ML14308A251

Final Operating Exam (Section a) (Folder 3)

ML14308A251
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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Text

Appendix C Indian Point Unit Facility:

2 Job Performance Measure Worksheet 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 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.

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-1 08, 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)

1. Performance Step:

Standard:

Comment:

2. Performance Step:

Standard:

Comment:

-1 3. Performance Step:

Standard:

Comment:

" 4. Performance Step:

Standard:

Comment:

Obtain Correct Procedures Obtains Technical Specifications and IP-SMM-LI-108.

Reviews Technical Specifications Determine No additional Tech Spec actions are required Determine Reportability using IP-SMM-LI-1 08 Determines 8 hr report due to valid actuation of AFW Item 59 (See item 49 for explanation) 1 OCFRSO. 72(b )(3)(iv)(A)

Determine who must be notified 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)

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 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.

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:

Facility Evaluator:

Method of testing:

Simulated Performance Classroom X

READ TO THE EXAMINEE NRC Examiner:

Date:

Actual Performance Simulator X

Plant 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-4B 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.Y)

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-4B 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 -1)

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 -Y)

.Y 8. Performance Step:

Standard:

Comment:

.Y 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 --./)

--.1 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 77.4%

( :!:0.5%)

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

--./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 I* 122.5 =

42 Top= 42T = ~

136.6 =

1.0637 42 Bottom= 42B ~

144.3 =

43 Top= 43T =

122.9 I* 118.3 -

1. Q3S~

43 Bottom = 43B =

124.2 I* 119.3 =

44 Top-44T-89.4 I* 87.4 =

1.Q,,~

44 Bottom - 44B -

109.7

/*107.1 -

2.

Answer Key Incorrectly Calculated Errors ldent1fled Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top

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

--~---

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

4 1.0506

.8344 1.0411 1 !J'::I3

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 QPTI = AN~~~e ~--====1;)

~!3,f,-----::f-------------

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: --:!:Ia!,!!d>!!a!,!i\\1,__--

TIME* 30 min11tes ago AVE REACTOR PWR* 1005

1.

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

[ITS] Technical Requirements Manuai3.2.A:

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

139.7 I* 129.1 -

l.OSZl 41 Bottom = 41B =

128.7 I* 122.5-1.0506 42 Top= 42T =

120.4 I* 136.6 =

.8814 42 Bottom = 42B =

145.3 I* 144.3-1.0Qfi2 43 Top= 43T=

122.9 I* 118.3 -

l.Q3S~

43 Bottom= 43B =

124.2 I* 119.3 =

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

l.QZZ~

44 Bottom - 44B -

109.7

/*107.1 -

1 QZ~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= 1 0821 QPTI = ANRT = 1.0063 Quadrant Power Tilt Bottom= QPTB = Highest value of 41B, 42B, 43B, or 44B ANRB Value =

1 0506 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)

SNSC REVIEW DATE DATE:

-:::I!:!'adO!!a~\\1,...._-

TIME* 30 minutes 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 I* 129.1 = 1.0821 41 Bottom = 41B =

128.7 I* 122.5 =

42 Top= 42T =

145.3 I* 136.6-1.0!2~7 42 Bottom = 42B =

120.4 I* 144.3 =

43 Top= 43T=

122.9 I* 118.3 =

l.Q3B~

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.

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= QPTI = Highest value of 41T, 42T, 43T, or 44T ANRT Value= 1.0821 QPTI = ANRT = 1.0519 1.0287 Quadrant Power Tilt Bottom= QPTB = Highest value of 41B. 42B. 43B. or 44B ANRB Value = 1.0506 QPTB = ANRB =

.9876

= ____

......;:;1,;.:;

.0;,:,:6,;;;;38~--------------

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_ _§_ 2...L 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 Previous SNSC #2545 11/5/98 SNSC REVIEW DATE APPROVED{RE)

DATE APPROVED DATE DSR-4B (QT-20-31}

Rev. 193 USING DETECTOR OUTPUT CURRENT Current QT number and Normalization Factors provided by Reactor Engineer.

