ML071550444
| ML071550444 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/31/2005 |
| From: | Gody A NRC Region 4 |
| To: | Edington R Nebraska Public Power District (NPPD) |
| References | |
| 50-298/05-302, ES-401, ES-401-1 50-298/05-302 | |
| Download: ML071550444 (12) | |
Text
II Facilitv Coooer Date of Exam: October 2005 Ensure that at least two topics from every applicable K/A category are sampled within each tier of tlie RO and SRO-only outlines (i,e., except for one category in Tier 3 of tlie SRO-only outline, the Tier Totals in each IUA catego!-y shall not be less I 2.
than two)
Thc point total for each group and tier in the proposed outline must match that specilied i n the table.
The final point total for cach group and tier may deviate by il 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. Systeins/evolutions within each group are identified on the associated outline; systeins or evolutions that do not apply at the iacility should be deleted and justified; operationally important, site-specific system that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
- 4. Select topics froin as inany system and evolutions as possible; sample every system or evolution in the group befoi-e selecting a second topic for any system or evolution.
- 5. Ahsent a plant-specific priority, only those K/As having an importance I-ating (In) of2.5 01- higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectivcly.
- 6. Select SRO topics for Tiers 1 and 2 fiom tlie shaded systems and K/A categories
- 7. 1:
The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the IUA Catalog, but the topics intist be relevant to the applicable evolution or system.
- 8. On the following pages, enter the IUA numbers, a brief description of each topic, the topics importance ratings (IRs) for tlie applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
- 9. Poi- Tier 3, select topics from Section 2 ofthe KIA catalog, and enter the IUA numbet-s, dcscriptions, IRs, and point totals (#)
on Form ES-401-3. Limit SRO selections to IUAs that are linlted to I O CFR 55.43. 1 1
I ES-401 BWR Exaiiiination Outline For111ES-401-1 IYAI'I: # / Name / Safety Function I< K I< A A G KIA Topic(s) IR #
1 2 3 1 2 295001 Partial or Complete Loss of Forced X AKI .O1 Knowledge o f the operational implications of the 2.5 1 C'ol-e I , h w (Circulation / I 614 following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : Natural Circulation (CFR: 41.8 to 41. IO) 205003 Partial or Complete Loss of AC'/ 6 X AK3.05 Knowledge of the reasons for the following responses 3.7 2 as they apply to PARTIAL OR COMPLEI'E LOSS OF A.C.
POWER : Reactor- SCRAM (CFR: 41 .S / 45.6) 205004 Pal-tial or Total Loss of DC Pwr / 6 X AK3.03 Knowledge ofthe reasons for the following responses 3.1 3 as they apply to PARTIAL OR COMPLETE LOSS OF D.C.
POWER : Reactor SCRAM: Plant-Specific (CFR: 41.5 /
45.6) 205005 Main Turbine Generator Trip / 3 X 2.4.49 Ability to perform without I-eferenceto procedures tliose 4.0 4 actions that require iminediate operation of system components and controls. (CFR: 41 . I O / 43.2 / 45.6) 295006 SC'RAM / 1 X AA2.05 Ability to determine and/or interpret the following as 4.6 5 they apply to SCRAM :Whether a reactor SCRAM has occurred. (CFR: 41.10/43.5/45.13) 29501 6 Control Room Abandonment / 7 X AK3.01 Knowledge ofthe reasons for the following responses 4.1 6 as they apply to CONTROL ROOM ABANDONMENT :
Reactor SCRAM (CFR: 41 .S / 45.6) 20501 X Partial or Total Loss of CCW / 8 X AK3.04 Knowledge of the reasons for the following responses 3.3 7 as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :Starting standby ptiiiip (CFR: 41.5 / 45.6) 2950 I 9 Pal-tial or Total Loss of Inst. Air / 8 X 2.4.4 Ability to recognize abnormal indications for system 4.0 8 operating parameters which are entry-level conditions for emergency and abnormal operating procedures. (CFR: 41 . I O /
43.2 /45.6)4.3 20502 I Loss of Shutdown Cooling / 4 X AA1.05 Ability to operate and/or iiioiiitor the following as they 3.1 9 apply to LOSS OF SHUTDOWN COOLING :Reactor recirculation (CFR: 41.7 / 45.6) 295023 Rel'ueling Acc / 8 X AIC2.03 Knowledge of the intei-relations bctween REFUELING 3.4 10 ACCIDENTS and the following: Radiation monitoring equipment.
