ML14010A036

Draft - Outlines (Folder 2)

ML14010A036
Person / Time
Site:	Millstone
Issue date:	09/03/2013
From:	Peter Presby Operations Branch I
To:	Dominion Nuclear Connecticut
Jackson D
Shared Package
ML13164A264	List: ML14010A036
References
TAC U01874
Download: ML14010A036 (20)

Text

Dominion Nuclear Connecticut, Inc.

Rope Ferry Road, Waterford, CT 06385 Web Address: www.dom.com EXAMINATION SECURITY AND INTEGRITY CONSIDERATIONS- WITHHOLD UNDER GUIDANCE OF NUREG-1021, ES201 OCT 0 2 2013 Donald E. Jackson, Chief Serial No. 13-464B Operations Branch - Division of Reactor Safety MPS Lic/LES RO U.S. Nuclear Regulatory Commission Docket No. 50-423 2100 Renaissance Blvd., Suite 100 License No. NPF-49 King of Prussia, PA 19406-2713 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 SENIOR REACTOR OPERATOR AND REACTOR OPERATOR INITIAL WRITTEN EXAMINATIONS, OPERATING TESTS AND SUPPORTING REFERENCE MATERIALS In a letter dated August 1, 2013, the U.S. Nuclear Regulatory Commission requested Dominion Nuclear Connecticut, Inc. submit written examinations, operating tests and supporting reference materials for Senior Reactor Operator and Reactor Operator Examinations - Millstone Power Station Unit 3, no later than October 3, 2013 for administration of examinations during the weeks of December 2 and 9, 2013. , Written Examinations, Operating Tests and Supporting Reference Materials, is being furnished in accordance with 10 CFR 55.40(b)(3) by an authorized representative of the facility. All materials are "complete and ready-to-use."

Consistent with guidance contained in NUREG-1021 Examination Standard 201, , "Examination Security and Integrity Considerations," the written examinations, operating tests and supporting reference materials contained in Enclosure 1 should be withheld from public disclosure until after the examination has been completed. No redacted versions are being supplied.

If you have any questions or require additional information, please contact John A.

Palmer at (860) 437-2830.

Sincerely, P-~

Site Vice President - Millstone NOTE: THE ENCLOSURE TO THIS LETTER CONTAINS REACTOR OPERATOR EXAMINATION INFORMATION- WITHHOLD UNTIL AFTER THE EXAMINATION HAS BEEN COMPLETED PER GUIDANCE IN NUREG-1021, ES201

Serial No. 13-4648 SRO and RO Initial Examinations- Written Examinations, Operating Tests and Supporting Reference Materials Page 2 of 2

Enclosure:

1 Commitments made in this letter: None.

cc: (w/o enclosure)

W. M. Dean, Region I Administrator U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 J.S. Kim NRC Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08-C2A One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

ES-401 PWR Examination Outline Form ES-401-2 Facility: Millstone 3 Date of Exam: December 09tn, 2013 RO Kl A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total 1.

Emergency & 1 2 1 4 1 5 5 18 3 3 6 Abnormal Plant Evolutions 2 3 1 0 N/A 1 2 N/A 2 9 2 2 4 Tier 5 2 4 2 7 7 27 5 5 10 Totals

2. 1 2 1 6 5 1 0 3 2 1 4 3 28 4 1 5 Plant Systems 2 2 1 0 2 1 2 0 1 1 0 0 10 0 0 3 3 Tier 4 2 6 7 2 2 3 3 2 4 3 38 4 4 8 Totals

3. Generic Knowledge and 1 2 3 4 1 2 3 4 Abilities Categories 10 7 3 2 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by+/- I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within 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/evolutions that are not included on the outline should be added. Refer to Section D of ES-40 1 for guidance regarding the elimination of inappropriate KJ A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting as second topic for any system or evolution.

5. Absent a plant-specific priority, only those KJ As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KJ A categories.

7.

• The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 ofthe K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l.b ofES-401 for the applicable K/As.

