Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML12054A208
Person / Time
Site:	Susquehanna
Issue date:	12/20/2011
From:	Caruso J; Operations Branch I
To:	Goff C; Susquehanna
	Jackson D
Shared Package
ML110190451	List: IR 05000387/2012301; ML110870684; ML120100426; ML12017A153; ML12017A155; ML12017A164; ML12017A168; ML12017A172; ML12054A149; ML12054A190; ML12054A193; ML12054A204; ML12054A208;
References
	TAC U01842
	Download: ML12054A208 (376)
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ES-301 Administrative Topics Outline Form ES-301-1 Facility: SSES Date of Examination:

Examination Level: SRO-I Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Heat up rate calculation Conduct of Operations N,R General KIA 2.1.25 R03.9 SR04.2

A-l.l M,R Review failed ST and determine required action Conduct of Operations General KIA - 2.2.12 RO 3.7 SRO 4.1

A-1.2 N,R Blocking and tagging a pump Equipment Control General KIA - 2.2.41 RO 3.5 SRO 3.9

A-2 M,R Review and approve a radioactive liquid release permit Radiation Control General KIA - 2.3.6 SRO 3.7 A-3 N,R Make EAL classification Emergency Procedures/Plan General KIA - 2.4.44 SRO 4.4

A-4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

{P)revious 2 exams ($; 1; randomly selected)

Not" Admin JPM, A- 1.1, A-1.2, A-21!iL~ l.-::'mmon J PM, for both R0 and SRO candidat es, Enm, administration of ~h~.~~om.,on JPMs occurs for all candidates during the same exam day for each of thes~

i JPMs. ~ ~ kf.1~ ~ /i..o J,l.O ~~/..J Tf!.IU ~-bJ. SiMI Lt4L / Jk StU} ~

--rJ24 fol#J !flO .~s'6rfl~S~_( 1//0;1"2....

Administrative Topics Outline Form ES-301-1 Facility: SSES Date of Examination:

Examination Level: RO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Heat Up rate Calculation Conduct of Operations N,R General KIA - 2.1.25 RO 3.9 SR04.2

A-Ll M,R Review failed ST and determine required action Conduct of Operations General KlA-2.2.12 RO 3.7 SRO 4.1

A-1.2 N,R Blocking and tagging a pump Equipment Control General KIA - 2.2.41 RO 3.5 SRO 3.9

A-2 Radiation Control N,S State and local notifications Emergency Procedures/Plan General KIA - 2.4.39 RO 3.9

A-4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator. or Class(R)oom

{D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes)

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

(P)revious 2 exams (~ 1; randomly selected)

~feIO(I'!.-

Note: Admin JPMs A-1.t, A-t.2, A-2 and - a e common JPMs for both RO and SRO candidates. Ensure administration of these common JPMs occurs for all candidates during the same exam day for each of these JP.:\1s.

Susquehanna Steam Electric Station Job Performance Measure Review pressure/temperature plots and determine compliance with TS 3.4.10 RO JPM Designation: A-1.1 Revision Number: 1 Date: 10/24/11 Developed By: Lall~ 06/20/11 Author Date Review By: Hedigan 01/05/12 Examiner Date Approved By: Caruso 01/05/12 Chief Examiner Date

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by Examiner review.

"7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date - - - - - -

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

REVISION RECORD (Summary):

Rev 0 Rev 1: Edited data tables and made cue more specific JPM Setup Instructions:

1. Provide SO-1 00-011, "Reactor Temperature And Pressure Monitoring", marked up through step 5.1.5 TASK STANDARD:

Review the data for a plant heatup, determine that 100°F LlT was exceeded between 1930-2030.

TASK CONDITIONS:

1. Unit 1 is in MODE 2

2. A reactor startup/heatup is in progress

3. SO-100-011, "Reactor Temperature And Pressure Monitoring", is being conducted RO INITIATING CUE:

Perform a review of the data recorded in SO-1 00-011 for 1800 through 2345 to confirm procedural compliance and document discrepancies found, if any.

Information for Evaluator's Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the "Comment Number" column. Then annotate that comment in the "Comments" section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

0 NLO RO [J SRO STA SRO Cert JPM

Title:

R,eview pressure/temperature plots and determine compliance with TS 3.4.10 JPM Number: A-1.1 Revision Number: 0 KIA Number and Importance: 2.1.25 RO 3.9 SRO 4.2 Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Perform in Classroom Alternate Path: No Time Critical: No Estimated Time to Complete: 25 min. Actual Time Used: - - - 'minutes

References:

1. NUREG 1123, Rev. 2 Supp. 1

2. SO-1 00-011, Rev. 17

3. SSES Unit 1 TS 3.4.10 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? 0 Yes 0 No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory Unsatisfactory Comments:

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ (Print)

Evaluator's Signature: Date: -----

==

Description:==

This JPM has the operator review surveillance data for temperature/pressure plots recorded during a reactor startup/heatup to determine procedural compliance with all heatup rates.

NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number EVALUATOR NOTE:

This JPM can be performed in the simulator, classroom or other similar environment.

Ensure 50-100-011, Unit 1 Tech Specs, and a calculator are available for I candidate use.

Ensure the answer key, which precedes the Cue Sheet page in the JPM package, are NOT given to the student.

EVALUATOR CUE:

Provide the candidate with the task I conditions, initiating cue, and the two pre-filled out SO-1 00-011 Attachment D pages 20 of 21 for the 1800 to 2045 and 2100 to 2345 times (last two pages of this JPM package)

Inform the candidate that they should assume all data entries are handwritten.

