ML081200338
| ML081200338 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/24/2008 |
| From: | Gody A Operations Branch IV |
| To: | |
| References | |
| 50-382/08-301, W3-2008-03 | |
| Download: ML081200338 (29) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: WATERFORD 3 Date of Examination: 3/24/2008 Examination Level (circle one): @SRO Operating Test Number: 1 Adm inistrative Topic TY Pe Describe activity to be performed (see Note) Code*
2.1.23 Ability to perform specific and integrated plant Conduct of Operations procedures during all modes of plant operation.(3.9)
JPM Calculate Shutdown Margin 2.1.25 Ability to obtain and interpret station reference Conduct of Operations materials such as graphs, monographs and tables which contain performance data.(2.8)
I JPM Determine Time to SDC (Condensate Inv.)
2.2.13 Knowledge of tagging and clearance Equipment Control procedures. (3.6)
JPM Review an Equipment Clearance 2.3.11 Ability to control radiation releases(2.7)
Radiation Control JPM Complete Prerequisites For GDT Release Not selected Emergency Plan 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)imuiator,or Class(R)oom (D)irect from bank ( 5 3 for ROs; s for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (s 1; randomly selected)
(S) imu Iat or NUREG-1021, Revision 9
ES-301 Administrative ToDics Outline Form ES-301-1 Facility: WATERFORD 3 Date of Examination: 3/24/2008 Examination Level (circle one): RO /@ Operating Test Number: 1 Administrative Topic TY Pe Describe activity to be performed (see Note) Code" 2.1.25 Ability to obtain and interpret station Conduct of Operations reference materials such as graphs, monographs and tables which contain performance data.(3.1)
JPM Calculate Shutdown Margin With One Untrippable CEA 2.1.2 Knowledge of operator responsibilities Conduct of Operations during all modes of plant operation. (4.4)
JPM Determine Event Notification Requirements 2.3.1 Knowledge of tagging and clearance Equipment Control R; M procedures. (3.8)
JPM Approve an Equipment Tagout 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.(3.3)
JPM Approve Conditions For a Containment Entry at Power 2.4.44 Knowledge of emergency plan protective I
Emergency Plan action recommendations. (4.0)
JPM Determine PARS 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 (5 3 for ROs; 5 for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams ( 5 1; randomly selected)
I (S)imulator NUREG-I 021 Revision 9
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: WATERFORD 3 Date of Examination: 3/24/2008 Exam Level (circle one): RO Operating Test No.: I Control Room Systems@(8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
System I JPM Title 1 Type Code* I Safety Function
- a. 003-Start A Reactor Coolant Pump (Alternate Path) P,A,D,L,S 4-P
- b. 015-Perform NI Startup Channel Functional Test (RO ONLY) S,M,L 7
- c. 064-Start and Load B EDG From CR S,MA 6
- d. APE068-Perform BOP Immediate Actions On CR Evacuation S,M,A 8
- e. 004-Blended Makeup To VCT Using Manual Mode S,D,A 1
- f. 026-Align LPSl Pump To Replace Containment Spray Pump S,D,L 5
- g. 013-Verify SlAS Automatic Actions -Train A s, N, L, A , 2
- h. 071-Respond To Waste Gas Discharge High Activity j NS,A I 9
- i. 008-Restore Power to Dry Cooling Tower Sump Pumps During R,L,D,E 8 Control Room Evacuation and Loss of Offsite power
- k. 062-Transfer AB SUPS From Alternate To Normal Power N 6 Supply
- Type Codes Criteria for RO / SRO-I / SRO-U (A)Iternate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank 91 81 4 (E)mergency or abnormal in-plant I/ I / I (L)ow-Power / Shutdown 11 I / 1 (N)ew or (M)odified from bank including 1(A) 21 21 1 (P)revious 2 exams 3i 31 2 (randomly selected)
(R)CA I/ 11 1 (S)imulator NUREG-1021, Revision 9
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: WATERFORD 3 Date of Examination: 3/24/2008 Exam Level (circle one): SRO(I) Operating Test No.: I Control Room Systems@(8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
System I JPM Title I I Safety Function
- a. 003-Start A Reactor Coolant Pump (Alternate Path) 1 P,A,D,L,S 1 4-P b.