8. On the following pages, enter the KJ A 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 SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10CFR55.43.

Revision 1

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions- Tier !/Group 1 (RO)

E/APE #I Name I Safety K K K A A G KIA Topic(s) IR #

Function 1 2 3 1 2 000007 Reactor Trip - 3 Interrelation with Reactor Trip Status Panel 3.5/3.6 1 Stabilization - Recovery I 1 000009 Small Break LOCA 21 Reasons for actions contained in the EOP 4.2/4.5 2 I3 000015117 RCP 2 Determine/interpret abnormalities in RCP 2.8/3.0 3 Malfunctions I 4 air vent path and/or oil cooling system 000025 Loss of RHR 2 Reasons for isolating RHR low pressure 3.3/3.7 4 System/ 4 piping prior to raising pressure 000026 Loss of Component 2.4.50 Ability to verify alarm setpoints and operate 4.2/4.0 5 Cooling Water I 8 controls per the alarm response manual 000027 Pressurizer Pressure 8 Determine/interpret letdown flow indication 3.2/3.2 6 Control Malfunction I 3 000029 ATWS I 1 8 Determine/interpret Rod Step Counters and 3.4/3.5 7 RPI 000038 Steam Gen. Tube 2.2.22 Knowledge oflimiting conditions for 4.0/4.7 8 Rupture I 3 operations and safety limits 000054 Loss of Main 2.1.23 Ability to perform specific system and 4.3/4.4 9 Feedwater I 4 integrated plant procedures during all modes of operation 000055 Station Blackout I 6 2.4.2 Knowledge of setpoints, interlocks and 4.5/4.6 10 automatic actions associated with EOP entry conditions 000056 Loss of Off-site 38 Determine/interpret Sequencer status lights 3.7/3.8 II Power I 6 000057 Loss of Vital AC 1 Reasons for actions contained in the EOP 4.1/4.4 12 Elec. lust. Bus I 6 000058 Loss of DC Power I 1 Operational implications of Battery Charger 2.8/3.1 13 6 equipment and instrumentation 000062 Loss ofNuclear 3 Reasons for actions contained in the EOP 4.0/4.2 14 Service Water I 4 000065 Loss of Instrument 5 Operate/monitor RPS 3.3/3.3 15 Air/ 8 W/E04 LOCA Outside 1 Operational implications of emergency 3.5/3.9 16 Containment I 3 systems W/E05 Loss of Secondary 2.4.47 Ability to diagnose and recognize trends 4.2/4.2 17 Heat Sink I 4 utilizing reference material 000077 Generator Voltage 3 Determine/interpret Generator current 3.5/3.6 18 and Electric Grid outside the capability curve Disturbances I 6 KIA Category Totals: 2 1 4 1 5 5 Group Point Total: 18

ES-401 3 Form ES-40 1-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions- Tier !/Group 2 (RO)

E/ APE # I Name I Safety K K K A A G KIA Topic(s) IR #

Function 1 2 3 1 2 000051 Loss of Condenser 2.4.18 Knowledge of specific bases for EOPs 3.3/4.0 19 Vacuum/ 4 000076 High Reactor 2 Determine/interpret corrective actions 2.8/3.4 20 Coolant Activity I 9 W /E 13 Steam Generator 2.4.21 Knowledge of parameters and logic used to 4.0/4.6 21 Over-pressure I 4 assess the status of safety functions W /E03 Post LOCA 2 Operational implications of procedures 3.6/4.1 22 Cooldown Depress. I 4 Site Specific: Turbine Trip 1 Operational implications of systems or Site 23 procedures Priority Site Specific: Severe 1 Determine/interpret conditions or Site 24 Weather procedures Priority Site Specific: Rapid 1 Operate/monitor indications, plant behavior, Site 25 Downpower and/or desired results Priority Site Specific: Loss of 1 Operational implications of systems or Site 26 Emergency Bus procedures Priority Site Specific: Loss of All 1 Interrelations with control, safety, and/or Site 27 AC Power- Recovery with heat removal systems Priority the SBO Diesel KIA Category Point Totals: 3 1 0 I 2 2 Group Point Total: 9