Obtain and review SO-100-011 Obtain and review surveillance procedure.

~~~

ELEMENT STANDARD SAT UNSAT Comment Number (Step 5.1.5) Verify temperature change Verify heatup rate calculations for calculations each 15 minute and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period I I

during which the heatup was conducted.

~

(Step 5.1.5) Confirm calculated Confirm compliance with:<100°F heatup rates comply with Tech Spec heatup in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period and procedure requirements Determine Steam Dome heatup rate between 1930 and 2030 exceeds 100°F/hr, actual

.6.T=103°F Determine Steam Dome heatup rate between 1945 and 2045 exceeds 100°F/hr, actual I .6.T=104°F I -- - ..... - .... - ..... - .... ~

-.- ............... -- .......... ~

ELEMENT STANDARD SAT UNSAT Comment Number Additional calculational and 15 minute Additionally, candidate should heatup rate excursions identify:

1. I Evaluator Note: 1815-1830: Steam dome TS Required Actions should only be temperature calculational entered if Rx Steam Dome Temperature error (actual L\T=17)

L\T's are> 100°F in anyone hour. 2.

However, ALL L\T's should be 1945-2045 Recirc Loop A maintained <25° in any 15 minute HUR >100°F (actual period during heatup L\T=100.6); TS entry only required on steam dome L\T 3.

2045-Recirc loop A L\T=27 4.

2030-Recirc loop B L\T=27 5.

2000-Bottom head drain L\T=28 6.

1945-2000: Bottom head drain calculational error (actual L\T=28)

SR 3.4.10 violation Applicant notifies evaluator that SR 3.4.10 and TS 3.4.10 are applicable EVALUATOR CUE: for HUR >1 OO°F/hr Roleplay as unit supervisor and acknowledge applicant report. If applicant does not identify any TS violation, ask them if there are any TS concerns.

I -_ ..... __ .......

ELEMENT STANDARD SAT UNSAT Comment Number EVALUATOR CUE:

No further actions are required for this 14 JPM

~

I EVALUATOR:

Do you have ALL your JPM exam materials? Task Cue Sheets?

Procedures?

I 1--

JPM Stop Time _ _ _ __

NOTE Do not give the next page (Key) to the student!

They are given the cue sheet and the last two pages of the JPM package, which are marked "Student's Copy" Page 1 of 2 and 2 of 2).

ANSWER KEY Attachment D 50-100-011 Revision 17 Page 20 of 21 TABLE 1 TABLE 2

~REACTOR PRESSURE VESSEL METAL I REACTOR COOLANT SYSTEM TEMPERATURE AND PRESSURE LOG TEMPERATURE LOG All RPV Metal Temperature Data shall be recorded until All Rx Coolant Temp and Press Data shall be recorded until Heatup, Cooldown or Inservice Leak and Hydrostatic testing is Heatup, Cooldown or Inservice Leak and Hydrostatic complete. TS Required Actions should only be entered if Rx Steam Dome Temperature tlT's are> 100°F in anyone hour.

Testing (ISLHT) is complete, until both temps> 200°F However, ALL tlT's should be maintained <25 0 in any 15 minute period during heatup or cooldown, and::; 5° in any 15 minute heating up or start when either temp < 200°F cooling down. Maintain the lowest recorded temperature to the period during system hydrotest.

right of:

Curve A for ISLHT Curve B for Operation Mode 4 and coolant S 100°F Curve C for Critical Operation AS IME/DATE Temp Recorder Point #5 Temp Recorder Point#11 CONFIRM I VSLWALLBY VSL BOTTOM COMPLIANCE I 'rIME/DATE CIRCLEDAIA pOURCE WHERE

~PPLICABLE

=1Sf PI-C32-1 R605 TR-B31-1 R650 NA REACTOR RECIRC OOPA RECIRCLOOP PELTA

(

~1R650 TO NRT53 NRT54 NA RECIRC LOOPB

(~

R-B21-1 ROO6 NA BTMHD DRAIN RECIRCLOOP DELTA !30TTOM HEAD DELTA

~ NA RXSTM DOME CONFIRM RXSTM DOME DELTA COMPLIANCE PRESSURE NECESSARY FLANGE HEAD WISR 3.4.10.1 AS NECESSARY PSIG ATEMP OF TEMP OF ~ TEMP OF ~EMP OF DRAIN TEMP OF ITEMpoF EMpoF EMpoF W/SR 3.4.10.1 1700 TO/DNY 207 208 ffff{ ! 1800 TO/DAlY 83 293.9 N/A 294.4 N/A 291 N/A 301 N/A dSd 1815 TO/DAlY 111 313.9 20.0 317.7 23.3 315 24 321 20 dse 1830 TO/DAlY 134 329.5 15.6 334.8 17.1 331 16 338 16 CtC 1845 TO/DAlY 162 345.5 16.0 348.9 14.1 344 13 356 18 CtC 1900 TO/DAlY 184 362.6 17.1 364.4 15.5 361 17 371 15 cse 1915 TO/DAlY 237 379.5 16.9 384.6 20.2 382 21 387 16 cac 1930 TO/DAlY 287 401.3 21.8 402.1 17.5 400 18 404 17 csc 1945 TO/DAlY 321 421.5 20.2 425.2 23.1 421 21 428 24 cae 2000 TO/DAlY 466 448.8 27.3 449.4 24.2 449 28 456 28 cse 2015 TO/DAlY 603 471.9 23.1 472.6 23.2 471 22 481 25 CSC 2030 TO/DAlY 738 495.1 23.2 497.6 25.0 498 27 507 26 CSC 2045 TO/DNY 885 522.1 27.0 522.9 25.3 521 23 532 25 csc Shiftly Review and Confirmation above recorded data is acc';urate, compliant, and complete. Actual Steam Dome t.T from 1930-2030 was 103°F, and 1945-2045 was 104°F; this exceeds the TS limit of $; 100°F/hr.

SHIFT SUPERVISION DATE TIME Other t.Ts highlighted should be noted, and although 100 0 6Twas exceeded between 1945 and 2045 on recire loop A, only steam dome 6T is applicable for TS entry

TASK CONDITIONS

1. Unit 1 is in MODE 2.

2. A reactor startup/heatup is in progress.

3.80-100-011, "Reactor Temperature and Pressure Monitoring", is being conducted.

INITIATING CUE Perform a review of the data recorded in SO-1 00-011 for 1800 through 2345 to confirm procedural compliance and document discrepancies found, if any.

TASK CONDITIONS

1. Unit 1 is in MODE 2.

2. A reactor startup/heatup is in progress.

3. SO-1 00-011, "Reactor Temperature and Pressure Monitoring", is being conducted.

INITIATING CUE Perform a review of the data recorded in SO-1 00-011 for 1800 through 2345 to confirm procedural compliance and document discrepancies found, if any.

Attachment 0 80-100-011 FOR TRAINING ONLY (STUDENT'S COPY Page 1 of 2) Revision17 Page 20 of 21 TABLE 1 TABLE 2 IREACTOR PRESSURE VESSEL METAL REACTOR COOLANT SYSTEM TEMPERATURE AND PRESSURE LOG I TEMPERATURE LOG IAII RPV Metal Temperature Data shall be recorded until IAII Rx Coolant Temp and Press Data shall be recorded until Heatup, Cooldown or Inservice Leak and Hydrostatic testing is Heatup. Cooldown or Inservice Leak and Hydrostatic complete. TS Required Actions should only be entered if Rx Steam Dome Temperature AT's are> 100°F in anyone hour.

h"esting (ISLHT) is complete, until both temps> 200°F However, ALL AT's should be maintained <25 0 in any 15 minute period during heatup or cooldown, and:::; 50 in any 15 minute heating up or start when either temp < 200°F cooling

~own. Maintain the lowest recorded temperature to the period during system hydrotest.

right of:

Curve A for ISLHT Curve B for Operation Mode 4 and coolant s; 1DO°F

!curve C for Critical Operation

= ~

CIRCLE DATA PI-C32-1 R605 TR-B31-1 R650 NA =lR650 NA [TR-B2H ROO6 NA NA Temp Recorder Point #5 Temp Recorder Point #11 SOURCE WHERE APPLICABLE e FPO [ 5 RECIRC TO NRT53 NRT54 RECIRC

(~

BTMHD RXSTM IrIMEIDATE CONFIRM REACTOR LOOPA LOOPB DRAIN DOME CONFIRM lAs VSLWALLBY VSLBOnOM COMPLIANCE IME/DATE PRESSURE RECIRCLOOP DELTA RECIRCLOOP DELTA BonOMHEAD DELTA RXSTM DOME DELTA COMPLIANCE NECESSARY FLANGE HEAD W/SR3A10.1 AS NECESSARY PSIG ~ TEMP of ITEMpoF B TEMP OF EMpoF DRAIN TEMP OF EMpoF [rEMpoF !rEMpoF W/SR 3.4.10.1 I 1700 TO/DAlY 207 208 d'd'{ 1800 TO/DAlY 83 293.9 N/A 294.4 N/A 291 N/A 301 N/A ctc 1815 TO/DAlY 111 313.9 20.0 317.7 23.3 315 24 321 20 Ctc 1830 TO/DNY 134 329.5 15.6 334.8 17.1 331 16 338 16 C8C 1845 TO/DNY 162 345.5 16.0 348.9 14.1 344 13 356 18 CtC 1900 TO/DNY 184 362.6 17.1 364.4 15.5 361 17 371 15 CtC !

I 1915 TO/DAlY 237 379.5 16.9 384.6 20.2 382 21 387 16 C8C 1930 TO/DAlY 287 401.3 21.8 402.1 17.5 400 18 404 17 CEC 1945 TO/DNY 321 421.5 20.2 425.2 23.1 421 21 428 24 C8C I

2000 TO/DNY 466 448.8 27.3 449.4 24.2 449 24 456 28 Ctc 2015 TO/DNY 603 471.9 23.1 472.6 23.2 471 22 481 25 ctc .

2030 TO/DNY 738 495.1 23.2 497.6 25.0 498 27 507 26 ctc 2045 TO/DAlY 885 522.1 27.0 522.9 25.3 521 23 532 25 C8C I Shiftly Review and Confirmation above recorded data is accurate, compliant, and complete.

SHIFT SUPERVISION DATE TIME

Attachment 0 80-100-011 FOR TRAINING ONLY (STUDENT'S COPY Page 2 of 2) Revision17 Page 20 of 21 TABLE 1 TABLE 2 REACTOR PRESSURE VESSEL METAL I ,--- REACTOR COOLANT SYSTEM TEMPERATURE AND PRESSURE LOG TEMPERATURE LOG All RPV Metal Temperature Data shall be recorded until All Rx Coolant Temp and Press Data shall be recorded until Heatup, Cool down or Inservice Leak and Hydrostatic testing is Heatup, Cool down or Inservice Leak and Hydrostatic complete. TS Required Actions should only be entered if Rx Steam Dome Temperature l,1's are> 10QoF in anyone hour.

Testing (ISLHT) is complete, until both temps> 200°F However, ALL l,1's should be maintained <25 0 in any 15 minute period during heatup or cooldown, and :s; 5° in any 15 minute heating up or start when either temp < 200°F cooling period during system hydrotest.

down, Maintain the lowest recorded temperature to the right of:

Curve A for ISLHT Curve B for Operation Mode 4 and coolant:; 100°F Curve C for Critical Operation

=

I r-.;IRCLE DATA PI-C32-1 R605 !fR.B31-1 R650 NA ~1R650 NA R-B2HROO6 NA ~ NA Temp ~OURCE WHERE I

(~

Temp TO Recorder Point #5 Recorder Point#11 I iApPLlCABLE

~ FP03 I RT5 N :.J NRT53 NRT54 RECIRC RECIRC BTMHD RXSTM TIME/DATE CONFIRM REACTOR LOOP A LOOPS DRAIN DOME CONFIRM AS VSLWALLBY VSLBOnOM COMPLIANCE ~IMEIDATE PRESSURE RECIRCLOOP DELTA RECIRCLOOP DELTA BonOMHEAD DELTA RXSTM DOME DELTA COMPLIANCE NECESSARY FLANGE HEAD W/SR 3.4.10.1 la,s NECESSARY PSIG ~ TEMP OF [rEMP'F B TEMP OF iTEMP OF DRAIN TEMP OF iTEMP 'F EMpoF EMP'F W/SR 3.4.10.1 2100 TO/DAlY 890 522.4 0.3 524.5 1.6 523 2 532 0 (jlJ(j 2115 TO/DAlY 894 523.6 1.2 526.8 2.3 524 1 533 1 (jlJ(j 2130 TO/DAlY 908 524.7 1.1 529.9 3.1 524 0 534 1 (jlJ(j 2145 TO/DAlY 917 525.9 1.2 533.6 3.7 525 1 536 2 (jlJ(j 2200 TO/DAlY 918 526.0 0.1 533.7 0.1 526 1 536 0 PEf" I

2215 TO/DAlY 925 527.1 1.1 537.1 3.4 528 2 537 1 PEr 2230 TO/DAlY 928 527.4 0.3 537.2 0.1 528 0 537 0 tJEf" ,

2245 TO/DAlY 930 530.4 3.0 537.4 0.2 530 2 538 1 PEr I 2300 TO/DAlY 934 532.7 2.3 537.6 0.2 531 1 538 0 PEr 2315 TO/DAlY 945 533.4 0.7 537.9 0.3 533 2 538 0 tJEf" 2330 TO/DAlY 955 533.7 0.3 538.1 0.2 533 0 540 2 PEr 2345 TO/DAlY 957 533.8 0.1 538.2 0.1 533 0 541 1 tJEf" Shiftly Review and Confirmation above recorded data is accurate, compliant, and complete.

SHIFT SUPERVISION DATE TIME

Susquehanna Steam Electric Station Job Performance Measure Review pressure/temperature plots and determine compliance with TS 3.4.10 SRO JPM Designation: A-1.1 Revision Number: 1 Date: 10/24/11 De!veloped By: lall~ 06/20/11 Author Date Review By: Hedigan 01/05/12 Examiner Date Approved By: Caruso 01/05/12 Chief Examiner Date

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below.

'1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by Examiner review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. ___ Date _ _ _ _ __

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

1'1. When JPM is revalidated, Examiner sign and date JPM cover page.

REVISION RECORD (Summary):

Rev 0 Rev 1: edited data tables and made cue more specific JPM Setup Instructions:

1. Provide 80-100-011, "Reactor Temperature And Pressure Monitoring" marked up through step 5.1.5 TASK STANDARD:

Review the data for a plant heatup, determine that 100°F AT was exceeded between 1930-2030 and determine T8 3.4.10 actions A.1 and A.2 are applicable.

TASK CONDITIONS:

1. Unit 1 is in MODE 2

2. A reactor startup/heatup is in progress

3. 80-100-011, "Reactor Temperature And Pressure Monitoring", is being conducted

4. The shiftly review of the 80-100-011 data is required SRO INITIATING CUE:

Perform a review of the data recorded in 80-100-011 for 1800 through 2345 to confirm procedural compliance and document discrepancies found, if any. Additionally, determine what actions are required, if any.

Information for Evaluator's Use:

UN8AT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the "Comment Number" column. Then annotate that comment in the "Comments" section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

80me operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

NLO RO SRO STA SRO Cert JPM

Title:

Review pressure/temperature plots and determine compliance with TS 3.4.10 JPM Number: A-1.1 Revision Number: 0 KIA Number and Importance: 2.1.25 RO 3.9 SRO 4.2 Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Perform in Classroom Alternate Path: No Time Critical: No Estimated Time to Complete: 25 min. Actual Time Used: _ _ _minutes

References:

1. NUREG 1123, Rev. 2 Supp. 1

2. SO-100-011, Rev. 17

3. SSES Unit 1 TS 3.4.10 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? Yes No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this ~IPM, and has been determined to be: 0 Satisfactory Unsatisfactory Comments:

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

==

Description:==

This JPM has the operator review surveillance data for temperature/pressure plots recorded during a reactor startup/heatup to determine procedural compliance with all heatup rates and determine required T8 actions.

NOTE: Critical Element( s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

-.- .......... -- ... --~-.,...-

I ELEMENT STANDARD SAT . UNSAT! Comment L EVALUATOR NOTE:

I Number This JPM can be performed in the simulator, classroom or other similar environment.

Ensure 80-100-011, Unit 1 Tech Specs, and a calculator are available for candidate use.

I Ensure the answer key, which precedes the Cue Sheet page in the I JPM package, are NOT given to the

, student.

EVALUATOR CUE:

Provide the candidate with the task conditions, initiating cue, and the two pre-filled out 80-100-011 Attachment D pages 20 of 21 for the 1800 to 2045 and 2100 to 2345 times (last two pages of I this JPM package)

Inform the candidate that they should assume all data entries are handwritten Obtain and review SO-100-011 Obtain and review surveillance procedure.

L -...... ~ .... _ .... _ _

- - ...... - .... ~ ... - ... -- _._ ....... _._ ... - --

ELEMENT STANDARD SAT UNSAT Comment Number (Step 5.1.5) Verify temperature change Verify heatup rate calculations for calculations each 15 minute and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period I during which the heatup was conducted.

(Step 5.1.5) Confirm calculated Confirm compliance with:<1 OO°F heatup rates comply with Tech Spec heatup in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period and procedure requirements Determine Steam Dome heatup rate between 1930 and 2030 exceeds 100°F/hr, actual

.1.T=103°F I Determine Steam Dome heatup rate between 1945 and 2045 Iexceeds 100°F/hr, actual

.1.T=104°F

ELEMENT STANDARD SAT UNSAT Comment Number Additional calculational and 15 minute Additionally, candidate should heatup rate excursions identify:

1.

Evaluator Note: 1815-1830: Steam dome TS Required Actions should only be temperature calculational I entered if Rx Steam Dome Temperature error (actuaI8T=17)

A1's are> 100°F in anyone hour. 2.

However, ALL 81'5 should be 1945-2045 Recirc Loop A maintained <25 0 in any 15 minute HUR >100°F (actual period during heatup 8T=100.6) ; TS entry only required on steam dome AT 3.

2045-Recirc loop A AT=27 4.

2030-Recirc loop B AT=27 5.

2000-Bottom head drain 8T=28 6.

1945-2000: Bottom head drain calculational error (actual AT=28)

- . - ......... - - ...... ~.- .... -- .... ~

ELEMENT STANDARD SAT UNSAT Comment Number

(Step 5.1.6) Refer to and evaluate Refer to Tech Spec 3.4.10 and compliance with Tech Spec 3.4.10 determine:

II I

EVALUATOR CUE: LCO 3.4.10 NOT met: I !

When asked provide copy of TS 3.4.10

- Exceeded SR 3.4.1 0.1.b:

100°F/Hr Condition A is applicable

Action A.1, Restore CDR within limits within 30 minutes I I II I

- Action A.2, Determine RCS is acceptable for continued operation within 72 hours3 days 0.429 weeks 0.0986 months .

Verify current heatup rate complies Applicant states that action for A.1 is with tech spec limits complete, current heatup rate is less than 100°F/Hr. i Applicant states that analysis is required by engineering within 72 hours3 days 0.429 weeks 0.0986 months to comply with action A.2 Initiate LCOITRO tracking record in Candidate states need to enter LCO SOMs LCO module into SOMs tracking software.

EVALUATOR CUE:

No further actions are required for this JPM

ELEMENT STANDARD SAT UNSAT' Comment Number EVALUATOR:

Do you have ALL your JPM exam I materials? Task Cue Sheets? I Procedures? I I

I I

J I

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

I I I JPM Stop Time _ _ _ __

NOTE Do not give the next page (Key) to the student!

They are given the cue sheet and the last two pages of the JPM package, which are marked "Student's Copy" Page 1 of 2 and 2 of 2).

ANSWER KEY Attachment D SO-100-011 Revision 17 Page 20 of 21 TABLE 1 TABLE 2 REACTOR PRESSURE VESSEL METAL REACTOR COOLANT SYSTEM TEMPERATURE AND PRESSURE LOG TEMPERATURE LOG iAll RPV Metal Temperature Data shall be recorded until fAil Rx Coolant Temp and Press Data shall be recorded until Heatup, Cooldown or Inservice Leak and Hydrostatic testing is Heatup, Cooldown or Inservice Leak and Hydrostatic complete. TS Required Actions should only be entered if Rx Steam Dome Temperature AT's are> 100°F in anyone hour.

~esting (ISLHT) is complete, until both temps> 200°F However, ALL AT's should be maintained <25 0 in any 15 minute period during heatup or cooldown, and $ 5° in any 15 minute heating up or start when either temp < 200°F cooling

~own. Maintain the lowest recorded temperature to the period during system hydrotest.

right of:

Curve A for ISLHT Curve B for Operation Mode 4 and coolant ~ 100°F

!curve C for Critical Operation

=

CIRCLE DATA PI-C32-1 R605 I R-B31-1R650 NA ~.1R650 NA R-B21-1 ROO6 NA ~ NA Temp Temp SOURCE WHERE

~

Recorder Point #5 Recorder Point#11 APPLICABLE If RECIRC NRT53 NRT54 RECIRC

(~

BTMHD RXSTM tnMEIDATE CONFIRM REACTOR lOOP A LOOPB DRAIN DOME CONFIRM

~S VSL WALL BY VSL BOTTOM COMPLIANCE IMEIDATE PRESSURE RECIRC LOOP DELTA RECIRCLOOP PELTA BonOMHEAD DELTA RXSTM DOME DELTA !cOMPLIANCE NECESSARY FLANGE HEAD WISR3.4.10.1 AS NECESSARY PSIG v\ TEMP OF h"EMpoF a TEMP OF trEMpOF DRAIN TEMP OF EMpOF TEMP OF h"EMpoF iwlSR 3.4.10.1 1700 207 208 55(

jrOfDAIY 1800 TO/DAlY 83 293.9 N/A 294.4 N/A 291 N/A 301 N/A cac 1815 TO/DAlY 111 313.9 20.0 317.7 23.3 315 24 321 20 cat 1830 TO/DAlY 134 329.5 15.6 334.8 17.1 331 16 338 16 tac 1845 TO/DAlY 162 345.5 16.0 348.9 14.1 344 13 356 18 cac 1900 TO/DAlY 184 362.6 17.1 364.4 15.5 361 17 371 15 cat 1915 TO/DAlY 237 379.5 16.9 384.6 20.2 382 21 387 16 etc 1930 TO/DAlY 287 401.3 21.8 402.1 17.5 400 18 404 17 cae 1945 TO/DAlY 321 421.5 20.2 425.2 23.1 421 21 428 24 tat 2000 TO/DAlY 466 448.8 27.3 449.4 24.2 449 28 456 28 tac 2015 TO/DAlY 603 471.9 23.1 472.6 23.2 471 22 481 25 tat 2030 TO/DAlY 738 495.1 23.2 497.6 25.0 498 27 507 26 ctJe 2045 TO/DAlY 885 522.1 27.0 522.9 25.3 521 23 532 25 cat Shiftly Review and Confirmation above recorded data is ao;urate, compliant, and complete. Actual Steam Dome,3.T from 1930-2030 was 103°F, and 1945-2045 was 104°F; this exceeds the TS limit of:s; 100°F/hr.

SHIFT SUPERVISION DATE TIME Other ,3.Ts highlighted should be noted, and although 100°,3.Twas exceeded between 1945 and 2045 on recirc loop A, only steam dome AT is applicable

TASK CONDITIONS

1. Unit 1 is in MODE 2.

2. A reactor startup/heatup is in progress.

3. SO-1 00-011, "Reactor Temperature and Pressure Monitoring", is being conducted.

4. The shiftly review of the SO-1 00-011 data is required INITIATING CUE Perform a review of the data recorded in 80-100-011 for 1800 through 2345 to confirm procedural compliance and document discrepancies found, if any.

Additionally, determine what actions are required, if any

TASK CONDITIONS

1. Unit 1 is in MODE 2.

2. A reactor startup/heatup is in progress.

3. SO-'100-011, "Reactor Temperature and Pressure Monitoring", is being conducted.

4. The shiftly review of the SO-1 00-011 data is required INITIATING CUE Perform a review of the data recorded in SO-1 00-011 for 1800 through 2345 to confirm procedural compliance and document discrepancies found. if any.

Additionally, determine what actions are required, if any.

Attachment 0 SO-100-011 FOR TRAINING ONLY (STUDENT'S COPY Page 1 of 2) Revision17 Page 20 of 21 TABLE 1 TABLE 2 REACTOR PRESSURE VESSEL METAL REACTOR COOLANT SYSTEM TEMPERATURE AND PRESSURE LOG TEMPERATURE LOG iAll RPV Metal Temperature Data shall be recorded until All Rx Coolant Temp and Press Data shall be recorded until Heatup, Cooldown or Inservice Leak and Hydrostatic testing is Heatup, Cooldown or Inservice Leak and Hydrostatic r.omplete. TS Required Actions should only be entered if Rx Steam Dome Temperature ~1'8 are> 100°F in anyone hour.

iTesting (ISLHT) is complete, until both temps> 200°F However, ALL ~1'8 should be maintained <25 0 in any 15 minute period during heatup or cooldown. and :s; 5° in any 15 minute heating up or start when either temp < 200°F cooling period during system hydrotest.

~own. Maintain the lowest recorded temperature to the right of:

iCurve A for ISLHT Curve B for Operation Mode 4 and coolant :s;100°F iCurve C for Critical Operation CIRCLE DATA PI-C32*1R605 rrR*B31-1 R650 NA ~-1R650 NA rrR-S21-1 ROD6 NA ~ NA

(~

Temp Temp I

'm SOURCE WHERE TO Recorder Point #5 Recorder Point #11 APPLICABLE ~ FPO NRT53 NRT54 I RECIRC RECIRC BTMHD RXSTM i IrIME/DATE CONFIRM REACTOR LOOP A LOOPB DRAIN DOME CONFIRM lAS VSLWALLBY VSLBOTTOM COMPLIANCE IME/DATE PRESSURE RECIRCLOOP DELTA RECIRC LOOP DELTA BOTTOM HEAD DELTA RXSTM DOME DELTA COMPLIANCE NECESSARY FLANGE HEAD W/SR3.4.10.1 AS NECESSARY PSIG 'A TEMP OF EMpcF B TEMP of TEMpcF DRAIN TEMP OF EMpoF IrEMpcF IrEMP'F iw/SR 3.4.10.1 1700 207 208 .J'.J'f 1800 TO/DAlY 83 293.9 N/A 294.4 N/A 291 N/A 301 N/A cec irO/DAIY 1815 TO/DAlY 111 313.9 20.0 317.7 23.3 315 24 321 20 cec 1830 TO/DNY 134 329.5 15.6 334.8 17.1 331 16 338 16 cec 1845 TO/DAlY 162 345.5 16.0 348.9 14.1 344 13 356 18 cec 1900 TO/DAlY 184 362.6 17.1 364.4 15.5 361 17 371 15 cec 1915 TO/DAlY 237 379.5 16.9 384.6 20.2 382 21 387 16 tee 1930 TO/DAlY 287 401.3 21.8 402.1 17.5 400 18 404 17 cec 1945 TO/DAlY 321 421.5 20.2 425.2 23.1 421 21 428 24 cec 2000 TO/DAlY 466 448.8 27.3 449.4 24.2 449 24 456 28 cec 2015 TO/DAlY 603 471.9 23.1 472.6 23.2 471 22 481 25 tet 2030 TO/DAlY 738 495.1 23.2 497.6 25.0 498 27 507 26 Cet 2045 TO/DAlY 885 522.1 27.0 522.9 25.3 521 23 532 25 tec Shiftly Review and Confirmation above recorded data is accurate, compliant, and complete.

SHIFT SUPERVISION DATE TIME

Attachment 0 80-100-011 FOR TRAINING ONLY (STUDENT'S COPY Page 2 of 2) Revision17 Page 20 of 21 TABLE 1 TABLE 2 REACTOR PRESSURE VESSEL METAL TEMPERATURE LOG I REACTOR COOLANT SYSTEM TEMPERATURE AND PRESSURE LOG

~II RPV Metal Temperature Data shall be recorded until ~II Rx Coolant Temp and Press Data shall be recorded until Heatup, Cooldown or Inservice Leak and HydrostatiC testing is Heatup, Cooldown or Inservice Leak and Hydrostatic ~omplete. TS Required Actions should only be entered if Rx Steam Dome Temperature LlT's are> 100°F in anyone hour.

Testing (ISLHT) is complete, until both temps> 200°F However, ALL LlT'S should be maintained <25° in any 15 minute period during heatup or cooldown, and:;; 5° in any 15 minute heating up or start wilen either temp < 200°F cooling

\:lawn. Maintain the lowest recorded temperature to the period during system hydrotest.

right of:

Curve A for ISLHT Curve B for Operation Mode 4 and coolant $; 10QoF

~urve C for Critical Operation

=

CIRCLE DATA PI-C32-1 R605 TR-B31-1 R650 NA ~-1R650 iNA [TR-B21-1 ROO6 NA

~ NA

(~

Temp Temp

~

pOURCE WHERE Recorder Recorder ~PPUCABlE FPO I RT5 NRT53 Point #5 Point #11 N NRT54 RECIRC RECIRC BTMHD RXSTM IME/DATE CONFIRM REACTOR LOOP A LOOPB DRAIN DOME CONFIRM f..S VSLWALLBY VSLBOTTOM COMPLIANCE IMEIDATE PRESSURE RECIRC LOOP DELTA RECIRC LOOP DELTA BOTTOM HEAD DELTA RXSTM DOME DELTA COMPLIANCE NECESSARY FLANGE HEAD W/SR 3.4.10.1 ~S NECESSARY PSIG ATEMP OF EMPQF B TEMP OF irEMP OF DRAIN TEMP OF IEMpoF irEMpoF rrEMpoF W/SR 3.4.10.1 2100 TO/DAlY 890 522.4 0.3 524.5 1.6 523 2 532 0 (}8(}

2115 TO/DAlY 894 523.6 1.2 526.8 2.3 524 1 533 1 (}8(}

2130 TO/DAlY 908 524.7 1.1 529.9 3.1 524 0 534 1 (}8(}

2145 TO/DAlY 917 525.9 1.2 533.6 3.7 525 1 536 2 C8C 2200 TO/DAlY 918 526.0 0.1 533.7 0.1 526 1 536 0 OEr 2215 TO/DAlY 925 527.1 1.1 537.1 3.4 528 2 537 1 OEr 2230 TO/DAlY 928 527.4 0.3 537.2 0.1 528 0 537 0 OEr 2245 TO/DAlY 930 530.4 3.0 537,4 0.2 530 2 538 1 OEF 2300 TO/DAlY 934 532.7 2.3 537.6 0.2 531 1 538 0 OEr 2315 TO/DAlY 945 533.4 0.7 537.9 0.3 533 2 538 0 OEr 2330 TO/DAlY 955 533.7 0.3 538.1 0.2 533 0 540 2 OEr 2345 957 533.8 0.1 538.2 0.1 533 0 541 1 OEF

_ ..... _TO/DAlY Shiftly Review and Confirmation above recorded data is accurate, compliant, and complete.

SHIFT SUPERVISION DATE TIME

Susquehanna Steam Electric Station Job Performance Measure Review failed surveillance test and determine action JPM Designation: A-1.2 Revision Number: 3 Date: 12/17/11 Developed By: Patel 06/10/11 Author Date Review By: Hedigan 01/05/12 Examiner Date Approved By: Caruso 01/05/12 Chief Examiner Date

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by Examiner review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8" Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. ___ Date _ _ _ _ __

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

REVISION RECORD (Summary):

1. Rev 3 JPM Setup Instructions:

1. Provide marked-up surveillance SO-151-A02 with data up through step 5.2 checked off as completed with Attachment B filled out with independent verification signed off.

2. Provide marked-up surveillance Authorization Cover Sheet with Date and Time information as current time minus 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

TASK STANDARD:

Review the data for a completed surveillance, and declare the Core Spray loop A inoperable. Enter appropriate TS.

TASK CONDITIONS:

Unit 1 is at 100% power.

SO-151-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

RO INITIATING CUE:

Review the surveillance testing data for SO-151-A02. Complete Attachment A and document status below.

SRO INITIATING CUE:

Unit 1 was in a normal electrical line up, then B EDG was taken OOS unplanned due to part 21 issue related to agastat relay. Expected recovery time of B EDG is 8 hours0.333 days 0.0476 weeks 0.011 months .

Complete SO-151-A02, Quarterly Core Spray Flow Verification Division 1, Attachment A, to a point where all required actions have been identified. Document all required actions below on the cue sheet.

Information for Evaluator's Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the "Comment Number" column. Then annotate that comment in the "Comments" section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

NLO RO SRO STAD SRO Cert JPM

Title:

Emergency Plan communications JPM Number: A-2 Revision Number: 0 KIA Number and Importance: 2.2.12 RO 3.7 SRO 4.1 Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Perform in Classroom Alternate Path: No Time Critical: No Estimated Time to Complete: 15 min. Actual Time Used: - - -minutes

References:

1. NUREG 1123

2. SO-1S1-A02, Rev. 18.

EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? Yes No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

==

Description:==

This JPM has the operator review surveillance data for Core Spray pump A and determine its operability. The RO and SRO applicants will determine the pump to be inoperable. The RO will inform the SRO on the operability status. The SRO applicant will also determine that the Core Spray Pump to be inoperable and determine that TS 3.5.1 Action A.1 to Restore low pressure ECCS injection/spray subsystem to OPERABLE status within 7days applies. Also TS 3.8.1 Action B.2 to declare Core Spray Pump B INOPERABLE within 4 hours0.167 days 0.0238 weeks 0.00548 months of entering TS 3.5.1 Action A.1. SRO will further determine that TS 3.5.1 Action 1.1 applies when 5 hours0.208 days 0.0298 weeks 0.00685 months has been elapsed since declaring Core Spray Pump A INOPERABLE.

NRC SSES INITIAL EXAMINA TlON ~

'--------------~

JPM A-1.2 NOTE: Critical Element( s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time ELEMENT STANDARD SAT I UNSAT Comment I Number Evaluator Note

Provide marked-up surveillance SO 151-A02 with data up through step 5.2 checked off as completed with Attachment B filled out with independent verification signed off.

Provide marked-up surveillance Authorization Cover Sheet with Date and Time information as "TO/DAlY" and "Now - 1 hr."

Ensure that pump A discharge pressure is recorded as 262.5 psig (step 5.1.16b) and calculated delta-p value recorded in Attachment A acceptance criteria 7 is recorded as 264.5 psid.

Give the candidate a few minutes to read the Task Conditions/Cue Sheet.

I

1. Reviews As-Found Column data on Reviews data on SO-151-A02, Attachment 'A' Quarterly Core Spray Flow Verification Division 1.

Attachment A.

2. Identifies that there is a calculation Compares the calculated CS error for calculating CS pump A pump A delta-P of 264.5 psid delta-P. (Attachment A acceptance with the actual discharge criteria 7) pressure and suction pressure valves (262.5 psig - 8psig) and determines that there is a math error. The actual calculated value would be 254.5 psid, and determines this to be UNACCEPTABLE due to being outside the criteria of 256.5 and 313.5 psid.

NRC SSES INITIAL EXAMINA TION JPM A-1.2 ELEMENT STANDARD SAT UNSAT Comment I Number

3. Notifies Shift Supervision that SO lAW Attachment A. Under 151-A02 has failed its acceptance Required Action:

criteria.

Notifies Shift Supervision that Evaluator Not~ SO-151-A02 A CS pump failed This completes the JPM for the RO its acceptance criteria.

candidate.

AND Initials the Confirm space.

I Evaluator Note If JPM is being used for a SRO candidate, continue the JPM.

