ML14307B565

Draft Operating Exam (Section a) (Folder 2)

ML14307B565
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Site:	Indian Point
Issue date:	10/29/2014
From:	Entergy Nuclear Indian Point 2
To:	Lally C M Operations Branch I
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ML14190B006	List: ML14195A131 ML14251A240 ML14307B385 ML14307B521 ML14307B565 ML14308A052 ML14308A251
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Appendix C Indian Point Unit Job Performance Measure Worksheet Facility:

2 Task No: 2000660122 Task Title: Determine Reportability Requirements 2.1.18 KIA

Reference:

SRO 3.8 Job Performance Measure No: Examinee: Facility Evaluator:

Method of testing: Simulated Performance Classroom X READ TO THE EXAMINEE NRC Examiner:

Date: X Actual Performance Simulator Plant Form ES-C-1 SROAdmin 1a I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:

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

• 3.3.5 Loss of Power Diesel Generator Start

• 3.8.1 AC Sources Operating

• Surveillance W-19 is complete

• The unit is in Mode 3

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

• 21 and 22 EDGs started

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

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

• 21 AFW pumps started

• 21 and 22 CCW pump started

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

1 of6 Appendix C Job Performance Measure Worksheet Required Materials:

Unti 2 Technical Specifications IP-SMM-LI-108, Event Notification and Reporting General

References:

Unti 2 Technical Specifications IP-SMM-LI-108, Event Notification and Reporting Time Critical Task: No Validation Time: 30 Minutes Form ES-C-1 Task Standard:

Applicable Tech Specs and Reporting requirements identified 2 of6 Appendix C Page3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 1. Performance Step: Standard:

Comment: 2. Performance Step: Standard: Comment: ...J 3. Performance Step: Standard:

Comment: ...J 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-ll-1 08 Determines 8 hr report due to valid actuation of AFW Item 59 (See item 49 for explanation) 1 OCFR50. 72(b)(3)(iv)(A)

Determine who must be notified Identifies:

NRC Operations Center within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Corporate Duty Manager Public Service Commission (PSC) 3 of6 Appendix C Page4 Form ES-C-1 Terminating Cue: JPM Complete 4 of6 Appendix C Page 5 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

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

5 of6 Form ES-C-1 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

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

• 3.3.S Loss of Power Diesel Generator Start

• 3.8.1 AC Sources Operating

• Surveillance W-19 is complete

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

• 21 and 22 EDGs started

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

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

• 21 AFW pumps started

• 21and 22 CCW pump started

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

Appendix C Job Performance Measure Worksheet Form ES-C-1 Indian Point Unit Facility: 2 Task No: 2000070122 Task Title: Review a Manual QPTR Calculation (4 Detectors 100%) 2.1.37 Job Performance Measure KIA

Reference:

SRO 4.6 No: SRO Admin 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 explain the initial conditions, which steps to simulate or discuss , and provide initiating cues. When you complete the task successfully , the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Reactor power is stable at 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 1.0643 and recommends a Power Reduction to s 81.7%. 4. No Physics testing is in progress. Initiating Cue: You are the CRS and the SM directed you to review the QPTR and sign as SM Designee and , approve any required actions by Tech Spec identified including maximum allowable power operation and time limits. Required Materials: Calculator General

References:

3-SOP-15.3, Quadrant Power Tilt Calculation DSR-48 Unit Two Quadrant Power Tilt Calculation Sheet 1 of 15 Appendix C Time Critical Task: No Validation Time: 20 Minutes Job Performance Measure Worksheet Form ES-C-1 Task Standard:

Calculation reviewed and errors corrected, identify incorrect TS actions. 2 of 15 Appendix C Page3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..../) EVALUATOR NOTE: Give the examinee the attached Detector Current Data Sheet and a DSR-48 form that has the proper normalization factors recorded.

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

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

SOP 15.3, "Quadrant Power Tilt Calculation" Comment: 2. Performance Step: Check top and bottom detector currents recorded. Standard: 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. Performance Step: Record Date , Time and Average Reactor Power Standard: Comment: Checks Current Date and Time and average Reactor Power of 1 00% recorded 3 of 15 Appendix C Page4 Form ES-C-1 Performance Informat i on (Denote critical steps with a check mark ...J) 4. Performance Step: Standard: DIVIDE each detector output by corresponding normalization factor Checks calculations

• CALCULATES normalization ratio

• RECORDS on form DSR-48 Comment: Candidate may identify error at this time. Candidate may elect to calculate independently and compare results. [See Key for actual values] 5. Performance Step: Standard: Comment: 6. Performance Step: Standard: 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 CALCULATE average normalized ratio for top and bottom Checks calculations

• CALCULATES the top and bottom normalized averages

• RECORDS on form DSR-48 Comment: [See Key for actual values] 4 of 15 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 7 Performance Step: Standard:

CALCUL.A TE Quadrant Power Tilt for top and bottom detectors Checks calculations

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

• RECORDS on form DSR-48 Comment: [See Key for actual values] ...J 8. Performance Step: Standard:

Comment: RECORD highest Quadrant Power Tilt and appropriate signatures.