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/Group I ~ RO)

System# I Name K K K K K K A A A A G KIA Topic(s) IR #

I 2 3 4 5 6 I 2 3 4 003 Reactor 1I Design feature/interlock which 3.0/3.0 28 Coolant Pump provides for: Isolation valve interlocks 004 Chemical 7 Effect of a malfunction on: PZR 3.8/4. I 29 and Volume level and pressure Control 005 Residual I Effect of a malfunction on: RCS 3.9/4.0 30 Heat Removal 005 Residual 4 Predict impact and mitigate: RHR 2.9/2.9 31 Heat Removal valve malfunction 006 Emergency 9 Physical connections and/or cause- 2.6/2.9 32 Core Cooling effect relationship with: Nitrogen 007 Pressurizer 10 Ability to manually operate and/or 3.6/3.8 33 Relief/Quench monitor: Recognition ofleaky Tank PORV/code safety 008 Component 2 Predict and/or monitor parameters 2.9/3. I 34 Cooling Water associated with operating controls including: CCW temperature 008 Component 2.4.9 Knowledge oflow 3.8/4.2 35 Cooling Water power/shutdown implications in accident mitigation strategies 0 I 0 Pressurizer 3 Design feature/interlock which 3.8/4. I 36 Pressure Control provides for: Over pressure control 012 Reactor I Effect of a malfunction on: CRDS 3.9/4.0 37 Protection 0 I 3 Engineered 1 Operational implications of: 2.8/3.2 38 Safety Features Definitions of safety train and ESF Actuation channel 0 I 3 Engineered I Ability to manually operate and/or 4.5/4.8 39 Safety Features monitor: ESF-initiated equipment Actuation which fails to actuate 022 Containment 3 Predict and/or monitor parameters 3.1/3.4 40 Cooling associated with operating controls including: Containment humidity 026 Containment I Bus power supplies to: 3.4/3.6 41 Spray Containment Spray Pumps 026 Containment 2 Monitor automatic operation, 3.9/4.2 42 Spray including: Verification that cooling water is supplied to the containment spray heat exchanger

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems- Tier 2/Group I (RO) Continued System# I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 039 Main and 4 Ability to manually operate 3.8/3.9 43 Reheat Steam and/or monitor: Emergency feed water pump turbines 059 Main 7 Predict and/or monitor 2.5/2.6 44 Feed water parameters associated with operating controls including:

Feed Pump speed normal control 061 Auxiliary/ I Effect of a malfunction on: RCS 4.4/4.6 45 Emergency Feedwater 061 Auxiliary/ 3 Predict impact and mitigate: 3.1/3.4 46 Emergency Loss of de power Feedwater 062AC 1 Effect of a malfunction on: 3.5/3.9 47 Electrical Major system loads Distribution 063 DC 3 Physical connections and/or 2.9/3.5 48 Electrical cause-effect relationship with:

Distribution Battery charger and battery 064 Emergency 11 Design feature/interlock which 3.5/4.0 49 Diesel Generator provides for: Automatic load sequencer: safeguards 073 Process 1 Design feature/interlock which 4.0/4.3 50 Radiation provides for: Release Monitoring termination when radiation exceeds setpoint 073 Process 2.4.2 Knowledge of setpoints, 4.5/4.6 51 Radiation interlocks and automatic actions Monitoring associated with EOP entry conditions 076 Service 7 Effect of a malfunction on: ESF 3.7/3.9 52 Water loads 076 Service 2.4.31 Knowledge of annunciator 4.2/4.1 53 Water alarms, indications, or response procedures 078 Instrument 1 Design feature/interlock which 2.7/2.9 54 Air provides for: Manual/automatic transfers of control 103 Containment 4 Ability to manually operate 3.5/3.5 55 and/or monitor: Phase A and phase B resets Kl A Category Point Totals: 2 1 6 5 1 0 3 2 1 4 3 Group Point Total: 28 Revision 1

