ML19298B557
| ML19298B557 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/26/2019 |
| From: | Cherie Crisden, Ted Wingfield Operations Branch I |
| To: | Susquehanna |
| Shared Package | |
| ML18289A614 | List: |
| References | |
| LOC:30 | |
| Download: ML19298B557 (23) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: SSES Units 1 and 2 Scenario No.: NRC-02 Op-Test No.: LOC:30 Examiners:
Operators:
Initial Conditions: The scenario begins with Unit 1 and Unit 2 operating at rated power.
Turnover: RCIC is out-of-service to inspect the governor valve. LCO 3.5.3, Condition A, entered six hours ago. HPCI is protected. Perform S0-158-001 at beginning of shift. Scram Pilot solenoid valve thermography was completed three hours ago.
'B' CRM is shutdown for pump oil replacement. Clearance Order to be applied next shift.
Critical Tasks:
- 1.
Perform a manual reactor scram prior to peak to peak oscillations exceeding 10% on APRMs
- 2.
Perform Emergency Rapid Depressurization II Event No.
Malf. No.
Event Event Type*
Desciription 1
N/A N-ALL Perform S0-158-001 2
(CN05U1_L I-BOP
[CST Level Switch failure SLLE411NO TS-SRO HPCI Supp Pool Suction valve fails Auto open]
02TVSP)
Open HV155F042 / Address Tech Specs 3
N/A R-ATC
[Min Generation Emergency]
Reduce Reactor Power with Recirculation 4
(1y216)
C-BOP
[Loss of 1Y216]
TS-SRO Cross tie CIG and IA, Transfer HSS0681A to Bypass/ Address Tech Specs 5
(NBFKU1_T C-ATC
['A' Recirc Pump Bearing High Temp]
E1457A1TS TS-SRO Trip 'A' RRP / reduce power/ Address Tech Specs VP)(TE_143 57A1 final) 6 (malf_e410)
C-ATC
[11 B Aux Bus Lockout]
Place Mode Switch in Shutdown 7
(MALF RR M-ALL
[LOCA inside Drywell]
- 03)
Initiate Containment Sprays 8
(CNMU1_1 C-ATC
['A' and 'C' Condensate Pumps Trip]
P102A OC Initiate HPCI ATF _ACT)
(CNMU1_1 P102A OCb TF ACT))
9 (HPATU1K1 C-ATC
[HPCI Trips]
2TSVP)
C-BOP Maximize CRD / lniect SLC / ED when< -161" feed with Core Spray 10 (MALF _AD4 C-ATC
[ADS Auto Initiation logic fails]
2A)
Manually initiate ADS (MALF AD4
- 28)
(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: SSES Units 1 and 2 Scenario No.:
NRC-04 Op-Test No.:.!:OC30 Examiners:
Operators:
Initial Conditions:
Unit 1 Reactor Power is 97% following control rod exercising. Unit 2 is at rated power. All systems and equipment are operable.
Turnover:
Restore power to 100% per CRC Book. 'B CRM is shutdown for pump oil replacE!ment. Clearance Order to be applied next shift.
Critical Tasks: See Scenario Guide
- 1.
Manually start an EDG and energize the 4kV Bus 1A (B, C, D)
- 2.
Maintain RPV level with available high pressure systems to prevent Automatic Depressurization System Initiation I
Event I Malf. No. I Event I
Evi:mt No.
Type*
Description 1
N/A R-ALL Raise power by increasing Recirc Flow N -ALL 2
(MALF_N I-ATC
[APRM 1 Fails Upscale] Bypass APRIVI 1 M30) 3 (MS25U1_
C-BOP
[Loss of Vacuum - SJAE Suction Spurious Isolation Flow]
FV10702A ATVFAIL SP) 4 (malf_rd19 C-BOP
['A' CRD Pump Trip & Accumulator 50-43 trouble] Start standby CRD Pump/
)
TS-SRO evaluate Tech Specs (RDBMRO D 5043TA MXACCPR
)
5 (MALF E5 C-BOP
[1 A ESS Bus Lockout]
- 01)
TS-SRO Transfer RPS to Alt, reset half-Scram, reset isolations 6
(EHAAU1 C-ALL
[EHC Pump Leak / Standby pump fails to Auto Start]
CCTVSP)
Attempt to start standby pump, insert Lim 2, and Scram the Reactor (EHABU1 CCTVSP)
(rem eh04
)
7 (MALF _E1 M-ALL
[Loss of Offsite Power with Diesel Failures]
- 01)
Manually start 'B' and 'D' diesels (MALF_DE 038) 8 (MALF _HP C-ATC
[Failure of HPCI & RCIC Auto Initiation}
- 11)
Start HPCI Component by Component/ Manually initiate RCIC (MALF_RC
- 01)
(P1C601_
HSS15677
- 2)
(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: SSES Units 1 and 2 Scenario No.:
NRC-06 Op-Test No.: LOC30 Examiners:
Operators:
Initial Conditions: Unit 1 Reactor Power is 90%. Unit 2 is operating at rated power. All systems and equipment are operable.
Turnover: Reactor power was reduced to 90% using Recirculation at the request of Generation. TB NPO is swapping the Lube Oil Conditioner from 'C' to 'A' RFPT Lube Oil Resen,oir. Work Control has requested swapping 'B' RFP Main Oil pumps. 'B' CRM is shutdown for pump oil replacement. Clearance Order to be applied next shift.
Critical Tasks:
- 1.
Insert control rods using RPS Manual Scram logic or Alternate Rod Insertion (ARI) system
- 2.
