Text

Final Written Examination and Operating Test Outlines (Folder 3)
	ML20303A016
Person / Time
Site:	Millstone
Issue date:	09/18/2020
From:	David Silk; NRC Region 1
To:	Jeffrey Riley; Dominion Energy Co
	Jackson, D
Shared Package
ML19105A205	List: ML20302A234; ML20302A235; ML20303A011; ML20303A012; ML20303A014; ML20303A016; ML20303A032; ML20303A144; ML20307A010; ML20307A019; ML20307A064;
References
	CAC 000500
	Download: ML20303A016 (32)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: 09/21/2020 Examination Level: RO SRO Operating Test Number: ES20LI Type Administrative Topic (see Note) Describe activity to be performed Code*

K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc Conduct of Operations (A1R) R,D Shutdown Safety Assessment Time to Core Boil K/A 2.1.25 Ability to interpret reference Conduct of Operations (A2R) R,D materials, such as graphs, curves, tables, etc.

Borated Water Sources Monthly Surveillance K/A 2.2.44 Ability to interpret control room indications to verify the status and operation ofl a system, and understand how operator actions and directives affect plant and system Equipment Control (A3R) R,N conditions.

Perform an AC Electrical Sources Inoperability assessment for one Emergency Diesel Inoperable.

K/A 2.3.11 Ability to control radiation releases.

Radiation Control (A3R) R,N Perform Waste Gas Pressure Drop Calculation and Flow Rate Determination NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

(P)revious 2 exams ( 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 A1R Shutdown Safety Assessment Time to Core Boil - (NRC 2014 Bank A2R)

Examinee will determine the RCS time to boil. The plant is in MODE 5, 28 days into a refuel outage, with the core reloaded and the RCS drained to 14 inches above the hot leg centerline.

The examinee will make determinations on certain multipliers and along with information from tables make a calculation to determine the time to RCS boil.

A2R Borated Water Sources Monthly Surveillance - (NRC 2014 ADMIN RO-3 Not in Bank)

Examinee will complete the monthly borated sources verification surveillance and determine that each individual BAST concentration is not sufficient for functionality per the TRM and determines that the weighted average of the concentration of the contents of both BASTs meet TRM requirements. The examinee is provided with the surveillance procedure, surveillance form, BAST concentrations, BAST levels, the Technical Specifications and Technical Requirements Manual.

A3R Perform an AC Electrical Sources Inoperability assessment for one Emergency Diesel Inoperable - (New)

Examinee will perform an AC Electrical Sources Inoperability assessment for one Emergency Diesel Inoperable. The surveillance will be required to be performed in preparation for an EDG pre-lube and air roll. Photos of the control room boards will be used. The examinee will look at annunciators, breaker positions, and voltage indications to complete the surveillance.

A4R Perform Waste Gas Pressure Drop Calculation and Flow Rate Determination - (New)

Examinee will perform a Waste Gas pressure drop calculation and with this calculation they will use graphs of flowrate versus pressure drop to determine the discharge flowrate. The flowrate determined when performing a Waste Gas discharge is used to make adjustments to the discharge pressure control valve.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: 09/21/2020 Examination Level: RO SRO Operating Test Number: ES20LI Type Administrative Topic (see Note) Describe activity to be performed Code*

K/A 2.1.27 Knowledge of system purpose and /

Conduct of Operations (A1S) R,N or function.

SRO Assess the Inoperability of the Main Control Room Vital Assess Door K/A 2.1.36 Knowledge of procedures and Conduct of Operations (A2S) R,M limitations involved in core alterations.

Loss of Containment Closure K/A 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system Equipment Control (A3S) R,N conditions.

Review an AC Electrical Sources Inoperability assessment for one Emergency Diesel Inoperable.

K/A 2.3.6 Ability to approve release permits.

Radiation Control (A4S) R,D SRO Review and Approve a Radioactive Liquid Waste Release Permit K/A 2.4.41 Knowledge of the emergency action Emergency Plan (A5S) R,D level thresholds and classifications.

EAL Classification and PARs NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

(P)revious 2 exams ( 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 A1S - SRO Assess the Inoperability of the Main Control Room Vital Assess Door (New)

Examinee will assess the Inoperability of the Main Control Room Vital assess door. There will identify that it is a vital (security) door, a fire door, and a control room boundary. Then enter the TRM and Technical Specifications.

A2S Loss of Containment Closure - (NRC 2014 - Modify)

Examinee will identify a loss of Containment Closure, enter the appropriate Technical Specification Action Statement and direct actions to complete in-progress irradiated fuel moves in Containment and the Spent Fuel pool. They will then direct suspending all operations involving movement of irradiated fuel assemblies in Containment. The initial conditions will be changed to modify this JPM. It is identified that the Main Feedwater Check valve 2-FW-5A is open with disc removed without having a closure plan.

