ML14307B565

Draft Operating Exam (Section a) (Folder 2)

ML14307B565
Person / Time
Site:	Indian Point
Issue date:	10/29/2014
From:	Entergy Nuclear Indian Point 2
To:	Christopher Lally Operations Branch I
Shared Package
ML14190B006	List: ML14195A131 ML14251A240 ML14307B385 ML14307B521 ML14307B565 ML14308A052 ML14308A251
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Download: ML14307B565 (48)

Text

Appendix C Job Performance Measure Form ES-C-1 Worksheet Indian Point Unit Facility: 2 Task No: 2000660122 Task Title: Determine Reportability Requirements 2.1.18 Job Performance Measure SROAdmin KIA

Reference:

SRO 3.8 No: 1a

---

~~~=-----

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing :

X Simulated Performance Actual Performance Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

In preparation for 2-PT-M048, 480 Volt Undervoltage Alarm, the following Tech Spec LCOs were not met:

• 3.3.5 Loss of Power Diesel Generator Start

• 3.8.1 AC Sources Operating

• Surveillance W-19 is complete

• The unit is in Mode 3

• During the performance of 2-PT-M048 the normal feed breaker to bus 6A tripped.

• 21 and 22 EDGs started

• The normal supply breakers for 5A, 2A, and 3A tripped

• The Emergency Feed Breakers for safeguards busses 5A, 2A, and 3A closed and re-energized the buses.

• 21 AFW pumps started

• 21 and 22 CCW pump started

• 21 and 22 Service Water Pumps started Initiating Cue: You are the FSS and the Shift Manager has directed you to determine any additional Tech Spec actions and reportability requirements.

1 of6

Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials: Unti 2 Technical Specifications IP-SMM-LI-108, Event Notification and Reporting General

References:

Unti 2 Technical Specifications IP-SMM-LI-108, Event Notification and Reporting Time Critical Task: No Validation Time: 30 Minutes Task Standard: Applicable Tech Specs and Reporting requirements identified 2 of6

Appendix C Page3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

1. Performance Step: Obtain Correct Procedures Standard: Obtains Technical Specifications and IP-SMM-LI-108.

Comment:

2. Performance Step: Reviews Technical Specifications Standard: Determine No additional Tech Spec actions are required Comment:

...J 3. Performance Step: Determine Reportability using IP-SMM-ll-1 08 Standard: Determines 8 hr report due to valid actuation of AFW Item 59 (See item 49 for explanation) 1OCFR50. 72(b)(3)(iv)(A)

Comment:

...J 4. Performance Step: Determine who must be notified Standard: Identifies:

NRC Operations Center within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Corporate Duty Manager Public Service Commission (PSC)

Comment:

3 of6

Appendix C Page4 Form ES-C-1 Terminating Cue: JPM Complete 4 of6

Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UN SAT Examiner's signature and date: - - - - - - - - - - - -

5 of6

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The unit is in Mode 3 As part of the test, the following Tech Spec LCOs were not met:

• 3.3.S Loss of Power Diesel Generator Start

• 3.8.1 AC Sources Operating

• Surveillance W-19 is complete

• During the performance of 2-PT-M048, 480 Volt Undervoltage Alarm, the normal feed breaker to bus 6A tripped.

• 21 and 22 EDGs started

• The normal supply breakers for SA, 2A, and 3A tripped

• The Emergency Feed Breakers for safeguards busses SA, 2A, and 3A closed and re-energized the buses.

• 21 AFW pumps started

• 21and 22 CCW pump started

• 21 and 22 Service Water Pumps started Initiating Cue: You are the FSS and the Shift Manager has directed you to determine any additional Tech Spec actions and reportability requirements.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Indian Point Unit Facility: 2 Task No: 2000070122 Task Title: Review a Manual QPTR Calculation (4 Detectors 100%)

2.1.37 Job Performance Measure KIA

Reference:

---

SRO 4.6 - No: SRO Admin 1b Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing :

Simulated Performance Actual Performance X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Reactor power is stable at 100% power.

2. The RO has calculated a QPTR manually.

3. There is indication of a misaligned rod. The RO calculated a QPTR of 1.0643 and recommends a Power Reduction to s 81.7%.

4. No Physics testing is in progress.

Initiating Cue: You are the CRS and the SM directed you to review the QPTR and sign as SM Designee and , approve any required actions by Tech Spec identified including maximum allowable power operation and time limits.

Required Materials: Calculator General

References:

3-SOP-15.3, Quadrant Power Tilt Calculation DSR-48 Unit Two Quadrant Power Tilt Calculation Sheet 1 of 15

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 20 Minutes Task Standard: Calculation reviewed and errors corrected, identify incorrect TS actions.

2 of 15

Appendix C Page3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..../)

EVALUATOR NOTE:

Give the examinee the attached Detector Current Data Sheet and a DSR-48 form that has the proper normalization factors recorded.

EVALUATOR NOTE:

A detector Current Data Sheet with ANRT/8 and QPTT/8 is provided for grading this JPM. Allow examinee to complete all calculations and determine appropriate Tech Spec actions. The examinee may use a calculator.

1 . Performance Step: Obtain correct procedure and form DSR-48.

Standard: SOP 15.3, "Quadrant Power Tilt Calculation" Comment:

2. Performance Step: Check top and bottom detector currents recorded.

Standard: Checks Detector currents recorded from QPTR Data Sheet recorded Comment: For this QPTR calculation, the values for N42 top and N42 bottom were incorrectly entered in the wrong location. The current value for N42 top was entered in N42 bottom and N42 bottom was entered in location for N42 top.

