ML090360406
| ML090360406 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/28/2008 |
| From: | Public Service Enterprise Group |
| To: | D'Antonio J Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML082600269 | List: |
| References | |
| 50-354/09-301, ES-401, ES-401-1, TAC U01693 50-354/09-301 | |
| Download: ML090360406 (24) | |
Text
ES-401 Written Examination Outline Form ES-401-1 Facility:
Hope Creek NRC Date of Exam:
February 2009
- 3. Generic Knowledge & Ab Note
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A 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.
Systems/evolutions within each group are identified on the associated 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 section D.l.b of ES-401, for guidance regarding 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 KAs 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 WA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l.b of ES-401 for the applicable WAS On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) 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 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 #I does not apply). Use duplicate pages for RO and SRO-only exams.
For Tier 3, select topics from Section 2 of the WA 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
ES-401 EAPE#/NameSafetyFunction Form ES-401-1 K1 K2 K3 AI A:!
G K/A Topic(s)
Imp.
Q#
Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 3.6 4.6 3.7 4.4 4.7 3.9 3.9 3.5 3.7 3.3 3.1 3.7 76 77 78 79 80 81 82 39 40 41 42 43 295021 Loss of Shutdown Cooling / 4 1
Refueling Accidents /
295019 Partial or Total Loss of inst. Air / 8 I
I I
295025 High Reactor Pressure / 3 I
295026 Suppression Pool High Water Temp. / 5 295031 Reactor Low Water Level / 2 295028 High Drywell Temperature / 5 295018 Partial or Total Loss of CCW I 8 295006 SCRAM I 1 X
~
295001 Partial or Complete
~ Loss of Forced Core Flow X
Circulation I 1 & 4 700000 Generator Voltage and Electric Grid Disturbances X
295030 Low Suppression Pool Water Level I 5 rnterpret the followmg as they apply to PARTIAL OR COMPLETE LOSS OF lNSTRUMENT AIR : Status of safefy-I I related mstrtmenf arr system loads I 2 7 23 - Conduct of Operatrons Abrlrty cedures during all owrng as they apply to HlGH DRYWELL TEMPERATURE :
Reactor wafer level they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Effects on componentlsystem CIRCULATION : Power/flow distribution interrelations between GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following:
Breakers. relavs.
interrelations between LOW SUPPRESSION POOL WATER LEVEL and the following: RCIC: Plant-Specific
ES-40 1 I
Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 I
295004 Partial or Total Loss of DC Pwr I 6 295023 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown I 1 295026 Suppression Pool High Water Temp. I 5 295025 High Reactor Pressure I 3 295031 Reactor Low Water Level I 2 295019 Partial or Total Loss of Inst. Air I 8 295038 High Off-site Release Rate I 9 I 295003 Partial or Complete Loss of AC I 6 295005 Main Turbine Generator Trip I 3 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown I 1
295021 Loss of Shutdown Cooling I 4 295024 High Drywell Pressure I 5 I
295016 Control Room Abandonment I 7 295028 High Drywell Temperature I 5 I 600000 Plant Fire O n - s i t e x AK2.01 - Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.
ES-401 EAPE#/NameSafetyFunction Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 K1 K2 K3 A I A2 G
K/A Topic(s)
Imp.
Q#
Form ES-401-1
EAPE#/NameSafetyFunction K1 K2 K3 A I A2 G
K/A Topic(s)
Imp.
