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Final Outlines (Folder 3)
	ML14308A052
Person / Time
Site:	Indian Point
Issue date:	10/29/2014
From:	; Entergy Nuclear Indian Point 2
To:	Christopher Lally; Operations Branch I
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ML14190B006	List: ML14195A131; ML14251A240; ML14307B385; ML14307B521; ML14307B565; ML14308A052; ML14308A251;
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Appendix C Indian Point Unit Job Performance Measure Worksheet Facility:

2 Task No:

2000660122 Task

Title:

Determine Reportability Requirements 2.1.18 KIA

Reference:

SRO 3.8

~~~------

Job Performance Measure No:

Examinee:

.Facility Evaluator:

Method of testing:

Simulated Performance Classroom X

READ TO THE EXAMINEE NRC Examiner:

Date:

X Actual Performance Simulator Plant Form ES-C-1 SROAdmin 1a 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 Condition G and H 3.8.1 AC Sources Operating Condition B Surveillance W-19 is complete The following plant conditions exist:

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 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 required Tech Spec actions and reportability requirements.

1 of 5

Appendix C Job Performance Measure Worksheet Required Materials:

Unti 2 Technical Specifications IP-SMM-LI-1 08, 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 Form ES-C-1 Task Standard: Applicable Tech Specs and Reporting requirements identified 2 of 5

Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -../)

1. Performance Step:

Standard:

Comment:

2. Performance Step:

Standard:

Comment:

-../ 3. Performance Step:

Standard:

Comment:

-../ 4. Performance Step:

Standard:

Comment:

Obtain Correct Procedures Obtains Technical Specifications and IP-SMM-LI-1 08.

Reviews Technical Specifications Determine No additional Tech Spec actions are required Determine Reportability using IP-SMM-LI-108 Determines 8 hr report due to valid actuation of AFW Item 59 (See item 49 for explanation) 1 OCFR50. 72(b)(3)(iv)(A)

Determine who must be notified Identifies:

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

Terminating Cue: JPM Complete 3 of 5

Appendix C Page 4 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: ___________ _

4 of 5 Form ES-C-1

Appendix C Initial Conditions Form ES-C-1 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 Condition G and H 3.8.1 AC Sources Operating Condition B Surveillance W-19 is complete The following plant conditions exist:

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 required Tech Spec actions and reportability requirements.

Appendix C Indian Point Unit Facility:

2 Job Performance Measure Worksheet Task No:

2000070122 Form ES-C-1 Task

Title:

Review a Manual QPTR Calculation (4 Detectors 100%)

Job Performance Measure KJA

Reference:

2.1.37 SRO 4.6 No:

SRO Admin 1 b Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance Actual Performance X

Classroom X

Simulator Plant READ TO THE EXAMINEE I will explai_n 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 1 00% power.

2. The RO has calculated a QPTR manually.

3. There is indication of a misaligned rod. The RO calculated a QPTR of 1.0638 and recommends a Power Reduction to::::; 80. 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.

1 of 14

Appendix C Required Materials: Calculator Job Performance Measure Worksheet General

References:

3-SOP-15.3, Quadrant Power Tilt Calculation Form ES-C-1 DSR-48 Unit Two Quadrant Power Tilt Calculation Sheet Time Critical Task: No Validation Time: 20 Minutes Task Standard: Calculation reviewed and errors corrected, identify incorrect TS actions.

2 of 14

Appendix C Page 3 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/B and QPTT/B 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:

Comment:

Checks Detector currents recorded from QPTR Data Sheet recorded 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 of 14

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -/)

3. Performance Step:

Standard:

Comment:

4. Performance Step:

Standard:

Record Date, Time and Average Reactor Power Checks Current Date and Time and average Reactor Power of 1 00% recorded DIVIDE each detector output by corresponding normalization factor 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:

Standard:

Comment:

If three detectors are to be used in the calculation, change denominator from 4 to 3 Checks "4" for denominator on top and bottom average equations recorded 4 of 14