Perform an Emergency Depressurization when two or more areas exceed Max Safe Operating Temperatures.
II Event Malf.
Event Event No.
No.
Type*
Descri1:>tion 1
N/A N-BOP Swap 'B' RFP main lube oil pumps 2
N/A R-ATC Raise power with Recirculation 3
(MSAHU C-ATC
[3A FW Heater Extraction Steam Isolation]
1RL42F C-BOP Reduce power with Recirculation to < 71 %
TVSP) 4 (NB03U I-SRO
['D' MSL flow transmitter fails high]
1FISB21 TS-SRO SRO evaluates Tech Spec 1N009D TVSP) 5 (MALF _
C-BOP
['A' RFPT and 'A' Lube Oil Pumps trip with foreign material report FL21A)
Remove 'A' RFPT from service 6
(P1C651 C-ATC
['A' and 'C' RFPs trip]
HS127 Place Mode Switch in Shutdown 45A 1) 7 (MALF_
C-BOP
[Failure to Scram on Mode Switch to Shutdown]
RP09A)
Initiate ARI (MALF _
RP09B) 8 (MALF_
C-BOP
[Loss of Offsite Power]
E101)
Use RCIC and HPCI for level control 9
(MALF_
M-ATC
[Unisolable Steam Leak HPCI Room]
HP04)
M-BOP Use RCIC, CRD, and SLC for level control TS-SRO SRO evaluates Tech Spec 10 (MALF_
M-BOP
[Steam Leak in Pipe Routing Area]
HP03)
Emerqencv Depressurize (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Susquehanna Date of Examination:
Examination Level: RO IZI SRO D Operating Test Number:
8/26/2019 LOC 30 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations R, D Conduct of Operations R,D Equipment Control R, p Radiation Control R, M Implement AOP*-145-001, Feedwater System Abnormal Operating Procedure, and Determine the Cause for Erroneous Water Level Indications KIA: 2.1.25 Determine Work Hour Controls KIA: 2.1.5 Describe RPS Response to APRM Upscale Votes Using Prints KIA: 2.2.41 Application of Radiation Exposure Limits for SDC/RHR KIA: 2.3.4 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s; 3 for ROs; s; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank {2=: 1)
(P)revious 2 exams (s; 1, randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Susguehanna Date of Examination:
8/26/2019 Examination Level: RO D SRO
~
Operating Test Number:
LOG 30 Administrative Topic (see Note)
Type Describe activity to be performed Code*
Implement AOP-145-001, Feedwater System Conduct of Operations R,D Abnormal Operating Procedure, Determine the Cause for Erroneous Water Level Indications, Determine the Cause for Erroneous Water Level Indications, AND )etermine Required Tech Specs KIA: 2.1.25 Determi,e Work Hour Controls Conduct of Operations R,D KIA: 2.1.5 Describe RPS Response to APRM Upscale Votes Equipment Control R,P Using Prints AND Determine Required Tech Specs KIA: 2.2.41 Application of Radiation Exposure Limits for Radiation Control R,M SDC/RHR KIA: 2.3.4 Post Scenario Event Classification (Scenario Emergency Plan R,M Dependent)
KIA: 2.4.41/2.4.44 NOTE: All items (five total) are required for SROs. RO applicants requi1*e only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:5 3 for ROs; :5 4 for SROs and RO retakes)
(N)ew or (M)odified from bank (:?: 1)
(P)revious 2 exams (:5 1, randomly selected)
ES-301 Control Room/In-Plant Systems Outli1ne Form ES-301-2 Facility:
Susguehanna Date of Examination:
8/26/2019 Exam Level: RO
~ SRO-I D
SRO-U D
Operating Test Number:
LOC 30 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*
Safety Function
- a.
Initiate SBLC A, E, L, D, S 1
211000 A3.06 4.0/4.1
- b.
Feed with an Additional Reactor Feed Pump/ Shutdown RFP A,M,S 2
due to Bearing Oil Low Pressure 259001 A4.02 3.9/3.7 C.
Open MSIVs During Reactor S/U L M, P, S 3
239001 A4.01 4.2/4.0
- d.
Core Spray System Shutdown A, EN, L, M, 4
209001 A4.03 3.7/3.6 s
- e.
Inert Unit 1 Drywell N,S 5
223001 A4.05 3.6/3.6
- f.
Restore Power to Bus 20 D, L, S 6
262001 A2.07 3.0/3.2
- g.
Control Rod Exercising Operability Test A,N,S 7
214000 A4.02 3.8/3.8
- h.
Restore Reactor Building HVAC EN, L, N, S 9
295032 EA1.03 3.7/3.7 In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i.
Shift CRD Drive Water Filters D,R 1
201001 A2.05 2.9/2.9
- j.
Perform Manual Operation of the ADS Valves from the Relay EN, D, E 3
Room 218000 A2.04 4.1/4.2
- k.
Manual Emergency Shutdown of Diesel Generator 'C' A E, M 6
264000 A4.04 3.7/3.7
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /SR0-1/SRO-U (A)lternate path 4-6/4-fi /2-3 (C)ontrol room (D)irect from bank s; 9/s; 8/5 4 (E)mergency or abnormal in-plant 2: 1/2: 1/2: 1 (EN)gineered safety feature 2: 1/2: 1/::: 1 (control room system)
(L)ow-Power/Shutdown 2: 1/2: 1/2: 1 (N)ew or (M)odified from bank including 1 (A) 2: 2/2: 2/ 2: 1 (P)revious 2 exams s; 3/s; 3/5 2 (randomly selected)
(R)CA 2: 1/2: 1/2: 1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Facility:
Susquehanna Date of Examination:
--~---------
Exam Level: RO D
SRO-I C8:l SRO-U D
Operating Test Number:
Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U
- a.