If Candidate does not identify the error, the QPTR will appear correct 5 of 15 Appendix C Page6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ...J 9. Performance Step: If quadrant power tilt exceeds 1.02 in either top or bottom of core, ensure requirements of Technical Specification 3.2.4, Quadrant Power Tilt Limits are met Standard:

PERFORMS both of the following:

• COMPARES the calculated QPTR to Tech Spec 3.2.4

• DETERMINES that the calculated QPTR is GREATER THAN the Tech Spec allowable value of 1.02 Comment: Due to error in data entry, the Calculated QPTR is 1.0648. This would result in a power reduction to <80. 7%. This is a second error The actual QPTR is 1.0753. This would result in a power reduction to S 77.4% . ...J 10. Performance Step: DETERMINE Required Tech Spec Actions. Standard:

PERFORMS both of the following:

• REFERS to Tech Spec action 3.2.4

• DETERMINES the following actions are required:

1. Either QPTR is reduced below 1.02 OR 2. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, a. Reactor Power must be reduced to below 77.5% ( ;t0.5%) Comment: Additional Tech Spec actions will be required within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, however they are not part of the requirement for satisfactory completion of this JPM 6 of 15 Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ...J 11. Performance Step: DETERMINES QPTR CALCULATION IS NOT CORRECT Standard:

Determines correct value for QPTR 1.0753. Determines correct maximum power level 77.5% Comment: Terminating Cue: JPM Complete 7 of 15 Appendix C Page 8 Form ES-C-1 UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. 193 Previous SNSC #2545 11/5/98 (QT-20-31)

SNSC REVIEW DATE DATE:

__ TIME* 30 mjgntes ago AVE REACTOR PWR: I 00% APPROVED (RE) DATE USING DETECTOR OUTPUT CURRENT APPROVED DATE Answer Key Incorrectly Calculated Errors Identified .

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

1. Determine normalized ratios by dividing indicated detector current by normalization factor as follows: £ITS] Technical Requirements Manual 3.2.A: Channel Det Current Nor Ratio Channel Det Current Nor Ratio 41Top=41T= 139.7 /*129.1= 1.0821 41 Bottom= 41B = 128.7 /* 122.5 = 1.0506 136.6= 1.0637 42 Bottom= 42B 144.3 = .8344 43 Top=43T= 122.9 I* 118.3 = 1 QJ82 43 Bottom = 438 = 124.2 /* 119.3 = 1.0411 44 Top=44T= 89.4 /* 87.4 = I !!222 44 Bottom = 448 = 109.7 /*107.1 = I Q2!1J Answer Key Incorrectly Calculated Errors Tdenttfied

2. Determine the average normalized ratio for the top and bottom. Average Normalized Ratio Top = ANRT = 41T + :2T + 43T +

Average Normalized Ratio Bottom= ANRB = 41B + :28 + 43B +

3. Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio. £ITS] Technical Requirements Manual 3.2.A: Quadrant Power Tilt Top = QPTT = Highest value of 41 T. 42T. 43T, or 44T ANRT QPTT=

4. The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of 1.0200. [ITS] Technical Requirements Manual 3.2.A: Enter the Higher QPT(Top or Bottom) Technical Specification Limit = 1 . AnswerKe I. If the quadrant power tilt exceeds the Tech. Spec. limits, the SM, OM , RE and GM-NPG shall be informed ASAP. 2. If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3). RO: ________________________

Page 1 of1 8 of 15 Appendix C Page9 Form ES-C-1 UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. 193 Previous SNSC #2545 11/5198 (QT-20-31)

SNSC REVIEW DATE DATE:

TIMF> 30 mjputes ago AVE REACTOR PWR

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

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

I. Determine normalized ratios by dividing indicated detector current by normalization factor as follows: [ITS] Technical Requirements Manual 3.2.A: An K C tiCIItd swer ey orrec .ty acu ae Channel Det Current Nor Ratio Channel Det Current Nor Ratio 41 Top=41T= 139.7 I* 129.1 = 1.0821 41 Bottom= 41B = 128.7 I* 122.5 = 1 05()6 42Top=42T= 120.4 I* 136.6 = .8814 42 Bottom= 42B = 145.3 I* 144.3= 1.0069 43 Top=43T= 122.9 l 43 Bottom = 43B = 124.2 I* I19.3 = 1.0411 44 Top=44T= 89.4 I* 87.4 = 1 Q222 44 Bottom= 448 = I09.7 1*107.1 =

2. Determine the average normalized ratio for the top and bottom. Average Normalized Ratio Top = ANRT = 41T + 42T + 43T + 44T=__, 1_,_,.0<><0"'6"'" 3 ______ _ 4 Average Normalized Ratio Bottom= ANRB = 41B + 428 + 438 + 44B=_"-'1.