~~~.

4. Declares CS pump A inoperable. lAW Attachment A. Under Required Action:

Determines that the measured values of pump delta-P fall outside of their acceptance criteria, and the pump shall be Declared INOPERABLE.

AND Initials the Confirm space.

NRC SSES INITIAL EXAMINA TlON JPM A-1 2 ELEMENT STANDARD SAT UNSAT Comment I Number

5. Determines required TS action for Determines TS 3.5.1 Condition CS inoperability. A.1 applies.

One low pressure ECCS injection/spray subsystem inoperable for reasons other than Condition B (One LPCI pump in one or both LPCI subsystems inoperable)

Restore low pressure ECCS Evaluator Cue injection/spray subsystem to If necessary, ask SRO candidate to OPERABLE status within 7 report the required TS actions to you days.

(as the Shift Manager).

AND TS 3.8.1 Condition B.2 applies When one required DG is inoperable. Declare the required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable within 4 hours0.167 days 0.0238 weeks 0.00548 months from discovery of Condition B concurrent with inoperability of redundant required feature(s)

INOPERABLE,

~,-~-~-~-~~-~-~-~~-~------.~----. .~-~.~-.

NRC SSES INITIAL EXAMINA TlON JPMA-1.2 ELEMENT STANDARD SAT UNSAT Comment Number I

6. Identifies a LCOfTRO will be Identifies a LCOfTRO entry in entered in e30M3. e30M3 is required.

Evaluator Cue Inform the applicant that it will not be necessary make an e30M3 LCOITRO entry at this time.

Evaluator Note This completes the .JPM --- r--~-~-

7. Identifies TS 3.0.3 entrl!. Determines Condition I Action 1.1 is applicable and LCO entry Evaluator Cue 3.0.3 is required.

Inform the applicant that 5 hours0.208 days 0.0298 weeks 0.00685 months has been elapsed since TS 3.5.1 Action A 1 For Two Core Spray entry and there is no change in subsystems inoperable equipment operability status. 'E' EDG is unavailable for substitution.

Identify T3 required actions. TS 3.0.3 Identifies that actions need to be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place Unit 1 in Mode 4 within 37 hours1.542 days 0.22 weeks 0.0507 months .

JPM Stop Time

NRC SSES INITIAL EXAMINA TlON JPM A-1.2 HANDOUT PAGE FOR RO:

TASK CONDITIONS:

Unit 1 is at 100% power.

SO-151-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

INITIATING CUE:

Review the surveillance testing data for SO-151-A02. Complete Attachment A and document status below.

REQUIRED ACTIONS:

NRC SSES INITIAL EXAMINA TION J JPM A-1.2 HANDOUT PAGE FOR RO:

TASK CONDITIONS:

Unit 1 is at 100% power.

SO-151-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

INITIATING CUE:

Review the surveillance testing data for SO-151-A02. Complete Attachment A and document status below.

REQUIRED ACTIONS:

' - - -_ _ _ _ NRC_ SSES_ INITIAL_ _

EXAMINA TlON_ _ _ _I.------.J JPM A-1.2 HANDOUT PAGE FOR SRO:

TASK CONDITIONS:

Unit 1 is at 100% power.

SO-151-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

Unit 1 is in a normal electrical line up with B EDG taken OOS unplanned due to part 21 issue related to agastat relay. Expected recovery time of B EDG is 8 hours0.333 days 0.0476 weeks 0.011 months .

INITIATING CUE:

Complete SO-151-A02, Quarterly Core Spray Flow Verification Division 1, Attachment A, to a point where all required actions have been identified. Document all required actions below on the cue sheet.

REQUIRED ACTIONS:

NRC SSES INITIAL EXAMINA TION JPM A-1.2 HANDOUT PAGE FOR SRO:

TASK CONDITIONS:

Unit 1 is at 100% power.

SO-1S1-A02, Quarterly Core Spray Flow Verification Division 1, was performed and is ready for review.

Unit 1 was in a normal electrical line up, then B EDG was taken out of service unplanned due to part 21 issue related to agastat relay. Expected recovery time of B EDG is 8 hours0.333 days 0.0476 weeks 0.011 months .

INITIATING CUE:

Complete SO-1S1-A02, Quarterly Core Spray Flow Verification Division 1, Attachment A, to a point where all required actions have been identified. Document all required actions below on the cue sheet.