- c. 064-Start and Load B EDG From CR S,M,A, 6
- d. APE068-Perform BOP Immediate Actions On CR Evacuation S,M,A 8
- e. 004-Blended Makeup To VCT Using Manual Mode S,D,A 1
- f. 026-Align LPSl Pump To Replace Containment Spray Pump S,D,L 5
- g. 013-Verify SlAS Automatic Actions -Train A s, N,L, A , 2
- h. 071 -Respond To Waste Gas Discharge High Activity NS,A 9
- i. 008-Restore Power to Dry Cooling Tower Sump Pumps During R,L,D,E 8 Control Room Evacuation and Loss of Offsite power j 061-Reset EFW Pump AB Mechanical Overspeed During CR L,D,E 4-s Evacuation With Fire
- k. 062-Transfer AB SUPS From Alternate To Normal Power 6 Supply
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank 91 81 4 (E)mergency or abnormal in-plant I / 11 1 (L)ow-Power 1 Shutdown I/ I/ 1 (N)ew f r (Mjodiiied from bank including 1(A) 2i 2i 1 (P)revious 2 exams 31 3 1 2 (randomly selected)
(WCA I I I/ 1 (S)imulator NUREG-1021, Revision 9
ES-301 Control RoomAn-Plant Systems Outline Form ES-301-2 Facility: WATERFORD 3 Date of Examination: 3/24/2008 Exam Level (circle one): SRO (U) Operating Test No.: I Control Room Systems@(8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
System / JPM Title
- a. 003-Start A Reactor Coolant Pump (Alternate Path) P,A,D,L,S I 4-P b
I I C.
I I d.
e.
f.
- 9. 013-Verify SlAS Automatic Actions -Train A
- h. 071-Respond To Waste Gas Discharge High Activity N,SA 9
- i. 008-Restore Power to Dry Cooling Tower Sump Pumps During Control Room Evacuation and Loss of Offsite power l 8 I
I
t I
@ AI! 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
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lterna te path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank 91 81 4 (E)mergency or abnormal in-plant I/ I/ 1 (L)ow-Power / Shutdown I/ I/ 1 (N)ew or (M)odified from bank including 1(A) 21 21 1 (P)revious 2 exams 3/ 3 1 2 (randomly selected)
(R)CA
. . I/ I/ 1 (S)imulator NUREG-1021, Revision 9
ES-301 Transient and Event Checklist Form ES-30 1-5 Facility: Date of Exam: Operating Test No.:
A Scenarios P
P 1 2 3 4 T M L 0 I I CREW CREW CREW CREW T N C POSITION POSITION POSITION POSITION A I A L M N U T
RX RO NOR SRO-I IIC SRO-U2 MAJ TS RX RO SRO-12 IIC MAJ SRO-U TS RX R02 NOR SRO-I IIC MAJ SRO-U TS RX RO NOR SRO-I I/C MAJ SRO-U Instructions:
- 1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)"
positions; Instant SROs must do one scenario, including at least two instrument or component (VC) malfunctions and one major transient, in the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a l-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
NUREG 1021 Revision 9
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Date of Exam: Operating Test No.:
A P
P L
I C
A N
T RO SRO-I 4 1 4 1 2 SRO-U1 RO SRO-I1 SRO-U R01 SRO-I 4 1 4 1 2 SRO-U R05 SRO-l 4 1 4 1 2 SRO-U Instructions:
- 1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)"
positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a l-for-I basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
NUREG 1021 Revision 9
ES-301 Transient and Event Checklist Form ES-301-5 I Facility: Date of Exam: Ooeratina Test No.:
M I
N I
M U
T 1
RO SRO-13 4 2 ik 1 4 ~
SRO-U 2 2 1 0 2 2 1 1 0 1 1 I SRO-I "4
SRO-U SRO-I 4 1 4 1 2 SRO-U RO SRO-I 4 4 2 SRO-U ~ 2 2 r
0 2 2 Instructions:
Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)"
positions; Instant SROs must do one scenario, including at least two instrument or component (VC) malfunctions and one major transient, in the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a l-for-I basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
NUREG 1021 Revision 9
Appendix D Scenario Outline Form ES-D-1 Facility: WATERFORD 3 Scenario No.: 1 &.VI Op Test No.: NRC Examiners: Operators:
Initial Conditions: 1OO%, MOC, AB buses aligned to B side.
A EFW pump 00s for seal replacement, A ACCW pump 00s for motor pms, Condenser Air Ejector Rad Monitor 00s.
Turnover: ATrain work week with Btrain protected.
Crew is to downpower to 90% power for Grid maintenance.
Critical Task: Ensuring LPSl flow by actions to manually start B LPSI.
0 Ensuring Containment Spray flow by manual actions to open Spray header isolation valve.
RCP trip criteria during loss of sub-cooling.