Initiate SBLC 211000 A3.06 4.0/4.1 System/JPM Title
- b.
Feed with an Additional Reactor Feed Pump/ Shutdown RFP due to Bearing Oil Low Pressure 259001 A4.02 3.9/3.7
- c.
Open MSIVs During Reactor S/U 239001 A4.01 4.2/4.0
- d. Core Spray System Shutdown 209001 A4.03 3.7/3.6
- f.
Restore Power to Bus 20 262001 A2.07 3.0/3.2
- g. Control Rod Exercising Operability Test 214000 A4.02 3.8/3.8
- h.
Restore Reactor Building HVAC 295032 EA1.03 3.7/3.7 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i.
Shift CRD Drive Water Filters 201001 A2.05 2.9/2.9
- j.
Perform Manual Operation of the ADS Valves from the Relay Room 218000 A2.04 4.1/4.2
- k.
Manual Emergency Shutdown of Diesel Generator 'C' 264000 A4.04 3.7/3.7 Type Code*
A, E, L, D, S A, M, S L, M, P, S A, EN, L, M, s
D, L, S A, N, S EN, L, N, S D, R E,D,E A, E,M Form ES-301-2 8/26/2019 LOC 30 Safety Function 2
3 4
6 7
9 3
6
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /SR0-1/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank
- 9/
- :, 8/5 4 (E)mergency or abnormal in-plant
~ 1/~ 1/~ 1 (EN)gineered safety feature
~ 1/~ 1/~ 1 (control room system)
( L )ow-Power/Shutdown
~ 1 /;c: 1/:~ 1 (N)ew or (M)odified from bank including 1 (A)
~ 2/~ 2h 1 (P)revious 2 exams
- 3/
- :; 3/5 2 (randomly selected)
(R)CA
~ 1/~ 1/;~ 1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Facility:
_S_us_g~u_e_h_an_n_a ____ __ _
Date of Examination:
Exam Level: RO D
SRO-I D
SRO-U IZI Operating Test Number:
Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title
- b. Feed with an Additional Reactor Feed Pump/ Shutdown RFP due to Bearing Oil Low Pressure 259001 A4.02 3.9/3.7
- h. Restore Reactor Building HVAC 295032 EA1.03 3.7/3.7 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i.
Shift CRD Drive Water Filters 201001 A2.05 2.9/2.9
- j.
Perform Manual Operation of the ADS Valves from the Relay Room 218000 A2.04 4.1/4.2
- k.
Manual Emergency Shutdown of Diesel Generator 'C' 264000 A4.04 3.7/3.7 Type Code*
A, M, S EN, L, N, S D,R EN,D, E A, E,M Form ES-301-2 8/26/2019 LOC 30 Safety Function 2
9 3
6 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different sa ety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /SR0-1/SRO-U
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams (R)CA (S)imulator 4-6/4-fi /2-3
- ,; 9/:£ 8/-5. 4
~ 1/~ 1/~ 1
~ 1/~ 1/~ 1 (control room system)
~ 1/~ 1/~ 1
~ 2/~ 2/~ 1
- ,; 3/:£ 3/-5. 2 (randomly selected)
~ 1 /~ 1 /::: 1
ES-401 Page 1 of 12 Form ES-401-1
~uehanna(Rev. 7)
Date of Exam: August, 2019 Tier Group RO KIA Category Points G~
SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 A2 G*
Total
- 1.
1 4
3 4
3 3
~I 20 4
3 7
Emergency and Abnormal Plant 2
1 1
1 N/A 2
1 N/A 7
2 1
3 Evolutions Tier Totals 5
4 5
5 4
LI 27 6
4 10
- 2.
1 3
2 3
2 3
3 2
2 2
2 26 2
3 5
Plant 2
1 1
1 2
1 2
0 1
2 1
(I 12 0
1 2
3 Systems Tier Totals 4
3 4
4 4
5 2
3 4
3 38 3
5 8
1 2
3 4
1 2
3 4
- . :::_.,~ric Knowledge and Abilities Categories 10 7
2 3
3 2
1 2
2 2
Note: 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 radiation control KIA is allowed if it is replaced by a KIA from another Tier 3 category.)
- 2. 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 +/-1 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.
- 3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-speci*'ic systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
- 4. 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.
- 5.
Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
- 7. The generic (G) Kl As in Tiers 1 and 2 shall be selected from Section 2 of the ~'"JA catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-4D1 for the applicable KIAs.
- 8. On the following pages, enter the KIA numbers, a brief description of each top c, the topics' I Rs 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. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply.) Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA nJmbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
G* Generic KIAs These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the KIA catalog.
These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan.
ES-401 Pa~e 2 of 12 Form ES-401-1 Susquehanna(Rev. 7)
BWR Examination Outline Form ES-401-Erner and Abnormal Plant Evolutions -Tier 1/Grou 1 RO/SRO Item E/APE # / Name / Safety K1 K2 K3 A1 KIA Topic(s)
IR Q#
Function (29500182.4.50) PARTIAL OR COMPLETE 295001 (APE 1) Partial or LOSS OF FORCED COFtE FLOW Complete Loss of Forced CIRCULATION/ 1 & 4:.ll.bility to verify system 4.2/4.0 72 Core Flow Circulation / 1 & 4 alarm setpoints and operate controls identified in the alarm response manual.
