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. 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).
- 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 +fromI 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/evolutionswithin 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.
- 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 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.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
- 7. 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
- 8. 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.
- 9. 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 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/NameSafetyFunction K1 K2 K3 AI A:! G K/A Topic(s) Imp. Q#
295021 Loss of Shutdown Cooling / 4 3.6 76 1 Refueling Accidents /
4.6 77 295019 Partial or Total Loss rnterpret the followmg as they apply to of inst. Air / 8 PARTIAL OR COMPLETE LOSS OF 3.7 78 lNSTRUMENT AIR :Status of safefy-I I I I I related mstrtmenf arr system loads I 2 7 23 - Conduct of Operatrons Abrlrty 295025 High Reactor Pressure / 3 4.4 79 cedures during all I
295026 Suppression Pool 4.7 80 High Water Temp. / 5 295031 Reactor Low Water Level / 2 3.9 81 owrng as they apply to 295028 High Drywell Temperature / 5 HlGH DRYWELL TEMPERATURE : 3.9 82 Reactor wafer level they apply to PARTIAL OR COMPLETE 295018 Partial or Total Loss of CCW I 8 LOSS OF COMPONENT COOLING 3.5 39 WATER : Effects on componentlsystem 295006 SCRAM I 1 X 3.7 40
~ 295001 Partial or Complete
~ Loss of Forced Core Flow X 3.3 41 Circulation I 1 & 4 CIRCULATION : Power/flow distribution interrelations between GENERATOR 700000 Generator Voltage and Electric Grid VOLTAGE AND ELECTRIC GRID X 3.1 42 Disturbances DISTURBANCES and the following:
Breakers. relavs.
295030 Low Suppression interrelations between LOW SUPPRESSION POOL WATER LEVEL 3.7 43 Pool Water Level I 5 and the following: RCIC: Plant-Specific I
ES-40 1 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 I AK2.01 - Knowledge of the 295004 Partial or Total Loss interrelations between PARTIAL OR of DC Pwr I 6 COMPLETE LOSS OF D.C. POWER 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 I1 295021 Loss of Shutdown Cooling I 4 I 295024 High Drywell Pressure I 5 295016 Control Room Abandonment I 7 295028 High Drywell Temperature I 5 I 600000 Plant Fire O n - s i t e x ES-401 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/NameSafetyFunction K1 K2 K3 AI 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 EAPE#/NameSafetyFunction K1 K2 K3 AI A2 G K/A Topic(s) Imp. Q#
295033 High Secondary Containment Area Radiation 3.9 83 Levels / 9 295017 High Offsite Release 4.6 84 Rate / 9 295075 Incomplete SCRAM / operation/status that must be reported to 4.1 85 I internal organizations or external encres, such as State, the NRC, or 295010 High Drywell 3.0 59 Pressure I 5 3.4 295022 Loss of CRD Pumps 60 295032 High Secondary Containment Area 3.6 61 Temperature I 5 295029 High Suppression monitor the following as they apply to 3.4 62 Pool Water Level I 5 HIGH SUPPRESSION POOL WATER 295012 High Drywell 3.9 63 Temperature I 5 295009 Low Reactor Water 4.6 64 Level I 2 295013 High Suppression 3.6 65 Pool Temperature I 5 WA Category Totals: 713 ES-40 1 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A2 System # I Name A A G Imp Q#
1 2 3 4 5 6 1 3 4 ermine opera 206000 HPCI 4.6 86 209001 LPCS 4.7 87 211000 SLC 4.2 88 7
205000 Shutdown Cooling 4.7 89 TION SYSTEM 218000 ADS 3.6 90 consequences of those abnormal cause- effect relationships 205000 Shutdown between SHUTDOWN COOLING X 2.7 1 Cooling 218000 ADS X 4.0 2 215004 Source Range 2.6 3 Monitor 239002 SRVs 2.8 4 REACTOR CORE ISOLATION 217000 RClC 3.5 5 I
