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
Shared Package
ML14190B006	List: ML14195A131 ML14251A240 ML14307B385 ML14307B521 ML14307B565 ML14308A052 ML14308A251
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Download: ML14308A251 (48)

Text

Append ix C Job Performance Measure Form ES-C- 1 Worksheet Indian Point Unit Facility: 2 Task No: 2000660122 Task Title: Determine Reportability Requirements 2.1.18 Job Performance Measure SROAdmin SRO 3.8 KIA

Reference:

---

~~~------ No: 1a Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

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

• 3.3.5 Loss of Power Diesel Generator Start 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 Form ES-C-1 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 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: Obtain Correct Procedures Standard : Obtains Technical Specifications and IP-SMM-LI-108.

Comment:

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

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

Comment:

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

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

Comment:

Terminating Cue: JPM Complete 3 of 5

Appendix C Page 4 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: _ _ _ _ __ _ _ _ __

4 of 5

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

2.1 .37 Job Performance Measure KJA

Reference:

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

Facility Evaluator: Date:

Method of testing :

Simulated Performance Actual Performance X Classroom X Simulator Plant READ TO THE EXAMINEE I will 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 100% power.

2. The RO has calculated a QPTR manually.

3. There is indication of a misaligned rod. The RO calculated a QPTR of 1.0638 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 Job Performance Measure Form ES-C-1 Worksheet Required Materials: Calculator General

References:

3-SOP-15.3, Quadrant Power Tilt Calculation 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: Checks Detector currents recorded from QPTR Data Sheet recorded Comment: For this QPTR calculation, the values for N42 top and N42 bottom were incorrectly entered in the wrong location. The current value for N42 top was entered in N42 bottom and N42 bottom was entered in location for N42 top.

Candidate may identify error at this time.

Candidate may elect to calculate independently and compare results.

3 of 14

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

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

4. Performance Step: DIVIDE each detector output by corresponding normalization factor Standard: 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: If three detectors are to be used in the calculation, change denominator from 4 to 3 Standard: Checks "4" for denominator on top and bottom average equations recorded Comment:

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: CALCULATE Quadrant Power Tilt for top and bottom detectors Standard: 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: RECORD highest Quadrant Power Tilt and appropriate signatures.

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

Comment:

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

• COMPARES the calculated QPTR to Tech Spec 3.2.4

• DETERMINES that the calculated QPTR is GREATER THAN the Tech Spec allowable value of 1.02 Comment: Due to error in data entry, the Calculated QPTR is 1.0638. 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 = 1.0506 42 Top= 42T = ~ 136.6 = 1.0637 42 Bottom= 42B ~ 144.3 = .8344 43 Top= 43T = 122.9 I* 118.3 - 1 . Q3S~ 43 Bottom = 43B = 124.2 I* 119.3 = 1.0411 44 Top- 44T- 89.4 I* 87.4 = 1.Q,,~ 44 Bottom - 44B - 109.7 /*107.1 - 1 !J'::I3

..

Answer Key Incorrectly Calculated Errors ldent1fled

2. 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

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

SNSC REVIEW DATE TIME* 30 min11tes ago AVE REACTOR PWR* 1005 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 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 100% power.

2. The RO.has calculated a QPTR manually.

3. There is indication of a misaligned rod. The RO calculated a QPTR of 1.0638 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: -:::I!:!'adO!!a~\1,...._-

SNSC REVIEW DATE 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 = 1.0506 42 Top= 42T = 145.3 I* 136.6- 1.0!2~7 42 Bottom = 42B = 120.4 I* 144.3 = .8344 43 Top= 43T= 122.9 I* 118.3 = l.Q3B~ 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 - 1 02~3

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

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

SNSC REVIEW DATE TIME* 30 min11tes 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= I* 129.1 = 41 Bottom = 41B = I* 122.s =

42 Top= 42T =

• 136.6 = 42 Bottom = 42B = I* 144.3 =

43 Top= 43T = I* 118.3 = 43 Bottom = 43B = I* 119.3 =

44 Top- 44T- I* 87.4 - 44 Bottom - 44B - /*107.1 -

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

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

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

4

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

[ITS] Technical Requirements Manual 3.2.A:

Quadrant Power Tilt Top= 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 Job Performance Measure Form ES-C-1 Worksheet Indian Point Unit Facility: 2 Task No: 2000340122 Task Title: Identify Isolation Boundaries and Required Actions High Pressure Fire Protection 2.2.41 Job Performance Measure KIA

Reference:

SRO-

---

