Text

CW 2024-301 2A-3 Administrsative
	ML24326A184
Person / Time
Site:	Catawba
Issue date:	11/21/2024
From:	; NRC/RGN-II
To:	; Duke Energy Corp
References
	Download: ML24326A184 (1)
	v • d • e

Form 3.2-1 Administrative Topics Outline Facility: __Catawba Nuclear Station______________

Date of Examination: __Sept 2024__

Examination Level:

RO SRO Operating Test Number: 2024301 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations VCT Blended Makeup Calculation 2.1.23 Ability to perform general and/or normal operating procedures during any plant condition (4.3)

R,N Conduct of Operations Perform a Manual Leakage Calculation 2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation (4.4)

R,D Equipment Control Determine NC Subcooling on a Loss of OAC 2.2.12 Knowledge of Surveillance Procedures (3.7)

R,M Radiation Control Determine Required Dose Extension 2.3.12 Knowledge of radiological safety principles and procedures pertaining to license operator duties. (3.2)

R,D ML24326A184

Instructions for completing Form 3.2-1, Administrative Topics Outline

1. For each license level, determine the number of administrative job performance measures (JPMs) and topic areas as follows:

Topic Number of JPMs RO*

SRO and RO Retakes Conduct of Operations 1 (or 2) 2 Equipment Control 1 (or 0) 1 Radiation Control 1 (or 0) 1 Emergency Plan 1 (or 0) 1 Total 4

5

2. Enter the associated knowledge and abilities (K/A) statement and summarize the administrative activities for each JPM.

3. For each JPM, specify the type codes for location and source as follows:

Location:

(C)ontrol room, (S)imulator, or Class(R)oom Source and Source Criteria:

(P)revious two NRC exams (no more than one JPM that is randomly selected from last two NRC exams)

(D)irect from bank (no more than three for ROs, no more than four for SROs and RO retakes)

(N)ew or Significantly (M)odified from bank (no fewer than one)

Reactor operator (RO) applicants do not need to be evaluated on every topic (i.e., Equipment Control, Radiation Control, or Emergency Plan can be omitted by doubling up on Conduct of Operations), unless the applicant is taking only the administrative topics portion of the operating test (with a waiver or excusal of the other portions).

Administrative JPMs - RO JPM A.1-1R - Manual VCT Blended Makeup Calculation - NEW JPM K/A Generic 2.1.23 Ability to perform general and/or normal operating procedures during any plant condition (CFR 41.10 / 43.5 / 45.2 / 45.6) IMPORTANCE: 4.3 / 4.4 Initial conditions are that Unit 1 is at 100% RTP with the NC Makeup Control in Manual for calibration of VCT level instrumentation. Level calibration is complete. Crew is preparing to perform a 300 gallon manual blended makeup to the VCT for a functional on VCT level. Applicant is given initial conditions for VCT level, NC Boron Concentration, BAT #1 Boron concentration, RMWST Boron concentration, and NC System Tavg.

Initiating cue is the CRS directs the applicant to perform applicable steps of OP/1/A/6150/009 (Boron Concentration Control) Enclosures 4.5, 4.5.1, and 4.1 to determine the amount of boric acid to be added for the blended makeup to maintain current NC system boron concentration and to lower NC system Tavg by 0.1°F and to determine the settings needed for the NV makeup controllers for 1NV-238A and 1NV-242A for a 90 gpm total makeup flow in preparation for placing the system back in AUTO.

JPM A.1-2R - Perform a Manual NC System Leakage Calculation - Bank JPM K/A Generic 2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation (CFR 41.5 / 43.5 / 45.12 / 45.13) IMPORTANCE: 4.4 / 4.7 Initial conditions have Unit 1 at 100% RTP with the Operator Aid Computer out of service.

Initiating cue is the CRS directs the applicants to perform an NC System Leakage Calculation per PT/1/A/4150/001 D (NC System Leakage Calculation). Applicants are also given a Data Sheet with values measured 64 minutes apart for NC System Tavg, VCT level, Pzr level, NCDT level, and PRT level. Data Sheet also has values for individual NC pump #1 Seal Leakoff flows and S/G Tube Leakage EMF readings. Applicants will determine that Unidentified Leakage is 8.628 - 8.828 gpm, Identified Leakage is 2.2 -

2.3 gpm, Total Accumulated Leakage is 21.538 - 21.838 gpm. Applicant determines that LCOs for T.S. 3.4.13 and SLC 16.7-9 are NOT met.