_,.03..., 0 .... 7 ,__ ____ _ 4 Answer Key Correctly Calculated

3. Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio. [ITS] Technical Requirements Manual 3.2.A: Quadrant Power Tilt Top= QPTT = Highest value of 41T. 42T, 43T, or 44T ANRT Value= I 0821 QPTT = ANRT = 1.0063 Quadrant Power Tilt Bottom= QPTB = Highest value of 41B, 428. 438. or 448 ANRB Value= I 0506 QPTB = ANRB = 1.0307 = ------L...IL.I.Ol.L-

---

4. The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of I.0200. [ITS] Technical Requirements Manual 3.2.A: Answer Key Correctl y Calculated Enter the Higher QPT(Top or Bottom) = _!_. JL 7 5 3 Technical Specification Limit = I . 0 2 0 0 NOTES: I. If the quadrant power tilt exceeds the Tech. Spec. limits, the SM, OM, RE and GM-NPG shall be informed ASAP. Answer Key Correctly Calculated

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

Page 1 of I 9 of 15 Appendix C Page 10 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation

Question: Response:

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

10 of 15 Form ES-C-1 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 1.0643 and recommends a Power Reduction to< 80.5%. 4. No Physics testing is in progress.

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

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

SNSC REVIEW DATE DATE:

TJME* 30 mjgntes ago AVE REACTOR PWR: I 00% APPROVED (RE) DATE USING DETECTOR OUTPUT CURRENT APPROVED DATE

• I. Channel Current QT number and Normalization Factors provided by Reactor Engineer. Determine normalized ratios by dividing indicated detector current by normalization factor as follows: [ITS) Technical Requirements Manual 3.2.A: DetCurrent Nor Ratio Channel DetCurrent Nor Ratio 41 Top=41T= 139.7 I* 129.1 = 1.0821 41 Bottom= 41B = 128.7 I* 122.5 = 42 Top=42T= 145.3 I* 136.6 = 1.0637 42 Bottom = 42B = 120.4 I* 144.3= 43 Top=43T= 122.9 I* 118.3 = 1 QJ82 43 Bottom = 43B = 124.2 I* 119.3 = 44 Top=44T= 89.4 I* 87.4 = 1 Q222 44 Bottom= 44B = 109.7 1*107.1 = 2. Determine the average normalized ratio for the top and bottom. Average Normalized Ratio Top = ANRT = 41T + 42T + 43T + 44T=__,_1""'.0o:::5.:..19"---------

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

4 1.0506 .8344 1.0411 I

3. Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio. [ITS) Technical Requirements Manual 3.2.A: Quadrant Power Tilt Top = QPTT = Highest value of 41 T, 42T. 43T. or 44T ANRT Value= 1.0821 QPTT = ANRT = 1.6519 1.0287 Quadrant Power Tilt Bottom= QPTB = Highest value of 41B. 42B.

43B, or 44B ANRB Value= 1.0506 QPTB = ANRB = .9876 -

4. The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of 1.0200. riTS) Technical Requirements Manual 3.2.A: Enter the Higher QPT(Top or Bottom) = .L _Q_ _§_ .1.. ..§.... Technical Specification Limit = 1 . 0 2 0 0 NOTES: 1. If the quadrant power tilt exceeds the Tech. Spec. limits, the SM , OM, RE and GM-NPG shall be informed ASAP. 2. If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3). RO: __________________________ 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 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:

TIME* 30 mjgutes 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 41 Top=41T= /* 129.1 = 41 Bottom= 41B = 42 Top=42T= ,. 136.6 = 42 Bottom= 42B = 43 Top=43T= ,. 118.3 = 43 Bottom = 43B = 44 Top-44T-,. 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 Det Current Nor Ratio ,. 122.5 = /*144.3= ,. 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= QPTT = Highest value of 4 IT. 42T. 43T.

or 44T ANRT QPTT = ANRT = 1.0519 Quadrant Power Tilt Bottom= QPTB = Highest value of 41B, 42B, 43B, or 44B ANRB Value= ______ _ QPTB = ANRB = .9876 = 4. The higher of the two quadrant oower tilts should be less than or equal to the Technical Specification Limit of 1.0200. [ITS] Technical Requirements Manuai3.2.A:

Enter the Higher QPT(Top or Bottom)= Technical Specification Limit 1 . 0 2 0 0 NOTES: I. If the quadrant power tilt exceeds the Tech. Spec. limits , the SM, OM , RE and GM-NPG shall be informed ASAP. 2. If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3).

Appendix C Initial Conditions Form ES-C-1 R O: _________________________ Page 1 o f l 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.

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

• Water is not spraying on any electrical equipment.

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

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

• identify affected components

• determine compensatory actions. Required Materials:

None 1 of 10 Appendix C Job Performance Measure 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 10 Appendix C Page3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 1. Performance Step: Obtain SA0-703 and required prints. Standard: Obtains procedure and prints Comment: Location of procedure and prints is not required for this JPM. Hand candidate the procedure and prints ..J 2. Performance Step: 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 Comer Transformer Yard) may be identified.

