ML050830137
| ML050830137 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/18/2005 |
| From: | Popielarski J Exelon Generation Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| Download: ML050830137 (22) | |
Text
L ES401 BWR Examination Outline FORM ES401-1
'acility Name: Peach Bottom 2 8 3 Date of Exam: February 7,2005 dote: 1.
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Ensure that at least two topics from every applicable WA category are sampled within each tier of the RC and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two).
The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by *I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
Systemdevolutions within each group are identified on the assodated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
The generic (G)
WAS in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
For Tier 3. select topics from Section 2 of the K/A catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.
ES-401 2
Form ES-401-I BWR Examination Outline Form ES-40 v
95003 Partial or Complete Loss of AC I 6 Cauw d parual OT canplete loar of A C power 95019 Partial or Total Loss of Inst. Air I 8 u
95024 High Drywell Pressure I5 95038 High Off-site Release Rate I 9
+
ES-401, Page 17 of 33
ES-401 3
Form ES-401-1 I
F 1
BWR Examination Outline F w ~
ES-401-actor Water Level / 2 v
95017 High Off-site Release Rate I 9 5022 Loss of CRD Pumps I I ES-401, Page 18 of 33
ES-401 4
Form ES-401-1 s-401 BWR Examination Outline Form Ea01 Plant Svstems - Tier ZGrouD 1 IROI ES-401, Page 19 of 33
ES-401-1 5
Form ES-401-1 ES-401, Page 20 of 33
ES-401 2
Form ES-401-1 IlES-401 Em II 11 EIAPE # I Name I Safety Function 95001 Partial or Complete Loss of Forced Flow Circulation I 1 8 4 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 295005 Main Turbine Generator Trip I 3
95006 SCRAM I 1
I1 95016 Control Room Abandonment I 7 It 95018 Partial or Total Loss of CCW I 8 It 95019 Partial or Total Loss of Inst. Air I 8 Ib 295021 Loss of Shutdown Cooling I 4
- 295023 Refueling Acc I 8 295024 High Drywell Pressure I 5 295025 High Reactor Pressure I 3
295026 Suppression Pool High Water Temp.
15 295027 High Containment Temperature I 5 295028 High Drywell Temperature I 5 95030 Low Suppression Pool Wtr Lvl I 5 Ib 95031 Reactor Low Water Level I 2 II.
SCRAM Condition Present and Power APRM Downscale or Unknown I 1 95038 High Off-site Release Rate I 9 00000 Plant Fire On Site I 8 Y
KIA Category Totals:
BWR Examination Wine Form ES-40 i and Abnom K
Plant Evolutions - Tier 1lGroup 1 (SRO)
KIA Topic(s) 2 IR m
0
- 02. Knowledge of limiting & i s for operaticm and 22 safelylimits.
4.,
0 Reaclorweterlevel 4.2
- 04. KnowMga of which events related Io system operahndstatus &odd be reported to outside agencies.
3.6 1
30 4
3 Group PointTotal:
7 ES-401, Page 17 of 33
ES-401 3
Form ES-4 31 0
295036 Secondary Containment High Sump/Area Water Level I5 5OOOOO High CTMT Hydrogen Cow. I 5 WA Category Totals:
0 0
0 0
2 1 GroupPointTotal:
3 0
BWR Examination Outline Form ES-401 Emergency and Abnormal Plant Evolutions - Tier 1lGroup 2 (SRO) 0 0
0 ES-401, Page 18 of 33
ES-401 4
Form ES-401-1 ES-401 BWR Examination Outline F
o
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ES-401-Plant Systems - Ti ZGmp 1 (SRO) 05000 Shutdown Cooling Mode 15005 APRM I LPRM ES-401, Page 19 of 33
ES-401 5
Form ES-401-1 BWR Examination W i n e Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)
ES-401, Page 20 of 33
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
FOm ES-401-3 ES-401, Page 26 of 33
ES-301 Administrative Topics Outline Form ES-301-I N, S N, S N/A N, S Facility: Peach Bottom Drywell Bulk Average Manual Temperature Verification.