RCP trip criteria on loss of CCW cooling.
Event Malf. No. Event Event Type* Description 1 R - ATC I Power reduction to 90%.
SRO N-BoP* I 2 RC19A I - ATC, Tcold input to A CPC fails LOW.
SRO TS-SRO I c-Bop*
SRO I The A CEDM Cooling fan trips on overload.
4 RC23B C - ATC, RCS leakage greater than TS limits.
SRO TS-SRO I 6
II ED05C RC23B C - ASRO TS- LL M - ALL II Loss of A 4160 Safety bus.
Large break LOCA.
I C - BOP, SRO c - BOP, B LPSl fails to auto start.
CS 1293, Containmen: Sprzj Header E IsoI, fails to auto open on SRO CSAS.
- (N)ormal, (R)eactivity, (i)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 1 tY 1 WaterFord 3 2008 NRC Scenario #I The crew assumes the shift at 100% power with instructions to reduce power to 90% for Grid maintenance.
At approximately 95% power the Tcold instrument input to the A CPC fails low. The crew bypasses affected channels IAW Technical Specification requirements.
After the affected RPS channels are bypassed the ACEDM Cooling fan trips on overload.
Starting the standby fan IAW the Off-normal procedure, OP-901-102, CEA or CEDMCS Malfunction, restores cooling flow.
When CEDM cooling has been restored an RCS leak ramping to 5 GPM to containment will be initiated. The operators should identify by leakrate indication trends or when the annunciator L-20, Containment Leakage High, annunciates. Actions are IAW OP-901-111 Reactor Coolant System Leak.
Once the crew has identified the leak and evaluated the TS implications there will be a loss of the A 4160V Safety Bus due to lockout which prevents the EDG from supplying the bus.
Actions to stabilize IAW OP-901-310, Loss of Train A Safety Bus should be carried out. The bus wili not be recovered during the scenario.
When the operators have restored CCW flows, initiated actions to rack out the faulted breakers and started to evaluate Technical specification implications then the RCS leak becomes a Large Break LOCA resulting in a Reactor trip and full ESFAS actuation.
When SIAS actuates the B LPSl pump will fail to auto start, manual actions will be successful.
When CSAS actuates CS 1258, Containment Spray Header B Isol, fails to auto open. Manual board actions to open are successful.
EOP f!owpath is OP-902-000, S?AND.ARD POS? ?R!P AC?!ONS to OP-902-002, LOSS OF COOLANT ACCIDENT RECOVERY Scenario Event Description NRC Scenario 2 1 Facility: WATERFORD 3 Scenario No.: 2 OpTestNo.: NRC Examiners: Operators:
Initial Conditions: 0 -60% power, MOC, AB buses aligned io B side.
A EFW pump 00s for seal replacement, A ACCW pump 00s for motor pm, Turnover: The A main feed pump outboard pump bearing vibration is elevated shortly after being placed in service and the crew needs to reduce power to <55%and remove the pump from service.
Critical Task: Ensuring Reactivity control post trip by actions to initiate Diverse Trip.
0 Ensuring feedwater to at least one SG utilizing Auxiliary Feedwater.
Event Malf. No. Event Event No. Type* Description 1 R - ATC Normal downpower to remove A Main feed pump from service due to high vibration.
N - BOP L MSOSB I - BOP, Steam Generator Steam Flow instrument fails HIGH.
SRO 3 Fw12A I -BOP, A Main feedwater pump vibration increases requiring manually SRO tripping 4 RD02A72 C - ALL Dropped Regulating group CEA, #72.
TS - SRO CV12A2 I - ATC, VCT level inst., VCV-ILT-0227, fails LOW.
FW03B M - ALL Second main feed pump trips, reactor fails to auto or manually trip.
Diverse Scram successful.
Fw05 C - BOP, AB EFW pump trips on overspeed, B EFW pump fails to start, SRO manual start successful.
- (N)orrnal, (R)eactivity, (I)nstrurnent, (C)ornponent, (M)ajor Scenario Event Description NRC Scenario 2 Waterford 3 2008 NRC Scenario #2 The crew assumes the shift at -60% power with elevated vibrations on the A FWPT outboard pump bearing which had just been placed in service. The crew is directed to reduce power and take the A FWPT 00s.
During the downpower the Steam Flow input to the FWCS #2 fails high requiring the ATC to take manual control of the #2 SG feedwater control.
When the reactivity manipulation has been satisfied the vibrations on the A Main feed pump worsen and require the crew to trip the pump.
