ML021070570
| ML021070570 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/04/2002 |
| From: | NRC/RGN-III |
| To: | |
| References | |
| 50-346/02301 | |
| Download: ML021070570 (35) | |
Text
INITIAL SUBMITTAL OF WRITTEN AND OPERATING OUTLINES, ES-201-2, AND NRC COMMENTS FOR THE DAVIS-BESSE INITIAL EXAMINATION - MARCH 2002
Davis-Besse Nuclear Power Station 5501 North State Route 2 S~Oak Harbor, Ohio 43449-9760 Guy G. Campbell 419-321-8588 Vice President - Nuclear Fax: 419-321-8337 Docket Number 50-346 License Number NPF-3 Serial Number 1-1253 November 30, 2001 Mr. M. Bielby Chief Examiner - Region III United States Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351
Subject:
Operator License Examination Outline
Dear Mr. Bielby:
Enclosed is the operator license examination outline required to support the operator license examinations being administered at the Davis-Besse Nuclear Power Station (DBNPS) during the week of March 4, 2002. This examination outline is considered confidential material and shall be withheld from public disclosure until after the scheduled operator examinations are complete.
Mr. Donald Bondy, Senior Nuclear Instructor, can respond to questions with regard to the submitted materials, at (419) 321-8275.
If you require additional information, please contact Mr. David H. Lockwood, Manager Regulatory Affairs, at (419) 321-8450.
Sincerely yours, AWB/s Enclosures cc:
D. E. Hills, Chief - Operations Branch, NRC Region III w/o S. P. Sands, DB-1 NRC/NRR Project Manager w/o D. S. Simpkins, DB-1 Senior Resident Inspector (Acting) w/o USNRC Document Control Desk w/o Utility Radiological Safety Board w/o
Docket Number 50-346 License Number NPF-3 Serial Number 1-1253 Attachment Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station in this document. Any other actions discussed in the submittal represent intended or planned actions by Davis-Besse. They are described only as information and are not regulatory commitments. Please notify the Manager - Regulatory Affairs (419) 321-8450 at Davis-Besse of any questions regarding this document or associated regulatory commitments.
COMMITMENTS DUE DATE N/A None
The following describes the method used to develop the written examination outline for Davis-Besse March 2002 Reactor Operator and Senior Reactor Operator NRC licensing examinations:
Reactor Operator Examination Outline Development
- 1. The Davis-Besse Examination Development computer program was used to randomly select the topics/evolutions that are applicable to Davis-Besse from each examination outline group.
- 2. The computer program also randomly selected the K/A category within each of the selected topics/evolutions.
- 3. The K/As within each selected K/A category, with importance numbers 2.5 or greater, were sequentially numbered. The computer program random number generator was used to select each individual K/A.
Senior Reactor Operator Examination Outline Development
- 2. Some groups in the SRO outline require a different number of questions as compared to the groups in the RO outline. For SRO groups that required K/As from additional evolutions/topics, the additional evolutions/topics for those groups were randomly selected. For SRO groups that required K/As with fewer evolutions/topics than the RO groups, the evolutions/topics were randomly de-selected.
- 3. If the additionally selected evolutions/topics for each group in the SRO outline were used in a different group within the RO outline then the K/As selected for the RO outline were used in the SRO outline.
- 4. For the remaining evolutions/topics on the SRO outline, the computer program was used to randomly select the K/A category within each of the additional selected topics/evolutions.
- 5. The K/As within each additionally selected K/A category, with importance numbers 2.5 or greater, were sequentially numbered. The computer program random number generator was used to select each individual K/A.
ES-201 Examination Outline Form ES-201-2 Quality Checklist Facility: Davis-Besse Date of Examination: March 4, 2002 Item Task Description Initials a
b*
c#
- a. Verify that the outline(s) fit(s) the appropriate model per ES-401. I DL R
- b. Assess whether the outline was systematically and randomly prepared in accordance with R
Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.
T T
- c. Assess whether the outline over-emphasized any systems, evolutions, or generic topics.
2 E
N
- d. Assess whether the justifications for deselected orrejected K/A statements are appropriate.
4
- a. Using form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, and major transients.
- 2.
- b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule S
without compromising exam integrity; ensure each applicant can be tested using at least one I
new or significantly modified scenario, that no scenarios are duplicated from the applicants; M
audit test(s)*, and scenarios will not be repeated over successive days.
- c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
- a. Verify that:
(1) the outline(s) contain(s) the required number of control room and in plant tasks, (2) no more than 30% of the test material is repeated from the last NRC examination, DT (3)* no tasks are duplicated from the applicants' audit test(s), and (4) no more than 80% of any operating test is taken directly from the licensee's exam banks.
- 3.
- b. Verify that:
(1) the tasks are distributed among the safety function groupings as specified in ES-301, 7 Q W
(2) one task is conducted in a low-power or shutdown condition, (3) 40% of the tasks require the applicant to implement an alternate path procedure, T
(4) one in-plant task tests the applicant's response to an emergency or abnormal condition, and (5) the in-plant walk-through requires the applicant to enter the RCA.
- c. Verify that the required administrative topics are covered, with emphasis on performance-based activities.
- d. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on successive days.
- 4.
appropriate exam section.
G
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
)
N
- c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
E
- d. Check for duplication and overlap among exam sections.
- e. Check the entire exam for balance of coverage.
L
-t XE 9 Printed Name / Signature Date
- a. Author
-q w_
LV4 M
mo30
- b. Facility Reviewer (*)
- Av~d
,W-.T I I Z
0 01
- c. NRC Chief Examiner (#)
ff*rAc
ý l
U1A t/
- d. NRC Supervisor D C1 J '
ý.\\%
I Note:
- Not applicable for NRC-developed examinations
- Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
NUREG-1021, Revision 8, Supplement I 23 of 24
ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Davis-Besse Date of Examination: March 4, 2002 Scenario Numbers:
1 / 2 / 3 Operating Test No.: 1 QUALITATIVE ATTRIBUTES Initials a
b*
c#
- 1.
The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but j
j it does not cue the operators into expected events.
- 2.
The scenarios consist mostly of related events.
- 3.
Each event description consists of:
the point in the scenario when it is to be initiated.
the malfunction(s) that are entered to initiate the event.
t i_
the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)
- 4.
No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
4*
- 5.
The events are valid with regard to physics and thermodynamics.
4"
- 6.
Sequencing and timing of events is reasonable, and allows the examination team to obtain complete.*( l evaluation results commensurate with the scenario objectives.
CE 4
- 7.
If time compression techniques are used, the scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
IJA UL...
- 8.
The simulator modeling is not altered.
- 9.
The scenarios have been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
- 10.
Every operator will be evaluated using at least one new or significantly modifies scenario. All other j
scenarios have been altered in accordance with Section D.4 ofES-301.