REQUIRED ACTIONS:

Susquehanna Steam Electric Station Job Performance Measure Determine Blocking Required per NDAP-QA-0322 "Energy Control Process" RO JPM Designation: A-2 Revision Number: 2 Date: 10/26/11 Developed By: La"~ 06/20/11 Author Date Review By: Hedigan 01/05/12 Examiner Date Approved By: Caruso 01/05/12 Chief Examiner Date

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST All steps of this checklist should be performed upon initial validation. Prior to JPM usage, INOTE: revalidate JPM using steps 8 through 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by Examiner review.

7. Critical steps meet the criteria for critical steps and are identified witl1 an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date - - - - -

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

REVISION RECORD (Summary):

Rev 0 Rev 1: Split JPM to separate RO and SRO actions. RO to provide proposed blocking, SRO to review and correct proposed blocking Rev 2: Edited per licensee comments to provide specific prints JPM Setup Instructions:

1. Provide NDAP-QA-0322

2. Provide prints E-145 sh. 8, E-4 sh. 3, and M-2109 sh. 1 and 2

3. Provide blank Proposed Blocking Sheet TASK STANDARD:

Provide a list of proposed blocking for 2A Service Water Pump lAW NDAP-QA-0322 lAW the attached Proposed Blocking List Key.

TASK CONDITIONS:

Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for impeller replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means RO INITIATING CUE:

Using the appropriate drawings, provide a list of proposed blocking that meets the requirements of NDAP-QA-0322.

The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service.

Minimum required information for each point must include: Component Number, Component Description, Required Position, and Tag Type Information for Evaluator's Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the "Comment Number" column. Then annotate that comment in the "Comments" section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

NLO RO SRO STA 0 SRO Cert JPM

Title:

Determine Blocking Required per NDAP-QA-0322 "Energy Control Process" JPM Number: A-2 Revision Number: 2 KIA Number and Importance: 2.2.41 RO 3.5 SRO 3.9 Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Perform in Classroom Alternate Path: No Time Critical: No Estimated Time to Complete: 20 min. Actual Time Used: - - -minutes

References:

1. NUREG 1123 Rev. 2, Supp. 1

2. NDAP-QA-0322 Rev. 35

3. E-145 sh. 8

4. E-4 sh. 3

5. M-2109 sh. 1,2 EVALUATION

SUMMARY

1 . Were all the Critical Elements performed satisfactorily? Yes 0 No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print}

Evaluator's Signature: Date: _ _ _ __

==

Description:==

This JPM has the operator determine blocking for the 2A Service Water Pump for a pump PM. The normal means of clearance development, eSoms, is unavailable. The applicant will provide proposed blocking lAW NDAP-QA-0322.

NOTE: Critical Element(s} indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number EVALUATOR NOTE

Ensure the following material is available to support performance of this JPM:

Prints: E-145 sh. 8, E-4 sh. 3, and M-2109 sh. 1 and 2

NDAP-QA-0322

Attached Proposed Blocking Sheet Reviews Attachment N for EVALUATOR NOTE General Equipment To begin this JPM, provide the Blocking Rules under candidate with the Task Conditions, Pumps (3) and Attachment Initiating Cue Sheet and Proposed o for Electrical Blocking Blocking Sheet. under 13.8kV breakers (2.1)

Reviews the scope of work planned Determines that motor for 2A SWP. needs blocked and should isolate all pump flowpaths to NDAP-QA-0322 is an information allow for work on pump.

use only procedure. Candidate should reference clearance Locates and uses standards (6.1) and attachments N & referenced drawings to o for general equipment blocking review blocking, Uses M-rules to develop proposed blocking 2109 Sheet 1/2, E-145 Sheet 8, and E-4 Sheet 3 to develop proposed blocking list.

I I ~ -

ELEMENT STANDARD SAT I UNSAT Comment Number EVALUATOR NOTE Candidate may at anytime reference NDAP-QA-0322 to ensure compliance and follow appropriate check sheets.

\--

Oevelops list of proposed blocking Proposed blocking list points based upon print review and generated matches NOAP-QA-0322 guidance attached proposed blocking list key, all critical steps met.

EVALUATOR CUE;.

Role play the Unit Supervisor and acknowledge the receipt of the proposed blocking points/corrected blocking and inform candidate that it will be forwarded to the WCC.

f--~--~--.-~-.-.

Give completed list of proposed Unit Supervisor is given the blocking points to the Unit list of proposed blocking Supervisor to be forwarded to WCC. points.

EVALUATOR CUE Once candidate turns in list of proposed blocking points, the JPM is complete.

DUE TO THE NATURE OF THIS JPM OTHER BLOCKING POINTS MAY BE ACCEPTABLE.

CONSULT WITH ADDITIONAL SMEs AS NECESSARY TO DETERMINE ACCEPTABILITY OF ALTERNATE BLOCKING POINTS.

ELEMENT STANDARD I SAT UNSAT Comment Number DO YOU HAVE ALL OF YOUR JPM EXAM MATERIALS?

JPM Stop Time _ _ __

NOTE Do NO give th next page (Key) to the student!

They are given the cue sheet and proposed blocking sheet

PROPOSED BL c I y o NOT GIVE I NOTE: Critical Element(s) indicated by

in Performance Checklist

[ Component Position Tag Type

~

1. *2A10106 Service Water Pump A 2P502A 13.8kV breaker *OPEN, *RACKED OUT, (applicant *Red tag may also request breaker REMOVED) I

~

2. *209001 Service Water Pump A Suction ISO VlV *CLOSED *Red tag

3. *209004 Service Water Puml2 A Discharge ISO VlV *CLOSED *Red tag

4. *209014 Service Wtr Pump A Seal Water Press CTl VlV Bypass *CLOSED *Red tag VlV

~. *209016 Service Wtr Pump A Seal Water Press CTl VLV Outlet *CLOSED I *Red tag ISO VlV I

6. *209166 Service Wtr Pump A Vent VlV *CLOSED 1 *Red tag I

7. *209801 Service Water Pump A 08 Casing Vent VlV *OPEN No tag/Pink tag

8. *209802 Service Water Pump A 18 Casing Vent VlV *OPEN No tag/Pink tag

19. *209048 Service Water Pump A Drain VLV *OPEN No tag/Pink tag 1Q._*_2Q9j19_Service_Water Pum~A I:?@il} VI..-Y_____________ *OPEN I No tag/Pink tag

TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for impeller replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means INITIATING CUE Using the appropriate drawings, provide a list of proposed blocking that meets the requirements of NDAP-QA-0322. The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service. Minimum required information for each point must include: Component Number, Component Description, Required Position, and Tag Type

TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for impeller replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means INITIATING CUE Using the appropriate drawings, provide a list of proposed blocking that meets the requirements of NDAP-QA-0322. The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service. Minimum required information for each point must include: Component Number, Component Description, Required Position, and Tag Type

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Library Clearance Order Susquehanna ##-### -2P502A SERVICE WATER PUMP o -Unit 2 SYS 2P502A SERVICE WATER PUMP A (PI' MOTOR MR N NOUN LOC TEXT:

RM:CW-020 A:52 E:676 R678.5 Clearance Order

Description:

SERVICE WATER PUMP 2P502A OOS FOR IMPELLER REPLACEMENT STANDARD CLEARANCE ORDER Notes:

1) OPERATIONS VENT AND DRAIN

2) Clearance order effectiveness determined by Live-Dead-Uve checks; no sustained pressure/flow exiting drains Opened within clearance order boundary Impacts I Effects:

LOSS OF CONTROL AND INDICATION FOR 2A SERVICE WATER PP 2P502A PMT: OPS-PLACE IN SERVICE lAW 01'-211-001 AND VERIFY PROPER OPERATION REF. E-145 SH. 8, E-4 SH. 3 ~{M-2109 SH. 1 Post Maintenance Testing Req.:

1'51'-29; PLACE SW PUMP 2PS02A liS lAW 01'-211-001 Wilkes, Barry Depressurized Continuously Vented

--T ---. ----

Purge Complete

~-

Tagged Tag Place Rest. Rest Tagged Restoration Tag Placement Tag Removal Description Location Component Type Verif seq. Verif Position Position Notes Notes

~~-'--.-~ .---~~-- .~~.~.-.~~.

._._ .~ . .~.~- --~ ~-~.-~.-~

I .~-----.~ . .---.~.~-~-

NOTE 1 SEE BLOCKING A:O E:O Info NV 3 NV SEE TAG SEE TAG ENSURE COMMENTS FOR PLACEMENT REMOVAL SERVICE WATER DETAILS NOUN NOTES NOTES PUMP 2PS02A NOT IN LOCTEXT:

SERVICE (and NOT in Standby) PER OP-211-001 SEC 2.7 PRIOR TO HANGING TAGS

--.~-~.~~---

2A10106 (RM) SERVICE WATER RM:Il-220 A:13 Red Tag 2 2 IN CV PUMP A 2PS02A E:699 R700' R668.S' 209001 COL:5 N 31.2

~.-------.

'~~~~l---~---

I Tagged Description Location Tag Placement Notes Tag Removal Notes

. S~mponE!n_t_ I ~_. ____ .~ __

SERVICE WATER RM:CW-OOl PUMP A A:52 E:661 DISCHARGE R667' COL:2

-1 ISO VLV NOUN S 30.2 LOC 2.09004 TEXT:

209014 SERVICE WTR RM:CW-020 Red Tag &-T-2--+-.,-----+-------,-c---+--QOSED---j------~-----------+----------

PUMP A SEAL A:52 E:676 WATER PRESS R681' COL:3 1

CTL VLV BYPASS N 31.2 VLV NOUN LOC TEXT:

20~--1~ERVICE Wi~-! -Ri'1:CW'{)W Red Tag 2 r~ 2 a$ED-t----::Occ-pE=N-:----t---------+--------

PUMP A SEAL A:52 E:676 WATER PRESS R682' COl:5 N CTL VLV OUTLET 31.6

-,-.-:::.--t- -CV I ~~~~CLOSED --+--O=PEN CV 2.

PUMP A VENT A:52 E:676 VLV NOUN LOC R686.S' COL:9 N TEXT: 31.2 I 209801----TIERVICE WATER l-RM:CW-OW- No Tag 2

+----

PUMP A OB A:52 E:676 CASING VENT R677.5' COL:8 N VLV NOUN LOC 31.2 TEXT: I OPEN CLOS*:::ED=---t---*--*-----------+-----

lW9s-02-- SERVICEWATER RM:CW-020 P '67 V

~. :::~:---~ SE~;CE WATE~

PUMP A DRAIN VLV NOUN LOC RM:CW-02.0 A:52 E:676 R678' COL:5 N

'-____ TE)(I=-___ ~LL _ _ _~.____ ~__ ___1_ _ _ _ ___'_ _ _ __'___ _ ___'__. _ - ' -_ _ _ _ _ _ _L _ _ _ _ _ _. _ ._ _- ' -_ _.._ _ __

Susquehanna Steam Electric Station Job Performance Measure Review and Verify Blocking Required per NDAP-QA-0322 "Energy Control Process" SRO JPM Designation: A-2 Revision Number: 2 Date: 10/26/11 Developed By: Lall~ 06/20/11 Author Date Review By: Hedigan 01/05/12 Examiner Date Approved By: Caruso 01/05/12 Chief Examiner Date

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by Examiner review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date _______

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

REVISION RECORD (Summary):

Rev 0 Rev 1: Split JPM to separate RO and SRO actions. RO to provide proposed blocking, SRO to review and correct proposed blocking Rev 2: Revised per licensee comments following pre-validation JPM Setup Instructions:

1. Provide NDAP-QA-0322

2. Provide prints E-145 sh. 8, E-4 sh. 3, and M-2109 sh. 1 and 2

3. Provide proposed 2A Service Water Pump Clearance TASK STANDARD:

Review the list of proposed blocking for 2A Service Water Pump; discrepancies identified and noted lAW attached Key.

TASK CONDITIONS:

Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for impeller replacement, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means SRO INITIATING CUE:

Using the appropriate drawings referenced on the proposed clearance, review the requested blocking to ensure it meets the requirements of NDAP-QA-0322 for accuracy and adequacy. The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service.

Information for Evaluator's Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the "Comment Number" column. Then annotate that comment in the "Comments" section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

Operator's Name: _______________________________

Job

Title:

NLO RO SRO STA SRO Cert JPM

Title:

Review and Verify Blocking Required per NDAP-QA-0322 "Energy Control Process" JPM Number: A-2 Revision Number: 2 KIA Number and Importance: 2.2.41 RO 3.5 SRO 3.9 Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Perform in Classroom Alternate Path: No Time Critical: No Estimated Time to Complete: 20 min. Actual Time Used: - - -minutes

References:

1. NUREG 1123 Rev. 2, Supp. 1

2. NDAP-QA-0322 Rev. 35

3. E-145 sh. 8

4. E-4 sh. 3

5. M-2109 sh. 1 and 2 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? Yes 0 No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory Unsatisfactory Comments:

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

==

Description:==

This .JPM has the operator review proposed blocking for the 2A Service Water Pump for a pump PM. The normal means of clearance development, eSoms, is unavailable. The applicant will review proposed blocking and identify/document any discrepancies.

NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time ELEMENT STANDARD SAT UNSAT Comment Number EVALUATOR NOTE

Ensure the following material is available to support performance of this JPM:

Prints: E-145 sh. 8, E-4 sh. 3, and M-2109 sh. 1 and 2

NDAP-QA-0322

Attached library clearance EVALUATOR NOTE Determines that motor To begin this JPM, provide the needs blocked and should candidate with the Task Conditions and isolate all pump flowpaths to Initiating Cue Sheet. allow for work on pump.

Reviews the scope of work planned for2ASWP.

NDAP-QA-0322 is an information use only procedure. Candidate should reference clearance standards (6.1) and attachments N &

o for general equipment blocking rules for verifying correct blocking EVALUATOR NOTE Candidate may at anytime reference NDAP-QA-0322 to ensure compliance and follow appropriate check sheets.

ELEMENT STANDARD SAT UNSAT Comment I Number

Using E-145, recognizes that the Candidate identifies requested 13.8kV breaker listed 2A10106 as correct 13.8kV (2A10103) is incorrect breaker for 2A Service Water Pump.

--~-----.-.-----------

Using M-21 09, Sheet 2, candidate Candidate identifies 209166 should recognize that the requested as the correct 2A Service Service Water Pump vent valve is Water Pump vent valve incorrect and is actually for 28

§ervice Water Pump (209167)

EVALUATOR CUE Role play the Unit Supervisor and acknowledge the receipt of the corrected blocking and inform candidate that it will be forwarded to theWCC.

-~~"~"-----

Give completed list of corrected Unit Supervisor is given the blocking sheet to the Unit Supervisor corrected blocking sheet.

to be forwarded to WCC.

EVALUATOR CUE Once candidate turns in list of corrected blocking sheet. the __'PM is complete.

DUE TO THE NATURE OF THIS JPM OTHER BLOCKING POINTS MAYBE ACCEPTABLE.

CONSULT WITH ADDITIONAL SMEs AS NECESSARY TO DETERMINE ACCEPTABILITY OF ALTERNATE BLOCKING POINTS.

i

ELEMENT STANDARD SAT I UNSAT Comment I Number DO YOU HAVE ALL OF YOUR JPM EXAM MATERIALS?

JPM Stop Time

NOTE T ive th n t a es (Ke )

t the student!