This is not required; however, it is not incorrect to isolate. v 3. Performance Step: Standard:

Comment: 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 3 of 10 Appendix C Page4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ...J 4. Performance Step: Standard:

Comment: Identifies Required Actions from SA0-703 Identifies the following Required Actions o 2.a.3 High-Pressure Water Fire Protection System (Not Critical) o 3.a.1 Fire Protection Spray Sytstems (Includes sprinkler systems and deluge systems) o 4.a Fire Hose Stations and Hydrants #25 o 4.b Fire Hose Stations and Hydrants (Not #25) See Key for Required Actions Terminating Cue: JPM Complete 4 of 10 Appendix C 1/2" *yp_) #23 H.P. HYDRA N T T O STORED AlJX. TRANS. SPRAY SYST E M SE E DtT. KK ON A 22755 4 A 10" R I SER SE E DE T. *cc* O'oiG

• A227554 I 1 RISER SEE O£T. Page 5 TO CLEA N ANO DIRTY OIL TAI<-<( <0 0:: w 1-< TO BOILER FEED PUW OElll(;E SE E TYP. DELUGE VALVE STAT. &. OET. *p*

A227552 TO SEAL OI L UNIT DELUGE SEE TYP. C<: L LGE VALVE S T AT. t OET. " L' OWG. A227552 Blue Affected Component Red Isolation Boundaries 0 0 "' M "' w FP-5 1 2 .. FP-:118 1-0-z;;'i "' g 5 of 10 TO HlSE RE EL 1 0" Form ES-C-1 #24 H.P. HYDRANT-8 CONTAINMEN T BLQG. UNIT N0.2 TO TRANSFOR>1=.R DELUGE VALVE SE E TYP. OELLGE V ALVE STAT. & on . *w oWG. A227552 I E LEC T. T tn.'EL OELU!iE SEE OET. "B" OWG. A22755 1 CONTROl BLDG. TANK FILL LINE RISER DET. " A" T H!S OWG. -6" RISER TO ELEV. I 47" SEE 08". "A" THIS O'oiG. STAIR fL I 1 0* N 673 126 -FI Appe_ndix C Page 6 Form ES-C-1 BE!J!.!IBO!!E t F 2. 1 H i gh-Pressur e a.1 t:IU 1 H motor-driven hre main Water Fire (1 1 FM B P g Protection 12FMB P) mD cf-1-driven fire System 1U11P (DFP) funaionll l and to me l mp!lired fire header. Refer t o ccr<<.ions 2.a.1.a Nrxes Z.Z.a ;nJ Z.Z.c fa and 2.a.2 may addirional glidance. concurreNiy , l mp!lired condi:ions 2.a.1.b and 2.a.2 may a.l A m i rimum avarlable water COI'lal/reMy , volume of 360 , 000 gallons I mpaired conlM!ed in me City Water Tank eoncfilions 2.a.1.c and 300 , 000 ga!lons contained 11'1 and 2.a.2 may 1fle F i re Water Storage T ank for ex i st concurreNiy fue protection Refer to Nae Z.Z.b fa addiianal Refer t o Not: Z a.J No and v!!lves necessary for adcftion.'li guidance for proper funclioning c:f any por1ion of the reqlired for pro!eCtlcfl of safety-rela:ed or sa f Hiutdown systems functional.

ReferrJ Nae l 2.cfrr addirionalglic/ance. b. Hi;l\1lressure water fire protection sys-:ern Ulctional as req ui red by 2.a.1 and 2.a.2. NOTE: Expiri!tion of the Aaion r tme for Items 2.a.1 and 2.a.2 teqUire en1ry i nto I tem 2.b. a.1 a.L a.J b. ADDENDUM I FP/ASSS EQUIPMENT IMPAIRMENT CRITER I A P ag e 2 of 2 3 IMM IBE!l Ala i! a.la One or bo:h mo1or driven fire main (1 1 FMBP and/or 1 2FM B P) 0111 of service QB. a.lb The cf5el-driven pu!1'f' (DFP) M of serw:e. QB.. a.lc h delemlined by FP Refer to Nae Z.Z.a fa gOOilfiCe. A! a ll a.£ One water si.Wiy out of service. Refer to Nrxe Z.Z.b fa gidJfiCe whe n the FWST leve l i nsromm clmne/ a tank refill cap:JlXfry is mpaired. a.J Ally vlllve or pipe to supply fixed suppressiOI'I systems or ho$e protec1ing safety-related or safe---.hutdcwn related areas CIUl of servic e. At a ll times. b.1 With the high-pressure water flle protection impa i red in a manner oth<< !han permitted by 2.a.1 or 2.a.2. b.l t-:equired Aaion and Adion Time c{ I mpa i red Con61ion b.1 noc met. BEQ!JIREQ 1\C TIO N a.l a 10 fLI!Ciional status. a.1.b a.1.c a.£ Res:ore 10 fllldional a.J See Required Aaion for specifiC fixed automatic syslem or hose served by the portion of the sy;tem i s illlailed. b.t All alternate fire pro:ection S)'Stem dla H be estab li shed. bLa 1!e in MUU I:: J. b.2.b Be in MOD E 5. provisions of paragraph 4.6 S HALL be followed if th e specifi e d " Ac tion T im e" f or A N Y It e m in th e Tabl e is e xceeded. 6 of 10 a.l.a a.l b a.l c a.2 a.J b.t b.l.a b.2.b SA0-703 REV34 1\CT!Qt:l IIME 1 'Mlhi'l/ days.