Candidate may identify error at this time.

Candidate may elect to calculate independently and compare results.

3. Performance Step: Record Date, Time and Average Reactor Power Standard: Checks Current Date and Time and average Reactor Power of 100% recorded Comment:

3 of 15

Appendix C Page4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

4. Performance Step: DIVIDE each detector output by corresponding normalization factor Standard: Checks calculations:

• CALCULATES normalization ratio

• RECORDS on form DSR-48 Comment: Candidate may identify error at this time. Candidate may elect to calculate independently and compare results.

[See Key for actual values]

5. Performance Step: If three detectors are to be used in the calculation, change denominator from 4 to 3 Standard: Checks "4" for denominator on top and bottom average equations recorded Comment:

6. Performance Step: CALCULATE average normalized ratio for top and bottom Standard: Checks calculations:

• CALCULATES the top and bottom normalized averages

• RECORDS on form DSR-48 Comment: [See Key for actual values]

4 of 15

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 7 Performance Step: CALCUL.ATE Quadrant Power Tilt for top and bottom detectors Standard: Checks calculations:

• CALCUL.ATES the top and bottom QPTR by using the highest top (bottom) and dividing by the top (bottom) average

• RECORDS on form DSR-48 Comment: [See Key for actual values]

...J 8. Performance Step: RECORD highest Quadrant Power Tilt and appropriate signatures.

Standard: If Candidate does not identify the error, the QPTR will appear correct Comment:

5 of 15

Appendix C Page6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

...J 9. Performance Step: If quadrant power tilt exceeds 1.02 in either top or bottom of core, ensure requirements of Technical Specification 3.2.4, Quadrant Power Tilt Limits are met Standard: PERFORMS both of the following:

• COMPARES the calculated QPTR to Tech Spec 3.2.4

• DETERMINES that the calculated QPTR is GREATER THAN the Tech Spec allowable value of 1.02 Comment: Due to error in data entry, the Calculated QPTR is 1.0648. This would result in a power reduction to <80. 7%. This is a second error The actual QPTR is 1.0753. This would result in a power reduction to S 77.4%.

...J 10. Performance Step: DETERMINE Required Tech Spec Actions.

Standard: PERFORMS both of the following:

• REFERS to Tech Spec action 3.2.4

• DETERMINES the following actions are required:

1. Either QPTR is reduced below 1.02 OR

2. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,

a. Reactor Power must be reduced to below 77.5% ( ;t0.5%)

Comment: Additional Tech Spec actions will be required within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, however they are not part of the requirement for satisfactory completion of this JPM 6 of 15

Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

...J 11. Performance Step: DETERMINES QPTR CALCULATION IS NOT CORRECT Standard: Determines correct value for QPTR 1.0753.

Determines correct maximum power level 77.5%

Comment:

Terminating Cue: JPM Complete 7 of 15

Appendix C Page 8 Form ES-C-1 UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. 193 Previous SNSC #2545 11/5/98 (QT-20-31) DATE: """""IyOO~a;wy,___ _

SNSC REVIEW DATE TIME* 30 mjgntes ago AVE REACTOR PWR: I 00%

APPROVED (RE) DATE USING DETECTOR OUTPUT CURRENT APPROVED DATE Answer Key Incorrectly Calculated Errors Identified .

• Current QT number and Normalization Factors provided by Reactor Engineer.

1. Determine normalized ratios by dividing indicated detector current by normalization factor as follows:

£ITS] Technical Requirements Manual 3.2.A:

Channel Det Current Nor Ratio Channel Det Current Nor Ratio 41Top = 41T = 139.7 /*129.1= 1.0821 41 Bottom = 41B = 128.7 /* 122.5 = 1.0506 42Top=42T= ~* 136.6 = 1.0637 42 Bottom= 42B ~/* 144.3 = .8344 43 Top = 43T = 122.9 I* 118.3 = 1 QJ82 43 Bottom = 438 = 124.2 /* 119.3 = 1.0411 44 Top=44T= 89.4 /* 87.4 = I !!222 44 Bottom = 448 = 109.7 /*107.1 = I Q2!1J Answer Key Incorrectly Calculated Errors Tdenttfied

2. Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top = ANRT = 41T +:2T + 43T + 44~'-----

Average Normalized Ratio Bottom= ANRB = 41B +:28 + 43B + 44B~.;----

3. Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio.

£ITS] Technical Requirements Manual 3.2.A:

Quadrant Power Tilt Top = QPTT = Highest value of 41 T. 42T. 43T, or 44T ANRT QPTT= ~;e=(fjj)=---~~ ~"'""w...-7------------

4. The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of 1.0200. [ITS] Technical Requirements Manual 3.2.A:

Enter the Higher QPT(Top or Bottom)

Technical Specification Limit = 1.

AnswerKe I. If the quadrant power tilt exceeds the Tech. Spec. limits, the SM, OM, RE and GM-NPG shall be informed ASAP.

2. If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3).

RO: ________________________~S~M~:

Page 1 of1 8 of 15

Appendix C Page9 Form ES-C-1 UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. 193 Previous SNSC #2545 11/5198 (QT-20-31) DATE: ~T~oo~a~Y~---

SNSC REVIEW DATE TIMF> 30 mjputes ago AVE REACTOR PWR

• I 005 APPROVED (RE) DATE USING DETECTOR OUTPUT CURRENT APPROVED DATE

• Current QT number and Normalization Factors provided by Reactor Engineer.

I. Determine normalized ratios by dividing indicated detector current by normalization factor as follows:

[ITS] Technical Requirements Manual 3.2.A:

.ty acu ae An swer K ey CorrectiCIItd Channel Det Current Nor Ratio Channel Det Current Nor Ratio 41 Top=41T= 139.7 I* 129.1 = 1.0821 41 Bottom = 41B = 128.7 I* 122.5 = 1 05()6 42Top = 42T = 120.4 I* 136.6 = .8814 42 Bottom= 42B = 145.3 I* 144.3 = 1.0069 43 Top=43T= 122.9 I*~ = l Q;2~2 43 Bottom = 43B = 124.2 I* I19.3 = 1.0411 44 Top=44T= 89.4 I* 87.4 = 1Q222 44 Bottom = 448 = I09.7 1*107.1 = l.Q2~J

2. Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top = ANRT = 41T + 42T + 43T + 44T=__,1_,_,.<0><0"'6"'"

3 _______

4 Average Normalized Ratio Bottom= ANRB = 41B + 428 + 438 + 44B=_"-'1._,. 03...,0....7,_______

4 Answer Key Correctly Calculated

3. Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio.

[ITS] Technical Requirements Manual 3.2.A:

Quadrant Power Tilt Top= QPTT = Highest value of 41T. 42T, 43T, or 44T ANRT Value= I 0821 QPTT = ANRT = 1.0063 Quadrant Power Tilt Bottom= QPTB = Highest value of 41B, 428. 438. or 448 ANRB Value= I 0506 QPTB = ANRB = 1.0307 = - - - - - - L...IL.I.Ol.L-- - - - - - - - - - - -

4. The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of I.0200. [ITS] Technical Requirements Manual 3.2.A:

Answer Key Correctly Calculated Enter the Higher QPT(Top or Bottom) = _!_. JL 7 5 3 Technical Specification Limit = I. 0 2 0 0 NOTES:

I. If the quadrant power tilt exceeds the Tech. Spec. limits, the SM, OM, RE and GM-NPG shall be informed ASAP.

Answer Key Correctly Calculated

2. If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3).

RO: _ _ _ _ _ _ _ _ _ _ _ _ _ _S~M~:

Page 1 of I 9 of 15

Appendix C Page 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UN SAT Examiner's signature and date: - - - - - - - - - - -

10 of 15

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

1. Reactor power is stable at 100% power.

2. The RO has calculated a QPTR manually.

3. There is indication of a misaligned rod. The RO calculated a QPTR of 1.0643 and recommends a Power Reduction to< 80.5%.

4. No Physics testing is in progress.

Initiating Cue:

You are the CRS and the SM directed you to review the QPTR and sign as SM Designee and, approve any required actions by Tech Spec identified including maximum allowable power operation and time limits.

Appendix C Initial Conditions Form ES-C-1 UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. 193 Previous SNSC #2545 1115198 (QT-20-31) DATE: ~Iynd~a~v~---

SNSC REVIEW DATE TJME* 30 mjgntes ago AVE REACTOR PWR: I 00%

APPROVED (RE) DATE USING DETECTOR OUTPUT CURRENT APPROVED DATE

• Current QT number and Normalization Factors provided by Reactor Engineer.

I. Determine normalized ratios by dividing indicated detector current by normalization factor as follows:

[ITS) Technical Requirements Manual 3.2.A:

Channel DetCurrent Nor Ratio Channel DetCurrent Nor Ratio 41 Top=41T= 139.7 I* 129.1 = 1.0821 41 Bottom= 41B = 128.7 I* 122.5 = 1.0506 42 Top=42T= 145.3 I* 136.6 = 1.0637 42 Bottom = 42B = 120.4 I* 144.3 = .8344 43 Top = 43T = 122.9 I* 118.3 = 1 QJ82 43 Bottom = 43B = 124.2 I* 119.3 = 1.0411 44 Top=44T= 89.4 I* 87.4 = 1Q222 44 Bottom= 44B = 109.7 1*107.1 = I Q2~J

2. Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top = ANRT = 41T + 42T + 43T + 44T=__,_1""'.0o:::5.:..19"---------

4 Average Normalized Ratio Bottom= ANRB = 41B + 42B + 43B + 44B=___,.~98""7...,6"---------

4

3. Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio.

[ITS) Technical Requirements Manual 3.2.A:

Quadrant Power Tilt Top = QPTT = Highest value of 41 T, 42T. 43T. or 44T ANRT Value= 1.0821 QPTT = ANRT = 1.6519 1.0287 Quadrant Power Tilt Bottom= QPTB = Highest value of 41B. 42B. 43B, or 44B ANRB Value= 1.0506 QPTB = ANRB = .9876 - -~--~'.:..::*0~63~8~-----------------------

4. The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of 1.0200. riTS) Technical Requirements Manual 3.2.A:

Enter the Higher QPT(Top or Bottom) = .L _Q_ _§_ .1.. ..§....

Technical Specification Limit = 1. 0 2 0 0 NOTES:

1. If the quadrant power tilt exceeds the Tech. Spec. limits, the SM, OM, RE and GM-NPG shall be informed ASAP.

2. If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3).

RO: __________________________~S~M~  :

Page 1 of 1

Appendix C Initial Conditions Form ES-C-1 Detector Current Data Sheet for QPTR Calculation Average Reactor Power 100%

Excore Instrument Detector "A" Detector "B" N-41 139.7 128.7 N-42 120.4 145.3 N-43 122.9 124.2 N-44 89.4 109.7

Appendix C Initial Conditions Form ES-C-1 UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. 193 Previous SNSC #2545 11/5/98 (QT-20-31) DATE: ~I~od~a~v~---

SNSC REVIEW DATE TIME* 30 mjgutes ago AVE REACTOR PWR: 100%

APPROVED (RE) DATE USING DETECTOR OUTPUT CURRENT APPROVED DATE

• Current QT number and Normalization Factors provided by Reactor Engineer.

1. Determine normalized ratios by dividing indicated detector current by normalization factor as follows:

(ITS] Technical Requirements Manual 3.2.A:

Channel Det Current Nor Ratio Channel Det Current Nor Ratio 41 Top=41T= /* 129.1 = 41 Bottom = 41B = ,. 122.5 =

42 Top = 42T = ,. 136.6 = 42 Bottom= 42B = /*144.3 =

43 Top=43T= ,. 118.3 = 43 Bottom = 43B = ,. 119.3 =

44 Top-44T- ,. 87.4 - 44 Bottom= 44B = /*107.1 =

2. Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top = ANRT = 41T + 42T + 43T + 44T=

4 Average Normalized Ratio Bottom= ANRB = 41B + 42B + 43B + 44B=

4

3. Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio.

(ITS] Technical Requirements Manual 3.2.A:

Quadrant Power Tilt Top = QPTT = Highest value of 4 IT. 42T. 43T. or 44T ANRT Value=------

QPTT = ANRT = 1.0519 Quadrant Power Tilt Bottom= QPTB = Highest value of 41B, 42B, 43B, or 44B ANRB Value= _______

QPTB = ANRB = .9876 =

4. The higher of the two quadrant oower tilts should be less than or equal to the Technical Specification Limit of 1.0200. [ITS] Technical Requirements Manuai3.2.A:

Enter the Higher QPT(Top or Bottom)=

Technical Specification Limit 1. 0 2 0 0 NOTES:

I. If the quadrant power tilt exceeds the Tech. Spec. limits, the SM, OM, RE and GM-NPG shall be informed ASAP.

2. If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3).

Appendix C Initial Conditions Form ES-C-1 RO: _________________________S~M~  :

