-4 and described in Appendix D. II
- 3. a. Verify that the outline (s) contain(s) the required number of control room and in-plant tasks and verify that no more than 30% of the test materialis repeated from the last NRC examination. / h,
- b. Verify that the tasks are distributed among the safety function groupings as specified in W ES-301: one task shall require a low-power or shutdown condition, one or two shall require -
4 f
I the applicent to '..-j. -. ..; an alternate poth procedure, and one should require entry to the j Al g' '
T RCA.
- c. Verify that the required administrative topics are covered, with emphasis on performance- g based activities. , M I
- d. Determine if there are snough different outlines to test the projected number and mix of ;
applicants and ensure that no more than 30% of the items are duplicated on successive days.y )"
4' e. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the ,
appropriate exam section.
N b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. '
hh M g E c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. h [ [
R d. Check for duplication and overlap among exam sections. h f [
[ [
A e. Check the entire exam for balance of coverage. (d l f. Assess whether the exam fits the appropriate job level (RO or SRO). $ h [
Printed N / Signature
' Date
- a. Author D M[U 4W.
- b. Facility Reviewer (') (N b I b N d Mee k 8 Mf
- c. Chief Examiner WbM)$ /ErfcucWt SMNAJ l1lfylf I
- d. NRC Supervisor u$dNNNk [b[d _
i/ U
(*) Not applicable for NRC-developed examinations NUREG-1021 23 of 24 Interim Rev. 8, January 1997
l f
l ES-301 Transient and Event Checklist Form ES-301-5 OPERATING TEST NO.:1 Applicant Evolution Minimum Scenario Number Type Type Number 1 2 3 4 i Reactivity 1 il 21 il il Normal 1 11 I2 11 /1 j RO Instrument 2 si4 4is 4i2 2is Component 2 2.7 i 5,7 1,7 t i,6 ria 4,7 is Major 1 6,8 / 6.8 5I5 5.6,815,6,8 5,615,6 Reactivity 1 1 2 1 1 Normal 0 As RO instrument 1 3 4 4 2 Component 1 2,7 1.7 7 4,7 Major 1 6,8 5 5,6,8 5.6 SRO-l Reactivity 0 l
Normal 1 1 2 1 1 i As SRO instrument 1 3,4 3.4 2,4 2,3 i Component 1 2.5.7 1,6,7 3.7 4,7,8 Major 1 6,8 5 5,6,8 5,6 Reactivity 0 N/A N/A N/A N/A Normal 1 MA N!A N/A N/A SRO-U instrument 1 N/A N/A N/A N/A Component i WA N/A N/A N/A Major 1 N/A N/A N/A N/A instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type. ,
(2) Reactivity manipulations must be significant as defined in Appendix D. l 4
NOTE: Scenario Number 4 is a ' spare" scenario and is represented for comparison purposes only l in Examination Outline submittal. l The '/" in the cells for the "R0"' applicant type represents the position the applicant is expected to i fill dunng the scenario. The eve are listed for the identified position: RO / BOP. i Author: sw . Ih Chief Ex iner,: MA h[/h- y n- w NUREG-1021 1 of 26 Interim Rev. 8, January 1997 ,
ES-301 Competencies Checklist Form ES-301-6 Operating Test: 1 Applicant #1 Applicant #2 Applicant #3 RO/SRO4/SRO U RO/SRO4/SRO-U RO(BOP)/SRO4/SRO4)
Competencies - SCENARIO SCENARIO SCENARIO 4 1 2 3 4 1 2 3 4 1 2 3 4 18 28 24 I Understand and Interpret 1, 2-3, 1, 34 2, 4 1,3, 2, 3 Annunciators and Alarms 17 % 4,7 4 54 54 54.8 Diagnose Events 24 1, 24 24 24, 1,4 34 2, 4-a 13, 2, 3, and Conditions .
17 u 5,7 o7 u u u.s Understand Plant 14 1-7 14 14 2-3, 1-2, 1, 12 1, 1-3, 1-2, 1,3, and System Response u 4.7 34 o u 54 54 54,8 Comply With and 14 1-7 14 14 1.3 1-2, 1, 1-2 1, 1 -3, 1-2, 1.3, H 4,7 34 4 4 % 9 u.s Use Procedures (1)
Operate Control 14 17 14 14 1.3.5 12, 1, 12 1, 1-3, 12, 1,3, Boards (2)
M 4,7 34 o u u u,e u,8 Communicate and 14 1-7 14 14 14 1-7 14 1 -2, 14 1-7 14 1,3, interact With the Crew
'8 "8 3
l Demonstrate Supervisory 14 1-7 14 14 N/A N/A N/A N/A N/A N/A N/A N/A l Ability (3)
Comply With and 3 1,4 2,3 2 N/A N/A N/A N/A N/A N/A N/A N/A Use Tech. Specs. (3)
Notes: )
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SR0s.
Instructions:
Circle the applicant's license type and enter the event numbers that !?st the competency for each scenario in the set.