ES-401 5 Form ES-40 1-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 RO)

System# I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 002 Reactor Coolant 1 Design feature/interlock which 2.7/3.0 56 provides for: Filling and draini~ the RCS 011 Pressurizer Level 5 Knowledge of the effect of a 3.1/3. 7 57 Control malfunction of the following will have on Pressurizer Level Control: Function ofPZR level gauges as post-accident monitors 014 Rod Position 2 Predict impact and mitigate: 3.1/3.6 58 Indication Loss of power to the RPIS 016 Non-nuclear 1 Operational implications of: 2.7/2.8 59 Instrumentation Separation of control and protection circuits 027 Containment 1 Bus power supplies to: Fans 3.1/3.4 60 Iodine Removal 035 Steam Generator 2 Design feature/interlock which 3.2/3.5 61 provides for: S/G level indication 041 Steam Dump 6 Physical connections and/or 2.6/2.9 62

/Turbine Bypass cause-effect relationship with:

Control Condenser 056 Condensate 3 Physical connections and/or 2.6/2.6 63 cause-effect relationship with:

MFW 086 Fire Protection 4 Knowledge of the effect of a 2.6/2.9 64 malfunction of the following will have Fire Protection: Fire, smoke, and heat detectors Site Specific: 1 Monitor automatic operation of Site 65 AM SAC AM SAC Priority Kl A Category Point Totals: 2 1 0 2 1 2 0 1 1 0 0 Group Point Total: 10

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier I /Group I (SRO)

E/APE #I Name I K K K A A G KIA Topic(s) IR #

Safety Function I 2 3 I 2 000015/17 RCP 2.1.32 Ability to explain and apply system limits and 4.0 76 Malfunctions I 4 precautions 000025 Loss of RHR 2.2.42 Ability to recognize system parameters that are 4.6 77 System/ 4 entry-level conditions for Technical Specifications 000027 Pressurizer 14 Determine/interpret RCP injection flow 2.9 78 Pressure Control Malfunction I 3 000057 Loss of Vital 6 Determine/interpret Instrument Bus alarms for the 3.7 79 AC Inst. Bus I 6 inverter and alternate source 000062 Loss ofNuclear 2.2.37 Ability to determine operability and/or availability of 4.6 80 Svc Water I 4 safety related equipment 000077 Generator 4 Determine/interpret VARS outside the capability 4.0 81 Voltage and Electric curve Grid Disturbances I 6 KIA Category Totals: 3 3 Group Point Total: 6 Revision 1

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions- Tier 1/Group 2 (SRO)

E/APE #I Name I Safety K K K A A G KIA Topic(s) IR #

Function 1 2 3 1 2 000032 Loss of Source Range NI 7 Determine/interpret maximum 3.4 82 I7 allowable channel disagreement 000060 Accidental Gaseous 2.4.11 Knowledge of abnormal condition 4.2 83 Radwaste Rei. I 9 procedures W/E13 Steam Generator Over- 2 Determine/interpret adherence to 3.4 84 pressure I 4 appropriate procedures WIE 16 High Containment 2.4.47 Ability to diagnose and recognize 4.2 85 Radiation I 9 trends utilizing_ reference material Kl A Category Point Totals: 2 2 Group Point Total: 4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/Group 1 (SRO)

System# I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 008 Component Cooling 9 Predict impact and 2.8 86 Water mitigate: Excessive exit temperature from the letdown cooler, including resins 012 Reactor Protection 4 Predict impact and 3.2 87 mitigate: Erratic power supply operation 039 Main and Reheat Steam 4 Predict impact and 3.7 88 mitigate: Steam dump malfunction 076 Service Water 2 Predict impact and 3.1 89 mitigate: Service water header pressure 103 Containment 2.1.23 Ability to perform 4.4 90 specific system and integrated plant procedures during all modes of operation KIA Category Point Totals: 4 1 Group Point Total: 5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/Group 2 (SRO)