JPM A.2R - Determine NC Subcooling on a loss of OAC - Modified Bank JPM (Modified NC temperatures so that calculated subcooling was above the required 30°F)

K/A Generic 2.2.12 Knowledge of Surveillance Procedures (CFR 41.10 / 43.2 / 45.13)

IMPORTANCE 3.7 / 4.1 Initial conditions are that Unit 1 is in Mode 3 and has experienced a loss of the Operator Aid Computer. PT/1/A/4600/009 (Loss of Operator Aid Computer) is in progress with both trains of the Plasma display monitors inoperable. The applicants are given a table of values for different NC System temperatures and pressures and are directed to complete 3.8 (Subcooling Data Sheet) to determine the °F that the NC system is subcooled and determine if the amount of subcooling margin meets the acceptance criteria of PT/1/A/4600/009. Applicants will determine the subcooling margin is 33 - 48°F and that this does meet the acceptance criteria of 30°F subcooling for the current Mode 3 condition.

JPM A.3R - Calculate total dose received for a job and determine if dose extension is required

- Bank JPM (MNS 2023 Audit Admin JPM A.3R)

K/A Generic 2.3.12 Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to high radiation areas, or alignment of filters (CFR 41.12 / 43.4 / 45.9 / 45.10) IMPORTANCE: 3.2 / 3.7 Initial conditions are that Unit 1 is in a refueling outage and the applicants have been assigned a job to complete non-emergency maintenance in the field in the Auxiliary Building. Applicants are given dose received this year at CNS and MNS and given the highest dose rate in the area of the work and told that the job will take between 60 and 90 minutes to complete. Initiating cue is that the WCC SRO directs the applicant to predict the MAXIMUM dose expected to be received for the job, to identify if any dose limit extensions are required, and if any extensions are required to determine who must approve the extension. Applicants will determine the MAXIMUM expected dose to be received will be 105 mrem, that the operator will require an extension, and that the extension must be approved by the Requesting Manager and the Radiation Protection Manager.

Form 3.2-1 Administrative Topics Outline Facility: __Catawba Nuclear Station_________

Date of Examination: _Sept 2024_____

Examination Level:

RO SRO Operating Test Number: _2024301__

Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations Review D/G Run Logbook Entry per OMP 2-28 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports (3.8)

R,N Conduct of Operations Determine License Status 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no solo operation, and maintenance of active license status, 10 CFR Part 55 (3.8)

R,M Equipment Control Determine Status of Decay Heat Removal Key Safety Function 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments and work prioritization (3.9)

R,N Radiation Control Review Total RL Discharge Flow and determine LWR approval 2.3.11 Ability to control radiation releases (4.3)

R,D,P Emergency Plan Classify an Event and Fill Out the Emergency Notification Form 2.4.41 Knowledge of emergency action level thresholds and classifications (4.6)

R,N

Instructions for completing Form 3.2-1, Administrative Topics Outline

1. For each license level, determine the number of administrative job performance measures (JPMs) and topic areas as follows:

Topic Number of JPMs RO*

SRO and RO Retakes Conduct of Operations 1 (or 2) 2 Equipment Control 1 (or 0) 1 Radiation Control 1 (or 0) 1 Emergency Plan 1 (or 0) 1 Total 4

5

2. Enter the associated knowledge and abilities (K/A) statement and summarize the administrative activities for each JPM.

3. For each JPM, specify the type codes for location and source as follows:

Location:

(C)ontrol room, (S)imulator, or Class(R)oom Source and Source Criteria:

(P)revious two NRC exams (no more than one JPM that is randomly selected from last two NRC exams)

(D)irect from bank (no more than three for ROs, no more than four for SROs and RO retakes)

(N)ew or Significantly (M)odified from bank (no fewer than one)

Reactor operator (RO) applicants do not need to be evaluated on every topic (i.e., Equipment Control, Radiation Control, or Emergency Plan can be omitted by doubling up on Conduct of Operations), unless the applicant is taking only the administrative topics portion of the operating test (with a waiver or excusal of the other portions).