A3S Review an AC Electrical Sources Inoperability assessment for one Emergency Diesel Inoperable - (New)

Examinee will review an AC Electrical Sources Inoperability assessment for one Emergency Diesel (EDG) Inoperable. The surveillance will be for an EDG pre-lube and air roll. Photos of the control room boards will be used. The examinee will look at annunciators, breaker positions, and voltage indications to complete the review surveillance. The examinee will identify that two items on the surveillance are not correct.

A4S SRO Review and Approve a Radioactive Liquid Waste Release Permit - (NRC 2014 Bank JPM-A3S)

Examinee will review a radioactive liquid discharge permit and identify that the permit can not be authorized under the current conditions. The examinee will be provided with all the required paperwork to authorize the discharge. The examinee will identify that a second independent chemistry sample is required because the radiation monitor is out of service. They will also identify that a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> recirculation time is required because the mixer is not available. Based on these two conditions not met the examinee will determine the discharge cant be authorized.

A5S EAL Classification and PARs - (Bank JPM-190)

Examinee will correctly classify the event and provide the appropriate Protective Action Recommendation (PAR). This is a time critical JPM. The event is a steam generator tube leak that progresses to a steam generator tube rupture. As part of the event Main Steam Line radiation monitors alarm at a radiation level above the General Emergency threshold. Once the classification is determine the examinee determines the applicable PAR.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 2 Date of Examination: 09/21/2020 Exam Level: RO SRO-I SRO-U Operating Test Number: ES20LI Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function

a. S1 Respond to an ATWS (KA 029EA1.12) A,D,E,S 1

b. S2 Raising #1 SIT level Using the A HPSI Pump (KA 006A1.13) D,S 2

c. S3 PORV witch Failure on Once-Through-Cooling A,D,E,L,S 3 (KA 074EA1.05)

d. S4 Evaluate RCP Upper Oil Reservoir Problem (KA 010A2.02) A,D,E,S 4(P)

e. S5 Shifting Containment Air Recirculation Units (KA 022A4.01) A,D,E,S 5

f. S6 Cross-tie 480 Volt Busses (RO Only) (KA 062A4.01) D,S 6

g. S7 Reset Inadvertent SIAS (KA 013A4.02) A,D,E,EN,S 7

h. S8 Respond to a trip of the A RBCCW pump (KA 008A2.01) A,E,M,S 8 S9 (Spare) Manual Makeup to the RWST (KA 004A2.13) N,S 1 In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. P1 Local Manual Operation of a FRV (KA 059A2.11) D 4(S)

j. P2 Placing Inverter 1 in Service (KA 062A3.04) M 6

k. P3 Aligning Firewater to the MP2 EDGs (KA 064K1.02) M,E,L,R 8 P4 (Spare) Cross-tie Station Air with Unit 3 to Supply Unit 2 D,E,L 8 Instrument Air (KA 079A2.01)

P5 (Spare) Manual Operations RB-8.1A RB to SFPC (KA 008A4.06) D,E,R 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature 1/ 1/ 1 (control room system)

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

(R)CA 1/ 1/ 1 (S)imulator S1 Respond to an ATWS - Alternate Path - (Bank JPM-069)

Examinee observes the low flow trip alarms (RED) and recognizes that that the reactor should have automatically tripped and didnt. Examine attempts to trip the reactor by pressing the manual trip pushbuttons. The manual trip pushbuttons do not trip the reactor. The examinee then takes the Response Not Obtained Action to open the CEDM MG set feeder breakers. This succeeds in tripping the reactor.

S2 Raising #1 SIT Level Using the A HPSI Pump - (NRC 2011 Bank JPM-025)

Examinee will raise #1 Safety Injection Tank (SIT) level using the A HPSI pump. The examinee will close the A HPSI header stop, start the A HPSI pump, open the HPSI header stop, open the fill and drain valve and monitors recirculating header pressure while throttling open the header check valve leakage drain stop valve. SIT level and rate of fill is monitored on the PPC and when level has been raised the determined amount the fill is stopped.

S3 PORV Switch Failure on Once-Through-Cooling - Alternate Path - (NRC 2014 Bank JPM-118)

Examinee will perform Contingency Actions to open the PORV in response to a key switch failure. The examinee will be directed to initiate Once-Through-Cooling (OTC). All the actions to initiate OTC will be taken. But the PORVs will fail to open. The examinee will recognize this failure by the green valve position lights staying green when the PORV handswitches are taken to open. They will then perform (simulated) the Response Not Obtained Action to pull two channels of the high pressure trip modules on RPS. This will open the PORVs completing the actions to initiate OTC.