• WJMldays.

Aclion Tme. Wlllin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Wi:lln j() hours. Wlllin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Appendix C Page 7 Form ES-C-1

3. F i r e Pro t ection a.l The Electrica l T UMe l F i re Spray Systems Protecral Wa:et Spra y System (Inc l u d es (El-3 3 ft. Caltro!Build i ng i o El-sprinklEr 68ft. P AS

• Fire Zone 32A) sha ll s yste m s and be funaiClnal deluge s ySiell15) a.£ The DieSe l Genera: cr SilkEn; Refer to Note 2.0 Water Spra y Sys (elll (i n EDG for adcftionJI Blildi ng

• Fe Zone 1 0) sh all be gridJnc e functioMI. b. The spray cys t ems lis: ed on Tab l e l-3 shal l be functional. a. b. ADDEND U M I FP/ASSS EQUIPMENT IMPAIRMENT CRITER I A P ag e 3 of 2 3 V.,enever saf e ly-related cr safe. a. M y spray system impailed. dlllclov.n re l a 1 ed equipmem i n the area is required to be operable. 'h'hene v er equ lptl1etll m the area 15 b. M y spra y syst e m impaired. requir ed i o be operab l e. BEQ!.!I R Eil a.l Add iti OMl t il e hoGe(s) sha ll be pro vi ded ancllabled to the affected loca tion(;) f rom a functional hose sta tion(c) or hy dr MI(s). Refer t1 Nate 2.3 far adcff.ioroll}itknce. a:J. The impai red spra y sys 1em (s) shal be res l ored to functional s tatui;. a.3 V e ri fy adonicna l compensa!ory fire hose i s staged as teqUired b y a.l above b.l.a I Es!ab l ish a 4-boll' fi re tour to i ,.;pect me affected fi re zcne (s). .00, b.1.b H fie affected zone is equ i pped with a fire detedion sys!etn (see Tab l e 1-l), ve rify thai the f w de t ect icln e quipm ent in the zone is Nnaional . .00, b.1.c Additiona l fue hos e(s) sha ll be provided to serve the afleo:ed location(s) fran a funcliona l hoGe sm lion(s) ot hydrant (s). Refer to N rxe 2. 3 fa addi!icml glidJn c e. b.l I ReslOie to f unaiona l status. provisions o f paragraph 4.6 SHALL be followed if th e specifi e d " Action T im e* for A N Y It e m i n th e Tabl e is e xceeded. 7 of 10 a..l a.£ a.J b.l b.2 SA0-703 REV34 'M llln 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. 1 Wi:lin 1 4 days. Every 90: 7 da ys ! 'Mlhn c hOu rs. 'M llin 30 clays.

Appendix C Page 8 Form ES-C-1 REQ!.!IREME rti 1 4. Fi r e Ho se a. F i re hose sta1rons and hydrants St&ions arxl llhcMn en Ta b le l-4 shall be Hydrants functional. Refer to Noe 2. o foradciioflo')/

glid.lrrce

b. Fi re ho5e stations and hydran;r; on the high-pressure fire loop those llhown on Ta b l e l-4 r;hal be Mctional.

NOTE: The hose stlJiion en !he roof ci the FSB and 1he law-pressure hyd r ants i n the City Water Sys:em are NO T I NClUDED in this Mlctionality requirement. a. b. A DDE N D UM I FP/ASSS EQ UI P M E NT IM P AI R M E NT CR I TER IA Page 4 of23 V'Jhenever safe'!y-teiated cr safe. a. My fire ho5e staucn or hydrant li G!ed on shutdcwm rela1ed equipmen t in the areas p!Otected by the hcr..e &latiom and hydrants is te<pired to be operable. Whenever equipment protected by b. My fire hos e cr 1he hoGe slalials and hydrants in die hydrant. than li sted on Table area i s required to be operable. 1-4 i mpaired. Rfg UIBE Q A!:;TIQN a.1 Additional fue hoGe(s) shall be p!Ovided and labled to serve lhe affected locaticn(s) from an fll'ldional hose staticn;s) cr Refer 1:1 Nrte2.3 fiX Jdcitioml rpdarrce. Atl2 a:L I he inpailed sha M be res:ored to funaicnal!iiaiU$. a.J V erity add\ticnal compensa:ory fire hose i s t;taged as required by a.l aboo;e b.1.a Es:abli&h a 4-hour file watch tour to inspect die alfec1ed fire zcne(s). .cB. b.1.b I f lhe a ffecled zone is equ i pped with a fi re detectioo sys:em (see T ab i es 1-1 an d 1-2), verify lhai 1he fire detection equipment in !he zone is functional . m b.1.c Additional fue hoGe(s) shall be p!OVided to serve lhe affeaed locaticn;s) from a fundional hose s1a1ion(s) 01 hydrant( c). Refer to Nrte 2. 3 fiX adclitiorol glid.lnce. Mil b1 The inpaired shal be res:ored to functicnal!iii!IIS.