They are given the cue sheet and the library clearance order

TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for pump PM, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means A paper copy of a library clearance has been sent to the Control Room for you to review the blocking request INITIATING CUE Using the appropriate drawings referenced on the proposed clearance, review the requested blocking to ensure it meets the requirements of NDAP-QA-0322 for accuracy and adequacy. The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service.

TASK CONDITIONS Unit 2 is at 100% power.

2A Service Water Pump has been scheduled for pump PM, but due to an oversight, no clearance package was developed Database problems within eSoms have prevented development of a clearance order by electronic means A paper copy of a library clearance has been sent to the Control Room for you to review the blocking request INITIATING CUE Using the appropriate drawings referenced on the proposed clearance, review the requested blocking to ensure it meets the requirements of NDAP-QA-0322 for accuracy and adequacy. The Clearance Order Office will generate the associated Clearance Order when eSoms is returned to service.

Library Clearance Order Susquehanna ##-### -2PS02A SERVICE WATER PUMP O-Unit 2 SYS 2PS02A SERVICE WATER PUMP A (PP MOTOR MR N NOUN LOC TEXT:

RM:CW-020 A:52 E:676 R678.5 Clearance Order

Description:

SERVICE WATER PUMP 2P502A OOS FOR IMPELLER REPLACEMENT STANDARD CLEARANCE ORDER Notes:

1) OPERATIONS VENT AND DRAIN

2) Clearance order effectiveness determined by Live-Dead-Uve checks; no sustained pressure/flow exiting drains Opened Impacts I Effects:

LOSS OF CONTROL AND INDICATION FOR 2A SERVICE WATER PP 2P502A PMT: OPS-PLACE IN SERVICE lAW OP-211-001 AND VERIFY PROPER OPERATION REF. E-145 SH. 8, E-4 SH. 3 & M-2109 SH. 1 Post Maintenance Testing Req.:

PSP-29; PLACE SW PUMP 2P502A 1/5 lAW OP-211-001 Wilkes, Barry Tagged Restoration Tag Pla.eemlent Tag Removal Position Position Notes Notes 2

cv cv

Rest. Rest Tagged Tag Removal Tagged Seq. Verif Position Position Notes 2 cv CLOSED OPEN CLOSED

Susquehanna Steam Electric Station Job Performance Measure Review and Approve Radioactive Liquid Release Permit JPM Designation: A-3 Revision Number: 1 Date: _12/06/11 Developed By: Patel 06114111 Author Date Review By: Hedigan 01/05/12 Examiner Date Approved By: Caruso 01/05/12 Chief Examiner Date

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by Examiner review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date - - - - -

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10.. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

REVISION RECORD (Summary):

1. Rev 1 JPM Setup Instructions:

1. Provide marked-up surveillance authorization package.

TASK STANDARD:

Identify less than required LRW sample tank recirculation time, incorrect settings for Actual High Rad setpoint and Actual Alert Rad setpoint, and determine that U1 & U2 Cooling Tower Slowdown Flow instrumentation is inoperable, requiring blowdown flow instruments to be bypassed.

TASK CONDITIONS:

Preparations are in progress to release LRW Sample Tanks OT303C&D.

OP-069-050, Release of Liquid Radioactive Waste Attachments '0', 'F' and 'H' have been prepared.

INITIATING CUE:

FUS is unavailable, Shift Manager directed you to review and approve OP-069-050 attachment D, F and H. Document any required actions below.

Information for Evaluator's Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the "Comment Number" column. Then annotate that comment in the "Comments" section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

Operator's Name:

Job

Title:

NLO RO SRO STA[J SRO Cert

..JPM

Title:

Review and Approve Radioactive Liquid Release Permit JPM Number: A*3 Revision Number: 0 KIA Number and Importance: 2.3.6 SRO 3.7 Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Perform in Classroom Alternate Path: No Time Critical: No Estimated Time to Complete: 15 min. Actual Time Used: - - -minutes

References:

1. NUREG 1123,

2. OP-069-050, Rev. 41 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? Yes No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory Unsatisfactory Comments:

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

==

Description:==

This JPM has the operator independently verify LRW sample tank radioactive liquid release permit. Applicants should identify various issues with the permit. Applicants should identify less than required LRW sample tank recirculation time, incorrect settings for Actual High Rad setpoint and Actual Alert Rad setpoint, and determine that U1 & U2 Cooling Tower Slowdown Flow instrumentation is inoperable, requiring blowdown flow instruments to be bypassed.

NRC SSES INITIAL EXAMINA TION JPMA-3 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time Action Standard SAT UNSAT Comment Number EVALUATOR NOTE:

Provide the candidate with a filled out copy of OP-069-050, Release of Liquid Radioactive Waste Attachment 0, F & H of "LRW Sample Tank OT303C&D Radioactive Liquid Release Permit".

Provide the* Applicant with a blank OP-069-050, Release of Liquid Radioactive Waste procedure.

1 Refers to a blank copy of OP-069 Refers to a copy of OP-069-050, 050, Release of Liquid Radioactive and completed attachment D, F, Waste and completed attachment D, and H.

F, and H.

2 Selects the correct section to perform Selects section step 2.3.3 review. through 2.3.9 of OP-069-050, Release of Liquid Radioactive Waste Attachment D "LRW Sample Tank OT-303C&D Radioactive Liquid Release Permit". Also, reviews form op 069-050-7, attachment F of op 069-050.

EVALUATOR NOTE:

If the applicant indicates that he/she would send this release back due to not enough recirculation time prior to sample, then indicate to applicant to finish review of the entire procedure.

NRC SSES INITIAL EXAMINA TlON JPMA-3 Action Standard SAT UNSAT Comment Number

3 Verifies Calculation of Required Performs the following Recirculation Time calculations:

=

98 x 0.75 73.5 minutes.

Compares this number with 71.5 minutes, and determines that Calculated required recirculation time is incorrect, and the earliest possible sample time would be 10:03 (not 10:01).

3 Verifies High Rad setpoint Performs the following calculation:

=

1.2SE4 + 2.77E3 1.S27E4 and compares this to the number in block 2.3.6.n (4.02E4). The applicant identifies that background count rate was inappropriately carried forward into high rad setpoint calculation as 2.77E4.

Therefore, the correct rad setpoint value should be 1.S27E4.

4 Verifies Alert Rad setpoint Performs the following calculation:

=

1.00E4 + 2.77E3 1.277E4 and compares this to the number in block 2.3.6.0 (3.77E4). The applicant identifies that background count rate was inappropriately carried forward into Alert rad setpoint calculation as 2.77E4.

Therefore, the correct rad setpoint value should be 1.277E4.

NRC SSES INITIAL EXAMINA TlON JPMA-3 Action Standard SAT UNSAT Comment I -

Number

5 Compares Calculated required High Determines that the actual Rad and Alert Rad setpoint with setpoint set out in the field are required setpoint and actual setpoint incorrectly set and requires in step 2.3.7. corrections.

6 Determines that Unit 1 AND Unit 2 Reviews Attachment F, to Cooling Tower Flowrate Instruments determine the satisfactory test are INOPERABLE, and requires results of blowdown flow permission from shift supervisor to instrumentation for Unit 1 and bypass coolinbJ tower low flow Unit 2.

interlock to be bypassed. Determines that for Unit 1 based on actual Cooling Tower Basin Blowdown valve position indication (45%) and blowdown flow rate (4000gpm) Unit 1 blowdown flow instrumentation falls within the Unacceptable Region of the Graph on Page 158 of Attachment F.

Determines that based on the Graph results, Unit 1 Blowdown flow instrumentation should be declared INOPERABLE and require to be bypassed.

Determines that for Unit 2 based on actual Cooling Tower Basin Blowdown valve position indication (40%) and blowdown flow rate (2500gpm) Unit 1 blowdown flow instrumentation falls within the Unacceptable Region of the Graph on Page 161 of Attachment F.

Determines that based on the Graph results, Unit 1 Blowdown flow instrumentation should be declared INOPERABLE and require to be bypassed.

NRC SSES INITIAL EXAMINA TlON JPMA-3 Action Standard SAT UNSAT Comment Number Evaluator Note:

EVALUATOR CUE:

If the applicant indicates that he/she In summary, once calculations would send this release back due to errors are corrected for recirc not enough recirculation time prior to flow, rad setpoints are sample, incorrect RAD setpoint, AND appropriately set, and HS flowrate instruments are 06443A is in the "Bypass" INOPERABLE then indicate to position, applicant should applicant that: determine that it is SAFE to discharge as long as TR 3.11 .1.4 Condition 0 Action to estimate

Recirculation time has been blowdown flow rate every 4 satisfactory been met per the hours, and log Cooling Tower corrected calculation level, Blowdown valve position

High Rad and Alert Rad and flowrate every 4 hours0.167 days 0.0238 weeks 0.00548 months lAW Setpoints are properly set in step 2.3.14.a(3).

accordance with the corrected calculation

Both U 1 and U2 Flowrate instruments are INOPERABLE As a Shift Supervisor, complete review and approval of OP-069-050 attachment 0, F and H and determine whether a discharge can continue and if it can under what conditions.

Marks up Attachment H to

7 Determines that HS-06443A is proper Switch Alignment of HS required to be in "Bypass" when total 06443A. Indicating the HS site, U-1 and U-2 Cooling tower 06443A, Cooling water blowdown instruments are blowdown low flow needs to be INOPERABLE. place in Bypass Position.

AND Draws Arrow towards "BYPASS" position.

Determines that TR 3.11.1.4 Condition 0 Actions apply, and Determines that TR 3.11.1.4 Cooling Tower level, Blowdown valve Condition 0 Actions apply, and position and flowrate needs to be Cooling Tower level, Blowdown logged every 4 HOURS lAW step valve position and flowrate 2.3.14.a(3). needs to be logged every 4 HOURS lAW step 2.3.14.a(3).

I NRC SSES INITIAL EXAMINA TION I

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

JPMA-3 Action Standard SAT UNSAT Comment Number EVALUATOR CUE:

That completes this JPM.

I il JPM Stop Time _ _ _ __

NRC SSES INITIAL EXAMINA TlON L . . - - . . -_ _ _ _ _ .~ _ _ _ _ _ _ _ __ J JPMA-3 HANDOUT PAGE TASK CONDITIONS:

Preparations are in progress to release LRW Sample Tanks OT303C&D.

OP-069-050, Release of Liquid Radioactive Waste Attachments 'D', 'F' and 'H' have been prepared.

INITIATING CUE:

FUS is unavailable, Shift Manager directed you to review and approve OP-069-050 attachment D, F and H.

Document any required actions below.

NRC SSES INITIAL EXAMINA TlON JPMA-3 HANDOUT PAGE TASK CONDITIONS:

Preparations are in progress to release LRW Sample Tanks OT303C&D.

OP-069-050, Release of Liquid Radioactive Waste Attachments '0', 'F' and 'H' have been prepared.

INITIATING CUE:

FUS is unavailable, Shift Manager directed you to review and approve OP-069-050 attachment 0, F and H.

Document any required actions below.

Susquehanna Steam Electric Station Job Performance Measure Emergency Plan communications RO JPM Designation: A-4 Revision Number: 3 Date: -,/...:,.1..:.,..1_

Note: This JPM is paired with Sim JPM E.

Developed By: Patel 06/10/11 Author Date Review By: Hedigan 01/05/12 Examiner Date Approved By: Caruso 01/05/12 Chief Examiner Date

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below.

REVISION RECORD (Summary):

1. Rev 3 JPM Setup Instructions:

Provide Event Notification Report.

Fill in thl3 declaration time as two minutes prior to the current time Sign the ENR form under approved section on bottom and fill in the current time as the time approved.

(when applicant starts the Admin JPM)

TASK STANDARD:

The applicant should obtain appropriate BNTD sticker and verbally communicate the ENR form to the offsite agencies by utilizing backup telephone numbers.

TASK CONDITIONS:

See Emergency Notification Report INITIATING CUE:

1. A General Emergency has been declared for Unit 1 as the initial emergency classification due to an airborne radiological release in progress.

2. Complete the emergency plan communication to the offsite agencies.

3. This is a time critical JPM Information for Evaluator's Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the "Comment Number" column. Then annotate that comment in the "Comments" section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

Operator's Name:

Job

Title:

NLO [J RO DSRO STA-: SRO Cert JPM

Title:

Emergency Plan communications

..'PM Number: A-4 Revision Number: 0 KIA Number and Importance: 2.4.39 RO 3.9 Suggested Testing Environment: Simulator Actual Testing Environment: Simulator Testing Method: Perform in Simulator Alternate Path: Yes Time Critical: Yes Estimated Time to Complete: 15 min. Actual Time Used: - - -minutes

References:

1. NUREG 112~"

2. EP-PS-126-A, Emergency Plan Communicator, Rev. 27 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? 0 Yes No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: D Satisfactory Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _(Print)

Evaluator's Signature: Date: _ _ _ __

==

Description:==

This JPM has the operator communicate the ENR form to the offsite agencies utilizing backup telephone numbers.

NRC SUSQUEHANNA INITIAL EXAMINATION 0112012 RO RO A-4 FINAL (17-Dec-11).DOC Page 5 of 7

NRC SSES INITIAL EXAMINA TION JPM A-4 NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time (Record Start of JPM Time when applicant acknowledges the initiating cue) Official start time for Time Critical JPM ELEMENT I

STANDARD I, SAT I.

UNSAT I* Comment Number Evaluator Notes

Finish the remainder of the attached ENR form when applicant is ready to begin JPM:

a. Fill in the declaration time (in Section 3) as two minutes prior to the current time

b. Sign the ENR form under approved section at the bottom of the form and fill in the current time as the time approv13d.

Remind Simulator Booth Operator to NOT answer any of the Notification calls

1. Obtains procedure and reviews Obtains EP-PS-126 and ENR procedure, prerequisites, and form.

precautions

2. Obtain and review Event Notification Applicant reviews ENR report.

Report (ENR) form with the Shift Evaluator Note: Applicant Manager/ED. may request to review form with Shift Manager/ED.

Evaluator Cue: Notify Applicant Shift Manger/ED are busy and you may proceed with notification with this ENR report.

NRC SSES INITIAL EXAMINA TlON JPMA-4 ELEMENT I STANDARD I SAT UNSAT I Comment I . Number

3. If the Shift Manger has not already Obtains label for General done so, obtain a label containing Emergency containing the the Brief Non-technical Descriptions brief Non-technical of the EALs and affix the description Descriptions of the EALs and to the ENR form in the space on the affix the description to the form. ENR form in the space on the form.

I

40btains "CG4" Brief Non-technical Obtains label for General Description Sticker from the EAL Emergency containing the folder in the center console desk brief Non-technical drawer and applies it in the field Descriptions of the EALs and block located above #5 .. affix the description to the ENR form in the space on the form.

Evaluator Note: . Pre-printed labels containing the Brief Non-technical Descriptions of the EALs are located in a marked folder in the center console desk drawer.

5. Log time for "Notification Time" Logs the time for "Notification when first individual answers the Time" when the first agency phone in the next step: answers the phone.

Time Critical Stop Time:

6. Within 15 minutes of declaration, Evaluator Note: The using the purple colored phone Simulator Booth Operator will button, dial "191" to transmit the not answer the" 191" call.

ENR form to the following:

(Dialing 191 will simultaneously connect the listed agencies in a conference call.)

