ML16064A171

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Final Operating Exam (Sections a, B, and C) (Folder 3)
ML16064A171
Person / Time
Site: Oyster Creek
Issue date: 02/10/2016
From:
AmerGen Energy Co
To: Brian Fuller
Operations Branch I
Shared Package
ML15219A259 List:
References
TAC U01929
Download: ML16064A171 (245)
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Text

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: COOO00044 Task

Title:

Week 4 Safety Related Equipment Verification Job Performance Measure No.: NRC Admin JPM1 (RO)

K/A

Reference:

G2.1.29 (4.1)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. The plant is at rated power Task Standard:

Three instances of improper EOP Jumper Bypass Plug placement have been identified. The Acceptance Criteria is declared UNSAT (not met)

Required Materials: None.

General

References:

1. 680.4.007, Safety Related Equipment Verification, Revision 14 Initiating Cue:

Complete Section 6.4, Week Four Verification, IAW 680.4.007, Safety Related Equipment Verification, starting at Step 6.4.3.

Time Critical Task: No.

Validation Time: 10 Minutes ILT 14-1 NRC RO ADMIN JPM1 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provide repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Verify Prerequisites and reviews Precautions and Limitations.

Standard: Verifies Prerequisites and reviews Precautions and Limitations.

Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 6.4.3.1 Verify that the bypass plugs are positioned as follows:

1. EOP Bypass Plug Panel in rear of Panel 2R
  • Bypass plug in position BP1
  • Bypass plug in position BP2
  • No other plugs inserted Standard: Verifies that the bypass plugs are positioned as follows:
1. EOP Bypass Plug Panel in rear of Panel 2R
  • Bypass plug in position BP1
  • Bypass plug in position BP2
  • No other plugs inserted Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 6.4.3.2 Verify that the bypass plugs are positioned as follows:

2. EOP Bypass Plug Panel in rear of Panel 3F
  • BP2, BP4, BP6, BP8, BP10, BP12, BP14
  • No other plugs inserted Standard: Verifies that the bypass plugs are positioned as follows:
2. EOP Bypass Plug Panel in rear of Panel 3F
  • BP2, BP4, BP6, BP8, BP10, BP12, BP14
  • No other plugs inserted
  • Reports that no plug is located in BP14 Cue: Acknowledge the report and tell the Candidate to continue (Leave the plugs in their current positions)

Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 6.4.3.3 Verify that the bypass plugs are positioned as follows

3. EOP Bypass Plug Panel in rear of Panel 6R
  • No plugs inserted Standard: Verifies that the bypass plugs are positioned as follows
3. EOP Bypass Plug Panel in rear of Panel 6R
  • No plugs inserted Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 6.4.3.4 Verify that the bypass plugs are positioned as follows

4. EOP Bypass Plug Panel in rear of Panel 7R
  • No plugs inserted Standard: Verifies that the bypass plugs are positioned as follows
4. EOP Bypass Plug Panel in rear of Panel 7R
  • No plugs inserted Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 6.4.3.5 Verify that the bypass plugs are positioned as follows

5. EOP Bypass Plug Panel in rear of Panel 11R
  • Bypass plug in position BP4
  • No other plugs installed Standard: Verifies that the bypass plugs are positioned as follows
5. EOP Bypass Plug Panel in rear of Panel 11R
  • Bypass plug in position BP4
  • No other plugs installed
  • Reports that plug is installed in BP2 instead of BP4 Cue: Acknowledge the report and tell the Candidate to continue (Leave the plugs in their current positions)

Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 8 Procedure Step: 6.4.3.6 Verify that the bypass plugs are positioned as follows

6. EOP Bypass Plug Panel inside of Panel 10XF
  • Bypass plug in position BP2
  • Bypass plug in position BP4
  • No other plugs installed Standard: Verify that the bypass plugs are positioned as follows
6. EOP Bypass Plug Panel inside of Panel 10XF
  • Bypass plug in position BP2
  • Bypass plug in position BP4
  • No other plugs installed
  • Reports that plug is installed in BP3 Cue: Acknowledge the report and tell the Candidate to continue (Leave the plugs in their current positions)

Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Compare results of this surveillance with Section 7.0, Acceptance Criteria.

Record comments/discrepancies.

Standard: Reviews Acceptance Criteria and determines the Acceptance Criteria 7.1.3 is Unsat (has not been met)

Note: For failure of the acceptance criteria, the procedure then directs that the requirements of LS-OC-125 be followed. That procedure has been superseded by LA-AA-125, Corrective Action program, which would require generation of an IR or AR (incident report). The Candidate may state generation of an IR is required. (Not required for critical step.) Writing comments in Step 6.4.4 is not required.

Comment:

SAT/UNSAT Terminating Cue: Three instances of improper EOP Jumper Bypass Plug placement have been identified. The Acceptance Criteria is declared UNSAT (not met)

JPM Stop Time: ___________

ILT 14-1 NRC RO ADMIN JPM1 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Admin JPM 1 (RO)

Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC RO ADMIN JPM1 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup

1. This JPM can be performed at any power level
2. Remove EOP Bypass Plug in rear Panel 3F at position BP14
3. Remove EOP Bypass Plug in rear Panel 11R from position BP4 and place in BP2
4. Place an additional EOP Bypass Plug in Panel inside Panel 10XF in position BP3
5. Place keep procedure 680.4.007 steps 6.4, 6.4.1, 6.4.2 ILT 14-1 NRC RO ADMIN JPM1 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power Task Cue:

Complete Section 6.4, Week Four Verification, IAW 680.4.007, Safety Related Equipment Verification, starting at Step 6.4.3.

ILT 14-1 NRC RO ADMIN JPM1 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2220201512 Task

Title:

Calculate Primary Containment Identified leak Rate IAW 351.2 Job Performance Measure No.: NRC RO Admin JPM 2 K/A

Reference:

G2.1.20 (4.6)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power
  • This identified leak rate calculation is for 1200 - 1600 today
  • The most previous identified leak rate was 19.5 GPM
  • The switches for the DWEDT Pumps were placed in OFF at 12:33:12 (HH:MM:SS)
  • The DRYWELL EQUIP DRAIN TANK HIGH LEVEL alarm annunciated at 12:47:22 (HH:MM:SS)

Initiating Cue:

With the information provided, calculate the Primary Containment identified leak rate IAW 351.2, High Purity Waste System. Determine if any Technical Specification limits have been exceeded.

Required Materials: Calculator General

References:

1. 351.2, High Purity Waste System, revision 84
2. Tech Spec 3.3.D.5 ILT 14-1 NRC RO Admin JPM 2 Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Task Standard:

Determines the current identified leak rate and determines that it does exceed a Technical Specification limit.

Time Critical Task: NO Validation Time: 8 Minutes ILT 14-1 NRC RO Admin JPM 2 Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: attachment 351.2-6 steps 1,2,3 Calculates elapsed time Standard: Calculates elapsed time:

  • 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />
  • 14 minutes
  • 10 seconds = 0.167 minutes
  • Total Minutes: 14.167 minutes Comment:

SAT/UNSAT ILT 14-1 NRC RO Admin JPM 2 Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: attachment 351.2-6 step 4 Calculate identified leak rate Standard: Calculates identified leak rate as:

  • (295 gallons)/(14.167 minutes) = 20.8 gpm Comment:

SAT/UNSAT Performance Step: 4 Determines Tech Spec applicability Standard: Determines that a Tech Spec limit has been exceeded.

Note: Tech Spec 3.3.D.1.b is exceeded:

25 gpm total (identified and unidentified Tech Spec limit)

(20.8 gpm identified + 4.5 gpm unidentified = 25.3 gpm actual)

Comment:

SAT/UNSAT Terminating Cue: Determines the current identified leak rate and determines that it does exceed a Technical Specification limit.

JPM Stop Time: ___________

ILT 14-1 NRC RO Admin JPM 2 Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC RO Admin JPM 2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC RO Admin JPM 2 Page 5 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Provide a copy of procedure 351.2 attachment 6 and Tech Spec 3.3.D to the applicant.

ILT 14-1 NRC RO Admin JPM 2 Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power
  • This identified leak rate calculation is for 1200 - 1600 today
  • The most previous identified leak rate was 19.5 GPM
  • The switches for the DWEDT Pumps were placed in OFF at 12:33:12 (HH:MM:SS)
  • The DRYWELL EQUIP DRAIN TANK HIGH LEVEL alarm annunciated at 12:47:22 (HH:MM:SS)

Task Cue:

With the information provided, calculate the Primary Containment identified leak rate IAW 351.2, High Purity Waste System (attached).

Determine if any Technical Specification limits have been exceeded.

Primary Containment identified leak rate: _________________

Tech Specs limit exceeded (Yes/No): _________________

Name: _________________

ILT 14-1 NRC RO Admin JPM 2 Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: EQC02022 Task

Title:

RPS Manual Scram Electrical Print Reading Job Performance Measure No.: NRC Admin JPM 3 (RO/SRO)

K/A

Reference:

2.2.41, RO 3.5/SRO 3.9 Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. None.
2. Ask the operator for any questions.

Task Standard:

Relays and contacts affected by depressing RPS 1 manual scram pushbutton are identified on station electrical drawings and operation is explained. For SRO candidates, additionally identify the surveillance requirements for testing the RPS 1 manual scram pushbutton and the Technical Specification impact if the pushbutton becomes inoperable.

Required Materials: None General

References:

1. DWG. NO. GE 237E566 SHEETS - 2,3,& 10 Initiating Cue:

Using station electrical prints, explain how depressing the RPS 1 manual scram pushbutton results in an RPS channel 1 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action.

Time Critical Task: NO Validation Time: 8 Minutes ILT 14-1 NRC RO/SRO Admin JPM3 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtains a copy of the reference print and reviews/utilizes the correct sheets Standard: Obtained current revision of DWG. NO. GE 237E566 SHEETS - 2,3,& 10 Comment:

SAT/UNSAT ILT 14-1 NRC RO/SRO Admin JPM3 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Using GE 237E566 SHEETS - 2,3,& 10, locates RPS 1 manual scram pushbutton Note: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet Standard: Locates RPS 1 manual scram pushbutton (1S2) on sheet 2 coordinate E-5 Comment:

SAT/UNSAT Performance Step: 4 Using GE 237E566 SHEETS - 2,3,& 10, identifies relay 1K21A Standard: Locates relay 1K21A on GE 237E566 on sheet 2 coordinate D-5 Note: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet Comment:

SAT/UNSAT ILT 14-1 NRC RO/SRO Admin JPM3 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Using GE 237E566 SHEET 3, identifies contacts 1K21A Note: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.

Note:

The candidate may also identify additional contacts and relays affected by pressing the 1S2 manual scram pushbutton. This is satisfactory but not required, as the task did not require discussion of the backup scram or any other functions.

Using GE 237E566 SHEET 3, identifies contacts 1K21A at coordinate Standard:

H-5, H-4, and H-3 Comment:

SAT/UNSAT Performance Step: 6 Using GE 237E566 SHEETS 3, identifies relays/solenoids 305-117 and/or 118.

Using GE 237E566 SHEETS 3, identifies relays/solenoids 305-117 Standard:

and/or 118 at coordinates B-8 Notes:

  • This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.
  • The candidate does not have to identify all solenoids/relays on this sheet, as long as a representative sample is identified and some indication is given that there are multiple solenoids/relays.

Comment:

SAT/UNSAT ILT 14-1 NRC RO/SRO Admin JPM3 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Describes how depressing the RPS 1 manual scram pushbutton on E console results in an RPS half scram Standard:

Describes the following:

  • Depressing RPS 1 manual scram pushbutton causes relay 1K21A to de-energize.
  • Relay 1K21A de-energizing causes contacts 1K21A to open.
  • Contacts 1K21A opening causes solenoid/relay 305-117 and/or 118 to de-energize at each HCU.

Notes:

  • Solenoid/relay 305-117 and 305-118 do not need to be specifically mentioned, as long as a representative sample is identified and some indication is given that there are multiple 305 solenoids/relays.
  • The candidate does not have to match this description word-for-word, but must include all concepts in their description.

Comment:

SAT/UNSAT RO Terminating Cue: Relays and contacts affected by depressing RPS 1 manual scram pushbutton are identified on station electrical drawings and operation is explained.

RO JPM Stop Time: ___________

ILT 14-1 NRC RO/SRO Admin JPM3 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Additional SRO Only Cue:

Provide SRO candidates the additional SRO only cue sheet and direct them to determine:

  • The surveillance requirement for testing the RPS 1 manual scram pushbutton and

Performance Step: 8 SRO Only: Determines the surveillance requirement for testing the RPS 1 manual scram pushbutton.

Determines the surveillance requirement for testing the RPS 1 Standard:

manual scram pushbutton is 1/3 month Comment:

SAT/UNSAT Performance Step: 9 SRO Only: Determines the Technical Specification impact if the RPS 1 manual scram pushbutton becomes inoperable.

Determines Technical Specification 3.1 is not met.

Standard:

Determines Technical Specification 3.1 requires control rods to be inserted OR Determines Technical Specification 3.1 requires placing the RPS 1 system in a tripped condition.

Comment:

SAT/UNSAT SRO Terminating Cue: Surveillance requirement and Technical Specification impact have been determined.

SRO JPM Stop Time: ___________

ILT 14-1 NRC RO/SRO Admin JPM3 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC RO/SRO Admin JPM 3 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC RO/SRO Admin JPM3 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup Have the following references available:

1. GE 237E566 SHEETS - 2,3,& 10 Have SRO ONLY references available:
1. SFCP ref. 5
2. T.S. 3.1 ILT 14-1 NRC RO/SRO Admin JPM3 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • None Task Cue:

Using station electrical prints, explain how depressing the RPS 1 manual scram pushbutton results in an RPS channel 1 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action.

ILT 14-1 NRC RO/SRO Admin JPM3 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SRO ADDITIONAL STUDENT HANDOUT Determine the following:

  • The surveillance requirement for testing the RPS 1 manual scram pushbutton and

ILT 14-1 NRC RO/SRO Admin JPM3 Page 10 of 10

RO Admin JPM 4 is not included here due to being Security Related.

A separate, non-publicly available file is in ADAMS

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 3410102411 Task

Title:

Review a Completed Pre-Critical Checkoff IAW Procedure 201 Job Performance Measure No.: NRC Admin JPM 1 (SRO)

K/A

Reference:

G2.1.23 (4.4)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

The plant has just completed all major activities during a refuel outage Preparations are being made for a plant startup The REACTOR MODE SELECTOR switch is in REFUEL Attachment 201-2, Pre-Critical Checkoff has been completed and is awaiting review Task Standard:

The plant is deemed NOT ready for an uninterrupted startup to rated power. The correct reasons and required actions are stated.

Required Materials: None General

References:

1. Procedure 201, Plant Startup, Revision 101
2. Technical Specifications ILT 14-1 NRC SRO Admin JPM1 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue:

Perform uncompleted items in Step 78 of the Pre-Critical Checkoff for Attachment 201-2.

From this review, determine if the plant is ready for an uninterrupted startup to rated power.

If the plant is NOT ready, state why and what actions are required to be ready.

Time Critical Task: NO Validation Time: 30 Minutes ILT 14-1 NRC SRO Admin JPM1 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Note: The following steps can be performed in any order.

Performance Step: 2 Determines the plant is not ready for an uninterrupted startup to rated power for the following reasons:

Step 12.4.1 shows only 1 operable SRM (SRM 21)

SRM 22 reads 1 SRM 23 reads 2 SRM 24 is bypassed TS 3.1.1.K requires a minimum of 2 operable SRMs to support the rodblock function.

Any inoperable SRM must be made operable to withdraw control rods.

Standard: Recognizes the Technical Specification applicability due to the inoperability of three (3) SRMs. Two (2) SRMs must be operable to withdraw control rods.

Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM1 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Determines the plant is not ready for an uninterrupted startup to rated power for the following reasons:

Step 45.1 shows that MCC 1A24 is not operable.

Technical Specification 3.7 states that the reactor shall not be made critical unless all of the following requirements are satisfied:

The listed buses or panel listed in the TS are energized, and this includes MCC 1A24.

Standard: Recognizes the Technical Specification applicability due to the inoperability of MCC 1A24. MCC 1A24 must be made operable prior to going critical.

Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM1 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Determines the plant is not ready for an uninterrupted startup to rated power for the following reasons:

Step 73.1 shows that conductivity and chlorides are above the allowable limits.

TS 3.3.E.1 provides the following:

3.3.E.1: The reactor coolant quality during power operation with steaming rates to the turbine-condenser of less than 100,000 pounds per hour shall be limited to: conductivity 2 us/cm[s=mhos at 25°C (77°F); chloride ion 0.1 ppm.

TS 3.3.E.2 provides the following:

3.3.E.2: When the conductivity and chloride concentration limits given in 3.3.E.1 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor coolant temperature shall be reduced to less than 212°F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Standard: Recognizes the Technical Specification applicability due high conductivity and chloride values which must be reduced below the limits in TS 3.3.E.1.

Comment:

SAT/UNSAT Terminating Cue: The plant is deemed NOT ready for an uninterrupted startup to rated power. The correct reasons and required actions are stated.

JPM Stop Time: ___________

ILT 14-1 NRC SRO Admin JPM1 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC SRO Admin JPM 1 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC SRO Admin JPM1 Page 6 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Have Technical Specifications available
2. Have a clean copy of procedure 201 available
3. Have a prepared copy of Attachment 201-2 ready
4. Have a prepared copy of attachment 201-6 ready ILT 14-1 NRC SRO Admin JPM1 Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

The plant has just completed all major activities during a refuel outage Preparations are being made for a plant startup The REACTOR MODE SELECTOR switch is in REFUEL Attachment 201-2, Pre-Critical Checkoff has been completed and is awaiting review Task Cue:

Perform uncompleted items in Step 78 of the Pre-Critical Checkoff for Attachment 201-2.

From this review, determine if the plant is ready for an uninterrupted startup to rated power.

If the plant is NOT ready, state why and what actions are required to be ready.

ILT 14-1 NRC SRO Admin JPM1 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2150101022 Task

Title:

Review Request to Allow LPRM (input into APRM) Bypass Job Performance Measure No.: NRC Admin JPM 2 (SRO)

K/A

Reference:

2.1.9 (4.5)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

The plant is at 17% power with control rod withdrawals in progressLPRM 28-33D, which inputs into APRM 5 has been spiking upscale, resulting in spurious 1/2 scrams A Troubleshooting Log has been developed which will remove LPRM 28-33D from the APRM 5 Drawer, and replace it with LPRM 28-41D, which is not currently associated to any APRM.

A Tech Eval has been approved to swap the LPRM Another Licensed Operator is available to support the activity.

A copy of the Troubleshooting Log and Attachment 403-2, LPRM and APRM Status Information Sheet, is attached.

Initiating Cue:

Review Attachment 403-2. State any actions required, if any.

Review and approve the Troubleshooting Log. If not approved, state why.

Required Materials:

1. Have a copy of Tech Specs Available
2. Have a copy of the Troubleshooting Log and completed attachment 403-2.

General

References:

1. 403 Revision 31 LPRM-APRM System Operations
2. MA-AA-716-004, Conduct of Troubleshooting
3. 620.4.002, APRM Surveillance Test - Front Panel Check ILT 14-1 NRC Admin JPM 2 (SRO) Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Task Standard:

Determine that APRM 5 will be inoperable when bypassed AND determines that APRM 5 cannot be bypassed until APRM 6 is restored.

Time Critical Task: NO Validation Time: 11 minutes ILT 14-1 NRC Admin JPM 2 (SRO) Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: Review Troubleshooting Log Standard: Reviews and does not approve Troubleshooting Log Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: Review Attachment 403-2 Standard: Reviews Attachment 403-2 Determines that APRM 6 is inoperable due to 2 LPRMs in the same radial string being inoperable Comment:

SAT/UNSAT ILT 14-1 NRC Admin JPM 2 (SRO) Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: Determine that APRM 5 will be inoperable when bypassed Standard: Determine that APRM 5 will be inoperable when bypassed OR determines that APRM 5 cannot be bypassed until APRM 6 is restored.

Comment:

SAT/UNSAT Task Standard: Determine that APRM 5 will be inoperable when bypassed AND determines that APRM 5 cannot be bypassed until APRM 6 is restored.

JPM Stop Time: ___________

ILT 14-1 NRC Admin JPM 2 (SRO) Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC SRO Admin JPM 2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Admin JPM 2 (SRO) Page 5 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup Have the following procedures ready:

1. 403 Revision 31 LPRM-APRM System Operations
2. MA-AA-716-004, Conduct of Troubleshooting
3. 620.4.002, APRM Surveillance Test - Front Panel Check ILT 14-1 NRC Admin JPM 2 (SRO) Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

The plant is at 17% power with control rod withdrawals in progressLPRM 28-33D, which inputs into APRM 5 has been spiking upscale, resulting in spurious 1/2 scrams A Troubleshooting Log has been developed which will remove LPRM 28-33D from the APRM 5 Drawer, and replace it with LPRM 28-41D, which is not currently associated to any APRM.

A Tech Eval has been approved to swap the LPRM Another Licensed Operator is available to support the activity.

A copy of the Troubleshooting Log and Attachment 403-2, LPRM and APRM Status Information Sheet, is attached.

Initiating Cue:

Review Attachment 403-2. State any actions required, if any.

Review and approve the Troubleshooting Log. If not approved, state why.

ILT 14-1 NRC Admin JPM 2 (SRO) Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: RPT00001 Task

Title:

Authorize Emergency Exposures Job Performance Measure No.: NRC Admin JPM 4 (SRO)

K/A

Reference:

2.3.4 (3.7)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant was at rated power when a severe earthquake occurred.
  • Chemistry has confirmed fuel failures.
  • Many plant systems have either failed to automatically isolate or are currently leaking from breaks or incomplete system isolations.
  • An emergency has been declared by the Shift Manager but no emergency operating facilities have been activated.
  • The RP Manager has forwarded 3 Authorization for Emergency Exposure forms to you for your approval. Personal information on the volunteers to perform the 3 different jobs is also provided.

Task Standard:

Determines that authorization should not be provided to Alan Able (JOB A) since it will only result in a dose of 3.75 Rem (25/60 hour x 9 Rem/hr).

Determines that authorization should not be provided to Bob Blake (JOB B) since he already has had an emergency exposure of >25 Rem before.

Determines that authorization should be authorized for Chris Cat (JOB C). He has had no prior emergency exposure > 25 Rem, and his expected exposure is > 5 Rem (35/60 x 11 = 6.4 Rem)

Required Materials: None

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information General

References:

1. EP-AA-113 Revision 12 Initiating Cue:

Authorize or NOT authorize the 3 Authorization For Emergency Exposure forms provided to you from the RP Manager. If not authorized, state why.

Time Critical Task: NO Validation Time: 30 Minutes

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Note: The following steps can be performed in any order.

Performance Step: 2 Evaluates and determines authorization for Emergency Exposure for Alan Able (JOB A)

Standard: Determines that authorization should not be provided to Alan Able (JOB A) since it will only result in a dose of 3.75 Rem (25/60 hour x 9 Rem/hr).

Comment:

SAT/UNSAT

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Evaluates and determines authorization for Emergency Exposure for Bob Blake (JOB B)

Standard: Determines that authorization should not be provided to Bob Blake (JOB B) since he already has had an emergency exposure of >25 Rem before.

Comment:

SAT/UNSAT

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Evaluates and determines authorization for Emergency Exposure for Chris Cat (JOB C)

Standard: Determines that authorization should be authorized for Chris Cat. He has had no prior emergency exposure > 25 Rem, and his expected exposure is >

5 Rem (35/60 x 11 = 6.4 Rem)

Comment:

SAT/UNSAT Terminating Cue: Determines that only the Authorization for Emergency Exposure form for Chris Cat should be authorized, and that the others should not be authorized.

JPM Stop Time: ___________

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC SRO Admin JPM 4 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Have a calculator available
2. Have a copy of EP-AA-113 Revision 12 available if the candidate requests
3. Hand out the 3 student copies of EP-AA-113-F-02, Authorization For Emergency Exposure, Revision B, to each candidate
4. Provide the Personal information on the volunteers to perform the 3 different jobs to each candidate

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant was at rated power when a severe earthquake occurred.
  • Chemistry has confirmed fuel failures.
  • Many plant systems have either failed to automatically isolate or are currently leaking from breaks or incomplete system isolations.
  • An emergency has been declared by the Shift Manager but no emergency operating facilities have been activated.
  • The RP Manager has forwarded 3 Authorization for Emergency Exposure forms to you for your approval. Personal information on the volunteers to perform the 3 different jobs is also provided.

Task Cue:

Authorize or NOT authorize the 3 Authorization for Emergency Exposure forms provided to you from the RP Manager. If not authorized, state why.

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Personal information on the volunteers to perform the 3 different jobs.

PURPOSE: To enter the Trunion Room to manually close the MSIVs to secure the steam leak into the Turbine Building.

JOB A DOSE RATE: 9 R/hour.

JOB DURATION: 25 minutes Volunteer: Alan Able Age: 44 Prior Lifetime No Employee 00111 Emergency Exposure?

ID:

Current 1000 mrem Dose:

PURPOSE: To rescue an unconscious worker in the Drywell.

JOB B DOSE RATE: 30 R/hour.

JOB DURATION: 55 minutes Volunteer: Bob Blake Age: 47 Prior Lifetime Yes Employee 00222 Emergency Exposure? 28 Rem ID:

Current 1150 mrem Dose:

PURPOSE: To close the RWCU isolation valves to stop a leak in the Reactor Building and to rescue a trapped worker who could drown from the flooding.

JOB C DOSE RATE: 11 R/hour.

JOB DURATION: 35 minutes Volunteer: Chris Cat Age: 40 Prior Lifetime No Employee 00333 Emergency Exposure?

ID:

Current 1400 mrem Dose:

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2000502401 Task

Title:

Emergency Event Classification Job Performance Measure No.: SRO NRC Admin JPM 5 K/A

Reference:

2.4.29 (4.4)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Plant conditions are as is in simulator once Scenario is complete Task Standard:
  • Completes the State and Local Notification Form for Emergency Directors Approval.

Initiating Cue:

  • State the minimum classification for these conditions
  • Complete the State and Local Notification Form for Emergency Directors Approval.

Required Materials: Prepare adequate copies of the General References to provide to each candidate.

General

References:

1. EP-AA-1010 Addendum 3 rev. 0
2. EP-MA-114-100-F-03 rev. H, Time Critical Task: NO Validation Time: 15 Minutes ILT 14-1 NRC SRO Admin JPM5 Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Denote critical steps with a check mark Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtains current copy of the required procedures Standard: Obtains controlled copy of procedure EP-AA-1010 and EP-MA-114-100-F03 Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM5 Page 2 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 3 Determine Emergency Classification and associated EAL.

Standard: If NRC Scenario 1 is used Declares FA-1, ANY loss or ANY potential Loss of either Fuel Clad or RCS If NRC Scenario 2 is used Declares MS-2, Automatic scram failure to shutdown the reactor and manual actions taken from the Rx control console are not successful in shutting down the reactor If NRC Scenario 3 is used Declares FS-1, Loss or potential loss of any two barriers If NRC Scenario 4 is used Declares FS-1, Loss or potential loss of any two barriers Time Critical Portion of JPM complete Time Complete ________ (<15 minutes)

Note:

Comment:

SAT/UNSAT Performance Step: 4 Complete Status block 1 Standard: Fill in the block with:

Check the line that states This is a Drill Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM5 Page 3 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 6 Complete Emergency Classification block 3 Standard: Fill in the block with:

If NRC Scenario 1 is used Check the line that states Alert If NRC Scenario 2 is used Check the line that states SAE If NRC Scenario 3 is used Check the line that states SAE If NRC Scenario 4 is used Check the line that states SAE Comment:

SAT/UNSAT Performance Step: 7 Complete Declared At block Standard: Fill in the block with:

Time: is current PPC time / Date is Current Date Comment:

SAT/UNSAT Performance Step: 8 Complete Represents A/AN block Standard: Fill in the block with:

For any scenario used: Check the line that states Initial declaration Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM5 Page 4 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 9 Complete EAL number and Event Description block 4 Standard: Fill in the block with:

If NRC scenario 1 is used: The EAL is FA-1, Description similar to: ANY Loss or ANY Potential Loss of either Fuel Clad or RCS If NRC scenario 2 is used: The EAL is MS-2, Description similar to:

Automatic scram failure to shutdown the reactor and manual actions taken from the Rx control console are not successful in shutting down the reactor If NRC scenario 3 or 4 is used: The EAL is FS-1, Description similar to; Loss or Potential Loss of Any two barriers Comment:

SAT/UNSAT Performance Step: 10 Complete Non-Routine Radioactive Release Status block 5 Standard: Fill in the block with:

If NRC Scenario 1 or 2 or 3 are used: Check the line that states that There is no non-routine radiological release in progress If NRC scenario 4 is used: Check the line that states that Airborne non-routine radiological release in progress Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM5 Page 5 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 11 Complete Meteorological Condition block 6 Standard: Fill in the block with:

If NRC Scenario 1 or 2 or 3 is used From the Weather screen record; Wind direction is from 269 degrees and wind speed is 8 miles per hour (use 380 elevation data)

If NRC Scenario 4 are used: From the Weather screen record; Wind direction is from 245 degrees and wind speed is 5 miles per hour (use 33 elevation data)

Comment:

SAT/UNSAT Performance Step: 12 Complete Conclusion block Standard: Fill in the block with:

For any NRC Scenario used: Check the line that states This is a Drill and Documents time Comment:

SAT/UNSAT Terminating Cue:

JPM Stop Time: ___________

ILT 14-1 NRC SRO Admin JPM5 Page 6 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: SRO NRC Admin JPM 5 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC SRO Admin JPM5 Page 7 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Run NRC 2016 scenario 1, 2, 3, or 4.

ILT 14-1 NRC SRO Admin JPM5 Page 8 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • Plant conditions are as is in simulator once Scenario is complete Task Cue:
  • State the minimum classification for these conditions
  • Complete the State and Local Notification Form for Emergency Directors Approval.

ILT 14-1 NRC SRO Admin JPM5 Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2010101009 Task

Title:

Perform Control Rod Exercising Test - uncoupled Rod (Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 1 K/A

Reference:

201003 A2.02 (3.7/3.8)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power
  • Control Rod Exercising Procedure 617.4.002 is in progress Task Standard: Perform CRD exercise and perform actions for an uncoupled Rod Required Materials: None General

References:

1. 617.4.002 Control Rod Exercise Procedure Rev 69
2. ABN-6 Control Rod Malfunctions Rev 14
3. RAP-H5a Rod Overtravel Rev 2 Initiating Cue:

Continue with procedure 617.4.002, Control Rod Exercising at step 6.4 for Control Rod 02-35 Time Critical Task: NO Validation Time: 11 Minutes ILT 14-1 NRC Control Room JPM 1 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtain a copy of the reference procedure and continue with Control Rod exercising of control rod 02-35 Standard: Obtains procedure 617.4.002 and continues with control rod exercising of control rod 02-35 Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 6.4 - 6.4.7.6 Insert Control Rod 02-35 from position 48 to position 46 Standard: Monitors CRD position indicators for any mispositioned control rod. Turns on Rod Power, On the Rod select matrix selects control rod 02-35, records initial position on attachment 3 and inserts control rod 1 notch from position 48 to position 46 by placing ROD Control Switch to Rod IN position for approximately one-second. Verifies Control Rod moves into position 46.

Inserts a check mark on 617-4-002-3 in the insert column.

BOOTH: uncouple rod 02-35 Insert MAL-CRD. 008_0235 ILT 14-1 NRC Control Room JPM 1 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Comment:

SAT/UNSAT Performance Step: 4 Procedure steps: 6.4.8 - 6.4.8.3 Withdraw Control Rod 02-35 from position 46 to 48 Standard: Places Rod Control switch to ROD OUT NOTCH for approximately one-second. Verifies Control rod moves to position 48 and latches. Records checkmark in the withdrawal column of 617-4-002-3 Comment:

SAT/UNSAT Alternate Path Performance Step: 5 Procedure Step: 6.4.15 - 6.4.15.3 Perform a coupling check and determines Rod is uncoupled Standard: Holds ROD CONTROL switch in ROD OUT NOTCH and simultaneously places the NOTCH OVERRIDE switch in NOTCH OVERRIDE.

Comment:

SAT/UNSAT Performance Step: 6 Recognize rod 02-35 is uncouples and make an update Standard: Recognizes alarm H5a(Rod overtravel) has come in and makes update.

Then enters RAP-H5a and enters ABN-6 Comment:

ILT 14-1 NRC Control Room JPM 1 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 7 Procedure Step: 7.3 - 7.3.1.3 Apply continuous insert signal for rod 02-35 until a response of nuclear instruments is notice Standard: Confirms Rod power switch is On, Rod 02-35 is selected, applies Continuous insert signal until a response is observed on the nuclear instruments BOOTH: re-couple rod 02-35 Delete MAL-CRD. 008_0235 CUE: If asked, Report a response was observed on nuclear instrumentation Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 7.3.2.1 Notify Reactor engineering of uncoupled rod Standard: Notifies Reactor engineering that rod 02-35 was uncoupled Comment:

SAT/UNSAT Performance Step: 9 Procedure step: 7.3.2.2 - 7.3.2.3 Verify rod 02-35 is recoupled ILT 14-1 NRC Control Room JPM 1 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Standard: Withdraws rod to position 48. Applies a continuous withdraw signal at position 48 an verifies Rod overtravel alarm is not alarming an control rod position display indicates position 48.

Comment:

SAT/UNSAT Performance Step: 10 Make update that rod is re-coupled Standard:

Makes update that Rod 02-35 is re-coupled.

Comment:

SAT/UNSAT Terminating Cue: Control Rod has been withdrawn to position 48 and Re-coupling check is complete JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 1 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Control Room JPM 1 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 1 Page 6 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup SIMULATOR SETUP INSTRUCTIONS

1. Reset to a full power IC (115 or other), but this JPM can be run at any power level.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

ILT 14-1 NRC Control Room JPM 1 Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power
  • Control Rod Exercising Procedure is in progress Task Cue:

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2760101005 Task

Title:

Sequential Loss of Service Water (Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 2 K/A

Reference:

400000 K1.01 (3.2/3.3)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power Task Standard: Perform actions for a total loss of Service Water flow per ABN-18 Required Materials: None General

References:

1. ABN-18 Service Water Failure Response Rev 7
2. 303, Reactor Cleanup Demineralizer system rev 147 Initiating Cue: You are the Reactor Operator; respond to plant annunciators and take any actions, if required Time Critical Task: NO Validation Time: 10 Minutes ILT 14-1 NRC Control Room JPM 2 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provide repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT BOOTH OPERATOR:

When directed by the evaluator, insert the following malfunction to trip an operating Service Water Pump INSERT: MAL-SWS001A Performance Step: 2 Responds to a trip of the operating Service Water Pump Standard: Acknowledges annunciator K-1-f SVC WATER PUMP TRIP Comment:

SAT/UNSAT Performance Step: 3 Obtains copy of ABN-18 Standard: Obtains copy of ABN-18 and implements procedure Comment:

ILT 14-1 NRC Control Room JPM 2 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 4 Procedure Step: 3.2 IF Loss of one pump with initially two in service, Then Go to Step 4.6.

Standard: Determines that one service water pump has tripped and proceeds to Step 4.6 CUE:

If asked: report TBCCW is on Service Water Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 4.6 - 4.6.1 IF Service Water loss has reduced RBCCW or TBCCW cooling Capacity, THEN PERFORM the following steps concurrently:

Standard: Lowers cleanup flow as directed Cue: Inform applicant RBCCW cooling has been reduced and as US direct: lower RWCU flow to 350 gpm.

Comment:

SAT/UNSAT BOOTH OPERATOR:

After RWCU flow has been reduced, insert the following malfunction to trip the second operating Service Water Pump:

1. INSERT: MAL-SWS001B ILT 14-1 NRC Control Room JPM 2 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Alternate Path Performance Step: 6 Procedure Step: 4.6.2 EXECUTE ABN-19, RBCCW Failure Response concurrently with this procedure Standard: Attempts to implement ABN-19, RBCCW Failure Response NOTE: This step may not be reached depending on when the second Service Water Pump is tripped.

Cue: Another operator will perform ABN-19 Comment:

SAT/UNSAT Performance Step: 7 Recognize trip of second Service Water Pump Standard: Recognizes trip of second Service Water Pump. Re-enters ABN-18 and responds per section 4.4 for a complete loss of service water Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 4.4 - 4.4.1 If a complete loss of service water has occurred, perform a rapid power reduction as directed by the US Standard: Performs rapid power reduction by lowering master recirc flow Cue: If requested, direct lowering power with recirc flow.

Comment:

ILT 14-1 NRC Control Room JPM 2 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT ILT 14-1 NRC Control Room JPM 2 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 4.4.2 SCRAM the reactor and ENTER ABN-1 Reactor Scram concurrently with this procedure Standard: Scrams the reactor by pushing the manual scram pushbuttons and taking the mode switch to shutdown.

Cue: After the reactor is scrammed, inform the applicant another operator will perform the remaining actions of ABN-1 Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 4.4.3 ENTER ABN-19, RBCCW Failure Response concurrently with this procedure Standard: Attempts to implement ABN-19, RBCCW Failure Response Cue: Another operator will perform ABN-19 Comment:

SAT/UNSAT Performance Step: 11 Procedure Step: 4.4.4 CONFIRM the main turbine is tripped if TBCCW is on Service Water Standard: Observes the main turbine is tripped CUE: If asked report TBCCW is on Service Water Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 2 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 12 Procedure Step: 4.4.6 ISOLATE the Service Water system as directed by the US Standard: Attempts to isolate the SW system CUE: Another operator will isolate the Service Water system Comment:

SAT/UNSAT Performance Step: 13 Procedure Step: 4.4.7 START one ESW pump in each system in order to keep system piping full of water.

Standard: Starts an ESW pump in system I and II.

CUE: Your task is complete.

Comment:

SAT/UNSAT Terminating Cue: ESW pumps are running JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 2 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Sim JPM 2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 2 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup SIMULATOR SETUP INSTRUCTIONS

1. Reset to a full power IC (115 or other), but this JPM can be run at any power level.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Ensure TBCCW is on Service Water
3. 1-1 and 1-2 service water pumps running
4. Student copy available of procedure ABN-18
5. Student copy available of procedure 303 for adjusting cleanup flow ILT 14-1 NRC Control Room JPM 2 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power Task Cue: You are the Reactor Operator; respond to plant annunciators and take any actions, if required ILT 14-1 NRC Control Room JPM 2 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2040101412 Task

Title:

Place the Second RWCU Pump In Service Job Performance Measure No.: NRC Control Room JPM 3 (RO ONLY)

K/A

Reference:

204000 A4.01 (3.1/3.0)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power, with elevated reactor water conductivity.
  • All prerequisites for starting the standby RWCU Pump have been verified.
  • An Equipment Operator is locally stationed and is standing by.
  • The plant announcement for the pump start has been made.

Task Standard:

Flow is established through the second RWCU Pump Required Materials: None General

References:

1. 303, Reactor Cleanup Demineralizer System rev 147 Initiating Cue:
  • Place the standby RWCU Pump in service IAW procedure 303, Reactor Cleanup Demineralizer System, starting at step 22.3.6.
  • Adjust flow to 650 gpm when both RWCU pumps are in service Time Critical Task: NO ILT 14-1 NRC Control Room JPM 3 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Validation Time: 15 Minutes Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtain a copy of the reference procedure and reviews/utilizes the correct section Standard: Current revision of 303 is obtained Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 22.3.6 START the second pump being placed in service Standard: Starts RWCU Pump B by placing the RECIRC PUMP ND02B switch CW to START. (red light ON, green light OFF)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: 22.3.7 Slowly OPEN the second pump discharge valve by momentarily cycling its discharge valve control switch between OPEN and mid position until a small increase in pump discharge pressure is noted.

  • V-16-49, RECIRC PUMP A DISCHARGE OR
  • V-16-50, RECIRC PUMP B DISCHARGE Standard: Slowly opens the RWCU Pump B discharge valve by momentarily cycling the RECIRC PUMP B DISCHARGE V-16-50 control switch between OPEN and mid position until a small increase in RECIRC PUMP DISCHARGE PRESS is noted. (Red light ON, green light ON; small increase in RECIRC PUMP DISCHARGE PRESS)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 22.3.8 PERFORM either or both of the following to reduce pump discharge pressure to approximately the original valve.

  • Slowly OPEN FCV-ND16
  • Slowly OPEN V-16-54, FCV Bypass Standard: Slowly opens SYSTEM FLOW CONTROLLER FCV-ND16 by rotating the manual knob CW to reduce RECIRC PUMP DISCHARGE PRESS to approximately the original valve. (SYSTEM FLOW CONTROLLER FCV-ND16 indicates further open; RECIRC PUMP DISCHARGE PRESS lowers)

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 22.3.9 ADJUST PCV-ND11 as needed to maintain system pressure at approximately 90 psig Standard: Verifies system pressure is approximately 90 psig.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 22.3.10 MONITOR demineralizer and filter (if in service) dP at RK05.

Standard: Directs an EO to monitor demineralizer and filter dP at RK05.

CUE: Repeat back the request to monitor demineralizer and filter dP at RK05.

(Note:No dP limits will be exceeded during this JPM.)

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 22.3.11 IF any of the following dP alarm setpoints are approached:

  • Demineralizer strainer dP (IJ22B) - 10 psid
  • Demineralizer dP (IJ22A) - 15 psid
  • Filter dP (IJ18) - 30 psid THEN STOP the flow increase.

Standard: Directs the EO to monitor/report any of the following:

  • Demineralizer strainer dP (IJ22B) - 10 psid
  • Demineralizer dP (IJ22A) - 15 psid
  • Filter dP (IJ18) - 30 psid CUE: Repeat back the request to monitor demineralizer and filter dP at RK05.

(Note:No dP limits will be exceeded during this JPM.)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 22.3.12 WHEN system flow exceeds 500 gpm, THEN CLOSE the Minimum Flow Valves with the local toggle switches:

  • V-16-37, Minimum Flow Valve Pump B
  • V-16-36, Minimum Flow Valve Pump A Standard: WHEN system flow exceeds 500 gpm, THEN directs the EO to close the Minimum Flow Valves with the local toggle switches:
  • V-16-37, Minimum Flow Valve Pump B
  • V-16-36, Minimum Flow Valve Pump A BOOTH Close both RWCU minimum flow valves by inserting the following remotes:

a) LOA-RCU022 to 0 (RWCU Pump A V-16-36) b) LOA-RCU023 to 0 (RWCU Pump B V-16-37)

CUE: When RWCU min flow valves are closed, report: V-16-36 and V-16-37 are closed Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 22.3.13 Continue to open the discharge valve by momentarily cycling the respective discharge valve control switch between OPEN and mid position while adjusting pressure and flow, until the valve is fully open Standard: Continues to open the discharge valve by momentarily cycling the RECIRC PUMP B DISCHARGE V-16-5 control switch between OPEN and mid position while adjusting pressure and flow, until the valve is fully open. Slowly opens SYSTEM FLOW CONTROLLER FCV-ND16 by rotating the manual knob CW to reduce RECIRC PUMP DISCHARGE PRESS. (Red light ON, green light OFF)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 22.3.14 PERFORM either or both of the following to continue to raise flow:

  • Throttle OPEN FCV-ND16
  • Throttle OPEN V-16-54, FCV Bypass.

Standard: Throttles either valve but does not exceed 760 gpm CUE: Another operator will complete the rest of the actions.

Comment:

SAT/UNSAT Terminating Cue:

Second RWCU pump in service with flow < 760 gpm JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 3 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Sim JPM 3 (RO ONLY)

Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 3 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup SIMULATOR SETUP INSTRUCTIONS

1. Reset to a full power IC (115 or other), but this JPM can be run at any power level.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Verify RWCU Pump A is in service, with an RWCU filter in-service and system flow between 380 - 420 GPM.
3. Open both RWCU minimum flow valves by inserting the following remotes:

c) LOA-RCU022 to 1 (RWCU Pump A V-16-36) d) LOA-RCU023 to 1 (RWCU Pump B V-16-37)

4. Place the heat balance screen up on the PPC screen
5. Input RWCU flow to 760 gpm
6. Verify both RBCCW Pumps running
7. Verify both Service Water Pumps running
8. Insert LOA-RBC009 to 0.6 (this opens V-5-122 to 60%; RBCCW outlet of the NRHX outlet)
9. Insert BKR-RCU001 to FAIL AUT TRIP
10. Insert BKR-RCU002 to FAIL AUT TRIP
a. This will prevent any automatic trips of the RWCU Pumps
11. Place placards for two RWCU pump operation at 3F and on the Letdown Flow Controller ILT 14-1 NRC Control Room JPM 3 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power, with elevated reactor water conductivity.
  • All prerequisites for starting the standby RWCU Pump have been verified.
  • An Equipment Operator is locally stationed and is standing by.
  • The plant announcement for the pump start has been made.

Task Cue:

  • Place the standby RWCU Pump in service IAW procedure 303, Reactor Cleanup Demineralizer System, starting at step 22.3.6
  • Adjust flow to 650 gpm when both RWCU pumps are in service ILT 14-1 NRC Control Room JPM 3 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2390201009 Task

Title:

Partial MSIV Stroke Test (Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 4 K/A

Reference:

239001 A4.01 (4.2/4.0)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is operating at 100% power.
  • All steps of Section 3.0 PREREQUISITES are met and the Unit Supervisor has granted permission to perform the surveillance Test.

Task Standard: Reactor is scrammed and the mode switch is shutdown.

Required Materials: Digital Stopwatch General

References:

1. 602.4.004 Main Steam Isolation Valve 10% Closure Test Rev 25 Initiating Cue: Perform Main Steam Isolation Valve 10% Closure Test 602.4.004 Sections 6.1 through 6.4 Time Critical Task: NO Validation Time: 10 Minutes ILT 14-1 NRC Control Room JPM 4 Page 1 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtain a copy of the reference procedure and reviews/utilizes the correct section Standard: Current revision of 602.4.004 is obtained Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 2 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Review Precautions and Limitations and obtains a digital Stop Watch Standard: Precautions and Limitations reviewed; stop watch obtained Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 6.1 VERIFY Section 3.0 Prerequisites are satisfied.

RECORD Digital Stopwatch Number Standard: Section 3.0 Prerequisites are satisfied, as given in Initial Conditions.

Records Digital Stopwatch Number CUE: If stopwatch has no number: report number is one.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 3 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 6.3.1 CONFIRM nitrogen receiver T-23-001 pressure > 95 psig Directs Equipment Operator to report nitrogen pressure locally and Standard:

determines nitrogen is in band.

CUE: Report as Equipment Operator that PI-23-523 indicates 100 psig Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 6.3.2 Reads Step 6.3.2 IF/Then step concerning increasing steam flow in lines not being tested Standard: Reads and places keeps step Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 4 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 6.3.3 Station personnel as required to observe indications Standard: Ensures Station personnel at the following:

  • Relay 2K17
  • Relay 2K18
  • PPC point SOE47
  • PPC point SOE48 CUE: Personnel are stationed Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 6.3.4 & 6.3.5 Simultaneously PERFORM the following two steps:

  • DEPRESS and HOLD TEST button for ValveV-1-0008 / NS03B.

(Panel 11F)

  • START the stopwatch
  • OBSERVE the Red Open indicating light Extinguishes for NS03B.

Standard: DEPRESSES and HOLDS TEST button for ValveV-1-0008 / NS03B. (Panel 11F), STARTS the stopwatch and OBSERVE the Red Open indicating light Extinguishes for NS03B Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 5 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 6.3.7 WHEN a half scram signal is received, AND both 2K17 and 2K18 have de-energized, simultaneously PERFORM the following two steps:

  • RELEASE the TEST button

Standard: Releases Test button and stops the stopwatch. Records Stroke time for NS03B CUE: (at time of 1/2 scram): Relays 2K17 and 2K18 are de-energized Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 6.3.8 - 6.3.10 Performs the following:

  • VERIFY relays 2K17 and 2K18 de-energized and all contacts opened. (Panel 7R)
  • VERIFY Plant Process Computer, PID: SOE47, tripped; MSIV CLOSURE SCRAM. (2K17)
  • VERIFY Plant Process Computer, PID: SOE48, tripped; MSIV CLOSURE SCRAM. (2K18)

Standard: Verifies relays are tripped and the appropriate Plant Process computer points are received CUE: Relays 2K17 and 2K18 are de-energized and all contacts opened (paper models in simulator)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 6 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 6.3.11 VERIFY that the MSIV returns to the fully open position by the Red Open light illuminating Standard: Verifies MSIV is FULLY OPEN (red light ON; green light OFF)

Comment:

SAT/UNSAT Performance Step: 12 Procedure Step: 6.3.12 - 6.3.13 VERIFY SCRAM SOLENOIDS lights extinguished. (Panel 7R)

VERIFY SCRAM CONTACTOR OPEN alarm (G-1-c) is received.

Standard: Verifies SCRAM SOLENOIDS lights extinguished. (Panel 7R) and SCRAM CONTACTOR OPEN alarm is received on panel G Comment:

SAT/UNSAT Performance Step: 13 Procedure Step: 6.3.14 - 6.3.15 VERIFY MSIV CLOSED II alarm (J-2-a) annunciated VERIFY MN STM VLVS OFF NORMAL alarm (J-8-b) annunciated.

Standard: Verifies J-2-a and J-8-b annunciators are in alarm Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 7 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 14 Procedure Step: 6.3.16 VERIFY relays 2K51A and 2K52A are de-energized. (Panel 7R)

Standard: VERIFIES relays 2K51A and 2K52A are de-energized. (Panel 7R)

CUE: Relays 2K51A and 2K52A are de-energized (paper models in simulator)

Comment:

SAT/UNSAT Performance Step: 15 Procedure Step: 6.3.17 - 6.3.21 RESET the half scram CONFIRM Plant Process Computer PIDs returned to normal state CONFIRM Alarms returned to normal state VERIFY all SCRAM SOLENOID lights lit. (4F/7R)

VERIFY SCRAM CONTACTOR OPEN alarm (G-1-c) clear Standard: Resets the half scram RPS signal by pushing scram reset pushbutton on 4F.

  • CONFIRMS Plant Process Computer PIDs returned to normal state
  • CONFIRMS Alarms returned to normal state
  • VERIFIES all SCRAM SOLENOID lights lit. (4F/7R)

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 8 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 16 Procedure Step: 6.3.22 - 6.3.27 VERIFY MSIV CLOSED II alarm (J-2-a) clear VERIFY MN STM VLVS OFF NORMAL alarm (J-8-b) clear.

VERIFY relays 2K17 and 2K18 energized. (Panel 7R)

VERIFY relays 2K51A and 2K52A energized. (Panel 7R)

VERIFY Plant Process Computer PIDs SOE47 and SOE48 are normal.

Verifies the following:

Standard:

  • MSIV CLOSED II alarm (J-2-a) clear
  • MN STM VLVS OFF NORMAL alarm (J-8-b) clear.
  • Relays 2K17 and 2K18 are energized. (Panel 7R)
  • Relays 2K51A and 2K52A are energized. (Panel 7R)
  • Plant Process Computer PIDs SOE47 and SOE48 are normal.

CUE: US has Verified plant parameters required to continue to next are satisfied

2K17 and 2K18 are energized and SOE47 and SOE48 are normal Comment:

SAT/UNSAT Performance Step: 17 Continues on with surveillance testing of Test of V-1-10 / NS04B.

Reads Step 6.4.1 Standard: Place keeping identifies candidate has read step 6.4.1 Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 9 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 18 Procedure Step: 6.4.2 Station personnel as required to observe indications Standard: Ensures Station personnel at the following:

  • Relay 2K17
  • Relay 2K18
  • PPC point SOE47
  • PPC point SOE48 CUE: Personnel are stationed Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 10 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 19 Procedure Step: 6.4.3 - 6.4.4 Simultaneously PERFORM the following two steps:

  • DEPRESS and HOLD TEST button for ValveV-1-0010 / NS04B.

(Panel 11F)

  • START the stopwatch
  • OBSERVE the Red Open indicating light Extinguishes for NS04B.

Standard: DEPRESSES and HOLDS TEST button for ValveV-1-0010 / NS04B. (Panel 11F), STARTS the stopwatch and OBSERVE the Red Open indicating light Extinguishes for NS04B BOOTH: INSERT MAL-NSS013D to severity to 0 over 1000 seconds Eval CUE: IF asked steam flow trends: Report no recognizable change in steam flow while applicant is holding button Comment:

SAT/UNSAT Alternate Path Performance Step: 20 6.4.6 when half scram signal received and both 2K17 and 2K18 have de-energized or there is a noticeable increase in reactor pressure or decrease in steam flow,

  • RELEASE the TEST button
  • STOP the stopwatch
  • RECORD stroke time for NS04B Standard: Releases Test button and stops the stopwatch. Records Stroke time for NS04B and notices Steam line pressure is still rising and the Red open light is not illuminated CUE: (at time of 1/2 scram): Relays 2K17 and 2K18 are de-energized
If asked any time after button is released for steam flow parameters:

Report: other operator is no longer available to monitor steam flow Comment:

ILT 14-1 NRC Control Room JPM 4 Page 11 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 12 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 21 Step 6.4.5 Remove fuse 11F-6F6 and verifies NS04B open Standard: Removes fuse 11F-6F6 and notices NS04B not fully open and steam pressure still rising CUE: fuse is removed (note: not modeled in simulator)

Comment:

SAT/UNSAT Performance Step: 22 Prior to auto scram operator Scrams reactor, Pushes scram pushbuttons and takes mode switch to shutdown Standard: Pushes Scram pushbuttons and takes mode switch to shutdown CUE: (after mode with to shutdown) report: another operator will perform further actions.

Comment:

SAT/UNSAT Terminating Cue:

Reactor is scrammed and the mode switch is shutdown.

JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 4 Page 13 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Validation of Completion JPM Number: NRC Control Room JPM 4 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 4 Page 14 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information JPM Setup

1. Rest to a full power IC (115 or other)

Note: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrntly ILT 14-1 NRC Control Room JPM 4 Page 15 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information STUDENT HANDOUT Initial Conditions:

  • The plant is operating at 100% power.
  • All steps of Section 3.0 PREREQUISITES are met and the Unit Supervisor has granted permission to perform the surveillance Test.

Task Cue:

Perform Main Steam Isolation Valve 10% Closure Test 602.4.004 Sections 6.1 through 6.4 ILT 14-1 NRC Control Room JPM 4 Page 16 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2000501401 Cool down the RPV using the Isolation Condenser tube side vents IAW SP-15, Alternate Pressure Control Systems - IC Tube Side Vents Task

Title:

(Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 5 K/A

Reference:

295021 AA1.04 (RO/SRO 3.7/3.7)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is shutdown and cooling down to COLD SHUTDOWN IAW RPV Control - no ATWS.
  • Isolation Condensers are not required to be isolated.
  • The Offsite radioactivity release rate is below that required for an Unusual Event.
  • All modes of pressure control for cooldown are unavailable except the Isolation Condenser Tube Side Vents.
  • The Isolation Condenser DC valves are isolated due to previous RPV level being >

180. RPV water level is currently 155 in and steady.

Task Standard:

RPV is being cooled down using Isolation Condenser B Tube Side Vents.

Required Materials: EMG-SP15 General

References:

1. Support Procedure 15, Alternate Pressure Control Systems - IC Tube Side Vents, Revision 1.

ILT 14-1 NRC Control Room JPM 5 Page 1 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue:

As the Unit Supervisor, I am directing you to establish a 10F/hr cooldown rate IAW SP-15, Alternate Pressure Control Systems - IC Tube Side Vents. A Isolation Condenser is the preferred system.

Time Critical Task: NO Validation Time: 11 minutes ILT 14-1 NRC Control Room JPM 5 Page 2 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 2.1.1 Verify Isolation Condensers are not required to be isolated.

Standard: Verifies Isolation Condensers are not required to be isolated.

Note: Initial Conditions state that Isolation Condensers are not required to be isolated.

Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 2.1.2 Verify Main Condenser is intact.

Standard: Verifies Main Condenser is intact.

Note: Initial Conditions state the Main Condenser is intact.

Comment:

ILT 14-1 NRC Control Room JPM 5 Page 3 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 4 Procedure Step: 2.1.3 Verify Offsite radioactivity release rate is expected to remain below the release rate, which requires an Unusual Event.

Standard: Verifies Offsite radioactivity release rate is expected to remain below the release rate, which requires an Unusual Event.

Note: Initial Conditions state that Offsite radioactivity release rate is expected to remain below the release rate, which requires an Unusual Event.

Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 2.2 Open the EOP BYPASS PLUGS panel inside of Panel 10XF.

Standard: Opens the EOP BYPASS PLUGS panel inside of Panel 10XF.

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 2.2.1 Remove the bypass plug from position BP2.

Standard: Removes the bypass plug from position BP2.

Comment:

ILT 14-1 NRC Control Room JPM 5 Page 4 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 7 Procedure Step: 2.2.2 Insert a bypass plug into position BP1.

Standard: Inserts a bypass plug into position BP1.

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 2.2.3 Remove the bypass plug from position BP4.

Standard: Removes the bypass plug from position BP4.

Comment:

SAT/UNSAT Performance Step: 9 Procedure Step: 2.2.4 Insert a bypass plug into position BP3.

Standard: Inserts a bypass plug into position BP3.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 5 Page 5 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 10 Procedure Step: 3.1 Verify that RPV Water Level is below 180 in.

Standard: Verifies that RPV Water Level is below 180 in.

CUE: If RPV water level has risen to > 180 in following the JPM setup, inform the applicant RPV water level is < 155 in and steady.

Comment:

SAT/UNSAT Performance Step: 11 Procedure Step: 3.2 Confirm open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser A: (Panel 1F/2F)

  • V-14-30
  • V-14-31 Standard: Confirms open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser A: (Panel 1F/2F)
  • V-14-30
  • V-14-31 Note: Places the CLOSE-AUTO-OPEN switch for the valves to the OPEN position.

Waits for valve indications to show red OPEN light lit and green CLOSED light extinguished.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 5 Page 6 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information NOTE: In the next step Isolation Condenser A vents will NOT open.

Alternate Path.

Performance Step: 12 Procedure Step: 3.3 Open the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11F)

  • V-14-5 / V-14-20 Standard: Opens the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11F)

V-14-5 / V-14-20 Note: Isolation Condenser A vent valves V-14-5 and V-14-20 will not open. The applicant will re-perform SP-15 starting at step 3.2 for Isolation Condenser B.

CUE: The applicant may inform the US that Isolation Condenser A vent valves will not open. Direct the applicant to continue with Support Procedure 15. (It is acceptable if the applicant establishes a cooldown using the Isolation Condenser B vents without first consulting the US.)

Comment:

SAT/UNSAT Performance Step: 13 Procedure Step: 3.2 Confirm open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser B: (Panel 1F/2F)

  • V-14-32 and V-14-33 Standard: Confirms open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser B: (Panel 1F/2F)
  • V-14-32 and V-14-33 Note: Places the CLOSE-AUTO-OPEN switch for the valves to the OPEN position.

Waits for valve indications to show red OPEN light lit and green CLOSED light extinguished.

Comment:

ILT 14-1 NRC Control Room JPM 5 Page 7 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 14 Procedure Step: 3.3 Open the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11F)

  • V-14-1 / V-14-19 Standard: Opens the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11F)
  • V-14-1 / V-14-19 Note: Waits for valve indications to show red OPEN light lit and green CLOSED light extinguished.

CUE: Another operator will continue with and control the cooldown that is already established.

Comment:

SAT/UNSAT Terminating Cue: RPV cooldown is in progress using Isolation Condenser B tube side vents.

JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 5 Page 8 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Control Room JPM 5 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 5 Page 9 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup

1. Reset to IC-115 or any shutdown IC where the Primary Containment is NOT isolated
2. Insert a manual scram
3. Stabilize RPV pressure around 500 psig
4. Stabilize RPV level below 180 in
5. Shut the IC A & B vents
6. Insert VLV-ICS002 to CLOSE
  • Keeps IC A vent valve V-14-5 closed
7. Insert VLV-ICS004 to CLOSE
  • Keeps IC A vent valve V-14-20 closed
8. Have a copy of SP-15 for the applicant ILT 14-1 NRC Control Room JPM 5 Page 10 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is shutdown and cooling down to COLD SHUTDOWN IAW RPV Control - no ATWS.
  • Isolation Condensers are not required to be isolated.
  • The Offsite radioactivity release rate is below that required for an Unusual Event.
  • All modes of pressure control for cooldown are unavailable except the Isolation Condenser Tube Side Vents.
  • The Isolation Condenser DC valves are isolated due to previous RPV level being > 180. RPV water level is currently 155 in and steady.

Initiating Cue:

As the US, I am directing you to establish a 10F/hr cooldown rate IAW SP-15, Alternate Pressure Control Systems - IC Tube Side Vents. A Isolation Condenser is the preferred system.

ILT 14-1 NRC Control Room JPM 5 Page 11 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2000501416 Task

Title:

Place the H2/02 Monitoring System in service Job Performance Measure No.: NRC Control Room JPM 6 (RO/SRO)

K/A

Reference:

500000 EA1.01 (RO/SRO 3.4/3.3)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • A LOCA is in progress

Task Standard:

Channel A H2/02 Monitoring System is in service.

Required Materials: None.

General

References:

1. Support Procedure 39, Placing the H2O2 Monitoring System in Service, Revision 1.

Initiating Cue:

As the US, I am directing you to place the H2/02 monitoring system in service IAW Support Procedure 39.

Time Critical Task: NO Validation Time: 7 minutes ILT 14-1 NRC Control Room JPM 6 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 3.1.1 (For Channel A) Verify the Power switch is in the ON position Standard: Verifies the Power switch is in the ON position for Channel A Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 3.1.2 Place switch for H2 Sample Supply V-38-37 to OPEN Standard: Places switch for H2 Sample Supply V-38-37 to OPEN Verifies that the red OPEN light is lit and the green CLOSE light is Note:

extinguished.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 6 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: 3.1.3 Place switch tor H2 Sample Supply V-38-38 to OPEN Standard: Places switch tor H2 Sample Supply V-38-38 to OPEN Note: Verifies that the red OPEN light is lit and the green CLOSE light is extinguished.

Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 3.1.4 Place switch for H2 Sample Return V-38-39 to OPEN Standard: Places switch for H2 Sample Return V-38-39 to OPEN Note: Verifies that the red OPEN light is lit and the green CLOSE light is extinguished.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 6 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 6 Procedure Step: 3.1.5 Place switch for H2 Sample Return V-38-40 to OPEN Standard: Places switch for H2 Sample Return V-38-40 to OPEN Verifies that the red OPEN light is lit and the green CLOSE llght is Note:

extinguished.

Comment:

SAT/UNSAT Performance Step: 7 Procedure Step: 3.1.6 Place switch for PUMP (P-38-5) in ENABLE position Standard: Places switch for PUMP (P-38-5) in ENABLE position Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 3.1.7 Depress Channel A ANALYZE PB to place Analyzer IT-1A in Analyze mode.

Standard: Depresses Channel A ANALYZE PB to place Analyzer IT-1A in Analyze mode.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 6 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 3.1.8 Touch CRT Screen and VERIFY:

  • GAS MONITORING SYSTEM screen ILLUMINATES
  • GAS MONITORING SYSTEM screen does not indicate Stand-By mode.

Standard: Touches CRT Screen and VERIFY:

  • GAS MONITORING SYSTEM screen ILLUMINATES
  • GAS MONITORING SYSTEM screen does not indicate Stand-By mode Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 3.1.9 Verify H2/02 Recorder AR-0002 begins recording Standard: Verifies H2/02 Recorder AR-0002 begins recording Cue: Inform the applicant Channel A has begun recording and another operator will continue with the support procedure Comment:

SAT/UNSAT Terminating Cue: Channel A of the H2/02 monitoring system has been placed in service IAW SP-39.

JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 6 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 14-1 NRC Control Room JPM 6 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 6 Page 6 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup

1. Reset to IC 115 (or similar IC)
2. Have a copy of SP-39 for the applicant ILT 14-1 NRC Control Room JPM 6 Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

Task Cue:

As the US, I am directing you to place the H2/02 monitoring system in service IAW Support Procedure 39.

ILT 14-1 NRC Control Room JPM 6 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2880101404 Task

Title:

Startup of the Turbine Building Ventilation System (Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 7 K/A

Reference:

288000 A4.01 (3.1/2.9)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is shutdown
  • The Turbine Building Ventilation System has been secured
  • All prerequisites to start the Turbine Building Ventilation System have been verified
  • Attachments 328-1, 328-2, 328-3 have been completed Task Standard:

The Turbine Ventilation System has been started utilizing Exhaust Fan 1-6 Required Materials: None.

General

References:

1. Procedure 328, Turbine Building Heating And Ventilation System, Revision 61 Initiating Cue:

Start the Turbine Building Ventilation System IAW Procedure 328, Turbine Building Heating And Ventilation System, starting at Step 5.1.2 Time Critical Task: NO Validation Time: 13 minutes ILT 14-1 NRC Control Room JPM 7 Page 1 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Reviews Precautions and Limitations.

Standard: Reviews Precautions and Limitations.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 7 Page 2 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Note: Exhaust Fan 1-7 will not start and initiates the Alternate Path.

Exhaust Fan 1-7 will not be re-started on the second attempt.

Alternate Path Performance Step: 3 Procedure Step: 5.1.2 Start EF-1-7 by placing EF-1-7 control switch to START.

Reports the fan does not start.

Standard: Starts EF-1-7 by placing EF-1-7 control switch to START.

Reports the fan will not start. (red light OFF; green light ON)

May contact EO to inspect the Fan.

Cue: As the SRO, acknowledge the fan will not start.

As the EO, report that you see no obvious abnormalities with the fan.

Comment:

SAT/UNSAT Note: The step below may occur any time during the JPM.

Performance Step: 4 Procedure Step: 5.1.2.1.1 Notify Radiation Protection anytime operating EF-1-6.

Standard: Notifies Radiation Protection anytime operating EF-1-6.

Cue: RP has been notified Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 7 Page 3 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 5 Procedure Step: 5.1.2.1.1 Confirm closed Dampers DM-28-8, DM-28-3 and their associated limit switches are made up Standard: Directs the EO to confirm closed Dampers DM-28-8, DM-28-3 and their associated limit switches are made up Cue: Dampers DM-28-8, DM-28-3 are closed and their associated limit switches are made up Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 5.1.2.1.4 Confirm open DM-28-4 and associated limit switches are made up.

Standard: Directs the EO to confirm open DM-28-4 and associated limit switches are made up.

Cue: Damper DM-28-4 is open and associated limit switches are made up.

Comment:

SAT/UNSAT Performance Step: 7 Procedure Step: 5.1.2.1.3 Start EF-1-7 by placing EF-1-7 control switch to START Standard: Starts EF-1-7 by placing EF-1-7 control switch to START and recognizes the fan will not start (red light OFF; green light ON)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 7 Page 4 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 8 Procedure Step: 5.1.2.1.4a If EF-1-7 fails to start on the second attempt, then place EF-1-6 in service as follows:

Open V-28-71 to drain any standing water from EF-1-6 Standard: Directs EO to Open V-28-71 to drain any standing water from EF-1-6 Cue: V-28-71 is open and a little water has drained out.

Comment:

SAT/UNSAT Performance Step: 9 Procedure Step: 5.1.2.1.4a When water has stopped draining, then close V-28-71 Standard: Directs EO to close V-28-71 when water has stopped draining Cue: Water has stopped draining and V-28-71 is closed Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 5.1.2.1.4c Confirm closed DM-28-8 Standard: Directs EO to confirm closed DM-28-8 Cue: DM-28-8 is closed Comment:

ILT 14-1 NRC Control Room JPM 7 Page 5 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SAT/UNSAT Performance Step: 11 Procedure Step: 5.1.2.1.4d Close DM-28-4.

Standard: Directs EO to close DM-28-4 Cue: DM-28-4 is closed Comment:

SAT/UNSAT Performance Step: 12 Procedure Step: 5.1.2.1.4e Open DM-28-3 Standard: Directs the EO to open DM-28-3 Cue: DM-28-3 is open Comment:

SAT/UNSAT Performance Step: 13 Procedure Step: 5.1.2.1.4f Start Exhaust Fan EF-1-6 by placing EF-1-6 control switch to ON Standard: Starts Exhaust Fan EF-1-6 by placing EF-1-6 control switch to START (red light ON; green light OFF)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 7 Page 6 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 14 Procedure Step: 5.1.3 Start Supply Fan SF-1-1 or SF-1-2 by placing Control Switch to ON Standard: Starts Supply Fan SF-1-1 or SF-1-2 by placing Control Switch to ON (red light ON; green light OFF) on panel 11R Comment:

SAT/UNSAT Performance Step: 15 Procedure Step: 5.1.4 Start Supply Fan SF-1-3 or SF-1-4 by placing Control Switch to ON.

Standard: Starts Supply Fan SF-1-3 or SF-1-4 by placing Control Switch to ON. (red light ON; green light OFF) on panel 11R Comment:

SAT/UNSAT Performance Step: 16 Procedure Step: 5.1.5 Start EF-1-33 by placing EF-1-33 control switch to ON.

Standard: Starts EF-1-33 by placing EF-1-33 control switch to ON. (red light ON; green light OFF) on panel 11R Comment:

ILT 14-1 NRC Control Room JPM 7 Page 7 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SAT/UNSAT Performance Step: 17 Procedure Step: 5.1.6 Start SF-1-5 or SF-1-6 by placing the control switch to ON.

Standard: Starts SF-1-5 or SF-1-6 by placing the control switch to ON. (red light ON; green light OFF) on panel 11R Comment:

SAT/UNSAT Performance Step: 18 Procedure Step: 5.1.7 Verify that EF-1-4 has started by observing the red indicating light Lit Standard: Verifies that EF-1-4 has started by observing the red indicating light Lit on panel 11R Comment:

SAT/UNSAT Performance Step: 19 Procedure Step: 5.1.8 Starts Feedwater Pump Room Supply Fan, SF-1-7, and Exhaust Fan, EF-1-1, by placing SF-1-7 and EF-1-1 control switch to ON Standard: Start Feedwater Pump Room Supply Fan, SF-1-7, and Exhaust Fan, EF-1-1, by placing SF-1-7 and EF-1-1 control switch to ON (red lights ON; green lights OFF)

Cue: Another Operator will continue with the procedure ILT 14-1 NRC Control Room JPM 7 Page 8 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Comment:

SAT/UNSAT Terminating Cue: The Turbine Ventilation System has been started utilizing Exhaust Fan 1-6 JPM Stop Time: ___________

Validation of Completion JPM Number: NRC Control Room JPM 7 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

ILT 14-1 NRC Control Room JPM 7 Page 9 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

Simulator Setup

1. IC-115. (but can be any IC)
2. Shutdown the TB Vent System IAW procedure 328, section 5.4
3. Insert the following:
a. LOA-TBS030 to OPEN
b. SWI-TBS017A to ON
c. These two malfunctions open the breaker to Exhaust Fan 1-7 but keeps the green light on
4. Insert ANN-L-2E to OFF
a. This keeps EF 7 TRIP annunciator off
5. Insert LOA-TBS011 to CLOSE (this closes DM-28-4)
6. Insert LOA-TBS012 to OPEN (this opens DM-28-3)
7. Insert LOA-TBS013 to OFF (stops SF 1-22)
8. Ensure the TURB BLDG VENT ISOLATION pushbutton on Panel 11R is depressed/reset before beginning JPM
9. Have a copy of 328, completed up to step 5.1.1 (for only section 5)

ILT 14-1 NRC Control Room JPM 7 Page 10 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is shutdown
  • The Turbine Building Ventilation System has been secured
  • All prerequisites to start the Turbine Building Ventilation System have been verified
  • Attachments 328-1, 328-2, 328-3 have been completed Task Cue:

Start the Turbine Building Ventilation System IAW Procedure 328, Turbine Building Heating and Ventilation System, starting at Step 5.1.2 ILT 14-1 NRC Control Room JPM 7 Page 11 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2150201401 Task

Title:

Perform an APRM Gain Adjustment Job Performance Measure No.: NRC Control Room JPM 8 K/A

Reference:

215005 A4.03 (RO 3.2/SRO 3.3)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Reactor Recirculation flow was just adjusted to attain 100% reactor power a short while ago.
  • Reactor power has been steady for the last 5 minutes.
  • Procedure 403 allows bypassing APRM 8.
  • The procedure revision, prerequisites and precautions and limitations have been verified by the Unit Supervisor.
  • APRM 8 is the ONLY APRM that requires an adjustment.

Task Standard:

APRM 8 should indicate 100% + 1% of Core Thermal Power (by meter on Panel 5R) and APRM 8 has been UNBYPASSED on Panel 4F.

Required Materials: None.

General

References:

1. 202.1-9, APRM Gain Adjustment From Heat Balance (Hard Card), revision 148 Initiating Cue:

Perform an APRM Gain Adjustment on APRM 8 IAW Attachment 202.1-9 starting at step 2.

Time Critical Task: NO ILT 14-1 NRC Control Room JPM 8 Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation Time: 5 minutes ILT 14-1 NRC Control Room JPM 8 Page 2 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Reviews Procedure revision, Prerequisites, and Precautions and Limitations.

Standard: Acknowledges the Initial Conditions state that the procedure revision, prerequisites and precautions and limitations have been verified with the US.

CUE: This was given in the Initial Conditions and the student may initial the step in section 1.0 as completed.

Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 2.1 Allow reactor power to stabilize for at least 2 minutes.

Standard: The student verifies from the Initial Conditions that reactor power has been stabilized for at least 2 minutes.

CUE: The Initial Conditions state that reactor power has been stable for 5 minutes.

Comment:

ILT 14-1 NRC Control Room JPM 8 Page 3 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SAT/UNSAT Performance Step: 4 Procedure Step: 2.2 If allowed by 403, bypass APRM 8.

Standard: Verifies from the Initial Conditions that Bypassing APRM 8 is allowed by Procedure 403.

Bypasses APRM 8 on Panel 4F by placing the APRM BYPASS joystick in the CH 8 position.

CUE: If the applicant begins reviewing Procedure 403, inform them (as stated in the Initial Conditions) 403 has already been reviewed and Bypassing APRM 8 is allowed.

Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 2.3 Pull out the APRM 8 drawer.

Standard: Pulls out APRM Drawer 8 on Panel 5R to allow access to the R10 screw (Gain adjustment screw).

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 2.4 Turn the gain adjustment pot with a small screwdriver (R10 on calibration and feedback unit) clockwise to raise gain or counterclockwise to lower gain while monitoring APRM output on the APRM 8 drawer.

Standard: Inserts small screwdriver and turns CCW or CW to change APRM power indication.

Comment:

ILT 14-1 NRC Control Room JPM 8 Page 4 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SAT/UNSAT Performance Step: 7 Procedure Step: 2.5 When output on APRM 8 drawer matches required APRM setting within 1%,

then stop gain adjustment.

Standard: When output on APRM 8 drawer matches required APRM (on PPC Heat Balance) setting within 1%, then stops gain adjustment. With reactor power at 100%, APRM 8 should indicate 100% + 1% of Core Thermal Power by meter indication on Panel 5R.

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 2.6 Verify the following:

  • FCTR Card Status light is GREEN
  • FCTR Active LEDs are GREEN
  • FCTR Curve Select Display is Zero Standard: Completes verification of FCTR card status light as green, FCTR active LEDs are green, FCTR curve select display as zero CUE: FCTR Card status light and Active LEDs are GREEN FCTR Curve select display is Zero Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 8 Page 5 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 9 Procedure Step: 2.7 Push in Selected drawer since FCTR card indications are indicating correctly Standard: APRM drawer pushed back into panel Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 2.8 Un-bypasses APRM 8.

Standard: Places the APRM 8 BYPASS joystick to the center position.

Comment:

SAT/UNSAT Performance Step: 11 Procedure Step: 2.9 If another APRM channel in the same drawer requires adjustment, then perform the APRM adjustment IAW steps 2.2 through 2.6.

Standard: Determines that no other APRM adjustments are required from the Initial Conditions.

CUE: Student will inform evaluator that APRM 8 Gain has been adjusted.

Comment:

SAT/UNSAT Terminating Cue:

APRM 8 should indicate 100% + 1% of Core Thermal Power (by meter on Panel 5R) and APRM 8 has been UNBYPASSED on Panel 4F.

JPM Stop Time: __________

ILT 14-1 NRC Control Room JPM 8 Page 6 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Control Room JPM 8 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 8 Page 7 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup

1. Reset the simulator to IC-115 or other rated power IC.
2. Change APRM 8 gain so that the APRM reads > 104%.
3. Have a blank copy of Attachment 202.1-9 rev 146, APRM Gain Adjustment From Heat Balance (Hard Card).
4. Ensure Heat Balance is displayed on PPC between Panel 3R and 4R.
5. Ensure APRMs 1 through 7 indicate 100%.
6. Ensure all APRM drawers are fully pushed in and latched.
7. Have a copy of procedure 403 for the students to Bypass APRM 8.
8. Have a copy of Attachment 403-2 which shows APRM bypass is allowed.

ILT 14-1 NRC Control Room JPM 8 Page 8 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • Reactor Recirculation flow was just adjusted to attain 100% reactor power a short while ago.
  • Reactor power has been steady for the last 5 minutes.
  • Procedure 403 allows bypassing APRM 8.
  • The procedure revision, prerequisites and precautions and limitations have been verified by the Unit Supervisor.
  • APRM 8 is the ONLY APRM that requires an adjustment.

Initiating Cue:

Perform an APRM Gain Adjustment on APRM 8 in accordance with Attachment 202.1-9 starting at step 2.

ILT 14-1 NRC Control Room JPM 8 Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2000501441 Task

Title:

Vent the Scram Air Header Job Performance Measure No.: NRC In-Plant JPM 1 K/A

Reference:

295037 EA1.05 (3.9/4.0)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant was at rated power when a valid RPS scram signal occurred.

Task Standard:

The scram air header has been vented and then restored to normal Required Materials: None.

General

References:

1. EMG-SP21, Alternate Insertion of Control Rods, revision 1 Initiating Cue: Vent the scram air header IAW EMG-SP21, section 4.3 Time Critical Task: NO Validation Time: 2 minutes ILT 14-1 NRC In-Plant JPM 1 Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 4.3.1 Close Scram Air Header isolation valve V-6-175 (RB 23 SE)

Standard: Closes Scram Air Header isolation valve V-6-175 (RB 23 SE) by rotating the valve operator CW until motion stops Cue: Scram Air Header isolation valve V-6-175 is closed Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 1 Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 4.3.2 Open Scram Air Header drain valve V-6-409 (RB 23 SE)

Standard: Opens Scram Air Header drain valve V-6-409 (RB 23 SE) by rotating the valve operator CCW until motion stops Cue:

  • Scram Air Header drain valve V-6-409 is open and air is heard rushing out the vent
  • The Control Room notifies you that all control rods indicate full-in Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 4.3.3.1 When control rods are no longer moving in, then perform the following:

1. Close Scram Air Header drain valve V-6-409 (RB 23 SE)

Standard: Closes Scram Air Header drain valve V-6-409 (RB 23 SE) by rotating the valve operator CW until motion stops Cue: Scram Air Header drain valve V-6-409 is closed Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 1 Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 4.3.3.2 When control rods are no longer moving in, then perform the following:

2. Open Scram Air Header isolation valve V-6-175 (RB 23 SE)

Standard: Opens Scram Air Header isolation valve V-6-175 (RB 23 SE) by rotating the valve operator CCW until motion stops Cue: Scram Air Header isolation valve V-6-175 is open Comment:

SAT/UNSAT Terminating Cue: The scram air header has been vented and then restored to normal JPM Stop Time: ___________

ILT 14-1 NRC In-Plant JPM 1 Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC In-Plant JPM 1 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC In-Plant JPM 1 Page 5 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Have a copy of EMG-SP21 for the applicant.

ILT 14-1 NRC In-Plant JPM 1 Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant was at rated power when a valid RPS scram signal occurred.

Task Cue:

Vent the scram air header IAW EMG-SP21, section 4.3 ILT 14-1 NRC In-Plant JPM 1 Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2640101401 Task

Title:

Start Diesel Generator 1 for Peaking Operations Job Performance Measure No.: NRC In-Plant JPM 2 K/A

Reference:

264000 K4.07 (3.3/3.4)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power.
  • The electrical grid is stable.
  • All prerequisites for starting EDG 1 have been verified.

Task Standard:

EDG 1 is started and loaded to within limits.

Required Materials: None.

General

References:

1. Procedure 341, Emergency Diesel Generator Operation, Revision 110 Initiating Cue:

Start EDG 1 for Peaking Operations IAW Procedure 341, Emergency Diesel Generator Operation, starting at Step 7.3.1.3.

Time Critical Task: NO Validation Time: 20 minutes ILT 14-1 NRC In-Plant JPM 2 Page 1 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Reviews Precautions and Limitations.

Standard: Reviews Precautions and Limitations Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 7.3.1.3 Place EDG-1 MODE SELECTOR SWITCH in the IDLE position Standard: Places EDG-1 MODE SELECTOR SWITCH in the IDLE position Cue: The EDG-1 MODE SELECTOR SWITCH in the IDLE position Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 2 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: 7.3.1.4 Start EDG-1 by placing the STOP/START SWITCH in the START position Standard: Starts EDG-1 by placing the STOP/START SWITCH in the START position (EDG speed rises)

Cue: The STOP/START SWITCH in the START position. The EDG has started.

The EDG is running at idle speed Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 7.3.1.5 Place EDG-1 MODE SELECTOR SWITCH in the RUN position Standard: Places EDG-1 MODE SELECTOR SWITCH in the RUN position after about 90 seconds Cue: The EDG-1 MODE SELECTOR SWITCH in the RUN position and the EDG noise has risen.

Note: 90 seconds is not critical Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 3 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 6 Procedure Step: 7.3.1.6 Verify engine speed increases Standard: Verifies engine speed increases Cue: The EDG speed and noise has increased.

Comment:

SAT/UNSAT Performance Step: 7 Procedure Step: 7.3.1.7 Place EDG-1 MODE SELECTOR SWITCH in the EXC position Standard: Places EDG-1 MODE SELECTOR SWITCH in the EXC position Cue: The EDG-1 MODE SELECTOR SWITCH in the EXC position Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 7.3.1.8 Compare EDG-1 output voltage with line voltage using the KILOVOLT METER selecting any GEN or BUS position on the VOLTAGE/FREQUENCY SELECTOR SWITCH Standard: Compares EDG-1 output voltage with line voltage using the KILOVOLT METER selecting any GEN or BUS position on the VOLTAGE/FREQUENCY SELECTOR SWITCH Cue: GEN volts is 3900 volts; BUS volts is 4160 volts Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 4 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 7.3.1.9 Adjust EDG-1 output voltage to be slightly higher than line voltage using the VOLTAGE CONTROL SWITCH Standard: Adjusts EDG-1 output voltage to be slightly higher than line voltage using the VOLTAGE CONTROL SWITCH in the RAISE position Cue: GEN volts is 4200 volts; BUS volts is 4160 volts Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 7.3.1.10.1 Place EDG-1 SYNCHROSCOPE ON/OFF SWITCH in the ON position with the synchroscope key Standard: Places EDG-1 SYNCHROSCOPE ON/OFF SWITCH in the ON position with the synchroscope key. The synchroscope is rotating slowly in the fast direction.

Cue: The EDG-1 SYNCHROSCOPE ON/OFF SWITCH in the ON position and the synchroscope is rotating slowly in the fast direction Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 5 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 7.3.1.10.2 Operate EDG-1 GOVERNOR CONTROL SWITCH so that the synchroscope hand is moving slowly in the fast direction, and the synchronizing lights are pulsing slowly in unison Standard: Confirms the synchroscope is rotating slowly in the fast direction and the synchronizing lights are pulsing slowly in unison Cue: The synchroscope is rotating slowly in the fast direction and the synchronizing lights are pulsing slowly in unison Comment:

SAT/UNSAT Performance Step: 12 Procedure Step: 7.3.1.10.3 Verify EDG-1 output voltage is slightly higher than line voltage Standard: Verifies EDG-1 output voltage is slightly higher than line voltage Cue: GEN volts is 4200 volts; BUS volts is 4160 volts Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 6 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 13 Procedure Step: 7.3.1.10.4 Place EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in one of the following positions; GEN 1-2, GEN 2-3, or GEN 3-1 Standard: Places EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in one of the following positions; GEN 1-2, GEN 2-3, or GEN 3-1 Cue: The EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in one of the following positions; GEN 1-2, GEN 2-3, or GEN 3-1 Comment:

SAT/UNSAT Performance Step: 14 Procedure Step: 7.3.1.10.5 Confirm the synchroscope hand is moving slowly in the fast direction Standard: Confirms the synchroscope hand is moving slowly in the fast direction Cue: The synchroscope hand is moving slowly in the fast direction Comment:

SAT/UNSAT Performance Step: 15 Procedure Step: 7.3.1.10.6 When EDG-1 synchroscope hand reaches the eleven o'clock position, then place EDG-1 BREAKER CONTROL SWITCH in the CLOSED position Standard: When EDG-1 synchroscope hand reaches the eleven o'clock position, then places EDG-1 BREAKER CONTROL SWITCH in the CLOSED position (red light ON; green light OFF; synchroscope remains stable)

Cue: The EDG-1 BREAKER indicates closed Comment:

ILT 14-1 NRC In-Plant JPM 2 Page 7 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Note: Minimum reactive load is +200 KVARS (lagging). Several repetitive pauses in raising load to switch between KWATTS and KVARS on the KILOWATT/KILOVAR Selector Switch may be required to achieve desired load without dropping below minimum KVARS. The Candidate may check VARS as KW load is rising.

Performance Step: 16 Procedure Step: 7.3.1.10.7 Raise load on EDG-1 to a minimum of 2500 KW by operating the GOVERNOR CONTROL SWITCH in RAISE position Standard: Positions the Ammeter Selector Switch to position 1 or 3 and positions the KILOWATT/KILOVAR Selector Switch to WATTS position to monitor KW Raises load on EDG-1 to a minimum of 2500 KW by operating the GOVERNOR CONTROL SWITCH in RAISE position (KW loading rises)

Position the Ammeter Selector Switch to position 1 or 3 and positions the KILOWATT/KILOVAR Selector Switch to VARS LAG position to monitor VARs Cue: The Ammeter Selector Switch is in position 1 or 3 and the KILOWATT/KILOVAR Selector Switch is in the WATTS position and KW Loading indicates 2700 KW after adjustment The Ammeter Selector Switch is in position 1 or 3 and the KILOWATT/KILOVAR Selector Switch is in VARS LAG position and VARs indicates >300 VAR as KW load is rising. When 2700 KW is obtained, state that VARS indicates 190 VARS.

Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 8 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Note: Step 7.3.1.10.8 and 7.3.1.10.9 are NA Performance Step: 17 Procedure Step: 7.3.1.10.10 If Auxiliary Transformer is supplying 4160V Bus 1C, then adjust EDG-1 VOLTAGE CONTROL SWITCH to control EDG KVAR loading to approximately +1000 KVAR (lagging) with an acceptable range of +200 to

+2000 KVAR (lagging).

Standard: Adjusts EDG-1 VOLTAGE CONTROL SWITCH to control EDG KVAR loading to approximately +1000 KVAR (lagging) with an acceptable range of

+200 to +2000 KVAR (lagging) by placing the switch to RAISE.

Cue: The KVAR loading is +1000 KVAR (lagging) after adjustment Note: This was adjusted in a prior step.

Comment:

SAT/UNSAT Performance Step: 18 Procedure Step: 7.3.1.10.11 Place EDG-1 SYNCHROSCOPE ON/OFF SWITCH in OFF position Standard: Places EDG-1 SYNCHROSCOPE ON/OFF SWITCH in OFF position Cue: The EDG-1 SYNCHROSCOPE ON/OFF SWITCH is in the OFF position Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 9 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 19 Procedure Step: 7.3.1.10.12 Place EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in OFF position Standard: Places EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in OFF position Cue: The EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH is in the OFF position Comment:

SAT/UNSAT Performance Step: 20 Procedure Step: 7.3.1.11 Monitor EDG-1 performance IAW Section 9.0 Standard: Monitors EDG-1 performance IAW Section 9.0 Cue: Another Operator will monitor EDG-1 performance IAW Section 9.0 Comment:

SAT/UNSAT Terminating Cue: EDG 1 is started and loaded to within limits JPM Stop Time: ___________

ILT 14-1 NRC In-Plant JPM 2 Page 10 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC In-Plant JPM 2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC In-Plant JPM 2 Page 11 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Setup

1. Have a copy of procedure 341, completed Section 7 up to step 7.3.1.3.

ILT 14-1 NRC In-Plant JPM 2 Page 12 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power.
  • The electrical grid is stable.
  • All prerequisites for starting EDG 1 have been verified.

Task Cue:

Start EDG 1 for Peaking Operations IAW Procedure 341, Emergency Diesel Generator Operation, starting at Step 7.3.1.3 NO plant manipulations or changes in plant configuration will be made. All actions will be simulated.

ILT 14-1 NRC In-Plant JPM 2 Page 13 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2010101001 Task

Title:

Line Up to Vent the TORUS through the Hardened Vent Job Performance Measure No.: NRC In-Plant JPM 3 K/A

Reference:

295024 EA1.14 (3.4/3.5)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • TORUS water level is 173".
  • Drywell pressure is 53 psig.
  • Hydrogen concentration less than 1.5 %.
  • CHRRMS indicates 1 x 103 R/Hr.
  • Exhaust fans 1-5 and 1-7 are operating.

Initiating Cue:

You are being dispatched from the OSC. Radiation Protection is on hand to support.

The US directs you to prepare the Torus to be vented through the hardened vent per EMG-SP35 section 2. You have a set of EO Building Keys.

Required Materials: None General

References:

1. EMG-SP35, Venting the TORUS via the Hardened Vent, Revision 2 Task Standard: The Torus is lined up to be vented via the Hardened Vent.

Time Critical Task: NO Validation Time: 10 minutes ILT 14-1 NRC In-Plant JPM 3 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 2.1 OBTAIN a MB-1 key.

Standard: Obtained a MB-1 key.

CUE: The Initiating Cue states the applicant already has a set of building keys (which includes a MB-1 key)

Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 2.2 VERIFY TORUS level is less than 348 in.

Standard: Verified TORUS level is less than 348 in. (Initial Condition)

CUE: If Control Room Contacted - TORUS Level is 173 Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 2.3 VERIFY Primary Containment H2 concentration is below minimum detectable (1.5% on H2/O2 Monitor)

Standard: Verified Primary Containment H2 concentration is below minimum detectable (1.5% on H2/O2 Monitor)

(Initial Condition)

CUE: If Control Room Contacted - H2 Concentration < 1.5%

Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 2.4 VERIFY CHRRMS Channels 1 and 2 are reading below 2 x 104 R/HR Standard: VERIFY CHRRMS Channels 1 and 2 are reading below 2 x 104 R/HR (Initial Condition)

CUE: If Control Room Contacted - CHRRMS Indicates 1X103 R/Hr Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 2.5 EVACUATE personnel from the Reactor Building SOUND the Reactor Building Evacuation alarm CONTACT Control Room to make evacuation announcement IAW EMG-SP35 Standard: Contacted Control Room to make evacuation announcement Evacuated personnel from the Reactor Building Sounded the Reactor Building Evacuation alarm IAW EMG-SP35 CUE: Reactor Bldg is evacuated Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 2.6 CONFIRM at least one Reactor Bldg. or Turbine Bldg. Exhaust Fan is running Standard: Confirmed at least one Reactor Bldg. or Turbine Bldg. Exhaust Fan is running (Initial Condition)

CUE: If Control Room Contacted - Exh Fans 1-5/1-7 are operating Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 2.7 CONFIRM N2 Purge Isolation Valve V-23-195 closed (Outside Rx Bldg, NE Corner)

Confirmed N2 Purge Isolation Valve V-23-195 closed Standard:

(Outside Rx Bldg, NE Corner)

CUE: V-23-195 is CLOSED Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 2.8 UNLOCK and CLOSE Nitrogen System Nitrogen Purge Header Isolation Valve V-23-357 (Outside Rx Bldg, NE Corner)

Standard: Unlocked and Closed Nitrogen System Nitrogen Purge Header Isolation Valve V-23-357 (Outside Rx Bldg, NE Corner)

CUE: V-23-357 is CLOSED Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 2.9 UNLOCK and OPEN the Nitrogen System Stack Isolation Valve V-23-358 (Outside Rx Bldg, NE Corner)

Unlocked and Opened the Nitrogen System Stack Isolation Valve V-23-358 Standard:

(Outside Rx Bldg, NE Corner)

CUE: V-23-358 is OPEN Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 2.10 INFORM the US that the Torus is ready to be vented via the Hardened Vent Standard: Informed the US that the Torus is ready to be vented via the Hardened Vent Comment:

SAT/UNSAT Terminating Cue: The Torus is ready to be vented via the Hardened Vent.

JPM Stop Time: ___________

ILT 14-1 NRC In-Plant JPM 3 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC In-Plant JPM 3 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC In-Plant JPM 3 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Provide a copy of EMG-SP35, Venting the TORUS via the Hardened Vent, Revision 2 ILT 14-1 NRC In-Plant JPM 3 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET INITIAL CONDITIONS

  • TORUS level is 173".
  • Drywell pressure is 53 psig.
  • Hydrogen concentration less than 1.5 %.
  • CHRRMS indicates 1 x 103 R/Hr.
  • Exhaust fans 1-5 and 1-7 are operating.

INITIATING CUE You are being dispatched from the OSC. Radiation Protection is on hand to support. The US directs you to prepare the Torus to be vented through the hardened vent per EMG-SP35 section 2. You have a set of EO Building Keys.

There will be NO manipulation or change of plant components.

ILT 14-1 NRC In-Plant JPM 3 Page 10 of 10

NRC 2016 Scenario 1 (New)

Scenario Outline Facility: Oyster Creek Scenario No.: 1 Op Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

  • 97% power
  • Risk is Yellow Turnover:
  • Lower power to 95% using recirculation flow IAW 1001.22-3, Core Maneuvering Daily Instruction Sheet.
  • Following the power reduction Backwash A North Condenser IAW procedure 323.6 Event No. Malf. No. Event Type* Event Description 1 N/A R ATC Lower power with Recirc flow SRO BOP 2 N/A N Backwash A North Condenser SRO MAL- C 3 CRD002 ATC A CRD pump trips TS SRO MAL- C BOP 4 ICS002A Isolable Isolation Condenser A tube leak TS SRO MAL- C ATC Respond to a reference leg leak in the A & C GEMAC 5 NSS012E TS SRO RPV level indicators ID13A and ID13C MAL- C BOP 6 TCS010 EPR failure low SRO MAL-CRD001 MAL-CRD010_ ATC/ Respond to B CRD pump to trip and Responds to an 7 1851 C

All HCU accumulator failure MAL-CRD010_

2251 NRC 2016 Scenario 1 Page 1 of 22

NRC 2016 Scenario 1 (New)

SRV-NSS001C MAL- MSIVs close and Safety Valve Lifts after Scram 8 M All NSS013C MAL-NSS013D BKR- BOP Trip of Containment Spray Pump 9 CNS008 C

SRO

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC 2016 Scenario 1 Page 2 of 22

NRC 2016 Scenario 1 (New)

Simulator Summary Event Event Summary 1 The ATC will lower reactor power to approximately 95% with recirculation flow using the Master Recirc Speed Controller. (ATC:

Reactivity Manipulation) 2 The BOP will backwash condenser A North IAW procedure 323.6, Backwashing Condensers. This will require several switch manipulations by the BOP and observe condenser parameters. (BOP:

Normal Evolution) 3 The ATC will respond to a trip of CRD Pump A IAW RAP H-1-c. The ATC will start CRD Pump B. The SRO will review and apply Tech Spec 3.4.D.2. (ATC: Component Malfunction; SRO: Tech Specs) 4 Then A Isolation Condenser develops a tube leak (MAL ICS002A).

Crew enters Rad Release Control and requires manually isolating the A IC (BOP: Component Malfunction; SRO: Tech Specs).

5 The ATC will diagnose a rising RPV water level. Indications of actual RPV water level will rise on Panel 4F and Panel 5F/6F Yarway indications. The ATC will perform actions to stabilize RPV water level IAW ABN-17, Feedwater System Abnormal Conditions. The ATC will take manual control of RPV water level and swap Feedwater Level Control to the alternate water level instrument ID13B. The increased Primary Containment leakage will result in a rise in unidentified leak rate and the SRO will review and apply Tech Spec 3.3.D.2. (ATC:

Instrument Malfunction; SRO: Tech Specs) 6 Rx pressure begins to drop and the crew recognizes that the EPR is failing low. The crew enters ABN-9 and transfers pressure control over to the MPR. (BOP: Component Malfunction) 7 Once Rx pressure is restored Following the EPR failure the B CRD pump will trip and there is no standby pump to start. The Crew will enter ABN-1 and attempt to scram the reactor when two accumulators come in. (ATC/Crew: Component) 8 Upon scramming the US enters RPV control no ATWS. When the Reactor is scrammed a Safety to fail open (SRV-NSS001C) which drives DW temp and Pressure up. The US then enters Primary Containment control (CREW: Major)

NRC 2016 Scenario 1 Page 3 of 22

NRC 2016 Scenario 1 (New) 9 When required the crew attempts to lineup containment spray system two in preparation for reducing containment pressure or temperature and recognizes that containment pump #1 started then tripped and must start the second containment pump in system two to reduce drywell parameters. (BOP: Component Malfunction)

Critical Given an isolable leak outside the Reactor Building , the crew must Task 1 isolate the leak, in accordance with Rad Release control.

Critical Given a loss of all CRD, the crew must insert a manual reactor scram Task 2 in accordance with ABN-1.

Critical The must initiate containment spray to restore and maintain <281of or Task 3 when containment pressure exceeds 12 psig IAW Primary Containment Control.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

2. Malfunctions after EOP entry (1-2) 2 8,9
3. Abnormal events (2-4) 3 5,6,7
4. Major transients (1-2) 1 8
5. EOPs entered/requiring substantive 2 Primary actions (1-2) Containment RPV control No ATWS
6. EOP contingencies requiring substantive 0 N/A actions (0-2)
7. EOP Critical tasks (2-3) 2 4,7,9 NRC 2016 Scenario 1 Page 4 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 1 Event

Description:

Lower reactor power to 95% using recirculation flow Initiation: Following shift turnover Cues: As directed by the SRO following shift turnover Time Position Applicants Actions or Behavior SRO

  • Approves the ReMA and provides to the ATC
  • Directs the ATC to lower power to 95% IAW the Core Maneuvering Daily Instruction Sheet
  • Acts as the reactivity Manager
  • Provides a reactivity brief
  • May notify the Power team when at 95% power ATC
  • Lowers power IAW the Core Maneuvering Daily Instruction Sheet o May review 202.1, section 6.0, Power Reductions o Rotates the MASTER RECIRC SPEED CONTROLLER manual knob CW o Monitors power, level, pressure o Reports to SRO when rated power is reached BOP o Provides second check for the reactivity manipulation Terminus: Reactor power is approximately 95%

BOOTH: If directed by lead evaluator to move to event #2:

- Call as SM to secure from Power reduction and maintain power where it currently is due to maintenance being moved.

Notes/Comments NRC 2016 Scenario 1 Page 5 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 2 Event

Description:

Continue backwashing Main Condenser Half A North Initiation: Reactor power is approximately 95%, or as directed by the Lead Examiner Cues: As directed by the SRO Time Position Applicants Actions or Behavior SRO Directs BOP to backwash A North Condenser IAW procedure 323.6, starting at step 5.1.3.1.

BOP

  • Performs backwash of condenser half A North IAW procedure 323.6, starting at step 5.1.3.1 o Verifies the following:

All condenser valves are in the normal position The inlet & outlet valves for each condenser half are open The backwash valves and the cross connect valves for each condenser are closed May verify the EO is aware of which valves will be operated [ROLE PLAY]

o Places the COND A NORTH BACKWASH CONTROL switch to BACKWASH o After about 10 seconds, places the COND A NORTH CIRC WATER INLET & OUTLET switch to CLOSE o Verifies the following:

V-3-12, COND A NORTH CIRC WATER INLET valve closed V-3-27, COND A NORTH CIRC WATER OUTLET valve closed V-3-18, COND A NORTH BACKWASH CONTROL valve open V-3-24, COND A NORTH CONNECT valve open V-3-28, COND A SOUTH CIRC WATER OUTLET valve closed NRC 2016 Scenario 1 Page 6 of 22

NRC 2016 Scenario 1 (New)

V-3-13, COND A SOUTH CIRC WATER INLET valve open V-3-19, COND A SOUTH BACKWASH CONTROL valve closed o Backwashes for about 3-5 minutes o Monitors the following during backwash:

Condenser Hotwell Level Turbine Exhaust Hood Temperature Condenser Vacuum o Places the COND A NORTH CIRC WATER INLET &

OUTLET switch to OPEN o After about 10 seconds, places the COND A NORTH BACKWASH CONTROL switch to CLOSE o Verifies the following:

V-3-12, COND A NORTH CIRC WATER INLET valve open V-3-27, COND A NORTH CIRC WATER OUTLET valve open V-318, COND A NORTH BACKWASH CONTROL valve closed V-3-13, COND A SOUTH CIRC WATER INLET valve open V-3-28, COND A SOUTH CIRC WATER OUTLET valve open V-3-19, COND A SOUTH BACKWASH CONTROL valve closed V-3-24, COND A CROSS CONNECT valve closed

  • Reports A North condenser backwash is complete ROLE PLAY When told as the EO which backwash valves will be operated, acknowledge the report Terminus: Main condenser backwash is complete Notes/Comments NRC 2016 Scenario 1 Page 7 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 3 Event

Description:

CRD Pump A trips requiring Tech Spec LCO entry (Trigger 1)

Initiation: Backwash of B North Condenser is complete or as directed by the Lead Examiner.

Cues: Annunciator H1c, PUMP A OL; H7c, CHARG WTR PRESS LO; COOLING WATER FLOW, CLG WTR/REACTOR P, DRV WTR/REACTOR P indicate downscale; CRD Pump A breaker open Time Position Applicants Actions or Behavior ATC

  • Responds to annunciator H1c, PUMP A TRIP o Reports CRD Pump A tripped o Dispatches EO to investigate pump/breaker [ROLE PLAY]

o Starts CRD Pump B by placing CRD PUMP NC08B switch to START o Ensures CRD parameters return to normal bands o Reports CRD Pump B running with CRD indications return to normal SRO

  • Notifies SM/WWM about the pump trip
  • Reviews and applies Tech Spec 3.4.D.2 o If one CRD hydraulic pump becomes inoperable when the reactor water temperature is above 212 ºF, the reactor may remain in operation for a period not to exceed 7 days provided the second CRD hydraulic pump is operating and is checked at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. If this condition cannot be met, the reactor water temperature shall be reduced to less than 212 ºF ROLE PLAY As the EO investigating the CRD Pump A trip, wait 1 minute and report the pump tripped on overload.

- If asked status of B CRD pump start

- Report Good start on B CRD pump Terminus: CRD Pump B is in service and the SRO has addressed Tech Specs Notes/Comments NRC 2016 Scenario 1 Page 8 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 4 Event

Description:

A Isolation condenser Tube leak (TRIGGER 3)

Initiation: Standby CRD pump running and T.S determination has been made or as directed by the Lead Examiner.

Cues: Rising levels in A shell level and temperature, RAP-10F-1-k, RAP-C6a Time Position Applicants Actions or Behavior CREW

  • Recognizes Area Rad Monitor C-3 is alarming.
  • Recognizes high level in A IC shell.
  • Recognizes high shell temperature
  • Makes update of Tube leak in A IC ROLE PLAY: 3 minute after inserting the leak or as directed by the lead evaluator:

Report as EO from Boiler House that steam is coming out of A IC vents to the yard.

SRO

  • Enters Radioactivity Release Control
  • Directs isolating A Isolation Condenser
  • Per Tech Spec 3.8, determines that the plant may continue operation for 7 days.

BOP

  • Reports Area Rad monitors levels
  • Isolates A Isolation Condenser CRITICAL TASK 1 Terminus: A IC is isolated and T.S declaration is made Notes/Comments NRC 2016 Scenario 1 Page 9 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 5 Event

Description:

Responds to a leak in the common variable leg to RPV water level instruments ID13A and ID13C (TRIGGER 5)

Initiation: Isolation condenser is isolated or as directed by the Lead Examiner Cues: ID13A and ID13C indication lowers; Other RPV water level indicators rising; Drywell pressure, temperature, unidentified leakage rising Time Position Applicants Actions or Behavior ATC

  • Reports Indicated RPV water level lowering on NR GEMACs ID13A and ID13C, with RPV water level rising on all other available RPV water level instruments
  • Reports small rise in Drywell pressure, temperature and Drywell unidentified leak rate
  • Performs ABN-17, Feedwater System Abnormal Conditions OR ABN-59, RPV Level Instrument Failures (same actions in both ABNs) o Places the MASTER FEEDWATER LEVEL CONTROLLER in manual by pressing the AUTO/MAN pushbutton o Confirms Feedwater flow is approximately equal to steam flow Lowers feedwater flow by turning the manual knob on the MASTER FEEDWATER LEVEL CONTROLLER CCW to match TOTAL STEAM FLOW and TOTAL FEEDWATER FLOW o Places the LEVEL TRANSMITTER SELECTOR to the B position o Selects the S display on the MASTER FEEDWATER LEVEL CONTROLLER o Matches the S display to the P display by turning the manual knob on the MASTER FEEDWATER LEVEL CONTROLLER o When the deviation = 0 (S = P; Y = 0), then places the turning the manual knob on the MASTER FEEDWATER LEVEL CONTROLLER in AUTO o Monitors RPV water level and Feedwater flow NRC 2016 Scenario 1 Page 10 of 22

NRC 2016 Scenario 1 (New) o Maintains RPV water level at 160 or as directed by the US Reports RPV water level transmitters swapped, Feedwater in auto and controlling.

BOP

  • May perform Drywell venting IAW attachment 312.11-10 or ABN-63, if directed o Opens Torus vent valve V-28-47 o Opens Torus vent valve V-28-18 o Monitors DW pressure
  • May perform Drywell venting IAW attachment 312.11-12 or ABN-63, if directed o Opens Drywell vent valve V-23-21 o Opens Drywell vent valve V-23-22
  • May maximize cooling and start 5th drywell fan IAW ABN-63
  • Directs entry into ABN-17, Feedwater System Abnormal Conditions OR ABN-59, RPV Level Instrument Failures
  • Notifies SM/WWM for repair/investigation of RPV water level instruments ID13A and ID13C
  • May direct Drywell venting and maximizing cooling IAW 312.11-10 or 312.11-12 or ABN-63
  • Enters Tech Spec 3.3.D.1 for 2 gpm increase in unidentified leakage in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period
  • With the reactor coolant system leakage greater than the limits in 3.3.D.1.a or b above, reduce the leakage rate to within the acceptable limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in the cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Terminus: RPV water level transmitters have been swapped, Feedwater is in auto and is controlling, and the SRO has reviewed/applied the Tech Specs NRC 2016 Scenario 1 Page 11 of 22

NRC 2016 Scenario 1 (New)

Notes/Comments NRC 2016 Scenario 1 Page 12 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 6 Event

Description:

EPR fails low requiring transfer to MPR (TRIGGER 7)

Initiation: Rx water level has been stabilized or as directed by the Lead Examiner Cues: Rx pressure lowers Time Position Applicants Actions or Behavior CREW

  • Recognizes lowering Rx pressure ATC
  • Monitors critical parameters
  • Reports DW pressure to crew US
  • Directs entry into ABN-9
  • Refers to procedure 202.1 for limitations on power with one pressure regulator out of service BOP
  • Makes update EPR failure
  • Performs ABN-9 actions
  • Transfers RPV pressure control to MPR by
  • Lowering MPR setpoint until MPR takes over
  • Verifies EPR controlling light off
  • Turns off EPR power switch to off
  • Verifies alarm Q6a is recieved
  • Slowly raises Rx pressure back to normal band with MPR as directed by US by
  • Slowly raising MPR setpoint until pressure back in band Terminus: The MPR is placed in service and pressure band is back in band Notes/Comments NRC 2016 Scenario 1 Page 13 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 7 Event

Description:

Trip of B CRD pump and two accumulator alarms come in forcing Rx scram B (TRIGGER 9)

Initiation: MPR is controlling pressure in band, or as directed by the Lead Examiner Cues: RAP H-7-c, RAP H-8-c, RAP H-7-a, CRD hydraulic parameters drop to 0 Time Position Applicants Actions or Behavior Crew

  • Refers to Raps
  • Determines B CRD pump has tripped and will not restart.
  • Makes update that B CRD pump cannot be restarted.
  • Directs EOs to investigate pump and breakers for CRD pumps.

SRO

  • Sets scram criteria when 2 HCU alarms come in Role BOOTH: If directed to investigate CRD pump as EO 3 minutes later play
  • Report B CRD breaker tripped on Overload.

ATC

  • PLACE the Reactor Mode Switch in SHUTDOWN position.
  • VERIFY that all rods are fully inserted (at or beyond position 04).
  • VERIFY that reactor power is lowering.
  • UPDATES US that immediate scram actions are complete.
  • ENTERS RPV CONTROL No-ATWS
  • DIRECT URO to maintain RPV water level 138 to 160 TAF using feed/condensate. Uses SP-2.
  • When RPV level begins to rise Trips two feed pumps, places MFRVs to manual and closes them when
  • CONFIRMs main turbine tripped, GC1 and GD1 OPEN, generator field breaker OPEN, S1A and S1B closed
  • EXECUTE the following RPV Control - No ATWS steps when directed:

NRC 2016 Scenario 1 Page 14 of 22

NRC 2016 Scenario 1 (New)

URO

  • MAINTAIN RPV level between 138 and 160 in. with SP-2.

Terminus: Rx is scrammed and all rods in Notes/Comments NRC 2016 Scenario 1 Page 15 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 8 Event

Description:

MSIVs close and Safety Valve Lifts after Scram (TRIGGER 11)

Initiation: When Reactor is scrammed and scram pushbuttons are pressed Cues: MSIV position indication Drywell pressure and temperature rise, safety acoustic high Time Position Applicants Actions or Behavior Crew

  • Recognizes that outboard MSIVs close and Safety valve is stuck open SRO
  • Enters Primary Containment Control when DW pressure exceeds 3.0 psig and directs the following operator actions:
  • Continues pressure control to B Isolation condenser and EMRVs per SP-11/12
  • When required directs maximizing drywell cooling per SP-27
  • Directs H 2 /O 2 IAW SP-39 when applicable
  • Monitor bulk drywell temperature.
  • Maximize drywell cooling per SP-27 when directed
  • Initiate H 2 /O 2 IAW SP-39 when directed.
  • Evaluates the usability of RPV water level instrumentation per SP-28 when directed.

BOP

  • Maintains RPV pressure as directed per SP-11 using B isolation and EMRVs as necessary with SP-12 US
  • Directs lineup of DW sprays before bulk drywell temperature reaches 281°F or DW or Torus pressure reaches 12 psig per SP-29.

RO

  • Performs SP-29 for lineup of DW spray
  • Confirms DW Fans and Recirc pumps are tripped

NRC 2016 Scenario 1 Page 16 of 22

NRC 2016 Scenario 1 (New)

Notes/Comments NRC 2016 Scenario 1 Page 17 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 9 Event

Description:

Trip of Containment Spray Pump (TRIGGER 13 or 15)

Initiation: When containment spray pump is started to reduce Drywell parameters Cues: Pump Red light off, Containment spray flow drops to 0 Time Position Applicants Actions or Behavior US

  • Directs spraying to the drywell IAW SP-29 when above 12 psig in the drywell RO
  • Once directed to spray the DW
  • Places system mode select to DW spray position
  • Verifies valves reposition
  • Starts ESW pump by turning switch

BOOTH If 1-3 Containment Spray pump running

  • INSERT: Trigger 15 RO
  • May start second ESW pump by turning switch CRITICAL TASK 3
  • Verifies system parameters

Terminus: Drywell parameters are in band along with Rx pressure and Level.

Final EAL FA Any Loss or Potential Loss of either the Fuel Clad or RCS.

Call Lost Reactor Coolant System Barrier.

NRC 2016 Scenario 1 Page 18 of 22

NRC 2016 Scenario 1 (New)

Procedures Used Event Procedure 1

  • 202.1
  • 301.2 2
  • 323.6 3
  • ABN-17
  • ABN-59
  • 312.11 6
  • ABN-9
  • 202.1 7
  • RPV Control No-ATWS
  • EMG-SP2 8
  • EMG-SP11
  • EMG-SP12
  • EMG-SP1
  • EMG-SP39
  • EMG-SP29
  • EMG-SP27 9
  • EMG-SP29 NRC 2016 Scenario 1 Page 19 of 22

NRC 2016 Scenario 1 (New)

Simulator Setup

1. Reset to IC-40 (bwr-2)
2. Lower power to 97%
3. Have a copy of 202.1 and 301.2 for the applicants
4. Have a Copy of 323.6 for applicants
5. Hang tags on Containment Spray system 1
6. Protect Containment Spray system 2
7. Risk is Yellow Event Trigger Malfunction Containment Spray System 1 Tag Out Preset n/a LOA-CNS054, rack out LOA-CNS051, rack out VLV-CNS002, close BKR-CNS007, fail control fuse BKR-CNS005, fail control fuse 1 NA NA 2 N/A N/A 3 T1 BKR-CRD002 to TRIP This trips CRD Pump A 4 T3 MAL-ICS002A, 5%, ramp 120 seconds A IC tube leak occurs 5 T5 MAL- NSS012E to 2% over a 900 Sec ramp This places a leak in the common variable leg to NR GEMAC water level instruments ID13A and ID13C (this also inputs into FWLC).

6 T7 MAL-TCS010, 900 psig, 60 sec ramp Fails EPR setpoint to 900 psig 7 T9 BKR-CRD001 , Trip trips "B" CRD pump MAL-CRD010_1851, 60 sec delay HCU 1851 accumulator alarm MAL-CRD010_2251, 100 sec delay HCU 2251 accumulator alarm NRC 2016 Scenario 1 Page 20 of 22

NRC 2016 Scenario 1 (New) 8 MAL-NSS013C, 0 Closes MSIVs T11 MAL-NSS013D, 0 Closes MSIVs SRV-NSS001C, 25% , ramp 200 seconds Lifts Safety Valve 25% open, 9 T13 If 1-3 containment spray pump running BRK-CNS008, Trip Trips 1-3 containment Spray pump T15 If 1-4 Containment Spray pump running BKR-CNS006, Trip Trips 1-3 containment Spray pump NRC 2016 Scenario 1 Page 21 of 22

NRC 2016 Scenario 1 (New)

Shift Turnover Current plant conditions:

  • 97% power
  • Risk is Yellow Shift Activities
  • Lower power to 95% using recirculation flow IAW 1001.22-3, Core Maneuvering Daily Instruction Sheet.
  • Following the power reduction Backwash A North Condenser IAW procedure 323.6 NRC 2016 Scenario 1 Page 22 of 22

NRC 2016 Scenario 2 (New)

Scenario Outline Facility: Oyster Creek Scenario No.: 2 Op Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

  • 100% power
  • Air Compressor #3 is tagged OOS
  • EDG #2 Out of service Turnover:
  • Diesel Generator #2 has been out of service for 2 days due to failure to start during the load test. It is scheduled to be returned to service the next day. The diesel load test for #1 diesel is due next shift.
  • Air Compressor #3 is OOS for troubleshooting due to failure to start.
  • Swap RBCCW pumps IAW 309.2 Event No. Malf. No. Event Type* Event Description 1 N BOP, N/A Swap RBCCW pumps SRO RWCU isolable leak (failure of one isolation valve)

MAL- C BOP, 2 EMG-3200.11, Secondary Containment Control RCU013 TS SRO T.S. 3.5 MAL- ALL Loss of VMCC 1B2 C

3 EDS004 ABN-51, Loss of VMCC 1B2 B TS T.S.-

SRO T.S. 3.7 MAL- ATC, CRD Flow Control Failure 4 CRD001 C SRO A ABN-6, Control Rod Malfunctions MAL-OGS003 C OFF-Gas Deflagration/ with condenser vacuum leak 5 ALL ABN-25, OFF-Gas Deflagration MAL- R ABN-14, Loss of Condenser Vacuum CFW017 NRC 2016 Scenario 2 Page 1 of 26

NRC 2016 Scenario 2 (New)

MAL-GEA005 Loss of Stator Cooling A C ALL 6 ABN-11 Loss of Generator Stator Cooling MAL-GEA005 EMG-3200.01A RPV control No-ATWS B

CAEP M 7 ATWS.C Electric ATWS ALL AE EMG-3200.01B RPV control-With ATWS MAL-TCS006 D C BOP, Failure of Turbine Bypass Fails 8

Through SRO EMG-3200.01B, RPV control w/atws TCS006I

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC 2016 Scenario 2 Page 2 of 26

NRC 2016 Scenario 2 (New)

Simulator Summary Event Event Summary 1 The BOP will swap RBCCW pumps IAW 309.2, Reactor Building Closed Cooling Water System, Section 15. (BOP: Normal Evolution) 2 A RWCU system break will occur with failure of cleanup to automatically isolate. The crew will enter secondary containment control and investigate radiation levels and temperatures in Rx Building. The RWCU HELB alarms will come in and the crew will manually attempt to isolate cleanup but will be unable to close cleanup isolation valves V-16-1. The US will determine T.S applicability IAW section 3.5. (BOP: Component Malfunction; SRO: Tech Specs) 3 The crew will respond to the trip of VMCC 1B2 and enter ABN-51, Loss of VMCC 1B2. The BOP will restore power to PSP-2 and the ATC will reset the 1/2 scram. The SRO will review TS 3.7 and enter a cold shutdown LCO. (BOP: Component Malfunction; SRO: Tech Specs) 4 The ATC will respond to in-service CRD Flow Control Valve failing closed. The ATC will swap Flow Control Valves IAW procedure 302.1, Control Rod Drive System. (ATC: Component Malfunction) 5 This is followed by an Off-Gas deflagration the isolates off-gas. Once the Off-Gas alarms clear the crew confirms no damage to plant and reset Off-Gas system. Once the Off-Gas system is reset a small vacuum leak occurs forcing the crew to reduce power until vacuum recovers (ATC: Component Malfunction, BOP: Component Malfunction) 6 The running Stator Water Cooling Pump will trip and ABN-11 will be entered. The standby Stator Water Cooling Pump is not available since it was powered from Bus 1B1 and therefore all stator water cooling is lost and a turbine runback will occur. IAW the ABN, when the runback occurs, the ATC will insert a manual scram. (ATC: Component) 7 The Crew will diagnose an electric ATWS and the SRO will direct entry into RPV Control - with ATWS EOP. The ATC will perform actions to insert control rods and the BOP will perform actions to control Torus water temperature and RPV water level. (Major Evolution) (PRA)

NRC 2016 Scenario 2 Page 3 of 26

NRC 2016 Scenario 2 (New) 8 While the crew Terminates and Prevents injection IAW SP-17, the bypass valves will go closed forcing the crew to augment Rx pressure control with Isolation Condensers and EMRVs for pressure control (Component Failure After EOP)

Critical Given a failure to scram, the crew must terminate and prevent injection Task 1 in accordance with EOP SP-17 Critical Given a failure to scram, the crew must recommence injection to the Task 2 reactor in accordance with EOP SP-19.

Critical Given a failure to scram, the crew must vent the scram air header in Task 3 accordance with EOP SP-21 Critical Given an isolable leak from RWCU, the crew must isolate the RWCU system Task 4 in accordance with secondary Containment Control ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

1. Malfunctions after EOP entry (1-2) 2 7,8
2. Abnormal events (2-4) 4 3,4,5,6
3. Major transients (1-2) 1 7
4. EOPs entered/requiring substantive 1 RPV control actions (1-2) No-ATWS
5. EOP contingencies requiring substantive 1 RPV Control actions (0-2) W/ATWS
6. EOP Critical tasks (2-3) 4 2,7,8 NRC 2016 Scenario 2 Page 4 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 1 Event

Description:

Swap RBCCW Pumps Initiation: Following shift turnover Cues: As directed by the SRO following shift turnover Time Position Applicants Actions or Behavior SRO

  • Directs the EO to open the RBCCW Pump 1 Casing Vent valve V-5-511 until a steady stream is established, then close the valve [ROLE PLAY 1]
  • Starts the RBCCW Pump 1 by placing its control switch to the START position [ROLE PLAY 2]
  • Verifies the RBCCW Pump 1 ON light lit
  • Verifies proper pump discharge pressure
  • Immediately stops RBCCW Pump 2 by placing its control switch to the STOP position
  • Monitors plant parameters ROLE 1)When asked to open RBCCW Pump 1 vent valve V-5-511, state that you PLAY have opened the valve, established a steady stream, then closed the valve (NO Booth actions are required).

2)WHEN RBCCW Pump 1 is started, report a good start on RBCCW Pump 1 Terminus: RBCCW Pumps have been swapped IAW 309.2 Notes/Comments NRC 2016 Scenario 2 Page 5 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 2 Event

Description:

Respond to isolable Leak in the RWCU System with a failure of one isolation valves (TRIGGER 1)

Initiation: When RBCCW pumps are swapped or as directed by the Lead Examiner.

Cues: Annunciators L6c, RB P LOW; D1d, D2d, RWCU HELB I/II; D8d, CU ROOM TEMP HI; 10F1k, AREA MON HI; 10F3k, CU SYS AREA HI Time Position Applicants Actions or Behavior BOP

  • Makes update that RB D/P alarm is in
  • Makes update on RB D/P pressure
  • Monitors Reactor building area temperatures and Radiation levels when directed
  • Reports that RWCU System should have isolated
  • Attempts to close RWCU valves V-16-1, V-16-14, V-16-61 with their control switches CRITICAL TASK 4
  • V-16-14 and V-16-61 Closed
  • Reports valves V-16-14 and V-16-61 did close
  • Reports the valve V-1-6-1 will not close Role Play BOOTH - If directed to investigate for leak around Cleanup
  • Report - Steam is coming out of the cleanup cage SRO
  • Directs investigating cause of RB D/P alarm
  • Directs attaining radiation levels and area temperatures in the Rx Building.
  • Directs isolating RWCU when determined system has developed a leak.
  • Refers to T.S. 3.5 for applicability and determines that V 14 and V-16-2 are closed and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> must be deactivated to met T.S 3.5.

ATC

  • Monitors 4F parameters and ensures 4F critical parameters stay in band
  • Lowers power with recirc if Rx power goes above license limit Role Play BOOTH - If directed to restore RBCCW temps back in band
  • Adjust RBCCW parameters to restore DW parameters back in band using RBCCW simulator PI&D.

NRC 2016 Scenario 2 Page 6 of 26

NRC 2016 Scenario 2 (New)

Terminus: RWCU is isolated and the SRO has addressed Tech Specs Notes/Comments NRC 2016 Scenario 2 Page 7 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 3 Event

Description:

Respond to trip of VMCC 1B2 (TRIGGER 3)

Initiation: When RWCU leak is isolated or as directed by the Lead Examiner Cues: Annunciators G3c, RPS MG SET 2 TRIP; G1c, SCRAM CONTACTOR OPEN; 9XF4a, PROT SYS PNL 2 PWR LOST; 9XF5c, CIP-3 INV AC INP LOST Time Position Applicants Actions or Behavior BOP

  • Recognizes and reports loss of VMCC 1B2
  • Performs ABN-51
  • Confirms CIP-3 INV AC INP LOST (9XF-5-c) alarm received
  • Verifies the Trans Output green Off light is lit on Panel 7R
  • Restores power to PSP-2 by placing the Power Select switch in the TRANS position
  • Resets the following:
  • APRM flow converters (3R, 5R)
  • NOTE: The following are simulated photographs. The candidate can simulate and assume indications are as expected.
  • Resets the INOP status LED on APRM FCTR cards
  • Verifies status LED on FCTR card is GREEN
  • Verifies Curve Select Display is 0

NRC 2016 Scenario 2 (New)

  • Informs the US the following valves inoperable (1F/2F)

IAW Tech Spec 3.7 and 3.5.A.3 (only if B Battery is unavailable - it will begin discharging but will be available for several hours)

  • V-14-31, DC Steam Inlet Valve to A Condenser
  • V-14-34, DC Condensate Return Valve from A Condenser
  • V-16-2, Inlet Isolation Valve to Cleanup Auxiliary Pump
  • V-16-14, Clean-Up Inlet Isolation Valve
  • Informs the US the B Battery is INOPERABLE as soon as it begins discharging
  • Monitors 125 VDC B Bus Voltage
  • Reduces loads as directed by the US utilizing the B Battery Load List
  • Monitors 125 VDC A Bus Voltage
  • Verifies the following alarms are received:
  • Confirms one Fire Diesel Pump is operating in MANUAL mode and the other Fire Diesel Pump in AUTO mode
  • Directs the EO to investigate the loss of VMCC 1B2
  • Notifies the Director of Operations and the WWM
  • Reports ABN-51 is complete Roleplay BOOTH: When directed to investigate loss of VMCC-1B2
  • Report VMCC-1B2 breaker is open and has an acrid order with no smoke and no fire.

FLOOR: When operator verifies LED on FCTR card is green

  • Cue: FCTR card is green FLOOR: When operator verifies Curve select display is 0
  • Cue: Curve Select displays 0 NRC 2016 Scenario 2 Page 9 of 26

NRC 2016 Scenario 2 (New)

SRO

  • Directs entry into ABN-51
  • Notifies SM/WWM about the loss of VMCC 1B2
  • Declares B Battery inoperable as soon as it begins to discharge
  • The reactor shall be PLACED IN the COLD SHUTDOWN CONDITION if the availability of power falls below that required by Specification A above
  • V-14-31, DC Steam Inlet Valve to A Condenser
  • V-14-34, DC Condensate Return Valve from A Condenser
  • V-16-2, Inlet Isolation Valve to Cleanup Auxiliary Pump
  • V-16-14, Clean-Up Inlet Isolation Valve ATC
  • Makes plant announcement of entry into ABN-51
  • Following restoration of RPS-2, resets the following:
  • Main Steam Isolation signal BOOTH: AFTER the ATC resets the 1/2 scram, insert CAEP ATWS for Event 6 Terminus: ABN-51 actions are complete and the SRO has reviewed/applied Tech Specs 3.7.B and 3.5.A.3 Notes/Comments NRC 2016 Scenario 2 Page 10 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 4 Event

Description:

Respond to CRD Flow Control Valve failed closed (TRIGGER 5)

Initiation: RWCU is isolated and T.S determination has been made or as directed by the Lead Examiner.

Cues: Annunciator H5c, CRD HIGH TEMP; DRIVE WATER FLOW, COOLING WATER FLOW, CLG WTR/REACTOR P, & DRIVE WTR/REACTOR P go downscale Time Position Applicants Actions or Behavior ATC

  • Reports abnormal CRD indications.
  • Reports the CRD FCV (NC30A) indicates closed.
  • Directs the EO to investigate the failed CRD FCV [ROLE PLAY 1].
  • Enters ABN-6, Control Rod Malfunctions, section 13, Flow Control Valve NC-30A/B Fails Closed.
  • Places CRD FCV NC30B in service IAW procedure 302.1, section 6.3.3.
  • Places the CRD FLOW CONTROLLER in MAN.
  • Directs the EO to open the standby FCV inlet/outlet valves [ROLE PLAY 2].
  • Directs the EO to place the 4-Way Valve in position to supply both controllers [ROLE PLAY 3].
  • Places the CRD FLOW CONTROL VALVES switch to the B position.
  • Directs the EO to place the 4-Way Valve in position to supply the in-service controller [ROLE PLAY 4].
  • Verifies normal CRD indications.
  • Places the CRD FLOW CONTROLLER in AUTO.
  • Directs the EO to close the failed FCV inlet/outlet valves [ROLE PLAY 5].
  • Reports the standby CRD FCV is in service and indications are normal.

BOP

  • Announces entry into ABN-6, Control Rod Malfunctions, due to CRD FCV NC30A failing closed.

NRC 2016 Scenario 2 Page 11 of 26

NRC 2016 Scenario 2 (New)

  • May check CRD Temperatures on Panel 8R and report there are several control rods with high temperatures.

SRO

  • Directs entry into ABN-6, Control Rod Malfunctions, due to CRD FCV NC30A failing closed.
  • Directs swapping CRD FCVs IAW procedure 302.1, section 6.3.3.
  • Notifies the SM/WWM about the failed CRD FCV.

ROLE 1. When/if asked as the EO to investigate the in-service CRD FCV (NC30A),

PLAY report that it is closed, was leaking air badly, and that you have isolated the air supply to the valve.

2. (Step 6.3.3.1.1.2.b) When/if asked as the EO to open the standby CRD FCV inlet/outlet valves, insert TRIGGER 7 and report the valves OPEN (V-15-18, V-15-19).
3. (Step 6.3.3.1.1.3) When/if asked as the EO to place the 4-Way Valve in position to supply both controllers, state it is in the position to supply both controller (NO booth actions are required).
4. (Step 6.3.3.1.1.5) When/if asked as the EO to place the 4-Way Valve in position to supply the in-service controller state it is in the position to supply NC30B (NO booth actions are required).
5. (Step 6.3.3.1.1.8.a) When/if asked as the EO to close the failed FCV inlet/outlet valves, state the valves are closed (Insert LOA-CRD009 and LOA-CRD010 to 0) (closes V-15-16, V-15-17).

Terminus: CRD FCV NC30B is in service and CRD parameters indicate normal.

Notes/Comments NRC 2016 Scenario 2 Page 12 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 5 Event

Description:

OFF Gas Deflagration/ loss of vacuum (TRIGGER 9)

Initiation: CRD flow controller swapped or as directed by the Lead Examiner (booth Look ahead): Delete malfunction once alarms come in Cues: RAP-10XF3d, 10F1a, 10F2a, RAP10F1b, 10F2b Time Position Applicants Actions or Behavior BOP Performs actions IAW ABN-25

  • Confirms V-267-005 closed
  • Places Off-gas drain valves selector switch to close
  • Sends EO to investigate Off-Gas building per RAP-10XF3d
  • Verifies Off-Gas inlet isolation valves closed
  • Verifies V-7-31 open
  • Determines cause of system isolation
  • Checks for proper system purge
  • Verifies off-gas press and temp alarms clear and resets Off-gas isolation
  • Confirms V-7-1 through 6 open and off-gas line flow is established Performs actions IAW ABN-14
  • Makes update that vacuum is recovering after power reduction
  • Confirms Circ water pumps are operating
  • Confirms SJAEs are operating properly
  • Confirms Gland seal system operating properly
  • Confirms Vacuum breaker is closed
  • Confirms SJAE drain pumps operating properly BOOTH Once OFF-Gas isolation act 1 and 2 along with temp and pressure alarms come in DELETE
  • DMF MAL-OGS003 (Explosion in off gas piping)

Role Play: AS RBEO Report: I am out near the stack and just heard a loud bang. I dont see any visible damage NRC 2016 Scenario 2 Page 13 of 26

NRC 2016 Scenario 2 (New)

Role Play: If asked to investigate Off-Gas:

Report: No visible damage to equipment or building and no sign of fire or smoke.

Once OFF-Gas has been reset INSERT

  • Trigger 11 (MAL-CFW017)

Once crew begins to lower power with Recirc

  • Insert MAL-CFW017 to 0 CREW Makes update that vacuum is degrading after OFF-Gas reset ATC Reduces power with the master recirc flow controller SRO
  • Directs entry into ABN-25
  • Directs entry into ABN-14 Terminus: Rx power has been lowered to stop vacuum reduction Notes/Comments NRC 2016 Scenario 2 Page 14 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 6 Event

Description:

Loss of all Stator Cooling Water requires manual scram (Trigger 13)

Initiation: Rx power has been lowered to stop vacuum reduction or as directed by the Lead Examiner Cues: Annunciator R6c, STATOR CLG TROUBLE; Turbine runback with generator electric lowering and Turbine Bypass Valves opening Time Position Applicants Actions or Behavior BOP

  • Directs EO to investigate the alarm [ROLE PLAY]
  • Directs entry into ABN-11
  • Directs the ATC to manually scram the reactor when the turbine runback is noticed, and to enter ABN-1
  • Manually scrams the reactor by pressing MANUAL SCRAM BUS 1 and BUS 2 pushbuttons and places REACTOR MODE SELECTOR switch in SHUTDOWN
  • Pushes ARI button
  • Bypasses ROPS
  • Reduces Recirc pumps to minimum ROLE When directed as the EO to investigate the stator cooling alarm, report PLAY that no stator cooling water pumps are running Terminus: The reactor has been manually scrammed and the ATWS has been recognized Notes/Comments NRC 2016 Scenario 2 Page 15 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 7/8 Event

Description:

Respond to an ATWS with reactor power > 2%; Bypass valves shut Initiation: inserted a manual scram, and have recognized ATWS conditions or as directed by the Lead Examiner Cues: The reactor has failed to scram and is in an electrical ATWS condition, all rods still out, power >50%

Time Position Applicants Actions or Behavior ATC/

  • Reports reactor power Crew
  • Determines the ATWS is electric
  • Trips all Recirculation Pumps when directed with the DRIVE MOTOR switches to STOP
  • May request to close V-15-52, Charging Header Isolation [ROLE PLAY]

CRITICAL TASK 3

  • Determines electrical ATWS
  • Confirms all available CRD pumps are running
  • Places Reactor Mode Switch in REFUEL
  • Closes CRD DRIVE WATER PRESSURE CONTROL NC18 to maximize CRD drive water differential pressure
  • Drives Cram Array first then normal patern ROLE PLAY: If requested to close V-15-52, INSERT LOA-CRD024 to 0, and report V-15-52 is closed ROLE PLAY: As the EO directed to vent the scram air header, acknowledge the request.

NRC 2016 Scenario 2 Page 16 of 26

NRC 2016 Scenario 2 (New)

NOTE: The crew may de-energize RPS by opening the RPS 100amp breakers when the MSIVs go closed, or after the crew has directed an EO to vent the scram air header, the Lead Examiner may direct the booth to vent the scram air header by inserting Trigger 7.

SRO

  • Confirms ARI initiated
  • Directs ROPS bypassed
  • Directs all Recirculation Pumps tripped
  • May direct initiation of SLC IAW SP-22, Initiating the Liquid Poison System
  • Directs SP-1, Confirmation of Automatic Initiation and Isolations
  • Directs ADS bypassed
  • Directs SP-16, Bypassing MSIV Lo-Lo Level Isolation Interlocks and the RBCCW Interlocks
  • Waits until MSIV isolations are bypassed, then directs terminate and prevent RPV injection IAW SP-17
  • Directs augmenting pressure control with EMRVs when Bypass valves close.
  • Directs RPV water level below -20 to 30 IAW SP-19, Feedwater/Condensate and CRD Operation
  • Directs Torus Cooling IAW Support Procedure 25
  • Directs RPV water level 138 - 175 using SP-2/3(FW)

BOOTH: When Core Spray pumps are in pull to lock during SP-17 fault bypass valves INSERT: TRIGGER 15 BOP/

  • Places ADS TIMERS to BYPASS
  • Obtains four (4) bypass plugs NRC 2016 Scenario 2 Page 17 of 26

NRC 2016 Scenario 2 (New)

  • Opens the EOP BYPASS PLUGS panel in the rear of Panel 6R INSERT a bypass plug in position BP1 INSERT a bypass plug in position BP2
  • Opens the EOP BYPASS PLUGS panel in the rear of Panel 7R INSERT a bypass plug in position BP1 INSERT a bypass plug in position BP2
  • Places the ISOL SIGNAL BYPASS V-6-395 switch in the BYPASS position
  • Informs the Unit Supervisor that the MSIV LO-LO Level Isolation Interlock has been bypassed
  • Verifies that the RBCCW System is not isolated due to high Drywell pressure/low RPV water level conditions
  • Opens the EOP BYPASS PLUGS panel in the rear of Panel 2R Removes the bypass plug from position BP1 Removes the bypass plug from position BP2
  • Performs SP-17 CRITICAL TASK 1
  • Terminates and prevents the Core Spray System injection into the RPV by performing the following:
  • Presses the OVERRIDE switches for all the sensors that are lit
  • Presses all ACTUATED switches, whether lit or unlit
  • Confirms Core Spray Parallel Isolation Valves closed
  • Confirms Core Spray Main Pumps that are not being used to provide makeup water to the torus per SP37 are in the PULL-TO-LOCK position CRITICAL TASK 1
  • Terminates and prevents Condensate and Feedwater injection by performing the following:
  • Confirms only one Condensate Pump running
  • Places all individual FRV Controllers in MAN position
  • Closes the Low Flow Valves NRC 2016 Scenario 2 Page 18 of 26

NRC 2016 Scenario 2 (New)

  • Reports RPV injection has been terminated and prevented
  • Makes update that EMRVs are open
  • Takes manual control of EMRVs to control Rx Pressure
  • Confirms only one Condensate Pump and only one Feedwater Pump operating CRITICAL TASK 2
  • Controls RPV Water level using the following:

Feedwater Regulating Valves Feed Regulating Valve Block Valves Feedwater Low Flow Valves Heater Bank Outlet Isolation Valves Feedwater and Condensate Pumps

  • Reports RPV water level in band
  • May perform SP-25 if directed (Torus cooling)
  • Confirm the SYSTEM MODE SELECT switch is in the TORUS COOLING position
  • Start an ESW Pump
  • Place and hold the System Pump Start Permissive Keylock for the selected pump in the appropriate position
  • Start the selected Containment Spray Pump using its control switch BOOTH After level is being controlled by SP-19 or as directed Vent the SAH INSERT: TRIGGER 17 Terminus: Control rods have been fully inserted from venting the scram air header.

RPV water level is rising towards the prescribed band as directed in the RPV Control - No ATWS EOP.

Final EAL MS-2 Automatic Scram Failure to shutdown the reactor and manual actions Call taken from the Rx control console are not successful in shutting down the reactor.

Notes/Comments NRC 2016 Scenario 2 Page 19 of 26

NRC 2016 Scenario 2 (New)

NRC 2016 Scenario 2 Page 20 of 26

NRC 2016 Scenario 2 (New)

Procedures Used Event Procedure 1

  • 309.2 2
  • ABN-51
  • T.S - 3.7
  • T.S. - 3.5 4
  • 302.1 5
  • ABN-14
  • RAP-10XF3d& 4d
  • RAP-10XF5c
  • ABN-25 6
  • ABN-11
  • EMG-3200.01b 7/8
  • EMG-SP21 NRC 2016 Scenario 2 Page 21 of 26

NRC 2016 Scenario 2 (New)

  • EMG-SP16
  • EMG-SP17
  • EMG-SP22
  • EMG-SP1
  • EMG-SP-19
  • EMG-SP25
  • EMG-3200.01b
  • EMG-SP2
  • EMG-SP3 NRC 2016 Scenario 2 Page 22 of 26

NRC 2016 Scenario 2 (New)

Simulator Setup

1. Reset to IC-40 (bwr-2)
2. Confirm RBCCW pump 1 is running
3. Confirm B CRD pump running
4. Risk is Yellow
5. Tag EDG #2 NORMAL START and EMERG START control switches
6. Protect #1 EDG
7. Protect A CRD pump
8. Protect system 1 Containment Spray
9. Protect system 1 Core spray pumps
10. Tag #3 Air Compressor Event Trigger Malfunction Preset Preset
  • IMF MAL-RCU014 (RWCU fail to auto isolate)
  • IMF VLV-RCU001 to Mech seize (opt 6)

(V-16-01 mech seize)

  • STL-DGN004 to fail off
  • STL-DGN005A to fail off
  • ANN-T-4-f to fail on
  • LOA-DGN012 to "trip"
  • LOA-DGN009 to "stop" (Places EDG#2 OOS)
  • LOA-CAS031 to Rack out (Places #3 Air compresser OOS) 1 NA NA 2 1
  • MAL-RCU013 to 10% over a 30-minute ramp (inserts a 10% RWCU leak in the RB over a 30-minute period) 3 3
  • MAL-EDS004B (causes a fault on VMCC 1B2) 4 5
  • MAL-CRD001A to 0 NRC 2016 Scenario 2 Page 23 of 26

NRC 2016 Scenario 2 (New)

(closes CRD FCV NC30A) 7

  • LOA-CRD012 to 1
  • LOA-CRD011 to 1 (This opens the alternate FCV NC30B inlet/outlet valves)

MAL-OGS003 5 9 (explosion in off-gas piping)

NOTE:

Once off gas alarms come in Delete MAL-OGS003 Once Off-Gas reset insert 11

  • MAL-CFW017,1.5, 120 sec (Vacuum leak in condenser) 6
  • MAL-GEA005A 13
  • MAL-GEA005B (trips A and B Stator water cooing pumps) 7 Set after event Activate after event # 2 (Loss of VMCC
  1. 2 1B2)
  • Insert ATWS.CAE file NOTE: This ATWS.CAE is File Path:

OPENSIM/CAEP/Training/ATWS.CAE Trigger 17

  • LOA-CAS022, 1
  • MAL-TCS006D, close, 5 seconds TD 8
  • MAL-TCS006E, close, 5 seconds TD Trigger 15
  • MAL-TCS006F, close, 5 seconds TD
  • MAL-TCS006G, close, 5 seconds TD
  • MAL-TCS006H, close, 5 seconds TD
  • MAL-TCS006I, close, 5 seconds TD This will close bypass valves 5 seconds after core spray pumps are in NRC 2016 Scenario 2 Page 24 of 26

NRC 2016 Scenario 2 (New) pull to lock is bypassed in SP-17 is complete in Event #7.

NRC 2016 Scenario 2 Page 25 of 26

NRC 2016 Scenario 2 (New)

Shift Turnover Current plant conditions:

  • 100% power
  • EDG #2 Out of service -
  • Diesel Generator #2 has been out of service for 2 days due to failure to start during the load test. It is scheduled to be returned to service the next day. The diesel load test for #1 diesel is due next shift. Fire diesel
  1. 1 is out of service until next shift for quarterly PMs.
  • Air Compressor #3 is OOS for troubleshooting due to failure to start.

Shift Activities

NRC 2016 Scenario 3 (New)

Scenario Outline Facility: Oyster Creek Scenario No.: 3 Op Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

  • 97% power
  • Main Generator voltage control is in Manual
  • Risk is Yellow Turnover:
  • Place the AVR from manual voltage regulation to automatic voltage regulation IAW 336.1, section 8, starting at Step 8.2 Event No. Malf. No. Event Type* Event Description BOP Return the AVR to service.

1 N/A N SRO 336.1 24 KV main generator electric system EMRV Spuriously opens MAL- R 2 NSS025 ALL ABN-40, Stuck open EMRV TS E

T.S 4.5.L MAL- C ATC CRD high temperature alarm 3 CRD01 SRO RAP- H5c, CRD High temp 3_3403 Trip of 1A3 MAL- C BOP, 4 EDS003 ABN-46, Loss of 1A3 TS SRO C

T.S -3.7 MAL- C RBCCW Pump Trip Leads to Reactor Scram 5 RBC001 ALL A ABN-19 RBCCW failure response NRC 2016 Scenario 3 Page 1 of 23

NRC 2016 Scenario 3 (New)

MAL-RBC001 B

MAL- M LOCA in Primary Containment 6 NSS01 ALL EMG-3200.02 Primary Containment Control 7A Containment Spray Fails to Swap to Spray Mode 7 VLV- C BOP, CNS005 SRO EMG-SP29 Initiation of the containment Spray system for Drywell Sprays RUN FLD.CA M RPV level flashing 8 E ALL NOLEV EMG-3200.08A RPV flooding-No ATWS EL.CAE

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC 2016 Scenario 3 Page 2 of 23

NRC 2016 Scenario 3 (New)

Simulator Summary Event Event Summary 1 The BOP will return the AVR to automatic service IAW 336.1. The BOP will place the AVR MODE Switch to the AUTO position and confirm indications voltage regulation is in automatic. (BOP: Normal Evolution) 2 The BOP will respond to a leaking EMRV IAW ABN-40, Stuck Open EMRV. The valve will stop leaking when the control switch is placed in OFF. The ATC will manipulate the Master FW Controller, and the SRO will apply TS 3.4 (R: Reactivity Manipulation, SRO: Tech Specs) 3 The ATC will respond to a control rod high temperature alarm (RAP-H5c). The ATC will apply stall flow IAW 617.4.002 (CRD Exercise and Flow Test/IST Cooling Water Header Check Valve), which will clear the alarm. (ATC: Component Malfunction) 4 The BOP will respond to a loss of USS 1A3 and execute ABN-46, Loss of USS 1A3. The BOP will start Service Water Pump 1-2, restore power to ER-42, and confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are running. The SRO will review and apply Tech Spec 3.7. (BOP: Component Malfunction; SRO: Tech Specs) 5 The in-service RBCCW pump will trip and the crew will enter ABN-19.

The BOP will diagnose a tripped pump and will attempt to the start the standby RBCCW pump. The Standby RBCCW pump will be mechanically seized resulting in a loss of all RBCCW flow. The ATC will manually scram the reactor and secure all running Recirculation Pumps. (All: Component Malfunction) 6/7 The Crew will respond to a primary coolant leak in the Primary Containment. The SRO will direct Drywell Sprays but sprays will not operate. The SRO will direct Emergency Depressurization when it has been determined that Torus pressure cannot be maintained below the Primary System Pressure (PSP) Curve. [Major Event; Component Failure after EOP]

Following emergency depressurization level instrument reference legs 8

will flash resulting in a loss of RPV level indication. The crew will enter RPV Flooding and commence flooding the vessel using the condensate and feedwater system IAW SP 58 and/or Core spray IAW SP 60 to ensure core submergence. [Major Event]

NRC 2016 Scenario 3 Page 3 of 23

NRC 2016 Scenario 3 (New)

Critical Given a failed open EMRV, the crew will need to take action to close the Task 1 EMRV in accordance with ABN-40, Stuck open EMRV.

Critical Given a LOCA in Primary Containment with challenges to RPV level control, Task 3 the crew must implement EOP SP-58, Feed and Condensate System and/or EOP SP-60, Core Spray operation, to restore RPV water level.

Critical Given a LOCA in Primary Containment with Drywell parameters degrading Task 2 beyond the capacity of the Containment Spray system, the crew will perform an Emergency Depressurization of the Reactor.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

1. Malfunctions after EOP entry (1-2) 2 7,8
2. Abnormal events (2-4) 3 2,4,5
3. Major transients (1-2) 2 6,8
4. EOPs entered/requiring substantive 2 RPV Control actions (1-2) No-ATWS Primary Containment
5. EOP contingencies requiring substantive 2 ED-No ATWS actions (0-2) RPV Flooding-No ATWS
6. EOP Critical tasks (2-3) 2 6/7,8 NRC 2016 Scenario 3 Page 4 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 1 Event

Description:

Return the AVR to service IAW 336.1.

Initiation: Following shift turnover Cues: As directed by the SRO following shift turnover Time Position Applicants Actions or Behavior SRO

  • Directs the BOP to shift from manual to automatic voltage regulation IAW 336.1, section 8, starting at Step 8.2 BOP
  • Shifts from manual to automatic voltage regulation IAW 336.1, section 8, step 8.2.
  • Verifies the EX2100e TRANSFER VOLTMETER (8F/9F) is reading Zero (+/- 1%)
  • Places the AVR MODE Switch (AVR\97CS Panel 8F/9F) to the AUTO position and allow switch to return to center. (Panel 8F/9F)
  • Confirms the AUTO light illuminated above AVR MODE Switch. (AVR\97CS Panel 8F/9F)
  • Confirms the PSS Status is Enabled locally at the HMI ROLE PLAY: As the EO at the HMI, report that the PSS is active (336.1 step 8.5)

BOP

  • Removes VOLTAGE CONTROL IN MANUAL operator aids installed per Section 7.0.
  • May verify Terminal Voltage or Excitation are within the requirements of 336.1, section 5.0, on the PJM website. [FLOOR ROLE PLAY]
  • May notify the Power team when in auto FLOOR If the applicant requests (or attempts to verify on the PJM website) that ROLE Terminal Voltage or MG Excitation (VARS) are within the limits of section 5.0, PLAY: inform them that the requirements of section 5.0 are satisfactory.

Terminus: The AVR is in automatic voltage control Notes/Comments NRC 2016 Scenario 3 Page 5 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 2 Event

Description:

Leaking EMRV NR108A [TRIGGER 17]

Initiation: AVR is in Auto or as directed by the Lead Examiner Cues: Annunciator B4g, SV/EMRV NOT CLOSED; EMRV NR108A indicates in the VALVE OPEN REGION; Elevated EMRV tailpipe temperatures Time Position Applicants Actions or Behavior BOP

  • Performs ABN-40 actions
  • Checks the following:
  • Acoustic monitoring indications
  • EMRV Tailpipe temperatures [ROLE PLAY]
  • Determines that EMRV NR108A is leaking Role If asked as the EO to check EMRV tailpipe temperatures locally on RB 23, Play: report that EMRV NR108A tailpipe temperature is about 300oF. EMRV NR108B & E are about 180 oF and NR108C and D are 125 oF BOP o Places EMRV NR108A AUTO DEPRESS switch to OFF o Reports EMRV not closed o Cycles EMRV NR108A AUTO DEPRESS switch between OFF to MAN to OFF [Booth Action]

CRITICAL TASK 1 o Reports EMRV indicates closed o Resets the MASTER ALARM to silence the alarm o Plots EMRV Dowmcomer temperature IAW the ABN attachment o Refers the SRO to Tech Specs 4.5.F.5 and 4.5.L for surveillance requirements Booth When the BOP cycles the EMRV NR108A switch to OFF, DELETE the Action EMRV leak MAL-NSS025A If operators place EMRV NR108A back to auto re-initiate leaking EMRV NR 108A SRO

  • Directs entry into ABN-40, Stuck Open EMRV

NRC 2016 Scenario 3 (New)

  • 3.4.B.1: Five electromatic relief valves, which provide the automatic depressurization and pressure relief functions, shall be operable when the reactor water temperature is greater than 212°F and pressurized above 110 psig, except as specified in 3.4.B.2 and during Reactor Vessel Pressure Testing consistent with Specifications 1.39 and 3.3.A.(i).
  • 3.4.B.2: If at any time there are only four operable electromatic relief valves, the reactor may remain in operation for a period not to exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are verified daily to be operable.
  • 4.5.F.5: Once every 3 months and following any release of energy which would tend to increase pressure to the suppression chamber, each OPERABLE suppression chamber - drywell vacuum breaker shall be exercised.

Operation of position switches, indicators and alarms shall be verified every 3 months by operation of each OPERABLE vacuum breaker.

  • 4.5.L.3: Whenever heat from relief valve operation is being added to the suppression pool, the pool temperature shall be continually monitored and also observed until the heat addition is terminated.
  • Notifies SM/WWM about the EMRV failure and of the required LCO ATC
  • Performs ABN-40 actions
  • Reduces Recirc flow control 2 Hz
  • Places the MASTER FEEDWATER CONTROLLER in MAN by pressing the AUTO/MAN button, and controls RPV water level 155 to 165 with the manual knob
  • Places the MASTER FEEDWATER CONTROLLER in AUTO
  • Selects the P display on the MASTER FEEDWATER CONTROLLER using the CHNG DISP button
  • Selects the S display on the MASTER FEEDWATER CONTROLLER using the CHNG DISP button
  • Raises or lowers the S Display to match the P Display NRC 2016 Scenario 3 Page 7 of 23

NRC 2016 Scenario 3 (New)

  • When S and P are matched, Places the MASTER FEEDWATER CONTROLLER in AUTO by pressing the AUTO/MAN button
  • Verifies the green AUTO light is on
  • Adjusts the auto setpoint to 160, or as directed by the SRO
  • Reports Feedwater Level Control is in auto Monitors RPV water level and feedwater flow Terminus: The EMRV is closed and the SRO has reviewed/applied the Tech Specs Notes/Comments NRC 2016 Scenario 3 Page 8 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 3 Event

Description:

CRD high temperature alarm [TRIGGER 19]

Initiation: EMRV is closed or as directed by the Lead Examiner.

Cues: Annunciator H5c, CRD TEMP HI Time Position Applicants Actions or Behavior ATC

  • Confirms cooling water differential pressure and flow within limits in accordance with Procedure 302.1
  • Directs EO to check for a leaking scram discharge valve on HCU 34-03 [ROLE PLAY]

ROLE PLAY: As the EO directed to check for a leaking scram discharge valve on HCU 34-03, report that there are no indications of a leaking scram discharge valve on HCU 34-03.

ATC

  • Attempt to clear alarm by performing the following:

Applies stall flow signal to the affected CRD IAW Procedure 302.2 section 11[FLOOR]

FLOOR: Provide copy of 302.2 section 11 to the applicants.

ATC

  • Turns Rod power on
  • Holds NOTCH OVERRIDE Switch in NOTCH OVERRIDE position
  • Holds ROD CONTROL Switch to ROD OUT NOTCH position
  • Releases ROD CONTROL Switch and NOTCH OVERRIDE Switch [BOOTH]
  • Turns off ROD POWER switch BOOTH: When the candidate applies stall flow the first time, then DELETE MAL-CRD013_3403. This will restore cooling water to the control rod and the high temperature alarm will clear shortly.

ATC

  • Determines which CRD is bringing in the high temperature alarm at Panel 8R

NRC 2016 Scenario 3 (New)

  • Verifies CRD temp hi condition has cleared on 8R recorder TR-RD0046
  • Resets recorder by pressing the alarm acknowledge button on 8R recorder TR-RD0046. This will clear annunciator H5c on Panel 5F/6F.

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 4 Event

Description:

Loss of 480 VAC Bus USS 1A3 [TRIGGER 21]

Initiation: CRD hi temp clear or as directed by the Lead Examiner.

Cues: Annunciators S8f, FDR TO 460V 1A3 TRIP, and U5a, 1A3 MN BRKR TRIP Time Position Applicants Actions or Behavior BOP Per RAPs S-8-f, FDR TO 460V 1A3 TRIP, and U-5-a, 1A3 MN BRKR TRIP (NOTE: Applicant may directly enter and execute ABN-46 instead of RAP).

  • Checks Breaker position and Bus amps
  • Has EO check at the local breaker cubicle for relay targets
  • Verifies trip of 4160V Breaker 1A3P
  • Refers to ABN-46
  • Checks Bus loads have shed
  • Determines cause of Breaker trip [BOOTH]
  • Has Intake operator confirm control power switch inside panel ER-42 in position 2 and restores power to ER-42 BOOTH: When requested to investigate cause of USS 1A3 trip, report that the 1A3P breaker tripped on overload BOOTH: Roleplay: Roleplay when directed to to swap ER-42 and restore power to ER-42 insert TRIGGER 7 and report.

BOP

  • Makes update that lost USS-1A3
  • Per ABN-46, LOSS OF USS 1A3:

IMMEDIATE OPERATOR ACTIONS

  • Has an EO restore power to Panel ER-42 [BOOTH]
  • Has an EO confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are running [BOOTH]

ROLE BOOTH: NOTE: Screen Wash Control Panel and Low Pressure Screen Wash pumps are not modeled. When requested to confirm HP Screen Wash PLAY Pump 1-2 and LP Screen Wash Pump 1-4 are running, report they are both running. May request EO to check intake dp.

NRC 2016 Scenario 3 Page 11 of 23

NRC 2016 Scenario 3 (New)

  • Monitors North intake DP, Circ Water pump amps and main condenser vacuum
  • Notifies Security of the loss of security lighting at the intake
  • Requests Work Week Manager to mobilize Electrical Maintenance for troubleshooting and repair
  • Reviews Attachment 1 Load list on USS 1A3, MCC 1A31 and lighting panel 1A31 for any additional loads lost.
  • Informs US to refer to T.S. 3.7 ATC
  • May assist in communications associated with execution of RAPs and ABN-46 SRO
  • Directs entry into ABN-46, Loss of USS 1A3
  • Determines that USS 1A3 is inoperable per Tech Spec 3.7 and determines that the plant must be placed in the cold shutdown condition Terminus: ABN-46 has been performed and the SRO has addressed Tech Specs.

Notes/Comments NRC 2016 Scenario 3 Page 12 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 5 Event

Description:

The in-service RBCCW pump trips [TRIGGER 9]

Initiation: ABN-46 actions complete or as directed by the Lead Examiner Cues: Annunciators C3c, RBCCW PUMP 1-1 TRIP; E7d, E7f, F7b, CCW FLOW LO for all Recirculation Pumps; RBCCW PUMP 1-1 indicates tripped Time Position Applicants Actions or Behavior BOP

  • Checks RBCCW HX OUTLET PRESS and RBCCW PUMP 1-1 indications and recognizes RBCCW Pump 1-1 has tripped
  • Enters and performs immediate actions of ABN-19.
  • Starts RBCCW Pump 1-2 by placing its control switch to START (must be started within 1 minute)
  • Reports RBCCW Pump 1-1 tripped and RBCCW Pump 1-2 did not start SRO
  • Directs entry into ABN-19
  • Recognizes a loss of all RBCCW flow has occurred and enters ABN-19
  • Directs tripping all Recirculation Pumps
  • Directs entry into RPV Control - No ATWS
  • Directs the Crew to maintain RPV water level 138 - 175 (or 138 - 160) using SP2 (Cond/FW) and/or SP3 (CRD)
  • If an RPV isolation did not occur, directs the Crew to maintain RPV pressure (approximately) 800 - 1000 psig using the Turbine Bypass Valves
  • If an RPV isolation occurred (due to reaching RPV Lo-Lo Level post scram), directs the Crew to maintain RPV pressure (approximately) 800 - 1000 psig using the Isolation Condensers (SP-11) and/or EMRVs (SP-12)
  • Directs SP-1 (Confirmation of Automatic Initiations and Isolations)

NRC 2016 Scenario 3 Page 13 of 23

NRC 2016 Scenario 3 (New)

ATC

  • Places the Reactor Mode Selector switch in SHUTDOWN
  • Reports immediate scram actions complete
  • Trips all operating Recirculation Pumps IAW ABN-19
  • Trips Recirculation Pump A for use with IC-A (or Recirculation Pump E for use with IC-B)
  • Verifies RPV water level < 160
  • Cycles Condensate Return Valve V 34 as necessary to maintain RPV Pressure with IC-A (or V-14-35 for IC-B)
  • Verifies Torus water level is > 90
  • Places one or more EMRV control switch in the MAN position, then back to AUTO BOP
  • Controls RPV water level as directed following the scram o Reports entry into RPV Control - No ATWS on low RPV water level o When RPV level begins to rise following the scram, then performs the following:

o Places all MFRVs in MANUAL, if in AUTO o Closes all MFRVs, if OPEN o Directs the EO to close CRD Supply Water Valve to Charging Water Header valve V-15-52 [ROLE PLAY]

NRC 2016 Scenario 3 Page 14 of 23

NRC 2016 Scenario 3 (New)

Roleplay As the EO directed to close CRD Supply Water Valve to Charging Water Header valve V-15-52, insert Trigger 15. Report when complete.

o Enters SP-2 (Cond/FW) when directed o Controls RPV water level using the following as necessary:

o Feedwater Regulating valves o Main Feed Regulating Valve (MFRV) Block valves o Feedwater Low Flow valves o Heater Bank Outlet Isolation valves o Feedwater and Condensate pumps

  • Performs SP-1 as directed
  • Makes plant announcement for reactor scram due to loss of all RBCCW flow Terminus: The reactor is scrammed, all Recirculation Pumps are tripped, and RPV water level and pressure are under control Notes/Comments NRC 2016 Scenario 3 Page 15 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 6/7 Event

Description:

Leak in Primary Containment

[TRIGGER 11, Nolevel.CAE, Run FLD.CAE]

Initiation: level is recovering or as directed by the Lead Examiner Cues: Drywell pressure and Temperature parameters are rising.

Time Position Applicants Actions or Behavior RO

  • Reports Drywell temperature and pressure are rising
  • Reports Drywell pressure > 3 psig - EOP entry
  • Confirms all Drywell Recirc Fans tripped
  • When directed, initiates Drywell Sprays Places the SYSTEM MODE SELECT switch for the selected system in the DW SPRAY position Verifies the Torus CLG Discharge valve closes
  • Verifies the DW Spray Discharge valve opens
  • Reports the DW Spray Discharge for System 2 (V-21-5) will not open and thus no Drywell Sprays are available
  • Directs EO to open DW Spray Discharge for System 2 (V-21-5) [Role Play]

Role As the directed as the EO to open DW Spray Discharge for System 2 (V Play: 5), report that the valve is stuck closed and you cannot open it.

RO

  • Reports when PSP is being approached
  • Reports when 281 °F Drywell bulk temperature is being approached CRITICAL
  • Opens all EMRVs by placing the AUTO DEPRESS VALVE TASK 2 switches to MAN

NRC 2016 Scenario 3 (New)

SRO

  • Directs SP-1, Confirmation of Automatic Initiations and Isolations
  • Directs line-up of Drywell Sprays IAW SP-29
  • Directs initiation of Drywell Sprays when either:

Drywell or Torus pressure exceeds 12 psig When Primary Containment conditions are within the Containment Spray Initiation Limit (CSIL) Curve

  • When determined that Torus pressure cannot be maintained <

PSP, or when bulk Drywell temperature cannot be restored and maintained < 281 °F, directs entry into Emergency Depressurization - With AWS EOP

  • Directs RO to Bypass ROPS
  • Verifies Torus water level > 90

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 8 Event

Description:

RPV Level instruments fail Initiation: Reactor Scrammed or as directed by the Lead Examiner Cues: RPV level instruments indicating high out of sight Time Position Applicants Actions or Behavior Crew

  • Determines that all level indications have flashed and cannot determine water level.

SRO

  • Based on RPV Control No ATWS Override level cannot be determined entry into RPV Flooding is required and directs the following operator actions:
  • Confirms all EMRVs are open, Confirms that the MSIVs are closed and Closes isolation condenser isolation valves.

RO Per SP-58, increases injection into the RPV with condensate/feedwater:

  • Confirms that the condensate and feedwater pumps are running.
  • Confirms the heater string outlets and FRV block valves are open.

CRITICAL

TASK 3

  • Monitors hotwell levels. Maximizes hotwell level make up.

And/OR Per SP-60, increases injection into the RPV with Core Spray

  • Overrides actuating signals
  • Confirms 1 Main pump running and 1 booster pump running in system started
  • Opens Parallel Valves as required to flood RPV Terminus: When RPV Flooding is established.

Final EAL FS-1 due to a loss of Reactor Coolant System barrier and a potential loss of Fuel call Clad barrier Notes/Comments NRC 2016 Scenario 3 Page 18 of 23

NRC 2016 Scenario 3 (New)

Procedures Used Event Procedure 1

  • Copy of 336.1 handed out 2
  • ABN-40
  • 617.4.002 (Handout) 4
  • ABN-46
  • T.S 3.7 5
  • ABN-19
  • EMG-3200.01A
  • EMG-SP29
  • EMG-3200.02
  • EMG-SP2
  • EMG-SP3
  • EMG-SP11
  • EMG-SP12 7
  • EMG-SP29
  • EMG-3200.02
  • EMG-3200 8
  • EMG-SP-58 NRC 2016 Scenario 3 Page 19 of 23

NRC 2016 Scenario 3 (New)

  • EMG-SP-60
  • EMG-3200.08A NRC 2016 Scenario 3 Page 20 of 23

NRC 2016 Scenario 3 (New)

Simulator Setup

1. Reset to IC-40 (bwr2)
2. Lower reactor power to 97% with recirc flow
3. Place the AVR in manual voltage control IAW 336.1, section 7
4. Confirm Transfer meter is at 0
5. Have copy of 336.1 (complete procedure) for applicants; mark step 8.1.1 and 8.1.2 complete
6. Have copy of 202.2 section 11 for applicants
7. Ensure Service Water Pump 1-1 is running and Service Water Pump 1-2 is secured
8. Hang tags on containment spray/ESW 1 pumps
9. Protect containment spray/ESW 2 system
10. Protect EDG #2
11. Risk is Yellow Event Trigger Malfunction VLV-CNS005, Mech Seize Preset Preset (Containment Spray mechanical seizure)

Containment Spray System 1 Tag Out LOA-CNS054, rack out LOA-CNS051, rack out VLV-CNS002, close BKR-CNS007, fail control fuse BKR-CNS005, fail control fuse 1 NA NA 2 17 MAL-NSS025A to 25%

(This inserts a 25% leak through EMRV NR108A) 3 19 MAL-CRD013_3403 (This will plug the cooling water to control rod 34-03 and result in a high temperature)

(This malfunction will be deleted within the scenario) 4 21 MAL-EDS003C (This will insert a loss of USS 1A3)

NRC 2016 Scenario 3 Page 21 of 23

NRC 2016 Scenario 3 (New) 7 LOA-CWS049 to B31 This will restore power to ER-42 5 9 MAL-RBC001A (Trips RBCCW Pump 1-1)

MAL-RBC001B (Trips RBCCW Pump 1-2) 15 LOA-CRD024 to 0 (This closes CRD Supply Water Valve to Charging Water Header valve V 52)

MAL-NSS017a, 6%, 300 seconds 6 11 (Steam leak inside drywell) file: NOLEVEL.CAE file: RUN FLD.CAE (RPV level flashing)

VLV-CNS005, Mech Seize 7 Preset in Initial (Containment Spray mechanical seizure) conditions file: NOLEVEL.CAE 8 Set in event 6 file: RUN FLD.CAE (RPV level flashing)

NRC 2016 Scenario 3 Page 22 of 23

NRC 2016 Scenario 3 (New)

Shift Turnover Current plant conditions:

  • 97% power
  • Main Generator voltage control is in Manual
  • Risk is Yellow Shift Activities
  • Place the AVR from manual voltage regulation to automatic voltage regulation IAW 336.1, section 8, starting at Step 8.2 NRC 2016 Scenario 3 Page 23 of 23

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: COOO00044 Task

Title:

Week 4 Safety Related Equipment Verification Job Performance Measure No.: NRC Admin JPM1 (RO)

K/A

Reference:

G2.1.29 (4.1)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. The plant is at rated power Task Standard:

Three instances of improper EOP Jumper Bypass Plug placement have been identified. The Acceptance Criteria is declared UNSAT (not met)

Required Materials: None.

General

References:

1. 680.4.007, Safety Related Equipment Verification, Revision 14 Initiating Cue:

Complete Section 6.4, Week Four Verification, IAW 680.4.007, Safety Related Equipment Verification, starting at Step 6.4.3.

Time Critical Task: No.

Validation Time: 10 Minutes ILT 14-1 NRC RO ADMIN JPM1 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provide repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Verify Prerequisites and reviews Precautions and Limitations.

Standard: Verifies Prerequisites and reviews Precautions and Limitations.

Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 6.4.3.1 Verify that the bypass plugs are positioned as follows:

1. EOP Bypass Plug Panel in rear of Panel 2R
  • Bypass plug in position BP1
  • Bypass plug in position BP2
  • No other plugs inserted Standard: Verifies that the bypass plugs are positioned as follows:
1. EOP Bypass Plug Panel in rear of Panel 2R
  • Bypass plug in position BP1
  • Bypass plug in position BP2
  • No other plugs inserted Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 6.4.3.2 Verify that the bypass plugs are positioned as follows:

2. EOP Bypass Plug Panel in rear of Panel 3F
  • BP2, BP4, BP6, BP8, BP10, BP12, BP14
  • No other plugs inserted Standard: Verifies that the bypass plugs are positioned as follows:
2. EOP Bypass Plug Panel in rear of Panel 3F
  • BP2, BP4, BP6, BP8, BP10, BP12, BP14
  • No other plugs inserted
  • Reports that no plug is located in BP14 Cue: Acknowledge the report and tell the Candidate to continue (Leave the plugs in their current positions)

Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 6.4.3.3 Verify that the bypass plugs are positioned as follows

3. EOP Bypass Plug Panel in rear of Panel 6R
  • No plugs inserted Standard: Verifies that the bypass plugs are positioned as follows
3. EOP Bypass Plug Panel in rear of Panel 6R
  • No plugs inserted Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 6.4.3.4 Verify that the bypass plugs are positioned as follows

4. EOP Bypass Plug Panel in rear of Panel 7R
  • No plugs inserted Standard: Verifies that the bypass plugs are positioned as follows
4. EOP Bypass Plug Panel in rear of Panel 7R
  • No plugs inserted Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 6.4.3.5 Verify that the bypass plugs are positioned as follows

5. EOP Bypass Plug Panel in rear of Panel 11R
  • Bypass plug in position BP4
  • No other plugs installed Standard: Verifies that the bypass plugs are positioned as follows
5. EOP Bypass Plug Panel in rear of Panel 11R
  • Bypass plug in position BP4
  • No other plugs installed
  • Reports that plug is installed in BP2 instead of BP4 Cue: Acknowledge the report and tell the Candidate to continue (Leave the plugs in their current positions)

Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 8 Procedure Step: 6.4.3.6 Verify that the bypass plugs are positioned as follows

6. EOP Bypass Plug Panel inside of Panel 10XF
  • Bypass plug in position BP2
  • Bypass plug in position BP4
  • No other plugs installed Standard: Verify that the bypass plugs are positioned as follows
6. EOP Bypass Plug Panel inside of Panel 10XF
  • Bypass plug in position BP2
  • Bypass plug in position BP4
  • No other plugs installed
  • Reports that plug is installed in BP3 Cue: Acknowledge the report and tell the Candidate to continue (Leave the plugs in their current positions)

Comment:

SAT/UNSAT ILT 14-1 NRC RO ADMIN JPM1 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Compare results of this surveillance with Section 7.0, Acceptance Criteria.

Record comments/discrepancies.

Standard: Reviews Acceptance Criteria and determines the Acceptance Criteria 7.1.3 is Unsat (has not been met)

Note: For failure of the acceptance criteria, the procedure then directs that the requirements of LS-OC-125 be followed. That procedure has been superseded by LA-AA-125, Corrective Action program, which would require generation of an IR or AR (incident report). The Candidate may state generation of an IR is required. (Not required for critical step.) Writing comments in Step 6.4.4 is not required.

Comment:

SAT/UNSAT Terminating Cue: Three instances of improper EOP Jumper Bypass Plug placement have been identified. The Acceptance Criteria is declared UNSAT (not met)

JPM Stop Time: ___________

ILT 14-1 NRC RO ADMIN JPM1 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Admin JPM 1 (RO)

Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC RO ADMIN JPM1 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup

1. This JPM can be performed at any power level
2. Remove EOP Bypass Plug in rear Panel 3F at position BP14
3. Remove EOP Bypass Plug in rear Panel 11R from position BP4 and place in BP2
4. Place an additional EOP Bypass Plug in Panel inside Panel 10XF in position BP3
5. Place keep procedure 680.4.007 steps 6.4, 6.4.1, 6.4.2 ILT 14-1 NRC RO ADMIN JPM1 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power Task Cue:

Complete Section 6.4, Week Four Verification, IAW 680.4.007, Safety Related Equipment Verification, starting at Step 6.4.3.

ILT 14-1 NRC RO ADMIN JPM1 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2220201512 Task

Title:

Calculate Primary Containment Identified leak Rate IAW 351.2 Job Performance Measure No.: NRC RO Admin JPM 2 K/A

Reference:

G2.1.20 (4.6)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power
  • This identified leak rate calculation is for 1200 - 1600 today
  • The most previous identified leak rate was 19.5 GPM
  • The switches for the DWEDT Pumps were placed in OFF at 12:33:12 (HH:MM:SS)
  • The DRYWELL EQUIP DRAIN TANK HIGH LEVEL alarm annunciated at 12:47:22 (HH:MM:SS)

Initiating Cue:

With the information provided, calculate the Primary Containment identified leak rate IAW 351.2, High Purity Waste System. Determine if any Technical Specification limits have been exceeded.

Required Materials: Calculator General

References:

1. 351.2, High Purity Waste System, revision 84
2. Tech Spec 3.3.D.5 ILT 14-1 NRC RO Admin JPM 2 Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Task Standard:

Determines the current identified leak rate and determines that it does exceed a Technical Specification limit.

Time Critical Task: NO Validation Time: 8 Minutes ILT 14-1 NRC RO Admin JPM 2 Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: attachment 351.2-6 steps 1,2,3 Calculates elapsed time Standard: Calculates elapsed time:

  • 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />
  • 14 minutes
  • 10 seconds = 0.167 minutes
  • Total Minutes: 14.167 minutes Comment:

SAT/UNSAT ILT 14-1 NRC RO Admin JPM 2 Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: attachment 351.2-6 step 4 Calculate identified leak rate Standard: Calculates identified leak rate as:

  • (295 gallons)/(14.167 minutes) = 20.8 gpm Comment:

SAT/UNSAT Performance Step: 4 Determines Tech Spec applicability Standard: Determines that a Tech Spec limit has been exceeded.

Note: Tech Spec 3.3.D.1.b is exceeded:

25 gpm total (identified and unidentified Tech Spec limit)

(20.8 gpm identified + 4.5 gpm unidentified = 25.3 gpm actual)

Comment:

SAT/UNSAT Terminating Cue: Determines the current identified leak rate and determines that it does exceed a Technical Specification limit.

JPM Stop Time: ___________

ILT 14-1 NRC RO Admin JPM 2 Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC RO Admin JPM 2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC RO Admin JPM 2 Page 5 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Provide a copy of procedure 351.2 attachment 6 and Tech Spec 3.3.D to the applicant.

ILT 14-1 NRC RO Admin JPM 2 Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power
  • This identified leak rate calculation is for 1200 - 1600 today
  • The most previous identified leak rate was 19.5 GPM
  • The switches for the DWEDT Pumps were placed in OFF at 12:33:12 (HH:MM:SS)
  • The DRYWELL EQUIP DRAIN TANK HIGH LEVEL alarm annunciated at 12:47:22 (HH:MM:SS)

Task Cue:

With the information provided, calculate the Primary Containment identified leak rate IAW 351.2, High Purity Waste System (attached).

Determine if any Technical Specification limits have been exceeded.

Primary Containment identified leak rate: _________________

Tech Specs limit exceeded (Yes/No): _________________

Name: _________________

ILT 14-1 NRC RO Admin JPM 2 Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: EQC02022 Task

Title:

RPS Manual Scram Electrical Print Reading Job Performance Measure No.: NRC Admin JPM 3 (RO/SRO)

K/A

Reference:

2.2.41, RO 3.5/SRO 3.9 Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. None.
2. Ask the operator for any questions.

Task Standard:

Relays and contacts affected by depressing RPS 1 manual scram pushbutton are identified on station electrical drawings and operation is explained. For SRO candidates, additionally identify the surveillance requirements for testing the RPS 1 manual scram pushbutton and the Technical Specification impact if the pushbutton becomes inoperable.

Required Materials: None General

References:

1. DWG. NO. GE 237E566 SHEETS - 2,3,& 10 Initiating Cue:

Using station electrical prints, explain how depressing the RPS 1 manual scram pushbutton results in an RPS channel 1 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action.

Time Critical Task: NO Validation Time: 8 Minutes ILT 14-1 NRC RO/SRO Admin JPM3 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtains a copy of the reference print and reviews/utilizes the correct sheets Standard: Obtained current revision of DWG. NO. GE 237E566 SHEETS - 2,3,& 10 Comment:

SAT/UNSAT ILT 14-1 NRC RO/SRO Admin JPM3 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Using GE 237E566 SHEETS - 2,3,& 10, locates RPS 1 manual scram pushbutton Note: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet Standard: Locates RPS 1 manual scram pushbutton (1S2) on sheet 2 coordinate E-5 Comment:

SAT/UNSAT Performance Step: 4 Using GE 237E566 SHEETS - 2,3,& 10, identifies relay 1K21A Standard: Locates relay 1K21A on GE 237E566 on sheet 2 coordinate D-5 Note: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet Comment:

SAT/UNSAT ILT 14-1 NRC RO/SRO Admin JPM3 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Using GE 237E566 SHEET 3, identifies contacts 1K21A Note: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.

Note:

The candidate may also identify additional contacts and relays affected by pressing the 1S2 manual scram pushbutton. This is satisfactory but not required, as the task did not require discussion of the backup scram or any other functions.

Using GE 237E566 SHEET 3, identifies contacts 1K21A at coordinate Standard:

H-5, H-4, and H-3 Comment:

SAT/UNSAT Performance Step: 6 Using GE 237E566 SHEETS 3, identifies relays/solenoids 305-117 and/or 118.

Using GE 237E566 SHEETS 3, identifies relays/solenoids 305-117 Standard:

and/or 118 at coordinates B-8 Notes:

  • This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.
  • The candidate does not have to identify all solenoids/relays on this sheet, as long as a representative sample is identified and some indication is given that there are multiple solenoids/relays.

Comment:

SAT/UNSAT ILT 14-1 NRC RO/SRO Admin JPM3 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Describes how depressing the RPS 1 manual scram pushbutton on E console results in an RPS half scram Standard:

Describes the following:

  • Depressing RPS 1 manual scram pushbutton causes relay 1K21A to de-energize.
  • Relay 1K21A de-energizing causes contacts 1K21A to open.
  • Contacts 1K21A opening causes solenoid/relay 305-117 and/or 118 to de-energize at each HCU.

Notes:

  • Solenoid/relay 305-117 and 305-118 do not need to be specifically mentioned, as long as a representative sample is identified and some indication is given that there are multiple 305 solenoids/relays.
  • The candidate does not have to match this description word-for-word, but must include all concepts in their description.

Comment:

SAT/UNSAT RO Terminating Cue: Relays and contacts affected by depressing RPS 1 manual scram pushbutton are identified on station electrical drawings and operation is explained.

RO JPM Stop Time: ___________

ILT 14-1 NRC RO/SRO Admin JPM3 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Additional SRO Only Cue:

Provide SRO candidates the additional SRO only cue sheet and direct them to determine:

  • The surveillance requirement for testing the RPS 1 manual scram pushbutton and

Performance Step: 8 SRO Only: Determines the surveillance requirement for testing the RPS 1 manual scram pushbutton.

Determines the surveillance requirement for testing the RPS 1 Standard:

manual scram pushbutton is 1/3 month Comment:

SAT/UNSAT Performance Step: 9 SRO Only: Determines the Technical Specification impact if the RPS 1 manual scram pushbutton becomes inoperable.

Determines Technical Specification 3.1 is not met.

Standard:

Determines Technical Specification 3.1 requires control rods to be inserted OR Determines Technical Specification 3.1 requires placing the RPS 1 system in a tripped condition.

Comment:

SAT/UNSAT SRO Terminating Cue: Surveillance requirement and Technical Specification impact have been determined.

SRO JPM Stop Time: ___________

ILT 14-1 NRC RO/SRO Admin JPM3 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC RO/SRO Admin JPM 3 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC RO/SRO Admin JPM3 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup Have the following references available:

1. GE 237E566 SHEETS - 2,3,& 10 Have SRO ONLY references available:
1. SFCP ref. 5
2. T.S. 3.1 ILT 14-1 NRC RO/SRO Admin JPM3 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • None Task Cue:

Using station electrical prints, explain how depressing the RPS 1 manual scram pushbutton results in an RPS channel 1 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action.

ILT 14-1 NRC RO/SRO Admin JPM3 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SRO ADDITIONAL STUDENT HANDOUT Determine the following:

  • The surveillance requirement for testing the RPS 1 manual scram pushbutton and

ILT 14-1 NRC RO/SRO Admin JPM3 Page 10 of 10

RO Admin JPM 4 is not included here due to being Security Related.

A separate, non-publicly available file is in ADAMS

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 3410102411 Task

Title:

Review a Completed Pre-Critical Checkoff IAW Procedure 201 Job Performance Measure No.: NRC Admin JPM 1 (SRO)

K/A

Reference:

G2.1.23 (4.4)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

The plant has just completed all major activities during a refuel outage Preparations are being made for a plant startup The REACTOR MODE SELECTOR switch is in REFUEL Attachment 201-2, Pre-Critical Checkoff has been completed and is awaiting review Task Standard:

The plant is deemed NOT ready for an uninterrupted startup to rated power. The correct reasons and required actions are stated.

Required Materials: None General

References:

1. Procedure 201, Plant Startup, Revision 101
2. Technical Specifications ILT 14-1 NRC SRO Admin JPM1 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue:

Perform uncompleted items in Step 78 of the Pre-Critical Checkoff for Attachment 201-2.

From this review, determine if the plant is ready for an uninterrupted startup to rated power.

If the plant is NOT ready, state why and what actions are required to be ready.

Time Critical Task: NO Validation Time: 30 Minutes ILT 14-1 NRC SRO Admin JPM1 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Note: The following steps can be performed in any order.

Performance Step: 2 Determines the plant is not ready for an uninterrupted startup to rated power for the following reasons:

Step 12.4.1 shows only 1 operable SRM (SRM 21)

SRM 22 reads 1 SRM 23 reads 2 SRM 24 is bypassed TS 3.1.1.K requires a minimum of 2 operable SRMs to support the rodblock function.

Any inoperable SRM must be made operable to withdraw control rods.

Standard: Recognizes the Technical Specification applicability due to the inoperability of three (3) SRMs. Two (2) SRMs must be operable to withdraw control rods.

Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM1 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Determines the plant is not ready for an uninterrupted startup to rated power for the following reasons:

Step 45.1 shows that MCC 1A24 is not operable.

Technical Specification 3.7 states that the reactor shall not be made critical unless all of the following requirements are satisfied:

The listed buses or panel listed in the TS are energized, and this includes MCC 1A24.

Standard: Recognizes the Technical Specification applicability due to the inoperability of MCC 1A24. MCC 1A24 must be made operable prior to going critical.

Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM1 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Determines the plant is not ready for an uninterrupted startup to rated power for the following reasons:

Step 73.1 shows that conductivity and chlorides are above the allowable limits.

TS 3.3.E.1 provides the following:

3.3.E.1: The reactor coolant quality during power operation with steaming rates to the turbine-condenser of less than 100,000 pounds per hour shall be limited to: conductivity 2 us/cm[s=mhos at 25°C (77°F); chloride ion 0.1 ppm.

TS 3.3.E.2 provides the following:

3.3.E.2: When the conductivity and chloride concentration limits given in 3.3.E.1 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor coolant temperature shall be reduced to less than 212°F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Standard: Recognizes the Technical Specification applicability due high conductivity and chloride values which must be reduced below the limits in TS 3.3.E.1.

Comment:

SAT/UNSAT Terminating Cue: The plant is deemed NOT ready for an uninterrupted startup to rated power. The correct reasons and required actions are stated.

JPM Stop Time: ___________

ILT 14-1 NRC SRO Admin JPM1 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC SRO Admin JPM 1 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC SRO Admin JPM1 Page 6 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Have Technical Specifications available
2. Have a clean copy of procedure 201 available
3. Have a prepared copy of Attachment 201-2 ready
4. Have a prepared copy of attachment 201-6 ready ILT 14-1 NRC SRO Admin JPM1 Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

The plant has just completed all major activities during a refuel outage Preparations are being made for a plant startup The REACTOR MODE SELECTOR switch is in REFUEL Attachment 201-2, Pre-Critical Checkoff has been completed and is awaiting review Task Cue:

Perform uncompleted items in Step 78 of the Pre-Critical Checkoff for Attachment 201-2.

From this review, determine if the plant is ready for an uninterrupted startup to rated power.

If the plant is NOT ready, state why and what actions are required to be ready.

ILT 14-1 NRC SRO Admin JPM1 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2150101022 Task

Title:

Review Request to Allow LPRM (input into APRM) Bypass Job Performance Measure No.: NRC Admin JPM 2 (SRO)

K/A

Reference:

2.1.9 (4.5)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

The plant is at 17% power with control rod withdrawals in progressLPRM 28-33D, which inputs into APRM 5 has been spiking upscale, resulting in spurious 1/2 scrams A Troubleshooting Log has been developed which will remove LPRM 28-33D from the APRM 5 Drawer, and replace it with LPRM 28-41D, which is not currently associated to any APRM.

A Tech Eval has been approved to swap the LPRM Another Licensed Operator is available to support the activity.

A copy of the Troubleshooting Log and Attachment 403-2, LPRM and APRM Status Information Sheet, is attached.

Initiating Cue:

Review Attachment 403-2. State any actions required, if any.

Review and approve the Troubleshooting Log. If not approved, state why.

Required Materials:

1. Have a copy of Tech Specs Available
2. Have a copy of the Troubleshooting Log and completed attachment 403-2.

General

References:

1. 403 Revision 31 LPRM-APRM System Operations
2. MA-AA-716-004, Conduct of Troubleshooting
3. 620.4.002, APRM Surveillance Test - Front Panel Check ILT 14-1 NRC Admin JPM 2 (SRO) Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Task Standard:

Determine that APRM 5 will be inoperable when bypassed AND determines that APRM 5 cannot be bypassed until APRM 6 is restored.

Time Critical Task: NO Validation Time: 11 minutes ILT 14-1 NRC Admin JPM 2 (SRO) Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: Review Troubleshooting Log Standard: Reviews and does not approve Troubleshooting Log Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: Review Attachment 403-2 Standard: Reviews Attachment 403-2 Determines that APRM 6 is inoperable due to 2 LPRMs in the same radial string being inoperable Comment:

SAT/UNSAT ILT 14-1 NRC Admin JPM 2 (SRO) Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: Determine that APRM 5 will be inoperable when bypassed Standard: Determine that APRM 5 will be inoperable when bypassed OR determines that APRM 5 cannot be bypassed until APRM 6 is restored.

Comment:

SAT/UNSAT Task Standard: Determine that APRM 5 will be inoperable when bypassed AND determines that APRM 5 cannot be bypassed until APRM 6 is restored.

JPM Stop Time: ___________

ILT 14-1 NRC Admin JPM 2 (SRO) Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC SRO Admin JPM 2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Admin JPM 2 (SRO) Page 5 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup Have the following procedures ready:

1. 403 Revision 31 LPRM-APRM System Operations
2. MA-AA-716-004, Conduct of Troubleshooting
3. 620.4.002, APRM Surveillance Test - Front Panel Check ILT 14-1 NRC Admin JPM 2 (SRO) Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

The plant is at 17% power with control rod withdrawals in progressLPRM 28-33D, which inputs into APRM 5 has been spiking upscale, resulting in spurious 1/2 scrams A Troubleshooting Log has been developed which will remove LPRM 28-33D from the APRM 5 Drawer, and replace it with LPRM 28-41D, which is not currently associated to any APRM.

A Tech Eval has been approved to swap the LPRM Another Licensed Operator is available to support the activity.

A copy of the Troubleshooting Log and Attachment 403-2, LPRM and APRM Status Information Sheet, is attached.

Initiating Cue:

Review Attachment 403-2. State any actions required, if any.

Review and approve the Troubleshooting Log. If not approved, state why.

ILT 14-1 NRC Admin JPM 2 (SRO) Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: RPT00001 Task

Title:

Authorize Emergency Exposures Job Performance Measure No.: NRC Admin JPM 4 (SRO)

K/A

Reference:

2.3.4 (3.7)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant was at rated power when a severe earthquake occurred.
  • Chemistry has confirmed fuel failures.
  • Many plant systems have either failed to automatically isolate or are currently leaking from breaks or incomplete system isolations.
  • An emergency has been declared by the Shift Manager but no emergency operating facilities have been activated.
  • The RP Manager has forwarded 3 Authorization for Emergency Exposure forms to you for your approval. Personal information on the volunteers to perform the 3 different jobs is also provided.

Task Standard:

Determines that authorization should not be provided to Alan Able (JOB A) since it will only result in a dose of 3.75 Rem (25/60 hour x 9 Rem/hr).

Determines that authorization should not be provided to Bob Blake (JOB B) since he already has had an emergency exposure of >25 Rem before.

Determines that authorization should be authorized for Chris Cat (JOB C). He has had no prior emergency exposure > 25 Rem, and his expected exposure is > 5 Rem (35/60 x 11 = 6.4 Rem)

Required Materials: None

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information General

References:

1. EP-AA-113 Revision 12 Initiating Cue:

Authorize or NOT authorize the 3 Authorization For Emergency Exposure forms provided to you from the RP Manager. If not authorized, state why.

Time Critical Task: NO Validation Time: 30 Minutes

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Note: The following steps can be performed in any order.

Performance Step: 2 Evaluates and determines authorization for Emergency Exposure for Alan Able (JOB A)

Standard: Determines that authorization should not be provided to Alan Able (JOB A) since it will only result in a dose of 3.75 Rem (25/60 hour x 9 Rem/hr).

Comment:

SAT/UNSAT

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Evaluates and determines authorization for Emergency Exposure for Bob Blake (JOB B)

Standard: Determines that authorization should not be provided to Bob Blake (JOB B) since he already has had an emergency exposure of >25 Rem before.

Comment:

SAT/UNSAT

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Evaluates and determines authorization for Emergency Exposure for Chris Cat (JOB C)

Standard: Determines that authorization should be authorized for Chris Cat. He has had no prior emergency exposure > 25 Rem, and his expected exposure is >

5 Rem (35/60 x 11 = 6.4 Rem)

Comment:

SAT/UNSAT Terminating Cue: Determines that only the Authorization for Emergency Exposure form for Chris Cat should be authorized, and that the others should not be authorized.

JPM Stop Time: ___________

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC SRO Admin JPM 4 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Have a calculator available
2. Have a copy of EP-AA-113 Revision 12 available if the candidate requests
3. Hand out the 3 student copies of EP-AA-113-F-02, Authorization For Emergency Exposure, Revision B, to each candidate
4. Provide the Personal information on the volunteers to perform the 3 different jobs to each candidate

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant was at rated power when a severe earthquake occurred.
  • Chemistry has confirmed fuel failures.
  • Many plant systems have either failed to automatically isolate or are currently leaking from breaks or incomplete system isolations.
  • An emergency has been declared by the Shift Manager but no emergency operating facilities have been activated.
  • The RP Manager has forwarded 3 Authorization for Emergency Exposure forms to you for your approval. Personal information on the volunteers to perform the 3 different jobs is also provided.

Task Cue:

Authorize or NOT authorize the 3 Authorization for Emergency Exposure forms provided to you from the RP Manager. If not authorized, state why.

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Personal information on the volunteers to perform the 3 different jobs.

PURPOSE: To enter the Trunion Room to manually close the MSIVs to secure the steam leak into the Turbine Building.

JOB A DOSE RATE: 9 R/hour.

JOB DURATION: 25 minutes Volunteer: Alan Able Age: 44 Prior Lifetime No Employee 00111 Emergency Exposure?

ID:

Current 1000 mrem Dose:

PURPOSE: To rescue an unconscious worker in the Drywell.

JOB B DOSE RATE: 30 R/hour.

JOB DURATION: 55 minutes Volunteer: Bob Blake Age: 47 Prior Lifetime Yes Employee 00222 Emergency Exposure? 28 Rem ID:

Current 1150 mrem Dose:

PURPOSE: To close the RWCU isolation valves to stop a leak in the Reactor Building and to rescue a trapped worker who could drown from the flooding.

JOB C DOSE RATE: 11 R/hour.

JOB DURATION: 35 minutes Volunteer: Chris Cat Age: 40 Prior Lifetime No Employee 00333 Emergency Exposure?

ID:

Current 1400 mrem Dose:

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2000502401 Task

Title:

Emergency Event Classification Job Performance Measure No.: SRO NRC Admin JPM 5 K/A

Reference:

2.4.29 (4.4)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Plant conditions are as is in simulator once Scenario is complete Task Standard:
  • Completes the State and Local Notification Form for Emergency Directors Approval.

Initiating Cue:

  • State the minimum classification for these conditions
  • Complete the State and Local Notification Form for Emergency Directors Approval.

Required Materials: Prepare adequate copies of the General References to provide to each candidate.

General

References:

1. EP-AA-1010 Addendum 3 rev. 0
2. EP-MA-114-100-F-03 rev. H, Time Critical Task: NO Validation Time: 15 Minutes ILT 14-1 NRC SRO Admin JPM5 Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Denote critical steps with a check mark Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtains current copy of the required procedures Standard: Obtains controlled copy of procedure EP-AA-1010 and EP-MA-114-100-F03 Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM5 Page 2 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 3 Determine Emergency Classification and associated EAL.

Standard: If NRC Scenario 1 is used Declares FA-1, ANY loss or ANY potential Loss of either Fuel Clad or RCS If NRC Scenario 2 is used Declares MS-2, Automatic scram failure to shutdown the reactor and manual actions taken from the Rx control console are not successful in shutting down the reactor If NRC Scenario 3 is used Declares FS-1, Loss or potential loss of any two barriers If NRC Scenario 4 is used Declares FS-1, Loss or potential loss of any two barriers Time Critical Portion of JPM complete Time Complete ________ (<15 minutes)

Note:

Comment:

SAT/UNSAT Performance Step: 4 Complete Status block 1 Standard: Fill in the block with:

Check the line that states This is a Drill Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM5 Page 3 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 6 Complete Emergency Classification block 3 Standard: Fill in the block with:

If NRC Scenario 1 is used Check the line that states Alert If NRC Scenario 2 is used Check the line that states SAE If NRC Scenario 3 is used Check the line that states SAE If NRC Scenario 4 is used Check the line that states SAE Comment:

SAT/UNSAT Performance Step: 7 Complete Declared At block Standard: Fill in the block with:

Time: is current PPC time / Date is Current Date Comment:

SAT/UNSAT Performance Step: 8 Complete Represents A/AN block Standard: Fill in the block with:

For any scenario used: Check the line that states Initial declaration Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM5 Page 4 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 9 Complete EAL number and Event Description block 4 Standard: Fill in the block with:

If NRC scenario 1 is used: The EAL is FA-1, Description similar to: ANY Loss or ANY Potential Loss of either Fuel Clad or RCS If NRC scenario 2 is used: The EAL is MS-2, Description similar to:

Automatic scram failure to shutdown the reactor and manual actions taken from the Rx control console are not successful in shutting down the reactor If NRC scenario 3 or 4 is used: The EAL is FS-1, Description similar to; Loss or Potential Loss of Any two barriers Comment:

SAT/UNSAT Performance Step: 10 Complete Non-Routine Radioactive Release Status block 5 Standard: Fill in the block with:

If NRC Scenario 1 or 2 or 3 are used: Check the line that states that There is no non-routine radiological release in progress If NRC scenario 4 is used: Check the line that states that Airborne non-routine radiological release in progress Comment:

SAT/UNSAT ILT 14-1 NRC SRO Admin JPM5 Page 5 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 11 Complete Meteorological Condition block 6 Standard: Fill in the block with:

If NRC Scenario 1 or 2 or 3 is used From the Weather screen record; Wind direction is from 269 degrees and wind speed is 8 miles per hour (use 380 elevation data)

If NRC Scenario 4 are used: From the Weather screen record; Wind direction is from 245 degrees and wind speed is 5 miles per hour (use 33 elevation data)

Comment:

SAT/UNSAT Performance Step: 12 Complete Conclusion block Standard: Fill in the block with:

For any NRC Scenario used: Check the line that states This is a Drill and Documents time Comment:

SAT/UNSAT Terminating Cue:

JPM Stop Time: ___________

ILT 14-1 NRC SRO Admin JPM5 Page 6 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: SRO NRC Admin JPM 5 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC SRO Admin JPM5 Page 7 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Run NRC 2016 scenario 1, 2, 3, or 4.

ILT 14-1 NRC SRO Admin JPM5 Page 8 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • Plant conditions are as is in simulator once Scenario is complete Task Cue:
  • State the minimum classification for these conditions
  • Complete the State and Local Notification Form for Emergency Directors Approval.

ILT 14-1 NRC SRO Admin JPM5 Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2010101009 Task

Title:

Perform Control Rod Exercising Test - uncoupled Rod (Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 1 K/A

Reference:

201003 A2.02 (3.7/3.8)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power
  • Control Rod Exercising Procedure 617.4.002 is in progress Task Standard: Perform CRD exercise and perform actions for an uncoupled Rod Required Materials: None General

References:

1. 617.4.002 Control Rod Exercise Procedure Rev 69
2. ABN-6 Control Rod Malfunctions Rev 14
3. RAP-H5a Rod Overtravel Rev 2 Initiating Cue:

Continue with procedure 617.4.002, Control Rod Exercising at step 6.4 for Control Rod 02-35 Time Critical Task: NO Validation Time: 11 Minutes ILT 14-1 NRC Control Room JPM 1 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtain a copy of the reference procedure and continue with Control Rod exercising of control rod 02-35 Standard: Obtains procedure 617.4.002 and continues with control rod exercising of control rod 02-35 Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 6.4 - 6.4.7.6 Insert Control Rod 02-35 from position 48 to position 46 Standard: Monitors CRD position indicators for any mispositioned control rod. Turns on Rod Power, On the Rod select matrix selects control rod 02-35, records initial position on attachment 3 and inserts control rod 1 notch from position 48 to position 46 by placing ROD Control Switch to Rod IN position for approximately one-second. Verifies Control Rod moves into position 46.

Inserts a check mark on 617-4-002-3 in the insert column.

BOOTH: uncouple rod 02-35 Insert MAL-CRD. 008_0235 ILT 14-1 NRC Control Room JPM 1 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Comment:

SAT/UNSAT Performance Step: 4 Procedure steps: 6.4.8 - 6.4.8.3 Withdraw Control Rod 02-35 from position 46 to 48 Standard: Places Rod Control switch to ROD OUT NOTCH for approximately one-second. Verifies Control rod moves to position 48 and latches. Records checkmark in the withdrawal column of 617-4-002-3 Comment:

SAT/UNSAT Alternate Path Performance Step: 5 Procedure Step: 6.4.15 - 6.4.15.3 Perform a coupling check and determines Rod is uncoupled Standard: Holds ROD CONTROL switch in ROD OUT NOTCH and simultaneously places the NOTCH OVERRIDE switch in NOTCH OVERRIDE.

Comment:

SAT/UNSAT Performance Step: 6 Recognize rod 02-35 is uncouples and make an update Standard: Recognizes alarm H5a(Rod overtravel) has come in and makes update.

Then enters RAP-H5a and enters ABN-6 Comment:

ILT 14-1 NRC Control Room JPM 1 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 7 Procedure Step: 7.3 - 7.3.1.3 Apply continuous insert signal for rod 02-35 until a response of nuclear instruments is notice Standard: Confirms Rod power switch is On, Rod 02-35 is selected, applies Continuous insert signal until a response is observed on the nuclear instruments BOOTH: re-couple rod 02-35 Delete MAL-CRD. 008_0235 CUE: If asked, Report a response was observed on nuclear instrumentation Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 7.3.2.1 Notify Reactor engineering of uncoupled rod Standard: Notifies Reactor engineering that rod 02-35 was uncoupled Comment:

SAT/UNSAT Performance Step: 9 Procedure step: 7.3.2.2 - 7.3.2.3 Verify rod 02-35 is recoupled ILT 14-1 NRC Control Room JPM 1 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Standard: Withdraws rod to position 48. Applies a continuous withdraw signal at position 48 an verifies Rod overtravel alarm is not alarming an control rod position display indicates position 48.

Comment:

SAT/UNSAT Performance Step: 10 Make update that rod is re-coupled Standard:

Makes update that Rod 02-35 is re-coupled.

Comment:

SAT/UNSAT Terminating Cue: Control Rod has been withdrawn to position 48 and Re-coupling check is complete JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 1 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Control Room JPM 1 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 1 Page 6 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup SIMULATOR SETUP INSTRUCTIONS

1. Reset to a full power IC (115 or other), but this JPM can be run at any power level.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

ILT 14-1 NRC Control Room JPM 1 Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power
  • Control Rod Exercising Procedure is in progress Task Cue:

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2760101005 Task

Title:

Sequential Loss of Service Water (Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 2 K/A

Reference:

400000 K1.01 (3.2/3.3)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power Task Standard: Perform actions for a total loss of Service Water flow per ABN-18 Required Materials: None General

References:

1. ABN-18 Service Water Failure Response Rev 7
2. 303, Reactor Cleanup Demineralizer system rev 147 Initiating Cue: You are the Reactor Operator; respond to plant annunciators and take any actions, if required Time Critical Task: NO Validation Time: 10 Minutes ILT 14-1 NRC Control Room JPM 2 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provide repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT BOOTH OPERATOR:

When directed by the evaluator, insert the following malfunction to trip an operating Service Water Pump INSERT: MAL-SWS001A Performance Step: 2 Responds to a trip of the operating Service Water Pump Standard: Acknowledges annunciator K-1-f SVC WATER PUMP TRIP Comment:

SAT/UNSAT Performance Step: 3 Obtains copy of ABN-18 Standard: Obtains copy of ABN-18 and implements procedure Comment:

ILT 14-1 NRC Control Room JPM 2 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 4 Procedure Step: 3.2 IF Loss of one pump with initially two in service, Then Go to Step 4.6.

Standard: Determines that one service water pump has tripped and proceeds to Step 4.6 CUE:

If asked: report TBCCW is on Service Water Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 4.6 - 4.6.1 IF Service Water loss has reduced RBCCW or TBCCW cooling Capacity, THEN PERFORM the following steps concurrently:

Standard: Lowers cleanup flow as directed Cue: Inform applicant RBCCW cooling has been reduced and as US direct: lower RWCU flow to 350 gpm.

Comment:

SAT/UNSAT BOOTH OPERATOR:

After RWCU flow has been reduced, insert the following malfunction to trip the second operating Service Water Pump:

1. INSERT: MAL-SWS001B ILT 14-1 NRC Control Room JPM 2 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Alternate Path Performance Step: 6 Procedure Step: 4.6.2 EXECUTE ABN-19, RBCCW Failure Response concurrently with this procedure Standard: Attempts to implement ABN-19, RBCCW Failure Response NOTE: This step may not be reached depending on when the second Service Water Pump is tripped.

Cue: Another operator will perform ABN-19 Comment:

SAT/UNSAT Performance Step: 7 Recognize trip of second Service Water Pump Standard: Recognizes trip of second Service Water Pump. Re-enters ABN-18 and responds per section 4.4 for a complete loss of service water Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 4.4 - 4.4.1 If a complete loss of service water has occurred, perform a rapid power reduction as directed by the US Standard: Performs rapid power reduction by lowering master recirc flow Cue: If requested, direct lowering power with recirc flow.

Comment:

ILT 14-1 NRC Control Room JPM 2 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT ILT 14-1 NRC Control Room JPM 2 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 4.4.2 SCRAM the reactor and ENTER ABN-1 Reactor Scram concurrently with this procedure Standard: Scrams the reactor by pushing the manual scram pushbuttons and taking the mode switch to shutdown.

Cue: After the reactor is scrammed, inform the applicant another operator will perform the remaining actions of ABN-1 Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 4.4.3 ENTER ABN-19, RBCCW Failure Response concurrently with this procedure Standard: Attempts to implement ABN-19, RBCCW Failure Response Cue: Another operator will perform ABN-19 Comment:

SAT/UNSAT Performance Step: 11 Procedure Step: 4.4.4 CONFIRM the main turbine is tripped if TBCCW is on Service Water Standard: Observes the main turbine is tripped CUE: If asked report TBCCW is on Service Water Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 2 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 12 Procedure Step: 4.4.6 ISOLATE the Service Water system as directed by the US Standard: Attempts to isolate the SW system CUE: Another operator will isolate the Service Water system Comment:

SAT/UNSAT Performance Step: 13 Procedure Step: 4.4.7 START one ESW pump in each system in order to keep system piping full of water.

Standard: Starts an ESW pump in system I and II.

CUE: Your task is complete.

Comment:

SAT/UNSAT Terminating Cue: ESW pumps are running JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 2 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Sim JPM 2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 2 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup SIMULATOR SETUP INSTRUCTIONS

1. Reset to a full power IC (115 or other), but this JPM can be run at any power level.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Ensure TBCCW is on Service Water
3. 1-1 and 1-2 service water pumps running
4. Student copy available of procedure ABN-18
5. Student copy available of procedure 303 for adjusting cleanup flow ILT 14-1 NRC Control Room JPM 2 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power Task Cue: You are the Reactor Operator; respond to plant annunciators and take any actions, if required ILT 14-1 NRC Control Room JPM 2 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2040101412 Task

Title:

Place the Second RWCU Pump In Service Job Performance Measure No.: NRC Control Room JPM 3 (RO ONLY)

K/A

Reference:

204000 A4.01 (3.1/3.0)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power, with elevated reactor water conductivity.
  • All prerequisites for starting the standby RWCU Pump have been verified.
  • An Equipment Operator is locally stationed and is standing by.
  • The plant announcement for the pump start has been made.

Task Standard:

Flow is established through the second RWCU Pump Required Materials: None General

References:

1. 303, Reactor Cleanup Demineralizer System rev 147 Initiating Cue:
  • Place the standby RWCU Pump in service IAW procedure 303, Reactor Cleanup Demineralizer System, starting at step 22.3.6.
  • Adjust flow to 650 gpm when both RWCU pumps are in service Time Critical Task: NO ILT 14-1 NRC Control Room JPM 3 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Validation Time: 15 Minutes Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtain a copy of the reference procedure and reviews/utilizes the correct section Standard: Current revision of 303 is obtained Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 22.3.6 START the second pump being placed in service Standard: Starts RWCU Pump B by placing the RECIRC PUMP ND02B switch CW to START. (red light ON, green light OFF)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: 22.3.7 Slowly OPEN the second pump discharge valve by momentarily cycling its discharge valve control switch between OPEN and mid position until a small increase in pump discharge pressure is noted.

  • V-16-49, RECIRC PUMP A DISCHARGE OR
  • V-16-50, RECIRC PUMP B DISCHARGE Standard: Slowly opens the RWCU Pump B discharge valve by momentarily cycling the RECIRC PUMP B DISCHARGE V-16-50 control switch between OPEN and mid position until a small increase in RECIRC PUMP DISCHARGE PRESS is noted. (Red light ON, green light ON; small increase in RECIRC PUMP DISCHARGE PRESS)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 22.3.8 PERFORM either or both of the following to reduce pump discharge pressure to approximately the original valve.

  • Slowly OPEN FCV-ND16
  • Slowly OPEN V-16-54, FCV Bypass Standard: Slowly opens SYSTEM FLOW CONTROLLER FCV-ND16 by rotating the manual knob CW to reduce RECIRC PUMP DISCHARGE PRESS to approximately the original valve. (SYSTEM FLOW CONTROLLER FCV-ND16 indicates further open; RECIRC PUMP DISCHARGE PRESS lowers)

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 22.3.9 ADJUST PCV-ND11 as needed to maintain system pressure at approximately 90 psig Standard: Verifies system pressure is approximately 90 psig.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 22.3.10 MONITOR demineralizer and filter (if in service) dP at RK05.

Standard: Directs an EO to monitor demineralizer and filter dP at RK05.

CUE: Repeat back the request to monitor demineralizer and filter dP at RK05.

(Note:No dP limits will be exceeded during this JPM.)

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 22.3.11 IF any of the following dP alarm setpoints are approached:

  • Demineralizer strainer dP (IJ22B) - 10 psid
  • Demineralizer dP (IJ22A) - 15 psid
  • Filter dP (IJ18) - 30 psid THEN STOP the flow increase.

Standard: Directs the EO to monitor/report any of the following:

  • Demineralizer strainer dP (IJ22B) - 10 psid
  • Demineralizer dP (IJ22A) - 15 psid
  • Filter dP (IJ18) - 30 psid CUE: Repeat back the request to monitor demineralizer and filter dP at RK05.

(Note:No dP limits will be exceeded during this JPM.)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 22.3.12 WHEN system flow exceeds 500 gpm, THEN CLOSE the Minimum Flow Valves with the local toggle switches:

  • V-16-37, Minimum Flow Valve Pump B
  • V-16-36, Minimum Flow Valve Pump A Standard: WHEN system flow exceeds 500 gpm, THEN directs the EO to close the Minimum Flow Valves with the local toggle switches:
  • V-16-37, Minimum Flow Valve Pump B
  • V-16-36, Minimum Flow Valve Pump A BOOTH Close both RWCU minimum flow valves by inserting the following remotes:

a) LOA-RCU022 to 0 (RWCU Pump A V-16-36) b) LOA-RCU023 to 0 (RWCU Pump B V-16-37)

CUE: When RWCU min flow valves are closed, report: V-16-36 and V-16-37 are closed Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 22.3.13 Continue to open the discharge valve by momentarily cycling the respective discharge valve control switch between OPEN and mid position while adjusting pressure and flow, until the valve is fully open Standard: Continues to open the discharge valve by momentarily cycling the RECIRC PUMP B DISCHARGE V-16-5 control switch between OPEN and mid position while adjusting pressure and flow, until the valve is fully open. Slowly opens SYSTEM FLOW CONTROLLER FCV-ND16 by rotating the manual knob CW to reduce RECIRC PUMP DISCHARGE PRESS. (Red light ON, green light OFF)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 3 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 22.3.14 PERFORM either or both of the following to continue to raise flow:

  • Throttle OPEN FCV-ND16
  • Throttle OPEN V-16-54, FCV Bypass.

Standard: Throttles either valve but does not exceed 760 gpm CUE: Another operator will complete the rest of the actions.

Comment:

SAT/UNSAT Terminating Cue:

Second RWCU pump in service with flow < 760 gpm JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 3 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Sim JPM 3 (RO ONLY)

Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 3 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup SIMULATOR SETUP INSTRUCTIONS

1. Reset to a full power IC (115 or other), but this JPM can be run at any power level.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Verify RWCU Pump A is in service, with an RWCU filter in-service and system flow between 380 - 420 GPM.
3. Open both RWCU minimum flow valves by inserting the following remotes:

c) LOA-RCU022 to 1 (RWCU Pump A V-16-36) d) LOA-RCU023 to 1 (RWCU Pump B V-16-37)

4. Place the heat balance screen up on the PPC screen
5. Input RWCU flow to 760 gpm
6. Verify both RBCCW Pumps running
7. Verify both Service Water Pumps running
8. Insert LOA-RBC009 to 0.6 (this opens V-5-122 to 60%; RBCCW outlet of the NRHX outlet)
9. Insert BKR-RCU001 to FAIL AUT TRIP
10. Insert BKR-RCU002 to FAIL AUT TRIP
a. This will prevent any automatic trips of the RWCU Pumps
11. Place placards for two RWCU pump operation at 3F and on the Letdown Flow Controller ILT 14-1 NRC Control Room JPM 3 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power, with elevated reactor water conductivity.
  • All prerequisites for starting the standby RWCU Pump have been verified.
  • An Equipment Operator is locally stationed and is standing by.
  • The plant announcement for the pump start has been made.

Task Cue:

  • Place the standby RWCU Pump in service IAW procedure 303, Reactor Cleanup Demineralizer System, starting at step 22.3.6
  • Adjust flow to 650 gpm when both RWCU pumps are in service ILT 14-1 NRC Control Room JPM 3 Page 10 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2390201009 Task

Title:

Partial MSIV Stroke Test (Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 4 K/A

Reference:

239001 A4.01 (4.2/4.0)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is operating at 100% power.
  • All steps of Section 3.0 PREREQUISITES are met and the Unit Supervisor has granted permission to perform the surveillance Test.

Task Standard: Reactor is scrammed and the mode switch is shutdown.

Required Materials: Digital Stopwatch General

References:

1. 602.4.004 Main Steam Isolation Valve 10% Closure Test Rev 25 Initiating Cue: Perform Main Steam Isolation Valve 10% Closure Test 602.4.004 Sections 6.1 through 6.4 Time Critical Task: NO Validation Time: 10 Minutes ILT 14-1 NRC Control Room JPM 4 Page 1 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Obtain a copy of the reference procedure and reviews/utilizes the correct section Standard: Current revision of 602.4.004 is obtained Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 2 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Review Precautions and Limitations and obtains a digital Stop Watch Standard: Precautions and Limitations reviewed; stop watch obtained Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 6.1 VERIFY Section 3.0 Prerequisites are satisfied.

RECORD Digital Stopwatch Number Standard: Section 3.0 Prerequisites are satisfied, as given in Initial Conditions.

Records Digital Stopwatch Number CUE: If stopwatch has no number: report number is one.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 3 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 6.3.1 CONFIRM nitrogen receiver T-23-001 pressure > 95 psig Directs Equipment Operator to report nitrogen pressure locally and Standard:

determines nitrogen is in band.

CUE: Report as Equipment Operator that PI-23-523 indicates 100 psig Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 6.3.2 Reads Step 6.3.2 IF/Then step concerning increasing steam flow in lines not being tested Standard: Reads and places keeps step Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 4 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 6.3.3 Station personnel as required to observe indications Standard: Ensures Station personnel at the following:

  • Relay 2K17
  • Relay 2K18
  • PPC point SOE47
  • PPC point SOE48 CUE: Personnel are stationed Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 6.3.4 & 6.3.5 Simultaneously PERFORM the following two steps:

  • DEPRESS and HOLD TEST button for ValveV-1-0008 / NS03B.

(Panel 11F)

  • START the stopwatch
  • OBSERVE the Red Open indicating light Extinguishes for NS03B.

Standard: DEPRESSES and HOLDS TEST button for ValveV-1-0008 / NS03B. (Panel 11F), STARTS the stopwatch and OBSERVE the Red Open indicating light Extinguishes for NS03B Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 5 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 6.3.7 WHEN a half scram signal is received, AND both 2K17 and 2K18 have de-energized, simultaneously PERFORM the following two steps:

  • RELEASE the TEST button

Standard: Releases Test button and stops the stopwatch. Records Stroke time for NS03B CUE: (at time of 1/2 scram): Relays 2K17 and 2K18 are de-energized Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 6.3.8 - 6.3.10 Performs the following:

  • VERIFY relays 2K17 and 2K18 de-energized and all contacts opened. (Panel 7R)
  • VERIFY Plant Process Computer, PID: SOE47, tripped; MSIV CLOSURE SCRAM. (2K17)
  • VERIFY Plant Process Computer, PID: SOE48, tripped; MSIV CLOSURE SCRAM. (2K18)

Standard: Verifies relays are tripped and the appropriate Plant Process computer points are received CUE: Relays 2K17 and 2K18 are de-energized and all contacts opened (paper models in simulator)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 6 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 6.3.11 VERIFY that the MSIV returns to the fully open position by the Red Open light illuminating Standard: Verifies MSIV is FULLY OPEN (red light ON; green light OFF)

Comment:

SAT/UNSAT Performance Step: 12 Procedure Step: 6.3.12 - 6.3.13 VERIFY SCRAM SOLENOIDS lights extinguished. (Panel 7R)

VERIFY SCRAM CONTACTOR OPEN alarm (G-1-c) is received.

Standard: Verifies SCRAM SOLENOIDS lights extinguished. (Panel 7R) and SCRAM CONTACTOR OPEN alarm is received on panel G Comment:

SAT/UNSAT Performance Step: 13 Procedure Step: 6.3.14 - 6.3.15 VERIFY MSIV CLOSED II alarm (J-2-a) annunciated VERIFY MN STM VLVS OFF NORMAL alarm (J-8-b) annunciated.

Standard: Verifies J-2-a and J-8-b annunciators are in alarm Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 7 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 14 Procedure Step: 6.3.16 VERIFY relays 2K51A and 2K52A are de-energized. (Panel 7R)

Standard: VERIFIES relays 2K51A and 2K52A are de-energized. (Panel 7R)

CUE: Relays 2K51A and 2K52A are de-energized (paper models in simulator)

Comment:

SAT/UNSAT Performance Step: 15 Procedure Step: 6.3.17 - 6.3.21 RESET the half scram CONFIRM Plant Process Computer PIDs returned to normal state CONFIRM Alarms returned to normal state VERIFY all SCRAM SOLENOID lights lit. (4F/7R)

VERIFY SCRAM CONTACTOR OPEN alarm (G-1-c) clear Standard: Resets the half scram RPS signal by pushing scram reset pushbutton on 4F.

  • CONFIRMS Plant Process Computer PIDs returned to normal state
  • CONFIRMS Alarms returned to normal state
  • VERIFIES all SCRAM SOLENOID lights lit. (4F/7R)

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 8 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 16 Procedure Step: 6.3.22 - 6.3.27 VERIFY MSIV CLOSED II alarm (J-2-a) clear VERIFY MN STM VLVS OFF NORMAL alarm (J-8-b) clear.

VERIFY relays 2K17 and 2K18 energized. (Panel 7R)

VERIFY relays 2K51A and 2K52A energized. (Panel 7R)

VERIFY Plant Process Computer PIDs SOE47 and SOE48 are normal.

Verifies the following:

Standard:

  • MSIV CLOSED II alarm (J-2-a) clear
  • MN STM VLVS OFF NORMAL alarm (J-8-b) clear.
  • Relays 2K17 and 2K18 are energized. (Panel 7R)
  • Relays 2K51A and 2K52A are energized. (Panel 7R)
  • Plant Process Computer PIDs SOE47 and SOE48 are normal.

CUE: US has Verified plant parameters required to continue to next are satisfied

2K17 and 2K18 are energized and SOE47 and SOE48 are normal Comment:

SAT/UNSAT Performance Step: 17 Continues on with surveillance testing of Test of V-1-10 / NS04B.

Reads Step 6.4.1 Standard: Place keeping identifies candidate has read step 6.4.1 Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 9 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 18 Procedure Step: 6.4.2 Station personnel as required to observe indications Standard: Ensures Station personnel at the following:

  • Relay 2K17
  • Relay 2K18
  • PPC point SOE47
  • PPC point SOE48 CUE: Personnel are stationed Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 10 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 19 Procedure Step: 6.4.3 - 6.4.4 Simultaneously PERFORM the following two steps:

  • DEPRESS and HOLD TEST button for ValveV-1-0010 / NS04B.

(Panel 11F)

  • START the stopwatch
  • OBSERVE the Red Open indicating light Extinguishes for NS04B.

Standard: DEPRESSES and HOLDS TEST button for ValveV-1-0010 / NS04B. (Panel 11F), STARTS the stopwatch and OBSERVE the Red Open indicating light Extinguishes for NS04B BOOTH: INSERT MAL-NSS013D to severity to 0 over 1000 seconds Eval CUE: IF asked steam flow trends: Report no recognizable change in steam flow while applicant is holding button Comment:

SAT/UNSAT Alternate Path Performance Step: 20 6.4.6 when half scram signal received and both 2K17 and 2K18 have de-energized or there is a noticeable increase in reactor pressure or decrease in steam flow,

  • RELEASE the TEST button
  • STOP the stopwatch
  • RECORD stroke time for NS04B Standard: Releases Test button and stops the stopwatch. Records Stroke time for NS04B and notices Steam line pressure is still rising and the Red open light is not illuminated CUE: (at time of 1/2 scram): Relays 2K17 and 2K18 are de-energized
If asked any time after button is released for steam flow parameters:

Report: other operator is no longer available to monitor steam flow Comment:

ILT 14-1 NRC Control Room JPM 4 Page 11 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT ILT 14-1 NRC Control Room JPM 4 Page 12 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 21 Step 6.4.5 Remove fuse 11F-6F6 and verifies NS04B open Standard: Removes fuse 11F-6F6 and notices NS04B not fully open and steam pressure still rising CUE: fuse is removed (note: not modeled in simulator)

Comment:

SAT/UNSAT Performance Step: 22 Prior to auto scram operator Scrams reactor, Pushes scram pushbuttons and takes mode switch to shutdown Standard: Pushes Scram pushbuttons and takes mode switch to shutdown CUE: (after mode with to shutdown) report: another operator will perform further actions.

Comment:

SAT/UNSAT Terminating Cue:

Reactor is scrammed and the mode switch is shutdown.

JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 4 Page 13 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Validation of Completion JPM Number: NRC Control Room JPM 4 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 4 Page 14 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information JPM Setup

1. Rest to a full power IC (115 or other)

Note: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrntly ILT 14-1 NRC Control Room JPM 4 Page 15 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information STUDENT HANDOUT Initial Conditions:

  • The plant is operating at 100% power.
  • All steps of Section 3.0 PREREQUISITES are met and the Unit Supervisor has granted permission to perform the surveillance Test.

Task Cue:

Perform Main Steam Isolation Valve 10% Closure Test 602.4.004 Sections 6.1 through 6.4 ILT 14-1 NRC Control Room JPM 4 Page 16 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2000501401 Cool down the RPV using the Isolation Condenser tube side vents IAW SP-15, Alternate Pressure Control Systems - IC Tube Side Vents Task

Title:

(Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 5 K/A

Reference:

295021 AA1.04 (RO/SRO 3.7/3.7)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is shutdown and cooling down to COLD SHUTDOWN IAW RPV Control - no ATWS.
  • Isolation Condensers are not required to be isolated.
  • The Offsite radioactivity release rate is below that required for an Unusual Event.
  • All modes of pressure control for cooldown are unavailable except the Isolation Condenser Tube Side Vents.
  • The Isolation Condenser DC valves are isolated due to previous RPV level being >

180. RPV water level is currently 155 in and steady.

Task Standard:

RPV is being cooled down using Isolation Condenser B Tube Side Vents.

Required Materials: EMG-SP15 General

References:

1. Support Procedure 15, Alternate Pressure Control Systems - IC Tube Side Vents, Revision 1.

ILT 14-1 NRC Control Room JPM 5 Page 1 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue:

As the Unit Supervisor, I am directing you to establish a 10F/hr cooldown rate IAW SP-15, Alternate Pressure Control Systems - IC Tube Side Vents. A Isolation Condenser is the preferred system.

Time Critical Task: NO Validation Time: 11 minutes ILT 14-1 NRC Control Room JPM 5 Page 2 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 2.1.1 Verify Isolation Condensers are not required to be isolated.

Standard: Verifies Isolation Condensers are not required to be isolated.

Note: Initial Conditions state that Isolation Condensers are not required to be isolated.

Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 2.1.2 Verify Main Condenser is intact.

Standard: Verifies Main Condenser is intact.

Note: Initial Conditions state the Main Condenser is intact.

Comment:

ILT 14-1 NRC Control Room JPM 5 Page 3 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 4 Procedure Step: 2.1.3 Verify Offsite radioactivity release rate is expected to remain below the release rate, which requires an Unusual Event.

Standard: Verifies Offsite radioactivity release rate is expected to remain below the release rate, which requires an Unusual Event.

Note: Initial Conditions state that Offsite radioactivity release rate is expected to remain below the release rate, which requires an Unusual Event.

Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 2.2 Open the EOP BYPASS PLUGS panel inside of Panel 10XF.

Standard: Opens the EOP BYPASS PLUGS panel inside of Panel 10XF.

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 2.2.1 Remove the bypass plug from position BP2.

Standard: Removes the bypass plug from position BP2.

Comment:

ILT 14-1 NRC Control Room JPM 5 Page 4 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 7 Procedure Step: 2.2.2 Insert a bypass plug into position BP1.

Standard: Inserts a bypass plug into position BP1.

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 2.2.3 Remove the bypass plug from position BP4.

Standard: Removes the bypass plug from position BP4.

Comment:

SAT/UNSAT Performance Step: 9 Procedure Step: 2.2.4 Insert a bypass plug into position BP3.

Standard: Inserts a bypass plug into position BP3.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 5 Page 5 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 10 Procedure Step: 3.1 Verify that RPV Water Level is below 180 in.

Standard: Verifies that RPV Water Level is below 180 in.

CUE: If RPV water level has risen to > 180 in following the JPM setup, inform the applicant RPV water level is < 155 in and steady.

Comment:

SAT/UNSAT Performance Step: 11 Procedure Step: 3.2 Confirm open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser A: (Panel 1F/2F)

  • V-14-30
  • V-14-31 Standard: Confirms open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser A: (Panel 1F/2F)
  • V-14-30
  • V-14-31 Note: Places the CLOSE-AUTO-OPEN switch for the valves to the OPEN position.

Waits for valve indications to show red OPEN light lit and green CLOSED light extinguished.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 5 Page 6 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information NOTE: In the next step Isolation Condenser A vents will NOT open.

Alternate Path.

Performance Step: 12 Procedure Step: 3.3 Open the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11F)

  • V-14-5 / V-14-20 Standard: Opens the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11F)

V-14-5 / V-14-20 Note: Isolation Condenser A vent valves V-14-5 and V-14-20 will not open. The applicant will re-perform SP-15 starting at step 3.2 for Isolation Condenser B.

CUE: The applicant may inform the US that Isolation Condenser A vent valves will not open. Direct the applicant to continue with Support Procedure 15. (It is acceptable if the applicant establishes a cooldown using the Isolation Condenser B vents without first consulting the US.)

Comment:

SAT/UNSAT Performance Step: 13 Procedure Step: 3.2 Confirm open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser B: (Panel 1F/2F)

  • V-14-32 and V-14-33 Standard: Confirms open the following Isolation Condenser Steam Inlet Valves for the Isolation Condenser B: (Panel 1F/2F)
  • V-14-32 and V-14-33 Note: Places the CLOSE-AUTO-OPEN switch for the valves to the OPEN position.

Waits for valve indications to show red OPEN light lit and green CLOSED light extinguished.

Comment:

ILT 14-1 NRC Control Room JPM 5 Page 7 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Performance Step: 14 Procedure Step: 3.3 Open the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11F)

  • V-14-1 / V-14-19 Standard: Opens the following Isolation Condenser Vents for the Isolation Condensers to be used: (Panel 11F)
  • V-14-1 / V-14-19 Note: Waits for valve indications to show red OPEN light lit and green CLOSED light extinguished.

CUE: Another operator will continue with and control the cooldown that is already established.

Comment:

SAT/UNSAT Terminating Cue: RPV cooldown is in progress using Isolation Condenser B tube side vents.

JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 5 Page 8 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Control Room JPM 5 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 5 Page 9 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup

1. Reset to IC-115 or any shutdown IC where the Primary Containment is NOT isolated
2. Insert a manual scram
3. Stabilize RPV pressure around 500 psig
4. Stabilize RPV level below 180 in
5. Shut the IC A & B vents
6. Insert VLV-ICS002 to CLOSE
  • Keeps IC A vent valve V-14-5 closed
7. Insert VLV-ICS004 to CLOSE
  • Keeps IC A vent valve V-14-20 closed
8. Have a copy of SP-15 for the applicant ILT 14-1 NRC Control Room JPM 5 Page 10 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is shutdown and cooling down to COLD SHUTDOWN IAW RPV Control - no ATWS.
  • Isolation Condensers are not required to be isolated.
  • The Offsite radioactivity release rate is below that required for an Unusual Event.
  • All modes of pressure control for cooldown are unavailable except the Isolation Condenser Tube Side Vents.
  • The Isolation Condenser DC valves are isolated due to previous RPV level being > 180. RPV water level is currently 155 in and steady.

Initiating Cue:

As the US, I am directing you to establish a 10F/hr cooldown rate IAW SP-15, Alternate Pressure Control Systems - IC Tube Side Vents. A Isolation Condenser is the preferred system.

ILT 14-1 NRC Control Room JPM 5 Page 11 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2000501416 Task

Title:

Place the H2/02 Monitoring System in service Job Performance Measure No.: NRC Control Room JPM 6 (RO/SRO)

K/A

Reference:

500000 EA1.01 (RO/SRO 3.4/3.3)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • A LOCA is in progress

Task Standard:

Channel A H2/02 Monitoring System is in service.

Required Materials: None.

General

References:

1. Support Procedure 39, Placing the H2O2 Monitoring System in Service, Revision 1.

Initiating Cue:

As the US, I am directing you to place the H2/02 monitoring system in service IAW Support Procedure 39.

Time Critical Task: NO Validation Time: 7 minutes ILT 14-1 NRC Control Room JPM 6 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 3.1.1 (For Channel A) Verify the Power switch is in the ON position Standard: Verifies the Power switch is in the ON position for Channel A Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 3.1.2 Place switch for H2 Sample Supply V-38-37 to OPEN Standard: Places switch for H2 Sample Supply V-38-37 to OPEN Verifies that the red OPEN light is lit and the green CLOSE light is Note:

extinguished.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 6 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: 3.1.3 Place switch tor H2 Sample Supply V-38-38 to OPEN Standard: Places switch tor H2 Sample Supply V-38-38 to OPEN Note: Verifies that the red OPEN light is lit and the green CLOSE light is extinguished.

Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 3.1.4 Place switch for H2 Sample Return V-38-39 to OPEN Standard: Places switch for H2 Sample Return V-38-39 to OPEN Note: Verifies that the red OPEN light is lit and the green CLOSE light is extinguished.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 6 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 6 Procedure Step: 3.1.5 Place switch for H2 Sample Return V-38-40 to OPEN Standard: Places switch for H2 Sample Return V-38-40 to OPEN Verifies that the red OPEN light is lit and the green CLOSE llght is Note:

extinguished.

Comment:

SAT/UNSAT Performance Step: 7 Procedure Step: 3.1.6 Place switch for PUMP (P-38-5) in ENABLE position Standard: Places switch for PUMP (P-38-5) in ENABLE position Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 3.1.7 Depress Channel A ANALYZE PB to place Analyzer IT-1A in Analyze mode.

Standard: Depresses Channel A ANALYZE PB to place Analyzer IT-1A in Analyze mode.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 6 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 3.1.8 Touch CRT Screen and VERIFY:

  • GAS MONITORING SYSTEM screen ILLUMINATES
  • GAS MONITORING SYSTEM screen does not indicate Stand-By mode.

Standard: Touches CRT Screen and VERIFY:

  • GAS MONITORING SYSTEM screen ILLUMINATES
  • GAS MONITORING SYSTEM screen does not indicate Stand-By mode Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 3.1.9 Verify H2/02 Recorder AR-0002 begins recording Standard: Verifies H2/02 Recorder AR-0002 begins recording Cue: Inform the applicant Channel A has begun recording and another operator will continue with the support procedure Comment:

SAT/UNSAT Terminating Cue: Channel A of the H2/02 monitoring system has been placed in service IAW SP-39.

JPM Stop Time: ___________

ILT 14-1 NRC Control Room JPM 6 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ILT 14-1 NRC Control Room JPM 6 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 6 Page 6 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup

1. Reset to IC 115 (or similar IC)
2. Have a copy of SP-39 for the applicant ILT 14-1 NRC Control Room JPM 6 Page 7 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

Task Cue:

As the US, I am directing you to place the H2/02 monitoring system in service IAW Support Procedure 39.

ILT 14-1 NRC Control Room JPM 6 Page 8 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2880101404 Task

Title:

Startup of the Turbine Building Ventilation System (Alternate Path)

Job Performance Measure No.: NRC Control Room JPM 7 K/A

Reference:

288000 A4.01 (3.1/2.9)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is shutdown
  • The Turbine Building Ventilation System has been secured
  • All prerequisites to start the Turbine Building Ventilation System have been verified
  • Attachments 328-1, 328-2, 328-3 have been completed Task Standard:

The Turbine Ventilation System has been started utilizing Exhaust Fan 1-6 Required Materials: None.

General

References:

1. Procedure 328, Turbine Building Heating And Ventilation System, Revision 61 Initiating Cue:

Start the Turbine Building Ventilation System IAW Procedure 328, Turbine Building Heating And Ventilation System, starting at Step 5.1.2 Time Critical Task: NO Validation Time: 13 minutes ILT 14-1 NRC Control Room JPM 7 Page 1 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Reviews Precautions and Limitations.

Standard: Reviews Precautions and Limitations.

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 7 Page 2 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Note: Exhaust Fan 1-7 will not start and initiates the Alternate Path.

Exhaust Fan 1-7 will not be re-started on the second attempt.

Alternate Path Performance Step: 3 Procedure Step: 5.1.2 Start EF-1-7 by placing EF-1-7 control switch to START.

Reports the fan does not start.

Standard: Starts EF-1-7 by placing EF-1-7 control switch to START.

Reports the fan will not start. (red light OFF; green light ON)

May contact EO to inspect the Fan.

Cue: As the SRO, acknowledge the fan will not start.

As the EO, report that you see no obvious abnormalities with the fan.

Comment:

SAT/UNSAT Note: The step below may occur any time during the JPM.

Performance Step: 4 Procedure Step: 5.1.2.1.1 Notify Radiation Protection anytime operating EF-1-6.

Standard: Notifies Radiation Protection anytime operating EF-1-6.

Cue: RP has been notified Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 7 Page 3 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 5 Procedure Step: 5.1.2.1.1 Confirm closed Dampers DM-28-8, DM-28-3 and their associated limit switches are made up Standard: Directs the EO to confirm closed Dampers DM-28-8, DM-28-3 and their associated limit switches are made up Cue: Dampers DM-28-8, DM-28-3 are closed and their associated limit switches are made up Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 5.1.2.1.4 Confirm open DM-28-4 and associated limit switches are made up.

Standard: Directs the EO to confirm open DM-28-4 and associated limit switches are made up.

Cue: Damper DM-28-4 is open and associated limit switches are made up.

Comment:

SAT/UNSAT Performance Step: 7 Procedure Step: 5.1.2.1.3 Start EF-1-7 by placing EF-1-7 control switch to START Standard: Starts EF-1-7 by placing EF-1-7 control switch to START and recognizes the fan will not start (red light OFF; green light ON)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 7 Page 4 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 8 Procedure Step: 5.1.2.1.4a If EF-1-7 fails to start on the second attempt, then place EF-1-6 in service as follows:

Open V-28-71 to drain any standing water from EF-1-6 Standard: Directs EO to Open V-28-71 to drain any standing water from EF-1-6 Cue: V-28-71 is open and a little water has drained out.

Comment:

SAT/UNSAT Performance Step: 9 Procedure Step: 5.1.2.1.4a When water has stopped draining, then close V-28-71 Standard: Directs EO to close V-28-71 when water has stopped draining Cue: Water has stopped draining and V-28-71 is closed Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 5.1.2.1.4c Confirm closed DM-28-8 Standard: Directs EO to confirm closed DM-28-8 Cue: DM-28-8 is closed Comment:

ILT 14-1 NRC Control Room JPM 7 Page 5 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SAT/UNSAT Performance Step: 11 Procedure Step: 5.1.2.1.4d Close DM-28-4.

Standard: Directs EO to close DM-28-4 Cue: DM-28-4 is closed Comment:

SAT/UNSAT Performance Step: 12 Procedure Step: 5.1.2.1.4e Open DM-28-3 Standard: Directs the EO to open DM-28-3 Cue: DM-28-3 is open Comment:

SAT/UNSAT Performance Step: 13 Procedure Step: 5.1.2.1.4f Start Exhaust Fan EF-1-6 by placing EF-1-6 control switch to ON Standard: Starts Exhaust Fan EF-1-6 by placing EF-1-6 control switch to START (red light ON; green light OFF)

Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 7 Page 6 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 14 Procedure Step: 5.1.3 Start Supply Fan SF-1-1 or SF-1-2 by placing Control Switch to ON Standard: Starts Supply Fan SF-1-1 or SF-1-2 by placing Control Switch to ON (red light ON; green light OFF) on panel 11R Comment:

SAT/UNSAT Performance Step: 15 Procedure Step: 5.1.4 Start Supply Fan SF-1-3 or SF-1-4 by placing Control Switch to ON.

Standard: Starts Supply Fan SF-1-3 or SF-1-4 by placing Control Switch to ON. (red light ON; green light OFF) on panel 11R Comment:

SAT/UNSAT Performance Step: 16 Procedure Step: 5.1.5 Start EF-1-33 by placing EF-1-33 control switch to ON.

Standard: Starts EF-1-33 by placing EF-1-33 control switch to ON. (red light ON; green light OFF) on panel 11R Comment:

ILT 14-1 NRC Control Room JPM 7 Page 7 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SAT/UNSAT Performance Step: 17 Procedure Step: 5.1.6 Start SF-1-5 or SF-1-6 by placing the control switch to ON.

Standard: Starts SF-1-5 or SF-1-6 by placing the control switch to ON. (red light ON; green light OFF) on panel 11R Comment:

SAT/UNSAT Performance Step: 18 Procedure Step: 5.1.7 Verify that EF-1-4 has started by observing the red indicating light Lit Standard: Verifies that EF-1-4 has started by observing the red indicating light Lit on panel 11R Comment:

SAT/UNSAT Performance Step: 19 Procedure Step: 5.1.8 Starts Feedwater Pump Room Supply Fan, SF-1-7, and Exhaust Fan, EF-1-1, by placing SF-1-7 and EF-1-1 control switch to ON Standard: Start Feedwater Pump Room Supply Fan, SF-1-7, and Exhaust Fan, EF-1-1, by placing SF-1-7 and EF-1-1 control switch to ON (red lights ON; green lights OFF)

Cue: Another Operator will continue with the procedure ILT 14-1 NRC Control Room JPM 7 Page 8 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Comment:

SAT/UNSAT Terminating Cue: The Turbine Ventilation System has been started utilizing Exhaust Fan 1-6 JPM Stop Time: ___________

Validation of Completion JPM Number: NRC Control Room JPM 7 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

ILT 14-1 NRC Control Room JPM 7 Page 9 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

Simulator Setup

1. IC-115. (but can be any IC)
2. Shutdown the TB Vent System IAW procedure 328, section 5.4
3. Insert the following:
a. LOA-TBS030 to OPEN
b. SWI-TBS017A to ON
c. These two malfunctions open the breaker to Exhaust Fan 1-7 but keeps the green light on
4. Insert ANN-L-2E to OFF
a. This keeps EF 7 TRIP annunciator off
5. Insert LOA-TBS011 to CLOSE (this closes DM-28-4)
6. Insert LOA-TBS012 to OPEN (this opens DM-28-3)
7. Insert LOA-TBS013 to OFF (stops SF 1-22)
8. Ensure the TURB BLDG VENT ISOLATION pushbutton on Panel 11R is depressed/reset before beginning JPM
9. Have a copy of 328, completed up to step 5.1.1 (for only section 5)

ILT 14-1 NRC Control Room JPM 7 Page 10 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is shutdown
  • The Turbine Building Ventilation System has been secured
  • All prerequisites to start the Turbine Building Ventilation System have been verified
  • Attachments 328-1, 328-2, 328-3 have been completed Task Cue:

Start the Turbine Building Ventilation System IAW Procedure 328, Turbine Building Heating and Ventilation System, starting at Step 5.1.2 ILT 14-1 NRC Control Room JPM 7 Page 11 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2150201401 Task

Title:

Perform an APRM Gain Adjustment Job Performance Measure No.: NRC Control Room JPM 8 K/A

Reference:

215005 A4.03 (RO 3.2/SRO 3.3)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Reactor Recirculation flow was just adjusted to attain 100% reactor power a short while ago.
  • Reactor power has been steady for the last 5 minutes.
  • Procedure 403 allows bypassing APRM 8.
  • The procedure revision, prerequisites and precautions and limitations have been verified by the Unit Supervisor.
  • APRM 8 is the ONLY APRM that requires an adjustment.

Task Standard:

APRM 8 should indicate 100% + 1% of Core Thermal Power (by meter on Panel 5R) and APRM 8 has been UNBYPASSED on Panel 4F.

Required Materials: None.

General

References:

1. 202.1-9, APRM Gain Adjustment From Heat Balance (Hard Card), revision 148 Initiating Cue:

Perform an APRM Gain Adjustment on APRM 8 IAW Attachment 202.1-9 starting at step 2.

Time Critical Task: NO ILT 14-1 NRC Control Room JPM 8 Page 1 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation Time: 5 minutes ILT 14-1 NRC Control Room JPM 8 Page 2 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Reviews Procedure revision, Prerequisites, and Precautions and Limitations.

Standard: Acknowledges the Initial Conditions state that the procedure revision, prerequisites and precautions and limitations have been verified with the US.

CUE: This was given in the Initial Conditions and the student may initial the step in section 1.0 as completed.

Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 2.1 Allow reactor power to stabilize for at least 2 minutes.

Standard: The student verifies from the Initial Conditions that reactor power has been stabilized for at least 2 minutes.

CUE: The Initial Conditions state that reactor power has been stable for 5 minutes.

Comment:

ILT 14-1 NRC Control Room JPM 8 Page 3 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SAT/UNSAT Performance Step: 4 Procedure Step: 2.2 If allowed by 403, bypass APRM 8.

Standard: Verifies from the Initial Conditions that Bypassing APRM 8 is allowed by Procedure 403.

Bypasses APRM 8 on Panel 4F by placing the APRM BYPASS joystick in the CH 8 position.

CUE: If the applicant begins reviewing Procedure 403, inform them (as stated in the Initial Conditions) 403 has already been reviewed and Bypassing APRM 8 is allowed.

Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 2.3 Pull out the APRM 8 drawer.

Standard: Pulls out APRM Drawer 8 on Panel 5R to allow access to the R10 screw (Gain adjustment screw).

Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 2.4 Turn the gain adjustment pot with a small screwdriver (R10 on calibration and feedback unit) clockwise to raise gain or counterclockwise to lower gain while monitoring APRM output on the APRM 8 drawer.

Standard: Inserts small screwdriver and turns CCW or CW to change APRM power indication.

Comment:

ILT 14-1 NRC Control Room JPM 8 Page 4 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET SAT/UNSAT Performance Step: 7 Procedure Step: 2.5 When output on APRM 8 drawer matches required APRM setting within 1%,

then stop gain adjustment.

Standard: When output on APRM 8 drawer matches required APRM (on PPC Heat Balance) setting within 1%, then stops gain adjustment. With reactor power at 100%, APRM 8 should indicate 100% + 1% of Core Thermal Power by meter indication on Panel 5R.

Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 2.6 Verify the following:

  • FCTR Card Status light is GREEN
  • FCTR Active LEDs are GREEN
  • FCTR Curve Select Display is Zero Standard: Completes verification of FCTR card status light as green, FCTR active LEDs are green, FCTR curve select display as zero CUE: FCTR Card status light and Active LEDs are GREEN FCTR Curve select display is Zero Comment:

SAT/UNSAT ILT 14-1 NRC Control Room JPM 8 Page 5 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 9 Procedure Step: 2.7 Push in Selected drawer since FCTR card indications are indicating correctly Standard: APRM drawer pushed back into panel Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 2.8 Un-bypasses APRM 8.

Standard: Places the APRM 8 BYPASS joystick to the center position.

Comment:

SAT/UNSAT Performance Step: 11 Procedure Step: 2.9 If another APRM channel in the same drawer requires adjustment, then perform the APRM adjustment IAW steps 2.2 through 2.6.

Standard: Determines that no other APRM adjustments are required from the Initial Conditions.

CUE: Student will inform evaluator that APRM 8 Gain has been adjusted.

Comment:

SAT/UNSAT Terminating Cue:

APRM 8 should indicate 100% + 1% of Core Thermal Power (by meter on Panel 5R) and APRM 8 has been UNBYPASSED on Panel 4F.

JPM Stop Time: __________

ILT 14-1 NRC Control Room JPM 8 Page 6 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC Control Room JPM 8 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC Control Room JPM 8 Page 7 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup

1. Reset the simulator to IC-115 or other rated power IC.
2. Change APRM 8 gain so that the APRM reads > 104%.
3. Have a blank copy of Attachment 202.1-9 rev 146, APRM Gain Adjustment From Heat Balance (Hard Card).
4. Ensure Heat Balance is displayed on PPC between Panel 3R and 4R.
5. Ensure APRMs 1 through 7 indicate 100%.
6. Ensure all APRM drawers are fully pushed in and latched.
7. Have a copy of procedure 403 for the students to Bypass APRM 8.
8. Have a copy of Attachment 403-2 which shows APRM bypass is allowed.

ILT 14-1 NRC Control Room JPM 8 Page 8 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • Reactor Recirculation flow was just adjusted to attain 100% reactor power a short while ago.
  • Reactor power has been steady for the last 5 minutes.
  • Procedure 403 allows bypassing APRM 8.
  • The procedure revision, prerequisites and precautions and limitations have been verified by the Unit Supervisor.
  • APRM 8 is the ONLY APRM that requires an adjustment.

Initiating Cue:

Perform an APRM Gain Adjustment on APRM 8 in accordance with Attachment 202.1-9 starting at step 2.

ILT 14-1 NRC Control Room JPM 8 Page 9 of 9

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Facility: Oyster Creek Task No.: 2000501441 Task

Title:

Vent the Scram Air Header Job Performance Measure No.: NRC In-Plant JPM 1 K/A

Reference:

295037 EA1.05 (3.9/4.0)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant was at rated power when a valid RPS scram signal occurred.

Task Standard:

The scram air header has been vented and then restored to normal Required Materials: None.

General

References:

1. EMG-SP21, Alternate Insertion of Control Rods, revision 1 Initiating Cue: Vent the scram air header IAW EMG-SP21, section 4.3 Time Critical Task: NO Validation Time: 2 minutes ILT 14-1 NRC In-Plant JPM 1 Page 1 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 4.3.1 Close Scram Air Header isolation valve V-6-175 (RB 23 SE)

Standard: Closes Scram Air Header isolation valve V-6-175 (RB 23 SE) by rotating the valve operator CW until motion stops Cue: Scram Air Header isolation valve V-6-175 is closed Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 1 Page 2 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 4.3.2 Open Scram Air Header drain valve V-6-409 (RB 23 SE)

Standard: Opens Scram Air Header drain valve V-6-409 (RB 23 SE) by rotating the valve operator CCW until motion stops Cue:

  • Scram Air Header drain valve V-6-409 is open and air is heard rushing out the vent
  • The Control Room notifies you that all control rods indicate full-in Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 4.3.3.1 When control rods are no longer moving in, then perform the following:

1. Close Scram Air Header drain valve V-6-409 (RB 23 SE)

Standard: Closes Scram Air Header drain valve V-6-409 (RB 23 SE) by rotating the valve operator CW until motion stops Cue: Scram Air Header drain valve V-6-409 is closed Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 1 Page 3 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 4.3.3.2 When control rods are no longer moving in, then perform the following:

2. Open Scram Air Header isolation valve V-6-175 (RB 23 SE)

Standard: Opens Scram Air Header isolation valve V-6-175 (RB 23 SE) by rotating the valve operator CCW until motion stops Cue: Scram Air Header isolation valve V-6-175 is open Comment:

SAT/UNSAT Terminating Cue: The scram air header has been vented and then restored to normal JPM Stop Time: ___________

ILT 14-1 NRC In-Plant JPM 1 Page 4 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC In-Plant JPM 1 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC In-Plant JPM 1 Page 5 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Have a copy of EMG-SP21 for the applicant.

ILT 14-1 NRC In-Plant JPM 1 Page 6 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant was at rated power when a valid RPS scram signal occurred.

Task Cue:

Vent the scram air header IAW EMG-SP21, section 4.3 ILT 14-1 NRC In-Plant JPM 1 Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2640101401 Task

Title:

Start Diesel Generator 1 for Peaking Operations Job Performance Measure No.: NRC In-Plant JPM 2 K/A

Reference:

264000 K4.07 (3.3/3.4)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The plant is at rated power.
  • The electrical grid is stable.
  • All prerequisites for starting EDG 1 have been verified.

Task Standard:

EDG 1 is started and loaded to within limits.

Required Materials: None.

General

References:

1. Procedure 341, Emergency Diesel Generator Operation, Revision 110 Initiating Cue:

Start EDG 1 for Peaking Operations IAW Procedure 341, Emergency Diesel Generator Operation, starting at Step 7.3.1.3.

Time Critical Task: NO Validation Time: 20 minutes ILT 14-1 NRC In-Plant JPM 2 Page 1 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Reviews Precautions and Limitations.

Standard: Reviews Precautions and Limitations Comment:

SAT/UNSAT Performance Step: 3 Procedure Step: 7.3.1.3 Place EDG-1 MODE SELECTOR SWITCH in the IDLE position Standard: Places EDG-1 MODE SELECTOR SWITCH in the IDLE position Cue: The EDG-1 MODE SELECTOR SWITCH in the IDLE position Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 2 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 4 Procedure Step: 7.3.1.4 Start EDG-1 by placing the STOP/START SWITCH in the START position Standard: Starts EDG-1 by placing the STOP/START SWITCH in the START position (EDG speed rises)

Cue: The STOP/START SWITCH in the START position. The EDG has started.

The EDG is running at idle speed Comment:

SAT/UNSAT Performance Step: 5 Procedure Step: 7.3.1.5 Place EDG-1 MODE SELECTOR SWITCH in the RUN position Standard: Places EDG-1 MODE SELECTOR SWITCH in the RUN position after about 90 seconds Cue: The EDG-1 MODE SELECTOR SWITCH in the RUN position and the EDG noise has risen.

Note: 90 seconds is not critical Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 3 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 6 Procedure Step: 7.3.1.6 Verify engine speed increases Standard: Verifies engine speed increases Cue: The EDG speed and noise has increased.

Comment:

SAT/UNSAT Performance Step: 7 Procedure Step: 7.3.1.7 Place EDG-1 MODE SELECTOR SWITCH in the EXC position Standard: Places EDG-1 MODE SELECTOR SWITCH in the EXC position Cue: The EDG-1 MODE SELECTOR SWITCH in the EXC position Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 7.3.1.8 Compare EDG-1 output voltage with line voltage using the KILOVOLT METER selecting any GEN or BUS position on the VOLTAGE/FREQUENCY SELECTOR SWITCH Standard: Compares EDG-1 output voltage with line voltage using the KILOVOLT METER selecting any GEN or BUS position on the VOLTAGE/FREQUENCY SELECTOR SWITCH Cue: GEN volts is 3900 volts; BUS volts is 4160 volts Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 4 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 7.3.1.9 Adjust EDG-1 output voltage to be slightly higher than line voltage using the VOLTAGE CONTROL SWITCH Standard: Adjusts EDG-1 output voltage to be slightly higher than line voltage using the VOLTAGE CONTROL SWITCH in the RAISE position Cue: GEN volts is 4200 volts; BUS volts is 4160 volts Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 7.3.1.10.1 Place EDG-1 SYNCHROSCOPE ON/OFF SWITCH in the ON position with the synchroscope key Standard: Places EDG-1 SYNCHROSCOPE ON/OFF SWITCH in the ON position with the synchroscope key. The synchroscope is rotating slowly in the fast direction.

Cue: The EDG-1 SYNCHROSCOPE ON/OFF SWITCH in the ON position and the synchroscope is rotating slowly in the fast direction Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 5 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 7.3.1.10.2 Operate EDG-1 GOVERNOR CONTROL SWITCH so that the synchroscope hand is moving slowly in the fast direction, and the synchronizing lights are pulsing slowly in unison Standard: Confirms the synchroscope is rotating slowly in the fast direction and the synchronizing lights are pulsing slowly in unison Cue: The synchroscope is rotating slowly in the fast direction and the synchronizing lights are pulsing slowly in unison Comment:

SAT/UNSAT Performance Step: 12 Procedure Step: 7.3.1.10.3 Verify EDG-1 output voltage is slightly higher than line voltage Standard: Verifies EDG-1 output voltage is slightly higher than line voltage Cue: GEN volts is 4200 volts; BUS volts is 4160 volts Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 6 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 13 Procedure Step: 7.3.1.10.4 Place EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in one of the following positions; GEN 1-2, GEN 2-3, or GEN 3-1 Standard: Places EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in one of the following positions; GEN 1-2, GEN 2-3, or GEN 3-1 Cue: The EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in one of the following positions; GEN 1-2, GEN 2-3, or GEN 3-1 Comment:

SAT/UNSAT Performance Step: 14 Procedure Step: 7.3.1.10.5 Confirm the synchroscope hand is moving slowly in the fast direction Standard: Confirms the synchroscope hand is moving slowly in the fast direction Cue: The synchroscope hand is moving slowly in the fast direction Comment:

SAT/UNSAT Performance Step: 15 Procedure Step: 7.3.1.10.6 When EDG-1 synchroscope hand reaches the eleven o'clock position, then place EDG-1 BREAKER CONTROL SWITCH in the CLOSED position Standard: When EDG-1 synchroscope hand reaches the eleven o'clock position, then places EDG-1 BREAKER CONTROL SWITCH in the CLOSED position (red light ON; green light OFF; synchroscope remains stable)

Cue: The EDG-1 BREAKER indicates closed Comment:

ILT 14-1 NRC In-Plant JPM 2 Page 7 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information SAT/UNSAT Note: Minimum reactive load is +200 KVARS (lagging). Several repetitive pauses in raising load to switch between KWATTS and KVARS on the KILOWATT/KILOVAR Selector Switch may be required to achieve desired load without dropping below minimum KVARS. The Candidate may check VARS as KW load is rising.

Performance Step: 16 Procedure Step: 7.3.1.10.7 Raise load on EDG-1 to a minimum of 2500 KW by operating the GOVERNOR CONTROL SWITCH in RAISE position Standard: Positions the Ammeter Selector Switch to position 1 or 3 and positions the KILOWATT/KILOVAR Selector Switch to WATTS position to monitor KW Raises load on EDG-1 to a minimum of 2500 KW by operating the GOVERNOR CONTROL SWITCH in RAISE position (KW loading rises)

Position the Ammeter Selector Switch to position 1 or 3 and positions the KILOWATT/KILOVAR Selector Switch to VARS LAG position to monitor VARs Cue: The Ammeter Selector Switch is in position 1 or 3 and the KILOWATT/KILOVAR Selector Switch is in the WATTS position and KW Loading indicates 2700 KW after adjustment The Ammeter Selector Switch is in position 1 or 3 and the KILOWATT/KILOVAR Selector Switch is in VARS LAG position and VARs indicates >300 VAR as KW load is rising. When 2700 KW is obtained, state that VARS indicates 190 VARS.

Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 8 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Note: Step 7.3.1.10.8 and 7.3.1.10.9 are NA Performance Step: 17 Procedure Step: 7.3.1.10.10 If Auxiliary Transformer is supplying 4160V Bus 1C, then adjust EDG-1 VOLTAGE CONTROL SWITCH to control EDG KVAR loading to approximately +1000 KVAR (lagging) with an acceptable range of +200 to

+2000 KVAR (lagging).

Standard: Adjusts EDG-1 VOLTAGE CONTROL SWITCH to control EDG KVAR loading to approximately +1000 KVAR (lagging) with an acceptable range of

+200 to +2000 KVAR (lagging) by placing the switch to RAISE.

Cue: The KVAR loading is +1000 KVAR (lagging) after adjustment Note: This was adjusted in a prior step.

Comment:

SAT/UNSAT Performance Step: 18 Procedure Step: 7.3.1.10.11 Place EDG-1 SYNCHROSCOPE ON/OFF SWITCH in OFF position Standard: Places EDG-1 SYNCHROSCOPE ON/OFF SWITCH in OFF position Cue: The EDG-1 SYNCHROSCOPE ON/OFF SWITCH is in the OFF position Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 2 Page 9 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 19 Procedure Step: 7.3.1.10.12 Place EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in OFF position Standard: Places EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH in OFF position Cue: The EDG-1 VOLTAGE/FREQUENCY SELECTOR SWITCH is in the OFF position Comment:

SAT/UNSAT Performance Step: 20 Procedure Step: 7.3.1.11 Monitor EDG-1 performance IAW Section 9.0 Standard: Monitors EDG-1 performance IAW Section 9.0 Cue: Another Operator will monitor EDG-1 performance IAW Section 9.0 Comment:

SAT/UNSAT Terminating Cue: EDG 1 is started and loaded to within limits JPM Stop Time: ___________

ILT 14-1 NRC In-Plant JPM 2 Page 10 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC In-Plant JPM 2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC In-Plant JPM 2 Page 11 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Setup

1. Have a copy of procedure 341, completed Section 7 up to step 7.3.1.3.

ILT 14-1 NRC In-Plant JPM 2 Page 12 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

  • The plant is at rated power.
  • The electrical grid is stable.
  • All prerequisites for starting EDG 1 have been verified.

Task Cue:

Start EDG 1 for Peaking Operations IAW Procedure 341, Emergency Diesel Generator Operation, starting at Step 7.3.1.3 NO plant manipulations or changes in plant configuration will be made. All actions will be simulated.

ILT 14-1 NRC In-Plant JPM 2 Page 13 of 13

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2010101001 Task

Title:

Line Up to Vent the TORUS through the Hardened Vent Job Performance Measure No.: NRC In-Plant JPM 3 K/A

Reference:

295024 EA1.14 (3.4/3.5)

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • TORUS water level is 173".
  • Drywell pressure is 53 psig.
  • Hydrogen concentration less than 1.5 %.
  • CHRRMS indicates 1 x 103 R/Hr.
  • Exhaust fans 1-5 and 1-7 are operating.

Initiating Cue:

You are being dispatched from the OSC. Radiation Protection is on hand to support.

The US directs you to prepare the Torus to be vented through the hardened vent per EMG-SP35 section 2. You have a set of EO Building Keys.

Required Materials: None General

References:

1. EMG-SP35, Venting the TORUS via the Hardened Vent, Revision 2 Task Standard: The Torus is lined up to be vented via the Hardened Vent.

Time Critical Task: NO Validation Time: 10 minutes ILT 14-1 NRC In-Plant JPM 3 Page 1 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark Performance Step: 1 Provides repeat back of initiating cue.

JPM Start Time: ____________

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

SAT/UNSAT Performance Step: 2 Procedure Step: 2.1 OBTAIN a MB-1 key.

Standard: Obtained a MB-1 key.

CUE: The Initiating Cue states the applicant already has a set of building keys (which includes a MB-1 key)

Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 2.2 VERIFY TORUS level is less than 348 in.

Standard: Verified TORUS level is less than 348 in. (Initial Condition)

CUE: If Control Room Contacted - TORUS Level is 173 Comment:

SAT/UNSAT Performance Step: 4 Procedure Step: 2.3 VERIFY Primary Containment H2 concentration is below minimum detectable (1.5% on H2/O2 Monitor)

Standard: Verified Primary Containment H2 concentration is below minimum detectable (1.5% on H2/O2 Monitor)

(Initial Condition)

CUE: If Control Room Contacted - H2 Concentration < 1.5%

Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 5 Procedure Step: 2.4 VERIFY CHRRMS Channels 1 and 2 are reading below 2 x 104 R/HR Standard: VERIFY CHRRMS Channels 1 and 2 are reading below 2 x 104 R/HR (Initial Condition)

CUE: If Control Room Contacted - CHRRMS Indicates 1X103 R/Hr Comment:

SAT/UNSAT Performance Step: 6 Procedure Step: 2.5 EVACUATE personnel from the Reactor Building SOUND the Reactor Building Evacuation alarm CONTACT Control Room to make evacuation announcement IAW EMG-SP35 Standard: Contacted Control Room to make evacuation announcement Evacuated personnel from the Reactor Building Sounded the Reactor Building Evacuation alarm IAW EMG-SP35 CUE: Reactor Bldg is evacuated Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 4 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 7 Procedure Step: 2.6 CONFIRM at least one Reactor Bldg. or Turbine Bldg. Exhaust Fan is running Standard: Confirmed at least one Reactor Bldg. or Turbine Bldg. Exhaust Fan is running (Initial Condition)

CUE: If Control Room Contacted - Exh Fans 1-5/1-7 are operating Comment:

SAT/UNSAT Performance Step: 8 Procedure Step: 2.7 CONFIRM N2 Purge Isolation Valve V-23-195 closed (Outside Rx Bldg, NE Corner)

Confirmed N2 Purge Isolation Valve V-23-195 closed Standard:

(Outside Rx Bldg, NE Corner)

CUE: V-23-195 is CLOSED Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 9 Procedure Step: 2.8 UNLOCK and CLOSE Nitrogen System Nitrogen Purge Header Isolation Valve V-23-357 (Outside Rx Bldg, NE Corner)

Standard: Unlocked and Closed Nitrogen System Nitrogen Purge Header Isolation Valve V-23-357 (Outside Rx Bldg, NE Corner)

CUE: V-23-357 is CLOSED Comment:

SAT/UNSAT Performance Step: 10 Procedure Step: 2.9 UNLOCK and OPEN the Nitrogen System Stack Isolation Valve V-23-358 (Outside Rx Bldg, NE Corner)

Unlocked and Opened the Nitrogen System Stack Isolation Valve V-23-358 Standard:

(Outside Rx Bldg, NE Corner)

CUE: V-23-358 is OPEN Comment:

SAT/UNSAT ILT 14-1 NRC In-Plant JPM 3 Page 6 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 2.10 INFORM the US that the Torus is ready to be vented via the Hardened Vent Standard: Informed the US that the Torus is ready to be vented via the Hardened Vent Comment:

SAT/UNSAT Terminating Cue: The Torus is ready to be vented via the Hardened Vent.

JPM Stop Time: ___________

ILT 14-1 NRC In-Plant JPM 3 Page 7 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC In-Plant JPM 3 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date:

ILT 14-1 NRC In-Plant JPM 3 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET JPM Setup

1. Provide a copy of EMG-SP35, Venting the TORUS via the Hardened Vent, Revision 2 ILT 14-1 NRC In-Plant JPM 3 Page 9 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET INITIAL CONDITIONS

  • TORUS level is 173".
  • Drywell pressure is 53 psig.
  • Hydrogen concentration less than 1.5 %.
  • CHRRMS indicates 1 x 103 R/Hr.
  • Exhaust fans 1-5 and 1-7 are operating.

INITIATING CUE You are being dispatched from the OSC. Radiation Protection is on hand to support. The US directs you to prepare the Torus to be vented through the hardened vent per EMG-SP35 section 2. You have a set of EO Building Keys.

There will be NO manipulation or change of plant components.

ILT 14-1 NRC In-Plant JPM 3 Page 10 of 10

NRC 2016 Scenario 1 (New)

Scenario Outline Facility: Oyster Creek Scenario No.: 1 Op Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

  • 97% power
  • Risk is Yellow Turnover:
  • Lower power to 95% using recirculation flow IAW 1001.22-3, Core Maneuvering Daily Instruction Sheet.
  • Following the power reduction Backwash A North Condenser IAW procedure 323.6 Event No. Malf. No. Event Type* Event Description 1 N/A R ATC Lower power with Recirc flow SRO BOP 2 N/A N Backwash A North Condenser SRO MAL- C 3 CRD002 ATC A CRD pump trips TS SRO MAL- C BOP 4 ICS002A Isolable Isolation Condenser A tube leak TS SRO MAL- C ATC Respond to a reference leg leak in the A & C GEMAC 5 NSS012E TS SRO RPV level indicators ID13A and ID13C MAL- C BOP 6 TCS010 EPR failure low SRO MAL-CRD001 MAL-CRD010_ ATC/ Respond to B CRD pump to trip and Responds to an 7 1851 C

All HCU accumulator failure MAL-CRD010_

2251 NRC 2016 Scenario 1 Page 1 of 22

NRC 2016 Scenario 1 (New)

SRV-NSS001C MAL- MSIVs close and Safety Valve Lifts after Scram 8 M All NSS013C MAL-NSS013D BKR- BOP Trip of Containment Spray Pump 9 CNS008 C

SRO

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC 2016 Scenario 1 Page 2 of 22

NRC 2016 Scenario 1 (New)

Simulator Summary Event Event Summary 1 The ATC will lower reactor power to approximately 95% with recirculation flow using the Master Recirc Speed Controller. (ATC:

Reactivity Manipulation) 2 The BOP will backwash condenser A North IAW procedure 323.6, Backwashing Condensers. This will require several switch manipulations by the BOP and observe condenser parameters. (BOP:

Normal Evolution) 3 The ATC will respond to a trip of CRD Pump A IAW RAP H-1-c. The ATC will start CRD Pump B. The SRO will review and apply Tech Spec 3.4.D.2. (ATC: Component Malfunction; SRO: Tech Specs) 4 Then A Isolation Condenser develops a tube leak (MAL ICS002A).

Crew enters Rad Release Control and requires manually isolating the A IC (BOP: Component Malfunction; SRO: Tech Specs).

5 The ATC will diagnose a rising RPV water level. Indications of actual RPV water level will rise on Panel 4F and Panel 5F/6F Yarway indications. The ATC will perform actions to stabilize RPV water level IAW ABN-17, Feedwater System Abnormal Conditions. The ATC will take manual control of RPV water level and swap Feedwater Level Control to the alternate water level instrument ID13B. The increased Primary Containment leakage will result in a rise in unidentified leak rate and the SRO will review and apply Tech Spec 3.3.D.2. (ATC:

Instrument Malfunction; SRO: Tech Specs) 6 Rx pressure begins to drop and the crew recognizes that the EPR is failing low. The crew enters ABN-9 and transfers pressure control over to the MPR. (BOP: Component Malfunction) 7 Once Rx pressure is restored Following the EPR failure the B CRD pump will trip and there is no standby pump to start. The Crew will enter ABN-1 and attempt to scram the reactor when two accumulators come in. (ATC/Crew: Component) 8 Upon scramming the US enters RPV control no ATWS. When the Reactor is scrammed a Safety to fail open (SRV-NSS001C) which drives DW temp and Pressure up. The US then enters Primary Containment control (CREW: Major)

NRC 2016 Scenario 1 Page 3 of 22

NRC 2016 Scenario 1 (New) 9 When required the crew attempts to lineup containment spray system two in preparation for reducing containment pressure or temperature and recognizes that containment pump #1 started then tripped and must start the second containment pump in system two to reduce drywell parameters. (BOP: Component Malfunction)

Critical Given an isolable leak outside the Reactor Building , the crew must Task 1 isolate the leak, in accordance with Rad Release control.

Critical Given a loss of all CRD, the crew must insert a manual reactor scram Task 2 in accordance with ABN-1.

Critical The must initiate containment spray to restore and maintain <281of or Task 3 when containment pressure exceeds 12 psig IAW Primary Containment Control.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

2. Malfunctions after EOP entry (1-2) 2 8,9
3. Abnormal events (2-4) 3 5,6,7
4. Major transients (1-2) 1 8
5. EOPs entered/requiring substantive 2 Primary actions (1-2) Containment RPV control No ATWS
6. EOP contingencies requiring substantive 0 N/A actions (0-2)
7. EOP Critical tasks (2-3) 2 4,7,9 NRC 2016 Scenario 1 Page 4 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 1 Event

Description:

Lower reactor power to 95% using recirculation flow Initiation: Following shift turnover Cues: As directed by the SRO following shift turnover Time Position Applicants Actions or Behavior SRO

  • Approves the ReMA and provides to the ATC
  • Directs the ATC to lower power to 95% IAW the Core Maneuvering Daily Instruction Sheet
  • Acts as the reactivity Manager
  • Provides a reactivity brief
  • May notify the Power team when at 95% power ATC
  • Lowers power IAW the Core Maneuvering Daily Instruction Sheet o May review 202.1, section 6.0, Power Reductions o Rotates the MASTER RECIRC SPEED CONTROLLER manual knob CW o Monitors power, level, pressure o Reports to SRO when rated power is reached BOP o Provides second check for the reactivity manipulation Terminus: Reactor power is approximately 95%

BOOTH: If directed by lead evaluator to move to event #2:

- Call as SM to secure from Power reduction and maintain power where it currently is due to maintenance being moved.

Notes/Comments NRC 2016 Scenario 1 Page 5 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 2 Event

Description:

Continue backwashing Main Condenser Half A North Initiation: Reactor power is approximately 95%, or as directed by the Lead Examiner Cues: As directed by the SRO Time Position Applicants Actions or Behavior SRO Directs BOP to backwash A North Condenser IAW procedure 323.6, starting at step 5.1.3.1.

BOP

  • Performs backwash of condenser half A North IAW procedure 323.6, starting at step 5.1.3.1 o Verifies the following:

All condenser valves are in the normal position The inlet & outlet valves for each condenser half are open The backwash valves and the cross connect valves for each condenser are closed May verify the EO is aware of which valves will be operated [ROLE PLAY]

o Places the COND A NORTH BACKWASH CONTROL switch to BACKWASH o After about 10 seconds, places the COND A NORTH CIRC WATER INLET & OUTLET switch to CLOSE o Verifies the following:

V-3-12, COND A NORTH CIRC WATER INLET valve closed V-3-27, COND A NORTH CIRC WATER OUTLET valve closed V-3-18, COND A NORTH BACKWASH CONTROL valve open V-3-24, COND A NORTH CONNECT valve open V-3-28, COND A SOUTH CIRC WATER OUTLET valve closed NRC 2016 Scenario 1 Page 6 of 22

NRC 2016 Scenario 1 (New)

V-3-13, COND A SOUTH CIRC WATER INLET valve open V-3-19, COND A SOUTH BACKWASH CONTROL valve closed o Backwashes for about 3-5 minutes o Monitors the following during backwash:

Condenser Hotwell Level Turbine Exhaust Hood Temperature Condenser Vacuum o Places the COND A NORTH CIRC WATER INLET &

OUTLET switch to OPEN o After about 10 seconds, places the COND A NORTH BACKWASH CONTROL switch to CLOSE o Verifies the following:

V-3-12, COND A NORTH CIRC WATER INLET valve open V-3-27, COND A NORTH CIRC WATER OUTLET valve open V-318, COND A NORTH BACKWASH CONTROL valve closed V-3-13, COND A SOUTH CIRC WATER INLET valve open V-3-28, COND A SOUTH CIRC WATER OUTLET valve open V-3-19, COND A SOUTH BACKWASH CONTROL valve closed V-3-24, COND A CROSS CONNECT valve closed

  • Reports A North condenser backwash is complete ROLE PLAY When told as the EO which backwash valves will be operated, acknowledge the report Terminus: Main condenser backwash is complete Notes/Comments NRC 2016 Scenario 1 Page 7 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 3 Event

Description:

CRD Pump A trips requiring Tech Spec LCO entry (Trigger 1)

Initiation: Backwash of B North Condenser is complete or as directed by the Lead Examiner.

Cues: Annunciator H1c, PUMP A OL; H7c, CHARG WTR PRESS LO; COOLING WATER FLOW, CLG WTR/REACTOR P, DRV WTR/REACTOR P indicate downscale; CRD Pump A breaker open Time Position Applicants Actions or Behavior ATC

  • Responds to annunciator H1c, PUMP A TRIP o Reports CRD Pump A tripped o Dispatches EO to investigate pump/breaker [ROLE PLAY]

o Starts CRD Pump B by placing CRD PUMP NC08B switch to START o Ensures CRD parameters return to normal bands o Reports CRD Pump B running with CRD indications return to normal SRO

  • Notifies SM/WWM about the pump trip
  • Reviews and applies Tech Spec 3.4.D.2 o If one CRD hydraulic pump becomes inoperable when the reactor water temperature is above 212 ºF, the reactor may remain in operation for a period not to exceed 7 days provided the second CRD hydraulic pump is operating and is checked at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. If this condition cannot be met, the reactor water temperature shall be reduced to less than 212 ºF ROLE PLAY As the EO investigating the CRD Pump A trip, wait 1 minute and report the pump tripped on overload.

- If asked status of B CRD pump start

- Report Good start on B CRD pump Terminus: CRD Pump B is in service and the SRO has addressed Tech Specs Notes/Comments NRC 2016 Scenario 1 Page 8 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 4 Event

Description:

A Isolation condenser Tube leak (TRIGGER 3)

Initiation: Standby CRD pump running and T.S determination has been made or as directed by the Lead Examiner.

Cues: Rising levels in A shell level and temperature, RAP-10F-1-k, RAP-C6a Time Position Applicants Actions or Behavior CREW

  • Recognizes Area Rad Monitor C-3 is alarming.
  • Recognizes high level in A IC shell.
  • Recognizes high shell temperature
  • Makes update of Tube leak in A IC ROLE PLAY: 3 minute after inserting the leak or as directed by the lead evaluator:

Report as EO from Boiler House that steam is coming out of A IC vents to the yard.

SRO

  • Enters Radioactivity Release Control
  • Directs isolating A Isolation Condenser
  • Per Tech Spec 3.8, determines that the plant may continue operation for 7 days.

BOP

  • Reports Area Rad monitors levels
  • Isolates A Isolation Condenser CRITICAL TASK 1 Terminus: A IC is isolated and T.S declaration is made Notes/Comments NRC 2016 Scenario 1 Page 9 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 5 Event

Description:

Responds to a leak in the common variable leg to RPV water level instruments ID13A and ID13C (TRIGGER 5)

Initiation: Isolation condenser is isolated or as directed by the Lead Examiner Cues: ID13A and ID13C indication lowers; Other RPV water level indicators rising; Drywell pressure, temperature, unidentified leakage rising Time Position Applicants Actions or Behavior ATC

  • Reports Indicated RPV water level lowering on NR GEMACs ID13A and ID13C, with RPV water level rising on all other available RPV water level instruments
  • Reports small rise in Drywell pressure, temperature and Drywell unidentified leak rate
  • Performs ABN-17, Feedwater System Abnormal Conditions OR ABN-59, RPV Level Instrument Failures (same actions in both ABNs) o Places the MASTER FEEDWATER LEVEL CONTROLLER in manual by pressing the AUTO/MAN pushbutton o Confirms Feedwater flow is approximately equal to steam flow Lowers feedwater flow by turning the manual knob on the MASTER FEEDWATER LEVEL CONTROLLER CCW to match TOTAL STEAM FLOW and TOTAL FEEDWATER FLOW o Places the LEVEL TRANSMITTER SELECTOR to the B position o Selects the S display on the MASTER FEEDWATER LEVEL CONTROLLER o Matches the S display to the P display by turning the manual knob on the MASTER FEEDWATER LEVEL CONTROLLER o When the deviation = 0 (S = P; Y = 0), then places the turning the manual knob on the MASTER FEEDWATER LEVEL CONTROLLER in AUTO o Monitors RPV water level and Feedwater flow NRC 2016 Scenario 1 Page 10 of 22

NRC 2016 Scenario 1 (New) o Maintains RPV water level at 160 or as directed by the US Reports RPV water level transmitters swapped, Feedwater in auto and controlling.

BOP

  • May perform Drywell venting IAW attachment 312.11-10 or ABN-63, if directed o Opens Torus vent valve V-28-47 o Opens Torus vent valve V-28-18 o Monitors DW pressure
  • May perform Drywell venting IAW attachment 312.11-12 or ABN-63, if directed o Opens Drywell vent valve V-23-21 o Opens Drywell vent valve V-23-22
  • May maximize cooling and start 5th drywell fan IAW ABN-63
  • Directs entry into ABN-17, Feedwater System Abnormal Conditions OR ABN-59, RPV Level Instrument Failures
  • Notifies SM/WWM for repair/investigation of RPV water level instruments ID13A and ID13C
  • May direct Drywell venting and maximizing cooling IAW 312.11-10 or 312.11-12 or ABN-63
  • Enters Tech Spec 3.3.D.1 for 2 gpm increase in unidentified leakage in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period
  • With the reactor coolant system leakage greater than the limits in 3.3.D.1.a or b above, reduce the leakage rate to within the acceptable limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in the cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Terminus: RPV water level transmitters have been swapped, Feedwater is in auto and is controlling, and the SRO has reviewed/applied the Tech Specs NRC 2016 Scenario 1 Page 11 of 22

NRC 2016 Scenario 1 (New)

Notes/Comments NRC 2016 Scenario 1 Page 12 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 6 Event

Description:

EPR fails low requiring transfer to MPR (TRIGGER 7)

Initiation: Rx water level has been stabilized or as directed by the Lead Examiner Cues: Rx pressure lowers Time Position Applicants Actions or Behavior CREW

  • Recognizes lowering Rx pressure ATC
  • Monitors critical parameters
  • Reports DW pressure to crew US
  • Directs entry into ABN-9
  • Refers to procedure 202.1 for limitations on power with one pressure regulator out of service BOP
  • Makes update EPR failure
  • Performs ABN-9 actions
  • Transfers RPV pressure control to MPR by
  • Lowering MPR setpoint until MPR takes over
  • Verifies EPR controlling light off
  • Turns off EPR power switch to off
  • Verifies alarm Q6a is recieved
  • Slowly raises Rx pressure back to normal band with MPR as directed by US by
  • Slowly raising MPR setpoint until pressure back in band Terminus: The MPR is placed in service and pressure band is back in band Notes/Comments NRC 2016 Scenario 1 Page 13 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 7 Event

Description:

Trip of B CRD pump and two accumulator alarms come in forcing Rx scram B (TRIGGER 9)

Initiation: MPR is controlling pressure in band, or as directed by the Lead Examiner Cues: RAP H-7-c, RAP H-8-c, RAP H-7-a, CRD hydraulic parameters drop to 0 Time Position Applicants Actions or Behavior Crew

  • Refers to Raps
  • Determines B CRD pump has tripped and will not restart.
  • Makes update that B CRD pump cannot be restarted.
  • Directs EOs to investigate pump and breakers for CRD pumps.

SRO

  • Sets scram criteria when 2 HCU alarms come in Role BOOTH: If directed to investigate CRD pump as EO 3 minutes later play
  • Report B CRD breaker tripped on Overload.

ATC

  • PLACE the Reactor Mode Switch in SHUTDOWN position.
  • VERIFY that all rods are fully inserted (at or beyond position 04).
  • VERIFY that reactor power is lowering.
  • UPDATES US that immediate scram actions are complete.
  • ENTERS RPV CONTROL No-ATWS
  • DIRECT URO to maintain RPV water level 138 to 160 TAF using feed/condensate. Uses SP-2.
  • When RPV level begins to rise Trips two feed pumps, places MFRVs to manual and closes them when
  • CONFIRMs main turbine tripped, GC1 and GD1 OPEN, generator field breaker OPEN, S1A and S1B closed
  • EXECUTE the following RPV Control - No ATWS steps when directed:

NRC 2016 Scenario 1 Page 14 of 22

NRC 2016 Scenario 1 (New)

URO

  • MAINTAIN RPV level between 138 and 160 in. with SP-2.

Terminus: Rx is scrammed and all rods in Notes/Comments NRC 2016 Scenario 1 Page 15 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 8 Event

Description:

MSIVs close and Safety Valve Lifts after Scram (TRIGGER 11)

Initiation: When Reactor is scrammed and scram pushbuttons are pressed Cues: MSIV position indication Drywell pressure and temperature rise, safety acoustic high Time Position Applicants Actions or Behavior Crew

  • Recognizes that outboard MSIVs close and Safety valve is stuck open SRO
  • Enters Primary Containment Control when DW pressure exceeds 3.0 psig and directs the following operator actions:
  • Continues pressure control to B Isolation condenser and EMRVs per SP-11/12
  • When required directs maximizing drywell cooling per SP-27
  • Directs H 2 /O 2 IAW SP-39 when applicable
  • Monitor bulk drywell temperature.
  • Maximize drywell cooling per SP-27 when directed
  • Initiate H 2 /O 2 IAW SP-39 when directed.
  • Evaluates the usability of RPV water level instrumentation per SP-28 when directed.

BOP

  • Maintains RPV pressure as directed per SP-11 using B isolation and EMRVs as necessary with SP-12 US
  • Directs lineup of DW sprays before bulk drywell temperature reaches 281°F or DW or Torus pressure reaches 12 psig per SP-29.

RO

  • Performs SP-29 for lineup of DW spray
  • Confirms DW Fans and Recirc pumps are tripped

NRC 2016 Scenario 1 Page 16 of 22

NRC 2016 Scenario 1 (New)

Notes/Comments NRC 2016 Scenario 1 Page 17 of 22

NRC 2016 Scenario 1 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 1 Event No.: 9 Event

Description:

Trip of Containment Spray Pump (TRIGGER 13 or 15)

Initiation: When containment spray pump is started to reduce Drywell parameters Cues: Pump Red light off, Containment spray flow drops to 0 Time Position Applicants Actions or Behavior US

  • Directs spraying to the drywell IAW SP-29 when above 12 psig in the drywell RO
  • Once directed to spray the DW
  • Places system mode select to DW spray position
  • Verifies valves reposition
  • Starts ESW pump by turning switch

BOOTH If 1-3 Containment Spray pump running

  • INSERT: Trigger 15 RO
  • May start second ESW pump by turning switch CRITICAL TASK 3
  • Verifies system parameters

Terminus: Drywell parameters are in band along with Rx pressure and Level.

Final EAL FA Any Loss or Potential Loss of either the Fuel Clad or RCS.

Call Lost Reactor Coolant System Barrier.

NRC 2016 Scenario 1 Page 18 of 22

NRC 2016 Scenario 1 (New)

Procedures Used Event Procedure 1

  • 202.1
  • 301.2 2
  • 323.6 3
  • ABN-17
  • ABN-59
  • 312.11 6
  • ABN-9
  • 202.1 7
  • RPV Control No-ATWS
  • EMG-SP2 8
  • EMG-SP11
  • EMG-SP12
  • EMG-SP1
  • EMG-SP39
  • EMG-SP29
  • EMG-SP27 9
  • EMG-SP29 NRC 2016 Scenario 1 Page 19 of 22

NRC 2016 Scenario 1 (New)

Simulator Setup

1. Reset to IC-40 (bwr-2)
2. Lower power to 97%
3. Have a copy of 202.1 and 301.2 for the applicants
4. Have a Copy of 323.6 for applicants
5. Hang tags on Containment Spray system 1
6. Protect Containment Spray system 2
7. Risk is Yellow Event Trigger Malfunction Containment Spray System 1 Tag Out Preset n/a LOA-CNS054, rack out LOA-CNS051, rack out VLV-CNS002, close BKR-CNS007, fail control fuse BKR-CNS005, fail control fuse 1 NA NA 2 N/A N/A 3 T1 BKR-CRD002 to TRIP This trips CRD Pump A 4 T3 MAL-ICS002A, 5%, ramp 120 seconds A IC tube leak occurs 5 T5 MAL- NSS012E to 2% over a 900 Sec ramp This places a leak in the common variable leg to NR GEMAC water level instruments ID13A and ID13C (this also inputs into FWLC).

6 T7 MAL-TCS010, 900 psig, 60 sec ramp Fails EPR setpoint to 900 psig 7 T9 BKR-CRD001 , Trip trips "B" CRD pump MAL-CRD010_1851, 60 sec delay HCU 1851 accumulator alarm MAL-CRD010_2251, 100 sec delay HCU 2251 accumulator alarm NRC 2016 Scenario 1 Page 20 of 22

NRC 2016 Scenario 1 (New) 8 MAL-NSS013C, 0 Closes MSIVs T11 MAL-NSS013D, 0 Closes MSIVs SRV-NSS001C, 25% , ramp 200 seconds Lifts Safety Valve 25% open, 9 T13 If 1-3 containment spray pump running BRK-CNS008, Trip Trips 1-3 containment Spray pump T15 If 1-4 Containment Spray pump running BKR-CNS006, Trip Trips 1-3 containment Spray pump NRC 2016 Scenario 1 Page 21 of 22

NRC 2016 Scenario 1 (New)

Shift Turnover Current plant conditions:

  • 97% power
  • Risk is Yellow Shift Activities
  • Lower power to 95% using recirculation flow IAW 1001.22-3, Core Maneuvering Daily Instruction Sheet.
  • Following the power reduction Backwash A North Condenser IAW procedure 323.6 NRC 2016 Scenario 1 Page 22 of 22

NRC 2016 Scenario 2 (New)

Scenario Outline Facility: Oyster Creek Scenario No.: 2 Op Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

  • 100% power
  • Air Compressor #3 is tagged OOS
  • EDG #2 Out of service Turnover:
  • Diesel Generator #2 has been out of service for 2 days due to failure to start during the load test. It is scheduled to be returned to service the next day. The diesel load test for #1 diesel is due next shift.
  • Air Compressor #3 is OOS for troubleshooting due to failure to start.
  • Swap RBCCW pumps IAW 309.2 Event No. Malf. No. Event Type* Event Description 1 N BOP, N/A Swap RBCCW pumps SRO RWCU isolable leak (failure of one isolation valve)

MAL- C BOP, 2 EMG-3200.11, Secondary Containment Control RCU013 TS SRO T.S. 3.5 MAL- ALL Loss of VMCC 1B2 C

3 EDS004 ABN-51, Loss of VMCC 1B2 B TS T.S.-

SRO T.S. 3.7 MAL- ATC, CRD Flow Control Failure 4 CRD001 C SRO A ABN-6, Control Rod Malfunctions MAL-OGS003 C OFF-Gas Deflagration/ with condenser vacuum leak 5 ALL ABN-25, OFF-Gas Deflagration MAL- R ABN-14, Loss of Condenser Vacuum CFW017 NRC 2016 Scenario 2 Page 1 of 26

NRC 2016 Scenario 2 (New)

MAL-GEA005 Loss of Stator Cooling A C ALL 6 ABN-11 Loss of Generator Stator Cooling MAL-GEA005 EMG-3200.01A RPV control No-ATWS B

CAEP M 7 ATWS.C Electric ATWS ALL AE EMG-3200.01B RPV control-With ATWS MAL-TCS006 D C BOP, Failure of Turbine Bypass Fails 8

Through SRO EMG-3200.01B, RPV control w/atws TCS006I

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC 2016 Scenario 2 Page 2 of 26

NRC 2016 Scenario 2 (New)

Simulator Summary Event Event Summary 1 The BOP will swap RBCCW pumps IAW 309.2, Reactor Building Closed Cooling Water System, Section 15. (BOP: Normal Evolution) 2 A RWCU system break will occur with failure of cleanup to automatically isolate. The crew will enter secondary containment control and investigate radiation levels and temperatures in Rx Building. The RWCU HELB alarms will come in and the crew will manually attempt to isolate cleanup but will be unable to close cleanup isolation valves V-16-1. The US will determine T.S applicability IAW section 3.5. (BOP: Component Malfunction; SRO: Tech Specs) 3 The crew will respond to the trip of VMCC 1B2 and enter ABN-51, Loss of VMCC 1B2. The BOP will restore power to PSP-2 and the ATC will reset the 1/2 scram. The SRO will review TS 3.7 and enter a cold shutdown LCO. (BOP: Component Malfunction; SRO: Tech Specs) 4 The ATC will respond to in-service CRD Flow Control Valve failing closed. The ATC will swap Flow Control Valves IAW procedure 302.1, Control Rod Drive System. (ATC: Component Malfunction) 5 This is followed by an Off-Gas deflagration the isolates off-gas. Once the Off-Gas alarms clear the crew confirms no damage to plant and reset Off-Gas system. Once the Off-Gas system is reset a small vacuum leak occurs forcing the crew to reduce power until vacuum recovers (ATC: Component Malfunction, BOP: Component Malfunction) 6 The running Stator Water Cooling Pump will trip and ABN-11 will be entered. The standby Stator Water Cooling Pump is not available since it was powered from Bus 1B1 and therefore all stator water cooling is lost and a turbine runback will occur. IAW the ABN, when the runback occurs, the ATC will insert a manual scram. (ATC: Component) 7 The Crew will diagnose an electric ATWS and the SRO will direct entry into RPV Control - with ATWS EOP. The ATC will perform actions to insert control rods and the BOP will perform actions to control Torus water temperature and RPV water level. (Major Evolution) (PRA)

NRC 2016 Scenario 2 Page 3 of 26

NRC 2016 Scenario 2 (New) 8 While the crew Terminates and Prevents injection IAW SP-17, the bypass valves will go closed forcing the crew to augment Rx pressure control with Isolation Condensers and EMRVs for pressure control (Component Failure After EOP)

Critical Given a failure to scram, the crew must terminate and prevent injection Task 1 in accordance with EOP SP-17 Critical Given a failure to scram, the crew must recommence injection to the Task 2 reactor in accordance with EOP SP-19.

Critical Given a failure to scram, the crew must vent the scram air header in Task 3 accordance with EOP SP-21 Critical Given an isolable leak from RWCU, the crew must isolate the RWCU system Task 4 in accordance with secondary Containment Control ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

1. Malfunctions after EOP entry (1-2) 2 7,8
2. Abnormal events (2-4) 4 3,4,5,6
3. Major transients (1-2) 1 7
4. EOPs entered/requiring substantive 1 RPV control actions (1-2) No-ATWS
5. EOP contingencies requiring substantive 1 RPV Control actions (0-2) W/ATWS
6. EOP Critical tasks (2-3) 4 2,7,8 NRC 2016 Scenario 2 Page 4 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 1 Event

Description:

Swap RBCCW Pumps Initiation: Following shift turnover Cues: As directed by the SRO following shift turnover Time Position Applicants Actions or Behavior SRO

  • Directs the EO to open the RBCCW Pump 1 Casing Vent valve V-5-511 until a steady stream is established, then close the valve [ROLE PLAY 1]
  • Starts the RBCCW Pump 1 by placing its control switch to the START position [ROLE PLAY 2]
  • Verifies the RBCCW Pump 1 ON light lit
  • Verifies proper pump discharge pressure
  • Immediately stops RBCCW Pump 2 by placing its control switch to the STOP position
  • Monitors plant parameters ROLE 1)When asked to open RBCCW Pump 1 vent valve V-5-511, state that you PLAY have opened the valve, established a steady stream, then closed the valve (NO Booth actions are required).

2)WHEN RBCCW Pump 1 is started, report a good start on RBCCW Pump 1 Terminus: RBCCW Pumps have been swapped IAW 309.2 Notes/Comments NRC 2016 Scenario 2 Page 5 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 2 Event

Description:

Respond to isolable Leak in the RWCU System with a failure of one isolation valves (TRIGGER 1)

Initiation: When RBCCW pumps are swapped or as directed by the Lead Examiner.

Cues: Annunciators L6c, RB P LOW; D1d, D2d, RWCU HELB I/II; D8d, CU ROOM TEMP HI; 10F1k, AREA MON HI; 10F3k, CU SYS AREA HI Time Position Applicants Actions or Behavior BOP

  • Makes update that RB D/P alarm is in
  • Makes update on RB D/P pressure
  • Monitors Reactor building area temperatures and Radiation levels when directed
  • Reports that RWCU System should have isolated
  • Attempts to close RWCU valves V-16-1, V-16-14, V-16-61 with their control switches CRITICAL TASK 4
  • V-16-14 and V-16-61 Closed
  • Reports valves V-16-14 and V-16-61 did close
  • Reports the valve V-1-6-1 will not close Role Play BOOTH - If directed to investigate for leak around Cleanup
  • Report - Steam is coming out of the cleanup cage SRO
  • Directs investigating cause of RB D/P alarm
  • Directs attaining radiation levels and area temperatures in the Rx Building.
  • Directs isolating RWCU when determined system has developed a leak.
  • Refers to T.S. 3.5 for applicability and determines that V 14 and V-16-2 are closed and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> must be deactivated to met T.S 3.5.

ATC

  • Monitors 4F parameters and ensures 4F critical parameters stay in band
  • Lowers power with recirc if Rx power goes above license limit Role Play BOOTH - If directed to restore RBCCW temps back in band
  • Adjust RBCCW parameters to restore DW parameters back in band using RBCCW simulator PI&D.

NRC 2016 Scenario 2 Page 6 of 26

NRC 2016 Scenario 2 (New)

Terminus: RWCU is isolated and the SRO has addressed Tech Specs Notes/Comments NRC 2016 Scenario 2 Page 7 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 3 Event

Description:

Respond to trip of VMCC 1B2 (TRIGGER 3)

Initiation: When RWCU leak is isolated or as directed by the Lead Examiner Cues: Annunciators G3c, RPS MG SET 2 TRIP; G1c, SCRAM CONTACTOR OPEN; 9XF4a, PROT SYS PNL 2 PWR LOST; 9XF5c, CIP-3 INV AC INP LOST Time Position Applicants Actions or Behavior BOP

  • Recognizes and reports loss of VMCC 1B2
  • Performs ABN-51
  • Confirms CIP-3 INV AC INP LOST (9XF-5-c) alarm received
  • Verifies the Trans Output green Off light is lit on Panel 7R
  • Restores power to PSP-2 by placing the Power Select switch in the TRANS position
  • Resets the following:
  • APRM flow converters (3R, 5R)
  • NOTE: The following are simulated photographs. The candidate can simulate and assume indications are as expected.
  • Resets the INOP status LED on APRM FCTR cards
  • Verifies status LED on FCTR card is GREEN
  • Verifies Curve Select Display is 0

NRC 2016 Scenario 2 (New)

  • Informs the US the following valves inoperable (1F/2F)

IAW Tech Spec 3.7 and 3.5.A.3 (only if B Battery is unavailable - it will begin discharging but will be available for several hours)

  • V-14-31, DC Steam Inlet Valve to A Condenser
  • V-14-34, DC Condensate Return Valve from A Condenser
  • V-16-2, Inlet Isolation Valve to Cleanup Auxiliary Pump
  • V-16-14, Clean-Up Inlet Isolation Valve
  • Informs the US the B Battery is INOPERABLE as soon as it begins discharging
  • Monitors 125 VDC B Bus Voltage
  • Reduces loads as directed by the US utilizing the B Battery Load List
  • Monitors 125 VDC A Bus Voltage
  • Verifies the following alarms are received:
  • Confirms one Fire Diesel Pump is operating in MANUAL mode and the other Fire Diesel Pump in AUTO mode
  • Directs the EO to investigate the loss of VMCC 1B2
  • Notifies the Director of Operations and the WWM
  • Reports ABN-51 is complete Roleplay BOOTH: When directed to investigate loss of VMCC-1B2
  • Report VMCC-1B2 breaker is open and has an acrid order with no smoke and no fire.

FLOOR: When operator verifies LED on FCTR card is green

  • Cue: FCTR card is green FLOOR: When operator verifies Curve select display is 0
  • Cue: Curve Select displays 0 NRC 2016 Scenario 2 Page 9 of 26

NRC 2016 Scenario 2 (New)

SRO

  • Directs entry into ABN-51
  • Notifies SM/WWM about the loss of VMCC 1B2
  • Declares B Battery inoperable as soon as it begins to discharge
  • The reactor shall be PLACED IN the COLD SHUTDOWN CONDITION if the availability of power falls below that required by Specification A above
  • V-14-31, DC Steam Inlet Valve to A Condenser
  • V-14-34, DC Condensate Return Valve from A Condenser
  • V-16-2, Inlet Isolation Valve to Cleanup Auxiliary Pump
  • V-16-14, Clean-Up Inlet Isolation Valve ATC
  • Makes plant announcement of entry into ABN-51
  • Following restoration of RPS-2, resets the following:
  • Main Steam Isolation signal BOOTH: AFTER the ATC resets the 1/2 scram, insert CAEP ATWS for Event 6 Terminus: ABN-51 actions are complete and the SRO has reviewed/applied Tech Specs 3.7.B and 3.5.A.3 Notes/Comments NRC 2016 Scenario 2 Page 10 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 4 Event

Description:

Respond to CRD Flow Control Valve failed closed (TRIGGER 5)

Initiation: RWCU is isolated and T.S determination has been made or as directed by the Lead Examiner.

Cues: Annunciator H5c, CRD HIGH TEMP; DRIVE WATER FLOW, COOLING WATER FLOW, CLG WTR/REACTOR P, & DRIVE WTR/REACTOR P go downscale Time Position Applicants Actions or Behavior ATC

  • Reports abnormal CRD indications.
  • Reports the CRD FCV (NC30A) indicates closed.
  • Directs the EO to investigate the failed CRD FCV [ROLE PLAY 1].
  • Enters ABN-6, Control Rod Malfunctions, section 13, Flow Control Valve NC-30A/B Fails Closed.
  • Places CRD FCV NC30B in service IAW procedure 302.1, section 6.3.3.
  • Places the CRD FLOW CONTROLLER in MAN.
  • Directs the EO to open the standby FCV inlet/outlet valves [ROLE PLAY 2].
  • Directs the EO to place the 4-Way Valve in position to supply both controllers [ROLE PLAY 3].
  • Places the CRD FLOW CONTROL VALVES switch to the B position.
  • Directs the EO to place the 4-Way Valve in position to supply the in-service controller [ROLE PLAY 4].
  • Verifies normal CRD indications.
  • Places the CRD FLOW CONTROLLER in AUTO.
  • Directs the EO to close the failed FCV inlet/outlet valves [ROLE PLAY 5].
  • Reports the standby CRD FCV is in service and indications are normal.

BOP

  • Announces entry into ABN-6, Control Rod Malfunctions, due to CRD FCV NC30A failing closed.

NRC 2016 Scenario 2 Page 11 of 26

NRC 2016 Scenario 2 (New)

  • May check CRD Temperatures on Panel 8R and report there are several control rods with high temperatures.

SRO

  • Directs entry into ABN-6, Control Rod Malfunctions, due to CRD FCV NC30A failing closed.
  • Directs swapping CRD FCVs IAW procedure 302.1, section 6.3.3.
  • Notifies the SM/WWM about the failed CRD FCV.

ROLE 1. When/if asked as the EO to investigate the in-service CRD FCV (NC30A),

PLAY report that it is closed, was leaking air badly, and that you have isolated the air supply to the valve.

2. (Step 6.3.3.1.1.2.b) When/if asked as the EO to open the standby CRD FCV inlet/outlet valves, insert TRIGGER 7 and report the valves OPEN (V-15-18, V-15-19).
3. (Step 6.3.3.1.1.3) When/if asked as the EO to place the 4-Way Valve in position to supply both controllers, state it is in the position to supply both controller (NO booth actions are required).
4. (Step 6.3.3.1.1.5) When/if asked as the EO to place the 4-Way Valve in position to supply the in-service controller state it is in the position to supply NC30B (NO booth actions are required).
5. (Step 6.3.3.1.1.8.a) When/if asked as the EO to close the failed FCV inlet/outlet valves, state the valves are closed (Insert LOA-CRD009 and LOA-CRD010 to 0) (closes V-15-16, V-15-17).

Terminus: CRD FCV NC30B is in service and CRD parameters indicate normal.

Notes/Comments NRC 2016 Scenario 2 Page 12 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 5 Event

Description:

OFF Gas Deflagration/ loss of vacuum (TRIGGER 9)

Initiation: CRD flow controller swapped or as directed by the Lead Examiner (booth Look ahead): Delete malfunction once alarms come in Cues: RAP-10XF3d, 10F1a, 10F2a, RAP10F1b, 10F2b Time Position Applicants Actions or Behavior BOP Performs actions IAW ABN-25

  • Confirms V-267-005 closed
  • Places Off-gas drain valves selector switch to close
  • Sends EO to investigate Off-Gas building per RAP-10XF3d
  • Verifies Off-Gas inlet isolation valves closed
  • Verifies V-7-31 open
  • Determines cause of system isolation
  • Checks for proper system purge
  • Verifies off-gas press and temp alarms clear and resets Off-gas isolation
  • Confirms V-7-1 through 6 open and off-gas line flow is established Performs actions IAW ABN-14
  • Makes update that vacuum is recovering after power reduction
  • Confirms Circ water pumps are operating
  • Confirms SJAEs are operating properly
  • Confirms Gland seal system operating properly
  • Confirms Vacuum breaker is closed
  • Confirms SJAE drain pumps operating properly BOOTH Once OFF-Gas isolation act 1 and 2 along with temp and pressure alarms come in DELETE
  • DMF MAL-OGS003 (Explosion in off gas piping)

Role Play: AS RBEO Report: I am out near the stack and just heard a loud bang. I dont see any visible damage NRC 2016 Scenario 2 Page 13 of 26

NRC 2016 Scenario 2 (New)

Role Play: If asked to investigate Off-Gas:

Report: No visible damage to equipment or building and no sign of fire or smoke.

Once OFF-Gas has been reset INSERT

  • Trigger 11 (MAL-CFW017)

Once crew begins to lower power with Recirc

  • Insert MAL-CFW017 to 0 CREW Makes update that vacuum is degrading after OFF-Gas reset ATC Reduces power with the master recirc flow controller SRO
  • Directs entry into ABN-25
  • Directs entry into ABN-14 Terminus: Rx power has been lowered to stop vacuum reduction Notes/Comments NRC 2016 Scenario 2 Page 14 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 6 Event

Description:

Loss of all Stator Cooling Water requires manual scram (Trigger 13)

Initiation: Rx power has been lowered to stop vacuum reduction or as directed by the Lead Examiner Cues: Annunciator R6c, STATOR CLG TROUBLE; Turbine runback with generator electric lowering and Turbine Bypass Valves opening Time Position Applicants Actions or Behavior BOP

  • Directs EO to investigate the alarm [ROLE PLAY]
  • Directs entry into ABN-11
  • Directs the ATC to manually scram the reactor when the turbine runback is noticed, and to enter ABN-1
  • Manually scrams the reactor by pressing MANUAL SCRAM BUS 1 and BUS 2 pushbuttons and places REACTOR MODE SELECTOR switch in SHUTDOWN
  • Pushes ARI button
  • Bypasses ROPS
  • Reduces Recirc pumps to minimum ROLE When directed as the EO to investigate the stator cooling alarm, report PLAY that no stator cooling water pumps are running Terminus: The reactor has been manually scrammed and the ATWS has been recognized Notes/Comments NRC 2016 Scenario 2 Page 15 of 26

NRC 2016 Scenario 2 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 2 Event No.: 7/8 Event

Description:

Respond to an ATWS with reactor power > 2%; Bypass valves shut Initiation: inserted a manual scram, and have recognized ATWS conditions or as directed by the Lead Examiner Cues: The reactor has failed to scram and is in an electrical ATWS condition, all rods still out, power >50%

Time Position Applicants Actions or Behavior ATC/

  • Reports reactor power Crew
  • Determines the ATWS is electric
  • Trips all Recirculation Pumps when directed with the DRIVE MOTOR switches to STOP
  • May request to close V-15-52, Charging Header Isolation [ROLE PLAY]

CRITICAL TASK 3

  • Determines electrical ATWS
  • Confirms all available CRD pumps are running
  • Places Reactor Mode Switch in REFUEL
  • Closes CRD DRIVE WATER PRESSURE CONTROL NC18 to maximize CRD drive water differential pressure
  • Drives Cram Array first then normal patern ROLE PLAY: If requested to close V-15-52, INSERT LOA-CRD024 to 0, and report V-15-52 is closed ROLE PLAY: As the EO directed to vent the scram air header, acknowledge the request.

NRC 2016 Scenario 2 Page 16 of 26

NRC 2016 Scenario 2 (New)

NOTE: The crew may de-energize RPS by opening the RPS 100amp breakers when the MSIVs go closed, or after the crew has directed an EO to vent the scram air header, the Lead Examiner may direct the booth to vent the scram air header by inserting Trigger 7.

SRO

  • Confirms ARI initiated
  • Directs ROPS bypassed
  • Directs all Recirculation Pumps tripped
  • May direct initiation of SLC IAW SP-22, Initiating the Liquid Poison System
  • Directs SP-1, Confirmation of Automatic Initiation and Isolations
  • Directs ADS bypassed
  • Directs SP-16, Bypassing MSIV Lo-Lo Level Isolation Interlocks and the RBCCW Interlocks
  • Waits until MSIV isolations are bypassed, then directs terminate and prevent RPV injection IAW SP-17
  • Directs augmenting pressure control with EMRVs when Bypass valves close.
  • Directs RPV water level below -20 to 30 IAW SP-19, Feedwater/Condensate and CRD Operation
  • Directs Torus Cooling IAW Support Procedure 25
  • Directs RPV water level 138 - 175 using SP-2/3(FW)

BOOTH: When Core Spray pumps are in pull to lock during SP-17 fault bypass valves INSERT: TRIGGER 15 BOP/

  • Places ADS TIMERS to BYPASS
  • Obtains four (4) bypass plugs NRC 2016 Scenario 2 Page 17 of 26

NRC 2016 Scenario 2 (New)

  • Opens the EOP BYPASS PLUGS panel in the rear of Panel 6R INSERT a bypass plug in position BP1 INSERT a bypass plug in position BP2
  • Opens the EOP BYPASS PLUGS panel in the rear of Panel 7R INSERT a bypass plug in position BP1 INSERT a bypass plug in position BP2
  • Places the ISOL SIGNAL BYPASS V-6-395 switch in the BYPASS position
  • Informs the Unit Supervisor that the MSIV LO-LO Level Isolation Interlock has been bypassed
  • Verifies that the RBCCW System is not isolated due to high Drywell pressure/low RPV water level conditions
  • Opens the EOP BYPASS PLUGS panel in the rear of Panel 2R Removes the bypass plug from position BP1 Removes the bypass plug from position BP2
  • Performs SP-17 CRITICAL TASK 1
  • Terminates and prevents the Core Spray System injection into the RPV by performing the following:
  • Presses the OVERRIDE switches for all the sensors that are lit
  • Presses all ACTUATED switches, whether lit or unlit
  • Confirms Core Spray Parallel Isolation Valves closed
  • Confirms Core Spray Main Pumps that are not being used to provide makeup water to the torus per SP37 are in the PULL-TO-LOCK position CRITICAL TASK 1
  • Terminates and prevents Condensate and Feedwater injection by performing the following:
  • Confirms only one Condensate Pump running
  • Places all individual FRV Controllers in MAN position
  • Closes the Low Flow Valves NRC 2016 Scenario 2 Page 18 of 26

NRC 2016 Scenario 2 (New)

  • Reports RPV injection has been terminated and prevented
  • Makes update that EMRVs are open
  • Takes manual control of EMRVs to control Rx Pressure
  • Confirms only one Condensate Pump and only one Feedwater Pump operating CRITICAL TASK 2
  • Controls RPV Water level using the following:

Feedwater Regulating Valves Feed Regulating Valve Block Valves Feedwater Low Flow Valves Heater Bank Outlet Isolation Valves Feedwater and Condensate Pumps

  • Reports RPV water level in band
  • May perform SP-25 if directed (Torus cooling)
  • Confirm the SYSTEM MODE SELECT switch is in the TORUS COOLING position
  • Start an ESW Pump
  • Place and hold the System Pump Start Permissive Keylock for the selected pump in the appropriate position
  • Start the selected Containment Spray Pump using its control switch BOOTH After level is being controlled by SP-19 or as directed Vent the SAH INSERT: TRIGGER 17 Terminus: Control rods have been fully inserted from venting the scram air header.

RPV water level is rising towards the prescribed band as directed in the RPV Control - No ATWS EOP.

Final EAL MS-2 Automatic Scram Failure to shutdown the reactor and manual actions Call taken from the Rx control console are not successful in shutting down the reactor.

Notes/Comments NRC 2016 Scenario 2 Page 19 of 26

NRC 2016 Scenario 2 (New)

NRC 2016 Scenario 2 Page 20 of 26

NRC 2016 Scenario 2 (New)

Procedures Used Event Procedure 1

  • 309.2 2
  • ABN-51
  • T.S - 3.7
  • T.S. - 3.5 4
  • 302.1 5
  • ABN-14
  • RAP-10XF3d& 4d
  • RAP-10XF5c
  • ABN-25 6
  • ABN-11
  • EMG-3200.01b 7/8
  • EMG-SP21 NRC 2016 Scenario 2 Page 21 of 26

NRC 2016 Scenario 2 (New)

  • EMG-SP16
  • EMG-SP17
  • EMG-SP22
  • EMG-SP1
  • EMG-SP-19
  • EMG-SP25
  • EMG-3200.01b
  • EMG-SP2
  • EMG-SP3 NRC 2016 Scenario 2 Page 22 of 26

NRC 2016 Scenario 2 (New)

Simulator Setup

1. Reset to IC-40 (bwr-2)
2. Confirm RBCCW pump 1 is running
3. Confirm B CRD pump running
4. Risk is Yellow
5. Tag EDG #2 NORMAL START and EMERG START control switches
6. Protect #1 EDG
7. Protect A CRD pump
8. Protect system 1 Containment Spray
9. Protect system 1 Core spray pumps
10. Tag #3 Air Compressor Event Trigger Malfunction Preset Preset
  • IMF MAL-RCU014 (RWCU fail to auto isolate)
  • IMF VLV-RCU001 to Mech seize (opt 6)

(V-16-01 mech seize)

  • STL-DGN004 to fail off
  • STL-DGN005A to fail off
  • ANN-T-4-f to fail on
  • LOA-DGN012 to "trip"
  • LOA-DGN009 to "stop" (Places EDG#2 OOS)
  • LOA-CAS031 to Rack out (Places #3 Air compresser OOS) 1 NA NA 2 1
  • MAL-RCU013 to 10% over a 30-minute ramp (inserts a 10% RWCU leak in the RB over a 30-minute period) 3 3
  • MAL-EDS004B (causes a fault on VMCC 1B2) 4 5
  • MAL-CRD001A to 0 NRC 2016 Scenario 2 Page 23 of 26

NRC 2016 Scenario 2 (New)

(closes CRD FCV NC30A) 7

  • LOA-CRD012 to 1
  • LOA-CRD011 to 1 (This opens the alternate FCV NC30B inlet/outlet valves)

MAL-OGS003 5 9 (explosion in off-gas piping)

NOTE:

Once off gas alarms come in Delete MAL-OGS003 Once Off-Gas reset insert 11

  • MAL-CFW017,1.5, 120 sec (Vacuum leak in condenser) 6
  • MAL-GEA005A 13
  • MAL-GEA005B (trips A and B Stator water cooing pumps) 7 Set after event Activate after event # 2 (Loss of VMCC
  1. 2 1B2)
  • Insert ATWS.CAE file NOTE: This ATWS.CAE is File Path:

OPENSIM/CAEP/Training/ATWS.CAE Trigger 17

  • LOA-CAS022, 1
  • MAL-TCS006D, close, 5 seconds TD 8
  • MAL-TCS006E, close, 5 seconds TD Trigger 15
  • MAL-TCS006F, close, 5 seconds TD
  • MAL-TCS006G, close, 5 seconds TD
  • MAL-TCS006H, close, 5 seconds TD
  • MAL-TCS006I, close, 5 seconds TD This will close bypass valves 5 seconds after core spray pumps are in NRC 2016 Scenario 2 Page 24 of 26

NRC 2016 Scenario 2 (New) pull to lock is bypassed in SP-17 is complete in Event #7.

NRC 2016 Scenario 2 Page 25 of 26

NRC 2016 Scenario 2 (New)

Shift Turnover Current plant conditions:

  • 100% power
  • EDG #2 Out of service -
  • Diesel Generator #2 has been out of service for 2 days due to failure to start during the load test. It is scheduled to be returned to service the next day. The diesel load test for #1 diesel is due next shift. Fire diesel
  1. 1 is out of service until next shift for quarterly PMs.
  • Air Compressor #3 is OOS for troubleshooting due to failure to start.

Shift Activities

NRC 2016 Scenario 3 (New)

Scenario Outline Facility: Oyster Creek Scenario No.: 3 Op Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

  • 97% power
  • Main Generator voltage control is in Manual
  • Risk is Yellow Turnover:
  • Place the AVR from manual voltage regulation to automatic voltage regulation IAW 336.1, section 8, starting at Step 8.2 Event No. Malf. No. Event Type* Event Description BOP Return the AVR to service.

1 N/A N SRO 336.1 24 KV main generator electric system EMRV Spuriously opens MAL- R 2 NSS025 ALL ABN-40, Stuck open EMRV TS E

T.S 4.5.L MAL- C ATC CRD high temperature alarm 3 CRD01 SRO RAP- H5c, CRD High temp 3_3403 Trip of 1A3 MAL- C BOP, 4 EDS003 ABN-46, Loss of 1A3 TS SRO C

T.S -3.7 MAL- C RBCCW Pump Trip Leads to Reactor Scram 5 RBC001 ALL A ABN-19 RBCCW failure response NRC 2016 Scenario 3 Page 1 of 23

NRC 2016 Scenario 3 (New)

MAL-RBC001 B

MAL- M LOCA in Primary Containment 6 NSS01 ALL EMG-3200.02 Primary Containment Control 7A Containment Spray Fails to Swap to Spray Mode 7 VLV- C BOP, CNS005 SRO EMG-SP29 Initiation of the containment Spray system for Drywell Sprays RUN FLD.CA M RPV level flashing 8 E ALL NOLEV EMG-3200.08A RPV flooding-No ATWS EL.CAE

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC 2016 Scenario 3 Page 2 of 23

NRC 2016 Scenario 3 (New)

Simulator Summary Event Event Summary 1 The BOP will return the AVR to automatic service IAW 336.1. The BOP will place the AVR MODE Switch to the AUTO position and confirm indications voltage regulation is in automatic. (BOP: Normal Evolution) 2 The BOP will respond to a leaking EMRV IAW ABN-40, Stuck Open EMRV. The valve will stop leaking when the control switch is placed in OFF. The ATC will manipulate the Master FW Controller, and the SRO will apply TS 3.4 (R: Reactivity Manipulation, SRO: Tech Specs) 3 The ATC will respond to a control rod high temperature alarm (RAP-H5c). The ATC will apply stall flow IAW 617.4.002 (CRD Exercise and Flow Test/IST Cooling Water Header Check Valve), which will clear the alarm. (ATC: Component Malfunction) 4 The BOP will respond to a loss of USS 1A3 and execute ABN-46, Loss of USS 1A3. The BOP will start Service Water Pump 1-2, restore power to ER-42, and confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are running. The SRO will review and apply Tech Spec 3.7. (BOP: Component Malfunction; SRO: Tech Specs) 5 The in-service RBCCW pump will trip and the crew will enter ABN-19.

The BOP will diagnose a tripped pump and will attempt to the start the standby RBCCW pump. The Standby RBCCW pump will be mechanically seized resulting in a loss of all RBCCW flow. The ATC will manually scram the reactor and secure all running Recirculation Pumps. (All: Component Malfunction) 6/7 The Crew will respond to a primary coolant leak in the Primary Containment. The SRO will direct Drywell Sprays but sprays will not operate. The SRO will direct Emergency Depressurization when it has been determined that Torus pressure cannot be maintained below the Primary System Pressure (PSP) Curve. [Major Event; Component Failure after EOP]

Following emergency depressurization level instrument reference legs 8

will flash resulting in a loss of RPV level indication. The crew will enter RPV Flooding and commence flooding the vessel using the condensate and feedwater system IAW SP 58 and/or Core spray IAW SP 60 to ensure core submergence. [Major Event]

NRC 2016 Scenario 3 Page 3 of 23

NRC 2016 Scenario 3 (New)

Critical Given a failed open EMRV, the crew will need to take action to close the Task 1 EMRV in accordance with ABN-40, Stuck open EMRV.

Critical Given a LOCA in Primary Containment with challenges to RPV level control, Task 3 the crew must implement EOP SP-58, Feed and Condensate System and/or EOP SP-60, Core Spray operation, to restore RPV water level.

Critical Given a LOCA in Primary Containment with Drywell parameters degrading Task 2 beyond the capacity of the Containment Spray system, the crew will perform an Emergency Depressurization of the Reactor.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number(s)

1. Malfunctions after EOP entry (1-2) 2 7,8
2. Abnormal events (2-4) 3 2,4,5
3. Major transients (1-2) 2 6,8
4. EOPs entered/requiring substantive 2 RPV Control actions (1-2) No-ATWS Primary Containment
5. EOP contingencies requiring substantive 2 ED-No ATWS actions (0-2) RPV Flooding-No ATWS
6. EOP Critical tasks (2-3) 2 6/7,8 NRC 2016 Scenario 3 Page 4 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 1 Event

Description:

Return the AVR to service IAW 336.1.

Initiation: Following shift turnover Cues: As directed by the SRO following shift turnover Time Position Applicants Actions or Behavior SRO

  • Directs the BOP to shift from manual to automatic voltage regulation IAW 336.1, section 8, starting at Step 8.2 BOP
  • Shifts from manual to automatic voltage regulation IAW 336.1, section 8, step 8.2.
  • Verifies the EX2100e TRANSFER VOLTMETER (8F/9F) is reading Zero (+/- 1%)
  • Places the AVR MODE Switch (AVR\97CS Panel 8F/9F) to the AUTO position and allow switch to return to center. (Panel 8F/9F)
  • Confirms the AUTO light illuminated above AVR MODE Switch. (AVR\97CS Panel 8F/9F)
  • Confirms the PSS Status is Enabled locally at the HMI ROLE PLAY: As the EO at the HMI, report that the PSS is active (336.1 step 8.5)

BOP

  • Removes VOLTAGE CONTROL IN MANUAL operator aids installed per Section 7.0.
  • May verify Terminal Voltage or Excitation are within the requirements of 336.1, section 5.0, on the PJM website. [FLOOR ROLE PLAY]
  • May notify the Power team when in auto FLOOR If the applicant requests (or attempts to verify on the PJM website) that ROLE Terminal Voltage or MG Excitation (VARS) are within the limits of section 5.0, PLAY: inform them that the requirements of section 5.0 are satisfactory.

Terminus: The AVR is in automatic voltage control Notes/Comments NRC 2016 Scenario 3 Page 5 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 2 Event

Description:

Leaking EMRV NR108A [TRIGGER 17]

Initiation: AVR is in Auto or as directed by the Lead Examiner Cues: Annunciator B4g, SV/EMRV NOT CLOSED; EMRV NR108A indicates in the VALVE OPEN REGION; Elevated EMRV tailpipe temperatures Time Position Applicants Actions or Behavior BOP

  • Performs ABN-40 actions
  • Checks the following:
  • Acoustic monitoring indications
  • EMRV Tailpipe temperatures [ROLE PLAY]
  • Determines that EMRV NR108A is leaking Role If asked as the EO to check EMRV tailpipe temperatures locally on RB 23, Play: report that EMRV NR108A tailpipe temperature is about 300oF. EMRV NR108B & E are about 180 oF and NR108C and D are 125 oF BOP o Places EMRV NR108A AUTO DEPRESS switch to OFF o Reports EMRV not closed o Cycles EMRV NR108A AUTO DEPRESS switch between OFF to MAN to OFF [Booth Action]

CRITICAL TASK 1 o Reports EMRV indicates closed o Resets the MASTER ALARM to silence the alarm o Plots EMRV Dowmcomer temperature IAW the ABN attachment o Refers the SRO to Tech Specs 4.5.F.5 and 4.5.L for surveillance requirements Booth When the BOP cycles the EMRV NR108A switch to OFF, DELETE the Action EMRV leak MAL-NSS025A If operators place EMRV NR108A back to auto re-initiate leaking EMRV NR 108A SRO

  • Directs entry into ABN-40, Stuck Open EMRV

NRC 2016 Scenario 3 (New)

  • 3.4.B.1: Five electromatic relief valves, which provide the automatic depressurization and pressure relief functions, shall be operable when the reactor water temperature is greater than 212°F and pressurized above 110 psig, except as specified in 3.4.B.2 and during Reactor Vessel Pressure Testing consistent with Specifications 1.39 and 3.3.A.(i).
  • 3.4.B.2: If at any time there are only four operable electromatic relief valves, the reactor may remain in operation for a period not to exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are verified daily to be operable.
  • 4.5.F.5: Once every 3 months and following any release of energy which would tend to increase pressure to the suppression chamber, each OPERABLE suppression chamber - drywell vacuum breaker shall be exercised.

Operation of position switches, indicators and alarms shall be verified every 3 months by operation of each OPERABLE vacuum breaker.

  • 4.5.L.3: Whenever heat from relief valve operation is being added to the suppression pool, the pool temperature shall be continually monitored and also observed until the heat addition is terminated.
  • Notifies SM/WWM about the EMRV failure and of the required LCO ATC
  • Performs ABN-40 actions
  • Reduces Recirc flow control 2 Hz
  • Places the MASTER FEEDWATER CONTROLLER in MAN by pressing the AUTO/MAN button, and controls RPV water level 155 to 165 with the manual knob
  • Places the MASTER FEEDWATER CONTROLLER in AUTO
  • Selects the P display on the MASTER FEEDWATER CONTROLLER using the CHNG DISP button
  • Selects the S display on the MASTER FEEDWATER CONTROLLER using the CHNG DISP button
  • Raises or lowers the S Display to match the P Display NRC 2016 Scenario 3 Page 7 of 23

NRC 2016 Scenario 3 (New)

  • When S and P are matched, Places the MASTER FEEDWATER CONTROLLER in AUTO by pressing the AUTO/MAN button
  • Verifies the green AUTO light is on
  • Adjusts the auto setpoint to 160, or as directed by the SRO
  • Reports Feedwater Level Control is in auto Monitors RPV water level and feedwater flow Terminus: The EMRV is closed and the SRO has reviewed/applied the Tech Specs Notes/Comments NRC 2016 Scenario 3 Page 8 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 3 Event

Description:

CRD high temperature alarm [TRIGGER 19]

Initiation: EMRV is closed or as directed by the Lead Examiner.

Cues: Annunciator H5c, CRD TEMP HI Time Position Applicants Actions or Behavior ATC

  • Confirms cooling water differential pressure and flow within limits in accordance with Procedure 302.1
  • Directs EO to check for a leaking scram discharge valve on HCU 34-03 [ROLE PLAY]

ROLE PLAY: As the EO directed to check for a leaking scram discharge valve on HCU 34-03, report that there are no indications of a leaking scram discharge valve on HCU 34-03.

ATC

  • Attempt to clear alarm by performing the following:

Applies stall flow signal to the affected CRD IAW Procedure 302.2 section 11[FLOOR]

FLOOR: Provide copy of 302.2 section 11 to the applicants.

ATC

  • Turns Rod power on
  • Holds NOTCH OVERRIDE Switch in NOTCH OVERRIDE position
  • Holds ROD CONTROL Switch to ROD OUT NOTCH position
  • Releases ROD CONTROL Switch and NOTCH OVERRIDE Switch [BOOTH]
  • Turns off ROD POWER switch BOOTH: When the candidate applies stall flow the first time, then DELETE MAL-CRD013_3403. This will restore cooling water to the control rod and the high temperature alarm will clear shortly.

ATC

  • Determines which CRD is bringing in the high temperature alarm at Panel 8R

NRC 2016 Scenario 3 (New)

  • Verifies CRD temp hi condition has cleared on 8R recorder TR-RD0046
  • Resets recorder by pressing the alarm acknowledge button on 8R recorder TR-RD0046. This will clear annunciator H5c on Panel 5F/6F.

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 4 Event

Description:

Loss of 480 VAC Bus USS 1A3 [TRIGGER 21]

Initiation: CRD hi temp clear or as directed by the Lead Examiner.

Cues: Annunciators S8f, FDR TO 460V 1A3 TRIP, and U5a, 1A3 MN BRKR TRIP Time Position Applicants Actions or Behavior BOP Per RAPs S-8-f, FDR TO 460V 1A3 TRIP, and U-5-a, 1A3 MN BRKR TRIP (NOTE: Applicant may directly enter and execute ABN-46 instead of RAP).

  • Checks Breaker position and Bus amps
  • Has EO check at the local breaker cubicle for relay targets
  • Verifies trip of 4160V Breaker 1A3P
  • Refers to ABN-46
  • Checks Bus loads have shed
  • Determines cause of Breaker trip [BOOTH]
  • Has Intake operator confirm control power switch inside panel ER-42 in position 2 and restores power to ER-42 BOOTH: When requested to investigate cause of USS 1A3 trip, report that the 1A3P breaker tripped on overload BOOTH: Roleplay: Roleplay when directed to to swap ER-42 and restore power to ER-42 insert TRIGGER 7 and report.

BOP

  • Makes update that lost USS-1A3
  • Per ABN-46, LOSS OF USS 1A3:

IMMEDIATE OPERATOR ACTIONS

  • Has an EO restore power to Panel ER-42 [BOOTH]
  • Has an EO confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are running [BOOTH]

ROLE BOOTH: NOTE: Screen Wash Control Panel and Low Pressure Screen Wash pumps are not modeled. When requested to confirm HP Screen Wash PLAY Pump 1-2 and LP Screen Wash Pump 1-4 are running, report they are both running. May request EO to check intake dp.

NRC 2016 Scenario 3 Page 11 of 23

NRC 2016 Scenario 3 (New)

  • Monitors North intake DP, Circ Water pump amps and main condenser vacuum
  • Notifies Security of the loss of security lighting at the intake
  • Requests Work Week Manager to mobilize Electrical Maintenance for troubleshooting and repair
  • Reviews Attachment 1 Load list on USS 1A3, MCC 1A31 and lighting panel 1A31 for any additional loads lost.
  • Informs US to refer to T.S. 3.7 ATC
  • May assist in communications associated with execution of RAPs and ABN-46 SRO
  • Directs entry into ABN-46, Loss of USS 1A3
  • Determines that USS 1A3 is inoperable per Tech Spec 3.7 and determines that the plant must be placed in the cold shutdown condition Terminus: ABN-46 has been performed and the SRO has addressed Tech Specs.

Notes/Comments NRC 2016 Scenario 3 Page 12 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 5 Event

Description:

The in-service RBCCW pump trips [TRIGGER 9]

Initiation: ABN-46 actions complete or as directed by the Lead Examiner Cues: Annunciators C3c, RBCCW PUMP 1-1 TRIP; E7d, E7f, F7b, CCW FLOW LO for all Recirculation Pumps; RBCCW PUMP 1-1 indicates tripped Time Position Applicants Actions or Behavior BOP

  • Checks RBCCW HX OUTLET PRESS and RBCCW PUMP 1-1 indications and recognizes RBCCW Pump 1-1 has tripped
  • Enters and performs immediate actions of ABN-19.
  • Starts RBCCW Pump 1-2 by placing its control switch to START (must be started within 1 minute)
  • Reports RBCCW Pump 1-1 tripped and RBCCW Pump 1-2 did not start SRO
  • Directs entry into ABN-19
  • Recognizes a loss of all RBCCW flow has occurred and enters ABN-19
  • Directs tripping all Recirculation Pumps
  • Directs entry into RPV Control - No ATWS
  • Directs the Crew to maintain RPV water level 138 - 175 (or 138 - 160) using SP2 (Cond/FW) and/or SP3 (CRD)
  • If an RPV isolation did not occur, directs the Crew to maintain RPV pressure (approximately) 800 - 1000 psig using the Turbine Bypass Valves
  • If an RPV isolation occurred (due to reaching RPV Lo-Lo Level post scram), directs the Crew to maintain RPV pressure (approximately) 800 - 1000 psig using the Isolation Condensers (SP-11) and/or EMRVs (SP-12)
  • Directs SP-1 (Confirmation of Automatic Initiations and Isolations)

NRC 2016 Scenario 3 Page 13 of 23

NRC 2016 Scenario 3 (New)

ATC

  • Places the Reactor Mode Selector switch in SHUTDOWN
  • Reports immediate scram actions complete
  • Trips all operating Recirculation Pumps IAW ABN-19
  • Trips Recirculation Pump A for use with IC-A (or Recirculation Pump E for use with IC-B)
  • Verifies RPV water level < 160
  • Cycles Condensate Return Valve V 34 as necessary to maintain RPV Pressure with IC-A (or V-14-35 for IC-B)
  • Verifies Torus water level is > 90
  • Places one or more EMRV control switch in the MAN position, then back to AUTO BOP
  • Controls RPV water level as directed following the scram o Reports entry into RPV Control - No ATWS on low RPV water level o When RPV level begins to rise following the scram, then performs the following:

o Places all MFRVs in MANUAL, if in AUTO o Closes all MFRVs, if OPEN o Directs the EO to close CRD Supply Water Valve to Charging Water Header valve V-15-52 [ROLE PLAY]

NRC 2016 Scenario 3 Page 14 of 23

NRC 2016 Scenario 3 (New)

Roleplay As the EO directed to close CRD Supply Water Valve to Charging Water Header valve V-15-52, insert Trigger 15. Report when complete.

o Enters SP-2 (Cond/FW) when directed o Controls RPV water level using the following as necessary:

o Feedwater Regulating valves o Main Feed Regulating Valve (MFRV) Block valves o Feedwater Low Flow valves o Heater Bank Outlet Isolation valves o Feedwater and Condensate pumps

  • Performs SP-1 as directed
  • Makes plant announcement for reactor scram due to loss of all RBCCW flow Terminus: The reactor is scrammed, all Recirculation Pumps are tripped, and RPV water level and pressure are under control Notes/Comments NRC 2016 Scenario 3 Page 15 of 23

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 6/7 Event

Description:

Leak in Primary Containment

[TRIGGER 11, Nolevel.CAE, Run FLD.CAE]

Initiation: level is recovering or as directed by the Lead Examiner Cues: Drywell pressure and Temperature parameters are rising.

Time Position Applicants Actions or Behavior RO

  • Reports Drywell temperature and pressure are rising
  • Reports Drywell pressure > 3 psig - EOP entry
  • Confirms all Drywell Recirc Fans tripped
  • When directed, initiates Drywell Sprays Places the SYSTEM MODE SELECT switch for the selected system in the DW SPRAY position Verifies the Torus CLG Discharge valve closes
  • Verifies the DW Spray Discharge valve opens
  • Reports the DW Spray Discharge for System 2 (V-21-5) will not open and thus no Drywell Sprays are available
  • Directs EO to open DW Spray Discharge for System 2 (V-21-5) [Role Play]

Role As the directed as the EO to open DW Spray Discharge for System 2 (V Play: 5), report that the valve is stuck closed and you cannot open it.

RO

  • Reports when PSP is being approached
  • Reports when 281 °F Drywell bulk temperature is being approached CRITICAL
  • Opens all EMRVs by placing the AUTO DEPRESS VALVE TASK 2 switches to MAN

NRC 2016 Scenario 3 (New)

SRO

  • Directs SP-1, Confirmation of Automatic Initiations and Isolations
  • Directs line-up of Drywell Sprays IAW SP-29
  • Directs initiation of Drywell Sprays when either:

Drywell or Torus pressure exceeds 12 psig When Primary Containment conditions are within the Containment Spray Initiation Limit (CSIL) Curve

  • When determined that Torus pressure cannot be maintained <

PSP, or when bulk Drywell temperature cannot be restored and maintained < 281 °F, directs entry into Emergency Depressurization - With AWS EOP

  • Directs RO to Bypass ROPS
  • Verifies Torus water level > 90

NRC 2016 Scenario 3 (New)

Op-Test No.: NRC 2016 Scenario No.: Scenario 3 Event No.: 8 Event

Description:

RPV Level instruments fail Initiation: Reactor Scrammed or as directed by the Lead Examiner Cues: RPV level instruments indicating high out of sight Time Position Applicants Actions or Behavior Crew

  • Determines that all level indications have flashed and cannot determine water level.

SRO

  • Based on RPV Control No ATWS Override level cannot be determined entry into RPV Flooding is required and directs the following operator actions:
  • Confirms all EMRVs are open, Confirms that the MSIVs are closed and Closes isolation condenser isolation valves.

RO Per SP-58, increases injection into the RPV with condensate/feedwater:

  • Confirms that the condensate and feedwater pumps are running.
  • Confirms the heater string outlets and FRV block valves are open.

CRITICAL

TASK 3

  • Monitors hotwell levels. Maximizes hotwell level make up.

And/OR Per SP-60, increases injection into the RPV with Core Spray

  • Overrides actuating signals
  • Confirms 1 Main pump running and 1 booster pump running in system started
  • Opens Parallel Valves as required to flood RPV Terminus: When RPV Flooding is established.

Final EAL FS-1 due to a loss of Reactor Coolant System barrier and a potential loss of Fuel call Clad barrier Notes/Comments NRC 2016 Scenario 3 Page 18 of 23

NRC 2016 Scenario 3 (New)

Procedures Used Event Procedure 1

  • Copy of 336.1 handed out 2
  • ABN-40
  • 617.4.002 (Handout) 4
  • ABN-46
  • T.S 3.7 5
  • ABN-19
  • EMG-3200.01A
  • EMG-SP29
  • EMG-3200.02
  • EMG-SP2
  • EMG-SP3
  • EMG-SP11
  • EMG-SP12 7
  • EMG-SP29
  • EMG-3200.02
  • EMG-3200 8
  • EMG-SP-58 NRC 2016 Scenario 3 Page 19 of 23

NRC 2016 Scenario 3 (New)

  • EMG-SP-60
  • EMG-3200.08A NRC 2016 Scenario 3 Page 20 of 23

NRC 2016 Scenario 3 (New)

Simulator Setup

1. Reset to IC-40 (bwr2)
2. Lower reactor power to 97% with recirc flow
3. Place the AVR in manual voltage control IAW 336.1, section 7
4. Confirm Transfer meter is at 0
5. Have copy of 336.1 (complete procedure) for applicants; mark step 8.1.1 and 8.1.2 complete
6. Have copy of 202.2 section 11 for applicants
7. Ensure Service Water Pump 1-1 is running and Service Water Pump 1-2 is secured
8. Hang tags on containment spray/ESW 1 pumps
9. Protect containment spray/ESW 2 system
10. Protect EDG #2
11. Risk is Yellow Event Trigger Malfunction VLV-CNS005, Mech Seize Preset Preset (Containment Spray mechanical seizure)

Containment Spray System 1 Tag Out LOA-CNS054, rack out LOA-CNS051, rack out VLV-CNS002, close BKR-CNS007, fail control fuse BKR-CNS005, fail control fuse 1 NA NA 2 17 MAL-NSS025A to 25%

(This inserts a 25% leak through EMRV NR108A) 3 19 MAL-CRD013_3403 (This will plug the cooling water to control rod 34-03 and result in a high temperature)

(This malfunction will be deleted within the scenario) 4 21 MAL-EDS003C (This will insert a loss of USS 1A3)

NRC 2016 Scenario 3 Page 21 of 23

NRC 2016 Scenario 3 (New) 7 LOA-CWS049 to B31 This will restore power to ER-42 5 9 MAL-RBC001A (Trips RBCCW Pump 1-1)

MAL-RBC001B (Trips RBCCW Pump 1-2) 15 LOA-CRD024 to 0 (This closes CRD Supply Water Valve to Charging Water Header valve V 52)

MAL-NSS017a, 6%, 300 seconds 6 11 (Steam leak inside drywell) file: NOLEVEL.CAE file: RUN FLD.CAE (RPV level flashing)

VLV-CNS005, Mech Seize 7 Preset in Initial (Containment Spray mechanical seizure) conditions file: NOLEVEL.CAE 8 Set in event 6 file: RUN FLD.CAE (RPV level flashing)

NRC 2016 Scenario 3 Page 22 of 23

NRC 2016 Scenario 3 (New)

Shift Turnover Current plant conditions:

  • 97% power
  • Main Generator voltage control is in Manual
  • Risk is Yellow Shift Activities
  • Place the AVR from manual voltage regulation to automatic voltage regulation IAW 336.1, section 8, starting at Step 8.2 NRC 2016 Scenario 3 Page 23 of 23
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