Note: The provisions of paragraph 4.6 SHALL be followed i f the specified

" Action Time" for ANY Item i n the Table i s exceeded. 8 of 10 a..l a..'J. a.J b.l b.2 SA0-703 RE V 34 AQ:IOrt !1 ME 1 Whtin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Wllhill14 Every 90:7 days 'Mlhi:nllhours.

'Mlhill30days.

Appendix C Page 9 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts: Time to complete: Question Documentation:

Question:

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

9 of 10 Form ES-C-1 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 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 100% power. Form ES-C-1

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

• LWDST has been isolated.

• R-54 source check failed.

• 6 Circulating Water Pumps are operating at slow speed.

• No dilution flow is borrowed from Unit 3.

• A Manual Radioactive Liquid Release Permit was prepared.

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

Calculator General

References:

Time Critical Task: No Validation Time: 30 2-SOP-5.1.5, Calculation and Recording of Radioactive Liquid Releases Task Standard:

Reviews manual calculation and identifies errors. Does not approve release. 2 of 11 Appendix C Page3 Form ES-C-1 Performance Information (Denote critical steps with a check mark --./) 1. Performance Step: Standard: Obtain Correct Procedure Obtain 2-SOP-%.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 tJCi/ml Allowed Diluted Concentration ppm Boron in the tank Comment: Observing the NOTE before step 4.3.2.4 the candidate should determine that the tank has not been recirculated for adequate time. The tank should be recirculated for 306 minutes. It has only been recirculated for 285 minutes. The candidate must identify that the tank needs to be recirculate for an additional 21 minutes. 3 of 11 Appendix C Page4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...f) 4. Performance Step: Standard:

Comment: 5. Performance Step: Standard:

Comment: 6. Performance Step: Standard: Comment: 7 Performance Step: Standard: Commen t: Verify from Chemistry the total gamma activity WITHOUT noble gas is less than 5.0E-5 JJCi/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 PageS Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 8. Performance Step: Standard:

Comment: ..J 9. Performance Step: Standard:

Comment: Determine the most restrictive release rate Determines 250 is correct Determine alarm settings if effluent radiation monitor is in service. Determine effluent monitor is INOPERABLE per ODCM surveillance requirement 3.3.1.3. v 10. Performance Step: Does not approve release permit Standard:

Comment: 5 of 11 Appendix C Page6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ...J 11. Performance Step: Make recommendations Standard:

Tank must be recirculated for an additional 21 minutes to satisfy 306 minutes. Verify compensatory actions for inoperable radiation monitor

• Two grab samples must be obtained after required recirc time

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

• Double verify release calculation

• An NPO SHOULD be present on the Support Facility Nuclear Side throughout the discharge Comment: The first three compensatory actions are required.

The third action is a "should" perform thus not required and NOT critical.

Terminating Cue: JPM Complete 6 of 11 CALCULATION AND RECORDING OR No: 2-SOP-5.1.5 RADIOACTIVE LIQUID RELEASES Page 16 of 23 ATTACHMENT 1 EXAMPLE RADIOACTIVE LIQUID RELEASE PERMIT PERMIT# 07300 TANK 10 13WDST RECIRC RATE: Chemistry

_ _..:..::15=0

__ gpm Sam le No. 4807 Pa e 1 of 1 (Date)

__ (D ate) Toda 01: 00 05:45 (Date) min limit of SMM-CY-001:

Rev:38 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-=0=E-5-=-

___ IJCilml Allowed Diluted Concentration (ADC) 5.31E-7 11-'------...----'

TOTAL DILUTION FLOW (T) --=504:..=,0=0=0

__ (GPM} From: _--'=-6_ Unit 2 Circulators

--=0-Unit 3 Circulators

--=0-Service Water Pumps BORON: 849 X 22972 x 8.33E-6 = 162.5 +/- .5 pounds ppm B tank vol M. gal Maximum Chemical Release Rate (Rc} = ( 504,000 x 1 ppm } + 849 = 593.6 +/- .5 gpm Avail Oil Flow (B), gpm ppm B Radioactive Release Rate: (Rr} = ( 504,000 x 5.31 E-7 } + 4.0E-5 = 6691 gpm Avail Oil Flow (B), gpm ADC, uCilml Gamma Act (C), uCilml --==-=---Most Restrictive Relea Rad Monitor# 54 Maximum Alarm Setpoint =