- 11.
All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form DE along with the simulator scenarios).
D__
- 12.
Each applicant will be significantly involved in the minimum number of transients and events specified on J(
Form ES-301-5 (submit the form with the simulator scenarios)."i I.
- 13.
The level of difficulty is appropriate to support licensing decisions for each crew position.
LX TARGET QUANTITIATIVE ATTRIBUTES (PER SCENARIO; SEE SECTION D.4.D)
Actual Attributes
- 1.
Total malfunction (5-8) 7/7/6
) i)./j
- 2.
Malfunctions after EOP entry (1-2) 1/3/2
{U,5 i.L/
- 3.
Abnormal events (2-4) 4/3/3
- ALA,
/1/I
- 4.
Major transients (1-2) 1/1/2
- 5.
EOPs entered/requiring substantive actions (1-2) 1 /1/1
/ IED
- 6.
EOP contingencies requiring substantive actions (0-2) 1/0/1
ý
- z, Fe
- 7.
Critical tasks (2-3) 2/3/2 2, 7 ['
24 of 26 NUREG-1021, Revision 8, Supplement 1
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
ED_
vi *d _*J rQwer
-Sttion Date of Examination:
-03=04-_02 Examination Level (circle one): RO/49)
Operating Test Number:----------J Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions A.1 Risk Summary Update Safety Monitor Risk Summary for taking MDFP out of Update service.
2.1.14 3.3 COLR/TECH Determine API in spec with alarms inoperable SPEC Utilization 2.1.11 3.8 A.2 Surveillance Perform Surveillance test for post accident panel, and determine Testing instrument out of tolerance.
2.2.12 3.4 A.3 Radiation Check out a radiation detector in the RRA Control 2.3.2 2.9 A.4 Emergency Plan Activate the Computer Automated Notification System on an Activate Cans Alert.
2.4.43 3.5 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 NUREG-1021, Revision 8 21 of 26
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
$lotion Date of Examination: _03=0_4,-.02 Examination Level (circle one):R0 SRO Operating Test Number:
Administrative Topic/Subject Description Control of Locked Valves 2.1.1 3.7 COLR/TECH SPEC Utilization 2.1.11 3.0 Describe method of evaluation:
- 2. TWO Administrative Questions Stroke timing of a Locked Valve Determine API in spec with alarms inoperable A.2 Surveillance Perform Surveillance test for post accident panel, and determine Testing instrument out of tolerance. SRO determine Tech Spec 2.2.12 requirements 3.0 A.3 Radiation Check out a radiation detector in the RRA Control 2.3.2 2.5 A.4 Emergency Plan Activate the Computer Automated Notification System on an Activate Cans Alert.
2.4.43 2.8 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 NUREG-1021, Revision 8 A.1 21 of 26
Facility: D-aYLsosNu@jclear Power Station---
Date of Examination: Q3,0_40.2.
Exam Level (circle one): RO / SRO(I) / SRO(U)
Operating Test No.:
B.1 Control Room Systems Type Safety SystemlJPM Title Code*
Function N,A,S,L 3
- a. Perform PORV Cycle Test M,S,L 2
- c. Energize 4.16kv bus D2 from the SBODG N,S 1
- d. Borate the Makeup Tank using attach 13 of DB-OP 02000.
D,A,S 7
- e. Trip an RPS Channel
- f. Start CTMT Purge on the penetration rooms N,S 8
D,A,S 2
- g. Manually Trip SFAS B.2 Facility Walkthrough D,R 2
- a. Primary Side Reactor Operator actions inside the RRA for Serious CTRM fire D
4
- b. Line up BUSW pmp to Service Water Secondary D
8
- c. Loss of a TPCW pump NUREG-1021, Revision 8
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA 22 of 26
Appendix D Scenario Outline Form ES-D-1 Facility: Davis Besse Scenario No.: 1 Op-Test No.: 1 Examiners:---------
Operators:
Initial Conditions: _e Turnover: Rui
_4.A_Circuump_operati Event ]
Event Event No.
Type*
Description 1
N (ROS)
Start Circ. Water Pump 3 2
CT-03-4C C (ROS)
Circ. Water Pump 3 Discharge Valve fails to open 3
RCS-10-12 I (ROP)
T-Hot input to SCM meter fails high 4
SG-06 I (ROS)
SG1 Startup level instrument midscale failure 5
MUP 12-1 C (ROP)
Makeup Pump 1 trip 6
MUP 12-2 C (ROP)
Makeup Pump 2 electrical fault 7
AC-06-2 C (All)
Dl bus lockout 8
R (ROP)
Power reduction 9
RCS-02-4 M (All)
Small break LOCA, loss of SCM 4
.4
+
- 4
.4 4
.4
-4 39 of 40 NUREG-1021, Revision 8, Supplement 1
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: Davis Besse Scenario No.: 2 Op-Test No.: 1 Examiners:---------
Operators:--------------------------
Initial Conditions: _5_oPAw
_2 1_Q sci...
TrvrIces4ert-(ml-to-p-...------------------------------------------------------------
Turnover:
nrae Qw LQ..
O bn s
eila c
esn.C W
u p2 Event Event Event No.
Type*
Description 1
R (ROP)
Add water to the Makeup Tank 2
N (ROP)
Start CCW Pump 3 for surveillance test 3
MFW 14-3 I (ROS)
MFW Control Valve delta pressure instrument fails low 4
MUP-16 I (ROP)
Seal Injection Flow Instrument fails low 5
CCW-08 C (All)
CCW System leak 6
CRD-04 C (ROP)
ATWS 7
AFW-02 C (ROS)
AFPT 1 overspeed trip 8
AFW-09 C (ROS)
MDFP Target Rock Valve fails open 9
MS-06 M (All)
Main Steam Safety Valve fails open, overcooling of the RCS I
+
+
39 of 40 NUREG-1021, Revision 8, Supplement 1
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: Davis Besse Scenario No.: 3 Op-Test No.: 1 Examiners:---------
Operators:
Initial Conditions: Moc2,2%_QLe JDtupJnpcgT sMEP.2_QUkPS Turnover:
Event MlfN Event Event No.