Administrative JPMs - SRO JPM A.1-1S - Review Diesel Generator Run Logbook Entry - NEW JPM K/A Generic 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports (CFR 41.10 / 45.12 / 45.13) IMPORTANCE: 3.6 / 3.8 Initial conditions are that the 1A D/G has been run per PT/1/A/4350/002 A (Diesel Generator 1A Operability Test). Applicants are given a timeline of the D/G run and told that the AOs have filled out OMP 2-28 Attachments 10.1 (Diesel Generator Log Sheet) and 10.2 (Index Sheet) for 1A D/G run and brought it to the control for approval. Initiating cue is for the applicants to review OMP 2-28 Attachments 10.1 and 10.2 and determine if the logbook entry should be approved and if applicable to list all issues that would prevent approval of the logbook entry. Applicants will determine that the logbook entry should NOT be approved due to the following: time loaded to > 2875 KW should be listed as 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months , and that the diesel run should be classified as a VALID FAILURE versus the listed INVALID TEST. Once they determine that the diesel run was a VALID FAILURE, a CR should be written to document the failure.

JPM A.1-2S - Determine License Status - Modified Bank JPM (Changed the hours worked for each of the listed individuals to change the correct answer)

K/A Generic 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical records, no-solo operation, maintenance of active license status, 10 CFR Part 55. (CFR 41.10 / 43.2) IMPORTANCE: 3.3 / 3.8 Initial conditions are that the applicant is evaluating the work histories of 3 licensed Senior Reactor Operators. All 3 have off shift assignments, are current in Licensed Operator Requalification training, and have had a medical exam in the past 2 years. Applicants are given a work history table for the second quarter and Unit power history for Units 1 and

2. Initiating cue is for the applicant to determine if each of the SROs are eligible to stand watch in the CRS position on July 1, 2024. If not eligible, the applicants need to state the reason why. Applicants will determine that one SRO is eligible to stand watch as the CRS on July 1st and the other 2 SROs are not.

JPM A.2S - Determine Status of Decay Heat Removal Key Safety Function - NEW JPM K/A Generic 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments and work prioritization (CFR 41.10 / 43.5 / 45.13) IMPORTANCE: 2.6 / 3.9 Applicants are given initial conditions for Unit 1 in Mode 5 for a refueling outage. Unit is in a Loops Not Filled condition with 1A D/G tagged out for maintenance and 2B RN pump removed from service for PMs. Subsequently 1B RN pump trips. Initiating cue is that the SM has directed the applicant to evaluate the Decay Heat Removal Key Safety Function status per AD-WC-ALL-0420 (Shutdown Risk Management) Attachment 3 (PWR Defense In Depth (DID) Status Sheet) by determining whether 2 points can be credited for #3 (1 Decay Heat Removal Train Available) and whether 1 point for #5 (Secondary Heat Sink Available) can be credited. Applicant determines that 2 points for 1 Decay Heat

Removal Train Available can NOT be credited and that 1 point for Heat Sink Available can NOT be credited on Attachment 3 of AD-WC-ALL-0420.

JPM A.3S - Review Total RL Discharge Flow and Determine Liquid Waste Release Approval -

Bank JPM / Previous 2 NRC Exams (2023 JPM A.3S)

K/A Generic 2.3.11 Ability to control radiation releases (CFR 41.11 / 43.4 / 45.10)

IMPORTANCE: 3.8 / 4.3 Initial conditions are that the low pressure service water discharge header flow instrumentation is inoperable and an LWR package has been delivered to the control room for approval. Applicants are given plant conditions and directed to review PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination) and determine if conditions exist to allow approval of the LWR. Applicant will determine that dilution flow has been miscalculated and the sufficient dilution flow does NOT exist for the LWR approval.

JPM A.4S - Classify an Event and Fill Out the Emergency Notification Form - NEW JPM K/A Generic 2.4.40 Knowledge of SRO responsibilities in emergency plan implementing procedures (CFR 43.5 / 45.11) IMPORTANCE: 4.5 Initial conditions are that both Units are at 100% RTP with 1A CA pump tagged out. A seismic event has been felt within the protected area. A Loss of Offsite Power (LOOP) occurs on both Units. 1B D/G fails to start. CAPT #1 experiences a mechanical overspeed trip. All S/G N/R levels are 5% and lowering slowly. Initiating cue is for the applicant as the Emergency Coordinator to classify this event per AD-EP-ALL-0101 (Emergency Classification) and to fill out the Emergency Notification Form per AD-EP-ALL-0304. This JPM is time critical for both the classification (< 15 minutes) and filling out the ENF form (<

15 minutes).