S4 Evaluate RCP Upper Oil Reservoir Problem - Alternate Path - (Bank JPM-302)

Examinee will receive an alarm for the C RCP. They will then observe indications and determine the C RCP upper lube oil reservoir level is lowering and that the reservoir level meets RCP trip criteria. The examinee will trip the reactor and secure the C RCP. The examinee will perform standard post trip actions in EOP 2525 and will recognize a stuck open spray valve and will secure the A RCP to mitigate the spray valve failure.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S5 Shifting Containment Air Recirculation Units - Alternate Path - (NRC 2014 Bank JPM-160)

Examinee is directed to start the D CAR fan and stop the B CAR fan. When the D CAR fan is started it trips. The trip annunciator for the D CAR fan is received and the alarm response procedure (ARP) referenced. The ARP directs starting the idle CAR fan. The examinee restarts the B CAR fan.

S6 Cross-tie 480 Volt Busses - (NRC 2014 Bank JPM-053)

Examine cross-ties 480 volt busses 22A and 22B, with 22B supplying bus 22A.

S7 Reset Inadvertent SIAS - Alternate Path - (NRC 2014 Bank JPM-281)

An inadvertent SIAS has occurred and Immediate Operations Actions have been performed. Examinee will be directed to reset SIAS using the applicable procedure. The examinee performs actions at ESAS to reset the SIAS. Actions taken by the examinee will not reset the SIAS. Contingency Actions will then be taken to mitigate the SIAS actuation. These actions include opening the TBCCW heat exchanger service water inlet valve, stopping HPSI and LPSI pumps, and closing LPSI injection valves.

S8 Respond to a Trip of the A RBCCW Pump - Alternate Path - (Modified JPM-278A)

Examinee will respond to a loss of the Facility 1 RBCCW with the spare RBCCW pump available.

Immediate Operators Actions will be performed, but the spare pump will not start. Contingency Actions will then be performed. The examinee will check that the overload trip alarm is not lit, obtain permission from the Shift Manager and then reset and restart the Facility 1 RBCCW pump. This is a bank JPM that is being modified to the use the Contingency Action. The current JPM trips the plant and the RCPs that are supplied by Facility 1 RBCCW.

S9 (Spare) Manual Makeup to the RWST - (New)

Examinee will perform a manual blended makeup to the Refueling Water Storage Tank (RWST). The examinee will be provided with the blend ratio and be directed to raise level by 1 %. Once the makeup has started and the examinee is monitoring the RWST level rise the JPM will be stopped.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 P1 Local Manual Operation of a FRV - (Bank JPM-063)

Examinee will be directed to simulate taking manual local control of the No. 1 Main Feedwater Regulating valve (FRV). This requires establishing communications with the control room, operating two handwheels to engage the large operating handwheel and then opening the Instrument Air equalizing valve. This was a spare JPM for the 2017 NRC Retake exam that was not used.

P2 Placing Inverter 1 in Service - (Modified Bank JPM-056)

Examinee will place Vital Inverter No. 1 in service. This is a new inverter. It requires manipulation of switches and understanding indications on the inverter front panel.

P3 Aligning Firewater to the MP2 EDGs - (Modified -Bank JPM-260A)

The unit will be in MODE 6 with the RCS vented and the Refuel Pool less than 35 6. The examinee will be assigned the duty of the operator stationed in the Auxiliary Building 14 6 vital area (RCA) ready to take action to shift EDG cooling water to Fire Water. Once assigned the examinee will be directed to align the A Emergency Diesel Generator to Fire Water using the procedure provided. The examinee will then simulate this task. This bank JPM is being modified by changing the initiating conditions and procedure used. It will be performed in the RCA without having to go in and out of the RCA.

P4 (Spare) Cross-tie Station Air with Unit 3 to Supply Unit 2 Instrument Air - (NRC 2005 Bank JPM-177)

Examinee will simulate valve alignments to cross-tie Unit 2 Station Air with Instrument Air, and then aligned Unit 2 Station Air with Unit 3 Service Air. This results in Unit 3 Service Air supplying Unit 2 Instrument Air. This requires simulated valve manipulation at the Station Air receiver, the Turbine building northwest stairway, and in the Condensate Polishing Facility railway access. This was a spare for the 2018 NRC exam that was not used.

P5 (Spare) Manual Operation of RB-8.1A RB to SFPC - (Bank JPM-244)

Examinee will restore cooling to the Spent Fuel Pool by simulating opening an Air Operated valve to from RBCCW to the SFPC system. The valve is located in the Auxiliary Building -25 6 elevation (RCA).

Examinee simulates closing valve bypass then rotating counterclockwise the torque motor handwheel to open the valve supplying cooling to the SFPC system.