Type*
Description 1
N (ROS)
Transfer from Motor Driven Feed Pump to MFP 1 2
R (ROP)
Increase power to 5%
3 SG-04 I (ROS)
SG2 pressure instrument fails high 4
MUP-17 I (ROP)
Makeup Tank level instrument fails low 5
SG-01 C (All)
SG1 tube leak 6
AC-02 M (All)
Loss of off-site power 7
SW-07 C (ROP)
Service Water Pump 1 fails to auto start 8
SFRCS-02 C (ROS)
SFRCS fails to automatically actuate 9
SG-01 C (All)
SG1 tube rupture
+
4-4-
39 of 40 NUREG-1021, Revision 8, Supplement 1
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
ES-301 Simulator Scenario Quality Checklist Form ES-301-6 Applicant #1 Applicant #2 Applicant #3 RO/SRO-I/SRO-U RO/SRO-I/SRO-U RO/SRO-I/SRO-U Competencies SCENARIO SCENARIO SCENARIO 1
2 3
4 1
2 3
4 1
2 3
4 4,5, 3,4, 3,4, 4,5, 3,4, 3,4, 4,5, 3,4, 3,4, Understand and Interpret 6,7, 5,7 5,6, 6,7, 5,7 5,6, 6,7, 5,7 5,6, Annunciators and Alarms 898989 8
9 8
9 8
9 Diagnose Events 2,3, 3,4, 3,4, 2,3, 3,4, 3,4, 2,3, 3,4, 3,4, and Conditions 4,5, 5,6, 5,6, 4,5, 5,6, 5,6, 4,5, 5,6, 5,6, 6,7 7,8, 7,8, 6,7, 7,8, 7,8, 6,7, 7,8, 7,8, 9
9 8
9 9
8 9
9 Understand Plant and 2,3, 3,4, 3,4, 2,3, 3,4, 3,4, 2,3, 3,4, 3,4, Udstan plnt 4,5, 5,6, 5,6, 4,5, 5,6, 5,6, 4,5, 5,6, 5,6, System Response 6,7 7,8, 7,8, 6,7 7,8, 7,8, 6,7 7,8, 7,8, 9
9 9
9 9
9 Comply With and 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 3,4, 3,5, 4,5, 3,4, 3,5, 4,5, 3,4, 3,5, 4,5, Use Procedures(I) 5,6, 6,7, 6,7, 5,6, 6,7, 6,7, 5,6, 6,7, 6,7, 7,8, 9
9 7,8, 9
9 7,8, 9
9 9
9 9
Operate Control 1,2, 1,2, 1,2, 1,2, 1,2, 1,2, 4,5, 3,4, 3,4, 4,5, 3,4, 3,4, Boards (2) 6,8 5,6, 5,7, 8
5,6, 6,7, 7,8, 8,9 7,8 8,9 9
Communicate and Interact 1,2, 3,4, 1,2, 1,2, 3,4, 1,2, 1,2, 3,4, With the Crew 3,4, 5,6, 3,4, 3,4, 5,6, 3,4, 3,4, 5,6, 5,6, 7,8, 5,6, 5,6, 7,8, 5,6, 5,6, 7,8, 7,8 9
7,8, 7,8, 9
7,8, 7,8, 9
9 9
9 9
1,2, 3,4, 2,3, 1,2, 3,4, 2,3, Demonstrate Supervisory 3,4, 5,7, 4,5, 3,4, 5,6, 4,5, Ability (3) 5,6, 8,9 7,8, 5,6, 7,8, 7,8, 7,8, 9
7,8, 9
9 9
9 Comply With and 5,6, 5
5,6, 5
Use Tech. Specs. (3) 7 Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
Circle the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
Author:
J.6\\ -- C C6 NRC Reviewer:
hrA, -
e~ &,/P 9,/ & tk,
~
i NUREG-1021, Revision 8, Supplement 26 of 26 I
ES-301 Transient and Event Checklist Form ES-301-5 OPERATING TEST NO.:
Applicant Evolution Minimum Scenario Number Type Type Number 1
2 3
4 Reactivity 1
1 1
1 Normal 1
1 1
1 RO Instrument /4 6
6 6
Component Major 1
1 1
1 Reactivity 1
1 1
1 Normal 0
0 1
0 As RO Instrument /
2 3
2 2
Component Major 1
1 1
1 SRO-I Reactivity 0
1 1
1 Normal 1
1 1
1 As SRO Instrument /
2 6
6 6
Component Major 1
1 1
1 Reactivity 0
1 1
1 Normal 1
1 1
1 SRO-U Instrument /
2 6
6 6
Component Major 1
1 1
1 Instructions:
Author:
NRC Reviewer:
(1)
Enter the operating test number and Form ES-D-1 event numbers for each evolution type.
(2)
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.
(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 requirement.
C -
25 of 26 NUREG-1 021, Revision 8, Supplement 1
ES-401 PWR SRO Examination Outline Form ES-401-3 Facility: Davis-Besse Date of Exam: March 4, 2002 Exam Level: SRO K/A Category Points Point Tier Group K
K K ýK 6K K
JA 1A 1A A G
Total 1
I I I12 3
4 5
6 1 2 3
4
- 1.
1 2
4 5
34 7
24 Emergency &
Abnormal 3
1 1
1 3
Plant Evolutions Tier 6otal 8
9 6
43 Totals 1
4 1
1 3 112 1
3 1
2 0
19
- 2.
2 2
1 2
2 1
2 2
1 2 1
17 Plant 3
1 1
1 4
Systems Tier 612 3
5 3 3
3 6
2 5 2
40 Totals
- 3. Generic Knowledge and Abilities Cat I Cat 2 Cat 3 Cat 4 17 5
4 4
l 4
Note:
- 1.
Ensure that at least two topics from every K/A category are sampled within each tier (i.e.,
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 +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
- 3.
Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4.
Systems/evolutions within each group are identified on the associated outline.
- 5.
The shaded areas are not applicable to the category/tier.
6.*
The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
- 7.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance rating for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
NUREG-1021, Revision 8, Supplement 1 26 of 46
ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions -Tier I/Group 1 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000001 Continuous Rod Withdrawal / 1 1
AA2.04-Reactor power trend 4.3 1
000003 Dropped Control Rod /1 1
1 AK2.05-CRD power supplies/AK3.03-Turbine auto 2.8/3.7 2
runback 000005 Inoperable/Stuck Control Rod / 1 1AK.03-Xenon transient 3.6 1
000011 Large Break LOCA / 3 EK2.02-Relationship with pumps 2.7 1
000015/17 RCP Malfunctions / 4 1
AK3.0 1-High bearing/winding temps 3.1 1
BW/E09; CE/A13; W/E09&E10 Natural Circ.