Q#
ES-401 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 83 -
84 85 295033 High Secondary Containment Area Radiation Levels / 9 3.9 295017 High Offsite Release Rate / 9 4.6 4.1 295075 Incomplete SCRAM /
I operation/status that must be reported to internal organizations or external encres, such as State, the NRC, or monitor the following as they apply to HIGH SUPPRESSION POOL WATER 295010 High Drywell Pressure I 5 3.0 3.4 59 -
60 295022 Loss of CRD Pumps 295032 High Secondary Containment Area Temperature I 5 3.6 61 295029 High Suppression Pool Water Level I 5 295012 High Drywell Temperature I 5 3.4 -
3.9 62 63 -
64 -
65 295009 Low Reactor Water Level I 2 4.6 295013 High Suppression Pool Temperature I 5 3.6 WA Category Totals:
713
ES-40 1 K
System # I Name Form ES-401-1 A
A G
I m p Q#
K K
K K
K A A2 1
2 3
4 5
6 1
3 4
Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 4.6 4.7 4.2 4.7 3.6 2.7 4.0 2.6 2.8 3.5 3.4 86 87 88 89 90 1
2 3
4 5
6 206000 HPCI 209001 LPCS 211000 SLC 7 205000 Shutdown Cooling 218000 ADS 205000 Shutdown Cooling X
218000 ADS X
215004 Source Range Monitor 239002 SRVs 217000 RClC I 206000 HPCI I
ermine opera TION SYSTEM consequences of those abnormal cause-effect relationships between SHUTDOWN COOLING REACTOR CORE ISOLATION
ES-40 1 System #I Name Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 Imp Q#
K K
K K
K K
A A
2 A
A 1
2 3
4 5
6 1
3 4
I Form ES-401-1 300000 Instrument Air 262001 AC Electrical Distribution 264000 EDGs 212000 RPS 263000 DC Electrical Distribution 215003 IRM 203000 RHWLPCI:
Injection Mode 261 000 SGTS 21 1000 SLC design feature(s) and or interlocks which provide for the following. Cross-over to other air operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM : Specific logic monitor changes in parameters associated with operating the RHWLPCI: INJECTION MODE (PLANT SPECIFIC) controls SYSTEM ; and (b) based on 3.0 3.4 3.4 -
3.3 3.2 3.1 4.2 3.0 3.1
ES-40 1 K
System # / Name I
Form ES-40 1-1 A
A G
Imp Q#
K K
K K
K A
A2 1
2 3
4 5
6 1
3 4
Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 223002 PClSlNuclear X
Steam Supply Shutoff 209001 LPCS 215005 APRM I LPRM 400000 Component Cooling Water I I 218000 ADS I
I 239002 SRVs I I 1
1 203000 RHWLPCI:
Injection Mode 209001 LPCS 259002 Reactor Water Level Control 261 000 SGTS UA Category Totals:
3 2
ES-40 1 System # / Name Form ES-401-1 K
K K
K K
1 2
3 4
5 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 245000 Main Turbine Gen.
1 Aux.
202001 Recirculation 215001 TIPS 201003 Control Rod and Drive Mechanism 226001 RHWLPCI: CTMT Spray Mode 234000 Fuel Handling Equipment 214000 RPlS 245000 Main Turbine Generator and Auxiliary Systems 204000 RWCU Plan AbrCty to perform without reference to procedures those actions tbaf require rrnrnedlate cause-effect re between CONT automatic operations of the RHWLPCI: CONTAINMENT SPRAY SYSTEM MODE Generator operations and
Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 System # I Name Q
A A
G Imp.
K K
K K
K K
A N
1 2
3 4
5 6
1 3
4 201001 CRD Hydraulic 239001 Main and Reheat Steam 215002 RBM 241000 Reactormurbine Pressure Regulator 223001 Primary CTMT and Aux.
259001 Reactor Feedwater WA Category Totals:
2.8 4.2 3.1 3.5 -
3.4 2.7 1213
ES-40 1 Generic Knowledge and Abilities Outline (Tier3)
Form ES-401-3 I Facility:
Hope Creek Written Exam Date:
Category I------
Topic t
S RO-On1 y Q#
7 00 IR 3.5 3.9 2.1.34 Knowledge of primary and secondary plant chemistry limits.
Knowledge of fuel-handling responsibilities of 2.1.35 94 SROs i
Knowledge of shift or short-term relief 3.7 71 -
2.1.3 turnover practices Knowledne of individual licensed oDerator
- 1.
Conduct of Operations responsibilities related to shift I staffing, such as medical requirements, n e solo operation, maintenance I of active license status, 1 OCFR55, etc.
Ability to locate and operate components, including local controls.
2.1.4 3.3 67 2.1.30 t
2 Subtotal 2.2.7 special or infrequent tests.
Knowledge of the process for conducting 95 96 1
Knowledge of the process for managing maintenance activities during shutdown work 3.9 -
- 2.