Use station prints to identify component Clearance Points.
Not Required.
Perform State and Local Notifications following the declaration of an Emergency Condition.
Date of Examination: Weeks of February 7 & 14,2005 Examination Level (circle one): RO / SRO Operating Test Number: RO Administrative Topic (see Note)
Conduct of Operations Temporary Procedure Change Conduct of Operations Parameter Verification Equipment Con t rot P&IDs/ Clearance Points Radiation Control Emergency Plan Emergency Communications I
Code*
Type I Describe activity to be performed D, P, S I initiate A Temporary Procedure Change.
rlOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless
' Type Codes & Criteria: (C)ontrol room they are retaking only the administrative topics, when 5 are required.
(D)irect from bank (I 3 for ROs; s 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (2 1)
(P)revious 2 exams ( I 1; randomly selected)
(S)imulator ES 301-1, Page 22 of 27
e Radiation Control Authorizing Emergency Exposure Emergency Plan Emergency Notifications.
I ES-301 Administrative Topics Outline Form ES-301-1 Facility: Peach Bottom Date of Examination: Weeks of February 7 & 14, 2005 Examination Level (circle one): RO / SRO Operating Test Number: SRO Administrative Topic (see Note)
Conduct of Operations Procedure Modification Conduct of Operations Parameter Verification Equipment Control Clearance and Tagging Type Code*
Describe activity to be performed Authorize a deviation from the Control Rod Sequence on a Control Rod Move Sheet.
Conduct a Manual Heat Balance.
Evaluate a Clearance for approval.
Authorize an Emergency Exposure.
Prepare the State and Local Notification Form for an Emergency Classification.
qOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless
' Type Codes & Criteria: (C)ontrol room (D)irect from bank (13 for ROs; I 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (2 1)
(P)revious 2 exams (I 1; randomly selected)
(Slimulator they are retaking only the administrative topics, when 5 are required.
ES 301-1, Page 22 of 27
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Valve (MSIV) (Alternate Path - AC Fuses fail to close MSIV)
. Reactor Protection System (RPS) I Scram Solenoid Deenergization
- t. Plant Ventilation / Restoring Control Room Ventilation following a High Radiation Trip Facility: Peach Bottom Exam Level (circle one): RO I SRO(I) I SRO(U)
Date of Examination: Week of Februarv 7 & 14. 2005 Operating Test Number:
D, E, R 7
(ESF)
D, R 9
Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
'Type Codes A)lternate path Criteria for RO / SRO-I I SRO-U 4-61 4-6 12-3
(C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (Mbdified from bank including (P)revious 2 exams (WCA (S)imulator Engineered Safeguard Feature (ESF)
ESF systems referenced from those listed in Section 1.6.2 of the Peach Bottom UFSAR.
ES-301, page 23 of 27
ES-301 Control RoomAn-Plant Svstems Outline Form ES-301-2
- i. Plant Ventilation I Restoring Control Room Ventilation following a High Radiation Trip Facility: Peach Bottom Exam Level (circle one): RO I SRO(I) I SRO(U)
Date of Examination: Week of Februarv 7 & 14, 2005 Operating Test Number:
SRO (1)
(ESF)
D, R 9
Control Room Systems" (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System I JPM Title Type Code Safety Function 1
- a. Standby Liquid Control (SBLC) I Inject Boron into the RPV (Alternate
- b. Reactor Core Isolation Cooling (RCIC) / Manual System Startup A, N, S Path - Low SBLC Pump Discharge Pressure)
A, N, S 2
- Type Codes
- A)lternate path
- C)ontrol room (Alternate Path - Cooling Water Valve Fails to Open Automatically)
(ESF)
D, S, L 3
- c. Automatic Depressurization System (ADS) I ADS Reset Following Criteria for RO I SRO-I I SRO-U 4-61 4-6 12-3 Blowdown (ESF)
A, D, S (ESF)
D, S 5
- d. High Pressure Coolant Injection (HPCI) I Raise HPCI Flow (Alternate
Path - Suction Valves Fail to Auto Swap on Low CST Level)
Containment during Normal Operations
- f. Emergency Generators I Diesel Generator Synchronization and Loading M, S (ESF)
N, S. L 8
6
- g. Component Cooling Water I Verify proper isolation of Drywell Chilled Water (DWCW) and Reactor Building Closed Cooling Water (RBCCW).