1 EK3.4-Procedure adherence, teamwork 3.8 1
000024 Emergency Boration / 1 1
AK3.01-Emergency boration 4.4 1
000026 Loss of Component Cooling Water /8 1
A3.04-Effects on loss of CCW 3.7 1
000029 Anticipated Transient w/o Scram / 1 1
EA2.05-System component valve position indication 3.4 1
000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture 1
EA 1.1-Components function of safety system 4.2 1
- Excessive Heat Transfer / 4 000051 Loss of Condenser Vacuum / 4 1
GEN2.4.8-Knowledge of event based vs symptom 3.7 1
based 000055 Station Blackout/6 EA1.02-Manual ED/G start 4.4 1
000057 Loss of Vital AC Elec. Inst. Bus / 6 1
AA2.1 1-MFP running indicator and controller 3.0 1
000059 Accidental Liquid Radwaste Rel. / 9 1
AA2.04-Valve lineup for release 3.5 1
000062 Loss of Nuclear Service Water / 4 1
AA2.06-Time after loss until component damage 3.1 1
000067 Plant Fire On-Site / 9 1
AA1.09-Plant fire zone panel 3.3 1
000068 (BW/A06) Control Room Evac. / 8 1
GEN2.4.5-Knowledge of organization of operating 3.6 1
procedures 000069 (W/El4) Loss of CTMT Integrity / 5 AK1.01-Effect of pressure on leak rate 3.1 1
000074 (W/E06&E07) Inad. Core Cooling / 4 1
EK2.06-Knowledge between ICC and TBV/AVVs 3.6 1
BW/E03 Inadequate Subcooling Margin / 4 1
1 EA1.1-Components/functions control and safety 3.8/4.0 2
system./EA2.02-Adherence to procedure 000076 High Reactor Coolant Activity / 9 1
AK2.01-Process Rad monitor 3.0 1
BW/A02&A13 Loss of NNI-X/Y / 7 AA2. 1-Selection of appropriate procedures 4.0 1
FK/A Category Totals:
I2 J4 I5 j4 7
[2
[Group Point Total:
24 NUREG-102 1, Revision 8, Supplement 1 27 of 46
ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions -Tier I/Group 2 E/APE # / Name / Safety Function KI K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000007 (BW/E02&E10; CE/E02) Reactor Trip -
1 EKl.1-Component, capacity, and function 4.0 1
Stabilization - Recovery /1 BW/AO1 Plant Runback / 1 1
GEN-2.1.30-Ability to locate/operate controls 3.4 1
BW/A04 Turbine Trip / 4 1
GEN-2.4.7-Knowledge of event based EOP 3.8 1
000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 1
EK2.03-S/Gs 3.3 1
BW/E08; W/E03 LOCA Cooldown - Depress.
4 1
EK2.1-Components,and function of control and safety 3.9 1
systems W/El 1 Loss of Emergency Coolant Recirc. / 4 000022 Loss of Reactor Coolant Makeup / 2 1
AK3.07-Isolating charging 3.2 1
000025 Loss of RHR System / 4 AKI.01-Loss of RHR all modes 4.3 1
000027 Pressurizer Pressure Control System Malfunction / 3 000032 Loss of Source Range NI / 7 1
AA2.06-Confimation of reactor trip 4.1 1
000033 Loss of Intermediate Range NI 7 AK3.02-Guidance in EOP for loss of Intermediate 3.9 1
range NIs 000037 Steam Generator Tube Leak / 3 1
AA 1.11-PZR level indication 3.3 1
000038 Steam Generator Tube Rupture / 3 1
EA1.27-Steam dump valve status lights 3.9 1
000054 (CE/E06) Loss of Main Feedwater / 4 1
AK3.02-Matching feedwater and steam flows 3.7 1
BW/E04; W/E05 Inadequate Heat Transfer - Loss of EKi1.3-Annunciator condition,indication,and remedial 4.0 1
Secondary Heat Sink / 4 action 000058 Loss of DC Power / 6 GEN 2.1.29-Knowledge of how to conduct/verify 3.3 1
valve lineups 000060 Accidental Gaseous Radwaste Rel. /9 1
AA1.02-Ventilation system 3.1 1
000061 ARM System Alarms / 7 W/E 16 High Containment Radiation / 9 000065 Loss of Instrument Air / 8 AA2.01-Cause and effect of low pressure alarm 3.2 1
CE/E09 Functional Recovery K/A Category Point Totals:
I3 2 J 3 I31213 Group Point Total:
-16 NUREG-1021, Revision 8, Supplement 1 28 of 46
ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions -Tier 1/Group 2 E/APE # / Name / Safety Function KI K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000007 (BW/E02&EI1; CE/E02) Reactor Trip -
EK1.1-Component, capacity, and function 3.6 1
Stabilization - Recovery /1 BW/AOI Plant Runback /
1 GEN-2.1.30-Ability to locate/operate controls 3.4 1
BW/A04 Turbine Trip / 4 1
GEN-2.4.7-Knowledge of event based EOP 3.8 1
000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 1
EK2.03-S/Gs 3.3 1
BW/E08; W/E03 LOCA Cooldown -Depress. /4 1
EK2. 1-Components,and function of control and safety 3.9 1
systems W/EI I Loss of Emergency Coolant Recirc. / 4 000022 Loss of Reactor Coolant Makeup / 2 AK3.07-Isolating charging 3.2 1
000025 Loss of RHR System / 4 AK1.01-Loss of RHR all modes 4.3 1
000027 Pressurizer Pressure Control System Malfunction / 3 000032 Loss of Source Range NI / 7 AA2.06-Confimation of reactor trip 4.1 1
000033 Loss of Intermediate Range NI / 7 1
AK3.02-Guidance in EOP for loss of Intermediate 3.9 1
range NIs 000037 Steam Generator Tube Leak / 3 1
AA1.11-PZR level indication 3.3 1
000038 Stear Generator Tube Rupture /3 1
EA1.27-Steam dump valve status lights 3.9 1
000054 (CE/E06) Loss of Main Feedwater / 4 1
AK3.02-Matching feedwater and steam flows 3.7 1
BW/E04; W/E05 Inadequate Heat Transfer-Loss of EKi1.3-Annunciator condition, indication,and remedial 4.0 1
Secondary Heat Sink / 4 action 000058 Loss of DC Power / 6 1
GEN 2.1.29-Knowledge of how to conduct/verify 3.3 1
valve lineups 000060 Accidental Gaseous Radwaste Rel. / 9 AA1.02-Ventilation system 3.1 1
000061 ARM System Alarms / 7 W/E 16 High Containment Radiation / 9 000065 Loss of Instrument Air/8 AA2.0 1-Cause and effect of low pressure alarm 3.2 1
CE/E09 Functional Recovery K/A Category Point Totals:
3 2
3 3 3 2
3 Group Point Total:
16 NUREG-1021, Revision 8, Supplement I I
28 of 46
ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions -Tier 1/Group 3 E/APE # / Name / Safety Function KI K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000028 Pressurizer Level Malfunction / 2 000036 (BW/A08) Fuel Handling Accident! 8 000056 Loss of Off-site Power/ 6 AK1.03-Use of steam table for SCM 3.4 1