= 1.07E-3 Avail Oil Flow (B), gpm Most Restrictive uCi/ml Release Rate (R), gpm Actual Alarm Set int = 4.0E-5 uCi/ml Warn Set int= 3.0E-5 DISCHARGE FLOW METER & RECORDER OPERABLE _lL_ YES NO (IF NO , COMPLETE AITACHMENT3)

The initial conditions identified R-54 source check failure i.e., INOPERABLE Release Authorized By:----------------

RELEASE INITIATED: ____ (Date) _____ Also need RELEASE TERMINATED

____ (D at e) _____ ( Attachment 3 FINAL TK LEVEL: __ (Inches)

TOTAL VOLUME RELEASED Remarks:

Appendix C PageS VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation

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

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

• The Unit is operating at 100% power.

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

• LWDST has been isolated.

• R-54 source check failed.

• 6 Circulating Water Pumps are operating at slow speed.

• No dilution flow is borrowed from Unit 3.

• A Manual Radioactive Liquid Release Permit was prepared.

• Additional Data: Permit Number TankiD Initial Tank Level Pre-release volume Recirculation Rate Recirc Start-Recirc Stop Chern Sample Number Sample Dateffime Total Gamma Activity ADC ppm Boron in tank Initiating Cue: 070300 13WDST 97 22972 150 gpm Today 01: 00 Today 05:45 4807 Today 05:30 4.0E-5 5.31E-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 of23 ATTACHMENT 1 EXAMPLE RADIOACTIVE LIQUID RELEASE PERMIT (Page 1 of 1) INITIAL PERMIT# 070300 TANK 10 13WDST Tank Levei:J!Z_ (Inches) 22972 Volume (V), gal RECIRC Recirc Start: (Date) 01: 00 (Time) RATE: 150 gpm Recirc Stop: (Date) 05:45 (Time) Chemistry Sample No. 4807 Sample Collection

Todav (Date) 05: 30 (Time) Gamma Activity without Gas and Tritium is less than the admin limit of SMM-CY -001: Yes I No Total Gamma Activity 4.0E-5 1JCi/ml Allowed Diluted Concentration (ADC) 5.31E-7 1JCi/ml 6 Unit 2 Circulators TOTAL DILUTION FLOW (T) 504,000 (GPM) From: 0 Unit 3 Circulators 0 Service Water Pumps BORON: 849 X 22972 x 8.33E-6 = 162.5 + .5 pounds ppm B tank vol (V), gal Maximum Chemical Release Rate (Rc) = ( 504,000 x 1 ppm) + 849 = 593.6 +/- .5 gpm Avail Oil Flow (B), gpm ppmB Radioactive Release Rate: (Rr) = ( 504,000 X 5.31 E-7 ) + 4.0E-5 = 6691 gpm Avail Oil Flow (B), gpm ADC, uCilml Gamma Act (C), uCi/ml Most Restrictive Release Rate (R) = 250 gpm (pump capacity most limiting)

Rad Monitor# 54 SOURCE CHECKED _x_ OPERABLE _!_YES --NO (IF NO. COMPLETE ATT 3) Maximum Alarm Setpoint = ( 504,000 X 5.31 E-7 ) + 250 = 1.07E-3 uCi/ml Avail Oil Flow (B), gpm ADC, uCilml Most Restrictive Release Rate (R), gpm Actual Alarm Setpoint = 4.0E-5 uCilml Warn Setpoint = 3.0E-5 uCilml DISCHARGE FLOW METER & RECORDER OPERABLE _!_YES --NO (tF NO , COMPLETE ATTACHMENT

3) Release Authorized By: (Date) RELEASE INITIATED:

(Date) (Tome) RELEASE TERMINATED

(Date) (Time) FINAL TK LEVEL: __ (Inches) gal TOTAL VOLUME RELEASED aal Remarks:

Appendix C Indian Po i nt Unit Facility: 2 Job Performance Measure Worksheet Task No: 1500010522 Form ES-C-1 Task T i t l e: Classify Emergency Events Requiring Emergency Plan Implementation (Time Critical)

KIA

Reference:

2.4.38 SR0-4.4 Examinee: Facility Evaluator: Method of testing: Simulated Performance Classroom X READ TO THE EXAMINEE X Job Performance Measure No: NRC Examiner:

Date: Actual Performance Simulator Plant SROAdmin 5 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 th i s job performance measure will be satisfied.

1 of 7 Appendix C Initial Conditions:

The Current Time is 0223 Job Performance Measure Worksheet The Unit was operating at 100% power At 0200 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/A TWS

• The Turbine was tripped

• Reactor Power is 42% and lowering.