System# I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 017 Hydrogen 2.2.38 Knowledge of conditions and 4.5 91 Recombiner and Purge limits in the facility license Control 033 Spent Fuel Pool 2.1.32 Ability to explain and apply 4.0 92 Cooling ~stem limits and precautions 068 Liquid Radwaste 2.2.40 Ability to apply Technical 4.7 93 Specifications for a system Kl A Category Point Totals: 0 3 Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Millstone Unit 3 Date of Exam:

Category KIA# Topic RO SRO-Only IR # IR #

Ability to locate and operate components, including local controls 4.4 66 4.0 2.1.30 Ability to locate control room switches, controls, and indications and 4.3

1. 2.1.31 4.6 67 determine they correctly reflect the desired plant lineup Conduct of 2.1.44 Knowledge of RO duties in the control room during fuel handling, such 3.9 68 3.8 as responding to alarms, communications, systems operated in the control room, and supporting instrumentation Ability to perform specific system and integrated plant procedures during 4.4 Operations 2.1.23 94 all modes of operation 2.1.35 Knowledge of fuel handling responsibilities of SROs 3.9 95 Subtotal  !;~;:.::.:,',' 3 I '~*,,~~*~£* 2

2. 2.2.6 Knowledge of the process for making changes to procedures 3.6 3.0 69 Equipment 2.2.38 Knowledge of conditions and limits in the facility license 3.6 70 4.5 Ability to determine operability and/or availability of safety related 4.6 Control 2.2.37 96 equipment 2.2.43 Knowledge of the process used to track inoperable alarms 3.3 97 Subtotal

>  ;~:.

2 r~," ,,;0' 2

3. Ability to use radiation monitoring systems, such as fixed monitors, 2.9 2.3.5 2.9 71 portable survey instruments, personnel monitoring equipment, etc.

Ability to control radiation releases Radiation 2.3.11 3.8 72 4.3 Ability to use radiation monitoring systems, such as fixed monitors, Control 2.3.5 2.9 98 portable survey instruments, personnel monitoring equipment, etc.

. *,~;:;\

Subtotal 2 I.,;L;: ...*.. 1

4. 2.4.19 Knowledge of EOP layout, symbols, and icons 3.4 73 4.1 Emergency 2.4.30 Knowledge of events related to system operation/status that must be 2.7 74 4.1 reported to internal organizations or external agencies, such as the State, NRC, or transmission system operator Procedures/ Ability to diagnose and recognize trends utilizing appropriate reference 4.2 4.2 2.4.47 75 material Plan Knowledge of fire protection procedures 3.7 99 2.4.25 Knowledge ofRO tasks performed outside the control room during an 4.1 100 2.4.34 emergency, and resultant op_erational effects Subtotal b</:!{" 3

..y*;* .. *.

(::

2 Tier 3 Point Total ...;:.*!;!,.;;:*. 10  ;:,"!?:!:~ 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected Kl A 111 015/017.AA2.11 N/A Millstone 3: RCPs are not jogged during an RCP Malfunction 111 027.AA2.14 Determine/interpret RCP injection flow. Double-jeopardy; same KA on SRO portion 111 029.EA2.06 N/A Millstone 3: No Turbine Trip Switch Position Indication (pushbutton) 1/1 062.AK3.04 N/A Millstone 3: No impact on Service Water flow due to loss ofCCW 111 038.GEN.2.2.36 Effect of Maintenance Activity on LCOs: Not relevant during SGTR 111 038.GEN.2.1.27 System Q_urpose: Not conducive to discriminating question for EOP topic 111 054.GEN.2.2.40 Applying Technical Specifications: 10CFR55.43. Not RO job function.