NOTE: OPERATING TEST NO.: 1. Scenario Number 4 is a ' spare" scenario and is represented for comparison purposes only in Examination Outline submittal. The order of listing for candidates is SRO, RO and BOP by position.
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Simulttion Freility Braidwood Scenario No.: J-1 Examin:rs: Applicant:' SRO i
E l BOP l: Objectives: To evaluate the applicants ability to use Normal, Abnormal, Emergency and alarm response l procedures to conduct a normal ramp down of reactor power at 5 MW/ min, to respond to a
' Thot instrument failing high coincident with control rod speed malfunction causing rods to move at I step / min when auto rod control :s indicated, a failure of the feedwater header discharge pressure instrument, a Main Feedwater Pump speed control malfunction resulting in the pump tripping, and a loss of offsite power with no Emergency Diesel Generators available
- (loss of all AC power).
Initial Conditions: IC-54; 100% power BOL, Equil. Xenon, Turnover: The Unit is at 100% power. Severe storm warnings are in effect. Circuit breaker 1423 (DG-1B feeder to bus 142) was declared OOS late last shift and is being replaced. DG-1B has been declared Out of )
Service. Directions have been received to lower power immediately to 60% at 5 MW/ min.
Event Malf. No. Event Event No. Type
MAINT_O Preload FW01 C BOP 1 A Motor driven Feedwater Pump fails to start SRO 1
N BOP. Ramp down turbine power to 60% at 5 MW/ min !
SRO !
R RO Lower reactor power using rods and/or boration 2 RD09, I C RO Rods move at I step / min. in AUTO SRO 3 RX18L,650 1 RO Loop 4 Thot (#2 RTD) fails high
! SRO 4 FWl6.1500 I BOP FW Header Discharge Pressuie PT-508 fails high on a 30 second ramp 30 SRO 5 FWO6B C BOP IC Main Feedwater Pump speed control fails to minimum speed over two (FWO1) SRO minutes 6 RFP iC03 M BOP Inadvertent turbine trip RO SRO
- 7. EDl5C C BOP Loss of 0ffsite Power RO SRO 8 EG08A M BOP EDGI A fails 90 sec after start resulting in a loss of all AC power RO SRO
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient
!~
, ' Demos Sample Submittal - 1 03/19/991:13 PM
SCENARIO 1-1 OVERVIEW Unit 1 is at 100% power, BOL The System Operator has requested a ramp down of reactor power ASAP due to problems on the grid, it is desired that power be lowered at the rate of 5 MW/ min.
Following clearly observable plant response from the reactivity changes, control rod speed unit will fail with rod speed at I step / min when automatic rod control is called for. Coincident with the rod speed failure, Loop 4 Thot fails high, resulting in demanded rod inward motion. It is expected that the RO will recognize improper rod motion for this condition cnd place rod control in manual. BwOA INST-2 (Attachment A) will be entered to address the failed Thot RTD. BwOA ROD-2 may be entered, but is NOT required, in response to the rod control problem. I&C will not be able to repair the rod speed problem and manual rod control will be the only way to move control rods at the proper speed. The SRO will address ITS for actions for the failed Thot instrument.
After the bistables for the failed Thot instrument are tripped, feedwater header pressure instrument, PT-508, will fail high.
This results in a demanded decrease in main FW Pumps speed. The operator is expected to recognize this condition, take manual control of the Master FW Pumps Speed controller and restore FW discharge pressure to within its normal band.
Once SG levels are stabilized, the IC Main Feedwater Pump speed control will experience a reduction in speed due to a speed feedback error until the FW Pump turbine trips. The operator is expected to initiate a turbine runback when the 1 A FW frils to start. The RO is expected to borate and drive rods in manual as necessary to restore Tave to Tref at final load.
Once the plant has stabilized, an inadvertent trip of the main turbine will occur. The crew will perform immediate actions of E-0 and transition will be made to ES-0.1. At step 9 of ES-0.1, a loss of all offsite power will occur due to weather c
conditions. The l A DG will start and energize ESF Bus 141. Approximately 90 seconds later, the l A DG will trip resulting in a loss of all AC power to the unit. Transition will be made to ECA-0.0. The scenario ends following energization of the ESF bus 141 from the crosstie to Unit 2 and restoration of charging flow.
Critical Tasks
- 1. E C: Energize at least one AC Emergency Bus before transition out of E-0, unless the transition is to ECA-0.0, in which case the critical task must be performed before placing safeguards equipment handswitches in pull-to-lock position.
- 2. ECA-0.0 - H: Isolate RCP seal injection before a charging pump starts or is started.
Demos Sample Submittal 2 03/19/991:13 PM
Simul: tion Freility Braidwood Scenario No.: h2 Examiners: Applicant: SRO EO BOP Objectives: To evaluate the applicants ability to use Normal, Abnormal, Emergency and alarm response procedures to respond to a small SGTL, a power reduction, an unstable SG level controller, a l
N44 power range failure, a non-isolable Steam Break with a SGTR, a failure of the turbine to trip automatically, and an Si pump that fails to start on SI. l Initial Conditions: IC-22; 100% power MOL, Equil. Xe Turnover: The unit is at 100% power. Circuit breaker 1423 (DG-1B feeder to bus 142) was declared OOS late last shift and is being replaced. DG-1B has been du:lared Out of Service.