At0204

• Both Main Boiler Feed Pumps were tripped

• All AFW Pumps started At 0206

• Conventional NPO reports that he is unable to trip the reactor locally. At 0210

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

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

• The harsh environment in the ABFP room caused both Motor Driven AFW pumps to trip. At 0223 (NOW)

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

• Wind Speed: 2.2 meters/second

• Wind Direction:

55 degrees @ 10 meters

• Stability Class: B Initiating Cue: You are the CRS and the SM is unable to get to the control room. Classify the event and complete the Radiological Emergency Data Form. Required Materials:

EAL Wall Chart. 2 of7 Appendix C Job Performance Measure 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. 3 of7 Appendix C Page4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 1. Performance Step: Standard:

Comment: ...J 2. Performance Step: Standard:

Obtain correct procedure IP-EP-120 or EAL chart Give candidate Wall Chart Evaluate Initiating Cues to determine a GE classification applies. GENERAL EMERGENCY EAL#SG2.1 Comment: This action is time critical Mark Time when Declaration is made . ...J 3. Performance Step: Standard:

Complete "New York State Radiological Emergency Data Form, Part 1" Complete IP-EP-115 Comment: Critical elements on Part 1 form are marked with an asterisk ...J 4. Performance Step: Standard:

Direct Communicator to initiate notification.

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

CUE: Acknowledge direction to initiate notification.

Comment: This action is time critical.

Terminating Cue: JPM Complete 4 of?

• Appendix C PageS Form ES-C-1 New York State -r' Indian Point Energy Center --RAD10t0GICAL EMERGENCY OATAFORM-=-PART I .

tr l I 1. This i s an: \._ EXERCIS.§/ ACTUAL EMERGENCY at the Indian Point Energy Center The Emergeng:

A. Unusu::ll Fvent B. Alert C. Site Area Emergency I Classification is: (£. General E. Emergency Terminated I 2. ! 1 This Emergency Classification declared on: at Cuf.tEIJr TIM G

• I I 1 {Date) (Time 24 hr clOCk) Release of Radioactive Mater i als due to the Classified Event: To Atmos(2here:

I To Water: 3. BELOW Federal Lim i ts B. Release BELOW Federal Limits C. Release ABOVE Federal Limits C. Release ABOVE Federal Limits D. Unmonitored Release Requiring Evaluation D. Unmonitored Release Requiring Evaluation The following Protective Actions are recommended to be implemented as soon as practicable

A. NO NEED for PROTECTIVE ACTIONS outside the site boundary I ( B. EVACUATE and IMPLEMENT the Kl PLAN for the following C. SHELTER-IN-PLACE and IMPLEMENT the Kl PLAN for the following Sectors 4. I t_ 2 miles around S-miles downw i nd:) rf@& e r; 12 In the following Sectors: 1 2 3 4 5 6 13 14 15 16 2 miles around 10-miles downwind: In the following Sectors: 1 2 3 4 5 6 7 8 9 10 11 12 13 1 4 15 16 All remaining Areas MONITOR the EMERGENCY ALERT SYSTEM NOTE: OFFSITE AUTHORITIES SHOULD CONSIDER SHELTER-IN-PLACE

+ TAKE KIIF EVACUATION IS NOT FEASIBLE l EAL#: SG..;)_ l Affected Location*/ 5. -t1l .(s-o U NIT 2::5 ' . . *.n . . I "'"'l'-'\ftt'\

1 1111. B. UNIT 3 'TlP-1\ """-h\ ,*W\ f:.D.. &.-4 f. Pr1 i C. IPEC SITE Reactor Status: 6. Unit 2: Operational at (Date) (Tim e) (24 hr clock) Unit Shutdown a t (Date) (Tim e) (2 4 hr clock) j I 7. I Wind :l.:J Meters/Sec at elevation 1 0 meters I 8. I Wind Direction: (From) _ ___, 5:...,.5'""'--------Degrees at elevation 1 0 meters I 9. 1 Stability Class: A G) C 0 E F G j 10_ I Reported by-Commun i cator:-------------

Telephone#--

---

(Communicator's Name) Page 1 of 1 Form EP-1. Rev 5 5 of7 Appendix C Page6 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator: Number of Attempts:

Time to complete:

Question Documentation

Question:

Response:

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

6 of7 Form ES-C-1 Appendix C Initial Conditions 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 Form ES-C-1

• 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/A TWS

• The Turbine was tripped

• Reactor Power is 42% and lowering.

At0204

• Both Main Boiler Feed Pumps were tripped

• All AFW Pumps started At0206

• Conventional NPO reports that he is unable to trip the reactor locally. At0210

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

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

• The harsh environment in the ABFP room caused both Motor Driven AFW pumps to trip. At 0223 (NOW)

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

• Wind Speed: 2.2 meters/second

• Wind Direction:

55 degrees@ 10 meters

• Stability Class: B Initiating Cue: You are the CRS and the SM is unable to get to the control room. Classify the event and complete the Radiological Emergency Data Form.