7. If the "191" function does not work, Evaluator Note: The attempt to use conference line Simulator Booth Operator will "196", then contact the Emergency not answer the "196.

Agencies directly. The JIC should be contacted last. I

NRC SSES INITIAL EXAMINA TlON JPMA-4 ELEMENT STANDARD SAT UNSAT Comment Number

8. Contact the Emergency Agencies Evaluator Note: When the directly. The JIC should be applicant dials the first contacted last. agencies number, role playas John Smith from that agency

(PEMA)

The applicant will need to utilize backup telephone i numbers.

BACKUP TELEPHONE NUMBERS The applicant uses the following backup numbers and If calling from a 4xxx extension, dial the backup numbers as follows: dials JIC last:

PEMA: 4960, 4961 or PEMA: 4960, 4961 or 8-1-71 '1-651-2001 8-1-717-651-2001 LCEMA: 4906,4907, or LCEMA: 4906, 4907, or 8-1-800-821-3715 8-1-800-821-3715 CCDPS: 4955, 4956, or

CCDPS: 4955,4956, or 8-1-570-389-5720 8-1-570-389-5720 PIM: 4901,4902 PIM: 4901,4902 JIC: 4903 JIC: 4903

If calling from a 3)(xx extension, dial the backup numbers as follows:

PEMA: 8-353-4960, 8-353-4961, or 8-1-717 -651-2001 LCEMA: 8-353-4906, 8-353-4907, or 8-1-,900-821-371 5 CCDPS: 8-353-4955, 8-353-4956, or 8-1-570-389-5720 PIM: 8-353-4901, 8-353-4902 JIC: 8-353-4903 ..

I

NRC SSES INITIAL EXAMINA nON JPMA-4 ELEMENT STANDARD SAT UNSAT Comment I Number

9. Verbally communicate the ENR When the first agency answers form to the offsite agencies. the phone, communicates ENR form verbally to the offsite agencies.

Identifies His/her Name.

Call back number

Declaration Time

Event Classification (GE)

Unit-1

"The water level inside the Unit 1 reactor has dropped and does not completely cover the uranium fuel.

The unit has been shut down prior to the event and remains shut down.

Protective actions will be recommended for the public".

'The water level inside the Unit 1 reactor has dropped and does not completely cover the uranium fuel.

The unit has been shut down prior to the event and remains shut down.

Protective actions will be recommended for the public".

There is an airborne radiological release in progress due to the event.

I

NRC SSES INITIAL EXAMINA TION JPM A-4 ELEMENT STANDARD SAT UNSAT Comment I Number Evaluator Cue: If required(requested by applicant), repeat back applicant message to complete 3 way communication.

Understand that U1 Declared a GE at (T-2min).

"The water level inside the Unit 1 reactor has dropped and does not completely cover the uranium fuel. The unit has been shut down prior to the event and remains shut down.

Protective actions will be recommended for the public".

There is an airborne radiological release in progress due to the event.

Your call back # is 570-759 4915 Evaluator Note: Once the aQQlicant has successfully:

communicated the event to the first offsite agency: (PEMA},

uQon dialing the correct extension number for the next agency: (LCEMA}, y:ou may:

END the JPM.

JPM Stop Time

NRC SSES INITIAL EXAMINA TlON JPMA-4 HANDOUT PAGE; TASK CONDITIONS:

See Emergency Notification Report INITIATING CUE:

1. A General Emergency has been declared for Unit 1 as the initial emergency classification due to an airborne radiological release in progress.

2. Complete the emergency plan communication to the offsite agencies.

3. This is a time critical JPM

NRC SSES INITIAL EXAMINA TlON JPMA-4 HANDOUT PAGE TASK CONDITIONS:

See Emergency Notification Report INITIATING CUE:

1. A General Emergency has been declared for Unit 1 as the initial emergency classification due to an airborne radiological release in progress.

2. Complete the emergency plan communication to the offsite agencies.

3. This is a time critical JPM

EMERGENCY NOTIFICATION REPORT Control #- CR-1

1. Call Status: ~ THIS IS A DRILL o THIS IS AN ACTUAL EVENT

2. This is: _______________ atPPLSusquehanna,LLC (Communicator's Name)

My telephone 570-542 3 ---- Notification time is:

- (Time notification number is: 570-759 4

initiated)

(Callback telephone number)

3. EMERGENCY CLASSIFICATION:

D UNUSUAL EVENT D SITE AREA EMERGENCY D ALERT lSI GENERAL EMERGENCY D The event has been terminated.

UNIT: lSI ONE Declaration Time:

~-~~~~~-

DATE: TODAY D Two (Time classification! (Date classification!

DONE & Two termination declared) termination declared)

THIS REPRESENTS AlAN: lSI INITIAL DECLARATION}

D ESCALATION IN CLASSIFICATION STATUS D NOCHANGE

4. The Classification Designation is:

BRIEF NON*TECHNICAL DESCRIPTION OF THE:

lSI EMERGENCY EVENT (Initial declaration and escalations) OR D OTHER SIGNIFICANT EVENT (No change in emergency classification or classification time)

5. THERE IS: D No }

lSI AN AIRBORNE RADIOLOGICAL RELEASE IN PROGRESS DUE TO THE EVENT D ALiQUID A Rad Release is in Progress if: in the judgment of ED!RM radioactive material is being released to the environment or into an area of the plant that will result in a release to the environment that is a result of the event. Example conditions that result in a rad release; Fuel Clad Barrier AND Containment Barrier LOSS, RCS Barrier AND Containment Barrier LOSS, RG1, RS1, RA1, RU1, MU7, SBGT initiation on RB Vent hi-rad, an increase in the detected gaseous radiation effluents that is a result of the event, or any radioactive liquid released beyond the Protected Area that is a result of the event.

6. WIND DIRECTION IS _ _ _ _-=2=7...:..7_°. WIND SPEED IS: -=-_ _ _ _ mph.

(Data from 10 meter meteorological tower, available on PICSY.)

7. REPEAT: IX! THIS IS A DRILL o THIS IS AN ACTUAL EVENT (When communicating form, request a repeat back by one of the agencies.)

APPROVED: shift M~ Time: Date: TOVAY (ED, RM, or EOFSS) (Time form approved) (Date form approved)

EP-AD-OOO-310, Revision 12, Page 1 of 1 (Electronic Form)

Susquehanna Steam Electric Station Job Performance Measure Classify a Site Area Emergency, Upgrade to General Emergency and Make Protective Action Recommendations SRO ..IPM Designation: A-4 Revision Number: 1 Date: 10/24/11 Developed By: Lall~ 06/21/11 Author Date R,eview By: Hedigan 01/05/12 Examiner Date Approved By: Caruso 01/05/12 Chief Examiner Date

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 through 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by Examiner review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. Date - - - - -

9. Pilot test the ...IPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When ..IPM is revalidated, Examiner sign and date JPM cover page.

REVISION RECORD (Summary):

Rev 0 Rev 1: Edited per licensee comments to correct answer key and task conditions JPM Setup Instructions:

1. Ensure sufficient quantity of EP-PS-100 Tabs 5 and 9 fomlS on hand

2. Provide EP-TP-001

3. Provide EP-PS-100 TASK STANDARD:

1. Declaration of a Site Area Emergency based on classification FS1 within 15 minutes of initiating cue

2. Declaration of a General Emergency based on classification FG1 within 15 minutes of second initiating cue

3. Make Protective Action Recommendation (PAR) [evacuate 0 to 2 miles, shelter 2 to 10 miles, and advise citizens take KI per state plans] within 15 minutes of declaring a General Emergency TASK CONDITIONS:

Unit 1 was initially at 100% power At T + 0 sec an earthquake with a magnitude of 0.07g occurred near the plant and was confirmed with seismic instrumentation and control room operators Due to the earthquake activity, a loss of offsite power has occurred At T + 30 sec, a LOCA occurred as a result of the seismic activity RPV level is -1';75" and rising slowly due to A Loop RHR injection All control rods are fully inserted Drywell pressure is 25 psig and rising INITIATING CUE:

Initiating Cue #1: Classify the Event, and implement the Emergency Plan as the Control Room Emergency Director in accordance with EP-PS-100. THIS IS A TIME CRITICAL JPM Initiating Cue #2: At time T= 30 minutes,

EDG 'A' tripped, resulting in RPV level momentarily reaching -215" and recovering to -182" and rising slowly by starting B RHR pump

Due to inability to spray, drywell pressure is currently 54 psig and rising slowly Assuming the other initial conditions are still valid, determine if this new condition will affect the current EAL classification, AND if so perform any other additional actions that may be required. THIS IS A TIME CRITICAL JPM Information for Evaluator's Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the "Comment Number" column. Then annotate that comment in the "Comments" section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

NLO ORO OSRO STA SRO Cert

..IPM

Title:

Classify and Communicate a Site Area Emergency, Upgrade to General Emergency and Make Protective Action Recommendations JPM Number: A-4 Revision Number: 1 KIA Number and Importance: 2.4.44 SRO 4.4 Suggested Testing Environment: Classroom Actual Testing Environment: Classroom Testing Method: Perform in Classroom Alternate Path: No Time Critical: Yes Estimated Time to Complete: 30 min. Actual Time Used: _ _ _minutes

References:

1. NUREG 1123 Rev. 2, Supp. 1

2. EP-PS-100, Rev. 26

3. EP-PS-100, Tab A, Rev. 18

4. EP-PS-100, Tab D, Rev. 23

5. EP-PS-100, Tab E, Rev. 28

6. EP-AD-000-126, Rev. 17

7. EP-AD-000-077 Rev 3.

8. EP-PS-100, Tab 9, Rev.

9. EP-TP-001, Rev. 3

EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? Yes No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory LJ Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _{Print)

Evaluator's Signature: Date: _ _ _ __

Descrjption: This JPM has the operator review plant conditions and make an emergency declaration of Site Area Emergency and perform actions to communicate the declaration. A second cue will be provided in which the operator will then declare a General Emergency and make Protective Action Recommendations.

NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD I SAT I UNSAT I Comment

I

Number !

EVALUATOR CUE:

To begin this JPM provide the candidate with CUE SHEET#1 :

When the candidate is ready to begin the JPM, inform the candidate that this is a TIME CRITICAL JPM.

Record START TIME

{EP-PS-100 Tab A, steps 1 (Step 1a) Evaluate updated and 2) Classify the emergency information.

as conditions indicate.

(Step 2a) Review Emergency EVALUATOR CUE: Classification Level Manual, EP-TP-001 table F.

If asked, conditions have not changed.

Declare a SITE AREA EMERGENCY in accordance EVALUATOR NOTE: with Classification FS 1 (RPV When candidate declares the level < -161")

initial EAL classification, Record TIME Candidate will also refer to Table M for the loss of offsite Time to determine correct power, but the FS1 declaration EAL must be within 14 i is the overriding classification

minutes, 30 seconds of for the site.

START TIME (Tab A step 4) Refer to EP-PS-100, Obtain a copy of EP-PS-*100 "Emergency Director, Control Room; . and refer to tab 0, Manage the Emergency-Plan Position Specific I SITE AREA EMERGENCY.

Instruction" I I

ELEMENT STANDARD SAT UNSAT I Comment I Number (EP-PS-100 Tab D) Document and (Step 1) Announce to Control communicate the emergency Room personnel classification.

1) Assuming duties of Emergency Director

2) Emergency Classification

3) Time and Date of !

Classification (Step 2) Appoint E-Plan Communicator. Appoint E-Plan Communicator.

Instruct E-Plan Communicator EVALUATOR CUE: to immediately perform EP-PS-126.

Acknowledge the appointment of the E-Plan Communicator, when given the ENR form indicate that the E-Plan Communicator will transmit the form. !

(Step 3) Appoint NRC Communicator. Appoint NRC Communicator.

Instruct NRC Communicator to EVALUATOR CUE: perform EP-PS-135, NRC Communicator. i Acknowledge the appointment of the NRC Communicator. ! I

(Step 4) Generate and approve ENR Fill out ENR Form from Tab 9, Form for transmittal. refers to Tab H to determine a release is NOT in progress EVALUATOR CUE: and authorizes Form for transmittal.

Provide ENR form if requested. IfJPM is not performed in the simulator, when Evaluator Note:

requested, inform the student that:

Acknowledge receipt of

Wind Direction is 157 degrees ENR form

Wind Speed is 9 mph If performed in the Simulator, student should use current PICSY data.

I I

ELEMENT STANDARD SAT UNSAT I Comment I Number EVALUATOR CUE:

1. Inform the student that no further EP-PS-100 actions are required with respect to the previous classification.

2. Provide candidate with CUE SHEET

2.

3. Record START TI ME

(Tab D, step 16) Refer to EP-TP-001 Refer to EP-TP-001 Table F, and evaluate the impact of new and determine that RPV level conditions. Reclassify emergency and exceeded Fuel Clad barrier appropriate tab for classification level: LOSS criteria of <205", and with Tab E. drywell pressure >53 psig and rising, has also met Primary EVALUATOR NOTE: Containment POTENTIAL LOSS. An escalation to When candidate identifies the GENERALEMERGENCYFG1 upgrade EAL classification is now required; Record TIME EP-PS-100 tab E must now be implemented.

Time to determine correct EAL must be within 15 minutes of START TIME i noted in 3, above. i

(Step 4) Generate and approve ENR Fill out ENR Form from Tab 9, Form for transmittal. also refers to Tab H to determine a release is NOT in EVALUATOR CUE: progress and authorizes Form for transmittal.

Provide ENR form if requested. If ..'PM is not performed in the simulator, when Evaluator Note:

requested, inform the student that:

Acknowledge receipt of

Wind Direction is 157 degrees ENR form

Wind Speed is 9 mph If performed in the Simulator, student should use current PICSY data.

I ELEMENT STANDARD SAT! UNSAT Comment Number

(Step 5) When a General Emergency Refer to EP-PS-1 00 tab Estep 5 and determine that a PAR is declared, make Protective Action Recommendation (PAR) within 15 must also be performed in minutes. accordance with EP-PS-100 Tab 5 I

EVALUATOR CUE:

After the candidate determines a PAR is required, direct the candidate to determine the correct PAR for current plant conditions I

ELEMENT STANDARD SAT UNSAT Comment Number

Perform EP-PS-100 Tab 5, "PPL Refer to EP-PS-100 Tab 5 and Emergency Dose Assessment and determine:

Protective Action Recommendation

PA-2: Has a GE been (PAR) Guide" declared? YES EVALUATOR CUE:

PA-3: Release via controlled direct When asked, inform student that a valid containment vent < 1 offsite dose projection is NOT available hr? NO yet.

PA-6: Valid Dose projection? NO EVALUATOR NOTE:

Per PA-7:

When candidate completes

Evacuate 0-2 PAR and indicates need to miles transmit it to the Senior State

Shelter 2-10 miles Official:

Citizens take KI Record TIME per state plans Time to determine PAR must be (Tab E, step 5c) Notify Senior within 15 minutes of General State Official, using PAR State Emergency declaration time noted in Notification Form, at 717-651 Step 7. *2148.

EVALUATOR CUE:

When student indicates need to transmit PAR to Senior State Official, inform student "This completes the JPM."

I

ELEMENT STANDARD SAT UNSAT Comment Number DO YOU HAVE ALL OF YOUR JPM EXAM MATERIALS?