Page 1 of l

Appendix C Job Performance Measure Form ES-C-1 Worksheet Indian Point Unit Facility: 2 Task No: 2000340122 Task Title: Identify Isolation Boundaries and Required Actions High Pressure Fire Protection 2.2.41 Job Performance Measure SRO- 3.9 KIA

Reference:

---

No: SRO Admin 3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

X Simulated Performance Actual Performance Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• The unit is operating at 100% power

• Flushing of fire hydrants in the transformer yard is underway.

• #25 HP Hydrant and its associated PIV cannot be closed

• Water is not spraying on any electrical equipment.

Initiating Cue: You are the CRS and you have been directed to:

• determine the valves that must be closed to isolate the leaking hydrant

• identify affected components

• determine compensatory actions.

Required Materials: None 1 of 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet General

References:

SA0-703, Fire Protection Impairment Criteria and Surveillance 9321 -F-4006 Yard Fire Protection Piping 227551, Fire Protection System Diagram Details Sheet 1 227552, Fire Protection System Diagram Details Sheet 2 227553, Fire Protection System Diagram Details Sheet 3 227554, Fire Protection System Diagram Details Sheet 4 Time Critical Task: No Validation Time: 45 Minutes Task Standard: Identify isolation boundaries, affected components, Required Action and Completion Time for impaired condition.

2 of 10

Appendix C Page3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)

1. Performance Step: Obtain SA0-703 and required prints.

Standard: Obtains procedure and prints Comment: Location of procedure and prints is not required for this JPM. Hand candidate the procedure and prints

..J 2. Performance Step: Identify Isolation Boundaries Standard: Identifies the following valves to be isolated:

o FP-632 High Pressure Hydrant Header Stop o FP-606 High Pressure Header Loop Isolation (In 138KV Yard North Manhole) o FP-724 PAB Supply Stop (West of PAB)

Comment: FP-616, Electric Tunnel Deluge Supply Stop (Southeast Comer Transformer Yard) may be identified. This is not required; however, it is not incorrect to isolate.

v3. Performance Step: Identifies affected equipment Standard: Identifies the following affected equipment o High Pressure Hydrants #23, #24, #25, #26 o Electrical Tunnel Deluge o PAB Hose Station (Alternate supply will maintain hose pressure. This is not required for evaluation for compensatory actions Comment:

3 of 10

Appendix C Page4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

...J 4. Performance Step: Identifies Required Actions from SA0-703 Standard: Identifies the following Required Actions o 2.a.3 High-Pressure Water Fire Protection System (Not Critical) o 3.a.1 Fire Protection Spray Sytstems (Includes sprinkler systems and deluge systems) o 4.a Fire Hose Stations and Hydrants #25 o 4.b Fire Hose Stations and Hydrants (Not #25)

See Key for Required Actions Comment:

Terminating Cue: JPM Complete 4 of 10

Appendix C Page 5 Form ES-C-1 A

1. 24 H .P. HYDRANT -

TO CLEAN ANO DIRTY OIL TAI<-

<(

o::"'

JO

<0 1- ~

CONDENSER #22 &

0::

w 0

0 ~ ~

1- 0- 10"

... INTAKE STilUCTl'RE

< "' z;;'i

, - - - - - - -- M

~ "' ~--"'

g

..

w TO BOILER FEED PUW OElll(;E FP-5 12 SEE TYP. DELUGE VALVE STAT. &. 126 OET. *p* O'~G. A227552 TO SEAL OIL UNIT DELUGE SEE TYP. C<:LLGE VALVE STAT. t OET. " L' OWG . A227552 FP-:118

~ TO TRANSFOR>1=.R DELUGE VALVE SEE TYP. OELLGE VALVE STAT. &

on . *w oWG. A227552 I

ELECT. Ttn.'EL OELU!iE SEE OET. "B" OWG . A22755 1 CONTROl BLDG .

TANK FILL LINE RISER DET . " A" TH! S OWG.

- 6 " RISER TO ELEV. I 47 "

SEE 08" . "A " THIS O'oiG.

STAIR fL - FI I 10*

Blue Affected Component Red Isolation Boundaries 5 of 10

Appe_ndix C Page 6 Form ES-C-1 ADDENDUM I FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA SA0-703 Page 2 of 23 REV34

!lE~BIPTIQt:l BE!J!.!IBO!!EtF l!~L.ICA6!L!IY IMMIBE!l ~Qt:l.O!IIQ~ BEQ!JIREQ 1\CTION 1\CT!Qt:l IIME 1

2. 1 High-Pressure a.1 t:IU 1Hmotor-driven hre main a.1 Alai! tim~. a.la One or bo:h mo1or driven fire main a.la R~:ore 10 fLI!Ciional status. a. l.a 'Mlhi'l/ days.

Water Fire ~ter p~.m~ (1 1FMBP g boosterp~.m~ (1 1FMBP and/or 12FMBP) a.1.b a. l b Protection 12FMBP) mD cf-1-driven fire 0111 of service a.1.c a.l c System 1U11P (DFP) funaionlll and QB.

properly~ to me hi~-

lmp!lired ~we fire header. Refer to a.lb The cf5el-driven pu!1'f' (DFP) M of ccr<<.ions 2.a.1.a Nrxes Z. Z. a ;nJ Z.Z.c fa serw:e.

and 2.a.2 may addirional glidance. QB. .

exi~t concurreNiy, a.lc h delemlined by FP ~-

lmp!lired condi:ions 2.a.1.b Refer to Nae Z.Z.a fa gOOilfiCe.

and 2.a.2 may a.l Amirimum avarlable water a.L A! all tim~. a.£ One water si.Wiy out of service. a.£ Res:ore 10 fllldional ~tall~$ .

exi~t COI'lal/reMy, a.2 *WJMldays.

volume of 360,000 gallons conlM!ed in me City Water Tank Refer to Nrxe Z.Z.b fa gidJfiCe when the Impaired and 300,000 ga!lons contained 11'1 FWST level insromm clmne/ a tank eoncfilions 2.a.1.c and 2.a.2 may 1fle Fire Water Storage Tank for refill cap:JlXfry is mpaired.

fue protection pu'POIO~.

exist concurreNiy Refer to Nae Z.Z.b fa addiianal Refer to Not: Z a.J No !~~Ping and v!!lves necessary a.J Alall ti~. a.J Ally vlllve or pipe nec~~ill'f to supply a.J See Required Aaion for specifiC fixed a.J Seeoo~

for adcftion.'li for proper funclioning c:f any fixed a~c suppressiOI'I systems or automatic -.~ion syslem or hose Aclion Tme.

guidance por1ion of the ~ern reqlired for ho$e s1~ants protec1ing safety- stations.'hydt~ served by the portion of pro!eCtlcfl of safety-rela:ed or related or safe---.hutdcwn related areas the sy;tem ~~ is illlailed.

safHiutdown systems CIUl of service.

functional. ReferrJ Nae l 2 .cfrr addirionalglic/ance.

