ML042190026
| ML042190026 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/19/2004 |
| From: | Wilson M Dominion Nuclear Connecticut |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-423/04-301 50-423/04-301 | |
| Download: ML042190026 (29) | |
Text
ES-301 Operating Test Quality Checklist Form ES-30 1 -3 Facility: Millstone Unit 3 Date of Examination: 19 - 23 July 2004 Operating Test Number: One (I
I
- 1. GENERAL CRITERIA Q
Q
' 6 07
- a.
The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).
There is no day-to-day repetition between this and other operating tests to be administered during this examination.
The operating test shall not duplicate items from the applicants' audit test(s)(see Section D.l.a).
Overlap with the written examination and between different parts of the operating test & e g e ~ ~ ~
is within acceptable limits.
It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.
- b.
C.
- d.
- e.
- 2. WALK-THROUGH-CRITERIA I
- a.
Each JPM includes the following, as applicable:
initial conditions initiating cues reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time critical by the facility licensee
- references and tools, including associated procedures
. specific performance criteria that include:
- detailed expected actions with exact criteria and nomenclature
- system response and other examiner cues
- statements describing important observations to be made by the applicant
- criteria for successful completion of the task
- identification of critical steps and their associated performance standards
- restrictions on the sequence of steps, if applicable Q
eb.
Repetition from operating tests used during the previous licensing examination is within acceptable limits (30% for the walk-through) and do not compromise test integrity.
6c.
At least 20 percent of the JPMs on each test are new or significantly modified.
Q
- 3. S I M U L A T O R W CRITERIA
- a.
The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.
Printed N a p /mt&
Date W
- b. Facility Reviewerr)
- c. NRC Chief Examiner (#)
- d. NRC Supervisor C. h ) d NOTE:
- The facility signature is not applicable for NRC-developed tests.
- Independent NRC reviewer initial items in Column "c;" chief examiner concurrence required.
ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Millstone Unit 3 Date of Exam: 19 - 23 July 2004 Scenario Numbers: 1 I 2 / 3 Operating Test No.: One I
II I
,Initials QUALITATIVE ATTRIBUTES TARGET QUANTITATIVE AlTRIBUTES (PER SCENARIO; SEE SECTION D.9;BS.d)
I Actual Attributes I I - I --
ES-301 Transient and Event Checklist Form ES-301-5 OPERATING TEST NO.: One Ap licant QYPe RO As RO I
Reactivity I
I r
1 1
3 4 s, 9' 7
instructions: (1)
(2)
(3)
Author:
NRC Reviewer:
Enter the operating test number and Form ES-D-I event numbers for each evolution type.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.45.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 one-for-one basis.
Whenever practical, both instrument and component malfunctions should be included; only those th e verifiable actions that provide insight to the applicant's c t toward the minimum requirement.
ES-301 Competencies Checklist Form ES-301-6 BOP-&k&&& -
SCENARIO Notes:
(I)
Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
t numbers that will allow the examiners to evaluate every applicable competency for every applicant.
NRC Reviewer:
OUTLINE COMMENTS Written Exam Overall, the written outline received from the licensee on May 5h appeared to meet expectations.
Some general feedback was provided on May 20th per telecom.
0 0
0 0
0 Tier 1/Grp 1, 00007. Be careful not to test at too basic a level for this topic.
There are a number of basis type questions on the outline make sure this area isnt over sampled and the questions are written at an appropriate level.
Tier 1/Grp2, 000024. Emergency Boration ability to prioritize and interpret significance of annunciators. Be careful annunciators already tested extensively on the operating exam.
For TS SRO questions make sure not direct look-up - make somewhat challenging.
For SRO questions make sure not just testing system knowledge.
Note: Feedback provided late to the licensee due to impact of OC exam and resolution of 12 post exam comments.
ODeratinq Exam (Draft In-house Comments)
JPMs 0
0 0
0 0
The following JPMs do not appear to meet the criteria for Alternate Path (i.e., for procedurally driven - see Appendix C section C.2 procedurally driven) b, d, e, g, and j.
This obviously needs be resolved before submittal to the licensee for review (minimum 4 required).
The new JPMs do not meet Appendix C criteria for task standards (Le., see Appendix C, sect. 8.3, Develop Performance Criteria). Get with the licensee during pre-validation if not before and fix JPM format - see specific comments for each JPM as marked.