Event Malf. No. Event Event No. Type
- Description Preload RPl4A "A" Train Si fails to actuate S101B "B" Train S1 Pump trips RF RP35, OUT Failure of MSIV auto closure, failure of
- losure on MSLI signal RF RP61 OUT MS01B,90 IB MSIV fails open at 90%
TC03 Turbine fails to trip on reactor trip ( manual runback desired)
IOR syTUO10 Override Turbine TRIP pushbutton i TH03B,25 C BOP Steam Generator B tube leak - small(25 gpm)
RO SRO 2 N BOP Ramp down turbine power at directed MW/ min due to tube leak .
SRO l R RO Lour oaetor power using rods and/or boration 3 RX02B,3 i BOP S/G Is ustabie level controller- 15% on 3 min cycle SRO 4 N109D,120 1 RO Power Range N44 fails high SRO 5 Ms08B,2MLB M BOP Non-isolable Steam Break outside containment of 2 MLB over 60 see T1103B,1000 RO S/G Tube leak increases on reactor trip (All MSIVs fail to auto close and 3
ho$gf/60 SRO IB MSIV fails at 90% open) 6 (TC03) C BOP On reactor trip, turbine fails to AUTO / MAN trip and must be manually (IOR SRO runback.
ZDIlliSTG010) 7 (S101B) C RO On Si, the "B" Train S1 Pump fails to start and the "A" train equipment fails (RPl4A) SRO to start and must be manually started.
- (N)ormal, (R)eactivity (1)nstrument, (C)omponent, (M)ajor Transient Demos Sample Submittal -3 03/19/991:13 PM
SCENARIO 1-2 OVERVIEW Unit 1 is at 100 % power. Following turnover, the crew is to maintain power steady for flux mapping. Shortly aner turnover a SGTL will be initiated. It is desired that the leak be large enough to cause the operators to initiate a power reduction but small enough that a reactor trip will not be called for. BwOA PRI-l may be entered in response to the RCS 1:akage. Once the leakage is determined to be SG tube leakage, BwOA SEC-8 will be entered. The crew will be directed to initiate a Unit shutdown . thin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> based on the determined leak rate.
Fol;owing clearly observable plant response from the reactivity changes, SG level controller for the leaking SG will become unstable. The operator will determine the FRV is oscillating and place the controller in manual to control SG level. Manual control will be required during any subsequent power reduction After i&C has been contacted to repair the SG level controller, a failure high of power range channel N44 will occur.
Entry is made into BwOA INST-1. Rods will be placed in manual, the channel will be placed in a tripped condition, and rods returned to automatic. The SRO will review ITS for the failed NI applicability and the tripping of bistables.
After the bistables are tripped for the failed NI channel, a non-isolable steam break outside containment will occur. A manual reactor trip is expected with the turbine failing to trip. The operator is expected to manually runback the turbine.
When the reactor is i:ipped, the IB SG tube leak will increase to a tube rupture over 10 minutes. All MSIVs will remain open due to a failure of the automatic steamline isolation circuit. When the MSIVs are manually closed, the MSIV for i B SG will fail at the 90% open position. Upon actuation of SI, the "A" Train SI signal fails requiring manual operation of the required equipment. Additionally, the "B" Train SI pump will fail to start or run. Following completion of the rppropriate steps of E-0 transition should be made to E-2 and then to E-3. When it is determined that the ruptured SG pressure is either < 320 psig OR that the ruptured SG pressure is < 250 psig above the intact SG pressure (following cooldown), transition is made to ECA-3.1. The scenario terminates after determination that no additional cooldown is required at step 10 of ECA-3.1.
Critical Tasks
- 1. E.0-J: Establish flow from at least on intermediate-head ECCS pump before transition out of E-0.
- 2. E A: Isolate the faulted SG before transition out of E-2.
- 3. E A: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.
Demos Sample Submittal 4 03/19/991:13 PM t
l
~
Simulation Facility Braidwood Scennio No.: 1-1 Examiners: Applicant: SRO RO I BOP Objectives: To evaluate the applicants ability to use Normal, Abnormal, Emergency and alarm response procedures to respond to a normal power increase, a SG pressure channel failure, an ECCS Accumulator water leak, a VCT level transmitter failure with the pre-loaded condition of the other channel OOS for I&C work, an inadvenent SI with a PORV failing open and with failure of the reactor trip breakers RTB A&B failing to open in auto OR manual from the control room, and a RCS LOCA.
Initial Conditions: IC-18; 74% power MOL. Equil. Xe.
Turnover: I&C is performing surveillance testing on ESFAS Train A. I&C has VCT level transmitter LT-il2 deenergized for repairs. Circuit breaker 1423 (DG-1B feeder to bus 142) was declared OOS late last shift and is being replaced. DG-1B has been declared Out of Service.