b. Hi;l\1lressure water fire b. At all times. b.1 With the high-pressure water flle b.t All alternate fire pro:ection S)'Stem dlaH b.t Wlllin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

protection sys-:ern Ulctional as protection s~em impaired in a manner be established.

required by 2.a.1 and 2.a.2. oth<< !han permitted by 2.a.1 or 2.a.2.

NOTE: Expiri!tion of the Aaion rtme for Items 2.a.1 and 2.a.2 b.l t-:equired Aaion and ~ted Adion bLa 1!e in MUUI:: J. b.l .a Wi:lln j() hours.

~NOT teqUire en1ry into Item Time c{ Impaired Con61ion b.1 noc met. ~

2.b.

b.2.b Be in MODE 5. b.2.b Wlllin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

~ The provisions of paragraph 4.6 SHALL be followed if the specified "Action Time" for ANY Item in the Table is exceeded.

6 of 10

Appendix C Page 7 Form ES-C-1 ADDENDUM I FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA SA0-703 Page 3 of 23 REV34 llE~BtrnQ~ BEQ!.!IBE:ld~:tfi A~LI~ABlLITI lMPlliBEQCQ~ll!I I OO BEQ!.!IREil A~TIO~ ~TIQHTIME '

3. Fire Protection a. l The Electrical TUMel Fire a. V.,enever safely-related cr safe. a. My spray system impailed. a.l AdditiOMl tile hoGe(s) shall be provided a.. l 'Mllln 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Spray Systems Protecral Wa:et Spray System dlllclov.n rela1ed equipmem in the ancllabled to ~;erve the affected (Includes (El-33 ft. Caltro!Building io El- area is required to be operable. location(; ) from a functional hose sprinklEr 68ft. PAS

• Fire Zone 32A) shall station(c) or hydrMI(s). Refer t1 Nate 2.3 systems and be funaiClnal far adcff.ioroll}itknce.

deluge sySiell15)

~

a.£ The DieSel Genera:cr SilkEn; Refer to Note 2.0 Water Spray Sys(elll (in EDG a:J. The impaired spray sys1em(s) shal be a.£ 1 Wi:lin 14 days.

for adcftionJI Blilding

• Fe Zone 10) shall be reslored to functional statui;.

gridJnce functioMI.

a.3 Verify adonicnal compensa!ory fire hose is a.J Every 90 : 7 days staged as teqUired by a. l above

b. The spray cystems lis:ed on b. 'h'henever equlptl1etll mthe area 15 b. My spray systemimpaired. b.l.a I Es!ablish a 4-boll' fire w~ tour to b.l  ! 'Mlhn c hOurs.

Table l-3 shall be functional. required io be operable. i,.;pect me affected fire zcne(s).

.00, b.1.b Hfie affected zone is equipped with a fire detedion sys!etn (see Table 1-l ), verify thai the fw detecticln equipment in the zone is Nnaional.

.00, b.1.c Additional fue hose(s) shall be provided to serve the afleo:ed location(s) fran a funclional hoGe smlion(s) ot hydrant(s).

Refer to Nrxe 2.3 fa addi!icml glidJnce.

~

b.l I ReslOie to funaional status. b.2 'Mllin 30 clays.

~Th e provisions of paragraph 4.6 SHALL be followed if the specified "Action Time* for ANY Item in the Table is exceeded .

7 of 10

Appendix C Page 8 Form ES-C-1 ADDENDUM I FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA SA0-703 Page 4 of23 REV 34 I:!~~Rie!IQ~ REQ!.!IREMErti A~Lii;A!l!LIIi IM~AIBEI:! ~Qt:I[2!!1 Qt:l RfgUIBEQA!:;TIQN AQ:IOrt !1ME 1

14. Fire Hose a. Fire hose sta1rons and hydrants a. V'Jhenever safe'!y-teiated cr safe. a. My fire ho5e staucn or hydrant liG!ed on a.1 Additional fue hoGe(s) shall be p!Ovided a.. l Whtin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

St&ions arxl llhcMn en Table l-4 shall be shutdcwm rela1ed equipment in the Tabl e l *4is~. and labled to serve lhe affected Hydrants functional. areas p!Otected by the hcr..e &latiom locaticn(s) from an fll'ldional hose and hydrants is te<pired to be staticn;s) cr hydra~t(s). Refer 1:1 Nrte2.3 Refer to Noe 2.o operable. fiX Jdcitioml rpdarrce.

foradciioflo')/ Atl2 glid.lrrce a:L Ihe inpailed ~eni shaMbe res:ored a..'J. Wllhill14 cia~.

to funaicnal!iiaiU$.

a.J Verity add\ticnal compensa:ory fire hose is a.J Every 90 :7 days t;taged as required by a. l aboo;e

b. Fire ho5e stations and hydran;r; b. Whenever equipment protected by b. My hi~-pressure fire hose ~tion cr b.1.a Es:abli&h a 4-hour file watch tour to b.l 'Mlhi:nllhours.

on the high-pressure fire loop 1he hoGe slalials and hydrants in die hydrant. than ~e listed on Table inspect die alfec1ed fire zcne(s).

~than those llhown on Table area is required to be operable. 1-4 ~ impaired. .cB.

l-4 r;hal be Mctional.

b.1.b If lhe affecled zone is equipped with a fire NOTE: The hose stlJiion en !he detectioo sys:em (see Tabies 1-1and 1-2),

roof ci the FSB and 1he law- verify lhai 1he fire detection equipment in pressure hydrants in the City !he zone is functional .

Water Sys:em are NOT INClUDED in this Mlctionality m

requirement. b.1.c Additional fue hoGe(s) shall be p!OVided to serve lhe affeaed locaticn;s) from a fundional hose s1a1ion(s) 01 hydrant( c).

Refer to Nrte 2.3 fiX adclitiorol glid.lnce.

Mil b1 The inpaired ~eni shal be res:ored b.2 'Mlhill30days.

to functicnal!iii!IIS.

Note: The provisions of paragraph 4.6 SHALL be followed if the specified "Action Time" for ANY Item in the Table is exceeded.

8 of 10

Appendix C Page 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts :

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - -

9 of 10

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The unit is operating at 100% power

• Flushing of fire hydrants in the transformer yard is underway.

• #25 HP Hydrant and its associated PIV cannot be closed

• Water is not spraying on any electrical equipment.

Initiating Cue: You are the CRS and you have been directed to:

• determine the valves that must be closed to isolate the leaking hydrant

• identify affected components

• determine compensatory actions.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Indian Point Unit Facility: 2 Task No: 2000240122 Task Title: Review a liquid Radioactive Release for #13 liquid Waste Distillate Storage Tank 2.3.6 Job Performance Measure KIA

Reference:

SRO

---