During pre-validation, please have licensee assist in determining suggested pre-grouping of JPMs for administration. This can be verified during validation week with the exam team present.
Make sure all involved licensee personnel are signed onto the security agreement during pre-va I id at i o n week.
Check with licensee on freezing of procedures for exam in regards to our exam material development. During pre-validation visit verify that we are referencing all the latest revisions to procedures for our exam material and that this wont change before exam administration.
Dominions.,
D Dominion Nuclear Connecticut, Inc.
hlillsrone Power Srarion Rope Ferr). Road Waterford, CT 06385 MAY 32004
- Mr. Richard Conte, Chief Serial No.
04-21 5 Operational Safety Branch, Region I MPS Lic/KD RO U.S. Nuclear Regulatory Commission Docket No.
50-423 475 Allendale Road License No.
NPF-49 King of Prussia, PA 19406 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 REACTOR OPERATOR AND SENIOR OPERATOR INITIAL EXAMINATIONS In accordance with NUREG-I 021 Examination Standard 201 -1, Draft Revision 9, this letter transmits the examination outlines for the Millstone Unit No. 3 Initial Reactor Operator and Senior Operator written examinations (Attachment 1 ).
Pursuant to 10 CFR 55.40(b)(3), an authorized representative of the facility has approved the outlines contained in Attachment I prior to their submittal. It is our belief that the enclosed materials are complete and ready-to-use.
Consistent with the guidance contained in NUREG-I 021 Examination Standard 201,, the examination outline transmitted herein should be withheld from public disclosure until after the examination has been completed. No redacted versions are being supplied.
L Should you have any questions regarding this submittal, please contact Mr. Trad A. Horner at (860) 437-2569.
Very truly yours, Suite President - Millstone
Serial No.04-215 Initial Licensed Operator Examination Outlines Page 2 of 2 Attachments:
1 Commitments made in this letter: None.
cc:
(w/o attachment)
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1 41 5 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11 555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station US. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Serial No.04-215 Docket No. 50-423 Reactor Operator and Senior Operator Initial Written Examinations Examination 0 ut I i nes Millstone Power Station Unit 3 Dominion Nuclear Connecticut, Inc. (DNC)
Description of the Process Used to Develop the 2004 Millstone 3 Written Exam Outline I.
Obtained copies of Form ES-40 1-2 P WR Examination Outline, and Form ES-40 1-3 Generic Knowledge and Abilities Outline (Tier 3).
- 11.
Used the Example Systematic Sampling Methodology per ES-40 1, Attachment 1 to select the Tier 1 and 2 topics for the written exam as follows:
A. Deleted all systems not applicable to Millstone 3 (BW & CE Evolutions, and the Ice Condenser).
B. Selected the topics for use on the exam by randomly selecting tokens.
C. If a group had more topics than required questions for a Tier / Group, tokens were selected to randomly remove the topics that would not be covered. These randomly removed topics were used for SRO topics, with additional SRO topics selected randomly.
D. If a group had less topics than required questions for a Tier / Group, each topic was selected once, and tokens were selected to randomly add topics that would receive double question coverage.
111.
Used the Example Systematic Sampling Methodology per ES-40 1, Attachment 1 to select the WA categories for each Tier 1 and 2 topic.
IV.
Used the Example Systematic Sampling Methodology per ES-40 1, Attachment 1 to select the individual WA statements for Tier 1 and 2 as follows:
A. All individual WA statements with an importance rating of < 2.5 were eliminated prior to selection.
B. If a WA category had no individual WA statements with an importance rating of 2 2.5, another WA category was randomly selected.
C. Prior to randomly selecting the individual WA statement for Tier 1 and 2 Generic categories, K/A statements not relevant to the WA topic were removed.
V.
WAS that were deemed inappropriate were rejectedjreselected, and documented on Form ES-401.10 Record of Rejected WAS. One Tier 1 KA statement on the RO outline was viewed as SRO level.
It was switched with a randomly selected KA statement from the SRO outline.
VI.
Checked each WA category in Tier 1 and Tier 2 for at least 2 points. From Tier 2, K6 and A1 had only 1 point each. Added one more statement to each of these two categories by randomly replacing WA statements from the highest-sampled categories.