BW/E13&E14 EOP Rules and Enclosures 1
GEN-2.4.39-Knowledge of E-Plan responsibility 3.1 1
BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 1
AA1.2-Behavior of facility 3.0 1
CE/A16 Excess RCS Leakage / 2 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5
[KlACategory Point Totals:
1 1 1
]
1 I Group Point Total:
[ 3 NUREG-1021, Revision 8, Supplement 1 29 of 46
ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System #/Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 001 Control Rod Drive 1
1 K5.56-Determining SCM/A4.15-Stop 4.6/3.1 2
boron dilution I
I K4. 11-Isolation valve interlocks/A2.05-3.0/2.8 2
Effects of VCT on seals 004 Chemical and Volume Control K6.07-Heat exchanger and condenser 2.8 1
013 Engineered Safety Features Actuation I
K 1. 12-ED/Gs/A4.02-Reset of SFAS 4.4/4.4 2
014 Rod Position Indication 015 Nuclear Instrumentation 1
1 K6.02-Discriminating/comp circuitlA3.02-2.9/3.9 2
Alarm signals 017 In-core Temperature Monitor K3.01-Natural circ indication 3.7 1
022 Containment Cooling I
K4.04-Cooling of CRDMs 3.1 1
025 Ice Condenser 026 Containment Spray 056 Condensate K1.03-MFW/A2.04-Loss of pumps 2.6/2.8 2
059 Main Feedwater I 1 K4.13-FW fill of SG loss of RCP/A1.07-2.9/2.6 2
FW pump speed control 061 Auxiliary/Emergency Feedwater K2.02-Electric driven pump 3.7 1
063 DC Electrical Distribution 061 liquid Diste A2.04-Failure of automatic isolation 3.3 1
068 Liquid R adw aste I_
T t
f1
_0 - e o e 1K1.05-Met tower 2.81 071 Waste Gas Disposal 1
K1.04-CTRM ventilation 3.5 1
072 Area Radiation Monitoring
[K/ACategory PointTotals:
4 1
[
1[3 1
2 1 13 1 12
[0 GroupPointTotal:
1 19 NUREG-1021, Revision 8, Supplement 1 30 of 46
ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 System # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 002 Reactor Coolant 1
A4.03-Indication/control/recognition 4.4 1
and correct saturated conditions 006 Emergency Core Cooling I
K5.01-Effects of temp on water level 3.3 indication 010 Pressurizer Pressure Control I
K4.03-Over pressure control 4.1 1
011 Pressurizer Level Control A4.04-Transfer to manual 2.9 1
012 Reactor Protection 1
A1.01-Trip setpoint adjust 3.4 1
016 Non-nuclear Instrumentation I
A2.04-Voltage too HI or LOW 2.6 1
027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge Al.03-CTMT press/temp/humidity 3.3 1
033 Spent Fuel Pool Cooling K1.02-RHRS 2.7 1
034 Fuel Handling Equipment 035 Steam Generator 039 Main and Reheat Steam K1.05-TG 2.6 1
055 Condenser Air Removal K3.01-Main condenser 2.7 1
062 AC Electrical Distribution A3.04-Operation of inverters 2.9 1
064 Emergency Diesel Generator K3.03-ED/G manual loads 3.9 1
073 Process Radiation Monitoring K5.02-Rad intensity change 3.1 1
075 Circulating Water K2.03-Emer/essen SWS pumps/GEN-2.7/2.6 2
2.1.26-Knowledge of non-nuclear safety related procedures 079 Station Air A2.01-Crossconnect w IA system 3.2 1
086 Fire Protection K6.04-Fire/smoke/heat detectors 2.9 1
103 Containment
[K/ACategory PointTotals:
2 2
l 2
[1 12 2 [
]2 I [ GroupPointTotal:
[
17 NUREG-1021, Revision 8, Supplement 1 31 of 46
ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 3 System#/Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 005 Residual Heat Removal 007 Pressurizer Relief/ Quench Tank 1
A2.05-Exceeding PRT pressure limit 3.6 1
008 Component Cooling Water 041 Steam Dump/Turbine Bypass Control A4.08-Steam dump valves 3.1 1
045 Main Turbine Generator GEN-2.4.50-Verify alarm/operate ctrls 3.3 1
076 Service Water 078 Instrument Air K4.02-Crossover to other air system 3.5 1
K/A Category Point Totals:
I1 1
Group Point Total:
4 Plant-Specific Priorities Summary / Topic Recommended Replacement for...
Reason Points
.1.
1 I
t t
i 1
SII__
i i
I_
1 I.
I-I.
Plant-Specific Priority Total: (limit 10)
NUREG-1021, Revision 8, Supplement 1 i
i I
32 of 46
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-5 Facility: Davis Besse Date of Exam: March 4, 2002 Exam Level: S Category K/A #
Topic Imp.
Points 2.1.03 Knowledge of shift turnover 3.4 1
2.1.17 Ability to make accurate/clear/concise verbal 3.6 1
report Conduct of 2.1.19 Ability to use plant computer to obtain and 3.0 1
Operations evaluate data 2.1.27 Knowledge of system purpose and function 2.9 1
2.1.11 Knowledge of one hour Tech Spec actions 3.8 1
Total 5
2.2.12 Knowledge of surveillance procedures 3.4 1
2.2.27 Knowledge of refueling process 3.5 1
Equipment 2.2.33 Knowledge of CRD programming 2.9 1
Control 2.2.05 Knowledge of making changes in facility as 2.7 1
described in the SAR 2.2.
Total 4
2.3.1 Knowledge of 10CFR20 and related facility 3.0 1
radiation controls 2.3.10 Ability to perform procedures to reduce radiation 3.3 1
2.3.11 Ability to control radiation releases 3.2 1
Radiation Control 2.3.05 Knowledge of use and function of personnel 2.5 1
monitoring equipment 2.3.
2.3.
Total 4
2.4.09 Knowledge of low power/shutdown implication 3.9 1
2.4.26 Knowledge of facility fire protection requirements 3.3 1
Emergency 2.4.39 Knowledge of RO responsibilities in E-Plan 3.1 1
Procedures/
Plan 2.4.43 Knowledge of emergency communication system 3.5 1
2.4.
Total 4
Tier 3 Point Total (RO/SRO) 13/17 NUREG-1021, Revision 8, Supplement I 40 of 46
ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Davis-Besse Date of Exam: March 4, 2002 Exam Level: RO Tier Group K/A Category Points Point K K 6K A ýA JA JA G Total 1______ 2_____3__
4 5
6 1J2 3
4j
- 1.
1 1
3 4
2 4
2 16 Emergency &
2 3
2 3
2 4
3 17 Abnormal31 Plant 3
3 Evolutions Tier 5
5 7
5 8
6 36 Totals 6
36 I
I I
1T4tals3 112 11 3 12 3
1 23
- 2.