JPM Stop Time _ _ __

NOTE Do n t give the next 5 pages (Keys) to the student!

Also, there are two sets of cue sheets. The 1st is given to the applicant at the beginning of the JPM. The JPM will direct when to provide the 2nd cue sheet. There are also two blank ENR forms in the package as well

ANSWER KEY (for 1 NR form)

EMERGENCY NOTIFICATI~N REPORT Control # CR-1

1. Call Status: I:2J THIS IS A DRILL THIS IS AN ACTUAL EVENT

2. This is: at PPL Susquehanna, LLC (Communicator's Name)

My telephone 570-542 3 Notification time is:

number is: 570-759 4 (Time notification (Callback telephone number) initiated)

3. EMERGENCY CLASSIFICATION:

D UNUSUAL EVENT I:2J SITE AREA EMERGENCY D ALERT D GENERAL EMERGENCY D The event has been terminated.

UNIT: I:2J ONE Declaration Time: Time of DATE: TODAY declaration D Two (Time classification/

termination declared)

(Date classification/

termination declared)

D ONE&Two THIS REPRESENTS AlAN: I:2J INITIAL DECLARATION}

D ESCALATION N CLASSIFICATION STATUS D NOCHANGE

4. The Classification Designation is: FS 1 BRIEF NON*,.ECHNICAL DESCRIPTION OF THE:

~ EMERGENCY EVENT (Initial declaration and escalations) OR D OTHER SIGNIFICANT EVENT (No change in emergency classification or classification time)

Applicant applies "FS1" Brief Non-technical Description Sticker here.

~ ~~ AIRBORNE LADIOLOGICAL RELEASE IN PROGRESS DUE TO THE EVENT

5. THERE IS:

D ALIQUID J A Rad Release is in Progress if: in the judgment of ED/RM radioactive material is being released to the environment or into an area of the plant that will result in a release to the environment that is a result of the event. Example conditions that result in a rad release; Fuel Clad Barrier AND Containment Barrier LOSS, RCS Barrier AND Containment Barrier LOSS, RG1, RS1, RA1, RU1, MU7, SBGT initiation on RB Vent hi-rad, an increase in the detected gaseous radiation effluents that is a result of the event, or any radioactive liquid released beyond the Protected Area that is a result of the event.

6. WIND DIREClrlON IS FROM: 1570

WIND SPEED 9 mph.

(Data from 10 meter meteorological tower, available on PICSY.)

7. REPEAT: ~ THIS IS A DRILL D THIS IS AN ACTUAL EVENT (When communicating form, request a repeat back by one of the agencies.)

APPROVED: Applicant signature Time: Current time Date TODAY (ED, RM, or EOFSS) (Time form approved) (Date form approved)

ANSWER KEY

ANSWER KEY (for 2nd ENR form)

EMERGENCY NOTIFICATION REPORT Control # CR-2

1. Call Status: fZl THIS IS A DRILL D THIS IS AN ACTUAL EVENT

2. This is: at PPL Susquehanna, LLC (Communicator's Name)

My telephone 570-542 3 Notification time is:

number is: 570-759 4 (Time notification (Callback telephone number) initiated)

3. EMERGENCY CLASSIFICATION:

D UNUSUAL EVENT D SITE AREA EMERGENCY D ALERT fZl GENERAL EMERGENCY D The event has been terminated.

UNIT: fZl ONE Declaration Time: Classification time DATE: TODAY D Two (Time classificationl termination declared)

(Date classificationl termination declared)

D ONE&Two THIS REPRESENTS AlAN: D INITIAL DECLARATION }

fZl ESCALATION N CLASSIFICATION STATUS D NOCHANGE

4. The Classification Designation is: FG1 BRIEF NON*TECHNICAL DESCRIPTION OF THE:

fZl EMERGENCY EVENT (Initial declaration and escalations) OR D OTHER SIGNIFICANT EVENT (No change in emergency classification or classification time)

Applicant applies "FG1" Brief Non-technical Description Sticker here.

5. THERE IS:

~

D D

No 1 AN AIRBORNE RADIOLOGICAL RELEASE IN PROGRESS DUE TO THE EVENT ALIQUID A Rad Release is in Progress if: in the judgment of EDfRM radioactive material is being released to the environment or into an area of the plant that will result in a release to the environment that is a result of the event. Example conditions that result in a rad release; Fuel Clad Barrier AND Containment Barrier LOSS, RCS Barrier AND Containment Barrier LOSS, RG1, RS1, RA 1, RU1, MU7, SBGT initiation on RB Vent hi-rad, an increase in the detected gaseous radiation effluents that is a result of the event, or any radioactive liquid released beyond the Protected Area that is a result of the event.

6. WIND DIRECTION IS FROM: 157 0

WIND SPEED 9 mph.

(Data from 10 meter meteorological tower, available on PICSY.)

7. REPEAT: fZl THIS IS A DRILL 0 THIS IS AN ACTUAL EVENT (When communicating form, request a repeat back by one of the agencies.)

APPROVED: Applicant signature Time: Current time Date TODAY (ED, RM, or EOFSS) (Time form approved) (Date form approved)

ANSWER KEY

CUE SHEET #1:

TASK CONDITIONS

Unit 1 was initially at 100% power

At T + 0 sec, an earthquake with a magnitude of 0.07g occurred near the plant and was confirmed with seismic instrumentation and control room operators

Due to the earthquake activity, a loss of offsite power has occurred

At T + 30 sec, a LOCA occurred as a result of the seismic activity

RPV level is -175" and rising slowly due to A Loop RHR injection

All control rods are fully inserted

Drywell pressure is 25 psig and rising INITIATING CUE Classify the Event, and implement the Emergency Plan as the Control Room Emergency Director in accordance with EP-PS-100. THIS IS A TIME CRITICAL JPM

CUE SHEET #1:

TASK CONDITIONS

Unit 1 was initially at 100% power

At T + 0 sec, an earthquake with a magnitude of 0.07g occurred near the plant and was confirmed with seismic instrumentation and control room operators

Due to the earthquake activity, a loss of offsite power has occurred

At T + 30 sec, a LOCA occurred as a result of the seismic activity

RPV level is -175" and rising slowly due to A Loop RHR injection

All control rods are fully inserted

Drywell pressure is 25 psig and rising INITIATING CUE Classify the Event, and implement the Emergency Plan as the Control Room Emergency Director in accordance with EP-PS-100. THIS IS A TIME CRITICAL JPM

CUE SHEET #2: (Do not provide until directed to by JPM.)

TASK CONDITIONS At time T= 30 minutes,

EDG 'A' tripped, resulting in RPV level momentarily reaching -215" and recovering to -182" and slowly rising by starting B RHR pump

Due to inability to spray, drywell pressure is currently 54 psig and rising slowly INITIATING CUE Assuming the other initial conditions are still valid, determine if this new condition will affect the current EAL classification, AND if so perform any other additional actions that may be required. THIS IS A TIME CRITICAL JPM

CUE SHEET #2: (Do not provide until directed to by JPM.)

TASK CONDITIONS At time T= 30 minutes,

EDG 'N tripped, resulting in RPV level momentarily reaching -215" and recovering to -182" and slowly rising by starting B RHR pump

Due to inability to spray, drywell pressure is currently 54 psig and rising slowly INITIATING CUE Assuming the other initial conditions are still valid, determine if this new condition will affect the current EAL classification, AND if so perform any other additional actions that may be required. THIS IS A TIME CRITICAL JPM

EMERGENCY NOTIFICATION REPORT Control #

1. Call Status: D THIS IS A DRILL D THIS IS AN ACTUAL EVENT

2. This is: at PPL Susquehanna, LLC (Communicator's Name)

My telephone 570-542 3 Notification time is:

number is: 570-759 4 (Time notification (Callback telephone number) initiated)

3. EMERGENCY CLASSIFICATION:

D UNUSUAL EVENT D SITE AREA EMERGENCY D ALERT D GENERAL EMERGENCY D The event has been terminated.

UNIT: D ONE Declaration Time: DATE:

D Two (Time classificationi termination declared)

(Date classification!

termination declared)

D ONE&Two THIS REPRESENTS AlAN: D INITIAL DECLARATION }

D ESCALATION IN CLASSIFICATION STATUS D NOCHANGE

4. The Classification Designation is:

BRIEF NON-TECHNICAL DESCRIPTION OF THE:

D EMERGENCY EVENT (Initial declaration and escalations) OR

5. THERE IS:

D AN AIRBORNE RADIOLOGICAL RELEASE IN PROGRESS DUE TO THE EVENT D ALIQUID A Rad Release is in Progress if: in the judgment of ED!RM radioactive material is being released to the environment or into an area of the plant that will result in a release to the environment that is a result of the event. Example conditions that result in a rad release; Fuel Clad Barrier AND Containment Barrier LOSS, RCS Barrier AND Containment Barrier LOSS, RG1, RS1, RA1, RU1, MU7, SBGT initiation on RB Vent hi-rad, an increase in the detected gaseous radiation effluents that is a result of the event, or any radioactive liquid released beyond the Protected Area that is a result of the event.

6. WIND DIRECTION IS FROM: o. WIND SPEED mph.

(Data from 10 meter meteorological tower, available on PICSY.)

7. REPEAT: D THIS IS A DRILL D THIS IS AN ACTUAL EVENT (When communicating form, request a repeat back by one of the agencies.)

APPROVED: Time: Date (ED, RM, or EOFSS) (Time form approved) (Date form approved)

EMERGENCY NOTIFICATION REPORT Control #

1. Call Status: D THIS IS A DRILL D THIS IS AN ACTUAL EVENT

2. This is: at PPL Susquehanna, LLC (Communicator's Name)

My telephone 570-542 3 Notification time is:

number is: 570-759 4 (Time notification (Callback telephone number) initiated)

3. EMERGENCY CLASSIFICATION:

D UNUSUAL EVENT D SITE AREA EMERGENCY D ALERT D GENERAL EMERGENCY D The event has been terminated.

UNIT: D ONE Declaration Time: DATE:

D Two (Time classificationl termination declared)

(Date classificationl termination declared)

D: ONE&Two THIS REPRESENTS AlAN: D INITIAL DECLARATION}

D ESCALATION IN CLASSIFICATION STATUS D NOCHANGE

4. The Classification Designation is:

BRIEF NON-TECHNICAL DESCRIPTION OF THE:

D EMERGENCY EVENT (Initial declaration and escalations) OR D OTHER SIGNIFICANT EVENT (No change in emergency classification or classification time)

I I

I

5. THERE IS: D NO*}* I D AN AIRBORNE ADIOLOGICAL RELEASE IN PROGRESS DUE TO THE EVENT D ALIQUID A Rad Release is in Progress if: in the judgment of ED/RM radioactive material is being released to the environment or into an area of the plant that will result in a release to the environment that is a result of the event. Example conditions that result in a rad release; Fuel Clad Barrier AND Containment Barrier LOSS, RCS Barrier AND Containment Barrier LOSS, RG1, RS1, RA1, RU1, MU7, SBGT initiation on RB Vent hi-rad, an increase in the detected gaseous radiation effluents that is a result of the event, or any radioactive liquid released beyond the Protected Area that is a result of the event.

6. WIND DIRECTION IS FROM: o. WIND SPEED mph.

(Data from 10 meter meteorological tower, available on PICSY.)

7. REPEAT: D THIS IS A DRILL D THIS IS AN ACTUAL EVENT (When communicating form, request a repeat back by one of the agencies.)

APPROVED: Time: Date (ED, RM, or EOFSS) (Time form approved) (Date form approved)

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 I Facility: SSES Date of Examination: 1/17/12 II

Exam Level: RO

SRO-I 0 SRO-U D Operating Test No.:

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) 1 System I JPM Title Type Code* Safety Function

a. CRD Mechanism/201003 Control Rod Withdrawals A,N,S 1

b. Perform HPCI Quarterly Surveillance/206000 A,N,S 2

c. Quarterly Turbine Valve Cycling/241 000 A,N,S 3

d. Core Spray System Shutdown/209001 N,S 4

e. PCIS/SDC restoration/223002 A, N,S 5

f. Manually Synchronize Diesel Generator B/264000 A,N,S 6

g. SBGT System Startup/288000 N,S 9

h. APRM Gain Adjustment/215005 N,S 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Venting Scram Air Header during A TWS D,E,R 1 i j. Maintaining RCIC Suction Source during SBO A, N,R 2

k. Secure Non-Class 1 E 250 VDC loads lAW EO-100-030 iN,E 6

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

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

(L)ow-Power 1 Shutdown ;::1/~1/~1 (N)ew or (M)odified from bank including 1(A) ?2/?2/?1 (P)revious 2 exams ::; 31 ::; 31 s 2 (randomly selected)

(R)CA ;:: 11 11 ~ 1 (S)imulator

ES-301 Control Room/l n-Plant Systems Outline Form ES-301-2 1/17/12 Facility: SSES Date of Examination:

Exam Level: RO D SRO-I SRO-U D Operating Test No.: 1 I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. CRD Mechanism/201003 Control Rod Withdrawals A,N,S 1

b. Perform HPCI Quarterly Surveillance/206000 A,N,S 2

c. Quarterly Turbine Valve Cycling/241 000 A,N,S 3

d. COfe Spray System Shutdown/209001 N,S 4

e. PCIS/SDC restoration/223002 A,L,N,S 5

f. Manually Synchronize Diesel Generator B/264000 A,N,S 6

g. SBGT System Startup/2880DO N,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Venting Scram Air Header during ATWS D,E,R 1

j. Maintaining RCIC Suction Source during SBO A,E,N,R 2

k. Secure Non-Class 1E 250 VDC loads lAW ED-100-D30 N,E 6

@ AIII~O and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-il SRO-U (A)ltemate path 4-61 4-6/2-3 (C)ontrol room (D)irect from bank :::;9/::;8/:S;4 (E)mergency or abnormal in-plant ;::1/:;::1/2:1 (EN)gineered safety feature - ! - / 2:1 (control room system)

(L)ow-Power / Shutdown ;::1/;::1/2:1 (N)ew or (M)odified from bank including 1(A) "2:.2/2:2/2:1 (P)revious 2 exams :::; 31 s 3/:s; 2 (randomly selected)

(R)CA "2:.1/:::::1/2:1 (S)imulator

Susquehanna Steam Electric Station Job Performance Measure Uncoupled Control Rod During Rod Withdrawals At Power JPM Designation: A Revision Number: 4 Date: 10/26/11 .

Note: This JPM is paired with JPM D with a staggered start Developed By: Chris Lall)l 4/15/11 Author Date Review By: Hedigan 01/05/12 Examiner Date Approved By: Caruso 01/05/12 Chief Examiner Date

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST INOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM I usage, revalidate JPM using steps 8 through 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by Examiner review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. ___ Date _ _ _ _ __

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, Examiner sign and date JPM cover page.