Equipment Control Knowledge of the process for making changes to procedures 226 2.2.12 Knowledge of surveillance procedures Knowledge of tagging and clearance 22m13 I procedures I
Subtotal Radiation I----
Control 2
pertaining to licensed operator duties such as L
Knowledge of radiation exposure limits under normal or emergency conditions.
23m4
ES-40 1 2.4.40
- 4.
Emergency Procedures I Plan 4.5 98 Knowledge of SRO resporrsibi/ifies in emergency plan imp~emen fation Generic Knowledge and Abilities Outline (Tier3)
Form ES-401-3 2.4.18 2m4m43 2.3.13 Knowledge of the specific bases for EOPs.
3.3 73 (terminating DW spray at o psig)
Knowledge of emergency communications 3.2 72 systems and techniques.
Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.
3.4 I
I I
I I
I
ES-401 I
Record of Rejected WAs Form ES-401-4 Tier / Group 211 211 211 211 211 2 / 2 Randomly Selected WA 264000 / K5.05 Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET) :
Paralleling A.C. power sources 223002 /A2.03 Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: system logic failures 259002 / 2.2.25 Reactor Water Level control - Equipment Control: Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
203000 / A4.08 RHWLPCI Injection Mode -Ability to manually operate and/or monitor in the control room: Reactor pressure 209001 I A I.05 Ability to predict and/or monitor changes in parameters associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls including:
Torus/suppression pool water level 21 4000 I K4.02 Knowledge of ROD POSITION INFORMATION SYSTEM design feature(s) and/or interlocks which provide for the following:
Thermocouple Reason for Rejection
(#9) Same topic as #8 (parallel of AC sources). Randomly selected K5.06
(#I 6) Double jeopardy/similar topic as #34 (system actuation logic). Randomly selected K1.03
(#21) System does not have related TS bases or LCOs.
Randomly selected 21 8000 ADS.
(#23) This is very similar in concept to #I 3 due to interrelations between reactor pressure & level regarding injection. Randomly selected A4.02
(#24) same concept as tested in question #I3 for the RHR system. Randomly selected K4.09
(#30) Could not write a discriminating question for the topic. Randomly selected K4.01
ES-401 Record of Rejected KIAs Form ES-401-4 1 / 1 1 / 1 1 / 1 1 / 2 1 / 2 2 / 2 3
3 I / 1 295031 / EA1.I2 -
Ability to operate andlor monitor the following as they apply to REACTOR LOW WATER LEVEL :
Feedwater 295023 / AK3.02 -
Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS : Interlocks associated with fuel handling equipment 600000 / 2.2.38 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
226001 / K2.01 Knowledge of electrical power supplies to the following: Knowledge of electrical power supplies to the following: Valves 500000 / EK2.09 Knowledge of the interrelations between HIGH CONTAINMENT HYDROGEN CONCENTRATIONS the following: Drywell nitrogen purge system 215005 / 2.1.19 4PRMs -Ability to use Dlant computers to svaluate system or mnponent status.
2.1.21 - Ability to derify the controlled xocedure copy.
2.2.43 - Knowledge
>f the process to track noperable alarms 295012 / AA2.02 sbility to determine md/or interpref the ollowing as they apply o HIGH DRYWELL rEMPERA TURE :
Irywell Pressure
(#21) Ability to operate plant equipment in the event of low RPV level is tested frequently in the operating exam.
Randomly selected EK3.05
(#45) Refueling topic is oversampled (#29, #94). Randomly selected 295037 K3.01
(#58) This is an SRO function at HC. Randomly selected MI.06
(#28) Not a discriminating topic at the RO level (valve power supply) reselected A3.03
(#60) Guidance is contained in SAGS for this event. Could not write an operational valid question for this topic at the RO level. Randomly selected 295022 AK2.03
(#26) System (Nls) & Topic oversampled (see #19).
Randomly selected 261 000 A3.02
(#67) Topic oversampled (see #68 & #69). Randomly selected 2.1.4
(#74) Could not write a discriminating question for the topic. Randomly selected 2.2.13
(#83) Same WA as # 63. Randomly selected 295033 EA2.0 I
ES-40 1 I / ?
I / 2 2 / 1 2 / 2 3
295030 / 2.4.20 -
Emergency Procedures
[Pian: Knowledge of operational implications of EOP warnings, cautions, and notes.