2 2
1 3
2,2 1
2 2
2 2
1 20 Plant 11 1
1 1
1 1
8 Systems______
S s e sT ier 7 i 2 6
6 1 3 4
3 6
5 6
3 51 Totals I
- 3. Generic Knowledge and Abilities Cat I Cat 2 Cat 3 Cat 4 13 4
3 3
l 3
Note:
- 1.
Ensure that at least two topics from every K/A category are sampled within each tier (i.e.,
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 +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
- 3.
Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4.
Systems/evolutions within each group are identified on the associated outline.
- 5.
The shaded areas are not applicable to the category/tier.
6.*
The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
- 7.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance rating for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
NUREG-1021, Revision 8, Supplement 1 33 of 46
ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions -Tier I/Group 1 E/APE # / Name / Safety Function KI K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000005 Inoperable/Stuck Control Rod / 1 1
000015/17 RCP Malfunctions / 4 1
AK3.01-Hi bearing/winding temp 2.5 1
BW/E09; CE/A3; W/E09&EIO Natural Circ. / 4 1
EK3.4-Procedure adherence, teamwork 3.8 1
000024 Emergency Boration / 1 1
AK3.0 1-Emergency boration 4.1 1
000026 Loss of Component Cooling Water / 8 1
AK3.04-Effects on loss of CCW 3.5 1
000027 Pressurizer Pressure Control System I
AK2.03-Controllers and positioners 2.6 1
Malfunction / 3 000040 (BW/E05; CE/E05; W/E 12) Steam Line Rupture I
EA 1.1-Components, function of safety system 4.2 1
- Excessive Heat Transfer / 4 CE/Al1; W/E08 RCS Overcooling - PTS / 4 000051 Loss of Condenser Vacuum / 4 GEN 2.4.8-Knowledge event based vs symptom 3.0 1
based 000055 Station Blackout/6 EA1.02-Manual ED/G start 4.3 1
000057 Loss of Vital AC Elec. Inst. Bus / 6 1
AA2.1 I-MFP running indicator and controller 2.9 1
000062 Loss of Nuclear Service Water / 4 1
AA2.06-Time after loss until component damage 2.8 1
000067 Plant Fire On-Site / 9 000068 (BW/A06) Control Room Evac. / 8 GEN-2.4.5-Knowledge of organization of operating 2.9 1
procedures 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 1
EK2.06-Knowledge between ICC and TBV/AVVs 3.5 1
BW/E03 Inadequate Subcooling Margin / 4 1
EA2.02-Adherence to procedures 3.5 1
000076 High Reactor Coolant Activity / 9 1
AK2.01-Process Rad monitor 2.6 1
BW/A02&A03 Loss of NNI-X/Y / 7 1
AA2. I-Selection of appropriate procedures 3.6 1
K/A Category Totals:
Group Point Total:
16 NUREG-1021, Revision 8, Supplement 1 34 of 46
ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions -Tier 1/Group 2 E/APE # / Name / Safety Function KI K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000001 Continuous Rod Withdrawal / 1 1
AA2.04-Reactor power trend 4.2 1
000003 Dropped Control Rod/ 1 000007 (BW/E02&EI0; CE/E02) Reactor Trip - Stabilization -
1 EKll-Component, capacity and function 3.6 1
Recovery / 1 BW/A01 Plant Runback / I 1
GEN-2.1.30Ability to locate/operate controls 3.9 1
BW/A04 Turbine Trip / 4 1
GEN-2.4.7-Knowledge of event based EOP 3.1 1
000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 1
EK2.03-S/Gs 3.0 1
000011 Large Break LOCA / 3 1
EK2.02-Relationship with pumps 2.6 1
W/E04 LOCA Outside Containment / 3 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 W/E II Loss of Emergency Coolant Recirc. / 4 W/EOI & E02 Rediagnosis & SI Termination /3 000022 Loss of Reactor Coolant Makeup / 2 1
AK3.07-Isolating charging 3.0 1
000025 Loss of RHR System / 4 1
AK1.01-Loss of RHR during all modes 3.9 1
000029 Anticipated Transient w/o Scram / 1 1
EA2.05-System component valve position indication 3.4 1
000032 Loss of Source Range NI / 7 1
AA2.06-Confirmation of Reactor trip 3.9 1
000033 Loss of Intermediate Range NI / 7 1
AK3.02-Guidance in EOP for loss of Intermediate range NIs 3.6 1
000037 Steam Generator Tube Leak / 3 000038 Steam Generator Tube Rupture / 3 1
EA1.27-Steam dump valve status lights 3.9 1
000054 (CE/E06) Loss of Main Feedwater / 4 1
AK3.02-Matching feedwater and steam flows 3.4 1
BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary 1
EK1.3-Annunciator condition, indication, and remedial 4.0 1
Heat Sink / 4 action 000058 Loss of DC Power / 6 1
GEN-2.1.29-Knowledge of how to conduct/verify valve 3.4 1
lineups 000059 Accidental Liquid Radwaste Rel. / 9 1
AA2.04-Valve lineup for release 3.2 1
000060 Accidental Gaseous Radwaste Rel. / 9 1
AA1.02-Vetilation system 2.9 1
000061 ARM System Alarms / 7 W/E 16 High Containment Radiation / 9 CE/E09 Functional Recovery K/A Category Point Totals:
3 2
3 2
4 3
Group Point Total:
17
~
~
TY TD/
1Ai1D..
0
.1-1 UIU i.i
'vsusaupemnI
%J_
-1Y-1, ReikVslion 8, Supplement I
ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions -Tier I/Group 3 E/APE # / Name / Safety Function KI K2 K3 Al A2 G
K/A Topic(s)
Imp.