II2 076.AA2.03 N/A Millstone 3: No RCS Activity Meter 2I 1 007.A4.01 N/A Millstone 3: No PRT Spray Valve 2I 1 026.K4.04 Rejected due to over-sample ofK4 and less than two K2 topics in Tier 2 112 W/E016.GEN.2.2.38 Knowledge of Conditions in Facility License: N/A for CTMT Hi Rad EOP 112 051.AK3.01 Double jeopardy with Steam Dump discharge to condenser selected in 041.K1.06 2/2 SRO 033.GEN.2.2.40 Ability to apply Technical Specifications for a system. Spent Fuel Pool Cooling System is not a Tech Spec System.

2/2 SRO 068.GEN.2.4.20 Knowledge ofEOP warnings, cautions, and notes. No EOP notes, cautions related to Liquid Waste System.

211 061.A2.02 Loss of air to AFW steam supply valve; double jeopardy with operating Emergency Feedwater Pump turbine in 039.A4.04, and with operating exam JPM.

Discussed with NRC lead examiner during outline review.

2/1 061.A2.01 Predict impact I mitigate Startup of MFW pump during AFW operation:

Oversample of MFW Pump operation. Previously selected APE.054.GEN.2.1.23 and 059.Al.07.

111 SRO W /E04.GEN.2.4.18 LOCA Outside Containment double jeopardy with operating exam scenario.

ES-401, Page 27 of33 Revision 1

ES-301 Administrative Topics Outline Form ES-301-1 REVISION 1 Facility: Millstone 3 Date of Examination: 12/2/13- 12/6/13 Examination Level: RO [!] SROD Operating Test Number: 2K13 Administrative Topic Type Describe activity to be performed (see Note)

Code*

Calculate a Reactivity Change Conduct of Operations M,R KIA 2.1.37 (Knowledge of procedures, guidelines, or limitations associated with reactivity management) KIA Rating: 4.3 /4.6 RO A.1.1 Determine Reactor Vessel Venting Time Conduct of Operations D,R KIA 2.1.25 (Ability to interpret reference materials, such as graphs, curves, tables, etc.) KIA Rating: 3.9/4.2 RO A.1.2 Recommend a clearance boundary for 3CCI*P1A Equipment Control M,R KIA 2.2.13 (Knowledge of tagging and clearance procedures)

KIA Rating: 4.1 /4.3 ROA.2 Review Radiological Work Procedure for Regenerative M,R Heat Exchanger Room Entry Radiation Control KlA 2. 3. 7 (Ability to comply with radiation work permit ROA.3 requirements during normal or abnormal conditions)

KIA Rating: 3.5/ 3.6 Emergency Procedures I 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, (S)imulator, or Class(R)oom (D)irect from bank ( ~ 3 for ROs; ~ 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( ~ 1)

(Pjrevious 2 exams ( < 1; randomly_ selectedl ES-301, Page 22 of 27 NUREG-1021, Rev 9, Supp 1

ES-301 Administrative Topics Outline Form ES-301-1 REVISION 1 Facility: Millstone 3 Date of Examination: 12/2/13- 12/6/13 Examination Level: RoD SRO[i] Operating Test Number: 2K13 Rev2 Administrative Topic Type Describe activity to be performed (see Note)

Code*

Review and Approve Reactivity Calculation Conduct of Operations N,R KIA 2.1.37 (Knowledge of procedures, guidelines, or limitations SRO A.1.1 associated with reactivity management.)

KIA Rating: 4.3 I 4.6 Respond to Degrading Intake Conditions Conduct of Operations P,D,R KIA 2.1.20 (Ability to interpret and execute procedure steps.)

KIA Rating: 4.6 I 4.6 SRO A.1.2 Response to Door lnoperability Equipment Control D,R KIA 2.2.21 (Knowledge of pre- and post-maintenance operability requirements) KIA Rating: 2.9 I 4.1 SRO A.2 N,R 3DAS-RE50, "Turbine Floor Drains Radmonitor", is inoperable Radiation Control SRO A.3 KIA 2.3.14 (Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities) KIA RatinQ: 3.4 I 3.8 M,R Emergency Plan Classification and Protective Action Recommendation Emergency Procedures I Plan KIA 2.4.41 (Knowledge of the emergency action level thresholds SRO A.4 and classifications.) KIA Rating: 2.9 I 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking onlythe administrative topics, when all 5 are re_guired.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D}irect from bank ( ~ 3 for ROs; ~ 4 for SROs & RO retakes)