Event Malf. No. Event Event No. Type
- Description Preload RP02A,B M RO Failure of RTB A&B to auto AND Manual open. (can be opened locally)
BOP CV16, O SRO VCT level LT-112 failed low. (deenergized) i N BOP Ramp up turbine power to 100% at directed MW/ min SRO R RO Raise reactor power using rods and/or dilution l 2 RX01 A,0,60 1 BOP 1 A SG pressure channel PT-514 fails low SRO 3 SH i^. 20 -t w, C BOP 3" ECCS Accumulator A water leak - 20 gpm (ramp to 100 gpm over 5 min.)
SRO 4 CVl7,0 1 RO VCT level transmitter LT-185 fails low SRO 5 RP24A M RO Inadvenent St BOP SRO -
6 (RP02) M RO Reactor trip breakers fail to open BOP SRO 7 T111IB,100 C RO RY-456 PORV fails open SRO g T1105c,4000 M BOP RCS leak, to be inserted after Si has been reset.
- (N)ormal, (R)eactivity (1)nstrument, (C)omponent, (M)ajor Transient L Demos Sample Submittal 5 03/19/991:13 PM
SCENARIO I-3 OVERVIEW j Th3 Unit is at 75% power. IB Emergency Diesel Generator is OOS. Power is to be increased at direction of the System Operator using normal procedures.
Following clearly observable plant response from the reactivity changes, the controlling pressure channel for 1 A SG will frit low. The operator will take manual control of I A SG FRV and control SG levels. Following entry into BwOA-
' INST-2(Attachment F), the operator will select the alternate channel for SG level control and place the FRV back in tutomatic. The SRO will review ITS and direct tripping of associated bistables.
After the power increase is resumed, a water leak on the l A ECCS accumulator will occur. The crew may enter OA PRI-1 until accumulator level alarms occur. The leak will increase from 20 gpm to 100 gpm over a 5 minute period. The operator will attempt a mfill of the accumulator using the system operating procedures. The SRO will review ITS for applicability and actions.
Afbr the attempt is made to fill the accumulator, VCT level transmitter LT-185 will fail low, it should be recognized that I I&C has been working on LT-ll2. The swapover to the RWST suction for the charging pumps will occur. I&C should - '
be contacted for repairs on both the channels.
Following the decision for Unit shutdown or trip, an inadvertent SI signal is generated. E-0 should be entered and FR-S.]
cntered when the reactor trip breakers will not open. Also, PORV 1RY456 will open in response to the RCS pressure rise and fail to reclose when pressure falls. The operator will be required to close the associated PORV isolation valve 1RY8000A.
' Afhr ES-1.1 has been entered, a RCS LOCA of 4000 gpm occurs. The scenario ends following RCS cooldown cytluation at step 6 of ES-1.2.~
Critical Tasks
- 1. FR-S.I - C: Insert negative re#vity into the core by it least one of the following methods before completing immediate action steps of FR-S.1: e De-energize the control rod drive MG sets;
- Insert RCCAs; e Establish emergency boration flow to the RCS.
- 2. E-0-M: Close the block MOV upstream of the stuck-open PZR PORV by completion of the first step in the ERG network that directs the crew to close the block MOV .
I l
l Demos Sampic Submittal 6 03/19/99 2:20 PM
1
.2 .
Simulation facility Braidwood Scenario No.: Uggt Examiners: Operators: SRO EQ BOP Objectives: To evaluate the applicants ability to use Normal, Abnormal, Emergency and alarm response procedures to respond to a normal power increase, a pressurizer level channel failure, HDT level controller failure, a leak in the letdown heat exchanger with failure of the letdown pressure control valve closed, a leak in the main turbine EHC system and a Large LOCA with failure of Ril pumps to start and failure of automatic transfer to sump suction for operating train of RH.
Initi:1 Conditions: IC-16. Unit at 49% power Turnover: Circuit breaker 1423 (DG-1B feeder to bus 142) was declared OOS late last shift and is being replaced.
DG-1B has been declared Out of Service Evint Malf. Event Event No. No. Type
- Description Preload RH01A C RO 1 A RH Pump fails to start / trip SRO Prele:d MRF RP85 open C RO IB RH Pump fails to start on SI with manual start available (PL2) ' RPl5F SRO Preload RH04B C BOP Failure of IS18811B (RH CNMT Sump) auto transfer (PL3) SRO 1 N 90P Ramp up turbine power to 75% at 5 MW/ min SRO R RO Raise reactor power using rods and/or dilution 2 RX13A,0,10 1 RO Pressurizer level channel fails low SRO 3 FWl7, O I BOP Heater Drain Tank level controller fails low SRO 4 CV23A,100 C RO Letdown Heat Exchanger tube leak w/PCV-131 fails closed (mechanical l RF CV01,0% SRO binding) 5 TC15,34 M BOP EHC System leak of 24 gpm results in turbine trip RO SRO 6 TH06A,450000 M BOP Large Break LOCA upon reactor trip RO i SRO 7 (RH01A) C RO l A and 1B RH Pump fail *o start with 1B RH pump manual start capable. !