206000 HPCI I 3.4 6 I
ES-401 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A 2 A A System #I Name Imp Q#
1 2 3 4 5 6 1 3 4 300000 Instrument Air design feature(s) and or 3.0 interlocks which provide for the following. Cross-over to other air 262001 AC Electrical Distribution 3.4 264000 EDGs 3.4 operational implications of the 212000 RPS following concepts as they apply 3.3 to REACTOR PROTECTION SYSTEM : Specific logic 263000 DC Electrical Distribution 3.2 215003 IRM 3.1 monitor changes in parameters 203000 RHWLPCI: associated with operating the Injection Mode 4.2 RHWLPCI: INJECTION MODE (PLANT SPECIFIC) controls 261000 SGTS 3.0 SYSTEM ; and (b) based on 21 1000 SLC 3.1 I
ES-401 Form ES-40 1-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A2 System # / Name A A G Imp Q#
1 2 3 4 5 6 1 3 4 223002 PClSlNuclear X Steam Supply Shutoff 209001 LPCS 215005 APRM I LPRM 400000 Component Cooling Water II 218000 ADS I I 239002 SRVs II 203000 RHWLPCI:
Injection Mode 11 209001 LPCS 259002 Reactor Water Level Control 261000 SGTS UA Category Totals: 3 2 ES-40 1 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K System # / Name 1 2 3 4 5 245000 Main Turbine Gen.
1 Aux.
Plan AbrCty to perform without reference to procedures those 202001 Recirculation actions tbaf require rrnrnedlate 215001 TIPS 201003 Control Rod and cause- effect re Drive Mechanism between CONT automatic operations of the 226001 RHWLPCI: CTMT RHWLPCI: CONTAINMENT Spray Mode SPRAY SYSTEM MODE 234000 Fuel Handling Equipment 214000 RPlS 245000 Main Turbine Generator and Auxiliary Systems Generator operations and 204000 RWCU Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A N Q System # I Name A 1 2 3 4 5 6 1 3 A4 G Imp.
201001 CRD Hydraulic 2.8 239001 Main and Reheat Steam 4.2 215002 RBM 3.1 241000 Reactormurbine Pressure Regulator 3.5 223001 Primary CTMT and Aux. 3.4 259001 Reactor Feedwater 2.7 WA Category Totals: 1213 ES-40 1 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3 I Facility: Hope Creek Written Exam Date:
I------
S RO-On1
- y t
Category Topic IR
-- Q#
Knowledge of primary and secondary plant 2.1.34 3.5 7 00 chemistry limits. -
Knowledge of fuel-handling responsibilities of 2.1.35 3.9 94 SROs 2.1.3 Knowledge of shift or short-term relief i
3.7 71 turnover practices - -
- 1. Knowledne of individual licensed oDerator Conduct responsibilities related to shift I of Operations 2.1.4 staffing, such as medical requirements, n e 3.3 67 solo operation, maintenance I of active license status, 10CFR55, etc.
Ability to locate and operate components, 2.1.30 including local controls.
Subtotal Knowledge of the process for conducting t 2 2.2.7 special or infrequent tests. 95 Knowledge of the process for managing maintenance activities during shutdown 1
work 3.9 96 2.
Equipment Control Knowledge of the process for making 226 changes to procedures 2.2.12 Knowledge of surveillance procedures I Knowledge of tagging and clearance I----
22m13 procedures I
Subtotal 2 Radiation Control pertaining to licensed operator duties such as L 23m4 Knowledge of radiation exposure limits under normal or emergency conditions.
ES-40 1 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3 Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, 2.3.13 3.4 containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.
Knowledge of SRO resporrsibi/ifies in 2.4.40 4.5 98 emergency plan imp~emen fation
- 4. Knowledge of the specific bases for EOPs. 3.3 73 Emergency 2.4.18 (terminating DW spray at o psig)
Procedures I Knowledge of emergency communications 3.2 72 Plan 2m4m43 systems and techniques.