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark >/)

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]

7 Performance Step:

Standard:

CALCULATE Quadrant Power Tilt for top and bottom detectors Checks calculations:

CALCULATES 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]

5 of 14

Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark -1)

,J 8. Performance Step:

Standard:

Comment:

,J 9. Performance Step:

Standard:

RECORD highest Quadrant Power Tilt and appropriate signatures.

If Candidate does not identify the error, the QPTR will appear correct.

If qua.drant 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 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 1.0638. 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~

77.4%.

6 of 14

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

...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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,

a.

Reactor Power must be reduced to below 77.4%

(,:!:0.5%)

Comment:

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

...J 11. Performance Step:

DETERMINES QPTR CALCULATION IS NOT CORRECT Standard:

Determines correct value for QPTR 1.0753.

Determines correct maximum power level 77.4%

Comment:

Terminating Cue: JPM Complete 7 of 14

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:

Iadav SNSC REVIEW DATE TIME* 30 mjn11tes ago AVE REACTOR PWR* 100%

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 41 Top= 41T =

139.7 I* 129.1 = 1.0821 41 Bottom= 41B = 128.7

/* 122.5 =

42 Top= 42T = ~136.6= 1.0637 42 Bottom= 42B ~

144.3 =

43 Top= 43T =

122.9 I* 118.3 -

l.Q~a~

43 Bottom = 43B =

124.2 I* 119.3 =

44 Top= 44T-89.4 I* 87.4 -

l.Q22~

44 Bottom - 44B -

109.7

/*107.1 -

2.

Answer Key Incorrectly Calculated Errors ldent1f1ed Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top

= ANRT = 41~ + 42T + 43T + 44T= 1.~---7----

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

4 1.0506

.8344 1.0411 1 02~~

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 Manuai3.2.A:

Quadrant Power Tilt Top= QPTI = Highest value of 41T, 42T, 43T, or 44T ANRT QPTI = AN~~~e ~--===""1~;)~~--T------------

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.

Answer Key ed Errors Identified 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

.8 of 14

Appendix C Page 9 UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. 193 Previous SNSC #2545 11/5/98 (QT-20-31)

SNSC REVIEW DATE APPROVED(RE)

DATE USING DETECTOR OUTPUT CURRENT APPROVED DATE Current QT number and Normalization Factors provided by Reactor Engineer.

Form ES-C-1 DATE:

Iadav TIME* 30 mjn11tes ago AVE REACTOR PWR* 1005

1.

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

[ITS] Technical Requirements Manual 3.2.A:

Answer Key Correctly Calculated Channel Det Current Nor Ratio Channel Det Current Nor Ratio 41 Top=41T=

139.7 I* 129.1 = l.OB2l 41 Bottom = 41B =

128.7 I* 122.5-l.OSQfi 42 Top= 42T =

120.4 I* 136.6 =.8814 42 Bottom = 42B =

145.3 I* 144.3 =

l.OQfi~

43 Top= 43T=

122.9 I* 118.3 =

LQ3B~

43 Bottom = 43B =

124.2 I* 119.3 =

1.0411 44 Top-44T-89.4 I* 87.4 -

l.Q22~

44 Bottom - 44B -

109.7

/*107.1 -

l 02~3

2.

Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top

= ANRT = 41T + 42T + 43T + 44T= 1.0063 4

Average Normalized Ratio Bottom= ANRB = 41B + 42B + 43B + 44B-___,!1'-:.!

.0~3~0!..!.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= QPTI = Highest value of 41T, 42T, 43T, or 44T ANRT Value= l 0821 QPTI = ANRT = 1.0063 Quadrant Power Tilt Bottom= QPTB = Highest value of 41B. 42B. 43B. or 44B ANRB Value=

l 0509 QPTB = ANRB =

1.0307 = --~====-~~---------------

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:

Answer Key Correctly Calculated Enter the Higher QPT(Top or Bottom) =..1_. _Q_ L 2.. 2._

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.

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 1 9 of 14

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 UNSAT Examiner's signature and date: ___________ _

10 of 14

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

1. Reactor power is stable at 1 00% power.

2. The RO has calculated a QPTR manually.

3. There is indication of a misaligned rod. The RO calculated a QPTR of 1.0638 and recommends a Power Reduction to< 80.7%.

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.

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:

Today SNSC REVIEW DATE TIME* 30 mjn11tes 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=