295024 High Dt-ywell Pressure / 5 X EK2.13 Knowledge of the interrelations between HIGH 3.8 11 DRYWELL PRESSURE and the Ihllowing: Suppression pool spray: Plant-Specific (CFR: 41.7 / 45.8) 295025 I-ligli Reactor Pi-essure/ 3 X EA2.04 Ability to detei-mine and/or interpret the following as 3.9 12 they apply to 1-IIGH REACTOR PRESSURE:Stippression pool level (CFR: 41. I O / 43.5 / 45.13) 205026 Suppression Pool High Water X EK3.01 Knowledge ofthe reasons for the following responses 3.8 13
'remp. / 5 as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:Etiiergency/noriiialdepressurization. (CFR:
41.5 /45.6) 2
I ES-40 I BWR Exainiiiation Outline Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (RO)(Continued)
Form ES-401-1 UAPr # i Name / Safety Function KIA Topic(s) 1R IEKI .01 Knowledge of the operational implications ofthe following concepts as they apply to HIGH DRYWELL TEMPERATURE : Reactor water level measurement (CFR:
41.8 to 41.10) 205030 Low Suppression Pool Wtr I v l / 5 EA2.02Ability to detel-mine and/or inteipret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL
- Suppression pool temperature (CFR: 41. I O / 43.5 / 45.1 3) 205030 L o w Suppression Pool Wtt Lvl / 5 EAI.06 Ability to operate and/or monitor the following as they apply to LOW SUPPRESSJON POOL WATER LEVEL:
Coiideiisate storage and ti-ansfer (make-up to the suppression pool): Plant-Specific (CFR: 41.7 / 45.6) 2.1.30 Ability to locate and ope!-atecomponents / including 3.9 local controls. (CFR: 41.7 / 45.7) 205017 SCRAM Condition Present and 2.4.31 Knowledge ofannunciatoi-s alarms and indications / and 3.3 Powci Above APRM Downscale oi use of the response insti-uctions. (CFR: 41. I O / 45.3)
EAI.06 Ability to operate and/or monitor the following as they 3.5 apply to HIGH OFF-SITE RELEASE RATE : Plant ventilation. (CFR: 41.7 / 45.6)
I 600000 Plant Fire On Site / 8 AK2.04 Knowledge of the intei-relations between PLANT FIRE ON SITE and the fol1owing:Brealters irelays /and 2.5 disconnects I I</A (ategoiy Totals: GPOLIP Point Total 3
4 I!S-401 BWR Examination Outline Form ES-40 1-1 Emergeiicy and Abnormal Plant Evolutions - Tier l/Gro~ip2 (RO) f / A P E # / N a m e / Safety Fuiiction K/A Topic(s) IR #
205002 Loss of Main Condcnser Vac / 3 2.1.14 ICiiowledge of system status criteria which 2.5 21 require the notification of plant pel-sonnel. (CFR: 43.5 /
45.12)
I 205007 High Reactor Pressure /3 I I 295008 I-Iigh Reactor Watci Lcvel / 2 I 205009 Low Reactor Water Level / 2 AK2.03 Knowledge ofthe interrclations between LOW 3.1 22 REACTOR WATER LEVEL and thc following:
Recirculation system. (CFR: 41.7 / 45.8) 20501 0 High Drywell Press~ire/ 5 X AKI .01 Knowledge of the operational implications of 23 the following concepts as they apply to HIGH DRYWELL PRESSURE : Downcomer submergence:
Mark-l&II(CFR: 41.8 to 41.10) 2050 14 Inadvertent Reactivity Addition / 1 AK3.01 Knowledge of the 1-easonsfor the following 24 responses as they apply to INADVERTENT REACTIVITY ADDITION: Reactoi- SCRAM (CFR:
41.5 / 45.6) 29501 5 Incomplete SCRAM / I 20501 7 High Off-site Release Rate / 9 205020 Inadvertent Cont Isolation / 5 & 7 2.4.50 Ability to verify system alarm setpoints and 3.3 25 operate coiitrols identified in the alai-in response manual.