295003 (APE 3) Partial or (295003AK1.02) Knowledge of the operational implications of the following concepts as they 2
Complete Loss of AC Power /
X apply to PARTIAL OR COMPLETE LOSS OF 3.1/3.4 11 6
A.C. POWER: Load shecding 295004 (APE 4) Partial or (295004AK2.01) Knowledge of the interrelations 3
X between PARTIAL OR C:JMPLETE LOSS OF 3.1/3.1 35 Total Loss of DC Power/ 6 D.C. POWER and the fol owing: Battery charger (295005AK3.05) Knowledge of the reasons for 4
295005 (APE 5) Main Turbine X
the following responses as they apply to MAIN 2.5/2.6 36 Generator Trip / 3 TURBINE GENERATOR TRIP: Extraction steam/moisture separato" isolations 5
295006 (APE 6) Scram / 1 X
(295006AA 1.01) Ability to operate and/or monitor 4.2/4.2 18 the following as they apply to SCRAM: RPS (295016AK3.01) Knowledge of the reasons for 6
295016 (APE 16) Control X
the following responses 1:,.s they apply to 4.1/4.2 55 Room Abandonment I 7 CONTROL ROOM ABAI\\ DONMENT: Reactor SCRAM (295018AK2.01) Knowledge of the interrelations 7
295018 (APE 18) Partial or X
between PARTIAL OR COMPLETE LOSS OF 3.3/3.4 75 Complete Loss of CCW / 8 COMPONENT COOLING WATER and the following: System loads 295019 (APE 19) Partial or (295019AA2.01) Ability to determine and/or 8
Complete Loss of Instrument interpret the following as they apply to PARTIAL 3.5/3.6 56 OR COMPLETE LOSS CF INSTRUMENT AIR:
Air/ 8 Instrument air system pressure 295021 (APE 21) Loss of (295021AK2.03) Knowleclge of the interrelations 9
X between LOSS OF SHUTDOWN COOLING and 3.6/3.6 21 Shutdown Cooling / 4 the following: RHR/shutdown cooling 295023 (APE 23) Refueling (295023AA 1.04) Ability tc, operate and/or monitor 10 X
the following as they apply to REFUELING 3.4/3.7 05 Accidents / 8 ACCIDENTS: Radiation monitoring equipment (295024EK1.01) Knowleclge of the operational 11 295024 (EPE 1) High Drywell X
implications of the followi11g concepts as they 4.1/4.2 06 Pressure/ 5 apply to HIGH DRYWELL. PRESSURE: Drywell integrity: Plant-Specific (295025EK3.03) Knowleclge of the reasons for 12 295025 (EPE 2) High Reactor X
the following responses as they apply to HIGH 3.8/3.8 07 Pressure/ 3 REACTOR PRESSURE: HPCI operation: Plant-Specific (29502682.1.31) SUPPRESSION POOL HIGH 295026 (EPE 3) Suppression WATER TEMPERATURE/ 5: Ability to locate 13 Pool High Water control room switches, controls, and indications, 4.6/4.3 03 Temperature/ 5 and to determine that they correctly reflect the desired plant lineup.
295028 (EPE 5) High Drywell (295028EA2.03) Ability ta determine and/or interpret the following as they apply to HIGH 14 Temperature (Mark I and DRYWELL TEMPERATURE: Reactor water 3.4/3.7 47 Mark II only) 15 level.
295030 (EPE 7) Low (29503082.1.20) LOW SUPPRESSION POOL 15 Suppression Pool Water WATER LEVEL / 5: Ability to interpret and 4.6/4.6 57 Level/ 5 execute procedure steps.
(295031 EK1.02) Knowlecge of the operational 16 295031 (EPE 8) Reactor Low X
implications of the following concepts as they 3.8/4.1 60 Water Level / 2 apply to REACTOR LOW WATER LEVEL:
Natural circulation: Plant-Specific
ES-401 Paae 3 of 12 Form ES-401-1 nna (Rev. 7)
BWR Examination Outline Form ES-401-1 Erner and Abnormal Plant Evolutions -Tier 1/Groue 1 {RO/SRO}
Item E/APE # / Name / Safety K1 K2 K3 A1 iJ.
KIA Topic(s)
IR Q#
Function (295037EK1.03) Knowlejge of the operational 295037 (EPE 14) Scram implications of the follow ng concepts as they 17 Condition Present and X
apply to SCRAM CONDITION PRESENT AND 4.2/4.4 08 Reactor Power Above APRM REACTOR POWER ABOVE APRM Downscale or Unknown / 1 DOWNSCALE OR UNKtJOWN: Boron effects on reactor power (SBLC) 295038 (EPE 15) High Offsite (295038EA1.05) Ability to operate and/or monitor 18 Radioactivity Release Rate /
X the following as they apply to HIGH OFF-SITE 3.0/3.5 30 9
RELEASE RATE: Post accident sample system (PASS): Plant-Specific (600000AK3.04) Knowle,jge of the reasons for 19 600000 (APE 24) Plant Fire X
the following responses as they apply to PLANT 2.8/3.4 33 On Site/ 8 FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on site 700000 (APE 25) Generator (700000AA2.04) Ability to determine and/or 20 Voltage and Electric Grid interpret the following as they apply to 3.6/3.6 53 Disturbances / 6 GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: VARs outside capability curve 295003 (APE 3) Partial or (295003AA2.04) Ability to determine and/or 21 Complete Loss of AC Power/
interpret the following as they apply to PARTIAL 3.7 78 OR COMPLETE LOSS OF A.C. POWER:
6 System lineups (29501682.4.21) CONTROL ROOM ABANDONMENT/ 7: Knowledge of the 295016 (APE 16) Control parameters and logic used to assess the status of 22 Room Abandonment / 7 safety functions, such as reactivity control, core 4.6 94 cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
(29501882.4.34) PARTIAL OR COMPLETE 295018 (APE 18) Partial or LOSS OF CCW / 8: Knowledge of RO tasks 23 Complete Loss of CCW / 8 performed outside the main control room during 4.1 86 an emergency and the resultant operational effects.