139.7

/* 129.1 = 1.0821 41 Bottom = 41B =

128.7

/* 122.5 =

42 Top= 42T=

145.3

/* 136.6 =

1.0!2~7 42 Bottom = 42B =

120.4

/* 144.3 =

43 Top= 43T =

122.9

/* 118.3 -

1.0389 43 Bottom = 43B =

124.2

/* 119.3-44 Top-44T-89.4

/* 87.4 -

l.Q22~

44 Bottom - 44B -

109.7

/*107.1 =

2.

Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top

= ANRT = 41T + 42T + 43T + 44T= 1.0519 4

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

.9876 ------

4 1.0506

.8344 1.0411 1 02~3

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= 1.0821 QPTT = ANRT = 1.0519 1.0287 Quadrant Power Tilt Bottom= QPTB = Highest value of 418, 428, 438, or 448 ANRB Value = 1.0506 QPTB = ANRB =

.9876

= ____

.....,;:;1~

.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. [ITS] Technical Requirements Manual 3.2.A:

Enter the Higher QPT{Top or Bottom) = _1_. _Q_ _§_ _l_ JL Technical Specification Limit

= 1. 0 2

0 0

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 UNIT TWO QUADRANT POWER TILT CALCULATION SHEET Rev. 193 Previous SNSC #2545 11/5/98 DSR-4B (QT-20-31)

SNSC REVIEW DATE APPROVED(RE)

DATE USING DETECTOR OUTPUT CURRENT APPROVED DATE Current QT number and Normalization Factors provided by Reactor Engineer.

Form ES-C-1 DATE:

..I2f1ay TIME* 30 min11tes ago AVE REACTOR PWR* 100%

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 =

I* 129.1 =

41 Bottom = 41B =

42 Top= 42T =

136.6 =

42 Bottom = 42B =

43 Top= 43T =

I* 118.3 =

43 Bottom= 43B =

44 Top-44T-I* 87.4 -

44 Bottom - 44B -

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 I* 122.5 =

!* 144.3 =

I* 119.3 =

/*107.1 =

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= QPTI = Highest value of 41T, 42T, 43T, or 44T ANRT Value=

QPTI = 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 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. 0 2

0 0

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 Indian Point Unit Facility:

2 Job Performance Measure Worksheet Task No:

2000340122 Form ES-C-1 Task

Title:

Identify Isolation Boundaries and Required Actions High Pressure Fire Protection 2.2.41 Job Performance Measure KIA

Reference:

SRO-3.9

=~~~----

No:

SRO Admin 3 Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance X

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 1 00% 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 12

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

References:

SA0-703, Fire Protection Impairment Criteria and Surveillance 9321-F-4006 Yard Fire Protection Piping Time Critical Task: No 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 Validation Time: 45 Minutes Task Standard: Identify isolation boundaries, affected components, Required Action and Completion Time for impaired condition.

2 of 12

Appendix C Page 3 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:

Standard:

Identify Isolation Boundaries 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 PAS Supply Stop (West of PAS}

Comment:

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

...J 3. Performance Step:

Standard:

Identifies affected equipment Identifies the following affected equipment o

High Pressure Hydrants #23, #24, #25, #26 o

Electrical Tunnel Deluge o

PAS Hose Station (Alternate supply will maintain hose pressure. This is not required for evaluation for compensatory actions Comment:

The affected equipment is identified using print 9321-F-4006 3 of 12

Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark >I)

>/ 4. Performance Step:

Standard:

19 Yard Area 15" 20 Yard Area 18'-6" 21 Yard Area 70' Identifies Required Actions from SA0-703 Identifies the following Required Actions o 2.a.3 High-Pressure Water Fire Protection System (Not Critical This is a routing statement. Candidate may go directly to 3.a. 1 and 4.a and 4.b) o Table 1-4 below Unit 2 intake structure Hydrant 21 HPH OR 22HPH and Hose Cabinet No. 5 (with fire hose and nozzles to serve the Unit 2 Intake area)*

Transformer yard, Hydrant 25HPH and Hose south of the ABFP Cabinet No. 7 (with fire hose Building and nozzles to serve the ABFP Building)

South of the EDG Hydrant 27HPH and Hose Building Cabinet No. 12 (with fire hose and nozzles to serve the EDG Building) o 3.a.1 Fire Protection Spray Systems a.1 The Electrical Tunnel Fire Protection Water Spray System (EI-33 ft. Control Building to El-68 ft.