VII. Checked for exam balance, and noted over-sampling of Annunciator Response Procedures (AMs),
Power Supplies, Refueling, Containment, and Tech Specs. Randomly removed KA statements and/or rejected weak KAs in these areas as annotated on Form ES-401-4 Record of Rejected WAS.
New WA statements were randomly selected from the same WA categories, where applicable.
VIII. Used the Example Systematic Sampling Methodology per ES-40 1, Attachment 1 to select the individual WA statements for Tier 3 by randomly selecting 2 from each of the 4 categories, then randomly selecting from all of the remaining statements. Too many SRO topics were selected before adequate RO coverage was reached. Two SRO topics were randomly removed and new Tier 3 WA Topics were randomly selected to replace the over-sampled SRO area.
Page 1 of 1
ES-401 PWR Examination Outline Form ES-40 1-2 Note:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6. *
- 7.
- 8.
- 9.
Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i. e., the Tier Totals in each WA category shall not be less than two). Refer to Section D. 1.c for additional guidance regarding SRO sampling.
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 If: 1 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.
Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system or evolution unless they relate to plant-specific priorities.
Systems/evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the categorykier.
The generic (G) WAS 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. The SRO WAS must also be linked to 10CFR55.43 or an SRO-level learning objective.
On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled Ky and A. Use duplicate pages for RO and SRO-only exams.
For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-40 1-3.
Refer to ES-40 1, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
__p NUREG-102 1, Draft Revision 9
ES-40 1 PWR Examination Outline Form ES-40 1-2 Emergency and Abnormal Plant Evolutions - Tier IIGroup 1 (RO I SRO)
Stabilization - Recovery I 1 00000008 Pressurizer Vapor Space Accident 13 000009 Small Break LOCA 1 3 00001 1 Large Break LOCA I 3 0000 15/17 RCP Malfunctions I 4 4
000022 Loss of Reactor Coolant Makeun I 2 000026 Loss of Comuonent I
Cooling Water I 8 000027 Pressurizer Pressure Control System Malfunction I 3 000029 ATWS I 1 000040 (WE 12) Steam Line Rupture - Excessive Heat Transfer 14 000054 Loss of Main Feedwater I 4
000055 Station Blackout 16 I
000057 Loss of Vital AC Elec.
I Inst. Bus 16 000058 Loss of DC Power I 6 1
000062 Loss of Nuclear Service Water / 4 000065 Loss of Instrument Air I 8 WE04 LOCA Outside Containment / 3 A
A G
1 2
WA Topic(s) 2.4.2 Knowledge of setpoints, interlocks, and auto_acfu;msassociated with EOP Intkrrelation between vapor space accident, sensors and detectors.
Knowledge of event based EOP mitigation strategies.
consequences of managing LOCA
~
entry c-ns.
2.4.7 3
Ability to determinelinterpret with loss of CCW.
Operational implications of steady I
I I state relationship between RCS and SGs resulting from unbalanced flow.
1 3 Determinelinterpret failures of flow control valve or controller.
Ability to operatelmonitor loads on CCW in the control room.
2 Perform actions without reference to I
I 2*4.49 I procedures that require immediate I operation of system controls.
I Ability to determinehnterpret
( 9 1 occurrence of a turbinelreactor trip.
difference between steamline rupture and LOCA.
4 Ability to determinelinterpret proper operation of AFW pumps and reg.
valves.
Knowledge of reasons for actions
~
3 Ability to determinelinterpret containedin the EOP. fl Hl=
3 Ability to operatelmonitor feed pump speed to control SG pressurellevel.
Operational implications of battery charger equipment and instruments Knowledge of autoFatic actions within service water on ESFAS 3 1 I
I Ability to restore systems after I instrument air pressure is regained.
I Knowledge of reasons for EOP responses-associated with LOGA outside containment. E&
Interrelation between loss of heat sink and components, systems, instruments, signals, interlocks, failure modes, automatic and manual features.