(CFR: 45.3)
I 2"l22 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl/ 5 EA2.03 Ability to detei-mine and/or inteipret the 3.4 26 following as they apply to HIGH SUPPRESSION POOL WATER LEVEL :Di-ywell/contaiiiinent water level (CFR:41.10/43.5/45.13) 205032 High Secondary Containment Area Radiation Levels / 9 205034 Secondary Containment Ventilation High Radiation / 9 5
ES-401 BWR Examination Outliiie Form ES-401.1 Emergency and Abnormal Plant Evolutions - Tier I/Group 2 (RO)(continued)
IYAPE # / Nainc / Safety Function I< IC K A A G WA Topic(s) IR #
1 2 3 1 2 295035 Secondary Containment High X EAl. Ability to operate and/or monitor the following as 3.8 27 L)il'i'erential Pressure / 5 they apply to SECONDARY CONTAINMENT I-IIGH DlFFERENTlAL PRESSURE: SBGTiFRVS (CFR:
41 .I 145.6) 205036 Secondary Conlainmenl High SunipiArea Water Level / 5 500000 High CTMT I-lydrogen Conc. / 5 I<iA Category Totals: 1 I 1 1 I 2 G ~ O LPoint I ~ Total 7 6
I S-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plaiit Evolutions - Tier ~ / G ~ o2 L(SRO)
I~
I / A P P # /Name / Safety Function G I</A Topic(s)
I AA2.05 Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION : tViolatioii of safety IitnitsJCFR: 41.10i43.5 145.13) 2.4.6 Knowledge syniptom based EOP mitigation EA2.02 Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION : Cause of high radiation levels (CFR:41.10/43.5/45.13) 1 Group Point Total 7
I 1 I ES-40 1 BWR Examination Outline Plant Systems - Tier 2/Group 1 (RO)
Form ES-401-1 I
Systeni#/Name System#/Name < IC </A Topic(s) 1 2 3 203000 IIIIWLPCI: Injection 41 .OSAbility to predict and/or monitor changes Mode n paraiiieters associated with operating the III-IR/LPCI: INJECTION MODE (PLANT 5PECIFIC) controls including: -'[Emergency
- enel-ator loading (CFR: 41 .5 / 45.5)
X 1K3.01 I<nowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following: Reactor pressure (CFR: 41.7 / 45.4) 2.1.23 Ability to perfot-in specific system and integrated plant procedures during different modes ofplant operation. (CFR: 45.2 / 45.6)
X K2.02 Knowledge of electrical power supplies Lo the following: System pumps: BWR-2,3,4 (CFR: 41.7)
Sce 200001 LPCS A4.1 1 Ability to manually operate and/or monitor in the control room: System flow (C'FR: 41.7 / 45.5 to 45.8)
A3.01 Ability to monitor automatic operations ofthe STANDBY LIQUID CONTROL SYSTEM including: Pump discharge pressure:
Plant-Specific (CFR: 41.7 / 45.7)
X K4.03 I<nowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or interloclts which provide for thc following: The prevention of supplying power to a given RPS bus from multiple sources simultaneously (CFR: 41.7)
A l . 04 Ability to predict and/or monitor 34 35 changes in parameters associated with opet-ating the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM controls including: Control rod block status (CFR: 41 .5
/ 45.5)
X K5.01 Knowledge of the operational 26 36 implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM : Detectoi-operation (CFR: 41 .5 / 45.3)
A4.05 Ability to manually operate and/or 31 37 tiionitor in the control rooin: SRM back panel switches, meters, and indicating lights (CFR:
41.7 / 45.5 to 45.8) 8
5-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier ~ / G ~ o1 L(KO)(Continucd)
I~
iystem#/Name </A Topic(s) IR Y
! I5005 APRM I LPRM (4.02 ICiiowledge of AVERAGE POWER 4.1 38 RANGE MONITOR/LOCAL POWER RANGE UONITOR SYSTEM design feature(s) a d o r interlocks which provide for the fo1lowing:Reactor SCRAM signals (CFR:
41.7)
I I7000 KCIC K6.01 ICnowledge ofthe effect that a loss or 3.4 39 tiialf~inctionof the following will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) : Electrical power (CFR:
41.7 145.7) 2 I8000 ADS K4.03 l<nowledge of AUTOMATIC 3.8 40 DEPRESSURIZATION SYSTEM design feature(s) and/or interloclis which provide for the following: ADS logic control (CFR: 41.7)
~~~ ~~~
223002 PCISAkicleai AI .01 Ability to predict and/or monitor 3.5 41 5tenmsLlpply Shutoff changes in parameters associated with ope!-ating the PRIMARY CONTAINMENT ISOLATION SYSTEMINUCLEAR STEAM SUPPLY SHUT-OFF controls including:
System indicating lights and alarms (CFR: 41.5
/ 45.5) 230002 SRVs K1.07 Knowledge ofthe physical connections 3.6 42 and/or cause effect relationships between RELIEF/SAFETY VALVES and the following:
Suppression pool (CFR: 41.2 to 41.9 I 45.7 to 45.8) 230007 SRVs K2.01 IGiowledge of electrical power supplies 2.8 43 to the following: SRV soleiloids (CFR: 41.7)
~~ ~~~ ~ -
250007_ Reactor Watei 1CG.03 I<nowledge of the effect tliat a loss or 3.1 44 LcvelConti ol malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM : Main steam flow input (CFR: 41.7 145.7) 201 000 SGTS K6.01 ICnowledge ofthe effect that a loss or 2.9 45 malfunction of the ibllowiiig will have on the STANDBY GAS TREATMENT SYSTEM :
A.C. electrical distribution (CFR: 41.7 145.7) 26200 1 AC Electrical Distribulion 2.4.4 Ability to recognize abnormal indications 4.0 46 for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures. (CFR: 41.10 /
43.2 145.6) 20200 I AC Electrical Distribution A3.02 Ability to monitor automatic operations 3.2 of the A.C. ELECTRICAL DISTRIBUTION including: Automatic bus transfer (CFR: 41.7 /
45.7) 9
ES-40 I BWR Examination Outline ForI11 ES-401-1 Plant Systems - Tier 21Group 1 (RO)(Contioued)
System#/Name IR
~~~
262002 UPS (AC/DC) A2.01 Ability to (a) predict the impacts ofthe 2.6 48 following on the UNINTERRUPTABLE POWER SUPPLY (A.C.1D.C.); and (b) based on those predictions, L I S procedures
~ to correct, control, or mitigate the consequences of ...:
(CFR: 41.5 / 45.6) Undei-voltage (2.612.8) 263000 DC ElectricalDistribution A2.02 Ability to (a) pi-edictthe impacts ofthe 2.6 49 following on the D.C. ELECTRICAL LIISTRIBUTION ;and (b) based on those predictions, use procedures to correct, control, 01- mitigate the consequences of those abnormal conditions or operations: Loss of ventilation during charging (CFR: 41.5 / 45.6) 264000 EDGs K5.06 Knowledge of the operational 3.4 50 implications of the ibllowiiig concepts as they apply to EMERGENCY GENERATORS (DIESEUJET) : Load sequencing (CFR: 41.5 /
45.3) 300000 Instrument Air IC1 .04 Knowledge ofthe connections and / or 2.8 51 cause effect relationships between INSTRUMENT AIR SYSTEM and the following: Cooling water to compressor (CFR:
41.2 to41.9/45.7 to45.8) 400000 Component CoohngWatei K3.01 Knowledge of the effect that a loss or 2.9 52 malfunction oE the CCWS will have on the Ibllowing: (CFR: 41.7 / 45.6) Loads cooled by CCWS 400000 Component CoolmgWatei- A4.01 Ability to manually operate and / or 3.1 53 monitor in the control I-oom:(CFR: 41.7 / 45.5 to 45.8) A4.01 CCW indications and control I</A C'alegory Point Totals:
- 26 10
ES-401 Record of Rejected K/As Form ES401-4 Tier/ Randomly Reason for Rejection Group Selected K/A RO 1/1 295005 G2.1.23 Generic K/A without applicability to the evolution.