REVISION RECORD (Summary):

Rev 0 Rev 1: Editorial changes via comments from branch, and changed . .IPM such that alternate path begins on second withdrawn rod vice first 5/9/11 Rev 2: Added procedure step numbers Rev 3: Revised following licensee review Rev 4: Revised following licensee request to perform at higher power level to support JPM pairing JPM Setup Instructions:

1. Reset Simulator to Ie 391, approximately 76% power

2. Run scenario file JPMA.scn to Insert uncoupled rod malfunction (IMF mfRD1550074631) for control rod 46-31

3. Provide OP-156-001 Reactor Manual Control System

4. Provide copy of SO-156-007 Control Rod Coupling Check

5. Provide copy of JPMA Reactivity Manipulation Request and Control Rod Movement Sheet TASK STANDARD:

Successfully insert Control Rod 46 - 31 per ON-155-001, Control Rod Problems Rev 34 TASK CONDITIONS:

1. The plant is operating at reduced power after the crew inserted control rods per steps 185 - 177 of the CI~C book due to an Offgas problem.

2. The Offgas system problem has been corrected and condenser vacuum is restored to normal.

3. Reactor Engineering has provided the SRO with the approved Reactivity Manipulation Package to return the nine rods to their target positions.

4. CRD Hydraulic System is in operation in accordance with OP-155-001

5. RMCS is operational in accordance with Section 2.1 of OP-156-001

6. All rod movements shall be performed in accordance with NDAP-QA-0338

7. The reactivity briefing has been completed.

INITIATING CUE:

The SRO has directed you to complete the requested reactivity manipulations by withdrawing control rods per the Reactivity Manipulation Request and Control Rod Movement Sheet.

Information for Evaluator's Use:

UNSAT requires written comments on respective step.

Denotes CRITICAL steps.

Number any comments in the "Comment Number" column. Then annotate that comment in the "Comments" section. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local

operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

Operator's Nc:lme: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

D NLO RO 0 SRO STA SRO Cert JPM

Title:

Uncoupled control rod withdrawals at power JPM Number: A Revision Number: 4 KIA Number and Importance: 201003 A2.02 RO 3.7 SRO 3.8 Suggested Testing Environment: Simulator Actual Testing Environment:

Testing Method: Perform in Simulator Alternate Path: Yes Time Critical: No Estimated Time to Complete: 25 min. Actual Time Used: - - -minutes

References:

1. NUREG 1123, 201003 A2.02 RO 3.7 8RO 3.8

2. GO-100-002 Rev 71

3. ON-155-001 Rev 35

4. AR-104-001 Rev 31

5. OP-156-001 Rev 16

6. 80-156-007 Rev 10 EVALUATION

SUMMARY

1. Were all the Critical Elements performed satisfactorily? Yes No

2. Was the task standard met?

The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: Satisfactory 0 Unsatisfactory Comments:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Note: Any grade of UNSAT requires a comment.

Evaluators Name: _ _ _ _ _ _ _ _ _ _ _ _ _{Print)

Evaluator's Signature: Date: _ _ __

==

Description:==

TI1is JPM has the operator withdraw control rods for power ascension, and upon finding an uncoupled control rod (second withdrawn rod), has the operator attempt to re-couple and eventually fully insert and disarm the control rod.

Evaluator Note: The steps of OP-156-001 are listed for reference and tracking of applicant's actions.

Per OP-156-001 note: "This procedure section is Information Use; however. the steps must be performed in the order written. Operator training ensures the steps are performed in the proper sequence without procedure in hand".

NRC SSES INITIAL EXAMINA TlON JPMA NOTE: Critical Element(s) indicated by

in Performance Checklist.

PERFORMANCE CHECKLIST:

JPM Start Time _ _ _ __

ELEMENT STANDARD SAT UNSAT Comment Number

1. Obtains procedure and reviews Applicant may obtain OP-156 001, references section 2.4 and reads 2.4.1 Prerequisites and 2.4.2 Precautions

2. (OP-156-001 Step 2.4.3) Establish a Applicant establishes target target position that is one notch position of 48 less than the desired position.

(Exception: The withdraw of control rods to the FULL OUT position and those control rods with settle times greater than 30 seconds.)

3. (Step 2.4.4) Select control rod to be Applicant depresses rod select withdrawn continuously by pushbutton for rod (14-31)

Depressing corresponding CONTROL ROD SELECTION pushbuUons.

4. (Step 2.4.5) Observe: Applicant Observes:

a. CONTROL ROD SELECTION a. CONTROL ROD pushbuttons ILLUMINATED SELECTION

b. FULL CORE DISPLAY pushblJttons ILLUMINATED GREEN at ILLUMINATED selected location. b. FULL CORE DISPLAY

c. Present position of selected rod ILLUMINATED Indicated on FOUR ROD GREEN at selected DISPLAY on CRT and Standby location.

Information Panel 1C652. c. Present position of selected rod Indicated on FOUR ROD DISPLAY on CRT and Standby Information Pane11C652.

5. (Step 2.4.6) Depress and Hold Applicant Depresses and CONT W/DRAW ROD pushbutton AND Holds CONT W/DRAW ROD pushbutton AND

NRC SSES INITIAL EXAMINA TlON JPMA E.LEMENT STANDARD SAT UNSAT Comment Number

6. (Step 2.4.7) Depress and Hold Depresses and Holds W/DRAW ROD pushbutton WIDRAW ROD pushbutton Evaluator Note: During rod withdrawal, the applicant will likely receive AR-103 001 (C04) RBM ROD BLOCK and AR 104-001 (H03) ROD OUT BLOCK. This is caused by the expected change in local core power around the withdrawing control rod. Expected operator actions are to verify correct rod selected, verify position on power/flow map, and confirm with RE that adequate margin exists to thermal limits.

Roleplay as reactor engineer as necessary to inform applicant that adequate thermal limit margin for the control rod exists.

Applicant will de-select and re-select the control rod to clear the rod block alarm and continue with control rod withdrawal.

NRC SSES INITIAL EXAMINA TlON JPMA E:LEMENT ! STANDARD SAT I UNSAT Comment i

Number

7. (Step 2.4.8) Observe: Note: Additional expected

a. ROD INSERT light applicant actions per MOMENTARILY ILLUMINATES precaution 2.4.2.b of OP-156-001, "Nuclear

b. ROD WIDRAWG light instrumentation must ILLUMINATES be monitored during

c. CO NT W/DRAWG light any rod movement" ILLUMINATES Applicant Observes:

d. Withdrawal drive flow of approx. a. ROD INSERT light 2-3 gpm during control rod MOMENTARILY withdrawal on CRT FOUR ROD ILLUMINATES DISPLAY

b. ROD W/DRAWG light

e. Changing rod position indicated ILLUMINATES on FOUR ROD DISPLAY on CRT and Standby Information c. CO NT W/DRAWG light Panel 1C652 for selected rod. ILLUMINATES

d. Withdrawal drive flow of approx. 2-3 gpm during control rod withdrawal on CRT FOUR ROD DISPLAY

e. Changing rod position indicated on FOUR ROD DISPLAY on CRT and Standby Information Panel 1C652 for selected rod.

8. (SO-156-007 Step 5.3.1) Maintain Applicant maintains withdraw the WITHDRAW command or single signal to perform coupling notch withdrawal. Confirm the rod does check, notes control rod at not uncouple. Uncoupling is position 48, full out red demonstrated by: indicator is lit, and no ROD

a. Loss of position 48 OVERTRAVEL alarm.

AND

b. Loss of full out red indicator OR

c. ROD OVERTRAVEL alarm

NRC SSES INITIAL EXAMINA TlON JPMA ELEMENT STANDARD ! SAT UNSAT Comment Number

9. (Step 5.3.2) Depress Display Rods Applicant depresses test Full-in/Full-out test button and button and confirms red FULL Confirm the FULL OUT red OUT indicator is illuminated indicator ILLUMINATED. OR AND/OR Confirms control rod remains (Step 5.3.3) Confirm the control rod at position 48 on the 4 rod remains at position 48 on the 4 display rod display.

10. (Step 5.3.4) Record date and Applicant documents control initials in appropriate space for rod 14-31, date and initials for the control rod in COUPLING coupling check on Attachment CHECK on Attachment C, Page C i

1.

11. (OP-156-001 Step 2.4.3) Establish Applicant establishes target a target position that is one position of 48 notch less than the desired position. (Exception: The withdraw of control rods to the FULL OUT position and those control rods with settle times greater than 30 seconds.) i

12. (Step 2.4.4) Select control rod to Applicant depresses rod select be withdrawn continuously by pushbutton for rod (46-31)

Depressing corresponding CONTROL ROD SELECTION push buttons. i

13. (Step 2.4.5) Observe: Applicant Observes:

a. CONTROL ROD SELECTION a. CONTROL ROD pushbuttons ILLUMINATED SELECTION

b. FULL CORE DISPLAY pushbuttons ILLUMINATED GREEN at ILLUMINATED selected location. b. FULL CORE DISPLAY

c. Present position of selected rod ILLUMINATED Indicated on FOUR ROD GREEN at selected DISPLAY on CRT and Standby location.

Information Panel 1C652. c. Present position of selected rod Indicated on FOUR ROD DISPLAY on CRT and Standby Information Panel 1C652.

NRC SSES INITIAL EXAMINA TlON JPMA ELEMENT STANDARD SAT UNSAT Comment Number

14. (Step 2.4.6) Depress and Hold Applicant Depresses and CaNT WIDRAW ROD pushbutton AND Holds CaNT W/DRAW ROD pushbutton AND

15. (Step 2.4.7) Depress and Hold Depresses and Holds W/DRAW ROD pushbutton W/DRAW ROD pushbutton Evaluator Note: During rod withdrawal, the applicant will likely receive AR-103 001 (C04) RBM ROD BLOCK and AR 104-001 (H03) I~OD OUT BLOCK. This is caused by the expected change in local core power around the withdrawing control rod. Expected operator actions are to verify correct rod selected, verify position on power!flow map, and confirm with RE that adequate margin exists to thermal limits.

Roleplay as reactor engineer as necessary to inform applicant that adequate thermal limit margin for the control rod exists.

Applicant will de-select and re-select the control rod to clear the rod block alarm and continue with control rod withdrawal.

NRC SSES INITIAL EXAMINA TlON JPMA ELEMENT STANDARD SAT UNSAT Comment Number ALTERNA TE Pit TH BEGINS HERE ALTERNA TE PATH BEGINS

16. (Step 2.4.8) Observe: Note: Additional expected

a. ROD INSERT light applicant actions per MOMENTARILY ILLUMINATES precaution 2.4.2.b of OP-156-001, "Nuclear

b. ROD W/DRAWG light instrumentation must ILLUMINATES be monitored during

c. CO NT W/DRAWG light any rod movement" ILLUMINATES Applicant Observes:

d. Withdrawal drive flow of approx. a. ROD INSERT light 2-3 gpm during control rod MOMENTARILY withdrawal on CRT FOUR ROD ILLUMINATES DISPLAY

b. ROD W/DRAWG light

e. Changing rod position indicated ILLUMINATES on FOUR ROD DISPLAY on CRT and Standby Information c. CONT WIDRAWG light Panel 1C652 for selected rod. ILLUMINATES

d. Withdrawal drive flow of approx. 2-3 gpm Evaluator Note:~ Alarm AR-104-001 during control rod (H06) is an expected alarm for this JPM withdrawal on CRT FOUR ROD DISPLAY

e. Changing rod position indicated on FOUR ROD DISPLAY on CRT and Standby Information Panel 1C652 for selected rod.

17. (SO-156-007 Step 5.3.1) Maintain Applicant maintains withdraw the WITHDRAW command or single signal to perform coupling notch withdrawal. Confirm the rod does check, notes control rod not uncouple. Uncoupling is position becomes blank, demonstrated by: loss of the full out red

a. Loss of position 48 indicator. and receipt of the ROD OVERTRA VEL alarm.

AND

b. Loss of full out red indicator OR

c. ROD OVERTRAVEL alarm

NRC SSES INITIAL EXAMINA TlON JPMA ELEMENT STANDARD SAT UNSAT Comment Number

18. Annunciator response to ROD Applicant:

OVERTRAVEL [AR-104-001 (H06)] a. Acknowledges alarm

b. Reports alarm to Unit Supervisor

c. References alarm response for AR-1 04 001 (H06)

d. Notifies Shift Supervision

e. Performs ON-155-001 Evaluator Note: Candidate may recognize entry condition and directly enter ON-155-001

'Control Rod Problems', vice entry from AR.

19. Enter ON-'155-001 'Control Rod Applicant obtains ON-155-001.

Problems' recognizes symptoms for rod overtravel and proceeds to step 4.5 Evaluator cue: Perform the required actions

NRC SSES INITIAL EXAMINA T/ON JPMA ELEMENT STANDARD I SAT UNSAT Comment Number

20. (Step 4.5."1) IF Rod Overtravel Applicant Perform the alarm ANNUNCIATES with rod beyond following only once:

48, Perform the following only once: a. Insert rod (46-31) to 46

a. Insert rod to 46. by depressing

b. Withdraw rod to 48. INSERT pushbutton one time.

c. With Rod at position 48, Notch Rod OUT OR Continuously b. Withdraw rod (46-31) withdraw Rod. to 48 by depressing WITHDRAW AND pushbutton one time.

d. Confirm control rod is coupled c. With Rod at position by observing: 48, applicant Notches (1) POSITION 48 on Standby Rod OUT by Information Panel or other depressing available rod position WITHDRAW indication pushbutton one time AND OR Continuously withdraw Rod by (2) FULL OUT RED indicator on depressing and full core display holding CONT AND WID RAW ROD pushbutton and (3) Rod Overtravel annunciator depressing and is CLEAR.

holding W/DRAW ROD pushbutton.

d. Applicant will again receive the "Rod Overtravel" annunciator and recognize that the control rod is still uncoupled.

Applicant recognizes that rod is still uncoupled and proceeds to step 4.5.2

NRC SSES INITIAL EXAMINA TlON JPMA ELEIVIENT I STANDARD SAT UNSAT Comment i

Number

21. (Step 4.52) IF rod fails to couple Evaluator Note: Some through one performance of Step 4.5.1: roleplay as Unit Supervisor may be required if applicant

a. Promptly Insert rod to position requests/recommends 00.

inserting rod and contacting

b. Contact Reactor Engineering. Reactor Engineering. Direct applicant to continue with the

c. IF < LPSP power:

procedure, and notify applicant (1) Comply with TS 3.1.3 and that Reactor Engineering has 3.9.5 been contacted, and Tech Spec entries are being (2) Hydraulically Disarm HCU prepared.

lAW OP-155-001 Control Rod Drive Hydraulic System Applicant:

(3) DO NOT continue to Move a. Promptly Inserts rod rods until Reactor 46-31 to position 00 by Engineering has supplied depressing and new control rod withdraw holding the INSERT sequence. pushbutton.

Evaluator Note: Reactor power is above the Low Power Setpoint (LPSP). Step 4.5.2.c i is N/A i CUE: JPM is complete. i JPM Stop Time _ _ _ __

NRC SSES INITIAL EXAMINA TlON JPMA HANDOUT PAGE TASK CONDITIONS:

1. The plant is operating at reduced power after the crew inserted control rods per steps 185 - 177 of the CRC book due to an Offgas problem.

2. The Offgas system problem has been corrected and condenser vacuum is restored to normal.

3. Reactor Engineering has provided the SRO with the approved Reactivity Manipulation Package to return the nine rods to their target positions.

4. CRD Hydraulic System in operation in accordance with OP-155-001

5. RMCS operational in accordance with Section 2.1 of OP-156-001