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 1D)irect from bank e 9 1 e 8 I C 4
(E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams Engineered Safeguard Feature (ESF)
( W A (S)imulator ESF systems referenced from those listed in Section 1.6.2 of the Peach Bottom UFSAR.
ES-301 Control Roodln-Plant Systems Outline F
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ESSOI-2 Engineered Safeguard Feature (ESF)
ESF systems referenced from those listed in Facility: Peach Bottom Exam Level (circle one): RO I SRO(I) I SRO(U)
Date of Examination: Week of Februarv 7 & 14.2005 Operating Test Number:
SRO (U)
I Control Room Systems" (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System I JPM Title Type Code A. N, S
- a. Standby Liquid Control (SBLC) I Inject Boron into the RPV (Alternate
- b. Reactor Core Isolation Cooling (RCIC) I Manual System Startup
- c. Component Cooling Water I Verify proper isolation of Drywell Chilled Path - Low SBLC Pump Discharge Pressure)
A. N, S (ESF)
N, s, L (Alternate Path - Coding Water Valve Fails to Open Automatically)
Water (DWCW) and Reactor Building Closed Cooling Water (RBCCW).
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
Safety Function 1
2 8
- d. Main and Reheat Steam I Closing a Stuck Open Main Steam Isolation M, A, E.
L, R (ESF)
D, E, R 7
(ESF) 3 Valve (MSIV) (Alternate Path - AC Fuses fail to close MSIV)
I Scram Solenoid Deenergization
@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap tho I
- Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including l(A)
(P)revious 2 exams
( W A (S)imulator
? tested in the control room.
Criteria for RO I SRO-I / SRO-U 4-61 4-6 12-3 ES-301, page 23 of 27
Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No.
- I Op Test No.
Examiners Operators CRS PRO URO Scenario Summary The scenario begins with the reactor at 4% power during a reactor startup. The E-1 Diesel Generatoi is 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> into a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance run. During the turnover, the crew is directed to swap RBCCW pumps for inspection of a noisy bearing on the 'B' RBCCW pump. Following the swap of RBCCW, the crew is to continue with the reactor startup pulling control rods in accordance with the approved startup sequence. A trip of the running ESW pump with a failure of the auto-start on the standby pump will require the operators to manually start the standby pump and consult Tech Specs.
After the Tech Spec determination, a high Standby Liquid Control Tank temperature alarm will be received. An investigation will determine that the tank heater had stuck on and the crew should take action to open the breaker for the heater. A review of Tech Specs will result in the SBLC system being considered inoperable due to the loss of NPSH to the pumps.
Once the Tech Spec interpretation is complete, a recirc leak develops in the drywell requiring entry into OT-101, High Drywell Pressure. The crew will take actions for the rising drywell pressure and will manually scram the reactor and enter T-101, RPV Control. During the scram, five rods will fail to insert resulting in an ATWS.
Attempts to spray the drywell will fail due to a drywell spray logic failure and the crew will need to perform a T-112, Emergency Blowdown when drywell temperature cannot be maintained below 281 degrees F. With several rods stuck out, the crew will need to terminate and prevent injection in accordance with T-240 prior to the emergency depressurization. The scenario may be terminated when the RPV depressurization is performed.
Initial Condition lC-121,4% power rurnover:
Event Malfunction Event Event See Attached "Shift Turnover" Sheet No.
No.
Type*
Description 1
ATC N
SRO Power Ascension with Control Rods.
I R I
Recirculation System leak in the drywell.
(N)ormal, (R)eactivity. (I)nstrument, (C)omponent, (M)ajor
I
. c Scenario Outline ES-D-1 Slmulatlon Facility Peach Bottom Scenario No.