~~~~----

3.8 No: Admin 4 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing :

Simulated Performance Actual Performance X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

1 of 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initial Conditions:

• The Unit is operating at 100% power.

• Liquid Waste Distillate Storage Tank #13 is to be discharged, tank level, as reported by the NPO, is 97 inches.

• LWDST has been isolated.

• R-54 source check failed.

• 6 Circulating Water Pumps are operating at slow speed.

• No dilution flow is borrowed from Unit 3.

• A Manual Radioactive Liquid Release Permit was prepared.

• Additional Data:

Permit Number 070300 TankiD 13WDST Initial Tank Level 97 Pre-release volume 22972 Recirculation Rate 150 gpm Recirc Start- Today 01:00 Recirc Stop Today 05:45 Chern Sample Number 4807 Sample DatefTime Today 05:30 Total Gamma Activity 4.0E-5 ADC 5.31E-7 ppm Boron in tank 849 Initiating Cue: You are the CRS and the SM has directed you to review the Manual Liquid Release Permit for 13 WDST in accordance with 2-SOP-5.1 .5, Calculation and Recording of Radioactive Liquid Releases Required Materials: Calculator General

References:

2-SOP-5.1.5, Calculation and Recording of Radioactive Liquid Releases Time Critical Task: No Validation Time: 30 Task Standard: Reviews manual calculation and identifies errors. Does not approve release.

2 of 11

Appendix C Page3 Form ES-C-1 Performance Information (Denote critical steps with a check mark --./)

1. Performance Step: Obtain Correct Procedure Standard: Obtain 2-SOP-%.1.5, Calculation and Recording of Radioactive Liquid Releases Comment: Give the candidate the procedure.

2. Performance Step: Review Precautions and Limitations Standard: Reviews Precautions and Limitations Comment:

--./ 3. Performance Step: Record the following Standard: Permit Number Tank to be released Conservative estimate of volume to be released Recirculation rate and date/time of recirculation start/stop Radiochemistry analytical results Sample Number Sample Date/Time Total Gamma Activity in tJCi/ml Allowed Diluted Concentration ppm Boron in the tank Comment: Observing the NOTE before step 4.3.2.4 the candidate should determine that the tank has not been recirculated for adequate time.

The tank should be recirculated for 306 minutes. It has only been recirculated for 285 minutes. The candidate must identify that the tank needs to be recirculate for an additional 21 minutes.

3 of 11

Appendix C Page4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...f)

4. Performance Step: Verify from Chemistry the total gamma activity WITHOUT noble gas is less than 5.0E-5 JJCi/ml.

Standard: Observes the value is 4.0E-5 given in initial conditions Comment:

5. Performance Step: Record the pre-determined dilution flow rate (B) for this release in gpm, from Step 4.1.5.

Standard: Records 504,000 based on 6 Circulator at low speed given in initial conditions.

Comment:

6. Performance Step: Calculate the pounds of Boron in tank AND Maximum Allowable Chemical Release Rate (Rc)

Standard: Determines 162.5+/- 0.5 is correct Comment:

7 Performance Step: Calculate the Permissible Radioactive Release Rate (Rr)

Standard: Determines 6691 is correct Comment:

4 of 11

Appendix C PageS Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)

8. Performance Step: Determine the most restrictive release rate Standard: Determines 250 is correct Comment:

..J 9. Performance Step: Determine alarm settings if effluent radiation monitor is in service.

Standard: Determine effluent monitor is INOPERABLE per ODCM surveillance requirement 3.3.1.3.

Comment:

v10. Performance Step: Does not approve release permit Standard:

Comment:

5 of 11

Appendix C Page6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

...J 11. Performance Step: Make recommendations Standard: Tank must be recirculated for an additional 21 minutes to satisfy 306 minutes.

Verify compensatory actions for inoperable radiation monitor

• Two grab samples must be obtained after required recirc time

• Two double verified valve line ups SHALL be documented on photocopy of this Section AND photocopy of Section 4.12(2-SOP-5.1.3) to be forwarded to CCR for attachment to Liquid Radioactive Release Permit for this release.

• Double verify release calculation

• An NPO SHOULD be present on the Support Facility Nuclear Side throughout the discharge Comment: The first three compensatory actions are required. The third action is a "should" perform thus not required and NOT critical.

Terminating Cue: JPM Complete 6 of 11

No: 2-SOP-5.1.5 Rev:38 CALCULATION AND RECORDING OR RADIOACTIVE LIQUID RELEASES Page 16 of 23 ATTACHMENT 1 EXAMPLE RADIOACTIVE LIQUID RELEASE PERMIT Pa e 1 of 1 PERMIT# 07300 TANK 10 13WDST RECIRC __,_T"""od,a~y__ (Date) 01 :00 Recirc time is RATE : _ _..:..::15=0__ gpm inadequate it

__,_T"""od"'"'a~y_ _ (Date) 05:45 should be 306 Chemistry minutes (5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Sam le No. 4807 Toda (Date) and 6 minutes) min limit of SMM-CY-001: Sample time too early Total Gamma Activity _..:.;4-=0=E-5-=-_ _ _IJCilml Allowed Diluted Concentration (ADC) 5.31E-7 11-'------...----'