295021 (APE 21) Loss of (295021AA2.03) Ability to determine and/or 24 Shutdown Cooling / 4 interpret the following as they apply to LOSS OF 3.5 77 SHUTDOWN COOLING: Reactor water level (29502382.1.23) REFUELING ACCIDENTS:
25 295023 (APE 23) Refueling Ability to perform specific system and integrated 4.4 90 Accidents / 8 plant procedures during all modes of plant operation.
(295025EA2.03) Ability to determine and/or 26 295025 (EPE 2) High Reactor interpret the following as they apply to HIGH 4.1 84 Pressure/ 3 REACTOR PRESSURE: Suppression pool temperature 295037 (EPE 14) Scram (295037EA2.01) Ability to determine and/or Condition Present and interpret the following as they apply to SCRAM 27 Reactor Power Above APRM CONDITION PRESENT AND REACTOR 4.3 92 Downscale or Unknown / 1 POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Reactor power KIA Cate 0 Totals:
4 3
4 3
Grou Point Total:
20/7
ES-401 Pa~e 4 of 12 Form ES-401-1 Susquehanna (Rev. 7)
BWR Examination Outline F
and Abnormal Plant Evolutions - Tier 1/Grou 2 RO/SRO Item E/APE # / Name / Safety K1 K2 K3 A1 KIA Topic(s)
IR Q#
Function (295014AA2.03) Ability to determine and/or 28 295014 (APE 14) Inadvertent interpret the following as they apply to 4.0/4.3 25 Reactivity Addition / 1 INADVERTENT REACTIVITY ADDITION: Cause of reactivity addition (295017 AK1.02) Knowledge of the operational 29 295017 (APE 17) Abnormal X
implications of the follow ng concepts as they 3.8/4.3 58 Offsite Release Rate / 9 apply to HIGH OFF-SITE RELEASE RATE:
Protection of the general public (295020AK3.04) Knowlejge of the reasons for 30 295020 (APE 20) Inadvertent X
the following responses as they apply to 4.1/4.1 66 Containment Isolation / 5 & 7 INADVERTENT CONTAINMENT ISOLATION:
Reactor pressure response 295032 (EPE 9) High (29503282.1.20) HIGH SECONDARY 31 Secondary Containment Area CONTAINMENT AREA --EMPERATURE / 5:
4.6/4.6 12 Temperature/ 5 Ability to interpret and e)ecute procedure steps.
295034 (EPE 11) Secondary (295034EA 1.03) Ability tQ operate and/or monitor 32 Containment Ventilation High X
the following as they ap~ly to SECONDARY 4.0/3.9 63 CONTAINMENT VENTILATION HIGH Radiation / 9 RADIATION: Secondary containment ventilation (295036EK2.01) Knowledge of the interrelations 295036 (EPE 13) Secondary between SECONDARY CONTAINMENT HIGH 33 Containment High X
SUMP/AREA WATER LEVEL and the following:
3.1/3.2 17 Sump/Area Water Level/ 5 Secondary containment equipment and floor drain system 500000 (EPE 16) High (500000EA 1.03) Ability t3 operate and monitor the following as they ap~*ly to HIGH 34 Containment Hydrogen X
CONTAINMENT HYDROGEN CONTROL:
3.4/3.2 45 Concentration / 5 Containment atmosphem control system 295015 (APE 15) Incomplete (295015AA2.02) Ability to determine and/or 35 interpret the following as they apply to 4.2 100 Scram/ 1 INCOMPLETE SCRAM: Control rod position (295002AA2.02) Ability to determine and/or 36 295002 (APE 2) Loss of Main interpret the following as they apply to LOSS OF 3.3 99 Condenser Vacuum / 3 MAIN CONDENSER VACUUM: Reactor power:
Plant-Specific 295009 (APE 9) Low Reactor (29500982.2.38) LOW FtEACTOR WATER 37 LEVEL/ 2: Knowledge of conditions and 4.5 83 Water Level / 2 limitations in the facility I cense.
KIA Cate o Totals:
2 Grou Point Total:
7/3
ES-401 Paae 5 of 12 Form ES-401-1 Susquehanna(Rev. 7)
BWR Examination Outline Form ES-401-1 Plant S stems - Tier 2/Grou 1 RO/SRO'!