2.712.7 1
3.113.8 1
3.714.2 1
2.9/3.1 1
3.113.6 1
3.213.3 1
4.014.0 1
4.214.3 1
4.314.6 1
3.613.6 1
2.8/3.1 1
3.613.9 1
2.913.1 1
3.414.0 1
-r
ES-40 1 PWR Examination Outline Form ES-40 1-2
ES-40 1 Emergencv and P PWR Examination Outline Form ES-40 1-2 normal K
K 2
3 1
2 3
2 1
3 3volutions -
IR EIAPE # I Name I Safety Function 000005 InoperableIStuck Control Rod I 1 WA Topic(s)
Knowledge of interrelations between inoperablelstuck rod and controllerslpositioners.
Ability to prioritize and interpret the significance of each annunciator.
1 -
1 2.512.5 3.313.6 000024 Emergency Boration I 1 000033 Loss of Intermediate Range NI I 7
Ability to determinelinterpret indication of blown fuse.
2.813.1 1
000036 Fuel Handling Accident I 8 Knowledge of reasons for interlocks associated with fuel handling equipment Knowledge of reasons for actions in the EOP. w 1 -
1 2.913.6 3.814.2 000060 Accidental Gaseous Rad waste Rel.
1 9 WE06 Inad Core Cooling 1 4 WIE02 SI Termination I 3
Knowledge of reasons Ability to operatelmonitor for desired operating results during emergencies.
Ability to operatelmonitor components, systems, instruments, signals, interlocks, failure modes, automatic and manual features.
Ability to operatelmonitor operating behavior characteristics of the facility.
responses.
P 3.514.0 1 3.814.0 2.913.0 2.913.0 W E 15 Containment Flooding I 5 WE16 High Containment Radiation I 9
KIA Category Totals:
Group Point Total:
ES-401 Emergency an E/APE # / Name I Safety Function 00000 1 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod/ 1 00059 Accidental Liquid Rad Waste Rel. / 9 W E 14 Loss of CTMT Integrity / 5 WE03 LOCA CooldodDepress. 14 K/A Category Totals:
PWR Examination Outline Form ES-40 1-2 I Plant E olutions - Tic G
2.4.30 2.4.1 1 2
Knowledge of which events related to system operations/status should be reDorted to outside agencies.
Knowledge of abnormal condition procedures.
Ability to determinelinterpret the occurrence of automatic actions as a result of a high PFW signal.
Ability to determinelinterpret facility conditions and select the appropriate procedure.
Ability to determinehnterpret adherence to appropriate procedures and operation within limits.
Group Point Total:
5 3.413.6 1
ES-401 System # I Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 006 Emergency Core Cooling 007 Pressurizer RelieflQuench Tank 008 Component Cooling Water 01 0 Pressurizer Pressure Control 0 12 Reactor Protection 0 12 Reactor Protection 0 13 Engineered Safety Features Actuation 022 Containment Cooling 026 Containment Spray 039 Main and Reheat Steam PWR Examination Outline t
A G
4 2.4.50 2.1.32 2.1.23 Form ES-40 1-2 I
IR I #
KIA Topic(s)
Physical connections or cause-effect between 3.013.3 1
Ability to verify alarm setpoints and operate controls per ARP.
Predictlmonitor changes in VCT level associated with operating controls. I Effect of malhnction on I RHR heat exchanger on 2.512.6 1
RHRS.
Knowledge of power supplies to accumulator 2.512.9 1
valves.
Ability to explain and apply all system limits 3.413.8 1
and precautions.
Ability to monitor components which 2.712.9 1
discharge to the PRT.
Ability to monitor automatic actions that 3.613.7 1
occur on SIS.
Predict impactlmitigate 4.114.2 1
PORV failure.
Physical connectionlcause-effect 3.113.1 1
between turbine and RPS.
Knowledge of power supplies to RPS 3.313.7 1
channels.
Operational implications of ESFAS logic and 2.913.3 1
reliability.
Ability to perform system and integrated 3.9/4.0 1
plant procedures in ail modes of operation.
Knowledge of design 1
featurelinterlock that 3.8/4.1 1
provides adequate level in Containment sump for CSS suction Predict impactlmitigate malfhnctioning steam 3.413.7 1
dump.
PWR Examination Outline Form ES-40 1-2 ES-40 1 System # I Name WA Topic(s)
Physical connections1 cause-effect between condensate and MFW.
Ability to monitor automatic Feedwater isolation.