(Low Suppression Pool Level) 295008 / 2.4.2 I -
Emergency Procedures 1 Plan: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containtnent conditions.
radioactivity release control, etc. [High Reactor Water Level) 263000 /A2.02 -
Ability to {a) predict the impacts of the following on the D.C.
EL EC TRlCA L DISTRIBUTION ; and (b) based on those predictions. use procedures to correct, control. or mitigate the consequences of those abnormal conditions or operations: Loss of ventilation during charging 268000 /A2.02 Ability to (a) predict the impacts of the following on the RADWASTE ;
and [b) based on those wedictions. use orocedures to correct, control, or mitigate the consequences of those abnormal conditions or Dperations: High Turbidity Water 2.2. 1-Ability to gerform pre-startup grocedures for the acility. including 2perating those controls 3ssociated with plant
?quipment that could sffect reactivity.
Record of Rejected WAs Form ES-401-4
(#80) System & Topic have very limited EOP notes/cautions for a discriminating question at the SRO level. Randomly selected 295026 2.7.7
(#84) Topic did not lend itself to a discriminating SRO level question. Randomly selected 29501 7
(#86) Topic (DC Power) is portions of questions 3,4, I I &
- 44. Additionally the topic does not lend itself to a discriminating SRO level question and has very limited Procedural guidance. Randomly selected 206000 G2.2.3 7
(#93) Does not apply at HC. Randomly selected 2 I500 I 42.07
?andomly selected 2.2.7
HC ILT 2009 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Hope Creek Date of Examination:
2/2/09 Examination Level: 0 RO SRO Operating Test Number:
NRC 2009 Administrative Topic (See Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Describe activity to be performed 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
RO: 2.9 SRO: 3.9 22009 Ensure Shift is Adequately Manned (RO will exceed guidelines. Requires Authorization Form) 2.1.I8 Ability to make accurate, clear and concise logs, records, status boards, and reports.
RO: 3.9 SRO: 4.0 ZZOl7 Initiate the Daily Surveillance Log (Shiftly Routine. Due to Plant Conditions, three optional attachments are reauired) 2.2.1 2 Knowledge of surveillance procedures RO: 3.7 SRO: 4.1 Authorize the Start of a Surveillance Test (One Hour ST.ZZ-0001 for Inoperable EDG) 2.3.1 1 Ability to control radiation releases RO: 3.8 SRO: 4.3 22032 Determine RCS Pressure Boundary Leak Rate (Review of completed surveillance determines math error made and actual leakage exceeds Tech Spec.
Determine reauired actions) 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required RO: 2.4 SRO: 4.4 ECGOOG Classifv Loss of All Barriers & Determine PAR NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Type Codes & Criteria:
(C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; S 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (21)
(P)revious 2 exams (SI; randomly selected)
(A)lternate Path
HC ILT 2009 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Hope Creek Date of Examination:
2/2/09 Examination Level:
RO 0 SRO Operating Test Number:
NRC 2009 Ad mi n istrative Topic (See Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control
/I Emergency Plan Type Code*
Describe activity to be performed 2.1.3 Knowledge of shift or short-term relief turnover practices RO: 3.7 SRO: 3.9 ZZOl2 Complete Equipment Status Checklist (HPCI Flow Controller is in MAN and should be in AUTO) 2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
RO: 4.1 SRO: 4.2 22030 Generate Off Normal Report (Shifilv Routine for Control Room NCO) 2.2.23 Ability to track Technical Specifications limiting conditions for operations.