Item E/APE # / Name I K1 K2 K3 K4 KIA Topic(s)
IR Q#
Safe! Function (203000A3.04) Ability to 203000(SF2, SF4 moni1or automatic 38 RHR/LPCI) operntions of the 3.8/3.7 27 RHR/LPCI:
RHR1LPCl:INJECTION Injection Mode MODE (PLANT SPECIFIC) including: System flow (205000K4.02) Knowledge of SI-UTDOWN COOLING SYSTEM(RHR 205000 (SF4 SCS)
SHUTDOWN COOLING 39 X
MODE) design feature(s) 3.7/3.8 64 Shutdown Cooling and/or interlocks which provide for the following:
High pressure isolation:
Plant -Specific (206000K5.08) Knowledge of the operational 206000 (SF2. SF4 implications of the following 40 HPCIS)
X concepts as they apply to 3.0/3.2 16 High-Pressure HIGH PRESSURE Coolant Injection COOLANT INJECTION SYs-*EM: Vacuum breaker operation:BWR-2,3,4 209001 (SF2, SF4 (2090011<2.02) LOW PRESSURE CORE SPRAY 41 LPCS)
X SYs--EM: Knowledge of 2.5/2.7 61 Low-Pressure Core Spray electrical power supplies to the following: Valve power (211000K5.06) Knowledge of the operational 211000(SF1 SLCS) implications of the following 42 Standby Liquid X
concepts as they apply to 3.0/3.2 59 Control STANDBY LIQUID CONTROL SYSTEM: Tank level measurement (212000K6.03) Knowledge of the effect that a loss or 212000 (SF? RPS) malfunction of the following 43 X
will have on the REACTOR 3.5/3.7 43 Reactor Protection PROTECTION SYSTEM:
Nuclear boiler instrumentation (215003A1.03) Ability to predict and/or monitor 215003 (SF? IRM) changes in parameters asso,:iated with operating 44 Intermediate-Range the IIHERMEDIATE 3.6/3.7 71 Monitor RANGE MONITOR (IRM)
SYSTEM controls inclu,jing: RPS status (2151l04A2.02) Ability to (a) predict the impacts of the following on the SOURCE RAN3E MONITOR (SRM) 215004 (SF?
SYSTEM; and (b) based on 45 SRMS) those predictions, use 3.4/3.7 44 Source-Range procedures to correct, Monitor control, or mitigate the consequences of those abnormal conditions or operations: SRM inop condition
ES-401 Pa~e 6 of 12 Form ES-401-1 (Rev. 7)
BWR Examination Outline Form ES-401-1 Plant S stems - Tier 2/Grou 1 Item E/APE # / Name /
K1 K2 K3 K4 K5 K6 A1 KIA Topic(s)
IR Q#
Safet Function (215005A1.05) Ability to predict and/or monitor 215005 (SF7 chanJes in parameters PRMS) Average assodated with operating 46 Power Range X
the AVERAGE POWER 3.3/3.2 39 Monitor/Local RAN13E MONITOR/LOCAL Power Range POWER RANGE Monitor MONITOR SYSTEM controls including: Lights and alarms (215005K5.04) Knowledge of the operational 215005 (SF7 implications of the following PRMS) Average conc,~pts as they apply to 47 Power Range X
AVEHAGE POWER 2.9/3.2 28 Monitor/Local RANGE MONITOR/LOCAL Power Range POWER RANGE Monitor MONITOR SYSTEM:
LPRM detector location and core symmetry (217000K3.01) Knowledge of the effect that a loss or 217000(SF2, SF4 malfunction of the REACTOR CORE 48 RCIC) Reactor Core X
ISOLATION COOLING 3.7/3.7 74 Isolation Cooling SYSTEM (RCIC) will have on following: Reactor water level (218000K1.04) Knowledge of the physical connections and/or cause-effect 218000 (SF3 ADS) relationships between 49 Automatic X
AUTOMATIC 3.9/4.2 73 De pressurization DEPl~ESSURIZATION SYSTEM and the following:
Dryv,ell/containment presi;ure: Plant-Specific (2181JOOK2.01) 218000 (SF3 ADS)
AUTOMATIC DEPl~ESSURIZATION 50 Automatic X
SYSTEM: Knowledge of 3.1/3.3 40 Depressurization elect*ical power supplies to the following: ADS logic (2231J02K3.03) Knowledge of the effect that a loss or 223002 (SF5 PCIS) malfunction of the Primary PRIMARY CONTAINMENT 51 Containment X
ISOLATION 3.6/3.8 13 Isolation/Nuclear SYSTEM/NUCLEAR Steam Supply STEAM SUPPLY SHUT-Shutoff OFF will have on following:
Off-site radioactive release rates (23900282.2.44) SAFETY RELIEF VALVES: Ability to interpret control room 239002 (SF3 SRV) indic3tions to verify the 52 Safety Relief Valves status and operation of a 4.2/4.4 01 system, and understand how operator actions and directives affect plant and syste,m conditions.
ES-401 Pa~e 7 of 12 Form ES-401-1 Susquehanna(Rev. 7)
BWR Examination Outline Form ES-401-1 Plant S stems - Tier 2/Grou 1 Item E/APE # / Name I K1 K2 K3 K4 KIA Topic(s)
IR Q#
Safe! Function (259CI02K1.08) Knowledge of the* physical connections 259002 (SF2 and/c,r cause-effect relationships between 53 RWLCS) Reactor X
REACTOR WATER LEVEL 3.2/3.2 70 Water Level Control CONTROL SYSTEM and the following: Recirculation system: Plant-Specific (261 CIOOK4.04) Knowledge of STANDBY GAS 261000 (SF9 TREJ\\TMENT SYSTEM 54 SGTS) Standby X
design feature(s) and/or 2.7/2.9 51 Gas Treatment interlocks which provide for the following: Radioactive particulate filtration (262CI01A4.05) A.C.
ELECTRICAL 262001 (SF6 AC)
DISTRIBUTION: Ability to 55 AC Electrical manually operate and/or 3.3/3.3 29 Distribution monilor in the control room:
Volta~e. current, power, and f1*equency on A.C.
buse:;
(262CI02K1.13) Knowledge of the, physical connections and/c,r cause-effect 262002 (SF6 UPS) relationships between 56 Uninterruptable X
UNINTERRUPTABLE 2.5/2.6 19 Power Supply POWER SUPPLY (AC/DC)
(A.C. 1D.C.) and the following: Recirculation pumr* speed control: Plant-Specific (262CI02K6.03) Knowledge 262002 (SF6 UPS) of the, effect that a loss or Uninterruptable malfunction of the following 57 X
will have on the 2.7/2.9 02 Power Supply UNINTERRUPTABLE (AC/DC)
POWER SUPPLY (A.C.'D.C.): Static inverter (263CIOOA4.03) D.C.