RO 1/1 295015 G2.1.27 Generic K/A without applicability to the evolution.
RO 1/1 295037 G2.4.30 Low RO importance (<2.5) with no related plant priority.
RO 2/1 215005 K4.03 Low RO importance (<2.5) with no related plant priority.
RO 2/1 217000 K6.02 Low RO importance (<2.5) with no related plant priority.
RO 2/1 400000 K5.01 Low RO importance (<2.5) with no related plant priority..
SRO 2/1 203000 A2.15 Loop Select Logic not used at CNS.
SRO 2/1 206000 G2.1.28 No associated plant SRO task and no link to a 10 CFR 55.43 topic for 206000 G2.1.28.
SRO2/1 211000 G2.1.30 No associated plant SRO task and no link to a 10 CFR 55.43 topic for 211000 G2.1.30.
RO 2/2 233000 A3.01 Low RO importance (<2.5) with no related plant priority.
RO 2/2 241000 K3.01 Low RO importance (<2.5) with no related plant priority.
RO 2/2 286000 K1.02 Low RO importance (<2.5) with no related plant priority.
SRO 2/2 259001 G2.1.28 No associated plant SRO task and no link to a 10 CFR 55.43 topic for 259001 G2.1.28.
RO 3 2.1.4 Low RO importance (<2.5) with no related plant priority.
RO 3 2.1.13 Low RO importance (<2.5) with no related plant priority.
RO 3 2.2.3 Cooper Nuclear Station is a single unit facility.
RO 3 2.2.20 Low RO importance (<2.5) with no related plant priority.
RO 3 2.2.10 Low RO importance (<2.5) with no related plant priority.
RO 3 2.2.15 Low RO importance (<2.5) with no related plant priority.
RO 3 2.3.8 Low RO importance (<2.5) with no related plant priority.
RO 3 2.3.7 Low RO importance (<2.5) with no related plant priority.
SRO 3 2.2.4 Cooper Nuclear Station is a single unit facility.
RO1/1 295001.AK1.04 Cooper Nuclear Station procedures no longer require operator action based on cycle oscillations for loss of forced circulation flow. Randomly selected AK1.01 as replacement.
RO2/1 239002.K1.08 Could not develop a psychometrically valid question for this K/A. This relationship is intuitive for even non-licensed operators. Any question developed would likely be of difficulty 1 and not provide any level of discrimination between the competent and non-competent candidate.
Randomly reselected K1.07 as its replacement.
RO2/1 262002.A2.02 Could not develop a psychometrically valid question that would include both parts of the K/A. Randomly reselected A2.01 as its replacement.
RO2/2 286000.A2.12 Could not develop a psychometrically valid question. Any question developed would likely be of difficulty 1 and not provide any discrimination. Randomly reselected A2.07 as its replacement.
SRO1/1 295004 G2.4.50 Could not develop a SRO Only question for operation of controls in the Alarm Response Manual as it applied to a loss of DC. Randomly Reselected 2.4.30 as its replacement.
SRO1/1 295005.AA2.01 Could not develop a SRO only question for a turbine trip and the ability to interpret turbine speed. Randomly reselected 295005.AA2.06 as its replacement.
RO2/2 268000.K1.06 Could not develop a psychometrically valid question with a difficulty of greater than 1. Randomly reselected 268000.K1.09 as its replacement.
RO2/2 272000.A4.04 Could not develop a psychometrically valid question with a difficulty of greater than 1. Randomly reselected 272000.A4.06 as its replacement.
SRO1/1 2.1.32 Could not develop a SRO only question for a procedure precaution and limitations for High Drywell Pressure.
Randomly reselected 2.4.30 as its replacement.