(PL2) SRO 8 -- (PL3) C BOP Failure of Auto transfer to cold leg recire for "B" Train SRO- ,
I l l l !
f
- (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient l
i i
Demos Sample S mittal 7 03/19/99 2:20 PM
SCENARIO Snare OVERVIEW l Unit 1 is at 50% power. Following turnover power increase is initiated to 75% power.
Following clearly observable plant response from the reactivity changes, the controlling pressurizer level channel will fail low. Pressurizer level will be placed in manual, an operable channel selected and level returned to nonnal. The SRO should contact I&C to assist in repair and the tripping of bistables. Technical. Specifications should be consulted for arpplicability.
After the bistables for pressurizer level have been tripped, lleater Drain Tank level controller will fail causing heater drain i tank level to rise. The overflow valve will open and level alarms will actuate. The operator is expected to take manual control of the level controller and reopen the valve.
Aft:r 11DT tank level is restored to normal band, a leak will develop in the letdown heat exchanger and when the heat exchanger is isolated, PCV-131 will fail closed. The operator should notice VCT level changing, and radiation levels in the CCW system increasing. Operators should troubleshoot and identify the failed letdown llX. When letdown is l c.stablished using the 1B letdawn heat exchanger, the crew should identify the failed PCV-131 valve and establish excess 1 letdown.
After excess letdown is established, an EllC leak will develop on :he EHC reservoir. EHC level will drop bringing in l several alarms. When level is sufficiently low to result in a trip of the EHC pumps, the main turbine also gets a trip '
signal. E-0 will be entered when the reactor trips.
At the time of the reactor trip, a large break LOCA occurs on the RCS. Both Rif pumps fail to start. The 1 A RH pump trips if a manual start is attempted, but the 1B RH pump will start on a manual start. When RWST level drops to the LO-2 lxl for automatic transfer to the CNMT sump suction, the "B" Train valve SI881 IB will fail to automatically open.
Operator action is required to stop the RH and CS pumps and manually open the sump suction valves. The scenario is terminated following completion of the alignment of ECCS for cold leg recirculation.
Critical Tasks
- 1. E H: Manually start at least one low-head ECCS pump before transition out of E-0.
- 2. ES-l.3 - A: Transfer to cold leg recirculation and establish ECCS recirculation flow that at least meets the assumptions of the plant-specific LOCA analysis.
1 j
Demos Sample Submittal 8 03/19/99 2:20 PM
r
.4 Facility: Braidwood .
Date of Examination: 06/07/97 Examination Level: SRO Operating Test Number: 1 System / JPM Title / Type Codes' Safety Planned Followup Questions:
Function K/A/G -Importance - Description
- 1. Pzr Pressure Control / 3 a. 010 K1.03 3.6/3.7 Spray valve effectiveness dependence on RCP Respond to Failed Pn Spray b. 010 4 103 4.1/4.2 DitTerence in plant response if PORV failed open Valve N A S
- 2. Containment Spray / Align 5 a. 026 A2.03 4.1/4.4 Actions if CS-007 valve failed to open, CS pump running Containment Spray for b. 026 K4.02 3.1/3.6 Significance of RWST LEVEL LO-3 Recirculation - Failure -
N A S
- 3. CVCS-RMS / Perform an I a. 004 A4.12 3.8/3.3 Determine the setting for the BA flow controller for the emergency boration - RCS boron concentration following boration Failure b. 004 A2.14 3.8'/3.9 How many gallons of boron would be required to N A S complete 58 ppm change
- 4. Main Steam / Opening the 4 a. 039 2.1.12 2.9/4.0 ITS response to failure of MSIV Main Steam isolation b. 039 A106 3.0/3.1 What causes MSIV closure when SG pressure falls from Valves [N-14] normal pressure to 940 psig D S L
- 5. SI Accumulator / Lower Si 2 a. 0062.2.22 3.4/41 Technical Specification REQ ACTION for closed St Accumulator Level- Mode AccumulatorIsol Valve when at power i 4 b. 006 K5.02 2.8/2.9 Effect of failure to lower level to within operating band N S L before pressurizing St Accumulator