Ability to operate or monitor feed control during power increase or decrease.
Operational implications of decay heat sources and magnitude.
Physical connectionslcause-effect between AC distribution and offsite power.
Knowledge of power supplies for major system loads.
Predict impactlmitigate ground.
Knowledge of effect of malfunction of EDG system on systems controlled by the sequencer.
Predictlmonitor changes in rad levels to prevent exceeding design limits.
Physical connectionslcause-effect between Service Water and PRMS.
Ability to monitor auto operation of IAS, including air pressure.
Knowledge of design featurelinterlocks which provides for containment isolation.
Knowledge of the purpose of major components and controls.
IR 2.612.6 3.213.3 2.912.9 056 Condensate 059 Main Feedwater 059 Main Feedwater 061 Auxiliary Feedwater 3.213.6 062 AC Electrical Distribution 3.714.2 1
062 AC Electrical Distribution 3.313.4 1
1 -
1 2.513.2 3.814.1 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 1 -
1 3.213.5 3.612.7 076 Service Water 078 Instrument Air 1 -
1 1
3.113.2 3.113.7 3.213.3 103 Containment 103 Containment Group Point Total:
28 -
KIA Category Totals:
'd c-ES-40 1 PWR System # I Name 003 Reactor Coolant Pump 026 Containment Spray 039 Main and Reheat Steam 064 Emergency Diesel Generator EUA Category Totals:
G 2.1.23 2.4.45 2.1.12 3
Form ES-40 1-2 K/A Topic(s)
Ability to perform specific system and integrated plant procedures during all modes of oDeration.
Predicdmitigate impact of failure of ESF on containment surav.
Ability to prioritize and interpret significance of each annunciator.
Ability to apply technical specifications for a system. -
P Group Point Total:
IR 3.914.0 4.114.4 3.313.6 2.914.O
ES-40 1 PWR Examination Outline Form ES-401-2 P
IR System # I Name KIA Topic(s)
Knowledge of rod bottom light design andor interlocks 0 14 Rod Position Indication 3.213.4 0 16 Non-nuclear Instrumentation Predict impact and mitigate high and low 2.5/2,6 voltage to instruments.
Predict impact and 0 17 In-core Temperature Monitor 027 Containment Iodine Removal mitigate the consequences of core damage.
Ability to manually operate or monitor CIRS controls.
3.614.1 3.313.3 034 Fuel Handling Equipment Knowledge of design feature or interlock which provides for fuel movement.
Knowledge of the effect of a malfunction of a secondary PORV on the SG.
Knowledge of the effect of a malfunction of the MTIG system will have on the plant.
Knowledge of physical connections/cause-e ffect between circ water system and emergency service water.
2.513.3 3.113.5 2.913.2 3.213.2 035 Steam Generator 045 Main Turbine Generator 075 Circulating Water 079 Station Air Knowledge of operator responsibilities during all modes of operation.
Ability to manually operate/monitor deluge valves in the control room.
3.014.0 3.013.5 086 Fire Protection WA Category Totals:
Grow Point Total:
L' ES-40 1 PWR Examination Outline Form ES-40 1-2 System#/Name K K I 1 12 002 Reactor Coolant Level Control Plant SE KIA Topic(s) and recognize trends utilizing reference material.
Ability to evaluate 3.714.4 plant performance I
and make operational Group Point Total:
1 -
1
ES-40 1 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Topic RO SRO-Only Facility: Mil Category IR tone Uni KIA #
IR Ability to evaluate the plant and make operational judgments.
Ability to apply technical specifications for a system.
Knowledge of system status which requires notification of 3.714.4 2.914.0 2.513.3 I
I Knowledge of refueling administrative requirements.
2.513.7 2.3.4 Knowledge of radiation exposure limits including 2.5/3.1 1
permissible levels in excess of those authorized.
2.3.1 1 Ability to control radiation releases.
2.713.2 1
Ability to prioritize/interpret significance of each alarm.
Knowledge of chemistrylhealth physics tasks during emergency operations.
Knowledge of SROs responsibilities in emergency plan implementation.
3.3/3.6 1
2.012.8 2.314.0 2.1.23 Ability to perform systemlplant procedures during all modes I 3.9/4.0 I
1 I I
I I
2.1.24 Ability to obtaidinterpret electricallmechanica1 drawings.
I 2.8/3.1 I 1 I I
I I
- 1.