Form 3.2-2 Control Room/In-Plant Systems Outline Facility: _Catawba Nuclear Station______ Date of Examination: Sept 2024 Operating Test Number: 2024301 Exam Level:

RO SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems

a.

Align Charging with NV Miniflow Valves Closed -

004 K6.14 (3.4)

A,D,L,S 1

b.

Perform ES-0.1 Actions to Ensure Complete Feed Isolation A,EN,L,N,S 2

c.

Isolate Cold Leg Accumulators During Shutdown LOCA A,L,D,P,S 3

d.

Establish NC System Bleed and Feed L,M,S 4P

e.

Isolate Faulted Steam Generator A,L,D,S 4S

f.

Upper Containment Ventilation Unit Additional Cooling N,S 5

g.

Shift Operating Condenser Circulating Water Pumps M,S 8

h.

Restore Normal Power to 1ETA from the Control Room D,S 6

In-Plant Systems

i. Establish Seal Injection from the SSF during a Loss of All AC A,E,L,N 6

j. Operate 2A Hydrogen Igniters from the SSF D,E,L,R 5

k. Align Alternate Cooling to 1A NV Pump D,E,R 8

1. Determine the number of control room system and in-plant system job performance measures (JPMs) to develop using the following table:

License Level Control Room In-Plant Total Reactor Operator (RO) 8 3

11 Senior Reactor Operator-Instant (SRO-I) 7 3

10 Senior Reactor Operator-Upgrade (SRO-U) 2 or 3 3 or 2 5

2. Select safety functions and systems for each JPM as follows:

Refer to Section 1.9 of the applicable knowledge and abilities (K/A) catalog for the plant systems organized by safety function. For pressurized-water reactor operating tests, the primary and secondary systems listed under Safety Function 4, Heat Removal from Reactor Core, in Section 1.9 of the applicable K/A catalog, may be treated as separate safety functions (i.e., two systems, one primary and one secondary, may be selected from Safety Function 4). From the safety function groupings identified in the K/A catalog, select the appropriate number of plant systems by safety functions to be evaluated based on the applicants license level (see the table in step 1).

For RO/SRO-I applicants: Each of the control room system JPMs and, separately, each of the in-plant system JPMs must evaluate a different safety function, and the same system or evolution cannot be used to evaluate more than one safety function in each location. One of the control room system JPMs must be an engineered safety feature.

For SRO-U applicants: Evaluate SRO-U applicants on five different safety functions.

One of the control room system JPMs must be an engineered safety feature, and the same system or evolution cannot be used to evaluate more than one safety function.

3. Select a task for each JPM that supports, either directly or indirectly and in a meaningful way, the successful fulfillment of the associated safety function. Select the task from the applicable K/A catalog (K/As for plant systems or emergency and abnormal plant evolutions) or the facility licensees site-specific task list. If this task has an associated K/A, the K/A should have an importance rating of at least 2.5 in the RO column. K/As that have importance ratings of less than 2.5 may be used if justified based on plant priorities; inform the NRC chief examiner if selecting K/As with an importance rating less than 2.5.

The selected tasks must be different from the events and evolutions conducted during the simulator operating test and tasks tested on the written examination. A task that is similar to a simulator scenario event may be acceptable if the actions required to complete the task are significantly different from those required in response to the scenario event.

Apply the following specific task selection criteria:

At least one of the tasks shall be related to a shutdown or low-power condition.

Four to six of the tasks for RO and SRO-I applicants shall require execution of alternative paths within the facility licensees operating procedures. Two to three of the tasks for SRO-U applicants shall require execution of alternative paths within the facility licensees operating procedures.

At least one alternate path JPM must be new or modified from the bank.

At least one of the tasks conducted in the plant shall evaluate the applicants ability to implement actions required during an emergency or abnormal condition.

At least one of the tasks conducted in the plant shall require the applicant to enter the radiologically controlled area. This provides an excellent opportunity for the applicant to discuss or demonstrate radiation control administrative subjects.