After the plant is stabilized then a regulating group CEA drops into the core. OP-901-102, CEA or CEDMCS Malfunction is entered and the CEA can be recovered.
When the CEA has been recovered the VCT level instrument, CVC-ILT-0227, fails low, causing the charging pump suction to shift to the RWSP. The crew implements OP-901-113, Volume Control Tank Makeup Control Malfunction.
After the crew completes the actions for the VCT level instrument failure the B FWPT trips and the crew attempts a manual Rx trip which is unsuccessful and the crew must utilize the Diverse Reactor Trip. If the crew doesnt manually trip the auto trips are also not successful.
Post-trip the AB EFW pump trips on overspeed when started and the B EFW pump failed to auto start.
EOP flowpath is OP-902-000, STANDARD POST TRIP ACTIONS, OP-902-006, LOSS OF MAIN FEEDWATER RECOVERY.
Scenario Event Description NRC Scenario 3 Facility: WATERFORD 3 Scenario No.: 3 OpTest No.: NRC Examiners: 0perato rs:
Initial Conditions: 25% power, MOC, AB buses aligned to "B" side.
Turnover: 0 Plant startup is in progress after being off-line for 2 days.
_ I Critical Task: 0 Preventing RCS repressurization by actions to stabilize RCS temperature using the non-ESD SG.
1I 0 Isolating the SG with ESD.
I 0 0
Tripping two RCP's when SIAS actuates with low RCS pressure.
Emergency borate or actuate SIAS due to uncontrolled cooldown.
0 Controlling RCS make-up to prevent RCS overpressure.
I No.
Malf.
No.
Event TY Pe" Event Description R - ATC Raising power from 25%.
N - BOP, SRO RX14A I - ATC, Controlling Pressurizer Pressure channel fails HIGH.
SRO NlOl F I - ATC, Safety Channel B EN1 middle detector fails HIGH.
SRO TS - SRO 4 CCOl A C - BOP, "A" ccw pump trip SRO TS - SRO SGOIA C- SGTL ramp from 0 - 5 gpm over 10 minutes on SG # I .
ATC/BOP/
SRO TS - SRO MS13A M - ALL ESDE on # I SG outside containment, upstream of MSIV.
~ EGO5 C - BOP, Exciter Field Breaker fails to auto open post trip SRO
- (N)ormal, (R)eactivity, (I)nstrument, (G)omponent, (M)ajor Scenario Event Description NRC Scenario 3 Waterford 3 2008 NRC Scenario #3 The crew assumes the shift at 25% power during a plant startup from a short notice outage. The crew is to continue the startup to 100% using OP-010-004, Power Operations.
During the up-power the controlling Pressurizer Pressure channel fails high which will cause heater output to go to zero and the in-service spray valve(s) will open. Operators take action IAW OP-901-120, Pressurizer Pressure Control Malfunction to select the operable channel and reset heaters.
After pressurizer pressure has been restored then there will be a failure of Safety Channel B EN1 middle detector. Operators diagnose the failure and bypass appropriate channels IAW Technical Specifications.
When appropriate channels are bypassed there will then be a trip of the A CCW pump on overload. Restoration actions will be IAW OP-901-510, Component Cooling Water System Malfunction.
While CCW restoration actions are on-going there will be a steam generator tube leak ramp in from 0-5 gpm over -10 minutes on the #I SG. Once identified operator actions are IAW OP-901-202, Steam Generator Tube Leakage or High Activity when primary to secondary leakage is identified.
Once the crew determines the shutdown requirements of the tube leakage then an ESDE will be initiated on the #1 Steam Generator, outside containment but upstream of the MSIV. It will ramp in slowly requiring the operators to manually trip and address the uncontrolled cooldown by either Emergency boration or initiation of SIAS.
Post trip the exciter field breaker fails to open requiring manual operator action by the BOP to open.
EOP flowpath is OP 902-000, SPTAs to OP 902-008, Safety Function Recovery.
Scenario Event Description NRC Scenario 4 outline submittal rev 1 Facility: WATERFORD 3 Scenario No.: 4 OpTest No.: NRC Examiners: Operators:
Initial Conditions: e 5 % power, MOC, AB buses aligned to B side.
Turnover: 0 Plant startup in progress, no equipment 00s.
Critical Task: Ensuring HPSl availability by manually closing in B EDG breaker.
0 Ensuring HPSl flow by manually starting B HPSl pump.
0 Securing 2 RCPs with SlAS and low RCS pressure.
Securing RCPs with no seal cooling flow within 3 minutes.