Conduct of 3perations 2.1.25 Ability to obtainlinterpret graphs and tables.
I2.8/3.1 I 1 I I
I I
2.1.7 1
2.1.12 1 -
3 -
2.1.14
- 2.
Equipment Control 2.2.1 1 2.2.13 2.2.33 1
1 -
2.2.14 2.2.26
- 3.
Radiation Control 0
- 4.
Emergency Procedures 2.4.1 1 Knowledge of abnormal condition procedures.
1 3.413.6 1
1 I I
I I
2.4.45 2.4.36 2.4.40 Plan I
I I
I NUREG-102 1, Draft Revision I
ES-4.01 Record of Rejected WAS Form ES-401-4 3 13 313 313 313 313 core load #lo. Also, over-sample of refueling.
GEN.2.3.3 KA < 2.5.
GEN.2.3.5 KA < 2.5.
GEN.2.3.6 KA < 2.5.
GEN.2.3.7 KA < 2.5.
GEN.2.3.8 KA < 2.5.
Page 1 of 1 NUREG-102 1, Revision 8, Supplement 1
ES-301 Administrative ToDics Outline Form ES-301-1 see Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Facility:
Millstone 3 Date of Examination:
19 - 23 Julv 2004 Examination Level (circle one): RB/@
Operating Test Number:
One Code*
N N
P N
N Describe activity to be performed
~~
~
==
Description:==
Administrative Requirements for Shift Manning Activities & Working Hour Limitations.
WA:
10 CFR 9 55.45 (12)
==
Description:==
Escalation and Control Rod Withdrawal (OP 3204,4.1.16).
WA:
2.1.25 (3.1) Ability to obtain and interpret station reference materials such as graphs, monographs, and table which contain performance data.
10 CFR 3 55.45 (5)
==
Description:==
Checklist.
WA:
during all modes of plant operation.
10 CFR Q 55.45 (12)
==
Description:==
a Radiation Monitor from Service (OP 3250.62, Att 3)
WA:
radiation control requirements.
10 CFR Q 55.45 (9)
==
Description:==
Emergency Plan Classification and Protective Action Recommendation for General Emergency WA:
thresholds and classifications.
10 CFR 3 55.45 (I 1).
2.1.5 (3.4) Ability to determine working hour limits.
Determine the Maximum Rate of Power Complete a Shutdown Safety Assessment 2.2.1 8 (3.0) Knowledge of Operator responsibilities Determine Appropriate Response to Remove 2.3.1 (3.0) Knowledge of 10 CFR: 20 and related facility 2.4.41 (4.1) Knowledge of the Emergency Action Level NUREG-1021, Revision 9 G:\\DRS\\Osb\\Balian\\Validation\\Outline\\MS3 ES301-1.wpd
ES-301 Administrative Topics Outline Form ES-301-1 Conduct of Operations Facility:
Millstone 3 Examination Level (circle one): @Y SRB Operating Test Number:
One Date of Examination: -1 9 - 23 Julv 2004 1
Administrative Topic (see Note)
Code*
N I N
' Conduct of Operations I Equipment Control N I Radiation Control I N Describe activity to be performed
==
Description:==
Administrative Requirements for Shift Manning Activities -Working Hour Limits & Fitness for Duty.
WA:
during all modes of plant operation.
10 CFR 9 55.45 (12)
==
Description:==
Escalation and Control Rod Withdrawal (OP 3204,4.1.16).
WA:
2.1 2 5 (2.8) Ability to obtain and interpret station reference materials such as graphs, monographs, and table which contain performance data.
10 CFR 5 55.45 (5) 2.1.2 (3.0) Knowledge of Operator responsibilities Determine the Maximum Rate of Power
==
Description:==
Surveillance KIA:
10 CFR 9 55.45 (13)
==
Description:==
a Radiation Monitor from Service (OP 3250.62, Att 3)
WA:
radiation control requirements.
10 CFR 3 55.45 (9)
Review a Completed Technical Specification 2.2.12 (3.4) Knowledge of Surveillance Procedures.