If it is not possible to develop or locate a suitable task for a selected system, return to step 2 and select a different system.

4. For each JPM, specify the codes for type, source, and location:

Code License Level Criteria RO SRO-I SRO-U (A)lternate path 4-6 (5) 4-6 (5) 2-3 (3)

(C)ontrol room (D)irect from bank 9 (6) 8 (5) 4 (2)

(E)mergency or abnormal in-plant 1 (3) 1 (3) 1 (2)

(EN)gineered safety feature (for control room system) 1 (1) 1 (1) 1 (1)

(L)ow power/shutdown 1 (7) 1 (7) 1 (4)

(N)ew or (M)odified from bank (must apply to at least one alternate path JPM) 2 (5) 2 (5) 1 (3)

(P)revious two exams (randomly selected) 3 (1) 3 (1) 2 (0)

(R)adiologically controlled area 1 (2) 1 (2) 1 (1)

(S)imulator

Control Room System JPMs JPM a - Align Charging with NV Miniflow Valves Closed - Bank JPM - Alternate Path K/A 004 K6.14 Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Chemical and Volume Control System (CFR: 41.5 to 41.7 / 45.7) IMPORTANCE: 3.4 Initial conditions are that Unit 1 has experienced a LOCA. The crew is performing actions of EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization). Initiating cue is that the CRS has directed the applicants to continue with steps in ES-1.2. The applicants will begin with verifying conditions to establish normal charging. They will then attempt to isolate the NV S/I flowpath, but the NV Miniflow isolation valves are closed. The applicant will attempt to open these valves but will be unsuccessful. This begins the ALTERNATE PATH for this JPM. The applicants will then transition to EP/1/A/5000/G-1 (Generic Enclosures) Encl. 13 (Aligning Charging with NV Miniflow Valves Closed). The applicants will align the normal charging flowpath, setting up the charging flow control valve for the current reactor coolant pressure to ensure that the NV pump miniflow will be maintained

> 80 GPM. The applicants will then isolate the NV S/I flowpath and establish proper NC pump seal water flow to complete the JPM.

JPM b - Perform ES-0.1 Actions to Ensure a Complete Feedwater Isolation - NEW JPM -

Alternate Path K/A 013 A4.14 Ability to manually operate and/or monitor in the control room: MFW isolation/reset (CFR 41.6 / 41.7 / 45.5 to 45.8) IMPORTANCE 3.9 Initial conditions are that the applicants are the OATC with the BOP having stepped out of the control room and the CRS performing an IPTE brief on Unit 2. Initiating cue is for the applicants to monitor the control boards. Subsequently, an inadvertent Turbine/Reactor trip will occur and the applicants will perform the immediate actions of E-0 (Reactor Trip or Safety Injection) with no failures. An examiner cue will be given for the applicant to begin at step 6 of ES-0.1 (Reactor Trip Response). The applicant will perform steps to verify that the Main Generator is offline and then steps to verify Feedwater Isolation. The applicant will determine that Feedwater Isolation has not automatically initiated and will manually initiate it. This begins the ALTERNATE PATH.

The applicant will identify that the feedwater isolation status lights are not lit for 1B and 1C S/Gs and will transition to ES-0.1 Encl. 3 (Closure of Feedwater Isolation Valves) and will manually close the S/G 1B CF Containment Isolation valve and the S/G 1C CA Nozzle Tempering Isolation valve to complete the JPM.

JPM c - Isolate Cold Leg Accumulators During Shutdown LOCA - Bank JPM given on the previous 2 NRC exams (2021 NRC JPM B) - Alternate Path K/A 006 A1.13 - Ability to predict and/or monitor changes in parameters associated with operation of the Emergency Core Cooling System, including: Safety Injection tank pressure, level, and boron concentration (CFR: 41.5 / 45.5 / 45.3 / 45.4) IMPORTANCE: 3.5 Initial conditions are Unit 1 is in Mode 4 when pressurizer level and pressure begin to decrease uncontrollably. The CRS enters AP/1/A/5500/027 (Shutdown LOCA) to

address the LOCA. The CRS directs the applicant to isolate the Unit 1 Cold Leg Accumulators by performing Enclosure 17 (Isolating Cold Leg Accumulators) of AP/27.

