Text

Final Written Examination and Operating Test Outlines (Folder 3)
	ML19045A424
Person / Time
Site:	Millstone
Issue date:	02/14/2019
From:	Brian Fuller; Operations Branch I
To:	; Dominion Energy Nuclear Connecticut
Shared Package
ML17234A732	List: ML18323A272; ML18323A273; ML18323A274; ML19044A566; ML19044A586; ML19045A343; ML19045A416; ML19045A424;
References
	CAC 000500
	Download: ML19045A424 (28)
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ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Millstone Unit 2 Date of Examination:

09/10/2018 Examination Level: RO SRO Operating Test Number:

ES18LI Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations (A1.1R)

R, D K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves and tables.

Determine Maximum Rate of Change of Power.

Conduct of Operations (A1.2R)

R, D K/A 2.1.20 Ability to interpret and execute procedure steps.

Calculate Spent Fuel Pool Heatup Time To 150 F.

Equipment Control (A2R)

R, N K/A 2.2.13 Knowledge of tagging and clearance procedures.

Prepare a Clearance for the A Containment Spray Pump.

Radiation Control (A3R)

R, N K/A 2.3.11 Ability to control radiation releases.

Flow Rate and Discharge Volume Calculation for a Clean Radioactive Liquid Waste Discharge.

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 A1.1R Determine Maximum Rate of Change of Power (Bank JPM-08-04)

At the completion of this JPM the examinee has correctly determined the applicable Fuel Conditioning Category, maximum rate of change in power level, and the minimum amount of time required to achieve 100% power.

A1.2R Calculate Spent Fuel Pool Heatup Time to 150 F (NRC 2011 A2R)

At the completion of this JPM the examinee has correctly determined the Spent Fuel Pool (SFP)

Heatup rate and time. The examinee is provided with a set of plant conditions and is directed to perform a calculation to determine when the SFP will reach 150 F.

A2R Prepare a Clearance for the A Containment Spray Pump (New)

At the completion of this JPM the examinee has correctly reviewed a clearance boundary associated with the A Containment Spray pump. The examinee must review a prepared clearance, determine the clearance is not adequate, and specify the deficiencies with the clearance.

A3R Flow Rate and Discharge Volume Calculation for a Clean Radioactive Liquid Waste Discharge (New)

At the completion of this JPM the examinee has used data provided to manually calculate the discharge flow rate and volume discharged. The manual calculation is required as a result of the inoperability of the flow recorder.

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Millstone Unit 2 Date of Examination:

09/10/2018 Examination Level: RO SRO Operating Test Number:

ES18LI Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations (A1S)

R, D K/A 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Shift Staffing Based on Administrative Requirements.

Conduct of Operations (A2S)

R, N K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves and tables.

Review a Power Ascension Plan.

Equipment Control (A3S)

R, D K/A 2.2.14 Knowledge of the process for controlling equipment configuration or status.

Approve a Clearance Boundary.

Radiation Control (A4S)

R, D K/A 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

Radiological Assessment and Task Supervision.

Emergency Plan (A5S)

R, D, P K/A 2.4.41 Knowledge of the emergency action 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 Shift Staffing Based on Administrative Requirements (NRC 2008 A1.1S)

At the completion of this JPM, the SRO will determine who is fit for duty and can be called in for shift coverage when the on shift RO becomes incapacitated (cannot perform licensed activities).

The examinee must determine how soon a relief must report for work, which relief is immediately eligible to assume shift duties, and for those reliefs not eligible the reason they are not eligible.

A2S Review a Power Ascension Plan (New)

At the completion of this JPM, the SRO has reviewed the provided power ascension plan and determined that it does not meet procedural requirements and identifies which specific requirements are not met. The SRO must assess the Fuel Conditioning Category, maximum rate of change in power level, and the minimum amount of time required to achieve 100%

power.

A3S Approve a Clearance Boundary (NRC 2008 A2S)

Given a completed Clearance Sheet and associated documents the examinee is tasked with reviewing and approving the Tag Clearance. Upon review the examinee will determine that the Clearance is not adequate to perform the work proposed since the tags for pump power supply and pump discharge stop valve are not correct.

A4S Radiological Assessment and Task Supervision (NRC 2011 A3S)

At the completion of this JPM, the SRO has analyzed the given conditions and designated which PEO should perform each of the two specified tasks, based on the radiological concerns of each. The SRO is provided with radiation information for the area, time to complete the tasks for an experienced PEO and newly qualified PEO, current exposure for the year for the two PEOs.

A5S EAL Classification and PARs (NRC 2016 Bank JPM-298)

At the completion of this JPM the examinee has correctly classified the event and provided the appropriate Protective Action Recommendations (PARs). The examinee classifies a General Emergency Alpha, due to the loss of three barriers, within 15 minutes. And then determines the PARs, within 15 minutes of the classification time, with associated evacuation and sheltering information.