Determine Appropriate Response to Remove 2.3.1 (2.6) Knowledge of 10 CFR: 20 and related facility
~
None 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 all 5 are required.
- Type Codes & Criteria:
(C)ontrol room (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (2 1)
(P)revious 2 exams (1.1 ; randomly selected)
(S)imulator NUREG-1021, Revision 9 G:\\DRS\\Osb\\Balian\\VaIidation\\Outline\\MS3 ES301-1.wpd
ES-301 Control Room / In-Plant Systems Outline F O ~ I ES-30 1-2
- b.
Vent Unisolated SI Accumulators (ES-I.2, GA-7)
Take the Plant Solid (RO Only)
- c.
- d.
Feedwater Bypass Level Control Valve in Auto with Feedwater Flow Control Valve Open and in Manual (OP 3321, Q 4.1 7).
facility: Millstone Generating Station, Unit 3 Exam Level (circle one):-
SRBfbF)
Operating Test No.:
One Date of Examination: 19-23 Julv 2004 A, L, M, S L, N, s N, S Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
- g.
Respond to Main Steam Pressure Transmitter MSS-PT2OD Failure Open. (OP3353.MB5C 5-7) to 100% Causing SG Atmospheric Relief Valve MSS-PV20 to System / JPM Title
/I N, s I Type Code*
- i.
Subsequent Actions in Response to Auxiliary Building Radiation Monitor 3HVR-RE13 Alarm (Spare)
II I I D, s 9
11 a.
Respond to and recover a dropped control rod (AOP 3552) 1 M,S
~~
- j.
Process Radiation Monitor DAS50-1 Alarm (AOP 3573)
II I
E, N 9
- k.
Respond to Potential Steam Binding of AFW Pumps 3FWA*PlA and 3FWA*P2 (OP 3322)
Establish Alternate Charging Pump Cooling (EOP 3501)
I.
- e.
Respond to Clogged Containment Sump (Loss of Cold Leg Recirculation).
E, N, R 4
D, E, R 8
Safety Function
- m.
Verify All Dilution Paths are Isolated EOP 35 FR-S.l (Spare) 1 D, E, R 1
2 4
5
~~
- f.
Start, Parallel, and Load the B EDG from MB8 7
- h.
Swap from RPCCW Train W to Train C - fouled RPCCW Heat I A, N, 1
8 Exchanger.
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 63 All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems the mnhhmm G :\\D RS\\Os b\\Bal ian\\Val idation\\Ou tl ine\\MS3 ES301-2.wpd NUREG-1021, Revision 9
ES-30 1 Control Room / In-Plant Systems Outline Form ES-301-2 Type Codes
- Type Codes SRO-I RO Criteria for RO I SRO-I I SRO-U (A)ltemate path (C)ontrol room (D)irect from bank (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow Power (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams (S)imulator 4
4 0
0 1
1 4-6 14-6 12-3
~~
(N)ew or (M)odified from bank including 1(A) 11 (P)revious 2 exams 0
>I I )I 111
>2 122 121
>I 121 111
<3 153 I52 (randomly selected) 10 0
(S)imulator I
8 7
(E)mergency or abnormal in-plant I
3 I
3 (L)ow Power I
3 I
3 (R)CA I
2 I
2 G:\\DRS\\Osb\\Balian\\Validation\\Outline\\MS3 ES301-2.wpd NUREG-I 021, Revision 9
Appendix D Form ES-D-I Event No.
1 2
3 4
5 6
Malf. No.
Event Event Type*
Description N, R CONVEX orders rapid power reduction to 60%
PZR Press Xmtr, 3RCS*PT455 Fails Low (TS - SRO)
Turb Imp Press Xmtr, 3MSS-PT505, Fails to 0%.
3RCS*PCV456 (B PZR PORV) Begins leaking (TS - SRO)
MS Hdr Press Xmtr, 3MSS*PT507, fails low 3FWC-FCV520. B FW FCV fails oDen forcina a Manual TriD RXO9A(O%)
I (RO)
RXI6A(O%)
RC07B(I%)
C(R0)
RX15 (0%)
I (BOP)
FW08B [loo%)
C (BOP)
9 10 I
I 1 I I
I SROclsssifiesthent
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor RDI 6 c (RO)
FW20A, B, C C (BOP)
SGOlB(38%)
M SGTR of 340 gpm in B SG S107B Five (5) Control Rods fail to insert, Immediate Boration.