The applicant will attempt to close all Cold Leg Accumulator discharge isolation valves, but only 1B and 1C will isolate. The applicant will transition to the RNO to begin the ALTERNATE PATH. Applicant will isolate the Nitrogen supply to the 1A and 1D Cold Leg Accumulators and then make the valve alignment to vent these accumulators to containment. This JPM is written to terminate at this time since all critical steps have been completed. Complete depressurization of these accumulators would take ~ 30 minutes.

JPM d - NC System Bleed and Feed - Modified Bank JPM (modified to make it not alternate Path)

K/A WE05 EA1.13 Ability to operate and/or monitor the following as they apply to Loss of Secondary Heat Sink: ECCS (CFR 41.5 to 41.8 / 45.5 to 45.8) IMPORTANCE: 3.9 Initial conditions are that a reactor trip has occurred on Unit 1 due to a loss of both Main Feedwater Pumps. The CA system will not function and a Red Path exists for the Heat Sink CSF and transition to EP/1/A/5000/FR-H.1 (Loss of Secondary Heat Sink) has occurred. Feed and Bleed initiation criteria has been met. Initiating cue is the CRS has instructed the applicant to initiate NC system feed and bleed per FR-H.1 beginning at step 21. The applicant will ensure all NC pumps are off and initiate both trains of S/I.

Following verification that the feed path has been aligned, the applicant will open two Pressurizer PORVs to align the bleed path. Once the applicant has verified that this path is aligned, the JPM will be complete.

JPM e - Isolate Faulted Steam Generator - Bank JPM - Alternate Path K/A APE040 AA2.01 Ability to determine and/or interpret the following as they apply to a Steamline Rupture: Occurrence and location of a steamline rupture from pressure and flow indications (CFR 41.10 / 43.5 / 45.13) IMPORTANCE: 3.6 / 4.0 Initial conditions are that a reactor trip and S/I have occurred due to high containment pressure. The crew has implemented EP/1/A/5000/E-2 (Faulted Steam Generator Isolation). Initiating cue is the CRS has directed the applicant to perform steps 6 through 10 to identify and isolate the faulted S/G. Applicant will determine based off of steamline pressure and flow that 1C is the faulted S/G. Applicant will determine that valve 1CA-187 (S/G 1C CA Nozzle Tempering Isolation) is not closed and will attempt to manually close it. 1CA-187 will not close beginning the ALTERNATE PATH. Applicant will close 1CF-100 (S/G CA Nozz Tempering Control), 1SM-75A (S/G 1C Otlt Hdr Blowdown C/V),

1CA-46B (CA Pmp B Disch To S/G 1C Isol), and 1CA-50A (CA Pmp 1 Disch to S/G 1C Isol) to complete isolation of the 1C S/G.

JPM f - Upper Containment Ventilation Unit Additional Cooling - NEW JPM K/A 022 A4.01 Ability to manually operate and/or monitor in the control room: CCS fans (CFR 41.7 / 45.5 to 45.8) IMPORTANCE: 3.7 Initial conditions are that Unit 1 is at 100% RTP. Upper Containment temperature is 95°F and rising. Maintenance is planning an Upper Containment entry to investigate and has requested that Upper Containment temperature be lowered to < 90°F prior to the entry.

The CRS directs the applicant to start an additional Upper Containment Ventilation Unit

(UCVU) and place the operating UCVUs in MAX cooling per OP/1/A/6450/001 (Containment Ventilation (VV) Systems) Enclosure 4.10 (Upper Containment Ventilation Unit Additional Cooling). Applicant will start an additional UCVU and once they have verified that it is operating correctly, will place the running UCVUs in MAX cooling mode to complete the JPM.

JPM g - Shift Operating Condenser Circulating Water Pumps - Modified Bank JPM (Modified to remove failures for the 1D discharge valve to automatically open and the 1B pump failing to secure automatically)

K/A 075 A4.02 Ability to manually operate and/or monitor in the control room: Circulating Water Pump (CFR 41.4 / 41.7 / 45.5 / 45.8) IMPORTANCE: 3.1 Initial conditions are that Unit 1 is at 100% RTP. Initiating cue is for the applicant to shift operating RC pumps by starting 1D RC Pump and securing 1B RC pump per OP/1/B/6400/001 A (Condenser Circulating Water) Enclosure 4.7 (Shifting of Operating RC Pumps). Following verification that the pump is ready to start, the applicant will start the 1D RC pump. Applicant will then secure the 1B RC pump by closing its discharge valve (pump normally secures when discharge valve is fully closed) to complete the JPM.

JPM h - Restore Normal Power to 1ETA from the Control Room - Bank JPM (RO Only)

K/A 064 A4.07 Ability to manually operate and/or monitor in the control room: ED/G (with load) to grid (CFR 41.7 / 45.5 to 45.8) IMPORTANCE: 3.8 Initial conditions are that Unit 1 is recovering from a blackout per AP/1/A/5500/007 Case I (Loss of Normal Power to an Essential Train). Initiating cue is the CRS directs the applicant to parallel 1A D/G to 1ETAs normal power source (1ATC) and shutdown 1A D/G per OP/1/A/6350/002 (Diesel Generator Operation) Enclosure 4.17 (Shutdown of D/G 1A After an Automatic Start). Applicant will sync the 1A D/G with the grid, close the 1ETA feeder from ATC breaker, and stabilize the 1A D/G with a positive load and a lagging power factor. Applicant will then, following a time delay, reduce 1A D/G load to 200 KW and open the 1A D/G output breaker to 1ETA. Finally, the applicant will secure the 1A D/G to complete the JPM.

In Plant System JPMs JPM i - Establish NC Makeup/Seal Injection from the SSF - NEW JPM - Alternate Path K/A 062 A2.20 Ability to (a) predict the impacts of the following on the AC Electrical Distribution System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Loss of offsite power sources (CFR 41.5 / 43.5 / 45.3 / 45.13) IMPORTANCE 3.8 / 4.1 Initial conditions are that a Loss of All AC power has occurred on Unit 1. Initiating cue is the CRS directs the applicant to perform EP/1/A/5000/G-1 (Generic Enclosures) 9 (Establishing NC Makeup/Seal Injection from the SSF). Applicant will perform an emergency start of the SSF D/G. This begins the ALTERNATE PATH. When the applicant tries to adjust frequency to 60 Hz, the frequency meter will indicate bottom of scale. With the frequency meter not indicating, the applicant will have to use the governor control to bring Diesel speed to 1800 rpm. Applicant will perform a manual load shed of 1SLXG, close the SSF D/G breaker, ensure correct valve alignment for the Standby Makeup Pump, and start the Standby Makeup Pump to complete the JPM.

JPM j - Operate 2A H2 Igniters from the SSF - Bank JPM K/A 028 G2.1.30 Ability to locate and operate components, including local controls (CFR 41.7 / 45.7) IMPORTANCE 4.4 / 4.0 Initial conditions are that Unit 2 has entered AP/0/A/5500/048 (Extensive Damage Mitigation). Initiating cue that the Emergency Coordinator directs the applicant to align 2A Hydrogen Igniters to the source and energize them per OP/0/B/6100/013 (Standby Shutdown Facility Operations) Enclosure 4.9 (2A Train Hydrogen Igniter Operation from the SSF). Applicant will ensure the 2A Hydrogen Igniter alternate feeder breaker is closed, place the Manual Transfer SSF B/U Power switch to the ALTERNATE SOURCE position, shutdown the NF AHUs by opening breakers on 2 motor control centers, and energize the 2A Hydrogen Igniters from the alternate source.

JPM k - Align Alternate Cooling to 1A NV Pump - Bank JPM - Time Critical (< 30 minutes)

K/A 008 A2.01 Ability to (a) predict the impacts of the following on the Component Cooling Water System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Loss of CCW pump (CFR 41.5 / 43.5 / 45.3 / 45.13) IMPORTANCE 4.3 / 4.0 Initial conditions are that Unit 1 was at 100% RTP when the running KC pump tripped.

Crew entered AP/1/A/5500/021 (Loss of Component Cooling Water) and attempts to start a standby KC pump were unsuccessful. Initiating cue is the CRS directs the applicant to align alternate cooling to 1A NV pump by performing steps 1 through 5 of AP/21 (Alternate Cooling to NV Pump 1A). This JPM is time critical and must be completed within 30 minutes. The applicant will locate the local copy of AP/21 Encl. 2.

Applicant will perform the valve lineup to isolate KC and to align YD to 1A NV pump and verify YD flow to 1A NV pump to complete the JPM.