Examiners operators CRS PRO URO Scenario Summary The scenario begins with the reactor at 100% power with a RClC surveillance in progress. Following the RClC testing, the crew is to commence a GP-3, Normal Plant Shutdown.
After the RCIC turbine is started, a low lube oil pressure alarm is received (similar to a recent Peach Bottom HPCl event). The crew will shutdown RClC and complete a Tech Spec interpretation. The crew will then commence a GP-3, Normal Plant Shutdown. After the reactivity manipulation has beer observed, the running Control Rod Drive pump will trip. The crew will pursue the issue using ON-107, Loss of CRD Regulating function. The inability to restore either CRD pump for 20 minutes after CRD Charging Header pressure drops below 940 psig with two accumulator alarms, will result in a required Tech Spec scram.
When the RO attempts to shutdown the plant, an electrical ATWS will occur requiring enby into T-101, RPV Control. Shortly after tripping the recirculation pumps, the 'D' SRV will fail full open requiring entry into OT-114, Stuck Open Safety Relief Valve, and ultimately T-102, Primary Containment Control.
When the RO maximizes torus coding, the 'A' Loop RHR Torus Cooling Valve (MO-39A) will trip on magnetic overcurrent resulting in no Torus Cooling on the 'A' Loop of RHR causing torus conditions continue to degrade. This will result in an entry into T-102, Primary Containment Control when 95°F is reached. When t o m temperature cannot be maintained below 1 10°F, Standby Liquid Control (SBLC) will be attempted and the pumps will fail to start.
After level has been lowered to control power, the ATWS will be terminated by T-214, Venting the Scram Air Header. The scenario may be terminated after all control rods are verified inserted.
nltial Condition rurnover:
lGl22,100% power with the 'B' loop of Torus Coding in service.
See Attached Shift Turnover Sheet
~
Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No.
- 3 Op Test No.
Examiners Operators CRS PRO URO Scenario Summary The scenario begins with the reactor at 95% power. The turnover directs the crew to swap Control Rod Drive (CRD) Flow Control Valves when maintenance is ready to observe operation of the standby valve.
Shortly after assuming the shift, a Drywell Pressure Instrument will fail upscale without inserting the appropriate half reactor scram. The crew will apply tech specs and insert the half scram using GP-25, Installation of Trips/lsolations to satisfy Tech SpedTRM Requirements. After the sciam is inserted, maintenance will call requesting that the CRD flow control valve be swapped to the standb) valve. When it is swapped, it will be recognized that the standby valve is failed open and CRD will bc swapped back to the original flow controller. When the swap is complete, a single control rod will begin to drift. The crew will enter ON-121, Drifting Control Rod and drive the rod in. A fast power reduction to 950 Mwe will be required due to the drifted control rod. Again, the crew will review and apply the tech spec requirements for these conditions.
A leak develops in the Reactor Water Cleanup (RWCU) System and the crew will enter T-103, Secondary Containment Control. The RWCU valves cannot be isolated and a T-112, Emergency Depressurization will be required when max safe temperatures are exceeded in two areas. If the Bypass Jack is attempted for a normal or a rapid depressurization, it will fail to function. When the manual blowdown is initiated, the 'C' SRV will not open, requiring the crew to open an alternate SRV.
Initial Condition rurnover:
IG123,95% Power, Full Power Rod Pattern See Attached -Shift Turnover" Sheet Event I Malfunction I
Event No.
No.
Type*
1 Overrides I
URO I
I PRO CRS N.- URO 2
PRO CRS Preinserted C. URO
.3 CRH03B PRO I
I CRS I
CRH043035 I C URO 4
1 1
. > PRO CRS R
URO Preinserted C
URO Event Description Drywell Pressure Instrument fails upscale without the expected half scram (Tech Spec).
Swap Control Rod Drive Flow Control Valves.
Control Rod Drive Flow Control Valve Fails Open.
Single Control Rod Drifts (Tech Spec).
Fast Power Reduction due to the Drifting Control Rod.
- ,~
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor