ML14059A258

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Draft Operating Exam (Sections a, B, and C) (Folder 2)
ML14059A258
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 01/06/2014
From:
Exelon Generation Co
To: Brian Fuller
Operations Branch I
Jackson D
Shared Package
ML13295A030 List:
References
TAC U01875
Download: ML14059A258 (347)
v • d • e


Text

CENCi.

NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC RO Admin C0-1 Revision: 0.0

Title:

Determine Containment Water Level Approvals:

Signature I Printed Name Developed By ~

~~----~---~~~~

David Huff 12/18/2013 Validated By Jerry Randall 12/13/2013 Facility Reviewer .L Aaron Armstrong Approximate Duration: 30 minutes Documentation of Performance:

Performer:

Evaluator:

Start Stop Completion Time: Time: Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

JPM RO C0-1 Page 1 of 10 NRC March 2014

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o=-~8 NINE MILE POINT NUCLEAR STATION References

1. N2-EOP-6.23, Containment Water Level Determination JPM RO CO-l Page 2 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operators ability to determine Containment Water Level when containment level is above 224 feet.
2. Task Information:
a. N2-EOP06-01001-23, Implement N2-EOP-6.23, Containment Level Determination.
b. 2.1.25 (3.9) Ability to interpret reference materials, such as graphs, curves, tables, etc.
3. Evaluation I Task Criteria Perform

.~~al~tion ~ocation Classroom No No Yes

4. Recommended Start Location
a. Training Classroom
5. JPM Setup (if required)
a. . Ensure book carts are available for the operators to use and that there is an up to date copy of N2-EOP-6.23.
b. Ensure a calculator is available for each operator.

JPM RO CO-l Page 3 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATIOI~

B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a pla.nt JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. Th!s evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM RO C0-1 Page 4 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Given:

  • Approximately one day ago the plant experienced a large break LOCA
  • In order to maintain adequate core cooling, operators have been injecting into the RPV with systems whose suction source is outside the primary containment.
  • The EOP Director has directed the performance of N2-EOP-6.23, Containment Level Determination. Steps 6.1 through 6.6 have been completed.
  • You are the RO assigned to determine and log Containment Water Level per N2-EOP-6.23.
  • Another operator has been assigned to monitor the Fuel Zone Level Instruments.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions

  • ~n:.,~\, (Operators Name), Given the plant parameters found on the provided

.~,:~J'; .* log, document the Primary Containment Water Level (PCWL) for 06:00 to 11:00. Additionally, on the log provided, document any required actions based on PCWL trend. Another operator will be taking care of all actions for monitoring the Fuel Zone instruments.

START TIME ACT. COD£. * '

P/S{NA *.

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.

JPM RO CO-l Page 5 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION

2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the STD: Obtains N2-EOP-6.23 procedure.

The Answer Key attached to this JPM provides the grading criteria for the below step. Documentation of the correct ~P is not required for successful completion of the below step. The operator need only determine the correct Primary Containment Water Level within +/- 1 foot in order to meet the intent of the critical step.

3. Using N2-EOP-6.23, Step 6.7 and Figure 1a, p determines containment water level.

The operator should notice that the ~P between 08:00 and 09:30 has remained the same and RPV injection flow has been constant. The operator should identify that Step 6.10 now applies and that the EOP DIRECTOR should be notified of a constant PCWL with no change in injection.

If the operator informs the EOP DIRECTOR of the constant ~P before completion of all PCWL logs, provide the following cue:

Cue: The EOP DIRECTOR has been informed, continue logging all PCWL 's through 11:00. Ensure you document your notification on the log.

The critical aspect of the below step is for the operator to determine the EOP DIRECTOR needs to be notified of a constant PCWL with continuous injection. It is not necessary to get the exact time frame documented to pass the below step.

JPM RO C0-1 Page 6 of 10 NRC March 2014

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NINE MILE POINT 8

-;~;aeoF NUCLEAR STATION P/S/~A

4. When logging the PCWL, determines the .D.P p has not changed but RPV injection flow has remained constant. Informs the EOP DIRECTOR.

~; The Operator logged all PCWL readings through 11:00 and documents the need to inform the EOP DIRECTOR of the constant LJ.P with continuous injection .

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,, .1-JPM RO C0-1 Page 7 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION 2CMS*P17A 2CPS-PI127, RPV Injection SUPPR PRIMARY CONTMT AP Time Injection Temperature CHAMBER PRESS INLET N2 PRESS Flow Of PSIG PSIG PSID Feet 6:00 Constant 68 20 20 0 224 +/- 1 6:30 Constant 68 22 21 1 226 +/- 1 7:00 Constant 68 22 20 2 228 +/- 1 7:30 Constant 68 15 12.5 2.5 230 +/- 1 8:00 Constant 68 17 13.5 3.5 232 +/- 1 8:30 Constant 68 20 16.5 3.5 232 +/- 1 9:00 Constant 69 25 21.5 3.5 232 +/- 1 9:30 Constant 69 22 18.5 3.5 232 +/- 1 10:00 Constant 69 23 19 4 234 +/- 1 10:30 Constant 69 26 21 5 236 +/- 1 11:00 Constant 69 32 26.5 5.5 238 +/- 1 Are any actions required to be taken based on the above readings?

Document any actions required here:

Inform the EOP Director that the 4P was constant with a constant injection rate for a period of time JPM RO CO-l Page 8 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • Approximately one day ago the plant experienced a large break LOCA
  • In order to maintain adequate core cooling, operators have been injecting into the RPV with systems whose suction source is outside the primary containment.
  • The EOP Director has directed the performance of N2-EOP-6.23, Containment Level Determination. Steps 6.1 through 6.6 have been completed.
  • You are the RO assigned to determine and log Containment Water Level per N2-EOP-6.23.
  • Another operator has been assigned to monitor the Fuel Zone Level Instruments.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Given the plant parameters found on the provided log, document the Primary Containment Water Level (PCWL) for 06:00 to 11:00. Additionally, on the log provided, document any required actions based on PCWL trend. Another operator will be taking care of all actions for monitoring the Fuel Zone instruments.

JPM RO CO-l Page 9 of 10 NRC March 2014

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a JO<Ot ventuce of I 0~ "'!~eDF NINE MILE POINT NUCLEAR STATION 2QJ5-PI127, nme I RPV Injection Flow Injection Temperature 2CMS*P17A SUPPR CHAMBER PRESS PRIMARY CONTMT INLET N2 PRESS I 4P f Primary Containment water Level

  • f PSIG PSIG I PSID I Feet 6:00 Constant 68 20 20 6:30 Constant 68 22 21 7:00 Constant 68 22 20 7:30 Constant 68 15 12.5 8:00 Constant 68 17 13.5 8:30 Constant 68 20 16.5 9:00 Constant 69 25 21.5 9:30 Constant 69 22 18.5 10:00 Constant 69 23 19 10:30 Constant 69 26 21 11:00 Constant 69 32 26.5 Are any actions required to be taken based on the above readings?

Document any actions required here:

JPM RO CO-l Page 10 of 10 NRC March 2014

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0 =:~.uon ~*~eDF NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC RO Admin C0-2 Revision: 0.0

Title:

Develop and get Approval for a Temporary Note Approvals:

Signature I Printed Name Developed By ~ David Huff 12/18/2013 Validated By Doug Mizener 12/13/2013 Facility Reviewer Aaron Armstrong Approximate Duration: 30 minutes Documentation of Performance:

Performer*:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

JPM RO C0-2 Page 1 of 14 NRC March 2014

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8JOintventureof--.J 0~ ~:eoF NINE MILE POINT NUCLEAR STATION References

1. CNG-OP-1.01-1005, Temporary Notes, Temporary Labels, Operator Aids, and Permanent Labels JPM RO C0-2 Page 2 of 14 NRC March 2014

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  • NUCLEAR STATION Instructor Information A. JPM Information
1. Description
a. This JPM tests the operators ability to develop and get approval for a Temporary Note.
2. Task Information:
a. NS-OM502-00004, Install and Use Authorized Labels.
b. 2.1.15 (2. 7) Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, operations memos, etc.
3. Evaluation I Task Criteria Perform Classroom No No Yes
4. Recommended Start Location
a. Training Classroom
5. JPM Setup (if required)
a. Ensure book carts are available for the operators to use and that there is an up to date copy of CNG-OP-1.01-1005 available.

JPM RO C0-2 Page 3 of 14 NRC March 2014

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O~k>>n ~*,eoF NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM RO C0-2 Page 4 of 14 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Given:

  • The plant is at 100% power.
  • The crew has recently discovered that 2SWP*TIK35A, CONTROL ROOM CHILLER 2HVK*CHL1A SVCE WTR OUTLET TEMP controller is difficult to place in MANUAL CONTROL.
  • Specifically, when shifting the controller from AUTO to MANUAL, the operators have to hold the MAN pushbutton down for 2 to 3 seconds to get the controller to shift into MANUAL.
  • I&C has been contacted and have setup a repair schedule. The controller is scheduled to be repaired in one week.
  • While waiting for repairs, I&C has said that the controller will still function and if it is necessary for the operators to shift the controller from AUTO to MAN, the operators will need to hold down the MAN pushbutton for 2 to 3 seconds.
  • The Control Room Supervisor has determined a Temporary Note is to be developed and posted next to the controller explaining this condition.
  • The controller is located on 2CEC*PNL870.
  • CR-2014-002568 is tracking the repair of the controller.
  • You are the operator assigned to develop the Temporary Note.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Develop and get approval to post a Temporary Note for 2SWP*TIK35A per CNG-OP-1.01-1005, Section 5.2 .

..ACTifCObE

  • I P/S}NA
1. Provide repeat back of initiating cue p SAT/ UNSAT STD: Proper communications Cue: Acknowledge repeat back providing used lAW CNG-OP-1.01-2001, correction if necessary. Communications and Briefings.

JPM RO C0-2 Page 5 of 14 NRC March 2014

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2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the STD: Obtains a copy of CNG-procedure.

OP-1.01-1005 and reviews section 5.2.

The remaining steps may be performed in any order.

The answer key attached to this JPM may be used to assist in the grading of the below steps. The operator may choose to use different words on the TEMPORARY LABEL and TEMPORARY LABEL LOG than what is listed on the answer key. This is acceptable as long as the intent of the TEMPORARY NOTE and LOG is consistent with the intent of the below steps. The Evaluator may use their judgment as to whether or not the intent of the below steps are met.

The operator may choose to fill out all portions of the Temporary Note and Log prior to presenting the note to the SM for approval. This is an acceptable action.

3. Using the provided blank Temporary Note, p documents the following information:
  • A note stating that in order to place 2SWP*TIK35A in MANUAL, the MAN button must be depressed for 2 to 3 seconds.
4. Presents the Temporary Note to the SM for p approval.

Cue: As the SM, when presented with the Temporary Note, sign on the block labeled "SM" and give it back to the operator.

5. Documents the following additional data on p SAT I UNSAT the temporary note:

STD: On the provided Temporary Note, places today's

  • The date date.

JPM RO C0-2 Page 6 of 14 NRC March 2014

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6. *
7. Fills out the provided Attachment 1, p Temporary Notes Log as follows:
  • Temporary Note Number
8.
  • Date p SAT I UNSAT STD: Documents today's date in the DATE block on the Temporary Notes Log.
9.
  • Requested By p SAT I UNSAT STD: The operator documents their name in the REQUESTED BY block on the Temporary Notes Log.

At a minimum, in the LOCATION block of the Temporary Notes Log, the operator must put P870. They may choose to add additional information such as 2SWP*TIK35A, however it is not required.

10.
  • Location p JPM RO C0-2 Page 7 of 14 NRC March 2014

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12.
  • Comments p SAT I UNSAT STD: Places the Condition Report Number CR-2014-002568 in the COMMENTS block of the TEMPORARY NOTES LOG.
13.
  • Shift Manager Approval Signature p Cue: As the SM, when presented with the Attachment 1, sign in the block labeled "Shift Manager Approval Signature".

Unless the operator would like to perform an additional review of all the paperwork, then when the operator requests the SM sign the Temporary Notes Log, inform the operator that another operator will perform the action of attaching the Temporary Note to the panel and their task is complete.

The Operator has presented the completed Temporary Notes Log and Temporary Note to the SM for review and approval.

JPM RO C0-2 Page 8 of 14 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate CR TEMP NOTE No. 0-14-03 Date Today's Date SM Eval. Sign Here When placing 2SWP*TIK35A in MANUAL control, hold in the MAN pushbutton for 2 to 3 seconds.

JPM RO C0-2 Page 9 of 14 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Evaluator's Answ.er Key Do Not Provide to Candidate Attachment 1, Temporary Notes Log Temporary Date Requested By Location Content of Temporary Note Shift Manager Comments Shift Manager Note (Please Print) Approval Signature (1) Removal Signature Number and Date P632, Printer turned off due to excessive paper CR-2013-0-13-036 09/17/13 Toothaker ~&~ Told Ml~ tojo5jtJ 2MSS*TRSH 1002 use. 006789 P851 Pump in PTL, auto starts when placed in CR-2013-0-13-037 11/10/13 Tanguay 2TML-P4 standby JohwM~ 007724 P873 Div. 1 H202 2CMS*PNL66A Inop when lined up to CR-2013- :Marft qreer 0-13-038 12/15/13 Hoskins Told Ml~

Sample Path Suppression Pool 008645 12/30/13 Selector Switch P623 Amps less than required. Below minimum CR-2014-0-14-01 01/12/14 Andrus :Marft qreer 2MSS*AOV7D amperage 001104 P851 CR-2014-0-14-02 02/20/14 Wilcox Dual Indication. J<9m Tansua~

2MSS-PV28A 002193 When placing 2SWP*TIK35A in MANUAL, Today's Operators CR-2014-0-14-03 P870 depress the MAN pushbutton for 2 to 3 Evaluator, Sign Here Date Name 002568 seconds.

JPM RO C0-2 Page 10 of 14 NRC March 2014

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0~ ~,eDF NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • The plant is at 100% power.
  • The crew has recently discovered that 2SWP*TIK35A, CONTROL ROOM CHILLER 2HVK*CHL1A SVCE WTR OUTLET TEMP controller is difficult to place in MANUAL CONTROL.
  • Specifically, when shifting the controller from AUTO to MANUAL, the operators have to hold the MAN pushbutton down for 2 to 3 seconds to get the controller to shift into MANUAL.
  • I&C has been contacted and have setup a repair schedule. The controller is scheduled to be repaired in one week.
  • While waiting for repairs, I&C has said that the controller will still function and if it is necessary for the operators to shift the controller from AUTO to MAN, the operators will need to hold down the MAN pushbutton for 2 to 3 seconds.
  • The Control Room Supervisor has determined a Temporary Note is to be developed and posted next to the controller explaining this condition.
  • The controller is located on 2CEC*PNL870.
  • CR-2014-002568 is tracking the repair of the controller.
  • You are the operator assigned to develop the Temporary Note.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions

{Operators Name), Develop and get approval to post a Temporary Note for 2SWP*TIK35A per CNG-OP-1.01-1005, Section 5.2.

JPM RO C0-2 Page 11 of 14 NRC March 2014

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a joint ventu-e of 0 =-- -!'eDF j NINE MILE POINT NUCLEAR STATION CONTROL ROOM CHILLER HVK *CHUA SVCE WfR OUTLET TEMP S---130

~120 CONTROL BLDG CHILLER i=110 HVK

  • CHUA

~100

~ 90

~80 r-..

=--

~60 t:so

!-40

~

DIV I CHILLER COMPRESSOR AUXOILPUMP 2SWP"TI K35A JPM RO C0-2 Page 12 of 14 NRC March 2014

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0~ -.:~eDF NINE MILE POINT NUCLEAR STATION CR TEMP NOTE No.

Date SM JPM RO C0-2 Page 13 of 14 NRC March 2014

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eon.te1111tton ~*.. eDF NINE MILE POINT NUCLEAR STATION Attachment 1, Temporary Notes Log Temporary Date Requested By Location Content of Temporary Note Shift Manager Comments Shift Manager Note (Please Print) Approval Signature (1) Removal Signature Number and Date P632, Printer turned off due to excessive paper CR-2013-0-13-036 09/17/13 Toothaker ~&~ Torirl k!~ tojo5jtJ 2MSS*TRSH 1002 use. 006789 P851 Pump in PTL, auto starts when placed in CR-2013-0-13-037 11/10/13 Tanguay 2TML-P4 standby ]ohwlvf~ 007724 P873 Div. 1 H202 2CMS*PNL66A Inop when lined up to CR-2013- 'Mar~qreer 0-13-038 12/15/13 Hoskins Torirl k!~

Sample Path Suppression Pool 008645 12/30/13 Selector Switch P623 Amps less than required. Below minimum CR-2014-0-14-01 01/12/14 Andrus 'Mar~qreer 2MSS*AOV7D amperage 001104 P851 CR-2014-0-14-02 02/20/14 Wilcox Dual Indication. "rem "ran3ua~

2MSS-PV28A 002193

1. During the quarterly review, initiate a Permanent Label Request for Notes exceeding a year with exception of Notes required due to an extended outage or equipment deficiency. For Notes exceeding a year, annotate in the "Comments" block either "Label Requested",

"WO # ",or "Extended Outage".

JPM RO C0-2 Page 14 of 14 NRC March 2014

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o~lon ot::::eoF NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC RO Admin EC Revision: 0.0

Title:

Defeat the Reactor Building Ventilation LOCA Isolation Signals Approvals:

Signature I Printed Name Developed By ~ David Huff 12/18/2013 Validated By Jerry Randall 12/13/2013 Facility Reviewer Aaron Armstrong J r1"5 1/ZL:J,"

Approximate Duration: ___4_:_c5::..__:_cm'-'-'i-'-'n~u~te"'-'s=-----

Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

JPM RO EC Page 1 of 18 NRC March 2014

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0~ *t::eoF NINE MILE POINT .

NUCLEAR STATION References

1. N2-EOP-6.26, Defeating Reactor Building Ventilation LOCA Isolation Signals JPM RO EC Page 2 of 18 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operators ability to describe how the Reactor Building Ventilation LOCA Isolation Signals are defeated.
2. Task Information:
a. N2-EOP06-01001-26, Implement N2-EOP-6.26, Defeat Reactor Building Ventilation LOCA Isolation Signals
b. 2.2.41 (3.5) Ability to obtain and interpret station electrical and mechanical drawings
3. Evaluation 1 Task Criteria Perform Classroom No No Yes
4. Recommended Start Location
a. Training Classroom
5. JPM Setup (if required)
a. Print out enough copies of N2-EOP-6.26 for each operator to have one.

JPM RO EC Page 3 of 18 NRC March 2014

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o~lon ~;:eoF NINE MILE POINT NUCLEAR STATION

b. Ensure a copy of the following ESKs have been printed out for use by the operators. Print out enough copies so that each operator may have a set.

It is best to print out the ESKs on 11X17 sheets:

1) 07HVR01 through 12 ( 17 drawings in all)
2) 06HVR01, Sheet 1 (2HVR*UC413A)

JPM RO EC Page 4 of 18 NRC March 2014

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0~ -::~eDF NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial.conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

c. Read Before Each Evaluated JPM
1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that a:dditional verification will not be provided.

JPM RO EC Page 5 of 18 NRC March 2014

a JOioJ veotu"' ol J 0~ ~,eDF NINE MILE POINT NUCLEAR STATION Given:

  • Drywell pressure is 10 psig and RPV Water level is 5 inches.
  • You are the operator assigned to perform N2-EOP-6.26.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Complete the attached worksheet regarding Defeating the Reactor Building Ventilation LOCA Isolation Signals.

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications
  • correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the STD: Obtains copies of N2-procedure.

EOP-6.26 and HVR ESKs The following steps may be performed in any order.

The Answer Key attached to this JPM will be used to assist in grading of the below steps.

JPM RO EC Page 6 of 18 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Due to the nature of this type of JPM, the answers given on the worksheet by the operator may not match exactly what is on the provided answer key. This is acceptable as long as the intent is met as determined by the Evaluator. If there is a question by Evaluator as to the intent of what information the operator is attempting to provide, the Evaluator may verbally question the operator to ascertain the intent. When grading the below steps, the Evaluator should take into account any information gained through verbal discussion with the operator.

The operator may include additional components not listed on the answer key that may be affected by the LOCA isolation signal. This is acceptable.

1. Determine which conditions will cause the p Reactor Building Ventilation System to isolate.
2. Determine which Division 1 components in p the Reactor Building Ventilation System are directly affected by a system isolation.

JPM RO EC Page 7 of 18 NRC March 2014

CENG . J a JOint venture of 0~ ~~eDF NINE MILE POINT NUCLEAR STATION Step 3 below should be graded by both reviewing the information the operator documented in Block 3 as well as a verbal discussion between the Evaluator and operator as to how the LOCA isolation is defeated.

3. Describe how the Division 1 LOCA Isolation is p defeated for the Reactor Building Ventilation System.
4. Determines what will happen to the Reactor Building Ventilation System if an Above Refuel Floor Radiation Monitor RE14A and B experience a high radiation condition above their ALARM setpoint when the LOCA signal isolation is defeated.

The Operator has completed the JPM worksheet and returned it to the Evaluator. The Evaluator has discussed any unclear information contained on the worksheet JPM RO EC Page 8 of 18 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate

  • Above Refuel Floor High Radiation I RE14A or B in Alarm
  • Below Refuel Floor High Radiation I RE32A or B in Alarm
  • R6 Ventilation Low Flow Condition
  • LOCA Signal -or- High Drywell Pressure I Low RPV Level The operator may choose to add additional isolation signals. That is acceptable provided at least the above information is provided.
  • 2HVR*AOD1A
  • 2HVR*AOD9A
  • 2HVR*AOD10A
  • 2HVR*UC413A The operator may list additional components affected (i.e. Supply/Exhaust Fans tripping). That is acceptable, but not required because the additional components will only trip when the above AOD's close.

JPM RO EC Page 9 of 18 NRC March 2014

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0~ ~~eDF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate I:"J'h'"'~vl

  • N2-EOP-6.23, Step 6.1.1 requires the operator to lift the lead on Contact 4 of relay 2A-10-2ISCA02 in 2CEC*PNL859.
  • The contact from which the lead is lifted can be found on ESK 07HVR10 Sheet 1 on the upper left hand side of the drawing.
  • When the lead (R4) is lifted, it prevents the following relays from energizing when a LOCA signal is present:

o Relay 3 o Relay 62-

  • If energized, Relay 3 would send a signal to the following contacts to OPEN:
  • o 2HVR*AOD1A Contact 3 Ml to Rl.

o 2HVR*AOD9A Contact 3 M2 to R2.

o 2HVR*AOD10A Contact 3 M3 to R3.

  • Each of the above contacts can be found on ESK 07HVR06, Sheet 1.

f?,J,p ,),.*,)*1

  • AOD1A/9A/10A will close if their associated solenoid valves deenergize.
  • By preventing a LOCA signal from opening the above contacts, it prevents th~ associated AOD solenoids from deenergizing thus preventing the AODs from isolating.
  • Additionally preventing Relay 62- from energizing will prevent 2HVR*UC413A from starting.
  • Relay 62-, Contact 5 to 1 for UC413A can be found on ESK 06HVR01, towards the upper left.
  • If Contact 5 to 1 cannot shut, then UC413A cannot start on a LOCA signal.

JPM RO EC Page 10 of 18 NRC March 2014

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0~ -::,eoF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate Division 1 LOCA isolation Signal from ESK 07HVR10, Sheet 1:

Lift Lead R4 from Here Relays 3 and 62- are prevented from energizing on JPM RO EC Page 11 of 18 NRC March 2014

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0~ ~~~eDF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate 2HVR*AOD1A from ESK 07HVR06, Sheet 1 (AOD9A and lOA are similar):

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311' PI/'}(J D s

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~

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llWII'M: z

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!""lA Contact M 1 to R1 is prevented from ZHVR*

t!IYIA opening. If it can't open, it cannot shut the AOD on a LOCA signal IJI JPM RO EC Page 12 of 18 NRC March 2014

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0=-'ton ~*::eoF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate 2HVR*UC413A from ESK 06HVR01:

PS70 Contact 5 to 1 from Relay 62-. If Contact 5 to 1 cannot shut, then UC413A cannot startup from a LOCA U Ll a.am NT I!

REo!iiCTOA SLOG. RECIRC. FA!i 2HVR*UC413.A CKT-2HVR.A03.

JPM RO EC . Page 13 of 18 NRC March 2014

a JOtnt venture of J 0~ ~*~eDF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate Continue to Run Isolate JPM RO EC Page 14 of 18 NRC March 2014

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NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • Drywell pressure is 10 psig and RPV Water level is 5 inches.
  • You are the operator assigned to perform N2-EOP-6.26.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Complete the attached worksheet regarding Defeating the Reactor Building Ventilation LOCA Isolation Signals.

JPM RO EC Page 15 of 18 NRC March 2014

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0~ -::~eDF NINE MILE POINT NUCLEAR STATION JPM Worksheet JPM RO EC Page 16 of 18 NRC March 2014

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0~ ~~er1F NINE MILE POINT NUCLEAR STATION JPM RO EC Page 17 of 18 NRC March 2014

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. l NINE MILE POINT NUCLEAR STATION Continue to Run Isolate JPM RO EC Page 18 of 18 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC RO Admin EP Revision: 0.0

Title:

Fire Fighting Response for a Fire in the Protected Area Approvals:

Signature I Printed Name Developed By ~

~----------~~~~~

David Huff 12/18/2013 Validated By Doug Mizener 12/13/2013 Facility Reviewer Aaron Armstrong Approximate Duration: _ ___.:1::...:5=--..:..:m:...:..:i:.:...:n:..=:u~te::...:s=-----

Documentation of Performance:

Performer:

Evaluator:

Start Stop Completion Time: Time: Time Grade: Pass I Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

JPM RO EP Page 1 of 13 NRC March 2014

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NINE MILE POINT NUCLEAR STATION References

1. _EPIP-EPP-28, Firefighting
2. EPIP-EPP-OSA, Local Area/Building Evacuation JPM RO EP Page 2 of 13 NRC March 2014

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0~ .~*,eoF NINE MILE POINT 8

NUCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operators ability to perform the RO actions for a fire in the protected area.
2. Task Information:
a.
  • N2-285001-01001, Utilize Interplant Communications Subsystems.
b. 2.4.39 (3.9) Knowledge of RO responsibilities in emergency plan implementation
3. Evaluation I Task Criteria
  • Eva~~tt9ri Mettidd u; ~Jy! :*:.' .'<'.~ ':'.~

Perform Simulator No No Yes

4. Recommended Start Location
a. Unit 2 Simulator
5. JPM Setup (if required)
a. Ensure book carts are available for the operators to use and that there is an up to date copy of EPIP-EPP-28. Print out enough copies of Attachment 1 so that each operator gets a copy.

JPM RO EP Page 3 of 13 NRC March 2014

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NINE MILE POINT 8

~:~eDF NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. (Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM RO EP Page 4 of 13 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Given:

  • You are the on-shift Control Room Operator (CRO).
  • The SM has been notified of a confirmed fire in the Unit 2 Turbine Building, 250' Elevation Truck Aisle.
  • This area is not a C02 or Halon Protected Area.
  • The OSC has not been activated.
  • This is a drill Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform the CRO actions for the fire per EPIP-EPP-28, Attachment 1 ACT *.CO.DE.

P/5/NA ..

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used JAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the STD: Obtains a copy of EPIP-procedure.

EPP-28 and reviews Attachment 1.

3. Upon notification of a fire, or upon receipt of p
  • ~~~.j:t,=~~~. * *

-i an alarm AND actuation of an automatic Fire S'TD:,~~*i Suppression System:

a. Place the GAitronics system in the Merge

'>'""N" ,./~~!<'{'

Mode JPM RO EP Page 5 of 13 NRC March 2014

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NINE MILE POINT NUCLEAR STATION

4. b. If the event is a drill, make the following p SAT I UNSAT announcement preceding the fire alarm:

STD: Announces into the "This is a drill, this is a drill."

HANDSET "This is a drill, This is a drill" while holding down the talk pushbutton or INST Switch.

5. c. Sound the Fire Alarm for 10 seconds. p
6. Make the following announcement: p "Attention, Attention, this is (an actual event) (a drill). A fire has been detected at Unit(1/2) in the (state building location, elevation, if known).

The Nine Mile Point Fire Brigade shall report to the Unit (1/2) assembly area or (other location as directed by the Fire Brigade Leader).

All other personnel are to remain clear of the (state building location, elevation)."

Cue: If asked, the FBL does not want a different assembly area.

7. Repeats the alarm and announcement. p SAT I UNSAT Cue: The alarm and announcement have STD: Repeats steps 4 through been repeated. 6 JPM RO EP Page 6 of 13 NRC March 2014

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o=--Ia NINE MILE POINT NUCLEAR STATION

./;y,,ij~~~*~ . .

8. d. IF the location of the alarm is a C02 p protected fire zone, state this SAT I UNSAT announcement following the message STD: Per the turnover above:

determines the area is not C02 protected and determines this

~'This is a C02 protected area. All step is not applicable.

personnel shall immediately evacuate the (state building, location, and elevation) and all areas adjacent to and below this location."

9. e. Take the GAitronics system out of the p SAT I UNSAT Merge Mode, unless OSC has been STD: Per the turnover activated determines the OSC is not activated. On the GAITRONICS, pushes UP on the MERGE switch. Observes the RED MERGE light is not lit.

Pushes DOWN on the OUTDOOR SPEAKERS and ADM ISOLATE switches to reactivate those speakers.

10. f. If the Fire Brigade Leader does NOT p SAT I UNSAT respond within 60 seconds, repeat Steps STD: Determines the FBL 1a- 1c responded and this step is not Cue: Inform the operator the Fire Brigade applicable.

Leader has responded.

11. g. Notify the SM if the fire is confirmed p SAT I UNSAT STD: Determines the SM has already been notified per the turnover.

JPM RO EP Page 7 of 13 NRC March 2014

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o~-~~

NINE MILE POINT NUCLEAR STATION t~~~~~~:,

'  ; ;', ; ;:, \'

}*1'f:;:;**:r ..... . . ..,.

12. Turn up volume on station radio base p SAT I UNSAT

~onsole, including Oswego County fire STD: On the station radio base frequency console, Turns up the volume including the one labeled "Oswego County Fire Control"

13. If this is a confirmed fire and it is outside the p SAT I UNSAT protected area, then request off-site fire STD: Per the turnover, the fire assistance. Call Oswego County 911Center is not outside the protected (343-1313) and request off-site fire area and determines this step assistance is NA
14. If requested by Fire Brigade Leader, then call p SAT I UNSAT Oswego County 911 Center (343-1313) and STD: Per the cue, determines request off-site fire assistance this step is NA Cue: As the FBL, inform the operator that off-site fire assistance is not required.
15. If off-site assistance is requested, then p SAT I UNSAT inform the Security Central Alarm Station STD: Determines off-site (X2872) that off-site fire assistance has been assistance was not required requested and determines this step is NA
16. If required, initiate any Special Operating p SAT I UNSAT Procedures OR Emergency Operating STD: Per the cue determines all Procedures applicable SOPs/EOPs have Cue: As the SM/CRS, inform the operator already been entered.

that all applicable SOPs/EOPs have been entered and actions are being carried out JPM RO EP Page 8 of 13 NRC March 2014

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o=-~8 NINE MILE POINT NUCLEAR STATION

" *' ,' <,' ~

 ; .., t:~~ *M,

17. If a discharge of Halon or C02 occurs, p SAT/ UNSAT reference EPIP-EPP-11, Hazardous Material STD: Per the turnover, Incident Response, N1-0P-21C, Fire determines this area is not Protection System - LP/HPC02, N1-0P-21D, protected by Halon or C02 Fire Protection System - Halon 1301, N2-0P-45, Fire Protection Carbon Dioxide, and N2-OP-46, Fire Protection - Halon
18. Check Process Radiation Monitors to p SAT/ UNSAT determine if there is any rise in effluent STD: At the DRMS computer activity screen, observes radiation Cue: The radiation monitors do not show any levels on the STACK.

rise in effluent activity Determines per the cue that radiation monitors do not show any rise.

19. If SM implements a local area/building p

~vacuation, then perform duties in EPIP-EPP-OSA Cue: As the SM, inform candidate the Turbine Building is to be evacuated and provide candidate with a prepared (last page of JPM) EPIP-EPP-5A, Attachment 1 Evacuation Form

  • Place the GAitronics system in the Merge Mode
20. Sound the Evacuation Alarm for 10 seconds. p JPM RO EP Page 9 of 13 NRC March 2014

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NINE MILE POINT NUCLEAR STATION

21. Makes the evacuation announcement per the provided Evacuation Attachment.

Cue: As the Unit 1 SM, inform the operator to leave GAITRONICS in MERGE.

Cue: When necessary, inform the operator the alarm and announcement have been repeated.

22. If fire is confirmed, then ensure the SAT/ UNSAT unaffected Unit SM is notified STD: Contacts the Unit 1 SM Cue: As the Unit 1 SM, inform the operator and informs him of the Fire.

you have been informed.

JPM RO EP Page 10 of 13 NRC March 2014

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NINE MILE POINT NUCLEAR STATION

23. When notification is received that the fire is p SAT I UNSAT out and the event may be terminated, then STD: Acknowledges report from perform the following the FBL that the fire is out and Cue: As the FBL, inform the operator that the drill may be terminated the fire is out and the drill may be terminated.
24. a. Place GAitronics system in the Merge p SAT I UNSAT Mode STD: Determines GAITRONICS is already in MERGE by observing the RED MERGE light lit.
25. b. If the event is a drill, make the following p SAT I UNSAT announcement preceding the fire alarm:

STD: Makes the following announcement into the "This is a drill, this is a drill." Handset (or similar) while holding down the talk

c. Sound the Station Alarm for 10 seconds, pushbutton or INST Switch:

and make the following announcement:

This is a drill, this is a drill "Attention, Attention, this is (an actual Sounds the station alarm for event) (a drill). The fire event is approximately 10 seconds.

terminated."

Attention, Attention, this is a drill. The fire event is Repeat alarm and announcement terminated.

Cue: The alarm and announcement have Repeats announcement been repeated.

Both the CRO Firefighting checklist and Turbine Building evacuation have been performed.

JPM RO EP Page 11 of 13 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Attachment 1, EMERGENCY ANNOUNCEMENT LOCAL AREA/BUILDING EVACUATION (No emergency classification has been declared)

Instructions: (check boxes to select appropriate announcement)

1. Place GAitronics in Merge,
2. Sound the EVACUATION alarm for 10 seconds
3. Announce (if checked, include in announcement),

X a. Attention, Attention all personnel, This is X a drill o is an actual emergency X b. Nine Mile Point (Unit 1 ~is

. location or building to b~cuated) ordering an evacuation of the (Unit 1 @: (Provide specific TURBINE BUILDING X c. Due to: (provide conditions necessitating the evacuation)_ _...:..A-'-'F'--'1"-R=E=------

X d. All personnel are to leave the (Unit 1 ~ TURBINE BUILDING (area/building).

o 1. Staying clear of _ _ _ _ _ _ _ _ _ _ _ _ (area/elevation) and reporlro _______________________

OR X 2. Using the closest possible exit, and reporl to RP ACCESS X e. Accountability is being performed; all personnel shall reporl to an assembly area, card in and remain in the area until furlher notice.

X f. Personnel in protective clothing should (select appropriate):

[J 1. Leave the area removing PC=s as indicated at the step off pad.

OR X 2. Leave the area immediately and obtain Radiation Protection assistance at the control point.

X g. I repeat, This is X a drill o is an actual emergency

4. Repeat the alarm and announcement.
5. Consult with opposite Unit's SM and determine if GAitronics should be left in Merge (required for dedared emergencies) for the duration of the event.

JPM RO EP Page 12 of 13 NRC March 2014

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NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • You are the on-shift Control Room Operator (CRO).
  • The SM has been notified of a confirmed fire in the Unit 2 Turbine Building, 250' Elevation Truck Aisle.
  • This area is not a C02 or Halon Protected Area.
  • The OSC has not been activated.
  • This is a drill Evaluator: Ask trainee if he/she has any questions after presenting initial conditions

{Operators Name), Perform the CRO actions for the fire per EPIP-EPP-28, Attachment 1 JPM RO EP Page 13 of 13 NRC March 2014

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0~ ~~eDF NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC SRO Admin C0-1 Revision: 0.0

Title:

Determine the Severity of a Reactivity Event and Actions Required Approvals:

Signature I Printed Name Developed By ------------------------------------ David Huff 12/18/2013 Validated By Carl Crawford 12/11/2013 Facility Reviewer Aaron Armstrong Approximate Duration : _____2_0.:..___m_i_n-=-u-=-te.::..._s:...._____

Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: ___________________ Date:

JPM SRO CO-l Page 1 of 11 NRC March 2014

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a)orntventureof--.J 0~ -:,'~eDF NINE MILE POINT NUCLEAR STATION References

1. N2-0P-96, Reactor Manual Control and Rod Position Indication System
2. CNG-OP-3.01-1000, Reactivity Management JPM SRO C0*-1 Page 2 of 11 NRC March 2014

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o~lon ~~eDF NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operators ability to determine the actions necessary for a mispositioned control rod and provide a recommendation for the Reactivity Management Issue Severity Level.
2. Task Information:
a. CNG-OPS301-00006, Report Reactivity Management Incidents
b. K/A 2.1.37 (4.6) Knowledge of procedures, guidelines, or limitations associated with reactivity management.
3. Evaluation I Task Criteria Perform Classroom No No Yes
4. Recommended Start Location
a. Training Classroom
5. JPM Setup (if required)
a. Ensure book carts are available for the operators to use and that there is an up to date copy of N2-0P-96 and CNG-OP-3.01-1000 JPM SRO CO-l Page 3 of 11 NRC March 2014

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0=:-n-"'" -::~eDF NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO C0-*1 Page 4 of 11 NRC March 2014

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0~ ~~eDF NINE MILE POINT NUCLEAR STATION Given:

  • The plant completed a rod pattern exchange at 72% power at 03:00 this morning.
  • At 03:15, reactor power was raised to 80%.
  • At 7:00, the crew determines control rod 02-43 was supposed to be withdrawn to position 42 per the RMI but was inadvertently withdrawn to position 44.
  • Rod 02-43 has been mispositioned for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 45 minutes.
  • No predictor case has been run with the Control Rod mispositioned.
  • You are the Control Room Supervisor (CRS)

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions

<",,;-,. ".:), .}cf>:, "1~;~~:' u' ,*<

~~~NtJJ~:;~: * ** ~~~=:~~:;.s ~=:~~a~~~e;:~::~~er~::~:~:~~~:s::;c:~~~t;od mis-Management Issue Severity Level for this event per CNG-OP-3.01-1000.

  • Document your results on the provided worksheet.
1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used JAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the STD: Obtains any of the procedure.

following as necessary to determine the plant impact:

  • N2-0P-96
  • CNG-OP-3.01-1000 The following steps may be performed in any order.

JPM SRO CO-l Page 5 of 11 NRC March 2014

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0~ ~~eDF NINE MILE POINT NUCLEAR STATION The Answer Key attached to this JPM may be used to assist in grading of the below steps.

When grading the below steps, the operator may choose to use different wording on the worksheet then what is on the answer key to represent the actions taken.

This is acceptable, provided the intent and answer is obvious to the Evaluator. If the Evaluator has a question as to what is documented on the worksheet, then the Evaluator may verbally question the operator to determine the intent. If the Evaluator verbally questions the operator as to what is documented, the answers the operator provides may be used to assist with the grading of the below steps.

The operator may include additional actions not listed below on the provided worksheet. This is acceptable but only the information in Steps 4 through 8 needs to be on the worksheet.

3. Per N2-0P-96, performs the following s SAT I UNSAT actions:

STD: Determines per N2-0P-96 that the SM needs to be

  • Notify the SM notified. Documents the SM notification on the provided Cue: If contacted as the SM, acknowledge worksheet.

the notification.

4.
  • IF a Control Rod was found mispositioned s when Control Rod movements were NOT being performed AND a periodic OR predictor case has NOT been run with the Control Rod(s) mispositioned AND Reactor power is above 50%, reduce Reactor power by 40 MWe.

JPM SRO C0-1 Page 6 of 11 NRC March 2014

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NINE MILE POINT NUCLEAR STATION

  • s o On-Call Reactor Engineer o General Supervisor Operations -

Unit 2 Cue: If contacted as the RE or GSO, acknowledge the notification and inform the operator you have no further direction at this time.

6.
  • Provide the Reactor Engineer with the s following information about mispositioned Control Rod(s):

o Location o Position o Duration

7.
  • Initiate a CR in accordance with CNG-CA- s 1..01-1000 to document the mispositioned Control Rod event regardless of the apparent cause.
8. Per CNG-OP-3.01-1000, Determines a s recommended Reactivity Management Issue Severity Level The Operator has completed the JPM hand out and returned it to the Evaluator.

JPM SRO CO-l Page 7 of 11 NRC March 2014

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CENG. J a JO;nt ventu"' of o~l.uon -::~eDF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate

  • Notify the Shift Manager
  • Reduce Power by 40 MWe
  • Contact Reactor Engineer (RE) and General Supervisor a*perations
  • Provide the RE with the mispositioned rod Location, Position, and Duration (Rod 02-43, At position 44, Been mispositioned for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 45 minutes).
  • Initiate a Condition Report (CR)

Severity Level 2 JPM SRO CO-l Page 9 of 11 NRC March 2014

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0~ -!,eDF NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • The plant completed a rod pattern exchange at 72% power at 03:00 this morning.
  • At 03:15, reactor power was raised to 80%.
  • At 7:00, the crew determines control rod 02-43 was supposed to be withdrawn to position 42 per the RMI but was inadvertently withdrawn to position 44.
  • Rod 02-43 has been mispositioned for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 45 minutes.
  • No predictor case has been run with the Control Rod mispositioned.
  • You are the Control Room Supervisor (CRS)

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Determine ALL required actions for this rod mis-positioning. Additionally, provide the recommended Reactivity Management Issue Severity Level for this event per CNG-OP-3.01-1000.

Document your results on the provided worksheet.

JPM SRO CO-l Page 10 of 11 NRC March 2014

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NINE MILE POINT NUCLEAR STATION JPM Worksheet JPM SRO C0-*1 Page 11 of 11 NRC March 2014

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0~ ~:eoF NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC SRO Admin C0-2 Revision: -0.0 ----

Title:

Determine Plant Impact for Inoperable Unit Cooler Approvals:

Signature I Printed Name Developed By ~ David Huff 12/18/2013 Validated By Carl Crawford 12/11/2013 Facility Reviewer Aaron Armstrong ' I/"3 I/zo t 't Approximate Duration: 30 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

JPM SRO C0-2 Page 1 of 10 NRC March 2014

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0~ ~:eoy NINE MILE POINT NUCLEAR STATION References

1. N2-0P-53E, Standby Switchgear/Battery Room Ventilation System
2. NMP Unit 2 Technical Specifications JPM SRO C0-2 Page 2 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operators ability to determine the plant impact of an inoperable unit cooler.
2. Task Information:
a. NS-PSllS-02003, Initiate Action to Comply With Technical Specifications
b. K/A 2.1.32 (4.0) Ability to explain and apply system limits and precautions.
3. Evaluation I Task Criteria Perform Classroom No No Yes
4. Recommended Start Location
a. Training Classroom
5. JPM Setup (if required)
a. Ensure book carts are available for the operators to use and that there is an up to date copy of N2-0P-53E and Unit 2 Technical Specifications.

JPM SRO C0-2 Page 3 of 10 NRC March 2014

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0~ ~,eDF NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO C0-2 Page 4 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Given:

  • The plant is operating at 100% power.
  • While taking building rounds, an operator notices the Division 1 Chiller Equipment Room is warmer than normal.
  • Upon investigation, operators found 2SWP*V221A, HVC*UC103A INLET ISOL valve shut.
  • All attempts to re-open 2SWP*V221A have failed.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions

~~tl'j~;; ** ' (Operators Name), Determine the impact of this valve failure on plant

~;~~~:*.*~~*~~iR.*I*.'f~ *~: ""'/ operations. Document your results on the provided worksheet.

,; r ,~: ' '> . *.. . ..

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of the reference material and p SAT I UNSAT review I utilize the correct section of the STD: Obtains any of the procedure.

following as necessary to determine the plant impact:

  • N2-0P-53E
  • PID 53E
  • PID 11J
  • Unit 2 Technical Specifications The following steps may be performed in any order.

JPM SRO C0-2 Page 5 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION The operator may choose to use different nomenclature to represent the affected component. This is acceptable provided it is obvious to the evaluator which component is affected. The Evaluators Aid at the end of this JPM may be used to assist in the grading of the below steps. The listing of the references on the Evaluators Aid is for ease of grading and review by the Evaluator, however it is not required for successful completion of the JPM.

3. Determines the following: p
  • The closure of 2SWP*V221A makes 2HVC*UC103A inoperable
4.
5.
  • Determines TS 3.7.3 Conditions A and B p are applicable.

JPM SRO C0-2 Page 6 of 10 NRC March 2014

NINE MILE POINT NUCLEAR STATION The Operator has completed the JPM hand out and returned it to the Evaluator.

JPM SRO C0-2 Page 7 of 10 NRC March 2014

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a joint venture of , J o~ton -!:eoF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate 2HVK*CHL1A, DIVISION 1 CONTROL AND RELAY ROOM CHILLER is INOPERABLE

' i ' ' ' '

document and section).

Enter TS 3. 7 .3, Conditions A and B. (N2-0P-53E, Attachment 1, Action 4)

Condition A: Restore Division 1 control room envelope AC subsystem for the Main Control Room area to OPERABLE status within 30 days.

Condition B: Restore Division 1 control room envelope AC subsystem f~r the Relay Room area to OPERABLE status within 30 days.

JPM SRO C0-2 Page 8 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • The plant is operating at 100% power.
  • While taking building rounds, an operator notices the Division 1 Chiller Equipment Room is warmer than normal.
  • Upon investigation, operators found 2SWP*V221A, HVC*UC103A INLET ISOL valve shut.
  • All attempts to re-open 2SWP*V221A have failed.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Determine the impact of this valve failure on plant operations. Document your results on the provided worksheet.

JPM SRO C0-2 Page 9 of 10 NRC March 2014

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0~ '-!::eoF NINE MILE POINT NUCLEAR STATION JPM Worksheet JPM SRO C0-2 Page 10 of 10 NRC March 2014

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0~ ~~eoF NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC SRO Admin EC Revision: 0.0

--=..::....::..__ __

Title:

Determine Components Which Need Protection Approvals:

Signature I Printed Name Developed By

~ David Huff 12/18/2013 Validated By Tom Tanguay 12/18/2013 Facility Reviewer Aaron Armstrong Approximate Duration: 30 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

JPM SRO EC Page 1 of 15 NRC March 2014

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0 =:""'ion ~*~eDF NINE MILE POINT NUCLEAR STATION References

1. S-ODP-OPS-0122, NMP Site Specific Equipment Protection Matrices
2. CN.G-0P-GL012, Equipment Protection Guideline JPM SRO EC Page 2 of 15 NRC March 2014

CENG~

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0~ ~~eDF NINE MILE POINT

  • NUCLEAR STATION Instructor Information A. JPM Information
1. Description
a. This JPM tests the operators ability to evaluate plant conditions and determine which components need to be protected.
2. Task Information:
a. NS-FLDSUP-013, Protect Plant Equipment.
b. K/A 2.2.14 (4.3) Knowledge of the process for controlling equipment configuration or status.
3. Evaluation I Task Criteria
  • ev<ltuation Method Perform Classroom Time Critical

. ' . . . . Task ' ,*

No No 1 L.G)O >1.0 Yes

4. Recommended Start Location
a. Training Classroom
5. JPM Setup (if required)
a. Ensure book carts are available for the operators to use and that there is an up to date copy of 5-0DP-OPS-0122 and CNG-0P-1.01-GL012.
b. Ensure a copy of the electrical print stick EE-001 series is available for the operators to review.

JPM SRO EC Page 3 of 15 NRC March 2014

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c. If multiple operators are going to perform the JPM at the same time, ensure each operator has a copy of 5-0DP-OPS-0122 and CNG-0P-1.01-GL012.

JPM SRO EC Page 4 of 15 NRC March 2014

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0~ ~*~eDF NINE MILE POINT NUCLEAR STAllON B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO EC Page 5 of 15 NRC March 2014

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0~ -::~eDF NINE MILE POINT 1

NUCLEAR STATION Given:

  • The plant is at 100% power and has just experienced a loss of 2NNS-SWG015
  • Prior to the loss of AC power, no equipment was out of service.
  • The crew has stabilized the plant and is in the process of determining the cause of the loss of power.
  • The Shift Manager has assigned you the task of determining which plant components will need to be protected based on this event.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions l~A~G.i (Operators Name), Determine which plant components need to be QJE* . protected per CNG-0P-1.01-GL012 and 5-0DP-OP5-0122. Document your results on the provided hand out.

Note: Ignore any equipment not specifically covered by 5-0DP-OP5-0122.

v;i:.;*:

~0 *
:*':'

~i-'

  • t<1~~Vf{;

. \c '

.~t;:;:~.*.t:-lRFORH,A~E
; ~ . . ' *. *. .*. . * :

.ACT~CODE*

} ...* ;p'j'§,{'NA .*

  • *evAWATOR

'< *:;.-\ ~,

1. Provide repeat back of initiating cue p SAT I UN SAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of CNG-OP-1.01-GL012 and s- p SAT I UN SAT ODP-OPS-0122 and review I utilize the STD: Current version of CNG-correct section of the procedure OP-1.01-GL012 and 5-0DP-OPS-0122 obtained and reviewed lAW CNG-PR-2.01-1000, Document Control.

JPM SRO EC Page 6 of 15 NRC March 2014

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3. Reviews any or all of the following SAT I UNSAT documents to determine which plant STD: Obtains one or more of components have been lost:

the listed documents and

  • N2-SOP-03, Loss of AC Power determines which components
  • N2-0P's, Operating Procedure Lineups
  • Additional EE-OOl's as applicable The following steps may be performed in any order.

The operator may choose to use different nomenclature to represent the affected components and equipment which will need to be protected. This is acceptable provided it is obvious to the evaluator which components are affected and which components the operator is choosing to protect. The Evaluators Aid at the end of this JPM may be used to assist in the grading of the below steps.

4. Determines the following components are p affected by the loss of 2NNS-SWG015:
5.
  • 2CCP-P1B, REAC BLDG CLOSED LOOP p COOLING WTR PUMP lB JPM SRO EC Page 7 of 15 NRC March 2014

a JOint venture of J 0~ ~::eoF NINE MILE POINT NUCLEAR STATION

  • p COOLING WTR BOOSTER PUMP 3B
7.
8.
9.
10. Reviews S-ODP-OPS-0122, Attachment 2 and P determines which components need to be protected based on the following components being unavailable:

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0~ -.:~eDF NINE MILE POINT NUCLEAR STATION

11.
12.
  • 2CCP-P3B, REAC BLDG CLOSED LOOP p COOLING WTR BOOSTER PUMP 3B

"-.- . " ,. << ~,; >-lt ' ... , '41: ,.,,_-

  • ~~~4;~p
  • Sn#a~2Ntl$:S:w.GblS~"VJ::;
. §iL,,. , *w~
  • ' .cct~,:;~pi!iinpc~mi5 ai1tti4t:Jtor
  • _*_ * *J
  • ~if.n.ls~5WG1.4'..6 JPM SRO EC Page 9 of 15 NRC March 2014

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14.
15.
  • 2.IAS-DRY3B, lAS DRYER B p The Operator has completed the JPM hand out and returned it to the Evaluator.

JPM SRO EC Page 10 of 15 NRC March 2014

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0~ ~,eDF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate CRD Pump A Control Room Pump Control Switch CRD Pump A Pump and Motor Breaker 2NNS-SWG014-7 CCP Pump A Control Room Control Switch CCP Pump A Pump and Motor Breaker 2NNS-SWG012-5 CCP Pump C Control Room Control Switch CCP Pump C Pump and Motor Breaker 2NNS-SWG14-9 CCP Booster Pump A Control Room Control Switch CCP Booster Pump A Pump and Motor

3. Breaker 2NNS-SWG013-9
4. CCP Booster Pump C Control Room Control Switch
5. CCP Booster Pump C Pump and Motor
6. Breaker 2NNS-SWG14-6 JPM SRO EC Page 11 of 15 NRC March 2014

CENG_

a]Ointventureof---J 0~ ~::eoF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate MG Set A Breaker 2NHS-MCC008-7EL WCS Pump A Control Room Control Switch Breaker 2NJS-US4D JPM SRO EC Page 12 of 15 NRC March 2014

CENG~

NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • The plant is at 100% power and has just experienced a loss of 2NNS-SWG015
  • Prior to the loss of AC power, no equipment was out of service.
  • The crew has stabilized the plant and is in the process of determining the cause of the loss of power.
  • The Shift Manager has assigned you the task of determining which plant components will need to be protected based on this event.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions

{Operators Name), Determine which plant components need to be protected per CNG-OP-1.01-GL012 and 5-0DP-OP5-0122. Document your results on the provided hand out.

Note: Ignore any equipment not specifically covered by 5-0DP-OP5-0122.

JPM SRO EC Page 13 of 15 NRC March 2014

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0~ -!~eDF NINE MILE POINT NUCLEAR STATION JPM Worksheet JPM SRO EC Page 14 of 15 NRC March 2014

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0~ --!::eoF NINE MILE POINT NUCLEAR STATION JPM SRO EC Page 15 of 15 NRC March 2014

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o=-- -::~eDF J NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC SRO Admin RC Revision: -0.0

Title:

Inspection of High Radiation Areas Approvals:

Signature I Printed Name Developed By ~ David Huff 12/18/2013 Validated By Carl Crawford 12/11/2013 Facility Reviewer Aaron Armstrong 1{!:. /zal'-j Approximate Duration: 30 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: -----

Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

JPM SRO RC Page 1 of 15 NRC March 2014

CENG .

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0~ ~,eDF NINE MILE POINT NUCLEAR STATION

  • References
1. GAP-RPP-01, Radiation Protection Program
2. GAP-RPP-02, Radiation Work Permit
3. GAP-RPP-07, Internal and External Dosimetry Program
4. GAP-RPP-08, Control of High, Locked High, and Very High Radiation Areas
5. 5-RAP-RPP-0703, Authorization to Exceed Administrative Dose Limits JPM SRO RC Page 2 of 15 NRC March 2014

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0~ ~*,eoF NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operators ability to evaluate radiological conditions and determine the appropriate work controls.
2. Task Information:
a. 5-RAP-RPP-08001, Control Access to Radiation Areas
b. K/ A .3.12 (3. 7) Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc
3. Evaluation I Task Criteria Perform Classroom No No Yes
4. Recommended Start Location
a. Training Classroom JPM SRO RC Page 3 of 15 NRC March 2014

CENG . J a JOint venture of 0~ -!~eo.F NINE MILE POINT NUCLEAR STATION

5. JPM Setup (if required)
a. Make enough copies of the RWP and Survey Map for each operator to have one.
b. Ensure book carts are available for the operators to use and that there is an up to date copies of the following:
1) GAP-RPP-01, Radiation Protection Program
2) GAP-RPP-02, Radiation Work Permit
3) GAP-RPP-07, Internal and External Dosimetry Program
4) GAP-RPP-08, Control of High, Locked High, and Very High Radiation Areas
5) S-RAP-RPP-0703, Authorization to Exceed Administrative Dose Limits JPM SRO RC Page 4 of 15 NRC March 2014

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0~ ~*,eoF NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO RC Page 5 of 15 NRC March 2014

CENG_* l ajo"t"Bntureof 0~ ~~eDF NINE MILE POINT NUCLEAR STATION Given:

  • The plant is operating at 100% power.
  • An operator must perform a valve lineup in the RWCU Pump P1A Room.
  • An RWP and survey map are provided.
  • There are no steam leaks in the room.
  • The operator's current year-to-date exposure is 1800 mrem TEDE.
  • The operator will be performing work for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in an average radiation field of 150 mremlhr.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Address the radiological aspects of performing this lineup and record your findings on the provided worksheet

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain one or more of the following p SAT I UNSAT procedures and review I utilize the correct STD: Current version of listed section of the procedure:

procedures obtained and

  • GAP-RPP-01 reviewed lAW CNG-PR-2.01-
  • GAP-RPP-02 1 000, Document Control.
  • GAP-RPP-07
  • GAP-RPP-08 The attached Evaluator Grading Sheets may be used to assist with the grading of the below steps. Steps 3 through 8 may be performed in any order.

JPM SRO RC Page 6 of 15 NRC March 2014

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0~ -!~eoF NINE MILE POINT NUCLEAR STATION Addresses radiological aspects of entering RWCU Pump PlA Room for inspection as follows:

  • Determines the radiological classification of the area
4.
  • Determines which Key is needed to p SAT I UNSAT access the area.

STD: Determines per the provided survey map that KEY H-20-2 is needed to access the area. Documents the key required on the provided worksheet.

When grading Steps 5 and 6, the operator may choose to use different nomenclature to represent the locations where the highest contact dose rate and highest dose rate at 30 em is. This is acceptable, provided the location description provided by the operator is obvious to the Evaluator. If the Evaluator has a question as to what location the operator is trying to describe on the worksheet, then the Evaluator may verbally question the operator to determine the location (i.e. the operator points to the location on the survey map). If the Evaluator verbally questions the operator as to the described locations, the answers the operator provides may be used to assist with the grading of Steps 5 and 6.

5.
  • Determines the highest contact dose rate p and location.

JPM SRO RC Page 7 of 15 NRC March 2014

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0~ -!:eoF NINE MILE POINT NUCLEAR STATION

6.
  • Determines the highest dose rate at 30 p em and location.
7.
  • Determines the RWP required to be used. p The Step 8 calculation is as follows:
  • 1800 mrem -Current Operator Exposure
  • The operator will work for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in a 150 mrem/hr radiation field.
  • Total radiation to be received is 2 x 150 = 300 mrem
  • Total dose the operator will have at completion of the job is 300 + 1800 =

2100 mrem.

8.
  • Determines if additional approvals are p required for the operator.

JPM SRO RC. Page 8 of 15 NRC March 2014

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O=:.uon ~;:eDF NINE MILE POINT NUCLEAR STATION Once the operator turns in the completed worksheet, determine if Step 8 above was completed successfully as indicated by the operator identifying that additional approvals are required for the operator to perform the work. If the operator did not correctly identify the need for approvals, then the JPM is complete and there is no need to perform the following additional steps. If the steps are not performed then they may be marked as NA. If the operator correctly identified the need for additional approvals, provide the following cue and second JPM worksheet Cue: {Operators Name), Identify the procedure and form required to be completed for the dose extension and the levels of approval needed for the dose extension. Record your findings on the worksheet below.

9. Provide repeat back of second initiating cue p SAT I UNSAT I NA Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.
10. Obtains S-RAP-RPP-0703 and review I utilize p SAT I UNSAT INA the correct section of the procedure.

STD: Current version of listed procedure obtained and reviewed lAW CNG-PR-2.01-1 000, Document Control.

Steps 11 and 12 may be performed in any order.

11. Determines the additional radiological p information as follows:
  • Determines the procedure and form required to be completed for the dose extension.

JPM SRO RC Page 9 of 15 NRC March 2014

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12.
  • Determines the approvals required for the P dose extension.

The Operator has completed the JPM worksheets and returned it to the Evaluator. The Evaluator has reviewed the worksheet to determine if any clarification is needed by the operator.

JPM SRO RC Page 10 of 15 NRC March 2014

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0~ -;:,eDF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate

1. Classify the Area (check one):

D Radiation Area

¥' High Radiation Area D Locked High Radiation Area D Very High Radiation Area

2. Designate the key to be obtained:

H-20-2

3. Designate the highest contact dose rate and the location:

230 mrem/hour, On the Pump

4. Designate the highest dose rate at 30 em and the location:

210 mrem/hour, Northeast Corner Piping

5. Designate the RWP required to be used (check one):

D The provided RWP is acceptable

¥' A Specific RWP should be requested

6. Evaluate the exposure for the operator:

D The expected exposure is acceptable without additional approvals

¥' Additional approval(s) (is)are required to receive the expected exposure JPM SRO RC Page 11 of 15 NRC March 2014

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0~ ~*,eoF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate

1. Identify the procedure and form required to be completed for the dose extension:

5-RAP-RPP-0703, Attachment 1

2. Check all appropriate boxes below for the approvals required for this dose extension:

./ Department Manager

./ General Supervisor of Radiation Protection D Plant General Manager D Site Vice President JPM SRO RC Page 12 of 15 NRC March 2014

8JOintventureof--.-]

0~ -:,*,eoF NINE MILE POINT NUCLEAR STATION 2"d JPM Handout and Worksheet (Operators Name), Identify the procedure and form required to be completed for the dose extension and the levels of approval needed for the dose extension. Record your findings on the worksheet below.

1. Identify the procedure and form required to be completed for the dose extension:
2. Check all appropriate boxes below for the approvals required for this dose extension:

D Department Manager D General Supervisor of Radiation Protection D Plant General Manager D Site Vice President JPM SRO RC Page 13 of 15 NRC March 2014

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0~ ~*,eoF NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • The plant is operating at 100% power.
  • An operator must perform a valve lineup in the RWCU Pump P1A Room.
  • An RWP and survey map are provided.
  • There are no steam leaks in the room.
  • The operator's current year-to-date exposure is 1800 mrem TEDE.
  • The operator will be performing work for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in an average radiation field of 150 mrem/hr.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Address the radiological aspects of performing this lineup and record your findings on the provided worksheet JPM SRO RC Page 14 of 15 NRC March 2014

a JOin! venture o f - - ]

0~ ~::eoF NINE MILE POINT NUCLEAR STATION .

JPM Worksheet D Radiation Area D High Radiation Area D Locked High Radiation Area D Very High Radiation Area

2. Designate the key to be obtained:
3. Designate the highest contact dose rate and the location:
4. Designate the highest dose rate at 30 em and the location:
5. Designate the RWP required to be used (check one):

D The provided RWP is acceptable D A Specific RWP should be requested

6. Evaluate the exposure for the operator:

D The expected exposure is acceptable without additional approvals D Additional approval(s) (is)are required to receive the expected exposure JPM SRO RC Page 15 of 15 NRC March 2014

Radiation Work Permit 0 Constellation Energy Nine Mile Point Nuclear Station Save Dose - Self Check -Always Work Safely RWP

Title:

Inspections, Tours, Rounds, Maintenance and Surveillances in th RCA (NOT for High Radiation or Locked High Radiation Areas)

RWPType:* ALARA Review Number: Comments: Unit 2 Standing RWP.

LOW RISK RWP 210000 Locked High Radiation Area: High Contamination Area:

No No PROTECTIVE CLOTHING RP may change protective clothing, respirator, or other requirements as work scope, location, and conditions chan 1/6/201 0 9:33:45AM Page 1 of 1

Survey#: 2RB-25378 Reactor Building 215' 13A WCS

  • P1A Room Date : 04/03/04@2300 Page : of

!1. - mRem/hr general area -contamination in dpm/1 No /3- detected unless otherwise noted .

tt. /3- mRad/hr general area -contamination on component in dpm/100cm 2

  1. @ cont -dose rate@ contact with component
  1. @ 30cm - dose rate @ 30cm from component -<----@+ - location of LAW

- - - boundary power level : 100%

rveyed by: DR.Biack 108 mRem 15 scfm V428A 204592

--~---~~--- -~ ---f WCS-V27A V385A WCS-V28A CCP-V2006A SOP Instrument lnst. # Cal Due date R0-2 5780 01/29/05

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o~lation 'j*~eDF NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC SRO Admin EP Revision: -0.0 ----

Title:

Emergency Classification (RPV Water Level, Unusual Event CU3.2)

Approvals:

Signature I Printed Name Developed By - - - - - - - - - - - - - - -David --- Huff

- 12/18/2013 Validated By Carl Crawford 12/11/2013 Facility Reviewer Aaron Armstrong I /,J IIC.CJI't Approximate Duration: 30 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

JPM SRO EP Page 1 of 13 NRC March 2014

CENG~

a Joint venture of  : J 0~ -!,eDF NINE MILE POINT NUCLEAR STATION References

1. EPIP-EPP-02, Classification of Emergency Conditions At Unit 2
2. Unit 2 EAL Chart JPM SRO EP Page 2 of 13 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operators ability to classify and declare an emergency e*vent within 15 minutes. THE operator shall also provide verbal and written notifications within 15 minutes of declaration.
2. Task Information:
a. NS-FLDSUP-013, Protect Plant Equipment.
b. K/A 2.2.14 (4.3) Knowledge of the process for controlling equipment configuration or status.
3. Evaluation I Task Criteria Perform Classroom Yes No Yes
4. Recommended Start Location
a. Training Classroom
5. JPM Setup (if required)
a. EP Packet containing the following forms in the order listed below (assembled per NAI-EPP-02):
1) EPIP-EPP-18, Attachment 1 (3 pages)

JPM SRO EP Page 3 of 13 NRC March 2014

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0~ ~~eDF NINE MILE POINT NUCLEAR STATION

2) EPIP-EPP-18, Attachment 1 Figure 1 & 2 (2 pages)
3) EPIP-EPP-18, Attachment 2 (2 pages)
4) EPIP-EPP-20, Attachment 1A (2 pages)
5) EPIP-EPP-20, Attachment 4 section E (1 page)
6) EPIP-EPP-20, Attachment 6A (2 pages) 7:) EPIP-EPP-20, Attachment 6B (3 pages)
8) EPIP-EPP-08, Attachment 1 ( 4 pages)
9) EPIP-EPP-18, Attachment 8 (1 page)
10) EPIP-EPP-18, Attachment 3, 4, 5, 6, 7 ( 1 page each)
b. Copy of the current version of EPIP-EPP-02 Attachment 1, Unit 2 EAL Flowchart
c. Copy of the current version of EPIP-EPP-02-EAL, Emergency Action Level Matrix Unit 2
d. Copy of the current version of EPMP-EPP-0102, Unit 2 Emergency Classification Technical Bases
e. If laminated copies used,
1) Vis-a-Vis wet erase marker(s) or equivalent 2-) Wet and dry paper towel(s) or equivalent
f. Clock or timer capable of displaying minutes and seconds JPM SRO EP Page 4 of 13 NRC March 2014

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NINE MILE POINT NUCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial*conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM SRO EP Page 5 of 13 NRC March 2014

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a JOint venture of J 0~ -::~eDF NINE MILE POINT NUCLEAR STATION Given:

  • The Plant is in mode 5.
  • The Reactor was shut down 5 days ago at 0100.
  • The Spent Fuel Pool gates are still installed
  • RPV water level is being raised in preparation to remove to Spent Fuel Pool gates and is currently 6 inches above the RPV flange.

Then:

  • A recirc. loop piping leak develops on the 'A' recirc. loop that cannot be immediately isolated.
  • Cavity level slowly drops below the RPV flange and has been below the flange for 15 minutes.
  • Current level is 350 inches on shutdown range and is slowly lowering.
  • Radiation levels remain unchanged.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Evaluate the need to classify conditions provided per EPIP-EPP-02. If emergency condition exists, complete the SM/ED checklist through Step 9 (Part 1 Notification Fact Sheet only)

,,," < ::4~~)~~~"'"' s:~9~~**:

> ~ P/S/tfA ,..,.

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary used per CNG-OP-1.01-2001, Communications and Briefings
2. Obtain a copy of the SMIED Checklist (EPIP- p SAT I UNSAT EPP*-18 Attachment 1) and review I utilize the correct section of the procedure STD: Preassembled SM/ED package is obtained (first five pages are EPIP-EPP-18, Att. 1)

JPM SRO EP* Page 6 of 13 NRC March 2014

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0~ -!:eoF NINE MILE POINT NUCLEAR STATION

3. Using the given initial conditions, the SM/ED p SAT I UNSAT will.classify the emergency per EPIP-EPP-02 STD: Determines EAL CU3.2, (within 15 minutes of indications available in UNUSUAL EVENT is the highest Control Room) as a UNUSUAL EVENT per classification.

CU3 . 2 The operator performing the JPM will take the ED responsibility.

4. For Site events, contact the opposite unit SM s SAT/ UNSAT and determine which SM will take the ED STD: Per EPIP-EPP-02, responsi bi Iity determines the operator will assume the role of the Cue: If Unit 1 SM contacted, report that Emergency Director.

Unit 1 is not in any EALs.

The declaration and the time are the pass/fail criteria, NOT the reason given or the assumption of the SM/ED position.

5. Announce to Control Room staff you are now p assuming SM/ED position and duties, and you are now declaring (state emergency classification level), and provide reason for classification/declaration/upgrade within 15 minutes of the conditions being available in the Control Room that an EAL has been met or exceeded.

Time Declared _ _ _ _ __

IF the announcement for a ground attack has been made as required by EPIP-EPP-10, THEN make no further announcements until safety is assured through coordination with security.

JPM SRO EP Page 7 of 13 NRC March 2014

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6. The SM/ED shall direct Communications Aide, s SAT I UNSAT Chemistry Tech and R.P. Tech to report to STD: Contacts the Chemistry the Control Rooms.

and RP Techs and Communications Aide and Cue: After approximately one minute, directs them to report to the identify that you are reporting as the control room.

Communications Aide (Chemistry Tech and R.P. Tech if directed to report).

7. Contact the opposite Unit control room and: s SAT I UNSAT
  • Inform SM of Drill I Actual Emergency STD: Contacts the Unit 1 SM and classification and informs them that this is a
  • Obtain opposite unit status Drill I Actual Emergency and
  • Direct SM to notify the ERO (ERONS) per provides the classification.

EPIP-EPP-20 Attachment 4 Additionally, directs the Unit 1 SM to notify the ERO. The operator may direct the Unit 1 Cue: As the Unit 1 SM, acknowledge all SM to either ACTIVATE or NOT provided information. Inform the ACTIVATE the emergency operator that Unit 1 is operating at facilities. Either action is rated power.

acceptable. Obtains the operating status of Unit 1 Because the classification is an Unusual Event, no evacuation is required.

However the operator has the discretion to direct an evacuation of either the protected area and/or a local area. This is an acceptable action, but not required.

8. Using EPIP-EPP-18, Attachment 1, Figure 1 p SAT I UNSAT flowchart determine the appropriate STD: Determines no evacuation evacuation and accountability.

is required.

Because the classification is an Unusual Event, there are very few required blocks to be filled out by the ED on EPIP-EPP-18, Attachment 2 Emergency Announcement. The PASS/FAIL criteria is based on providing direction to perform the announcement and not in the filling out the attachment.

JPM SRO EP Page 8 of 13 NRC March 2014

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0~ '-::~eDF NINE MILE POINT NUCLEAR STATION 9.

Emergency Announcement and direct the app:ropriate announcement to be made to the site.

Cue: As necessary, acknowledge the direction to make the emergency announcement. Inform the operator the emergency announcement is complete.

The attached Evaluators Aid has an answer key for correctly filling out EPIP-EPP-20, Attachment 1A. Only those steps marked with a" * "and red "box" need to be filled out correctly to receive a PASS on the next step.

10. Complete EPIP-EPP-20 Attachment 1A, Part 1 P Notification Fact Sheet. Include information frol'!l Unit 1 as applicable.

The Comm. Aid must have time to begin roll call and check blocks for State Emergency Communications Center (SECC) and Oswego County Warning Point within 15 minutes of the declaration. Handing the completed NFS Part 1 to the Comm. Aide at the 15 minute point does not meet the time requirement.

11. Provide completed Part 1A Notification Fact p sheet to the Communications Aid so that off site notifications are initiated within 15 minutes of the EAL declaration Cue: As Communications Aid, accept the Part 1 Notification Fact sheet and state that you will proceed with the notifications SM/ED checklist completed through Step 9 (Part 1 Notification Fact Sheet only)

JPM SRO EP Page 9 of 13 NRC March 2014

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0~ ~:eoF NINE MILE POINT NUCLEAR STATION JPM SRO EP Page 10 of 13 NRC March 2014

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0~ ~,eDF NINE MILE POINT NUCLEAR STATION Evaluator's Answer Key Do Not Provide to Candidate EMER.GENCY NOTIFICATIONS EPIP-EPP-20 Revision 02900 Page 15of38 Attachment 1A: Nine Mile Point Nuclear Station Notification Fact Sheet- Part 1 INJTI~L ROLL CALL MUST BE COMPLETED BY: (TIME) Sheet 1 of 5

{Do nat say .il'efM in ilatics)

PicA: MP 1t1oe dl~~~~e, DR!A A

  • wat a0oot 10 ~ ~hen av. "'This is lo R!DOrt ~n incident a Nine Mile Point standby for roll call.-

I a Oswego County I I" lNIIIeded NMP ~it I

" 5tH Emergency r= JA Filzpalric:t Power Plant Notification #

Ccnmunicalions Center (SECC) Wii!Tiiiig Pont (not ieq"d in 15 min) (not req"d in 15 nm) a=..

1.

This mesYgl! is being bilnsmitled on:(dalel 31 (Wne -24 hr} via: A. RECS B. Other

-ut<_.

2. This is: (AlAn adUal ( a) All Exercise 3.

F The Eml!rgenc:y Classilicmon is:

B. Ak!rt EVEnt C. Sill! Area Emergency D. Gener.ll Emergency E. Emergency T erminilled F. Othl!r:

D*

4.

5.

ThisE ctii'5Silicition- decliftd on*...tcWel Today Release of mlioal:tive Mllerials due lo the alassilied ewnt ali!ne-24hrl TJ.me or: Dec. D*

~re-B. ReiNa below federilllmits (OOCM). n To all'niJsphefe u To Waler C. ReiNa~ federilllimils (ODCM), n To all'niJsphefe u To Water D. I..WncJniiDnM:I R!IAsl! reauirina l!'llillualion.

6. ~fallowing Pmlective Adions ill"l! I"'!CCOIIIIIHdlo be impleiiiC!IIIIed u soon f t pnctic;ll:

need far prolecliW! actions outside 1ht! site bcund;;uy B. Ewaa~ale iiOd i~ !he Kl Plan for !he following ERPAs and <Ill remaining ERPAs monitor the Emergency Alert Sys1Em. 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 2!6 27 28 2Q D*

C. Shelll!r-in-plaicl! iiOd implement the Kl Plan for !he following ERPAs AND all mnaining ERPAs moniiiDrlhe Emergency Alerts~ 1 2 3 4 56 1 8 9 10 11 12 13 14 15 16 11 t8 111 20 21 22 23 24 25 26 21 2B 29 7_ U1 BIRI e¥1!Rt ~ ~nd other significilnt illftlrllnmon: ("If nelli!S5ar)'. Do nat X U2 Sill!

EAL#

cu

~ EAl description)

D*

3.2 8_ RNCtor Stmis: l.klit1: ~ng r!) Shutdown {dale!

Shutdown (dale\ - S 31 (lime* 24 hr dockL__

0 ~~lime-24hrdock)_ 01:00

~it 2: A. Qperaling

9. A. EleoiHI wind 5peM l 3

mill!slhr at 200 ft A. EleAied wind din!Ction (fran l 11 idl!pi!S at B. Ground wind speed 9 l'lilesl1w 31 30 ft. D*

10.

11.

200t.

Sbbilitv Clilss: A 6 c 0 B. Ground wind dileetion (from)~~ at 30ft_

(E) F G D*

12.

Rl!portH by: (ComiTIIII'Iic:alor 111311M!l ai!Tet No. (315)

ASK "Does Oswego County or Nl!wYark State IIHdfurtherclilliiCillion on any inl'annmon? (provide as appcpiate) THEN "This is the end of Ute IIIII!S!YE. standbv for verilicman roll Cilll-.

Check those i!Mllvl!d in wriicalian ral cal u Slate Emergency CommuniCilllions Center

{SECC) I Ol Oswego County Wilming Point I tl JA Fllzpalridt PCIWI!f"Piant I u Unalfecll!d NMP Unit THEil STA l'E: "Nine Mile Point out

  • time: * (time- 24 hr cloct)

Apprwed by; (SUIEO or EDJRM):

Print name: Print Name Signatu~:

Signature JPM SRO EP Page 11 of 13 NRC March 2014

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a Jdnt ventl.Jre of J 0~ ~~eDF NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • The Plant is in mode 5.
  • The Reactor was shut down 5 days ago at 0100.
  • The Spent Fuel Pool gates are still installed
  • RPV water level is being raised in preparation to remove to Spent Fuel Pool gates and is currently 6 inches above the RPV flange.

Then:

  • A recirc. loop piping leak develops on the 'A' recirc. loop that cannot be immediately isolated.
  • Cavity level slowly drops below the RPV flange and has been below the flange for 15 minutes.
  • Current level is 350 inches on shutdown range and is slowly lowering.
  • Radiation levels remain unchanged.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Evaluate the need to classify conditions provided per EPIP-EPP-02. If emergency condition exists, complete the SM/ED checklist through Step 9 (Part 1 Notification Fact Sheet only)

JPM SRO EP Page 12 of 13 NRC March 2014

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0~ -!,eDF NINE MILE POINT NUCLEAR STATION Emergency Meteorology Report Last 15 Minute Emergency Meteorology Report Data Data from Nine Mile Point Met System Date: Today Time (Local): Now Elevated Ground 200' Wind Speed (Main) 13 (mph) 30' Wind Speed (Main) 9 (mph) 200' Wind Dir From (Main) 110 (deg) 30' Wind Dir From (Main) 112 (deg) 200' Delta Temperature 0.05 (deg F) 100' Delta Temperature 0.7 (deg F)

Stability Class E Stability Class c 30' Air Temperature 50 (deg F) Precipitation (15 min) 1.02 (in)

JPM SRO EP Page 13 of 13 NRC March 2014

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NINE MILE POINT .

NUCLEAR STATION Training Id: 2013 NRC Simulator S-1 Revision: -----=----- 0.0

Title:

Rotate Drywell Unit Coolers (Alternate Path)

Approvals:

Signature I Printed Name Developed By ___d:_:__ __:=-=-==---__;;D::...::a=--=v...:...:id::........:....H..::.u.:...:.ff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer Aaron Armstrong Approximate Duration: 15 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

JPM S-1 Page 1 of 9 NRC March 2014

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NINE MIL£ POINT NUCLEAR STATION References

1. N2*-0P-60, Drywell Cooling
2. N2-ARP-873200 JPM S-1 Page 2 of 9 NRC March 2014

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NINE MILE POINT NLCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operator's ability to rotate the Drywell Unit Coolers 3A and B and respond to a degraded condition on Unit Cooler 3B
b. This JPM is considered alternate path because once the unit coolers have been rotated, the operator will receive indication that the unit cooler placed in service has degraded. The operator will be required to respond per the applicable ARP and place the previously running unit cooler back in service and place in pull to lock the degraded unit cooler.
2. Task Information:
a. N2-223004-01002, Rotate Drywell Unit Coolers 3A and 3B
b. K/A 223001, A4.12 (3.5/3.6)
3. Evaluation I Task Criteria Perform Simulator No Yes Yes
4. Recommended Start Location
a. Unit 2 Simulator JPM S-1 Page 3 of 9 NRC March 2014

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5. Simulator Setup (if required)
a. This JPM can be performed in Mode 1, 2, or 3 as long as power is available to both Unit Coolers 3A and B
b. Ensure Drywell Unit Cooler 3A is running and 3B is secured
c. Set Malfunction PC36B, DW Unit Cooler 3B Vibration High on Trigger 1 with a 3 second delay.
d. Set the following Event Trigger on Event 1:

Event Action: HZLCW2CCPMOV3A{1)==1 .AND. HZLPC1DRSB03{2)==1 Command: Blank

Description:

2CCP-MOV3A Green Light On and UC3B Red Light On

6. JPM Setup (if required)
a. Prepare a copy of N2-0P-60, Section 2.0. Include a copy of the Precautions and Limitations. No steps need to be marked up.
b. If this JPM is run multiple times, ensure ARP 873214 is erased after each JPM.

JPM S-1 Page 4 of 9 NRC March 2014

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NINE MILE POINT NLCI.EAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that*additional verification will not be provided.

JPM 5-l Page 5 of 9 NRC March 2014

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0:::---- ~;eof NINE MILE POINT NUCLF.AR STATION

  • Given:
  • The plant is in Mode 1
  • Unit Coolers 3A and 3B need to be rotated to equalize runtime Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Rotate Drywe/1 Unit Coolers by starting 2DRS-UC3B and stopping 2DRS-UC3A in accordance with N2-0P-60, Section F.2.0
1. Provide repeat back of initiating cue p SAT I UNSAT C':Je: Acknowledge repeat back providing STD: Proper communications correction if necessary. used JAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-0P-60 and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-0P-60 obtained and section F.2.0 reviewed JAW CNG-PR-2.01-1 000, Document Control.
  • 2DRS-UC3A and UC3B should be rotated occasionally to equalize operating time and equipment wear.
  • All control switches and indicating lights are located on 2CEC*PNL873, unless otherwise noted.
3. Open CCP-MOV3B (3A), UNIT COOLER 3B p (3A) RBCLC INLET to the standby unit cooler.

JPM S-1 Page 6 of 9 NRC March 2014

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NINE MILE POINT NLCLF_AR STATION

4. Start standby unit cooler DRS-UC3B (UC3A) p
5. Stop DRS-UC3A (UC3B) by placing control p switch to STOP Two seconds after completion of the following step, a high vibration condition will occur on 2DRS-UC3B. The operator will reference ARP 873214 which will direct restarting UC3A and placing in Pull To Lock UC3B
6. Close CCP-MOV3A (3B), UNIT COOLER 3A p (3:B) RBCLC INLET to the standby unit cooler.
7. Recognizes and reports Annunciator 873214 p SAT I UNSAT in alarm STD: Proper alarm response used JAW CNG-OP-1.01-2003, References ARP for 873214 Alarm Response and Control.
8. IF 2DRS-UC3A, UNIT COOLER is available, p SAT I UNSAT PERFORM the following:

STD: Determines 2DRS-UC3A is available.

9.
  • Open CCP-MOV3A, UNIT COOLER 3A p RBCLC INLET.

JPM S-1 Page 7 of 9 NRC March 2014

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NINE MILE POINT Ntr.LF_AR STATION

10.
11.
  • STOP 2DRS-UC3B by placing control p switch in PULL TO LOCK
12.
  • CLOSE CCP-MOV3B, UNIT COOLER 3B p RBCLC INLET Once CCP-MOV3B is closed, provide the following Cue:

Cue: Your task is complete, another operator will complete the remainder of the ARP actions.

CCP-MOV3B is closed.

JPM S-1 Page 8 of 9 NRC March 2014

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NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • The plant is in Mode 1
  • Unit Coolers 3A and 3B need to be rotated to equalize runtime Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Rotate Drywe/1 Unit Coolers by starting 2DRS-UC3B and stopping 2DRS-UC3A in accordance with N2-0P-60, Section F.2.0 JPM S-1 Page 9 of 9 NRC March 2014

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0~ ~;:eDF I NINE MILE POINT NUCLEAR STATION Training_Id: 2013 NRC Simulator S-2 Revision: 0.0

--=-=-=----

Title:

Perform RPS Weekly Surveillance Approvals:

Signature I Printed Name Developed By ~ David Huff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer Aaron Armstrong I r

J, lz.t:~l'1 1

Approximate Duration: 20 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

JPM S-2 Page 1 of 10 NRC March 2014

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NINE MILE POINT NUCI£AR STATION References

1. N*2*-0SP-RPS-W002 JPM 5-2 Page 2 of 10 NRC March 2014

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NLCLEAR STATION

  • Instructor Information A. JPM Information
1. Description
a. This JPM tests the operator's ability to perform the RPS Weekly Surveillance.
2. Task Information:
a. N2-212000-01029, Perform N2-0SP-RPS-W002, Manual Scram Channel
Functional Test
b. K/A 212000, A2.03 (3.3/3.5)
3. Evaluation I Task Criteria Perform Simulator No No Yes
4. Recommended Start Location
a. Unit 2 Simulator
5. Simulator Setup (if required)
a. This JPM can be performed in Mode 1, 2, or 3
b. Ensure that both RPS A and B are reset
c. There are no malfunctions or event triggers associated with this JPM.

JPM S-2 Page 3 of 10 NRC March 2014

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6. JPM Setup (if required)
a. Prepare a copy of N2-0SP-RPS-W002. Mark up Section 7.0. The operator will only be performing testing on RPS A channel, so N/ A the remaining sections of C, B and D.
b. If the JPM is to be run multiple times, make sufficient copies of the marked up procedure to run them.

B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that :additional verification will not be provided.

JPM S-2 Page 4 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Given:

  • The plant is in Mode 1
  • Maintenance has just been completed on RPS A1
  • Post Maintenance testing is required for RPS Channels A1
  • Communications have been established between 2CEC*PNL603 and 2CEC*PNL609 Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform a Manual Scram Channel Functional Test on RPS Channel A in accordance with N2-0SP-RPS-W002, Section 8.2 Cue: Provide the marked up copy of N2-0SP-RPS-W002 to the operator.
1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used JAW CNG-OP-1.01-2001, Communications and Briefings.
2. Reviews marked up copy of N2-0SP-RPS- p SAT I UNSAT W002 and utilizes the correct section of the STD: N2-0SP-RPS-W002 is procedure reviewed JAW CNG-PR-2.01-1 000, Document Control.
  • All indicators and controls for this test are located on panel 2CEC*PNL603 unless otherwise specified.
3. Verify that there is NO half scram on the "B" p SAT I UNSAT side.

STD: Observes the four white RPS B power lights are lit on 2CEC*PNL603.

JPM S-2 Page 5 of 10 NRC March 2014

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o=:--- ..:~eor NINE MILE POINT

  • NUCLEAR STATION
4. Notify CRO that a half scram on "A" side will p SAT I UNSAT be generated.

STD: Proper communications used JAW CNG-OP-1.01-2001, Cue: As the CRO, acknowledge the report of Communications and Briefings.

a half scram on the A side.

The operator may choose to perform the actions for an Expected Annunciator which involves informing the CRS and reviewing the associated ARP. As the Evaluator, and as necessary, during the course of this JPM, acknowledge the Expected or Actual Annunciators as the CRS. Additionally at your discretion you may choose to inform the operator that all further notifications for Expected Annunciators are not required.

5. Arm the REACTOR SCRAM A1 pushbutton p
6. Verify annunciator 603113, RPS A MANUAL p SAT I UNSAT SCRAM SWITCH ARMED, has alarmed.

STD: Observes Annunciator 603113 illuminated. May depress the 2CEC*PNL603 annunciator SILENCE and ACKNOWLEDGE BUTTONS.

7. Depress AND hold for 2 to 3 seconds the p REACTOR SCRAM A1 pushbutton.
8. Verify the following annunciators have p SAT I UNSAT alarmed:

STD: Observes Annunciators 603110 and 603111

  • 603110, RPS A AUTO TRIP illuminated. Depresses the

JPM S-2 Page 6 of 10 NRC March 2014

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NINE MILE POINT NUCLEAR STATION If the Plant Computer Printouts and/or Sequence of Events do not print out the right computer points, then provide a cue as necessary to indicate to the candidate that all required computer points are in.

11. Verify the following occurred for the tripped p SAT/ UNSAT condition:

STD: Observes on the Plant

  • Verify the following Plant Computer Process Computer, Computer Printouts: Points RPSUC01 and 03 are in o RPSUC01, RPS A MANUAL TRIP, the TRIPPED condition.

TRIPPED o RPSUC03, RPS A AUTO TRIP, TRIPPED

12.
  • Verify the following Sequence of Events p SAT I UNSAT Printouts:

STD: Observes on the o RPSUC01, RPS A MANUAL TRIP, Sequence of Events Printouts, TRIPPED Computer Points RPSUC01 and o RPSUC03, RPS A AUTO TRIP, 03 are in the TRIPPED TRIPPED condition.

JPM S-2 Page 7 of 10 NRC March 2014

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NINE MILE POINT NU:::LEAR STATION

13. Verify the following alarms AND indications p SAT I UNSAT for the reset condition:

STD: Observes Annunciators

  • Verify the following alarms AND 603110 and 603111 clear.

indications for the reset condition: Depresses the 2CEC*PNL603 0 603110, RPS A AUTO TRIP annunciator SILENCE, 0 603111, RPS A MANUAL TRIP ACKNOWLEDGE, and RESET BUTTONS.

14.
  • Verify the following Plant Computer p SAT I UNSAT Printouts:

STD: Observes the Plant 0 RPSUC01, RPS A MANUAL TRIP, Process Computer, Computer ALRMCLR Points RPSUC01 and 03 are 0 RPSUC03, RPS A AUTO TRIP, shown in the ALRMCLR ALRMCLR condition.

15. . . Verify the following Sequence of Events p SAT I UNSAT Printouts:

STD: Observes on the 0 RPSUC01, RPS A MANUAL TRIP, Sequence of Events Printouts, ALRMCLR Computer Points RPSUC01 and 0 RPSUC03, RPS A AUTO TRIP, 03 are in the ALRMCLR ALRMCLR condition.

16. Verify the status of the following indicating p SAT I UNSAT lights:

STD: Observes the four white pilot lights on 2CEC*PNL603 for

  • REACTOR SCRAM TRIP LOGIC A1 on RPS A lit.

2CEC*PNL609 is ILLUMINATED.

Cue: REACTOR SCRAM TRIP LOGIC A1 on 2CEC*PNL609 are ILLUMINATED.

  • PILOT SCRAM VALVE SOLENOIDS A, C, E, AND G are extinguished.
17. Disarm the REACTOR SCRAM A1 pushbutton p JPM 5-2 Page 8 of 10 NRC March 2014

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NINE MILE POINT :

Ntx:l.EAR STATION

18. Verify annunciator 603113, RPS A MANUAL p SAT I UNSAT SCRAM SWITCH ARMED, is extinguished.

STD: Observes Annunciator 603113 not lit. Depresses the 2CEC*PNL603 annunciator SILENCE, ACKNOWLEDGE, and RESET BUTTONS.

Once the RPS A Manual Scram Switch is in the DISARM position, provide the following cue:

Cue: Your task is complete, another operator will complete the remainder of the paperwork for the surveillance procedure.

RPS Manual Scram Switch is in the DISARM position JPM S-2 Page 9 of 10 NRC March 2014

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NINE MILE POINT NLCLEAR STATION JPM Handout Given:

  • The plant is in Mode 1
  • Maintenance has just been completed on RPS A1
  • Post Maintenance testing is required for RPS Channels A1
  • Communications have been established between 2CEC*PNL603 and 2CEC*PNL609 Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform a Manual Scram Channel Functional Test on RPS Channel A in accordance with N2-0SP-RPS-W002, Section 8.2 JPM S-2 Page 10 of 10 NRC March 2014

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0&:::;-" "!"t:eDF NINE MILE POINT NUCLIEAR STATION Training Id: 2013 NRC Simulator S-3 Revision: 0.0

---=....::...;:;__ __

Title:

M~ximize Control Rod Drive Flow (Alternate Path)

Approvals:

Signature I Printed Name Developed By ~ David Huff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer <' .. ~(\.= Aaron Armstrong '/.,

I I lzat't Approximate Duration: 10 minutes Documentation of Performance:

Performer:

Evaluator;.

Start Time: Stop Time: Completion Time Grade: Pass I Fail Evaluators Signature: __________________ Date:

JPM S-3 Page 1 of 12 NRC March 2014

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NINE MILE POINT

  • Ntr.lEAR STATION References
1. N2-0P-30, Control Rod Drive
2. N2-EOP-RPV, RPV Control JPM S-3 Page 2 of 12 NRC March 2014

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0=:--- ~::eor NINE MILE POINT NL.CI.EAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operator's ability to Maximize RDS Flow after a reactor scram as well as respond to a high suction strainer differential pressure.
b. This JPM is considered alternate path because once RDS flow is maximized, a high suction strainer differential pressure alarm will occur.

The operator will be required to recognize the degraded condition and

take conditional steps to mitigate it in accordance with the operating procedure.
2. Task Information:
a. N2-201001-01012, Respond to Annunciator 603318, CRD PUMPS SUCTION FLTR DIFF PRESSURE HIGH
b. K/A 201001, A2.06 (2.9/2.9)
3. Evaluation I Task Criteria Perform Simulator No Yes Yes
4. Recommended Start Location
a. Unit 2 Simulator JPM S-3 Page 3 of 12 NRC March 2014

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0=::---- ~~eDf NINE MILE POINT NUCLEAR STATION

5. Simulator Setup (if required)
a. :Prepare the simulator as follows:
1) Snap to any full power IC
2) Ensure RDS Pump 1A is running and Pump 1B is in standby.
3) Place HPCS in PTL
4) Trip the RCIC Turbine
5) Insert malfunctions FW01A, B, and C (Condensate Pump Trip) to remove the condensate pumps from service.
6) Allow the Feed Pumps to trip and level to lower to the scram setpoint.
7) Once the Reactor has scrammed, place the mode switch to shutdown.
8) Allow RPV level to stabilize out between 100 and 150 inches and house loads to transfer to Lines 5 and 6.
b. Set Malfunction AN603318, CRD PUMPS SUCTION FLTR DIFF PRESSURE HIGH, FV=CRY WOLF on Trigger 1 with a 2 second time delay
c. Set the following Event Trigger on Event 1:

Event Action: HZLRDF003(2}==1 .AND. HZLRDF003(1}==0 Command: Blank

Description:

2RDS-PV101 Red Light On and Green Light Off (PV101 is fully open).

JPM S-3 Page 4 of 12 NRC March 2014

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NINE MILE POINT NUCLEAR STATION

6. JPM Setup (if required)
a. Prepare a copy of N2-0P-30, Section 3.0. Include a copy of the Precautions and Limitations. No steps need to be marked up.
b. Have a yellow sticky available with the following computer point written on it indicating it is in alarm: RDSPC06, CRD PMPS SUCT FLT 0/P.

JPM S-3 Page 5 of 12 NRC March 2014

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NINE MILE POINT NOCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-3 Page 6 of 12 NRC March 2014

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NINE MILE POINT NLClEAR STATION Given:

  • The plant has scrammed due to a loss of all condensate pumps
  • The mode switch is in shutdown
  • The crew is executing N2-EOP-RPV, RPV Level Control Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Maximize RDS Flow per N2-0P-30, Control Rod Drive, Section H.3.0
1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-0P-30 and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-0P-30 obtained and section H.3.0 reviewed lAW CNG-PR-2.01-1000, Document Control.

Performance may be required by the EOPs. Changes to this section of the procedure (including renumbering) are required to be reviewed by the EOP Coordinator.

JPM S-3 Page 7 of 12 NRC March 2014

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0=::--- ~~--

NINE MILE POINT NUCLF.AR STAllON .

3. IF (at any time in this Subsection) p SAT I UNSAT annunciator 603318, CRD PUMPS SUCTION STD: Observes that FLTR DIFF PRESSURE HIGH, is received; Annunciator 603318 is not lit perform the following on RB 215' el.: and determines that this step is
  • Open 2RDS-V2B(A), SUCTION FILTER-1B not applicable at this time .

(A) INLET ISOL

  • 3.1.2 Open 2RDS-V3B(A), SUCTION FILTER-1B (A) OUTLET ISOL
  • 3.1.3 Open 2RDS-V8, FLT.-BYPASS-LINE SUCTION STRAINER ISOL
  • 3.1.4 Open 2RDS-V9, FLT.-BYPASS-LINE SUCTION STRAINER ISOL.
4. IF (at any time in this Subsection) p SAT I UNSAT annunciator 603317, CRD DRV WTRIRCS STD: Observes that PMP SEAL FILTR DIP HIGH, is received, Annunciator 603317 is not lit perform the following on RB 261' el.: and determines that this step is
  • Open 2RDS-V23B(A), DISCH. FLT 2B (A) not applicable at this time .

INLET ISOL.

2B (A) OUTLET ISOL.

5. Verify RPS is tripped per N2-SOP-101C. p SAT I UNSAT STD: Observes the eight white scram solenoid power lights for RPS A and B are not lit on 2CEC*PNL603
6. Verify the following pumps are running p SAT I UNSAT (2CEC*PNL603), IF available:

STD: Determines RDS-P1A is

  • RDS-P1A, CRD PUMP 1A already running by observing the control switch is in Normal After Start (red flagged) and amps are indicated on the amp meter on 2CEC*PNL603.

JPM S-3 Page 8 of 12 NRC March 2014

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o::::--- ~~.,.:

NINE MILE POINT NUCLEAR STATION

7.
  • RDS-P1B, CRD PUMP 18 p
8. Place 2RDS-FC107, CRD FLOW CONTROL, in p MANUAL (2CEC*PNL603).

To prevent pump motor damage or tripping the supply breaker, RDS pump motor current shall not exceed 40 amps.

RDS P1A and B amps should be "'23 amps. After performance of this step, amps should rise to "'27 amps.

9. Open 2RDS-FC107 UNTIL RDS pump motor current(s) approach 40 amps OR controller output meter is 100% (2CEC*PNL603).

Two seconds after completion of the following step, Annunciator 603318 will alarm. The operator will reference Step H.3.1 to mitigate the event At the completion of the below step, RDS-P1A and B amps should be "'28 amps.

JPM S-3 Page 9 of 12 NRC March 2014

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NINE MILE POINT NUCLEAR STATlON

10. IF NOT driving control rods, open 2RDS-PV101, DRIVE WTR PRESS CONTROL MOV, UNTIL RDS pump motor current(s) approach 40 amps OR fully open (2CEC*PNL603).
11. Recognize Annunciator 603318 is in alarm. SAT/ UNSAT Cue: If the operator attempts to check which STD: Observes 603318 computer point is in alarm on the plant annunciator tile is lit. May process computer, place the yellow depress the silent and sticky with the computer point number acknowledge pushbuttons. May on the computer screen. report annunciator to CRS.

Cue: If required, as CRS acknowledge report of annunciator. Direct the operator to "Respond per the appropriate procedure".

The next critical step may be performed in multiple ways. The operator may choose to contact a PO and direct them to perform N2-0P-30, Step H.3.1 -or- the operator may choose to direct the PO to perform each step individually. Either method is acceptable. The critical aspect of the below step is that the operator recognize that step H.3.1 is now applicable and direct action in accordance with the step. It is inappropriate for the operator to enter N2-SOP-30 or the actions of the ARP. If the operator gives the PO direction to simply "Swap suction filters" then this step should be graded as "Fail"

12. References step H.3.1, contacts a Plant Operator, and direct them to perform N2-0P-3d, Step H.3.1.

Cue: As PO, acknowledge direction to perform N2-0P-30, Step H.3.1. or acknowledge the individual step Cue: If asked as the PO, inform the operator that Suction Filter A is in service.

JPM S-3 Page 10 of 12 NRC March 2014

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O=:--- ~'eDf NINE MILE POINf NUCLEAR STATION Once a PO is contacted and directed to perform N2-0P-30, Step H.3.1, give the following cue:

Cue: Your task is complete, another operator will complete any remaining actions.

A Plant Operator is contacted and directed to perform N2-0P-30, Step H.3.1.

JPM S-3 Page 11 of 12 NRC March 2014

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0=:--- -!~etJF NINE MILE POINT NUClEAR STATION JPM Handout Given:

  • The plant has scrammed due to a loss of all condensate pumps
  • The mode switch is in shutdown
  • The crew is executing N2-EOP-RPV, RPV Level Control Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Maximize RDS Flow per N2-0P-30, Control Rod Drive, Section H.3.0 JPM 5-3 Page 12 of 12 NRC March 2014

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s pnt ventvre 0=- ':!'feDF ol--*J NINE MILE POINT NUCLeAR S'OOION Training Id: 2013 NRC Simulator S-4 Revision: 0.0

--=-=-=----

Title:

Reset LVlOB Lockout and Place FWLC in Automatic (Alternate Path)

Approvals:

Signature I Printed Name Developed By -------.~~=-------------=D:....:a:....::v....:...:id::........:....H..::..uff.:....:. 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Re-viewer Ji '

Aaron Armstrong I ,b ,/2.0/Y Approximate Duration: 20 minutes Documentation of Performance:

Performer:

Evaluator:

Start Tirne: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

JPM S-4 Page 1 of 12 NRC March 2014

a)OII'~Vf!l'l~Ul'nol----

0::::--- ~~eof NINE MILE POINT NUC!.EAR STATION References

1. N2*-SOP-06, Feedwater Failures JPM S-4 Page 2 of 12 NRC March 2014

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o==--- ~~eDF NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1.

Description:

a. This JPM tests the operator's ability to reset an LVlO lockout and place FWLC in full automatic control.
b. This JPM is considered alternate path because once the LVlO is reset and placed back in automatic, the master FWLC controller will fail requiring the operator to place FWLC in manual and restore level to the normal band.
2. Task Information:
a. N2-SOP-06-01001, Respond to SOP-06 Feedwater Failures
b. K/A 259001, A4.05 (4.0/3.9)
3. Evaluation /Task Criteria Perform Simulator No Yes Yes
4. Recommended Start Location
a. Unit 2 Simulator
5. Simulator Setup (if required)
a. :Prepare the simulator as follows:

JPM 5-4 Page 3 of 12 NRC March 2014

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0~ -t~eof NINE MILE POINT :

NLCLEAR STATION

1) Reset to any full power IC
2) Place LV10B in manual control
3) Adjust LV10B valve position to rv35% open
4) Insert Malfunction FW52B, 2FWS-LV10B Lockup
5) Verify the LV10B 86-device has actuated
6) Set LV10B Controller Horizontal Output to rv45%
7) Delete Malfunction FW52B "8) Allow plant conditions to stabilize
b. Set Malfunction FW13, FEEDWATER MASTER CONTROLLER FAILURE -

HIGH, FV=95°/o, on Trigger 1 with no Delay Time

c. Set the following Event Trigger on Event 1:

Event Action: HZLC33R601B(2)= = 1 Command: Blank

Description:

LV10B Controller AUTO Green Indicating Light is ON.

6. JPM Setup (if required)
a. Prepare a copy of N2-SOP-06. Include a copy of both flow charts marked up to "Restore Valve Control per Attachment 1, Step 1.1.3". Mark up Attachment 1, Steps 1.1.3.a and 1.1.3.b as complete.

JPM S-4 Page 4 of 12 NRC March 2014

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NINE MILE POINT NLCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-4 Page 5 of 12 NRC March 2014

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O=:--- ~~eof NINE MILE POINT NUCLEAR STAllON Given:

  • The plant is at 100% power.
  • The crew has entered N2-SOP-06, Feedwater Failures due to an LV10B Lockup
  • The cause of the LV10B Lockup was due to an operator inadvertently bumping a power supply breaker on 2NHS-MCC003
  • The breaker was inspected for damage and determined to be functioning correctly.
  • Operators have restored power to LV10B.
  • The Master FWLC Controller is currently controlling LV10A in automatic with LV10B in manual and locked up at "'35% open
  • There is no evidence that LV10B is drifting or that Feedwater Pump Limits are being challenged.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Restore LV108 valve control and return LV108 to automatic control per N2-SOP-06, Attachment 1, Step 1.1.3

1. Provide repeat back of initiating cue p SAT I UNSAT C1;1e: Acknowledge repeat back providing STD: Proper communications correction if necessary. used JAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-SOP-06 and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-SOP-06 obtained and Attachment 1, Step 1.1.3 reviewed JAW CNG-PR-2.01-1 000, Document Control.

JPM S-4 Page 6 of 12 NRC March 2014

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o:::::--- ~:eDF NINE MILE POINT NUCLEAR STATION

3. Af 2NHS-MCC003, verify power is available p SAT I UNSAT AND breaker is ON:

STD: Determines these steps

At 2FWS-PNL10A (B,C), verify circuit breaker is:ON

4. Verify affected controller 2FWS-HIC1010A p SAT I UNSAT (B, C) in Manual STD: At 2CEC*PNL603, observes the AMBER manual light is lit and the GREEN auto light is not lit on 2FWS-HIC10108 controller.

If the horizontal output indicator does not match actual valve position, the valve will reposition when the 86 device is reset.

Due to the size of the position increments on the LV10B controller, it may be difficult for an evaluator to determine if the valve position and controller outputs are correctly matched per Steps 5 and 10 of this JPM.

The evaluator may ask the simulator booth operator to document the exact values shown on the controller as the candidates complete these steps. The evaluator may then use these values to assist in grading of these steps. See the Evaluator Job Aide at the end of this JPM for additional information.

5. Set 2FWS-HIC1010A (B,C) output p (horizontal) to match actual valve position JPM S-4 Page 7 of 12 NRC March 2014

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0:::::-- ~:;_,

NINE MILE POINT NUClF_AR STATION

6. Verify Annunciator 603143 is clear (within p SAT/ UNSAT dead band)

STD: At 2CEC*PNL603, observes Annunciator 603143 not lit.

7. At panel 603, reset 86 device (Control signal p reset)
8. IF desired, return valve to automatic control p SAT I UNSAT as follows:

STD: Per the provided initiating cue determines it is desired to return the valve to automatic control.

9. * . IF a single feed pump is in service, p SAT I UNSAT r*estore control to automatic per N2-0P-3, STD: At 2CEC*PNL852, F.8.4 observes that two feed pumps are running and determines this step is not applicable.

Steps 10 and 11 may be performed concurrently.

10.
  • Using OPEN/CLOSE detent pushbuttons p on 2FWS-HIC1010A (B, C) controller, throttle 2FWS-LV10A (B, C), Feedwater Pump 1A (B, C) Level Control Valve, UNTIL input signal (vertical) AND output signal (horizontal) on 2FWS-HIC1010A (B, C) controller are matched JPM S-4 Page 8 of 12 NRC March 2014

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NINE MilE POINI NUCLEAR STATION

11.
  • Verify unaffected valve responds to p SAT/ UNSAT control level STD: At 2CEC*PNL603, observes that L V1 OA position indication responds to control RPV water level.

After completion of the next step, the Master FWLC Controller will fail causing RPV water to rise. The operator will take manual control of the FWLC system to mitigate the event.

12.
  • Place 2FWS-LV10A (B, C) in Auto by p momentarily depressing Auto (A) pushbutton on 2FWS-HIC1010A (B, C) controller
13. Observe RPV Level is Rising p SAT I UNSAT Cue: As necessary, respond as the CRS to STD: At 2CEC*PNL603, reports of rising RPV water level. observes that RPV level is Direct the operator to "Respond per the rising.

appropriate procedure".

There are several methods available to mitigate this event. The most likely action to take by the operator would be to place the FWLC Master Controller in MANUAL and control level manually. However, the operator may also choose to place LV10B back in MANUAL control and attempt to control level using the OPEN/CLOSE pushbuttons. This is an acceptable action but it may also cause the operator to have to place LV10A in MANUAL as well. In the end, the critical aspect of the below steps is to take MANUAL control of the FWLC system and control level to prevent a Level 3 or 8 trip -and- to prevent a trip of either feed pump due to runout/low suction conditions.

JPM S-4 Page 9 of 12 NRC March 2014

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  • Jo"i""*"'ol- - -

NINE MIL£ POINT :

NUCLEAR STA110N PERFORMANCE ACT. CODE EVALUATOR P/5/NA

14. Place FWLC system in MANUAL p *PASS I FAIL STD: At 2CEC*PNL603, depresses the MANUAL pushbutton for the FWLC Master Controller and/or LV10B and/or LV10A.
15. Manually operate the FWLC System and p *PASS I FAIL restore RPV water level to normal band.

STD: At 2CEC*PNL603, using the OPEN and CLOSE pushbutton on the FWLC Master Controller and/or LV10A, and/or LV10B, adjusts RPV water level to prevent level from reaching the Level 8 trip setpoint (202.5 inches) or the Level 3 trip setpoint (159.3 inches). Additionally, feed flow is controlled such that a feed pump does not trip on low suction or runout conditions.

Once level is under control, adjusts the controller to reestablish ,..184 inches in the RPV.

At the evaluator's discretion, after the operator has demonstrated that he has adequate control over RPV water level and level is being returned to Evaluator Note: the normal band, provide the following cue:

Cue: Your task is complete, another operator will complete any remaining actions.

TERMIN~TING FWLC Master Controller is in manual control and RPV Water Level is being CUE restored to the normal band.

STOP TIME JPM S-4 Page 10 of 12 NRC March 2014

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NINE MILE POINT NUCLEAR STATlON Evaluator lob Aid Do Not Provide to Candidate Step 10:

Step 5:

FEEDWATER FEEDWATER 8 TO 8 TO Valve Position FWS- LY108 FWS- LY108 Input Signal (Vertical) 2FWS-HIC1 01 OB 100

- 100 The Valve Position Meter and -

- eo  :::-- eo Controller Output Meter must -::- &J The Controller Output Meter must

-::" 150 match within 5°/o of each other ~'10

- match within 5% of the Input prior to resetting the 86 device  ::" 20 Signal Meter prior to placing the

- o controller in Automatic Controller Output (Horizontal)

Controller Output (Horizontal)

JPM S- 4 Page 11 of 12 NRC March 2014

a.l(lff-*verr.un!ul--*-

0~ ~:eDF NINE MILE POINT NLCLEAR STATION JPM Handout Given:

  • The plant is at 100% power.
  • The crew has entered N2-SOP-06, Feedwater Failures due to an LV10B Lockup
  • The cause of the LV10B Lockup was due to an operator inadvertently bumping a power supply breaker on 2NHS-MCC003
  • The breaker was inspected for damage and determined to be functioning correctly.
  • Operators have restored power to LV10B.
  • The Master FWLC Controller is currently controlling LV10A in automatic with LV10B in manual and locked up at rv35% open
  • There is no evidence that LV10B is drifting or that Feedwater Pump Limits are being challenged.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name}, Restore LV10B valve control and return LV10B to automatic control per N2-50P-06, Attachment 1, Step 1.1.3 JPM S-4 Page 12 of 12 NRC March 2014

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Training Id: 2013 NRC Simulator S-5 Revision: 0.0

=...::.....:=..__ __

Energize 2ENS*SWG103 from Division 2 EDG and Energize 2NNS-

Title:

SWG015 (Stub Bus) from 2ENS*SWG103 During a Station Blackout Approvals:

Signature I Printed Name Developed By ~ David Huff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer C'h.~~ £ ~ Aaron Armstrong , J~ j?..o/'1 Approximate Duration: 20 minutes Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

JPM s-s Page 1 of 12 NRC March 2014

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aJtNflr.vontutnof--** -

0=:--- ~ieDF NINE MILE POINT NUCLEAR STATION References

1. N2--SOP-03, Loss of AC Power
2. N:2-SOP-01 and 02, Station Blackout JPM 5-5 Page 2 of 12 NRC March 2014

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0::=--- ,.;~.,

NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operator's ability to Maximize RDS Flow after a reactor scram as well as respond to a high suction strainer differential pressure.
b. This JPM is considered alternate path because once RDS flow is maximized, a high suction strainer differential pressure alarm will occur.

The operator will be required to recognize the degraded condition and take conditional steps to mitigate it in accordance with the operating

procedure.
2. Task Information:
a. N2-SOP-03-01001, Respond to N2-SOP-03, Loss of AC Power
b. K/A 262001, A4.01 (3.4/3.7)
3. Evaluation I Task Criteria Perform Simulator No No Yes
4. Recommended Start Location
a. :unit 2 Simulator JPM S-5 Page 3 of 12 NRC March 2014

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NINE MILE POINT NIXI.EAR STATION

5. Simulator Setup (if required)
a. :Prepare the simulator as follows:
1) Reset to a Full Power IC
2) Insert the following Malfunctions:

DGOSA EDG 1 OVERS PEED DGOSB EDG2 OVERSPEED DG04B EDG3 FAIL TO UV/LOCA AUTO START

3) Insert Malfunctions ED02A and 028 Loss of Line 5 and 6
4) Place the Mode Switch in Shutdown S) Complete the steps of N2-SOP-03, Attachment 1, Step 1.6 Fault Identification
6) Allow plant conditions to stabilize.
7) Place the Control Switch for the Division 2 EDG to Start
6. JPM Setup (if required)
a. Prepare a copy of N2-SOP-03, and markup section 1.6 as complete.

Provide a copy the Precautions and Limitations, marked up Section 1.6, Section 1. 7, Attachment 8, and Attachment 9.

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0~ ~,.,.t NINE MILE POINT :

NUClEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initi~l conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my c;:ues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and thatadditional verification will not be provided.

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0~ ~~eDf NINE MILE POINT NUClEAR STATION Given:

  • The Reactor has just been manually scrammed.
  • A Station Blackout (SBO) is in progress.
  • A loss of coolant condition does NOT exist.
  • Fault identification per N2-SOP-03, Attachment 1, Section 1.6 is complete Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Energize 2ENS*SWG103 from the DIV 2 EDG and 2NNS-SWG015 from 2ENS* SWG103, in accordance with N2-SOP-03, Attachment 1, Section 1. 7.
1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used JAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-SOP-03 and review I p SAT I UNSAT ut11ize the correct section of the procedure STD: Current version of N2-0P-03 obtained and Attachment 1, Step 1.7.5 and Attachment 8 reviewed JAW CNG-PR-2.01-1 000, Document Control.

The following steps are performed at Panel 852 unless otherwise noted.

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NINE MILE POINT NUCt.EAR STAliON

3. Attachment 8 Prerequisites: p SAT I UNSAT STD: Per the turnover PRIOR to executing the following steps, provided, determines power is power must be available from one of the available from the Division 2 following sources: EDG.
  • Aux Boiler transformer (Attachment 10)
  • Division II EDG (2EGS*EG3) (N2-0P-100A)
  • Division III EDG (2EGS*EG2) (N2-0P-100B)
4. Attachment 1, Section 1.6, Fault p SAT I UNSAT Identification and Isolation, is complete.

STD: Per the turnover provided, determines Attachment 1, Section 1.6 Fault Identification is Complete.

5. Upon completion of Attachment 8, return to p SAT I UNSAT Attachment 1, Section 1. 7, as appropriate to STD: Determines return to restore power to the plant.

Attachment 1, Section 1.7 is not required at this time.

6. At switchgear 2ENS*SWG103 (CB 261'), p SAT I UNSAT verify reset the following lockouts:

STD: Contacts a PO and directs

  • 86A-2ENSY02 for Breaker 103-2 them to reset lockouts on
  • 86B-2ENSY02 for Breaker 103-2 2ENS*SWG103 per N2-SOP-03,
  • 86-2EJSY03 for Breaker 103-1
  • 86-2EJSY04 for Breaker 103-13 Cue: As PO, inform the operator that all lockouts listed in Attachment 8 Step 8.1.4 are reset.

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o:::::-- ~~erw NINE MILE POINT NUClF.AR STATlON

7. Attachment 8, Section 8.4: p SAT I UNSAT STD: Contacts a PO and directs At 2ENS*SWG103 (CB 261') verify reset the them to reset lockouts on following lockouts: 2ENS*SWG103 per N2-SOP-03,
  • 86 2EGPY01 for Breaker 103-13 Attachment 8, Step 8.4.1
  • 86-2-2EGPY02 for Breaker 103-14
  • 86-1-2EGPY02 for Breaker 103-14 Cue: As PO, inform the operator that all lockouts listed in Attachment 8 Step 8.4.1 are reset.
8. Place the SYNC switch to ON (SYNCHRONIZE p TO BUS 103)
9. Close 103-14 p
10. Place the SYNC switch to OFF p SAT I UNSAT STD: On 2CEC*PNL852, places the Division 2 EDG SYNCHRONIZE TO BUS 103 switch to OFF.
11. At Panel 601, verify started, one Division II p SAT I UNSAT service water pump.

STD: On 2CEC*PNL601, observes GREEN LIGHT off and RED LIGHT on for 2SWP*P18.

Fluid systems may have drained due to the loss of power.

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o==--- -!,eDF NINE MIL£ POINT NUCLEAR STATION

12. St:art additional loads as directed by SMICRS p SAT I UNSAT in accordance with Attachment 12 Section STD: Contacts the SM and 12.1 determines no additional loads Cue: As SM, inform the operator that no need to be started at this time.

additional loads need to be started at this time.

13. Return to Attachment 1, Section 1. 7 and p SAT I UNSAT then reference Attachment 9.

STD: References Attachment 1 Section 1. 7 and determines Attachment 9 is the next section to go to.

14. Prerequisites: p SAT I UNSAT PRIOR to executing the following steps, STD: Determines power is power must be available from one of the available from 2ENS*SWG103.

following sources:

  • 2ENS*SWG103 (Division II Emergency Switchgear) (Attachment 8)
15. Attachment 1 Section 1.6 Fault Identification p SAT I UNSAT and Isolation is complete.

STD: Per the turnover provided, determines Attachment 1, Section 1.6 Fault Identification is Complete.

16. Upon completion of Attachment 9, return to p SAT I UNSAT At:tachment 1, Section 1.7, as appropriate to STD: Determines return to restore power to the plant.

Attachment 1, Section 1.7 is not required at this time.

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NINE MILE POINT Ntr.LEAR STATION

17. At Panel 804 (CB 288'), verify reset 86- p 2NNSY15 (4.16KV BUS NNS-015 SAT I UNSAT PROTECTION LOCKOUT RELAY).

STD: Contacts a PO and directs Cue: As PO, inform the operator that the them to reset the lockout on lockout listed in Attachment 9 Step Panel 804 per N2-SOP-03, 9.1.4 is reset. Attachment 9, Step 9.1.4 Energizing 2NNS-SWG015 from 2ENS*SWG103 when the Div II Diesel is supplying the bus is not permitted during a LOCA.

18. Section 9.3: p SAT I UNSAT STD: On 2CEC*PNL852, Place 15-3 in PULL-TO-LOCK.

determines Breaker 15-3 is already in PULL- TO-LOCK.

The following step requires a PA 2235 Key located in the CRO's desk.

19. IF:2NNS-SWG015 is needed for SBO p recovery, THEN at Panel 852, place the Div II LOCA SIGNAL BYPASS switch to ON.
20. Do NOT exceed the emergency diesel p SAT I UNSAT generator rating, 4400 KW (4840 KW 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> STD: Observes on the Division limit) WHEN re-energizing STUB Bus 2NNS-2 EDG Load Meter at SWG015. 2CEC*PNLB52 that the diesel is operating with <4400 KW load.

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NINE MILE POINT NLCLEAR STATION

21. At 2ENS*SWG103 (CB 261'), verify reset 86- p SAT/ UNSAT 2ENSY12. (Breaker 103-8)

STD: Contacts a PO and directs Cue: As PO, inform the operator that the them to reset the lockout on lockout listed in Attachment 9 Step 2ENS*SWG103 per N2-SOP-03, 9.3.4 is reset. Attachment 9, Step 9.3.4

22. Close 103-8 p
23. Close 15-8. p 2ENS*SWG103 is being powered from the Division 2 EDG and 2NNS-SWG015 is being powered from 2ENS*SWG103.

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0=::--- ~:eDf NINE MILE POINT NUCLF.AR STATION JPM Handout Given:

  • The Reactor has just been manually scrammed.
  • A Station Blackout (SBO) is in progress.
  • A loss of coolant condition does NOT exist.
  • Fault identification per N2-SOP-03, Attachment 1, Section 1.6 is complete Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Energize 2ENS*SWG103 from the DIV 2 EDG and 2NNS-SWG015 from 2ENS* SWG103, in accordance with N2-SOP-03, Attachment 1, Section 1. 7.

JPM S-5 Page 12 of 12 NRC March 2014

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NINE MILE POINT NUCI..SAR SiATION Training Id: 2013 NRC Simulator S-6 Revision: 0.0 _ __

--=..:....::::....

Title:

Bypass RCIC Room High Temperature Isolation (Alternate Path)

Approvals:

Signature I Printed Name Developed By

~ David Huff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer Aaron Armstrong , }3 ,17...oJ Approximate Duration: _ _. . . ;.1.:. . : 5. . . ;.m_in--'u:. . .:t. . . ;.e. :. . s_ _

Documentation of Performance:

Performer:

Evaluator::

Start Time: - - - - Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

JPM S-6 Page 1 of 11 NRC March 2014

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NINE MILE POINT NLClEAA STATION References

1. N2-SOP-02, Station Blackout Support Procedure JPM S-6 Page 2 of 11 NRC March 2014

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NINE MILE POINT NUCLEAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operator's ability bypass the RCIC Room High Temperature Isolations during a Station Blackout as well as reset a RCIC Turbine Trip from the Control Room.
b. This JPM is considered alternate path because once the RCIC Room High Temperature Isolations have been bypassed, a RCIC Turbine Trip will occur. The operator will mitigate by resetting the RCIC turbine from the Control Room.
2. Task Information:
a. N2-21700-01048, Latch the RCIC TTV From The Control Room
b. K/A 217000, A4.02 (3.9/3.9)
3. Evaluation I Task Criteria Perform Simulator No Yes Yes
4. Recommended Start Location
a. Unit 2 Simulator JPM S-6 Page 3 of 11 NRC March 2014

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0=:---- ~~eof NINE MILE POINT .

NUCLEAR STATION

5. Simulator Setup (if required)
a. Prepare the simulator as follows:
1) Reset to a full power IC
  • 2) Place the Mode Switch in Shutdown and manually trip the turbine
3) Insert Malfunctions ED02A and ED02B, Loss of Lines 5 and 6.
4) Manually initiate RCIC
5) Insert Remote Function RC02A, RCIC Level 8 Defeated, FV=DEFEATED
6) Manually Initiate Division 1 and 2 ECCS Systems
7) Insert Malfunctions EDOSA, EDOSB, and EDOSC to deenergize Division 1, 2, and 3 emergency busses.
8) Insert Malfunction RR20, DBA LOCA at a value of 0.2°/o
9) Insert Override AN601332, RCIC TEMPERATURE HIGH to ON
b. Set Malfunction RC06, RCIC TURBINE TRIP FV=TRUE on Trigger 1 with a no time delay
c. :Set the following Event Trigger on Event 1:

Event Action: ZDLDS4B{1)==1 Command: Blank

Description:

Keylock Switch E31-S4B in BYPASS.

d. :Set the following Event Trigger on Event 2:

Event Action: HZLRCV150{2)==0 Command: DMF RC06

Description:

MOV150 Red Light Off.

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NINE MILE POINT Nlr.LEAR STATION

6. JPM :Setup (if required)
a. Prepare a copy of N2-SOP-02, Attachment 4. No steps need to be marked up.

JPM S-6 Page 5 of 11 NRC March 2014

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NINE MILE POINT NUCt.F-AR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that*additional verification will not be provided.

JPM 5-6 Page 6 of 11 NRC March 2014

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0::::--- ~~eDF NINE MILE POINT NUCLEAR STATION Given:

  • The plant has experienced a Station Blackout.
  • N2-SOP-2, Station Blackout Support Procedure, is in progress.
  • Drywell pressure is above 1.68 psig due to a LOCA
  • RCIC is in service, injecting into the core.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name),) Bypass the RCIC Room High Temperature Isolations in accordance with N2-SOP-02, Attachment 4.

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used JAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-SOP-02 and review I p SAT I UNSAT utilize the correct section of the procedure, STD: Current version of N2-SOP-02 obtained and Determines that Attachment 4, Step 3.1 is Attachment 4 reviewed IA W not applicable at this time. CNG-PR-2.01-1000, Document Control.

The following annunciators will alarm during performance of the next step:

  • 601306, Division I RWCUIRCICIRHR ISOLATION IN BYPASS
  • 601307, DIVISION II RWCUIRCICIRHR ISOLATION IN BYPASS
3. Places the following switches in BYPASS p
  • E31A-S2A, STEAM SUPPLY LINE OUTBD ISOL. VLV. BYPASS ICS*MOV121 JPM S-6 Page 7 of 11 NRC March 2014

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NINE MILE POINT NOCLEAR STATION

4.
5.
  • 31A-52B, STEAM SUPPLY LINE INBD p ISOL. VLV. BYPASS ICS*MOV128 Completion of the next step will cause the RCIC Turbine to trip. The operator will mitigate the event by resetting the RCIC TTV from the Control Room
6.
7. p SAT/ UNSAT Cue: If the operator does not respond to the RCIC turbine trip, provide a prompt to STD: Identifies that have them evaluate conditions on Annunciators 601301 and 2CEC*PNL601.

601305 are in alarm. Observes the 2ICS*MOV150 is closed.

Identify and report RCIC Turbine Has Tripped Informs the CRS.

Cl;le: As CRS, acknowledge report. Inform the operator that the cause of the trip is known and corrected. Direct the operator to reset and reopen 2ICS*MOV150 from the control room.

The following annunciators will alarm during performance of the next step:

  • 852136 EDG 1 LOCA Bypass Switch ON JPM 5-6 Page 8 of 11 NRC March 2014

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0:::::--- ~;eDf NINE MILE POINT NUCLF.AR STATION .

8. References N2-SOP-02, Attachment 4, Step p 3.1:

IF: the RCIC turbine trip throttle valve (2ICS*MOV150) trips with a LOCA signal present, THEN perform the following:

  • Place in ON the Division I LOCA SIGNAL BYPASS switch at P852 Reset 2ICS*MOV150 at P601 p
9.
  • The following annunciator will clear during performance of the next step:
10.
  • At Panel 2CEC*PNL852, verify LOCA p SAT I UNSAT SIGNAL BYPASS switch in OFF for STD: At 2CEC*PNL851, places 2EGS*EG1 Division I Diesel Generator the DIVISION 1 EDG LOCA SIGNAL BYPASS keylock switch to OFF The reopening of 2ICS*MOV150 may be done prior to placing the LOCA SIGNAL BYPASS switch to OFF. Additionally, the operator may choose to reference N2-EOP-HC and/or N2-0P-35 for guidance on reopening 2ICS*MOV150. The critical step is to reopen 2ICS*MOV150 from CEC*PNL601. Which procedure (or no procedure) they use to accomplish this is not important to the grading of the step.

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0::::---- ..:~801' NINE MILE POINT NUCLEAR STATION

11. Open 2ICS*MOV150 p Once 2ICS*MOV150 has been opened, provide the following cue:

Cue: Your task is complete, another operator will complete any remaining actions.

The RCIC Room High Temperature Isolations are bypassed and 2ICS*MOV150 has been reset and reopened.

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0=.:-- ~'eot' NINE MILE POINT NUGLF.AR STAllON JPM Handout Given:

  • The plant has experienced a Station Blackout.
  • N2-SOP-2, Station Blackout Support Procedure, is in progress.
  • Drywell pressure is above 1.68 psig due to a LOCA
  • RCIC is in service, injecting into the core.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name),) Bypass the RCIC Room High Temperature Isolations in accordance with N2-SOP-02, Attachment 4.

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NINE MILE POINT NUCLEAR STATION Training Id: 2013 NRC Simulator S-7 Revision: 0.0

_..::;_.:..=.__ __

Override the Control Room Envelope ACU Cross-Divisional

Title:

Op:erating Interlock (Time Critical)

Approvals:

Signature I Printed Name Developed By David Huff 12/18/2013

~~~~~

Validated By Jason Sawyer 12/03/2013 Facility Reviewer Aaron Armstrong Approximate Duration: 13 minutes Documentation of Performance:

Performer:

Evaluator:.

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: ___________________ Date:

JPM S-7 Page 1 of 12 NRC March 2014

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0=:-- --!:ettf NINE MILE POINT NLClEAR STATION References

1. N2-0P-53A, Control Building Ventilation System JPM S-7 Page 2 of 12 NRC March 2014

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0=:--- ~~eof NINE MILE POINT NLC!.EAR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operator's ability to override the Control Room Envelope ACU Cross-Divisional Operating Interlock.
b. The critical tasks of this JPM must be completed within 13 minutes of starting the JPM. Failure to complete the steps may cause the control

-room temperature to rise above 90°F.

2. Task Information:
a. N2-288003-01051, Perform Override of Control Room Envelope ACU Cross-Divisional Operations Interlock
b. :K/A 290003 A3.01 3.3/3.5
3. Evaluation I Task Criteria Perform Simulator Yes No Yes
4. Recommended Start Location
a. Unit 2 Simulator
5. Simulator Setup (if required)
a. Prepare the simulator as follows:

JPM S-7 Page 3 of 12 NRC March 2014

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o::::--- .;~erw NINE MILE POINT NLCLEAR STATION

1) Reset to full power IC
2) Place the control switches for ACU 1A and 2A to PULL TO LOCK.

Observe that ACU18 and 28 have auto started. The interlocks have a time delay so it may take a few seconds.

3) Place the control switches for ACU1A and 2A back to RED FLAG.

ACU1A and 2A should not restart due to interlock. The point is to make it look like ACU1A and 2A tripped and 18 and 28 auto started.

4) Insert Overrides for AN870326 and AN870327, CONTROL ROOM C UNIT 1A AUTO TRIP and RELAY ROOM AC UNIT 2A AUTO TRIP, FV=CRY WOLF
5) Insert Override AN849128, FIRE DETECTED PNL 129 W STAIR/288, FV=CRY WOLF
6. JPM Setup (if required)
a. Prepare a copy of N2-0P-53A, Section 15.0. Include a copy of the
precautions and limitations.

JPM S-7 Page 4 of 12 NRC March 2014

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0::::::-- ,*:eoF NINE. MILE. POINT NUCLEAR STATION B. Read Before Every lPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior. to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated lPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM S-7 Page 5 of 12 NRC March 2014

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O~ ~-:eoF NINE MILE POINT NlX'A.EAR STATION Given:

  • The reactor is at 100% power.
  • A fire has occurred in the Control Building
  • Annunciator 849128, FIRE DETECTED PNL 129 W STAIRI288 is in alarm, with Fire Zone 352 NW as the affected zone.
  • The Fire Brigade Leader has confirmed the fire
  • 2HVC*ACU1A and 2A were running and have since tripped due to the fire.
  • 2HVC*ACU1B and 2HVC*ACU2B have auto started.
  • The Shift Manager's permission has been received to override the control room envelope ACU cross-divisional operating interlock.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Override the Control Room Envelope ACU Cross-Divisional Operating Interlock per N2-0P-53A, Section H.15.0.

This is a Time Critical JPM

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-0P-53A and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-0P-53A obtained and Step H.15.0 reviewed lAW CNG-PR-2.01-1 000, Document Control.

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NINE MILE POINT NUCLEAR STATION 2HVC*ACU1AIB and *ACU2AIB includes a start permissive which precludes simultaneous operation the units and is intended to auto start the unit in the opposite division in the event of a trip of the running unit. A fire affecting one division has the potential to override this interlock such that the opposite division ACU may become disabled. This subsection will utilize override switches to ensure operability of the division without the fire.

Actuation of the override switches is required to be completed within 13 minutes after a fire that has disabled the previously running Control Room Envelope ACUs to ensure Control Room Envelope temperature remains <90°F.

This section is only used in response to a confirmed fire in Fire Areas 16, 17, 18 or 19.

The actions in this section are performed at 2CEC*PNL870(871) unless otherwise specified.

The Fire Zones listed in Step H.15.1 affect Division I components.

3. IF the fire is in any of the following Fire p SAT I UNSAT Zones:

STD: Determines per the

  • 321NW- Cable Chase West, Control Bldg, turnover that the fire is in Fire 237' (Fire Area 16) Zone 352 NW (Fire Area 16).
  • 332NW - Cable Chase West, Control Bldg, Determines that the Division 1 261' (Fire Area 16) ACUs are affected and that the Cross-Divisional interlocks need
  • 352NW - Cable Chase West, Control Bldg, to be disabled for Division 2 288'6" (Fire Area 16) components. Continues on in
  • 371NW- Cable Chase West, Control Bldg, Section H.15.1.

306' (Fire Area 16)

  • 333XL - Div I Switchgear Room, Control 131dg, 261' (Fire Area 17)

THEN perform the following:

4. Check the following ACUs are available OR p SAT I UNSAT are in service:

STD: Observes the RED

  • HVC*ACU1B, CONTROL ROOM AC FAN running lights for ACU1B and
  • HVC*ACU2B, RELAY ROOM AC FAN 28 are lit and that the GREEN not-running lights are not lit.

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NINE MILE POINT Ntr.LEAR STATION already running.

5. Verify control switch is in PULL-TO-LOCK for p the following:
  • HVC*ACUlA, CONTROL ROOM AC FAN
6.
  • HVC*ACU2A, RELAY ROOM AC FAN p
7. Notify SM to declare 2HVC*ACU1A AND p SAT I UNSAT 2HVC*ACU2A inoperable AND to take actions STD: Contact the SM and per TS 3.7.2 AND 3.7.3.

informs him that HVC* 1A and Cue: As SM, inform the operator that ACU1A 2A are inoperable.

and 2A have been declared inoperable and TS 3.7.2 and 3.7.3 have been reviewed.

8. Obtain SM permission to override the HVC p SAT I UNSAT ACU cross divisional operating interlock for STD: Refers to the initial 2HVC*ACU1A AND 2HVC*ACU2A conditions and determines that Cue: If necessary, as the SM, inform the the SM has been given operator that he has permission to permission to override the override the cross divisional interlock cross divisional interlocks for for ACU1A and 2A. ACU1A and 2A.

If HVC*ACUlB is not running, the following step should cause an automatic start of HVC*ACUlB.

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o=:--- ~~eDF NINE MILE POINT .

NUCLEAR STATION *

9. At 2CEC*PNL871, place keylock switch p APPENDIX R CR ACU1B OVERRIDE SW, to OVERRIDE.
10. Verify HVC*ACU1B running. p SAT I UNSAT STD: Observes the RED running light is lit and the GREEN off light is not lit for ACU1B
11. WHILE continuing in this subsection, wait p SAT I UNSAT approximately 2 minutes, THEN confirm STD: Determines the time the proper operation of HVC*ACU1B.

Appendix R switch was placed in OVERRIDE and determines when two minutes will be completed. Continues on to the next step while waiting for two minutes to be complete.

12. Place HVC*ACU1B control switch, CONTROL p SAT I UNSAT ROOM AC FAN, in Normal-After-START.

STD: At 2CEC*PNL871, places the control switch for HVC*ACU18 in NORMAL-AFTER-START (i.e. Red Flag).

If HVC*ACU2B is not running, the following step should cause an automatic start of HVC*ACU2B.

13. At 2CEC*PNL871, place keylock switch p APPENDIX R RR ACU2B OVERRIDE SW, to OVERRIDE.

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0~ .;~eDf NINE MILE POINT Nl.Ct.EAR STATION Once the second Appendix R switch is placed in OVERRIDE, mark down the time the step was completed here:

Calculate the time the operator took to complete the critical steps of the JPM by subtracting the start time from the time documented above. Document the completed time here: minutes

14. Evaluator, determine if the critical task NIA completion time was within the required timeframe.
15. Verify HVC*ACU2B running. p SAT I UNSAT STD: Observes the RED running light is lit and the GREEN off light is not lit for ACU28
16. WHILE continuing in this subsection, wait p SAT I UNSAT approximately 2 minutes, THEN confirm STD: Determines the time the proper operation of HVC*ACU2B.

Appendix R switch was placed in OVERRIDE and determines when two minutes will be completed. Continues on to the next step while waiting for two minutes to be complete.

17. Place HVC*ACU2B control switch, RELAY p SAT I UNSAT ROOM AC FAN, in Normal-After-START.

STD: At 2CEC*PNL871, places the control switch for HVC*ACU28 in NORMAL-AFTER-START (i.e. Red Flag).

Once the HVC*ACU2B control switch is placed in NORMAL-AFTER-START, provide the following cue:

Cue: Your task is complete. Another operator will complete any remaining actions.

JPM 5-7 Page 10 of 12 NRC March 2014

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o::::--- ~~

NINE MILE POINT NUCLEAR STATION The two appendix R switches for ACU18 and 28 have been placed in OVERRIDE.

JPM S-7 Page 11 of 12 NRC March 2014

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0:::--- -!:eDF NINE MILE POINT NLX:LEAR STATION JPM Handout Given:

  • The reactor is at 100% power.
  • A fire has occurred in the Control Building
  • Annunciator 849128, FIRE DETECTED PNL 129 W STAIR/288 is in alarm, with Fire Zone 352 NW as the affected zone.
  • The Fire Brigade Leader has confirmed the fire
  • 2HVC*ACU1A and 2A were running and have since tripped due to the fire.
  • 2HVC*ACU1B and 2HVC*ACU2B have auto started.
  • The Shift Manager's permission has been received to override the control room envelope ACU cross-divisional operating interlock.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Override the Control Room Envelope ACU Cross-Divisional Operating Interlock per N2-0P-53A, Section H.15.0.

This is a Time Critical JPM JPM S-7 Page 12 of 12 NRC March 2014

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o=-- -~~I NINE MILE POINT NUCLEAR ST.-:noN Training Id: 2013 NRC Simulator S-8 Revision: 0.0

Title:

Respond to an Inadvertent Closure of 2SWP* MOVSOB Approvals:*

Signature I Printed Name Developed: By ~ David Huff 12/18/2013 Validated By Jason Sawyer 12/03/2013 Facility Reviewer Aaron Armstrong 1 I

/3 Jz.o 1'1 Approximate Duration: ----=2=-0=---.:...m:..:.:i:..:.:n:...:::u:...::.te=s=----

I Documentation of Performance:

Performer~

Evaluator:*

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: Date:

JPM S-8 Page 1 of 14 NRC March 2014

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0=::--- ~~eof NINE MILE POINT Ntr.lEAR STATION References

1. N2-SOP-11, Loss or Degraded SWP System JPM S-8 Page 2 of 14 NRC March 2014

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O~ -t~eof NINE MILE POINI NUCLF_AR STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operator's ability to respond to an inadvertent closure of 2SWP*MOVSOB per N2-SOP-11
2. Task Information:
a. N2-SOP-11-01001, Respond to SOP-11, Loss of or Degraded Service Water System
b. K/A 400000, A4.01 (3.1/3.0)
3. Evaluation I Task Criteria Perform Simulator No No Yes
4. Recommended Start Location
a. Unit 2 Simulator
5. Simulator Setup (if required)
a. Prepare the simulator as follows:
1) Reset to full power IC
2) Place the control switches for 2SWP*MOVSOB in the CLOSE position and allow it to fully shut.

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NINE MILE POINT NUCLEAR STATlON

3) Allow plant conditions to stabilize for a few minutes.
6. JPM Setup (if required)
a. Prepare a copy of N2-SOP-ll. Include a copy of the Discussion section as well as Attachment 1.

JPM S-8 Page 4 of 14 NRC March 2014

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0~ ~~.eDf NINE MILE POINT NIX:LEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that:additional verification will not be provided.

JPM S-8 Page 5 of 14 NRC March 2014

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0:::::--- ~~I!Of; NINE MILE POINT NUGLF_AR STATION Given:

  • The plant is at 100% power
  • An inadvertent closure of 2SWP*MOVSOB, PMP 1B DISCH HEADER CROSS-TIE ISOL VLV occurred.
  • NO Operator Actions have been completed.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Enter N2-SOP-11, Loss or Degraded Service Water and perform all applicable actions for an inadvertent closure of 2SWP*MOV50B.

1. Provide repeat back of initiating cue p SAT/ UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-SOP-11 and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-0P-11 obtained and the flowchart and Attachment 11 reviewed lAW CNG-PR-2.01-1000, Document Control. Writes the Date and Time the SOP was entered on the top of the flowchart.

Steps 3 through 6 may be performed in any order and/or may be delayed until the "THEN" statement of the override is ready to be performed.

JPM S-8 Page 6 of 14 NRC March 2014

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O=::--- ~:..,

NINE MILE POINT NUClEAR STATION

3. Reviews the overrides of N2-SOP-11 and p SAT I UNSAT determines the following overrides are met:

STD: On 2CEC*PNL601, observes that the Division 1

  • SWP pump flow is GREATER THAN 10,000 SWP flow indicators gpm 2SWP*FI96A and C indicate SWP P1A and C flows are >10K gpm.
4.
  • Additional SWP flow is required p SAT I UNSAT STD: On 2CEC*PNL601, observes that the Division 1 SWP flow indicators 2SWP*FI96A and C indicate SWP P1A and C flows are >10K gpm and that additional SWP flow could be necessary at this time.
5.
  • Pump flow can NOT be maintained above p SAT I UNSAT low flow alarm, STD: On 2CEC*PNL601, observes that Annunciator 601219 is in alarm and that 2SWP*FI968 and D indicate low flow.
6.
  • 2SWP*MOVSOA(B) is inadvertently closed p SAT I UNSAT AND SWP non-essential header isolation STD: Determines per the valves are NOT closed.

turnover that 2SWP*MOV50B Cue: If asked, inform the operator that inadvertently closed.

MOVSOB was inadvertently shut due to Additionally, on 2CEC*PNL601, operator error. observes the RED OPEN light lit and the GREEN CLOSED light not lit for 2SWP*MOV508.

JPM S-8 Page 7 of 14 NRC March 2014

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0==----- ~~...

NINE MILE POINT NUCLEAR STATION There are several strategies for successful mitigation of this event prior to executing Attachment 1. The expected course of action would be for the operator to first start SWP P1E and then throttle the MOV74's of the Division 1 pumps to maintain flows ~10K gpm. The low flow alarm on Division 2 would then be mitigated by establishing SWP flow through RHS B Heat Exchanger.

Alternatively, the operator may choose to not start an extra Division 1 pump at this time and instead choose to only throttle the MOV74s on the already running Division 1 pumps. Either of these methods is acceptable. If the operator chooses not to start another pump at this time, then that step may marked as N/A and is not required to be graded.

Steps 7, 8, and 9 may be performed in any order. Step 11 (Attachment 1) however should not be performed without first completing Steps 8 and 9.

While executing the following step, the operator may choose to reference N2-0P-11 for starting of the additional service water pump. Additionally, the operator may choose to use the general guidance of N2-SOP-11 for starting of the pump.

Either method is acceptable.

Start additional SWP pumps. p Cue: As appropriate, if contacted as a PO, provide feedback to the operator that

7. prestart checks/venting of strainers/good start checks/etc. have been completed.

Successful completion of Step 8 may require the operator to alternate throttling of MOV74's to maintain both pump flows below 10K gpm as indicated on 2SWP*FI96A, C, and/or E. This is acceptable and the step should be graded as PASS provided that at the completion of the step, all pump flows are~ 10K gpm.

8. Throttle SWP*MOV74s as required to p maintain pump flow LESS THAN 10,000 gpm.

JPM S-8 Page 8 of 14 NRC March 2014

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NINE MILE POINT NLCLEAR STATION

9. Throttle SWP flow through an RHR HX as p required.
10. p Cue: If asked as RP, inform the operator that RE23B has been placed in service.

Attachment 1:

  • Initial actions to stabilize the Service Water System are taken per the flowchart and should result in three Division I Service Water Pumps running (if available) with their associated Discharge MOVs throttled as required to maintain pump flows at 10,000 gpm and Service Water flow established to RHS "B" Heat Exchanger to maintain flow for the running Division II Pumps above 2,500 gpm.
11. Perform Attachment 1: p SAT/ UNSAT STD: Contacts a PO and Dispatch Operators to the Valves AND dispatches them to Breakers to determine whether SWP Cross- 2SWP*MOVSOB and its Tie MOV(s) may be re-opened associated breaker and directs them to inspect them for Cue: As the PO dispatched to perform an abnormalities.

inspection of the valve and breaker, inform the operator that the inspection was completed and there are no issues with the valve or breaker.

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NINE MILE POINT Ntx:lF_AR STATION For grading of the below step, the operator may choose either 2SWP*P1B or D to secure. Either one is acceptable. For the pump that is not secured, grading of the applicable step is not required and the step may be marked as N/A.

12. WHEN it has been determined that Service p Water System conditions allow re-opening the SWP Cross-Tie MOV(s), reduce the number of operating Division II Service Wf;lter Pumps to one by placing control switches in Normal-After-STOP AND verifying that the associated Discharge MOVs close:

Cue: If asked as the CRS, inform the operator you have no preference for which pump to secure.

  • 2SWP*P1B AND 2SWP*MOV74B
13.
  • 2SWP*P1D AND 2SWP*MOV74D p
14.
  • 2SWP*P1F AND 2SWP*MOV74F p SAT/ UNSAT STD: At 2CEC*PNL601, determines 2SWP*P1E is already secured. Marks this step as NA JPM S-8 Page 10 of 14 NRC March 2014

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NINE MILE POINT NUCLEAR STATION

15. IF 2SWP*MOVSOA was closed, open p SAT/ UNSAT 2SWP*MOVSOA by taking BOTH control STD: At 2CEC*PNL601, switches to OPEN determines that 2SWP*MOV50A is NOT closed by observing the RED OPEN light lit and the GREEN CLOSED light not lit.

Marks this step as NA

16. IF 2SWP*MOVSOB was closed, open p 2SWP*MOVSOB by taking BOTH control switches to OPEN The following two steps may be performed concurrently.

Steps 17, 18, and 19 may be performed in any order.

If the operator chose to not start an additional pump while performing the initial flow chart actions, then in order to successfully complete the step for reopening the MOV74's in Division 1, they must start one additional service water pump. If 4 service water pumps are all ready running, then Step 17 may be marked as N/A and is not required to be graded. If however only 3 service water pumps are running at this time, then the operator is required to start an additional service water pump and Step 17 is required to be graded. For Step 17, the operator may choose to start/restart any additional SWP pump from Division 1 or 2.

Additionally, the operator may choose to reference N2-0P-11 or N2-SOP-11 for starting of the additional service water pump. Either method is acceptable. Step 17 may be performed at anytime while in Attachment 1.

JPM S-8 Page 11 of 14 NRC March 2014

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0=:;--- ~~eDf NINE MILE POINT NLCLF_AR STATION

17. Start an additional Service Water Pump p Cue: If asked as the CRS, inform the operator you have no preference for which pump to start.

Cue: As appropriate, if contacted as a PO, provide feedback to the operator that prestart checks/venting of strainers/good start checks/etc. have been completed.

18. WHILE maintaining a minimum of 2,500 gpm p on the running Division II Service Water Pumps, slowly close 2SWP*MOV33B If the operator has not started a 4th service water pump before attempting to complete the next step, they will be unable to fully open all Division 1 MOV74's.

If necessary, provide the following cue if this situation occurs:

Cue: Start a fourth service water pump per the initial flow chart override of N2-SOP-11.

19. WHILE maintaining Pump flows less than p 10,000 gpm, slowly open Discharge MOVs for the running Division I Service Water Pumps JPM S-8 Page 12 of 14 NRC March 2014

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0=:---- ~ietw NINE MILE POINT NUCLEAR STATION

20. Close 2SWP*MOV90B p SAT I UNSAT STD: On 2CEC*PNL601, places the CONTROL SWITCH for 2SWP*MOV908 to CLOSE.

Observes the RED OPEN light not lit and the GREEN CLOSED light lit.

Once the operator has placed the control switch for 2SWP*MOV90B in the CLOSE position, then provide the following cue:

Cue: Your task is complete. Another operator will complete any remaining actions.

2SWP*MOV508 is open, flow is secured through RHS B Heat Exchanger, all MOV74's are fully open with all pump flows 5:10K gpm.

JPM S-8 Page 13 of 14 NRC March 2014

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0=:---- ~~eof NINE MILE POINT NUCLEAR STATION

  • JPM Handout Given:
  • The plant is at 100% power
  • An inadvertent closure of 2SWP*MOVSOB, PMP 18 DISCH HEADER CROSS-TIE ISOL VLV occurred.
  • NO Operator Actions have been completed.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Enter N2-SOP-11, Loss or Degraded Service Water and perform all applicable actions for an inadvertent closure of 2SWP*MOV50B.

JPM S-8 Page 14 of 14 NRC March 2014

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c;;;:~J NINE MILE POINT NUCl.iAA $TATION .

Training Id: 2013 NRC Plant P-18 Revision: 0.0

--=-=-=----

Title:

Local Start of Division 2 Diesel Generator (Alternate Path)

Approv~ls:

Signature I Printed Name Developed By ~ David Huff 12/18/2013 Validated By Mike Storms 12/13/2013 Facility Reviewer '/.,

  • */zot'-1 Aaron Armstrong Approximate Duration: ---=1=-=S:..._m:....:...:...::in..:...:u=-=t=e-=-s_ _

Documentation of Performance:

Performer.:

Evaluator:

Start Time: - - - - Stop Time: Completion Time Grade: ** Pass I Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

JPM P-lB Page 1 of 16 NRC March 2014

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o=::--- -!:f!Df NINE MILE POINT NUCLEAR STATION References

1. NS-OSP-EGS-M@001, Diesel Generator and Diesel Air Start Valve Operability Test - Division 1 and 2
2. N2-0P-100A, Standby Diesel Generators JPM P-lB : Page 2 of 16 NRC March 2014

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O=:-- ~:,.

NINE MILE POINT NLCLFJ\R STATION Instructor Information A. JPM Information

1. Description
a. This JPM tests the operator's ability to locally start and secure the Division 2 Emergency Diesel Generator.
b. :This JPM is considered alternate path because after locally starting the Division 2 Emergency Diesel Generator, a low lube oil condition will occur.

The operator will mitigate the event by manually shutting down the diesel.

c. Note this JPM is written for the Division 2 Diesel. If plant conditions do
  • not support entering the Division 2 Diesel Room, then an alternate JPM is available (JPM P-1A) to use for the Division 1 Diesel.
2. Task Information:
a. N2-264001, Perform Emergency Stop of Division 1 (2) Emergency Diesel Generator
b. K/A 264000, A4.04 3.7/3.7
3. Evaluation I Task Criteria Simulate Plant No Yes Yes JPM P-lB Page 3 of 16 NRC March 2014

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0==---- ~-::..

NINE MILE POINT NUCLEAR STATION

4. Recommended Start Location
a. Unit 2 WEC
5. JPM Setup (if required)
a. Prepare a copy of N2-0SP-EGS-M@001, Section 8.2. Include a copy of the precautions and limitations.
b. Print out a full copy of N2-0P-100A and N2-0SP-EGS-M@001 for use by the operators when they are preparing to perform the JPM.
c. Additionally, prepare separate copies of N2-0P-100A, Section H.1.0. Do not hand this section out to the operator until cued by the JPM.

JPM P-18 Page 4 of 16 NRC March 2014

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NINE MILE POINT NLO.EAR STATION B. Read Before Every lPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This*evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM P-lB Page 5 of 16 NRC March 2014

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NINE MILE POINT Ntr.LF.AR STATION Given:

  • The plant is at 100% power.
  • N2-0SP-EGS-M@001, Diesel Generator and Diesel Air Start Valve Operability Test is about to be performed for the Division 2 Diesel.
  • N2-0SP-EGS-M@001, Steps 8.2.1 through 8.2.6 have been completed
  • You are the Plant Operator in the Field assigned to support the Diesel Run.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform the Diesel Generator Regular Monthly Start and Load Test for the Division 2 Diesel per N2-0SP-EGS-M@001, Section 8.2.

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used JAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-0SP-EGS-M@001 and p SAT I UNSAT review I utilize the correct section of the STD: Current version of N2-procedure 0SP-EGS-M@001 obtained and Section 8.2 referenced JAW CNG-PR-2.01-1000, Document Control.

All indications and controls are located at 2CES*IPNL406 (408) unless otherwise specified.

JPM P-1B Page 6 of 16 NRC March 2014

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NINE MILE POINT NUCLEAR STATION .

3. At 2CES*IPNL407 (412), GENERATOR s SAT/ UNSAT CONTROL PANEL, verify Voltage Regulator STD: At 2CES*IPNL412, Switch in AUTO.

Observes the Voltage Regulator Cue: The Voltage Regulator Switch is in Switch is already in AUTO.

AUTO

4. At 2CES*IPNL406 (408), ENGINE CONTROL s PANEL, place CONTROL MODE keylock switch in LOCAL AND ensure the white LOCAL indicating light is illuminated.

CL;Je: The CONTROL MODE keylock switch is in LOCAL and the white LOCAL indicating light is illuminated.

5. At 2CEC*PNL852, ELECTRIC CONTROL p SAT/ UNSAT BOARD, perform the following:

STD: Contacts the control room

  • Verify DIVISION 1 (2) 2EGS*EG1 (EG3) and directs them to perform START switch in Normal-After-STOP. Step 8.2.9.
  • . Verify 2ENS*SWG101-N1 (103-N1),

NEUTRAL BREAKER 101-N1 (103-N1),

closed.

  • Verify EMERGENCY DSL GEN 1 (3)

VOLTAGE REGULATOR MODE SELECT switch in AUTO.

Cue: As the control room, acknowledge the direction to perform Step 8.2.9.

Inform the operator that Step 8.2. 9 is complete.

In the following step when the EMERGENCY DSL GEN 1 (3) PARALLEL switch is placed to ON, the REMOTE indicating light will illuminate for the CONTROL MODE switch at panel 2CES*IPNL406 (408) resulting in dual LOCAL/REMOTE indication.

JPM P-1B

  • Page 7 of 16 NRC March 2014

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Oc:-- ~:erw NINE MILE POINT NUCLEAR STATION

6. At 2CEC*PNL852, place EMERGENCY DSL s SAT I UNSAT GEN 1 (3) PARALLEL switch to ON.

STD: Contacts the control room Cue: As the control room, acknowledge the and directs them to perform direction to perform Step 8.2.10. Step 8.2.10. Once the step is Inform the operator that Step 8.2.10 is completed, observes the complete. REMOTE indicating light is illuminated at 2CES*IPNL406 Cue: The REMOTE indicating light is illuminated.

False negative results for IST test of air start valves can be received if diesel air compressor(s) are running prior to taking data in the following step.

7. Record 2EGA-PI15A (B), STARTING AIR s SAT I UNSAT PRESS:

STD: At 2EGA-PI15B,

  • RED-L. RECEIVER documents the pressures
  • BLACK-R. RECEIVER indicated in Step 8.2.11 Cue: Both receiver tanks read 240 psig.
8. At 2CES*IPNL406 (408), depress ENGINE s CONTROL START pushbutton.

Cue: The ENGINE CONTROL START pushbutton has been depressed. You hear the sound of the diesel starting up. It sounds like a normal start.

9. At 2CES*IPNL407 (412), GENERATOR s SAT I UNSAT CONTROL PANEL, observe the following STD: At 2CES*PNL412, Diesel Generator start indications:

observes the diesel speed on the RPM meter indicates 600

  • Diesel Speed as indicated on 12ESI- RPM.

2EGSA04 (12ESI-2EGSB04), ENGINE SPEED, rises to about 600 RPM Cue: Diesel Speed indicates 600 RPM JPM P-1B Page 8 of 16 NRC March 2014

NINE MILE POINT NUCLF.AR STATION

10. *
  • Generator Voltage as indicated on GVM- s SAT I UNSAT 2EGPA22 (GVM-2EGPB22), VOLTS STD: At 2CES*PNL412, GENERATOR, rises to about 4160 A-C observes the Diesel Voltage at VOLTS 4160 Volts.

Cue: Diesel Voltage indicates 4160 Volts

11.
  • Generator Frequency as indicated on FM- s SAT I UNSAT 2EGPA22 (FM-2EGPB22), FREQUENCY STD: At 2CES*PNL412, GENERATOR, rises to about 60 HERTZ observes the Diesel Frequency Cue: Diesel Frequency indicates 60 Hertz at 60 Hertz.
12.
  • Generator Field Current as indicated on s SAT I UNSAT GFAM-2EGPA21 (GFAM-2EGPB21), AMPS STD: At 2CES*PNL412, FIELD, rises to about 91 DC AMPERES observes the Generator Field Cue: Generator Field Current has risen to 91 Current has risen to 91 DC DC AMPS Amps.
13. At 2CEC*PNL852, observe the following s SAT I UNSAT Diesel Generator start indications:

STD: Contacts the control room

  • SWP*MOV66A (B), SERVICE WTR and directs them to perform OUTLET, opens Step 8.2.14.
  • Diesel Service Water Flow indicated on 2SWP*FI76A (B), SERVICE WTR FLOW, is

~800 GPM

RUNNING, alarms Cue: As the control room, acknowledge the direction to perform Step 8.2.14.

Inform the operator that Step 8.2.14 is complete Once the diesel is up and running, the Evaluator will give a cue to the operator that there is an alarm at the Diesel Control Panel. The operator will respond and determine that a low oil pressure condition exists and the diesel should have shutdown automatically. The operator will take action to manually shutdown the diesel.

JPM P-1B Page 9 of 16 NRC March 2014

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o::::::--- ~~

NINE MILE POINT NUCLEAR STATION The cause of the low lube oil pressure condition must be corrected prior to restart of the Diesel Generator.

14.

Cue: Inform the operator that there is an s SAT I UNSAT audible alarm coming from STD: Responds to the 2CES*IPNL408. When the operator annunciator by referencing the looks at the Annunciator tiles, inform ARP for 408-1-1. Determines the operator that Annunciator 408-1-1, the Diesel is operating in TEST Low Lube Oil Pressure Engine is MODE and should have shut alarming.

down automatically.

Acknowledges direction to ARP for Annunciator 408-1-1: perform an emergency shutdown of the Division 2 IF in the test mode, VERIFY that the EDG.

automatic response occurs.

Cue: Inform the operator that the diesel is still running and if asked for Lube Oil Pressure, inform him that lube oil pressure indication is 15 psig.

Cue: Once the operator determines the diesel did not shutdown and should have, direct the operator to "Perform an Emergency Shutdown of the Division 2 Emergency Diesel lAW N2-0P-100A, Section H.1. 0". Hand the operator the procedure section for N2-0P-1 OOA, Section H.1.0.

JPM P-1B Page 10 of 16 NRC March 2014

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O:::;--u- ~:eDF NINE MILE POINT NLCLEAR STATION

15. IF Diesel Generator is in Test Mode, perform s the following: SAT I UNSAT
  • At 2CEC*PNL852, using GOVERNOR STD: May determine this step switch, reduce Diesel Generator Load to is already complete as the 100 KW. diesel has not been loaded -or-
  • Using VOLTAGE REGULATOR switch, may contact the control room adjust VARS to >0 AND <100 A-C and directs them to perform N2-0P-100A, Step H.1.1.

KILOVARS TO BUS.

  • Open 2ENS*SWG101-1 (103-14),

OUTPUT BREAKER 101-1 (103-14).

  • Continue at Step H.1.3.

Cue: If necessary as the control room, acknowledge the direction to perform N2-0P-1 OOA, Step H.1.1. Inform the operator that Step H.1.1 is complete The following step will cause the Diesel Generator to stop immediately without a cooldown period.

16. At 2CES*IPNL406 (408), ENGINE CONTROL s SAT I UNSAT PANEL, depress EMERGENCY STOP red STOP STD: At 2CES*INPL408, pushbutton.

depresses the EMERGENCY Cue: The EMERGENCY STOP red STOP STOP pushbutton. Determines pushbutton has been depressed. The the diesel did not stop.

diesel continues to run.

In order to shutdown the diesel, the operator is required to perform Step 17, 18, or 19. Performance of any one of the steps will cause the diesel to shutdown. Once the operator decides on which method they would like to use to shutdown the diesel, the step must be graded. If the operator fails to perform that step correctly, then the step is graded as FAIL. The steps not performed are not required to be graded and may be marked as NA.

For a description of each of the below methods see the evaluators job aide at the end of this JPM.

JPM P-1B Page 11 of 16 NRC March 2014

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dJOIL:vorJtumof---

0=::--- ~;ew NINE MILE POINT NUClEAR STATION

17. IF Diesel does NOT stop, perform one of the s following:

Depress button AND pull Manual Fuel Control Quadrant Handle down AND hold down UNTIL Diesel Generator comes to a complete st~p.

Cue: The BUTTON has been depressed and MANUAL FUEL CONTROL QUADRANT HANDLE is down. The diesel is starting to coast down.

Cue: After 5 seconds, as long as the operator continues to hold the handle down, provide the following cue "The diesel has come to a complete stop".

18. Pull out latching rod of Overspeed Trip Valve s at Overspeed Governor.

Cue: The LATCHING ROD of the OVERS PEED TRIP VALVE at the overspeed GOVERNOR has been PULLED. The diesel is coasting down.

19. Trip Combustion Air Inlet Butterfly Valve s closed by pulling Overspeed Governor output lever towards the Generator End with a 1" open ended wrench. (The action will force the output arm towards the Butterfly Valve.)

Cue: A 1 inch open ended wrench has been obtained.

Cue: The OVERSPEED GOVERNOR OUTPUT LEVER has been PULLED towards the GENERATOR END. The COMBUSTION AIR INLET BUTTERFLY VALVE has been tripped. The diesel is coasting down.

JPM P-1B Page 12 of 16 NRC March 2014

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NINE MILE POINT NLIC'A.F.AR STATION Once the operator is informed that the diesel is coasting down, provide the following cue:

Cue: Your task is complete. Another operator will complete any remaining actions.

An Emergency Trip has been performed on the Division 2 Diesel.

JPM P-lB Page 13 of 16 NRC March 2014

CENG.

NINE MILE POINT Ntx:LEAA STATION Evaluator lob Aid Do Not Provide to Candidate Manual Fuel Control Quadrant Handle:

Manual Fuel Handle (Push Button and Pull Down)

JPM P-lB Page 14 of 16 NRC March 2014

CENG.

NINE MILE POII>lf NUCLEAR STATION Evaluator lob Aid Do Not Provide to Candidate Overspeed Trip Valve and Combustion Air Inlet Butterfly Valve:

  • On the Walkway where the Diesel Connects to the Generator.
  • Looking over the railing straight down at the two trip devices.

Combustion Air Inlet Butterfly Valve (Using Wrench, pull towards Generator end)

Latching Rod of the Overspeed Trip Valve (Pull Out)

JPM P-lB Page 15 of 16 NRC March 2014

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NINE MILE POINT NUCLEAR STATION JPM Handout Given:

  • The plant is at 100% power.
  • N2-0SP-EGS-M@001, Diesel Generator and Diesel Air Start Valve Operability Test is about to be performed for the Division 2 Diesel.
  • N2-0SP-EGS-M@001, Steps 8.2.1 through 8.2.6 have been completed
  • You are the Plant Operator in the Field assigned to support the Diesel Run.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Perform the Diesel Generator Regular Monthly Start and Load Test for the Division 2 Diesel per N2-0SP-EGS-M@001, Section 8.2.

JPM P-18 Page 16 of 16 NRC March 2014

CENG.*

J

  • =-

a joint venture of NINe MII.E POINT NUCl.SAR ST..moN

-tr-Training I<;l: 2013 NRC Plant P-2 Revision: 0.0

_..::....::....:=.__ __

Title:

Isolate a Hydraulic Control Unit with Cooling Water Approvals:

Signature I Printed Name Developed By ---~/----__

  • _ _ _ _ _ _ _D=-a=-v: . .:. id=-. :._H=-=u~f 12/18/2013 Validated By Mike Storms 12/13/2013 Facility Reviewer Aaron Armstrong I rr Jg /l.J:J/'-j Approximate Duration:

"' 15 minutes Documentation of Performance:

Performer*:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

JPM P-2 Page 1 of 9 NRC March 2014

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0=:---- ~~.eoF NINE MILE POINT NUGLF.AR STATION References

1. N2-0P-30, Control Rod Drive JPM P-2 Page 2 of 9 NRC March 2014

CENG~

NINE MILE POINT NUClEAR STAllON Instructor Information A. JPM Information

1. Description
a. This JPM tests the operator's ability to isolate a Hydraulic Control Unit With Cooling Water.
2. Task Information:
a. N2-201001-04006, Isolate a Hydraulic Control Unit
b. K/A 203000, A2.02 3.5/3.5
3. Evaluation I Task Criteria Simulate Plant No No Yes
4. Recommended Start Location
a. Unit 2 WEC
5. JPM Setup (if required)
a. Prepare a copy of N2-0P-30, Section 8.0. Include a copy of the precautions and limitations.

JPM P-2 Page 3 of 9 NRC March 2014

aj01f1:verrturoof--

O=:-- -::~-

NINE MILE POINT NLCLEAR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM P-2 Page 4 of 9 NRC March 2014

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0=:::--- ~~eof NINE MILE POINT NUClEAR STATION Given:

  • The plant is at 100% power.
  • The CRS has determined HCU 22-59 needs to be isolated.
  • No other HCUs are currently isolated.
  • Maintenance is not going to be performed on HCU 22-59 and it will not be isolated for an extended period of time.
  • A drain line has already been installed and routed per N2-0P-30, Step

8.2.5 Evaluator

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Isolate HCU 22-59 with cooling water per N2-0P-30, Section F.B.O.

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used JAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-0P-30 and review I p SAT I UNSAT utilize the correct section of the procedure STD: Current version of N2-0P-30 obtained and Section 8.0 referenced JAW CNG-PR-2.01-1 000, Document Control.

Where XX-YY appears, XX-YY is the number of the HCU being manipulated.

JPM P-2 Page 5 of 9 NRC March 2014

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0~ ~:erw NINE MILE POINT NUCLEAR STATlON Isolating an HCU without cooling water should be performed when reactor water temperature is less than 200°F, or isolating an HCU without cooling water when reactor water temperature is greater than 200°F should be minimized (less than one shift duration) or seal degradation could occur.

When returning an isolated HCU to service, extreme care must be taken.

Restore cooling water slowly or thermal shock and seal damage could occur.

Isolating HCUS with 2RDS*V101(XX-YY) or 2RDS*V104(XX-YY) closed raises the Cooling Water Differential Pressure. A Cooling Water Differential Pressure of 35 psid is sufficient to operate the Collet Piston and unlatch Control Rods which could result in unplanned Control Rod withdrawals. Isolating more than 80 HCUs with a CRD Pump in service could raise Cooling Water Differential Pressure to ~35 psid and result in unplanned Control Rod withdrawals. Refer to INPO SEN 264. [C12]

The following step is to be performed to prevent control rod movement, not for maintenance.

A withdrawn control rod that is stuck should be disarmed hydraulically, preferably with cooling water flow, per the following step (hydraulically disarming a withdrawn control rod that is stuck is required in accordance with Technical Specification 3.1.3).

3.

IF. an RDS Pump is in service, verify '5.79 s SAT/ UNSAT HCUs are isolated.

STD: Determines per the turnover that 2RDS-P1A is in service and no additional HCUs are isolated.

4.

Close 2RDS*V101, (XX-YY) Insert Isolation.

s Cue: 2RDS*V1 01 is closed.

JPM P-2 Page 6 of 9 NRC March 2014

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o:::--- ~~..,.

NINE MILE POINT

  • NUCLEAR STATION 5.

Close 2RDS*V102, (XX-YY) Withdraw s

Isolation.

Cue: 2RDS*V1 02 is closed.

6.

Close 2RDS-V113, (XX-YY) Charging Water s

Isolation.

Cue: 2RDS*V113 is closed.

Rx water will drain out of 2RDS*V107 if a Reactor Scram occurs.

7.

Using thread lubricant, (Locktite 58031 -

s SAT I UNSAT symbol number 95-74-180), ATTACH drain STD: Determines per the line to HCU at 2RDS*V107, (XX-YY) turnover that this step is Accumulator Drain AND route to complete.

floor/equipment drain. (Lubricant use N/A for Swagelok Fittings) 8.

Slowly open 2RDS*V107 (XX-YY) to s

depressurize accumulator.

Cue: 2RDS*V107 is open. The accumulator is depressurized.

9.

Close 2RDS*V107 (XX-YY).

s Cue: 2RDS*V107 is closed.

JPM P-2 Page 7 of 9 NRC March 2014

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NINE MILE POINT NUClEAR STATION 10.

Open 2RDS*V107 (XX-YY) one turn.

s Cue: 2RDS*V107 is open one turn.

11.

Close 2RDS-V103, (XX-YY) Drive Water s

Isolation.

Cue: 2RDS*V103 is closed.

12.

Close 2RDS-V105, (XX-YY) Exhaust Water s

Isolation.

Cue: 2RDS*V105 is closed.

13.

Open 2RDS*V101, (XX-YY) Insert Isolation.

s Cue: 2RDS*V101 is open.

2RDS*V101 has been opened for HCU 22-59 JPM P-2 Page 8 of 9 NRC March 2014

CENG .

NINE MILE POINT NUClEAR STATION

  • JPM Handout Given:
  • The plant is at 100% power.
  • The CRS has determined HCU 22-59 needs to be isolated.
  • No other HCUs are currently isolated.
  • Maintenance is not going to be performed on HCU 22-59 and it will not be isolated for an extended period of time.
  • A drain line has already been installed and routed per N2-0P-30, Step

8.2.5 Evaluator

Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Isolate HCU 22-59 with cooling water per N2-0P-30, Section F.B.O.

JPM P-2 Page 9 of 9 NRC March 2014

o.- '*-"I '

NINE MILE POINT

  • NUCLEAR ST.oJION Training Id: 2013 NRC Plant P-3 Revision: 0.0

--=-=-=----

Title:

Align Firewater to RHS B Approvals:

Printed Name Developed By Validated By Mike Storms 12/13/2013 Facility Reviewer c . :~C\ =.... Q

- Aaron Armstrong Approximate Duration: ---=2=-=0:.....:m:..:..:...:.:in..:....:u=-=t:..=:e=-s_ _

Documentation of Performance:

Performer:

Evaluator:

Start Time: Stop Time: Completion Time Grade: Pass I Fail Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ __ Date:

JPM P-3 Page 1 of 9 NRC March 2014

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NINE MILE POINT NLCLEAR STATION References

1. N2-EOP-6.6, RHR Fire Water Cross-Tie JPM P-3 Page 2 of 9 NRC March 2014

CENG~

aJQII;~Vflfl~utnol--

o==---- ~~etlf NINE MILE POINT NUCLEAR STAl10N Instructor Information A. JPM Information

1. Description
a. This JPM tests the operator's ability to align Fire Water to the RHS
  • system.
2. Task Information:
a. N2-EOP06-01001-06, Implement N2-EOP-6.6, Cross-Tie RHR Fire Water System
b. K/A 203000, A2.02 3.5/3.5
3. Evaluation I Task Criteria Simulate Plant No No Yes
4. Recommended Start Location
a. Unit 2 WEC
5. JPM Setup (if required)
a. Prepare a copy of N2-EOP-6.6, Section 6.2. Include a copy of the
precautions and limitations.

JPM P-3 Page 3 of 9 NRC March 2014

CENG.

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0=:---- ..:,.,

NINE MILE POINT NUCLF_AR STATION B. Read Before Every JPM Performance

1. For the performance of this JPM, I will act as all those you need to talk to.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

(Note, read the next only if conducting a plant JPM). With the exception of accessing panels, no plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

C. Read Before Each Evaluated JPM

1. This evaluated JPM is a measure of your ability to perform this task independently. The CRS has determined that a verifier is not available and that additional verification will not be provided.

JPM P-3 Page 4 of 9 NRC March 2014

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0=:---- ..:~eof NINE. MILE POINT NUCI.EAR STATION Given:

  • A LOCA has occurred.
  • The CRS has determined Fire Water is needed for injection into the RPV via RHS B.
  • N2-EOP-6.6, Steps 6.2.1 through 6.2.5 have been completed.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Align Fire Water to RHS Loop B per N2-EOP-6.6, Section 6.2.

1. Provide repeat back of initiating cue p SAT I UNSAT Cue: Acknowledge repeat back providing STD: Proper communications correction if necessary. used lAW CNG-OP-1.01-2001, Communications and Briefings.
2. Obtain a copy of N2-EOP-6.6 and review I p SAT I UNSAT utilize the correct section of the procedure.

STD: Current version of N2-EOP-6. 6 obtained and Section 6.2 referenced lAW CNG-PR-2.01-1000, Document Control.

3.

Verify closed 2CNS-V622, CNS TO RHR s SAT I UNSAT SUPPLY ISOL (Rx Bldg, EL289 Southside STD: Checks 2CNS-V622 is across from CRD maintenance room) closed by rotating the hand Cue: 2CNS-V622 is closed. wheel in the clockwise direction and observing no movement.

JPM P-3 Page 5 of 9 NRC March 2014

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0=:-- -::.-

NINE MILE POINT Nlr.LEAR STATION 4.

Verify closed 2RHS*V79, CONDENSATE s SAT I UNSAT FLUSH TO HEAD SPRAY HDR ISOL. (Rx Bldg STD: Checks 2RHS*V79 is EL 289) closed by rotating the hand Cue: 2RHS*V79 is closed. wheel in the clockwise direction and observing no movement.

Residual pressure may exist when removing the test connection blind flange between valves 2CNS-V622 and 2RHS*V79 (Figure 4).

Several of the remaining steps require specific tools and/or equipment from the EOP Gang Box Located on RB 289'. The operator should show the evaluator where the gang box is, but SHOULD NOT open the gang box or break the inventory seal for any step in this JPM. As necessary the evaluator may question the operator as to what tools he/she is obtaining from the box.

5.

Remove test connection blind flange from s

between valves 2CNS-V622 AND 2RHS*V79 (Figure 4). (Rx Bldg EL 289)

Cue: Blank Flange is removed.

6.

Install 2V2" firehose adapter to test s

connection flange (Figure 4). (Rx Bldg EL 289)

Cue: The 2.5" firehose adapter to test connection flange is installed.

JPM P-3 Page 6 of 9 NRC March 2014

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0:::-- ~~.eOF NINE MILE POINT

  • NLClEAR STATION 7.

Connect male end of 2112 firehose from EOP s

gangbox, to test connection flange a~apter(Figure 4). (Rx Bldg EL 289 Cue: The male end of the 2.5" firehose is connected to the test connection flange adapter.

FHR 78 (Rx Bldg EL 289 near South stairwell entrance) OR FHR 86 (Rx Bldg EL 289 Across from SLS Tank) may be used to supply firewater to RHS B.

N2-EOP-6.6 allows the operator to lineup fire water from either FHR 78 or FHR 86. The operator may choose either one.

8.

Align firewater supply to RHR B via test s

connection flange adapter as follows: (Rx Bldg, EL 289, near South stairwell entrance)

  • Disconnect firehose at FHR 78 OR FHR 86 Cue: The firehose is disconnected from FHR 78(86) 9.
  • Connect 2V2" EOP firehose from test s

connection flange adapter, to FHR 78 OR FHR 86 Cue: The EOP firehose is connected to FHR 78(86) 10.

OR 2FPW-V383, FHR 86 ANGLE VALVE Cue: 2FPW-V375 -or- 2FPW-V383 is open.

The firehose is pressurizing.

JPM P-3 Page 7 of 9 NRC March 2014

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NINE MILE POINT NLCLEAR STATlC)N 11.

  • Unlock AND open 2RHS*V79. (Rx Bldg EL s

289)

Cue: 2RHS*V79 is open.

The firehose has been connected to the test flange and is pressurized.

2RHS*V79 is open.

JPM P-3 Page 8 of 9 NRC March 2014

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a 101'~: \'Qflturn:Jf

  • 0:=:--- -!~.,

NINE MILE POINT NUCLEAR STAT10N JPM Handout Given:

  • A LOCA has occurred.
  • The CRS has determined Fire Water is needed for injection into the RPV via RHS B.
  • N2-EOP-6.6, Steps 6.2.1 through 6.2.5 have been completed.

Evaluator: Ask trainee if he/she has any questions after presenting initial conditions (Operators Name), Align Fire Water to RHS Loop B per N2-EOP-6.6, Section 6.2.

JPM P-3 Page 9 of 9 NRC March 2014

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a p!nl verrturo ~--~--

1 0~ ~~f:

NINo MILE POINT NliCL F.AR S fA110N Copy of __

Training Id: NRC 2013 Scenario 1 Revision: -0.0 ----

RL 2- Small break LOCA and loss of high pressure injection.

Title:

BIQwdown Required and recover level with low pressure ECCS Signature I Printed Name Developed By David Huff (2[11/zon Validated By Michael Storms r2/f~/LDIJ Phil MacEwen Doug Mizener Facility Reviewer Aaron Armstrong , /3/2-ai'J Page 1 of 33 NRC Scenario 1

CENG NINE MILE POINT NUCLEAR STATION References

1. N2-0P-101D, Power Changes
2. N2-0P-11, Service Water System
3. N2-0P-33, High Pressure Core Spray System
4. N2-SOP-30, Control Rod Drive Failures
5. N2-SOP-03, Loss of AC
6. N2-EOP-RPV, RPV Control
7. N2-EOP-PC, Primary Containment Control
8. N2-EOP-C2, RPV Slowdown
9. Unit 2 Technical Specifications Page 2 of 33 NRC Scenario 1

CENG.

NINE MILE POIN1 NUCI EAR STATION NOTES Instructor Information A. Scenario Description Sequence of Events I Expected Crew Response:

The plant is operating at 90% power with 2WCS-P1B out of service for maintenance. The crew will take the shift and raise reactor power to 95% using recirculation flow. After the reactivity maneuver, Service Water Pump 1A will trip on motor electric fault.

The crew will take action to start a standby service water pump per N2-0P-11.

  • When starting the standby pump, the discharge valve will fail to automatically open requiring the crew to manually open the valve.

Once the standby service water pump is started, HPCS inadvertently initiates and injects into the RPV. FWLC will respond and automatically maintain RPV level below the Level 8 setpoint.

The crew will attempt to reset HPCS and place it back in standby per N2-0P-33, however the HPCS malfunction will prevent the system from being returned to standby. The crew will be required to place HPCS in pull to lock (PTL). After the HPCS pump is in PTL, suction strainer clogging will cause the running Control Rod Drive Pump to trip. The crew will take action per N2-SOP-30 and swap suction strainers. Once the suction strainers have been swapped, the crew will restart the Rod Drive pump.

Following the restoration of the Control Rod Drive Pump, a loss of both Line 5 and 6 will occur. An electrical fault will cause a complete loss of the Division 1 electrical switchgear. A fault on the Division 2 EDG will prevent it from automatically starting. The crew will take actions per N2-SOP-03 and manually start the Division 2 EDG and power the Division 2 electrical switchgear (CRITICAL TASK). The loss of Division 1 switchgear will require the crew to manually scram the reactor, trip the turbine, and trip Page 3 of 33 NRC Scenario 1

,,l(uf'*;~:,v,,*i*:ll---

NINE MILE POIN 1 NUCI EAR STATION NOTES both recirq.Jiation pumps. The crew will enter N2-EOP-RPV and begin actions to stabilize RPV pressure and level.

After the reactor is scrammed, a small LOCA will occur. The LOCA will cause RPV level to lower. The crew will attempt to maintain level using HPCS, however once HPCS is taken out of PTL, it will trip on motor electric fault. The crew will attempt to start RCIC for level control, however it will fail to automatically start using the initiation pushbutton. Once the crew manually starts up RCIC, it will trip on a failed pressure transmitter. The crew will manually start the Standby Liquid Control system (SLS). When RPV level reaches the TAF, the CRS will enter N2-EOP-C2 and direct all 7 ADS valves be opened. The crew will open the ADS valves and blowdown the reactor (CRITICAL TASK). As RPV pressure lowers, the low pressure ECCS systems will begin to inject and recover RPV level. The crew will control the low pressure ECCS systems to raise RPV level back to the normal band.

1. Termination Criteria
a. :RPV level has been recovered above the top of active fuel.
2. Critical Tasks CT-1. 0 Justification: This task is identified as critical because without operator action to manually start the Division 2 EDG, the station would be in Station Blackout conditions.
a. CT-1.0, Given a failure of the Division 2 EDG to start, the crew will take action to manually start the Division 2 EDG lAW N2-SOP-03 CT-2.0 Justification: This task is identified as critical because without operator action to open the 7 ADS valves, RPV water level would continue to lower until the fuel is no longer adequately cooled.

Page 4 of 33 NRC Scenario 1

CENG.

NINl MILE POINl NLCLEAR STATION NOTES

b. CT-2.0, Given RPV water level at or below the TAF but above the MSCWL, the crew will open 7 ADS valves lAW

.N2-EOP-C2

3. Length
a. "'70 minutes
4. Mitigation Strategy Code
a. :RL 2- Small break LOCA or loss of high pressure injection, RPV level cannot be maintained above the top of active fuel, RPV Blowdown, recover level above TAF with low pressure systems and I or alternate coolant injection systems.
5. Technical Specifications
a. TS 3.7.1
b. TS 3.5.1
6. EAL Classification
a. Alert, FA1.1, ANY loss or ANY potential loss of EITHER Fuel Clad barrier OR RCS barrier.
b. Table F-1, RCS Barrier A.1, B.2, C.4
c. Alert, SA1.1, AC power capability to 4.16 KV emergency buses 2ENS*SWG101 and 2ENS*SWG103 reduced to a single power source, Table S-1, for~ 15 min. (Note 4)

AND ANY additional single power source failure will result in a loss of all power to 4.16 KV emergency buses 2ENS*SWG101 and 2ENS*SWG103

7. Special Orders
a. None Page 5 of 33 NRC Scenario 1

CENG .

NIN£ MILE f'OINl NUCLEAR STATION NOTES B. Initial Conditions

1. IC Number
a. IC-150
2. Presets I With Triggers
a. Malfunctions
1) CWlOE, 2SWP*MOV74E FAILS TO AUTO-OPEN INSERTED
2) CWlOF, 2SWP*MOV74F FAILS TO AUTO-OPEN INSERTED
3) DG04B, DIV 2 EDG FAILS TO AUTO START, INSERTED FV=TRUE
4) RCOl, RCIC AUTO START FAILURE INSERTED
5) CWOlA, SWP A TRIP, FV=TRUE TRGl
6) CSOlB, HPCS INITIATION ON LOW LEVEL, TRG2 FV=TRUE
7) RD18, CLOGGED RDS SUCTION STRAINER, TRG3 FV=TRUE
8) ED02A, LOSS OF LINE 5, FV=TRUE TRG4
9) ED02B, LOSS OF LINE 6, FV=TRUE, DT=3 TRG4
10) EDOSA, DIV 1 BUS FAULT, FV=TRUE, DT=10 TRG4
11) RR20, DBA LOCA, FV=0.5, RT=15:00 TRG15
12) RC06, RCIC TURBINE TRIP, FV=TRUE, DT=30 TRG16
13) CSOS, HPCS PUMP TRIP, FV=TRUE, DT=5 TRG17
b. Remotes
1) CWSS, 2SWP*MOV95A BKR, FV=OPEN, DT=120 TRGS
2) CW54, 2SWP*MOV95A VALVE POSITION, FV=O, TRGS DT=120
3) CWSS, 2SWP*V1230 VALVE POSITION, FV= 100, TRGS DT=130 Page 6 of 33 NRC Scenario 1

CENG.

NINE MIL£ POINT NUCLEAR STATION NOTES

4) CW59, 2SWP-V1233 VALVE POSITION, FV=OPEN, TRG5 DT=130
5) DG10, HPCS LOCKOUT RESET, FV=RESET, TRG5 DT=140
6) CW57, 2SWP*MOV95B BKR, FV=OPEN, DT=20 TRG6
7) CW56, 2SWP*MOV95B VLV POSITION, FV=O, TRG6 DT=25
8) RM02-041, SWP 23B RAD MONITOR ONLINE, TRG7 FV=ON
9) RM03-041,SWP 23B RAD MONITOR SAMPLE PUMP TRG7 POWER, FV=ON
c. Overrides
1) None
d. Annunciators
1) None
e. Event Triggers Event # Event Action command 15 zdrps1d==1 (mode switch to SD) Blank 16 hzarcr606>0.625 (RCIC flow meter Blank

>500 gpm) 17 zdrps1d==1 .and. hzacshr603>0.04 Blank (mode switch in shutdown and HPCS flow meter >2K gpm)

f. .Equipment Out of Service
1) 2WCS-P1B in Pull To Lock
g. Support Documentation
1) None Page 7 of 33 NRC Scenario 1

CENG

.if(M"If\ll'.,TI.J:ll---

NINE MILE POINT NUCLEAR STATION SHIFT TURNOVER INFORMATION ON COMING SHIFT: D N I D DATE: _,Tc.. : o:. : :d:.: : aJ.. y_ __

PART I: To be performed by the oncoming Operator before assuming the shift.

  • Control Panel Walkdown (all panels) (SRO, ROs)

PART II: To be reviewed by the oncoming Operator before assuming the shift.

  • LCO Status (SRO)
  • Shift Turnover Information Sheet Evolutions/General Information/Equipment Status:
  • Reactor Power = 90% due to Reactor Engineering request.
  • 2WCS-P1 B is out of service for maintenance.
  • AII"LCOs are met PART Ill: Remarks/Planned Evolutions:
  • Raise power to 95% using Recirculation Flow per N2-0P-1 01 D and provided RMI.

Page 8 of 33 NRC Scenario 1

CENG_

NINE MILE POINT NUCLEAR STATION ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Raise Power to 95% Step: 3697 I INITIAL CONDITIONS/STEP DESCRIPTION

./

I RE presence required in the Control Room? Yes~ No If YES above, RE presence not required for steps Initial conditions to be verified prior to initiation of step:

Parameter Expected Range Actual Parameter Expected Range Actual CTP 3600-3630 MWth Load Line <100%

Time Now MFLCPR <0.90 Description of Step:

1. .Raise recirculation flow to achieve 95% CTP (3783-3793 MWth) at a 25%CTP/hr rate Critical parameters to be monitored DURING Step:

Critical parameters not used must be deleted OR marked N/A Critical Contingency Limit Owner Frequency Parameter Hourly and every 5% rise Notify SM and RE Supervision; Demand MFLCPR 0.98 STA in CTP and review 3D cases every 15 minutes.

MFLPD or Hourly and every 5% rise Notify SM and RE Supervision; Demand 0.97 STA MAPRAT in CTP and review 3D cases every 15 minutes.

Plot location on power flow map every 15 Load Line 114.5% STA Every% hour minutes; Implement contingency RMI to lower load line.

RMI evaluated against approved power profile:

  • N/A D.

Other Comments:

  • Recirculation flow adjustments may be made per Shift Manager direction at the recommendation of Reactor Engineering.

Step Prepared By: Joe Engineer Today Step Reviewed By: John Engineer Today REIST A Date RE/STA/SRO Date Approval to Perform Step: Joe Manager Today Shift Manager Date Step Completed By:

SRO Date Page 9 of 33 NRC Scenario 1

CENG

<1!('111

  • vru*:u*i*'-Jl--*- -

0~ ..:ieDF NINE MILE POINT NUCLEAR STATION Shift Turnover

  • ;..lnstbtdor A.CtiUDs I Pl.mt.Response

---./(,\!\..*. ' ',* ... ' ..

"'*."."<~:?"~~ ~>**

operator ~ns. ; ..

Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

  • If recording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown Crew the panels.
  • Walkdown panels
  • Conduct shift turnover brief
  • Assume the shift Page 10 of 33 NRC Scenario 1

CENG.

NINE MILE POINT NUCLEAR STATION

  • Event #1: Raise Power to 95°/o using Recirculation Flow Event
  • Initial reactor power is rv9Q%
M~*~}*
  • The crew will raise reactor power using Recirc to rv95% power SRO
  • Directs RO to raise power to 95% using Recirc flow per RMI and N2-0P-101D.

RO

  • Acknowledges direction to raise reactor power to 95% using Recirc flow.
  • Raises power to 95% by raising core flow:

0 Moves RCS*HYV17A&B individually in the open direction, maintaining loop flow differential at a minimal value by alternating between the two valves.

BOP

  • Monitors plant parameters to verify proper operations.
  • Provides peer checks as needed
  • Reactor power has been raised sufficiently as determined by the Lead Evaluator.

Page 11 of 33 NRC Scenario 1

CENG.

.i/(!ll:*...el~!.II~Ol---

0~ ~'eDf NINE MILE POINT NUCLEAR STATION Event #2: Service Water Pump Trip

  • Operators will respond per the ARPs and start an additional pump.
  • The discharge valve will not automatically open when starting the standby pump requiring operators to manually open the valve.

Verify inserted the following malfunctions:

CWlOE, 2SWP*MOV74E FAILS TO AUTO-OPEN CWlOF, 2SWP*MOV74F FAILS TO AUTO-OPEN When directed by lead instructor/evaluator, insert the following malfunction:

TRGl CWOlA, SWP A TRIP, FV=TRUE Service Water Pump P1A trips The following annunciators alarm:

  • Recognizes and reports loss of SWP PlA Page 12 of 33 NRC Scenario 1

CENG.

<*!ft!!",fif 1 ~1>!<!0f---

o~ . . ,.Df NINE MILE POINT NlJCLFAR STATION Note: SRO The SRO :may determine that a SWP must be

  • Directs BOP to respond to trip of SWP P1A started immediately and direct the BOP to
  • References TS 3.7.1 and determines <4 start a pump without going through the in operable service water pumps are in plant actions. This method is acceptable. If operation the SRO decides on this course of action, then
  • Enters conditionE ofTS 3.7.1 and throttling of the MOV74's will not be required. determines he has 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore 4 service water pumps to operation.

BOP

  • Acknowledges direction to respond to SWP P1A trip Role Play
  • May contact PO and direct them to inspect As PO dispatched to inspect SWP P1A, wait SWP A pump and breaker two minutes and inform them that the pump
  • References ARP 60113 and determines motor is abnormally hot to the touch and the flows on the operating SWPs are > 10,000 breaker overcurrent flag is tripped. gpm
  • Throttles shut on 2SWP*MOV74B, C, D to maintain flows <10,0000 gpm Note:
  • Determines that time permits to start a The SRO may direct starting either SWP E or F SWP per N2-0P-11, Section E.2.0 Role Play
  • Contacts PO and directs him to perform As PO dispatched to perform prestart checks prestart checks of SWP E(F) on SWP E or F, wait one minute and report that prestart checks have been completed satisfactorily.

Note:

  • Determines conditions in P&L 13.0 are P&L 13. States the following: With three met operable and running SWP pumps, the plant
  • Verifies 2SWP*MOV74E(F) IS SHUT shall restore 4 operable pumps to service in an expedited fashion. In this condition the plant is in a degraded state, see Tech Spec 3.7.1 for required actions.

Page 13 of 33 NRC Scenario 1

0~ ~*:eoF NINE. MILE POINl NUClEAR STATION Role Play BOP Ccont.l As PO directed to perform steps E.2.4 through

  • Contacts PO and directs them to perform E.2.6, wait one minute and inform the control N2-0P-11, Steps E.2.4 through E.2.6 for room that those steps have been complete SWP E(F)
  • Determines sufficient flow is available for each SWP to have at least 2500 gpm
  • Starts SWP E(F) by placing control switch in NORMAL AFTER START Note:
  • Verifies the following parameters:

When SWP P1E(F) is started, its associated o Red running light lit.

discharge valve will fail to open. o Pump Current is -.5.76 amps.

o 2SWP*MOV74E(F)opens fully.

o ALL running Service Water Pump Flows are <:::2500 gpm.

  • Determines that 2SWP*MOV74E(F) failed to open and manually opens MOV74E(F).
  • Informs SRO that SWP E(F) has been started and its associated discharge valve failed to open automatically.
  • May place SWP P1A control switch in PTL Role Play
  • Contacts Electrical Maintenance As Electrical Maintenance contacted for SWP A
  • Fully opens 2SWP*MOV74B, C, and D trip, inform them you will begin working on a troubleshooting plan.

SRO

  • Acknowledges BOP report of 2SWP*MOV74E(F) failing to automatically open.
  • If P1E was started, declares 2SWP*P1E inoperable and determines he is still in conditionE of TS 3.7.1 and also TS 3.7.1, Condition C now applies (only one operable service water pump in one division). Determines he has 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the Division 1 SW Subsystem to operable status.

Page 14 of 33 NRC Scenario 1

NINE MILE POIN f NUCLEAR STATION SRO (cont.)

  • If P1F was started, declares 2SWP*P1F inoperable and determines he is still in TS 3.7.1, ConditionE and has 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to start a fourth operable SWP.

Role Play

  • Contacts SM and informs him that both As the SM, acknowledge the report from the SWP P1A and E(F) are inoperable.

SRO and inform him to maintain SWP P1E(F) running until an evaluation can be made.

  • 2SWP*P1E(F) is running and its associated discharge valve is open.

Page 15 of 33 NRC Scenario 1

CENG.

,J.I(IIP"Vfl!I.<.J'f!Uf---

NIN£. MILE POINT NUCLEAR STATION Event #3: Inadvertent Initiation of HPCS

  • ~Eieftt
  • With the plant at power, an inadvertent initiation of HPCS will occur.

~..*.*.*

  • FWLC will automatically respond and the plant will remain online.
  • The crew will take action to secure HPCS.

When directed by lead instructor/evaluator, insert the following malfunction:

TRG2 CSOlB, HPCS INITIATION ON LOW LEVEL, FV=TRUE HPCS will auto start and begin injecting into the core.

RPV water level will rise and FWLC will respond to lower level.

MWth lowers.

The following annunciators alarm:

  • 852311 EDG 2 TROUBLE
  • 852317 EDG2 RUNNING
  • 603139 REACTOR WATER LEVEL HIGH/LOW CREW
  • Recognizes and reports HPCS initiation and injection into the RPV RO
  • Monitors RPV water level and FWLC response.
  • Reports to the SRO that FWLC is responding Page 16 of 33 NRC Scenario 1

CENG .

NINE MILE POINT NUCLEAR STATION SRO

  • Acknowledges report of HPCS initiation and injection into the core and FWLC responding
  • Directs BOP to determine if the HPCS initiation signal is valid BOP
  • Determines drywell pressure is < 1.68 psig
  • Determines RPV water level is >108.8 inches Role Play
  • Goes to back panels and calls the booth If contacted as booth to provide indication of for indication on the HPCS trip units the HPCS: trip units all read normal and are not
  • Informs the SRO that HPCS did not initiate tripped. on a valid signal Note: SRO The SRO may direct a normal shutdown first
  • Acknowledges report from BOP that HPCS before directing a shutdown to inoperable did not initiate on a valid signal status.
  • Directs BOP to shutdown HPCS per N2-OP-33, Section G.3.0 or place HPCS in Pull-To-Lock BOP
  • Acknowledges direction to shutdown HPCS
  • May depresses HPCS MANUALLY OUT OF SERVICE pushbutton
  • Informs SRO that HPCS is shutdown Role Play
  • May contact PO and direct them to As PO dispatched to perform running checks perform running checks on HPCS DG on HPCS diesel, acknowledge report Page 17 of 33 NRC Scenario 1

.Jti'm'~\'t:ff**'ll<rf---

0~ ":.':::eDF NINE MILE PO!Nl NUCLEAR STATION SRO

  • Acknowledges report that HPCS is shutdown
  • May contact SM and inform them of HPCS As SM, acknowledge report of HPCS initiation inadvertent initiation and inform the control room that you will contact the work week manager.

event

  • The HPCS pump is in Pull to Lock Page 18 of 33 NRC Scenario 1

CENG.

NINE MILE POINT NUCI EAR STATION Event #4: Loss of CRD due to Suction Strainer Clogging

.'ev:ent

  • A clogged suction strainer will cause a loss of the running CRD pump.
  • .lara~ation
  • The crew will take action to swap suction strainers and restart the CRD pump.

When directed by lead instructor/evaluator, insert the following malfunction:

TRG3 RD18, CLOGGED RDS SUCTION STRAINER, FV=TRUE The following annunciator alarms:

  • 603318 CRD Pmp Suction Fltr Diff Press High After the CRD pump trips then:
  • 603308 CRD Pmp 1A/1B Auto Trip
  • 603309 CRD Pmp 1A Suet Press Low
  • 603311 CRD Charging Wtr Press Low
  • 603315 CRD PMP 18 Suet Press Low
  • 603446 CRD Pmp Disch Hdr Press Low

After a period of time following the pump trip:

603316 CONTROL ROD TEMPERATURE HIGH 602324, RWCU PUMP CLG WTR TEMP HIGH CREW

  • Recognizes and reports to the SRO RDS high suction filter DP
  • References ARP 603318
  • Reports trip of RDS*P1A Page 19 of 33 NRC Scenario 1

CENG.

NINE MILE POINT NUCLEAR STATION SRO

  • Acknowledges trip of RDS*PlA
  • Directs RO to enter N2-SOP-30 BOP
  • References AN603441:

o Determines which accumulators have trouble alarms by looking at the full core display o References N2-0P-30, Section F.7.0 Role Play o Contacts a PO and directs them to As PO directed to report accumulator report accumulator pressures for the pressures, wait two minutes and report that all alarming accumulators accumulator pressures are rvlQOO psig. o Reports to the SRO that Accumulators are all reading above 940 psig RO

  • Acknowledges direction to enter N2-SOP-30
  • Performs the actions of N2-SOP-30:

o Determines a RDS pump is not operating o Shifts RDS flow controller to manual and closes it Role Play o Contacts PO and directs them to swap As PO directed to go swap RDS suction filters, RDS suction filters per N2-SOP-30, wait until WCS is isolated then delete the Section F.l.O following malfunction: o While waiting for the PO to swap suction filters, responds to Annunciator 602324 RD18, CLOGGED RDS SUCTION (when it alarms) as follows:

STRAINER

  • Throttles 2WCS*MOV200 until the in-service filters are on hold.

Inform ttie RO that the RDS suction filters

  • Trips WCS pump.

have been swapped.

Page 20 of 33 NRC Scenario 1

CENG.

~l(llf:vttf'",UfllOf---

0~ ~,erw NINE MILE POINf NUClfAR STATION Role Play RO Ccont.l When contacted by the RO to verify seal flows 0 Once PO reports back the suction filters and backfill flows, wait two minutes and say have been swapped, restarts RDS*PlA they are satisfactory. 0 Once an RDS pump is running, adjusts the RDS flow control valve so system flow is approximately 63 gpm 0 Places RDS flow controller back in automatic 0 Contacts PO and directs them to verify WCS/RCS seal flows and backfill flows per N2-0P-30, Section F.2.5 through F.2.9 Note: BOP Approximately 4 minutes after trip of RDS

  • Recognizes and reports high CRDM pump, AN603316, Control Rod Temp. High will temperature alarm alarm.

Role Play

  • Contacts PO and dispatches them to As PO dispatched to monitor CRDM monitor CRDM temperatures at 2RDS-temperatures, wait two minutes after start of TRS165 RDS pump, (and AN603316 is clear), and report CRDM temperatures are back to normal.
  • CRD Suction Strainers have been swapped and a CRD pump has been restarted.

Page 21 of 33 NRC Scenario 1

CENG .

N!N( MILE POINT NUCLEAR STATION Event # 5: Loss of Line 5 and 6, Division 2 EDG Fails to Auto Start

  • A loss of Line 5 and 6 will occur.
  • Division 1 bus will not be reenergized due to a bus fault
  • Division 2 EDG will not auto start however it can be manually started.

Verify inserted the following malfunction:

DG04B, DIV 2 EDG FAILS TO AUTO START, FV=TRUE When directed by lead instructor/evaluator, insert the following malfunction:

TRG4 ED02A, LOSS OF LINE 5, FV=TRUE ED02B, LOSS OF LINE 6, FV=TRUE, DT=3 EDOSA, DIV 1 BUS FAULT, FV=TRUE, DT= 10 Power is lost to Div 1 and 2 SWG Div 1 EDG starts, but does not power its bus Div 2 EDG fails to start Division ~ EDG starts up and powers its bus CREW

  • Recognizes and reports loss of line 5 and 6 and failure of Div 2 EDG to automatically start SRO
  • Acknowledges report of loss of line 5 and 6
  • Directs BOP to enter N2-SOP-03 Page 22 of 33 NRC Scenario 1

CENG.

NINE MILE POINT NUCLEAR STATION BOP CN2-SOP-03l

  • Acknowledges direction to enter N2-SOP-03
  • Determines HPCS EDG has started and Division I and II EDGs are not powering their bus Note:
  • Using HPCS DIESEL ENGINE EMERGENCY The crew may attempt to start the start the STOP pushbutton on 2CEC*PNL852, Division 2 EDG before dispatching an operator immediately trips the HPCS Diesel.

to align Firewater to the HPCS EDG. If this is the case, then they will be able to start the diesel and not have to supply Firewater to the HPCS EDG.

Role Play

  • Contacts PO and directs them to supply As PO, if dispatched to align firewater to HPCS fire water to HPCS EDG per N2-SOP-03, EDG, insert the following remote functions: Detail B
  • Determines both divisions lost power TRGS CWSS, 2SWP*MOV95A BKR,
  • Determines Division 1 EDG will not be able FV=OPEN, DT=120 to power its bus due to a bus fault CWS4, 2SWP*MOV95A VALVE (Annunciators 852131 and 852148)

POSITION, FV=O, DT=120

  • Determines Division 2 EDG did not start CWSS, 2SWP*V1230 VALVE and power its bus POSITION, FV=100, DT=130
  • Attempts to manually start and load the CWS9, 2SWP-V1233 VALVE Division II EDG as follows:

POSITION, FV=OPEN, DT= 130 o Verifies the following annunciators are DG10, HPCS LOCKOUT RESET, not lit:

FV=RESET, DT=140

  • 852211
  • 852225 When the above remotes are in, contact the
  • 852227 control room and confirm that flow is indicated
  • 852231 in the control room on 2SWP*FI535. When
  • 852235 flow is confirmed, insert the following remote
  • 852239 functions:
  • 852247
  • 852248 Page 23 of 33 NRC Scenario 1

NINE MILE POINT NUCLEAR STATION TRG6 CWS7, 2SWP*MOV95B BKR, BOP (N2-SOP-03} (cont.}

FV=OPEN, DT=20 CWS6, 2SWP*MOV95B VALVE POSITION, FV=O, DT=25 Report to the control room that firewater has been aligned to the HPCS EDG CT-1.0: Given a failure of the Division 2 0 Places Division II 2EGS*EG3 control EDG to automatically start, the crew will switch to START.

take action to manually start the Division o Verifies Emergency DSL GEN 3 II EDG lAW N2-SOP-03 frequency 60 Hz.

o Verifies Emergency DSL GEN 3 voltage is 4160 V.

0 Determines that Division 2 EDG started and re-energized the Division 2 SWG

  • Reports to the SRO that EDG has started and is powering the Division II SWG
  • Informs the SRO that N2-SOP-03 requires entry into N2-SOP-11 SRO (N2-SOP-11}
  • Acknowledges report of Division 2 EDG running and powering its bus and the requirement to enter N2-SOP-11
  • Directs RO/BOP to enter N2-SOP-11.

Note: RO/BOP (N2-SOP-11}

Because only Division 2 has electrical power, a

  • Acknowledges direction to enter N2-SOP-reactor scram will be required per N2-SOP-11. 11.
  • Enters N2-SOP-11
  • Determines that SWP Non-Essential Headers are isolated and cannot be restored.
  • Informs the SRO that N2-SOP-11 requires the following actions:

0 Scram the reactor o Trip the Turbine 0 Trip both Recirculation Pumps Page 24 of 33 NRC Scenario 1

NINE MILE POINl NUCLEAR STATION SRO

  • Acknowledges report from BOP that a reactor scram is required.
  • Directs the RO to manually scram the reactor.

RO CN2-SOP-11)

  • Acknowledges direction to manually scram the reactor.
  • Places the Mode Switch in SHUTDOWN .
  • Determines all rods inserted .

BOP (N2-SOP-21}

  • Trips the Turbine as follows per N2-SOP-21:

0 Determines power is <21%

0 Depresses both Turbine TRIP push buttons.

0 Determines the Turbine Tripped and verifies the MSVs, CVs, and CIVs closed.

  • Recognizes that the turbine trip caused a loss of both SWG001 and 003.
  • Verifies tripped both Recirculation Pumps by placing the control switches to STOP.
  • As timer permits, continues actions in Attachment 1 of N2-SOP-03 SRO
  • Acknowledges scram report .
  • Enters N2-EOP-RPV
  • Reactor is scrammed
  • N2-EOP-RPV is entered.

Page 25 of 33 NRC Scenario 1

CENG .

NINE MILE POINT Nl.CLEAR STATION Event #6: Small LOCA and Loss of High Pressure Injection

  • A small LOCA and loss of high pressure injection sources will require an RPV Blowdown due to RPV Level.
  • RPV Level will be recovered using low pressure ECCS pumps.

Note:

When the crew placed the mode switch in shutdown in the previous event, the below malfunction was inserted:

RR20, DBA LOCA, FV=O.S, RT=15:00 OW pressure starts to rise slowly RPV water level starts to lower The following annunciator alarms:

  • 851254 PROCESS AIRBORNE RADN MON ACTIVATED CREW
  • Recognizes and reports rising drywell pressure and lowering RPV level SRO CN2-EOP-RPVl
  • Acknowledges report of rising drywell pressure and lowering RPV level.
  • When drywell pressure reaches 1.68 psig, enters N2-EOP-PC.
  • Directs RO to perform actions of N2-SOP-101C
  • Directs RO to maintain RPV water level 160 to 200 inches using RCIC Page 26 of 33 NRC Scenario 1

NiNE MILE POINT NUCLEAR STATION Note:

  • Directs BOP to coordinate with the RO and Due to th;e electrical failure of Division 1, the maintain RPV pressure 800 to 1000 psig SRO may given out the order of 500 to 1000 (500 to 1000 psig) using RCIC, psig using sustained opening of the SRVs supplement with SRVs instead of 800 to 1000 psig.

RO CN2-SOP-101Cl

  • Acknowledges direction to take actions per N2-SOP-101C
  • Acknowledges direction to maintain RPV water level 160 to 200 inches using RCIC
  • Performs initial actions of N2-SOP-101C:

o Verifies turbine has tripped and TSV/TCVs are shut o Verifies generator has tripped and house loads have transferred 0 Verifies SDV vent and drain valves have closed o Verifies RCS pumps are not running o As necessary inserts SRMs and IRMs Role Play 0 May direct energizing 2WCS-MOV107 As PO directed to energize 2WCS-MOV107, 0 May shutdown HWC acknowledge the report.

BOP CN2-EOP-RPVl

  • Acknowledges direction to coordinate with the RO and maintain RPV pressure 800-1000 (500 to 1000) psig using RCIC and supplement with SRVs
  • Monitors RPV pressure and cycles SRVs as necessary to maintain 800-1000 (500 to 1000) psig.

Note: RO CN2-EOP-HCl Malfunctions will prevent RCIC from

  • Initiates RCIC as follows:

automatically starting with the RCIC 0 Determines RCIC is not already running, Pushbutton. and arms AND depresses RCIC MANUAL INITIATION pushbutton 0 Determines RCIC did not start using the Page 27 of 33 NRC Scenario 1

CENG .

NINE MILE POINT NIX LEAR STATION initiation pushbutton and a manual RCIC start is required.

  • Manually initiates RCIC as follows:

0 Places 2ICS*FC101 in Manual AND sets output to 20%

RO <cont.)

o Starts GLAND SEAL SYSTEM AIR COMPRESSOR o Opens ICS*MOV116, LUBE OIL COOLING WATER SUPPLY o Opens ICS*MOV120, TURB STM SUPPLY VLV, AND observes RCIC Turbine speed rising o Verifies open ICS*MOV143, PMP MINIMUM FLOW TO SUPPRESSION POOL o WHEN ICS*MOV120 is full open, opens ICS*MOV126, PMP 1 DISCH TO REACTOR o Slowly raises RCIC Turbine speed using RCIC FLOW CONTROLLER in Manual AND verifies the following:

  • RCIC Turbine speed rises on ESl-C002-Ml
  • RCIC pump discharge pressure rises on E51-R601 o WHEN RCIC pump discharge pressure exceeds reactor pressure, verifies the following:
  • ICS*V156, REACTOR INJECTION OUTBD CHECK VLV, opens
  • ICS*V157, REACTOR INJECTION INBD CHECK VLV, opens
  • RCIC injection flow rises on ESl-R606 o WHEN system flow exceeds 220 gpm, verify ICS*MOV143, PMP MINIMUM FLOW TO SUPPRESSION POOL, closes Page 28 of 33 NRC Scenario 1

CENG .

ui(NI'~ > O H ! I . / P . O I - - -

0~ ~;"*Df NINE MILE POINf NUCI EAR STATION After RCIC flow is above 500 gpm, verify o WHEN RCIC injection flow reaches 600 inserted the following malfunction: gpm, place flow controller in Automatic RC06, RCIC TURBINE TRIP, FV=TRUE, DT=30 RCIC trips on high turbine exhaust pressure.

RO Ccont.l

  • "'30 seconds after RCIC flow reaches 500 gpm, determines that RCIC tripped and cannot be restarted.
  • Informs SRO that RCIC has tripped .

SRO CN2-EOP-RPVl

  • Acknowledges report of RCIC trip .
  • Directs BOP to maintain RPV pressure 800-1000 psig using SRVs.
  • Directs RO to maintain RPV Level 160-200 inches using HPCS.

RO CN2-EOP-RPV)

  • Acknowledges order to maintain RPV Level 160-200 inches using HPCS.

"'8 seconds after HPCS starts, verify inserted

  • Takes HPCS control switch out of PTL the following malfunction:
  • Determines that HPCS tripped on motor electric fault.

CSOS, HPCS PUMP TRIP, FV=TRUE,

  • Reports to the SRO that HPCS tripped on DT=5 motor electric fault.

HPCS pump trips on motor electric fault.

BOP CN2-EOP-RPVl

  • Acknowledges direction to maintain RPV pressure 800-1000 psig using SRVs only.

SRO CN2-EOP-RPVl

  • Acknowledges report that HPCS has tripped.
  • Determines alternate injection systems Page 29 of 33 NRC Scenario 1
    • ICW*d~n*u*nuf--*--

0~ ..;ieDf NIN[ MILE POINT NIXLEAR STATION are needed and performs the following:

0 Directs RO to inject with SLS per N2-OP-36A, Section H.l.O SRO (cont.)

0 Determines water level cannot be restored and maintained above -14 inches and enters center leg of N2-EOP-RPV 0 Directs BOP to inhibit ADS RO (N2-EOP-RPV)

  • Acknowledges direction to inject with SLS per N2-0P-36A, Section H.l.O
  • Injects with SLS as follows:

0 Places keylock switches for both SLS*P1B in RUN 0 Recognizes SLS P1B started as expected and all indications are normal 0 Reports to the SRO that SLS is injecting with SLS P1B BOP (N2-EOP-HC)

  • Acknowledges direction to inhibit ADS
  • Inhibits ADS by performing the following:

0 Places BOTH DIV I and Div II ADS AUTOMATIC INITIATION DISABLE keylock switches in ON

  • Informs the SRO that ADS is inhibited Page 30 of 33 NRC Scenario 1

CENG.

NINE MILE POINT NUCLEAR STAT10N Note: SRO (N2-EOP-RPV and N2-EOP-C2}

The SRO may also direct to lineup RHS B for

  • Determines at least two injection systems injection through shutdown cooling before are lined up blowing down. This is an acceptable action
  • Waits until RPV water level is at TAF but not required.
  • Determines LPCI B and C ECCS systems Note: are lined up with a pump running At the Lead Evaluator's discretion, the
  • Waits until RPV water level is at TAF following malfunction may be adjusted to raise
  • Determines LPCI Band C ECCS systems or lower the rate at which RPV level is are lined up with a pump running lowering:
  • Enters N2-EOP-C2, RPV Blowdown:

0 Determines Reactor will stay shutdown RR20, DBA LOCA without boron 0 Determines drywell pressure is above 1.68 psig 0 Determines there is no need to prevent LPCI or LPCS injection 0 Determines suppression pool level is

>192 feet CT -2.0 Given RPV level at or below the 0 Directs BOP to open 7 ADS valves.

TAF but above the MSCWL, the crew will open 7 ADS valves IAW N2-EOP-C2 BOP (N2-EOP-HC}

  • Acknowledges direction to open 7 ADS valves and performs the following:

0 Determines no SRVs are stuck open and an ECCS pump is running CT-2.0 Given RPV level at or below the o Arms and depresses both ADS TAF but above the MSCWL, the crew will pushbuttons for each division open 7 ADS valves IAW N2-EOP-C2 o Informs the SRO that 7 ADS valves are open

  • Verifies LPCI Band C ECCS systems inject when pressure is lowered sufficiently Note: SRO (N2-EOP-RPV}

As RPV pressure lowers, LPCI Band C will

  • Acknowledges report from BOP that 7 ADS inject and RPV level will begin to rapidly rise. valves are open Page 31 of 33 NRC Scenario 1

CENG. .

ajl)e~Vflf*:umuf---

0=:--- -!~*Of NINE MILE POINT NUCLEAR STATlON SRO Ccont.l

  • Directs BOP to inject with all available injection system to restore RPV level

>MSCWL

  • As water level rises above MSCWL and TAF, directs RO to secure injection sources as necessary to establish and maintain an RPV water level of 160 to 200 inches
  • May direct BOP to remove RHS B and place it into suppression chamber sprays per N2-EOP-6, Attachment 22 Note SRO, CN2-EOP-PC)

Actions in EOP-RPV regarding establishing

  • Determines DW pressure cannot be adequate core cooling will be prioritized, maintained < 1.68 psig however ?S systems become available, the
  • Directs BOP to place suppression chamber SRO may choose to use systems as necessary sprays in service on RHS B per N2-EOP-to mitigate primary containment parameters 6.22 BOP CN2-EOP-6.22l
  • Acknowledges direction from SRO to spray the suppression chamber using RHS B:

o Verifies open MOV90B o Verifies shut and overridden MOV24B o Verifies RHS B is running o Verifies open 2RHS*MOV33B o Throttles open 2SWP*MOV33B as necessary to establish service water flow to RHS heat exchanger Page 32 of 33 NRC Scenario 1

np.n: vcnt~.Jroof. _ _ _

0~

__..:____..:__ ___ ~;:eoF:1 NINE MILE POINT NUCLEAR STATION Copy of __

Training Id: NRC 2013 Scenario 2 0.0 Revision: -=--=-=-----

PC. 4, High containment pressure approaching PCPL, exceeds PSP,

Title:

RPV Blowdown required Signature I Printed Name Developed By ~ David Huff )2/)7 /'YJJ ~

Validated By Michael Storms 12/ n}t..o *,)

Phil MacEwen Doug Mizener Facility Reviewer Aaron Armstrong Page 1 of 42 NRC Scenario 2

CENG.

NINE MILE POINT NUCLEAR STATION References

1. N2-0P-101D, Power Changes
2. N2-0P-92, Neutron Monitoring System
3. N2-0P-25, Auxiliary Steam, Auxiliary Condensate, and Gland Seal
4. N2-SOP-97, RPS Failures
5. N2-SOP-11, Loss or Degraded Service Water
6. N2-EOP-RPV, RPV Control
7. N2-EOP-PC, Primary Containment Control
8. N2-EOP-C2, RPV Blowdown
9. Unit 2 Technical Specifications Page 2 of 42 NRC Scenario 2

CENG.

NINE MILE POINT NUCLEAR STATION NOTES Instructor Information A. Scenario Description The crew will take the shift at rv65% power. The shutdown is on hold pending surveillance results. Instrument Air Compressor C is out of service due to maintenance. After the crew takes the shift, a malfunction in the normal station service transformer cooling system causes transformer temperatures to rise. The crew will dispatch a PO to investigate. The PO will report that several of the transformer cooling fans are not running and cannot be started.

The crew will coordinate with the PO and lower power per N2-SOP-101D to stabilize transformer temperatures. Once temperatures are under control, APRM 2 will fail upscale. The crew will take action per the ARP's and N2-0P-92 to bypass APRM 2. The CRS will evaluate TS 3.3.1.1 for the inoperable APRM.

Once APRM 2 is bypassed, the running Gland Seal Exhaust Fan will trip on motor electric fault. The crew will take action per the ARP's and N2-0P-25 to isolate the tripped Gland Seal Exhaust Fan and start a standby fan. After the Gland Seal Exhaust Fan is started, the RPS B Motor Generator will trip causing a half scram on RPS B side. The crew will enter N2-SOP-97 and align the RPS B solenoids to their alternate power supply. While resetting the EPA's per N2-SOP-97, the Plant Operator will report that the undervoltage trip relay had to be bypassed in order to reset one of the EPA's. The CRS will declare the associated EPA inoperable and evaluate TS 3.3.8.3.

After the RPS B solenoids are powered from their alternate power supply, Service Water intake clogging will occur causing Service Water intake bay level to lower. The crew will take action per N2-SOP-11 and attempt to clean the traveling screens. Intake bay will continue to lower to 234 feet. The intake bay bypass valves 2SWP*MOV77A/B will fail to automatically open requiring the crew Page 3 of 42 NRC Scenario 2

CENG_

ilJ(}t! ~'tlf!C'::$lltl1---

o~ ~:*OF NIN£ MILE POINT NUCLEAR STATlON NOTES to take manual action to open the valves (CRITICAL TASK).

Once MOV77A and Bare open, intake bay level will recover.

Once Service Water intake bay level is restored, a loss of all feed pumps will occur. The loss will require the crew to place the Mode Switch in ~hutdown. Once RPV level has been stabilized using alternate level control systems, a LOCA will occur. The LOCA will cause Primary Containment (PC) parameters to degrade and the crew will enter N2-EOP-PC to stabilize PC parameters.

Malfunctions in the Division 1 RHS systems will prevent RHS A from being used for primary containment control and the crew will be required to use RHS B to spray the suppression chamber. As PC conditions continue to degrade, the crew will attempt to spray the drywell using RHS B. While the crew is attempting to align drywell sprays, 2RHS*MOV25B (Drywell Spray Valve) will stick shut. Plant Operators will be dispatched in an attempt to manually open MOV25B. While the POs are attempting to manually open MOV25B, primary containment parameters will continue to degrade. The CRS will determine that Suppression Chamber Pressure cannot be restored and maintained within the Pressure Suppression Limit and will enter N2-EOP-C2 and direct 7 ADS valve be opened. The crew will open 7 SRV's and blowdown the reactor (CRITICAL TASK). The scenario may be terminated once 7 SRV's are opened.

1. Termination Criteria
a. 7 SRV's are open.

Page 4 of 42 NRC Scenario 2

CENG.

NINE MILE POINT NUCI EAR STATION NOTES

2. Critical Tasks CT-1.0 Justification: This task is identified as critical because without operator action, the plant will lose its ultimate heat sink.
a. CT-1.0, Given service water intake bay level less than 234ft and a failure of 2SWP*MOV77A & 77B to
  • automatically open, the crew will take action to manually open 2SWP*MOV77A & 77B per N2-SOP-ll.

CT-2.0 Justification: This task is identified as critical because without operator action the primary containment pressure suppression function would continue to degrade and would not be able to accept a full blowdown of the reactor.

b. CT-2.0, Given Suppression Chamber Pressure unable to be restored and maintained within the Pressure Suppression Limit, the crew will open 7 SRV's lAW N2-EOP-C2.
3. Length
a.
  • tv80 minutes
4. Mitigation Strategy Code
a. PC 4, High containment pressure approaching PCPL, exceeds PSP, RPV Slowdown required
5. Technical Specifications
a. *Ts 3. 3 .1. 1
b. TS 3.3.8.3
6. EAL Classification
a. Alert, FAl.l, ANY loss or ANY potential loss of EITHER Fuel Clad barrier OR RCS barrier.
b. Table F-1, RCS Barrier B.2, C.4
7. Special Orders
a. None Page 5 of 42 NRC Scenario 2

CENG.

uJOU'" *w*tulf'Hf 0=:--- ~*;:eDF NINE MILE POINT NUCLEAR STATION NOTES B. Initial Conditions

1. IC Number
a. IC-151
2. Presets I With Triggers
a. Malfunctions
1) ED16, Main Transformer Loss of Cooling, FV = 89 INSERTED
2) RH14A, ECCS FAILS TO INITIATE (DIV 1), INSERTED FV=TRUE
3) RH10B,RHS*MOV25BJAMMED,FV=TRUE INSERTED
4) NM11B, APRM 2 FAIL UPSCALE, FV=TRUE TRGl
5) MS20A, GLAND SEAL EXHAUST FAN TRIP, TRG2 FV=TRUE
6) RP06B, LOSS OF MOTOR GENERATOR MG01B, TRG3 FV=TRUE
7) CW09, SW INTAKE CLOGGING, FV=50, RT=4:00 TRGS
8) RR20, DBA LOCA, FV=1.5, RT=15:00 TRG6
9) FW03A, FEED PUMP TRIP (P1A) FV=TRUE TRG6
10) FW03B, FEED PUMP TRIP {P1B) FV=TRUE, DT=3 TRG6
11) FW03C, FEED PUMP TRIP {P1C) FV=TRUE, DT= 15 TRG7
12) RD12A, CRD FEED PUMP TRIP (P1A) FV=TRUE TRGS
13) RD12B, CRD FEED PUMP TRIP {P1B) FV=TRUE, TRGS DT=3
b. Remotes
1) CW26, 2SWP*MOV77A/B FAIL TO AUTO OPEN, INSERTED FV=TRUE
2) RP02, RPS MG2 EPA, FV=RESET TRG4 Page 6 of 42 NRC Scenario 2

CENG.

  • "i.l(ltl':\'tifl"u'il! _ _ _

0~ -;,*"'

NINE MILE POIN f NUCI EAR STATION NOTES

3) RM02-041, SWP 238 RAD MONITOR ONLINE, TRG9 FV=ON
4) RM03-041, SWP 238 RAD MONITOR SAMPLE TRG9 PUMP POWER, FV=ON
c. Overrides
1) DI03513, RHS A SWITCH IN PTL, FV=OFF INSERTED
2) DI03514, RHS A SWITCH IN STOP, FV=OFF INSERTED
3) DI03515, RHS A SWITCH IN NORMAL AFTER INSERTED STOP, FV=ON
4) DI0360, RHS A SWITCH IN NORMAL AFTER INSERTED START, FV=OFF
5) DI0361, RHS A SWITCH IN START, FV=OFF INSERTED
d. Annunciators
1) None
e. Event Triggers 6 zdrps1d==1 (mode switch to shutdown) Blank 7 zdrps1d==1 .and. zdfwsc11(2)==1 Blank (mode switch to shutdown and Feed Pump C control switch to start) 8 zdrps1d==1 .and. zdrd001b(2)==1 Blank (mode switch to shutdown and RDS Pump 8 control switch to start)
f. Equipment Out of Service
1) Instrument Air Compressor C is out of service for maintenance. Red Tag compressor switch in PTL and protect lAS A and 8
g. Support Documentation
1) None Page 7 of 42 NRC Scenario 2

<~.l(.l!t:\1m"d'r!:.Jf---

O~ -!:eoF NINE MILE P01NT NUCLEAR STATION SHIFT TURNOVER INFORMATION ON COMING SHIFT: D N I D DATE: --'T-=o=d=a.L..y_ __

PART I: To be performed by the oncoming Operator before assuming the shift.

  • Control Panel Walkdown (all panels) (SRO, ROs)

PART II: To be reviewed by the oncoming Operator before assuming the shift.

  • LCO Status (SRO)
  • Shift Turnover Information Sheet Evolutions/General Information/Equipment Status:
  • Reactor Power -65% and in the process of shutting down
  • Sh:utdown is on hold awaiting surveillance testing results. Results are expected in -3 hrs.
  • lAS Compressor C is red tagged for maintenance.
  • All LCOs are met PART Ill: Remarks/Planned Evolutions:
  • There are no evolutions planned for the next 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of shift.

Page 8 of 42 NRC Scenario 2

CENG.

NINE MILE POINT NUCLEAR STATION Shift Turnover Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

  • If re~ording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown Crew the panels.
  • Walkdown panels
  • Conduct shift turnover brief
  • Assume the shift Page 9 of 42 NRC Scenario 2

CENG~

NIN£ MILE POINl

  • Initial reactor power is "'65%

Verify inserted the following malfunction and ensure transformer temperatures have stabilized:

ED16, Main Transformer Loss of Cooling, FV = 89 When directed by the lead evaluator, modify the following malfunction:

ED16, Main Transformer Loss of Cooling, FV = 100 The following computer point alarms after

"'1.5 minutes:

  • SPMTC01, MN XFMR XM1A OIL TEMP The following annunciator alarms:
  • 852618, Main XFMR 1A/1B/1C/1D Oil System Trouble Crew
  • Determines computer point SPMTC01 in alarm and references ARP 852618 Page 10 of 42 NRC Scenario 2

CENG.,

.\)OV'.refl~u*nof---

NIN£ MILE POINT NLCIEAR STATION Role Play:

  • Dispatches Field Operator to investigate When directed as field operator to investigate local temperature indications local main transformer oil temperatures and indications, wait 3 minutes and report that local gauge temperature indicates 100°C and rising slowly and it appears one bank of the cooling fans are not running. Attempts to start the additional cooling fans have not been successful. Also, if asked, both oil pumps are running.

Role Play:

  • May ask field operator if red Alarm light If asked, report that the red alarm light on the on gas analyzer is lit gas analyzer is not lit.

Role Play:

  • May contact a PO and ask them to check If asked to verify breaker status for the breaker status for the transformer transformer cooling, report the following cooling fans.

status for only those breakers requested:

  • Circuit Breaker 8-3 Group No. 1 Cooler-on
  • Circuit Breaker 8-4 Group No. 2 Cooler -

on

  • Circuit Breaker 8P-1 Pump No. 1 -on
  • Circuit Breaker 8P-1 Pump No. 2 -on
  • Determines that local gauge temperature When requested by the control room for a will exceed 105°C.

temperature update, report local gauge main

  • Informs the SRO that:

transformer temperatures indicate 103°C and o A MVAR reduction is required rising slowly. As necessary, continue to o A rapid power reduction is required per provide indication of up to 105°C N2-SOP-101D.

Page 11 of 42 NRC Scenario 2

CENG. .

  • l.l(}ll':,,tm:,,n~uf---

0~ -!~eDF NINE MILE POINT NUClEAR STATION SRO

  • Acknowledges report from BOP of the need to reduce MVAR loading and reduce reactor power per N2-SOP-101D
  • Directs RO to enter N2-SOP-101D and lower reactor power using Rods and/or Recirc.

Note:

  • May direct BOP to contact power control The SRO may direct MVAR reduction without for guidance to reduce MVAR loading contacting power control.

Role Play: BOP If contacted as power control, report that a

  • May contact power control to determine reduction in MVAR to 0 MVAR's (unity) is what value of MVAR loading is acceptable permissible
  • Informs SRO that power control can support an MVAR reduction to 0 MVAR CRS
  • Acknowledges direction to reduce generator MVAR loading
  • Using the guidance of N2-0P-68, reduces MVAR loading by lowering the Main Generator AC Voltage Regulator control switch position until 0 MVAR is indicated on the Main Generator MEGVARS meter
  • Reports to CRS that main generator VARS have been adjusted to 0 MVAR's Page 12 of 42 NRC Scenario 2

CENG .

NINE MILE POINT NLICLI'AR STATION RO

  • Acknowledges direction to enter N2-SOP-101D to reduce power
  • Determines that Core flow is > 60 Mlbm/hr
  • Determines that core power/flow is not above the MELLLA boundary
  • Determines that Reactor Manual Control is available
  • Lowers reactor power to pre-established power level using recirculation flow control and or rods.

Role Play: BOP When contacted as field operator to provide

  • Contacts field operator to request to local main transformer temperatures report update local temperature indication that local gauge temperature indicates 105°C
  • Informs the SRO and RO that transformer and rising slowly, but the rate of temperature temperatures have begun to lower.

rise has ~lowed. Once power has been lowered at least 5%, give a report that temperatures are beginning to lower and delete the following malfunction:

ED16, Main Transformer Loss of Cooling CRS

  • Reactor power has been lowered sufficiently as determined by the Lead Evaluator.

Page 13 of 42 NRC Scenario 2

CENG.

NINE MILE POINT Nt JCLEAR STATION Event #2: APRM 2 Fails Upscale

  • APRM 2 fails upscale
  • The crew will respond per the ARP's and bypass APRM 2 When directed by lead evaluator, insert the following malfunction:

TRGl NM11B, APRM 2 FAIL UPSCALE, FV=TRUE APRM 2 indication will fail upscale The following annunciators alarms:

  • 603202, APRM Trip System Upscale/Inoperable
  • 603208, APRM Trip System Upscale
  • Recognizes and reports APRM 2 failure SRO
  • Acknowledges report of the APRM 2 failure
  • Directs RO to respond per the ARP's RO
  • Acknowledges direction to respond per the ARPs.
  • Refers to ARP 603202 and/or 603208
  • Informs the SRO that APRM 2 may be bypassed per N2-0P-92 SRO
  • Acknowledges report that APRM 2 may be bypassed.

Page 14 of 42 NRC Scenario 2

NINE MILE POINT NUClEAR STATION RO

  • Acknowledges report to bypass APRM 2
  • References N2-0P-92 and bypasses APRM 2 as follows:

0 Determines no other APRM is bypassed.

0 Performs a channel check by verifying APRM 1, 3, and 4 are all reading within 2% of each other.

The following annunciators clear: 0 Places the APRM BYPASS joystick to the

  • 603202, APRM Trip System "2" position Upscale/Inoperable o Verifies APRM 2 BYPASS light on
  • 603208, APRM Trip System Upscale 2CEC*PNL603 is lit .
  • 603442, Control Rod Out Block o Asks the BOP to go to the back panel and verify APRM 2 bypass indications BOP
  • Verifies APRM 2 is bypassed in the back panels as follows:

0 Determines that "BYP" is displayed in inverse video in the header for APRM 2 0 Determines the blue BYPASSED LED is lit for APRM 2 on the 2/4 MDL Role Play o Contacts the booth and asks for the As the booth operator, inform the BOP that BYPASSED LED 2/4 MDL indications on APRM 2 indicates bypassed on all 2/4 MDL APRMs 1, 3, and 4.

modules.

  • Informs the RO that APRM 2 indicates bypassed on the back panels.

RO

  • Acknowledges report from BOP that APRM 2 indicates bypassed on the back panels.
  • Informs the SRO that APRM 2 has been bypassed per N2-0P-92.
  • May continue on with ARP 603200 actions and ask the BOP to reset the memories on the 2/4 MDL Modules per N2-0P-92, Section F.4.0.

Page 15 of 42 NRC Scenario 2

CENG.

NIN£ MIL£ POINl NUCLEAR STATION BOP

  • May reset the 2/4 MDL Modules per N2-OP-92, Section F.4.0 as follows:

0 Depresses the TRIP MEMORY RESET pushbutton for APRM 2 on the 2/4 MDL Module.

o Observes that all Red and Yellow LEDs are extinguished on the 2/4 Module.

Role Play o Contacts the booth and directs them to As the booth operator, inform the BOP that all Depresses the TRIP MEMORY RESET memories have been cleared on the 2/4 MDL pushbutton for APRM 1, 3, and 4.

Modules for APRMs 1, 3, and 4.

  • Informs the RO that the 2/4 MDL Module memories have been cleared.

SRO

  • Acknowledges report from RO that APRM 2 is bypassed.
  • References TS 3.3.1.1, Table 3.3.1.1-1 and no additional actions are required due to APRMs 1, 3, and 4 being still operable.

Role Play

  • May contact the SM and inform him of the As the SM, acknowledge the failed APRM 2 and APRM 2 Failure.

inform the SRO that you will contact I&C and inform th~m of the failure.

Page 16 of 42 NRC Scenario 2

    • ,w.:w*,'f!fl':wmof---

0~ -!,eor NINE MILE POINT NUCLEAR STATION Event #3: Gland Seal Exhaust Fan Trip

  • A trip of the running gland seal exhaust fan will occur.
  • The crew will take action to start a standby exhaust fan.

When directed by lead evaluator, insert the following malfunction:

TRG2 MS20A, GLAND SEAL EXHAUST FAN TRIP, FV=TRUE Steam Packing Exhaust Blower Fan 1A trips on motor electrical fault Steam seal exhaust vacuum begins to degrade as read on 2TME-PI108 The following annunciators alarm:

  • 851211, Gland Seal Exhaust Fan 1A/1B/2A/2B Mot Temp High
  • 851201, Gland Seal Exhaust Fan 1A/18/2A/2B Mot Overload
  • 851231, Gland Seal Exhaust Fan 1A/18/2A/28 Auto TRIP/FTS The following annunciator alarms approximately 2 minutes after event initiation:
  • 851203, Gland Seal Exhaust Fan 1A/1B/2A/2B Vacuum Low CREW
  • Recognizes and reports TRIP OF Gland Seal Exhaust Fan lA.

Page 17 of 42 NRC Scenqrio 2

NINE MILE POINT NIX!. EAR STATION SRO

  • Acknowledges report of the trip of Gland Seal Exhaust Fan 1A.
  • Acknowledges direction to respond per the ARPs.
  • References ARP 851201 and 861203 and performs the following:

0 Determines that no steam packing exhausters are running 0 Closes TME-MOV22A, steam packing exhaust fan 1A inlet valve 0 Determines that ARP 851201 requires the standby TME fan be started using N2-0P-25.

Note:

  • References N2-0P-25 and performs the The BOP may choose to start FN1B, 2A, or 2B. following:

o Throttles open 2TME-MOV22B(23A, 23B), steam packing exhaust fan 1B(2A, 2B) inlet valve 0 Starts TME-FN1B(2A, 2B)

  • Throttles 2TME-MOV22B(23A, 23B) to achieve 10 - 14 inches vacuum on the TME System Role Plav
  • Dispatches a PO to investigate the trip of If dispatched as PO to investigate the trip of TME-FN1A TME-FN1A, wait 2 minutes and then report that the power supply breaker is tripped with no visible indications why and that TME-FN1A looks O.K. no visible signs of damage RO

CENG.

NINE MILE POINT NLCLEAR STATlON Note: SRO The SRO may choose to enter N2-SOP-09 to

  • May enter N2-SOP-09, Loss of Condenser establish extra monitoring of condenser Vacuum.

vacuum. This is not necessary but it is an acceptable action, however no actions should be taken :in SOP-09, only monitoring.

Role Play

  • Contacts SM and reports that Gland Seal As SM, acknowledge the report for trip of the Exhaust Fan 1A tripped on motor electric exhaust fan and inform the SRO that you will fault.

take action to inform the WWM and maintenance groups.

  • Gland Seal Exhaust Fan 1B(2A, 2B) is running and Gland Seal Exhaust Pressure is being controlled between 10 to 14 inches of vacuum Page 19 of 42 NRC Scenario 2

CENG.

atotn:.*m*tu!P.o!---

0=:--- ~~eDF NINE MILE POINT NUCLEAR STATION Event #4: Trip of RPS B MG Set

  • A trip will occur of RPS B MG Set.
  • The crew will respond per N2-SOP-97 to transfer power to the alternate power supply and reset the EPA's.

Note:

At the lead evaluator's discretion, this event may be initiated prior to the end of the previous event.

When directed by lead instructor/evaluator, insert the following malfunction:

TRG3 RP06B, LOSS OF MOTOR GENERATOR MGOlB, FV=TRUE The four white RPS power lights for RPS B go out.

CREW

  • Recognizes and reports the loss of RPS MG Set B.

SRO

  • Acknowledges report for trip of MG Set B Note:
  • Directs RO to enter N2-SOP-97 The SRO may assign N2-SOP-97 to either the BOP or RO, however some actions of N2-SOP-97 are in the back panels so if the RO is taking actions per N2-SOP-97, he must either turn over the OATC position to the BOP, or transfer action of N2-SOP-97 to the BOP.

Page 20 of 42 NRC Scenario 2

CENG.

NINE MILE POINT NUCLEAR STATION RO

  • Acknowledges direction to enter N2-SOP-97
  • Performs the following actions per N2-SOP-97:

o Makes an announcement to stop any half scram or isolation testing o Determines cause of entry into N2-SOP-97 is due to loss of scram solenoid power o Determines all lights are out on the B trip system o Determines the power source selector switch is in NORM Role Play o Contacts PO and directs him to check:

As PO directed to check the EPAs and MG set,

  • RPM-EPAs wait one minute and inform the control room
  • RPM-MG set that the ~PS B RPM-EPAs are tripped, the B
  • MG set supply breakers RPM-MG set is not running and the B RPS MG o Determines the MG set is not running set supply breaker is closed Role Play o Directs PO to place output switch forB As PO directed to adjust the MG set, wait one MG set to OFF and hold MOTOR OFF minute and inform the control room that the B pushbutton until green light is lit MG set output switch is OFF and the MOTOR o Determines the ALT B FEED AVAILABLE OFF pushbutton was depressed until the green light is illuminated at PNL610 light was lit. o Places the power source selector switch for MG set Bin ALT B Page 21 of 42 NRC Scenario 2

CENG_

dl(l!f':\'flfl\I"P.:J!---

0:.::--- -t~eDF NINE MILE POINT NUCLEAR STATION Role Play RO Ccont.l As PO directed to reset the A RPM-EPAs, wait o Contacts PO and directs them to one minute and insert the following remote attempt to reset the RPS B EPAs per function: N2-SOP-97, Detail B o Acknowledges report from PO that the TRG4 RP02, RPS MG2 EPA, FV=RESET UNDERVOLTAGE RELAY on ACBlA had to be bypassed prior to resetting the Inform the control room that the B RPM-EPAs EPA.

have been reset, however the UNDERVOLTAGE o Determines the 4 white RPS solenoid RELAY on ACBlB could not initially be reset lights are on at P603.

and you had to bypass the relay using the red o Informs SRO that the RPS A solenoids knife switch before it would reset. have been reenergized and the UNDERVOLTAGE RELAY on ACBlA had to be bypassed.

SRO

  • Acknowledges report that the UNDERVOLTAGE RELAY on ACBlB had to be bypassed.

Role Play

  • Contacts the SM and informs him of the As SM, acknowledge the report for trip of the loss of MG set and inoperable EPA MG Set and inform the SRO that you will take action to inform the WWM and maintenance groups.
  • RPS B Scram Solenoids energized from their alternate power supply

Page 22 of 42 NRC Scenqrio 2

CENG.

NINE MILE POINT NUCLEAR STATION Event #5: Clogging of Service Water Traveling Screens

  • Operators will take action to monitor and ultimately open the traveling screen bypass valves to restore intake bay level.

Note:

This event takes several minutes before an annunciator alerts the crew to a problem with the service water system. At the discretion of the lead evaluator, this malfunction may be inserted prior to completing the previous event.

Verify inserted the following remote function:

CW26, 2SWP*MOV77A/B FAIL TO AUTO OPEN, FV=TRUE When directed by lead evaluator, insert the following malfunction:

TRGS CW09, SW INTAKE CLOGGING, FV=SO, RT=4:00 Expected Annunciators:

601124 TRAVELING SCREEN WASH SYSTEM TROUBLE (first alarm)

After a period of time:

601115 SWP PUMP 1A/C/E SUCTION PRESSURE LOW 601127 SWP INTAKE BAY WATER LEVEL LOW 601218 ~WP PUMP 1B/D/F SUCTION PRESSURE LOW Page 23 of 42 NRC Scenario 2

CENG.

  • 'ifl;ltf'~vt.'lf!.u!f'0!---

0~ ~;eoF NINE MILE POINT NUCLEAR STATION Note: CREW When Service Water Intake Bay Level reaches

  • May identify that SW intake bay level is 238 feet ( "'6 min.), modify the following lowering prior to any annunciator malfunction:
  • Acknowledges report
  • Directs actions per appropriate ARPs Role Pial£ BOP As PO dispatched to investigate the trash
  • Contacts PO and dispatches them to rakes and travelling screens, wait two minutes inspect and report the status of the trash and report that the travelling screens are rakes and traveling screens clogged with debris but no additional debris is
  • Recognizes and reports SW intake bay coming in. As necessary, respond to the level lowering control room that you are attempting to clean the travelling screens SRO
  • Acknowledges report of lowering intake bay level
  • Directs BOP to enter N2-SOP-11 BOP
  • Acknowledges direction to enter N2-SOP-11 Role Pial£
  • Contacts PO and dispatches them to verify As PO di~patched to verify proper operation of proper operation of traveling screens and the traveling screens and trash rakes per N2- trash racks per N2-0P-12 OP-12, acknowledge report.
  • Trips the Jet Motive Pump (SWP-P3)
  • When intake bay level lowers to 238 feet, verifies 2SWP*MOV30A/B are open Page 24 of 42 NRC Scenario 2

CENG.

NINE MILE POINT NUCLEAR STATION CT-1.0 Given service water intake bay

  • When intake bay level lowers to 234 level less than 234 ft and a failure of feet, determines 2SWP*MOV77A &

2SWP*MOV77A & 778 to automatically 778 failed to open automatically and open, the crew will take action to manually opens them.

manually open 2SWP*MOV77A & 778 per

  • Determines intake bay level is rising and N2-SOP-11 informs the SRO.

Note: SRO The crew may choose to place the mode

  • Acknowledges report of rising intake bay switch in shutdown during the course of the level.

event based on operator judgment. This is an acceptable action and will not prevent evaluation of the critical task nor interfere with the remaining events in this scenario.

  • 2SWP*MOV77A and 77B open
  • Service Water Intake Bay level rising Page 25 of 42 NRC Scenario 2

CENG.

NINE MILE POINT NUCI.EAR STATION Events #6 and #7: Loss of Feed Pumps and Level Control Issues

  • A Loss of feed pumps will occur.
  • The crew will use alternate level control systems to maintain RPV water level Note:

If the crew placed the mode switch in shutdown in the previous event, the below malfunctions were inserted:

RR20, DBA LOCA, FV=l.S, RT=lS:OO FW03A, FEED PUMP TRIP (PlA)

FV=TRUE FW03B, FEED PUMP TRIP (PlB)

FV=TRUE, DT=3 When dir~cted by lead evaluator, insert the following malfunction:

TRG6 RR20, DBA LOCA, FV=l.S, RT=lS:OO FW03A, FEED PUMP TRIP (PlA)

FV=TRUE FW03B, FEED PUMP TRIP (PlB)

FV=TRUE, DT=3 Feed Pumps A and B trip OW pressure starts to rise slowly RPV water level starts to lower Page 26 of 42 NRC Scenario 2

CENG.

NINE MILE POINT NUCI EAR STATION The following annunciators alarm:

  • 603139, REACTOR WATER LEVEL HIGH/LOW
  • 8515f!9, REACTOR FEED PUMP 1A/1B/1C AUTO TRIP
  • 851519, REAC FEED PMP 1A/1B/1C MOTOR ELEC FAULT
  • 851523, CNST BSTR PMP 2A/2B/2C SUCTION FLOW LOW
  • 851254, PROCESS AIRBORNE RADN MON ACTIVATED CREW
  • Recognizes and reports loss of feed pumps and rising drywell pressure SRO
  • Acknowledges report of loss of feed pumps and rising drywell pressure.
  • Directs the RO to place the mode switch in shutdown.

RO

  • Acknowledges direction to place the mode switch to shutdown.
  • Places mode switch to shutdown .
  • Provides scram report to SRO Page 27 of 42 NRC Scenario 2

CENG. .

NINE MILE POINT NUCLEAR STATION SRO

  • Acknowledges scram report
  • Enters N2-EOP-RPV on low RPV water level
  • Directs RO to perform actions of N2-SOP-101C
  • Directs RO to maintain RPV water level 160 to 200 inches using any one or a combination of the following injection sources:

0 Feed Pump by starting Feed Pump C 0 Maximize RDS Flow per N2-0P-30, H.3.0 0 RCIC 0 HPCS o Condensate Booster Pumps (requires a pressure reduction)

  • Directs BOP to maintain RPV Pressure 800 to 1000 psig with the EHC system or to coordinate with RO to maintain 500 to 600 psig with EHC to facilitate booster pump injection.

RO CN2-SOP-101C)

  • Acknowledges direction to take actions per N2-SOP-101C
  • Acknowledges direction to maintain RPV water level 160 to 200 inches using 0 Feed Pump by starting Feed Pump C 0 RDS Flow per N2-0P-30, H.3.0 0 RCIC 0 HPCS 0 Condensate Booster Pumps
  • Performs initial actions of N2-SOP-101C:

o Verifies turbine has tripped and TSV/TCVs are shut Page 28 of 42 NRC Scenario 2

CENG .

.l!(nl'",*an:umof---

0=:---- --t~eoF NINE MILE POINT NUCLEAR STATION RO (cont.)

o Verifies generator has tripped and house loads have transferred o Verifies SDV vent and drain valves have closed o Verifies RCS pumps have downshifted o As necessary inserts SRMs and IRMs 0 Determines scram cannot be reset due to high drywell pressure 0 Places all FWLC Valves to MANUAL and verifies all FWLC Valves are fully shut Role Play 0 May direct energizing 2WCS-MOV107 As PO directed to energize 2WCS-MOV107, 0 May shutdown HWC acknowledge the report.

Note: RO (N2-SOP-101C- Start Feed Pum12 C)

The starting of Feed Pump C may or may not

  • Attempts to start Feed Pump C per N2-be performed based on the level control SOP-lOlC as follows:

strategy selected by the SRO. 0 Determines at least one condensate pump is available 0 Places Feed Pump A and B control switches in Pull To Lock 0 Determines at least two condensate pumps and two condensate booster pumps are already running.

0 Places the FWLC Master and individual controllers in MANUAL and shuts all FWLC valves.

0 Determines that it is not required to reset the Level 8 trips.

0 Confirms Feed Pump C suction is >500 psig o Verifies Feed Pump C Aux Oil Pump is running.

Page 29 of 42 NRC Scenario 2

CENG.

,)l(:llf'~.:tifl!~<tP.0!---

0=:--- ~'"eof NINE MILE f'OINT NLCLEAR STAiiON When the RO places the Feed Pump C switch 0 Places Feed Pump C control switch to to start, verify inserted the following START malfunction: o Confirms Feed Pump C starts when the minimum flow valve is tv19% open.

TRG7 FW03C, FEED PUMP TRIP (PlC) 0 Opens Feed Pump C FWLC Valve and FV=TRUE, DT=15 injects to maintain RPV Level 160 to 200 inches .

After 15 seconds, Feed Pump C trips 0 Recognizes and reports that Feed Pump C has tripped on motor electric fault and that Feed Pump C is not available.

Note: RO (N2-0P Maximize RDS flow)

The maximizing of RDS Flow may or may not

  • Attempts to maximize RDS Flow as be performed based on the level control follows:

strategy selected by the SRO. 0 Determines that both RPS A and Bare tripped.

o Verifies RDS Pump lA is already running.

When the RO places the RDS Pump lB switch 0 Places RDS Pump lB control switch in to start, verify inserted the following START malfunctions: 0 Recognizes and reports that both RDS Pumps have tripped on motor electric TRGS RD12A, CRD FEED PUMP TRIP fault and are not available (PlA) FV=TRUE RD12B, CRD FEED PUMP TRIP (PlB) FV=TRUE, DT=3 RDS Pumps P1A and P1B trip.

Note: RO (Starting HPCS - N2-0P-33)

Use of HPCS may or may not be performed

  • Starts HPCS as follows:

based on the level control strategy selected by o If not already initiated due to Level 2 or the SRO. high drywell pressure, ARM's and DEPRESSES the HPCS MANUAL INITIATION PUSHBUTTON.

o Verifies HPCS Pump starts o Verifies HPCS Injection Valve opens o Verifies HPCS Minimum Flow Valve closes on rising HPCS flow Page 30 of 42 NRC Scenario 2

CENG.

NiNE MILE POINT NUCLEAR STATION Role Play o Verifies Division 3 EDG starts.

If contacted as PO to perform running checks o At 2CEC*PNL851, verifies open 2CNS-on the Division 3 EDG, wait two minutes and AOV123, CONDENSATE STORAGE TKS inform the control room that running checks MAKE UP VLV have been completed satisfactorily o OPENS and SHUTS HPCS Injection Valve as necessary to maintain RPV Water Level 160 to 200 inches.

RO (Starting RCIC - N2-EOP-HC)

  • Initiates RCIC as follows:

o If RCIC is not already running, arms AND depresses RCIC MANUAL INITIATION pushbutton o Verifies the following:

  • GLAND SEAL SYSTEM AIR COMPRESSOR starts
  • ICS*MOV116 opens
  • ICS*MOV120 opens
  • ICS*MOV126 opens
  • WHEN RCIC flow >220 gpm, ICS*MOV143 closes
  • WHEN RCIC discharge pressure >

Reactor pressure, ICS*V156 AND ICS*V157 open

  • RCIC injection to Reactor controlled at 600 gpm
  • ICS*AOV109 closes
  • ICS*AOVllO closes
  • ICS*AOV130 closes
  • ICS*AOV131 closes o Controls RCIC as follows:
  • If maintained in Automatic Control, maintains Turbine Speed >1500 rpm and Injection Flow between 400 to 600 gpm.

Page 31 of 42 NRC Scenario 2

CENG.

  • >IQtf'~\'ftfl~lJteol--*--

0~ ~~*Of NINE MILE POINT NUCLEAR STATION RO <cont.)

  • If maintained in manual Control, maintains Turbine Speed >1500 rpm and Injection Flow <600 gpm.

0 If it is desired to reject RCIC to the CST (i.e. tank to tank mode), performs the following:

  • Opens 2ICS*MOV124, TEST BYPASS TO CON. STORAGE TANK
  • Throttles 2ICS*FV108 TEST BYPASS TO CON. STORAGE TANK as necessary to control RPV Level.

Note: BOP (Lowering RPV Pressure for Inject.}

Use of Condensate Booster Pumps for injection

  • Acknowledges direction to maintain RPV may or may not be performed based on the pressure 500 to 600 psig using EHC.

level control strategy selected by the SRO. If

  • Coordinates with RO and lowers RPV this strat~gy is selected, then an RPV pressure pressure as follows:

reduction will be required to allow booster 0 DEPRESSES the INCREASE pushbutton pumps to inject. for the BYPASS OPENING JACK until 5 bypass valves indicate full open o Adjusts the bypass valves as necessary to control RPV Pressure 500 to 600 psi g.

RO (Injecting with Cond. Booster PumRS}

  • Coordinates with BOP to lower RPV pressure and injects with Condensate Booster Pumps as follows:

o As RPV pressure lowers, opens LV10A, B, orCas required to maintain RPV level 160 to 200 inches.

0 May place FWLC back into automatic.

Page 32 of 42 NRC Scenario 2

CENG .

NINE MILE POINT Nlr.LEAR STA110N

  • BOP (N2-SOP-101C - Pressure Control}
  • Acknowledges direction to maintain RPV pressure 800 to 1000 psig using EHC.
  • As necessary to control pressure, performs the following:

0 Closes 2MSS-AOV87A/B/C/D and AOV88A/B 0 Closes 2ASS-MOV152 o Starts 2ARC-P1A orB as follows:

  • Confirms there is no fuel damage
  • Opens SWP-HV98A(B)
  • Verifies proper operation 0 Closes 2ASS-MOV148 o As necessary to prevent excessive cooldown, closes the MSIV's.

SRO

  • As required, acknowledges report of trip of Feed Pump C and RDS Pumps.
  • Adjusts level control and pressure control strategies as appropriate based on equipment malfunctions.
  • RPV Level Control has been established.
  • RPV Pressure Control has been established.

Page 33 of 42 NRC Scenario 2

ol!{llf~ VUf'~~l'IJOi---

0=:--- -t~eOF NINE MILE POINT NUCLEAR STATION Event #8 and #9: LOCA with failure of PC Spray Systems

  • A LOCA will occur causing drywell pressure to rise.
  • The crew will respond and attempt to mitigate Primary Containment parameters, however due to failure of the spray systems, a blowdown will eventually be required due to PSP.

Note: Crew The following malfunction was inserted in

  • Recognizes and reports rising drywell the previous event: pressure.

RR20, DBA LOCA, FV= 1.5, RT=15:00 Based on the level and pressure control strategies chosen by the crew, the rate of drywell pressure rise may rise or lower. As determined by the lead evaluator, the severity value on the above malfunction may be modified :as necessary to raise or lower the rate of drywell pressure rise.

A few minutes after the initiation of the previous event, the following additional annunciators alarm:

  • 603140, DRYWELL PRESSURE HIGH/LOW
  • 6031f:?1, RPS A DRYWELL PRESSURE HIGH TRIP
  • 603401, RPS B DRYWELL PRESSURE HIGH TRIP BOP
  • Recognizes and reports that Division 1 ECCS Systems failed to automatically initiate
  • ARMs and DEPRESSES the Division 1 ECCS Manual Initiation Pushbutton.

Page 34 of 42 NRC Scenario 2

CENG,.

NINE MILE POINT NUCLEAR STATION BOP (cont.)

  • Determines that the initiation pushbutton failed to operate.
  • Manually starts the LPCS pump by placing the control switch to START Note:
  • Attempts to manually start RHS Pump lA A malfunction will prevent manually starting of
  • Determines RHS Pump lA will not start RHS Pump lA. from the control room.

Role Play

  • May dispatch an operator to investigate If directed to investigate the cause of why cause and/or locally shut the RHS Pump RHS Pump lA would not start and/or directed lA breaker.

to locally shut the RHS Pump lA breaker, wait

  • Reports to the SRO that RHS Pump lA two minutes and inform the control room that failed to start.

there is nothing visibly wrong with the pump and breaker but you were not able to get the breaker to shut locally.

SRO CN2-EOP-PC)

  • Acknowledges report of rising drywell pressure and that RHS Pump lA failed to start.
  • Enters N2-EOP-PC and reenters N2-EOP-RPV when drywell pressure reaches 1.68 psi g.
  • Determines drywell pressure cannot be maintained below 1.68 psig.
  • Determines Suppression Pool water level is below 217 feet.
  • Directs BOP to spray the suppression chamber using RHS B per N2-EOP-6.22
  • As necessary, directs RO/BOP to restore pneumatics to the Drywell.

Page 35 of 42 NRC Scenario 2

CENG.

NINE MILE POINT NUC'A.EAR STATION RO£BOP (N2-EOP-HC- 5th SW Pum12)

o Selects either SWP E or F to start o Verifies 2SWP*MOV74 shut for the associated pump.

o Starts SWP Pump lE or lF by placing its associated control switch to START o Verifies the associated MOV47 opens.

RO£BOP (N2-EOP-HC Restore Pneum.)