ELECTRICAL 263000 (SF6 DC)
DISTRIBUTION: Ability to 58 DC Electrical manually operate and/or 2.7/2.8 31 Distribution monitor in the control room:
Battery discharge rate:
Plant-Specific (264000A3.01) Ability to monilor automatic 264000 (SF6 EGE) operations of the EMEl~GENCY 59 Emergency GENERATORS 3.0/3.1 09 Generators (DIESEUJET) including:
(Diesel/Jet) EDG Automatic starting of com~ressor and emer~ency generator (300CIOOK3.02) Knowledge of the, effect that a loss or malfL nction of the 60 300000 (SF8 IA)
X (INSTRUMENT AIR 3.3/3.4 41 Instrument Air SYSTEM) will have on the following: Systems having pneu11atic valves and contmls
ES-401 Page 8 of 12 Form ES-401-1 Susquehanna (Rev. 7)
BWR Examination Outline Form ES-401-1 Plant S stems - Tier 2/Grou 1 RO/SROI IFlt=em==;ii="E=/A"'P""E=#,::=/ N=a=m=e=/ =;===;====;=K=3==r=K=4==;==!:=;===;==
==*===========;======;=Q=#=ll Safe! Function K1 K2 KIA Topic(s)
IR 61 62 63 64 65 66 67 300000 (SF8 IA)
Instrument Air 400000 (SF8 CCS)
Component Cooling Water 400000 (SF8 CCS)
Component Cooling Water 203000(SF2.SF4 RHR/LPCI)
RHR/LPCI:
Injection Mode 215004(SF7 SRMS)
Source-Range Monitor 212000 (SF7 RPS)
Reactor Protection 211000 (SF1 SLCS)
(300000K6.07) Knowledge of the, effect that a loss or malfL nction of the following will have on the INSTRUMENT AIR SYSTEM: Valves (400CIOOA2.01) Ability to (a) predi,~t the impacts of the following on the CCWS and (b) based on those predi,~tions, use procedures to co1Tect, control, or mitigate the consequences of thc,se abnormal operation: Loss of CCW pump (400CIOOG2.4.34)
COMPONENT COOLING WATER: Knowledge of RO tasks performed outside the main control room durinJ an emergency and the resultant operational effec*:s.
(20300082.4.20)
RHR,'LPCI: INJECTION MODE: Knowledge of the operational implications of EOP warnings, cautions, and notes.
(21500482.2.25)
SOURCE-RANGE MONITOR: Knowledge of the bases in Technical Specifications for limiting cond lions for operations and i,afety limits.
(21200082.4.21)
REACTOR PROTECTION:
Knowledge of the parameters and logic used to assess the status of safetf functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
(211 OOOA2.03) Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the cons,equences of those abnormal conditions or operations: A.C. power failures 2.5/2.6 49 3.3/3.4 42 4.2/4.1 15 4.3 97 4.2 85 4.6 80 3.4 87
ES-401 Pa~e 9 of 12 Form ES-401-1 Susquehanna (Rev. 7)
BWR Examination Outline Form ES-401-1 Plant S stems - Tier 2/Grou 1 Item E/APE # / Name /
K1 K2 K3 K4 KIA Topic(s)
IR Q#
Safe! Function (223002A2.11) Ability to (a) predi:t the impacts of the following on the PRIMARY CONTAINMENT 223002 (SF5 PCIS)
ISOLATION svs-,EM/NUCLEAR Primary STEAM SUPPLY SHUT-68 Containment OFF; and (b) based on 3.9 93 Isolation/Nuclear Steam Supply those, predictions, use Shutoff procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Standby liquid initia1ion KIA Category 3
2 3
2 3
3 Group Point Total:
26/5 Totals:
ES-401 Pa~e 10 of 12 Form ES-401-1 Susquehanna(Rev. 7)
BWR Examination Outline Form ES-401-1 Plant S stems - Tier 2/Grou 2 E/APE # / Name I K1 K2 K3 K4 KS K6 A1 KIA Topic(s)
IR Q#
Safet Function (201 J01 K2.05) CONTROL ROC DRIVE HYDRAULIC 201001 (SF1 SYSfEM: Knowledge of 69 CRDH)CRD X
electrical power supplies to 4.5/4.5 26 Hydraulic the following: Alternate rod insertion valve solenoids:
Plan:-Specific (201 J02K6.01) Knowledge of the effect that a loss or 201002 (SF1 malfunction of the following 70 RMCS) Reactor X
will rave on the REACTOR 2.5/2.6 65 Manual Control MAI\\ UAL CONTROL SYSfEM: Select matrix powm (201 J03A4.02) CONTROL 201003 (SF1 ROC AND DRIVE CRDM) Control Rod MECHANISM: Ability to 71 and Drive manually operate and/or 3.5/3.5 38 Mechanism monitor in the control room:
CRD mechanism position:
Plan:-Specific (215J02K4.01) Knowledge of ROC BLOCK MONITOR 215002 (SF7 SYSfEM design feature(s) 72 RBMS) Rod Block X
and/or interlocks which 3.4/3.5 37 Monitor provide for the following:
Prevent control rod withclrawal:BWR-3,4,5 (223J01A2.07) Ability to (a) pred ct the impacts of the following on the PRIMARY CONTAINMENT SYSTEM 223001 (SFS PCS)
AND AUXILIARIES; and (b) 73 Primary based on those predictions, 4.2/4.3 20 Containment and use procedures to correct, Auxiliaries control, or mitigate the consequences of those abnc,rmal conditions or oper3tions: High drywell pres:;ure (234JOOK5.02) Knowledge of the c,perational implications 234000 (SF8 FH) of th,~ following concepts as 74 Fuel-Handling X