~~~~----

3.9 No: SRO Admin 3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

Initial Conditions:

• The unit is operating at 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 Form ES-C-1 Worksheet General

References:

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

2 of 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: Identify Isolation Boundaries Standard: Identifies the following valves to be isolated:

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

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

.Y 3. Performance Step: Identifies affected equipment Standard: Identifies the following affected equipment o High Pressure Hydrants #23, #24, #25, #26 o Electrical Tunnel Deluge o PAB Hose Station (Alternate supply will maintain hose pressure. This is not required for evaluation for compensatory actions Comment: 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: Identifies Required Actions from SA0-703 Standard: 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 19 Yard Area 15" 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)*

20 Yard Area 18'-6" Transformer yard, Hydrant 25HPH and Hose south of the ABFP Cabinet No. 7 (with fire hose Building and nozzles to serve the ABFP Building) 21 Yard Area 70' 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 Page 7 Form ES-C-1 F

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

DET. "R" OWG. A227oo2 BLDG. I l/2 "

2

"'P.) N673 6" -

TO fi()SE REEL 10" FP*711 RISER SEE DET . *ss*. w

. DWG. A227554 H z

ClJ

>- cr ;;;

0

<( ~

(!) f- ...

0 a 0 N~

CONDENSER #22 I> w ~ D r;:,

,._ I NTAKE STRUCTURE 1- C\!

z ,., 10"

-"'

<(

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

w I

"'~ f-UJ H TO BOILER FEED PU.V.P D~Lu:;~ FP-5 12 SEE TYP. DELUGE V~.LVE STAT. !.

DET. "P" D'.IG. A227552 5

TO SEAL OIL UN IT DELUGE SEE TYP. OSLUGE VALVE STAT. !.

DET, " L

• OWG. A227552 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 brsER SEE 4" SEE DET. "B" OWG. A227551 PET. "AA" DWG. A.227~'5L I

II CONTROL BLDG.

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

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

STAIR #L * - FI I 1o*

Blue Affected Con1ponents Red Isolation Boundaries 7 of 12

Appendix C Page 8 Form ES-C-1 ADDENDUM I SA0-703 FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA REV 34 Page 2 of 23 DESCRIPTION REQUIREMENT APPLICABllllY IMPAIRED CONDITION REQUIRED ACTION ACTION TIME1

z. High-Pressure a1 BOTH motor-1Jriven fue main a.l At all times. a.la One or beth rooior driven fire main a.l.a Res~cre to functional stallm. a. t a Wr.hirll da)*s.

Water Fire booster pum~ (1 1FMBP and booster pum~ (1 1FMBP and/or 12FMBP) a.tb a.lh Protection 12fMBP) AND ciiesel-clriven fire cui of ser-..X:e a.I.e aJ .c System pump (DFP) funr.1ional and OR properly aligned to !he nigh-lmpa;ired pressure fire header. Refer to a.lb The diesel-driven pump (DFP) cx.rt of condncns 2.a. ta Nrxes 2.2.a and 2.2.cfa- service.

and2.a.2may add~it:rul gtidance. OR exist coocwreN!y, a.lc As determined by FP Engineering.

lmpa;ired condi'jcns 2. a.1.b Refer w Na~.e 2. 2. a far gui.-J aoce.

and 2.a.2 may One water supply out of service. a ..i' Restore to functional stallm. a.Z W~hin I days.

a.2 A minimum a*1ailable waler a.2 At all times. a7 exist coocwreN!y, volume of 300,000 gallons oomained in !he Citt Water Tank Refer tolifot.e 2.2.b frx guidaoce wren ihe lmpa;ired and 300,000 gallons contained irl FWST level inslnlmffll channel or tank condrncns 2.a. I.e the Fire Water StOfage Tank for reliH capai:Kiity is impaired.

and2.a.2may fire protedioo p~es.