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

Millstone Unit 2 Date of Examination:

09/10/2018 Exam Level: RO SRO-I SRO-U Operating Test Number:

ES18LI Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function S1 Manual Makeup to the VCT (KA 004 A2.06)

A,D,S 1

S2 Inadvertent AEAS Actuation (KA 013 A2.06)

EN,N,S 2

S3 Respond to a Failed Open PORV (KA 010 A2.03)

A,D,S 3

S4 Respond to CTMT Sump Clogging (KA 011 EA1.11)

A,D,L,S 4(P)

S5 Containment Isolation and CRAC Operation due to Fuel Handling Accident (KA 103 A4.01)

A,M,S 5

S6 Transfer Electrical Buses from the NSST to the RSST (KA 062 A4.01)

N,S 6

S7 Securing of CVCS due to VCT Level Instrument Failure (RO Only) (KA 016 A2.02)

N,S 7

S8 Change the Setpoint of the SJAE RM 5099 (KA 071 A4.25)

D,S 9

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U P1 Supplying Emergency Backup Air to 2-CH-192 (KA 2.1.23)

D,E,R 8

P2 Local Manual Air Start of the Emergency Diesel Generator (KA 064 A4.06)

D,E 6

P3 Local Manual Operation of the Turbine Driven Auxiliary Feedwater Pump (KA 054 AA1.02)

A,D,E,L 4(S)

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6 /2-3 9/ 8/ 4 1/ 1/ 1 1/ 1/ 1 (control room system) 1/ 1/ 1 2/ 2/ 1 3/ 3/ 2 (randomly selected) 1/ 1/ 1 S1 Manual Makeup to the VCT - Alternate Path - (NRC 2011 Bank JPM-022)

At the completion of this JPM the examinee has recognized a malfunction with Boric Acid injection, during attempted manual makeup to the Volume Control Tank (VCT), and terminates the dilution. The examinee is provided with a Blend Ratio and is directed to raise VCT level by 2%. The examinee must set up the Boric Acid and Primary Makeup Water controllers with the proper blend, align the system for the blend, determine the number of gallons required for a 2% change to the VCT and initiate the blended makeup.

Once the blend commences the examinee determines there is no Boric Acid flow and terminates the dilution.

S2 Inadvertent AEAS Actuation (New)

At the completion of this JPM the examinee has reset the Engineered Safety Features Actuation System (ESFAS). The examinee will be directed to complete procedure steps for an inadvertent Auxiliary Exhaust Actuation Signal (AEAS). The examinee will check Spent Fuel Pool radiation is less than 50 mr/hr, align Condenser Air Removal to the Unit 2 Stack and then reset the AEAS signal on the ESFAS.

S3 Respond to a Failed Open PORV - Alternate Path - (Bank JPM-280(A))

The examinee will carry out Immediate Operator Actions for a failed open Power Operated Relief Valve (PORV). At the completion of this JPM the examinee will recognize that PORV, RC-402 has failed open by any or all of the following; RCS pressurizer lowering, Main Control Board annunciator and valve indicator lights. They will then verify RCS pressure < 2,250 psia and close the PORV Block valve RC-403. The Block valve will fail to close. This will require the examinee to take contingency action to trip the reactor. The manual reactor trip must be initiated prior to an automatic trip for the JPM to completed successfully.

S4 Respond to CTMT Sump Clogging - Alternate Path - (Bank JPM-156)

At the completion of this JPM the examinee will have performed SRAS supplemental actions, assessed HPSI pump post SRAS performance, determined that HPSI pump performance is degraded as a result of sump clogging, and taken Contingency Actions to stop the running Containment Spray (CS) pumps. The examinee will determine that HPSI performance is still degraded after stopping the CS pumps and will implement additional Contingency Actions to throttle HPSI to a flow value greater than or equal to the minimum ECCS flow for decay heat removal.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S5 Containment Isolation and CRAC Operation due to Fuel Handling Accident - Alternate Path (Modified NRC 2011 Bank JPM-S5.1)

At the completion of this JPM, the examinee will have performed the actions of AOP 2577, Fuel Handling Accident, Section 3.0, Fuel Handling Accident in Containment. This includes performing the applicable actions to have containment evacuated, isolate containment ventilation and place a full train of Control Room A/C (CRAC) in service in Recirc. mode. When the examinee places the running train of CRAC (Facility 1) in Recirc per the AOP, the running exhaust fan, F-31A, will trip and its exhaust damper will close. This will require the examinee to proceed to the next part of the step covering Facility 2 CRAC and fully start that facility and place it in Recirc. mode.

S6 Transfer Electrical Buses from the NSST to the RSST (New)

At the completion of this JPM the examinee has transferred a 6.9 KV bus and a 4.16 KV bus from the Normal Station Service Transformer (NSST) to the Reserve Station Service Transformer (RSST). The examinee will ensure the RSST is energized from the 345 KV bus to both the 6.9 KV and 4.16 KV windings. They will then perform switch manipulations to transfer both a 6.9 KV bus and 4.16 KV bus from the NSST to the RSST.