RO: 3.2 SRO: 4.2 New : DL-26 Attachment 5 (Track isolation valve breaker open time for surveillance) 2.3.1 1 Ability to control radiation releases RO: 3.8 SRO: 4.3 New: Perform Alternate RCS Leakage Determination (RMS Leak Detection Inoperable. Manually calculate from Level Transmitter mA readings given by lac)
I NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Type Codes & Criteria:
(C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (21)
(P)revious 2 exams (SI; randomly selected)
(A)lternate Path I
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-Type Code*
Facility: HoDe Creek Exam Level: RO SRO-I 0 SRO-U 0 Operating Test No.: NRC2009 Date of Examination: 2/2/09 Safety Function Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
A, C, D, EN, L, S System / JPM Title 2
- a. Place The Control Room Emergency Filter Unit System In Standby (GK001)
C, D, S
- b. Manually Start The Core Spray System (BE005) 1
~
~
~
- c. Open The MSlVs With The Reactor Pressurized (>200 Psig) (AB006)
- Type Codes
- d. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) (BC009)
- e. Respond To A Containment Isolation (SM002)
Criteria for RO I SRO-I / SRO-U
- f. Perform Non-Emergency Operation Of The Diesel Generator (KJ008)
- g. Respond To A Reactor Auxiliary Cooling Malfunction (ED002)
(NRC 2005)
- h. Perform Scoop Tube Positioner Lockup Operation (BB002) RO ONLY In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j. Perform Torus Makeup Via Core Spray System (BE002)
1 3
C, D, L, S l
4 l
6 D, E, R 1
E:"
I (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including I(A)
(P)revious 2 exams (RFA (S)imulator 4-6 14-6 12-3 5 9 / 5 8 / 1 4 21 I 2 1 l b l 21 I 2 1 I 2 1 2 2 1 2 2 1 2 l 1 3 I 5 3 I1 2 (randomly selected) 2 1 121 I > 1
- I - I 21 (control room system)
I
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-,
II Facility: Hope Creek Exam Level: RO 0 SRO-I SRO-U 0 Date of Examination: 2/2/09 Operating Test No.: NRC2009 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. Place The Control Room Emergency Filter Unit System In Standby (GK001) l g
- b. Manually Start The Core Spray System (BE005)
- c. Open The MSlVs With The Reactor Pressurized (>200 Psig) (AB006)
A, C, D, EN, L, S C, N, S 2
3
- d. Place B RHR Loop In Suppression Pool Cooling From The Remote
- e. Respond To A Containment Isolation (SM002)
C, D, L, S A, C, N, L, S 4
Shutdown Panel (RSP) (BCOO9) 5
~~
- f. Perform Non-Emergency Operation Of The Dieselenerator (KJ008)
I C, D, S
- g. Respond To A Reactor Auxiliary Cooling Malfunction (ED002)
A, C, D, P, S 8
(NRC 2005)
- h. NA In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j. Perform Torus Makeup Via Core Spray System (BE002)
- k. Transfer RPS Bus AIB Power From Alternate Source To D, E, R 5
A, D 7
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions: in-plant systems and functions may overlap those tested in the control room.
li I
II
- Type Codes I
Criteria for RO I SRO-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)oditied from bank including I(A)
(P)revious 2 exams (S)imulator (R)CA 4-6 14-6 12-3 5 9 / 1 8 / 5 4 2 1 I 2 1 I 2 1 2 1 / 2 1 / 2 l 2 2 / 2 2 / 2 1 5 3 / 5 3 / 5 2 (randomly selected) 2 1 I 2 1 121
- I - I 21 (control room system)
I I
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2
- Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)oditied from bank including I(A)
(P)revious 2 exams (RFA (S)imulator Facility: HoDe Creek Date of Examination: 2/2/09 Criteria for RO / SRO-I / SRO-U 4-6 14-6 12-3 1 9 / 6 8 / < 4 2 1 I2 1 / 2 1 2 1 / r 112 1 22122121 I
3 I I 3 1 5 2 (randomly selected) 2 1 / 2 1 IZ 1
- / - / 21 (control room system)
Exam Level: RO SRO-I SRO-U Operating Test No.: NRC2009 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title
- a. NA
- b. Manually Start The Core Spray System (BE005)
- c. NA
- d. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) (BC009)
- e. Respond To A Containment Isolation (SM002)
- f. NA
- g. NA
- h. NA In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
Type Code*
Safety Function A, C, D, EN, L, S
I
A, C, N, L, S
- j. NA
- k. Transfer RPS Bus A/B Power From Alternate Source To 7
Appendix D Scenario Outline Form ES-D-I Facility: Hope Creek Examiners: J. DAntonio
- 9.
Fuller G. Johnson II Scenario No.: 1 Op-Test No.: NRC2009 Operators:
FRO)
Initial Conditions:
Plant is operating at 4% power. Startup in progress.