I I I I I I I
ES-401 Record of Rejected WAs Form ES-401-4 Randomly Selected Tier / Group Reason for Rejection WA 264000 / K5.05 Knowledge of the operational implications of the following concepts as they apply to (#9) Same topic as #8 (parallel of AC sources). Randomly 211 EMERGENCY selected K5.06 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 (#I 6) Double jeopardy/similar topic as #34 (system 211 SHUT-OFF ; and (b) based on those actuation logic). Randomly selected K1.03 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 (#21) System does not have related TS bases or LCOs.
211 bases in technical Randomly selected 218000 ADS.
specifications for limiting conditions for operations and safety limits.
203000 / A4.08 RHWLPCI Injection (#23) This is very similar in concept to #I 3 due to 211 Mode -Ability to manually operate and/or interrelations between reactor pressure & level regarding monitor in the control injection. Randomly selected A4.02 room: Reactor pressure 209001 I A I .05 Ability to predict and/or monitor changes in parameters associated with operating the LOW (#24) same concept as tested in question # I 3 for the RHR 211 PRESSURE CORE system. Randomly selected K4.09 SPRAY SYSTEM controls including:
Torus/suppression pool water level 214000 I K4.02 Knowledge of ROD POSITION INFORMATION SYSTEM design (#30) Could not write a discriminating question for the 2/2 feature(s) and/or topic. Randomly selected K4.01 interlocks which provide for the following:
Thermocouple ES-401 Record of Rejected KIAs Form ES-401-4 295031 / EA1. I 2 -
Ability to operate andlor monitor the following as (#21) Ability to operate plant equipment in the event of low 1/1 they apply to REACTOR RPV level is tested frequently in the operating exam.
LOW WATER LEVEL :
Feedwater Randomly selected EK3.05 295023 / AK3.02 -
Knowledge of the reasons for the following responses as they apply (#45) Refueling topic is oversampled (#29, #94). Randomly 1/1 to REFUELING selected 295037 K3.01 ACCIDENTS : Interlocks associated with fuel handling equipment 600000 / 2.2.38 Ability to analyze the effect of maintenance activities, such as
(#58) This is an SRO function at HC. Randomly selected 1/1 degraded power sources, on the status of MI.06 limiting conditions for operations.
226001 / K2.01 Knowledge of electrical power supplies to the
(#28) Not a discriminating topic at the RO level (valve 1/ 2 following: Knowledge of electrical power supplies power supply) reselected A3.03 to the following: Valves 500000 / EK2.09 Knowledge of the interrelations between HIGH CONTAINMENT (#60) Guidance is contained in SAGS for this event. Could 1/ 2 HYDROGEN not write an operational valid question for this topic at the CONCENTRATIONS the following: Drywell RO level. Randomly selected 295022 AK2.03 nitrogen purge system 215005 / 2.1.19 4PRMs -Ability to use 2/2 Dlant computers to (#26) System (Nls) & Topic oversampled (see #19).
svaluate system or Randomly selected 261000 A3.02 mnponent status.
2.1 .21 Ability to derify the controlled (#67) Topic oversampled (see #68 & #69). Randomly 3 xocedure copy. selected 2.1.4 2.2.43 - Knowledge
>f the process to track (#74) Could not write a discriminating question for the 3 noperable alarms topic. Randomly selected 2.2.13 295012 / A A 2 . 0 2 sbility to determine md/or interpref the ollowing as they apply (#83) Same WA as # 63. Randomly selected 295033 I/1 o HIGH DRYWELL EA2.0 I rEMPERA TURE :
Irywell Pressure ES-40 1 Record of Rejected WAs Form ES-401-4 295030 / 2.4.20 -
Emergency Procedures
[Pian: Knowledge of (#80) System & Topic have very limited EOP I/? operational implications of EOP warnings, notes/cautions for a discriminating question at the SRO cautions, and notes. level. Randomly selected 295026 2.7.7 (Low Suppression Pool Level) 295008 / 2.4.2 I -
Emergency Procedures 1Plan: Knowledge of the parameters and logic used to assess the status of safety functions, such as (#84) Topic did not lend itself to a discriminating SRO level I /2 reactivity control, core cooling and heat question. Randomly selected 29501 7 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.