- 6. Essential Service Water / 8 a. 076 2.1.33 3.4/4.0 Cross Unit SX pump operability requirements Swap SW Pumps b. 076 2.1.24 2.8/3.1 SX Pump start interlocks N S l 7 CETC Instruments / Test the 7 a. 017 A2.013.1/3.5 Response of single CETC failure CETC [N-65] b. 017 2.2.22 3.4/4.1 Actions for CETC failures
! D C
! 8. Main Steam / Local 4 a. 039 2.1.30 3.9/3.4 Operation from RSDP Operation of a SG PORV b. 002 K5.09 3.7/4.2 Evaluation of cooldown limits
[N-E3]
D P
- 9. ESFAS Instrumentation / 2 a. 013 K4.13 3.7/3.9 FW isolation reset from control room post trip i Local Reset of FWIsolation b. 013 A3.02 4.1/4.2 System response to HI-HI SG level Signal (N-91]
D- P
- 10. Containment Post LOCA 5 a. 028 A4.01 4.0*/4.0* Operation of Post LOCA Purge Unit Filter Deluge Purge / Adjust Post LOCA b. 028 A1.013.4*/3.7* Hydrogen concentration affect on H2 control Purge Flow N P R 1
Type Codes: (D) Direct from bank, (M)odified from bank,(N)ew,(A)lternate Path,(C)ontrol Room,(S)imulator, (P)lant, I (L)ow Power,(R)CA l
l i
l J
I Facility: Braidwood Date of Examination: 06/07/97 Examination Level: RO Operating Test Number: 1 System / JPM Title / Type Codes
- Safety Planned Followup Questions:
Function K/A/G -Importance - Description
- 1. Pzr Pressure Control / 3 a. 010 Kl.03 3.6/3.7 Spray valve efTectiveness dependence on RCP Resporw to Failed Pzr Spray b. 010 A2.03 4.1/4.2 Difference in plant response if PORV failed open Valve N A S
- 2. Containment Spray / Align 5 a. 026 A2.03 4.1/4.4 Actions if CS-007 valve failed to open, CS pump running Containment Spray for b. 026 K4.02 3.1/3.6 Significance of RWST LEVEL LO-3 Recirculation - Failure N A S
- 3. CVCS-RMS / Perform an 1 a. 004 A4.12 3.8/3.3 Determine the setting for the 13A flow controller for the emergency boration - RCS boron concentration following boration Failure b. 004 A2.14 3.8'/3.9 Ilow many gallons of boron would be required to N A S complete 58 ppm change
- 4. Main Steam / Opening the 4 a. 039 K4.08 3.3/3.4 Difference between manual & auto steamline isolation Main Steam Isolation actuation Valves [N 14] b. 039 A106 3.0/3.1 What causes MSIV closure when SG pressure falls from D S L normal pressure to 940 psig
- 5. SI Accumulator / Lower S1 2 a. 006 2.2.22 3.4/4.1 Technical Specification REQ ACTION for closed SI Accumulator Level- Mode Accumulator Isol Valve when at power i 4 b. 006 K5.02 2.8/2.9 Effect of failure to lower level to within operating band N S L before pressurizing St Accumulator
- 6. Essential Service Water / 8 a. 076 2.1.32 3.4/3.8 RCFC operation with single SX pump Swap SW Pumps b. 076 2.1.24 2.8/3.1 SX Pump start interlocks N S 7 CETC Instruments / Test the 7 a. 017 A2.013.1/3.5 Response of single CETC failure CETC [N-65] b. 017 K4.013.4/3.7 Effect of lowering CNMT pressure on Core Subcooling i D C display
- 8. Main Steam / Local 4 a. 039 2.1.30 3.9/3.4 Operation from RSDP '
Operation of a SG PORV b. 002 K5.09 3.7/4.2 Evaluation of cooldown limits ;
[N-83] !
D P
- 9. ESFAS Instrumentation / 2 a. 013 K4.13 3.7/3.9 FW isolation reset from control room post trip Local Reset of FW Isolation b. 013 A3.02 4.1/4.2 System response to lil-HI SG level Signal [N-91]
D P i
- 10. Containment Post LOCA 5 a. 028 A4.01 4.0*/4.0* Operation of Post LOCA Purge Unit Filter Deluge Purge / Adjust Post LOCA b. 028 A1.013.4*/3.7* liydrogen concentration afTect on H2 control Purge Flow N P R Type Codes: (D) Direct from bank, (M)odified ikm bank, (N)ew, (A)lternate Path, (C)ontrol Room, (S)imulator, (P)lant, (L)ow Power (R)CA
f ;
9 JPM INFO t
JPM 1 - Normal 100% power operation. After position assumed, fail Pzr spray valve RY455C to 25 % open position. BwAR 1 12 Cl. (RefiBwOA INST-2 Attachment B Step 2.b RNO).
l JPM 2 - Post LOCA conditions with ECCS aligned in Recirculation Mode, CS pumps running. RWST leveljust above 8%(<l2%).
Step 9 ofIBwEP ES 1.3.-
JPMs 3 & 4 - Mode 3 NOP NOT. MSIVs and Bypass MSIVs closed.
JPM 3: BwOA PRI-2. Setup with valve on emergency boration line provides < 30 gpm BA flow indication.
JPM-4: Section F of BwOP MS-9.
JPMs 5&6 - Mode 4,350*F. RHR shutdown. St Accumulator A level at 63% and pressure at 50 psig. SX valve ISX016B RCFC IB
& D Inlet valve closed JPM-5: Section F.3 of BwOP SI-6.
JPM-6: BwOP SX-7.
JPM-7: In the main Control Room at the plant. Section F.7 of BwOP RC-12.