S7 Securing of CVCS due to VCT Level Instrument Failure (RO Only) (New)

At the completion of this JPM the examinee has identified the lost of vital instrument bus VA-10 and isolated Charging and Letdown. A loss of VA-10 will fail one of the VCT level instruments causing the Charging pump suction to transfer from the Volume Control Tank (VCT) to the Refueling Water Storage Tank (RWST). This starts boration of the RCS. If this boration is not stopped additional complications resulting from the loss of VA-10 (one Feedwater Regulating valve locks up) will challenge the ability to maintain the plant operating. The examinee must recognize that a loss of VA-10 has occurred in the mist of multiple alarms. And take immediate operator actions to secure Charging and Letdown by closing a Letdown valve and turning off all Charging pumps.

S8 Change the Setpoint of the SJAE RM 5099 (NRC 2005 Bank JPM-120)

At the completion of this JPM the examinee will have adjusted the setpoint of the Steam Jet Air Ejector Radmonitor (RM 5099) to a new setpoint. The examinee will be provided a SJAE Radiation Monitor RM 5099 & PPC Alarm Setpoint Change Request. Then using this information the setpoint will be changed and then verified.

P1 Supplying Emergency Backup Air to 2-CH-192 (NRC 2011 Bank JPM-045)

At the completion of this JPM the examinee will have aligned a Backup Air supply to the valve that aligns water from the Refueling Water Storage Tank (RWST) to the suction of the Charging pumps (CH-192).

This alignment provides borated water to the Reactor Coolant system (RCS) for reactivity control. The examinee must sign onto a Radiation Work Permit (RWP), enter the Radiation Control Area (RCA), go to the backup air bottle location, and simulate valve manipulations to align Backup Air at a specified pressure.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 P2 Local Manual Air Start of the Emergency Diesel Generator (NRC 2008 Bank JPM-060A(B))

At the completion of this JPM, the examinee will have performed a local manual air start of the A (B)

Emergency Diesel Generator EDG). The examinee must go to the EDG, which is located outside the RCA. Then simulate resetting the local panel alarms, simulate ensuring the Shutdown Relay (SDR) is reset, simulate unlocking and closing the EDG Air Start Vent Header isolation valves, simulate coordination to have the EDG Manual Start Switch placed in start in the control room, and simulate locally starting the EDG by pressing on the levers on the Control Air Supply valves. Once the EDG has simulated starting the lever is released and the Air Start Vent Header isolation valves are simulated opened and locked to return the system to a normal configuration.

P3 Local Manual Operation of the Turbine Driven Auxiliary Feedwater Pump (Bank JPM-085(A))

At the completion of this JPM, the examinee has simulated manually starting the Turbine Driven Auxiliary Feedwater (TDAFW) pump locally. The examinee must simulate checking temperatures in the area, simulate opening the steam supply to the Turbine, identify that the TDAFW pump has tripped, and simulate closing the steam supply. Once the steam supply valve is simulated closed the examinee simulates valve manipulation to drain water out of the steam supply piping, and simulates resetting the TDAFW pump mechanical overspeed trip latch. Once the TDAFW pump turbine is reset the examinee simulates opening the steam supply valve and simulates adjusting the speed control knob to raise the TDAFW pump speed to a condition required to feed the Steam Generators. Local speed indication, Steam Generator pressure and TDAFW pump discharge pressure are indications utilized by the examinee to simulate starting and bringing the TDAFW pump to the conditions required to feed the Steam Generators.

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

Millstone Unit 2 Date of Examination:

09/10/2018 Exam Level: RO SRO-I SRO-U Operating Test Number:

ES18LI Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function S1 Manual Makeup to the VCT (KA 004 A2.06)

A,D,S 1

S2 Inadvertent AEAS Actuation (KA 013 A2.06)

EN,N,S 2

S3 Respond to a Failed Open PORV (KA 010 A2.03)

A,D,S 3

S4 Respond to CTMT Sump Clogging (KA 011 EA1.11)

A,D,L,S 4(P)

S5 Containment Isolation and CRAC Operation due to Fuel Handling Accident (RO Only) (KA 103 A4.01)

A,M,S 5

S6 Transfer Electrical Buses from the NSST to the RSST (KA 062 A4.01)

N,S 6

S7 Securing of CVCS due to VCT Level Instrument Failure (RO Only) (KA 016 A2.02)

N,S 7

S8 Change the Setpoint of the SJAE RM 5099 (KA 071 A4.25)

D,S 9

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U P1 Supplying Emergency Backup Air to 2-CH-192 (KA 2.1.23)

D,E,R 8

P2 Local Manual Air Start of the Emergency Diesel Generator (KA 064 A4.06)

D,E 6

P3 Local Manual Operation of the Turbine Driven Auxiliary Feedwater Pump (KA 054 AA1.02)

A,D,E,L 4(S)

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1(A)