  • Acknowledges direction to restore pneumatics to the Drywell
  • Restores pneumatics to the Drywell as follows:

o At 2CEC*PNL851:

  • Places LOCA OVERRIDE VLV IAS*SOV166 to OVERRIDE
  • OpensiAS*SOV166 o At 2CEC*PNL851:
  • Places LOCA OVERRIDE VLV IAS*SOV184 to OVERRIDE
  • Opens IAS*SOV184 o At 2CEC*PNL601:
  • Places LOCA OVERRIDE VLV IAS*SOV164 to OVERRIDE
  • Opens IAS*SOV164 o At 2CEC*PNL601:
  • Places LOCA OVERRIDE VLV IAS*SOV165 to OVERRIDE
  • OpensiAS*SOV165
  • Informs the SRO that pneumatics have been restored to the drywell.

Page 36 of 42 NRC Scenario 2

CENG."

  • IIOtl\'tlfl'tJl'!!Ul---

0==---- -!:erw NINE MILE POINT NUCI.EAR STATION BOP CN2-EOP-6.22l

  • Acknowledges direction to spray the suppression chamber using RHS B
  • Sprays the suppression chamber using RHS Bas follows:

0 Determines a LOCA Signal is present and drywell pressure is > 1.68 psi g.

0 Opens 2SWP*MOV90B o Verifies closed and overridden 2RHS*MOV24B o Verifies running RHS*PlB 0 Sprays the suppression chamber by opening 2RHS*MOV33B o Verifies >450 gpm on the suppression chamber spray flow meter.

o Throttles 2SWP*MOV33B as necessary to supply Service Water Flow of "'7400 gpm to the RHS B Heat Exchanger.

Role Pial£ 0 Contacts RP and directs them to start As RP contacted to place RE-23B in service, 2SWP*RE23B wait two minutes and insert the following

  • Informs the SRO that RHS Pump lB is remote function : spraying the suppression chamber TRG9 RM02-041, SWP 23B RAD MONITOR ONLINE, FV=ON RM03-041, SWP 23B RAD MONITOR SAMPLE PUMP POWER, FV=ON Report back to control room that RE-23B is in service SRO CN2-EOP-PC)
  • Acknowledges report of RHS Pump lB spraying the suppression chamber
  • Waits until suppression chamber pressure reaches 10 psig Page 37 of 42 NRC Scenario 2

CENG.

  • ~ll*'~\*nn:tn!of---

0~ "'4',eDF NINE MILE POINT NL.CI.EAR STATION SRO (cont.)

  • Determines suppression pool water level is still below 217 feet
  • Determines parameters or within the Drywell Spray Initiation Limit
  • Directs the RO/BOP to trip both recirculation pumps
  • Directs the RO/BOP to trip all drywell unit coolers.
  • Directs BOP to spray the drywell with RHS Pump lB.

ROlBOP (Trill Recirculation Pumlls}

  • Acknowledges direction to trip the Recirculation Pumps
  • If not already completed, trips the Recirculation Pumps as follows:

0 Places Control Switch(s) for Recirculation Pumps A and B to STOP

  • Informs the SRO that Recirculation Pumps A and B are tripped.

Note: ROLBOP (Orl£well Unit Coolers}

Unless Drywell Unit Coolers have been

  • Acknowledges direction to verify tripped restored per N2-EOP-6.24, the coolers should all Drywell Unit Coolers already be tripped.
  • Verify tripped all Drywell Unit Coolers as follows:

o At 2CEC*PNL873, observes that all red running lights for all drywell coolers are off.

  • Informs SRO that all drywell coolers are verified tripped.

BOP (N2-EOP-6.22}

  • Acknowledges direction to spray the drywell using RHS B
  • Sprays the drywell using RHS Bas follows:

Page 38 of 42 NRC Scenario 2

CENG.

d!Dlf*:'l'flf'tu<P.<Ji---

0=:--- ..::eDF NINE MILE POINT NUCLEAR STAllON BOP Ccont.l 0 Determines drywell spray interlocks are met o Verifies open 2SWP*MOV90B o Verifies closed 2RHS*FV38B o Verifies running RHS Pump lB o Verifies 2RHS*MOV33B is open o Verifies >450 gpm on the suppression chamber spray flow meter.

Note: o Attempts to spray the drywell by When attempting to spray the drywell, opening 2RHS*MOV15B and MOV25B will fail to open due to it being stuck 2RHS*MOV25B shut. 0 Recognizes that 2RHS*MOV25B will not open.

Role Play 0 Dispatches a PO to attempt to manually As PO directed to attempt to open open 2RHS*MOV25B 2RHS&MOV25B, wait 3 minutes and inform the 0 Informs the SRO that the he cannot control room that it is stuck shut and you are spray the drywell using RHS Pump lB.

getting additional operators to help you open the valve:.

SRO CN2-EOP-PC)

  • Acknowledges report of the inability to spray the drywell using RHS Pump lB
  • Directs the BOP to spray the drywell using Fire Water through RHS A per N2-EOP-6.6
  • Analyzes the Pressure Suppression Pressure curve.
  • Determines he cannot restore and maintain suppression chamber pressure and suppression pool water level within the Pressure Suppression Pressure limits.
  • Enters N2-EOP-C2, RPV Blowdown Page 39 of 42 NRC Scenario 2

CENG .

.l!(.'1f\'$!~uleHI---

o~ ~'eDf NINE MILE POINT NUCLEAR STATION BOP CN2-EOP-6.6l

  • Acknowledges direction to spray the drywell using Firewater through RHS A
  • Sprays the drywell using Firewater through RHS A as follows:

o Starts Firewater Pump 1 or 2 0 Determines RHS A is not in operation 0 Places RHS Pump lAin Pull To Lock o Verifies closed the following valves:

  • RHS*MOVlSA, OUTLET TO DRYWELL SPRAY
  • RHS*MOV25A, OUTLET TO DRYWELL SPRAY
  • RHS*MOV33A, OUTLET TO SUPPR POOL SPRAY
  • RHS*FV38A, RETURN TO SUPPR POOL COOLING
  • RHS*MOV40A, SDC A Return
  • RHS*MOV12A, HEAT EXCHANGER lA OUTLET VLV o If possible, verifies closed RHS*MOV8A, HEAT EXCHANGER lA INLET BYPASS VLV Role Play 0 Directs a PO to lineup Firewater to RHS As PO directed to lineup Firewater to RHS A, A per N2-EOP-6.6, Starting on Step acknowledge report. Note; this action will not 6.1.6 be completed prior to the end of the scenario.

If contacted for updates, acknowledge the request and inform the control room that you are still working on getting the lineup completed.

SRO CN2-EOP-C2l

  • Enters N2-EOP-C2, RPV Blowdown:

0 Determines Reactor will stay shutdown without boron 0 Determines drywell pressure is above 1.68 psig Page 40 of 42 NRC Scenario 2

CENG.

NINE MILE POINT

  • NUCLEAR STATION Note: SRO (cont.}

Based on the chosen level control strategy, o As necessary based on Level Control the SRO may choose to prevent injection with strategy, directs RO/BOP to prevent some or all low pressure ECCS Pumps. LPCS and LPCI injection.

0 Determines suppression pool level is

>192 feet CT-2.0: Given Suppression Chamber 0 Directs BOP to open 7 ADS valves.

Pressure unable to be restored and maintained within the Pressure Suppression Limit, the crew will open 7 SRV's IAW N2-EOP-C2 RO[BOP (Prevent LPCS[LPCI Iniection}

  • Acknowledges direction to prevent LPCS and LPCI Injection
  • As required, prevents LPCS and LPCI Injection as follows:

0 If necessary, places LPCS in PTL.

o Verifies shut and overridden the following valves:

  • Informs the SRO that LPCS and LPCI Injection has been prevented BOP (N2-EOP-HC - Slowdown}
  • Acknowledges direction to open 7 ADS valves and performs the following:

0 Determines no SRVs are stuck open and an ECCS pump is running CT-2.0: Given Suppression Chamber o Arms and depresses both ADS Pressure unable to be restored and pushbuttons for each division maintained within the Pressure 0 Informs the SRO that 7 ADS valves Suppression Limit, the crew will open 7 are open SRV's IAW N2-EOP-C2 Page 41 of 42 NRC Scenario 2

CENG .

<l<tQI~"*!'I!lJ-'i'lPf---

0~ .:~*Of NINE. MIL[ POINT NUCLEAR STATION SRO CN2-EOP-RPVl

  • Acknowledges report from BOP that 7 ADS valves are open
  • RPV Pressure is lowering Page 42 of 42 NRC Scenario 2

CENG~

NINE MILE POINT .

NUCLE!\fl STATION .

Copy of __

Training Id: NRC 2013 Scenario 4 Revision: 0.0

---=....::...=__ __

Title:

SCl- Secondary containment leak. Blowdown Required.

Signature I Printed Name Developed: By David Huff Validated By Michael Storms Phil MacEwen Doug Mizener Facility Reviewer Aaron Armstrong Page 1 of 34 NRC Scenario 4

CENG_

,'iiCJtf'"\'tlf'~Utf!OI---

0==---- -!::..,

NINE MILE POINT NUCLEAR STATION Referen"ces

1. N2-0P-101A, Reactor Startup
2. N2-0P-30, Control Rod Drive System
3. N2-SOP-60, Loss of Drywell Cooling
4. N2-SOP-19, Loss of Instrument Air
5. N2-0P-31, Residual Heat Removal System
6. N2-SOP-90, Natural Events
7. N2-EOP-RPV, RPV Control
8. N2-EOP-SC, Secondary Containment Control
9. N2-EOP-C2, RPV Slowdown
10. Unit 2 Technical Specifications Page 2 of 34 NRC Scenario 4

CENG~

a tow* ,q;n:uH~uf---

0~ ~~ettf NINE MILE POINT NUCLEAR STATION NOTES Instructor Information A. Scenario Description The crew will take the shift at "'3% power. The RO will raise power using rods. While withdrawing rods, a control rod will stick. The crew will take action to raise drive water pressure per N2-0P-30. Raising drive water pressure will free the stuck* rod and allow the startup to continue. After power has been sufficiently raised, an instrument failure will cause one pair of Suppression Chamber to Drywell Vacuum Breakers to fail open. There are no operator actions; however the CRS will evaluate TS 3.6.1.7.

OnceTS 3.6.1.7 has been evaluated, an electrical fault will cause a loss of all drywell cooling. The crew will respond per N2-SOP-60 and restart the drywell cooling fans in "Fan Only" mode. After Drywell Cooling has been restored, an electrical fault will occur on Instrument Air Compressor A.

Compressors Band C will fail to auto start. The crew will take action per N2-SOP-19 and manually start either Compressor B or C (CRITICAL TASK} to restore air header pressure.

After the loss of instrument air, a failure will cause a spurious initiation of Division 1 ECCS systems. Additionally, the minimum flow valve for RHS Pump A will fail to open leaving RHS Pump A without minimum flow protection. The crew will take action to shutdown the Division 1 ECCS systems. The CRS will evaluate TS 3.5.1 and 3.8.1. Following the inadvertent initiation of Division 1 ECCS systems, a seismic event occurs. The event will cause an unisolable RCIC steam leak and a FWLC failure. The crew will take action per N2-EOP-SC and enter N2-EOP-RPV to manually scram the reactor (CRITICAL TASK}. RPV level control will be complicated by the FWLC failure. Due to the RCIC steam leak, Secondary Containment conditions will continue to degrade requiring the Page 3 of 34 NRC Scenario 4

CENG:"

NINE MILE POINT NUCLEAR STATION NOTES crew to either anticipate RPV blowdown per N2-EOP-RPV, or perform a blowdown per N2-EOP-C2 (CRITICAL TASK}. The scenario may be terminated when the RPV is being depressurized.

1. Termination Criteria
a. RPV is being depressurized.
2. Critical Tasks CT-1.0 Justification: This task is identified as critical because without operator action to start the lag or backup air compressor, instrument air header pressure will degrade until the reactor scrams due to low RPV level and/or loss of scram air header pressure.
a. CT-1.0, Given a trip of the running instrument air compressor and a failure of the lag and backup air
compressors to automatically start, the crew will take action to manually start the lag or backup air compressor.

CT-2.0 Justification: This task is identified as critical because without operator action to scram, the reactor will continue to provide energy to the RCIC steam line break and cause increased secondary containment temperatures and radiation levels.

b. CT-2.0, Given secondary containment temperatures approaching a maximum safe value in one area, the crew will initiate a manual reactor scram lAW N2-EOP-RPV Page 4 of 34 NRC Scenario 4

CENG_

NINE MILE POINT NUCI EAR STATION

  • I NOTES CT-3.0A Justification: This task is identified as critical because without operator action to depressurize the reactor, secondary containment integrity, the integrity of equipment located in the secondary containment, and continued safe operation of the plant cannot be assured. Note:

The crew may choose to wait until two or more areas are above maximum safe values before depressurizing the reactor. If the crew chooses to depressurize the reactor via the SRVs, then CT-3.0A does not have to be evaluated.

c. CT-3.0A, Given secondary containment temperatures approaching or above maximum safe values in one area, the crew will open 5 main turbine bypass valves lAW N2-EOP-RPV CT-3.08 Justification: This task is identified as critical because without operator action to depressurize the reactor, secondary containment integrity, the integrity of equipment located in the secondary containment, and continued safe operation of the plant cannot be assured. Note:

The crew may choose to "anticipate blowdown" and depressurize the reactor to the main condenser. If the crew chooses to depressurize the reactor to the main condenser and are successful in preventing two areas from exceeding the maximum safe temperatures, then CT-3.08 does not have to be evaluated.

d. CT-3.0B, Given secondary containment temperatures above maximum safe values in two areas, the crew will open 7 ADS valves lAW N2-EOP-C2
3. Length
a. . "'70 minutes
4. Mitigation Strategy Code
a. SC1- Secondary containment leak. Blowdown Required
5. Technical Specifications
a. TS 3.6.1. 7
b. TS 3.5.1
c. TS 3.8.1
6. EAL Classification
a. Site Area Emergency, FS1.1, Loss or potential loss of ANY two fission product barriers.

Page 5 of 34 NRC Scenario 4

CENG. .

b. Table F-1, RCS Barrier Loss C3 and C4, Potential Loss C1
c. Table F-1, Containment Barrier Loss C3.
7. Special Orders
a. None B. Initial Conditions
1. IC Number
a. IC-153
2. Presets I With Triggers
a. :Malfunctions
1) IA04A, LAG COMPRESSOR AUTO START FAILURE, INSERTED FV=TRUE
2) IA04B, B/U COMPRESSOR AUTO START FAILURE, INSERTED FV=TRUE
3) RC11, RCIC ISOLATION FAILURE, FV=TRUE INSERTED
4) PClOA, DRYWELL VACUUM BKR PAIR FAIL OPEN TRGl (2ISC*RV33A/B), FV=TRUE
5) PCOl, LOSS OF DRYWELL COOLING, FV=TRUE TRG2
6) IA02A, 2IAS-C3A THERMAL OVERLOAD TRIP, TRG3 FV=TRUE
7) RH13A, ECCS INADVERTENTLY INITIATES (DIV I), TRG4 FV=TRUE
8) RH15, RHS*MOV4A VALVE FAILS SHUT, FV=TRUE TRG4
9) MTOl, SEISMIC ACCELERATION, FV=2 TRGS
10) FWOSB, LV55B FAILURE- CLOSED, FV=TRUE TRGS
11) RC12, RCIC STEAM LEAK IN RB, FV=35, TRGS RT=15:00 Page 6 of 34 NRC Scenqrio 4

CENG.

NINE MILE POINT Nlx:LEAR STATlON NOTES

12) RD07-26-43, ROD 26-27 STUCK, FV=TRUE TRG10
b. Remotes

.1) None

c. Overrides
1) 01A2S041DI0365, ICS*MOV121 SWITCH CLOSE, INSERTED FV=OFF
2) 01A2S041DI0366, ICS*MOV121 SWITCH OPEN, INSERTED FV=OFF
3) 01A2S042DI0564, ICS*MOV128 SWITCH CLOSE, INSERTED FV=OFF
4) 01A2S042DI0418, ICS*MOV128 SWITCH OPEN, INSERTED FV=OFF
d. Annunciators
1) None
e. Event Triggers 10 RDVPOSB(137}==160 Blank (Rod 26-43 at position 10) 11 hzardr602>0.863 dmf RD07-26-43 (Drive Water DP greater than 300 psid)
f. Equipment Out of Service
1) None
g. :Support Documentation
1) Turnover Sheet and RMI
2) N2-0P-101A marked up to step E.3.4
3) A2 Startup Rod Sequence marked up to RWM Step 15, Rod 14-35 Page 7 of 34 NRC Scenario 4

CENG.

UIOU".>'P.f'~l.lfi~ni---

0~ ~:eDf NINE MILE POINT NUCLEAR STATlON NOTES h.

1) Ensure that when IC-153 is loaded, the RWM latches on to RWM step 15, Rod 14-35 and there are no RWM rod blocks
2) Ensure the rod position plaque is posted with position 12 on it.

Page 8 of 34 NRC Scenario 4

CENG .

.aiOU':w.tttvr;,:.>f---

0~ -!:eoF NINE MILE POIN r NUCLEAR SiATION SHIFT TURNOVER INFORMATION ON COMING SHIFT: D N I D DATE: -'T-=o=da=y.____

PART I: To be performed by the oncoming Operator before assuming the shift.

  • Control Panel Walkdown (all panels) (SRO, ROs)

PART II: To be reviewed by the oncoming Operator before assuming the shift.

  • LCO Status (SRO)
  • Shift Turnover Information Sheet Evoluti<?ns/Generallnformation/Equipment Status:
  • Reactor Power is 3%
  • A Reactor Startup is in progress
  • RPV Pressure is 925 psig with 1 bypass valve partially open
  • Feed Pump B is running with level control on LV55B
  • A reactor startup in progress per N2-0P-101A. Currently on step E.3.4. The Clean Steam Reboiler is still on the Aux Boilers per SM direction. The SM wants to complete an inspection on an aux steam component prior to transferring the Reboiler to aux steam.

Once the inspection is complete, the SM will inform the control room.

  • All LCOs are met PART Ill: Remarks/Planned Evolutions:
  • Raise reactor power using rods per the startup rod sequence and provided RMI to 8% in preparation for transferring the mode switch to run. RE and STA are available in the control room.

Page 9 of 34 NRC Scenario 4

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NINE MILE POINT NIJ('.tEAR STATION ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Reactor Startup Step: A2 Startup I INITIAL CONDITIONS/STEP DESCRIPTION I

RE presence required in the Control Room? Yes~ No- -

If YES above, RE presence not required for steps Initial conditions to be verified prior to initiation of step:

Parameter Expected Range Actual Parameter Expected Range Actual Core Flow 20 to 59 Mlb/hr 28 Mlb/hr RWM A2 Sequence A2 Time Today Today Description of Step:

CD Perform Reactor Startup in accordance with A2 startup sequence and appropriate procedures Critical parameters to be monitored DURING Step:

Critical parameters not used must be deleted OR marked N/A Critical Contingency Limit Owner Frequency Parameter SRM Count 3 Continuous when SRMs RO Single Notch Withdrawal Rates doublings inserted Continuous when SRMs Rx Period 60 sec RO Insert last control rod one notch inserted RMI evaluated against approved power profile:

  • N/A D.

IOther Comments

  • None Step Prepared By: Joe Engineer Today Step Reviewed By: John Engineer Today I

REIST A Date RE/STAISRO Date Approval to Perform Step: Joe Manager Today Shift Manager Date Step Completed By:

SRO Date Page 10 of 34 NRC Scenario 4

CENG .

NINE MILE POINT NUCLEAR STATION Shift Turnover Take the Simulator out of freeze before the crew enters for the pre-shift walkdown.

  • If recording scenario, start the recording device during the pre-shift walkdown Allow no more than 5 minutes to walkdown Crew the panels.
  • Walkdown panels
  • Conduct shift turnover brief
  • Assume the shift Page 11 of 34 NRC Scenario 4

dl(lll'",vflf1C!$£ltl1---

o=:---- -::,eDf NINE MILE POINT NUCLEAR STAT10N Events #1 and 2, Withdraw rods to raise power and one rod sticks.

  • Initial reactor power is 3%.
  • The crew will withdraw rods to raise power

SRO

  • Directs RO to raise reactor power to 8%

using the A2 startup rod sequence and provided RMI RO

  • Monitors RPV, CRD and Nuclear Instruments
  • Withdraws control rods lAW rod sequence using single notch withdrawal.

Note:

  • Determines and reports rod 26-43 is stuck When rod 26-43 is moved from position 8 to at position 10 position io, verify the following malfunction is inserted:

TRG10 RD07-26-43, ROD 26-43 STUCK, FV=TRUE SRO

  • Acknowledges report that rod 26-43 is stuck at position 10 Role Pial£
  • May contact SM/RE for direction If contacted as the SM/RE for direction, inform
  • Directs RO to respond to the stuck rod per them to follow the appropriate procedures for N2-0P-30.

a rod which fails to withdraw.

Page 12 of 34 NRC Scenario 4

CENG_

ilfOll'~vnrl:urnuf---

0~ -t'."'

NINE MILE POINT NUCLEAR STATlON RO

  • Acknowledges direction to respond to the stuck control rod per N2-0P-30
  • References section H.1.2, Failure to Withdraw Using Single Notch Withdrawal.
  • Attempts to withdraw rod 26-43 again while monitoring drive water flow Note:
  • Determines one of the following:

Do to variations in drive water flow o Drive water flow was not approximately indications, the crew may determine that the 4 GPM during the insert portion of the insert portion of the DCV sequence is rod withdrawal.

operating correctly and continue on H.1.2. If -OR-the crew determines the insert portion of the o Drive water flow was approximately 4 DCV sequence is operating correctly, then they GPM during the insert portion of the rod will refer to section H.l.l to continue trying to withdrawal.

free the stuck rod. The actions are relatively

  • May refers to section H.l.l, Failure to the same, so either action is acceptable. Insert Note:
  • Raises drive water pressure 50 psid by When drive water pressure is raised above throttling shut on 2RDS-PV101 300 psid, verify deleted the following
  • Attempts to INSERT/WITHDRAW rod 26-malfunction: 43 one notch
  • Lowers drive water pressure back to 260 psid
  • Withdraws rod 26-43 to position 12 if necessary.

Note:

Once rod 26-43 has been withdrawn to position ~2, the Lead Evaluator may choose to either continue the startup to 8%, or may move on to the next event.

Page 13 of 34 NRC Scenario 4

ilJOII'"vun:urnut---

0~ ~~eDF NINE. MILE POINT NUClEAR STATION

  • Reactor power has been raised sufficiently as determined by the Lead Evaluator.

Page 14 of 34 NRC Scenario 4

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NINE MILE POINT NUCLEAR STATION Event #3: One Pair of Drywell Vacuum Breakers Fail Open

  • One pair of Drywell to Suppression Chamber Vacuum Breakers will fail open. No operator action is required. The SRO will evaluate per TS 3.6.1.7 Note:

At the lead evaluator's discretion, this event may be initiated concurrently with the next event.

When directed by the lead evaluator, insert the follo~f!ing malfunction:

TRGl PClOA, DRYWELL VACUUM BKR PAIR FAIL OPEN (2ISC*RV33A/B),

FV=TRUE 2ISC*RV33A and B fail open Drywe/1 and Suppression Chamber pressure equalize.

The following annunciator alarms:

  • 601556, DRYWELL VACUUM BRKR INBOARD DISC OPEN
  • 601557, DRYWELL VACUUM BRKR OUTBOARD DISC OPEN Crew
  • Recognizes and reports AN601556 and AN 601557 SRO
  • Directs BOP to respond per the ARPs Page 15 of 34 NRC Scenario 4

CENG_

a.l(lf!-; ven:~cilol---

0~ ~,.eof NINE MILE POINT Nlr.l EAR STATION BOP

  • Acknowledges direction to respond per the ARPs.
  • References ARP 601556 and 601557 .
  • Determines that both 2ISC*RV33A and B indicate open on 2CEC*PNL628.
  • Informs the SRO that there are no additional actions which can be taken per the ARPs and that both 2ISC*RV33A and Bare open.

SRO

  • Acknowledges report of 2ISC*RV33A and B being open.
  • References TS 3.6.1.7, Conditions Band C and determines he has two hours to close at least one of the open vacuum breakers and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to close the remaining one.

Role Play

  • Contacts SM and informs him of the As the SM, acknowledge the report of the vacuum breaker failures.

failure of the vacuum breakers and inform the SRO that you will contact maintenance and the work week manager.

Page 16 of 34 NRC Scenario 4

CENG~

<*lf)ll'~vtlfi~Utnlli---

0=:--- ~'"'

NINE MILE POINT NUGLEAR STATION Event #4: Loss of Drywell Cooling

  • An instrumentation fault will cause a loss of drywell cooling.
  • The crew will respond per N2-SOP-60 and restart Drywell Cooling Fans in "Fans Only" mode.

Note:

At the discretion of the lead evaluator, this event may be imitated concurrent with the previous event.

When directed by lead evaluator, insert the following malfunction:

TRG2 PCOl, LOSS OF DRYWELL COOLING, FV=TRUE All drywell unit coolers trip off Drywell temperature slowly starts to rise The following annunciators alarms:

  • 873201 DRYWELL UNIT COOLING GROUP 1 SYS TROUBLE
  • 873202 DRYWELL UNIT COOLING GROUP 2 SYS TROUBLE
  • 873304 DIVISION I DRYWELL TEMPERATURE HIGH CREW
  • Recognizes and reports loss drywell cooling.

SRO

  • Acknowledges report of the loss of drywell cooling
  • Directs BOP to enter N2-SOP-60 Page 17 of 34 NRC Scenario 4

CENG~

NINE MILE POINT NUCLEAR STATION .

BOP CN2-SOP-60)

  • Acknowledges direction to enter N2-SOP-60
  • Informs SRO that N2-SOP-60 directs monitoring of drywell temperature and pressure
  • Determines Division I drywell cooling valves are closed
  • Attempts to restore drywell cooling using the cooling leg of N2-SOP-60 Note:
  • May determine that drywell cooling valves The amber light for DIVISION I DRYWELL cannot be opened based on 2CEC*PNL602 UNIT COOLER COOLING WATER manual DIVISION I DRYWELL UNIT COOLER isolation will be lit on 2CEC*PNL602. If the COOLING WATER manual isolation amber crew recognizes this, they will be able to make light being lit and continue in the Fan leg the determination immediately that the of N2-SOP-60 drywell cooling valves will not be able to be
  • Attempts to re-open Drywell Cooling reopened. If this is the case, they may Isolation valves as follows:

continue only in the fan leg of N2-SOP-60. o Places DRYWELL UNIT COOLER WTR DIV I LOCA OVERRIDE switch in OVERRIDE o Closes the CCP inlet isolation valves for all drywell unit coolers o Attempts to re-open 2CCP*MOV265 AND MOV124 o Determines and reports that valves will not reopen

  • Continues in the fan only leg of N2-SOP-60
  • Restores drywell fans as follows:

o Places the following switches in OVERRIDE:

  • UNIT COOLER FANS GRl LOCA OVERRIDE
  • UNIT COOLER FANS GR2 LOCA OVERRIDE Page 18 of 34 NRC Scenario 4

CENG.

.;ll(.l<<'tVWJf!;Uif!Ol---

0~ ~'eDF NINE MILE POINT NLCtEAR STATlON BOP Ccont.l o Starts the following DRS Unit Cooler Fans:

  • Reports drywell fans are restored SRO
  • Acknowledges report of drywell fans restored.

Role Play

  • Contacts SM and informs him of the loss As the SM, acknowledge the report of the loss of Drywell Cooling of drywell cooling and inform the SRO that you will contact maintenance and the work week manager:
  • Drywell cooling fans restored in the "Fan's Only" Mode.

Page 19 of 34 NRC Scenario 4

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NINE MILE POINT NUCLEAR STATION Event #5: Loss of Instrument Air

  • The running instrument air compressor trips and the lag and backup compressors fail to auto start.
  • The crew will respond per N2-SOP-19 and start either the lag or backup air compressors.

Verify inserted the following malfunctions:

IA04A, LAG COMPRESSOR AUTO START FAILURE, FV=TRUE IA04B, B/U COMPRESSOR AUTO START FAILURE, FV=TRUE When directed by lead evaluator, insert the following malfunction:

TRG3 IA02A, 2IAS-C3A THERMAL OVERLOAD TRIP, FV=TRUE IAS-C3A trips on thermal overload Standby CCP Mini-Loop Pump Auto Starts lAS Header Pressure begins to lower The following annunciators alarm:

  • INSTR AIR CPSR 3A/3B/3C AUTO TRIP/FAIL TO START
  • INST AIR COMPRESSOR CLG WTR FLOW LOW
  • 851260, INST AIR COMPRESSOR COOLING SYS TROUBLE CREW
  • Acknowledges trip of IAS-C3A
  • Directs BOP to enter N2-SOP-19 Page 20 of 34 NRC Scenario 4

CENG.

NINE MILE POINT NUCLEAR STATION BOP

  • Acknowledges direction to enter N2-SOP-19 Role Play
  • May dispatch POs to monitor the following If dispatched as a PO to monitor lAS lAS pressures:

pressures, use Simulator Computer Screen o 2IAS-PI194, (RB 261')

IA01 to monitor and report pressures as o 2RDS-PI133, (RB 261')

required by the control room.

  • Determines an air compressor has tripped.
  • Determines the loss of air compressor was not due to a slow transfer or loss of control power Note:
  • Manually starts IAS-C3B or C as follows:

The BOP may wait until lAS pressure lowers to 100 psig and observing IAS-C3B did not auto start before taking manual action to start a backup air compressor -or- the BOP may choose to manually start a backup air compressor before the failure of the backup air compressor to auto start is apparent. Either action is acceptable.

CT-1.0, Given a trip of the running o Places IAS Compressor Selector instrument air compressor and a failure Switch to either BCA or CAB of the lag and backup air compressors to o Places IAS-C3B or 3C control switch automatically start, the crew will take in START action tQ manually start the lag or backup o Verifies IAS-C3B or 3C starts and lAS air compressor. Air Header pressure is rising.

  • Informs the SRO that IAS-C3B or 3C is lAS Air Header Pressure begins to rise. running and that lAS Air Header Pressure is rising.
  • Refers to Attachment 1 of N2-SOP-19 SRO
  • Acknowledges report from BOP that lAS Air Header Pressure has been restored.

Page 21 of 34 NRC Scenario 4

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NINE MILE POINT NLCLEAR STATION Role Play SRO Ccont.l As the SM, acknowledge the report of the loss

  • Contacts SM and informs him of the loss of instrument air and inform the SRO that you of Instrument Air will contact maintenance and the work week manager.
  • IAS-C3B or 3C is running
  • Instrument Air Header pressure is rising Page 22 of 34 NRC Scenario 4

CENG_

a)QIJ!..ur1:Uir>oi---

O=::-- -:::eof NINE MIL£ POINT NUCLEAR STATION Event #6: Spurious Initiation of Division 1 ECCS Systems

  • A spurious initiation of Division 1ECCS Systems will occur with a failure of RHS A Pump Minimum Flow Valve to Open.
  • The crew will take action to secure the Division 1 ECCS Systems.

When directed by lead instructor/evaluator, insert the following malfunction:

TRG4 RH13A, ECCSINADVERTENTLY INITIATES (DIV I), FV=TRUE RH15, RHS*MOV4A VALVE FAILS SHUT, FV=TRUE Division 1 ECCS Systems and diesel automatically start The following annunciators alarm:

  • 601413, LPCS PUMP 1 AUTO START
  • 601426, LPCS SYSTEM ACTUATED
  • 601442, RHR PUMP 1A AUTO START
  • 601451, RHR A SYSTEM ACTUATED
  • 852109, DIVISION I EDG 1 START SYSTEM TROUBLE
  • 852117, EDG 1 RUNNING CREW
  • Recognizes and reports inadvertent initiation of Division 1 ECCS Systems SRO
  • Acknowledges report of Division 1 ECCS Systems running.
  • Directs the BOP to respond per the ARPs Page 23 of 34 NRC Scenario 4

CENG:-

3!(% ~ ven:l1tf!UI 0~ ~~etJF NINE MILE POINT NUCLFAR STATION BOP

  • Acknowledges direction to respond per the ARPs.
  • References ARP for 601413 and 601442 Role Pial£:
  • Determines by looking at multiple If requested to provide RHR and CSL trip unit indications that RPV Level is not below indications (2CEC*PNL629), report that no trip Level 1 and Drywell Pressure is not above units are in alarm and that no gross failures 1.68 psig.

are present.

  • Informs the SRO that there are no valid initiation signals for Division 1 ECCS Systems.
  • Reviews the automatic response of Division 1 ECCS systems and determines and reports 2RHS*MOV4A did not open
  • Attempts to manually open 2RHS*MOV4A
  • Determines 2RHS*MOV4A did not open and informs the SRO SRO
  • Acknowledges report of no valid Division 1 ECCS Initiation signal and 2RHS*MOV4A failing to open
  • Directs BOP to place RHS Pump 1A in Pull to Lock.

Note:

  • May direct BOP to also attempt to At this time, there is no requirement to shutdown the remaining Division 1 ECCS attempt to shutdown the remaining Division 1 Systems ECCS Systems. The SRO may choose to wait to shutdown the systems until after he has had a chance to talk with the SM. This is an acceptable action. If the SRO waits until after he contacts the SM, a role play from the SM will direct the SRO to shutdown the remaining Division 1 ECCS Systems per the appropriate OP's.

Page 24 of 34 NRC Scenario 4

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NINE MILE POIN l NLX:I.EAR STATION; BOP

  • Acknowledges report to place RHS Pump 1A in Pull To Lock
  • Places RHS Pump 1A control switch in Pull To Lock
  • As required, acknowledges direction to shutdown the remaining Division 1 ECCS Systems.

Role Play

  • Dispatches PO to perform running checks As directed to perform running checks on on Division 1 EDG.

Division 1 EDG, wait 2 minutes and inform the control room that running checks have been completed satisfactorily.

Role Play

  • May contact the booth and ask for any trip As the booth, if contacted for any trip units, units which may have actuated.

inform the operator that there are no trip units

  • As required, performs a shutdown of the tripped. LPCS system per N2-0P-32 as follows:

0 Depresses LPCI A/LPCS RESET pushbutton.

0 Determines white reset seal-in light did not extinguish 0 Places LPCS pump control switch in Pull to Lock

  • As required, performs a shutdown of the Division 1 EDG per N2-0P-100A, Section H.16.0 as follows:

0 Places EMERGENCY DSL GEN 1 LOCA SIGNAL BYPASS switch to ON 0 Places DIVISION 1 2EGS*EG1 START switch in PULL-TO-LOCK

  • Informs the SRO that the Division 1 ECCS Systems are shutdown.

SRO

  • Acknowledges report of RHS Pump 1A control switch in Pull to Lock.
  • As required, acknowledges report of Division 1 ECCS Systems Page 25 of 34 NRC Scenario 4

CENG.

rijOII~:\"fMI':ufP.!)1*---

o~ ~~*Df NINE MILE POINT NUCLEAR STATION Role Play SRO (cont.)

As the SM, acknowledge the report of the

  • Contacts SM and informs him of the Division 1 ECCS System Failure and inform the Division 1 ECCS System Failure SRO that you will contact maintenance and the
  • If necessary, acknowledges direction to work week manager. If the SRO has not shutdown the remaining Division 1 ECCS already shutdown the Division 1 ECCS Systems.

Systems, direct the SRO to attempt to

  • Refers toTS 3.5.1 and determines that shutdow~ or place the systems in PTL per the with both LPCS and RHS A inoperable that appropriate OPs. Condition A and C applies and he has 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore one of the pumps to operable status and 7 days to restore the remaining pump.
  • Refers toTS 3.6.1.6 and determines that Condition A applies and he has 7 days to restore RHS A drywell spray system to operable status.
  • Refers toTS 3.6.2.3 and determines Condition A applies and he has 7 days to restore RHS A suppression pool cooling to operable status Note:
  • Refers toTS 3.8.1 and determines Because the Division 1 ECCS systems are Condition B applies and that he must inoperable, the SRO cannot use the extended perform SR 3.8.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 14 day completion time allowed per Condition restore the Division 1 EDG to operable B. He is required to use the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

completion time as references in the TS 3.8.1 Bases.

  • Division 1 ECCS Systems are shutdown
  • SRO has referenced Technical Specifications, (At the Lead Evaluator's discretion, the referencing of all Tech Specs may be deferred until after the end of the scenario as long as appropriate follow up questions are used at the completion of the scenario).

Page 26 of 34 NRC Scenario 4

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