JPM 8 e BwOP MS-6, directed to open the A SO PORV (_HOV-MS018A) 25% locally.
JPM 9 - BwFR-H.1 Step 5.d RNO & S.h., deenergize FWI signal at Aux Safeguard Relay Cabinet ,PA28J.
JPM 10 - BwOP VQ-7, Section F.4, startup and adjust flow for Post LOCA Purge.
(- '.
1 -
l-l~ ES-301
,, Administrctive Topics Outline Form-ES-301-1 Facility: Braidwood I & 2 Date of Examination: 06/07/99 ;
Examination Level: SRO Operating Test Number: 1
- i. Administrative Describe method of evaluation:
l Topic / Subject 1. ONE Administrative JPM, OR l l Description 2. TWO Administrative Questions A1 Conduct of Operations / Plant 1. JPM K/A 2.1.7 3.7/4.4 Parameter Verification -
I-Review of Calorimetric [N-08 mol) l Conduct of Operations / Fuel 1. JPM K/A '.32 3.5/3.3 :
Handling
)
1 A2 Equipment Control / Complete 1. JPM K!A 2.2.14 2.1/3.0 Documentation for a Temporary Alteration {S-Ol]'
l l
A.3 Radiation Control / Review 1. JPM K/A 2.3.6 2.1/3.1 Radwaste Liquid Release Form i
j l
A4 Emergency Plan / Emergency 1. JPM K/A 2.4.41 2.3/4.1, 2.4.44 2.1/4.0 Classification and Protective Actions I
l l
l i
l l
l l
l
- 1. 8 i
l I
NUREG 1021 Interim Rev. 8, January 1997 l l l
1 J
[
t l e ES-301 Administrative Topics Outline i
Form-ES-301-1 f ~ Facility: Braidwood I & 2 Date of Examination: 06/07/99 l Examination Level: RO Operating Test Number: 1 l Administrative Describe method of esaluation: !
Topic / Subject 3. ONE Administrative JPM, OR Description 4. TWO Administrative Questions i AI Conduct of Operations / Plant 1. JPM K/A 2.1.19 3.0/3.0 Parameter Verification - )
Perfonn Calorimetric Using i
Process Plant Computer [N-08]
l l
Conduct of Operations / Fuel 1. JPM K/A 2.2.32 3.5/3.3 liandling i
A2 Equipment Control / Replace 1. JPM K/A 2.1.30 3.9/3.4 ,
Control Panel Lamp l l
l l
l A.3 Radiation Control / Perform a 1. JPM K/A 2.3.11 2.7/3.2 l Radwaste Liquid Release [N- l 32]
A.4 Emergency Plan / E-Plan 2. Q1 K/A 2.4.39 3.3/3.1 Escort duty responsibility l questions
- 2. Q2 K/A 2.4.29 2.6/4.0 When is site assembly & accountability required NUREG-1021 Interim Rev. 8, January 1997
[-( _. . .
. Admin Section Ccmm:nts l
SRQ
' A.l.1 - Evaluation of BwOS 3.1.1-2 Calorimetric w;31 error l
A.I.2 - Update the tracking fuel movement from core location to SFP location. BwAP 370-3, BwAP 370-3Al2.
A.2. - Complete required documentation of NSWP-A-21 (used to be BwAP 2321-1ETl & 2321-18T7)
A.3 - Review LIQUID RELEASE TANK OWX0lT RELEASE FORM with error. BwOP WX-50lT1 section E
, A.4 - Perform classification & recommend PARS for given conditions.
l l
- EQ A.l.1 - Complete BwOS 3.1.1-2 Calorimetric A.I.2 - Update the tracking fuel movement from core location to SFP location. BwAP 370-3, BwAP 370-3A12.
A2. - Replace light bulb for Reactor Trip Bypass Breaker position. BwAP 350-4 & 350-4A1.
A.3. ' Perform steps for radwaste release using LIQUID RELEASE TANK OWX0lT RELEASE FORM . BwOP WX-50lTI section E
A.4 - Questions for topic given (Note: Q1 was also asked on '97 Admin exam)
' Q1 - BwZP 2000-10 Q2- BwZP 2000-10
/
I l
1 L
1 1
1 i
\
l 0
l l
Facility Braidwood Date of Exam: 06/07/99 Exam Level: SRO l Tier Group K/A Category Points Point Total !
K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
- 1. 1 3 2 5 4 6 24 Emergency 2 2 6 7 1 16
__ l
& Abnormal 3 1 i 1 1 3 Plant .
Evoludons Tota s 3 3 7 11 14 5 43 1 TT 1 1 1 1 2 3 2 2 3 19
- 2. Plant 2 1 1 1 l2l1l1 l2 4l1 l l3 17 Systems 3 1 l l1 l l 1 l1 l l 4 Tier l l Totals 3 3 2 3l3 2l4 8 4 2 6 40
- 3. Generic Knowledge and Abilities l Cat 1 l Cat 2 Cat 3 l Cat 4 l 5 l 5 2 l 5 17 l
Note: -
Attempt to distribute topics among all K/A Categories: select at least one topic from every K/A category within each tier.