ELEC TRlCAL DISTRIBUTION ;and (#86) Topic (DC Power) is portions of questions 3,4, I I &
(b) based on those 44. Additionally the topic does not lend itself to a 2/1 predictions. use procedures to correct, discriminating SRO level question and has very limited control. or mitigate the Procedural guidance. Randomly selected 206000 G2.2.37 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 2/2 wedictions. use (#93) Does not apply at HC. Randomly selected 2 I500 I orocedures to correct, 42.07 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 #95) Not SRO level due to operating contro1spart of KA.
3 2perating those controls ?andomly selected 2.2.7 3ssociated with plant
?quipment that could sffect reactivity.
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 Describe activity to be performed (See Note) 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
Conduct of Operations RO: 2.9 SRO: 3.9 22009 Ensure Shift is Adequately Manned (RO will exceed guidelines. Requires Authorization Form) 2.1 . I 8 Ability to make accurate, clear and concise logs, records, status boards, and reports.
RO: 3.9 SRO: 4.0 Conduct of Operations 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 Equipment Control 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 Radiation Control 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 Plan 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 ministrative Topic Type Describe activity to be performed (See Note) Code*
2.1.3 Knowledge of shift or short-term relief turnover practices Conduct of Operations 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.
Conduct of Operations 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.
Equipment Control 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 Radiation Control New: Perform Alternate RCS Leakage Determination (RMS Leak Detection Inoperable. Manually calculate from Level Transmitter mA readings given by lac)
/I Emergency Plan I
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 ( S I ; randomly selected)
(A)lternate Path
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-Facility: HoDe Creek Date of Examination: 2/2/09 Exam Level: RO SRO-I 0 SRO-U 0 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)
- b. Manually Start The Core Spray System (BE005) A, C, D, EN, L, S l 9 2
~ ~ ~
- c. Open The MSlVs With The Reactor Pressurized (>200 Psig) (AB006) 1 3
- d. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) (BC009)
- e. Respond To A Containment Isolation (SM002)
C, D, L, S l 4
- f. Perform Non-Emergency Operation Of The Diesel Generator (KJ008) l 6
- g. Respond To A Reactor Auxiliary Cooling Malfunction (ED002)
(NRC 2005)
- h. Perform Scoop Tube Positioner Lockup Operation (BB002) RO ONLY C, D, S 1 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Conduct Emergency Makeup To The RPV Using Two D, E, R 1 '
E:"
CRD Pumps (BF013)
- j. Perform Torus Makeup Via Core Spray System (BE002)
I
- Type Codes Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank 59/58/14 (E)mergency or abnormal in-plant 21 I 2 1 l b l (EN)gineered safety feature -
- I I 21 (control room system)
(L)ow-Power I Shutdown 21 I 2 1 I 2 1 (N)ew or (M)odified from bank including I(A) 2212212l (P)revious 2 exams 1 3 I 5 3 I12 (randomly selected)
(RFA 2 1121 I > 1 (S)imulator I
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-,
II Facility: Hope Creek Date of Examination: 2/2/09 Exam Level: RO 0 SRO-I SRO-U 0 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) A, C, D, EN, L, S 2
- c. Open The MSlVs With The Reactor Pressurized (>200 Psig) (AB006) C, N, S 3
- d. Place B RHR Loop In Suppression Pool Cooling From The Remote C, D, L, S 4 Shutdown Panel (RSP) (BCOO9)
- e. Respond To A Containment Isolation (SM002) A, C, N, L, S 5 I
~~
- f. Perform Non-Emergency Operation Of The Dieselenerator (KJ008) 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) D, E, R 5
@ 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 I
- Type Codes I Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank 59/18/54 (E)mergency or abnormal in-plant 2 1 I 2 1I 2 1 (EN)gineered safety feature - I- I 21 (control room system)
(L)ow-Power I Shutdown 2 1/ 2 1 / 2 l (N)ew or (M)oditied from bank including I(A) 22/22/21 (P)revious 2 exams 5 3 / 5 3 / 5 2 (randomly selected)
(R)CA 2 1I 2 1121 (S)imulator I I
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: HoDe Creek Date of Examination: 2/2/09 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 Type Code* Safety Function
=I
- a. NA
- b. Manually Start The Core Spray System (BE005) A, C, D, EN, L, S
- 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) A, C, N, L, S
- f. NA
- g. NA
- h. NA In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j. NA
- k. Transfer RPS Bus A/B Power From Alternate Source To 7
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-614-6 12-3 (C)ontrol room (D)irect from bank 19/68/<4 (E)mergency or abnormal in-plant 2 1 I2 1 / 2 1 (EN)gineered safety feature - / - / 21 (control room system)
(L)ow-Power I Shutdown 2 1 / r 112 1 (N)ew or (M)oditied from bank including I(A) 22122121 (P)revious 2 exams I3 I I3 1 5 2 (randomly selected)
(RFA 2 1 / 2 1 IZ 1 (S)imulator
Appendix D Scenario Outline Form ES-D-I I Facility: Hope Creek Examiners: J. DAntonio Scenario No.: 1 Operators:
Op-Test No.: NRC2009 FRO) 9.Fuller G. Johnson 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
Appendix D Scenario Outline Form ES-D-1 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 NIA N (BOP) Start D Circ Water Pump.