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

a.J AJI J;iping and vall'es necessarf a.3 At all times. a.3 Any valve or pipe necessary to s:upply a.J See Required Aclion for ~ecific fi~ed a.3 See oorre<iponding for addtionai for proper functioning c4 any fixed automatic suppression sr:;tems or automatic SJ.!Ppree>>ioo sysiem or hose l".dion Time. I gbTdarJCe portion of the sysl.em required lor nose sla:iar..Jhydrants protecting safety- statiOOGihydran:s served by the ponion cf proredion of safety-rela:ed or relared or sale"'lnutdcwm related area.s the S/'Slem !hal is impaired.

safe-stl.rtdown systems oul ol ser..X:e.

functionaL Refer tD Nrxe 2.2. e fer add~ir:ml quidance.

b. fiigl'l-preosure water fire b. At all times. b.1 'ilith the high-pressure water fire b.t An akemate fire pro\ecticn system shall b.t Wl\tin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

protection sys(em functional as protedion syslem impaired 1n a manner be established.

required by 2.a. 1 and 2.a.2. other than permitted by 2.a.1 or2.a. 2.

NOTE: Expiration of the Aclion Time for Items 2.a. 1 a'ld 2.a.2 b2 Required Action and as-sociated Aciion b.L.a Be in MODE J. b.2.a Wl:Nn 3() hours.

does NOT re~uire enlry ir.:o Item Time of Impaired Condlioo b.1 noi met AND 2.b.

b.2.b Be in MODE 5. b.2.b Wl1tin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Not e: 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

Appendix C Page 9 Form ES-C-1 ADDENDUM I SA0-703 FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA REV34 Page 3 of 23 DESCRIPTION REOUIREJ.IHIT APPLICABILITY IMPAIRED CONDITION REQUIRED ACTION ACTION TIME1

3. Fire Protecti.on a.1 The Electrical Tunnel Fire a. IA'henever safeiy-related ex safe- a. kiy spray system iflllaired. a.1 Additional fire hose{s) mall be provided a_ l VYhtin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Spray Systems Protection Wa:e1 Spl'l!y System shutdom1 rela:ed equipmeni in the and Ia bled to seJVe the alfede..d (Includes (EJ-33 ft. Cont10l Building to EJ- area is required to be opel'l!ble. location(s) from a functional hose sprinkler 68 ft. PAS - Fire Zone 32A) shall stiltior(si 01 hydr<~nt(s). Refer ll> Nrxe2.3 systems and be functional lrx :Jddit.iarul guidance.

deluge systems) AND a.Z The Diesel Ger;era:ar Building Refer to Nate 2. 0 Water Spl'l!y Sys:em {in EDG a.i' The impaired spl'l!y syslem (s) shall be a.Z W!thn 1~ days_

for additiornl BW:Jing - Fire Zone 10) shaBbe res:ored to functional s!a:us.

guidance functionaL a.3 lferify add:iCIIill ccmpensa:OI'f fire hose is a.3 =

'::veri 9() 7 days st:~ged as required by a_1 abC'1e

b. The spray systems lisled oo b_ 1Nherever equipment in 1he area is b. kly spray system iflllaired. b.l.a E.siablish a 4-llour fire watch tour to b.l VYI:tin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Table 1-3 shall be functional. required tiJ> be q~erable. 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. b.2 VYhbn jl) days_

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

9 of 12

Appendix C Page 10 Form ES-C-1 ADDENDUM I SA0-703 FP/ASSS EQUIPMENT IMPAIRMENT CRITERIA REV 34 Page 4 of23 DESCRIPTION REQUIREMENT APPLICABiliTY IMPAIRED CONDITION REOUIRHl ACTION ACTION TIMEI

4. Fire Hose a. Fire hose stations and nydrams a. Wherever safely-related a safe- a. Arly fire hose sta~ioo or hydrant li31ed on a.1 Additmrul fire hcse(s) shall be pro*1ided a. l Wi:hin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Stations and shewn on Table 1-4 shall be shutdcum relaled equipmeni in the Table 1-~ is impaired and labled to serve ihe affected Hydrants functicnaL areas protected by !he oose stations localioo(s) from an funcliooal hose and hydrants is r~ired to be stati~s) 01 hydrant(s). Refer ta NO(e 2.3 Refer to Nore 2. 0 operable. fa: addi!iooal !)tiidance.