Malf. No. Event Event Type* Description R ATC
~ Power increase.
N - BOP, SRO AI-04A303-1 C - ATC/ Letdown TCV fails closed in auto SRO HVOGB C - BOP, Compressor failure on B Chiller SRO TS -
SRO CVOl B C - ATC/ Running charging pump (9) trips.
SRO TS - SRO DI-02A07S19-0 C - ATC, RCP Seal Water TCV fails closed requiring manual Rx trip and SRO tripping affected RCP.
RC23A M - ALL SBLOCA w/LOOP during the trip.
ED01A-D EGl2A1 C - BOP, A EDG starts but A EDG breaker fails to close and does not EGO9A SRO manually close, B EDG fails to start, manual actions are EGO89 successful to start B EDG and it loads onto the bus.
5i02i3 2- 9 tips1 iails io auto siari. Will manuaiiy siari.
ATC/BOP
/ SRO Scenario Event Description NRC Scenario 4 outline submittal rev 1 Waterford 2008 NRC Scenario #4 The crew assumes the shift at -5% power during plant startup, MOC, with the AB busses aligned to the B side.
The crew is to continue with plant startup IAW OP-010-003 Plant Startup and OP-010-004 Power Operations.
During the preparations to raise power the Letdown TCV controiier faiis in auto causing the valve to close resulting in high letdown temperature and auto bypass of the ion exchangers.
Operator actions to take manual control are successful.
When Letdown has been stabilized the 6 Chiller fails due to compressor oil pump failure. The crew assesses, enters CCW TS actions until the AB Chiller can be aligned for operation.
After required actions are complete the running charging pump, B , trips. The crew takes actions IAW OP-901-112 Charging or Letdown Malfunction.
When charging and Letdown actions are complete the RCP 1A Seal Cooler isolation valve closes and will not reopen. The crew takes actions IAW OP-901-510 Component Cooling Water System Maifunction which wiii require the Rx and then the RCP to be tripped.
On the trip a SBLOCA develops and there is a loss of Off-Site power. The A side EDG starts but the output breaker fails to close and cannot be manually closed in by the operator. The B side EDG fails to start but will start when the operator attempts to start from the control panel and then restores power to the B safety busses.
The 9HPSl pump does not auto start and the operator must take action to manually start.
EOP flowpath- OP 9002-000, SPTAs to OP 902-002, LOCA Recovery ES-401 PWR Examination Outline Form ES-401-2 Facility: Waterford 3 2008 NRC Exam Date of Exam: 3/24/2008 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 (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA category shall not be less than two).
- 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 r t l 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 ooints.
- 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 ES-401, Attachment 2, 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, onlj, those YAs having an impodanze rating (IRj 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.
- 8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; 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
§BO-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 10CFR55.43 NUREG-1021 1
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Category I I Topic 1.
Conduct of oncise logs, '1 ,, CC Operations records, status boards, and reports.
Ability to apply technical specifications for a 2.9 67 tI - 7 L. I . I L
, 2.1.12 system.
I I I I Subtotal 2.2.25 I 2.2.18 2.
Equipment Control Subtotal I 1 3 1 1 2 I
3.
Radiation Control 1 2.3.4 2.3.9 2.3.1
- 4. Knowledge of communications procedures Emergency 3.0 74 2'4'15 associated with EOP implementation Procedures / Plan I 2.4.18 Knowledge of the specific bases for EOPs. I 2.7 75 I Subtotal Tier 3 Point Total I I 10 I 1 7 NUREG-I021 12
Tier I Randomly Reason for Rejection Grour, Selected WA 1 2/ 1 I 026 G2.4.30 I Q #13. Importance less than 2.5 for RO. Randomly reselected 026 G2.1.30 1 1 2I 1 I 013 K4.22 I Q #IO. Not applicable to facility. Randomly selected 013 K4.12 /I Q #25. No RBCCW at facility, and also topic overlap with SRO #90.
07 02 Randomly selected 076 A3.02 1 2/2 I 001 K1.09 I Q #29. No credible tie between systems. Randomly selected 001 X I .05 I Q #35. Topic selected not suitable for RO level test item. Randomly selected 212 07 A208 071 A2.05.
Q #37. Excessive selection of simple power supply topics. Randomly 212 07 K203 reselected 075 A2.03 Q #6. No LCOs or technical specifications associated with system/component.
Oo7 G2222 Randomly reselected G2.1.32 NUREG-I021 13