Points 000028 Pressurizer Level Malfunction / 2 000036 (BW/A08) Fuel Handling Accident! 8 000056 Loss of Off-site Power / 6 AK1.03-Use of steam table for SCM 3.1 1
00065 Loss of Instrument Air / 8 BW/E13&E14 EOP Rules and Enclosures 1
GEN-2.4.39-Knowledge of E-Plan responsibility 3.3 1
BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 1
AAI.2-Behavior of facility 2.8 1
CE/A16 Excess RCS Leakage / 2 W/E 13 Steam Generator Over-pressure / 4 W/E 15 Containment Flooding / 5 t
i i
i i-i I
1
+/-
I I
I I
I I
J
+/- ____
I I
I I
I I
1 4
- 4. ____
I I
I I
I I-
1 4
1 I
I I
I I
1 1
4 1
1 I
I-I I
F I
1 1
I I
I I
- l i
i i
i F
i*
I I
NUREG-1021, Revision 8, Supplement 1 K/A Category Point Totals:
I 1 1 1
1
[ Group Point Total:
3 36 of 46
ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 001 Control Rod Drive 1
1 1
K5.56-Determining SCM/A4.15-4.2/3.1/
3 Stopboron dilution/GEN-2.1.33-Ability to 3.4 recognize entry into Tech Specs 003 Reactor Coolant Pump K4.1 1-Isolation valve interlocks/A2.05-3.0/2.5/
3 Effects of VCT on seals/A4.08-RCP 3.2 cooling water supplies 004 Chemical and Volume Control K6,07-Heat exchanger and condenser 2.7 1
013 Engineered Safety Features Actuation K 1.12-ED/Gs/A4.02-Reset of SFAS 4.1/4.3 2
015 Nuclear Instrumentation I
K6.02-Discriminating/comp 2.6/3.7 2
circuits/A3.02-Alarm signals 017 In-core Temperature Monitor K3.01-Natural circ indications 3.5 1
022 Containment Cooling I
K4.04-Cooling of CRDMs/A3.01-2.8/4.1 2
Initiation of safeguards 025 Ice Condenser 056 Condensate 1
KI.03-MFW/A2.04-Loss of pumps 2.6/2.6 2
059 Main Feedwater K3.03-S/Gs/K4.13-FW fill of SG loss of 3.5/2.9 3
RCP/Al.07-FW pump speed control 2.5 061 Auxiliary/Emergency Feedwater K2.02-Electric driven pump 3.7 1
068 Liquid Radwaste I
A2.04-Failure of automatic isolation 2.7 1
1K 1.05-Met tower 2.7 1
071 Waste Gas Disposal 1
1K 1.04-CTRM ventilation 3.3 1
072 Area Radiation Monitoring K/A Category Point Totals:
4 1 [2 3
1 2
1!
3 2
3 1
Group Point Total:
23 NUREG-1021, Revision 8, Supplement 1 37 of 46
ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group
]
System#/Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/ATopic(s)
Imp.
Points 001 Control Rod Drive I1 1
K5.56-Determining SCM/A4.15-4.2/3.1/
3 Stopboron dilution/GEN-2.1.33-Ability to 3.4 recognize entry into Tech Specs 003 Reactor Coolant Pump IK4.11I-Isolation valve interlocks/A2.05-3.0/2.5/
3 Effects of VCT on seals/A4.08-RCP 3.2 cooling water supplies 004 Chemical and Volume Control K6.07-Heat exchanger and condenser 2.7 1
013 Engineered Safety Features Actuation I
Kl.12-ED/Gs/A4.02-Reset of SFAS 4.1/4.3 2
015 Nuclear Instrumentation K6.02-Discriminating/comp 2.6/3.7 2
circuits/A3.02-Alarm signals 017 In-core Temperature Monitor K3.01-Natural circ indications 3.5 1
022 Containment Cooling K4.04-Cooling of CRDMs/A3.01-2.8/4.1 2
Initiation of safeguards 025 Ice Condenser 056 Condensate KI.03-MFW/A2.04-Loss of pumps 2.6/2.6 2
059 Main Feedwater K3.03-S/Gs/K4.13-FW fill of SG loss of 3.5/2.9 3
RCP/A1.07-FW pump speed control 2.5 061 Auxiliary/Emergency Feedwater K2.02-Electric driven pump 3.7 1
068 Liquid Radwaste A2.04-Failure of automatic isolation 3.3 1
1K1.05-Met tower 2.71 071 Waste Gas Disposal 1
1K1.04-CTRM ventilation 3.3 1
072 Area Radiation Monitoring K/A Category Point Totals:
4 1
2 3
1 12 1
13
]2 13 1
Group Point Total:
23 NUREG-1021, Revision 8, Supplement 1 I
37 of 46
ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 002 Reactor Coolant 1
A4.03-Indication/control/recognition 4.3 1
and correct saturated conditions 006 Emergency Core Cooling I
K5.01-Effects of temp on water level 2.8 indication 010 Pressurizer Pressure Control I
K4.03-Over pressure control 3.8 1
011 Pressurizer Level Control 1
A4.04-Transfer to manual 3.2 1
012 Reactor Protection 1A 1.01-Trip setpoint adjust 2.9 1
014 Rod Position Indication I
GEN-2.1.21-Obtain/verify procedure 3.1 1
016 Non-nuclear Instrumentation A2.04-Voltage too HI or LOW 2.5 1
026 Containment Spray K3.02-Recirc spray system 4.2 1
029 Containment Purge Al.03-CTMT press/temp/humidity 3.0 1
033 Spent Fuel Pool Cooling Kl.02-RHRS 2.5 1
035 Steam Generator 1
A3.01-SG water level control 4.0 1
039 Main and Reheat Steam K1.05-TG 2.5 1
055 Condenser Air Removal K3.01-Main condenser 2.5 1
062 AC Electrical Distribution 1
A3.04-Operation of inverters 2.7 1
063 DC Electrical Distribution K4.02-Breaker interlock 2.9 1
064 Emergency Diesel Generator K3.03-ED/G manual loads 3.6 1
073 Process Radiation Monitoring 1
K5.02-Rad intensity change 2.5 1
075 Circulating Water K2.03-Emer/essen SWS pumps 2.6 1
079 Station Air 1
A2.01-Crossconnect w/ IA system 2.9 1
086 Fire Protection1 K6.04-Fire/smoke/heat detectors 2.6 1
[K/A Category Point Totals:
2 1
3 2
12 I
12 12 2
2 1
Group Point Total:
20 NUREG-1021, Revision 8, Supplement 1 38 of 46
ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 System #/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
K/A Topic(s)
Imp.
Points 005 Residual Heat Removal 1
K6.03-Loss of heat exchanger 2.5 1
007 Pressurizer Relief/Quench Tank 1
A2.05-Exceeding PRT pressure limit 3.2 1
008 Component Cooling Water I
K3.03-RCP 4.1 1
027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 034 Fuel Handling Equipment 041 Steam Dump/Turbine Bypass Control A4.08-Steam dump valves 3.0 1
045 Main Turbine Generator I
GEN-2.4.50-Verify alarm/operate ctrls 3.3 1
076 Service Water Kl.01-CCW System 3.4 1
078 Instrument Air K4.02-Crossover to, other air system 3.2 1
103 Containment A3.01-CTMT isolation 3.9 1
K/A Category Point Totals:
1 1
1 1
1 1
1 1
Group Point Total:
8 Plant-Specific Priorities Summary / Topic Recommended Replacement for...
Reason Points I.
L _____
i I.
I F
I I
+
4.
i
+
-I I
+
- 1.
i
+
I.
1
- 4.
.1 I __________
NUREG-1021, Revision 8, Supplement 1 i
i I
F'F"nII-SpectIcI lPrlwlty I Otal: kuit lllI.0) 39 of 46
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-5 Facility: Davis Besse Date of Exam: March 4, 2002 Exam Level: RO Category K/A #
Topic Imp.