far additio!lill AND grida~:e a.Z The impaired equipment shall be resr.ared a-2 Whlin 14 day>>.

to functicnal !t.aius.

a.3 Verify eddi:icnal campensa~o!J' fire hose is a.J Every 91} :7 days staged as req11ired by a.1 abC'Ie

b. Fire hose stations and nydrants b. \l','henever equipment protected by b. Any hi<;jl-pressure fire nose stati:Jn a b.1 .<l Establish a ¢-hour fire watch tour 1D b.l Whhin il hours.

on the high-pressure fire loop the hose sta~cm and hydrants in lhe hydrant other than 1hose listed on Tahle inspect the affected fire zcne(s)_

other than those shown on Table area is required to be operable. l-4 is impaired. .00.

l-4 shall be functional.

b.tb If ~e affected zone is equipped with a fire NOTE: The flose sta!icn oo the detectioo s~em (see Tables 1-1 and 1-2).

roof ci the FSB and the law- ~erify !hal the fire detection equipment in pressure hydrants in the City the zcrne is functional .

i'~ter Sy~em are NOT 00 I INCLUDED in this functionality requireme11t. 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 shanbe res:ored b.2 Vvhhin 30 day>>.

to functiooal ~alii£.

Nate: The provisions of paragraph 4.6 SHALL be fol lowed if the specified "Action Time" for AN Y Item in the Table is exceeded.

10 of 12

Appendix C Page 11 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: _ _ _ _ _ _ _ _ _ _ __

11 of 12

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

• The unit is operating at 100% power

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

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

• Water is not spraying on any electrical equipment.

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

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

• identify affected components

• determine compensatory actions.

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

Reference:

SRO

---

~~~~----

3.8 No: Admin 4 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

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

1 of 11

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

• The Unit is operating at 100% power.

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

• LWDST has been isolated.

• R-54 source check failed.

• 6 Circulating Water Pumps are operating at slow speed.

• No dilution flow is borrowed from Unit 3.

• A Manual Radioactive Liquid Release Permit was prepared.

• Additional Data:

Permit Number 070300 TankiD 13WDST Initial Tank Level 97 Pre-release volume 22972 Recirculation Rate 150 gpm Recirc Start- Today 01:00 Recirc Stop Today 05:45 Chern Sample Number 4807 Sample Dateffime Today 05:30 Total Gamma Activity 4.0E-5 ADC 5.31 E-7 ppm Boron in tank 849 Initiating Cue: You are the CRS and the SM has directed you to review the Manual Liquid Release Permit for 13 WDST in accordance with 2-SOP-5.1.5, Calculation and Recording of Radioactive Liquid Releases Required Materials: Calculator General

References:

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

2 of 11

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

1. Performance Step: Obtain Correct Procedure Standard : Obtain 2-SOP-5.1.5, Calculation and Recording of Radioactive Liquid Releases Comment: Give the candidate the procedure.

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

--./ 3. Performance Step: Record the following Standard: Permit Number Tank to be released Conservative estimate of volume to be released Recirculation rate and date/time of recirculation start/stop

• Radiochemistry analytical results Sample Number Sample Date/Time Total Gamma Activity in 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: Verify from Chemistry the total gamma activity WITHOUT noble gas is less than 5.0E-5 IJCi/ml.

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

5. Performance Step: Record the pre-determined dilution flow rate (B) for this release in gpm, from Step 4.1 .5.

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

Comment:

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

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

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

Standard: Determines 6691 is correct Comment:

4 of 11

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

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

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

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

Comment:

~ 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

No: 2-SOP-5.1.5 Rev: 38 CALCULATION AND RECORDING OR RADIOACTIVE LIQUID RELEASES Page 16 of 23 ATTACHMENT 1 EXAMPLE RADIOACTIVE LIQUID RELEASE PERMIT Pa e 1 of 1 INITIAL PERMIT# 07300 TANK 10 13 WDST Tank Level :~ (Inches) 22972 Volume (V), gal RECIRC ___,_T""od"-'a"-.J.y_ _ (Date) 01 :00 Recirc time is RATE: ------'-'15=0_ _ gpm inadequate it

___,_T=od=a"-'y__ (Date) 05:45 should be 306 Chemistry minutes ( 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Sam le No. 4807 Toda (Date) and 6 minutes)

Sample time too early Total Gamma Activity _4;!:.:*~0E,_--"'5_ _ _ _ ~Cilml Allowed Diluted Concentration (ADC) 5.31 E-7

~-~-----.-~

---

>.: Unit 2 Circulators TOTAL DILUTION FLOW (T} _......:5=0_.;.;4,=00=0'-----_(GPM) From: -----" 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 The initial Actual Alarm Set oint = 4.0E-5 uCi/ml Warn Set oint= 3.0E-5 conditions DISCHARGE FLOW METER & RECORDER OPERABLE _X_YES NO (IF NO. COMPLETE ATIACHMENT 3) identified R-54 source check Release Authorized By: - - - - - - - - - - - - - - - - -

failure i.e.,

INOPERABLE RELEASE INITIATED: _ _ _ _(Date) _____ ( Also need RELEASE TERMINATED: _ _ _ _ _(Date) _____ ( Attachment 3 FINAL TK LEVEL: _ _ (Inches) _ _ _ _g,al TOTAL VOLUME RELEASED _ _ _ _ _gal Remarks:

Appendix C Page 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __

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

• The Unit is operating at 100% power.

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

• LWDST has been isolated.

• R-54 source check failed.

• 6 Circulating Water Pumps are operating at slow speed.

• No dilution flow is borrowed from Unit 3.

• A Manual Radioactive Liquid Release Permit was prepared.

• Additional Data:

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

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

No: 2-SOP-5.1.5 Rev: 38 CALCULATION AND RECORDING OR RADIOACTIVE LIQUID RELEASES Page 16 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 Job Performance Measure Form ES-C-1 Worksheet Facility Indian Point Unit 2 Task No: 1500010522 Task Title: Classify Emergency Events Requiring Emergency Plan Implementation (Time Critical)

KIA 2.4.38 Job Performance

Reference:

SRO- 4.4 Measure No: SROAdmin 5 Examinee: NRC Examiner:

---

Facility Date:

Evaluator:

Method of testing:

Simulated X Actual Performance 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.

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

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

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

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

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

• The Turbine 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 Form ES-C-1 Worksheet General

References:

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

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

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

1. Performance Step: Obtain correct procedure IP-EP-120 orEAL chart 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

- -- - - - -- - - -- -- - ,

i New York State  ;

Notification # (

Release of Radioactive Materials due to the Classified Fvent

_*

i To Atmosphere: To W ater:

~~~

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

t~ N;;-;ela~

~ ....

I B. Release BELOW Faderallimits i B. Release BELOW Federal Limits I

j C. Release ABOVE Federal Limits , C. Release ABOVE Federal limits

._

'

___ _  ; 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:

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

C. SHELT =R-IN-PLACE and IMPLEMEN I the Kl PLAN for the following Sectors

.. I 2 miles around 5-rniles downwind:

in the following Sectors: 1 2 3 4 5 13 14 15 16 i 2 miles around 10-rniles downwind:

• I II lnt'lefollowingSectors: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 II II Ij Ail remaining Areas MONITOR the ::MERGENCY ALERT SYSTEM 1

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

'

i I I

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

• j

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

'*" ~NIT 2 __)

I

5. 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 (Date) I til> A1./ (T ime) !lJ,j 3 (24 hr c!ockj 1,'

-Unit- 3~~::Uor

....:...--- Shutdmvn at (Date}._ _ _ __ _ (Time) _ __ _ __ (24 hr clock)

I

~7_:_*_:_i=VIfi=m=d=S~:"'ee=d~:==:J =*=.;;;

===::;;;;::::~M:_:eters1Sec at elevation 10 meta_rs_ _ __ _ __ _ _ _ _ __ _ _ _ __

8.

• Wind Direction: i Frcml 55"" 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.r1 I i:

---

~

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 Form ES-C-1 Initial Conditions:

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

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

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

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

• The Turbine 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.