they apply to FUEL 3.1/3.7 10 Equipment HANDLING EQUIPMENT:
Fuel handling equipment interlocks (290J01A3.02) Ability to 290001 (SFS SC) monitor automatic operations of th,~ SECONDARY 75 Secondary COi\\ TAINMENT including:
3.5/3.5 46 Containment Normal building differential pres:;ure: Plant-Specific (241 JOOK1.15) Knowledge of the ~,hysical connections 241000 (SF3 and/or cause-effect 76 RTPRS)
X relationships between 2.6/2.7 67 Reactor/Turbine REACTOR/TURBINE Pressure Regulating PRESSURE REGULATING SYSfEM and the following:
D.C. electrical power
ES-401 Paae 11 of 12 Form ES-401-1 Susquehanna (Rev. 7)
BWR Examination Outline Form ES-401-1 Plant S stems - Tier 2/Grou 2 E/APE # / Name I K1 K2 K3 K4 KIA Topic(s)
IR Q#
Item Safe! Function (245DOOK6.06) Knowledge of the effect that a loss or 245000 (SF4 malfunction of the following MTGEN) Main X
will have on the MAIN 3.0/3.2 04 77 Turbine TURBINE GENERATOR Generator/Auxiliary AND AUXILIARY SYSTEMS:
Elec:rical distribution (259:J01 K3.02) Knowledge of the e*ffect that a loss or 259001 (SF2 FWS) malfunction of the REACTOR 3.8/3.8 14 78 X
FEEDWA TER SYSTEM will Feedwater have on following: Reactor water level control system (272)00K4.03) Knowledge of RADIATION MONITORING System design feature(s) 272000 (SF?, SF9 and/or interlocks which 79 RMS) Radiation X
provide for the following: Fail 3.6/3.9 23 Monitoring safe tripping of process radiation monitoring logic durirg conditions of instrument failure (286000A3.03) Ability to monitor automatic operations 286000 (SF8 FPS) of the FIRE PROTECTION 3.3/3.3 52 80 Fire Protection SYSTEM including: Actuation offire detectors (202002A2.02) Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW 202002 (SF1 CONTROL SYSTEM; and (b)
RSCTL) based on those predictions, 3.0 91 81 Recirculation Flow use procedures to correct, Control control, or mitigate the consequences of those abnormal conditions or operations: Loss of AC.
(230000G2.1.32) RHR/LPCI:
230000 (SF5 RHR TORUS/SUPPRESSION SPS) RHR/LPCI:
POOL SPRAY MODE: Ability 4.0 95 82 Torus/Suppression to explain and apply system Pool Spray Mode limits and precautions.
(288000G2.4.6) PLANT 96 288000 (SF9 PVS)
VENTILATION: Knowledge 4.7 83 Plant Ventilation of EOP mitigation strategies.
KIA Cate o Totals:
2 2
Grou Point Total:
12/3
ES-401 Page 12 of 12 Form ES-401-1 Susquehanna BWR Examination Outline Form ES-401-1 (Rev. 7)
Plant Systems - Tier 3 (RO/SRO)
Category K/A#
Topic CEWOr SRO-onlv G2.1.17 Ability to make accurate, clear, and concise verbal reports.
84 3.9 34 G2.1.1 Knowledge of conduct of operations requirements.
85 3.8 69 G2.1.38 Knowledge of the station's requirements for verbal communications when 86 3.8 98
- 1. Conduct of implementing procedures.
Operations Subtotal
~
G2.2.1 Ability to perform pre-startup procedures for the facility, including operating 87 4.5 62 those controls associated with plant equipment that could affect reactivity.
G2.2.38 Knowledge of conditions and limitations in the facility license.
88 3.6 48 G2.2.6 Knowledge of the process for making changes to procedures.
89 3.0 22
- 2. Equipment G2.2.40 Ability to apply Technical Specifications for a system.
90 4.7 82 Control G2.2.39 Knowledge of less than or equal to one hour Technical Specification action 91 4.5 76 statements for systems.
Subtotal
]~
G2.3.11 Ability to control radiation releases.
92 3.8 24 G2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation 93 2.9 32 monitors and alarms, portable survey instruments, personnel monitc ring equipment, etc.
G2.3.7 Ability to comply with radiation work permit requirements during normal or 94 3.5 54 abnormal conditions.
- 3. Radiation G2.3.4 Knowledge of radiation exposure limits under normal or emergency 95 3.7 88 Control conditions.
G2.3.13 Knowledge of radiological safety procedures pertaining to licensed 96 3.8 81 operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, acceBs to locked high-radiation areas, aligning filters, etc.
Subtotal
]~
G2.4.26 Knowledge of facility protection requirements, including fire brigade and 97 3.1 50 portable fire fighting equipment usage.
G2.4.29 Knowledge of the emergency plan.
98 3.1 68 G2.4.12 Knowledge of general operating crew responsibilities during emergency 99 4.3 79 operations.
- 4. Emergency G2.4.4 Emergency Procedures/ Plan: Ability to recognize abnormal indications 100 4.7 89 Procedures/Plan for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
IHIIE Subtotal Tier 3 Point Total 7