Form ES-C-1 DATE:

-:-I2f!illt:!::!:!!:~--

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.s =

I* 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:

Facility Evaluator:

Method of testing:

Simulated Performance Classroom X

READ TO THE EXAMINEE NRC Examiner:

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.

Initial Conditions:

The unit is operating at 1 00% power Flushing of fire hydrants in the transformer yard is underway.

1. 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 -Y)

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

.Y 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 PAB Supply Stop (West of PAB)

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.

.Y 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

PAB 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 >/)

>/ 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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)

...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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 l/2 "

"'P.)

6" -

RISER SEE DET. *ss*.

Page 7 TO CLEA'I AND DIRTY OIL TA<'I',{S SEE TYP. JELUGE VALVE STAT.

DET. "R" OWG. A227oo2 FP*711 w

Form ES-C-1 F

TO fi()SE REEL 10"

. DWG. A227554 z

H CONDENSER #22 I>

,._ I NTAKE STRUCTURE

"'4c. ---- ---

<(

(!)

a w

1-

<(

w I

TO BOILER FEED PU.V.P D~Lu:;~

SEE TYP. DELUGE V~.LVE STAT. !.

DET. "P" D'.IG. A227552 TO SEAL OIL UNIT DELUGE SEE TYP. OSLUGE VALVE STAT. !.

DET, " L

• OWG. A227552 0

~

C\\!

~

UJ brsER SEE PET. "AA" DWG.

A.227~'5L I

II Blue Affected Con1ponents FP-5 12 4"

ClJ ;;;

cr

~ 0 f-0...

N~

D r;:,

10" z,.,

f- -

H 5

TRANSFORMER YARD (UNDERGRClUN'O 9321-F-223&)

• - TO TRANSFORM~R DELUGE VALVE SEE TYP. DELUGE VALVE STAT. &

DET, *w DWG. A227552 I

ELECT. TUNNEL DELUGE SEE DET. "B" OWG. A227551 CONTROL BLDG.

TANK FILL LINE RISER DET. "A" THIS OWG.

• -- &" RISER TO ELEV. 147' SEE OET. "A" THIS OWG.

STAIR #L I 1o*

Red Isolation Boundaries 7 of 12 BLDG. I 2

N673

• - FI

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

z.

High-Pressure a1 BOTH motor-1Jriven fue main Water Fire booster pum~ (11FMBP and Protection 12fMBP) AND ciiesel-clriven fire System pump (DFP) funr.1ional and properly aligned to !he nigh-lmpa;ired pressure fire header. Refer to condncns 2.a. ta Nrxes 2.2.a and 2.2.cfa-and2.a.2may add~it:rul gtidance.

exist coocwreN!y, lmpa;ired condi'jcns 2. a.1.b and 2.a.2 may a.2 A minimum a*1ailable waler exist coocwreN!y, volume of 300,000 gallons lmpa;ired oomained in !he Citt Water Tank condrncns 2.a. I.e and 300,000 gallons contained irl and2.a.2may the Fire Water StOfage Tank for exist concurren!ly fire protedioo p~es.

Refer to N0(~2.2.b for addirir:rol Refetr to fV(!(e 2.

a.J AJI J;iping and vall'es necessarf for a ddtionai gbTdarJCe for proper functioning c4 any portion of the sysl.em required lor proredion of safety-rela:ed or safe-stl.rtdown systems functionaL Refer tD Nrxe 2.2. e fer add~ir:ml quidance.

b.

fiigl'l-preosure water fire protection sys(em functional as required by 2.a. 1 and 2.a.2.

NOTE: Expiration of the Aclion Time for Items 2.a. 1 a'ld 2.a.2 does NOT re~uire enlry ir.:o Item 2.b.

a.l a.2 a.3

b.

ADDENDUM I FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA Page 2 of 23 APPLICABllllY IMPAIRED CONDITION At all times.

a.la One or beth rooior driven fire main booster pum~ (11FMBP and/or 12FMBP) cui of ser-..X:e OR a.lb The diesel-driven pump (DFP) cx.rt of service.

OR a.lc As determined by FP Engineering.

Refer w Na~.e 2. 2. a far gui.-J aoce.

At all times.

a7 One water supply out of service.