Turnover:
Withdraw Control Rods.
Inert the Containment.
T I
I I
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39
Scenario Outline Form ES-D-1 Appendix D Facility: Hope Creek Scenario No.:
Op-Test No.: NRC2009 Examiners: J. DAntonio B. Fuller G. Johnson Initial Conditions:
Plant is operating at 51% power.
Turnover:
Place D Circ Water Pump in service.
Raise power to 60% by withdrawing control rods and Recirc IAW 10-3 and RE guidance.
Event Malf.
Event Type*
Event No.
No.
Description 1
Start D Circ Water Pump.
Raise power with control rods.
11 3
I CDIOA I
C(R0)
CRD Pump Trip (TS) 4 110 1 A I 75 C (BOP)
C (SRO) 5 TCO7A C (ALL)
TC16 TC07B TCOI -1 0 6
RP07 M (All) 7 SL04A C (BOP)
SLOl B Rx Building Ventilation Supply Damper fails. (TS)
Place FRVS in service Trip of EHC Pump EHC Filter Clogging Manual Scram Loss of EHCl TBVs fail closed ATWS A SLC Pump Auto Start Failure B SLC Pump Trip
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: 3 Op-Test No.: NRC2009 Examiners: J. DAntonio B. Fuller G. Johnson initial Conditions: Reactor power is 90%.
Turnover:
Reduce power from 90% to 84.5% by inserting control rods IAW 10-6 and RE guidance to remove A RFPT from service.
Swap TACS to the B SACS Loop IAW HC.OP-SO.EG-0001.
1 2
3 4
5 6
Malf.
No.
NIA NIA RZ02A CU03 CUI 1A CUI 1 B TC02-1 TC02-2 TC02-3 TC02-4 TCOl-10 RZ03A RZ03C RR31 B1 RR31 B2 PC04 PC03E PC03G Event Type*
R (RO)
N (SRO)
N (BOP)
I (SRO)
I (ALL)
M (All)
C (BOP)
Event Description Reduce power with control rods.
Swap TACS to B SACS Loop PT-N403A RRCS Pressure Transmitter will fail downscale. (TS)
RWCU leak.
Automatic isolation valve failure. (TS)
EHC logic failure.
TCVs drift closed.
TBVs fail closed.
RPS and RRCS High Pressure logic failures.
Manual Scram due to rising RPV pressure.
LOCA with downcomer failure.
PT-N094E/G will fail to respond to High Drywell Pressure 7
8
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 3
AD04H 4
NM12C 5
PC07B RC09 RCIO 6
IAOlA 7
IAO 1 I
CDOI 1427 CDOI 1827 CDO12227 CD062627 8
EG12 HP04 DGOI C DG02B DG02D I
Facility: Hope Creek Scenario No.:
Op-Test No.: NRC2009 Examiners: J. DAntonio B. Fuller G. Johnson Operators:
FRO)
I nitial Conditions :
Plant is operating at 84.5% power following repair of B RFPT.
Turnover:
Raise power to 90% by increasing Reactor Recirc IAW 10-6 and RE guidance.
Place B RFPT in service to feed the RPV.
I I
RR31 A2 RH08C Event Type*
N (BOP)
N (SRO)
I (SRO)
R (RO)
I (RO)
C (BOP)
C (SRO)
C (SRO)
M (All)
M (All)
C (BOP)
Event Description Place B RFPT in service to feed the RPV.
Raise power with recirculation flow.
H SRV Tailpipe Temperature fails high. (TS)
Recirc Loop Flow Summer failure.
Seismic Event >SSE RClC Steam Leak RClC Fail to Isolate (TS)
Trip of Service Air Compressor Air Leak w/Multiple Rod Drift/ Manual Scram Control Rod Drift In 14-27 Control Rod Drift In 18-27 Control Rod Drift In 22-27 Control Rod Scram 26-27 LOP HPCl Failure C EDG Failure to Start (Auto or Man) (recoverable)
Failure of B EDG Failure of D EDG LOCA A RHR Pump Trip A EDG Trip (recoverable)
C RHR Failure to Auto-Startllnject I
APPENDIX D, Page 38 of 39