Points 2.1.03 Knowledge of shift turnover 3.0 1
2.1.17 Ability to make accurate/clear/concise verbal 3.5 1
report Conduct of 2.1.19 Ability to use plant computer to obtain and 3.0 1
Operations evaluate data 2.1.27 Knowledge of system purpose and function 2.8 1
2.1.
Total 4
2.2.12 Knowledge of surveillance procedures 3.0 1
2.2.27 Knowledge of refueling process 2.6 1
2.2.33 Knowledge of CRD programming 2.5 1
Equipment Control 2.2.
2.2.
2.2.
Total 3
2.3.1 Knowledge of 10CFR20 and related facility 2.6 1
radiation controls 2.3.10 Ability to perform procedures to reduce radiation 2.9 1
Radiation 2.3.11 Ability to control radiation releases 2.7 1
Control 2.3.
2.3.
2.3.
Total 3
2.4.09 Knowledge of low power/shutdown implication 3.3 1
2.4.26 Knowledge of facility fire protection requirements 2.9 1
Emergency 2.4.39 Knowledge of RO responsibilities in E-Plan 3.3 1
Procedures/
Plan 2.4.
2.4.
Total 3
Tier 3 Point Total (RO/SRO) 13/17 NUREG-1021, Revision 8, Supplement 1 40 of 46
Davis-Besse Outline Review NRC Comments/ LIC Response 12/5/01 WRITTEN:
- 1. NRC: What computer program do you use to randomly select KAs?
LIC: Skyscraper program developed by the site.
- 2. NRC: Were any KAs suppressed/rejected?
LIC: No, except for the KAs in the Catalog that are not designated for B&W.
(Not applicable questions: Were justification statements prepared? Were KAs suppressed/rejected/justified on a case-by-case basis? Which ones? Why? How many? We need to review the suppressed/rejected/justified KA information.)
ADMIN JPMs:
- 1. Make sure the admin JPMs have significant, verifiable consequences such that if they are performed incorrectly, the task cannot be successfully completed. For example, key control does not appear to have significant consequence of incorrectly performed.
- 2. NRC: RO A.la), Control of Locked Valves, Stroke Timing of a Locked Valve; 2.1.1, Knowledge of conduct of operations requirements (41.10, 45.13). a) What is involved with this admin JPM? This appears to be equipment control and probably belongs under A.2, however; I am willing to accept if you get a more appropriate KA, such as 2.1.29, Knowledge of how to conduct and verify valve lineups; or 2.1.20, Ablility to execute procedural steps.(CHANGE KA or R EPLACE A. Ia) for RO?)
LIC: Emphasis is on the required paperwork that needs to be filled out and approved for performance of the surveillance on a locked valve.
NRC: KA appears appropriate based on licensee response. Review the JPM in more detail once exam is received.
- 3. NRC: SRO A.la), Risk Summary Update, Update Safety Monitor Risk Summary for taking MDFP out of service; 2.1.14, Knowledge of system status criteria which require the notification of plant personnel (43.5, 45.12). a) Is information obtained from a computer? b) I would prefer that this admin JPM require the SRO to evaluate equipment out of service and make a determination that it is too risky to take this piece of equipment out of service. '(REVISE A.1a for SRO?)
LIC: Information is obtained from a computer. There is equipment initially OOS, the SRO must input the information, then evaluate the output information and determine if the equipment can be taken OOS.
- 4. NRC: SRO/RO A.lb), COLR(core operating limits requirements)/TECH SPEC Utilization, Determine API (axial power imbalance) in spec with alarms inoperable; 2.1.11, Knowledge of conduct of operations requirements (41.10, 45.13). a) Is this appropriate for an RO? Need an admin JPM that discriminates between SRO and RO tasks. Would be OK if RO has some procedural actions to take. Then it would be appropriate for the SRO to review the actions taken and verify the applicable tech spec LCO, or the like. REVISE A.
i b) for SRORO?
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Davis-Besse Outline Review NRC Comments/ LIC Response 12/5/01 LIC: RO required to identify problem based on printout, and notify the SRO. The SRO is required to review the information and identify the correct TS LCO requirement.
.(REVERSE RO and SRO A.2 OUTLINE WIRIT'EUP)'
LIC: Will review and fix.
- 6. NRC: SRO/RO A.3, RADIATION CONTROL, Check out a radiation detector in the RRA; 2.3.2, Knowledge of facility ALARA program (41.12, 43.4, 45.9/10). a) The JPM does not appear to match the KA. b) Does the JPM have significant, verifiable consequences such that if they are performed incorrectly, the task cannot be successfully completed? Are there procedural requirements for checking out the rad detector? c) Does the admin JPM task discriminate between SRO and RO? d) (REPLACE A.3 for SRO, and RO(?))*
LIC: Operators are required to perform checks on the detectors. Will pick a more appropriate KA.
- 7. NRC: SRO/RO A.4, Emergency Plan, Activate the Computer Automated Notification System (CANS) on an ALERT; 2.4.43, Knowledge of emergency communications systems and techniques (45.13). a) This is ok for RO, but not SRO. Would prefer to have the SRO make a classification and PARS recommendation. (REPLACE A.4 for SRO)
LIC: This is a new process. There are applicable RO and SRO parts to it.
OPERATING JPMs:
General: Want alternate path JPMS to follow guidance in Appendix C, ie, procedurally driven (ARPs or ABNs are good), completes the task or mitigates the problem without reliance on actions by other control room operators...
- 1. I need to review a list of audit exam JPMs (to verify none of those JPMs are repeated on the NRC exam).
- 2. NRC: Replace either B.1.b or B.1.g. Ref: ES-301, D.3.a, "..AI of the systems and evolutions in each subcateaory of the test shou IId Ibe selected from different safety function.
lists, and the same system or evolution should not be u~sed to evaluate more than on,e safety function in each suboateg'ory."
LIC: Will look at and replace.
SCENARIOS:
Scenario 1:
- 1. NRC: Events 5 and 6, are parts of one event (loss of makeup pumps). As such, they can only be counted as one failure.
LIC: Will review.
- 2. Only one failure after the MT, want additional failures so recovery is not straight forward and predictable.
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Davis-Besse Outline Review NRC Comments/ LIC Response 12/5/01 Scenario 2:
- 1. NRC: Events 5, 6, 7, 8, why are these component failures? Can the systems be recovered through proper operator actions and used to mitigate plant conditions (ie, CCW system leak stopped, rods successfully inserted, AFPT1 recovered and used for level control, Target Rock Valve closed) If not, they are probably enhancements to the MT.
LIC: CCW leak gives procedural actions to take. Rods can be inserted. AFPT doesn't auto start, must be manually started. MDFP valve has to be isolated.
Scenario 3:
- 1. NRC: Event 7, what is significance of SW Pump 1 failing to auto start?
LIC: Have to manually start.
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