Refer tolifot.e 2.2.b frx guidaoce wren ihe FWST level inslnlmffll channel or tank reliH capai:Kiity is impaired.

At all times.

a.3 Any valve or pipe necessary to s:upply fixed automatic suppression sr:;tems or nose sla:iar..Jhydrants protecting safety-relared or sale"'lnutdcwm related area.s oul ol ser..X:e.

At all times.

b.1

'ilith the high-pressure water fire protedion syslem impaired 1n a manner other than permitted by 2.a.1 or2.a. 2.

b2 Required Action and as-sociated Aciion Time of Impaired Condlioo b.1 noi met REQUIRED ACTION a.l.a Res~cre to functional stallm.

a.tb

a. I.e a..i' Restore to functional stallm.

a.J See Required Aclion for ~ecific fi~ed automatic SJ.!Ppree>>ioo sysiem or hose statiOOGihydran:s served by the ponion cf the S/'Slem !hal is impaired.

b.t An akemate fire pro\\ecticn system shall be established.

b.L.a Be in MODE J.

AND b.2.b Be in MODE 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. t a a.lh aJ.c a.Z a.3 b.t b.2.a b.2.b SA0-703 REV 34 ACTION TIME1 Wr.hirll da)*s.

W~hin I days.

See oorre<iponding l".dion Time.

Wl\\tin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Wl:Nn 3() hours.

Wl1tin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

I

Appendix C Page 9 Form ES-C-1 DESCRIPTION REOUIREJ.IHIT

3.

Fire Protecti.on a.1 The Electrical Tunnel Fire Spray Systems Protection Wa:e1 Spl'l!y System (Includes (EJ-33 ft. Cont10l Building to EJ-sprinkler 68 ft. PAS - Fire Zone 32A) shall systems and be functional deluge systems) a.Z The Diesel Ger;era:ar Building Refer to Nate 2. 0 Water Spl'l!y Sys:em {in EDG for additiornl BW:Jing -Fire Zone 10) shaB be guidance functionaL

b.

The spray systems lisled oo Table 1-3 shall be functional.

a.

b_

ADDENDUM I FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA Page 3 of 23 APPLICABILITY IMPAIRED CONDITION IA'henever safeiy-related ex safe-

a.

kiy spray system iflllaired.

shutdom1 rela:ed equipmeni in the area is required to be opel'l!ble.

1Nherever equipment in 1he area is

b.

kly spray system iflllaired.

required tiJ> be q~erable.

REQUIRED ACTION a.1 Additional fire hose{s) mall be provided and Ia bled to seJVe the alfede..d location(s) from a functional hose stiltior(si 01 hydr<~nt(s ). Refer ll> Nrxe2.3 lrx :Jddit.iarul guidance.

AND a.i' The impaired spl'l!y syslem(s) shall be res:ored to functional s!a:us.

a.3 lferify add:iCIIill ccmpensa:OI'f fire hose is st:~ged as required by a_ 1 abC'1e b.l.a E.siablish a 4-llour fire watch tour to irr.pect the affeaed fire zooe(s)_

OR b.1.b If frle affected zcr.e is ec;uipped with a fire detection sys:em (see Table 1-3}, ;*erify tha1 the fire de~edioo equipment in me zone is functional.

OR b.lc Additional fire hose(s) shall be pro*1ided to serve d:e affeo:ed locatior(s) from a functional hose s!a:ioo[s) or hydrant(s}.

Refer to Note 2. 3 fct add~imll gridance.

AND b.Z Res:ore to furd ional status.

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

9 of 12 a_l a.Z a.3 b.l b.2 SA0-703 REV34 ACTION TIME1 VYhtin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

W!thn 1 ~ days_

'::veri 9() =

7 days VYI:tin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

VYhbn jl) days_

Appendix C Page 10 Form ES-C-1 DESCRIPTION REQUIREMENT

4.

Fire Hose

a.

Fire hose stations and nydrams Stations and shewn on Table 1-4 shall be Hydrants functicnaL Refer to Nore 2. 0 far additio!lill grida~:e

b.

Fire hose stations and nydrants on the high-pressure fire loop other than those shown on Table l-4 shall be functional.

NOTE: The flose sta!icn oo the roof ci the FSB and the law-pressure hydrants in the City i'~ter Sy~em are NOT I

INCLUDED in this functionality requireme11t.

a.

b.

ADDENDUM I FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA Page 4 of23 APPLICABiliTY IMPAIRED CONDITION Wherever safely-related a safe-

a.

Arly fire hose sta~ioo or hydrant li31ed on shutdcum relaled equipmeni in the Table 1-~ is impaired areas protected by !he oose stations and hydrants is r~ired to be operable.

\\l','henever equipment protected by

b.

Any hi<;jl-pressure fire nose stati:Jn a the hose sta~cm and hydrants in lhe hydrant other than 1hose listed on T ahle area is required to be operable.

l-4 is impaired.

REOUIRHl ACTION a.1 Additmrul fire hcse(s) shall be pro*1ided and labled to serve ihe affected localioo(s) from an funcliooal hose stati~s) 01 hydrant(s). Refer ta NO(e 2.3 fa: addi!iooal !)tiidance.

AND a.Z The impaired equipment shall be resr.ared to functicnal !t.aius.

a.3 Verify eddi:icnal campensa~o!J' fire hose is staged as req11ired by a.1 abC'Ie b.1.<l Establish a ¢-hour fire watch tour 1D inspect the affected fire zcne(s)_

.00.

b.tb If ~e affected zone is equipped with a fire detectioo s~em (see Tables 1-1 and 1-2).

~erify !hal the fire detection equipment in the zcrne is functional.

00 b.1.c Additional fire hose{s) shall be provided to serve !he affected location(s) fran a functional hose sta~ ion(s) 01 h;*drant(s).

REier to Noie 2.3 /()( add~iooal guidance.

AND b.2 The impaire<J equipment shan be res:ored to functiooal ~alii£.

Nate: 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-2 a.J b.l b.2 SA0-703 REV 34 ACTION TIME I Wi:hin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Whlin 14 day>>.

Every 91} :7 days Whhin il hours.

Vvhhin 30 day>>.

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.

1. 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:

Facility Evaluator:

Method of testing:

Simulated Performance Classroom X

READ TO THE EXAMINEE NRC Examiner:

Date:

Actual Performance Simulator Plant 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 1 00% 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 13WDST 97 22972 Chern Sample Number Sample Dateffime Total Gamma Activity ADC 150 gpm Today 01:00 Today 05:45 4807 Today 05:30 4.0E-5 5.31 E-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:

--./ 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 1JCilml 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 -Y)

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 IJCi/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 ~ )

8. Performance Step:

Standard:

Comment:

~ 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.

~ 10. 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...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

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 Pa e 1 of 1 INITIAL PERMIT# 07300 TANK 10 13 WDST Tank Level :~

(Inches) 22972 Volume (V), gal RECIRC RATE:

Chemistry

---

'-'15=0 __ gpm Sam le No.

4807

___,_T""od"-'a"-.J.y __ (Date)

___,_T=od=a"-'y__ (Date)

Toda 01 :00 05:45 (Date)

Recirc time is inadequate it should be 306 minutes ( 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 6 minutes)

Sample time too early Total Gamma Activity _4;!:.:*~0E,_--"'5 ____

~Cilml Allowed Diluted Concentration (ADC) 5.31 E-7

~-~-----.-~

TOTAL DILUTION FLOW (T} _......:5=0_.;.;4,=00=0'-----_(GPM)

From:

---

>.: Unit 2 Circulators

---

" Unit 3 Circulators

---

" 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, uCi/ml Gamma Act (C), uCi/ml Most Restrictive Relea Rad Monitor #

54 1.07E-3 uCi/ml Actual Alarm Set oint =

4.0E-5 uCi/ml Warn Set oint=

3.0E-5 DISCHARGE FLOW METER & RECORDER OPERABLE _X_YES NO (IF NO. COMPLETE ATIACHMENT 3)

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) g,al 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 Date/Time 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 (PaQe 1 of 1)

INITIAL PERMIT#

070300 TANK ID 13WDST Tank Levei:JIT__ (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 iJCi/ml Allowed Diluted Concentration (ADC) 5.31 E-7 iJCi/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 Dil Flow (B), gpm ppm B Radioactive Release Rate:

(Rr) = (

504,000 X

5.31 E-7

) +

4.0E-5

=

6691 gpm Avail Dil Flow (B), gpm ADC, uCi/ml Gamma Act (C), uCi/ml Most Restrictive Release Rate (R) =

250 gpm (pump capacity most limiting)

Rad Monitor #

54 SOURCE CHECKED _X_

OPE.RABLE __LYES -- NO (IF NO, COMPLETE ATT 3)

Maximum Alarm Setpoint = (

504,000 X

5.31 E-7

) +

250

=

1.07E-3 uCi/ml Avail Dil 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:

SROAdmin 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.

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.

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 --J)

1. Performance Step:

chart Obtain correct procedure IP-EP-120 orEAL Standard:

Give candidate Wall Chart Comment:

-../ 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.

-../ 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

-../ 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 New York State Release of Radioactive Materials due to the Classified Fvent i

To Atmosphere:

~~~

3. 11-...;:::::

B. Release BELOW Faderallimits I

j C. Release ABOVE Federal Limits To Water:

t~ N;;-;ela~ *

~ _

i B. Release BELOW Federal Limits I

, C. Release ABOVE Federal limits Notification #

(

D. Unmonitored Release Requiring Evaluation

! D. Unmonitored Release Requiring Evaluation I

j The following Protective Actions are recommended to be Implemented as soon as practicable:

.. I A. NO NEED for PROTECTIVE ACTIONS outside the site boundary B. EVACUATE and IMPLEMENT the Kl PLAN for the following Sectors

.:,(:

C. SHEL T =R-IN-PLACE and IMPLEMEN I the Kl PLAN for the following Sectors 2 miles around 5-rniles downwind:

in the following Sectors: 1 2

3 4

5 13 14 15 16 i ;

i 2 miles around 10-rniles downwind:

• I II 2

3 II II lnt'lefollowingSectors: 1 4

5 6

7 8

9 10 11 12 13 14 15 16 I

1 1 I j

Ail remaining Areas MONITOR the ::MERGENCY ALERT SYSTEM I

I I

NOTE: OI=FSITE AuTHORITIES SHOULD CONSIDER SH!::LTER-IN-0 lACE + TAKE KJ IF EVACUATION IS NOT !"EASIBLE i I

! EAL#: S6.:l.l f~d"'-~"t of. ScA.;tDrl\\~1\\c ~

~

"'*"""~(.fnpj Affected Location* j I

~\\~~l S -tt. r'!'~ Cl ~~~ t'~~ ~ ilj#Jo

~NIT 2 __)

5. ;

A~ l).

. L '

l ~~\\

1'(\\Mf.A.II\\I~t e""""-me'll\\'\\ ("t"f..t-4 \\fl*\\~ """+r!( I~TV B. UNIT 3 "D-'f'b Oa.th ;"'

f.J). ~ ~fA:f ~~~

C. lPEC SITE I

Reactor Status:

6_ ; Unit 2: Operational o(i:~ at 1,' Unit 3~~::Uor Shutdmvn at (Date) I til> A 1./

(Time) !lJ,j 3 (24 hr c!ockj (Date}. _ _____ (Time) _____

_ (24 hr clock)

I

~7_:_* _:_

i =VIfi=m=d=S~:"'ee=d~:==:J=*=.;;;

===::;;;;::::~M:_:eters1Sec at elevation 10 meta_rs _ ____________ ____ _

55""

8.

• Wind Direction: iFrcml Degrees ai elevation -, 0 meters

9. ' Stabilitv Class:

A ~

C--D-E F

G

, "! O. ; Reported by - Communicator:--------------- Telephone# __________ _

(Carnmunicator s fl:ar;;s}

-*-----Jl~~;~

71-

• 11_

• Emergency Director Approval: AJ(,___,..,

Date/Time: ~'t CU U6..[""TIU~ i i f~*irectcr's Name.1 r

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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.