_--'=-6_ Unit 2 Circulators TOTAL DILUTION FLOW (T) --=504:..=,0=0=0_ _(GPM} From: --=0- Unit 3 Circulators

--=0- Service Water Pumps BORON: 849 X 22972 x 8.33E-6 = 162.5 +/- .5 pounds ppm B tank vol M. gal Maximum Chemical Release Rate (Rc} = ( 504,000 x 1 ppm } + 849 = 593.6 +/- .5 gpm Avail Oil Flow (B), gpm ppm B Radioactive Release Rate: (Rr} = ( 504,000 x 5.31 E-7 } + 4.0E-5 = 6691 gpm Avail Oil Flow (B), gpm ADC, uCilml Gamma Act (C), uCilml --==-=---

Most Restrictive Relea Rad Monitor# 54 Maximum Alarm Setpoint = (;:--~5~04~,00!!!!!:0~~~~¥~b-!~~~~.....,....,....,...- = 1.07E-3 uCi/ml Avail Oil Flow (B), gpm Most Restrictive Release Rate (R), gpm The initial Actual Alarm Set int = 4.0E-5 uCi/ml Warn Set int= 3.0E-5 conditions DISCHARGE FLOW METER & RECORDER OPERABLE _lL_YES NO (IF NO, COMPLETE AITACHMENT3) identified R-54 source check Release Authorized By: - - - - - - - - - - - - - - - - failure i.e.,

INOPERABLE RELEASE INITIATED: _ _ _ _(Date) _____ Also need RELEASE TERMINATED: _ _ _ _(Date) _____ ( Attachment 3 FINAL TK LEVEL: _ _ (Inches) ---~gal TOTAL VOLUME RELEASED ----~al Remarks:

Appendix C PageS Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response :

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The Unit is operating at 100% power.

• Liquid Waste Distillate Storage Tank #13 is to be discharged, tank level, as reported by the NPO, is 97 inches.

• LWDST has been isolated.

• R-54 source check failed.

• 6 Circulating Water Pumps are operating at slow speed.

• No dilution flow is borrowed from Unit 3.

• A Manual Radioactive Liquid Release Permit was prepared.

• Additional Data:

Permit Number 070300 TankiD 13WDST Initial Tank Level 97 Pre-release volume 22972 Recirculation Rate 150 gpm Recirc Start- Today 01 :00 Recirc Stop Today 05:45 Chern Sample Number 4807 Sample Dateffime Today 05:30 Total Gamma Activity 4.0E-5 ADC 5.31E-7 ppm Boron in tank 849 Initiating Cue:

You are the CRS and the SM has directed you to review the Manual Liquid Release Permit for 13 WDST in accordance with 2-SOP-5.1.5, Calculation and Recording of Radioactive Liquid Releases. Recommend corrective actions if necessary.

No: 2-SOP-5.1.5 Rev: 38 CALCULATION AND RECORDING OR RADIOACTIVE LIQUID RELEASES Page 16 of23 ATTACHMENT 1 EXAMPLE RADIOACTIVE LIQUID RELEASE PERMIT (Page 1 of 1)

INITIAL PERMIT# 070300 TANK 10 13WDST Tank Levei:J!Z_ (Inches) 22972 Volume (V), gal RECIRC Recirc Start: Toda~ (Date) 01 :00 (Time)

RATE : 150 gpm Recirc Stop: Toda~ (Date) 05:45 (Time)

Chemistry Sample No. 4807 Sample Collection : Todav (Date) 05:30 (Time)

Gamma Activity without Gas and Tritium is less than the admin limit of SMM-CY-001 : Yes I No Total Gamma Activity 4.0E-5 1JCi/ml Allowed Diluted Concentration (ADC) 5.31E-7 1JCi/ml 6 Unit 2 Circulators TOTAL DILUTION FLOW (T) 504,000 (GPM) From: 0 Unit 3 Circulators 0 Service Water Pumps BORON: 849 X 22972 x 8.33E-6 = 162.5 + .5 pounds ppm B tank vol (V), gal Maximum Chemical Release Rate (Rc) = ( 504,000 x 1 ppm) + 849 = 593.6 +/- .5 gpm Avail Oil Flow (B), gpm ppmB Radioactive Release Rate: (Rr) = ( 504,000 X 5.31 E-7 ) + 4.0E-5 = 6691 gpm Avail Oil Flow (B), gpm ADC, uCilml Gamma Act (C), uCi/ml Most Restrictive Release Rate (R) = 250 gpm (pump capacity most limiting)

Rad Monitor# 54 SOURCE CHECKED _x_ OPERABLE _!_YES - - NO (IF NO. COMPLETE ATT 3)

Maximum Alarm Setpoint = ( 504,000 X 5.31 E-7 ) + 250 = 1.07E-3 uCi/ml Avail Oil Flow (B), gpm ADC, uCilml Most Restrictive Release Rate (R), gpm Actual Alarm Setpoint = 4.0E-5 uCilml Warn Setpoint = 3.0E-5 uCilml DISCHARGE FLOW METER & RECORDER OPERABLE _!_YES - - NO (tF NO, COMPLETE ATTACHMENT 3)

Release Authorized By: (Date)

RELEASE INITIATED: (Date) (Tome)

RELEASE TERMINATED: (Date) (Time)

FINAL TK LEVEL: _ _ (Inches) gal TOTAL VOLUME RELEASED aal Remarks:

Appendix C Job Performance Measure Form ES-C-1 Worksheet Indian Point Unit Facility: 2 Task No: 1500010522 Task Title: Classify Emergency Events Requiring Emergency Plan Implementation (Time Critical)

KIA

Reference:

2.4.38 Job Performance Measure SR0-4.4 No: SROAdmin 5 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing :

X Simulated Performance Actual Performance Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

1 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initial Conditions:

The Current Time is 0223 The Unit was operating at 100% power At 0200

• A small feedwater break occurred on the suction to 21 MBFP

• The crew attempted to trip the reactor, but the reactor trip breakers failed to open

• The crew is performing actions in FR- S.1, Response to Nuclear Power Generation/ATWS

• The Turbine was tripped

• Reactor Power is 42% and lowering.

At0204

• Both Main Boiler Feed Pumps were tripped

• All AFW Pumps started At 0206

• Conventional NPO reports that he is unable to trip the reactor locally.