PAB Fire Zone 32A) shall be functional. Below are the Required Actions and Action Time Required Action Action Time a.l Additional fire hose(s) shall be Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided and labled to serve the affected location(s) from an functional hose station(s) or hydrant(s). Refer to Note 2.3 for additional guidance AND a.2 The impaired equipment shall be Within 14 days restored to functional status a.3 Verify additional compensatory fire Every 90 +/-7 hose is staged as required by a.1 days above a.3 4 of 12

Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark..../)

...J 4. Performance Step:

Identifies Required Actions from SA0-703 o

4.a Fire Hose Stations and Hydrants shown on Table 1-4 shall functional. Only hydrant #25 is listed in Table 1-4. Following are the Required Actions and Action Time.

Required Action Action Time a.l Additional fire hose(s) shall be Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided and labled to serve the affected location(s) from an functional hose station(s) or hydrant(s). Refer to Note 2.3 for additional guidance AND a.2 The impaired equipment shall be Within 14 days restored to functional status a.3 Verify additional compensatory fire Every 90 +/-7 hose is staged as required by a.1 days above a.3 5 of 12

Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y)

.Y 4. Performance Step:

Identifies Required Actions from SA0-703 o

4.b Fire Hose Stations and Hydrants (Not #25)

Required Action Action Time b.1.a Establish a 4-hour fire watch tour Within 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months toinspect the affected fire zone(s).

OR b.1.b If the affected zone is equipped with a firedetection system (see Tables 1-1 and l-2),verify that the fire detection equipment in the zone is functional.

OR b.1.c Additional fire hose(s) shall be provided to serve the affected location(s) from a functional hose station(s) or hydrant(s). Refer to Note 2.3 for additional guidance.

AND b.2 The impaired equipment shall be Within 30 days restored to functional status Comment:

When SA0-703 is entered. Addendum 1 contains Impairment Criteria and actions. Section 2 addresses High-Pressure Water Fire Protection. Section 2 Requirement a.3 directs operator to perform actions for specific hose /hydrants or fixed suppression system.

Terminating Cue: JPM Complete 6 of 12

Appendix C 6" -

TO STOReD AUX. TRANS.

SPRAY SYSTEM SEE DET. KK DN A227554 RISER SEE

DET. *ss*.

Page 7 TO CLEAN AND DIRTY OIL T At'l"t{S SEE TYP. JELUGE VALVE STAT.

DET * "R" Oh'G. A227552 FP-711 RISER SEE ocr. *o-o*

OWG. A2275':l4 w

TO HOSE REEL F

Form ES-C-1 1 DWG. A227554 z

H

!D 0

a:

CONDENSER n2 &

w

~

~ INTAKE STRUCTURE

<(

w

~

I TO BOILER FEED PUMP DELUGE SEE TYP. DELUGE VALVE STAT. !,

DET. *p* OWG. A227552 TO SEAL OIL UNIT DELUGE SEE TYP.

OET. "L" II CSlUGE VALVE STAT.

~

OWG. A227552 biSER SEE DET. "AA" OWG. A227!55.d.

Blue Affected Con1ponents Cil C<

J f-N 0 z f-FP-5 12

..... 5 4

FP-518 0

0..

~

c;;

10" TRANSFORMER YARD (U'JOERGROUNO 932 1-F-2236)

- TO TRANSFORMER DELUGE VALVE SEE TYP. DELUGE VALVE STA T.~

DET. "M" DWG. A227552 I

ELECT. TUNNEL DELUGE SEE DET. *s* DWG. A227551 CONTROl BLDG.

TANK FILL LINE RI SER DET. "A" THIS DIIG.

-- 6" RISER TO ELEV. 147 '

/

L__~S~E~E~

O~~

-T_.~"-A_

" _T~H~I~S_D~WG~-~-L-r--~~

STAIR fL I 1o*

Red Isolation Boundaries 7 of 12 N-673

26 FI

Appendix C Page 8 Form ES-C-1 DESCRIPTION REQUIREMENT f..

High-Pressure a1 BOTH motor-driven fire main Water Fire booster pump; (11 FMBP and Protection 12FMRP) AND diesel-clri~-en fire System pump {DFP) functional and properly aligned to the high-Impaired pre;s.!lUre fue header. Reier to eo11dr.ions 2.a.1.. a Naes Z.Z.aand2.2.cf1¥'

and 2.a.2 may additimllglidance.

exist concwrenlly, Impaired C011al'kns 2. a.1.b and 2.a.2 may a.i.

A mintmum available willet exist concwrenll'y,

'<'Oiume of 360,000 gallOns Impaired oomained in the Citt Water Tank eo11di:icns 2.a.1..c and 300,000 gallons contained in the Fire Watet Storage Tank for and 2.a.2 may exist concurrently f~e protection pi.rpCSes.

Reier to NO(e Z.Z.b fiX 00diri0011i' Refer to Neff: 2.

a.J All !X>ing and valves neoessar1 lor a dditiona/

gridance for proper functi<Yiing o( any portion of the system required fer protection of safety-rela:ed ar safe-st..rtdown systems functional. Reier rD N'O(e22.cfrr addir.iooa I quid a nee.

b.

High-pressure water fire protectioo system functional as required by 2.a.1 and 2.a.2.

NOTE: Expiration of the Action Time for Items 2.a.l and :La.2 does NOT require en!ry in~o Item 2.b.

a.l a.i.

a.J

b.

ADDENDUM I FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA Page 2 of23 APPLICABilllY IMPAIRED CONDITION At all times.

a.'i.a Ore or bo:h mo'.or dri~en f~re main booster pump; (! 1 FMB? and/Ol' 12F MBP) oul of seM:e OR a.lb The diesel-driven pump {DFP) OJ! of service.

OR a.lc k; del ermined by H' Enfjneerin;.

Reier ca Nrxe 2.2.a ffJf guidance.

Alai! times.

a.i Ore water Sl41PlV out of service.

Reiflf to Nrxe 2.2. b for guidance when tilfl FWST lf!'~el instrument channa fJf tank refill capatxlity is impa~ed.

At al ~ times.

a.J Any valve or pipe r;ecessary ro supply fiXed automatic suppression systems or hcr.e si&iar.Jhydrants protec1in; safety-relall;d or sa!e-snutda'lin related areas ou1 of ser~ice.

At all times.

b.1

'Nnh the high-pressure water fire p10tectioo syS:em impaired in a manner othet iMn permitted by 2.a.1 or 2.a. 2.

b.Z Required Action and a>sociated Action Time of Impaired Condtm b.1 1101 met.

REQUIRED ACTION a.1.a Res:cre to funaional status.

a.tb a.tc a.L Res:ore to functional status.

a.J See Required Ac:ioo fer specific fix~d automatic S1.fJpression sys:em or hose stations/hydran:s served by the portioo of the system r.ha1 is impaired.

b.1.

An ahemate fire pro\\ecticn S'jGtem shall be established.

b2.a Be in MODE j_

AND b1.b Be in kiDDE 5_

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 12 a.l.a a.lb aJ.c a.Z a_j b.l

b. f.. a b.2.b SA0-703 REV 34 ACTION TIME I Wr.twl f days.

Wt.hin I days.

See corresponding

.t>.dion Tune.

Wl:lin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Wl:lin JU hours.

Wl:tln 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

' I

Appendix C Page 9 Form ES-C-1 DESCRIPTION REQUIREJ.IE~H

3.

Fire Protection a.l The Electrical T uMel Fire Spray Systems Protection Wa:er Spray System (includes (E!-33 h. CootroiBuilding io 8-sprinkler 68 ft. PAS - Fire Zone 32A) shall systems and be functional deluge systems) a.£.

The Diesel Ger.era:or Buildi~

Refer to NrXe 2. 0 Water Spray Sysl REQUIREMENT

4.
Fire Hose
a.
Fire hoce statons and lnydrams Stations and slncv;n on Table l-4 shall be Hydrants functional.
Refer to Nat:e 2.0 foradr:lir.iorol guidance
b.
Fire hose statJ.ons and hydran:S on the high-pressure fire loop otha than those shaAn on Table l-4 shall be f~.~nctional.
NOTE: The hose st31icn oo the roof ci the FSB and the low-pressure hydrants in the City Water Sys1em are NOT I
l~lCLUDED in this functionality requirement.
a.
b.
ADDENDUM!
FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA Page 4 of23 APPLICABILITY IMPAIRED CONDITION lh'herever safely-related rx safe-
a.
Any fire hose stalion or hydrant liilled on shutdcwn rela:ed equipmen1 in the Table 1-4 is impaired.
areas protected by the nose stalions and tl}'dr ams is r~red to be operable.
ll.'herever equipment protected by
b.
Any h i~*pressure fire nose station rx 1he hose sla:icns and hydrants in the hydrant other than those liste-d on To ble area is required to be operable.
l-4 is impaired.
REQUIRED ACTIO!~
a.1 Mditiorel fire hose(s) shall be provided and lab!ed to ser;e the affected localion(s) from an functiooal hose st<~tior(s) 01 hydrant[s). Refer ia NGI.e2.3 for adr:lir.ionJI guida nee.
AND a.2 The impaired equipmenl shall be res:ored to funcrjcnal :>.aiLAS.
a.J Verify edd i~cnal oompensa:ory fire nose is staged as req1.1ired by a. I abO'.. e b.l.a Es:ablis.h a ll-hour fire watch toor ro inspect the affected fire zone(s).
.00.
b.1.h lf ~e affected zone is equipped with a fire detectioo sys:em (see T abies 1-1 and 1-2).
verify thal 1M fire detection equipment in the zone is functronal.
00 b.1.c Mditional fire hose{s) shall be provided ro serve the affected location(s) frcm a functicn~~l hcGe s:a:ioo(s) Of h)*drant[s).
Refer to Nale 2.3 frx add~ioru! grJI'dJnce.
AND b.2 The impaired equipmer~ shall be res:cred to functicnal ~ams.
Note: The provisions of paragraph 4.6 SHALL be followed if the specified "Action Time* for ANY Item in the Table is exceeded.
10 of 12 a..l a..l a.J b.l b.2 SA0-703 REV 34 ACTION TIME I Wi:~n l hour.
Wiilin 14 days.
=very 9(1 : 7 days Wi:hin tl hours.
V\\1\\:lin 30 days.
Appendix C Page 11 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: __________ _
11 of 12 Form ES-C-1
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
The unit is operating at 1 00% 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 Indian Point Unit Facility:
2 Job Performance Measure Worksheet Task No:
2000240122 Form ES-C-1 Task
Title:
Review a Liquid Radioactive Release for #13 Liquid Waste Distillate Storage Tank 2.3.6 KIA
Reference:
SRO 3.8

~~~~----

Job Performance Measure No:
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance Actual Performance Classroom X
Simulator Plant READ TO THE EXAMINEE Admin 4 X
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 Initial Conditions:
Job Performance Measure Worksheet The Unit is operating at 100% power.
Form ES-C-1 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 TankiD Initial Tank Level Pre-release volume Recirculation Rate Recirc Start-Recirc Stop 070300 13 WDST 97 22972 Chem Sample Number Sample Date!Time Total Gamma Activity ADC 150 gpm Today 01:00 Today 05:45 4807 Today 05:30 4.0E-5 5.31E-7 ppm Boron in tank Initiating Cue:
849 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:
Time Critical Task: No Validation Time: 30 2-SOP-5.1.5, Calculation and Recording of Radioactive Liquid Releases Task Standard: Reviews manual calculation and identifies errors. Does not approve release.
2 of 11
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -../)
1. Performance Step:
Standard:
Obtain Correct Procedure Obtain 2-SOP-5.1.5, Calculation and Recording of Radioactive Liquid Releases Comment:
Give the candidate the procedure.
2. Performance Step:
Standard:
Comment:
...J 3. Performance Step:
Standard:
Review Precautions and Limitations Reviews Precautions and Limitations Record the following 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 iJCilml 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 Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark...J)
4. Performance Step:
Standard:
Comment:
5. Performance Step:
Standard:
Comment:
6. Performance Step:
Standard:
Comment:
7 Performance Step:
Standard:
Comment:
Verify from Chemistry the total gamma activity WITHOUT noble gas is less than 5.0E-5 1-JCi/ml.
Observes the value is 4.0E-5 given in initial conditions Record the pre-determined dilution flow rate (B) for this release in gpm, from Step 4.1.5.
Records 504,000 based on 6 Circulator at low speed given in initial conditions.
Calculate the pounds of Boron in tank AND Maximum Allowable Chemical Release Rate (Rc)
Determines 162.5+/- 0.5 is correct Calculate the Permissible Radioactive Release Rate (Rr)
Determines 6691 is correct 4 of 11
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark...J)
8. Performance Step:
Standard:
Comment:
...J 9. Performance Step:
Standard:
Comment:
Determine the most restrictive release rate Determines 250 is correct Determine alarm settings if effluent radiation monitor is in service.
Determine effluent monitor is INOPERABLE per ODCM surveillance requirement 3.3.1.3.
...J 1 0. Performance Step:
Does not approve release permit Standard:
Comment:
5 of 11
Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark 1/)
,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
CALCULATION AND RECORDING OR No: 2-SOP-5.1.5 RADIOACTIVE LIQUID RELEASES Page 16 of 23 ATTACHMENT 1 EXAMPLE RADIOACTIVE LIQUID RELEASE PERMIT PERMIT#
07300 TANK ID 13 WDST RECIRC RATE :
Chemistry 1_,_,5=0 __ gpm Sam le No.
4807 Total Gamma Activity --"4.=0=E-...:::5 ____ 1JCilml Pa e 1 of 1
___,_T=od=a"-J.y __ (Date)
-!.T~od,_,ac!:t.y__ (Date)
Toda 01:00 05:45 (Date) min limit of SMM-CY-001:
Allowed Diluted Concentration (ADC) 5.31 E-7 Rev: 38 Recirc time is inadequate it should be 306 minutes ( 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and 6 minutes)
Sample time too early TOTAL DILUTION FLOW (T) _
__.:.;50:...;4=,0=0-=-0 __ (GPM)
From:

=6 _

Unit 2 Circulators
_--=.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 ppm B Radioactive Release Rate:
(Rr) = (
504,000 x
5.31 E-7
) +:--4:..:.;
. 0:..:E=--~5-;-;-;~-=" __
.:.;66:..:9:....:.1 __ gpm Avail Oil Flow (B), gpm ADC, uCilml Gamma Act (C), uCilml Most Restrictive Relea Rad Monitor #
54 s -- NO (IF NO, COMPLETE ATT 3)
_.....:1..:.!.0::..!7..!::E:....!-3~_uCi/ml Maximum Alarm Setpoint = ( :--~5~04~.~00!!!0~~~~¥!J.J==b.,-~.,_~~~::---.,....,--~
Avail Oil Flow (B), gpm Most Restrictive Release Rate (R), gpm Actual Alarm Set oint =
4.0E-5 uCi/ml Wam Set oint=
3.0E-5 DISCHARGE FLOW METER & RECORDER OPERABLE _X_YES NO (IF NO, COMPLETE ATTACHMENT3)
The initial conditions identified R-54 source check failure i.e.,
INOPERABLE Release Authorized By: ________________ _
RELEASE INITIATED: _____
(Date) _____ (
Also need RELEASE TERMINATED: _____
(Date) _____ ( Attachment 3 FINAL TK LEVEL: __ (Inches)
____ gal TOTAL VOLUME RELEASED _____
gal Remarks:
Appendix C Page 8 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: ___________ _
Form ES-C-1
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 TankiD Initial Tank Level Pre-release volume Recirculation Rate Recirc Start-Recirc Stop Chern Sample Number Sample Dateffime Total Gamma Activity ADC ppm Boron in tank Initiating Cue:
070300 13 WDST 97 22972 150 gpm Today 01:00 Today 05:45 4807 Today 05:30 4.0E-5 5.31 E-7 849 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.
CALCULATION AND RECORDING OR No: 2-SOP-5.1.5 Rev: 38 RADIOACTIVE LIQUID RELEASES Page 16 of 23 ATTACHMENT 1 EXAMPLE RADIOACTIVE LIQUID RELEASE PERMIT (Page 1 of 1)
INITIAL PERMIT#
070300 TANK ID 13 WDST Tank Levei:Jrr_ (Inches) 22972 Volume (V), gal RECIRC Recirc Start:
Today (Date) 01:00 (Time)
RATE:
150 gpm Recirc Stop:
Today (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 1JCilml 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 ppm B Radioactive Release Rate:
(Rr) = (
504,000 X
5.31 E-7
) +
4.0E-5
=
6691 gpm Avail Oil Flow (B), gpm ADC, uCi/ml Gamma Act (C), uCi/ml Most Restrictive Release Rate (R) =
250 gp_m (pump capacity most limiting)
Rad Monitor#
54 SOURCE CHECKED _X_
OPE.RABLE..lL_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, uCi/ml Most Restrictive Release Rate (R), gpm Actual Alarm Setpoint =
4.0E-5 uCiiml Warn Setpoint =
3.0E-5 uCi/ml DISCHARGE FLOW METER & RECORDER OPERABLE X
YES NO
{IF NO, COMPLETE ATTACHMENT 3)
Release Authorized By:
(Date)
RELEASE INITIATED:
(Date)
(Time)
RELEASE TERMINATED:
(Date)
(Time)
FINAL TK LEVEL: __ (Inches) gal TOTAL VOLUME RELEASED gal Remarks:
Appendix C Facility Indian Point Unit 2 Job Performance Measure Worksheet Task No:
1500010522 Form ES-C-1 Task
Title:
Classify Emergency Events Requiring Emergency Plan Implementation (Time Critical)
KIA
Reference:
Examinee:
2.4.38 SRO-4.4 Job Performance Measure No:
NRC Examiner:
SRO Admin 5 Facility Evaluator:
Method of testing:
Simulated Performance Classroom X
READ TO THE EXAMINEE Date:
X Actual Performance Simulator Plant 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.
Appendix C Initial Conditions:
The Current Time Is 0223 Job Performance Measure Worksheet The Unit was operating at 100% power At0200 Form ES-C-1 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 ws 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.
At 0210 A steam break occurs upstream of PCV-1139, 22 AFW Pump Steam Supply Pressure Control Valve All 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.
Required Materials: EAL Wall Chart.
Appendix C Job Performance Measure Worksheet General
References:
IP-EP-115 IP-EP-120 IP-EP-210 IP-EP-410 Form ES-C-1 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.
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark.Y)
1. Performance Step:
chart Obtain correct procedure IP-EP-120 orEAL Standard:
Give candidate Wall Chart Comment:
.Y 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.
.Y 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
Appendix C Page 5 Form ES-C-1 l
~
C. Site Area Emergency
\\1 tme 24 hr cloc.l<.)

~

3.
Release of Radioactive Materials due to the Classified Fvent
, D. Unmonitcired Release Requiring Evaluation To Water:
~
1~:~;.),1; i 8. Release BELOW Federal Limits
, C. Release ABOVE Federa! Limits I
D. Unmonitorad Release Requiring Evaluation

~

i ! The following Protective Actions are recommended to be ;mplemented as soon as cracticable:
l A. NO NEED for PROTECTIVE ACTIONS outside the site boundary
~CUA; E and iMPLEMENT the KiPLAN fcrth;following Sectors C. SH!::LTER-IN-PLACE and IMPLEMEN I the Kl PLAN for the following Sectors 2 miles around S-miles downwind:
In the following Sectors: 1 2
3 4
5
J 2 miles around 10-miles downwind:
I In t'le following Sectors: 1 2
3 4
5 6
7 8
9 10 A!! remaining Areas MONITOR the ::MERGENCY ALERT SYSTEM 12 13 14 15 13 14 15 I
i l i
NOTE: OFFSITE AUTHORITIES SHOULD CONSIDER SH"'LTER-!N-P!.ACE +TAKE Kl IF EVACUATION !S NOT f'EASIBLE at (Date) ltlOAV (24 hr clock) at (Date), _ ______ (Time) ______ (24 hr clock) 16 16
8. - Wind Direction: iFroml =:::;~55"'
=*=======-~D:eg:'r~e::e:_s_:a~
i e:!_:ev:_:a:_:t:_-:
io~n_':_-:
' 0:_-m~-:_et:e_::rs~-------------------------!
A (i) C
9. ; Stabilitv Class:
0 F
G
, '\\O. : Reported by-Communicator:------------------------- Telephone# ____________ _
(Communicators Narns) i~
1
- l E~ergency Directo; Approva!:~A1!
~7i.""
7
~~.~~-~~-
...,.,-'-"-"'----_-_-_-_-_-_-_-_-_-_-~---_-_--0-a--:-te--fT-I-im-.e-:-~
. --'1-C.U
--~---If-11-U--
~---~
{D!t¥:ctcfs lVame}
Page 1 of 1 Form EP-1, Rev 5 5 of?
Appendix C Page 6 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 Initial Conditions:
The Current Time Is 0223 The Unit was operating at 100% power At0200 Form ES-C-1 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 ws 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 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.

ML14308A052

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ML14308A052

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ANRT = 41T + 42T + 43T + 44T

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