AFW Pumps fail to start, BOP manually starts them.
C iRO1 3SISPl B Fails to Automaticallv Start on SI Sianal NUREG-I 021, Revision 9
Appendix D Page 1 of I Form ES-D-1 Event No.
Malf. No.
Event Event Type*
Description Power Range Nuclear Instrument (PRNI) N-41 fails hiah
- 1)
- 1.
N107A 1 I(R0) 1 2*
- 3.
FW13E R
Feedwater Heater Tube Failure forces Power (5 min ramp) C (BOP) Reduction to 95%
CS04
. C (RO)
Refueling Water Storage Tank leak
- 4.
Service Water Pump Trips. Standby Pump fails (Ro) to start in AUTO.
SWOIC
- 5.
3RCS-PI D Locks Up (Trips). Automatic Reactor Trip fails.
RTBs opened manually - 5 minutes later.
RCI I D RPIOA & B RPOgA (Ro)
ATWS: crew performs FR-S.I.
- 7.
- 8.
TC03 Automatic turbine trip fails.
TC04 RC03D M
Manual trip succeeds while performing FR-S.l Large Break Loss of Coolant Accident (L B LOCA).
SRO Classifies the Event
Appendix D Page 1 of 1 Form ES-D-1
~
C (BOP)
M C (BOP)
~~
Facility: Millstone, Unit 3 Scenario No.: Three Examiners: John Caruso Operators: SRO Surrosate Op-Test No.: Scenario 3 SRO Applicants I to 3 RO Applicants 5 to 8 Don Jackson Gill Johnson Initial Conditions:
Turnover:
service for emergent maintenance.
9% Power. Steadv State Unit is at 9% power with one MDAFW Pump (3FWA*PlA) out of 3RCS-PlC, Upper Reservoir Oil Leak MSlV "A" closes inadvertently.
FW Rupture on "D" feedwater line.
MSlVs "Br1. "C". "D" stick open Event
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
I O.
- 11.
Malf. No.
RX12F CV05 ED08A RC12C MSO6A FWIOD MSIZB. C. D RP07A & B FWl8B, 21B Event Type*
Event Description I
R I Raise power from 9% to 11%. P-IO Fails.
I (BOP)
I SG "BI' LT529, fails to 0 over 5 mins.
I (RO)
I Letdown Press Xmtter, PT131, fails low.
I LOSS of VIAC-1 (3VBA*INV-1 Deene raized C(R0,BoP) I C
SI Fails to Actuate, can be manually actuated.
_ _ ~
No flow from 3FWA*Pl B; Trips later in scenario SRO Classifies the Event G:\\DRS\\Osb\\Balian\\Validation\\Outline\\MS3 ES-D-1 Scenario 3.wpd NUREG-1021, Revision 9
Appendix D Page 1 of 1 Form ES-D-1
- 1.
- 2.
Facility: Millstone, Unit 3 Scenario No.:
four Op-Test No.: One Examiners: John Caruso Operators: SRO Amlicants 1 to 4 RO Amkants 5 to 8 RO Amlicants 9 to 12 Don Jackson Gil Johnson Initial Conditions:
Turnover:
Maintenance. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO
? 00% Power. Steady State Unit is at 100% power with the Turbine Driven AFW Pump 00s For RXOIOA l(R0)
Pressurizer Level Transmitter fails high.
CV04B I (RO)
Letdown Temperature Instrument fails low Event Malf.
No. I No. I EventType* I
- 4.
1
- 5.
- 6.
- 7.
- 8.
- 9.
Loss of Condenser Vacuum, Reactor Trip TC03 C (BOP)
Failure of Turbine To Trip, MSIV Isolation FW18B C(BoP)
Trip of AFW Pump (3FWA*P1 B)
Loss of Cond Vacuum, Rapid Load Reduction M (RO, BOP)
Loss of All Feed, Requires Feed and Bleed SRO Determines the EAL
Loss of 4160 Volt Bus 34C I
I I
G:\\DRS\\Osb\\Balian\\Validation\\Outline\\MS3 ES-D-I Scenario 4.wpd NUREG-1021, Revision 9