At 0210

• A steam break occurs upstream of PCV-1139, 22 AFW Pump Steam Supply Pressure Control Valve

• All SG Wide Range levels are 45% and lowering At 0217

• The harsh environment in the ABFP room caused both Motor Driven AFW pumps to trip.

At 0223 (NOW)

• The conventional NPO reports that the Rod Drive MG sets are secured and the reactor is tripped.

Meteorological Conditions:

• Wind Speed: 2.2 meters/second

• Wind Direction: 55 degrees @ 10 meters

• Stability Class: B Initiating Cue:

You are the CRS and the SM is unable to get to the control room. Classify the event and complete the Radiological Emergency Data Form.

Required Materials: EAL Wall Chart.

2 of7

Appendix C Job Performance Measure Form ES-C-1 Worksheet General

References:

IP-EP-115 IP-EP-120 IP-EP-210 IP-EP-410 Time Critical Task: Yes (Declare event in 15 minutes and Initiate notification within 15 minutes of declaration)

Validation Time: 30 min Task Standard: Proper E-Pian Classification and Part 1 form properly filled out.

3 of7

Appendix C Page4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)

1. Performance Step: Obtain correct procedure IP-EP-120 or EAL chart Standard: Give candidate Wall Chart Comment:

...J 2. Performance Step: Evaluate Initiating Cues to determine a GE classification applies.

Standard: GENERAL EMERGENCY EAL#SG2.1 Comment: This action is time critical Mark Time when Declaration is made.

...J 3. Performance Step: Complete "New York State Radiological Emergency Data Form, Part 1" Standard: Complete IP-EP-115 Comment: Critical elements on Part 1 form are marked with an asterisk

...J 4. Performance Step: Direct Communicator to initiate notification.

Standard: Hand completed Part 1 form to evaluator and direct them to initiate notification.

CUE: Acknowledge direction to initiate notification.

Comment: This action is time critical.

Terminating Cue: JPM Complete 4 of?

• Appendix C PageS Form ES-C-1

-r' --

New York State Indian Point Energy Center RAD10t0GICAL EMERGENCY OATAFORM -=- PART I . NotificaHo~ tr l I 1. This is an: \._ EXERCIS.§/ ACTUAL EMERGENCY at the Indian Point Energy Center The Emergeng: A . Unusu::ll Fvent B. Alert C . Site Area Emergency I

Emerge~~

Classification is:

(£. General E. Emergency Terminated I

!

2.

1 1

This Emergency Classification declared on : ~\(

{Date) at Cuf.tEIJr TIM G (Time 24 hr clOCk)

• II Release of Radioactive Materials due to the Classified Event:

To Atmos(2here:

I To Water:

3.

~Rele~.¥- ~ORelea;) ~

B. Release BELOW Federal Limits B~ase BELOW Federal Limits C. Release ABOVE Federal Limits C. Release ABOVE Federal Limits D. Unmonitored Release Requiring Evaluation D. Unmonitored Release Requiring Evaluation The following Protective Actions are recommended to be implemented as soon as practicable:

A. NO NEED for PROTECTIVE ACTIONS outside the site boundary I

( B. EVACUATE and IMPLEMENT the Kl PLAN for the following Secto~ ~

C. SHELTER-IN-PLACE and IMPLEMENT the Kl PLAN for the following Sectors

4. It_2 miles around S-miles downwind: )

In the following Sectors: 1 2 miles around 10-miles downwind:

2 3 4 5 6 rf@& er; 12 13 14 15 16 In the following Sectors: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 All remaining Areas MONITOR the EMERGENCY ALERT SYSTEM NOTE: OFFSITE AUTHORITIES SHOULD CONSIDER SHELTER-IN-PLACE + TAKE KIIF EVACUATION IS NOT FEASIBLE l

EAL#: SG..;)_ l Fa\lv.~ c~ ~~-be~ ~ N\a.N-(~t-tnp Affected Location*/

~\~~lS -t1l rt~et ~~~ t~e .(s-o ~ U NIT 2::5 '

5. A~l) .

~.\ p(\~M\~--~ ~~ ~'

. *.n . .1 ~om(

"'"'l'-'\ftt'\ ~

1111. B. UNIT 3 I 'TlP-1\ """-h\ ,*W\ f:.D.. ~ &.-4 f. Pr1 I~ i C. IPEC SITE Reactor Status:

6. Unit 2: Operational oGhut~ at (Date) "T()"TJ~V (Time) ~~ (24 hr clock)

Unit 3~or Shutdown at (Date) (Time) (24 hr clock) j I 7. I Wind S~eed: :l.:J Meters/Sec at elevation 10 meters I

8. I Wind Direction: (From) _ ___,5...,.

5'""

'-------- Degrees at elevation 10 meters I

9. 1 Stability Class: A G) C 0 E F G I

j 10 _ Reported by- Communicator: -- - - - - - - - - - - - Telephone#--- - - - -- - -

(Communicator's Name)

Page 1 of 1 Form EP-1 . Rev 5 5 of7

Appendix C Page6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: - - - - - - - - - - - -

6 of7

Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

The Current Time is 0223 The Unit was operating at 100% power At0200

• A small feedwater break occurred on the suction to 21 MBFP

• The crew attempted to trip the reactor, but the reactor trip breakers failed to open

• The crew is performing actions in FR- S.1, Response to Nuclear Power Generation/ATWS

• The Turbine was tripped

• Reactor Power is 42% and lowering.

At0204

• Both Main Boiler Feed Pumps were tripped

• All AFW Pumps started At0206

• Conventional NPO reports that he is unable to trip the reactor locally.

At0210

• A steam break occurs upstream of PCV-1139, 22 AFW Pump Steam Supply Pressure Control Valve

• All SG Wide Range levels are 45% and lowering At0217

• The harsh environment in the ABFP room caused both Motor Driven AFW pumps to trip.

At 0223 (NOW)

• The conventional NPO reports that the Rod Drive MG sets are secured and the reactor is tripped.

Meteorological Conditions:

• Wind Speed: 2.2 meters/second

• Wind Direction: 55 degrees@ 10 meters

• Stability Class: B Initiating Cue:

You are the CRS and the SM is unable to get to the control room. Classify the event and complete the Radiological Emergency Data Form.