2 NIA R (RO) Raise power with control rods.
1 3 I CDIOA I C(R0) CRD Pump Trip (TS) 4 110 1A I 75 C (BOP) Rx Building Ventilation Supply Damper fails. (TS)
C (SRO) Place FRVS in service 5 TCO7A C (ALL) Trip of EHC Pump TC16 EHC Filter Clogging TC07B Manual Scram TCOI -10 Loss of EHCl TBVs fail closed 6 RP07 M (All) ATWS 7 SL04A C (BOP) A SLC Pump Auto Start Failure SLOl B 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.
Malf. Event Type* Event No. Description 1 NIA R (RO) Reduce power with control rods.
N (SRO) 2 NIA N (BOP) Swap TACS to B SACS Loop 3 RZ02A I (SRO) PT-N403A RRCS Pressure Transmitter will fail downscale. (TS) 4 CU03 RWCU leak.
CUI 1A Automatic isolation valve failure. (TS)
CUI 1B 5 TC02-1 EHC logic failure.
TC02-2 TCVs drift closed.
TC02-3 TBVs fail closed.
TC02-4 TCOl-10 6 RZ03A I (ALL) RPS and RRCS High Pressure logic failures.
RZ03C Manual Scram due to rising RPV pressure.
7 RR31B1 M (All) LOCA with downcomer failure.
RR31B2 PC04 8 PC03E C (BOP) PT-N094E/G will fail to respond to High Drywell Pressure PC03G
- * (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.: Op-Test No.: NRC2009 Examiners: J. DAntonio Operators: FRO)
B. Fuller G. Johnson 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 Event Type* Event Description I
N (BOP) Place B RFPT in service to feed the RPV.
R (RO) Raise power with recirculation flow.
N (SRO)
I 3 AD04H I (SRO) H SRV Tailpipe Temperature fails high. (TS) 4 NM12C I (RO) Recirc Loop Flow Summer failure.
5 PC07B C (BOP) Seismic Event >SSE RC09 C (SRO) RClC Steam Leak RCIO RClC Fail to Isolate (TS) 6 IAOlA C (BOP) Trip of Service Air Compressor 7 IAO1 c (RO) Air Leak w/Multiple Rod Drift/ Manual Scram CDOI 1427 C (SRO) Control Rod Drift In 14-27 CDOI 1827 Control Rod Drift In 18-27 CDO12227 Control Rod Drift In 22-27 CD062627 Control Rod Scram 26-27 8 EG12 M (All) LOP HP04 HPCl Failure DGOI C C EDG Failure to Start (Auto or Man) (recoverable)
I DG02B Failure of B EDG DG02D Failure of D EDG RR31A2 M (All) LOCA A RHR Pump Trip A EDG Trip (recoverable)
RH08C C (BOP) C RHR Failure to Auto-Startllnject I
APPENDIX D, Page 38 of 39