(N)ew or (M}odified from bank ( ~ 1)

_(P}revious 2 exams ( < 1; randomly selected)

ES-301, Page 22 of 27 NUREG-1021, Rev 9, Supp 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 REVISION 1 Facility: Millstone Unit 3 Date of Examination: 12/2/13 Exam Level: RO IX I SR0-1 I I SRO-U u Operating Test No.: 2K13 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF System I JPM Title Type Code* Safety Function

a. S.1 I Control Rod Out of Alignment (KIA Number :001 A2.03 3.5/4.2) D,S 1-001

b. S.2 I Manual CIA (KIA Number: 013 A4.01 4.5/4.8) M,EN,S,A 2-013

c. S.3 I Transfer to Cold Leg Recirculation D,S,A 3-006 (KIA Number: 006 A4.05 3.9/ 3.8)

d. S.4 I Aligning RHR for SDR Inventory Control P,D,S,L 4.1-005 (KIA Number: 005 A4.01 3.6/3.4)

e. S.5 I Natural Circulation Cooldown using GA-26 M,S,A 4.2-039 (KIA Number: 039 A1.05 3.2* /3.3)

f. S.6 I Respond to a Loss of all AC Power and Energize an AC M,S 6-062 Emergency Bus (KIA Number: EPE: 055 EA 1.07 4.3/4.5)

g. S. 7 I Respond to High Containment Pressure P,A,EN,S 5-026 (KIA Number: West. EPE: E14-EA1.1 3.7/3.7)

h. S.8 I EOP 3502 Fuel Handling Accident N,S 8-034

{KIA Number: 034 A2.01 3.6/4.4)

In-Plant Systems@ (3 for ROJ; (3 for SR0-1); (3 or 2 for SRO-U)

i. P.1 I Locally Start an EDG (ECA-O.O)j_KIA Number: 064 k.105 3.4/3.9) D,A,E 6-064

j. P.2 I Locally Restore AFW Flow (Includes opening 3MSS*MSV5) M,A,R,E 4.2-061 (KIA Number: 061 A2.04 3.4/3.8)

k. P.3 I Align 'C' RPCCW Pump and Heat Exchanger to the 'A' train D,R,E 8-008 (KIA Number: 008 A.201 3.3/3.6)

@ All RO and SR0-1 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 I SR0-1 I SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~91~81~4 (E)mergency or abnormal in-plant _::1/_::11_::1 (EN)gineered safety feature - I- I _:: 1 (control room system)

(L)ow-Power I Shutdown _::11_::11_::1 (N)ew or (M)odified from bank including 1(A) _::21 _::21 _::1 (P)revious 2 exams ~ 3 I ~ 3 I ~ 2 (randomly selected)

(R)CA _::11_::11_::1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 REVISION 1 Facility: Millstone Unit 3 Date of Examination: 12/2/13 Exam Level: RO I I SR0-1 I I SRO-U IX I Operating Test No.: 2K13 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF System I JPM Title Type Code* Safety Function a.

b. S.2 I Manual CIA (KIA Number: 013 A4.01 4.5/4.8) M,EN,S,A 2-013 c.

d. S.4 I Aligning RHR for SDR Inventory Control P,D,S,L 4.1-005 (KIA Number: 005 A4.01 3.6/3.4) e.

f. S.6 I Respond to a Loss of all AC Power and Energize an AC M,S 6-062 Emergency Bus (KIA Number: EPE 055 EA1.07 4.3/4.5) g.

h.