Actual point totals must match those specified in the table.
Sek 0t topics from many systems: avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities. i Systems / evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category / tier.
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, ES/01 Generic Knowledge cnd Abilities Outline (Tur 3) ES-401-5 4 i Exam l
Facility Braidwooo Date: June 7,1999 Level: SRO Category KA # KA Topic imp. Points Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements. 3.8 1 Knowledge of operator responsibilities during all modes of plant 2.1.2 operation. l 4.0 1 i 2.1.4 Knowledge of shift staffing requirements. 3.4 1 l Knowledge of facihty requirements for controlling vital / controlled l 2.1.13 access. 2.9 1 I
Knowledge of system status criteria which require the notification of !
2.1.14 plant personnel. 3.3 1 Total 5 Knowledge of the process for making changes in the facility as Equipment Control 2.2.5 described in the safety analysis report. 2.7 1 2.2.12 Knowledge of surveillance procedures. 3.4 1 2.2.13 Knowledge of tagging and clearance procedures. 3.8 1 2.2.23 Abikty to track limiting conditions for operations. 3.8 1 2.2.24 Ability to analyze the affect of maintenance activities on LCO status. 3.8 1 I
f 1
Total 5 Knowledge of 10 CFR: 20 and related facility radiation control Radiation Control 2.3.1 requirements. 3.0 1 j Knowledge of radiation exposure limits and conta5 nation control, j 2.3.4 including permissible levels in excess of those authorized. 3.1 1
)
l l
Total 2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. Note: The issue of setpoints and automatic safety features is not specifically covered in the Emergency Procedures 2.4.2 systems sections. 4.1 1 Knowledge of low power / shutdown implications in accident (e.g.
and Plan 2.4.9 LOCA or loss of RHR mitigation strategies). 3.9 1 2.4.14 Knowledge of general guidelines for EOP flowchart use. 3.9 1 2.4.27 Knowledge of fire in the plant procedure. 3.5 1 2.4.29 Knowledge of the emergency plan. 4.0 1 Total 5 Tier 3 Target Point Total (RO/SRO) 17
~
4 Facility Braidwood Date of Exam: 06/07/99 Exar
- evel: RO Tier Group K/A Category Points Point Total gg K K3 K4 K5 K6 A1 A2 A3 A4 G
- 1. 1 11 4 5 2 1 16 Emergency 2 11 4 7 1 1 17
& Abnormal 3 1 1 1 3 Plant .
lu ns Tota s _4_ 5 8 13 4 2 36 1 2 1 2 3 1 2 2 3 2 2 3 23
- 2. Plant 2 2 2 2l2l1 l1 l2 2l2l2l2 20 Systems 3 1 1l l1 l l1 1 l1 l1 l1 8 Tier l l l l Totals 4 4 5l5l3 3 5 6l5l5 6 51
- 3. Generic Knowledge and Abilities l Cat 1 l Cat 2 Cat 3 l Cat 4 l 3 l 3 2 l 5 13 Note: -
Attempt to distribute topics among all K/A Categories: select at least one topic from every K/A category within each tier.
Actual point totals must match those specified in the table. ,
Select topics from many systems: avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
Systems / evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category / tier.
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ES-401 Gen:ric Knowledg. and Abiliti:s Outlinn (Ti:r 3) t ES-401-5 '
Exam Facility Braidwood Date: June 7,1999 Level: RO Category KA # KA Topic Imp. Points, Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements. 3.7 1 Knowledge of system status criteria which require the notification of 2.1.14 plant personnel. 2.5 1 Knowledge of operator responsibilities during all modes of plant 2.1.2 operation. 3.0 1 Total 3 Equipment Control 2.2.12 Knowledge of surveillance procedures. 3.0 1 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 2.2.23 Ability to track limiting conditions for operations. 2.6 1 Total 3 Knowledge of 10 CFR: 20 and rel%ed facility radiation control Radiation Control 2.3.1 requirements. 2.6 1 Knowledge of radiation exposure limits and contamination control, 2.3.4 including permissible levels in excess of those authorized. 2.5 1 Total 2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. Note: The issue of setpoints and automatic safety features is not specifically covered in the Emergency Procedures 2.4.2 systems sections. 3.9 1 Knowledge of low power / shutdown implications in accident (e.g.
End Plan 2.4.9 LOCA or loss of RHR mitigation strategies). 3.3 1 2.4.14 Knowledge of general guidelines for EOP flowchart use. 3.0 1 2.4.27 Knowledge of fire in the plant procedure. 3.0 1 2.4.32 Knowledge of operator response to loss of all annunciators. 3.3 1 Total 5 T6^r 3 Target Point Total (RO/SRO) 13
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T INITIAL SUBMITTAL OF THE BRAIDWOOD INITIAL EXAMINATION THE WEEK OF JUNE 7,1999 ,
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