In-Plant SystemsCCB (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U) i.

j. P.2 I Locally Restore AFW Flow (Includes opening 3MSS*MSV5) M,A,R,E 4.2-061 (KIA Number: 061 A2.04 3.4 I 3.8)

k. P.3 I Align 'C' RPCCW Pump and Heat Exchanger to the 'A' train D,R,E 8-008 (KIA Number: 008 A.201 3.3/3.6)

@ All RO and SR0-1 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 I SR0-1 I SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~91~81~4 (E)mergency or abnormal in-plant ~11~11~1 (EN)gineered safety feature - I- I ~ 1 (control room system)

(L)ow-Power I Shutdown ~11~11~1 (N)ew or (M}odified from bank including 1(A) ~21~21~1 (P)revious 2 exams ~3I ~3I ~2 (randomly selected)

(R)CA ~11~11~1 (S)imulator ES-301, Page 23 of 27

Appendix D Scenario Outline Form ES-D-1 REVISION 1 Facility: Millstone 3 Scenario No.: 2K13 NRC-01 <Rev Ol Op-Test No.: 2K13 Examiners: Operators:

Initial Conditions: IC-13, 100% Power, Beginning of Life, Eguilibrium Xenon Turnover:

The Plant is stable at 100% Power. 'C' CCP heat exchanger is tagged out for tube leak re(2air. Control Rods are in manual for re(2air of auto circuitey (which is not functional due to Tavg I Tref circuit card failure).

Event Malf. Event Event No. No Type* Description 1 - us TIS 'B' EDG INOP based on field report of an empty

_governor sightglass 2 RX09A RO I Controlling channel of pressurizer pressure fails high us TIS (AOP 3571).

3 FW16A RO R 'A' Heater Drain Pump trips requiring a 7% downpower.

BOP c us R 4 CV05 RO c Letdown pressure transmitter, PT -131, fails to intermediate value below setr:>_oint 5 SG01B RO M 'B' SG has a tube leak that develops into a 200 gpm MS12B BOP M tube rupture. Crew trips Reactor and ultimately us M mitigates using E-3, SG Tube Rupture. 'B' MSIV fails to close complicating E-3 recovery_

6 RP10A/B BOP c Automatic and manual Reactor trip switches fail. BOP RP9A/B is successful using load center switches.

7 RP11F RO c Multiple Charging components fail to re-align.

8 RP11L BOP c Feed Water Isolation (FWI) components fail to re-align.

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 REVISION 1 Facility: Millstone 3 Scenario No.: 2K13 NRC-02 (RevO) Op-Test No.: 2K13 Examiners: Operators:

Initial Conditions: IC-12, 74% gower, Beg oflife, Xenon building in@ 90 gem I hr.

Turnover:

The (21ant is being returned to service following a refueling outage. The crew is to stabilize reactor (2ower at 74% while Reactor Engineering (2erforms EN 31015 "Power Ascension Testing of Millstone Unit 3". Additional!~, the 'A' SIH (2Um(2 was taken out of service one hour ago to re(2air a newl~ discovered oil leak.

Event Malf. Event Event No. No Type* Description 1 NI09A RO I Power range nuclear instrument, N41, fails high us TIS causing control rods to auto insert (AOP 3571 ).

2 RX13C BOP I The controlling 'B' SG Feed flow instrument fails high (AOP 3571).

3 RC12A RO R Convex requested emergency downpower.

BOP N us R 4 - RO c 'A' RCP develops an oil leak and requires shutdown.

BOP c 'A' RCP is removed from service iaw AOP 3554.

us TIS 5 RP05A RO M A spurious 'A' train Safety Injection is caused from a tin SI06C BOP M whisker on MSI card. The reactor fails to auto trip. An RP10A us M isolable, inter-system LOCA develops in the RHR RP10B system and out a break in the ESF building (outside containment).

6 - RO c 'B' train of Sl did not actuate and must be actuated.

7 MSDI23 BOP c Partial MSI generated caused only the MSIV's to close.

Thru The remainder of the MSI components need to be MSDI26 manually re-aligned.

8 RP11H RO c Component Cooling Water valves fail to reposition and must be manually re-aligned.

9 EG13A BOP c 'A' EDG fails to auto start and is manually started.

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39